ACCELERATED DISj BUTION DEMONSTI TION SYSTEM

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9205220118 DOC.DATE: 92/05/13 NOTARIZED: NO DOCKET # FACIL:50-269 Oconee Nuclear Station, Unit 1, Duke Power Co. 05000269

50-270 Oconee Nuclear Station, Unit 2, Duke Power Co. 05000270 50-287 Oconee Nuclear Station, Unit 3, Duke Power Co. 05000287

AUTH.NAME AUTHOR AFFILIATION HAMPTON,J.W. Duke Power Co. R RECIP.NAME RECIPIENT AFFILIATION

Document Control Branch (Document Control Desk)

SUBJECT: Forwards Request for Relief 92-09 from requirements of Section XI of ASME Boiler & Pressure Vessel Code due to D impracticality of pressure testing borated water storage tank piping to HPI pumps. S

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ( ENCL _ SIZE: / TITLE: OR Submittal: Inservice Inspection/Testing/Relief from ASME Code

A NOTES:

D RECIPIENT COPIES RECIPIENT COPIES

ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-3 LA 1 0 PD2-3 PD 1 1 WIENS,L 2 2 s

INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NUDOCS-ABSTRACT 1 1 0CLFMB ~ 1 0 OGC/HDS2 1 0

REG FILE 01 1 1 RES MILLMAN,G 1 1 RES/DSSR3EIB 1 1

EXTERNAL: EG&G BROWN,B 1 1 EG&G RANSOME,C 1 1 NRC PDR 1 1 NSIC 1 1

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I

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D

D NOTE TO ALL "RIDS" RECIPIENTS:

S PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 19

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Duke Power Company J W HAMPTON Oconee Nuclear Generation Department Vice President PO. Box 1439 (803)885-3499 Office Seneca, SC 29679 (704)373-5222 FAx

DUKE POWER

May 13, 1992

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Subject: Oconee Nuclear Station Docket No. 50-269, 270, 287 Second Ten Year Interval Request for Relief No. 92-09

Gentlemen:

Pursuant to 10CFR50, 50.55a, please find attached Request for Relief from the requirements of Section XI of the ASME Boiler and Pressure Vessel Code (with Addenda through Winter 1980). This request is being submitted due to the impracticality of pressure testing of the Borated Water Storage Tank Suction Piping to the High Pressure Injection Pumps as required by the Code. The attached request concerns the inservice inspections at Oconee being performed during the second ten year interval. Please review and approve this request by the end of the third period of the second inspection interval ending February 28, 1994.

Very truly yours,

. W. Hampton Site Vice President Oconee Nuclear Station

xc: Mr. L. A. Wiens Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555

Mr. S. D. Ebneter Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW., Suite 2900 Atlanta, GA 30323

9205220118 920513 PDR ADOCK 05000269 P PDR

Printed on recycled paper

U. S. Nuclear Regulatory Commission Page 2

Mr. Heyward G. Shealy Bureau of Radiological Health SC Dept. of Health & Environmental Control 2600 Bull St. Columbia, SC 29201

Mr. P. E. Harmon Senior NRC Resident Inspector Oconee Nuclear Station

Duke Power Company Oconee Nuclear Station Second Ten Year Interval Request for Relief #92-09

I. Component for which relief is requested:

a) Name and Number: Piping and Welds between 1, 2, 3 HP-25 and 1, 2, 3 HP-102; piping and welds between 1, 2, 3 HP-24 and 1, 2, 3 HP-101.

b) Function: Borated Water Storage Tank suction piping for HPI pumps.

c) 'ASME/Duke/ISI Class:

ASME Class 2, Duke Class B, ISI Class B

d) Drawings OFD 101A-1, 2, 3.3 and 102A-1, 2, 3.1

II. Reference code requirement that has been determined to be impractical.

IWC 5222(a) and Table IWC-2500-1, Category C-H, Item C7.21; IWC-2420(a)

III. Basis for requesting relief:

The piping on the upstream side of HP-24 and 25 is rated at 100 psig at 2000 F. The piping downstream of HP-24 and 25 is rated at 350 psig at 2000 F. Valves HP-101 and 102 are check valves. The HP-101 and 102 check valves make it impractical to perform the hydrostatic test with HP-24 and 25 closed and pressurizing from the downstream piping to HP-24 and 25. To pressurize the piping from the upstream direction with HP-24 and 25 open would cause overpressurization of the low pressure upstream piping. This request is to delay this test until the HP-101 and HP-102 valves can be disassembled.

IV. Alternate Examination:

No alternate examinations are needed as this request for relief is only to delay the periodic ISI hydrostatic test to a later time. The welds associated with this request have not been changed since the previous pressure test was performed.

V. Acceptability of proposed alternate testing with respect to the level of quality and safety, as well as public health and safety:

The welds have been previously inspected and tested as' required by ASME Section XI. This relief is only to delay the periodic ISI hydrostatic test until a time HP-101 and HP-102 can be disassembled. An acceptable level of quality and safety as well as public health and safety has been provided.

VI. Implementation schedule:

At the next refueling outage for each unit where disassembly of HP-101 and HP-102 is practical, but no later than the last refueling outage for each unit during the third period of the Second Inspection Interval, ending February 28, 1994.

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May 12, 1992

Docket Nos. 50-269, 50-270 and 50-287

Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, South Carolina 29679

Dear Mr. Hampton:

SUBJECT: GENERIC ISSUE 143 - CHILLED WATER SYSTEMS AND ROOM COOLING

This is to inform you that on September 9 and 10, 1992, a team consisting of an NRC staff member and two NRC consultants will visit your Oconee Nuclear Site. The purpose of this visit will be to collect information in support of the resolution of Generic Issue 143 "Availability of Chilled Water Systems and Room Cooling." Details of the specific information needed are included in the attached information sheet.

