indian point, units 2 and 3 - request for approval for ...nozzle to vessel weld rpvn3 @ 1130 azimuth...

dEntery

Entergy Nuclear NortheastIndian Point Energy Center295 Broadway, Suite 1P.O. Box 249Buchanan, NY 10511-0249Tel 914 734 5340Fax 914 734 5718

Fred DacimoVice President, Operations

December 30? 2003NL-03-188

U. S. Nuclear Regulatory CommissionATTN: Document Control DeskMail Stop O-P1 -17Washington, DC 20555-0001

SUBJECT: Indian Point Nuclear Generating Units No. 2 and No. 3Docket No. 50-247, and 50-286Alternative to Use Code Case N-613-1 forReactor Vessel Nozzle to Vessel Weld Inspection

References: 1. NRC Letter from James W. Clifford to Roy A. Anderson, uHope CreekGenerating Station - Evaluation of Relief Request HC-RR-B08 (TAC NO.MB7839)," dated August 26, 2003.

Dear Sir

Pursuant to IOCFR50.55a(a)(3)(i), Entergy Nuclear Operations, Inc. (ENO) hereby requests theNuclear Regulatory Commission (NRC) to approve the use of an alternative to the American Societyof Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl requirementsregarding the inspection of Class 1, Examination Category B-D, Reactor Vessel Nozzle to VesselWelds.

Enclosed are two (2) similar requests for relief (RRs) to use the proposed alternatives for IndianPoint Nuclear Generating Unit No. 2 (P2, Enclosure 1) and Indian Point Nuclear Generating UnitNo. 3 (P3, Enclosure 2). The proposed alternative would allow the plants to perform therequired inspections in accordance with Code Case N-613-1, in lieu of the ASME Section XlCode requirements. In accordance with 10 CFR 50.55a(a)(3)(i), the proposed alternative to useCode Case N-613-1 in its entirety provides an acceptable level of quality and safety for theexamination of the affected welds.

These requests for relief for P2 and P3 are for their 3rd ISI Interval, and the applicable code ofrecord is the 1989 Edition, No Addenda of the ASME Section Xi Code.

A similar request for relief was approved for Hope Creek (Reference 1).

M q q

Entergy requests approval of the P2 relief request (Enclosure 1) by June 2004 to support its Fall2004 refueling outage. Since these RRs are practically identical, Entergy requests that the P3relief request (Enclosure 2) be approved at the same time.

There are no new commitments made in this letter. If you have any questions, please contactMs. Charlene Faison at 914-272-3378.

AdVery truly yours,

redR. DacimoVice President, OperationsIndian Point Energy Center

List of Enclosures:

1. Indian Point Generating Station Unit No. 2, RR-672. Indian Point Generating Station Unit No. 3, RR 3-36

cc:

Mr. Hubert J. MillerRegional Administrator, Region IU.S. Nuclear Regulatory Commission475 Allendale RoadKing of Prussia, PA 19406-1415

Mr. Patrick D. Milano, Sr. Project ManagerProject Directorate IDivision of Licensing Project ManagementOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionMail Stop 0-8-C2Washington, DC 20555-0001

Mr. Paul EddyNew York State Departmentof Public Service

3 Empire State PlazaAlbany, NY 12223

Mr. Peter R. Smith, Acting PresidentNew York State Energy, Research, andDevelopment Authority

Corporate Plaza West286 Washington Avenue ExtensionAlbany, NY 12203-6399

Resident Inspector's OfficeIndian Point Unit 3U.S. Nuclear Regulatory CommissionP.O. Box 337Buchanan, NY 10511-0337

Senior Resident Inspectors OfficeIndian Point Unit 2U.S. Nuclear Regulatory CommissionP.O. Box 38Buchanan, NY 10511-0038

2

PNL-03-188

Enclosure I

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM

RELIEF REQUEST RR-67

Proposed AlternativeIn Accordance with IOCFR50.55a(a)(3)(i)

-Alternative Provides Acceptable Level of Quality and Safety-

1. ASME Code Component(s) Affected

Component Numbers: ASME Code Class 1 Reactor Vessel Nozzle to Vessel Welds.

