ML062130018

Email: (Pa:) Fwd: Questions and Answers of Pilgrim LRA Aging Management Reviews

ML062130018
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Site:	Pilgrim
Issue date:	06/30/2006
From:	Dan Hoang NRC/NRR/ADRO/DLR
To:	Jennifer Davis, Dang Nguyen, Wen P Office of Nuclear Reactor Regulation
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James Davis-Fwd: Questions and Answers of Pilgrim LRA Aging Management Reviews Page 1 From:

Dan Hoang To:

Duc Nguyen; James Davis; Peter Wen; wapavinich @ comcast.net;jacksonwr@ msn.com;erachp @ comcast.net Date:

Fri, Jun 30, 2006 2:07 PM

Subject:

Fwd: Questions and Answers of Pilgrim LRA Aging Management Reviews Gentlemen, Here they are.

Enjoy Dan

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Fwd: Questions and Answers of Pilgrim LRA Aging Management Fri, Jun 30, 2006 2:07 PM Dan Hoang DVH@nrc.gov Recipients comcast.net wapavinich (wapavinich @comcast.net;j acksonwr@msn.com;erachp @comcast.net) nrc.gov OWGWPOO3.HQGWDOO1 JAD (James Davis) nrc.gov TWGWPO01.HQGWDOO1 DTN1 (Duc Nguyen) nrc.gov TWGWPO04.HQGWDOO1 PXW (Peter Wen)

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James Davis - Fwd: Questions and Answers of, Pilgrim LRA Aging Management Reviews Page 11 James Davis - Fwd: Questions and Answers of Pilgrim LRA Aging Management Reviews Page 1 From:

Ram Subbaratnam To:

dvh Date:

Fri, Jun 30, 2006 1:57 PM

Subject:

Fwd: Questions and Answers of Pilgrim LRA Aging Management Reviews Dan distribute to AMR team members for review.

Ram P.S. I wonder how without a definitive number of crane load cycles, can we take a blanket certificaion that it met 54.3 for TLAAs (example 0.341 )

>>> "Ellis, Douglas" <dellisl @entergy.com> 06/30/2006 1:44 PM >>>

Jim - as you requested, including cc:s. Doug Ellis, Pilgrim Licensing.

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Questions and Answers of Pilgrim LRA Aging Management Reviews Fri, Jun 30, 2006 1:44 PM "Ellis, Douglas" <dellis I @entergy.com>

dellis 1 @entergy.com Recipients nrc.gov OWGWPOO3.HQGWDO01 JAD (James Davis) nrc.gov TWGWPO02.HQGWDOO1 RXS2 (Ram Subbaratnam) entergy.com BFord CC (Bryan Ford) pillsburylaw.com david.lewis nrc.gov NRCWIAO1.NRCWDO01 "duh@nrc.gov"

James Davis - AMR - Report to the NRC.doc.pdf Page 1 I NRC LRA AMR Audit of PNPS Number Status Request 341 Accepted InTable 41-1 tithe IRAl theappicart dd rot ioerlity a crane load cycle limit as a TLAA for the cranes within the scops of license r at. Norrysly, based an the desigt code of the crane, a load cycle limit is specified at rated capacity over the cran"e's projected life. Theroate, tis generally necessary to pertorm aTLA* relating tocrans load cycles estimated to -CCcr up to the end ci the eraterced period f peration Plese explain why the crane load cycle limid was net included as a TLAA 342 Accepted InTale 43-1, MIlamum CUFsoforCa*assTICoxosents, note 2 addresses esclulscn rules for ASM Coda PResse eiplain what these ries are

Response

NRC PNPS Lead The license renewal ruet in 10 CFR 54.3, dciires a TLAA as a Paid, Erach Finnin, Ron licensee calculation or analysis that. among other things, invove tiroe-tirrited assumptions defined by the currert cprating tero For cranes, there is no celculation er analysis related to crane load cycles. In erditior, the number of cycles is NOT besed onthe current operating terms CMAA-70 specifies anallowatle stress range based onjoinr category an serviceclass. Service class is based onload class (mrent efective load lacoer) asd number di cycles. Th. projectled cycles for the PNPS rector building crane are well below any d the cycle rangese give in CMAA-70.

The discussicnonumn of itern 3a3.-t 11 Tale 3.at willbe clarified to read as follows "No PNPS calculation or wnlysis related tocumulative fatigue danage fhr sted cranes rod the definitice dt TLAA in 10 CFR 54.3. The projected cycles for the PNPS reactor building cn are well below the cycle ranges gien inoCMA-70. Sted cranes we evaluated as strutretal comporerts InsSection 3.S."

This requires ane srm-n*ent tothe IRA The tranients anthe RPV min steas, verd and instrumret cezzles Paed, Erach Firnin, Ron wre mild and stresses remain belcw the edurance limit. The origirat CE (Corobutitn Engineer ing) casel aoreysis derocostreas that the requirements ASME Section l1.1965 with sut er r

966 Addendc (Originsa Construction Code), Paragraph N-41t.1 Vessels Not Reqiring Analysis for CyclicOperation, were met. The was Ier corairmed to be the case in the Altran analysie.

A mistake esists inTa*le 4.3-1 i the LRA The recirslation oudlst nozle usage factcr does ort tre the criteria ot paragraph N-4151.

IRA Table 43-1 willoberecised toadd the roprqiate usage factor

,.r the recirculation otlat nozzle, Noate 2 will no longer be epqied to h reiculatien ontlet nozzle. Nte 2 will he reised to read as Iollows.

Ddtailed fatigue analysis is not retired since ccrrtenrl rheds the requiremoets ciASMC Section 111-t 9 witheurvnir 1966 Addenda (Ohrginal Construction Cede). Paragraph N-415t1 Vessels Not Requiring Analysis for Cyclictorsior.

ThN.retuiresanamocknrent tothe IRA Patee Of 77

James Davis-AMR-Report to the NRC.doc.pdf Page2 I Number Status Request 343 Accepted Section 4.3.1.3. Class I piping ard omnponets states all roaning RCS presasre noundary piping is designed and enstyzed in accordance with ANSI B31.1. However, in section 4,33, onpage 43-8, it inplies that faetige andysis exists for feadwater piping (which is part of the RCS pressure boundary piping designed and eralyzed lAW B31.1.).

Please clarify this discrepancy, ainme B31t1 does rn require a fatigue analysis oteriatior 344 Anaepted Section 4.3.1.3, Class I piping andon ponrlts seond paragraph states lst the design transients ae Iracked and esalswed to enswre that cycle tinits are not

exeeded, threrby assuring that CUFs do Nt scat 1.0. ft further staes that nontiation cd ltis pragram tteralone, will

-srse that the attoned srnba d trarsiart cycle5is AN-sceeded. Coweqraftly, the TLAA (fatigue aneyses) Io Class I piping and oenresls wilirewain valid for the pwicd of esteaded operation inaccortance with 10 CFR 54.2 1(c)(1)(i)or the cfets daging onlie inrerded funstilc(s) will beadequately noaged for the parelo ci adeslded operation inaccordance withl0CFR 5421(c)(i)(iii) This by itself aowld bea rue statetern, however, cycle cooting does not address the edaects d enironenrtal fatigue, which ia An inclded here, Aknowleaing that ection 4.33 addresses swironeswal fatigue, piease clarity hw that section is tied into the -o-liaon sae in section 43-1.a

Response

Section 43 1.3 cd the LRA is carect. PNPS has no site-specllit latigue artysls for the feedwater piping Section 4.3.3 dthe LRA is discussing the edaects cd the reactor coolant erviroenrnet on fatige Ertorgy will r-are the generic (NUREI-626D) oals for the ca spray saae cr4 the RR otlet nozzle and the feedwater piping Iroor Tasbe 4.3-3 There e no PNPS-specitic aralyses fir thom Iccations.

Sea AN, response Io Question 346A baon for the PNPS orrtrins for performing EAP (erwironnrrselly adjusted r

alige) analyses.

This reres anamenwrfent Iothe IRA PNPS willadd the fAollowing sentence atthe end oi Section 4,313-

• The effects of the reactor coolant ervirosrrert onfatigue are addressed inSection 4.3.3 of0the LRA The TLAA addressed by Section 43A1.3 is calculeion d1 CUFs withJoL acoorting ios the effects c reactor corlant

,ironmnot Ths TLAA rensns valid for the period cf steaded operation as long as the anslyzed rnber o trnsienos is Ant aceeded.

The catloation od CUFs accounting for the effects f ANs reator coolat errironrwent does nDI sist, asthe crrent licensing basis dose not repire consideratlofr enriror-a liiguie fators.

Since 10 CFR 543 dlfnes TLAAe as liconsee cauciwaions and an-dyses. there i*n N a TLAA that oonslers eswiroenrtsl fatigs factors.

To reoae the perceived inrlicet ion OhW1 sceeding At allowable intmer od transients world

-ause A CUFs to eaed 1.o the following chnges will betade to he LRA LRA Section 43. I, p*ge 4.3-4 will be rdified as follows: The PNPS FaPigue Koisitaing Program eoraes that the nmotes of transient cycles spereMared by the plans rerarn within the allowable nwters d cycles, atd ht e the conpoonet CUFs rennin baeon their analyzed valus LRA Section 4.31.3, Seo sentenr e dw the second peragraph will ie o*ned aw I.los:

wThe design trersias we tracked and ivaluated to ensue list cycle litits we rot mceeded, thereby asseing tlei CUFs remain batow "raen elyzed vsates.'

ThIsresporse reqlres anosrerret tothes FIA NRC Paetl, Erach Patd, Erash PNPS Lead Firrin, Ron Finsni Ron FPe 2d 77

James Davis - AMR - Report to the NRC.doc.pdf.

Page 3]

Number Status Request 345 Accepted Section 4.3.1.4, Feedwater Nozzle Fatigue states Oe this extrapolated wage factor for the Ioedwater nozlas, considering both the correrty anatyzed system design transients aid rapid cycling through the pernal a extamcfn operation, is nus <0.&99. Ths nrber is nra correct Pleasa explain how this nmber was calctiated 346 Open -

Section 433. Effects of Reactor Water Etironrmeot ao NRC Fotige Life.

Pleas procida wore taso your implemaneatiort plant

• A How will the firtlher relinertien of the fatigue eanysis be pedormed? ell W

t consider finite Sleword anlysas?

B If an agng mnrgamel program is medc please ir*lude

. eoritment toissue for NRCq*proal 24tmorthe prior bo earing penald fextended operaion.

C. Wit replacement bed the same material type?

347 Accepted Tade 4.3-3. Note t sates "No PNPS-specific value was ailate; ased generic valon fron NUREG/CR-620."

& Wrong NUREG identified -aheud ithe NUREQ-62E0?

b. The NUREG-eM CUFis based onthe specific plant used inthat NUREGad Issdepondeit onthat plairs piping corfiguatlir Thea valus carrot benead for PNPS catctationa Please justify how the va]- applies to PNPS a1e"s the PNPS piping rfigor ations ore sarn as the NUREG-6260 pla or rpovide aPNPS specific CUFvals

Response

NRC The Therma Power Optimizatiat Task Report T0302 updated the Patel, Erach feedwater nozzle CUF to, 10 based onthe a*sociated (1t5%) power uprate. The ectrapodation in LRA section 43.1.4 is thu no lorger valid PNPS willsomlify the LRAtodelete this etrapolatiort PNPS willperform anew feidiater

-nozlefatigue analysis prior tofhe period ot eatend opedat.ior Ttis aomritment is Htan 35oa ohn PNPS comritoents for license renewal.

Tife rewhres anamerdment lothe LRA A Further ratirnerat a the ASfE Class I fatigue aratysis hor the Patd, Erach RPV and noule location willbeperformed cornsidering the preacted snober ot traneienrs at ech location sclustnd tothe and afthe extended license period mUing relined fihite Slernet waltstiat as applicable The retined alalysis will tiscorul for anironnenal effacts as applic able using the FEN methodclota described by the GALL report or other industry Codes and Standards as approed by NRC.

B License rnewe Coaietttnmet 31 includes a oea maitmeot to subwnit the aging management program to the NRC 24 moathe prior a lthe period of eateaded operation ifthe aging neragesnare program option la clsern C. Appropriate replac*menl maerial willbesalected inaccodrarne with PNPS deign cuo proedres, if rqplacerne-is achosen option.

AYe., this is a typo, at ahtld be NUREG-6B0a Pate, Erach B. The CUIvalms from NUREG-6260 were irtwsted as typicat values teed to predict the magitude f fthe effect of corsidering the reactor coald earsiroarnere onfatigoe fhe PNPS. PNPS will amead the LRA to rerrae the CUFs Irom Tasle 43-3 that ra taken fran NUREG-620.

Sex Iter 346 fhe PNPSa cammtseif to peraorm addition erironras l y emuated feigd e analyses prior tothe period of extended operationr The nrespn retumreeanrensdnene tolhe LRA PNPS Lead Finrin, Ron Finain, Ron Frnirkn Ron PFb 3od 77

James Davis - AMR - Report to the NRC.doc.pdf Page 4 Number Status Request 349 Closed 13.4.1-W-01]

In renerus line items inTahies 34.2-Z 3.2-4-3, 9.10, It. 17and 18Aof sh Steam and Poer Conlversion System.

Ith Wppicant credits TLAA - Met Fatigue tomn fl e Ith aging effect f metal fatigue (ctmusative latligue datoage),

and ijnedies that the ealuation dais TLAA is addressed inSection 4.30the LRA However, it appears that the wrile-p of the Section 43 does not cover the discusion for nost onmpnns Please Mplein Ane discrepancy.

350 Accepted

[3.4.14-W-02 Section 3.4.2.22 (1)nifth LRA(page a4-4), the applinean stales:

o*nsed rmaeriel du to general, pitting and neavice norresinl for carbon sted piping, piping nomponents, aid tanks, sposed otreteed water and for mon steld piping and noponeree exposed tnsteean is an aging effect reiuiring nm gament in th stearn and power nneenieinn systems a[ PNPS. and is managed by the Water Chemistry Contrd -BWR and Periodic Surveillance and Preventive IMlniemn-e (PSPIA Programs."

Pleese clarify the above emmay,. regarding Ans use to PSPM progran Is th e

u t PSPM program in in lieu Athe OTI prngrar to verity the effectivesnens of tw Water Chemistry Contrd -BWR pregr-n or so-othe AEM nmbiretnlonn willber anaged by sing PSPM alon 351 Closed

[3.4.1 -W-031 WlV is OTI program no creilted for those line Items in Tabes 3.42-x and Tabe 332-14-x (norresponding In VIItE.-3, condenssate system VIII.C-B. estraction steen, sytemye VII.D2-7. feeinln system and VIq0B2-6. rrdn telan systet) 9ati reference it-n 41-4?

Response

NRC PNPS Lead Usting TLAA -metal fatigue inthe tables in Section 3 endicatee We, Peter Finnn, Rn fthl ft condltions for ftigas were present and that they nedd to be evluated.

Associated oneponarns were suboequenly evatluated in LRPi-,

TLAA - Motad Fatigue If the evaluation found no, TLAA i was not listed in Section 4d Asf LRA For olarifinatione Entergy will revisethe Section 3tables to reImve the TLAAM

-notlfatigu entries whenever there was no essociated TLAA discussed in Section 4 d the LIRA The Itn is dlosed toiten 5(36 Tim section n

.4.222 (1) lirther oevaluatio discussion is rioerenced Wen, Peter

UrnrdtHl, byTable 3.4.1 ite 3.41-2 34.1-4 aid 3.4.1-6. Th. discussion ceoumn entry of item, 3.41-6 indioales tht the PSPM program applies toth nordeleste sto*'es ateA. Althog the water in lhese tarej would besbiect tothe water chnistry controls -BWR program, the PSPM peogram is sufficient to manage loss d material no was th only program credted fIr these brite. See At response ltoquetion 3.4.1-5 (ite #3053) which dnuents that the Water Chemistry Control - BWR pengram should h1we been credited along with As PSPM program for t condednsate storage rks, Tas requires a saippgenlwarne ndment to the IRA Since At One-Time Inspecion (OTI) Proegram is appicaee to eadh Wet Pot.

FPeew

ger, water nhemistry controd program, it is also applicable to ench line iteo that credits a water Chemistr y corntol proeparn IRA Tabe 3.4.1 Indicates that Ahs One-Time Inspection Program Is credited along with Ore water oristry ontrol programs lot line items for winch GAL mecosmends acnne-limo inspentim to connirm wate chaeistry control. Table 2credlt As OTI program ihroun reference tothe associated Table I line itenn THIs reaqres antamendment to the chtmistry program descriptions in iRA Appendices A and 8 to clearly indicate that t1e Oe-Time Inspection Program willnoreirm As MlnWi-enss f Athe Mtie Chemistry Coneroe-BWR, oter Chemistry Control-Auoiliary Systems and the Water Chenaistry Control-Closed Coating Water proegrams.

ThIs itm is closed to,e, 372.

