LR-N970686, Forwards Supplemental Info Which Supports Request for Approval of Repair Plan for Core Spray Nozzle Weld through- Wall Leakage Identified on 970919

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Forwards Supplemental Info Which Supports Request for Approval of Repair Plan for Core Spray Nozzle Weld through- Wall Leakage Identified on 970919
ML20198J636
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 10/15/1997
From: Storz L
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20198J640 List:
References
LR-N970686, NUDOCS 9710210217
Download: ML20198J636 (15)
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i ec c as Company Louis F, Stor: Public Service EJectric and Gas Cocpany P.O. Box 236. Hancocks Bridge. f4J 08038 009-339-5700 sencrvice Pr sonni uxiw opeavons LR-N970686 0CT 151997 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENTAL INFORMATION

- CORE SPRAY NOZZLE WELD THROUGH WALL LEAKAGE HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO 50-354 Gentlemen:

In Letter LR-N970667, dated October 9,1997, PSE&G submitted information related to l the Core Spray nozzle weld through-wall leakage identified on September 19,1997 and requested approval of a repair plan for the associated weld. PSE&G is submitting the e

attached supplemental information to further support the request.

Attachment 4 to LR-N970667 contained PSE&G's commitments for performing additional examinations during the current refueling outage. Attachment 1 to this letter is a revision to the original information and is intended as a replacement for Attachment 4 to LR-N970667 dated October 9,1997 Attachment 1 includes the following:

1) The repair history for each of the 20 Category "D" welds
2) The weld procedures for each of the 20 Category "D" welds
3) Susceptibility to IGSCC and Hydrogen Water Chemistry protection for each of the 20 Category "D" welds
4) Conclusions relative to the acceptability of each of the remaining 19 Category "D" welds
5) Additional exams planned for the current refueling outage Attachment 2 to this letter includes a copy of the welding procedure to be used in performing the repair, h'

t 9710210217 971015 A ADOCK 050o gDR ll!!!!f!!!k!{!!k!!i!!I!!,! !!,! ,

hx! Paper

OCT 151997 Document Control Desk LR-N970686.

Attachment 3 includes information related to the repair plan that was submitted as Attachment 2 to IR N970667 dated October 9,1997.

- Should you have any questions regarding this information, we will be pleased to discuss them with you, i

Sincerely, V '

b/}

Attachment i

I OCT 151997 l l

l Document Control Desk - - LR-N970686 j

'C Mr. H. Miller, Administrator - Region 1

- U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Jaffe, Licensing Project Manager - HC U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mall Stop 14E21 Rockville, MD 20852 Mr. S. Morris (X24) ,

USNRC Resident inspector - HC Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway Trenton, NJ 08625

ATTACHMENT 1 HOPE CREEK GENERATING STATION -

FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 ADDITIONAL EXAMINATIONS Hope Creek has identified 20 welds classified as Category D, in accordance with

, NRC Generic Letter 88-01. Our augmented inspection program requires examination of all 20 Category D welds on an every other refueling outage basis. Accordingly, all 20 welds were examined during the sixth refueling outage. No examinations were scheduled for the current refueling outage.

Following discovery of the through-wall leak on the Core Spray nozzle to safe-end weld; PSE&G requested that a full Code ultrasonic (UT) detection examination be performed to assist in the determination of the extent of the defect. Sizing techniques were invoked to characterize the defect.

Additionally, PSE&G requested our NDE vendor to re-evaluate the UT data from the sixth refueling outage for all the Category D welds. A review of the construction radiographs for those Category D welds replaced on-site during the 1982 safe-end replacement modifications was also performed. These reviews did not identify any flaws or suspect indications.

PSE&G has requested that EPRI provide an independent review of the sixth refueling outage mechanized UT data. EPRI NDE Center personnel evaluated this data and the results are shown on the attached matrix.

A review of the sample expansion criteria found within the referenced documents was performed. No specific requirements for sample expansion of Category D welds could be found within NUREG 0313, Rev. 2. - As there were no scheduled examinations for the current refueling outage, the ' Additional Examination' requirements of ASME Section XI (1983 Edition, including Addenda through Summer 1983), Para. IWB-2430 (a) do not clearly apply.