Examination Category: B-D

Item Number. B3.90 - Nozzle to Vessel Welds

2. Applicable Code Edition and Addenda

The Code of Record for the third Inservice Inspection Interval is ASME Section Xl Code, 1989Edition, No Addenda.

3. Applicable Code Requirements

ASME Boiler and Pressure Vessel Code, Section Xi, Rules for Inservice Inspection of NuclearPower Plant Components, 1989 Edition with No Addenda: Table IWB-2500-1 Code Item B3.90,Figures IWB-2500-7 (a) thru (d) for defining the examination volume of the reactor vessel nozzleto shell welds. The examination requirements for reactor vessel nozzle to shell welds are definedin the ASME Code, Section Xi, Appendix Vil, Supplements 4, 6 and 7, 1995 Edition, 1996Addenda as modified by 10 CFR 50.55a. Eight (8) RPV nozzle to shell welds, 4 inlet and 4 outlet,are planned for examination in 2004 as follows:

Nozzle to Vessel Weld RPVN1 @ 220 Azimuth





Nozzle to Vessel Weid RPVN6 @ 2470 Azimuth



1

S

NL-03-1 88Enclosure 1

4. Reason for Request

The Code required examination volume of the nozzle to vessel welds is unnecessarily large. Theproposed alternative to use Code Case N-613-1 in its entirety will not affect the flaw detectioncapabilities in the weld and the heat affected zone, and provides an adequate level of quality andsafety for examination of the affected welds.

5. Proposed Alternative

In accordance with 1 OCFR50.55a(a)(3)(i), P2 requests relief from the t2 (t. is equal to the vesselwall thickness) examination volume requirement and instead proposes examination of the basematerial volume extending 1/2 inch from each side of the weld. This refined examination volume isdefined in detail within Code Case N-613-1 (Attachment 1) and the WesDyne sketches(Attachment 2).

Basis for Use

The examination (exam) volumes for the reactor vessel nozzle to vessel welds are unnecessarilylarge. For the P2 reactor vessel, the nozzle to shell volume would extend about 5 inches into thenozzle forging and the same distance into the upper shell course forging. This proposedalternative would re-define the examination volume boundary to 1/2 inch of base metal on eachside of the thickest portion of the weld. This reduction in base metal inspection will not affect theflaw detection capabilities in the weld and heat affected zone.

Compliance with these requirements will assure the requisite level of quality and safety ismaintained.

The proposed reduction in exam volume is base metal only, extensively interrogated by ultrasonicexamination during fabrication, preservice examinations and the last inservice examinationsperformed in 1995 at the end of the second interval. In 1995, the data was acquired, archivedand analyzed using automated ultrasonic systems. Entergy Nuclear Operations, Inc. (Entergy) isconfident that reasonable comparisons can be made between the past and present if necessary.During the 1995 examinations, there were no unacceptable indications found in the eight-reactorvessel nozzle to vessel examination volumes including the base metal areas proposed forexclusion from examination in this request. The 1995 results were based on examinationsperformed in accordance with the ASME Code, Section Xl, Section V and Regulatory Guide1.150, Rev. 1.

The Section Xl examination volume for the pressure-retaining nozzle to vessel welds extendsfrom the edge of the weld to include a significant portion of the nozzle forging body (inward) andreactor vessel upper shell course (outward) which is a forged ring. The large volume results in asignificant increase in examination time with no corresponding increase in safety as the greatestportion of the volume is base material not prone to inservice cracking.

The implementation of this request for relief would reduce the examination volume next to thewidest portion of the weld from half the vessel wall thickness to 1/2 inch from the weld. Thisreduction applies only to base metal and not the stressed areas of the nozzle to shell weld.

Entergy shall ensure that the high stressed areas of the P2 reactor vessel nozzle to shell weldsshall be included in the examination. The examinations shall consist of techniques and

2

NL-03-188Enclosure I

procedures qualified in accordance with the ASME Code, Section Xl, Appendix Vil, andsupplements 4, 6 and 7. The weld and surrounding 1/2 inch volume will be interrogated from thenozzle bore using techniques and procedures specifically qualified to inspect the nozzle to shellweld from the nozzle bore. These procedures were qualified in January 2003 in accordance withAppendix Vil, Supplement 7 as administered by the PDI.