1M 4d 77

James Davis.- AMR - Report to the NRC.doc.pdf Page 5 Number Status Request 362 Closed 134.1-W-041 Wht is OTI program at crediled far those line items in Table 33.2-14-x (cosrespone5 ng to VIILE-7, heal echanger corponents incorndensate system) that reference iten 341-5W 353 Closed 13.4.1-W-C The appiicant rederences GALL item VIII.-40 (sted tank in condereate system) for the ondensate storage cysten wahbon sted tark, as listed in LRA Tabte 34.2-1. (page 34-28), bLA takes credit of PSPM to manege the aging affect d ossed maerial. The GALL recommends uwing -Water Chemistry" and c

OTF programs for he aoosnponaer and AEM ornitinatiwn. Altheadh the PSPM as described in PNPS ERA B1.24, has more stringeon inspection rwreeWr than OTI, it ýl rot mincluds orrolling wate shemistry to mnirmize cepnen exposure toaggreseesine nironmwt.

Pleass ta*rain why relying on PSPM alone is sufflcieit for emeeing the GALL's recomndrtions o manage Ste eaging effect e 0oss of material for the condensate storage systen webon Msto tafr The carbon stMd lark listed inTable 32-14-,Q feedwater aystee (Page3a3-171) arnd Table33.2-14-11, feedwster feeter drainlm cd vents ynteer (page 33-178), ade r..ofste GALL heem VIII.E-40. Why is OTI prowam re credited for these line itemn that reference it-e 3.41-6.

Response

NRC Sime the One-Time Inspection (OTI) Programn is aplicable to each Won, Pelor water chernistry cotrol program, itisalso applicable toesch line item thet credits a water chnistry control progra.n ERA Table 341 indicates t the One-Time Inspection Program is credited ordsng with the watetschanistry control programs for lineitems for which GALL reeommereds acore-frne inspection t confirm water chemistry conorol. Table 2credts the OTI program through reference tow associated Table I line iteem This requirce ancendestlesr tothe sheerstry program descriptions in ERA Appedices A and B to clesrly indcate that the One-Time Inspection Program willortirmn the effectiveness of the Water Chesistry Coatror-BWF, Watsr Chemistry Coalrol-t*wiliary Systems and the Water Chemistry Conrol-Closed Ceoling Wter programs.

This itent is elsed to Iten 372.

Since the cordensate storage tork cortalns flud thOt ins toect 1o Wen, Pete the controls 0 the Watet Chenistry Conrol - BMR Program, the program applies tothe tark The LRAwill bealaritied toI plisitly credit the Water Chemistry Cordtl - BVW Program inaddition to PSPM with man ing the edfects of agi he for the oosdesrate storage tank surface sepoeeed to the treated water erwiroroerd.

Sines the One-Time Inspection (OTI) Progam is applicable to eech water chemistry eaotrol programn, it in also applicabe to each line leer that credits a water eheristry control program As slated in LRA T*e 3a4.1. the One-Timn Inspection Program is crdited to weriy edfetivens of the0 water chemistry control program for line items Sha rteresce hten 341-8.

This reqyiren anamendmeri tothe chemistry program dlescripions in LRA Appendices A and B to dearly indicatee thl the One-Time Inspection Program will carlirm the effectieness of the Water Chemistry Cortrol-BAR, Water Cheen istryCorlrel-Auxiliary Systems and Otw Wator Cherndstry Cordtol-Closed Coding Wate programs.

This item is closeed to itO 372 PNPS Lead Fronebarger, Orlicek, Jack PA 5cd 77

James Davis - AMR - Report to the NRC.doc.pdf Page 6 I Number Status Request 384 Closed

[3.4.1-W-06]

Wly is OTI program no creadted for these line iters in Table 3.3.2-14-35 (correspordng toVIIA-14) that reference it-e 3.4t-7?

Response

During the performarne o routirn rrmintnance oncorrponents that cortain lutricating oil, visual inspecliois oi these corponerts would identify degraded conditions that coUkd bealtribied toew ineolective Oil Analyais Program The corrective action program at PNPS has a low threshold for the iderlification of degraded oo*dltions such that corrosion or cractdng of conponerts would be identified as pert of the program The review of operating eperiene at PNPS for the lest live years did not idertiy any oordKtios raerts that irdicated an isnetective oil analysis program or that idereiied degraded.,on t c itions such a corrosion or cracking Ina lubricating oil enviromrns.

This review oi operating eapewnce ad PNPS serves in lieu o a one-time irepection to provide onfirmr neato of te efteotiosreso the Oil Analysis Program During "" pest iv yeyas, snay visual irepections of corqorrats containing lubricatig oil hae been peformed during corrective ant preventive smantenance activities. The visual irepections of tIese ceelororts would kiaelify degraded orditione such as corrosion or cracking tfat could bheettibded tow inefftctive Oil Aleysis Program PNPS has a In threshod for the identification of degraded cordilior. such that corresion or cracking of coepones would be ideritified ard entered into the corrective action program Nocoroition reports thei kderlt 8ed degraded oenpornnt coritiorle, such as corrosion or cracking in a lutricating oil envirornnt, were Ihitiated as a result f these inspectione. These past inspecliore a PNPS serve in lies cie one-time irspeclion to provide cortirnnalon of the eOfective'ss of the Oil Analysis Progran This iter is doserd to itw 376.

Since the One-Tires Inspection (OTI)Program is applicable toeach water oheriatry cotroi program it is also applicable to each line itern that credits a water chesnistry controi program LRA Table 34.1 irna*tes that the One-Time inspection Program is crecited Song with the water cheistry cnntroi prograrne or ftie itees for whichGALL reomesrnds cone-lime ilspection tocorfirm water chehnistry corlro. Teabe 2 orerits the OTIprogeam thrroo relerenc to the easocniated Taibe I line item.

ThN reqrdrem namr toent tothe ch-icstry program descriptiora inLRA Aiperoices A ard Bto clearly irdcate the the One-Time Inspection Programt will cornirm the eftectiwerses of the Water Chaeristry Conroi-BWR. Water Chem eatry Coriref-Auxiliary Syslpee and the Water ChaInstry Control-Cloned Cooling Water progrart.

This item to closed o Ite 3M NRC PNPS Lead Wen, Peter Frorobarger, 355 Cloed

[3.4.r.1-W--o Why is OTI program not crelted for thoet line Horns in Table 3.22-4. HPCt Systerm, (page 3.2-49) and Table 322-5a RCIC Systew, (pege 3.2-62) (correspcrdng to VlII.E-tO) thV reference item 3.41-97?

Wen, Peter Fronebarger, PA 6d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 71 Number Status Request 356 Cloned 1341-W-08]

wV is OTI program not cradSled for those line iterr in T'bee 3.32-5. Station Blackocu Dieeo. (page 33-90) and Tabe 3.32-6, Security Diesel Generator System, (page 3.3-102) (corresponling toVIII.G-15) that referenne ism 34.1-10?

357 Closed

[3.41-W-091 VMty, i[ OTI program not credited tor those line Itmne in Table 34.2-Z Main Condaener and MSIrV Ialge Ptheway, Tabe 332-14.9, E-actiton Stnw System. Table 332-14-161 HPCI, Teale 3.32-14-18, Main Stem System ard Table 3.32-14-19, O0fg.e ac-d AWrwted OGag.c System that rdw-e--

iten 34.1-13?

Response

DOing the peormnere Oroutine mnirtenance on confoonrts thc-nerlain [luricaitng oil, visual inspections oethnee oponTentM would Idenify degraded onditions that could beattributed town ineffective Oil Analysis Program The corrective action proogram at PNPS has alow threshold for the identificatinm of degraded corditions such that corrosion or cracking of oarpneele would be identified as part of tis program The review of operating experie-ne at PNPS for the last live years did not idertity any ncni-tion reports thai irdicated an inlfeclive al analysis program or fInal identified degraded oornpown I corptions such as ooroiejon or cracking in. lubricating oi eMir'o Ths viewo of operating apepriene at PNPS serves in lieu of. ore-time inspection to provide coneirnation of tie effectiveness of the Oil Aleysis Prog-ram DOwing the pest fiv years, ony visunl inspections of components ooaieiang lubricating oil hane been performed during correctite c-td prevenlive, rneintanoe activities. The visual inspectione of these nncmponents would identify degraded Cc-nitonlesch as oorreon Oa cracking Set harid beattributed ton Infelfftive Oi Analysis Program PNPS has alow tireshold for the identification of degraded conditions ucwh the corroesni or cracking of Monanorert would beidenified and entered into the corrective actinn pogro s Nonondition reports tha idel Sfied degraded cornonent codtlor, scCh as oorrocion or cracking in a lubricaeing oil envirorrinan, were Initilted as a result o See irnspections. These pest inepections at PNPS serve in lieu of a onee-tine inspection to provide cnfirmnstion of the aefectiveness of the Oil Aralysis Program.

Thi iten i. cosed to Ien 376.

Since the Ore-Tire Inspection (OTI) Program is appRitable to ench wSter chercistry control prograe it is also applicable to each line bten thet credits awater cheristry cor-roa programn IRA Taebe 331 irdicates thi the O0c-Tine Inspection Program Is credited along with the water chernistry conreol prograen fto line items tor which GALL recncene s a one-time inspection to oomitrm water chOnistry contrd. Table 2 credits tie OTI program trougli roference tothe assooiated Table I line Item, The requires anenrndrenr tothe ohrnietry progc-rc descritiorn in IRA Apperdices A and B to clearly indIcatet that the One-Time trpection Program will confirm te effectiveness of the Wter Chenistry Control-BWR, Water Chen istry Control-Auxiliery Systemns a the Waler Cheniesty Control-Closed Cooling Water prograrne.

TtNa it-1. odeo*ed to it*e 737 NRC Wen, Pete-Wean Peter PNPS Lead Fro-barger.

Froreharger, Ag 7d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 8 1 Number Status Request 35B Closed 3.41 -W-10l Since notes Ward "C'wae used invarious Tone 332 line items, which rederere item 3,4,1-14, why OTI program is not crealed for tlose lines?

359 Closed

[3.4.1-W-11l Sine note -C-was wsed In TaNe 3.3.2-14-4 Cone atee Denineraljzer Systm line items, which relerence ltem 341-15, why OTI program is not credited Ito those liree?

Response

NRC Since the One-Timnt Insestion (OTI) Program is qaplicable to erh War% Peer water chermsley sorol program it is also applicalie to ech line itew that creits awater chernistry control program

.RA Table 331 irdoates Ihat the Gne-Time Inspection Progaom is crested along with the waler chemistry control prograrm Ior line itels bor which GALL recoomernds aone-Utrle inspection to cotirm waler chemistry cotrd. Table 2 credts tre OTI program through relerane tothe asesciated Table I line item.

This requiree wanerdmeolt Join chemistry program dscriptiors in LRA Apperdos A aid B to clarly indicate that the One-Time Impection Program willoordirm the elfectivenses of the Water Cheeistry Coddrol - BWR, Worer Chelstry Control - Ausiliary Systems ad the Water Cheristry Coderol -Closed Cooling Waler prograns.

This itern is osled to lte 372 Sire the One-Time Inspection (OTI) Progern is applicable toech Waen Peter water cheristry sortroe program it is also applicable to eech line eem that credits a water chemistry control program LRA Table 331 irdicates that the One-Time Inepection Program is craedled along with the water chelnistry control prog*an for i items lor which GALL recosendst a ons-lim inpectlion toconfirm water chemistry conrol. Table 2 crecAitw OTI program through relererce toothe associated Table I line item Thisrequirees nerrs rdmes tothe chmistry program descriptions in IRA Appeedioes A ard Bto clearly idicate that the One-Time Inspection Program willoortirm the eWolttioerees of the Waler Chemistry Coerol - BW, Water Chenmistry Control - Auxiliary Systems and the Water Chemistry Control - Closed Cooling Water programs This item

d.

closed to Item 372 PNPS Lead Fronabarger, Fronabarger, P

Bd 77

James Davis - AMR,- Report to the NRC.doc.pdf

'Page 9 Number Status Request 3

C0 closed 13.4.1-W-12j Since hote. A'nd "Cwere. used inTable 3.4.2-14, Condensate Sarage System and various Table 3.32-14-x lie iteas which reference iten 34t1-16, why OTI program Is not credited r those lines?

Wt Closed 3.41-W-13 Why is OTI program nrt credited for those ine items in Table 3.42-4-35, Turbnne Gaenrate, ael Awiliary System (correspording toVItIA-3) tSet reference iten 34.1-18?

Response

NRC Sime the One-Time Impection (OTI) Program is applicable to each Wear Peter water chemistry conrol prograrn, it is riso applicatle to each line itern that credits a water chenistry osol

progres, LRA Tabl 13.1 irdsiates fhat the Or-Time Inspection Prograe is credted along with the water cherrdstry control programs for lei items lot which GALL recommend a mm-tine inspection toconirm water chemstry sontrod. Table 2 credts the OTI program lhraoag ref-eme lothe associated Taele I tine ite*r This requires anesmend n to the chemristry prrgram descriptions in LRA Appendices Aard Bto cetrly irdicate thet the Ore-Time Itspection Program willottlirm tSh effectivenee oa the Water Cheristry Contral - BWM. Water Chemistry Carlrdl -Auxiliary Systems atd the Water Cheristry Control - Closed Co*nrr Water programs.

This item Is clded o Item 372 During the performance darotire mneirtan ce onca paenta thal Wear Peter contadn libricating oil, disul inspections d thiee eomponents wmad idenaily degraded aerditions that soad be attitried toan inrefective Oi Analysis Pragrane The -r-reei-e action progr*m a PNPS has asm threshold for me Idenlification dodegraded ooaditire suh that c-roseorr m cracking at sampt-ra s womad be Identified -

part d

.th progran, The reviw atopwerfing rpeoniece ad PNPS for the last hive years did not idernify aer ooncition reports ihat indcated an i nsiefctive oil analysis program or that identified degraded aooponen t conditions such as corrosion or meacking in alubricating ol envirorentm This resiem loperaing raperience a PNPS semres in lieu aea mre-time ispection to prowide onufirmation at the eflectivenres at the Oil Analysis Program DOring the Pest five ye"s. many viLead Inpectione af caponenta orteihing IUbricaing dl have been perormaed dering oorreehiveand prenervaie r*nt-t--m*e activities. Tne visua irepections oa thse comrpoents wolad Identify degraded rondtions such as otrroeion e cracking that sooad beaeltibUded toe ineffective Oil Arlysis Prog-ern PNPS has alow threshold for She identification of degraded omndtitn such that corrosion Wm cracking at aononerts would besidenified and enmed into the aorracsive aclion program.

Noaondition reports that Identified degraded aomporae aorditions, such as corrosion or cracking in a lubricating dl emwifrarenrt, were iritialed as a result ad these Inspections. These pest inspections aS PNPS sarve in lies oata er-line irmaration to proside rondirmation of the efectiveness of the CiI Analysis Program Th. item is closed t Item 376.

PNPS Lead Fro-rsbarger, Fronaheger, ROD 9d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 10 Number Status Request

Response

NRC PNPS Lead 362 Clsead

[34 1-W-14t During the petorrrrnce of rortine maireensnre osvomponerts Ps Wen, Peter Frorabarger, oortain lubricating oil, visual inspections of these ocmorerts Wht is OTI program not oreaitear tor those line iters in would identify degraded conrtion that Codd be antribded to an Table 3.42-14-35, Turbine Generator ard Aeiliary System inrlfective Oti Analysis Program The corrective action progrars at (correspording toVIII.A-9 ard Ntl G-3 ) the reference dien PNPS has a loa threshold (or the idenification oa degraded 3.41-191?

orditiona such thae corrosion or cracking o

f owpcreres world be identified as part f tls program The rwis of operating epesnece rl PNPS for Ite last five years did rot idertity any condition reports the indiated an inerfective oil analysis program or tist dertitie degraded corrpcn t corotrtions such as corrosion or sracking in a lubricating oil evirornntor Ttis rsier of cperating esoeriece at PNPS serves in lieu cia ones-tires inspection to provide eoriirmesion of the eftectiveness of the Oil Anlysis Program During the past Wisa years, smrsy visual inspectioes of cormprents containing tltricatirg oil have bean pertormed during corrective and preventive instenarce activities. The visaud inspectises of thise comrporents would identity degraded conditions such as eorrcjion or cracking ha could beattributed toes irefltective Oil Anelysis Program PNPS -as a low twheshod for the identification of degraded cordtiors such thlit orrosion or cracking of rorponerns would heidentified ard sntered into the corrective action program Noooctliton reports tiOW idert ified degraded coorpnat cornitiors, such as corrosion or cracking in a abricating oil envirormeart, were irlitiaed ace result of thse inspections. These past inspections at PNPS serve inslie of a ones-time inspection to preside confirmation of the efectiveress ofthe Oi Analysis Program Tia iteir inclosed totter 37r, AW SVd 77

James Davis - AMR - Report to the NRC.doc.pdf Page 11jj Number Status 363 Open-NRC Request 13.4.1-W-15]

Teea 3.4.1, itar 34.1-20 for sled tanks nqrosed oair -

ouldor. PNPS uoes the Sysem Walkdown Program to manage the agong Sool of loss of atemrial due to general, pittito and crvice oorr-sion through the use of periodic viesaI inrpectios. The GALL Report rawnesorrno the AMP of Aboveground Steel Tanks Program (GALL )a. W9) tobe red While the System Walkidown Program may bean acceptatle atefrrate for.ouseground Sledl Tarks AMP for inspeclior% the Aboveground Sted Taoks AM' has some program aftribotes not addressed in"tn System Wslkdown Program For exaropies, the System Walkdown Program is silent oft. preverive actions, bul the Abovegrourd Sledl Tatks AM inclrdes prwe aive measures to iligale corrosion by protesting the etrenal surface of sted fatks wfithppainl or oalirngs aacortdance with alnodad idstry practioe Please explain how the prevent lse actiones a doetectio of aging eStts at inacceessible locatios euch as ft* tark bottom surface willibperomesd for the subject tanks using the System Walkdown AtoP.