However, due to the significance of a through-wall reactor coolant system leak, PSE&G will examine additional welds of a similar nature during the current refueling outage. Using the guidance from Section XI, and given that one examination was performed during this refueling outage for this category, one additional weld would be' required to be examined.

Page 1 of 2

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Att:chment 1 LR-N970686 Addition:l Examin:ti:ns Using the guidance from NUREG-0313, Rev. 2, considerable effort was given toward the determination of a technicaljustification for selection of a specific inspection sample distribution. Reviews were performed on safe-end replacement modification records (for example; weld process, filler materials, repair areas, NDE results, etc.), operating history of the unit for cold water injections, and effects of Reactor Coolant chemistry control efforts and

. transients. See attached matrix.

Based on the above, six welds were selected for examination. These examinations will be performed in accordance with a procedure and personnel qualified in accordance with the requirements of ASME Section XI, Appendix Vill,1992 Edition with 1993 Addenda as modified by the Performance Demonstration Initiative (PDI) document 'PDI Program Description'; currently Revision 1, Change 1. These requirements are being incorporated as an alternative (IWA-2240) to those requirements of the current ISI Program which complies with the 1983 Edition, including Summer 1983 Addenda of Section XI.

, The additional welds are:

, 1. The NSA Core Spray nozzle to safe-end weld was selected because its operational environment is similar to that of the NSB nozzle. Although no repairs were performed and the filler material is Inconel 82; this nozzle is the other Core Spray nozzle located at the same Reactor Vessel

, elevation, and is not protected by hydrogen water chemistry.

2. The N2J recirculation inlet nozzle to safe-end weld was selected because of its technical characteristics being quite similar to those of the NSB
nozzle weld. The review of 1995 UT data from N2J identified indications near the detection threshold in the area of repairs which would require further investigation. Also, the weld contained repairs made during the safe-end replacement in 1982, the filler metal used was inconel 182.
3. There are 4 nozzles that received manual examinations; N8A, N88, N9, and N6A. Manual examination results are documented on Data Sheets.

This information is limited to only the information recorded and a thorough evaluation of previous examinations is not possible. Therefore, current

- ultrasonic examinations will provide additional confidence in identifying the extent, if any, of lGSCC.

Page 2 of 2

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ROOT CAUSE EVALUATIONS 1

HOPE CREEK CATEGORY "D" WELDS LR-N970686 ATTACHMENT 1 COMP.ID NOZZLE PIPE NOZZLE BUTTER ROOT WELD FILL WELD WPS-7D WPS-2D 'SUSCEPDBLE HWC NUMBER OF DESCRIPTION SIZE ELEVATION MATERIAL FILLER FILLER INSERT (GTAW + MATERIAL (AS OF 2/93) IN-PROCESS

[UPWArtD] + SMAW) REPAIRS ORBITAL [ UPWARD]

(GTAW)

RPV1-N1ASE Recirc Oudet 28" 128'8.5" INCO 182 see comments see comments YES PROTECTED see comments RPV1-N1BSE Recirc Outlet 28" 128'8 5- INCO 182 see comments see w.. mats YES PROTECTED see comments RPV1-N2ASE-30 Recirc inlet 12" 130'4" INCO 182 GTAW INCO 82 GTAW INCO 82 X. YES PROTECTED 0 RPV1-N28SE-60 Rectre intet 12" 130'4" INCO 182 GTAW INCO 82 SMAW INCO 182 X T YES PROTECTED 1 RPV1-N2CSE-90 Recirc Inlet 12" 130'4" INCO 182 GTAW INCO 82 GTAW INCO 82 X YES PROTECTED 0 RPV1-N2DSE-12 Recirc Inlet 12" 130'4" INCO 182 GTAW INCO 82 SMAW INCO 182 X X YES PROTECIED 3 RPV1-N2ESE-15 Rectre inlet 12" 130'4" INCO 182 GTAW INCO 82 GTAW INCO 82 X X YES PROTECTED 1 SMAW repair i

RPV1-N2FSE-21 Recirc Inlet 12" 130'4" INCO 182 GTAW INCO 82 GTAW INCO 82 X YES PROTECTED 0 ,

1 i

1 Table Page 1 -

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ROOT CAUSE EVALUATIONS HOPE CREEK CATEGORY "D" WELDS .