The nozzle to vessel examination volume is also accessible from the vessel ID surface and will beexamined in four orthogonal directions for the first 15 percent of weld thickness with respect to thevessel ID surface using Appendix ViII, Supplement 4 qualified techniques. The remaining 85percent of weld volume accessible from the vessel ID surface will be examined in two opposingcircumferential scanning directions using Appendix Vil, Supplement 6 qualified techniques tointerrogate for transverse defects.

This combination of scans addresses the requirements set forth by the ASME Code, Section Xl,1995 Edition with 1996 Addenda as modified by 1OCFR50.55a and assures that current qualifiedtechnology will be applied to the re-defined examination volume specified herein to the maximumextent practical. Compliance with these requirements will assure the requisite level of quality andsafety is maintained.

6. Duration of Proposed Altemative

It is proposed to use the alternative for the remainder of the Third Inservice Inspection Interval forIP2.

7. Precedents

A similar request for relief was approved for Hope Creek (Docket No. 50-354, TAC NO. MB7839,dated August 26, 2003).

8. Attachment

1. Code Case N-613-1 (for information)

2. WesDyne Sketch, Indian Point Units 2 and 3 (TYP.), RPV Inlet and Outlet NozzlesExamination Volume - Code Case N-613-1 (2 pages)

3

NL-03-188, Enclosure iAttachment 1, page 1 of 4

N-613-1CASMS OF ASM BO AM pESSR VES CODE

ApPOW Da: August 2. 20

Se Mmik hW& for expksonind AY nefrfmsfon datu

Cse N441.1Ulr a oaEnmunatim of FA PenetratonNozJkS In Veck~ Bzanslraton Category B.D%11cm NoL BU31D u D30, Reactor Neozle-To.Vend Weds, Figs M-S0-7(a) (b), and (c section U l, Dwou I

InquirY: W cIternaves to die uxaminaon voluneMq=Mts of Ftf. WB-2500-7(a) (b) and (c) ae

peMible for ultnsonk examlation of eaWror-0-yenssl we

Reply: it Is she opinion of Sc COnuitecSIM Cate-gory B-D wmd-o-vausd welds prviusly ulasoul-cally cxained using the exmino OlU Figs.IWB-2500-7t (b). and (C) ma1y be, exmlned uingIIX rued eUdnatIon VoIume (A-B-C.DE.F.O-H)of Hp 1,2. Zand 3.

1029 S p,- lC

NL-03-188, Enclosure IAttachment 1, page 2 of 4

CASE (conUnued)

N-613-1CAS OF DO AM MSUBE VRSEL O

,t f noe *aU tioknesIS a bell (or hd) Ilnenuaq nozle kde orne rdius

Co

M _ _

Cornrt law

EXAMINATION EGION INote Ill EXAMIMATlON VOLUME Nle 1211

sheo (or head dJolnfa regionAftochant weld regionNozz cylinder eglonNozle Intide corne region

C-D-r-FI-C-F-GA-B-G-HM-N-O-P

NOTES;11) Examnation reglons er Identified ler t purpose of differentlinog ow ecpun= andards in MW13512.(2) Eanuaion bms any e dtermIned ter by dlrect mumurements on e ompn or by

m sement based en dusdgn drawdngsi

.

FIG. 1 NOZZLE IN SHELL OR HEAD(ExamInatbn Zones ael T* Nozzes JolneOd by Fun Petvon Cer Welw

SUPP. -NC 1030

NL03-188, Enclosure IAttachment 1, page 3 of.4

CASE (continued)

N-613-1

fjt, rQ - nozzle wa ticknis - shall or heedl lknssq - noze Inside corner radius

GC

INI

where

/ fe M_Corno no^w

EXAMINATION REGION INote M1)Shell (or haed) sdoinng regionAtachment weld regionNozzle cinder regionNol hslde corner region

XAMINATIN VOLUME Plote 121C-D-E-FB-C-f-GA-B-G-Hbl-N-O-P

NOTES(1) ExamInatonreglons ar IdenUled b rthspurpose ofdifferentiangg Uapsun erands In NWMS1212) Eaminationvolumesmsybe dermnedeIther bydirectmeasumenuon temponentorby

musurements based on design drawings.