Response

NRC PNPS Lead Preventive Actions:

Wen Peter Fort4 Bryan Protective coatings were applied dlur ing fatrication or installation of the subject tanks well before dedopmerti of aging mnagemsret programs (or license renreal The System Walkdown Program enstais visual iropeotions of stornad surfaces of oarbon sted talas to ientlfy degradation of coatings, sealants, and caulking plus indicationa of leakage. The site oorrective actie process would require evaluation and repair, f necessry, ofdegfadedf ioslng.

oroaulking Detertion of Aging Efforts:

The conroenste storage tatk is a non-safely related carbon steel fatk that ortlains treted water. The tatn sits onca ororte pad with a saed atd oil base cushion that is designed to remove moisture froee the botsom of the tank tomririozo the potential for corrosioro The Internales of the tank wich are stboeted to contriuous welling ore perioicea yirpomafcted boe corrosion and pittiog iroliUing inaccessible areas (under water) as documenred in site procedure NE8t.0_ Thssa trn procedure also inspects sterir caulking at the aese of the tank focraoking inorder to prevent water acoumulation unda the.tsar This procedure is creted n thef Periodc Surveillanre ard Prevenrive Kalt erarce program sortion 417 and of LRPD-02 for managemrnt of the toednal and internal smoace of this fant A

ny degradaf on of the inrernals of the tark will result Ina condition report and anevaluatisn of the sltend of the oordortio which ma involve ultrasonic erainatien todeoernine remaining thickness.

Because the asiroonss inside te tatk is significantly hanrher than the eirolrernrw onsthe undrrside of the, tank, ioteral degradatfon would be expecteff eg balore corrosion sthe outside, ft degradation occurs o the inside (including the bott-o),

scanrnatiios of the degradedl areas would require ad aermnatin of the reraming wadl thicknes wih ensures the iotegrity of the tank is maintained However, toemnure that significntr degradation onthe bortom ofthe tatk is not occurring PNPS oosmrits topeark rwaorne-tima ultrasonic fickneers sarninalion inaoessifle aoreas onthe bottom of GA eordensale storage fort prior to the period of eltended operation. Standard eanisnation and sarmping techniques will be utilized This is comritmrnt nustor 36 This requires ansao nrr srt tothe LRA AV 11id 77

James Davis - AMR - Report to the NRC.doc.pdf Page 121 Number Status Request 364 Closed 13.4.1-W-161 Table 34.1, ter 34.1-2Z, for sled bolling and closure boiting er-posol to air with stean or water leakageh

, ai-ouldcor (ed-rerl), or ar - ndoor unoontrloled (external). The roph.ars retererss GALL items VIII.H-l and H-4 W the closure Wtting in sarious Steers and Power Corsersion Systos, aslisted insIRA Table 342-1 and 3.3.2-14x, Wt takes oredt for the System Whkdown Program to mwerge the aong effect ot toss at reriat The GALL Report rncomoerds AMP XIMIS, Botling Itegrity Prograo, which includes aoormprhenive bolting integrity progra, a

detineated inNUREG-t133, and irsistry reromrrdaliore,

.s detneetld inthe EPRI report NP-5769. Ptesse justify how the ackitinorl attributes listed inGALL AMP XIMt8 for aong trnge'nent f sclosure btoing we addressed int".

System WItkdo-n Progoam,

Response

NRC ABolting Integrity Program witlhetdeeoped that willaddreos tie Wen, Peter agng rregemnr at botting intle scope of liceoso rerewoo The toiting toegrity Progam willhe irrplemerred pror tothe period of seroded operation inacrordanco withcommotmenrt ruae 32 This reuiyrea anso adhrot totthe LRA to incude descriptiorns d the Bolting Irlegrity Program inApperndice Aand Bard to idenrtity where the program is applicable This item is closed to Item 373.

PNPS Lead Frorehargar, Ap 12d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 13 Number Status 65 Open-NRC Request 136.22-N-01 I In LRATable 3.6.2-undaer Cable connections (metallic panrs), you have stated that no agng effects and roMP is reouired NUREG-18tt, Revision 1, AM X(.E6, *Betrical Cable Connection nd Stbject to 10 CFR 5049 Ermiro rnmeaI ucaliiaion Reqgirewres,* specifies that onrtectiore easociated with cables within the scope of license renewal we part of ths prog'am, reardless of their associated with active Or passive ccrrponerts.

Aso, raer to pages107, 256, end 257 of NURE3-1833, *Technical Bases to, Revision to the Ucense Recewal Guidance Donaumntso, for eddtltrl irfornehion regarding AM Xl.E6, Provide a basis dtomev inctletdid anWAM with the ten der*Ist r h able

-9nectirs or pokido ejustiticatior for why aMP isnar necessary.

Response

The PNPS electrical AM*. AMRE-01, in section 3.41 states for cable corrections (redallic parts), "An ealuatihon of thwerm cycling, ohnic heatirg, electrical traensierts, vibration, chemical octamietiocr\\ corrosion, and oxidation stressors to, the metallic parts f dectrical cable conectiores tiet1ified noagcng effcts reqoiring rnawagawt.

- Metallic parts of electrical cable connectione potentially spoased to thermal cycling ars ohmic hesti ng oe those carrying signiticant current inpower supply cirouits. Typically, power cables ore ina orlinuots run from the atupqy to the load Therefore, the connrections are part of an active cnrtmpor and not Sutltect to aging vrgwerrt resion.

• The fast acton of circUit praective devicas at hlgh currents nitigtes stresses associated with electrical faits and trnienis, Inaddition mechanocal stress associated with electrical faits ais not acredible aging mechrianm because at the Iow frequoncry at occurrence for such fatits. Thorelore. electrical transrei.

ore t aoplicable streesors.

• Metallie parts at electrical.Weconrctions exposed ton1-r11ion we three associated with active compones he cauee vibration Be3-se they we part di an active coortceri, they are rot asteact to aging mretgerert reaieo.

• Corrosivenchmicats wre rat stored inmost maas of the plant.

Rot*ieo releases ofcorroeive behelcals to areas inside plant bulainge do no, oct during plant operation, Such a release, asd its ffects. wood be an aes, not aaffect of arng In ebdfioi, ther location intsde active comt ponents protacts te rmtalli parts of electrical able eona tions from contaminationr Therorae, this strassor i na applicable SOCxidslfon and oorroason ueeulty =ccnr inthe presence o tmosture or outaminrion sech as irndtrial poltutancs and salt deposits Enclosures or splice mte-rials protect mstal consnctions front rolatute or contmaetion.

Stnre bhated oonnections we considered part of as active device matd e martained by te plant Itrtnawn RLe prog*arm, there we oaging effecte repuiring mriagemen to, bolted connectons of cable systems. Since PNPS meisiaens cable connections urder a ctrrarl mairntenaoe progrsn and has no Indication of an aging rethanist due to loose contectiors, no AiP is needed in addition tothe Nlaintenanse Rule program.

NRC PNPS Lead Ngyent O.

Stroud, Mike Paw 13d 17

James Davis - AMR - Report to the NRC.doc.pdf Page 14 Number Status Request 366 AoeptWd 13622-N-021 In LRA Tabe 3.6 2-1 undwr tigh voltage instiator (SBO), you have stated that no agg*n efifts snd no ArP is required Yea fut statedl, in Section 3.6.222 oftha LRA&

that PNPS is located nar th seacoast where salt spray is coreideared c

However, salt spray buildup is a shrt-term cencern bsse colcal weather conditions (eart driven).

Thereire, you have concluded that slface cortarirstion is not wapplicabte aging techis low high voltage irsators at PNPS.

NUREG 1IB, Rev. I, Standard Review Plan is Reaiew o Ucense Rercal Application for Nuclear Power Pant.

Sectia 3.6222 idertitisd dgradation of high voltage itsulatcr in prw se of salt deposits or surac ctanirsicrv Varins airbeorne mterias salh a dust, salt and irvutrial ifftluer c= can rnisal irsjatfo s.rea.e

.Arger uloildup ontamination anailes the c.oducttr voltage to track along the Islsace more easily and can lead to imlator flash as" Surface a

onarinration can bipridles i nMeass whser thene aregreater conceration of airborne Isticles s*ch as ne acilities that discharge so er new sea cast where salt spray is prevaalrt Irsstly operating sperieance identified the potsetial of loss of offisite power du to salt deposition toswitohyard irsuators.

On March 17, 199, Crystal RiverUnit 3ltparisnced alons of the 23 kV switctyard (normal offsits Power to saley-rlata d bsss) when a light rain caused arcirg acroes salt-taden 230 kV insators and opened breakers inswitchysrd. In Mauch 1199, the Brunaswick Unit 2switclyard aperienced a flash overofsamn ligh-vnctage insulators. The incident was ataitbod toa winter storm inthe arm Srn.e 19tZ Pilgrim station has aeso eperiened several loe of offiten power everts when ocean storm deposited salt onets 345 kV eswitcyard ca~sing the inslator to wn to gtsas In light of tas windutry and plars operat irg esperiences, provide jstitcation co owhy anA' is nt necessary.

Response

As shown by 'he CE (Operating periernce) vied in mis question, fiash-oar due to sall cortoiallno n of insrlators is caused by eaents, typically stormns, regardless of five a.

ci the insuators.

This is nlearly no an einftc of aging Therore, surface octaminaition is not an app licaboe agng mechanism for hil'-voltage inslators at PNPS. Since the condition is caued by severe weather eoditions 1rM ated toagirK, anag ag n smrnaent program isnot appropriate to addreass this cocern Howeve, whle salt spray iLilduip is a short-ter convern based on local weather cordfir (wes--&vw), swl bui can cause problers wilh thi disite power eupply system Because of this operating aperiece, PNPS has applied Sylgtrd (RTV sili.oe) coding. toso-s saitcyard inuLdators to redce flashover. The addilion of Sylgard to n insueltors has reduced the likelihood of insUator flasirser.

Systeat walkodnrs we perormed at least once per refueling cycle and Me normally performed more fraequntly to do a visual insyection of the switychard higih-tagv Insulatats thst ae i-sope of lices rerswal inacood e with EN-DC-178. Thew walidowns willcontinne too pertormed into the period of exended operattion LRPPD-02 will be evsed as follows:

Toe System Walkdown Program will be revised to icludethe nvisual inspection of high-votage imulato Is in-i-oqe of license rerswao.

NRC PNPS Lead Nyen, Duc Stroud, Mke Pge4d4 77

James Davis - AMR - Report to the NRC.doc.pdf Page 15 Number Status Request 367 Cloed 13,6.22-N-03 In LRA, Table 3.6.2-1. under switclyard bua and cornectiors, you hava stated that no agng effects reqiiring rawgewt and no=A is required NUREG 1800, Rev. 1, Stanrdad Review Plan t Review Of Livers. Renewal Applicatie for Nuclea Power Rant, Section 3.ZZ3 idletifes loss of preeoad is an aging effect for switchyard hs oraoectiona. Torque relaxalion for boted connection is a ooncern for switchyard bus connectiora and transrission ceadutor correcliors. An dectrical sonnactin must be designad to rertan fig" and eairtain good conductivity tlrougoh a large teperature rangte. Meeting this design recArevesi is difficult ilts material specified for the bolt and the ccductor re different and have differer raiese of thnerrf erxpansion For arnler copper or alurinua

,oaooehortor materiels expond faster than fmast boifing materials. If thtrmel stress is idded to stresses inherert at

..ssarly. the joint netrtabs ortastarors eva yiald Nf plastic dlutretion

-o.ore during thmeal loading (i.e..

haetup) when the conrtetion cds, the joiat will be loose.

EPRI dourntrt TR-104213, 'Boted Joint MrenaW*-e &

Application Guide" recornaends inspetior of bolted joints for evidene ed ooerheatingr signs of burring or discoloration and indicationf Iooe boeds Provide a discsasiot, for why torque relhiation for bolted connectio-of switchyard bus is boe otaoe-hor PNPS.

368 Closed 13.6.22-N-041 In IRA, Sectiont 16.223, you hIe-stated that PNPS does tat utilize tranarission codurrto r. is the ciwuits hoe r-awry of Offlite powera foltowvingan SB.

Desoribe SBO rewey pathl for PNPS. Cornirm that notrarswmissat conductors are utilized ine"e iaLits for raccoery paths.

Support lime answers with a e sin one linediagrarr

Response

At PNPS, bus tohbus connections are welded instead of bolted Swiltchyard buses oe saortected by ftiible connectors to itlsators and active comoponents. Since switchyard bus is typically ornder a constant lod, thernal cyclingthat CouLd cause torque relaxahib is irfrernt. Vith rorolhirs tovibrating eqiparnt, vibation is ot awaging tucharlwsm for switchyard buss The switchyard oonnections tothe slartkp transforser are part of ke active assembly mnaintained by the poant aeirtarnce prngraie Therefore tanya relaxatiom isnot anagng offects requiringrmanagamen for switchyard bus.

NRC PNPS Lead Nguye, Oc Stroud, Mks Ineddition, flerm-gaphy is perform ad at least once aery 6nrnthe to trilsen the iregrity of t he connections This progra will continue into the period of rtteoded operation.

The preferred -rce of Oftfit. power

-or I the 345kV Nguyen, D.n Strod, Wike waituhyard The tead ftea the switchyard beeskers. 352-2 and 352-3.

bevels by switchyard bus tothe startwu traneforrner, X4, and than Irenels by urnderground mes to the salry buses in the art Th alienate Ofifate power sorce coases frot the 23kV ewitchyard and ravels fron breaker 252 by unsegroord oables hotke ehutdown transformer, Xt13 and thean by urdergroud cables tobus AS. From ASthe power traiels by ndergroind cables tothe safety buses in the plant. Nelther PNPS reovery path Ior Oftaite power uses tranasission condtors.

These pal he are shown o Figure 25-f1 o the LRA Pap ld 77

James Davis - AMR - Report to the NRC.doc.pdf Page 16 Number Status Request 369 Closed

[3E622-N-05 10 CFR 544 (a)(3) reqoires, insprt, that all systems, strsoturea, and cornporals (SSCa) reliedwin safety aralyses or pant aluation.toyarrm aft.oction that damorstrates octrplijaie withthe ooersiaiorK regulat*so o station black out (10 CFR 50.63) aewithin the soo.je license renewal.

mt is yo ae altwte ac (AAC)

_oco med to eMS SBO rauiremwts? Are all SSCs (iratdcig elaetrical soticera) associated with AAC soros icluoed in the *cope it Iicetaee renewal? If they are tee, eaupan why not I they are, proite an AMs tr long-tivwt passive SSCs associated with the AAC sobcas 370 Accepted 13.622-N-06]

Are all electrical and I&C oalarsrerI penetrations EQ? I vat, prsids AMts aid AMcs for ra-EQ dectrical and I&C containment peasoraiona.

The A3s athod incrdae both ertgrwi ( XLPE, XLPO, and SR irnarl conouctpglgal I r

arion, wo.,) as well as inorganic maerial (stch a cable fillers, epoxiei. potti ng ooepounds, cornnctor pins, phugs, and tacial grommels).

Response

NRC At PNPS. the etation blackoJ doiesel generator providos the Ngren, Du.

alterate AC power source AI SSCs aseociated with the AAC decal are inscpa hr license 1owal.

The LRA peonides the aging management reaiew results hr long-lived, passive SSCc associated with the AAC power sobca in each discipine aection dthe LRA The PNPS IRA Section 3.622 will be reaised to read as ollows:

NguPer, Dec

'Some d the peneration asserrblies a& PNPS are not EQ The n--EQ penetration asseablier aWe saOect loaaging rW nt review. The aging managevert rasiw is peoided in AtME-Ot and the AlP for pietration assembly pigealts is provided inthe sos-EQ instlated otbles and connections program willt nw"a the aging alffets t the peateration assesbly cases and connections. Table 3E62 includes the alectr ical penaation oonductoas and eolactiore in the line itew for Ilectrioal cables and onneactions rot subject to 10 CFR 50.49 -EQ."

The atructural report for bhLk comordities, AMRC'6, addresses the pasaetraios assemtly ooenes, aeeis and sealing elemerts that form the radioogical cntrd herrierfor ertoinrnes inTable a52-1.

This regAree arsamaeenene tothe LRA PNPS Lead Stroud, Mike Strouc Mike PAW 161 77

James Davis - AMR - Report to the NRC.doc.pdf Page 17 Number Status Request 371 Closed

[G.3"3"I-P-Ot]

Tailes 33214-1 through 3.324-35 address norsefdy related corponents affecting esdty reaied systems.

However, these tables addr es all such systems insection 33, Ausillary Oystems,.et though some of thee systems belong tosecoi 3.SZ ESF Systems, ard section 3.0, Seeom and Power Corwersion (S&PC) Systems Tables 33.14-7.

