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•• ~Enferpv bJ ® 1CAN081808 August 27, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 205.55 SUBJECT: lnseryice Testing Plan for the Fifth 10-Year Interval Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51 Dear Sir or Madam: Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One 10 CFR50.55a requires an lnservice Test (1ST) Program be developed in accordance with the applicable American Society of M_echanical Engineers (ASME) Code requirements. The ASME Code requirements for 1ST progra'ms are provided in the Operation and Maintenance of Nuclear Power Plants (OM Code). ASME OM Code-2004 through 2006 Addenda, Subsection ISTA-3110 requires the development of 1ST plans for each test interval. 1ST plans are to be filed with the regulatory authorities having jurisdiction at the plant site. Entergy Operations, Inc. (Entergy) is therefore providing the current 1ST plan for Arkansas Nuclear One, Unit 1 (AN0-1) for the fifth 10-year inspection interval. This interval commenced on December 1, 2017, and concludes on November 30, 2026. The plan is enclosed. Entergy is providing this plan for information only. Entergy is not requesting NRC approval of the plan. Any relief requests associated with this plan will be submitted as a separate document. No new regulatory commitments are included in this letter. If you have any questions or require additional information, please contact me. Sincerely, SLP/rwc Enclosure: AN0-1 lnservice Testing, Plan for the Fifth 10-Year Interval

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Page 1: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

•• ~Enferpv bJ ®

1CAN081808

August 27, 2018

U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 205.55

SUBJECT: lnseryice Testing Plan for the Fifth 10-Year Interval Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51

Dear Sir or Madam:

Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704

Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One

10 CFR50.55a requires an lnservice Test (1ST) Program be developed in accordance with the applicable American Society of M_echanical Engineers (ASME) Code requirements. The ASME Code requirements for 1ST progra'ms are provided in the Operation and Maintenance of Nuclear Power Plants (OM Code). ASME OM Code-2004 through 2006 Addenda, Subsection ISTA-3110 requires the development of 1ST plans for each test interval. 1ST plans are to be filed with the regulatory authorities having jurisdiction at the plant site. Entergy Operations, Inc. (Entergy) is therefore providing the current 1ST plan for Arkansas Nuclear One, Unit 1 (AN0-1) for the fifth 10-year inspection interval. This interval commenced on December 1, 2017, and concludes on November 30, 2026. The plan is enclosed.

Entergy is providing this plan for information only. Entergy is not requesting NRC approval of the plan. Any relief requests associated with this plan will be submitted as a separate document.

No new regulatory commitments are included in this letter.

If you have any questions or require additional information, please contact me.

Sincerely,

SLP/rwc

Enclosure: AN0-1 lnservice Testing, Plan for the Fifth 10-Year Interval

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1CAN081808 Page 2 of 2

cc: Mr. Kriss M. Kennedy Regional Administrator U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511

NRC Senior Resident Inspector Arkansas Nuclear One P. 0. Box 310 London, AR 72847

U.S. Nuclear Regulatory Commission Attn: Mr. Thomas Wengert MS 0-8B1A . One White Flint North 11555 Rockville Pike Rockville, MD 20852

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Enclosure to

1CAN081808

AN0-1 lnservice Testing Plan for the Fifth 10-Year Interval

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PaQe 1 of 165

ANO UNIT 1 INSERVICE TESTING PLAN SITE ENGINEERING PROGRAM SECTION

APPLICABLE SITES

ANO Unit 1: C8J ANO Unit 2: D GGNS: D IPEC Unit 1: D IPEC Unit 2: D

JAF:0 PAL:0 PNPS: D RBS:0

Safety Related: Yes

D No ANO Unit 1 5th Interval 1ST Plan

Interval Dates: 12-1-2017 to 11-30-2026

VY:0 JAF:0

Owner: Entergy Nuclear Operations, Inc. -1340 Echelon Parkway, Jackson MS 39213 Plant: Arkansas Nuclear One -1448 SR 333, Russellville, AR, 72802

Commercial.Service Date: 12/19/1974

Program Section Revision Summary

Current Revision Description of Change

This revision incorporates updates for changes made to the Fifth Interval update for ANO- I. Updated Pump PMT instructions to reflect the requirement for Group A, Comprehensive, or Preservice testing after maintenance/modification. Documented ANO's position on RB Dampers. Added reference

5 EPG-10. Updated CSJs and ROJs to match current test procedures. Added VPS-003 to document alternative check valve testing options. This revision incorporates all outstanding PCNs. NMM EN Ll-100, Revision 21, 5.2[4](d) states: "A PAD is not required for changes to those portions of the Inservice Inspection (ISi) and Inservice Testing (IST) Programs that are controlled in accordance with IO CFR 50.SSa" and such is the case for this IST program section.

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ANO Unit 1 1ST PLAN

Program Section Title:

Prepared By:

Checked By:

Concurred:

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 PAGE: 2 OF 165

REVIEW AND CONCURRENCE SHEET

ANO Unit 1 lnservice Testing Plan

Robert S Smith

Braden M Wa~ne ~-·W-Date:

$/lfJ//fi

t1-IO-l6

8/,o/ts ~ J

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 PAGE: 3 OF 165

REVISON STATUS SHEET SECTION PAGE NO. REV.

Front Section Pages 1 -22 5

Pump Summary Listing Pages 23-26 5-

Skid Mounted Pump Summary Pages 27 5

Pumps Exempt from Testing Page 28 5

Valve Summary Listing Pages 29 - 92 5

Augmented Valve Summary Listing Pages 93 - 98 5

Skid Mounted Valve Summary Pages 99 5

Condition Monitoring Justifications Pages 100 - 108 5

Cold Shutdown Justifications Pages 109 - 141 5

Refueling Outage Justifications Page 142 - 155 5

Valve Relief Request Pages 156 - 157 5

Pump Position Statement Pages 158 -160 5

Valve Position Statements Pages 161 -165 5

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 PAGE: 4 OF 165

SECTION

Cover Sheet

Concurrence

Revision Status

Table of Contents

Introduction

Valve Program

Pump Program

ATTACHMENTS

TABLE OF CONTENTS

Pump Summary Listing

Skid Mounted Pump Summary

Pump Exempt from Testing

Valve Summary Listing

Augmented Valve Summary Listing

Skid Mounted Valve Summary

Condition Monitoring Justifications

Cold Shutdown Justifications

Refueling Outage Justifications

Valve Relief Request

Pump Position Statement

Valve Position .Statement

PAGE NUMBER

1

2

3

4

5

14

21

Pages 23- 26

Page 27

Page 28

Pages 29 - 91

Pages 92 - 98

Page 99

Pages 100 -108

Pages 109 - 141

Pages 142-155

Pages 156 - 157

Pages 158 -160

Pages 161 - 165

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 PAGE: 5 OF 165

Introduction

This 10 CFR 50.55a lnservice Testing (1ST) Plan, hereafter referred to as the 1ST Plan, is for Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required by Section 50.55a of 10 CFR Part 50 to implement the requirements of ASME OM Code-2004 through 2006 Addenda. As documented in ULD-O-TOP-02 and ULD-O-TOP-22, AN0-1 was designed to achieve a safe shutdown condition equivalent to the hot shutdown mode of operation defined in Technical Specifications.

The 1ST Plan is designed to contain the information necessary to identify the pumps and valves subject to 1ST, categorization of components, identification of tests to be performed, and the frequencies of those tests. It also provides relief requests, justifications for cold shutdown and refueling testing, and positions taken with respect to the prescribed testing in 1 O CFR 50.55a.

Program Description

The 1ST Program identifies the Arkansas Nuclear One systems subject to the inservice testing requirements of the ASME OM Code. The subject systems are derived from station drawings, Upper Level Documents (ULDs), calculations, Safety Analysis Report (SAR), and plant commitments.

The 1ST Plan identifies the pumps and valves to be tested in accordance with the ASME OM Code. The pumps and valves are listed followed by both general and specific relief requests · where it has been found that the testing requirements for that pump or valve are impractical, as applicable. In such instances, appropriate alternative testing provisions have been identified. General relief requests are used when the impracticality of a particular test requirement applies to more than one pump or more than one valve. Specific relief requests are unique to a . particular component. Should certain ASME OM Code requirements prove to be impractical due to unforeseen circumstances, subsequent relief from that requirement will be requested.

The 1ST Plan is just one part of the ANO Unit 1 1ST Program; other parts include:

o Site Program Section No. SEP-AN0-1-IST-1, ANO Unit 1 1ST Bases Document: Primarily used to document the component function reviews performed to determine those components that are subject to 1ST.

o Program Section No. CEP-IST-4, Standard on 1ST: Primarily used to provide the consolidated and standardized technical requirements, including Entergy positions, for compliance with the regulatory requirements governing pump and valve 1ST.

o ANO Unit 1 1ST Program Files: Defined as all of the elements (Microsoft Word files, lddeal Version 9.0, and Microsoft Access databases) used to produce the 1ST Program.

o ANO Unit 1 1ST Testing Procedures: Defined as all implementing procedures and supplements for testing 1ST Components in accordance with the ASME OM Code.

The 1ST Plan is controlled and implemented in accordance with NMM Procedure EN-DC-332, lnservice Testing Duties and Responsibilities and NMM Procedure EN-DC-174, Engineering Program Sections. Program Change Notices (PCNs), which may be used to request changes to this 1ST Plan, are initiated and processed per EN-DC-174.

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/

ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 PAGE: 6 OF 165

Introduction

This document constitutes the 1ST Plan for ANO Unit 1. This document contains the following information:

o Valve Relief Requests and Valve Position Statements

o Pump Relief Requests and Pump Position Statements

o Cold Shutdown Justifications, Refueling Outage Justifications, and Check Valve Condition Monitoring Justifications, as applicable

o Valve Summary Listings

o Pump Summary Listings Applicability

Consistent with Section 50.55a of 1 O CFR Part 50, this program is applicable to the inservice testing of in-scope ASME OM Code Class 1, 2 and 3 components for AN0-1 fifth ten-year interval. The AN0-1 INSERVICE TESTING PROGRAM is defined in AN0-1 Technical Specifications. This program is responsible for demonstrating operational readiness of all ASME OM Code Class 1, 2, or 3 components and safety related non code class components necessary to bring the unit to a safe shutdown condition.

The Code of Federal Regulations, Title 10, Part 50.55a (1 O CFR 50.55a), paragraph (f)(5)(i) requires each licensee of pressurized water-cooled nuclear reactors to revise their inservice testing program to meet the requirements of 10 CFR 50.55a(f)(4)(ii). As a result, the inservice testing program must be revised at 120-month intervals to comply with the requirements of the latest edition and addenda of the ASME OM Code incorporated by reference in 1 O CFR 50.55a(b) 12 months prior to the start of the 120-month interval subject to the conditions listed in 1 O CFR 50.55a(b )(3).

In accordance with 10 CFR 50.55a(f)(4) and NUREG-1482, Rev. 2, "Guidelines for lnservice Testing at Nuclear Power Plants" paragraphs 2.2 and 2.2.1, the scope of 1ST includes ASME OM Code Class 1, 2, and 3 components. Additionally, for pumps and valves that are within the scope of the ASME OM Code but are not classified as ASME OM Code Class 1, Class 2, or Class 3 will be tested within the AN0-1 1ST Program. All deviations from the ASME OM Code will be documented providing an acceptable level of quality and safety.

10 CFR 50.55a Conditions

Conditions from 10 CFR 50.55a(b)(3) are incorporated into this 1ST Program as descri6ed below.

10 CFR 50.55a(b)(3)(i) - NQA-1, "Nuclear Quality Assurance Requirements for Nuclear Facilities"

This condition is incorporated into the 1ST Program by means of reference to AN0-1 's quality assurance program to implement these requirements.

1 O CFR 50.55a(b )(3)(ii) - Motor-Operated Valve Testing

AN0-1 will maintain and implement motor-operated valve testing program to ensure motor-operated valves will continue to be capable of performing the design basis safety function. The AN0-1 motor-operated valve testing program is governed by SEP-MOV-AN0-001 "ANO Motor Operated Valve (MOV) Program Implementation."

1 O CFR 50.55a(b )(3)(iii) - New Reactors

No action required.

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ANO Unit 1 1ST PLAN

Program Interval History:

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 PAGE: 8 OF 165

Introduction

This 1ST plan meets the rules set forth in the applicable ASME OM Code as required by 10 CFR 50.55a. The applicable ASME OM Codes are based on the start of the 10-Year Intervals, unless an alternative is specifically approved otherwise. The 10-Year l,ntervals for AN0-1 is as noted below:

10-Year Interval Dates and References

Owner Entergy Nuclear.Operations, Inc Reference

Address of Corporate 1340 Echelon Parkway, Jackson Office MS 39213 SEP-AN0-1-IST-2 R3

Arkansas Nuclear One,

Name and Address of 1448 SR 333, Russellville AR Power Plant 72802 ' SEP-AN0-1-IST-2 R3

Applicable Nuclear Power Units ANO Unit 1 SEP-AN0-1-IST-2 R3

Commercial Operation Date 12/19/1974 SEP-AN0-1-IST-2 R3

First 10 Year 1ST Interval 12-19-1974 to 12-18-1984 1CNA099203

1 CNA099203, 1CNA089402

OCNA089626*

Second 10 Year 1ST GNR0-96/00074 L Interval 12-19-1984 to 12-1-1997* GNRl-96/00184

Third 10 Year 1ST 1CAN109904, Interval 12-2-1997 to 12-1-2007* 1CNA109801

Fourth 10 Year 1ST SEP-AN0-1-IST-2 R3, Interval 12-1-2007 to 11-30-2017* CN R0-2007-00044

Fifth 10 Year 1ST . Interval 12-1-2017 to 11-30-2026* SEP-AN0-1-IST-2 R4

' *OCNA089626 notes that the approved second ten year interval for AN0-1 was scheduled to end on 12/1/1996. The second interval was extended by one year to the "no later than December 1, 1997" documented in OCNA089626 as allowed by ISTA-3120( d). This interval extension was carried forward into the third and fourth intervals. To return to the base interval of 12/1/1996, the Fifth 10 Year 1ST Interval will be shortened to nine years to allow additional margin as needed in the future ..

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ANO Unit 1 1ST PLAN

Justifications:

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 PAGE: 9 OF 165

Introduction

Cold Shutdown ·Justifications (CSJ) or Refueling Outage Justifications (ROJ) are provided for those components where test frequency varies within ASME OM Code allowances. NUREG-1482 Rev. 2 was used in developing these justifications.

Valve Position Statements (VPS) are provided for those components where test frequency varies within Code allowances for Non-Safety related components. Guidance provided with NUREG-1482 Rev. 2, was used in developing these justifications.

Pump Position Statements (PPS) are provided for those components where test requirements vary from Subsection ISTB allowances and an alternative, such as an approved Code Case, is utilized. Guidance provided with NUREG-1482 Rev. 2, was used in developing these justifications.

Relief Requests

Relief requests are written in accordance with 1 O CFR 50.55a when specific requirements for inservice testing are considered impractical or pose an undue burden on the licensee. The enclosed relief requests, if any, are subject to change throughout the inspection interval. If requirements are determined to be impractical, or result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, during the course of the interval, additional or modified relief requests will be submitted in accordance with 10 CFR 50.55a. NUREG-1482 Rev. 2 is used in developing justification for the basis of the relief requests. The NRG staff has reviewed the subject request and concludes, as set forth in the safety evaluation (1 CNA051701) that Entergy Operations, Inc. has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for relief request VRR-AN01-2017-1. Therefore, the NRG staff authorized the use of the requested alternative at AN0-1 for the fifth 10-year 1ST program interval which starts on December 1, 2017, and may be extended until November 30, 2027.

Code Cases

In accordance with 10 CFR 50.50a(b ), code cases referenced in Regulatory Guide (RG) 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code" may be used without obtaining further review. RG 1.192 provides a list of code cases that are acceptable, provided they are used in their entirety, with any supplemental conditions specified in the regulatory guide. In addition, RG 1.192 provides a list of code cases which are "conditionally acceptable," meaning that they are acceptable within the limitations described in RG 1.192.

Application of Code Cases

• Code cases to be used during a preservice or inservice test are listed in this 1ST Program.

• Code cases used in this 1ST Program are applicable to code of record and will be listed in the Plan.

• Code cases shall be in effect at the time this 1ST Program is filed, except as provided below.

• Code cases issued subsequent to filing this 1ST Program may be proposed for use in amendments to this 1ST Program, subject to the necessary conditions and limitations imposed by the NRG.

• OMN-20 - "lnservice Test Frequency"- 10 CFR 50.55a(b)(3)(x) authorizes Licensees to utilize ASME OM Code Case OMN-20 "lnservice Test Frequency" for ASME OM Codes

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 10 OF 165 -------------1 n trod u ct ion

of record which have been incorporated by reference in paragraph 10 CFR 50.55a(a)(1 )(iii)(G).

• OM N-16, "Use of a Pump Curve for Testing", is listed in RG 1.192 Revision 1, Table 1 of Acceptable ASME OM Code Cases (2006 Addenda). 10 CFR 50.55a(a)(iii) incorporated Revision 1 of RG 1.192 as approved in accordance witn paragraph (b )(6) of 10CFR 50.55a. OMN-16 is used for testing AN0-1 Service Water Pumps P-4A. P-4B, and P-4C.

Application of Revised Code Cases

• Superseded code cases approved for use in accordance with the above may continue to be used.

Application of Annulled Code Cases

• Code cases approved for use may be used after annulment for the duration of that 1ST Program Interval Program Plan.

Appendix B Program Positions/Exceptions

The Appendix B Program may be administered using the ASME OM Code as guidance for testing and trending. Another term for this category of tested components is "Augmented".

Relief Requests and Justification for Deferrals will not be submitted for Appendix B components. Valve Position Statements are used to justify any alternative tests or frequencies.

Program Changes:

The NRC shall be notified of 1ST Program changes; however, component additions and deletions will be submitted and testing implemented or deleted without prior NRC approval. In the instance where a component has been added to the 1ST Program, testing and the appropriate program changes will take place within 90 days of revising the program source documents unless determined to be impractical. If a hardship is identified, notification will be submitted to the NRC and an interim extension from testing implementation obtained.

The content of this program documenfis based on recommendations stated in NUREG-1482 Rev. 2 and is intended for the purpose of maintaining program continuity and documenting additional discussions and positions relative to Code interpretations. Therefore, changes to this program document will not require prior NRC review and/or approval unless the licensee determines a need to do so.

Fail-Safe Testing of Valves

All Fail-Safe valves shall be tested in accordance with ISTC-3560. Valves used only for system control, are typically excluded from testing in the 1ST Program; however, if a control valve must change position to support a safety-related function and it has a fail-safe position, then it will be included in the program and tested to verify the ability to perform that function with power and/or air removed (or simulated power and/~r air removal). Power Operated Valves (MOVs, AOVs, SOVs, and HOVs) which require stroke timing will demonstrate their fail-safe testing during the respective Stroke Time Open (STO) and/or Stroke Time Closed (STC) test. Additionally, for power-operated control valves that only have a fail-safe safety function, the requirements for valve stroke-time measurement testing, the associated stroke time test acceptance criteria, and any corrective actions that would result from stroke-time testing need not be met (ISTC-5100).

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 11 OF 165

Introduction

Full Stroke Exercising of Power Operated Valves

All program valves shall be tested in accordance with Table ISTC-3500-1 unless specifically authorized otherwise by application of a Code Case or Approved Relief Request. Power Operated Valves (MOVs, AOVs, SOVs, and HOVs) which require stroke timing will demonstrate their full stroke exercise during the respective Stroke Time Open (STO) and/or Stroke Time Closed (STC) test.

T2 and T3 Augmented ISi Piping

T2 and T3 ISi piping illustrated in SEP-RR-ANOC-001, "ASME Section XI Repair/Replacement Program" and P-200 Sheet 1, "LS.I Boundary Diagram Instrumentation Component Symbols, and Drawing Index Sheet" Note 12 are defined as "Treated as ISi Class 2" (T2) and ''Treated as ISi · Class 3" (T3) means that the designated systems and components (which are designed, fabricated and installed to standards other than ANSI B31.7 (I.E. B31.1)) are treated for the purposes of Section XI lnservice Inspection, Repair/Replacement and pressure testing as any other ISi Code Class 2 or class 3 system. Therefore, the lnservice Testing program illustrates these as Class 2 and Class 3 piping.

Reactor Building HVAC Dampers

CV-7470, CV-7471, CV-7472, CV-7473 are identified in the program database and in previous revisions of 1ST Program documentation as excluded since they are dampers in ductwork and, therefore, are excluded from the 1ST program. The dampers are located in a portion of the system that is not identified as ASME Class 1, 2 or 3 on the P boundary drawing. The dampers have an identified safety related or accident mitigation function and-receive an ES signal to open. These dampers are tested outside of 1ST Program requirements. Since the dampers are tested consistent with. their safety function there is no need for additional testing in the 1ST Program.

Snubber Testing and Examination Program

All AN0-1 Snubbers shall be examined and tested in accordance with Subsection ISTD; however, specific documentation and implementation requirements for snubbers are provided in SEP-SNB-AN0-001, ANO Snubber Program Section. ASME OM Code provisions associated with dynamic restraints (snubbers) will be covered by snubber program plan documents and submitted to the NRC separately.

Observation of Erratic Action during Exercising of Power Operated Valves

All program valves shall be tested in accordance with Table ISTC-3500-1. Power Operated Valves (MOVs, AOVs, SOVs, and HOVs) which require stroke timing demonstrate their full

· stroke exercise during the respective Stroke Time Open (STO) and/or Stroke Time Closed (STC) test. COPD001 "Operations Expectations and Standards" established Additional Standards and Expectations that operators shall be attentive to plant parameters and investigate abnormal trends and conditions. This is a continuous expectation, and therefore the generic operator instruction of COPD001 documents ANO's Observation for Erratic or Abnormal Action during quarterly power operated valve strokes.

Skid-Mounted Valves

As specified in ISTC-1200, skid mounted valves will be excluded from the scope of 1ST test requirements provided they are adequately tested as part of the "major'' component. The licensee, however, may opt to include certain components contained on these skids in the 1ST Program for testing and trending purposes. In such cases, any program changes, exceptions, exemptions, or deferrals will not be submitted to the NRC for prior approval but simply documented in the Program Plan. ·

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 12 OF 165

Introduction

Pump Post Maintenance Testing Requirements

CEP-IST-4, Standard on 1ST, describes the requirements for Post Maintenance Testing (PMTs) of pumps in Attachment 1, Table 2. This guideline provides the required testing for PMTs. ISTB-3310 requires that a new set of reference values determined, or the current reference values reconfirmed prior to by a Comprehensive or Group A test prior to being declared operable. Group B testing is not an acceptable test for pump maintenance with the potential to affect flow, pressure, or vibration reference values. A pre-service test may be substituted for any of the previous tests if desired.

'\, Valve Stroke-Time Acceptance Criteria:

The following cases present the options available for determining valve operability based on stroke time:

CASE 1:

CASE 2:

CASE 3:

The valve strokes within its acceptable stroke time. The valve is considered operable.

The valve fails to change position on the first try or exceeds the LIMITING VALUE. The valve shall be immediately declared inoperable.

The valve fails to meet the acceptance stroke time but strokes in less than the LIMITING-VALUE. Per ISTC-5100, the valve shall be immediately stroked again to achieve an acceptable stroke time, or the valve shall be immediately declared inoperable.

If the valve successfully strokes on the second stroke, the valve is considered operable. The cause of the initial deviation shall be analyzed and the results documented in the record of test (i.e. Condition Report).

If the valve does not fall within the acceptable range on the second stroke, then the valve will be analyzed within 96 hours OR declared inoperable (if applicable). An evaluation must be performed to determine the cause of the failed test (deviation). The evaluation may determine that either corrective maintenance must be performed on the valve or the new stroke data is acceptable and new baselines must be established. Such results must be documented in the record of test (i.e. Condition Report).

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 13 OF 165

Introduction

The following documents were used as references in the development of this document:

1. ASME OM Code 2004 Edition through 2006 Addenda 2. Generic Letter 89-10 - Safety-Related Motor-Operated Valve Testing and Surveillance 3. Generic Letter 96-05 - Periodic Verification of Design-Basis Capability of

Safety-Related Power-Operated Valves 4. Generic Letter 96-06 - Assurance of Equipment Operability and Containment .

Integrity During Design-Basis Accident Conditions

5. 10 CFR 50, Appendix B 6. 1 O CFR 50.55a 7. AN0-1 Technical Specifications 8. AN0-1 Safety Analysis Report (SAR) 9. Regulatory Guide 1.192, Revision 1 "Operations and Maintenance Code Case

Acceptability, ASME OM Code" 10. NRG Inspection Procedure 73756, lnservice Testing of Pumps and Valves 11. NUREG/CP-0123, Proceedings of the NRC/ASME Symposiums on Pump and Valve

Testing 12. NUREG-1482 (Rev. 2), Guidelines for In-service Testing at Nuclear Power Plants,

October 2013 13. NRG Information Notice 97-90, Use of Nonconservative Acceptance Criteria in Safety­

Related Pump Surveillance Tests 14. NRG Information Notice 97-16, Preconditioning of Plant Structures, Systems, and

Components before ASME OM Code lnservice Testing or Technical Specification Surveillance Testing

15. EN-DC-131, Check Valve Maintenance and Monitoring Program 16. SEP-CV-AN0-001, ANO Check Valve Program 17. ULD-O-TOP-02, Fire Protection NFPA-805 Topical

18. ULD-O-TOP-22, ANO Unit 1 and 2 ANO Component Classification Topical 19. 1 CNA051701, Arkansas Nuclear One, Unit 1 - Relief Request VRR-AN01-2017-1 for the

Fifth 10-Year Interval of the lnservice Testing Program (CAC No. MF8853) 20. SEP-MOV-AN0-001, ANO Motor Operated Valve (MOV) Program Implementation

21. SEP-ANO-AOV-001, ANO Air Operated Valve (AOV) Program 22. SEP-SNB-AN0-001, ANO Snubber Program Section

23. SEP-RV-AN0-001, ANO Relief Valve Program 24. SEP-APJ-002, ANO - Primary Containment Leakage Rate Testing (Appendix J)

Program Section 25. CEP~IST-4, Standard on lnservice Testing 26. COPD001, Operations Expectations and Standards 27. EPG-10, INPO Engineering Program Guide, lnservice Testing Program 28. 1CAN111602, Fifth Ten-Year Interval lnservice Testing Program Relief Request VRR­

AN01-2017-1

29. SEP-RR-ANOC-001, ASME Section XI Repair/Replacement Program

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 14 OF 165

Valve Program

GENERAL

The valve test requirements are presented on the Valve Summary Listing forms, along with pertinent valve, system, and plant information. The forms, organized by systems; are to be used in conjunction with Piping and Instrument Diagrams (P&IDs).

The following pages contain instructional information to aid in the use of the Valve Summary Listings and are keyed to the various heading categories.

As noted in the Introduction, other parts of the 1ST Program provide bases for the selection of valves, cross-reference to testing procedures, and requirements for the performance of 1ST.

INSTRUCTIONS FOR USE OF VALVE SUMMARY LISTING FORM

VALVE ID - Indicates valve (component) number.

FUNCTION - Brief description of each valve.

DRAWING - P&ID number on which each valve is located.

· COORDINATE - Coordinate on the P&ID at which each valve is located.

CAT - Valve category as defined by the Code for each nonexempt valve. Combined category valves are identified in this program when more than one Code category is needed to identify the valve functions. Examples are "C, A" and "C, B".

Category A - Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function(s), as specified in ISTA-1100.

Valves for which seat leakage is important may also be classified as Pressure Isolation Valves (PIV), Containment Isolation Valves (CIV), or both Pressure and Containment Isolation Valves (PIV/CIV).

Category B - Valves for which seat leakage in the closed position is inconsequential for fulfillment of their required function(s), as specified in ISTA-1100.

Category C - Valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves) for fulfillment of their function(s), as specified in ISTA-1100.

Category D - Valves which are actuated by an energy source capable of only one operation, such as rupture disks or explosively actuated valves.

' ACT/PASS - "Active" for 1ST Active valves; "Passive" for 1ST Passive valves.

Active valves are those valves which are required to change obturator position to accomplish the required function(s) for shutting down the reactor to the safe shutdown condition, maintaining the reactor in safe shutdown, or in mitigating the consequences of an accident.

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,~ I

ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 15 OF 165

Valve Program

Passive valves are those valves which maintain obturator position and are not required to change obturator position to accomplish the required function(s) for shutting down the reactor to the safe shutdown condition, maintaining the reactor in safe shutdown, or in mitigating the consequences of an accident.

Valves that are locked or de-energized in their required positions, or are only repositioned from their safety position under administrative controls for the performance of surveillance procedures are considered passive. Valves that are periodically repositioned during plant operation are notconsidered passive. "Periodic" includes valve operations that occur as a result of normal operating procedures. Valve operations included within off-normal or emergency procedures are not considered periodic. Valve operations that occur as a result of system startup or shutdown procedures, or infrequent operating procedures may be considered periodic.

CLASS

valve Classification Designation

ASME OM Code Class 1, 2, or 3 valves within the scope 1, 2 or 3 of the Code.

Safety related non-ASME valves. NC

SIZE - Size of valve (in inches)

TYPE - Type of each valve. Valve types not included in this list are described in the "NOTES" column of the Summary Listing:

Valve Type Designation

Ball BA Butterfly BF

Check CK Diaphragm DIA

Gate GA Globe GL

Plug PLG

Relief or Safety RV

Sluice Gate SG Stop Check SCK

Angle ANG ~

Rupture Disk RD

Needle NOL Three Way 3W

Vacuum Relief VRV

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 16 OF 165

Valve Program

ACT - Type of actuator(s) for each valve: "' •, ., ' '

': besighati<>n ' . '

Actuator Type-

Air Operated AO

Hand (Manual) H

Motor Operated MO

Self (system) actu.ated SA

Solenoid Operated so Hand/Self Actuated H/SA

Hydraulic Operated HO

Motor/Self Actuated MO/SA

NORM - Position the valve is normally in or may be expected to be in during normal system operation or allowable alternate alignments without administrative controls.

0-0pen

LO - Locked Open

C-Closed

LC - Locked Closed

0/C - Open or. Closed

TH - Throttled Open

SAFE - Safety Position the valve is required to be in to perform its safety function.

0- Open

C-Closed

0/C - Open and Closed

TH - Throttled Open

FAIL- Fail Safe Position the valve goes to on a loss of power.

0- Open

C-Closed

0/C - Open and Closed

FAI - Fail As Is

N/A - Valve does not have a motive power source to fail.

TEST REQ - Required valve tests for the respective safety position of each valve are indicated by an entry for the associated test frequency in the Summary Listing and are described below. These columns will describe the method(s) of testing for each valve, using the following test designations:

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 17 OF 165

Valve Program

.. Va,lve Test Tyl:)e . Abbreviat.ion

.. ,·· . . . ,.

Check Valve Bi-directional Closed - A closure exercise test method for check BOC

valves that do not perform a safety function in the closed position. (

Check Valve Bi-directional Open - An open exercise test method for check valves that do not perform a safety function in the open position. This test BOO only requires the valve to be exercised to the partially open position.

Check Valve Close - A close exercise test method for check valves that perform a safety function in the closed position. This method verifies that the obturator travels to the seat. For valves in a defined CVCM plan, specific eve testing requirements for the closure test are illustrated in the CVCM Testing Plan.

Check Valve Open - An open exercise test method for check valves that perform a safety function in the open position. This test method verifies the obturator travels to the full open position (e.g. disc on backstop) or position cvo required to fulfill its safety function (e.g. passes required accident flow rate). For valves in a defined CVCM plan, specific testing requirements for the open test are illustrated in the CVCM Testing Plan.

Exercise Test Closed -A test method for power-operated valves. This test ETC

full stroke exercises the valve in the closed direction.

Exercise Test Open -A test method for power-operated valves. This test full ETO

stroke exercises the valve in the open direction.

Fail Safe Closed - A test method for valves that have an actuator that causes the valve to fail in the closed position. This test verifies that the valve travels to the closed position upon loss of valve actuating power. This test may be

FSC credited by observation of valve indicating lights during normal valve operation or full-stroke exercising, if normal valve stroking involves or simulates loss of valve actuating power.