FIG. 2 NOZZLE IN SHELL OR HEAD(Examinaton Zones In Flnge Type Nozzles Joined by Ful Penetration Butt Welds)

1031

.

!

NL03-188, Enclosure IAttachment 1, page 4 of 4

VADC Ilomnluuai

N-613-1CS OF AIM I l AMD FRE= VSEL CODE

4- .lzil %Wl hkineut dll orh ead) gss t a Iside co norroida

l i.

whereprust

Corner fw

EXAMINATIO RIEGION INoto lleSha bored) adoialng regionAttedwrt Ield regionNodo cyndor regionNozzle bide coner region

EXAMINATION VOLUME INoto Oil. C-D-E-F-G

U-C-GA-D-O-HM-N-0-P

NOIES:11) Examneon region edended Ir eurpos f dlflmbllng Ve panc ads h MI94S1Z1) Exrninalon volums m be detrmined eihr by dw tmeuremens en ecoasnim r b y

maesurements based an design drawingL

FIG. 3 NOZZLE IN SHELL OR HEAD(Examination Zenes In Set-On Te Nzts Joined by Full Penetration Comer Welds)

1032

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iII

SUPP. I - NC

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IEXAMINATION VOLUME - SECTION XI EXAMINATION VOLUME - CODE CASE N-613-1

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INDIAN PINT UNITS 2 AND 3 ( TYP. )

RPV INLET NOZZLE

e CDE CASE NOZZLE VOLJME REFINEMENT

EXAMINATION PROGRAM PLAN 2003

a M wIom M-9

Westinhouse Proprietary Class 2C

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rIVArAIA-T rnrI %Zfll I Ifr - rin rAC'r Al-Zl1 _f

EXAMINATION VOLUME - SECTION XI C>A1IIIVf I.IV VLIIC - LUJC SYNC 1V01Q1

INDIAN POINT UNITS 2 AND 3 TYP ) n m

RPV LIULET NOZZLE79 CODE CASE NOZZLE VOLUME REFINEMENT

XAMINA TION PROGRAM PLAN 2003

AML uAmmIUrm N cu1 IAMtTh"I NoM fXPDV 1n

NL-03-188Enclosure 2

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM

RELIEF REQUEST RR 3-36

Proposed AlternativeIn Accordance with 1 OCFR50.55a(a)(3)(i)

-Alternative Provides Acceptable Level of Quality and Safety-

1. ASME Code Comoonent(s) Affected

Component Numbers: ASME Code Class 1 Reactor Vessel Nozzle to Shell Welds.

Examination Category: B-D

Item Number B3.90 - Nozzle to Vessel Welds

2. Applicable Code Edition and Addenda

The Code of Record for the third Inservice Inspection Interval is ASME Section Xl Code, 1989Edition, No Addenda.

3. Applicable Code Requirements

ASME Boiler and Pressure Vessel Code, Section Xl, Rules for Inservice Inspection of NuclearPower Plant Components, 1989 Edition with No Addenda: Table WB-2500-1 Code Item B3.90,Figures IWB-2500-7 (a) thru (d) for defining the examination volume of the reactor vessel nozzleto shell welds. The examination requirements for reactor vessel nozzle to shell welds are definedin the ASME Code, Section Xl, Appendix Vil, Supplements 4, 6 and 7, 1995 Edition, 1996Addenda as modified by 10 CFR 50.55a. Eight (8) RPV nozzle to shell welds, 4 inlet and 4 outlet,are planned for examination in 2009 as follows:

Nozzle to Vessel Weld 21 @ 1130 Azimuth



Nozzle to Vessel Weld 24 @ 247° Azimuth


Nozzle to Vessel Weld 26 @ 338° Azimuth



1

NL-03-1 88Enclosure 2

4. Reason for Reauest

The Code required examination volume of the nozzle to vessel welds is unnecessarily large. Theproposed alternative to use Code Case N-613-1 in its entirety will not affect the flaw detectioncapabilities in the weld and the heat affected zone, and provides an adequate level of quality andsafety for examination of the affected welds.