14-16, 14-25, and 14-28 are for systems that belong to Sectiort 3.2 af tables 33114-i, 14-3, 14-5, 14-., 14-10, 14-11, 14-17, and 14-t18 re for systems thft belong to Section 3.4 The Table 1 item reference also specilies Tebd. 3.21 and 3.4.1. The amdt report and the SER are based snsyste(-

asaleined inGALL Report sectihe of ESF. AL.iliary, ard SMC systems. As writteninthe LRA, it will reake the aucit report rod SER confusing becase the OSF systems section 3.2 writeqp will intude Tables lows seetion 33 nd the SPC systems seetion 3.4 write-ep will include Tables Ito section 3,3 Different reewers write these esetiore.

Please justify why-the non-satesy systems associated with ESF rod S&PI systems wereirnleded inthe Aexiliary system sectieor 372 Accepted 1331A-P-021 Discrepancy betwee Table 3.3.1 line items ard Tables 3.32-X for thie lioe items tat credit water heornstry or dl arlysis program and averificatisn peogram such as ore-time ismpectisn (OTi) program The Table I iter is conistent with the GALL report arod crrectly credits the cheristry program and the OTI program or for plart-specilic program alsooreets chemistry rnd OTI programs. Howa er, the Taele 2 line items thaI reference these Table I line items do nort redi the OTI progeam. These Tedle 2 line fetes.. ser have sfootnote A, or 'C'w'ch stases that it iso.rist.l with the MEAP cotinrdi iethe GALL Report.

please justify why the OTI program is rot credited in Table Z een though it is credited in Taele I and footnote 'A' irnplief total consisstecy with GALL for APP ooerinstiore

Response

Sectioe 14 ircudes all the systems OWst hfee inltrded feunticns that mee tOCFR 54.4(a)(2) for physical interaction. To indicate individual systesm included insthe ang managemnt treiew for (a)(2), Table 3.32-14 is subdivlded by system. For exarnoe, Table 3A2-14-1 isfor the circatisng water system, asyster whichorhy has componets included for (a)(2). For the more spray system Tale 3.3.2-14-7 shows the oponents irclded for (s)(2) bt sliow the system is also in scope for other resos, Table a32-2 shows tle compnsert included for 54.6"a)(1) and (a)(3).

The aging manegernat reeiew of the systems thst h-e kunctioe that mis 10 CFR 54d(a)(2) for physical interaction was done separately how the ree of seystems with inlended lonctisns that met 10 CFR 54.4 (a)(1) or (a)(3). The esuts of this review were presented separefsly *owthat they cowld bereeiewed seprartely on the besis of physical prasirrity rather then system functione This albows a reviewer toclealy disfinguish which corponrwt types inrs system were included for 10CFR 54"a()(2) for physical interactisr Since mt of these systems wre asailisry systems they were aedded as pert of the aueiliary systems section, NRC PNPS Lead Petd, Erach Froribarger, Since the One-Time inspeetion (OTI) Program is applicable to each Paeld, Erach water cheristry corolr program i is as pplicable to esih line itew thal orehits a water chemistry corolr program. LRA Tlde 33S1 Indcatet that the Ose-Time inspection Program is cresited alonr witi the water cheristry controd programs for liow items for whiho GALL recommerosba sasowe-rn inspectio to lonfirm water cherristry control. Tabed 2 credits the OTI program through reference fothe associaled Table I line ithne This reqirestanamteeni tolhe chetistry program desecriptione insLRA Appendces Aard Bto clearly indicate thet the One-Time Irspeetion Program willoortirm the difeotioeess ot the hater Chemistry Control - SW, Vets. Cherristry Control - Auiliary Systems and the Water Chernistry Cosrof - Closed Cooling Water programs.

Froashrger, Pw 17d 77

James Davis-AMR - Report to the NRC.doc.pdf Page 18 Number Status Request 373 Acelad (a.3.31-P-ix31 PNPS does not include Bolting Ilterity Progam inthe IRA, howemer credits other programas w alternate to the bolting integrity program The GALL Repont AMP 1l MiB, Bolting Integrity Program ynovides seweran recaureteions inthe 10eemet eveluatioeM-peniticallyreaoesnennttiers associeted with prerio actions such as seection of bolting Maerial., se tubricas and sealants and additional reconmm'dations Ol NUREG-1339. Soine dl the altenate prograrns my beaceptable hoe inspection, howeer, they doert adtess the preventive actions Plasse cairify how PNPS meats these recornrt-a*terone when ing alternate pWora rt please credit a Bolting Intigity Progran for the various Table 2 tine items as appropriate For section 33. this epgiis toTable 33,1, line itern 331-19, 3.31-27, 33.1-4 33A-43, 3.3.1-58, and 3.3.1-78.

374 Accepted

[T.3.3.1-P-01t Table 3.3.1. itern 3.3.1-t, for steel aranes witheaving etfect d auensative fatigie dhrage, the GALL recernmnerd TLAA to he eval ted stfiruct-la girders of erie. The cse-ssio setien states B this line itemn was not awed in satIlr 33, howener steel cranes are evluated in section 35 Table 3&2-2 ad 3&52-4 address ara bL forha aging tffect of l d mnaterials. CurnuLteive fatige damage o craen is rot addressed in section 35 or in the TLAA section 4.7 (platr specific TIAA). Al see TLAA question Please e*ylain where tBis line itet Is addressed inthe IRA

Response

A Boeting Ilegr1ty Protram willhbe devaoped that willaddress the aying managernenr d belting inthe scope ofelicense renewal A copy of the eging ne-agarta program basis docuaent forthe Bolting riegrity Program willbewoeidal for review with the IRA stqdiaret.

The Bolting Inteegity Program wil tbe inqpl erted prior tothe peled of xt-ended operation ineaeodanie with corenitmnt nutber r3 This requres at ernmardtne to the LRA to include descriptions of the Bolting Integrity Program in Appendicee Aad Band to identity where the wogram is applicable NRC PNPS Lead Paed, Eraeh Froenbarger.

As delinet In 10 CFR 54.3, a TLAA is a licensee calculation en analysis that, among other tings, iraoves tirne-linited assuitlions dlirned by the eunrel operating term Thee is eo analysis for sled cranes at PNPS that sausties the ddintion.

CMAA-70 defines allowable stress range besed ejolni category end service class. Seroice cas is based on load class (nasn tfeative load factr) and mrern of cycles.

However. the nmrten ocycles is NOT bhsed on4A yearsof operation of thie crae The antic ipated cycles fte the PNPS reacto building crane re werl below may of hte cycde ranges oivan in CMAA-70. Baed enrealistie estimates and the hstorical rate of Ce d the eoras todat, the PNPS reactor building and turbine talding rarnas woLdd take ver 350 years to reach the trinimant cycle rane tar CMAM-70 Cosequently taoe is n TLAA ssciated witherana loed cycles Patd, Erach Fiin Ronl Fa d8 77

James Davis,- AMR - Report to the NRC.doc.pdf Page 19]

Number Status Request 375 Closed rT.r3.1t-P-021 Table

31. item 3.1-5, for hal exchaoger exposed to treted water >,6C (>140F). distussion states that OTI will be used as verioticaton program tor water cemristry.

However, for lmhoe lineies in Table.32-Z3lhere item 3.al-5 is rdensnol, OTI proram isnrd credited. See queslict G.3.31.2 above 376 Closed

[T.3.3.1-P-W3J Table sat, Kem3.3.1-14 for steel oonpor*wt nctposed to lubricating oil, GALL report reomrmends lubridcing oil ebalysis program and OTI as a verification program However, intha discuoion soection only the ail analysie pograem iscrlledi Section 3.-Z27. item I states the operating -periwee at PNFS tee confirmed the effectveaness o this program inninitaining cortarrnadrs within limits such that corrosion ta noo and will rot affect the inrtwded tuncti*ns dtthee anomrnerois.

Pleess eaplein how PNPS can nmke trio etateent if Inspection has ur been perforned

Response

Sime the Or-Time Inspection (OTI) Program is appliclble toeach water chemistry control prograrm, it is also applicable to eech line itern that arodis a water chemistry contreo program LRA Table 3S3.1 indcates that the One-Time Inspction Program is crelited along with the water aesristry coded programs for lineiters ler which GALL recommends aoee-fime irspection tocorlirm water chemistry controi. Table 2 credle e OTI program through relerence tothe asociaetd Table t line item.

This requires artamendtmblr toth" chemistry program descriptins in IRA Appetdices Aard Bto cletrly irdicale that the On,-Time Inspettion Program willoartirm the eftectiveness d the Wter Chemistry Coitrel - BWR, Water Cheristry Coarol - Auiliary Systems and the Water Chemistry Cortree -Closed Cooling WVder programs.

Thio item is closed to ite 3M2 During the pertformence oa routine mainterance oncotpaods that contain lubricating dl, visual inspections of these orrponerts would idenify degraded coritionr that ocid beattri*oted toan inefrective at1 Analysis Program The aorrective action program at PNPS has alow threshld for tha identitcation os degraded conditiros etchthat corrosion or cracking co omnpc*rnets Woitd be Identified as part dthiea program The review o operating epeierce al PNPS for the last five yers did r identity anty aocetiion reports that inrcated wr Ineffective oil analysis program or tet idereified degraded aorgcar t condtion such as corrosion or

-reking in: lubricating oil eomirotrvt Thio resis at operating eperlon"e PNPS serves in lieu os a one-tin inspection to provide conirrmaion o the ilectiveess a the Oil Analysis Program During the pest live years. many visual Inspectione d conpcreds containing lbricalting oil twe been perfornemd during correctiveande preventive maertenance activitie. The visual inspection, oa thee ompoernts would identify degraded onrditions ech as aorrotion e' cre*king th could beattributled toan ineffective ail Amnly.c Program PNPS hasa ow threshold for the identificton degraded conditions such that corroion or cracking of components would be identified and entered into the corrective action program Noao-diaio reports that iderified degraded aomponert oedtioti,

such as orrosion ar cracking in a lubricating oil ercironnarr, were initioted ae a reautd these inspections. These pest inspections at PNPS seve in lieu ofa cne-tme inspection toppro*ide contirmation oa the efectiveness afthe Oil Analysis Programc NRC Pat*, Eraeh Patel, Erach PNPS Lead Fronabargar, Froobargtr,

PaW 19d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 20 i Number Status Request 377 Closed fT.3.3 -P-04]

Table 331, ftem 3.31-17 for sled derrnot exposed treated water cdiscesnio states that OTI willheused as veriitcaite roratn for water cheoistry. Refer toqesiton T331.2 and t.3.31.

Thisappties tosewerad tine itmss invsao Table Zs ihat referens. item 331-17.

378 Accepted

[T,3,3,1-P-05]

Table 3.31, ite-e331-18 mcested eend Sdesed engne ewhaust piping inthe dscussion" column rderernoes section 3.3.227 iten 3 for bathe ealtuation. Senton 33227 Ieem 3 states Wet the carbon st l diese exheuat piping and omner s inhe fire protectio* system is managed by the Fire Prolecien Progern The Fire Protection Program wees visual inspetiok e -.

e el d

sheust piping and cosernnrts to ge loss of mateiand. Iowter, Apedsx B.1.131 program description wh iderntifies the systesdonrnodi lies inscope for inspeliton does not inlude lhe Ispection dl t he deed ha.ist piping and nomrtnerts. There isno enhancement identified inthe program write-upto inctud thiis inspectdion, cring the period d extemled owaiiolo Pleae esplain this discrepency between secrtion 3.3.22Z7 item 3and the AM B 1.131 progr*m denscrion or bitude this inspection inthe AMP as eshanemseseni.

Response

NRC SiEn the OCr-Time Inspection (OTI) Program is sypiicale to each Paied, Erach water chernistry cotreo program, itis also a*icaiie toieach line iternthat credits a wate cheristry sonlre program LRA Tabe 33.1 Indcates tht the On-Time Inspection Program is creted adong with the water chneistry oertrel programs for line items Ior which GALL reoonenerle asone-time inspection to cofirm water chemistry control. Taele 2creits the OTI program through referenet the associaeld Taede I line Ietr This reqtires anisentrent tothe chemistry program descripiions is LRA Appemtoes Aand Bito olely indicate that the One-Time Inepestion Program will oortirm the edlectioNerss ad the Water Chenistry Control - BWM, Water Cheiristry Control -Ae*ili*ty Systemrs and the Water Cheristry Cororl - Closed Coding Wer programs.

This iten Is cosed io Item 372 E

searetesn will be rds tothe FireProtection program tocrelit Patei, Erach misting or irrtlemerel new prevetive mainterance tasks for ihe fire pump diesel Io sehes heat all aeing elfects identified in Tele 332-9 line items lW apply tothe lire pump desel oeerse*enes we adespatly managed and isended lsfutione we mrnitained withotd creaiting the ddtectiof e teak age as mrnagsng an aging effec.

This rqefree ansesnierwt to LRA appeeclices Aand E PNPS Lead Fr-neearge.

Frosmbrger, PW 20d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 21 Number Status Request 379 Closed (T3.31-P-06]

Tale 33.1, itern 33.1-21 tor Steel osnrporneets exposed to tubicating oil. The is the same issue es in questivo T.33A1.3 above, except the secfion is 3.322-9, item 2.

380 Closed

[T.3.1-P-o7]

Tabe 331, fler 331-23 for SShed eha otnrw sosres exposed totreated water. Thi is the smee issue as in question T 331.2 above, exept the section Is 332.ZZO. htenZ

Response

During the pertormnce of routine maintenrance onscornpor that contain lubricating oil, visual irnpections of these comonlents would Identily degraded conditions that void be attributed ton inelfective Oi Analysis Program The corrective ection prog-am at PNPS has a low threshold tor the lerlificatioe of degraded conditions such thet corrosion e cracking of corlponerls would be identified as prt o thle program The review of operating eperience at PNPS for the lost five yeares did rot idertify ary condition reports that irdicated an inalective oil analysis program ar that identitied degraded ornponn I cornitions such as corrosion or cracking in a rurtivling oil erirortere.

This review of operating xpeleroe at PNPS an-n in iey. a onet-time irspection to provkie onfirnetion of fh ateectivenees ofthe Oilt Aalysis Program During the post five years, trey vial imapections of oompor*ets cortaining lubricatig oil t*ave been peorormed during corrective and prevenive neirnernane activities. The visual inspectiors these xfporr ftlx would identify degraded conditions such s corrosion a orracking thrt xould beattributed toan irradfeetive Cit Aeysix Program. PNPS has alow thevehold for the idenification of degraded conditions such that corrosio oeroracking of xorr ft would beidelitfied ad enered into so oorreciveaction program Nocondition reports thae Wden ified degraded romponenw coidtions, such as corrosion er oracking in a lubricating oil environni, were initiated asea result f these inspectior.

These past impections at PPS serve in lieu of a vx-rome irpecton to provide cofirrmnon ofh v

the etfotiveessoxthe O imlysis Program The itee, is dosed to Ieer 376.

Since the OC-Tiere Inspection (OTt) Progaro is appicate toeech water chemistry sortred program, it is also applicable to each lin iter that credits awater chemistry conlrdo program bRA Table 3.31 indicates the the OnTirme Inspetion Program Is credited along with the water leheriatry control program f line Itim s for which GALL reoomvrwend aseer-time inspection tooorfirm water xtenriatry control. Tle 2 creolts fhe OTIptogram tlrough reference tothe associated Table I line fter TN. rediree e rsre*nvmrnt tothle chemistry programr descriptionr in LRA Appendices A and B to clearly indicate that the O-Time tnspection Program willonfirm "h atfectios of the VWter Cheristry Controd - BWR, Water Chleristry Conard - Auiliary Systems and the Water Cheeristry Contrd - Closed Codling Water programer.

This itew is closed to fem 372 NRC Part, Ebch Petal, Erach PNPS Lead Fromeargetr, Fror*abger, PaP 2Wd 77

James Davis - AMR - Report to the NRC.doc.pdf Page 22 Number Status Request 381 Closed

[T.331-P-0C6 Table 3.3 1, itte 3.3.1-24 for SSard alumninum corrponents erposed tofreated wats Thisis the sae iss as in question T.3Sa.2 above, except the section is 3,3.22.10, ithrn 2-There aeover 80 line itens associated with this in difWere tale 29.

382 Closed

[r.3t-P-09J Table a3.1, iten 3.3.1-26 for nopper alloy oosnw*ents exposed to lubricoing oil. This is the sane Issue as in tuestion T.3.S1.3 above, evoept the section is 3.3210, itet 4

Response

since the Ore-Time Inspection (OTI) Program is appticable toeach water chenistry contror progran, it is also applicabile to each lirne iten that credits a water chenistry control program LFiA Table 33.1 inricates thet the One-Time Inspection Progream is credited eaong with the water chenislry control proeaen for line items ton which GALL reconrrertns aone-time irnpection toconfirm water cheristry control. Table 2crecits the OTI program through reference tothe aesociated Table 1 line item, This requires aenamordmnat tothe chernistry progam descriptions in LIA Appendioes A tand Bto clealy indicate that Whe One-Time rnpection Program willcortirm the effectiveness oi the Water Chemistry Control - BWR, Wats Chemistry Control -A..iliary Systems and the Water Cheaitry Control - Closed Cooding Water program.