Fail Safe Open -A test method for valves that have an actuator that causes the valve to fail in the open position. This test verifies that the valve travels to the open position upon loss of valve actuating power. This test may be

FSO credited by observation of valve indicating lights during normal valve operation or full-stroke exercising, if normal valve stroking involves or simulates loss of valve actuating power.

Leak Rate Test App J - Seat Leakage Test in accordance with 10 CFR 50 Appendix J. This test type is shown for CIVs that are leak rate tested in accordance with the AN0-1 Appendix J Program (SEP-APJ-002). There are LTJ no specific 1ST requirements beyond the Appendix J program testing requirements.

Leak Rate Test - Seat Leakage Test for reasons other than 1 O CFR 50 Appendix J. This test verifies the leakage rate of other Category A valves is LT within Owner Specified limits.

Manual Stroke - A test method for manual valves. This test full stroke MS exercises the manual valve using the handwheel.

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 18 OF 165

Valve Program

,i' ,,

" ·:: ',

' :, ''

··. Valv,e.Test TyiJ,e , ' • Abbreviati9n. ' ' '' ' .',, ''

Partial Stroke Open - Test method for Active valves which are partially stroked in the open direction in lieu of a full stroke exercise test. This test PSO type is associated with a valve that has a deferred full stroke test but still requires a periodic exercise to verify operational readiness.

Position Indication Test- Test method for valves that are equipped with remote position indication. This test verifies the indication method (lights, etc) accurately reflect actual valve position. In most cases, this test is performed by local observation of valve stem position. Other acceptable methods

RPI include supplemental verification of a change in system conditions (flow, pressure, temperature, etc) relative to valve obturator position as compared to the normal indication method. Only those remote indicators used for inservice testing are required to be verified.

Relief Valve Test-A test method for relief valves. This test method verifies relief valves lift at their specified setpoint (within Owner specified criteria) and

RV verifies other required parameters as specified in Appendix I of the ASME OM Code.

Rupture Disk -A test method for rupture discs. This method performs an inspection and replacement of installed rupture discs at the specified RD frequency.

Stroke Time Closed - A closure exercise for active power operated valves which perform a safety function in the closed position. This test performs a full

STC stroke exercise from open to close position and measures the elapsed time of the valve stroke in the closed direction.

Stroke Time Open - An Open exercise for active power operated valves which perform a safety function in the open position. This test performs a full

STO stroke exercise from close to open position and measures the elapsed time of the valve stroke in the open direction.

Seat Tightness Test- Seat Tightness Test for reasons other than 10 CFR 50

Appendix J. This test verifies the leakage rate of relief valves is within Owner STT

Specified limits.

Vacuum Relief Valve- A test method for vacuum relief valves. This test method verifies relief valves lift at their specified setpoint (within Owner specified criteria) and verifies other required parameters as specified in

VRV Appendi_x I of the ASME OM Code. Additionally, this test verifies the leakage

rate of vacuum relief valves is within Owner Specified limits (where applicable.)

'

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 19 OF 165

Valve Program

FREQUENCY: Frequencies are the Code Required Test.Frequency.

T.est FreqHency Abbreviation .. .. .. ' ..... ; ': . ' '' ', :'

Appendix J - 10 CFR 50 Appendix J Type C leak rate tests are controlled by the ANO Unit 1 Local Leak Rate Test (LLRT) Program. Refer to the LLRT AppJ Program for individual valve leak rate test requirements.

Cold Shutdown - Test performed every cold shutdown but not more frequently cs than once every 92 days (3 months). (Note 1)

Condition Monitoring - Variable test sample frequency based on condition CM

monitoring plan requirements.

Every 10 years (Note 4) 10Y

Every 2 years - Test performed once every two years. 2Y

Every 5 years (Note 2) (Note 3) SY

Every 18 Months (547 days) 18M

Normal Operation-Tests performed during normal operation, such as monthly,

bimonthly, weekly, or daily tests controlled by processes outside of the 1ST NO

Program

Quarterly - Test performed once every 92 days (3 months). Q

Refueling Outage - Test performed at each reactor refueling outage. R

Skid Mounted- Skid-Mounted Component {adequately tested via periodic SK

testing or operation of major component or skid)

Technical Specification-As specified by Technical Specification TS

As Required - Variable based on other programmatic requirements. AR

Note 1 - Cold Shutdown Testing - Entergy plants will commence testing no later than 48 hours after cold shutdown condition is achieved and will continue until all tests are complete or the plant is ready to return to power. This time requirement is necessary such that scheduling arrangements, appropriate valve lineups, and system adjustments can be made prior to valve testing. Any testing not completed at one cold shutdown will be

· performed during any subsequent cold shutdowns that may occur before refueling to meet the ASME OM Code-specified testing frequency. For planned cold shutdowns, where Entergy plants will complete all the valves identified in the 1ST Program for testing in the cold shutdown mode, exception to the 48-hour start time may be taken. In the case of frequent cold shutdowns, valve testing will not be performed more often than once every 92 days (3 months) for Category A, B, and C valves.

Note 2 - All Class 1 pressure relief valves and Main Steam Safety Valves (MSSVs) of each type and manufacture are to be tested within each subsequent 5 year period following the initial 5 year period, with a minimum of 20% of the valves tested within any 24 months. This 20% is to be previously untested valves (from the current 5 year period), if they exist. If less than 20% of each type and manufacture of the group of all Class 1 pressure relief valves remain to be tested in the current 5 year period, then valves are to be retested as necessary such that at least 20% of each type and manufacture is tested within any 24 month period. -

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 20 OF 165

Valve Program

Note 3 - Class 1, 2, and 3 non-reclosing pressure relief devices are to be replaced every 5 years, unless historical data indicates a requirement for more frequent replacement.

Note 4 - All Class 2 and 3 pressure relief valves of each type and manufacture are to be tested within each subsequent 10-year period following the initial 10-year period, with a minimum of 20% of the valves tested within any 48 months. This 20% is to be previously untested valves (from the current 1 O year period), if they exist. If less than 20% of each type and manufacture of the group of all Class 2 and 3 pressure relief valves remain to be tested in the current 1 O year period, then valves are to be retested as necessary such that at least 20% of each type and manufacture is tested within any 48 month period.

Note 5 - Frequencies are the Code Required Test Frequency. Actual Plant testing may be more frequent than the minimum noted time period due to scheduling needs.

PROCEDURE: Identifies the procedure(s) used to perform the associated valve test. The procedures are listed for information only and are subject to change.

NOTES: Any explanatory notes required are either provided or reference other portions of the 1ST Plan.

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ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 .REVISION NO. 5 PAGE: 21 OF 165

Pump Program

GENERAL

The pump test requirements are presented on the Pump Summary Listing form, along with pertinent pump, system, and plant information. The form, organized by system/component, is to be used in conjunction with P&IDs. Each inservice test shall include the measurement and observation of all quantities at the frequency indicated on the Pump Summary Listing forms.

The following pages contain instructional information to aid in the use of the Pump Summary Listing and are keyed to the various heading categories.

As noted in the Introduction, other parts of the 1ST Program provide bases for the selection of pumps, cross-reference to testing procedures, and requirements for the performance of 1ST.

INSTRUCTIONS FOR USE OF PUMP SUMMARY LISTING

PUMP ID - Indicates pump (component) number.

FUNCTION - Brief description of each pump.

DRAWING - P&ID number on which each pump is located.

COORDINATE - Coordinate on the P&ID at which each pump is located.

GROUP - Pump Group as defined by the Code for each nonexempt pump.

Group A - Pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations.

Group B - pumps in standby systems that are not operated routinely except for testing.

Cl,.ASS

Pump Code Class Designation

ASME OM Code Class 1, 2, or 3 pumps within the scope of the Code. 1, 2, or 3

Safety related non-ASME pumps. NC

TYPE - Describes the type of installed pump and driver as delineated in the ASME OM Code. Pump types include Centrifugal, Vertical Line Shaft, Positive Displacement, and Reciprocating Positive Displacement. Driver types are either Motor Driven or Turbine Driven.

FIXED OR VARIABLE

Abbreviation Description

Fixed Pump speed is fixed.

Var Pump speed is variable.

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_J

ANO Unit 1 1ST PLAN PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5

PAGE: 22 OF 165

Pump Program

ACTUAL SPEED

Abbreviation Description •;, '

GE600 Pump speed is greater than 600 rpm.

LT600 Pump speed is less than 600 rpm.

TEST REQ. - Required tests for each pump are indicated by an entry for the associated test frequency in the Summary Listing column for the tests described below.

N - Rotational speed measurement (required for variable speed pumps only; pumps directly coupled to synchronous or induction motors are exempt).

dP - Differential pressure across the centrifugal or vertical line shaft pump, either by direct measurement or by calculating the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe.

Q- Flow rate measurement.

Pd - Pump discharge pressure (required for positive displacement pumps only.)

V - Broad band (unfiltered) measurement of pump vibration (velocity or displacement). If velocity measurements are used they shall be peak; if displacement measurements are used, they shall be peak-to-peak.

FREQUENCY

Test Frequency · - Abbreviation

Every 2 years - Test performed once every two years. 2Y

Every 18 Months (54 7 days) 18M

Quarterly - Test performed once every 92 days (3 months). Q

FREQUENCY: Frequencies are the Code Required Test Frequency. Actual Plant testing may be more frequent than the minimum noted time period due to scheduling needs.

PROCEDURE - Identifies the procedure(s) used to perform the associated valve test. The procedures are listed for information only and are subject to change.

NOTES - Any explanatory notes required are either provided or referenced.

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ANO Unit 1 1ST Plan

PUMP ID FUNCTION DRAWING/COOR

P-34A Decay Heat Removal Pump A M-232, SH. 1 / E-5

P-34B Decay Heat Removal Pump B M-232, SH.1 / C-5

P-35A Reactor Building Spray Pump A M-236, SH. 1 / F-3

P-35B Reactor Building Spray Pump B M-236, SH. 1 / F-3

GROUP

A

A

B

B

Pump Summary Listing

Page 1 of 4

CLASS TYPE FIXED OR VAR.

2 Centrifugal Fixed

2 Centrifugal Fixed

2 Centrifugal Fixed

2 Centrifugal Fixed

ACTUAL TEST SPEED REQ

GE600 dP

Q

V

dP

Q

V

GE600 dP

Q

V

dP

Q

V

GE600 dP

Q

V

dP

Q

GE600 dP

Q

V

dP

Q

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 23 of 165

FREQ PROCEDURE NOTES

2Y 1104.004 1104.004S11

2Y 1104.004 1104.004S11

2Y 1104.004 1104.004S11

Q 1104.004 1104.004S1

Q 1104.004 1104.004S1

Q 1104.004 1104.004S1

2Y 1104.004 1104.004S12

2Y 1104.004 1104.004S12

2Y 1104.004 1104.004S12

Q 1104.004 1104.004S2

Q 1104.004 1104.004S2

Q 1104.004 1104.004S2

2Y 1104.005 1104.005S9

2Y 1104.005 1104.005S9

2Y 1104.005 1104.005S9

Q 1104.005 1104.005S3

Q 1104.005 1104.005S3

2Y 1104.005 1104.005S10

2Y 1104.005 1104.005S10

2Y 1104.005 1104.005S10

Q 1104.005 1104.005S5

Q 1104.005 1104.005S5

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ANO Unit 1 1ST Plan

PUMP ID FUNCTION DRAWING/COOR

P-36A High Pressure Safety Injection M-231, SH. 1 / G-Pump A 5

P-368 High Pressure Safety Injection M-231, SH. 1 / E-Pump B 5

P-36C High Pressure Safety Injection M-231, SH. 1 / 8-PumpC 5

GROUP

A

A

A

Pump Summary Listing

Page 2 of 4

CLASS TYPE FIXED OR VAR.

2 Centrifugal Fixed

2 Centrifugal Fixed

2 Centrifugal Fixed

ACTUAL TEST SPEED REQ

GE600 dP

Q

V

dP

Q

V

GE600 dP

Q

V

dP

Q

V

GE600 dP

Q

V

dP

Q

V

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 24 of 165

FREQ PROCEDURE NOTES

2Y 1104.002 1104.002S8 1104.002S9

2Y 1104.002 1104.002S8 1104.002S9

2Y 1104.002 1104.002S8 1104.002S9

Q 1104.002 ,

1104.002S3 Q 1104.002

1104.002S3 Q 1104.002

1104.002S3

2Y 1104.002 1104.002S8 1104.002S9

2Y 1104.002 1104.002S8 1104.002S9

2Y 1104.002 1104.002S8 1104.002S9

Q 1104.002 1104.002S4

Q 1104.002 1104.002S4

Q 1104.002 1104.002S4

2Y 1104.002 1104.002S8 1104.002S9

2Y 1104.002 1104.002S8 1104.002S9

2Y 1104.002 1104.002S8 1104.002S9

Q 1104.002 1104.002S5

Q 1104.002 1104.002S5

Q 1104.002 1104.002S5

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ANO Unit 1 1ST Plan

PUMP ID FUNCTION DRAWING/COOR GROUP

P-4A Service Water Pump A M-209, SH. 1 / F- A 4

P-4B Service Water Pump B M-209, SH. 1 / D- A 4

P-4C Service Water Pump C M-209, SH. 1 / C- A 4

Pump Summary Listing

Page 3 of 4

CLASS TYPE FIXED OR VAR.

3 Vertical Line Fixed Shaft

3 Vertical Line Fixed Shaft

3 Vertical Line Fixed Shaft

ACTUAL SPEED

GE600

GE600

GE600

TEST REQ

dP

Q

V

dP

Q

V

dP

Q

V

dP

Q

V

dP

Q

V

dP

Q

V

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 25 of 165

FREQ PROCEDURE NOTES

2Y 1104.029 PPS-001 1104.029S8

2Y 1104.029 PPS-001 1104.029S8

2Y 1104.029 1104.029S8

Q 1104.029 PPS-001 1104.029S1

Q 1104.029 PPS-001 1104.029S1

Q 1104.029 1104.029S1

2Y 1104.029 PPS-001 1104.029S9

2Y 1104.029 PPS-001 1104.029S9

r2y 1104.029 1104.029S9

Q 1104.029 PPS-001 1104.029S2

Q 1104.029 PPS-001 1104.029S2

Q 1104.029 /

1104.029S2

2Y 1104.029 PPS-001 ',

1104.029S10 2Y 1104.029 PPS-001

1104.029S10 2Y 1104.029

1104.029S10 Q 1104.029 PPS-001

1104.029S3 Q 1104.029 PPS-001

1104.029S3 Q 1104.029

1104.029S3

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ANO Unit 1 1ST Plan

PUMP ID FUNCTION DRAWING/COOR

P-7A Emergency Feedwater Pump M-204, SH. 3 / 8-

' 5

P-78 Emergency Feedwater Pump M-204, SH. 3 / G-5

GROUP

B

B

Pump Summary Listing

Page 4 of 4

CLASS TYPE FIXED OR VAR.

3 Centrifugal Var

3 Centrifugal Fixed

ACTUAL TEST SPEED REQ

GE600 dP

N

Q

V

dP

N

Q

GE600 dP

Q

V

dP

Q

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 26 of 165

FREQ PROCEDURE NOTES

2Y 1106.006 1106.006S16

2Y 1106.006 1106.006S16

2Y 1106.006 1106.006S16

2Y 1106.006 1106.006S16

Q 1106.006 1106.006S12

Q 1106.006 1106.006S12

Q 1106.006 1106.006S12

2Y 1106.006 1106.006S15

2Y 1106.006 1106.006S15

2Y 1106.006 1106.006S15

Q 1106.006 1106.006S11

Q 1106.006 1106.006S11

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ANO Unit 1 1ST Plan

Skid Mounted Pump Summary Listing

Component ID Description

P-102A-1 Ging Wtr Pump

P-102A-2 DG1 Cooling Water Pump

P-1028-1 Ging Wtr Pump

P-1028-2 Ging Wtr Pump

P-104A DG1 Fuel Priming Pump

P-104BJ Fuel Priming Pump 'B EDG

P-105A DG1 Fuel Pump

P-1058 Fuel Pump For 'B' EDG

P-106A-1 DG1 DC Lube Oil Soak Backpump

P-106A-2 DG1 AC Lube Oil Soak Backpump

P-106A-3 DG1 AC Lube Oil Soak Backpump

P-1068-1 DC LO. Soak Back Pump

P-1068-2 DG2 AC Lube Oil Soak Backpump

P-1068-3 DG2 AC Lube Oil Soak Back Pump

P-107A DG1 Lube Oil Scavenging Pump

P-1078 L.O. Scavenging Pump

P-108A Main L.O. Pump

P-1088 Main L.O. Pump '

P-109A DG1 Piston Cooling Lube Oil Pump

P-1098 Piston Cooling L.0. Pump

P-16A Fuel Oil Transfer Pump A

P-168 Fuel Oil Transfer Pump B

P-240 K-3 Shaft Driven Oil Pump

P-64A P-36A HPI Pump Aux Lube Oil Pump

P-648 P-368 HPI Pump Aux Lube Oil Pump

P-64C P-36C HPI Pump Aux Lube Oil Pump

P-88A P36A PRI MU PP Main LO PP

P-888 P36B PRI MU PP Main LO PP

P-BBC P36C PRI MU PP Main LO PP

RE-3809 A DH Rad Monitor Pump

RE-3810 B DH Rad Monitor Pump

RE-3814 SW Disch Gig Coils Pump

RE-3815 RB Ging Coils Rad Monitor Pump

VP-SA VCH-4A Chill Wtr Pmp

VP-58 VCH-48 Chill Wtr Pmp

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 27 of 165

BPVClass OM Class Exempt

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

N NC Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

N NC Yes

N NC Yes

Page 31: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

Pumps Exempt from Testing

Component ID Description

P-132 Core Flood Tank Make-up & Recirc Pump

P-32A RC Pump

P-328 RC Pump

P-32C RC Pump

P-320 RC Pump

P-39A Boric Acid Pump

P-39B Boric Acid Pump

P-40A Spent Fuel fool Circulating Pump (P40A)

P_-40B Spent Fuel Pool Circulating Pump (P40B)

P-43A Deg~sifier Drain Pump (Pump-Mtr Assy)

P-43B Degasifier Drain Pump (Pump-Mtr Assy)

P-44 Quench Tank Transfer Pump (Pmp-Mtr Assy)

P-46 Aux Bldg Equip Orn Tank Pump (Pump-Mtr Assy)

P-47A Treated Waste Monitor Pump (Pmp-Mtr-Assy)

P-47B Treated Waste Monitor Pump (Pump-Mtr Assy)

P-48 T-12 Recirc Pump

P-49A T-12 Xfer Pump

P-49B T-12 Xfer Pump

P-51A Aux Building Sump Pump

P-51B Aux Building Sump Pump

P-52A Dirty Waste Drain Pump (Pump-Motor Assy)

P-52B Dirty Waste Drain Pump (Pump-Motor Assy)

P-53A Filtered Waste Pump (Pump-Motor Assy)

P-53B Filtered Waste Pump (Pump-Motor Assy)

P-99 T-14 Vac Degas Seal Wtr Pump (Pmp-Mtr Assy)

r

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 28 of 165

BPVClass OM Class Exempt

N NC Yes

1 1 Yes

1 1 Yes -3 1 Yes

3 1 Yes

N NC Yes

N NC Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

Page 32: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

AC-60 CHILLED WTR TO RB M-222 Sh 1 / F-4 NC ACT CLRS CHK

BA-140 BA SUPPLY TO RX BLDG M-218 Sh 5 / E-3 A PASS ISOL

BA-141 BATO RX BLDG M-218 Sh 5 / D-3 A PASS

BS-4A SPRAY HDR 'A' CK VLV M-236 Sh 1 / F-6 NC ACT

BS-4B SPRAY HDR 'B' CK VL V M-236 Sh 1 / F-6 NC ACT

~

BW-2 BWST SUPPLY TO P-36C M-231 Sh 1 / B-7 C ACT SUCTION (STOP CHECK)

BW-3 P-36NB SUCTION STOP M-231 Sh 1 / G-7 C ACT CHECK ISOL FROM BWST

Valve Summary Listing

Page 1 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 6 CK SA 0 0/C

2 2 GA H C C

2 2 GA H C C

2 8 CK SA C 0/C

' 2 8 CK SA C 0/C

'

2 6 SCK SA C 0/C

-

2 6 SCK SA C 0/C

TEST

FAIL REQ

N/A LTJ

eve

cvo

N/A LTJ

N/A LTJ

N/A LT

eve

cvo

N/A LT

eve

cvo

N/A eve

cvo

N/A eve

cvo

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 29 of 165

FREQ PROCEDURE NOTES

AppJ 1305.018 1305.018A60

CM 1305.018 CVCM 1305.018A60

CM 1305.007 CVCM 1305.007S1A

AppJ 1305.018 1305.018A49 1305.018A50

AppJ 1305.018 1305.018A47 - . 1305.018A48

2Y 1104.005 1104.005S11 1104.005S13

CM 1104.005 CVCM 1104.005S11 1104.005S13

CM 1104.005 CVCM 1104.005S11 1104.005S 13

2Y 1104.005 1104.005S12 1104.005S14

CM 1104.005 CVCM 1104.005S12 1104.005S14

CM 1104.005 CVCM 1104.005S12 1104.005S14

R 1104.002 ROJ-002 1104.002S5

R 1104.002 ROJ-002 1104.002S7

R 1104.002 ROJ-002 1104.002S3

R 1104.002 ROJ-002 1104.002S7

Page 33: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

BW-4A BWST OUT CK TO P-34A M-232 Sh 1 / F-7 C ACT & P-35A

BW-4B BWST OUTLET CHECK M-232 Sh 1 / F-7 C ACT TO P-34B & P-35B

BW-6A P35A SUCTION CHECK M-236 Sh 1 / F-2 C ACT

BW-6B P35B SUCTION CHECK M-236 Sh 1 / F-2 C ACT

CA-61 NaOH TO P-34A/P-35A M-232 Sh 1 / F-7 A/C ACT SUCTION

CA-62 NaOH TO P-34B/P-35B M-232 Sh 1 / E-7 A/C ACT SUCTION

Valve Summary Li~ting

Page 2 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 14 CK SA C 0/C

2 14 CK SA C 0/C

2 10 CK SA C 0

/

2 10 CK SA C 0

2 4 SCK H/SA C 0/C

2 4 SCK H/SA C 0/C

TEST

FAIL REQ

N/A PSO

eve

cvo

N/A PSO

eve

cvo

N/A BOC

_, cvo

N/A BOC

cvo

N/A LT

eve

cvo

PSO

N/A LT

eve

cvo

PSO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 30 of 165

FREQ PROCEDURE NOTES

Q 1104.004 1104.00481 1104.004811

R 1104.004 ROJ-003 1104.00481 1104.004811

R 1104.005 ROJ-003 1104.00586

Q 1104.004 1104.004S12 1104.004S2

R 1104.004 ROJ-003 1104.004812 1104.004S2

R 1104.005 ROJ-003 1104.00587

CM RT CVCM ~

CM 1104.005 CVCM 1104.005S3 1104.005S9

CM RT CVCM

CM 1104.005 CVCM 1104.005S10 1104.005S5

2Y 1104.005 1104.00588

CM 1104.005 CVCM 1104.00588

CM 1104.005 CVCM 1104.00588

CM 1104.005 CVCM 1104.00588

2Y 1104.005 1104.00588

CM 1104.005 CVCM 1104.00588

CM · 1104.005 1104.00588

; CVCM

CM 1104.005 CVCM 1104.00588

Page 34: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CF-1A CFT T-2A OUT CHECK M-230 Sh 1 / H-3 A/C ACT VLV

CF-1B CFT T-2B OUT CHECK M-230 Sh 1 / G-3 A/C ACT VLV

CF-2 CORE FLOOD COMBINED M-236 Sh 1 / B-4 A ACT SAMPLE & BLEED

CS-26 RB COND SUPP CHECK M-230 Sh 2 / C-5 A/C ACT

CS-261 EMERGENCY FW PUMP M-204 Sh 3 / D-6 C ACT SUCTION HOR CHECK

CS-262 EMERGENCY FW PUMP M-204 Sh 3 / D-6 C ACT SUCTION HOR CHECK

Valve Summary Listing

Page 3 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

1 14 CK SA C 0/C

1 14 CK SA C 0/C

2 1 GA H C C

2 3 CK SA C 0/C

3 8 CK SA C C

3 8 CK SA C C

TEST

FAIL REQ

N/A LT

eve

cvo

PSO

N/A LT

eve cvo PSO

N/A MS

RPI

LTJ

N/A LTJ

eve

cvo

N/A BOO

eve

N/A BOO

eve

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 31 of 165

FREQ PROCEDURE NOTES

2Y 1104.001 1104.001S4

CM 1104.001 CVCM 1104.001S4

CM 1104.001 CVCM 1104.001S2

CM 1104.001 CVCM 1104.001S1

2Y 1104.001 1104.001S5

CM 1104.001 CVCM 1104.001S5

CM 1104.001 CVCM 1104.001S3

CM 1104.001 CVCM 1104.001S1

2Y 1305.007 1305.007S2

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A17

AppJ 1305.018 1305.018A40

CM 1305.018 CVCM 1305.018A40

CM 1305.007 CVCM 1305.007S1A

R 1305.042 ROJ-007

R 1305.042 ROJ-007

R 1305.042 ROJ-007

R 1305.042 ROJ-007

Page 35: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CS-293 EFW SUCTION LINE M-204 Sh 5 / D-8 C ACT CHECK VALVE

CS-294 EFW SUCTION LINE M-204 Sh 5 / D-8 C ACT CHECK VALVE

CS-98 EMERGENCY FW PUMP M-204 Sh 3 / D-6 C ACT SUCTION HDR CHECK

CS-99 EMERGENCY FW PUMP M-204 Sh 3 / D-6 C ACT SUCTION HDR CHECK

CV-1000 PZRERV ISOL M-230 Sh 1 / G-5 A ACT

Valve Summary Listing

Page 4 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 10 CK SA C 0/C

3 10 CK SA C 0/C

3 8 CK SA C C

3 8 CK SA C C

1 4 GA MO 0 0/C

I

TEST

FAIL REQ

N/A eve cvo

PSO

N/A eve cvo

PSO

N/A BDO

eve

N/A BDO

eve

FAI LT

RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 32 of 165

FREQ PROCEDURE NOTES

CM 5120.410 CVCM

CM 1106.006 CVCM 1106.006S15

Q 1106.006 1106.006S11

-- 1106.006S12 1106.006S15

CM 5120.410 CVCM

CM 1106.006 CVCM 1106.006S15

Q 1106.006 1106.006S11 1106.006S12 1106.006S15.

R 1305.042 ROJ-007

R 1305.042 ROJ-007

R 1305.042 ROJ-007

R 1305.042 ROJ-007

2Y 1103.005 1103.005S2

2Y 1305.007 1305.007S2

Q 1305.007 1305.007S1 B

Q - 1305.007 1305.007S1B

Q 1305.007 1305.007S1B

Q 1305.007 1305.007S1 B

Page 36: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 11ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1050 DH SUCTISOL M-230 Sh 1 / F-5 A ACT

CV-1052 QUENCH TANK OUTLET- M-230 Sh 2 / A-6 A ACT ISOL. VALVE OUTSIDE RB

CV-1053 QUENCH TK OUT ISOL M-230 Sh 2 / A-6 A ACT

CV-1054 QUENCH TK T-42 GAS M-230 Sh 2 / B-6 A ACT SPACE SAMPLE ISOL

Valve Summary Listing

Page 5 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

1 12 GA MO C 0/C

2 3 GA AO 0/C C

2 3 GA MO 0/C C

2 1 GA MO 0/C C

TEST

FAIL REQ

FAI LT

RPI

ETC

ETO

STC

STO

C RPI

LTJ

ETC

FSC

STC

FAI RPI

LTJ

ETC

STC

FAI RPI

LTJ

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 33 of 165

FREQ PROCEDURE NOTES

2Y 1104.004 1104.00486

2Y 1104.004 1104.004S3

cs 1104.004 CSJ-011 1104.00483

cs 1104.004 CSJ-011 1104.00483

cs 1104.004 CSJ-011 1104.004S3

cs 1104.004 CSJ-011 1104.004S3

2Y ., 1305.007 1305.007S2

AppJ 1305.018 1305.018A90

Q 1305.007, 1305.007S1 B

Q 1305.007 1305.00781B

Q 1305.007 1305.007S1B

2Y 1305.007 1305.00782

AppJ 1305.018 1305.018A91

Q 1305.007 1305.00781A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A6

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Page 37: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1065 COND TRANSFER M-230 Sh 2 / C-4 A ACT SUPPLY TO QUENCH TANK

CV-1206 RCP SEAL INJECTION M-231 Sh 1 / E-2 B ACT

- BLOCK

CV-1214 LD CLR E-29A OUT ISOL M-231 Sh 2 / H-7 A ACT

CV-1216 LD CLR E-29B OUT !SOL: M-231 Sh 2 / E-7 A. ACT

CV-1219 HPI TO P-32C M-231 Sh 3 / D-7 B ACT DISCHARGE

'

Valve Summary Listing

Page 6 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 3 GA AO 0/C C

2 2 GA MO 0 C

1 2.5 GA MO 0 C

1 2.5 GA MO 0 C

2 2.5 GL MO C 0/C

TEST

FAIL REQ

C RPI

LTJ

ETC

FSC

STC

FAI RPI

ETC

STC

FAI RPI

LTJ

ETC

STC

FAI RPI

LTJ

ETC

STC

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 34 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A39

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1104.002 1104.002S9

cs 1104.002 CSJ-032 1104.002S9

cs 1104.002 CSJ-032 1104.002S9

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A19

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A20

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

Page 38: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1220 HPI TO P-320 M-231 Sh 3 / C-7 B ACT DISCHARGE

CV-1221 LETDOWN COOLERS M-231 Sh 2 / G-6 A ACT OUTLET

\

CV-1227 HPI TO P-32B M-231 Sh 3 / G-3 B ACT DISCHARGE

CV-1228 HPI TO P-32A M-231 Sh 3 / F-3 B ACT DISCHARGE

CV-1233 PRESSURIZER MAKEUP M-231 Sh 1 / F-2 B ACT BLOCK VALVE

Valve Summary Listing

Page 7 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 2.5 GL MO C 0/C

2 2.5 GA MO 0 C

2 2.5 GL MO C 0/C

2 2.5 GL MO C 0/C

2 2.5 GA MO 0 C

TEST

FAIL REQ~

FAI RPI

ETC

ETO

STC

STO

FAI RPI

LTJ

ETC

STC

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 35 of 165

FREQ PROCEDURE NOTES

2Y 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A18

Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S1B

2Y 1104.002 1104.002S2

Q 1104.002 1104.002S2

Q 1104.002 1104.002S2

Q 1104.002 1104.002S2

Q 1104.002 1104.002S2

2Y 1104.002 1104.002S2

Q 1104.002 1104.002S2

Q 1104.002 1104.002S2

Q 1104.002 1104.002S2

Q 1104.002 1104.002S2

2Y 1305.007 1305.007S2

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Page 39: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1234 PRESSURIZER MAKEUP M-231 Sh 1 / G-2 B ACT BLOCK VALVE

CV-1270 P32D SEAL RETURN M-231 Sh 2 / A-6 A ACT

CV-1271 P-32C SEAL RETURN M-231 Sh 2 / C-6 A ACT

CV-1272 P328 SEAL RETURN M-231 Sh 2 / D-6 A ACT

CV-1273 P-32A SEAL RETURN M-231 Sh 2 / E-6 A ACT

CV-1274 RCP BLEEDOFF NORMAL M-231 Sh 2 / E-5 A ACT RETURN

Valve Summary Listing

Page 8 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 2.5 GA MO 0 C

2 1 GA MO 0 C

2 1 GA MO 0 C

2 1 GA MO 0 C

2 1 GA MO 0 C

2 1 GA MO 0 C

TEST

FAIL REQ

FAI RPI

ETC

STC

FAI RPI

LTJ

ETC

STC

FAI RPI

LTJ

ETC

STC

FAI RPI

LTJ

ETC

STC

FAI RPI

LTJ

ETC

STC

FAI RPI

LTJ

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 36 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S2

Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S18

2Y 1104.002 1104.002S6

AppJ 1305.018 1305.018A 11

cs 1104.002 CSJ-009 1104.002S6

cs 1104.002 CSJ-009 1104.002S6

2Y 1104.002 1104.002S6

AppJ 1305.018 1305.018A10

cs 1104.002 CSJ-009 1104.002S6

cs 1104.002 CSJ-009 1104.002S6

2Y 1104.002 1104.002S6

AppJ 1305.018 1305.018A9

cs 1104.002 CSJ-009 1104.002S6

cs 1104.002 CSJ-009 1104.002S6

2Y 1104.002 1104.002S6

AppJ 1305.018 1305.018A8

cs 1104.002 CSJ-009 1104.002S6

cs 1104.002 CSJ-009 1104.002S6

2Y 1104.002 1104.002S6

AppJ 1305.018 1305.018A7

cs 1104.002 CSJ-009 1104.002S6

cs 1104.002 CSJ-009 1104.002S6

Page 40: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1275 MAKEUP TANK OUTLET M-231 Sh 1 / D-7 B/C ACT

CV-1276 'A' DH LOOP DISCH TO M-231 Sh 1 / G-7 B ACT MU PUMP P-36A SUCTION

CV-1277 'B' DH LOOP DISCH TO M-231 Sh 1 / B-7 B ACT MU PUMP P-36C SUCTION

Valve Summary Listing

Page 9 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 4 SCK MO 0 C

2 4 GA MO C 0/C

,

2 4 GA MO C 0/C

TEST

FAIL REQ

FAI RPI

ETO

STO

eve

ETC

STC

BOO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 37 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S2

cs 1305.007 1305.007S2

cs 1305.007 1305.007S2

cs 1104.002 CSJ-028 1104.002S8 1104.002S9

cs 1305.007 CSJ-028 1305.007S2

cs 1305.007 CSJ-028 1305.007S2

Q 1305.007 1305.007S1A

2Y 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

2Y 1104.002 1104.002S2

Q 1104.002 1104.002S2

Q 1104.002 1104.002S2

Q 1104.002 1104.002S2

Q 1104.002 1104.002S2

Page 41: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1278 HPI TO P-32A DISCH M-231 Sh 3 / D-3 B ACT

CV-1279 HPI TO P-32B DISCH M-231 Sh 3 / C-3 B ACT

CV-1284 'C' HPI BLOCK VALVE M-231 Sh 3 / G-7 B ACT

CV-1285 HPI TO P-32D DISCH M-231 Sh 3 / F-7 B ACT

Valve Summary Listing

Page 10 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 2.5 GL MO C 0/C

2 2.5 GL MO C 0/C

2 2.5 GL MO C 0/C

2 2.5 GL MO C 0/C

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 38 of 165

FREQ PROCEDURE NOTES

2Y 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

2Y 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.002S1

Q 1104.002 1104.00281

Q 1104.002 1104.00281

2Y 1104.002 1104.00282

Q 1104.002 1104.00282

Q 1104.002 1104.00282

Q 1104.002 -1104.002S2

Q 1104.002 1104.00282

2Y 1104.002 1104.002S2

Q 1104.002 1104.00282

Q 1104.002 1104.002S2

Q 1104.002 1104.00282

Q 1104.002 1104.00282

Page 42: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1300 SEAL RTN CLR ISOL M-231 Sh 1 / G-4 B ACT

'

CV-1301 MU PUMPS RECIRC ISOL M-231 Sh 1 / F-4 B ACT

'

CV-1400 LPI/DECAY HEAT BLOCK M-232 Sh 1 / F-1 B ACT

CV-1401 LPI/DECAY HEAT BLOCK M-232 Sh 1 / G-1 B ACT

Valve Summary Listing

Page 11 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 2 GA MO 0 C

2 2 GA MO 0 C

2 10 GA MO C 0/C

2 10 GA MO C 0/C

TEST

FAIL REQ

FAI RPI

ETC

STC

FAI RPI

ETC

STC

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 39 of 165

FREQ PROCEDURE NOTES

2Y 1104.002 1104.00288 1104.00289

cs 1104.002 CSJ-010 1104.00288 1104.00289

cs 1104.002 CSJ-010 1104.00288 1104.00289

2Y 1104.002 1104.00288 1104.00289

cs 1104.002 CSJ-010 1104.00288 1104.00289

cs 1104.002 CSJ-010 1104.00288 1104.002S9

2Y 1104.004 1104.004S12

Q 1104.004 1104.004S12 1104.00482

Q 1104.004 1104.004812 1104.00482

Q 1104.004 1104.004812 1104.00482

Q 1104.004 1104.004S12 1104.00482

2Y 1104.004 1104.004811

Q 1104.004 1104.004S1 1104.004S 11

Q 1104.004 1104.00481 1104.004811

Q 1104.004 1104.00481 1104.004S11

Q 1104.004 1104.004S1 1104.004811

Page 43: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1404 P-34A/B SUCT SUPP M-232 Sh 1 / C-7 B ACT FROM RCS

CV-1405 RB SUMP LINE A OUTLET M-232 Sh 1 / 8-7 B ACT

CV-1406 RB SUMP LINE B OUTLET M-232 Sh 1 / A-7 B ACT

CV-1407 BWST T-3 OUTLET M-232 Sh 1 / F-7 B ACT

Valve Summary Listing

Page 12 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 12 GA MO C 0/C

2 14 GA MO C 0/C

2 14 GA MO C 0/C

2 14 GA MO C 0/C

l

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 40 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S2

Q 1305.007 1305.007S1A

Q - 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S2

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S2

.Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S1B

Q 1305.007 1305.007S1B

Q 1305.007 1305.007S1 B

2Y 1104.004 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

(

Page 44: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1408 BWST T-3 OUTLET M-232 Sh 1 / F-7 B ACT

CV-1410 DECAY HEAT SUCTION M-232 Sh 1 / B-8 A ACT FROM RCS ISOL

CV-1414 RB SUMP - LINE A M-232 Sh 1 / B-8 B ACT OUTLET (INSIDE RB)

-

CV-1415 RB SUMP - LINE B M-232 Sh 1 / A-8 B ACT OUTLET (INSIDE RB)

Valve Summar,y Listing

Page 13 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 14 GA MO C 0/C

2 12 GA MO C 0/C

2 14 GA MO 0 0/C

2 14 GA MO 0 0/C

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

FAI LT

RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 41 of 165

FREQ PROCEDURE NOTES

2Y 1104.004 1104.004S12

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

2Y 1104.004 1104.004S6

2Y 1104.004 1104.004S3

cs 1104.004 CSJ-011 1104.004S3

cs 1104.004 CSJ-011 1104.004S3

cs 1104.004 CSJ-011 1104.004S3

cs 1104.004 CSJ-011 1104.004S3

2Y 1305.007 1305.007S2

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S2

Q 1305.007 1305.007S1B

Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S1 B

Page 45: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1416 PZR AUX SPRAY VALVE M-232 Sh 1 / D-1 A ACT

/ -

CV-1428 OHR COOLER E-35A M-232 Sh 1 / G-3 B ACT OUTLET

CV-1429 OHR COOLER E-358 M-232 Sh 1 / E-3 B ACT OUTLET

Valve Summary Listing

Page 14 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 1.5 GL MO C 0/C

2 10 GL MO 0 0

2 10 GL MO 0 0

--

TEST

FAIL REQ

FAI RPI

LTJ

ETC

ETO

STC

STO

FAI RPI

ETC

STC

ETO

STO

FAI RPI

ETO

/

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 42 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A37

cs 1305.007 CSJ-031 1305.007S2

cs 1305.007 CSJ-031 1305.007S2

cs 1305.007 CSJ-031 1305.007S2

cs 1305.007 CSJ-031 1305.007S2

2Y 1104.004 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S 11

Q 1104.004 1104.004S1 1104.004S11

2Y 1104.004 1104.004S12

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Page 46: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 11ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1432 DECAY HEAT COOLER E- M-232 Sh 1 / B-3 B ACT 35B BYPASS

i

CV-1433 DH CLR E-35A BYPASS M-232 Sh 1 / E-3 B ACT

CV-1434 DECAY HEAT P-34A M-232 Sh 1 / D-6 B ACT SUCTION FROM RCS

Valve Summary Listing

Page 15 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 6 BF AO C 0/C

2 6 BF AO C 0/C

2 12 GA MO C 0/C

TEST

FAIL REQ

C ETC

ETO

FSC

STC

STO

C ETC

ETO

FSC

STC

STO

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 43 of 165

FREQ PROCEDURE NOTES

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S1 1104.004S 11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

2Y 1104.004 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S 11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Page 47: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1435 DECAY HEAT P-348 M-232 Sh 1 / D-6 8 ACT SUCTION FROM RCS

CV-1436 DECAY HEAT P-34A M-232 Sh 1 / E-7 8 ACT SUCTION FROM BWST

CV-1437 DECAY HEAT P-348 M-232 Sh 1 / 8-7 8 ACT SUCTION FROM BWST

CV-1438 BWST PURIF RECIRC ISO M-232 Sh 1 / H-4 8 ACT DOWNSTRM

Valve Summary Listing

Page 16 of 63

CLASS SIZE TYPE ACT POSITION-

NORM SAFE

2 12 GA MO C 0/C

2 14 GA MO 0 0/C

-

2 14 GA MO 0 0/C

2 4 GA MO 0 C

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 44 of 165

FREQ PROCEDURE NOTES

2Y 1104.004 1104.004S12

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

2Y, 1104.004 1104.004S11

Q 1104.004 1104.004S1 1104.004S 11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

2Y 1104.004 1104.004S12

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

2Y 1305.007 1305.007S2

Q 1305.007 1305.007S18

Q 1305.007 1305.007818

Page 48: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1441 BWST PURIF RECIRC ISO M-232 Sh 1 / H-4 B ACT UPSTRM

CV-1616 NAOH TO P-34A/P-35A M-233 Sh 1 / E-1 A ACT SUCTION

CV-1617 NAOH TO P-349 & P35B M-233 Sh 1 / E-1 A ACT SUCT

CV-1814 PRESSURIZER STEAM M-237 Sh 1 / G-7 A PASS SPACE SAMPLE VALVE

CV-1816 PRESSURIZER WATER M-237 Sh 1 / G-7 A PASS SPACE SAMPLE VALVE

Valve Summary Listing

Page 17 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 3 GA MO 0 C

3 4 GA MO C 0/C

3 4 GA MO C 0/C

1 0.75 GA MO C C

1 0.75 GA MO C C

TEST

FAIL REQ

FAI RPI

ETC

STC

FAI LT

RPI

ETC

ETO

STC

STO

FAI LT

RPI

ETC

ETO

STC

STO

FAI RPI

LTJ

ETC

STC

FAI RPI

LTJ

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 45 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1104.004S2

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y OP-TBD

2Y 1104.005 1104.005S8

R 1104.005 ROJ-001 1104.005S8

R 1104.005 ROJ-001 1104.005S8

R 1104.005 ROJ-001 1104.005S8

R 1104.005 ROJ-001 1104.005S8

2Y OP-TBD

2Y 1104.005 1104.005S8

R 1104.005 ROJ-001 1104.005S8

R 1104.005 ROJ-001 1104.005S8

R 1104.005 ROJ-001 1104.005S8

R 1104.005 ROJ-001 1104.005S8

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A3

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A2

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Page 49: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-1820 SG E24A SAMPLE ISOL M-237 Sh 1 / F-7 A PASS \

CV-1826 SG E24B SAMPLE ISOL M-237 Sh 1 / E-7 A PASS -

CV-1845 QUENCH TK GAS SPACE M-237 Sh 1 / A-7 A ACT OUTSIDE RB ISOL

CV-2214 RCP SEAL CLR & L TON M-234 Sh 2 / G-6 A ACT CLRS NUC ICW RTN ISOL

Valve Summary Listing

Page 18 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 1 GL MO C C

2 1 GL MO C C

2 0.5 GL AO C C

2 8 GA AO O' C

TEST

FAIL REQ

FAI RPI

LTJ J

FAI RPI

LTJ

C RPI

LTJ

ETO

STO

ETC

FSC

STC

C RPI

LTJ

ETC

FSC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 46 of 165

-FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A13

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A14

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A5

Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S18

Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S18

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A78

cs 1305.007 CSJ-014 1305.007S2

cs 1305.007 CSJ-014 1305.007S4

cs 1305.007 CSJ-014 1305.007S2

Page 50: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 11ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-2215 RCP SEAL CLR & L TON M-234 Sh 2 / F-6 A ACT CLRS ICW RTN ISOL FROM RB

-

CV-2220 RCP MTR AIR & LO CLRS M-234 Sh 1 / H-4 A ACT & CRD NON-NUC ICW OUTISOL

CV-2221 CRD CLNG & RCP MTR M-234 Sh 1 / H-4 A ACT AIR & LO CLR COMBINED RTN ISOL

Valve Summary Listing

Page 19 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 8 GA MO 0 C

--

2 8 GA MO 0 C

2 8 GA MO 0 C

TEST

FAIL REQ

FAI RPI

LTJ

ETC

STC

FAI RPI

LTJ

ETC

STC

FAI RPI

LTJ

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 47 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A79

cs 1305.007 CSJ-014 1305.007S2

cs 1305.007 CSJ-014 1305.007S2

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A76

cs 1305.007 CSJ-013 1305.007S2

cs 1305.007 CSJ-013 1305.007S2

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A77

cs 1305.007 CSJ-013 1305.007S2

cs 1305.007 CSJ-013 1305.007S2

Page 51: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-2233 RCP SEAL CLR & L TON M-234 Sh 2 I C-4 A ACT CLRS NUC ICW SUPPLY ISOL

CV-2234 RCP MTR AIR & LO CLRS M-234 Sh 1 / E-6 A ACT NON-NUC ICW SUPP ISOL

CV-2235 CRD NON-NUC ICW INLET M-234 Sh 1 / E-4 A ACT RB ISOL

Valve Summary Listing

Page 20 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 8 GA AO 0 C

2 8 GA AO 0 C

2 3 GA MO 0 C

TEST

FAIL REQ

C RPI

LTJ

ETC

FSC

STC

c' RPI

LTJ

ETC

FSC

STC

FAI RPI

LTJ

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 48 of 165

FREQ PROCEDURE NOTES

2Y. 1305.007 1305.007S2

AppJ 1305.018 1305.018A68

cs 1305.007 CSJ-014 1305.00782

cs 1305.007 CSJ-014 1305.007S4

cs 1305.007 CSJ-014 1305.007S2

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A61

cs 1305.007 CSJ-027 1305.00782

cs 1305.007 CSJ-027 1305.007S4

cs 1305.007 CSJ-027 1305.00782

2Y 1305.007 1305.00782

AppJ 1305.018 1305.018A55

cs 1305.007 CSJ-012 1305.00782

cs 1305.007 CSJ-012 1305.00782

Page 52: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-2400 B RB SPRAY BLOCK M-236 Sh 1 / F-5 A ACT

CV-2401 A RB SPRAY BLOCK M-236 Sh 1 / F-5 A ACT

CV-2415 CORE FLOOD TANK T-2A M-236 Sh 1 / B-5 B PASS ·ouTLET ISOL

CV-2416 CORE FLOODING TANK M-236 Sh 1 / C-5 A ACT T-2A BLEED/SAMPLE ISOL VLV

CV-2417 CORE FLOODING TANK M-236 Sh 1 / D-5 B PASS T-2AVENT

Valve Summary Listing

Page 21 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 8 GL MO C 0/C

2 8 GL MO C 0/C

2 14 GA MO 0 0

2 1 GL MO 0/C C

2 1 GL MO C C

TEST

FAIL REQ

FAI LT

RPI

ETC

ETO

STC

STO

FAI LT

RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

FAI RPI

LTJ

~

ETC

STC

FAI RPI

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 49 of 165

FREQ PROCEDURE NOTES

2Y OP-TBD

2Y 1104.005 1104.005S4

Q 1104.005 1104.005S4

Q 1104.005 1104.005S4

Q 1104.005 1104.005S4

Q 1104.005 1104.005S4

2Y OP-TBD

2Y 1104.005 1104.005S2

Q 1104.005 1104.005S2

Q 1104.005 1104.005S2

Q 1104.005 1104.005S2

Q 1104.005 1104.005S2

2Y 1104.001 1104.001S2

Q 1104.001 1104.001S2

-

Q 1104.001 1104.001S2

2Y 1305.007 1305.007S2 1305.007S7

AppJ 1305.018 1305.018A17

Q 1305.007 1305.007S2 1305.007S7

Q 1305.007 1305.007S2 1305.007S7

2Y 1104.001 1104.001S4

Page 53: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-2418 CORE FLOODING TANK M-236 Sh 1 / C-4 A ACT T-2B BLEED/SAMPLE ISOL VLV

CV-2419 CORE FLOOD TANK T-2B M-236 Sh 1 / B-3 B PASS OUTLET ISOL

CV-2420 CORE FLOODING TANK M-236 Sh 1 / D-3 B PA~ T-2B VENT

CV-2613 EFW PP TURBINE K-3 M-204 Sh 6 / F-5 B ACT STEAM ADMISSION VLV

CV-2615 EFW PUMP TURBINE K3 M-204 Sh 6 / F6 B ACT STEAM ADMISSION VALVE BYPASS

CV-2617 EFW PP TURBINE K-3 M-204 Sh 6 / G-7 B ACT STEAM FROM SG-B

-

Valve Summary Listing

Page 22 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 1 GL MO 0/C C

2 14 GA MO 0 0

2 1 GL MO C C

3 4 GA MO C 0/C

3 2 GA MO C 0

2 4 GA MO 0 0/C

TEST

FAIL REQ

FAI RPI

LTJ

ETC

STC

FAI RPI

ETO

FAI RPI

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETO

STO

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 50 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S2 1305.007S7

AppJ 1305.018 1305.018A17

Q 1305.007 1305.007S2 1305.007S7

Q 1305.007 1305.007S2 1305.007S7

2Y 1104.001 1104.001S3

cs 1104.001 1104.001S3

2Y 1104.001 1104.001S5

2Y 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

2Y 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

2Y 1106.006 1106 .. 006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Page 54: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-2619 ATMOS DUMP 'B' BLOCK M-206 Sh 1 / H-2 B ACT VALVE

'

CV-2620 EFW P-7A TO SG-B ISOL M-204 Sh 3 / C-2 B ACT

CV-2626 EFW P-7B TO SG-B ISOL M-204 Sh 3 / D-2 B ACT

CV-2627 EFW P-7A TO SG-A ISOL M-204 Sh 3 / F-2 B ACT

Valve Summary Listing

Page 23 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 10 GA MO C 0/C

(

2 4 GA • MO 0 0/C

2 4 GA MO 0 0/C

2 4 GA MO 0 0/C

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 51 of 165

FREQ PROCEDURE NOTES

2Y 1105.005 1105.005S3

cs 1105.005 CSJ-030 1105.005S3

cs 1105.005 CSJ-030 1105.005S3

cs 1105.005 CSJ-030 1105.005S3

cs 1105.005 CSJ-030 1105.005S3

2Y 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q \. 1106.006 1106.006S14

2Y 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

2Y 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Page 55: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-2630 FW ISO CONTROL VALVE M-206 Sh 1 / D-2 B ACT TO OTSG 'B'

'.

CV-2645 P-7A TO SG-A CONTROL M-204 Sh 3 / F-3 B ACT

CV-2646 P-7B TO SG-A CONTROL M-204 Sh 3 / G-3 B ACT VALVE

Valve Summary Listing

Page 24 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 18 GA MO 0 C

3 4 GL so 0 0/C

3 4 GL so 0 0/C

TEST

FAIL REQ

FAI RPI

ETC

STC

0 RPI

'--

ETO

FSO

STO

ETC

STC

0 RPI

ETO

FSO

STO

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 52 of 165

FREQ PROCEDURE NOTES

2Y 1102.001 1102.001S3

cs 1102.001 CSJ-002 1102.001S3

cs 1102.001 CSJ-002 1102.001S3

2Y 1106.006 1106.006S12 1106.006S16

Q 1106.006 1106.006S12 1106.006S 16

Q 1106.006 1106.006S12 1106.006S16/

Q 1106.006 1106.006S12 1106.006S16

Q 1106.006 1106.006S12 1106.006S16

Q 1106.006 1106.006S12 1106.006S16

2Y 1106.006 1106.006S11 1106.006S15

Q 1106.006 1106.006S11 1106.006S15

Q 1106.006 1106.006S11 1106.006S15

Q 1106.006 1106.006S11 1106.006S15

Q 1106.006 1106.006S11 1106.006S15

Q 1106.006 1106.006S11 1106.006S15

Page 56: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 ls'T Plan

VALVE ID FUNCTION DRAWING/COOR· CAT ACT/ PASS

CV-2647 P-7A TO SG-B CONTROL M-204 Sh 3 / C-3 B ACT

CV-2648 P-78 TO SG-B CONTROL M-204 Sh 3 / D-3 B ACT VALVE

J

Valve Summary Listing

Page 25 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 4 GL so 0 0/C

3 4 GL so 0 0/C

TEST

FAIL REQ

0 RPI

ETO

FSO

STO

ETC

STC

0 RPI

ETO

FSO

STO

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 53 of 165

FREQ PROCEDURE NOTES

2Y 1106.006 1106.006S12 1106.006S16

Q 1106.006 1106.006S12 1106.006S16

Q 1106.006 1106.006S12 1106.006S16

Q 1106.006 ' 1106.006S12

1106.006S16 Q 1106.006

1106.006S12 1106.006S 16

Q 1106.006 1106.006S12 1106.006S16

2Y 1106.006 1106.006S11 1106.006S15

Q 1106.006 1106.006S11 1106.006S15

Q 1106.006 1106.006S11 1106.006S15

Q 1106.006 1106.006S11 1106.006S15

Q 1106.006 1106.006S11 1106.006S15

Q 1106.006 1106.006S11 ' 1106.006S15

Page 57: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-2663 EFW PUMP TURBINE K-3 M-204 Sh 6 / H-5 B ACT STEAM ADMISSION VLV

CV-2665 EFW PUMP TURBINE K3 M-204 Sh 6 / G6 B ACT STEAM ADMISSION VALVE BYPASS

CV-2667 EFW PP TURBINE K-3 M-204 Sh 6 / F-7 B ACT STEAM FROM SG-A

CV-2670 EFW P-7B TO SG-A ISOL M-204 Sh 3 / G-2 B ACT

Valve Summary Listing

Page 26 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 4 GA MO C 0/C

~

3 2 GA MO C 0

2 4 GA MO 0 0/C

2 4 GA MO 0 0/C

'

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETO

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC,

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 54 of 165

FREQ PROCEDURE NOTES

-2Y 1106.006 1106.006S14

r

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

2Y 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

2Y 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

2Y 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

Page 58: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-2676 - ATMOS DUMP 'A' BLOCK M-206 Sh 1 / H-7 B ACT VALVE

CV-2680 FW ISO CONTROL VL V M-206 Sh 1 / D-7 B ACT TOSTMGENA

CV-2691 MAIN STEAM ISOLATION M-206 Sh 2 / E-7 B ACT VALVE A

CV-2692 MAIN STEAM ISOLATION M-206 Sh 2 / E-5 B ACT VALVE B

CV-2800 EFW P-7B SUCTION M-204 Sh 3 / F-7 B ACT FROM CST

Valve Summary Listing

Page 27 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 10 GA MO C 0/C

2 18 GA MO 0 C

2 36 GL AO 0 C

2 36 GL AO 0 C

3 8 GA MO 0 0/C

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

STC

C RPI

ETC

FSC

STC

C RPI

ETC

FSC

STC

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 55 of 165

FREQ PROCEDURE NOTES

2Y 1105.005 1105.005S3

cs 1105.005 CSJ-030 1105.005S3

cs 1105.005 CSJ-030 1105.005S3

cs 1105.005 CSJ-030 1105.005S3

cs 1105.005 CSJ-030 1105.005S3

2Y 1102.001 1102.001S3

cs 1102.001 CSJ-002 1102.001S3

cs 1102.001 CSJ-002 1102.001S3

2Y 1102.001 1102.001S3

cs 1102.001 CSJ-001 1102.001S3

cs 1102.001 CSJ-001 1102.001S3

cs 1102.001 CSJ-001 1102.001S3

2Y 1102.001 1102.001S3

cs 1102.001 CSJ-001 1102.001S3

cs 1102.001 CSJ-001 1102.001S3

cs 1102.001 CSJ-001 1102.001S3

2Y 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

Page 59: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-2802 EFW P-7A SUCTION M-204 Sh 3 / C-7 8 ACT FROM CST

CV-2803 EFW P-78 SUCTION M-204 Sh 3 / G-7 8 ACT FROM SW

CV-2806 EFW P-7A SUCTION M-204 Sh 3 / 8-7 8 ACT FROM SW

CV-2869 EFW TEST RECIRC P-78 M-204 Sh 3 I E-3 8 PASS ISOL

CV-2870 EFW TEST RECIRC P-7A M-204 Sh 3 I E-3 8 PASS ISOL

CV-3640 '8' DISCH TO LOOP II SW M-209 Sh 1 / C-3 8 ACT

Valve Summary Listing

Page 28 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 8 . GA MO 0 0/C

3 6 GA MO C 0

3 6 GA MO C 0

/

3 4 GA MO C C

I

3 4 GA MO C C

3 18 BF MO 0/C 0/C

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETO

STO

FAI RPI

ETO

STO

FAI RPI

STC

FAI RPI

STC

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 56 of 165

FREQ PROCEDURE NOTES

2Y 1106.006 1106.006S14

Q 1106:006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

2Y 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

2Y 1106.006 1106.006S14

Q 1106.006 '\ 1106.006S14

Q 1106.006 1106.006S14

2Y 1106.006 1106.006S13

Q 1106.006 1106.006S13

2Y 1106:006 1106.006S14

Q 1106.006 1106.006S14

2Y 1104.029 1104.029S10

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Page 60: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-3642 P-4B TO P-4C DISCH M-209 Sh 1 / C-3 B ACT CROSSOVER

CV-3643 ACW LOOP ISOL M-209 Sh 1 / D-3 A ACT

--

CV-3644 P-4A TO P-4B DISCH M-209 Sh 1 / E-3 B ACT CROSSOVER

Valve Summary Listing

Page 29 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 18 BF MO 0/C 0/C

3 18 BF MO 0 C

3 18 BF MO 0/C 0/C

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

FAI LT

RPI

ETC

STC

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 57 of 165

FREQ PROCEDURE NOTES

2Y 1104.029 1104.029S10

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

2Y 1104.029 1104.029S4

2Y 1305.007 1305.007S2

cs 1305.007 CSJ-003 1305.007S2

cs 1305.007 CSJ-003 1305,007S2

2Y 1104.029 1104.029S8

Q 1104.029 1104.029S1 1104.029S8

Q 1104.029 1104.029S1 1104.029S8

Q 1104.029 1104.029S1 1104.029S8

Q 1104.029 1104.029S1 1104.029S8

Page 61: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-3646 P-4A TO P-48 DISCH M-209 Sh 1 / E-3 B ACT CROSSOVER

'

CV-3804 A RB SPRAY LO CLR E- M,210 Sh 1 / F-8 B ACT 47A SW INLET

CV-3805 B RB SPRAY LO CLR E- M-210 Sh 1 / E-8 B ACT 478 SW INLET

CV-3806 SERV WTR TO DG1 CLRS M-210 Sh 1 / F-5 B ACT

Valve Summary Listing

Page 30 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 18 BF MO 0/C 0/C

3 1.5 GL AO C 0

3 1.5 GL AO C 0

,

3 6 GA MO C 0

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

0 RPI

ETO I

FSO

STO

0 RPI

ETO

FSO

STO

FAI RPI

ETO

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 58 of 165

FREQ PROCEDURE NOTES

2Y 1104.029 1104.029S8

Q 1104.029 1104.029S1 1104.029S8

Q 1104.029 1104.029S1 1104.029S8

Q 1104.029 1104.02981 1104.029S8

Q 1104.029 1104.029S1 1104.02988

2Y 1104.005 1104.005S9

Q 1104.005 1104.00583 1104.00589

Q 1104.005 1104.005S3 1104.005S9

Q 1104.005 1104.005S3 1104.005S9

2Y 1104.005 1104.005810

Q 1104.005 1104.005810 1104.005S5

Q 1104.005 1104.005810 1104.00585

Q 1104.005 1104.005S10 1104.005S5

2Y 1305.007 1305.007S2

Q 1305.007 1305.00781A

Q 1305.007 1305.007S1A .