5. Proposed Alternative

In accordance with 10CFR50.55a(a)(3)(i), P3 requests relief from the tJ2 (ts is equal to the vesselwall thickness) examination volume requirement and instead proposes examination of the basematerial volume extending 1/2 inch from each side of the weld. This refined examination volume isdefined in detail within Code Case N-613-1 (Attachment 1) and the WesDyne sketches(Attachment 2).

Basis for Use

The examination (exam) volumes for the reactor vessel nozzle to vessel welds are unnecessarilylarge. For the 1P3 reactor vessel, the nozzle to shell volume would extend about 5 inches into thenozzle forging and the same distance into the upper shell course forging. This proposedalternative would re-define the examination volume boundary to 1/2 inch of base metal on eachside of the thickest portion of the weld. This reduction in base metal inspection will not affect theflaw detection capabilities in the weld and heat affected zone.

Compliance with these requirements will assure the requisite level of quality and safety ismaintained.

The proposed reduction in exam volume is base metal only, extensively interrogated by ultrasonicexamination during fabrication, preservice examinations and the last inservice examinationsperformed in 1999 at the end of the second interval. In 1999, the data was acquired, archivedand analyzed using automated ultrasonic systems. Entergy Nuclear Operations, Inc. (Entergy) isconfident that reasonable comparisons can be made between the past and present if necessary.During the 1999 examinations, there were no unacceptable indications were found in the eight-reactor vessel nozzle to shell examination volumes including the base metal areas proposed forexclusion from examination in this request. The 1999 results were based on examinationsperformed in accordance with the ASME Code, Section Xl, Section V and Regulatory Guide1.150, Rev. 1.

The Section Xl examination volume for the pressure-retaining nozzle to shell welds extends fromthe edge of the weld to include a significant portion of the nozzle forging body (inward) andreactor vessel upper shell course (outward) which is a forged ring. The large volume results in asignificant increase in examination time with no corresponding increase in safety as the greatestportion of the volume is base material not prone to inservice cracking.

The implementation of this request for relief would reduce the examination volume next to thewidest portion of the weld from half the vessel wall thickness to 1/2 inch from the weld. Thisreduction applies only to base metal and not the stressed areas of the nozzle to shell weld.

2

NL-03-188Enclosure 2

Entergy shall ensure that the high stressed areas of the P3 reactor vessel nozzle to shell weldsshall be included in the examination. The examinations shall consist of techniques andprocedures qualified in accordance with the ASME Code, Section Xl, Appendix Vill, andsupplements 4, 6 and 7. The weld and surrounding 1/2 inch volume will be interrogated from thenozzle bore using techniques and procedures specifically qualified to inspect the nozzle to shellweld from the nozzle bore. These procedures were qualified in January 2003 in accordance withAppendix Vil, Supplement 7 as administered by the PDI.

The nozzle to vessel examination volume is also accessible from the vessel ID surface and will beexamined in four orthogonal directions for the first 15 percent of weld thickness with respect to thevessel ID surface using Appendix Vil, Supplement 4 qualified techniques. The remaining 85percent of weld volume accessible from the vessel ID surface will be examined in two opposingcircumferential scanning directions using Appendix Vill, Supplement 6 qualified techniques tointerrogate for transverse defects.

This combination of scans addresses the requirements set forth by the ASME Code, Section Xi,1995 Edition with 1996 Addenda as modified by 10CFR50.55a and assures that current qualifiedtechnology will be applied to the re-defined examination volume specified herein to the maximumextent practical. Compliance with these requirements will assure the requisite level of quality andsafety is maintained.

6. Duration of Proposed Alternative

It is proposed to use the alternative for the remainder of the Third Inservice Inspection Interval forIP3.

7. Precedents

A similar request for relief was approved for Hope Creek (Docket No. 50-354, TAC NO. MB7839,dated August 26, 2003).