This item is closed to ties 372 During the performane oi routine mriteew ene oncomponen eth ontDain lubricating dl.odsual inspections oi these oompoarets would Idetify degraded conditiom thae could heattributed toan ineffective Oil Analysis Program The corrective action program a PNPS hae atow threshdd for the ideti*ication oi degraded conritions such that corrosion oacracingof coiponeets would be IdMrified as peat oitis program The reviewofi operating eponence Sf PNPS for the last tin years oeid not idereily eny eesition reports that indicated an ineffective oil analysis progeam or W idetified degraded oosprpoa t conditions such a corrosion or eracking ina lubricating oil erwirorneret Ths reniws otperalint esperince at PNPS ertvee in lieu oda Ome-time ispection to proide oorlirmalion i the effectiveness oi the Oilh Anysis Program During the past five yeprs, many visual inspections comnponrels containing lubricating oil have been performed during cerrectiveeasd preelwive mairter-ce activities. The visual inspections oi these corrponent would idetify degraded aortome such as corrosion or cracking thet could heattributed toan ineffective Oi Analysis Program PNPS has elow threshold for the idetificatlon of degraded conditiohs such teht cormeion or cracking oi cenpents would beidrtitited a entered into the corrective action programs Nocondition reports that identified degraded comnent corcitiore, seJh as cormeioenr cracking in a lubricating oil eniroiwred, were intiated asa result oithee ispections. These pest inspectione at P=PS serve in lieu of a mne-hme inspection to provide ondirmration oi the etfective-ess oi the Ott Analysis Program This item is closed to htem 376.

NRC Patet, Erech Petl, Erach PNPS Lead Fronemger, Frorabarger, Film 2d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 231 Number Status Request 383 Closed fT.33t-P-101 Tlse 3.3.1, iteo 3.31-30 tor SSCunWorMea esp**se to gdiumn pentaborate sohution Ths is the sane issue as in question T.32t1.2 above, cept the section is 3.322t10, ite 8.

384 Closed (T.33t-P-ttj Tale 3.3.1. ilen 3.3.1.33 tor SSconponerts esosed to lubricating Htt. This is the sa-e is.-e s in question T.33.1.3 above, aoept te section is 3.32212. iten 2 Resonse NRC Stnce the One-Time Inspection (OTI) Prog"am is applicable to each Patie, Erach water chernstry control progra-, it is also aplicable to ech tine item that credits awats, chenistry nonrdol progret LRATaele 3.31 irdcates that the One-Tine Inspection Prug-em is credited Wosng withthe waterchet-istry control prograrne he lireiterns ho which GALL recommends aon-tine inspection tocornirm water chenistry corsol. Table 2credits the OTI program through rderence tothe associeted Table t line item This resuire anannenhrnele tothe cheuistry program descripties-in LRA A.peoiuea Arnd Bto cleary indicate that the One-Tine Inspection Prograen willtcoiim the elfectiveness d the Waets Chenistry Control - BWR, Water Chesintry Control -Auxiliary Systens ard the Water Chessistry Control - Closed Cooing Water programs.

Th.n item is closed to Ien 372 PNPS Lead Frobearger, DOing the perloemance doroaeire ntmltenante snoonugpnas Set contain lutricating oil,.visual insectione tifthese nonponerns would identify degraded oonditiors that coud be atritbed tosan inetfective ai Arnlysis Prograrn The corrective action progarn at PNPS has a low threshold hoe the identification degraded conditions such that corroesio nr crackinga of oorqponers would be ide-ified as part ot tis program The review of operating apenerise at PNPS hoe the last live years did not ide-lily ary condition reports that irdnated an ineluective oilat alysis proern or elt idertified degraded connpoen t ooditoner such as corrosion or uceoking in a lubricating oil ensirornorl.

This reviewn i operating eaperience at PNPS

-enes in lieu of a one-ine inspection to pro*ide confirmation of the oleutivenes of the Oil At lysis Progr-e DOing the pest five yws, many visuad inspeclions ilconponsnts containing lubricating oil have been petoened during ourrectiveand preveative nairtenence activities. The visul inspections at these oonporerts would idetlify degraded oorndtions such as corros;[n a cracking the could heattributed toen inelfective Oil Analysis Prog-an PNPS has a low fteheld for the idetification of degredll onuditions such tet corrion or cracking oi conpenr-t would be idenlified and entered into We corrective astion progrem Noccondition reports hei idetified degraded corpmnent oorndtions, such es corosion or cracking in a lubicating oil emvironmer, were initiated s a result odthese inspections. These past inspeclins ai PNPS serve in liou aea one-mfie inspection to provide condirnetion aWthe atfectiversa ofithe Oil Analysia prog-an.

Th ite-is dosed to Ien 376.

Pstai, Erach PR 23F d 77

James Davis - AMR-Report to the NRC.doc.pdf Page,24 Number Status Request 38 Closed

[T,3.,1-P-121t Tle 3.3,1. item 33.1-37 kor SS compormls erposed to treated water >60C (>140F). Ths lineitem aplgies toRWCU systeml and GALL Report recomrends AMP Xl hG5, SWR Resctr Water Clearup System The applicari states "Stpphernl Ito GL8B-01 states that IGSCC inspection of RWCU piping 'tAside of the oontainert isolation veves is recomendered only until actions associated withOL89-10 on o*or operated valves ae ecom-plated Sice PNPS hes satisfactorily copreted all actions reqxested in NRC aL 89-10, the Water Chemistry Control BWR Program is wed in lieof the BWM Reector Water Cleanup System Program to manage this potential aging effect." How-e, the As also states that in addition to esd ing this criterion, piping is made of trterial that is resistarn to GSCC.

Response

NRC Original Type 3a4 stainless sted pitpng aed fittlings between trywelt Peal. Erach peneration X-14 and the W x 4ý reducer dowrstream of MC-1201-5 were replaed with type 316L stainless steel PNPS Lead Taylor. Andy Froreherge*.

Please confirm what grade of stainless naterial is wsed and jestiy that it is resietart to IGSCC.

386 Closed JT.3.3.1-P-122j

&mese the Ore-Time Inspection (OTI) Program is applicable to each Patd, Erach water chemistry cortrd program, ils aso applicale to each ltes Sames issue as q-stoim T.3.31.2 *leve also 'pplies here iten that credits a water cheristry control programrr IRA Table where OTI is not credited in Table 2 line items where 33.1 indicates that the Ore-Time Inspection Program is credited 3.3 1-37 Is reteenceds Mong with the water cherritry control romgrers for lieitems for which GALL recoeense aocne-tite inspection toconfirm water chemistry conrd. Table 2crecits the OTI program through relereree tothe associated Table I ties it-e This requires anamehmdent tothe chemristry prc*gram descripions in IRA Apperdices Aand B to clearly indicate ilat the Ore-Time Inspection Program willlonfirm the effectiveness of the Watr.

Chaerstry Control - BWR. Water Chemistry Contrd -Auxiliary Systems and the Water Chemistry Control - Clesed Cooling Water programs.

This itear is closed to It-i 375 Pabe 21d 77

James Davis - AMR.- Report to the NRC.doc.pdf Page 25]

Number Status Request 387 Closed jT.3.3.1-P-13]

Tabl 3.31, ite, n 3.3.1-38 for SSeomponetes sposed to treated water >60C (>140F).

The is the same isete win question T.33.1.2 above 3Se Accepted

[T.S.3.1-P-l4]

Table 3.3.1, iten 3.3.1-40 for sed tank Indeed futi oil system apset teedk

-oAdor astsnta awirrmwart. The GALL Repert reeoenaeeds AM' XltAG Aboveground Sted Tanks, however PNPS is creeting a different progran, System Walkdown Program The program is consistent with GALL Report AMP )(1.103, Elernal Surfaces Montloringg Wile the Syatern Walkdown Progran isan acceptle asterrnse for Aboeegroued Steel Tarkt AM' for inspeotiont however, the Ab"'eegned Sted Tarks MP hea some pr/ealtivn atione assoiated with it that se ino addressed in the Systern Walkdown Program. Furthereore the GALL AM' epecifies wall ttcknew meesueremnt of tant boltom if A is supported onearthn oreconcrete ouedations.

Please clarity if the steel Lteks awe ooed with protective pairt or oeating inecoertdhw a with industry practice, and whether stisn! o caulking is applied atthe intelaace edge between the tank and the henetion as per the GALL AMP XI.IW9 Please state how the tank is suppeored

Response

tihee the One-Time Inspection (OTI) Program is applicale to each water cherstry tonlrol prosram, it is also applicab:e to each line itern tht credits a water chemistry corol program LRA Table 33.1 indicates thet the Ge-Time Inspection Program is credited along wth the water chernstry conetol te:rras for lnieiterr for whch GALL reommnands aee-time irwpectin tocoetirm water chenistry control. Table 2credits the OTI progam thiroug redererce tothe associated Table I line item.

The requires aeamen-rnent tothe chenistry program description in LRA Appenraies Aatd Bto clearly innicate that the One-Time Ihspection Program willteeiew the eltectiveness of the Water Chemistry Control - BR, Water Chemestry Conerol - Auxiliary Systeers and the Water Cheristry Contern - Closed Cooling Water programsa.

The iteon is celned to tem 37M Noee"bon steel tanks inthe kAol ol ssten exposed toat -outdcor seaimluded in scope for license rerewal. The LRA willhe aesnded toreseere the line itam inltae a3.2-7 for carbon atse tanks exposed to air-ousoor. The discuesion fte line tem 3.3.1-40 willheearnandad to state the line itern is in wed.

Tharedquires a secernertamn wexenwt tothe LRA.

NRC Patel, Erach Patel, Erach PNPS Lead Froasbarger, Ni.hote, Bil PAP 25d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 26 ]

Number Status Request 389 Closed

[T.33AIP-15F Table 3.3.1, item 3.3.1-43, for sted bolting and closure bolting esposed to air -iedaot uncotwrolled (eslarwi) o air -

outddo (External). The GALL Report recosrnerds AMP XlM18,Bolting lItegity program, howeer PNPS iscrediting adiferto prograrm, System Wkdkdown Programr PNPS idcates thet the system walkdown program is sirrilar to XI.M36, External Salsoes Monitoring Program Howeer, the XIM36 AMW does not haee any preento

actions, herees the Bolting Ina t

ey Program considers prevsetive actian.

Please justify how the pyeeerlive ations of GALL AP XI.MIB are addressed inthe systen wakdown program 39D Accepted

[T.3.3.1-P-16}

Table 3.3.1, tos 3.t-58, forsteel esternal surles eposed toadr - indoor inctroll ad (esteresl), air omdoor (eaerrln), and sondawetaos (external). For those lineitens inTabie 2s where this Table i line item is reaerenced for bolting, sa issue as q-fion T.15 ahord beaddreseed In Table a3.2-10, LA page &3.-123, for ta in Hale systes, which relereras line item a3.1-58, Fire Protection Program is credited Please j..tity why the Fire Protection Program was noidenrtfied inthe dcuesio column of Table 3.3.1, itema3.31-SB orapplerrent the LRAtoineret Itis program

Response

NRC ABolting integrity Program wilibedeeloped that willaddress the Paid, Ereoh agng nisegani of0bolting inthe scopeof licese renewal.

The Bolting Insegity Program willhbe impitssersed priar 1othe period f eadended operation in accordane with conrmitlmeat tret 32.

This reoirep an amendsant tothe WIA toinclude descriptiors d the Boiting Inhegrity Program insAppendices Aand eand to idetfity where the program is applicaole This Rta is dosed to Item 373.

A Boling Integrity Program willbedeveloped that willaecdres Paid, Erach oweang the effects of agng nbsedling inthe sope of licres renewal The Boiling Integrity Program willheitrnpemented prim to the period 01extended operation inacoatotdce with ommrtreist

-1ter 32 The LWA willbeclarified to inclede FireProlection Prograwn inthe dsoso foret he a 3I.1-58 dTable a3.1.

The revised discussion test will read as follows: *The system Welkodown Program manages Icesof m terisl air mtetlr stsaces 01 steel oornponert.

For sore fire prolection system co'rponeats.

the Fire Protection Prograw will rresge loss o0 material." The Nols for te related line inTabe 3.3.2-10 (sted helom tank esposed to adr) willbechhngd frhom Bto"E.

This reqoiree an ams ent to the LRA to inlude descriptios d the Boiting Inregrity Program inoAppenodes Aand Bed to Idenify where the program is applicable This first part o this tem is olosed to Item 373.

The Fire Proection porion of Its item requires anarrerdmest to the LRA PNPS Lead Frorebarger, Ungertdlter, Fb-oZ16 77

James Davis - AMR - Report to the NRC.doc.pdf Page 27 Number Status Request 391 Accepted fTf3`31-P-171 Table 33.1. teon 3.3.1-61, for lasltone fire barrier penetration seals eaposed to air -otiWor a air indoor Uncontolled PNPS credits Fire Protection Program atd elate. infth discussion colunr that this line item was ro ted enthe eauiliary systems table. Fire barrier sale we enatitse-atrturat comrenents in Section 35. Cracking and the change in material propert ead of atestomr sats are managed by ite Fire Prtection Prog-am HowIeer, in section 35, Tale 3S.2-6, Bulk Commedities,

-n pages 3.5-St eId 3,5-3S evre lineitem 3.3.1-61 is rererened, PNP3 creditsthe Fire Protection Program aid Ste StructMree onitoring program H-wewr, fine item 3.3.1-61 does not credit atrutures menitoring prog-am s ea rmat*to fadct the Structuea lsMitoting Program is iuatad toadd guidance for inspecticeno d altomer ealt.

aSo. Plase clarify it both programs we credited for mnanging agng ddfcts for penetration sents as stated in Table 3.5.2-6, and if so, please supplement the ISA to include She Strctras Monitoring prngram inTine 33.1, item 33.1-61.

Response

NRC InTtble 3.5,2-6 onPage 35-82 of the I1A, the aging odects for the Patd, Erach aleetotner crongiarts peonaration seadart aid seisric jclt filHer in a protected from weather enironrent are cracking ad cstange in material propertia. Depending onthe specific application, the Fire ProFection Program or fi Struatea Monitoring Program will manage te effects of agieg For cahiieation, these componeor line items will beaseparated into irdividual line items as follows.

Delete the fdleieng line items Penetration ealart(fire rated, fScot radiation) #IEN. FB, FPB, PB, SN fI BEatomner 1 Prteacted from weather f/Cracking Chenge in nmterial properlies /#Firepretac tioStractures Monitoring 11i.A15-12 (TF-7)//3.5.1-44 tIC Seisaic joint fillera PFB, SNS # El atomer //Protected from weethr I/ Cracking Chaege in mteriat properties ff Strtures taoaitoring.

FirePrF ction I/VII.G-l (A-19)//3.3.1-61 HC AddO Se fodlowing line items:

Penetration sealant (fire rated) # EN, FB. PB, SNS 1

Eaastomar #n Protected fromweatht llCrackingChenge inmatteial pioperties I FireProtection /VII.G-l(,*9)(f 3.3.1-61 StB Penetration atsonL (flood, radiation) HEN, FMB PB, SNS f1 Baslomee U Prected from weathertI CrackingCheage in materiat properties l Starctureta Meoitoring 11 IIA6-12 (TP-7)/35.,1t-44 #C Seismic isolation joinf UFB, ENS II Etaatoner I/ Protetetd from weather # Cracesng Changes inmaterial properties /Fire protection #

VI.GI (A-19)U/33`1-61 /D Saisrric isolati (jodl1//SNS El8atomner #Protected from rnweatte S Cracking Chaege inmatertai priope'lies Structures monitoreng II.A6-12 (TP-7)fU35.-44 //C THde rresirasanarendmara tothe tlRA PNPS Lead Unerfelaer, flge 27d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 28 Number Status Request 392 Accepted

[T.3.3.1-P-18t Table 3.3.1, item 3.3.1-64 o ceel piping, piping oomponents, and piping elaeents -posed tofuel dl. The intent d thes fne is to address the diaeel-driven fire pumrp, which is wh/ the Fire Protection Program is recoederdae by the GALL Report. PNP statles that this line ier was notl used. Loss of rnterial of sted corrponerta exposed totued eld was eddressed by do r there. including line herrs 3.3.1 20aec 331

_ The Fire Proteetion prograrr specifies thae the dle~ed diven fire purnp be perioially tested to recte that the tues supply tinomn perfonr its intended function PNPS F.1.13.1 has not teken any eception tofts test and isidentified "hbeing consistent withthe GALL program.

Howioon. E1.131, Fire Protection program is cet credited in tine hier 33.1 20.

Pleese clarity it PNPS has a mesed driven firerpup andr it rot, should oanmepiiorr betaken tothe GALL Report AM'.

It PNPS ctose hwe acied! driven fire puap. where inthe LRA seetio 3a3 is it address d eand is the Fire Protection progerim credlted.

39 Closed

['T.3.31-P-19l Table 331, Jnem 3.3.1-72 tor steel HVAC ducting and conponeit inteeal suriacee exposed to ondeosation (Internal). However, there iscoty inin Tae 2whren thic Table line item is rdeereced ThIe line iter is inTable 3.32-3, RBCCW ysteir and the onmponest is haM anchenger housing PNPS states inthe discusion colurnn of line 3.3.1-72 that leses d raterial of sled componert interni suialees exposed to osdeansation is mhanaged by the Syter %lilkdown Prgeosr The Systen Wallodows Programo thiages lees of imaterial for aterned carbon sted ornponenil by cisua inpeetion of ateenel slurfaes. For systwem where interel cearbon sleel surfaces me eposed to oe f ironinert a anternal srawlaes, eternl surfaces condition willberepprsen Wived internal surfaces.