LR-N970686 ATTACHMENT 1 COMP.ID NOZZLE PIPE NOZZLE BUTTER ROOT WELD FELL WELD WPS-7D WPS-2D SUSCEPTIBLE HWC NUMBER OF DESCRIPTION SIZE ELEVATION MATERIAL FILLER FILLER INSERT (GTAW + MATERIAL (AS OF 2/93) IN-PROCESS

[ UPWARD] + SMAW) REPAIRS ORBITAL [ UPWARD]

(GTAW)

RPV1-N2GSE-24 RectrC inlet 12- 130'4' INCO 182 GTAW INCO 82 GTAW INCO 82 X YES PROTLCTED 0 RPV1-N2 HSE-27 Recirc Inlet 12- 130'4' !NCO 182 GTAW INCO 82 GTAW INCO 82 X X YES PROTECTED 1 SMAW repasr RPV1-N2JSE-30 Recirc Inlet 12' 137 4" INCO 182 GTAW INCO 82 SMAW INCO 182 X X YES PROTECTED 1 RPV1-N2KSE-33 Rectre inlet 12" 130'4' INCO 182 GTAW INCO 82 GTAW INCO 82 X YES PROTECTED 0

. RPV1-N5ASE-12 Core Spray 10" 155'7.5" INCO 1ts2 GTAW INCO 82 GTAW INCO 82 X YES UNPROTECTED 0 RPV1-NSASEX Core Spray 10" 155'7.5" INCO 182 see comments see comments YES UNPROTECTED see comments Extension  ;

i RPV1-NSBSE-24 Core Spray 10' 155'7.5" INCO 182 GTAW INCO 82 SMAW INCO 182 X X YES UNPROIECTED 9 i

RPV1-N5BSEX Core Spray 10~ 155'7.5" INCO 182 see comments see comments YES UNPROTECTED see comments  ;

Extension t i

RPV1-NBASE Jetpump 4' 127*11" INCO 182 see comments see comments YES UNPROTECTED see comments Instrument hne i

Table Page 2 L

)

ROOT CAUSE EVALUATIONS ,

HOPE CREEK CATEGORY "D" WELDS LR-N970686 ATTACHMENT 1 t

COMP.ID NOZZLE PIPE NOZZLE BUTTER ROOT WELD FILL WELD WPS-7D WPS-2D SUSCEPTIBLE HWC NUMBER OF DESCRIPTION SIZE ELEVATION MATERIAL FILLER FILLER INSERT (GTAW + MATERIAL (AS OF 2/93) IN-PROCESS

[ UPWARD] + SMAW) REPAIRS ORBITAL [ UPWARD]

(GTAW)

RPV1-NBBSE Jetpump 4' 127'11" INCO 182 see comments

^

see wi. ..er.6 YES UNPROTECTED see w....e.s Instrumere hne RPV1-N9SE-1 CRD Retum kne 4' 152'7 5" INCO 182 GTAW INCO 62 SMAW INCO 182 YES UNPROTECTED see comments (capped)

RFV1-N6ASE RHR Head Spray

^

6' TOP OF HEAD INCO 182 see comments see w.. w..d YES UNPROTECTED see comments WPS = Weld Proceoure Specification I

Table Page 3

ROOT CAUSE EVALUATIONS HOPE CREEK CATEGORY "D" WELDS LR-N970686 ATTACHMENT 1 1980-1982 1997 1989 1992 1995 1997 1997 1997 1997 1997 1997 1997 COMP.ID NOZZLE FINAL RT PSE&G RT 1989 UT 1992 UT 1995 UT 1997 1989 UT 1992 UT 1992 UT EPRI 1995 UT 1995 UT 1997 UT DESCRIPTION ACCEPTED FILM Southwest GE GE " manual" Southwest GE review GE Final GE GE w/ INDICATION REVIEW Original Original Original GE UT Review - Review initial Review Results Results Review RPV1-N1ASE Rectre Outlet see comments see CLEAN CLEAN CLEAN n/a n/a n/a n/a n/a CLEAN n/a comments RPV1-N1BSE Rectre Outlet see comments see CLEAN CLEAN CLEAN n/a n/a n/a n/a n/a CLEAN n/a Comments ,