8. Attachment

1. Code Case N-613-1 (for information)

2. WesDyne Sketch, Indian Point Units 2 and 3 (TYP.), RPV Inlet and Outlet NozzlesExamination Volume - Code Case N-613-1 (2 pages)

3

NL-03-1 88, Enclosure 2Attachment 1, page 1 of 4

N-613-1CWSES OFS3OU=R MND rssU VES oDn

DAl Da . Augut .2SHe IAl ha fr exatOn

and any eatimaon dat.&

Case N4131UlUrso Examitto of Fa PetrationNozzles In Vasek Ex fml u Catory B-DUem No% B31g rnd B390, Rector N=ze-To-Vesed Weds, SL IWB 70, (b), and WSetion l OhuoU 1

lnguir Wit ves Ia e esmnlion volumeMequh= ts f Figs. lWB-2S007(4 (b), ad (c) aePMnissibe for alsonlc eamiAon of Arnozle-o-vessel W s

RCpAY. It is the Cpinion of Ihe Comn)tehaz Cato-gory B D =zIlCeO-vssd welds pr:ibusly urasoni-aly eana using & exanination VOlum or FIS

IWB-2500-7(. (W . and c) inay be exanined usingthe reduced examinlation volume (A-B-C-D-E-F-0H)of Figs. 1. , an 3.

A:'

1m9 SuPP.e -Nc

NL-03-188, Enclosure 2Attachment 1, page 2 of 4

CASE (continued)

N-613-1CASZS 0O AB DO AD PRISSURE VSEL CODE

4gdS 4 a nowesaivlt aes* sehaUorhaaihidmassa nozzle kuld corner radlux

.CD

Cornertaw

EXAMINATiON REGION INot 11ihul (or hesal adiolhnt ulan

Aftschmertweld rgtonNozle cUnder rgionNozzle eld, orner lion

EXAMINATIONVOUME INote(211C-D-E-FB-C-F-¢A-B-C-HU-R-O-P

NOTES:11) Exambuilon reglons are dandfied fort purpose of differendatng thr ecpance slandards In 1YB4511 Examiration volumes may be determined elther by diec mneasuremeot an the componat or by

neasurements based an design drawings..S

flG I NZZL I SHELL OR HAD(Examination Zones In Barrel Type Nozzles Joined by Ful Peneratulon Corner Weds)

1030SUPP. , - NC

NL-03-188, Enclosure 2Attachment 1, page 3 of.4

CASE (contlnued)

N-613-1

rta a * nozdI walf thiks1, sheR r hordl ShIunussq * nozne iside corner rsdius

no_12 L Whom

poso

Corner flow

EXAMINATION REGION INoto 1111 XAMINAMION VOUM E INoto 12)

ho (or adl ao~hingdregion C-D-E-FAftachmentwold rooin B-C-f-tNozzl cylinder region A-5-G-HNoe Inside cor regin U-N-O-P

NOTES:(1) ExamInation glon art Iderfied fbr f pufpoe cf dlfferenatgit eptanca.sundard In M 412M Examinaton 1tume may bO dtermnbwd ther by ect mesurmmenu oni scnmponen trby

mouuramontas based on design drwings.

FIG. 2 NOZZLE IN SHELL OR HEAD(Exambiaton Zones In Flange Type Nozzles Jolned by Fll Penetation Buu Welds)

1031

NL3-188, Enclosure 2Attachment 1, page 4 of 4

VAuC 10olnueal

N-613-1CASMS OF "M I0If AM P&SU VIS CME

I

&I aoszl . I tiflms* al IMrhad) thickesq* azle kiidaeeonw dus

present

' a

M

Cor faw

EXAMINATION REGION INote 1SheD lorhad) dning regionAtachment wold nglonNo2e cylndar rgionNozzle Inside corner region

EXAMINATION VOLUME INote 1nC-0-E-F-G

A-B-O-HM-N-O-

NOlES:11) ExadnatbnregionIdenffl forhei efdiffrenitingtecceptaetndadsHVW451242) Exanintlon volumes may be detramined elther by 4rece measurements on th compcnernt or by

meesuremants bed on design drawings.

FIG. 3 NOZZLE IN SHELL OR HEAD(Examination Zones I Set-On Type Noes Joined by ull Penetration Corner Welds)

1032

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EXA4MINA TIVN VOLUME - 5CCTN XEXAMINA TLON

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INDIAN PNT UITa

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EXAMINATION PROGRAM PLAN 2003ALI DKENONS IN INCS 7

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indian point, units 2 and 3 - request for approval for ...nozzle to vessel weld rpvn3 @ 1130 azimuth...

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