Thus, lAMs n miterial oninternr carbon steed surfaces is also mreaged bythe Syrtm Wailddown Program ReFse clarify how PNPS oiocluded that the interna seace of the haMt rncheaqe ilthe samne as the antered surface in the RBCCWsystemn

Response

PNPS hls adiesed driven fOre puarr with comrorts addte-sed in Table 33.2-9h The ud oil supply toed dieed driven tire puarp is included in Table 332-7. The ine leer d carbon sled piping with atfudl alalrOal erwirorrnet in Table 3.3.2-7 hoe the lfu supply tine does noG credit the Fire Protection Progran Although the programs credaled in Teb 33.2-7 tor the fuid supply line prnide an acceptable alternative approach to rn*ege the Sffects of aging in order toachieee consistency with NUREG-1801 the LRAwill be Wesised tocredit the Fire Protection Progra.n LRA Table 3.3.2-7 will be reised toewd aen aedItiorsl line itee tocredit the Fire Prtection Prog-ra to manage the fuel supply line in addtion tothe Diesel Fuel Monitoring Progranin This will also rewire a change to line itern 3.3.1-64 sinces he -lw finesler witll Ipecity 3.31-64 as the Tabe I itO This reqires anawrneherent lothe LRA NRC PNPS Lead Pa*d, Erach Fresbarger, Theainteald ocpoamerc o the A anhengea housing haes the Paid, Eresh potendial forbeing welped toea crnbination of kw teanirature closed cooling water and high dewpoint indoor drywedI air which oild result (though nrot apected) inceoleeation milthe coding coilthat would becodlected in the bottotal dlthe houainug Condensation was also identified onethe un-ineoated nteeda surfaces ofthe AtM achanger housing due tothe potential tithe hMuming surface teraneriue downetrearn o the fling all being less thra or eqia to the dew point sl the surrounding air in the drywell. These aecironerenia were n-eneantively identified ane though the eapected environerrent would beindoor air withno condernatien since le coding waterterlperature is enorreiy maintaisanet S-BWF. Syster Wlekdown wascreoited because he anpected ersirorrmnt for both the intednal and wterned surfaces would bethe eare in either case Oricedk Jack Pap Ad 77

James Davis - AMR - Report to the NRC.doc.pdf Page 291 Number Status Request 394 Accepted

[T.3.3.2-P-0J Corrne types filter htsing and turbo charger inTable 3.32-9, Fire Protection - Water systerm and piping in Table 332-10, FirePrctection - Halon syster, refererce Table 3.1, iter 3211-32. This Table I line iten addresses steel piping and duting coonneros and itlena surfaces exposed ltar-indtr ereco'irol ad (internal) ercirorneart Disoussion ado.. ci it-m 321-32 oredts Syster, Walkdowri Period. S-n*illatte and Preventive Mtalers..e" and One-Time Inspection prograes

However, the Table 3.32-9 and Table 33.2-10 coorrpoents identified above credit FireProection Program, wsihis rot credted in the discussion odorn d itha 3.2 1-32 Fertermorero the progam descriptlo. dLRA Appendix B1.13.1. Fire Protection Prog:aer dtoe not include inspection of th aboe ide*aied nemporents.

Please clarity the diserepnecy hbeween the credited progr'ams in iteo. 3.21-32 ard the progrrsn credited tor the abone idernified sompe mnt types. NJ, p ease juetitywhy the FireProtaection progra'n desoription doe not address irnpection C these ceTormeo Wypes inthese two system er er.e the progrern to Include tO ese irspeptiors.

395 Closed rT.332-P-02]

crponrer t

head changer tibes inTable a32-4.

Eeergrecy Diee Generator system and Table 332-9. Fire Protection - Water syste. ere made frot copper alloy ad*

exposed to libricating dil aevirorner, which refererce Table 321, Iterm 3.21-9. PNPS Only credits the Oil Analysis proamne ThN tso. is ahe same as in qiestion T.33.13.

Response

Sine it h-reger irterrl and esterel asurtacs with the sarre raterial and ensirorferte, the Systerm, Walkdow Progarn described inB,.30 is a nore appropriate program for the line iters in Ta*le 3.3.2-9 that heve Indoor air (irt) as an erwironorst and credit the Fire Protection Progan In adedition, line iten 321-32 stol s lade the FireProtection Progran sirce Table 3.3.2-10 irtludes Hate syster, piping internal surfacee that oredit the Fire Protection Progran and rollu4 toNs literiten.

This reqduireseanercndern tollt LRA NRC PNPS Lead PaId, Erach Froehargser, During the perloreance di route ine srierneae on onerts that Pal, Erach eontn lubricating dl, visal itrpectione ditlse corepoeert wod identity degraded corditior-s tht aid beattritoed too.

indlfetive Ol Anatysis program The corrective rtio progrrn al PNPS has a low threhold for the identification od degraded rdritiore su hthat 9

orarioni crrking ofoibr¶onerts wos d be Identified as pert dthis progr-rn The riew oi operaling erperise S1 PNPS Is the last tine years did not idsntity any condilion reports th indicated an Ineffeetive di analysias progra er that identified degraded omponen I conditiors sh as corrosion er craeking inao uLicating oil erviroante.

TNs retiewdioperaling erperiene alPNPS saers in lieu dia o-tim itspection to proide conrirmstion of the effectiveness di the Oil An*ysis Progr-a See respomse toita 376.

Frorelieger, PAM 2d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 30 1 Number Status Request 396 Closed

[1r.3.32-P-If!

Componwe types hea exchla ger tubes inTable 33.2-5.

Station Blackhot dtesnd General or system, ld Tabe 33.2-6.

Security Dinede Generator system are ade from slted and anposed Ian aow d uwinumo of kid oi withanaging affect d reduction o heal transfer due tofouling, which riene*en Ta*lle 241. item 341-10. PNPS only credits the Oil Analysis program This sue is the saen as in question T.331.3 Alo, please darify why erud the above onontxne type idntfies footnote VDwhereas the other idenei ies Iootnote

'E, eaen cr0l thy hens the -asn MEAP toonbinetio*r 397 Closed

[Tr33.2-P-04]

Steel nonponent types thermnowed. tubing and valve body in Table 3.3.2-14-19, Off-Ges systeor reoerece Table 3.41, ite, 34.1-t3, whichcredita water cher-itry and ore-hime impectionn yrcg e

fnoriticai-orc However thae table 2line iteam do in credit the verification prngrmu This is the iwnse as. qUho G.&3.1.2 and T.3..1.2

Response

During the performane of routine maunterance onnonponrns thae contin lubricating oil. visua inspections of these oornpoents would identify degraded crdatioons that could be attributed toat ineffective Oh Aualysis Programe The corrective action prograr at PNPS hee alow threshld for the identification of degraded oondlitons such that corrorion a cracking oi nconnc s would be identilied as paet oi this pg-ramn The review Oi operating experience at PNPS for the last five years did not identily any condition reports tha irdicated an inoilective oil arnlysis program or hut iderfitied degraded onncortur t conlstiorw such a corosion or cracking ina lubricating oil e-sirornstt. Thls reviewmo opeialing eyperience at PNPS oerves in lieu o a one-tivw inspection to provide confirration ol IPt effective-ese oi the Oil Analysis program During the past five yaes, many visuel irnpoctiorw oforpnnrs oonraiding luhticating oil have been performed during norrective ad Preventive mainteance activities. The visual inspections o thtse comnponerts would identify degraded corctitin' such as corrosion or cracking hat could beattributedl to irntfective Oil Aatlysis Program PNPS has asow threshold for the ideudificaon of degraded conditios such that corrsion or cracking of ncomonnts would beideruified and enteren to the ne-restive actioe prog-cn Noncondltion reports thit iderI illed degrI*ed nn concndtioes, such ans corroion or cracking in a lubricating oil nvirorne-yr, were INitiated asa result i theee inspections. Ttes past Inspections al PNPS serveinlieu ia one-hme inspection to provoie cortiruation ofthe eectiveanes ithe Oil Analysis Progra-This item is dloned to Reun 3M6.

Stnce the Onr-Tirn Inspection (OTI) Program Is appicable toeach water cteistry ointrol pnogram, it is also applicable to each line item that credits awater chlntistry n*onrol program LRA Table a4.1 indicates tht the Onu-Tiw Inspection Program is creoited along with the water cheeistry contri prograns fr litn itemsh for which(GALL reco-.ranm s aorse-tinw inupection toncrhirm water chunelstry contrl. Tabe 2 credits the OTI program trough reference tothe ansoialed Table I Hne item This retie ranamendmrnt to the chdrnitry program descriptiore in LRA Appuntces Aad BEto clearly irnicate that the One-Timw Inspection Program willtortirm the tffectiveness oi the Water Chemistry Contro - BWR, *t*r Chelrnistry Conrol -Anciliary Systeus and the Water Cheiatry Coltroi -Closed Cooling Wuter progrmshe TH.s itern i. closed to h-e 37"2 NRC PNPS Lead Patel, Erach Foorearger, Paetl, Erach FroPaintge-.

PW 302 77

James Davis - AMR - Report to the NRC.doc.pdf Page 311 Number Status Request 398 Closed IT.3,32-P-0]

St*lres sted eorrporenl types thuroereol, hubing ard valve body inTable 332-14-19, Off-Gas system reerence Table 3.4.1, item 34.1-14, whichorezits water cherristry ad ore-tiren inspecion program for verification, However the taie 2 lir itears do not oret the verification pogram Thie isttsesasie issue qestions G.3.31.2 ard T.3231.2 399 Closed rT332-P-06]

Steel sortprerl types ejetor. feet wioherger

hheai, oritics, piping, purp casir thermowll, eand vatve boil in Tale 3.3.2-14-19. Off-Gas system ro-etere Table 34.1, ite 3.4.1-2, which credits water charistry ant one-tire irspection program for verification. Howe Te table 21Ine iters do not ereit the verificaton program THi sithe ia aseesqeestiaw G.33.1.2 and T.3.3.1.2 4M Accepted

[T.332-P-071 Table 332-14-27. RfWCU systemrr sl component type heat eet-nger salt, ins reated water enirasnert withan aging sffect does o mteriar. PNPS credits Water Chertatry Control - Closed Cooling Water program and refere-es Table 33.1. line item-31-17. Howe.er, tine item 33.1-17 addresses Water Cherristry Control - BWR programt StAid lineitem 3.3.1-47 berderenet, which addresses the Water Chesristry Control - Closed Cooling Water f[ the seaes hEAP eoatntion? Plesse suppilenan the LRA emcordngly.

Response

trnce The Ore-Time Inspection (OTI) Program is appicble to each water cheraistry control program, it is also aplicatle to each time item That credits awater chrristry control program ILRATable 34.1 indrcates that The One-Tire Inrpetion Program is medited along with the water chetritry control programs for Tiesitees Tor which GALL reortomedso asone-tire inspection tocornirm water oheetstry coarol. Table 2crecits the OTT program throug reference to the assoiated Taibe I tie Item.

Tide reruires anarrerit tothe chemistry program descriptions in LA Appendices Aand Bto clearly indicate that the One-Tirm Impeotion Program wilicordirm the elfectiveness ofthe Water Chtwirttry Conerol - BWR, Water Chestietry Conirol -Auiliary Systesre and the Water Cheristry Control - Closed Cooling Water program.

TH. item is Ioeoed to hem 372 Sirce the Ore-Ties Inspection (OTI) Progeam is applicable toeach water chearistry control program, il s also aplicable to each time item that credits a water chemiary cotrol programu IRA Tatle 34.1 inldcates e Whe One-Tire Inspecfion Program is merited adong with the water oherniatry control prograist for time itere for whichGALL reoorrnet asoree-le ireIepaction toconfirm water cherristry cornrol. Table 2 creits Whe OTT program through relerence tothe ssoiated Table flies item.

Thisrepores anamese ienrt tothe cheristry program descripteon insLRA Appendices Aand BSto clrly indicate that the One-Tine Inspection Program willtontirm the eltetiveness of the Water Cheristry Coetrol - SMRt, Waser Chelistry Coerol - Aetliary Systere and the Water Chertistry Conrol - Closed Cooling Watet prog-s.

This ilem is doed to Item 372 The appropriate ernter for The tast Three eolur for the ines in Taile 332-14-27. RWCU system, steel arporert type heat esheger shal. intreated water enmirotaraet witharealiry effect dt Ifsde. rmaterat. eWVlC2-14 (A-25),331-47, and Thie requires an trent tothe LRA NRC Patel, Erach Patd. Erach PaFd, Erach PNPS Lead Froa*argwr, Frorelaeger.

Ungerdter, PAe 31 o"77

James Davis - AMR -,Report to the NRC.doc.pdf Page 32]

Number Status Request 401 AMWed

[T.3 32-P-C0]

Table 3,2-14.27, RWGUsysterm stainress stst corpoanet type orifice, intreated water emiroosnent withai aging effect of dis of material, raleferes Table 3.3.1, [ine item 33.1-17. Howe-er, this line itan is in steal Should line 41erw 3.3 1-24 bereferenced, which addreses stariness sted onarwws for the s-EaAP? Pleese supplmenl the lRA accordingy.

402 CGned 3.5221.4-H-0 11 Loss d material th to G-erl, Pitting and Crevice Covrroioni PIePep wlisn for your tast atemenet, in tWe e806ia1 en it said.Theraeor.,

eigificntl corrnsion f lthe dcywell shelt is rot enpntsd. Doese this mal you DOhce heae ncrrosion? If not, wy signiticar?

40 Ciessd

[3.5.A21.7-H-0 I]

Stress C erroion Craecking (SCC)becones signtficant for stenless steel if a tensile stress and a corrosion eniroaseel mist. The stress may beapplied elerned w residual (Internal). Visue VT-3 saiminatiosm twy be unable to detect this agng taeft. Potential susceptible campanents at PNPS we penetration sleeves end bellows.

Please identify the GOth tmetheod od enasinstion toddtect this style d effent?

4D$

Closed

[35.2221-H-0 11 Aging of etrctures not oeed by Structures Monitoing Progrear Do you (PNPS) heve aeny operating epenisnet related to the enes? Plsse, prnnide the details.

405 Cloeed

[13.5.2221.8-H -01]

Lock Updue towear e Lctulrile Radial beam Seats inBWR dryweIl and odher Sliing Support Surfaces.. Ac indloated in this eltion thSt ¶...lock-qp due towear is t wnaging sffect requiring rreregerst at PNPS. However, Lubrite plate, we Including within ths Structures ittoring Program end Irenninse Irspection (ISI-IWF) Progrmss..w Plese provide the cro-s retecence inbstween these twoprcgrass.

Response

NRC The approprilte Table I ltnn entry for the line in Table 3.32-14-27, Patel, Erach RWCU systsm, stainless sled corrponert type orilice intrested water enwirormeil with an agng difect f iose of rmiteriai, is 33.1-24 This re*ires anencnenva t tthe IRA PNPS Lead Ungerietler.

As itatnd inSecion 3.5221,4, PNPS inspections ofthe drywall Hcaer Dan shall bdlow floor levnl idenitifie no eidence of corrosion di the drywdts s"l. The drywell shell sled has acosted surface and nw degradation of the ocating was Idenlified The statemenl in questi*n is not adretessing the current socition bPt rathe the conditions etd inthe Mutre, It isdifficult toy there willbe aiboutely noonrromnin the future, buP there is reasoires assurawne that corrsion, it any, will not besigfisant oi meaningful with respect to degradationc The doher method whichrmy be used toIselect cracking is the Hcang, Dan mistlng CoGtainrernt Leak Rate Program withaugmaesed ultrasonic mares. OGsemved eordtisrs that have the potential for irpaecting an inended Icrution are ealuated or corrented inaccordance wit the ecorectiv action proeess The Cortairredl Leak Rate Program is described inAppenx B.

As stated in Section 32.22t1 of tie LRA PNPS has no strentres Harng Dan that we not covered by Structures Moitoring Program that ene withs the scope d licenes renewal and subent to ging lrnegsret reniew.

The dxite plates associated with the radial beem seats eansr Hoan Dan Impected under the Structures Monitoing Program The dubrite plates associated withthe torus support seructure ene Inpected by the ISI (QWF)program Ahris5i, Resa Ahrti, Reza AhrabPi, Reza Ahrabli, Raez PtW 32d "77

James Davis - AMR - Report to the NRC.doc.pdf Page 33 Number Status Request 406 Closed 13.5.2.22.6-H-0 t1 Aging Support rod cevered by Structures Monitoring Progran Please proide:

I eor. irtorrmtion is needed about bilting omaerial wsed instructuarl appdicatione a PNIPS ircludng Group 81.1 applistions Whn are the beiting mrterials cwed? What are the rntina yield strenghs and upper-bond as-received yield strengths? Descrihe the PNPS resolution of the bolting irntegrty generic issue, asit retates tostructusal bolting Was any structural bolting identified as potentially susceptible tocracking sdue to SCC? Gas any structural bolting replaced as part i the reeiluion?

2 Desorihe the scope and AMR for Class MC Pressure Retairing Bolting Hto istoes o preioad rnanaged?

407 Accepted a3.51-13-H-011 thTable 352-1 onPage a5-51 dithe IRA. forn eniornape Beloves the AWe shown is CIt-WE, which is a phane-pecific A*IP. A Note C hse been asaigned to this A

i nhe it, conpo isifferentl. but consistent with rretiald, ewnironmet agingeer and aging menagenGt program for NUREG-18t1 It-item This AMP is neistet wih NUREG-801 the GALL description Table I ine iten 3.5.1-13 bellows. Explain how ft plaot-specific PNPS CII-tWE AMP iscorsistent with the GALL specified AMP.