Page 62: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-3807 SERV WTR TO DG2 CLRS M-210 Sh 1 / E-5 B ACT

CV-3811 LOOP 2 SUPPLY TO ICW M-210 Sh 1 / H-4 A ACT COOLERS

c'

CV-3812 SW TO VCC-2A AND 28 M-210 Sh 1 / C-4 B ACT

CV-3813 LOOP II SW SUPPLY TO M-210 Sh 1 / B-4 B ACT VCC-2C AND 20

Valve Summary Listing

Page 31 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 6 GA MO C 0

3 14 BF MO 0 C

2 10 GA MO C 0/C

2 10 GA MO C 0/C

TEST

FAIL REQ

FAI RPI

ETO

STO

FAI LT

RPI

ETC

STC

FAI RPI

ETC

ETO

STC

STO

FAI RPI

LTJ

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 59 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S2

Q 1305.007_ 1305.007S1 B

Q 1305.007 1305.007S1B

2Y 1104.029 1104.029S4

2Y 1104.029 1104.02988

Q 1104.029 1104.029S1 1104.02988

Q 1104.029 1104.029S1 1104.029SB

2Y 1104.033 1104.03386

Q 1104.033 1104.03386

Q 1104.033 1104.03386

Q 1104.033 1104.03386

Q 1104.033 1104.03386

2Y 1104.033 1104.033S5

AR 1305.018 1305.018A23

Q 1104.033 1104.033S5

Q 1104.033 1104.033S5

Q 1104.033 1104.033S5

Q 1104.033 1104.033S5

Page 63: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-3814 SW OUTLET TO VCC-2A M-210 Sh 1 / D-2 B ACT AND2B

CV-3815 VCC-2C/D OUTLET M-210 Sh 1 / C-2 B ACT

CV-3820 LOOP 1 SUPPLY TO ICW M-210 Sh 1 / H-3 A ACT COOLERS

CV-3821 DECAY HEAT CLR M-210 Sh 1 / H-8 B ACT 0 SERVICE WTR E-35B

INLET

Valve Summary Listing

Page 32 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 10 BF MO C 0/C

2 10 BF MO C 0/C

3 14 BF MO 0 C

3 12 BF MO C 0

TEST

FAIL REQ

FAI RPI

LTJ

ETC

ETO

STC

STO

FAI RPI

LTJ

ETC

ETO

STC

STO

FAI LT

RPI

ETC

STC

FAI RPI

ETO

STO

Program Section No. SEP-AN0-1-IST -2

Revision No. 5

Page 60 of 165

FREQ PROCEDURE NOTES

2Y 1104.033 1104.033S6

AR 1305.018 1305.018A80

Q 1104.033 1104.033S6

Q 1104.033 1104.033S6

Q 1104.033 1104.033S6

Q 1104.033 1104.033S6

2Y 1104.033 1104.033S5

AR 1305.018 1305.018A22

Q 1104.033 1104.033S5

Q 1104.033 1104.033S5

Q 1104.033 1104.033S5

Q 1104.033 1104.033S5

2Y 1104.029 1104.029S10

2Y 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

2Y 1104.004 1104.004S12

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Page 64: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-3822 DECAY HEAT CLR M-210 Sh 1 / H-8 B ACT SERVICE WTR E-35A INLET

CV-3823 SERVICE WATER DISCH M-210 Sh 1 / A-5 B ACT TO EMERGENCY POND -

'

CV-3824 SW RTN TO DISCH M-210 Sh 1 / E-2 A ACT FLUME

CV-3840 LPI/DECAY HEAT PUMP M-210 Sh 1 / C-8 B ACT BRG CLR E-50A INLET

Valve Summary Listing

Page 33 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 12 BF MO C 0

3 18, BF MO C 0

3 18 BF MO 0 0/C

3 1.5 GL AO C 0

TEST

FAIL REQ

FAI RPI

ETO

STO

FAI MS

RPI

ETC

STC

ETO

STO

FAI LT

RPI

MS

ETC

ETO

STC

STO

0 RPI

ETO

FSO

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 61 of 165

FREQ PROCEDURE NOTES

2Y 1104.004 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

2Y OP-TBD

2Y 1305.007 1305.007S2

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1104.029 1104.029S4

2Y 1305.007 1305.007S2

2Y OP-TBD

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1104.004 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

Q 1104.004 1104.004S1 1104.004S11

,-

-, ~----~,-------------~~----------------------

Page 65: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 11ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

~

CV-3841 LPI/DECAY HEAT PP BRG M-210 Sh 1 / 0-8 B ACT CLR E-50B INLET

CV-3850 EFW SERV WTR LOOP I M-204 Sh 3 / H-8 B ACT ISOLATION

CV-3851 EFW SERV WTR LOOP II M-204 Sh 3 / A-8 B ACT ISOLATION

/ -

CV-4400 RB SUMP ISOLATION - M-213 Sh 2 / C-3 A ACT OUTSIDE RB

CV-4446 RB SUMP ISOLATION- M-213 Sh 2 / C-2 A ACT INSIDE RB

Valve Summary Listing

Page 34 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 1.5 GL AO C 0

3 6 GA MO C 0

3 6 GA MO C 0

2 4 GA AO 0/C C

2 4 GA MO 0/C C

TEST

FAIL REQ

0 RPI

ETO

FSO

STO

FAI RPI

ETO

STO

FAI RPI

ETO

STO

C RPI

LTJ

ETC

FSC

STC

FAI RPI

LTJ

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 62 of 165

FREQ PROCEDURE NOTES

2Y 1104.004 1104.004S12

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

Q 1104.004 1104.004S12 1104.004S2

2Y 1106.006 1106.006S13

Q 1106.006 1106.006S13

Q 1106.006 1106.006S13

2Y 1106.006 1106.006S14

Q 1106.006 1106.006S14

Q 1106.006 1106.006S14

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A85 1305.018A86

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A87

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

/

Page 66: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-4803 RB VENT HEADER ISOL M-215 Sh 1 / H-7 A ACT VALVE INSIDE RB

CV-4804 RBVH ISOL TO T-17 M-215 Sh 1 / H-6 A ACT OUTSIDE RB

CV-5611 FIREWATER TO RB M-219 Sh 1 / E-5 A ACT OUTSIDE ISOL

CV-5612 INSIDE REACTOR M-219 Sh 1 / E-6 A ACT BUILDING ISOLATION

CV-6202 CH WS RB INLET ISO M-222 Sh 1 / F-5 A ACT

Valve Summary Listing

Page 35 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 2 GA MO 0/C C

2 2 GL AO 0/C C

2 3 GA MO 0/C C

2 3 GA MO 0/C C

2 6 GA AO 0 C

TEST

FAIL REQ

FAI RPI

LTJ

ETC

STC

C RPI

LTJ

ETC

FSC

STC

FAI RPI

LTJ

ETC

STC

FAI RPI

LTJ

ETC

STC

0/C RPI

LTJ

ETC

FSC

FSO

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 63 of 165

FREQ .PROCEDURE NOTES

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A16

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A 15

Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S1B

Q 1305.007 1305.007S1 B

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A41

Q 1305.007 - 1305.007S1A Q 1305.007

1305.007S1A

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A42

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A59

cs 1305.007 CSJ-004 1305.007S2 .. cs 1305.007 CSJ-004 1305.007S2

cs 1305.007 CSJ-004 1305.007S2

cs 1305.007 CSJ-004 1305.007S2

Page 67: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CV-6203 CH WS RB OUTLET ISO M-222 Sh 1 / F-5 A ACT

c'

' '

CV-6205 CHILL WTR RTN RB ISOL M-222 Sh 1 / F-4 A ACT

CV-6601A EFW TURBINE K-3 M-204 Sh 6 / E-3 B PASS TRIP/THROTTLE VALVE

CV-7401 RB PURGE OUTLET M-261 Sh 1 / G-8 A PASS

CV-7402 RB PURGE INLET M-261 Sh 1 / F-8 A PASS

CV-7403 RB PURGE OUTLET M-261 Sh 1 / G-7 A PASS

CV-7404 RB PURGE INLET M-261 Sh 1 / F-7 A PASS

'

CV-7444 H2 SAMPLER C178 M-261 Sh 3 I E-8 A ACT RETURN

Valve Summary Listing

Page 36 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 6 GA AO 0 C

2 6 GA MO 0 C

3 4 GL SA 0 0

2 54 BF AO C C

2 54 BF AO C C

2 54 BF AO C C

2 54 BF AO C C

2 2 GL MO 0 C

TEST

FAIL REQ

0/C RPI

LTJ

ETC

FSC

FSO

STC

FAI RPI

LTJ

ETC

STC

N/A RPI

C RPI c_

LTJ

C RPI

LTJ

C RPI

LTJ

C RPI

LTJ

FAI RPI

LTJ

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 64 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A7 4

cs 1305.007 CSJ-004 1305.007S2

cs 1305.007 CSJ-004 1305.007S2

cs 1305.007 CSJ-004 1305.007S2

cs 1305.007 CSJ-004 1305.007S2

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A75

cs 1305.007 CSJ-004 1305.007S2

cs 1305.007 CSJ-004 1305.007S2

2Y 1106.006 1106.006S12

2Y 1104.033 1104.033S4

AppJ 1305.037 1305.037S12

2Y 1104.033 1104.033S4

AppJ 1305.037 1305.037S11

2Y 1104.033 1104.033S4

AppJ 1305.037 1305.037S12

2Y 1104.033 1104.033S4

AppJ 1305.037 1305.037S11

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A64

Q 1305.007 1305.007S1B

Q 1305.007 1305.007S1B

Page 68: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ~

CV-7445 STANDBY H2 PURGE M-261 Sh 3 / D-6 A SUPPLYISOL

CV-7446 H2 SAMPLER M-261 Sh 3 / D-8 A C179/PASS/RAD MONITOR RETURN

CV-7448 H2 SAMPLER C178 M-261 Sh 3 / F-8 A SUPPLY

CV-7449 STANDBY H2 PURGE M-261 Sh 3 / G-7 A EXHAUST ISOL

CV-7450 RB H2 PURGE OUTLET M-261 Sh 3 / G-8 A ISOL TO VEF-37B

CV-7453 RB LEAK DETECTOR M-261 Sh 3 / A-8 A ISOL

ACT/ PASS

PASS

ACT

ACT

PASS

ACT

ACT

Valve Summary Listing

Page 37 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 2 GL MO C C

2 2 GL MO 0 C

2 2 GL MO 0 C

2 2 GL MO C C

2 2 GL MO 0 C

2 1 GL MO 0 C

TEST

FAIL REQ

FAI LTJ

FAI RPI

LTJ

ETO

STO

ETC

STC

FAI RPI

LTJ

ETC

STC

FAI LTJ

FAI RPI

LTJ

ETO

STO

ETC

STC

FAI RPI

LTJ

ETC

STC

Program Section No. SEP-ANO:-t-lST-2

Revision No. 5

Page 65 of 165

FREQ PROCEDURE NOTES

AppJ 1305.018 1305.018A25 1305.018A26

2Y 1305.007 1305.00782

AppJ 1305.018 1305.018A27

Q 1305.007 1305.00781A

Q 1305.007 1305.00781A

Q 1305.007 1305.00781A

Q 1305.007 1305.00781A

2Y 1305.007 1305.00782

AppJ 1305.018 1305.018A65 1305.018A66

Q 1305.007 1305. 007S 1 B

Q 1305.007 1305 .007S 1 B

AppJ 1305.018 1305.018A28

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A28

Q 1305.007 1305.00781A

Q 1305.007 1305.00781A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A31

Q 1305.007 1305.00781A

Q 1305.007 1305.00781A

Page 69: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

CZ-46 CZ TO RCS FILL LINE CK M-231 Sh 1 / H-6 C ACT

DH-12 PZR AUX SPRAY CK M-230 Sh 1 / G-5 NC ACT

DH-13A P34A LPI OUT CK M-230 Sh 1 / H-3 NC ACT

DH-13B P34B LPI OUT CK M-230 Sh 1 / G-3 NC,. ACT

DH-14A P34A LPI RX CK M-230 Sh 1 / F-5 NC ACT

DH-14B P34B LPI RX CK M-230 Sh 1 / F-4 NC ACT

DH-16 PZRAUX SPRAY CK M-230 Sh 1 / G-5 NC ACT

Valve Summary Listing

Page 38 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 2.5 CK SA C C

1 1.5 CK SA C 0/C

1 12 CK SA C 0/C

1 12 CK SA C 0/C

1 14 CK SA C 0/C

1 14 CK SA C 0/C

1 1.5 CK SA C 0/C

TEST

FAIL REQ

N/A BOO

eve

N/A LT

eve cvo

N/A LT

eve

cvo

N/A LT

eve

cvo

N/A LT

eve

cvo

N/A LT

eve

cvo

N/A LT

eve cvo

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 66 of 165

-FREQ PROCEDURE NOTES

CM 5120.410 CVCM

CM 5120.410 CVCM

2Y OP-TBD

CM OP-TBD CVCM

CM 1104.004 CVCM 1104.004S9

2Y 1102.001 1102.001S4

cs 1104.004 CSJ-029 1104.004S1 1104.004S 11

cs 1104.004 CSJ-029 1104.004S3

2Y 1102.001 1102.001S4

cs 1104.004 CSJ-029 1104.004S12 1104.004S2

cs 1104.004 CSJ-029 1104.004S3

2Y 1102.001 1102.001S4

CM 1102.001 CVCM 1102.001S4

CM 1104.004 CVCM 1104.004S3

2Y 1102.001 1102.001S4

CM 1102.001 CVCM (' '1102.001S4

CM 1104.004 CVCM 1104.004S3

2Y OP-TBD

CM OP-TBD CVCM

CM 1104.004 CVCM 1104.004S9

Page 70: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

DH-17 P34A X-OVER CK M-230 Sh 1 / H-3 A/C ACT

DH-18 P34B X-OVER CK M-230 Sh 1 / G-3 A/C ACT

DH-2A 'A' DH PUMP P34A DISCH M-232 Sh 1 / E-4 C ACT CK

DH-2B 'B' DH PUMP P34B DISCH M-232 Sh 1 / C-4 C ACT CK

DH-63 PRESSURIZER AUX M-232 Sh 1 / D-1 A PASS SPRAY VALVE

DH-93 DH TO PZR AUX SPRAY M-232 Sh 1 / D-2 A/C ACT

DH-96 RB PZR AUX SPRAY M-230 Sh 1 / G-4 A/C ACT CHECK

DWD-4411 RB SUMP SAMPLE ISOL M-213 Sh 2 / B-3 A PASS VALVE

Valve Summary Listing

Page 39 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

1 8 CK SA C 0/C

1 8 CK SA C 0/C

2 10 CK SA C 0

2 10 CK SA C 0

2 1 1/2 GA H LC C

2 1.5 CK SA C C

2 1.5 CK SA C 0/C

2 0.75 GL H C C

TEST

FAIL REQ

N/A LT

eve

cvo

N/A LT

eve

cvo

N/A cvo

BOC

N/A cvo

BOC

N/A LT

N/A LT

BOO I eve cvo

N/A LTJ

eve cvo

N/A LTJ

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 67 of 165

FREQ PROCEDURE NOTES

2Y 1102.001 1102.001S4

cs 1104.004 CSJ-029 1104.004S1 1104.004S11

cs 1104.004 CSJ-029 1104.004S3

2Y 1102.001 1102.001S4

cs 1104.004 CSJ-029 1104.004S12 1104.004S2

cs 1104.004 CSJ-029 1104.004S3

Q 1104.004 1104.004S1 1104.004S11

R 512Q.410 ROJ-004

Q 1104.004 1104.004S12 1104.004S2

R 5120.410 ROJ-004

2Y OP-TBD

2Y OP-TBD

Q 1305.041 1305.041S1

R 1305.041 ROJ-010 1305.041S1

R 1305.041 ROJ-010 1305.041S1

AppJ 1305.018 1305.018A38

CM 1305.018 CVCM 1305.018A38

CM 1104.004 CVCM 1104.004S9

AppJ 1305.018 1305.018A85

Page 71: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

FW-10A P-7A RECIRC CHECK M-204 Sh 3 / B-4 A/C ACT

FW-10B P-7B RECIRC CHECK M-204 Sh 3 / G-4 A/C ACT

FW-13A STEAM GEN A SUPPLY M-204 Sh 3 / G-1 C ACT HDRCHK

FW-13B STEAM GEN B SUPPLY M-204 Sh 3 / C-1 C ACT HDRCHK

FW-55A STEAM GEN B SUPPLY M-204 Sh 3 / C-3 A/C ACT HDRCHK

FW-55B STEAM GEN A SUPPLY M-204 Sh 3 / F-2 A/C ACT HDRCHK

Valve Summary Listing

Page 40 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 6 , CK SA C 0/C

3 6 CK SA C 0/C

2 4 CK SA C 0/C

I

2 4 CK SA C 0/C

3 4 CK SA C 0/C

3 4 CK SA C 0/C

TEST

FAIL REQ

N/A LT

eve

cvo

N/A LT

eve

cvo

N/A eve

cvo

N/A eve

cvo

N/A LT

eve cvo

N/A LT

eve

cvo

Program Section No. SEP-AN0-1-IST-2 Revision No.- 5

Page 68 of 165

FREQ PROCEDURE NOTES

2Y 1106.006 1106.006S9

cs 1106.006 CSJ-019 1106.006S9

cs 1106.006 CSJ-019 1106.006S12 1106.006S16

2Y 1106.006 1106.006S9

cs 1106.006 CSJ-019 1106.006S9

cs 1106.006 CSJ-019 1106.006S11 1106.006S15

cs 1106.006 CSJ-024 1106.006S11 1106.006S12 1106.006S15 1106.006S16

cs 1106.006 CSJ-024 1106.006S10 1106.006S4

cs 1106.006 CSJ-024 1106.006S11 1106.006S12 1106.006S15 1106.006S16

cs 1106.006 CSJ-024 1106.006S10 1106.006S4

2Y 1106.006 1106.006S9

cs 1106.006 CSJ-019 1106.006S9

cs 1106.006 CSJ-019 1106.006S12 1106.006S16

2Y 1106.006 1106.006S9

cs 1106.006 CSJ-019 1106.006S9

cs 1106.006 CSJ-019 1106.006S12 1106.006S16

Page 72: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT' ACT/ PASS

FW-56A STEAM GEN A SUPPLY M-204 Sh 3 / G-3 NC ACT HDRCHK

FW-56B STEAM GEN B SUPPLY M-204 Sh 3 / D-3 NC ACT HDRCHK

FW-61 EMERG FW PUMP P-7A M-204 Sh 3 / C-4 C ACT MINIFLOW CHK

FW-62 EMERG FW PUMP P-7B M-204 Sh 3 / G-4 C ACT MINIFLOW CHK

HV-139 B OTSG SECONDARY M-206 Sh 1 / D-1 A PASS DRAIN TO .E-11A

HV-140 B OTSG SECONDARY M-206 Sh 1 / D-1 A PASS DRAIN TO E-11A

HV-150 A OTSG SECONDARY M-206 Sh 1 / D-8 A PASS DRAIN TO E-11B

HV-151 A OTSG SECONDARY M-206 Sh 1 / D-8 A PASS DRAIN TO E-11B

IA-15 IA TO RX BLDG INSIDE M-218 Sh 4 / G-4 A PASS HEADER ISOL EL 354

IA-37 RX BLDG IA SUPPLY !SOL M-218 Sh 4 / E-4 A PASS

-IA-823 CV-7403, 7404, IA ISOL M-218 Sh 4/ E-7 A PASS

Valve Summa_ry Listing

Page 41 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 4 CK SA C 0/C

3 4 CK SA C 0/C

3 2 CK SA C 0/C

3 2 CK SA C 0/C

2 4 GA H C C

2 4 GA H C C

2 4 GA H C C

2 4 GA H C C

2 1.5 GA H C C

2 1 GA H C C

2 1 GA H C C

FAIL

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

TEST REQ

LT

eve

cvo

LT

eve

cvo

eve

cvo

eve

cvo

LTJ

LTJ

LTJ

LTJ

LTJ

LTJ

LTJ

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 69 of 165

FREQ PROCEDURE NOTES

2Y 1106.006 1106.00689

cs 1106.006 CSJ-019 1106.00689.

cs 1106.006 CSJ-019 1106.006811 1106.006815

2Y 1106.006 1106.00689

cs 1106.006 CSJ-019 1106.00689

cs 1106.006 CSJ-019 1106.006811 1106.006815

Q 1106.006 1106.006811 1106.006815

Q 1106.006 1106.006812 1106.006816

Q 1106.006 1106.006812 1106.006816

Q 1106.006 1106.006811 1106.006815

AppJ 1305.018 1305.018A82

AppJ 1305.018 1305.018A81

AppJ 1305.018 1305.018A73

AppJ 1305.018 1305.018A72

AppJ 1305.018 1305.018A53 1305.018A54

AppJ 1305.018 1305.018A51 1305.018A52

AppJ 1305.018 1305.018A93

Page 73: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 11ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT

IA-824 CV-7403, CV-7404 IA ISOL M-218 Sh 4 / E-8 A/C CHECK

ICW-114 RCP SEAL CLR & L TON M-234 Sh 2 / C-4 A/C CLR ICW SUPPLY CHECK VALVE

ICW-26 RCP MOTOR COOLANT M-234 Sh 1 / F-6 A/C INLET CHECK

'-

ICW-30 ' CONTROL ROD DRIVE M-234 Sh 1 / E-5 A/C COOLANT INLET CHECK

MS-271 CV-2617 CHECK VALVE M-204 Sh 6 / G-7 C

MS-272 CV-2667 CHECK VALVE M-204 Sh 6 / F-7 C

MU-1211 HPI TO P-32C CHECK M-231 Sh 3 / D-6 C

ACT/ PASS

ACT

ACT

ACT

ACT

ACT

ACT

ACT

Valve Summary Listing

Page 42 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 1 CK SA C C

2 8 CK SA 0 0/C

2 8 CK SA 0 0/C -

2 3 CK SA 0 0/C

3 4 CK SA :c 0/C

3 4 CK SA C 0/C

2 3 CK SA C 0

TEST

FAIL REQ

N/A LTJ

BOO

eve

N/A LTJ

eve

cvo

N/A LTJ

eve cvo

N/A LTJ

eve

cvo

N/A eve

cvo

N/A eve

cvo

N/A BOC

cvo

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 70 of 165

FREQ PROCEDURE NOTES

AppJ 1305.018 1305.018A92

CM 1104.033 CVCM 1104.033S4

CM 1305.018 CVCM 1305.018A92

AppJ 1305.018 1305.018A69

CM 1305.018 CVCM 1305.018A69

CM 1305.007 CVCM 1305.007S1A

AppJ 1305.018 1305.018A62

CM 1305.018 CVCM 1305.018A62

CM 1305.007 CVCM 1305.007S1A

AppJ 1305.018 1305.018A56

CM 1305.018 CVCM 1305.018A56

CM 1305.007 CVCM 1305.007S1A

CM 5120.410 CVCM

CM 1106.006 CVCM 1106.006S12 1106.006S16

CM 5120.410 CVCM

CM 1106.006 CVCM 1106.006S12 1106.006S16

CM OP-TBD CVCM

CM 1104.002 CVCM 1104.00288 1104.002S9

Page 74: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

MU-1212 HPI TO P-320 CHECK M-231 Sh 3 / C-5 C ACT

MU-1213 HPI TO P320 CK M-231 Sh 3 / C-6 C ACT

MU-1214 HPI TO P32B CK M-231 Sh 3 / G-3 C ACT

MU-1215 HPI TO P32A CK M-231 Sh 3 / F-3 C ACT

MU-1306 'A' HPI FLOW CHECK M-231 Sh 3 / 0-2 C ACT VALVE

MU-1307 'B' HPI FLOW CHECK M-231 Sh 3 / C-2 C ACT VALVE

MU-1308 'C' HPI FLOW CHECK M-231 Sh 3 / G-6 C ACT

MU-1309 'O' HPI FLOW CHECK M-231 Sh 3 / F-6 C ACT VALVE

Valve Summary Listing

Page 43 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 3 CK SA C 0

2 3 CK SA C 0

2 3 CK SA C 0

2 3 CK SA C 0

2 2.5 CK SA C 0

2 2.5 CK SA C 0

2 2.5 CK SA C 0

2 2.5 CK SA C 0

TEST

FAIL REQ

N/A BOC

cvo

N/A BOC

cvo

N/A BOC

cvo

N/A BOC

cvo

N/A BOC

cvo

N/A BOC

cvo

N/A BOC

cvo

N/A BOC

cvo

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 71 of 165

FREQ PROCEDURE NOTES

CM OP-TBO CVCM

CM 1104.002 CVCM 1104.00288 1104.002S9

CM OP-TBO CVCM

CM 1104.002 CVCM 1104.00288 1104.002S9

CM OP-TBO CVCM

CM 1104.002 CVCM 1104.00288 1104.002S9

CM 5120.410 CVCM

CM 1104.002 CVCM 1104.00288 1104.002S9

CM OP-TBO CVCM

CM 1104.002 CVCM 1104.00288 1104.002S9

CM OP-TBO CVCM

CM 1104.002 CVCM 1104.00288 1104.002S9

CM OP-TBO CVCM

CM 1104.002 CVCM 1104.00288 1104.00289

CM OP-TBO CVCM

CM 1104.002 CVCM 1104.00288 1104.002S9

Page 75: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

MU-19A MU PUMP P36A DISCH CK M-231 Sh 1 / G-4 C ACT

MU-19B MU PUMP P36B DISCH CK M-231 Sh 1 / E-4 C ACT

MU-19C P36C DISCH CHECK M-231 Sh 1 / C-4 C ACT

MU-22A MAKEUP PUMP P-36A M-231 Sh 1 / F-4 B/C ACT MINIMUMRECIRC ISOL

-

MU-22B MAKEUP PUMP P-36B M-231 Sh 1 / D-4 B/C ACT MINIMUMRECIRC ISOL

Valve Summary Listing

Page 44 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 4 CK SA 0/C 0/C

2 4 CK SA 0/C 0/C

2 4 CK SA 0/C 0/C

2 2 SCK H/SA 0/C C

2 2 SCK H/SA 0/C C

TEST

FAIL REQ

N/A eve

cvo

PSO

N/A eve

cvo

PSO

N/A eve

cvo

PSO

N/A MS

BOO

eve

PSO

N/A MS

BOO

eve

PSO

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 72 of 165

FREQ PROCEDURE NOTES '

cs 1104.002 CSJ-018 1104.002S4

cs 1104.002 CSJ-018 1104.002S8 1104.002S9

Q 1104.002 1104.002S3

cs 1104.002 CSJ-018 1104.002S3 1104.002S5

cs 1104.002 CSJ-018 1104.00288 1104.002S9

Q 1104.002 1104.002S4

cs 1104.002 CSJ-018 1104.002S4

cs 1104.002 CSJ-018 1104.00288 1104.002S9

Q 1104.002 1104.002S5

2Y OP-TBD

cs 1104.002 CSJ-025 1104.002S8 1104.002S9

cs 1104.002 CSJ-025 1104.002S4

cs 1104.002 CSJ-025 1104.002S8 1104.002S9

2Y OP-TBD

cs 1104.002 CSJ-025 1104.002S8 1104.002S9

cs 1104.002 CSJ-025 1104.002S3 1104.002S5

cs 1104.002 CSJ-025 1104.002S8 1104.002S9

Page 76: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

MU-22C MAKEUP PUMP P-36C M-231 Sh 1 / B-4 B/C ACT MINIMUMRECIRC !SOL

MU-29A P-32A SEAL SUPP ISOL M-231 Sh 1 / G-1 C ACT STOP CHECK

MU-29B P-32B SEAL SUPP ISOL M-231 Sh 1 / F-1 C ACT STOP CHECK

MU-29C P-32C SEAL SUPP ISOL M-231 Sh 1 / E-1 C ACT STOP CHECK

MU-29D P-320 SEAL SUPP ISOL M-231 Sh 1 / C-1 C ACT STOP CHECK

MU-34A 'A' HPI LINE CK M-230 Sh 1 / A-4 A/C ACT

MU-34B 'B' HPI LINE CK M-230 Sh 1 / A-4 A/C ACT

Valve Summary Listing

Page 45 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 2 SCK H/SA 0/C C

2 1.5 SCK SA 0/C 0/C

2 1.5 SCK SA 0/C 0/C

2 1.5 SCK SA 0/C 0/C

2 1.5 SCK SA 0/C 0/C

1 2.5 CK SA C 0/C

1 2.5 CK SA C 0/C

TEST

FAIL REQ

N/A MS

BOO

eve

PSO

N/A eve cvo

N/A eve

cvo

N/A eve cvo

N/A eve cvo

N/A LT

eve

cvo

N/A LT

eve

cvo

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 73 of 165

FREQ PROCEDURE /

NOTES

2Y OP-TBD

cs 1104.002 CSJ-025 1104.002SB 1104.002S9

cs 1104.002 CSJ-025 1104.002S4

cs . 1104.002 CSJ-025 1104.002SB 1104.002S9

R 1305.007 ROJ-011 1305.007S2

R 1305.007 ROJ-011 1305.007S1A

R 1305.007 ROJ-011 1305.007S2

R 1305.007 ROJ-011 1305.007S1A -

R 1305.007 ROJ-011 1305.007S2

R 1305.007 ROJ-011 1305.007S1A

R 1305.007 ROJ-011 1305.007S2

R 1305.007 ROJ-011 1305.007S1A

2Y OP-TBD

R OP-TBD ROJ-005

R 1104.002 ROJ-005 1104.002SB 1104.002S9

2Y OP-TBD

R OP-TBD ROJ-005

R 1104.002 ROJ-005 1104.002SB 1104.002S9

Page 77: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

MU-34C 'C' HPI LINE CK M-230 Sh 1 / A-5 A/C ACT

-'

MU-34D 'D' HPI LINE CK M-230 Sh 1 / A-5 A/C ACT

-

MU-35A CFT T-2A SUPPLY ISOL M-236 Sh 1 / D-7 A ACT

MU-35B CFT T-2B SUPPLY ISOL M-236 Sh 1 / D-2 A ACT

MU-36A CHECK VLV ON T-2A FILL .M-236 Sh 1 / D-6 A/C ACT LINE

MU-36B CK VLV ON CFT T-2B FILL M-236-Sh 1 / D-2 A/C ACT LINE

MU-66A A HPI LOOP B STOP M-230 Sh 1 / A-4 A/C ACT CHECK

Valve Summary Listing

Page 46 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

1 2.5 CK SA C 0/C

1 2.5 CK SA C 0/C

----2 1 GL H 0/C C

2 1 GL H 0/C c-

2 1 CK SA C 0/C

2 1 CK S6_ C 0/C

1 2.5 SCK SA C 0/C

TEST

FAIL REQ

N/A LT

eve

cvo

N/A LT

eve

cvo

N/A MS

LTJ

N/A MS

LTJ

N/A LTJ

eve

cvo

N/A LTJ

eve cvo

N/A LT

eve

cvo

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 74 of 165

FREQ PROCEDURE NOTES

2Y OP-TBD

R '

OP-TBD ROJ-005

R 1104.002 ROJ-005 1104.00288 1104.002S9

2Y OP-TBD

R OP-TBD ROJ-005

R 1104.002 ROJ-005 1104.00288 1104.002S9

2Y 1104.001 1104.00186

AppJ 1305.018 1305.018A32

2Y 1104.001 1104.001S6

AppJ 1305.018 1305.018A35

AppJ 1305.018 1305.018A34

CM 1104.001 CVCM 1104.001S6

CM 1104.001 CVCM 1104.00186

AppJ 1305.018 1305.018A36

CM 1104.001 CVCM 1104.00186

CM 1104.001 CVCM 1104.00186

2Y OP-TBD

R OP-TBD ROJ-006

R 1104.002 ROJ-006 1104.002S8 1104.002S9

Page 78: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

MU-668 B HPI LOOP 8 STOP M-230 Sh 1 / A-4 NC ACT CHECK

MU-66C C HPI LOOP A STOP M-230 Sh 1 / A-5 NC ACT CHECK

MU-660 HPI LOOP "A" CHECK M-230 Sh 1 / A-5 NC ACT

N2-3 N2 SUPPLY TO CF TANK M-236 Sh 1 / C-7 A ACT T-2AANO PZR

N2-32 RB N2 SUPP CK M-233 Sh 1 / 0-4 NC ACT

N2-34 N2 CK UP OF QUENCH TK M-230 Sh 2 / 8-7 C ACT

N2-47 RB N2 SUPPLY M-233 Sh 1 / 0-4 A ACT PENETRATION ISOL

N2-5 N2 SUPPLY TO CF TANK M-236 Sh 1 / C-2 A ACT T-28

N2-61 HP N2 SUPPLY ISOL TO M-230 Sh 1 / G-7 A PASS PRESSURIZER

Valve Summary Listing

Page 47 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE 1. 2.5 SCK SA C 0/C

1 2.5 SCK SA C 0/C

1 2.5 SCK SA. C 0/C

2 1 GL H C C

2 1 CK SA C C

3 1 CK SA C C

2 1 GA H 0/C C

2 1 GL H C C

2 1 GA H C C

TEST

FAIL -REQ

N/A LT

eve

cvo

N/A LT

eve cvo

N/A LT

eve

cvo

N/A MS

LTJ

N/A LTJ

800

eve

N/A 800

eve

N/A MS

LTJ

N/A MS

LTJ

N/A LTJ

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 75 of 165

FREQ PROCEDURE NOTES

2Y OP-TBO

R OP-TBO ROJ-006

R 1104.002 ROJ-006 1104.002S8 1104.002S9

2Y OP-TBO

R OP-TBO ROJ-006

R 1104.002 ROJ-006 1104.002S8 1104.002S9

2Y OP-TBO

R OP-TBO ROJ-006

R 1104.002 ROJ-006 1104.002S8 1104.002S9

2Y 1104.001 1104.001S6

AppJ 1305.018 1305.018A32

AppJ 1305.018 1305.018A43

CM 1103.005 CVCM 1103.005S3

CM 1305.018 CVCM 1305.018A43

CM 1103.005 CVCM 1103.005S3

CM 5120.410 CVCM

2Y 1103.005 1103.005S3

AppJ 1305.018 1305.018A44

2Y 1104.001 1104.001S6

AppJ 1305.018 1305.018A35

AppJ 1305.018 1305.018A33

Page 79: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

PH-17 RB OUTSIDE PLANT M-220 Sh 3 / D-7 A PASS HEATING SUPPLY ISOL

PH-18 RB PH SUPPLY ISOL M-220 Sh 3 / D-7 A PASS INSIDE RB

PH-19 RTN HDR ISOL INSIDE RB M-220 Sh 3 / D-7 A PASS

PH-20 RB OUTSIDE PLANT M-220 Sh 3 / D-6 A PASS HEATING RETURN ISOL

PSE-1051 QUENCH TANK RUPTURE M-230 Sh 2 / B-7 D ACT DISC

PSV-1000 PZRERV M-230 Sh 1 / G-3 B ACT

'