RPV1-N2ASE-30 Reorc iclet POROSITY / ACCEPT CLEAN CLEAN CLEAN n/a n/a n/a n/a n/a CLEAN n/a SLAG RPV I-N2BSE-60 Reore tnlet POROSITY / ACCEPT CLEAN CLEAN CODE n/a n/a n/a n/a n/a CODE n/a ,

SLAG '

RPV1-N2CSE-90 Rearc inlet POROSITY ACCEpi CLEAN CLEAN CLEAN n/a n/a n/a n/a CLEAN n/a gn/a RPVI-N2DSE-12 Recrc inlet POROSITY ACCEPT CLEAN CLEAN CLEAN n/a n/a n/a n/a n/a CLEAN n/a RPV1-N2ESE-15 Rearc inlet POROSITY ACCEPT CLEAN CLEAN CLEAN n/a n/a n/a n/a n/a CLEAN n/a i

RPV1-N2FSE-21 Recrc inlet POROSITY ACCEPT CLEAN CLEAN CLEAN n/a n/a n/a n/a n/a CLEAN n/a Table Page 4

8 TOOT CAUSE EVALUATIONS HOPE CREEK CATEGORY "D" WELDS LR-N970686 1 ATTACHMENT 1 COMP.ID NOZZLE FINAL RT PSE&G RT 1989 UT 1992 UT 1995 UT 1997 1989 UT 1992 UT 1992 UT EPRI 1995 UT 1995 UT 1997 UT DESCRIPTION ACCEPTED FILM Southwest GE GE' " manual" Southwest GE review GE' Rnal GE GE w/ INDICATION REVIEW Original Original Original GE UT Review Rev'ww initial Review Results Results Review RPV1-N2GSE-24 Reorc in!et SLAG ACCEPT CLEAN CLEAN CLEAN n/a rua n/a n/a n/a CLEAN n/a RPV1-N2 HSE-27 Recirc Intet NO ACCEPT CLEAN CLEAN CLEAN n/a n/a n/a n/a n/a CLEAN n/a INDICATIONS RPV1-N2JSE-30 Reorc intet POROSITY ACCEPT CLEAN CLEAN CLEAN n/a rua n/a n/a n/a CLEAN n/a RPV1-N2KSE-33 Recre Intet POROSITY /SLA ACCEPT CLEAN CLEAN CLEAN n/a n/a n/a n/a n/a CLEAN n/a G ,

t RPV1-NSASE-12 Core Spray POROSITY /N22 ACCEPT CLEAN CLEAN CLEAN n/a n/a n/a CLEAN n/a CLEAN n/a R+N1800T CONCAVITY RPV1-N5ASEX Core Spray see cornments see CLEAN CLEAN CLEAN n/a n/a n/a CLEAN n/a CLEAN n/a Extension comments

  • RPV1-N5BSE-24 Core Spray SLAG Reject - LOS CLEAN CLEAN CLEAN CLEAN CLEAN CLEAN 000TIONAl:LE CLEAN Reject - Reject - r IGSCC IGSCC RPV1-N5BSEX Core Spray see comments see CLEAN CLEAN CLEAN n/a n/a n/a CLEAN n/a CLEAN n/a Extension comrnents l RPV1M8ASE Jetpump see comments see CLEAN CLEAN CLEAN n/a n/a n/a n/a n/a see n/a l Instrument line comments comments Table Page S

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ROOT CAUSE EVALUATIONS HOPE CREEK CA TEGORY "D" WELDS -

LR-N970686 ATTACHMENT 1 COMP.ID NOZZLE FINAL RT PSE&G RT 1989 UT 1992 UT 1995 UT 1997 1989 UT 1992 UT 1992 UT EPRI 1995 UT 1995 UT 1997 UT DESCRIPTION ACCEPTED FILM Southwest GE GE "manuar Southwest GE review GE Final GE GE w/lNDICATION REVIEW Original Original Original GE UT Review Review initial - Review Results Results Review RPVI-N8BSE Jetpump see comments see CLEAN rm CLEAN n/a n/a n/a n/a n/a see n/a instrument line comments ~..-.t.