Response

Need claritication. What is meant by 1.he bolting inlegrity generic

1) Bolting mnalrial s PNPS comists of A325 -Type I cootorning to ASTM-A325 adMA490 Type 1 coontoring to ASTM-A490, per PNPS specification C-94-ER-C-E3. The nominal yidedstrength tor A325 is 92 ksi and for A4M9 is 130 kal. For structural bolting applications. PNPS is consistent with NUREG 1801 in noesngitng the eifectt of aging withthe structures monitoring program or ISI (IWF). as applicabe, No PNPS bolting hes been identfied that is soliepd.ibe to sCC.

2) In general, PNPS manages lose of material too bolting with vialo imptonsti For structural boIting the visal nspections are pert of GAe Structures Moritaring Program Loss i preload due tostress relaxation (creep) would only bea aoncern invery high ternperature applications (I> 70F) as stated inGhe ASME Cods, Section i, Part D, Table 4 No PNPS structural bSeting operates at >700'F.

Therefore, loss of prlsoad due to stress relaxation (creep) is rot on applicable aging effect for structural boling Other causes of toes of preload include inadequate bolted joite design and inaefective tonirta nce practices. Lows oi prload due to these causes is prevented by itncoporation of irdustry guidance for good bolting practices into PNPS procetdures for design and rnanterence ci hooked jints.

Une item 3.51-13 addreses steel, stadness steel eemeneots dissinilar nisal welds: Sus; venoline; vent header; vertline bellows a downcomers. For PNPS verlline bellowsan aesociated welds, this line item is consisten with Gre NUREG-1i0i AMR

results, but the PNPS CII-IWE program descrihed inApperdix Bis a rsant-specific progaam The Drywalltotleus vent line bettows item on LRA Page 3a5-51 relerer*s line Item 35.1-13 and correctly indica*es Note *E¶.

For Gt BEsloos (reactor vessel Gad dryweil) line item in Table a&52-1 onPage as5-51 cithe LtA& reeorerce toline item 3.5.f-13 is rto approprisea The Table 3a52-1 line item *BllOWs (renctor vesel and drywell)'and the corresponsing line Item inTable 4-.1, Page 7d-13, were inredorteotly intluded in the LRAand sheoud be deletedi The reactor vesedl and drywell bellows perform nolicese renewal intended functim Th..e aoponerfn are nro wasty-ralated and wea ru reaired todemonstrate oepliancie with regulatiom identified in 10 CFR 54.(a)(3). FPilure iGthe beilow will tot provern satisfactory accomnplishment of a safety function Leakage, if any, through the bellows is directed toa drain system that prevenos the letkage frto contacting the cuter surtae of the drywil shall.

Deleting the line items discussed aaove requires an amenedmen to th IRA NRC PNPS Lead Htong, Dan AMthrei, Rea HIoang Dan Ahrabl, Rears PieSd 27

James Davis - AMR - Report to the NRC.doc.pdf Page 34 Number Status Request 40B Accepted 135.1-16-H-011 In Talne as.2-1 onpage 3.5-55 ithe LRA foe Primary Conlairanrt Electrical Pantl ration seals and sealan, the ASP shown is Strnturess Nhito*erng The applicarnt is asked to verity that the CII-IWE AMP will rot be wed instead to manageg the agng of the moistse barrier.

409 Accepted 3-S 1-44-H-01]

In Table 5.2-6 on Page 3.5-83 of the IRA, for nonroril-seals and gaskets, rmterial nubber In a protected front weather envronesnt; the aging effects areornacking and change inmatertal properties. One oi the aging management programs shown is the Strutues Monitoring Program The GALL line Itemn raefenced is lI.-I12 and fle Tab I refereneo is 35.1-44 The roe shown isE, a different AW than shewn inGALL Ho-ener, GALL Line Iten flAS-12 and Table 1 Umne Ite 35.1-44 both specify the Strnctures Monitoring Progranm Explain why the nute chewn is net A insteed ofE for the lower hall oftIie AMR tine itea 410 Accepted 13.51-51-H-01]

In Tale 35.2-6 on Page 3.5-73 di the LRA, fte nornneriri electrical and instrumenf pan alWe aed encloaes, rmterial galvanized seei ina protected tron weather enirornment th agng eftcat is rno The GALL line itern referenced in 111.f3-3, whichnisiothe fGtlowing conponents: Support meankers; wehde; bohed conrnetion; support anchorage to building structre, Explain why the LRA AlR line hem hes a Note A shown instead d a Note C, different component with respect to the GALL line itwe Or as an alterneftive a letten Note A with a enaier otne explaining that Ghe ocel-n is different.

Response

NRC PNPS Lead PNPS primary onrftarnrera does not hve a moisture barrier.

Hneng, Dan Aerabs, Reza Therofree an AWP is not rexired. The roinoenoed ine Item on Page a5-5s applies only toprirnary conrtainreenl eletrical penedration seals and sealart.

Table Line Item 3.5.1-16 willheupdated toreed: "The aning etlects cited inte NUREG-10It Item are less of seaing and leakage LSn of sealing is a cornsoersce oi the aging effects cracking ard change in maleria propeties. For PNPS. the Cortainrent Leak Rate program manages cracking amd cherge inmateial properties for the primary conrainment seals and gaskets. There is no moinstre barrier where the dthywd Il st hd ell becomes eatbedded inthe drywal onrees floor" This regUyres ananenfimert tothe LRA.

InTa.le a5.2-6 mnPage 35-83 oithe LAP for conponenrt seats Hoang. Dan Arabli, Reza ad geskets, mtterial rutber ina protected frotn weather erNironrwet, Note rE*

was used becauee it appliie io the top hWf of Ghe li-nit-The IRA willhbela rilied to indicate that Noe -A" applies to the lower half of GA line it This reqnires eeaerrenront toGthe ISA NUREG-1s8l doe rot menion eventype ofcomponet tht may be Hoee Dan Wahldi, Rena stject toaging nngemnent review (elg, panel Iseot in NUREG-1801) nor dtes the tennirtiogy used t a specific plarn always align with thet used in GALL Consequetly. matching plers cor*ponents toNUREG-1801 copnrents isetten subjective In this psericunar case, panels, winch hwen nospecific Itnctine other then to spport and protect electrical eqUipre, were conidered support mserbees and Note Awn appliedl The uae ocithei Nte A or Ches neirmpact wnthe agirg rmanagemenr relew resdlts Note "AwIllbhenhrged 5oNotet C'Ior ooronet dectricaland Instrunenl panels and enclones, material gelvanized steel ie protected from weathen eriiormene inTatle 3s2-6 on Page 35-73 oithe LRA Nochenge is requiredroethe oGheA erries for this line Iter This requpres annamerdmen tothe LRA FPe 34d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 35 1 Number Status Request 411 Accepted (35.1-8-1--011 In Taele 35`2-1 on Page 15-54 olthe LRA tar cornporeni Twa.u shell with the aging elfect orqcking-atiguet, the nrt.

essigeed I. E Note E.is onsoetent withNUREG-1801 reerial, eironment, and agin effect bIu a different aing management program is credted Explain why this rote isE when the AM' shown for this tineites is TLAA and the reererced GALL Une htsm B,81.1-4 alsospeclfies aTLAA 412 Accepted

[15.1-5-H-011 LRAtbWe s5%t. Mere Numiber 3.5.1-S, has the following statemert under the discussion cohumnn "Thadetywl steel where the drywel ehell i. ertedded is irepected in

... ord-ne withthe Conlairenera Ineervice Itrpection (IWE)

Program and Structures Monloriong Prograrr". This is er tifficult Itspection Chang.e INs dscussion statemrent t.

agree with IRA Selono 315.22 1.4 that states: The t&y.el steel shell art the ois.tue narder whein the dry-well s"ti becomes erbed in:he drywell crncrete ito are inspected inaccordaree with the Cortasnrrment Iteice Inspection (WE) Program art Structures Mnitoring Program Reponse NRC For Table 3,2-1 on Page 35-54 of the IRA I.o component Twiu Hoang. Dan shell with the aeng effect cracking-latigue, Note "E" willhbecharged to Note "AW.

Thisrrettieseanamenrdtern tothe IRA For LRA Table 35.1, fes 3.5.1-5, the disoussion in Section Hoerg, Dan a5`.2.21.4, Page 3.5-9, should hae the relerence to.noisture berrier deleted, sintethe PNPS dryweldoes rut conrain thisoerraity.

For IRA Table 35A, Itaers 3.5A-5, the discussion column should read "The drywell steel shell and the area whie the drywell shell becomee embedded inthe drywell cocrele foor we inspected in aecortance with the Cornairern Ieseroice Irnspection (IWE)

Program" The last esterce of the first paragraph in IRA Section 3.5.2 2 1.4, should readc "The drywell steel shel and the area where the diywds "I becomes embedded inthe dryweltl creee floor areinspected In accorder-e with the Contairnrernt Inervice Inspection (ME)

Program" Thisrequires anamenmenhe tothe IRA PNPS Lead Ahralbi, Reza Ahreali, Reza FPaS3 d 77

James Davis -,AMR - Report to the NRC.doc.pdf Page 36 Number Status Request 413 Accepted 3`5.1-9-H-01l IRATable 351, ltwe Number a5.1-9, has the [dlowing state eenl unde thdiscussion columr Nd applicable See Sevts 35.221. ThNsshodd bereed as Section 35.2z21.6.

However, the fdIowing slaternet is eade in LRA Section 25,221.6. 'Fatigue TLAAs for the steel drywell, tor.s, and associated peritrastione e evantualst and docuewnted inSectSon 46." The-wporrerds associated with IRA Tale a5.1, Iter Narorn 3.5.1-9 ar pevelratite sleeves, penetlation Iblows;,ressilon pool shell, utraced dtrwrs Explain how Iaew rnuber 3,5.1-9 is ret applicable when a fatige TLAA has been pertornsl lor the tore and penruratione. Explain why the VeNl lire, V header and vent linebellws are ste listed in IRA Sections 35.2Z 1.6 and 46 as referenced inTabi e 351, Une Iee 35.1-8,

Response

Fatigue anlseys have bes evnluatede for the torte, torte veal system and torte penetratiwe. The following line willbeadded to Table 3.52-I: "Tortsrechanical porenratlre //PB, SSR fl Caotn steel ad Prolected ftore weather R Cracking U TI.AA-mele fatigu Ul ILBd-4(C-13) J135.1-9 XA" The evdtation d the "for vent syfsote latigtt analysis determned that it was no a TLAA The sigrnificant coriributor tofatigue dthate ven systes is post-LOCA chuging, asore sip.a-Ide eent As Shae will still beady o design basis LOCA for the lifeoal th plar, incdluing te period Of ale nred operation, his analysis is nro based an a litre-lirnited assumrptio and is not a TLAA Fatigue for the vert ystlem is eard-dirvess and is nrt anaga-reated efdect ThM olsvsis ss w

coluin entry bor Tabe 3.5.1 ant 25.1-8 willbe changed to reed as follows: "Fatigue aralysis is a TLAA for the tort shael Fadigue a the vert systel is sear-drives and the analysis is d aTLAA. See Section 3.5`ZZt."

The diseasie colurnn eitry for Table 3.5.1 itfm o5.1-9 wifibe charged to read as follows: "Fatigue arlysis is a TLAA for the torte penetrations. See Sectios 3.52_21.5 Sectiort 25221.6 willbechenged foread asfollows "TLAAare evaluated iseccordance with 10 CFR 54.21(c) as docueleod in Section 4 Fatigue TLAAs for the torte and assocrated penetratiose are e/vlutew anddtcunented in Section 46" Section a5.23, Tirne-Usited Aging Analyses, wilibecchanged Io read as fllows: "TLAA Idetified for strtural ecaivoarss amid acasredities rnblsd fatigue anayses for the torte and forte peretrations. These topics are discussed in Sectivb 46."

Theese chnges requirevannenmeet to te IRA NRC PNPS Lead Hostj Dan Ahabli, Revs PSt 36d 77

James Davis - AMR,- Report to the NRC.doc.pdf.

Page 37 Number Status Request 414 Accepted

[3.5.1-12-H-011 LRATabile 351, Iten Nueber 3.51-12 and 3.5.1-13, under the discussion column, does not make relorence to LRA Sactio 35221.8 torfurther evaluation Explain why this

=ir is man d n

lothe further enalcation section Explain the ee to, augmented ultrasoric ams to detect fim cracks sine a CLB fatigue anelysis does exist.

Response

Alink fram items 3.51-12 and 35.1-13 will beadded tosection 3221.8, Section a 5221.8 should state "Cycliclocwing can lead to cracking of slee and stainles stled penetration bdlcows, and dissimilar metal wslds of BWR eonrainrstes and BSWR suppresion pod shell and downcomers."

Cracking due to cyclic Ioading is rin epected toi =

inthe drywoil, torus and sooiataled penetration bellows, penetration elens, unbrtaced dcwlormers, and doissirrilar mal welds. A review of plant cpersting experience did n identify cracking ol the cori rs and primary containment leakage has not been tierlified ass ncroti Nonerftal ess, the Cortasinror Leak Rate Program with augmreted uitrasonric enacts and Conltirnmed Iroeice Inspection -IME, will corntinue obe waed to detect cracking. Ob:ented conditions that have the polaerial for impaoting en Irnended tunction wo enaiduaed or corrected in accordance with the orractive action procens. The Cotainmeet Inservice Ispclion -IWtE aid Cortalrmn t Leek Rate programs ae desoribed inAppetrlx a Thiarequliree anertracs tothe LFIA There [a no gap to seal at to joint between the ortainmet drywdl s"Il and the concrete floor. Concrete grout is poured directly against te drywell shell. The installation is shoen as Dala otn Drawing 0-71. The C*otalnrent Inservice Inspection Program incluides inspection of the ont.

(Also see audit questiao #408 which addreesee chtnges to IRA)

NRC PNPS Lead Hoang, Dan Arabli, R-a 415 Closed 1351-16-H-01 LRATablae3 1, Itam Number a5.1-16, unde to discesien eciucrs states that seods and gaskets we rno Included in the Contlinment Insrice Inspection Program at PNPS. One of the oormponres for lids ilen matte is snistr. baerrics. Explain how PNPS seats the joint between toe contanlmet drywall shiel ani drywed concrete flco if there ise momstccure barrier. Explain why the inspection of ths joint is no part otihe Coraienmer Inseace Inspection Program.

416 Closed (351t-3-H-011 For LRATalce 3.5.1, Iten Number a5.1-33, proride ft maxirruam termperatures that oncrrete experience intGroup 1-5 srtrctures.

Hoeqi Dan Ahrali, Reza dhrabli, Rýa The msirmusm bulk a s

arm asiers temoratrcm for Groups 1-5 occurs Hoa-Dan in the drywell aid is an average temetrsture of 14rF, raltrce UFSAR Table 5.2-2 For structuret outside the drywell t bulk wea mincmurm terrperature is 12O"F for Groups 1-5 structcree as identified inTable 10.9-2 of PNPS UFSAR. Concrete withintoe drywoil conrist of the reator pedestal, sacrificial shield walld the drywdi floor. Assurance tal bulk concrete ternperatlces within the dywell grasn lo t degees Fie ditained through tnttrtaring average bldk cntainmsnt temperature withntohe uimits allowed by PNPS Technical Speciticatio Section 22-H (Page 342-5). Althogh upper eneations of the dywll my exceed IrVF, the co-arate of the drywell lsat lower denaliom. The drywel cOling system provides cooling toensure telasprature limits re in exceededm The highest concrete inthe dbywell is lthe sacriliciad selda wall. The concrate in this wall is -n load bering.

FPWe,'d ;7

,James Davis',- AMR - Report to the NRC.doc.pdf Page38 Number Status Request 417 Accepted

[35`1-34-H-01l LRATable 3.St, Be1" Number 351-34, under the dscussion cduMi does n make referenae toLRA Section 3522224 (1) for lurther ealuat ion Eoxplain whythis linkis not made tothe urthe eraiuetion section.

418 Aaptsd (3.5.t-35-H--01 LRATable Te5.1. It"' Nuwter 35.1-35, under the diacosion edumn, does not make raterence to LRA Section 352224 (2) for furher evaluet ion SExplaen w

this link is iot made lothte further ealuation aeetoli 419 Accepted (3.5.1-36-H-01O LRA Table 35.1, Ithe Nuiter 35.1-36, under the discussion cewun, does not iak eraten toLRA Section 3.5.3234 (3) for ul enalud ion Explain Why this [itk is int rate tothe further aluation section. The ttemnrt:

• See Sectio5 3,5.22.21 (5) for additional discussion' reeac utwthar clatification that tie section is for Groups 1-5, 7-9, however It wmud apply toaccessible Group 6concrete.

Expain wmt LRA Section 3.52-2234 (3) lists crecking of orate due to Siroes Corrosion Cracking (SCC).

42D Accepted (3.5.1-40-H-011 LRATablea321, hem Nuiber 3.51-40, odor the daocusion a*tuan% state*a...Ptnl aspeiernce has not Identified reduction incorordte attncr capacity or odher concree agng machanism.

Nonetheless, the Storuturee Monitoring Prograrn wiitoonirm absence oaging effects requiring nanegemed for PNPS concrete ormuae erns."