PSV-1001 PZR CODE SAFETY M-230 Sh 1 / G-4 C ACT

PSV-1002 PZR CODE SAFETY M-230 Sh 1 / G-5 C ACT

PSV-1003 P-39 THERMAL OVER- M-230 Sh 2 / C-4 C ACT PRESSURE RELIEF

PSV-1004 P-70 THERMAL OVER- M-230 Sh 2 / A-6 NC ACT PRESSURE RELIEF

PSV-1200 P-14 THERMAL OVER- M-231 Sh 2 / G-6 NC ACT PRESSURE RELIEF

PSV-1201 P-9 THERMAL OVER- M-231 Sh 2 / E-5 NC ACT PRESSURE RELIEF

PSV-1241 P36A SUCT RELIEF· M-231 Sh 1 / G-6 C ACT

Valve Summary Listing

Page 48 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 3 GA H C C

2 3 GA H C C

2 3 GA H C C

2 3 GA H C C

3 18 RD SA C 0/C

1 4 GL so C 0/C

1 6 RV SA C 0/C

1 6 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

TEST

FAIL REQ

N/A LTJ

N/A LTJ

N/A LTJ

N/A LTJ

N/A RD

C STT

ETC

ETO

FSC

STC

STO

N/A RV

N/A RV

N/A RV

N/A RV

LTJ

N/A RV

LTJ

N/A RV

LTJ (

N/A RV

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 76 of 165

FREQ PROCEDURE NOTES ~

AppJ 1305.018 1305.018A57

AppJ 1305.018 1305.018A58

AppJ 1305.018, 1305.018A46

AppJ 1305.018 1305.018A45

5Y . OP-TBD

2Y 1103.005 1103.005S2

cs 1103.005 CSJ-008 1103.005S1

cs 1103.005 CSJ~008 1103.005S1

cs 1103.005 CSJ-008 1103.005S1

cs 1103.005 CSJ-008 1103.005S1

cs 1103.005 CSJ-008 1103.005S1

5Y 1306.011

5Y 1306.011

10Y 1306.038

10Y 1306.038

AppJ 1305.018 1305.018A90

10Y 1306.038

AppJ 1305.018 1305.018A18

10Y 1306.038

AppJ 1305.018 1305.018A7

10Y 1306.038

Page 80: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR

PSV-1242 P36B SUCT RELIEF M-231 Sh 1 / D-6

PSV-1243 P36C SUCT RELIEF M-231 Sh 1 / B-6

PSV-1403 DH SUCT RELIEF M-232 Sh 1 / C-7

PSV-1404 DH PMP P34B SUCT M-232 Sh 1 / A-7 RELIEF

PSV-1405 DH PMP P34A SUCT M-232 Sh 11 E-7 RELIEF

PSV-1406 DH PP P34B DISCH M-232 Sh 1 / C-4 RELIEF

PSV-1407 DH PP P34A DISCH M-232 Sh 1 / F-4 RELIEF

PSV-1409 THERMAL RELIEF VALVE M-232 Sh 1 / C-8 FOR CCA-8-12' PIPING

PSV-1617 NAOHTANK M-233 Sh 1 / H-2 PRESSURENAC RELIEF

PSV-1800 PENETRATION P-7A M-237 Sh 1 / G-7 THERMAL OVERPRESSURE RELIEF

PSV-1801 P-10 THERMAL OVER- M-237 Sh 1 / F-7 PRESSURE RELIEF

PSV-2203 P-60 THERMAL OVER- M-234 Sh 1 / H-4 PRESSURE RELIEF

PSV-2205 P-52 THERMAL OVER- M-234 Sh 1 / F-6 PRESSURE RELIEF

PSV-2206 P-62 THERMAL OVER- M-234 Sh 2 / F-6 PRESSURE RELIEF

------- --------------------------;-------------------~

CAT ACT/ PASS

C ACT

C ACT

C ACT

C ACT

C ACT

C ACT

C ACT

C -

ACT

C ACT

A/C ACT

A/C ACT

A/C ACT

C ACT

A/C ACT

Valve Summary Listing

Page 49 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

1 0.75 RV SA C 0/C

3 2 VRV SA C 0

1 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

TEST

FAIL REQ

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A cvo

RV-SET

N/A RV

LTJ

N/A RV

LTJ

N/A RV

LTJ

N/A RV

N/A RV

LTJ

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 77 of 165

FREQ PROCEDURE NOTES

10Y 1306.038

10Y 1306.038

10Y 1306.036

10Y 1306.038

10Y 1306.038

10Y 1306.038

10Y 1306.038

10Y 1306.038

2Y 1306.034 VRR-AN01-2017-1

2Y 1306.034 VRR-AN01-2017-1

10Y 1306.038

AppJ 1305.018 1305.018A1

10Y 1306.038

AppJ 1305.018 1305.018A12

10Y 1306.038

AppJ 1305.018 1305.018A76

10Y 1306.038

10Y 1306.038

AppJ 1305.018 1305.018A78

Page 81: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

PSV-2400 P-12 THERMAL OVER- M-236 Sh 1 / C-4 NC ACT PRESSURE RELIEF

PSV-2415 CFT T2A RELIEF M-236 Sh 1 / D-5 C ACT

PSV-2421 CFT T28 RELIEF M-236 Sh 1 / D-3 C ACT

PSV-2600 · P-58 THERMAL OVER- M-206 Sh 1 / D-8 NC ACT PRESSURE RELIEF

PSV-2601 P-64 THERMAL OVER- M-206 Sh 1 / D-1 NC ACT PRESSURE RELIEF

PSV-2602 THERMAL RELIEF VALVE M-206 Sh 1 / E-8 C ACT FOR EBD-19 (LOOP A) PIPING

PSV-2603 THERMAL RELIEF VALVE M-206 Sh 1 / E-1 C ACT FOR EBD-19 (LOOP 8) PIPING

PSV-2684 MAIN STEAM RELIEF M-206 Sh 1 / G-3 C ACT

PSV-2685 MAIN STEAM RELIEF M-206 Sh 1 / G-3 C ACT

PSV-2686 MAIN STEAM RELIEF M-206 Sh 1 / G-3 C ACT

PSV-2687 MAIN STEAM RELIEF M-206 Sh 1 / G-3 C ACT

PSV-2688 MAIN STEAM RELIEF M-206 Sh 1 / G-4 C ACT

PSV-2689 MAIN STEAM RELIEF M-206 Sh 1 / G-4 C ACT

PSV-2690 MAIN STEAM RELIEF M-206 Sh 1 / G-4 C ACT

PSV-2691 MAIN STEAM RELIEF M-206 Sh 1 / G-4 C ACT

PSV-2692 MAIN STEAM RELIEF M-206 Sh 1 / G-5 C ACT

Valve Summary Listing

Page 50 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 0.75 RV SA C 0/C

2 1 RV SA C 0/C

2 1 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 0.75 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

TEST

FAIL REQ

N/A RV

LTJ

N/A RV

N/A RV

N/A RV

LTJ

N/A RV

LTJ

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 78 of 165

FREQ PROCEDURE NOTES

10Y 1306.038

AppJ 1305.018 1305.018A17

10Y 1306.038

10Y 1306.038

10Y 1306.038

AppJ 1305.018 1305.018A72

10Y 1306.038

AppJ 1305.018 1305.018A81

10Y 1306.038

10Y 1306.038

SY 1306.017

SY 1306.017

SY 1306.017

SY 1306.017

SY 1306.017

SY 1306.017 -· ,·

SY 1306.017

SY 1306.017

SY 1306.017

Page 82: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

PSV-2693 MAIN STEAM RELIEF M-206 Sh 1 / G-5 C ACT

PSV-2694 MAIN STEAM RELIEF M-206 Sh 1 / G-5 C ACT

PSV-2695 MAIN STEAM RELIEF M-206 Sh 1 / G-5 C ACT

.PSV-2696 MAIN STEAM RELIEF M-206 Sh 1 / G-5 C ACT

PSV-2697 MAIN STEAM RELIEF M-206 Sh 1 / G-6 C ACT

PSV-2698 MAIN STEAM RELIEF M-206 Sh 1 / G-6 C ACT

PSV-2699 MAIN STEAM RELIEF M-206 Sh 1 / G-6 C ACT

PSV-6205 P-59 THERMAL OVER- M-222 Sh 1 / F-4 NC ACT PRESSURE RELIEF

,;

RBD-23 RBDH ISOL TO ABEDT M-214 Sh 3 / F-3 A PASS

RBD-24 RBDH ISOL TO ABEDT M-214 Sh 3 / F-3 A PASS

RBS-10 T-111 TO QUENCH TK M-230 Sh 2 / C-7 C ACT CHECK

RC-1009 INTERNAL VENT VALVE, M-230 Sh 1 / E-4 C ACT X2

RC-1010 INTERNAL VENT VALVE M-230 Sh 1 / E-4 C ACT Y1

RC-1011 INTERNAL VENT VALVE M-230 Sh 1 / E-4 C ACT Y2

..

RC-1012 INTERNAL VENT VALVE M-230 Sh 1 / E-4 C ACT 21

Valve Summary Listing

Page 51 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 6 RV SA C 0/C

2 0.75 RV SA C 0/C

2 4 GA H C C

2 4 GA H C C

3 2 CK SA C C

1 14 CK SA C 0/C

1 14 CK SA C 0/C

1 14 CK SA C 0/C

1 14 CK SA C 0/C

TEST

FAIL REQ

NIA RV

N/A RV

N/A RV

NIA RV

N/A RV

NIA RV

N/A RV

NIA RV

LTJ

N/A LTJ

NIA LTJ

NIA BOO

eve

NIA eve

cvo

NIA eve cvo

N/A · eve

cvo

NIA eve

cvo

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 79 of 165

FREQ PROCEDURE NOTES

SY 1306.017

SY 1306.017

SY 1306.017

SY 1306.017

SY 1306.017

SY 1306.017

SY 1306.017

10Y 1306.038

AppJ 1305.018 1305.018A74

AppJ 1305.018 1305.018A88

AppJ 1305.018 1305.018A89

R 1103.007 ROJ-009

R 5120.410 ROJ-009

CM 1306.008 CVCM

CM 1306.008 CVCM

CM 1306.008 CVCM

CM 1306.008 CVCM·

CM 1306.008 CVCM

CM 1306.008 CVCM

CM 1306.008 CVCM

CM 1306.008 CVCM

Page 83: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

RC-1013 INTERNAL VENT VALVE M-230 Sh 1 / E-4 C ACT Z2

RC-1014 INTERNAL VENT VALVE M-230 Sh 1 / E-4 C ACT W1

RC-1015 INTERNAL VENT VALVE M-230 Sh 1 / E-4 C ACT W2

RC-1016 INTERNAL VENT VALVE M-230 Sh 1 / E-4 C ACT X1

SF-42 FTC INCORE INST TANK M-235 Sh 1 / E-6 A PASS FILUDRAIN RB ISOL

SG-1 SLUICE GATE M-209 Sh 1 / F-4 A ACT

'

-

Valve Summary Listing

Page 52 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

1 14 CK SA C 0/C

1 14 CK SA C 0/C

1 14 CK SA C 0/C

1 14 CK SA C 0/C

2 8 GA H C C

3 36X GA MO 0 0/C 36

TEST

FAIL REQ

N/A eve cvo

N/A eve

cvo

N/A eve cvo

N/A eve cvo

N/A LTJ

FAI LT

RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 80 of 165

FREQ PROCEDURE NOTES

CM 1306.008 CVCM '

CM 1306.008 CVCM

CM 1306.008 CVCM

CM 1306.008 CVCM

CM 1306.008 CVCM /

CM 1306.008 CVCM

CM 1306.008 CVCM

CM 1306.008 CVCM

AppJ 1305.018 1305.018A21

2Y 1306.037

2Y 1104.029 1104.02988

Q 1104.029 1104.02981 1104.02988

Q 1104.029 1104.02981 1104.029S8

Q 1104.029 1104.029S1 1104.029SB

Q 1104.029 1104.02981 1104.02988

Page 84: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SG-2 SLUICE GATE M-209 Sh 1 / C-4 A ACT

SG-3 SLUICE GATE M-209 Sh 1 / E-2 B ACT

SG-4 SLUICE GATE M-209 Sh 1 / D-2 B ACT

Valve Summary Listing

Page 53 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 36X GA MO 0 0/C 36

3 36X GA MO 0/C 0/C 36

3 36X GA MO 0/C 0/C 36

TEST

FAIL REQ

FAI LT

RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 81 of 165

FREQ PROCEDURE NOTES

2Y 1306.037

2Y 1104.029 1104.029S10

Q 1104.029 . 1104.029S10

1104.029S3 Q 1104.029

1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

2Y 1104.029 1104.02988

Q 1104.029 1104.029S1 1104.02988

Q 1104.029 1104.029S1 1104.02988

Q 1104.029 1104.029S1 1104.02988

Q 1104.029 1104.029S1 1104.02988

2Y 1104.029 1104.029S10

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

------~

Page 85: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SG-5 SLUICE GATE M-209 Sh 1 / F-1 B ACT

SG-6 SLUICE GATE M-209 Sh 1 / D-1 B ACT

SG-7 SLUICE GATE M-209 Sh 1 / C-1 B ACT

SS-146 SS SG E24A ISO TO E31A M-237 Sh 1 / F-7 A PASS

Valve Summary Listing

Page 54 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 36X GA MO C 0/C 36

3 36X GA MO C 0/C 36

3 36X GA MO C 0/C 36

2 0.75 GA H C C

,,-

TEST

FAIL REQ

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

FAI RPI

ETC

ETO

STC

STO

N/A RPI

LTJ

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 82 of 165

FREQ PROCEDURE NOTES

2Y 1104.029 1104.029S8

Q 1104.029 1104.029S1 1104.029S8

Q 1104.029 1104.029S1 1104.029S8

Q 1104.029 1104.029S1 1104.029S8

Q 1104.029 1104.029S1 1104.029S8

2Y 1104.029 1104.029S9

Q 1104.029 1104.029S2 1104.029S9

Q 1104.029 1104.029S2 1104.029S9

Q 1104.029 1104.029S2 1104.029S9

Q 1104.029 1104.029S2 1104.029S9

2Y 1104.029 1104.029S10

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

Q 1104.029 1104.029S10 1104.029S3

2Y 1305.007 1305.007S2

AppJ 1305.018 1305.018A12

Page 86: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SS-2 'B' SG SAMPLE ISOL M-206 Sh 1 / E-2 B ACT

SS-5 'A' SG TUBE SHEET M-206 Sh 1 / E-7 B ACT SAMPLE ISOL

SV-1071 RV HEAD HIGH POINT M-230 Sh 2 / G-5 B ACT VENT

SV-1072 RV HEAD HIGH POINT M-230 Sh 2 / H-5 B ACT VENT

SV-1073 RV HEAD HIGH POINT M-230 Sh 2 / G-5 B ACT VENT

Valve Summary Listing

Page 55 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 1 GL H 0 C

2 1 1/2 GL H 0 C

1 1 GL so C 0/C

1 1 GL so C 0/C

1 1 GL so C 0/C

TEST

FAIL REQ

N/A MS

N/A MS

C RPI

ETC

ETO

FSC

STC

STO

C RPI

ETC

ETO

FSC

STC

STO

C RPI

ETC

ETO

FSC

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 83 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S10

2Y 1305.007 1305.007S10

2Y 1102.001 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

2Y 1102.001 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

2Y 1102.001 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

Page 87: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SV-1074 RV HEAD HIGH POINT M-230 Sh 2 / H-5 B ACT VENT

SV-1077 PZR VENT TO QUENCH M-230 Sh 1 / H-7 B ACT TANK (DOWNSTREAM)

SV-1079 PZR VENT TO Q!JENCH M-230 Sh 1 / G-7 B ACT TANK (UPSTREAM)

Valve Summary Listing

Page 56 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

1 1 GL so C 0/C

1 1 GL so C 0/C

1 1 GL so C 0/C

FAIL

C

C

C

TEST REQ

RPI

ETC

ETO

FSC

STC

STO

RPI

ETC

ETO

FSC

STC

STO

RPI

ETC

ETO

FSC

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 84 of 165

FREQ PROCEDURE NOTES

2Y 1102.001 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

cs 1102.001 CSJ-006 1102.001S1

2Y 1102.001 1102.001S1

cs 1102.001 CSJ-005 1102.001S1

cs 1102.001 CSJ-005 1102.001S1

cs 1102.001 CSJ-005 1102.001S1

cs 1102.001 CSJ-005 1102.001S1

cs 1102.001 CSJ-005 1102.001S1

2Y 1102.001 1102.001S1

cs 1102.001 CSJ-005 1102.001S1

cs 1102.001 CSJ-005 1102.001S1

cs 1102.001 CSJ-005 1102.001S1

cs 1102.001 CSJ-005 1102.001S1

cs 1102.001 CSJ-005 1102.001S1

----------------------------~

Page 88: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SV-1081 TH LOOP A VENT M-230 Sh 2 / G-7 8 ACT

SV-1082 TH LOOP A VENT M-230 Sh 2 / H-7 8 ACT

SV-1083 TH LOOP A VENT M-230 Sh 2 / G-7 8 ACT

-

SV-1084 TH LOOP A VENT M-230 Sh 2 / H-7 8 ACT

Valve Summary Listing

Page 57 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

1 1 GL so C 0/C

1 1 GL so C 0/C

1 1 GL so C 0/C

1 1 GL so C 0/C

TEST

FAIL ~EQ

C RPI

ETC

ETO

FSC

STC

STO

C RPI

ETC

ETO

FSC

STC

STO

C RPI

ETC

ETO

FSC

STC

STO

C RPI

ETC

ETO

FSC

STC

STO

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 85 of 165

FREQ PROCEDURE NOTES

2Y 1102.001 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 . CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

2Y 1102.001 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

2Y 1102.001 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

2Y 1102.001 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.00.1S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

>

- - - ---- ----------------~

Page 89: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SV-1091 TH LOOP B VENT M-230 Sh 2 / G-3 B ACT

-

SV-1092 TH LOOP B VENT M-230 Sh 2 / H-3 B ACT

SV-1093 TH LOOP B VENT M-230 Sh 2 / G-3 B ACT

SV-1094 TH LOOP B VENT M-230 Sh 2 / H-3 B ACT

Valve Summary Listing

Page 58 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

1 1 GL so C 0/C

1 1 GL so C 0/C

1 1 GL so C 0/C

1 1 GL so C 0/C

TEST

FAIL REQ

C RPI

ETC -

ETO

FSC

STC

STO

C RPI

ETC

ETO

FSC

STC /

STO

C RPI

ETC

ETO

FSC

STC

STO

C RPI

ETC

ETO

FSC

STC

STO

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 86 of 165

FREQ PROCEDURE ·NOTES

.2Y 1102.001 1102.00181

cs 1102.001 CSJ-007 1102.00181

cs 1102.001 CSJ-007 1102.00181

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.00181

2Y 1102.001 1102.00181

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.00181

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.00181

2Y 1102.001 1102.00181

cs 1102.001 CSJ-007 1102.00181

cs 1102.001 CSJ-007 , 1102.00181 cs 1102.001 CSJ-007

1102.00181 cs 1102.001 CSJ-007

1102.00181 cs 1102.001 CSJ-007

1102.00181

2Y 1102.001 1102.00181

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.00181

cs 1102.001 CSJ-007 1102.001S1

cs 1102.001 CSJ-007 1102.00181

Page 90: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SV-1818 PZR/HOT LEG SAMPLE M-237 Sh 1 / G-7 A PASS

SV-1840 HOT LEG SAMPLE M-237 Sh 1 / F-7 A PASS

SV-3812 RB COOLERS VCC-2A/B M-210 Sh 1 / 0-3 B ACT SW FILL BYPASS

SV-3813 RB COOLERS VCC-2C/O M-210 Sh 1 / 0-3 B ACT SW FILL BYPASS

SV-7454 RB LEAK DETECTOR M-261 Sh 3 / A-6 A ACT ISOL FROM RB

Valve Summary Listing

Page 59 of s:f CLASS SIZE TYPE ACT POSITION

NORM SAFE

1 1 GL so C C

1 1 GL ·so C C

2 2 GA so 0 0/C

2 2 GA so 0 0/C

2 1 GL so 0 C

FAIL

C

C

0

0

C

TEST REQ

RPI

LTJ

ETC

RPI

LTJ

RPI

ETC

ETO

STC

STO

FSO

RPI

ETC

ETO

STC

STO

FSO

RPI

LTJ

ETC

FSC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 87 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S6

AppJ 1305.018 1305.018A1

Q 1305.007 1305.007S1B

2Y 1305.007 1305.007S6

AppJ 1305.018 1305.018A4

2Y 1305.007 1305.007S2

Q 1104.033 1104.033S6

Q 1104.033 1104.033S6

Q 1104.033 1104.033S6

Q 1104.033 1104.033S6

Q 1104.033 1104.033S6

2Y 1305.007 1305.007S2

Q 1104.033 1104.033S5

Q 1104.033 1104.033S5

Q 1104.033 1104.033S5 -

Q 1104.033 1104.033S5

Q 1104.033 1104.033S5

2Y 1305.007 1305.007S6

AppJ 1305.018 1305.018A30

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

- -- ----------------------~

Page 91: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SV-7456 RB LEAK DETECTOR M-261 Sh 3 / 8-4 A ACT ISOL RETURN TO RB

SV-7457 H2 SAMPLER C178 INLET M-261 Sh 3 / C-5 A ACT ISOL

SV-7459 H2 SAMPLER C179 INLET M-261 Sh 3 / 8-5 A ACT ISOL

Valve Summary Listing

Page 60 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

2 1 GL so 0 C

2 1 GL so 0/C C

2 1 GL so 0/C C

TEST

FAIL REQ

C RPI

LTJ

ETC

FSC

STC

C RPI

LTJ

ETO

STO

ETC

FSC

STC

C RPI

LTJ

ETO

STO

ETC )

FSC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 88 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.00786

AppJ 1305.018 1305.018A25

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.00786

AppJ 1305.018 1305.018~65

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.00786

AppJ 1305.018 1305.018A28

Q 1305.007 1305.007S18

Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S1B

Q 1305.007 1305.007S18

Q 1305.007 1305.007S1 B

Page 92: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SV-7467 H2 SAMPLER C178 M-261 Sh 3 / C-6 A ACT OUTLET ISOL

SV-7469 H2 SAMPLER C179 M-261 Sh 3 / 8-6 A ACT OUTLET ISOL

/

SV-7479 RB LEAK DETECTOR M-261 Sh 3 / 8-6 A ACT ISOL RETURN TO RB

SW-11 SW SUPP CK VLV TO M-204 Sh 3 / H-8 C ACT EFW

SW-12 SW SYSTEM LOOP M-210 Sh 1 / 8-2 8 ACT OUTAGE SEPARATION (SEE OP-1104.029 OPERABILITY SE

Valve Summary Listing

Page 61 of 63

CLASS SIZE TYPE ACT POSITION_,

NORM SAFE FAIL

2 1 GL so 0/C C C

2 1 GL so 0/C C C

2 0.75 GL SO. 0 C C

3 6 CK SA C 0 N/A

3 18 BF H LO 0/C N/A

TEST REQ

'RPI

LTJ

ETO

STO

ETC

FSC

STC

RPI

LTJ

ETO

STO

ETC

FSC

STC

RPI

LTJ

ETC

FSC

STC

BOC

cvo

MS

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 89 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S6

AppJ 1305.018 1305.018A63

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

2Y 1305.007 1305.007S6

AppJ 1305.018 1305.018A26

Q 1305.007 1305.007S18

Q 1305.007 1305.007S18

Q 1305.007 1305.007S18

Q 1305.007 1305.007S1 B

Q 1305.007 1305.007S18

2Y 1305.007 1305.007S6

AppJ 1305.018 1305.018A26

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

Q 1305.007 1305.007S1A

CM OP-TBD CVCM

CM 1106.006 CVCM 1106.006S13 1106.006S6

2Y OP-TBD

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ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SW-13 SW SUPP CK VLV TO M-204 Sh 3 / A-8 C ACT EFW

SW-1A LOOP I SW P-4A DISCH M-209 Sh 1 / F-3 NC ACT CK

SW-1B P4B DISCH CK VLV M-209 Sh 1 / D-3 NC ACT

SW-1C P4C DISCH CK VLV M-209 Sh 1 I C-3 NC ACT

SW-23 MAINTENANCE M-210 Sh 1 I E-2 A ACT ISOLATION VALVE DOWNSTREAM OF SW-9

SW-3A CIRC WTR PP P-3NB- M-209 Sh 1 / F-3 B ACT SUPP

SW-3C CIRC WTR PP P-3CID M-209 Sh 1 I B-3 B ACT SUPP

SW-6047 FLEX SW to FS Cross-Tie M-209 Sh 1 I C-2 A PASS Isolation

SW-632 2VE-1A & 2VE-1B SUPPLY M-210 Sh 1 I F-5 B ACT

Valve Summary Listing

Page 62 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 6 CK SA C 0

3 18 CK SA 0/C 0/C

3 18 CK SA 0/C 0/C

3 18 CK SA OIC OIC

3 14 BF H LO 0/C

..

3 2 GA H 0 C

3 2 GA H 0 C

3 12 GA H LC C

3 3 GA H C 0/C

TEST

FAIL REQ

N/A BOC

cvo

N/A LT

eve

cvo

N/A LT

eve

cvo

NIA LT

eve

cvo

NIA LT

MS

N/A MS

NIA MS

N/A LT

NIA MS

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 90 of 165

FREQ PROCEDURE NOTES

CM OP-TBD CVCM

CM 1106.006 CVCM 1106.006S14 1106.006S6

2Y 1104.029 1104.029S4

cs 1104.029 CSJ-020 1104.029S1 1104.029S8

cs 1104.029 CSJ-020 1104.029S1 1104.029S8

2Y 1104.029 \

1104.029S4 cs 1104.029 CSJ-020

1104.029S2 1104.029S9

cs 1104.029 CSJ-020 1104.029S2 1104.029S9

2Y 1104.029 1104.029S4

cs 1104.029 CSJ-020 1104.029S10 1104.029S3

cs 1104.029 CSJ-020 1104.029S10 1104.029S3

2Y 1104.029 1104.029S4

2Y 1104.029 1104.029S4

2Y 1305.007 1305.007S9

2Y 1305.007 1305.007S9

2Y 1104.029 1104.029S4

2Y 1305.007 1305.007S8

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ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT ACT/ PASS

SW-69 SW LOOP II SUPPLY ISOL M-210 Sh 1 / 8-4 8 ACT TO EMERG CONT ROOM CHILLER

SW-72 SW TO SFP EL 404' SERV M-210 Sh 1 / A-4 8 ACT CONN

SW-814 vcc~2A/8 DISCHARGE M-210 Sh 1 / D-3 8 ACT THROTILE VALVE

SW-815 VCC-2C/D DISCHARGE M-210 Sh 1 / C-2 8 ACT THROTILE VALVE

SW-84 2VE-1A & 2VE-18 M-210 Sh 1 / D-6 8 ACT OUTLETS

SW-9 E-28 A,B,C SW RTN CK M-210 Sh 1 / E-2 A/C ACT VLV

Valve Summary Listing

Page 63 of 63

CLASS SIZE TYPE ACT POSITION

NORM SAFE

3 2 GA H C 0/C

3 2 GA H C 0/C

3 10 GA H 0 0

3 10 GA H 0 0

3 3 GA H C 0/C

3 14 CK SA 0 C

TEST

FAIL REQ

N/A MS

N/A MS

N/A MS

N/A MS

N/A MS

N/A LT

BOO

eve

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 91 of 165

FREQ PROCEDURE NOTES

2Y 1305.007 1305.007S5

2Y 1305.007 1305.007S5

2Y 1305.007 1305.007S11

2Y 1305.007 1305.007S11

2Y 1305.007 1305.00788

2Y 1104.029 1104.029S4

cs 1305.007 CSJ-021 1305.007S1A

cs 1104.029 CSJ-021 1104.029S6

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ANO Unit 11ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT

CS-1196 P-78 BRG CLNG RTN M-204 Sh 3 / F-4 Aug-C CHECK

CS-1198 P-7A BRG CLNG RTN M-204 Sh 3 / F-4 Aug-C '- CHECK

CV-2216 L TON CLR (E29A) SUPPLY ISOL

M-23f Sh 2 / E5 Aug-8

CV-2217 L TON CLR (E29B) SUPPLY M-234 Sh 2 / C5 Aug-8 ISOL

CV-2618 SG B STEAM DUMP TO M-206 Sh 1 / H-1 Aug-8 ATMOS

CV-2622 LO LOAD CONTROL M-206 Sh 1 / 8-6 Aug-8 VALVE

CV-2623 STARTUP FW CONTROL M-206 Sh 1 / 8-6 Aug-8 VALVE

Augmented Valve Summary Listing

Page 1 of 7

ACT/ CLASS SIZE TYPE ACT POSITION PASS

NORM SAFE

ACT NC 0.5 CK SA 0 0

ACT NC 0.5 CK SA 0 0

PASS NC 6 BF MO 0 0

PASS NC 6 BF MO 0 0

ACT NC 10 GA AO C 0

ACT NC 10 GL AO 0 C

ACT N~ 6 GL AO C C

TEST

FAIL REQ

N/A BOC

cvo

PSO

N/A BOC

cvo

PSO

FAI RPI

FAI RPI

C RPI

ETO

FSC

STO

FAI RPI

ETC

STC

FAI RPI

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 92 of 165

FREQ PROCEDURE NOTES

CM RT

CM 1106.006 1106.006S15

CM 1106.006 1106.006S11

CM RT

CM 1106.006 1106.006S16

CM 1106.006 1106.006S12

2Y 1305.007 1305.007S2

2Y 1305.007 1305.007S2

2Y 1105.005 1105.005S3

Q 1105.005 1105.00581 1105.005S3

Q 1105.005 1105.005S1 1105.005S3

Q 1105.005 1105.005S1 1105.005S3

2Y 1102.001 1102.001S6 1102.001S7

cs 1102.001 CSJ-016 1102.00186 1102.001S7

cs 1102.001 CSJ-016 1102.00186 1102.001S7

2Y 1102.001 1102.00186 1102.001S7

cs 1102.001 CSJ-017 1102.00186 1102.001S7

cs 1102.001 CSJ-017 1102.001S6 1102.001S7

Page 96: Arkansas Nuclear One, Unit 1, Inservice Testing Plan for ... · Arkansas Nuclear One Unit ·.1 (AN0-1 ). The lnservice Testing Program described herein has been developed as required

ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT

CV-2625 MAIN FW BLOCK VALVE M-206 Sh 1 / C-6 Aug-B

CV-2668 SG A STEAM DUMP TO M-206 Sh 1 / H-8 Aug-B ATMOS

CV-2672 B MAIN FW LO LOAD M-206 Sh 1 / B-2 Aug-B CONTROL VALVE

CV-2673 STARTUP FW CONTROL M-206 Sh 1 / B-3 Aug-B VALVE

Augmented Valve Summary Listing

Page 2 of 7

ACT/ CLASS SIZE TYPE ACT POSITION PASS

NORM SAFE

ACT NC 18 GA MO 0 C

ACT NC 10 GA AO C 0

ACT NC 10 GL AO 0 C

ACT NC 6 GL AO C C

TEST

FAIL REQ

FAI RPI

ETC

STC

C RPI

ETO

FSC

STO

FAI RPI

ETC

STC

FAI RPI

ETC

STC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 93 of 165

FREQ PROCEDURE NOTES

2Y 1102.001 1102.00186 1102.001S7

cs 1102.001 CSJ-015 1102.00186 1102.001S7

cs 1102.001 CSJ-015 1102.00186 1102.001S7

2Y 1105.005 1105.005S3

Q 1105.005 1105.005S1 1105.005S3

Q 1105.005 1105.005S1 1105.005S3

Q 1105.005 1105.005S1

-- 1105.005S3

2Y 1102.001 1102.00186 1102.001S7

cs ,· 1102.001 CSJ-016 1102.00186 1102.001S7

cs 1102.001 CSJ-016 1102.00186 · 1102.001S7

2Y 1102.001 1102.00186 1102.001S7

cs 1102.001 CSJ-017 1102.00186 1102.001S7

cs 1102.001 CSJ-017 1102.00186 1102.001S7

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ANO Unit 11ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT

CV-2675 MAIN FW BLOCK VAL VE M-206 Sh 1 / C-3 Aug-8 TO'B'OTSG

CV-5218 KMA-3/4 AIR RELAY M-217 Sh 4 / E-6 Aug-8

/

CV-5233 KMA-1/2 AIR RELAY M-217 Sh 4 / D-6 Aug-8

CV-5237 KMB-3/4 AIR RELAY M-217 Sh 4 / E-4 Aug-8

CV-5239 KMB-1/2 AIR RELAY M-217 Sh 4 / D-4 Aug-8

F0-10A DG1 EMERG DESL FUEL M-217 Sh 1 / C-6 Aug-8 TANK T-57A CROSSOVER

F0-108 DG2 EMRG DIESEL FUEL M-217 Sh 1 / C-4 Aug-8 TANKT-578 CROSSOVER

F0-54A1 T-31A 1/A2 AIR RECEIVER M-217 Sh 4 / H-7 Aug-C INLET CHECK

Augmented Valve Summary Listing

Page 3 of 7

ACT/ CLASS SIZE TYPE ACT POSITION PASS

NORM SAFE

ACT NC 18 GA MO 0 C

ACT NC 1.5 PLG AO C 0/C

ACT NC 1.5 PLG AO C 0/C

ACT NC 1.5 PLG AO C 0/C

ACT NC 1.5 PLG AO C 0/C

ACT NC 3 GA H C 0

ACT NC 3 GA H C 0

ACT NC 1.5 CK SA 0/C 0/C

(

TEST

FAIL REQ

FAI RPI

ETC

STC

STO

C ETC

ETO

FSC

C ETC

ETO

FSC

C ETC

ETO

FSC

C ETC

ETO

FSC

N/A MS

N/A MS

N/A eve

cvo

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 94 of 165

FREQ PROCEDURE NOTES

2Y 1102.001 I

1102.001S6 1102.001S7

cs 1102.001 CSJ-015 1102.001S6 1102.001S7

cs 1102.001 CSJ-015 1102.001S6 1102.001S7

cs 1102.001 1102.001S6

Q 1104.036 VPS-001 1104.036S1

a. 1104.036 VPS-001 1104.03631

Q 1104.036 VPS-001 1104.036S1

Q 1104.036 VPS-001 1104.03631

Q 1104.036 VPS-001

' 1104.03631 Q 1104.036 VPS-001

1104.036S1

Q 1104.036 VPS-001 1104.03632

Q 1104.036 VPS-001 1104.03632

Q 1104.036 VPS-001 1104.03632

Q 1104.036 VPS-001 1104.03632

Q 1104.036 VPS-001 1104.03632

Q 1104.036 VPS-001 1104.036S2

2Y 1104.036. 1104.03631

2Y 1104.036 1104.03632

CM 1104.036 1104.03633

CM 1104.036 1104.03633

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ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT

F0-54A2 T-31A3/A4 AIR RECEIVER M-217 Sh 4 / A-7 Aug-C INLET CHECK

F0-5481 T-3181/82 AIR RECEIVER M-217 Sh 4 / H-3 Aug-C INLET CHECK

F0-5482 T-3183/84 AIR RECEIVER M-217 Sh 4 / A-3 Aug-C INLET CHECK

..