RPV1-N9SE-1 CRD Retum hne POROSITY - ACCEPT CLEAN CLEAN CLEAN n/a n/a rt's n/a n/a see n/a (capped) UNDERCUT comments RPV1-N6ASE RHR Head Spray see comments see CLEAN CLEAN CLEAN n/a n/a n/a n/a n/a see n/a comments comments CLEAN = NO flaw mdcatons CODE = Acceptable flew in carbon steel rezzle (forgeng flap)

OUESTIONABLE = Contains ultrasonic indcatons at or near threshold of detectabildy l

l r

Table Page 6 i

ROOT CAUSE EVALUATIONS HOPE CREEK CATEGORY "D" WELDS LR-N970686 ATTACHMENT 1 1

1997 1997 .

1 FOMP.ID NOZZLE 1997 UT 1995 UT COMMENTS CONCLUSIONS '

DESCRIPTION EPRI EPRI Review independent  ;

I Review n/a CLEAN No record of Safe-end replacements at We*** m'ommeo 01 cans prome reymmen m RPV1-NIASE Rectre Outlet g, saetarwme em aesence or no. n me .e=1 Re.w.s acre corusucsed by GE, PSE&G, wws EPRI NDE carew to mnfrm ew absenes or UT oges sender to rose observed sn NSBSE RPV1-N1BSE Recirc Outlet n/a CLEAN No record of Safe-end replacements at We'a* *8ammea u t e==,= proves rearmem e mestanew em atmence er es a ew as Rev

'#8 .ere cmduczed ty GE, PSE&G sus EPRI fuDE career to confrm em speence or UT swyws sender to those neeervee on No8SE RPV1-N2ASE-30 Rectre inlet n/a CLEAN Weram maammea ut exams proven rearmarm = = maane censinnon

.es.mnwe tw steence or ns.s e e ased pens e suppen m ut resuas were conducwd ty GE. PSE&G. and EPRf NDE conrw e enrrm ew absenos er UT sywa erneur to emos ceservee on NSBSE W. cus maammea vi .=ams provee reo rmmen s n amen mnen,xn RPV1-N2BSE-60 Recirc inlet n/a CODE subenew the atmmco ce %.s et tNs ki Raw 6 mepert ew UT reeufs

. ore conessed ty GE, PSE&G and EPRf NDE certer to g

wrwm tw absence or ur news sendar to emee et,eervee on N58SE RPV1-N2CSE-90 Recirc inlet n/a CLEA*t * =a rsommea vi =was provee nro mmm io n emm enenaan suecanew ew steence orn mens *d Reww

  • e support to UT reeues were ennaweted ty GE PSE&G and EPRI NDE cenwr to ardrm te absence of UT syws sender e twee eteerwee ionN58SE RPV1-N2DSE-12 Recirc Inlet n/a CLEAN Weveus maameea ut e ams proves nearmarmio n esacen. ecesowaan mestanare se abeerwm cf fis.s ri rue .edd Reww.s -seographs meport tw UT resuas were corthcsod by GE. PSE&G. wws EPRf NDE corner to oc=vm em atrJance of UT spels sandar to these otnoorvec m NSBSE RPV1-N2ESE-15 Recare inlet n/a CLEAN Wevous a8or%e u r ==ams provee rearmmon = n esseen. conannon ouestannte to obsente d fle.s em ens .eNf Re e.s adegraphe memort ew UT *ssums more conducted ty GE. PSERG. and EPRI NDE certer to unrrm the aosence of ur sgnes sensar toihose absorve on N*.8SE RPV1-N2F SE-21 Rectre Intet n/a CLEAN * **us ado ***a u r == ens proves nearmem m n saarrm conanoon ee.mm.ew .e ence or no.* n s Re wachs .uppare ine ur re.u=*