I have discussed the schedule for this visit with Mr. Mark Patrick of your staff. Additional details concerning this visit will be provided prior to the visit. Station support in providing a knowledgeable escort and assembling the requested information would be appreciated.

If you have questions regarding this matter, contact me at (301) 504-1495.

Sincerely, /s/

L. A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure: As stated

cc w/enclosure: See next page

Distribution oQ~cketF-il-e L. Reyes, RII

NRC & Local PDRs A. Belisle, RII PDII-3 R/F V. Leung, RES, NLS314 Oconee R/F G. Mazetis, RES, NLS314 S. Varga D. Jones, 12E4 G. Lainas D. Matthews

L. Wiens OGC, 15B18 ACRS (10), P-315

OFC: PDII-3. PI -3/PM: P I-3/D NAME: L.BERR L.WIENS : D. TTHEWS DATE: 5/S,/92 : 5//hy92 : 5/11/92 OFFICIAL RECORD COPY

1 ()G'12 A:ONS.143 0 G NRC HLE CENTER COPY

& pkREGUZ

UNITED STATES NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 205

Docket Nos. 50-269, 50-270 and 50-287

Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, South Carolina 29679

Dear Mr. Hampton:

SUBJECT: GENERIC ISSUE 143 - CHILLED WATER SYSTEMS AND ROOM COOLING

This is to inform you that on September 9 and 10, 1992, a team consisting of an NRC staff member and two NRC consultants will visit your Oconee Nuclear Site. The purpose of this visit will be to collect information in support of the resolution of Generic Issue 143 "Availability of Chilled Water Systems and Room Cooling." Details of the specific information needed are included in the attached information sheet.

I have discussed the schedule for this visit with Mr. Mark Patrick of your staff. Additional details concerning this visit will be provided prior to the visit. Station support in providing a knowledgeable escort and assembling the requested information would be appreciated.

If you have questions regarding this matter, contact me at (301) 504-1495.

Sincerely,

&L. A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure: As stated

cc w/enclosure: See next page

Mr. J. W. Hampton Duke Power Company Oconee Nuclear Station

cc: Mr. A. V. Carr, Esquire Mr. M. E. Patrick Duke Power Company Compliance 422 South Church Street Duke Power Company Charlotte, North Carolina 28242-0001 Oconee Nuclear Site

P. 0. Box 1439 J. Michael McGarry, III, Esquire Seneca, South Carolina 29679 Winston and Strawn 1400 L Street, NW. Mr. Alan R. Herdt, Chief Washington, DC 20005 Project Branch #3

U. S. Nuclear Regulatory Commission Mr. Robert B. Borsum 101 Marietta Street, NW. Suite 2900 Babcock & Wilcox Atlanta, Georgia 30323 Nuclear Power Division Suite 525 Ms. Karen E. Long 1700 Rockville Pike Assistant Attorney General Rockville, Maryland 20852 North Carolina Department of

Justice Manager, LIS P. 0. Box 629 NUS Corporation Raleigh, North Carolina 27602 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Mr. R. L. Gill, Jr.

Licensing Senior Resident Inspector Duke Power Company U. S. Nuclear Regulatory Commission P. 0. Box 1007 Route 2, Box 610 Charlotte, North Carolina 28201-1007 Seneca, South Carolina 29678

Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323

Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health

and Environmental Control 2600 Bull Street Columbia, South Carolina 29201

Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603

County Supervisor of Oconee County Walhalla, South Carolina 29621

7 L11tLUJUXL,

TOPICS FOR PLANT VISITS IN SUPPORT OF 01-143, CHILLED WATER SYSTEMS AND ROOM COOLING

PURPOSE OF VISIT

Collect information needed to determine the temperature rises following loss of room cooling in roome containing safety-related equipment and sensitivity of components to failures at high temperatures.

GENERAL INFORMATION REQUIREMENTS...

* thermal loads in rooms containing safety-related equipment from operation of the equipment and, in some rooms, from piping systems containing heated water.

* capabilities of the safety-related equipment to withstand relatively high temperatures

* possible actions that could be taken to respond to losses of room cooling, including actions to restore or supplement cooling in these rooms

SPECIFIC INFORMATION NEEDED

Room Cooler Systein Deign and Operation :

general flow diagram for room cooler system(s), including cooling water source (e.g., cooled directly by service water or plant Includes intermediate chilled water cooling loop between service water system and room coolers), list of safety-related rooms requiring room cooling, and overall system flow rates and heat removal capacty(les); operating procedures to cope with loss of room cooling.

Auxiliary Building Layout Information

description and dimensions of ECCS pump rooms, control room, electrical switchgear rooms, battery rooms, and diesel generator rooms; capacities of room coolers provided In these rooms; assessments of heat generation rates from equipment and piping systems contained in these rooms;

Vital Equipment Information

location and equipment qualification Information (Appendix A and environmental qualification) on all ECCS equipment in rooms requiring room cooling, including; pumps, valves, electrical power supplies, control circuits, electrical cabinets, etc.

NOTE: For most of this Information, it should be sufficlent for the utility representative to simply provide for our review the environmental quallf/cat/on and Appendix R Information, This should minimize the Inconvenience to utility staff resources. A relatively brief tour of the appropriate auxiliary building rooms should be sufficient for us to gather the needed room layout data.