F0-55A1 T-31A1/A2 AIR RECEIVER M-217 Sh 4 / H-7 Aug-C INLET CHECK

F0-55A2 T-31A3/A4 AIR RECEIVER M-217 Sh 4 / A-7 Aug-C INLET CHECK

F0-5581 T-3181/82 AIR RECEIVER M-217 Sh 4 / H-3 Aug-C INLET CHECK

F0-5582 T-3183/84 AIR RECEIVER M-217 Sh 4 / A-3 Aug-C INLET CHECK

FO-BA P-16A DISCH CHECK M-217 Sh 1 / C-7 Aug-C

F0-88 P-168 DISCH CHECK M-217 Sh 1 / C-3 Aug-C

IA-280 CV-2691 IA CHECK VALVE M-218 Sh 4 / G-7 Aug-C

-

Augmented Valve Summary Listing

Page 4 of 7

ACT/ CLASS SIZE TYPE ACT POSITION PASS

NORM SAFE

ACT NC 1.5 CK SA 0/C 0/C

ACT NC 1.5 CK SA 0/C 0/C

ACT NC 1.5 CK SA 0/C 0/C

ACT NC 1.5 CK SA 0/C 0/C

ACT NC 1.5 CK SA 0/C 0/C

ACT NC 1.5 CK SA 0/C 0/C

ACT NC 1.5 CK SA 0/C 0/C

ACT NC 2 CK SA C 0

ACT NC 2 CK SA C 0

ACT NC 1 CK SA 0/C C

TEST

FAIL REQ

N/A eve cvo

N/A eve

cvo

N/A eve

cvo

N/A eve

cvo

N/A eve cvo

N/A eve

cvo

N/A eve

cvo

N/A BOC

cvo

N/A BOC

cvo

N/A eve

cvo

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 95 of 165

FREQ PROCEDURE NOTES

CM 1104.036 1104.036S3

CM 1104.036 1104.03683

CM 1104.036 1104.03684

CM 1104.036 1104.036S4

CM 1104.036 1104.03684

CM 1104.036 1104.03684

CM 1104.036 1104.03683

CM 1104.036 1104.03683

CM 1104.036 1104.03683

CM 1104.036 1104.03683

CM 1104.036 1104.036S4

CM 1104.036 1104.036S4

CM 1104.036 1104.03684

CM 1104.036 1104.03684

CM 5120.410

CM 1104.036 1104.03681 1104.036811

CM 5120.410

CM 1104.036 1104.036812 1104.036S2

R 1305.032 ROJ-008 1305.03284

R 1305.032 ROJ-008 1305.03284

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ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT

IA-283 CV-2692 IA CHECK VALVE M-218 Sh 4 / G-8 Aug-C

IA-767 CV-2214 ACCUMULATOR M-234 Sh 2 / G-5 Aug-C T-209 CHECK

IA-771 CV-2233 ACCUMULATOR M-234 Sh 2 / E-4 Aug-C T-210 CHECK

IA-775 CV-2234 ACCUMULATOR M-234 Sh 1 / E-5 Aug-C T-208 CHECK

PSV-2214 L TON CLR (E29A) ICW M-234 Sh 2 / F-5 Aug-C OUTLET RELIEF

PSV-2215 L TON CLR (E29B) ICW M-234 Sh 2 / D-5 Aug-C OUTLET RELIEF

PSV-5215 DG1 AIR RECEIVER T- M-217 Sh 4 / G-7 Aug-C 31A2 RELIEF

PSV-5216 DG1 AIR RECEIVER T- M-217 Sh 4 / G-8 Aug-C 31A1 RELIEF

PSV-5231 DG1 AIR RECEIVER T- M-217 Sh 4 / C-7 Aug-C · 31A3 RELIEF

PSV-5232 DG1 AIR RECEIVER T- M-217 Sh 4 / C-8 Aug-C 31A4 RELIEF

PSV-5237 DG2 AIR RECEIVER T- M-217 Sh 4 / G-2 Aug-C 3182 RELIEF

PSV-5238 DG2 AIR STARTER T-31 B1 M-217 Sh 4 / G-2 Aug-C RELIEF

PSV-5240 DG2 AIR RECEIVER M-217 Sh 4 / C-2 Aug-C RELIEF

PSV-5241 DG2 AIR STARTER T-3184 M-217 Sh 4 / C-2 Aug-C RELIEF

PSV-5414 T-93A PRESS RELIEF M-218 Sh 4 / F-8 Aug-C

PSV-5415 T-93B PRESS RELIEF M-218 Sh 4 / G-7 Aug-C

Augmented Valve Summary Listing

Page 5 of 7

ACT/ CLASS SIZE TYPE ACT POSITION PASS

NORM SAFE

ACT NC 1 CK SA 0/C C

ACT NC 0.375 CK SA C 0/C

ACT NC 0.5 CK SA C 0/C

ACT NC 0.375 CK SA C 0/C

ACT NC 0.75 RV SA C 0/C

ACT NC 0.75 RV SA C 0/C

ACT NC 0.5 RV SA C 0/C

ACT NC 0.5 RV SA C 0/C

ACT NC 0.5 RV SA C 0/C

ACT NC 0.5 RV SA C 0/C

ACT NC 0.5 RV SA C 0/C

ACT NC 0.5 RV SA C 0/C

ACT NC 0.5 RV SA C 0/C

ACT NC 0.5 RV SA C 0/C

ACT NC 1 RV SA C 0/C

ACT NC 1 RV SA C 0/C

TEST

FAIL REQ

N/A eve

cvo

N/A eve cvo

N/A eve

cvo

N/A eve

cvo

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 96 of 165

FREQ PROCEDURE NOTES

R 1305.032 ROJ-008 1305.03283

R 1305 .. 032 ROJ-008 1305.03283

. cs 1305.007 CSJ-014 1305.007S4

cs 1305.007 CSJ-014 1305.007S4

cs 1305.007 CSJ-014 1305.007S4

cs 1305.007 CSJ-014 1305.00784

cs 1305.007 CSJ-027 1305.00784

cs 1305.007 CSJ-027 1305.00784

10Y 1306.038

10Y 1306.038

10Y 1306.038

10Y 1306.038

10Y' 1306.038 -

10Y 1306.038

10Y 1306.038

10Y 1306.038

10Y 1306.038

10Y 1306.038

10Y 1306.038

10Y 1306.038

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ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT

PSV-6203 P-51 THERMAL OVER- M-222 Sh 1 / F-4 Aug-C PRESSURE RELIEF

PSV-6515 RC P32A COOLING M-238 Sh 1 / 8-2 Aug-C WATER DISCHARGE HOR RELIEF

PSV-6516 RC P328 COOLING M-238 Sh 2 / D-2 Aug-C WATER DISCHG HOR RELIEF

PSV-6517 RC P32C COOLING WTR M-238 Sh 3 / 8-2 Aug-C DISCHG HOR RELIEF

PSV-6518 RC P32D COOLING WTR M-238 Sh 1 / 8-2 Aug-C DISCH HOR RELIEF

SV-5218 KMA-3/4 AIR START M-217 Sh 4 / E-6 Aug-8 SOLENOID

SV-5233 KMA-1 /2 Al R START M-217 Sh 4 / D-6 Aug-8 SOLENOID

SV-5237 KM8-3/4 AIR START M-217 Sh 4 / E-3 Aug-8

Augmented Valve Summary Listing

Page 6 of 7

ACT/ CLASS SIZE TYPE ACT POSITION PASS

NORM SAFE

ACT NC 0.75 RV SA C 0/C

ACT NC 0.75 RV SA C 0/C

ACT NC 0.75 RV SA C 0/C

ACT NC 0.75 RV SA C 0/C

ACT NC 0.75 RV SA C 0/C

ACT NC 1.5 GL so C 0/C

ACT NC 1.5 GL so C 0/C

ACT NC 1.5 GL so C 0/C

TEST

FAIL REQ

N/A RV

N/A RV

N/A RV

N/A RV

N/A RV

C ETC

ETO

FSC

C ETC

ETO

FSC

C ETC

ETO

FSC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 97 of 165

FREQ PROCEDURE NOTES

10Y 1306.038

10Y 1306.038

10Y 1306.038

10Y 1306.038

10Y 1306.038 (

Q 1104.036 VPS-001 1104.036S1 1104.036S11

Q 1104.036 VPS-001 1104.036S1 1104.036S11

Q 1104.036 VPS-001 1104.036S1 1104.036811

Q 1104.036 VPS-001 1104.03681 1104.036811

Q 1104.036 VPS-001 1104.03681 1104.036811

Q 1104.036 VPS-001 1104.036S1 1104.036811

Q 1104.036 VPS-001 1104.036S12 1104.036S2

Q 1104.036 VPS-001 1104.036812 1104.036S2

Q 1104.036 VPS-001 1104.036812 1104.036S2

\.

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ANO Unit 1 1ST Plan

VALVE ID FUNCTION DRAWING/COOR CAT

SV-5239 KMB-1/2 AIR START M-217 Sh 4 / D-3 Aug-B

Augmented Valve Summary Listing

Page 7 of 7

ACT/ CLASS SIZE TYPE ACT POSITION PASS

NORM SAFE

ACT NC 1.5 GL so C 0/C

TEST

FAIL REQ

C ETC

ETO

FSC

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 98 of 165

FREQ PROCEDURE NOTES

Q 1104.036 VPS-001 1104.036S12 1104.036S2

Q 1104.036 VPS-001 1104.036S12 1104.036S2

Q 1104.036 VPS-001 1104.036S12 1104.036S2

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ANO Unit 1 1ST Plan

Skid Mounted Valve Summary Listing

Component ID Description

CV-5260 EDG K4A JACKET WTR CONTROL

CV-5261 EDG K4B JACKET WTR CONTROL

F0-151A DG1 SOAK BACK P-106A1/A3 DISCH CHECK

F0-1518 P10681 & P10683 DISCH 75# CHECK/RELIEF

F0-152A DG1 LUBE OIL VENT/PRIME LINE CHECK

F0-1528 DG2 LO VENT/PRIME LINE CHECK

F0-163 CV-5239 AIR START CHECK

F0-164 CV-5237 AIR START CHECK

F0-165 CV-5233 AIR START CHECK

F0-166 CV-5218 AIR START CHECK

F0-5213A DG1 DC LUBE OIL SOAK BACKPP P-106A1 DISCH CHECK

F0-52138 P10681 DISCH CHECK

F0-5214A DG1 AC LUBE OIL SOAK BACKPP P-106A3 DISCH CHECK

F0-52148 P-106-83 DISCH CHECK

F0-81A DG1 FUEL PRIMING PUMP P-104A DISCH CHECK

F0-818 P1048 DISCH CHECK

F0-82A DG1 FUEL PUMPS DISCH CHECK

F0-828 P1058 DISCH CHECK

F0-84A DG1 AC LUBE OIL SOAK BACKPUMP P-106A2 DISCH CHECK

F0-848 P106 82 DISCH CK

F0-90A DG1 FUEL RETURN TO DAY TANK LINE CHECK

F0-908 DG2 FUEL.RETURN TO DAY TANK LINE CHECK

L0-126A P-64A PRI MU PP AUX LO PP DISCH CK VLV

L0-1268 P-648 PRI MU PP AUX LO PP DISCH CK VLV

L0-126C P-64C PRI MU PP AUX LO PP DISCH CK VLV

L0-127A P-88A PRI MU PP MAIN LO PP SUPP CK VLV

L0-1278 P-BBA PRI MU PP MAIN LO PP SUPP CK VLV

L0-127C P-BBC PRI MU PP MAIN LO PP SUPP CK VLV

PSV-5270 K4A LO MANIFOLD PRESS RELIEF

PSV-5271 K4B LO MANIFOLD PRESS RELIEF

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 99 of 165

BPVClass OM Class Exempt

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

NC NC Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

3 3 Yes

NC NC Yes

NC NC Yes

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ANO Unit 1 1ST Plan

Condition Monitoring Justifications

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 100 of 165

CONDITION MONITORING JUSTIFICATIONS

NOTE: CEP-IST-1, AN0-1 Appendix, Enclosure 1 provides the data collected, and the Advisory Panel review, that supports the following testing requirements.

Valves in Grouping:

Condition Monitoring Justification: AC-60

AC-60

CM Testing Requirements: Perform open flow testing and closed leak testing at a frequency aligned with Appendix J testing. . 1

Condition Monitoring Justification: 8S-4A

Valves in Grouping: 8S-4A & BS-48

CM Testing Requirements: Perform disassembly and inspection at a frequency that may be extended to one valve in the group every 2R. Perform partial flow testing and leakage testing every 2Y on each valve in the group.

Valves in Grouping:

Condition Monitoring Justification:

8S-4A & BS-48

85-48

CM Testing Requirements: Perform disassembly and inspection at a frequency that may be extended to one valve in the group every 2R. Perform partial flow testing and leakage testing every 2Y on each valve in the group.

Condition Monitoring Justification: 8W-6A

Valves in Grouping:

CM Testing Requirements:

BW-6A & BW-68

Perform open flow verification and close testing using NIT or leak test starting at baseline then at a frequency that may be extended to one valve in the group every 1 R.

Condition Monitoring Justification: 8W-68

Valves in Grouping: BW-6A & BW-68

CM Testing Requirements: Perform open flow verification and close testing using NIT or leak test starting at baseline then at a frequency that may be extended to one valve in the group every 1 R. \

Condition Monitoring Justification: CA-61

Valves in Grouping:

CM Testing Requirements:

CA-61 & CA-62

Perform disassembly and insp~ction at a frequency that may be extended to one valve in the group every 2R. Perform partial flow testing and leakage testing every 2Y on each valve in the group.

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Condition Monitoring Justifications

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 101 of 165

CONDITION MONITORING JUSTIFICATIONS

NOTE: CEP-IST-1, AN0-1 Appendix, Enclosure 1 provides the data collected, and the Advisory Panel review, that supports the following testing requirements.

Valves in Grouping:

Condition Monitoring Justification: CA-62

CA-61 & CA-62

CM Testing Requirements: Perform disassembly and inspection at a frequency that may be extended to one valve in the group every 2R. Perform partial flow testing and leakage testing every 2Y on each valve in the group.

Condition Monitoring Justification: CF-1A

Valves in Grouping: CF-1A

CM Testing Requirements: Perform open flow verification and close leak testing at a frequency aligned with the Category A leak test.

Condition Monitoring Justification: CF-18

Valves in Grouping: CF-1 B

CM Testing Requirements: Perform open flow verification and close leak testing at a frequency aligned with the Category kleak test.

Condition Monitoring Justification: CS-1196

Valves in Grouping:

CM Testing Requirements:

CS-1196

Perform open flow verification and close testing using NIT starting at baseline then at a frequency that may be extended to every 1 R.

Condition Monitoring Justification: CS-1198

Valves in Grouping: CS-1198

CM Testing Requirements: Perform open flow verification and close testing using NIT starting at baseline then at a frequency that may be extended to every 1 R.

Valves in Grouping:

Condition Monitoring Justification: CS-26

CS-26

CM Testing Requirements: Perform open flow testing and closed leak testing at a frequency aligned with Appendix J testing.

Condition Monitoring Justification: CS-293

Valves in Grouping:

CM Testing Requirements:

CS-293 & CS-294

Perform open flow and close testing using NIT starting at baseline then at a frequency that may be extended to one valve in the group every 1 R.

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Condition Monitoring Justifications

Program Section No. SEP-AN0-1-IST-2 Revisiqn No. 5

Page 102 of 165

CONDITION MONITORING JUSTIFICATIONS

NOTE: CEP-IST-1, AN0-1 Appendix, Enclosure 1 provides the data collected, and the Advisory Panel review, that supports the following testing requirements.

Condition Monitoring Justification: CS-294

Valves in Grouping:

CM Testing Requirements:

CS-293 & CS-294

Perform open flow and close testing using NIT sta_rting at baseline then at a frequency that may be extended to one valve in the group every 1 R.

Condition Monitoring Justification: CZ-46

Valves in Grouping: CZ-46

CM Testing Requirements: Perform disassembly and inspection at a frequency that may be extended to every 3R.

Condition Monitoring Justification: DH-12

Valves in Grouping:

CM Testing Requirements:

DH-12 & DH-16

Perform open verification using normal operations and close testing using RT at a frequency of one valve in the group every 2R. Perform Leakage Testing every 2Y.

Condition Monitoring Justification: DH-14A

Valves in Grouping:

CM Testing Requirements:

DH-14A

Perform open flow verification and close leak testing at a frequency aligned with Category A leak test.

Condition Monitoring Justification: DH-148

Valves in Grouping: DH-148

CM Testing Requirements: Perform open flow verification and close leak testing at a frequency aligned with Category A leak test.

Condition Monitoring Justification: DH-16

Valves in Grouping: DH-12 & DH-16

CM Testing Requirements: Perform open verification using normal operations and close testing using RT at a frequency of one valve in the group every 2R. Perform Leakage Testing every 2Y.

Condition Monitoring Justification: DH-96

Valves in Grouping:

CM Testing Requirements:

DH-96

Perform open flow testing and closed leak testing at a frequency aligned with Appendix J testing.

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Condition Monitoring Justifications

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 103 of 165

CONDITION MONITORING JUSTIFICATIONS

NOTE: CEP-IST-1, AN0-1 Appendix, Enclosure 1 provides the data collected, and the Advisory Panel review, that supports the following testing requirements. ·

Condition Monitoring Justification: F0-54A1

Valves in Grouping:

CM Testing Requirements:

F0-54A1

Perform disassembly and inspection at a frequency that may be extended to every 6 years.

Condition Monitoring Justification: F0-54A2

Valves in Grouping: F0-54A2

CM Testing Requirements: Perform disassembly and inspection at a frequency that may be extended to every 6 years.

Condition Monitoring Justification: F0-54B1

Valves in Grouping: F0-5481

CM Testing Requirements: Perform disassembly and inspection at a frequency that may be extended to every 6 years.

Condition Monitoring Justification: F0-54B2

Valves in Grouping:

CM Testing Requirements:

F0-5482

Perform disassembly and inspection at a frequency that may be extended to every 6 years.

Condition Monitoring Justification: F0-55A1

Valves in Grouping:

CM Testing Requirements:

F0-55A1

Perform disassembly and inspection at a frequency that may be extended to every 6 years.

Condition Monitoring Justification: F0-55A2

Valves in Grouping: F0-55A2

CM Testing Requirements: Perform disassembly and inspection at a frequency that may be extended to every 6 years.

Condition Monitoring Justification: . F0-55B1

Valves in Grouping: F0-5581

CM Testing Requirements: Perform disassembly and inspection at a frequency that may be extended to every 6 years.

I I

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Condition Monitoring Justifications

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 104 of 165

CONDITION MONITORING JUSTIFICATIONS

NOTE: CEP-IST-1, AN0-1 Appendix, Enclosure 1 provides the data collected, and the Advisory Panel review, that supports the following testing requirements.

Condition Monitoring Justification: F0-5582

Valves in Grouping:

CM Testing Requirements:

F0-5582

Perform disassembly and inspection at a frequency that may be extended to every 6 years.

Condition Monitoring Justification: FO-BA

Valves in Grouping: F0-8A & F0-88

CM Testing Requirements: Perform disassembly and inspection at a frequency that may be extended to one valve in the group every 6 years. ·

Condition Monitoring Justification: F0-88

Valves in Grouping:

CM Testing Requirements:

F0-8A & F0-88

Perform disassembly and inspection at a frequency that may be extended to one valve in the group every 6 years.

Condition Monitoring Justification: IA-824

Valves in Grouping:

CM Testing Requirements:

IA-824

Perform open flow testing and closed leak testing at a frequency aligned with Appendix J testing.

Condition Monitoring Justification: ICW-114

Valves in Grouping: ICW-114

CM Testing Requirements: Perform ,open flow testing and closed leak testing at a frequency aligned with Appendix J testing.

Condition Monitoring Justification: ICW-26

Valves in Grouping:

CM Testing Requirements:

ICW-26

Perform open flow testing and closed leak testing at a frequency aligned with Appendix J testing.

Condition Monitoring Justification: ICW-30

Valves in Grouping:

CM Testing Requirements:

ICW-30

Perform open flow testing and closed leak testing at a frequency aligned with Appendix J testing.

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Condition Monitoring Justifications

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 105 of 165

CONDITION MONITORING JUSTIFICATIONS

NOTE: CEP-IST-1, AN0-1 Appendix, Enclosure 1 provides the data collected, and the Advisory Panel review, that supports the following testing requirements.

Condition Monitoring Justification: MS-271

Valves in Grouping:

CM Testing Requirements:

MS-271 & MS-272

Perform disassembly and inspection at a frequency that may be extended to one valve in the group every 1 R.

Condition Monitoring Justification: MS-272

Valves in Grouping: MS-271 & MS-272

CM Testing Requirements: Perform disassembly and inspection at a frequency that may be extended to one valve in the group every 1 R. ·

Condition Monitoring Justification: MU-1211

Valves in Grouping:

CM Testing Requirements:

MU-1211, MU-1212, MU-1213, MU-1214, & MU-1215

Perform open flow verification and close testing using leak testing or NIT starting at baseline then at a frequency that may be extended to one valve in the group every 1 R.

Condition Monitoring Justification: MU-1212

Valves in Grouping:

CM Testing Requirements:

MU-1211, MU-1212, MU-1213, MU-1214, & MU-1215

Perform open flow verification and close testing using leak testing or NIT starting at baseline then at a frequency that may be extended to one valve in the group every 1 R.

Condition Monitoring Justification: MU-1213

Valves in Grouping: MU-1211, MU-1212, MU-1213, MU-1214, & MU-1215

CM Testing Requirements: Perform open flow verification and close testing using leak testing or NIT starting at baseline then at a frequency that may be extended to one valve in the group every 1 R.

Condition Monitoring Justification: MU-1214

Valves in Grouping:

CM Testing Requirements:

l

MU-1211, MU-1212, MU-1213, MU-1214, & MU-1215

Perform open flow verification and close testing using leak testing or NIT starting at baseline then at a frequency that may be extended to one valve in the group every 1 R.

Condition Monitoring Justification: MU-1215

Valves in Grouping:

CM Testing Requirements:

MU-1211, MU-1212, MU-1213, MU-1214, & MU-1215

Perform open flow verification and close testing using leak testing or NIT starting at baseline then at a frequency that may be extended to one valve in the group every 1 R.

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ANO Unit 1 1ST Plan

Condition Monitoring Justifications

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 106 of 165

CONDITION MONITORING JUSTIFICATIONS

NOTE: CEP-IST-1, AN0-1 Appendix, Enclosure 1 provides the data collected, and the Advisory Panel review, that supports the following testing requirements.

Valves in Grouping:

Condition Monitoring Justification: MU-1306

MU-1306, MU-1307, MU-1308, & MU-1309

CM Testing Requirements: Perform open flow verification and close testing using NIT starting at baseline then at a frequency that may be extended to one valve in the group every 2 years.

Condition Monitoring Justification: MU-1307

Valves in Grouping: MU-1306, MU-1307, MU-1308, & MU-1309

CM Testing Requirements: Perform open flow verification and close testing using NIT starting at baseline then at a frequency that may be extended to one valve in the group every 2 years.

Valves in Grouping:

Condition Monitoring Justification: MU-1308

MU-1306, MU-1307, MU-1308, & MU-1309

CM Testing Requirements: Perform open flow verification and close testing using NIT starting at baseline then at a frequency that may be extended to one valve in the group every 2 years.

Condition Monitoring Justification: MU-1309

Valves in Grouping: MU-1306, MU-1307, MU-1308, & MU-1309

CM Testing Requirements: Perform open flow verification and close testing using NIT starting at baseline then at a frequency that may be extended to one valve in the group every 2 years.

Condition Monitoring Justification: MU-36A

Valves in Grouping: MU-36A & MU-368

CM Testing Requirements: Perform open flow testing and closed leak testing at a frequency aligned with Appendix J testing. ·

Condition Monitoring Justification: MU-368

Valves in Grouping:

CM Testing Requirements:

MU-36A & MU-36B

Perform open flow testing1and closed leak testing at a frequency aligned

with Appendix J testing .

Valves in Grouping:

. Condition Monitoring Justification: N2-32

N2-32

CM Testing Requirements: Perform open flow testing and closed leak testing at a frequency aligned with Appendix J testing.

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Condition Monitoring Justifications

Program Section No. SEP-AN0-1-IST-2 Revision No. 5

Page 107 of 165

CONDITION MONITORING JUSTIFICATIONS

NOTE: CEP-IST-1, AN0-1 Appendix, Enclosure 1 provides the data collected, and the Advisory Panel review, that supports the following testing requirements.

Condition Monitoring Justification: N2-34 \

Valves in Grouping: N2-34

CM Testing Requirements: Perform a forward flow verification and RT or disassembly every 2R.

Condition Monitoring Justification: RC-1009

Valves in Grouping: RC-1009, RC-1010, RC-1011, RC-1012, RC-1013, RC-1014, RC-1015, & RC-1016

CM Testing Requirements: Exercise and Inspect a minimum of two valves in the group every 1 R.

Condition Monitoring Justification: RC-1010

Valves in Grouping: RC-1009, RC-1010, RC-1011, RC-1012, RC-1013, HC-1014, RC-1015, & RC-1016

CM Testing Requirements: Exercise and Inspect a minimum of two valves in the group every 1 R.

Condition Monitoring Justification: RC-1011

Valves in Grouping: RC-1009, RC-1010, RC-1011, RC-1012, RC-1013, RC-1014, RC-1015, & RC-1016

CM Testing Requirements: Exercise and Inspect a minimum of two valves in the group every 1 R.

Condition Monitoring Justification: RC-1012

Valves in Grouping: RC-1009, RC-1010, RC-1011, RC-1012, RC-1013, RC-1014, RC-1015, & RC-1016

CM Testing Requirements: Exercise and Inspect a minimum of two valves in the group every 1 R.

Condition Monitoring Justification: RC-1013

Valves in Grouping: RC-1009, RC-1010, RC-1011, RC-1012, RC-1013, RC-1014, RC-1015, & RC-1016 .

CM Testing Requirements: Exercise and Inspect a minimum of two valves in the group every 1 R.

Condition Monitoring Justification: RC-1014

Valves in Grouping: RC-1009, RC-1010, RC-1011, RC-1012, RC-1013, RC-1014, RC-1015, & RC-1016

CM Testing Requirements: Exercise and Inspect a minimum of two valves in the group every 1 R.

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ANO Unit 1 1ST Plan

Condition Monitoring Justifications

Program Section No. SEP-AN0-1-IST-2

Revision No. 5

Page 108 of 165

CONDITION MONITORING JUSTIFICATIONS

NOTE: CEP-IST-1, AN0-1 Appendix, Enclosure 1 provides the data collected, and the Advisory Panel review, that supports the following testing requirements.

Condition Monitoring Justification: RC-1015

Valves in Grouping: RC-1009, RC-1010, RC-1011, RC-1012, RC-1013, RC-1014, RC-1015, & RC-1016

CM Testing Requirements: Exercise and Inspect a minimum of two valves in the group every 1 R.

Condition Monitoring Justification: RC-1016

Valves in Grouping: RC-1009, RC-1010, RC-1011, RC-1012, RC-1013, RC-1014, RC-1015, & RC-1016

CM Testing Requirements: Exercise and Inspect a minimum of two valves in the group every 1 R.

Condition Monitoring Justification: SW-11

Valves in Grouping: SW-11 & SW-13

CM Testing Requirements: Perform a forward flow verification and NIT starting at baseline then at a frequency that may be extended one valve in the group every 1 R.

Valves in Grouping:

Condition Monitoring Justification: SW-13

SW-11 & SW-13

CM Testing Requirements: Perform a forward flow verification and NIT starting at baseline then at a frequency that may be extended one valve in the group every 1 R.

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System:

Valve(s):

CSJ-001

Steam Generator Secondary System

CV-2691, CV-2692

Code Class: 2

Code Category:

Function:

B

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 109 of 165

These spring-loaded normally-open air-operated valves have a closed safety function to isolate the steam generators on a MSLI actuation signal to prevent unrestricted blowdown of both steam generators in the event of a downstream steam leak, help ensure a source of steam for EFW pump operation, and to isolate the steam generators in the event of a tube rupture. In the open position this valve provides a pathway for steam from the steam generators to the main turbine generator and auxiliaries. There is no safety function associated with steam flow downstream of this valve.

Cold Shutdown Justification:

Closure of either of these valves under power conditions effectively isolates the associated steam generator. This, in turn, would result in an extreme power transient and a plant trip. There is a valve control mechanism that allows a partial stroke (approximately 10%) during power operation. However, Improved Technical Specifications state that it is imprudent to stroke the valves at power due to risk of valve closure.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in the closed direction and fail safe tested during cold shutdown periods in accordance with the provisions of the Code.

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CSJ-002

System: Steam Generator Secondary System

Valve(s): CV-2630, CV-2680

Code Class: 2

Code Category:

Function:

B

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 110 of 165

These normally-open motor-operated valves have a closed safety function to isolate the main feedwater system from the steam generators following a MSLI actuation signal. They are normally open to provide feedwater supply to the steam generators - non-safety function.

Cold Shutdown Justification:

Closure of either of these valves, during power operatipns, results in loss of feedwater to its associated steam generator. This, in tum, would cause a loss of steam generator level control, severe plant transient, and ultimately a plant trip. There is, however, a valve control mechanism that allows a partial stroke (approximately 10%) during power operation. However, Improved Technical Specifications state that it is imprudent to stroke the valves at power due to risk of valve closure.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in the closed direction during cold shutdown periods in accordance with the provisions of the Code.