.or. mneucwd e rGE. PSE&G end EM NOE cenwr e enerm a steence or uf .gwe nn.iar e inose eeser.ee m NSBSE Table Page 7 l

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ROOT CAUSE EVALUATIONS HOPC CREEK CATEGORY "D" WELDS LR-N970686 ATTACHMENT 1 COMP. ID - NOZZLE 1997 UT 1995 UT COMMENTS CONCLUSIONS DESCRIPTION EPRI EPRI Review independent Review RPV1 N2GSE-24 Recare Intet n/a CLEAN Frewmus mAammed ul exams prowne rearmete to m entet annerm.aon anestarese the accence of fl a mihis eed Revens 6 sipport the UT results

.ers omducted by GE P$EEG and EPRI NDE career to curfum ew absorts or UT syws sender to those eteervoa m fe58SE RPV1-N2 HSE 27 Recus inlet n/a CLEAN Pr**'ous ado ***e ut mams provee rearm aun se n act eat conewucre sieses,mm the steence er to.s e eus weed Revues 6 se the UT essues were conducled by CE. PSE&G and EPfU NDE conter to contem en annonce at UT eyes senmar m those ateervee a NS85E RPV1-N2JSE-30 Recare inlet n/a QUESTlONABL wa m uI row . meng sn ku. te2 tuer E *****"U***'"**

RPV1-N2KSE-33 Recare inlet n/a CLEAN Prevous a:aommee ut asms provee =*y wien e m m cmewinzem ametanee em somence er news e e=s ems Reve.s <admgracru sw we ut me

.gro conexsed by GE. PSE&G ard EPRt NDE corner as e e. steerm a UT sews senaar to eene eteervee m N58SE RPV1-N5ASE-12 Core Spray n/a CLEAN **rauga no repar* *** peorme we ew '*m mmme

.ma was eco a2, Nss., s e some waramas en es.wnere and elevaten rs NSB. endspel UT repechor s recured RPV1-NSASEX Core Spray n/a CLEAN No record of Safe-end replacements at P*'ous *nomsma ut emens proven rearmeen e

***""*"'*d""****'d "*****

Extension site . ore cowsxsed by GE. PSEEG. and EPRt NDE conier to cartem em steers er uT s ,yws sendar to vs.ae eneen.a m wesE RPV1-N583SE-24 Core Spray Reject - Reject -IGSCC escc inwo-nau. cwx ReeAte Rwumto IGSCC RPVI-NSBSEX Core Spray n/a CLEAN No record of Safe-end replacements at Pravon asommea ul marns prevne rearmem m Extension site

.ere cor4Jcted by GE. PSESG, arid EPRf NDE mnser to

'2irdam the at orre of UT segres sensar to bese coservec on NCasE RPVI-N8ASE Jetpump n/a see comments Manual UT examination. Data sheets Om e nsi cl W) WAR 1" ome t rovew amnem ul Instrument line "'**"**

st.ow NO flaw indications. No record of Safe +rv.! replacements at site Table Page 8

ROOT CAUSE EVALUATIONS HOPE CREEK CATEGORY "D" WELDS LR-N970606 ATTACHMENT 1 comp.lD NOZZLE 1997 UT 1995 UT COMMENTS CONCLUSIONS DESCRIPTION EPRI EPRI Review independent Review RPV2-NABSE Jetpump n/a see comments Manual UT examination Data sheets vuo n sum a ss waa r nem e ==. awx,w ui instrument line ' ' ' ' ' ' " "

  • show NO ftsw indications. No record of Safe <md replacements at site RPV1-N9SE-1 CRD Retum line n/a see comments Manual UT examinaten. Data sheets uus e u a vs mr ama m . monnons ut (capped) show NO flaw indications '"*""***"**

l RPU1-N6ASE RHR Heaa Spray nra see comments Manual UT examinaten. Data sheets uu.= m a e er ama w . maaarm vi I

show NO flaw Mcatens. No record o' " " ' * ' " * * * " *

  • l Safe-rM replacements at site i

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ATTACHMENT 2 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 WELD PROCEDURE 1

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