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System:

Valve(s):

Service Water System

CV-3643

Code Class: 3

Code Category:

Function:

A

CSJ-003

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 111 of 165

This normally-open motor-operated valve has a closed safety function to max1m1ze service water flow to the Loop 1 and 2 headers by isolating the auxiliary cooling water (ACW) loop under emergency conditions. It is required to be leak tested to ensure maintenance of ECP inventory per OBA analysis requirements.

Cold Shutdown Justification:

Closing this valve requires a shutdown of cooling water to various coolers supplied by the ACW cooling line. During normal plant operation at !;)OWer the he.at removal demands of the ACW system requires the supply of cooling water to the various coolers. Perturbation of flow to any of the on-line heat exchangers served by ACW (including main turbine generator auxiliaries) could have a severe adverse impact on plant operation with the potential for unacceptable flow and temperature transients, equipment damage, and a plant trip.

Alternate Test Schedule:

This valve will be full-stroke exercised and stroke timed in the closed direction during cold shutdown periods in accordance with the provisions of the Code.

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System:

Valve(s):

CSJ-004

Chilled Water System

CV-6202, CV-6203, CV-6205

Code Class: 2

Code Category:

Function:

A

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 112 of 165

These normally-open power-operated valves have a closed safety function on an ES actuation signal to provide containment isolation. In the open position they provide flowpaths for the supply and return of chilled water for cooling in the reactor building - non-safety function.

Cold Shutdown Justification:

Testing of these valves would require isolation of chill water to the reactor building coolers. Since the reactor building coolers are a significant chilled water load, the main chillers would have to be secured to avoid an automatic trip on low chilled water flow or temperature. To avoid an unacceptable rise in reactor building temperatures, service water would also need to be aligned to the reactor building cooling coils. Auxiliary cooling water system flows and the associated secondary plant components would be affected by the reduction in available cooling water. A number of secondary plant components require manual valve operations to control ACW flow including the seal oil coolers, exciter air coolers, condenser vacuum pump coolers and electro-hydraulic control fluid coolers. Intermediate cooling water system temperatures would also be affected by the reduction in available service water to the ICW coolers. Manual valve operations are also required to adjust ICW temperatures. The service water bays should also be injected with biocide while service water is aligned to the reactor building ·cooling coils to avoid the potential of biological fouling. The required valve operations coincident with the activity of securing and restarting a main chiller present a significant operating burden. The demands on the plant staff and potential adverse temperature effects on plant equipment are not commensurate with any gain in safety resulting from performing this test every three months.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in the closed direction during cold shutdown periods in accordance with the provisions of the Code. CV-6202 and CV-6203 will be fail-safe tested in the closed position during cold shutdown periods in accordance with the provisions of the-Code.

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System:

Valve(s):

Reactor Coolant System

SV-1077, SV-1079

Code Class: 1

Code Category:

Function:

B

CSJ-005

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 113 of 165

These normally-closed solenoid-operated valves provide the pressure boundary between the RCS and the containment atmosphere. They have an open safety function to vent non-

. condensable gases from the pressurizer to ensure natural circulation under accident conditions. Each solenoid valve has a safety function in the closed position. Each valve, if open, would need to close to provide a reactor coolant pressure boundary isolation break to the quench tank. The valve redundancy of the vent paths serves to minimize the probability of inadvertent actuation and breach of reactor coolant pressure boundary while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path. This valve fails closed.

Cold Shutdown Justification:

These valves connect directly to the reactor coolant system (RCS) and are the Class 1 isolation valves for the system, forming part of the RCS boundary. Opening any of these valves during power operation exposes the plant to the possibility of a valve failure in the open position. While a dual valve isolation configuration exists, the potential for developing a reactor coolant leak is increased by testing at power. Although the maximum leakage potential from this line is less than that defined as a loss of coolant accident, it could be of sufficient magnitude as to exceed the AN0-1 Technical Specification limits and force an expedited plant shutdown and cooldown. In addition, historical data and operational experience related to these valves indicate a high potential for seat leakage, a problem that would be exacerbated by repeated (quarterly) operation at RCS operating pressure.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in the open and closed direction during cold shutdown periods in accordance with the provisions of the Code. These valves will be fail-safe tested in the closed position during cold shutdown periods in accordance with the provisions of the Code.

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System:

Valve(s):

CSJ-006

Reactor Coolant System

SV-1071, SV-1072, SV-1073, SV-1074

Code Class: 1

Code Category:

Function:

B

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 114of 165

These normally-closed solenoid-operated valves provide the pressure boundary between the RCS and the containment atmosphere. They have an open safety function to vent non­condensable gases from the reactor vessel to ensure natural circulation under accident conditions. Each solenoid valve has a safety function in the closed position. Each valve, if open, would need to close to provide a reactor coolant pressure boundary isolation break to the containment atmosphere. The valve redundancy of the vent paths serves to minimize the probability of inadvertent actuation and breach of reactor coolant pressure boundary while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path. This valve fails closed.

Cold Shutdown Justification:

These valves connect directly to the reactor coolant system (RCS) and are the Class 1 isolation valves for the system, forming part of the RCS boundary. Opening any of these valves during power operation exposes the plant to the possibility of a valve failure in the open position. While a dual valve isolation configuration exists, the potential for developing a reactor coolant leak is increased by testing at power. Although the maximum leakage potential from this line is less than that defined as a loss of coolant accident, it could be of sufficient magnitude as to exceed the AN0-1 Technical Specification limits and force an expedited plant shutdown and cooldown. In addition, historical data and operational experience related to these valves ir:idicate a high potential for seat leakage - a problem that would be exacerbated by repeated (quarterly) operation at RCS operating pressure.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in the open and closed direction during cold shutdown periods in accordance with the provisions of the Code. These valves will be fail-safe tested in the closed position during cold shutdown periods in accordance with the provisions of the Code.

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~---------------~

ANO Unit 1 1ST PLAN

System:

Valve(s):

CSJ-007

Reactor Coolant System

SV-1081, SV-1082, SV-1083, SV-1084 SV-1091, SV-1092, SV-1093, SV-1094

Code Class: 1

Code Category:

Function:

B

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 115 of 165

These normally-closed solenoid-operated valves provide the pressure boundary between the RCS and the containment atmosphere. They have an open safety function to vent non­condensable gases from the reactor coolant loop high points to ensure natural circulation under accident conditions. Each sol.enoid valve has a safety function in the closed position. Each valve, if open, would need to close to provide a reactor coolant pressure boundary isolation break to the containment atmosphere. The valve redundancy of the vent paths serves to minimize the probability of inadvertent actuation and breach of reactor coolant pressure boundary while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path. These valves fail closed.

Cold Shutdown Justification:

These valves connect directly to the reactor coolant system (RCS) and are the Class 1 isolation valves for the system, forming part of the RCS boundary. Opening any of these valves during power operation exposes the plant to the possibility of a valve failure in the open position. While a dual valve isolation configuration exists, the potential for developing a reactor coolant leak is increased by testing at power. Although the maximum leakage potential from this line is less than that defined as a loss of coolant accident, it could be of sufficient magnitude as to exceed the AN0-1 Technical Specification limits and force an expedited plant shutdown and cooldown. In addition, historical data and operational experience related to these valves indicate a high potential for seat leakage - a problem that would be exacerbated by repeated (quarterly) operation at RCS operating pressure.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in the open and closed direction during cold shutdown periods in accordance with the provisions of the Code. These valves will be fail-safe tested in the closed position during cold shutdown periods in accordance with the provisions of the Code.

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System:'

Valve(s):

Reactor Coolant System

PSV-1000

Code ·Class: 1

Code Category:

Function:

B

CSJ-008

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 116 of 165

This pilot-operated electromatic relief valve (PORV) has an open safety function to relieve RCS pressure to preclude challenging the Code safety valves, mitigate a tube rupture event, and when the reactor coolant system is operated at low temperatures this valve provides over­pressure protection (L TOP) to reactor coolant system components. )"his electromatic relief valve (PORV) has a safety function in the closed position. This relief valve provides reactor coolant boundary integrity, when no overpressure condition exists, or the valve has opened and recloses, to prevent reactor coolant inventory loss.

Cold Shutdown Justification:

This valve is part of the Class 1 isolation for the RCS, forming part of the RCS boundary. Opening this valve during power operation exposes the plant to the possibility of a valve failure in the open position and the potential of developing a significant reactor coolant leak. In addition, historical data and operational experience related to this valve indicate a high potential for failure of this valve to re-close.

Alternate Test Schedule:

This valve will be full-stroke exercised and stroke timed in both the open and closed directions during cold shutdown periods in accordance with the provisions of the Code. This valve will be fail-safe tested in the closed position during cold shutdown periods in accordance with the provisions of the Code.

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CSJ-009

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 117 of 165

System:

Valve(s):

Primary Makeup and Purification System

CV-1270, CV-1271, CV-1272, CV-1273, CV-1274

Code Class: 2

Code Category:

Function:

A

These normally-open motor-operated valves provide flowpaths for seal water leakoff from the reactor coolant pumps - non-safety function. They have a closed safety function on an ES actuation signal to provide containment isolation.

Cold Shutdown Justification:

Isolation of the reactor coolant pump seal bleedoff lines or alternate seal bleedoff line to the quench tank would subject the seals to severe hydraulic and/or thermal transients, potentially resulting in seal damage or even failure.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in the closed direction during cold shutdown periods in accordance with the provisions of the Code.

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System:

Valve(s):

CSJ-010

Primary Makeup and Purification System

CV-1300, CV-1301

Code Class: 2

Code Category:

Function:

B

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 118 of 165

These normallyiopen motor-operated valves have a closed safety function on an ES actuation signal to isolate the minimum flow recirculation flowpath in order to maximize high pressure injection flow to the reactor coolant system.

Cold Shutdown Justification:

These valves remain open during normal operation to provide minimum flow for pump protection to the running makeup pump. Isolation of this flowpath in a non-ES actuated condition places the pump at risk. A small perturbation in makeup flow requirements could reduce pump flow to less than that required to preclude pump damage. The makeup pumps are particularly vulnerable to this phenomenon in a very short time due to their high speed, high head design.

Alternate Test Schedule:

These valves will be fu'll-stroke exercised and stroke timed in the closed direction during cold shutdown periods in accordance with the provisions of the Code.

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PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 119 of 165

/ System:

Valve(s):

CSJ-011

Decay Heat Removal System

CV-1050, CV-1410

Code Class: CV-1050 - Class 1 CV-1410 - Class 2

Code Category:

Function:

A

These normally-closed motor-operated valves have a closed safety function to act as a redundant pressure boundary between the reactor coolant system and the decay heat removal system during power operation. Due to past commitments, isolation of the reactor coolant system is considered to be significantly important and, in response to this, these valves are seat leakage tested. They have an open function to provide a decay heat removal flowpath to effect plant cooldown. Note that although this function supports plant cooldown, it is not required since AN0-1 is licensed for hot shutdown only, decay heat removal is considered to be significantly important to safety and testing in the open direction is justified.

Cold Shutdown Justification:

These valves are provided with an interlock feature that prevents opening when reactor coolant pressure exceeds 290 psig. Overriding this interlock and opening either of these valves would subject the low pressure rated portions of the decay heat removal/low pressure coolant injection system to reactor coolant pressures separated by only a single closed valve. This is considered to be imprudent under normal RCS operating pressure.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in both the open and closed directions during cold shutdown periods in accordance with the provisions of the Code.

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CSJ-012

System: Intermediate Cooling Water System I

Valve(s): CV-2235

Code Class: 2

Code Category:

Function:

A

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 120 of 165

This motor-operated valve opens to provide a flowpath for cooling water to the control rod drive (CRD) coolers. Cooling of these components is not required for accident mitigation nor for reactor cooldown. This is not considered to be a safety function. It has an active closed safety function to provide containment isolation.

Cold Shutdown Justification:

Closing this valve requires isolating cooling water flow to the CRDs. High temperature alarm response for multiple CRDs requires a plant trip.

Alternate Test Schedule:

This valve will be full-stroke exercised and stroke timed in the closed direction during cold shutdown periods in accordance with the provisions the Code.

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PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 121 of 165

\

System:

Valve(s):

CSJ-013

Intermediate Cooling Water System

CV-2220, CV-2221

Code Class: 2

Code Category:

Function:

A

These motor-operated valves open to provide a flowpath for cooling water from the reactor coolant pump (RCP) and control rod drive coolers. Cooling of these components is not required for accident mitigation or for reactor cooldown. This is not considered to be a safety function. It has a closed safety function to provide containment isolation.

Cold Shutdown Justification:

Closing these valves requires isolating cooling water flow to the RCPs and the CRDs. High temperature alarm response for multiple CRDs requires a plant trip.

Alternate Test Schedule: \

These valves will be full-stroke exercised and stroke timed in the closed direction during cold shutdown periods in accordance with the provisions of the Code.

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System:

CSJ-014

Intermediate Cooling Water System

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 122 of 165

Valve(s): CV-2214 (AOV), CV-2215 (MOV), CV-2233 (AOV), IA-767 (CKV), IA-771 (CKV)

Code Class: 2 (CV-2214, CV-2215, CV-2233), NC (IA-767, IA-771)

Code Category:

Function:

A (CV-2214, CV-2215, CV-2233), Aug-C (IA-767, IA-771)

CV-2214, CV-2215, and CV-2233 open to provide a flowpath for cooling water to and from the reactor coolant letdown heat exchangers. Cooling of these components is not required for accident mitigation or for reactor cooldown. This is not considered to be a safety function. They have a closed safety function to provide containment isolation. The associated check valves, IA-767 and IA-771, maintain accumulator pressures following a loss of instrument air to provide motive force for closure of CV-2214 and CV-2233 given a subsequent engineering safeguards

~isolation signal.

Cold Shutdown Justification:

At power operation closing CV-2214, CV-2215, or CV-2233 would result in securing letdown flow. Securing letdown flow during power operation would result in thermal transients to nozzles and piping and perturbations to the makeup system which among other effects will result in a transient in RCP seal injection which could result in damage to the RCP seals. Likewise, testing IA-767 or IA-771 would require closure of CV-2214 or CV-2233, respectively.

Alternate Test Schedule:

CV-2214, CV-2215 and CV-2233 will be full-stroke exercised and stroke timed in the closed direction during cold shutdown periods in accordance with the provisions of the Code. CV-2214 and CV-2233 will be failed safe tested at that time which additionally provides IA-767 and IA-771 closure verification. IA-767 and IA-771 will also be open stroke tested on a cold shutdown periodicity, in accordance with 1STC-3522(a).

Note:

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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ANO Unit 1 1ST PLAN

System:

Valve(s):

CSJ-015

Steam Generator Secondary System

CV-2625, CV-2675

Code Class: NC

Code Category:

Function:

B

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 123 of 165

These normally-open motor operated valves have· an active closed safety function to isolate the main feedwater system from the steam generators. They are normally open to provide feedwater supply to the steam generators - non-safety function.

Cold Shutdown Justification:

Closure of either of these valves during power operation results in the loss of feedwater to the . associated steam generator. This; in turn, would cause a loss of steam generator level control, severe plant transient, and ultimately a plant trip.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in the closed position during cold shutdown periods in accordance with the provisions of the Code.

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ANO Unit 1 1ST PLAN

System:

Valve(s):

CSJ-016

Steam Generator Secondary System

CV-2622, CV-2672

Code Class: NC

Code Category:

Function:

B

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 124 of 165

These normally-open air operated valves have an active closed safety function to isolate the main feedwater system from the steam generators. They are normally open to provide control of the feedwater supply to the steam generators - non-safety function.

Cold Shutdown Justification:

Closure of either 0f these valves during power operation results in feedwater flow perturbations to the associated I steam generator. This, in turn, could cause a loss of steam generator level control, severe plant transient, and possibly a plant trip.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in the closed position during cold shutdown periods in accordance with the provisions of the Code.

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ANO Unit 1 1ST PLAN

System:

Valve(s):

CSJ-017

Steam Generator Secondary System

CV-2623, CV-2673 i

Code Class: NC

Code Category:

Function:

B

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 125 of 165

These normally-closed air operated valves have an active closed safety function to isolate the main feedwater system from the steam generators. They are normally closed to provide control of the feedwater supply to the steam generators - non-safety function.

Cold Shutdown Justification:

Cycling of either of these valves during power operation results in feedwater flow perturbations to the associated steam generator. This, in turn, could cause a loss of steam generator level control, severe plant transient, and possibly a plant trip.

Alternate Test Schedule:

These valves will be full-stroke exercised and stroke timed in the closed position during cold shutdown periods in accordance with the provisions of the Code.

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ANO Unit 1 1ST PLAN

CSJ-018

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 126 of 165

System:

Valve(s):

Primary Makeup and Purification System/High Pressure Injection

MU-19A, MU-198, MU-19C

Code Class: 2

Code Category:

Function:

C

These check valves have an open safety function during an ES actuation to provide flow paths . from the primary makeup pumps via the high pressure injection headers to the RCS. They have a closed safety function to maximize high pressure injection flow following an ES actuation by preventing recirculation through an idle pump.

Cold Shutdown Justification:

These are check valves with no external means of moving the obturator in the open or closed directions or any external position indication devices. During plant operation at power the maximum flow that can be directed through these valves is limited to that of the reactor coolant system makeup rate which is substantially less than that required under accident conditions. This limitation is based on the following design issues:

1. With a pump operating at the design accident flow, the flow rate into the reactor coolant system will exceed the letdown capacity and there is insufficient space available in the · pressurizer to accommodate the influx of water.

2. At. the accident flow rate, normal makeup flow would necessarily be augmented by additional flow directed into the RCS via the high pressure injection nozzles. This would result in additional thermal stress cycles at these critical areas.

3. The capacity of the·normal makeup pump suction source (reactor coolant makeup tank) is not sufficient to provide flow to the pump suction at the accident flow rate, thus water from the borated water storage tank (BWST) would be needed to supplement this water source. Water in the BWST is maintained at a higher boric acid concentration than that of the RCS and, as a result, injection of BWST water into the RCS would result in an unacceptable power transient that would jeopardize plant operation.

Alternate Test Schedule:

These check valves are partial stroke exercised open with flow quarterly. These check valves will be full-stroke exercised with flow in the open and closed directions on a cold shutdown periodicity in accordance with the provisions of ASME OM ISTC, Section ISTC-3522.

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ANO Unit 1 1ST PLAN

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 127 of 165

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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System:

CSJ-019

Emergency Feedwater (EFW) System

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 128 of 165

Valve(s): FW-10A, FW-108, FW-55A, FW-558, FW-56A, FW-568

Code Class: 3

Code Category: · C

Function:

Check valves FW-55A, FW-558, FW-56A, and FW-568 have an open safety function to provide a flowpath from the emergency feedwater pumps to the steam generators following an EFIC actuation. They have a closed safety function to prevent recirculation and provide the required EFW flow to a steam generator in the event that the associated EFW pump should fail.

FW-10A and FW-108 have an open safety function to provide a flowpath from the emergency 'feedwater pumps to the steam generators following an EFIC actuation. They also have an open safety function to provide a minimum recirculation flowpath for the emergency feedwater pumps. They do not have a closed safety function.

Cold Shutdown Justification:

In order to test the closure of these check valves, the following sequence of events takes place. First, one train of EFW has to be tested to prove operability prior to tagging out the train to be tested. Then the train to be tested is tagged out, several valves are manipulated, DI water is aligned to EFW, a vent valve is opened, and leakage is checked. This process is repeated for the other check valve in that train. Then tags are cleared for that train and the train is tested for operability. The p·rocess is then repeated for the other train. Entergy Operations estimates that it would take a crew of three approximately 12 hours to complete this test. It is felt that due to the length of time that one train of EFW is unavailable and the amount of manpower involved that the burden of performing this test outweighs any gain in safety resulting from performing

. this test every three months.

Alternate Test Schedule:

These check valves are full-stroke exercised in the open and closed direction during cold shutdown periods in accordance with the provisions of ASME OM Code, Section ISTC-3522.

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time, if they are both performed within the same interval."

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System:

Valve(s):

CSJ-20

Service Water System - Intake Structure

SW-1A, SW-1 B, SW-1 C

Code Class: 3

Code Category:

Function:

AC

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 129 of 165

These check valves have an open safety function to provide service water flow from the service water pumps to the service water headers. They have a closed safety function to prevent reverse flow through an idle pump. This valve is required to be leak tested to ensure maintenance of ECP inventory per OBA analysis requirements.

Cold Shutdown Justification:

These are check valves with no external means of moving the obturator or any external position indication devices. The service water system provides a continuous supply of cooling water to the two safety-related (essential) service water headers as well as the non-essential header related to main turbine generator and other plant support auxiliaries. During normal plant operation at power the heat removal demands of the service water system require the operation of at least two and sometimes three pumps. After the system operation reaches a degree of stability, perturbation of flow to any of the on-line heat exchangers could have a severe adverse impact on plant operation with the potential for unacceptable flow and temperature transients. This situation also precludes any major flow adjustments on specific heat loads. As such, there is no assurance that, under certain heat load requirements, a pump can be secured to reverse­flow test its associated discharge check valve.

· Alternate Test Schedule:

These check valves are full-stroke exercised in the open and closed direction on a cold shutdown periodicity in accordance with the provisions of ASME OM ISTC, Section ISTC-3522.

Note:

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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ANO Unit 1 1ST PLAN

System:

Valve(s):

Service Water System

SW-9

Code Class: 3

Code Category:

Function:

AC

CSJ-021

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 130 of 165

' This check valve has a closed safety function to prevent reverse flow from the service water , system through the intermediate cooling water (ICW) coolers upon isolation of the service water supply to the coolers. This valve is required to be leak tested to ensure maintenance of ECP inventory per OBA analysis requirements.

Cold Shutdown Justification:

This is a check valve with no external means of moving the obturator or any external position indication devices, thus reverse flow testing of this valve requires an extended shutdown of cooling water to the ICW coolers. During normal plant operation at power the heat removal demands of the ICW system requires the supply of cooling water to the ICW coolers. Perturbation of flow to any of the on-line heat exchangers served by ICW (including reactor plant auxiliaries) could have a severe adverse impact on plant operation with the potential for unacceptable flow and temperature transients, equipment damage, and a plant trip.

Alternate Test Schedule:

This check valve is full-stroke exercised in the open and closed direction during cold shutdown periods in accordance with the provisions of ASME OM Code, Section ISTC-3522.

Note:

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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System:

Valve(s):

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 131 of 165

CSJ-022

(CANCELLED, See ROJ-005)

Makeup and Purification / High Pressure Injection

MU-34A, MU-348, MU-34C, MU-34D

Code Class: 1

Code Category:

Function:

C

These check valves have an open safety function during an ES actuation to provide HP injection flow into the reactor vessel from HP injection loops. These check valves have a safety function in the closed position. This normally closed valve provides reactor coplant boundary isolation for the piping of the high pressure injection system.

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System:

Valve(s):

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 132 of 165

CSJ-023

(CANCELLED, See ROJ-006)

Makeup and Purification / High Pressure Injection

MU~6~MU~6B,MU~6C,MU~6D

Code Class: 1

Code Category:

Function:

C

These check valves have an open safety function during an ES actuation to provide HP injection flow into the reactor vessel from HP injection loops. These check valves have a safety function in the closed position. Each normally closed valve provides reactor coolant boundary isolation for the piping of the high pressure injection system. Each valve is also the inboard containment isolation valve but is not required to be Appendix J leak tested.

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ANO Unit 1 1ST PLAN

System:

Valve(s):

,, CSJ-024

Emergency Feedwater System

FW-13A, FW-13B

Code Class: 2

Code Category:

Function:

C

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 133 of 165

These check valves have an open safety function to provide flowpaths from the EFW pumps to the steam generators. They have a closed safety function to prevent reverse flow from the steam generator. They have a closed safety function to prevent reverse flow from the steam generator when EFW system is not in service to preclude steam biQding of the EFW pumps or damage to the pump suction header due to over-pressurization.

Cold Shutdown Justification:

These are check valves with no external means for exercising and no external position indication mechanism. The only practical means of exercising is to operate an EFW pump discharging to the steam generators. During plant operation at power this is not practical due to the potential for thermal shock of the steam generator nozzles and internals. During quarterly testing of the EFW pumps, flow is routed through a test recirculation line branching off upstream of these check valves that returns condensate to the Condensate Storage Tank, thus testing via this flowpath is also impossible.

Alternate Test Schedule:

These check valves are full-stroke exercised in the open and closed direction during cold shutdown periods in accordance with the provisions of ASME OM Code, Section ISTC-3522.

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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System:

Valve(s):

CSJ-025

Primary Makeup and Purification System

MU~2A.MU~2B,MU~2C

Code Class: 2

Code Category:

Function:

C

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 134 of 165

These stop-check valves open to provide a flowpath for minimum recirculation flow through the primary makeup pumps during reduce flow conditions - non-safety function. They have a closed safety function (self-actuated mode} to maximize high pressure injection flow following an ES actuation by preventing recirculation flow through an idle pump.

Cold Shutdown Justification:

During normal operation the primary makeup pumps are operating and no method exists to confirm flow through the recirculation header. During cold shutdowns the primary makeup pump will be started and its injection line will be isolated and Makeup Tank level will be monitored to confirm a rise in tank level hence confirming flow though the associated recirculation valve.

Alternate Test Schedule:

These check valves are part-stroke exercised in the open and full-stroke exercised closed direction during cold shutdown periods in accordance with the provisions of ASME OM Code, Section ISTC-3522.

.)

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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System:

Valve(s):

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 135 of 165

CSJ-026

(Cancelled, See ROJ-011)

Primary Makeup and Purification System

MU-29A, MU-29B, MU-29C, MU-29D

Code Class: 2

Code Category:

Function:

C

These stop check valves open to provide a flowpath for seal water injection to the reactor coolant pumps - non-safety function. Each stop check valve has a safety function in the open position. This valve opens to provide a flow path when the containment penetration is subjected to thermal expansion to prevent over pressurization. The valve is credited with protecting the penetration. This stop check valve has a safety function in the closed position. Each stop check valve is identified as part of the containment boundary. This valve is categorized as a Containment Isolation Valve but is not subject to testing by the Appendix J leak rate testing program since the penetration is associated with a closed system.

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System:

Valve(s):

CSJ-027

Intermediate Cooling Water System

CV-2234 (AOV), IA-775 (CKV)

Code Class: 2 (CV-2234), NC (IA-775)

Code Category:

Function:

A (CV-2234), Aug-C (IA-775)

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 136 of 165

CV-2234 opens to provide a flowpath for cooling water to the reactor coolant pump (RCP) motor air and lube oil coolers - non-safety function. Cooling of these components is not required for accident mitigation or for reactor cooldowsi. It has a closed safety function to, provide containment isolation. IA-775 is the check valve which maintains accumulator pressure

)

following a loss of instrument air to provide motive force for closure of CV-2234 given a subsequent engineering isolation signal.

Cold Shutdown Justification:

Closing CV-2234 isolates cooling water flow to the RCP motor air and lube oil 'coolers. The loss of cooling water would quickly require securing RCP motors as bearing and winding temperature rise. Therefore, closing CV-2234 would jeopardize continued operation of the plant in addition to the actual temperature transient. Likewise, testing IA-775 would require CV-2234 closure.

Alternate Test Schedule:

CV-2234 will be full-stroke exercised and stroke timed in the closed direction during cold shutdown periods in accordance with the provisions of the code. CV-2234 will also be fail safe tested at that time which additionally provides IA-775 closure verification. IA-775 will be open exercised during cold shutdown periods in accordance with the provisions of ASME OM Code, Section ISTC-3522.

Note:

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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ANO Unit 1 1ST PLAN

System:

Valve(s): \

CSJ-028

Primary Makeup and Purification System

CV-1275

Code Class: 2

Code Category:

Function:

BC

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 137 of 165

This normally-open motor operated stop-check valve has a closed safety function to preclude losing suction flow to the HPI pumps by empting the reactor coolant makeup tank when the BWST is aligned to the HPI pump suction. In addition, during "piggy-back" operation it prevents coolant from entering the reactor coolant makeup tank and the remainder of the purification system.

Cold Shutdown Justification:

Closing this valve would necessitate the shutdown of the running makeup pump due to the loss of suction. This, in turn, would result in a transient of pressurizer level and the loss of seal injection flow to the reactor coolant pump (RCP) seals. The resulting hydraulic and/or thermal transient has the potential to result in damage to the RCP seals.

Alternate Test Schedule:

This motor operated check valve is parf-stroke exercised in the open and full-stroke exercised in the closed direction during cold shutdown periods in accordance with the provisions of ASME OM Code, Section ISTC-3522. This valve will be stroke timed in the closed position during cold shutdown periods in accordance with the provisions of the Code.

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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ANO Unit 1 1ST PLAN

System:

Valve(s):

Code Class:

Code Category:

Function:

CSJ-029

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 138 of 165

Decay Heat Removal System/Low Pressure Coolant Injection

DH-13A, DH-138, DH-17, DH-18

1 /

AC

These normally-closed check valves have an open safety function to provide for decay heat removal and low pressure injection flow to the reactor vessel. They have a closed safety function during normal plant operation to act as a pressure boundary between the RCS and the low pressure decay heat removal system.

Cold Shutdown Justification:

These are check valves with no external means for exercising and no external position indication mechanism. Exercising (open) requires operating a LPI (decay heat removal) pump at full flow and injecting into the reactor coolant system. At power operation this is not possible because the LPI pumps cannot develop sufficient discharge pressure to overcome reactor coolant system pressure.

Alternate Test Schedule:

These check valves are full-stroke exercised in the open and closed direction during cold shutdown periods in accordance with the provisions of ASME OM Code, Section ISTC-3522.

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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ANO Unit 1 1ST PLAN

System:

CSJ-030

Steam Generator Secondary System

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 139 of 165

Valve(s): CV-2619, CV-2676 (Atmospheric Dump Valve Block Valves)

Code Class: 2

Code Category:

Function:

B

Each main steam header is fitted with an eight inch Atmospheric Dump Valve (ADV) upstream of the MSIV's. The ADV for the 'A" OTSG is CV-2668 and associated ADV Block Valve CV-2676. The ADV for "B''- OTSG is CV-2618 and its ADV Block valve CV-2619. Each motor operated valve has a safety function in the open position. Each normally closed valve opens to allow a steam flow path to its respective atmospheric dump valve (ADV). Each ADV Block Valve automatically opens on associated SIG MSLI. The atmospheric dump valve block valves begin opening and the Atmospheric Dump Valves (ADV) will begin to relieve pressure to the atmosphere. The pressure will rise to 1,050 psig at which point the first group of main steam safety valves (MSSVs) will lift. Upon reseating of the safety valves, EFIC controls steam generator pressure at the selected setpoint by modulating the ADV. Each motor operated ADV Block valve has a safety function in the closed ~osition. Each normally closed valve is the class 2 to non-safety related piping isolation valve and is an outside containment isolation valve for penetration P2, P1 respectively. These valves are not tested per the Appendix J Program.

Cold Shutdown Justification:

It is not practical to test the block valves during power operation. Opening of these valves during full power operation would allow main steam pressure against the ADVs. The pressure set point of the ADVs is too close to the operating pressure of the main steam header and would cause an unnecessary transient. Therefore the testing of these valves will be performed during cold shutdown conditions.

Alternate Test Schedule:

These valves will be full-stroke exercised in the open and closed direction during cold shutdown periods in accordance with the provisions of the Code.

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ANO Unit 1 1ST PLAN

System:

Valve(s):

CSJ-031

Decay Heat Removal System

CV-1416

Code Class: 2

Code Category:

Function:

A

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 140 of 165

This normally-closed and de-energized motor-operated valve has a closed safety function to act as a redundant pressure boundary between the reactor coolant system and the decay heat removal system during power operation. This valve is seat leakage tested in accordance with Appendix J. This valve has an open function to provide an alternate method of post-LOCA boron precipitation control and to assist in expediting de-pressurization in certain situations.

Cold Shutdown Justification:

This valve is normally closed with the breaker de-energized to protect downstream low pressure piping on the decay heat system. Opening this valve could subject the low pressure rated portions of the decay heat removal/low pressure coolant injection system to reactor coolant pressures separated by check valves.- This is considered to be imprudent under normal RCS operating pressure, as there is no way to verify upstream pressure (Reference NUREG-1482 R2, 3.1.1 (2).)

Alternate Test Schedule:

This valve_ will be full-stroke exercised and stroke timed in both the open and closed directions during cold shutdown periods in accordance with the provisions of the Code.

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ANO Unit 1 1ST PLAN

System:

Valve{s):

CSJ-032

Primary Makeup and Purification System

CV-1206

Code Class: 2

Code Category:

Function:

C

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 141 of 165

This motor operated gate valve has no safety function in the open position. This normally open RCP seal water injection block valve provides a flow path for RCP seal water injection during normal operations. This is an operational consideration and a non-safety function. This motor operated gate valve has a safety function in the closed position. This normally open RCP seal water injection block valve is identified as part of the containment boundary. This valve is categorized as a Containment Isolation Valve but is not subject to testing by the Appendix J leak rate testing program since the penetration is associated with a closed system.

Cold Shutdown Justification:

Isolating this valve at power would interrupt flow to the reactor coolant pump seals potentially leading to seal failure.

Alternate Test Schedule:

This valve will be full-stroke exercised and stroke timed in the closed direction during cold shutdown periods in accordance with the provisions of the Code.

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ANO Unit 1 1ST PLAN

System:

Valve(s):

Sodium Hydroxide

CV-1616, CV-1617

Code Class: 3

Code Category:

Function:

B

ROJ-001

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 142 of 165

These motor operated gate valves have a safety function in the open pqsition. These sodium hydroxide valves to reactor building (RB) spray supply receive an ES-9 signal to open and provide sodium hydroxide to RB spray pump suction. These valves have a safety function in the closed position. These normally closed, fail a.s is, valves close to prevent diversion of decay heat removal flow and also must be manually closed during the transfer from the BWST to the Reactor Building Emergency Sump to prevent an unmonitored release from the NaOH tank vent during recirculation.

Refueling Outage Justification:

Stroke timing and exercising these valves during power operation or during cold shutdowns introduces sodium hydroxide into Reactor Building Spray Pump suction headers. Once the sodium hydroxide is in the suction header, starting a pump associated with the suction header introduces the sodium hydroxide into the Borated Water Storage Tank (BWST). When the Spent Fuel Pool Demineralizer (T-3) is place into service to purify the BWST, the higher than normal levels of sodium are removed thus shortening the life of the resin.

To avoid shortening the T-3 resin life, ANO had attempted to build a buffer of Demineralized Water (DI) around CV-1616 and CV-1617. Building this buffer necessitated the use rubber hoses which contain pressurized sodium hydroxide and routing the resulting mixture to floor drains. Then the water was flushed to Laundry Tanks and had been neutralized prior to being released. The Laundry Tanks, are not design to neutralize chemicals, i.e. it does not have an installed chemical addition pot. The above process caused personnel risk, exposure to caustic when draining hoses and during the neutralization phase, increased dose due to connecting, disconnecting, arid draining hoses in !he decay heat vaults, and increased costs for neutralizing the sodium hydroxide.

Other methods of flushing the lines of sodium hydroxide had been investigated and were found to be infeasible. One method involves flushing DI water towards the Sodium Hydroxide Storage Tank during valve operation. T~is method results in the dilution and inventory addition to the NaOH tank over time. The end result is that the NaOH tank has to be drained, the effluent chemically treated to neutralize it, and NaOH added to the storage tank.

In summary, these valves will be exercised and stroke timed during refueling outages when the piping is drained and flushed, since exercising these valves results in the following hardships: Reduction in life of plant equipment - decreased resin life; Personal safety concerns - exposure to caustic; and, Dose.

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ANO Unit 1 1ST PLAN

Alternate Test Schedule:

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 143 of 165

These valves are full-stroke exercised and stroke timed in the open and closed direction during refueling outage periods in accordance with the provisions of the ASME OM Code.

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ANO Unit 1 1ST PLAN

ROJ-002

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 144 of 165

System:

Valve(s):

Makeup and Purification/ High Pressure Injection

BW-2, BW-3

Code Class: 2

Code Category:

Function:

C

These stop-check valves have a safety function in the open position. These valves open to provide a flowpath for injection of borated water from the BWST to the RCS during postulated accidents such as small break LOCA, main steam line break, and steam generator tube rupture. These stop-check valves have a safety function in the closed position. These valves close to prevent diversion of recirculating injection water from the reactor building sump when long term core cooling following small break LOCAs is accomplished through the Low Pressure Injection System and HPI System in series and into the core.

Refueling Outage Justification:

These are stop-check valves with no external means of moving the obturators in the open direction. Due to their size it is impractical to RT these valves. The only practical means of exercising them open during power operation is to pump water from the BWST via the makeup pumps. Because a makeup pump is normally in operation pumping to the reactor coolant system, a flowpath for testing is available; however, adding water in this way is undesirable for the following reasons.

a. The boron concentration in the BWST is considerably greater than that of the RCS, thus injecting this water into the RCS would cause an undesirable negative power transient.

b. This additional volume of water would cause an undesirable upset in the makeup system flow balance with a transient in the Reactor Coolant Makeup Tank water level.

These valves cannot be full stroke exercised during cold shutdown since operation of the makeup pumps in other than a makeup mode is not permitted due to the possibility of low

· temperature over-pressure (L TOP) concerns.

Alternate Test Schedule:

These check valves are full-stroke exercised in the open and closed direction during refueling outage periods in accordance with the provisions of ASME OM Code, Section ISTC-3522.

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ANO Unit 1 1ST PLAN

------ -----~----

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 145 of 165

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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ANO Unit 1 1ST PLAN

ROJ-003

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 146 of 165

System:

Valve(s):

Decay Heat Removal/ Low Pressure Injection

BW-4A, BW-4B

Code Class: 2

Code Category:

Function:

C

These check valves have a safety function in the open position. This valve must open to allow a flow path from the borated water storage tank (BWST) to the suction of the decay heat removal/low pressure injection pumps and the reactor building spray pumps during an engineered safeguards (ES) actuation. This check valve has a safety function in the closed position. These valves must close to prevent backflow into the borated water storage tank (BWST).

Refueling Outage Justification:

These check valves are in the suction lines to the low pressure injection, high pressure injection and reactor building spray pumps from the BWST. They are not equipped with external actuators and do not have position indicators. Due to their size it is impractical to RT these valves. To provide maximum accid~nt flow in these lines during power operation would require simultaneous operation of a low pressure injection pump and reactor building spray pump. These pumps share common pump discharge test header piping. The first check valve in the reactor building spray pump piping is on the suction side of the pump. Consequently, a trip or failure of the reactor building spray pump would allow the low pressure injection pump to pressurize the failed reactor building spray pump piping back to the first check valve in the reactor building spray system. Therefore, the suction piping of the reactor building spray pump could be overpressurized by an operating low pressure injection pump.

These check valves cannot be full flow tested during cold shutdowns since during decay heat removal operations the low pressure injection pumps cannot be aligned to the BWST due to insufficient RCS volume. Filling of the · refueling transfer canal while the reactor head is removed is required in order to have sufficient volume to full flow test these valves.

Alternate Test Schedule:

These check valves are full-stroke exercised in the open and closed direction during refueling outage periods in accordance with the provisions of ASME OM Code, Section ISTC-3522.

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PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 147 of 165

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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ROJ-004

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 148 of 165

System:

Valve(s):

Decay Heat Removal/ Low Pressure Injection

DH-2A, DH-28

Code Class: 2

Code Category:

Function:

C

These check valves have an open safety function during an ES actuation to provide a flowpath for the decay heat removal pumps discharge to the RCS for low pressure injection. Since the decay heat removal pumps d_o not operate in parallel these valves do not have a closed safety function. Due to their size it is impractical to RT these valves.

Refueling Outage Justification:

These are check valves with no external means for exercising and no external position indication mechanism. The decay heat removal pumps do not operate in parallel. There is not a method to reverse flow test these check valves.

Alternate Test Schedule:

The open safety function for these valves will be confirmed quarterly with flow.

The ciose non-safety function of these valves will be confirmed by disassembling, inspecting, and exercising one valve in the group each refueling outage. The valve disassembly will be alternated in accordance with ISTC-5221 (c).

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ROJ-005

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 149 of 165

System:

Valve(s):

Makeup and Purification / High Pressure Injection

MU-34A, MU-34B, MU-34C, MU-34D

Code Class: 1

Code Category:

Function:

C

These check valves have an open safety function during an ES actuation to provide HP injection flow into the reactor vessel from HP injection loops. These check valves have a safety function in the closed position. This normally closed valve provides reactor coolant boundary isolation for the piping of the high pressure injection system.

Refueling Outage Justification:

These are check valves with no external means for exercising and no external position indication mechanism. These valves are in series with MU-66A, MU-66B, MU-66C, and MU-66D. The only way to reverse flow test these valves would be to use the RCS as a pressure source. In addition, an extensive amount of hoses would have to be routed to the containment building sump. It is impractical to RT the valves due to the outage impacts - RT boundary, shutting down work in adjacent areas, etc.

Alternate Test Schedule:

The open safety function of these valves is confirmed during cold shutdowns via flow.

The close non-safety function of these valves will be confirmed by disassembling, inspecting, and exercising one valve in the group each refueling outage. The valve disassembled will be alternated in accordance with ISTC-5221 (c).

Note:

1STC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval.

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ROJ-006

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 150 of 165

System: Makeup and Purification / High Pressure Injection I

Valve{s): MU-66A, MU-66B, MU-66C, MU-66D

Code Class: 1

Code Category:

Function:

C

These check valves have an open safety function during an ES actuation to provide HP injection flow into the reactor vessel from HP injection loops. These check valves have a safety function in the closed position. Each normally closed valve provides reactor coolant boundary isolation for the piping of the high pressure injection system. Each valve is also the inboard containment isolation valve but is not required to be Appendix J leak tested.

Refueling Outage Justification:

These are check valves with no external means for exercising and no external position indication mechanism. These valves are in series with MU-34A, MU-34B, MU-34C and MU-34D. The only way to reverse flow test these valves would be to close the associated manual valve MU-45A, MU-45B, MU-45C, and MU-45D and use a hydro pump or to use hoses and jumper around MU-34A, MU-34B, MU-34C or MU-34D. The MU-45 valves stems are tack welded in the open position. In addition, an extensive amount of hoses would have to be routed to the containment building sump. It is impractical to RT the valves due to the outage impacts -RT boundary, shutting down work in adjacent areas, etc.

Alternate Test Schedule:

The open safety function of these valves is confirmed during cold shutdowns via flow.

The close non-safety function of these valves will be confirmed by disassembling, inspecting, and exercising one valve in the group each refueling outage. The valve disassembled will be alternated in accordance with ISTC-5221 (c).

Note:

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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ROJ-007

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 151 of165

System:

Valve(s):

Makeup and Purification/ High Pressure Injection

CS-98, CS-99, CS-261, CS-262

Code Class: 3

Code Category:

Function:

C

These check valves do not have an open safety function. They can be utilized as a non-safety supply to EFW from T-41. These check valves have a safety function in the closed position. They must be closed to prevent diversion of safety related EFW suction to the non-safety condensate storage tank.

Refueling Outage Justification:

These are check valves with no external means for exercising and no external position indication mechanism. Testing of these valves requires set up of test equipment and draining of portions of the EFW suction piping to verify bi-directional check valve operation. Additionally, it is impractical to perform this testing online, as it could render multiple trains of a safety system inoperable. NUREG-1482 R2 Section 4.1.6 documents that it is impractical to stage testing equipment quarterly for the purposes of check valve testing.

Alternate Test Schedule:

These check valves are exercised in the open and closed direction during refueling outage periods in accordance with the provisions of ASME OM Code, Section ISTC 3522.

Note:

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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System:

Valve(s):

Instrument Air System

IA-280, IA 283

Code Class: NC

Code Category:

Function:

C

ROJ-008

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 152 of 165

These check valves open to provide makeup air to the MSIVs and ADVs. On a loss of instrument air, these valves will close to maintain accumulator air pressure in T-93A/B. These valves must open and close to provide air to the ADVs. The testing of the ADVs and Air Supply check valves are augmented into the 1ST Program

Refueling Outage Justification:

Closure of either of the main steam isolation valves under power conditions effectively isolates the associated steam generator. This, in turn, would result in an extreme power transient and a plant trip. There is a valve control mechanism that allows a partial stroke (approximately 10%) during power operation. However, Improved Technical Specifications state that it is imprudent to stroke the valves at power due to risk of valve closure. In addition, NUREG-1482 R2 Section 4.1.6 documents that it is impractical to stage testing equipment quarterly for the purposes of check valve testing.

Alternate Test Schedule:

These valves will be exercised in the open and closed direction during refueling outage periods in accordance with the provisions of the Code.

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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System:

Valve(s):

ROJ-009

Reactor Building Sump System

RBS-10

Code Class: 3

Code Category:

Function:

C

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 153 of 165

This check valve opens to allow RCP seal leakage to be pumped to the quench tank, which is not a safety function. This check valve provides a code class and safety class boundary for the quench tank piping.

Refueling Outage Justification:

Verification of open function of the check valve can be performed by verification of changes in tank level. However, check valve closure cannot be verified by exercising and external position mechanism. There is no method to provide reverse flow testing of the valves

Alternate Test Schedule:

The closed function of this valve will be confirmed by disassembly and inspection each refueling outage.

ISTC-3522(a) states: "Each check valve exercise test shall includ~ open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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. ANO Unit 1 1ST PLAN

ROJ-010

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 154 of 165

System:

Valve(s):

Decay Heat Removal/ Low Pressure Injection

DH-93

Code Class: 2

Code Category:

Function:

C

This check valve does not have an active open safety function. It opens to provide a flowpath to the pressurizer auxiliary spray system as a means of cooldown and boron dilution. This check valve has a closed safety function to protect low pressure piping from ~ high pressure tie in to RCS and Makeup.

Refueling Outage Justification:

This check valve is installed in a location which is not readily testable during plant operation. Providing a pressure source and drain path for testing of this check valve would require a temporary pressure source and multiple test connections and other materials. NUREG-1482 R2 Section 4.1.6 documents that it is impractical to stage testing equipment quarterly for the purposes of check valve testing.

Alternate Test Schedule:

These valves will be exercised in the open and closed direction during refueling outage periods in accordance with the provisions of the Code.

1STC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both·tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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System:

Valve(s):

ROJ-011

Primary Makeup and Purificati_on System

MU~9~MU~9B,MU~9C,MU~9D

Code Class: 2

Code Category:

Function:

C

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 155 of 165

These stop check valves open to provide a flowpath for seal water injection to the reactor coolant pumps - non-safety function. Each stop check valve has a safety function in the open position. This valve opens to provide a flow path when the containment penetration is subjected to thermal expansion to prevent over pressurization. The valve is credited with protecting the penetration. This stop check valve has a safety function in the closed position. Each stop check valve is identified as part of the containment boundary. This valve is categorized as a Containment Isolation Valve but is not subject to testing by the Appendix J leak rate testing program since the penetration is associated with a closed system.

Refueling Outage Justification:

Isolating these valves at power would interrupt flow to the reactor coolant pump seals potentially leading to seal failure.

Alternate Test Schedule:

These check valves are full-stroke exercised in the open and closed direction during refueling outage periods in accordance with the provisions of ASME OM Code, Section ISTC 3522.

ISTC-3522(a) states: "Each check valve exercise test shall include open and close tests. Open and close tests need only be performed when it is practicable to perform both tests. Test Order (e.g., whether the open test precedes the close test) shall be determined by the Owner. Open and close tests are not required to be performed at the same time if they are both performed within the same interval."

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ANO Unit 1 1ST PLAN

PLANT/UNIT:

INTERVAL:

COMPONENTS AFFECTED:

CODE EDITION

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 156 of 165

10 CFR 50.55a Request Number VRR-AN01-2017-1

Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1)

Arkansas Nuclear One Unit 1

Fifth 120 Month lnservice Testing Interval

Valve ID: PSV-1617

Function: NAOH TANK PRESSURENAC RELIEF

(The above valve is an ASME OM Code Class 3, ASME OM Code Category C relief valve.)

AND ADDENDA: ASME OM Code-2004 Edition with addenda through 0Mb Code-2006

REQUIREMENTS: ASME OM Code-2004 Edition with addenda through 0Mb Code-2006 Addenda, Appendix I, Paragraph 1-8200:

"Seat Tightness Testing. Seat tightness testing shall be performed in accordance with the Owner's valve test procedure."

REASON FOR RELIEF REQUEST:

Pursuant to 1 O CFR 50.55a, "Codes and Standards", paragraph (z)(1) an alternative is requested when using the requirements of ASME OM Code-2004 Edition with addenda through ASME OM Code-2006 Addenda (as listed above).

Relief valve PSV-1617 has an active open safety function to relieve overpressure and vacuum conditions in the sodium hydroxide storage tank. Note that although,the tank vent valve AV-10 is normally open to perform these functions, PSV-1617 is considered to be the primary and most reliable mechanism for performing this function. The seat leakage testing of PSV-1617 produces no useful information since PSV-1617 has no significant safety function in the closed position.

PROPOSED ALTERNATIVE AND BASIS FOR.USE:

Seat leakage testing of this vacuum breaker valve, PSV-1617, will not be performed. This vacuum breaker valve, PSV-1617, has no significant safety function in the closed position. Furthermore, seat leakage is irrelevant since, in effect, PSV-1617 is normally bypassed by a line with a normally-o'pen vent valve, AV-10.

Based on the determination that compliance with the ASME OM Code-2004 Edition, with addenda through 0Mb Code-2006 Addenda, requirements results in a hardship without a compensating increase in the level of quality or safety, this proposed alternative should be granted pursuant to 10 CFR 50.55a(z)(2).

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PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 157 of 165

10 CFR 50.55a Request Number VRR-AN01-2017-1 (Continued)

Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1)

NRC Review (1 CNA051701) determined that the proposed alternative provided an acceptable level of quality and safety per 10 CFR 50.55a(z)(1).

DURATION OF PROPOSED ALTERNATIVE:

Arkansas Nuclear One, Unit 1 's Fifth Ten-Year lnservice Testing Interval (December 1, 2017, through November 30, 2027)

PRECEDENTS:

This alternative is a re-submittal of the AN0-1 Fourth Ten-Year Interval Relief Request VRR­AN01-2007-1. That relief request was approved by the NRC in letter dated April 30, 2008 (ML081130082).

The previous relief request was based on the ASME OM Code 2001 Edition with addenda through OMb-2003 Addenda. This Fifth Ten-Year .Interval relief request is based on the ASME OM Code-2004 Edition, with addenda through ASME OM Code-2006 Addenda. There have been no substantive changes to this relief request, to the ASME OM Code requirements or to the basis for use, which would alter the previous NRC Safety Evaluation conclusions.

REFERENCES:

TAC No. MA0275 related correspondences: September 26, 2000 (NRC); October 29, 1999 (EOI); October 9, 1998 (NRC); December 1, 1997 (EOI), 1 CAN111602, 1 CNA051701

STATUS:

Submitted for Nuclear Regulatory Commission review and approval in 1 CAN111602.

Approved by NRC Review in 1CNA051701 (ML 17104A255).

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System:

Components:

Code Class:

Pump Category:

Code Requirement:

Function:

PPS-001

SeNice Water

P-4A, P-48, P-4C

3

A

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 158 of 165

ISTB-5221 (b ): The resistance of the system shall be varied until the flow rate equals the reference point. The differential pressure shall then be determined and compared fo its reference value. Alternatively, the flow rate shall be varied until the differential pressure equals the reference point and the flow rate determined and compared to the reference flow rate value.

ISTB-5223{b): For centrifµgal and vertical line shaft pumps, the resistance of the system shall be varied until the flow rate equals the reference point. The differential pressure shall then be determined and compared to its reference value. Alternatively, the flow rate shall be varied until the differential pressure equals the reference point and the flow rate determined and compared to the reference flow rate value.

Under emergency conditions these vertical line-shaft pumps provide an assured source of cooling water and the ultimate heat sink to various safety related and safe shutdown components. In addition, they provide cooling water to non-safety related plant components during normal plant operation.

JUSTIFICATION BASES:

OMN-16, "Use of a Pump CuNe for Testing," is listed in RG 1.192 Revision 1, Table 1 of Acceptable ASME OM Code Cases (2006 Addenda.) 10 CFR 50.55a(a)(iii) incorporated Revision 1 of RG 1.192 as approved in accordance with paragraph (b )(6) of 10 CFR 50.55a. OMN-16 is used for testing AN0-1 SeNice Water Pumps P-4A, P-48, and P-4C.

The seNice water system provides a continuous supply of cooling water to the two safety­related (essential) seNice ,water headers as well as the non-essential header related to main turbine generator and other plant support auxiliaries. During normal plant operation at power the heat removal demands of the seNice water system require the operation of at least two (frequently three) pumps. After the system operation reaches a degree of stability, perturbation bf flow to any of the on-line heat exchangers could have a severe adverse impact on plant operation with the potential for unacceptable flow and temperature transients. This situation precludes flow adjustments on specific heat loads and certainly throttling of pump or header isolation valves. As such, returning the system operating parameters to a prescribed unique reference value (either flow or differential pressure) is impractical and could result in an

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PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 159 of 165

unreasonable and unwarranted risk to plant operation with little or no apparent gain in plant safety or reliability.

This alternative is a replacement of 4th Interval Pump Relief Request PRR-AN01-2007-1. This Fourth Interval alternative request was based on the ASME OM Code-2001 Edition with addenda through 0Mb Code-2003 Addenda. The proposed relief was in accordance with Code Case OMN-16, which had not been approved by RG 1.192 and incorporated by reference in 10 CFR 50.55a.

OMN-16 ALTERNATIVE AND BASIS:

Following maintenance activities or when the pump is known to be operating acceptably the reference curve will be either reconfirmed or a new curve created. Alternatively, a new reference curve may be created in cases where the test parameters are in the alert or required action range and the pump's continued use at the changed values is supported by an analysis. The analysis shall include verification of the pump's operational readiness at both a component and system level analysis. This analysis shall document the cause of the deviation and an evaluation of all applicable trends indicated by performance data.

If a new reference curve is required, it shall be created as follows:

a. The subject flow rate will be varied over a specified range with the pump operating at or near its design basis flow rate. Per SAR Table 9-8 a service water pump design capacity is 6500 gpm. This specified range, approximately 4000 gpm to 7500 gpm, will be beyond the theoretical "flat" portion of the pump performance curve.

b. At least five (5) points over the test range, corresponding differential pressure and flow rate measurements will be recorded after flow stability is achieved at each point (minimum 2 minutes run time). The points will include at least one point below .5200 gpm, one point between 5200 gpm to 6500 gpm, and one point greater than 6500 gpm. Instruments used for obtaining pump performance data will satisfy the accuracy and range requirements as set forth in ISTB-3500.

c. The recorded curve data will be plotted graphically or electronically and an equivalent pump curve will be derived.

Individual acceptance criteria will be developed for each pump as follows:

a. For the Group A test, an acceptable range of operation will be established when pump differential pressure, corresponding to a specific flow rate, deviates by no more than 0.95 times the reference value for the lower limit and 1.10 times the reference value for the upper limit. For the Comprehensive test, an acceptable range of operation will be established when pump differential pressure, corresponding to a specific flow rate, deviates by no more than 0.95 times the reference value for the lower limit and 1.03 times the reference value for the upper limit.

b. For the Group A test and the Comprehensive test, an alert range of operation will be established when pump differential pressure, corresponding to a specific flow rate, falls between 0.93 times the reference value to 0.95 times the reference value. If test values are determined to enter the alert range, appropriate corrective actions will be implemented in accordance with OMN-16 paragraph 16-6200(A), including doubling\of the testing frequency.

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PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 160 of 165

c. Each of the pump's acceptance criteria curves shall be compared to the applicable and corresponding requirements for these pumps as set forth in the AN0-1 Technical Specifications, Safety Evaluation Report, and Safety Analysis Report. This review will ensure that a pump cannot be declared operable if it is operating outside the requirements of any of these documents.

d. In the event that a pump's operational parameters fall outside of these stated ranges (Group A test: 0.93 times the reference value for the lower range and 1.1 times the reference value for the upper range) or greater than 1.03 times the reference value for the Comprehensive test in the "required action range", appropriate corrective actions will be implemented in accordance with OMN-16 paragraph 16-6200(b).

e. The acceptance criteria for pump/motor vibration will be derived from Table ISTB-5121-1 based on reference values measured during typical pump operation (e.g., between approximately 4000 gpm and 7500 ~fpm.) A curve of vibration levels versus flow rate is not required to be developed since vibration levels are essentially the same over the flow rates of interest.

Each of these pumps will be Group A and Comprehensive tested as follows: With the subject pump operating at a condition based on system demands, measurements for pump flow rate, differential pressure, and vibration will be recorded. Should any of the pump's operating points fall outside the plotted areas of acceptability, the appropriate corrective action as prescribed in OMN-16 Paragraph 16-6200 will be applied.

DURATION:

Arkansas Nuclear One Unit 1 's Fifth 120-month lnservice Testing Interval (December 1, 2017 through November 30, 2026).

REFERENCES:

Regulatory Guide 1.192 10 CFR 50.55a(b)(6) 10 CFR 50.55a(a)(iii) OMN-16, "Use of a Pump Curve for Testing"

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System:

Components:

Code Class:

Code Category:

Code Requirement:

Function:

VPS-001

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 161 of 165

Emergency Diesel Generator

CV-5218, CV-5233, CV-5237, CV-5239, SV-5218, SV-5233, SV-5237, SV-5239

NC

Aug-B

Power Operated Valve Stroke Timing

The stroke time of all power operated valves shall be measured to at least the nearest second.

These valves comprise the means by which starting air is admitted to the emergency diesel generators (EOGs) air start motors. An electrical signal from the EOG start circuitry causes one of the two solenoid valves associated with a particular EOG to change position such that pressurized air is admitted to the pinion engagement mechanism of the first of two air start motors arranged in series. As the pinion is engaged, a port is open to allow air flow to the pinion engagement of the second air start motor. Air flow then continues to the associated control valve to cause it to open to admit air to the vaned air start motors in order to crank the EOG. When the EOG starts, speed sensors cause the start signal to be removed at which time the solenoid valve repositions to isolate starting air to and, via the associated check valve, depressurize the piping to the air start motor's pinion engagement mechanism and the air supply control valve. This action allows the air supply control valve to close and the pinion to disengage from the EOG ring gear. One solenoid valve, one check valve, and one control valve comprise one train of air start capability. An alternator switches the start signal such that the two trains operate in an

Justification Basis:

These valves do not have position indicating lights or other means of directly monitoring the time required for a change in valve position. Exercising of the valves is accomplished during EOG surveillances at a frequency which meets or exceeds Code requirements. The proper operation of the air start solenoid, check, and air control valves can be monitored by virtue of proper starting operation of the EOG. The normal time required from the receipt of a start signal for the EOG to start and achieve rated speed and voltage is 9 to 13 seconds based on surveillance test results. The required time per AN0-1 Technical Specifications 4.6.1.1 is less than 15 seconds. Therefore, by virtue of proper EOG starting operation, the air start solenoid, check, and air control valves are verified to be operating properly.

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Alternative Testing:

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 162 of 165

AN0-1 will monitor proper operation of the air start valves by verification of EOG operability during the EOG surveillance. The base frequency for EOG testing is once per month. Surveillance procedures are written such that every other month the EOG is started both locally and remotely. At this time local verification is performed to ensure that the EOG starts from each of the two trains. The time required to start and achieve rated speed and voltage on each train is monitored and recorded. If the required time is greater than 15 seconds for either train, then the associated train is declared inoperable and corrective actions taken.

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ANO Unit 1 1ST PLAN

System: Various

Component ID Code Class

PSV-1003 2

PSV-1004 2

PSV-1200 2

PSV-1201 2

PSV-1404 2 PSV-1405 2

PSV-1801 2

PSV-2203 2

PSV-2205 2

PSV-2206 2

PSV-2214 N

PSV-2215 N

PSV-2400 2

PSV-2600 2

PSV-2601 2

PSV-2602 2

PSV-2603 2

PSV-6203 2

PSV-6205 2

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 163 of 165

VPS-002

Category Description

C P-39 THERMAL OVER-PRESSURE RELIEF

C,A P-70 THERMAL OVER-PRESSURE RELIEF

C,A P-14 THERMAL OVER-PRESSURE RELIEF

C,A P-9 THERMAL OVER-PRESSURE RELIEF

C DH PMP P34B SUCT RELIEF

C DH PMP P34A SUCT RELIEF

C,A P-10 THERMAL OVER-PRESSURE RELIEF

C,A P-60 THERMAL OVER-PRESSURE RELIEF

C P-52 THERMAL OVER-PRESSURE RELIEF

C,A P-62 THERMAL OVER-PRESSURE RELIEF

C L TON CLR (E29A) ICW OUTLET RELIEF

C L TON CLR (E29B) ICW OUTLET RELIEF

C,A P-12 THERMAL OVER-PRESSURE RELIEF

C,A P-58 THERMAL OVER-PRESSURE RELIEF

C,A P-64 THERMAL OVER-PRESSURE RELIEF

C THERMAL RELIEF VALVE FOR EBO-19 (LOOP A ) PIPING

C THERMAL RELIEF VALVE FOR EBO-19 (LOOP B) PIPING

C P-51 THERMAL OVER-PRESSURE RELIEF

C,A P-59 THERMAL OVER-PRESSURE RELIEF

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ANO Unit 1 1ST PLAN

Code Requirement: Thermal Relief Valve Testing.

Function:

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 164 of 165

The purpose of this Technical Position is to establish the station position on the method and frequency of testing of valves t.hat can be classified as Thermal Relief Valves.

Justification Basis:

In the 2004 Edition of the ASME OM Code through 2006 Addenda, Mandatory Appendix I, lnservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear power Plants, . Section 1-1390 states:

Test shall be performed on all Class 2 and 3 relief devices used in thermal relief application every 10 years, unless performance data indicate more frequent testing is necessary. In lieu of tests the Owner may replace the relief devices at a frequency of every 1 O years, unless performance data indicate more frequent replacement are necessary.

Alternative Testing:

AN0-1 will treat those valves designated as thermal relief valves per the requirements of 1-1390 in that they will be tested or replaced on a 10 year frequency unless performance data indicates more frequent replacement being necessary.

Justification Note:

PSV-1409 and PSV-1800 are also considered to be thermal relief valves; however, they are Class 1 components, therefore the provisions of 1-1390 do not apply.

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ANO Unit 1 1ST PLAN

System:

Components:

Code Class:

Code Category:

Code Requirement:

Function:

Various

Check Valves

Any

C

VPS-003

PROGRAM SECTION NO. SEP-AN0-1-IST-2 REVISION NO. 5 Page 165 of 165

Check Valve Condition Monitoring

The purpose of this Technical Position is to establish the station position on the method· of testing of valves within Check Valve Condition Monitoring.

Justification Basis:

In the 2004 Edition of the ASME OM Code through 2006 Addenda, Mandatory Appendix II, Check Valve Condition Monitoring Program, Paragraphs ll-4000(a)(1)and ll-4000(b)(1), the licensee is required to select applicable test and examination activities which will be used to monitor the performance of selected check valves.

Tests performed on ANO check valves include NIT and RT per approved check valve condition monitoring plans. These check valve tests are designed to demonstrate valve obturator position without significant system or component intrusive inspections. However, these tests are not all inclusive, and may require an alternative depending on the needs of the plant.

Alternative Testing: -

AN0-1 will allow substitution of check valve disassembly at the discretion of the 1ST Engineer or Check Valve component engineer. Check Valve internal inspection is a superior analysis technique for identifying check valve degradation and allowing valve trending. However, there are alternative risks for maintenance induced failure during periodic inspections. This position is to document that where necessary, engineering may substitute internal inspection in accordance the with 1ST Check Valve internal inspection procedure. This will allow flexibility of meeting test requirements if NIT or RT are determined to be not feasible for a required test window.