The project teamrn onroN find ani AM00im1item inTable 2for thde c onent (Building concrete at locations of expaesion and grouted rchors; :

W pads for sepport base plates).

Provida the Table 2 nmbTe, LRA page enuber, and conrroner for where this Ah line itm is evaluated and shown

Response

NRC NUREG-1800, Boem Nunt-e 3.51-34 inrdicatts that uhr eaeloeualion Hosing, Dan is necessary only tor agressive eorironrneets. No re*ernae was provided totfr0her evaluation LIRA Section 3`22324 (1) since the PNPS eorironrne is not aggressiv as noted in LIRA Tatle 3.5.1, Stom Nuibor 3.5.1-34, under the dis0*0siom codutnn For coarificatu,% LIRA Table 3.5.1, Line Itern 3.51-34 discussion will be rwrised toadd "Sen Section 3.52.22_4(l)'.

This reyuirescnaaetdornt tothle LIA For clarification, LIRA Table 35.1, Sem 35.1-35 discussion wilh be Hoeng Dan rwised boed retlerte toSecton 3.2-2.24(2). IRATable3.5.1, teor 35t-35 discuhsion will be reised torder toAC1 31t inlieut ACI-Mll, since 2i proided reerence toACI should have been ACI 318 ard not AC 301.

Thsre uireyi an ecernndma tothe LIA IRA Table 35.1, ULe iteni Nuntr 3.5.1-36 dscusslon willbe Hoang, Dan laised to red as lodiowsi "Reaction with aeggegtes is net an applicable aging mrechesom for PNPS conrete ocponents. Sen Section 3522.21 (5) (although fr Groups 1-52 7, 9 the discussion is also applicable for Group 6) axi Section 3.5.22.24(3) adecitiorSl decssion, Nonetheless, the Suctures Monitoring Prograo will corirm She abeence of aging eafeots requiring oegeret for PNPS Group 6oororetea orrponent."

Due to an actrindstraive oersaig the heading of LIA Section 35.2.2324 (3) irndvertenly lists cracking di concrete due to Stress Corrosion Cracking (SCC).Ttis section heading ahould have begun with 'Cracking Due to Exparmi on and Reaction with Aggre*ate..n.

Stre.

corrosion cracking is ret diacussed In the body of this sectionr This change requires anamanderst tothe IRA Buildng ooncrere at locations of epainsion and grouted aohars; Horng Dan grout pads for support baee plates are shown as teouhdatiorn aid "lRector vo ela suppo pedestal in LIRA Table 3.5.2-1 (page 3!5-ý5), at.ocalaoir inTaes 35.2-2 throigi 3.522-5 (pages 3.2-59, 35-61, 35-64, and 3.67), aid as "Eqeipmnt padiloundaitona 'in Table 3.5.2-6 (page 3.5-80). Furtha erkaluation is proridd In LIRA section 353.2326(1), page 35-15.

For clarificatiorn LRATable 3.5.1, Itec Nurber 3.51-40 discusson willbe reised toead "See Section 35.2.22-6(t)(.

Thisrequiresean iie t tothe LIRA PNPS Lead Ahrabli, Raze Ahrabli, Reae Ahribli, Raza Ahrabit, Raze Pawge 38d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 391 Number Status Request 421 Accepted

[35l-50-H-011 LRATable 3.51, Ite" Nuiber a51-50, under the discion column, states that loss of materlal is rna applicne toPNPS. NUREG-1833 onPage 931r Iter TP-6 states anapproved precedet mists for adlirg ths restatred, envirortient, aging effect, ard program coroniration tothe GALL Report. As shown inRNPSER Section 35242, galvanized steel and stainiess sted inan ould:e air e"ir.nret could rsult in l*ss of rrlerial due to constant watting and drying csndaiions. Aurinrn would also be suscerhible toea eimilar kindic aging effect in the outdoor rnircnren Preside adscussion the actual group B2 ard B"g v*eaized steel, alumiirm and staniess steel PNPS oacirirs whach we within the scope of license rereial and mipesed toew outdoor air on'irournext Discuss the Iocaticn of these corsoneirs at PNPS aid how they we protected fror eonstanl waiting and drying condtions.

422 Accepted

[3.5.t-52-H-01t IRA Table 3.5.1, ite Nueser 151-52. under the discussion cunM acrte thea toss o

-hectanical function duetothe listed rmchanisne is nian aging cited. Proper design preytes dstortion, overload, and fatigue due to vibtorey ad cydicthernel oede. Explain how t

otar a

n

rteice functiort i

rnging rffsct witchneeds tobe rarged forthe period al exterhed opreraio tproper design presets distortiona overload, aid faigue due.tvibratory sad cyclic Iheirel oads, erplain If there has ever beesl eargart faurelatePNPS duetesaay c, these earcitre. Explal nit there has eer been ornponeaiel bure in the nuclear Industry dM toany ad these conditions. Explain where sliding support besring ad sliding support suiaces me wsed insconrpni groups B2 and B4et PNPS and provide the erniroaera Itay wre exposed No

Response

NRC For LRA Table 5t, itea Ndaterr 3.5.1-M0 the discussion -clI Hoaeg Dan should read. *This aging effect is rneraged by the Structures Mottorinig Progrea."

Coaporents that ay beonaidered inthe Basd B49rgping consist of those line iterns in Table 3.52-6 with rmeerials galvairzed sted, alurinurt, or stairlese sted.

Ths reiuires aniarrmnersar tothe LRA Lass of mreerial Mue teao rosion is an aging efect tod can cause a Hoang, Dan los ci irWended fuitionh Loss di aechracil urtiton would he acrnidered a less of irnesded function Lo-s di iecharical function Is i an aging effect, but is the result oe aging effects.

There hers been conprerw failures intte industry dMe to dstortion, overlosad. and esceesive vibration Such helures typically result fro ire* adeite design ix welts rather than the aelects of aging Failures due tocyclic thwnW todm are very rare for structural supports duetotheir relatively low terpeeaturee.

The aliding surface riaterial wed at PNPS is lubrite, which is a corrosion resistanl raterial. Corporasn' me inspected under ISI-eIF for torus saedle supports and Structurea Mueoaitoring Progame for the kbriteceipc*rasis of racial boom seeds. Part operating experienxe he s t identriled failure of liuirite ooernpoarts used in structure l aplicaion. Nocurrent industry mperiane has Ideriflied failure arssciated withlutbrite sliding suaces. Cononoerers ssociated withB2gcoqng me lirritedt tethe beeus radial beir tis and support saleces. There me nosliding support surfaces associated witthhe B4doonpoqtnil grouping for sliding turoes ca PNPS.

For clariition, LRA T sble 3.5.1, enm 3.51-52 will be revised to aerd aes floows: "Las of eachanical lunctson de tolthe listed rhenisis is ina anlagng alfect. Such failures typicaily result froii inadequate design or operating eoreds rather than from the efects of aging. Failures due tocyclic thermal oads me raref-r struitural supports due to their relativly low termperurei."

Thisraituiresa namerndrert tethe IRA.

PNPS Lead Ah'rabi, Reza Aerili, Rntz Paig 3d 77

James Dav-is - AMR - Report to the NRC.doc.pdf..

Page 40 Number Status Request 423 Acopled (3.51 H-011 LIATaboe 3.5.1, Itern Nueber 35.1-54, under the discussion odwum states tha loss of echwnic function due to te listed suechnisoo is no naging efect. Prope design prevents distortion, overload, and fatigue due to vifrfory eand cysjlic nhermal loads. Expiain how tess of neeohedila-luton due to corrosion is ret a aging dect whichneds bobse -ged for the period otf ended opara" if prop.e design prevests dtstorticn, overload. asd fatigue des tovibratory and cyclic thlem-e loads, explai if fhere ins eoer been asonorent failuore at PNPS due toeay of these conditios.

Expai n if tiere hf s ewar been a conwonent failure in te nuclear industry due toany of tlewe conditions. Explain what PNPS imspacts for dauring VT-3 visual esadreitions to group. B1f, B1.2 and B1.3 conpornents oraer ih Ilesoioe Inepestion Proerarn during its carreot license and atls anticipated VT-3 visuel ssdetizore deuar-tg its possblte Wended licese.

Response

The discussion for tern Numnber 3.5.1-54 was not irnyirng hat falures have not occurred, but t loss of meceltroa function is rot waging effect. For license renewal, Entergy iddreifies a ofrt.

a aging effects the oan cause Iossof inreaded funrtioe Loss.t intended function includes Ies of rnschanical fret ion The loss of functon is et ornsidered an aging effet. Aging effects thae could csuse loss of escharicajl function for omponentse in Kenn Nurster 3.5.1-54 se addressed elsewhere in the aring mnrwagrnse reviews. For ewarrie, lose ao erntorial due to ans reschaism is addressed inTable 35.2-6 under listings for ornponent atd piping supports AWE Class 1,2, 3and KC (Page 35-71). and conponernt and piping saegoorts (Page 35-72).

Cosrqore lailuores at PNPS aea inthe nuclea industry here certainly occurred due btoverload (lypically ceusetd by an esent such as water hernnse) or vbratory and cyhiotherreal eads. Because of the low operating terpaturres, failures due tocynlic hsemna loads see mtremely rare for stbuctral corrtodties. Failures due to dstortion or vibratory loeds have also occurred due to inadqeqate design, but reely if ever, due tothe nermal effects oa aging PNPS insyptions darlog VT-3visual sarrinahions of groups Bf.lt 812 and B1.3 eorrnponels sae ronasterl with whal is reeuired by code Fortclarification, LRA Table 3.5,1, Ite 3.5&1-54 willbere.siow to etate: "Loss Of rnschenical function due todiototion, dirt, oerload, fatigue de tovibratory, atd cyclic thermal owads is noh swasing dffect requiring rra-gernet Such failres typically result ftrum irnadequat eeign or eseets rathes fhan the dffects of aging Loss of talsterialoe To orroeion, whichColid case loes of amscaical function, Is ddreessed under hten 35.1-53 for Groups B1.1, f1.l.

and B1.3 suppeort menmes."

The reqirets enariedren tothll LIA PNPS included lee exansion joint with the eshaust piping in Section 4&2 of the LRA PNPS dooeuerenation does not identify ary design sode for the espsrielon join sqearate bone the ewheust piping (B31.1). Partial cycles we not a concern for the desel esheust systese sinre the hesust tenperature is asesured to reach norne l operting smserature with each abart athe egnine, The paneeion j(tnt is eposoed only tothe sane nuber of full cycles to wa-chthe rest oflhe piping iseeposed. The epasrelon jointis designed specilioally bosoormnedate rsovernenrt hat ould reult free the henting and oooling oftheheaust piping inosthm words, its design intent is to have behte r fatigue response than the rest of the piping Theloroe, PNPS assumsd the piping woad be sers limiting than the epeesion jsinr for the allowable nuerst of cycles prior to respiring waragerert of cracking edue tofatigue.

NRC PNPS Lead Hoang, Dan Ahri, Resa 424 Acoeted Table 332-4, Emnrgency Diesed Generator System, for eaten steel esyapeesion jtres inan Ibenerls ervrironmelt of et-aust geses creits the TLAA -fatigue for Manang cracking due to fatigue. TIAA section 43.Z Non-Class I Falgu assueses, ingeneral 70D0 thfrnal cyoles for piping syetstm, allowing as trers reduction taeor of 1.0 in the stress ardysis. ThIe is a good assutrption for pipa fittings, dt., however, mwy nh bea good assutxption fhr epaiseln Plesos ooreirmn if the mpefalon jornts anse ieludled in section 4.32, and justify thet the assumsption of 70M0 cycles is appropriate Patal, Erach Finrsn, Ron Pag 40d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 41 Number Status 425 Open-NRC Request As pt art the Therma" Power Optirization Project, GE performed another fatigue analysis. GE issued a report GE-NE-OOOD-00 0-1892-09, Ro. 0. M.rch 20*2 Thermal Power Optimization, Task-.3

- RPV -Streas Evaluatiors Thie report calcudated new CUFswhich in sme cses are difere*rt than what isnshown inth. RA, Table 43-1, 1,-inmua CUFs for Class 1 Coponeons.

The GE Reort, Section 3A, Results, states thait feedwater mozzle CUF recalcuaation Indicate a CUF that wet from c0. to<10.

Similarly, Table 33.1.3 fatigue smary, last colamn, indceat* CLTP/TLTP values Aga.in specific values ere proided for 3 ine ites, however, for fewlwater nozzle, only

<t 0 is aspecified.

Please justify what <1.0 ternt.

Please pronide a specific calculated valuei Aso, pleass justify why the revised TPCP CUoalna were nat identified inthe LRA Table 43-I, instead Itold alues calculated by ALTRAN Corporation in 1994.

Ae tihere olher LRA TLAA sections atfected by the TPO project, such as Section 42, RPV Neuron Embrittlearent Analysis.

Response

a) The Pilgrim records system had eno been updated to include the cherges in CUF due to the 2=0 TPO program intics tosupport LRAprepeaiorci TPO hs amtl imeact orCUF asdetailed in GE-NE-T0000-00 -1898-02, Ron I. 3120 Thi records system has been updated ard the PNPS corrective action program requires that the irtorneation heassssed for potenta impact onathar LiRA sections. PNPS will update LRA table 43-1 toircludt the valuis from the TPO.

In preparing the TPO stress ecauat isot GE reciewed only thme RPV comtonents whose pressure, tenperature, and flow cordttiorn were more severe due to the TPO ard withfstigue usage teotors greater thee 0.. Tise CUFs wee rent recalculated by tradtional methods, but rather were setirorted by conrservativel y soaling the stranaoo, dstemniting the code allowale ruriter of cycles for those stresses, then daternniing the incremental usage tactoror a group at cyclea considered in the original stress report. Bel-te n TPO.

the CUF for to teelewater snzle (Atran Report) was listed as <0c,

for the TPO ths CUF ircreased to <l1,0 No praise value was calculated. As stated in the response toQuestion 345. PNPS will perform a nI feecwater r-zle faigue anelysis prior to the period at atended operation.

b)Nother seniors ofsth LRA.reatfected bythe TPO. Th.

flueres wan ased in Section 4.2 were based onthi higher power lendl.

NRC PNPS Lead Pald. Erach Firnin Ron 428 Accepted

[T.332-P-0Sj Table 3.32-4, EWG Systet, page 3-78, for carbon sted

-pension joints. in an inrernal eanironmnrt of atheust gas credits TLAA-fatig to mags in. aring Wfect ofcrecking due to lotigm Pltese cenfirt it TLAA Section 43.Z Non-Class I Fatigue, includes thmessenpoerion joints. Aso, see TLAA question 8.

TLAAmetol fatigue is not enagng mremeg t program Urder the Padel, Erach standard IRA format, TLAAm-lal fatigue is Inserted under itn aging managemnte program ae soneniene toiredlcale that a TLAA for naal fatigue applieno that Iona iteo The carbon stal aspearion jrints are designed er ihe requpremrnts of ASav B31.1 for alimited wuiber t athermal cycleu. The ealuation of fatigue for ASMW B31.1 components is discussed in Section 4.3.2 The evaluation deternined Oat it EDG com**rerts will remaen below the cycle limit for OD years such that crcking is not teyctedt Frorbargw, Page 41 d 77

James Davis - AMR - Report to the NRC.doc.pdf

'Page 42 Number Status Request 427 Closed

[T.332-P-10]

For agng effect of cracking due to fstigu, PNPS has credited TLAA - metal tab" as an aging mnurgenr program for components ino internal enironment of

.o.heast e inTable 3.3.2-4, EDO Systems; hower. in Tabe 3.32-5. S0)0 System and Tale 3.3.2-6. SDG System, the Periodic Suillamn e and Prevenive M.

..enre (PSPM) Program isocredited, whichincludes vislod or rhto NOE teconicq-e to inpect echeuot system Vqio s Onnarge

-reoking Pleuse justify why the pSPM program is not credited for the EDO system coponentso for manrging agng effect of cracking It is only credited for loss f nmalerial aid touing 42B Cloud fT.3.3.2-P-ttj Table 3.3.2-9. Fire Protection - Water System. for piping silencer and turbocharger insan internal thest get erorweerlt withanagng effect of cracking dem lofatigue, PNPS has credited the Fire Profection Program to rige s aging effct. The program elsment S. Acceptance Criterie, is enhanced to verity thea the 0usdm engine did not exhibit igro dodegrauatiin while it was ruingr such as

..heast lge sakage PFeas. justify how the agng effect of cracking is enaedgl by venifying for ehaest gas leakage Iftere is leakage it Inmpiis. hrough-wall crack has oourred Verifying 'or leakage is eno nluadcste agingm "rgem"e programr fh marng cracking

Response

TLAA-mefal fatigm isn he waging manrgunen! program Under the standard IRA forhe, TLAA-,dal Weig-e is ineded der the aging meranaO progrem me converience toindimte that a TLAA for metal satigu applies to that line ftem The EDO exhaust systens aeredeeigned per the rectuirements of ASKE B31.1 or a limited mtber of thermral cycles. The waohration of fafigue for ASWE B31.1 ccnponarfo is diocused in Sectot 43.2 The etalustion doeterninr that the EDO nconrorts will remain below the cycle fitn for 60yaewr suth the cracking is hot expected The uheust systets for the station NLckoe uiesed generator and security diusel genordor arseno designed toha ode or stfandard wheretherma cycles are aconsider atior Therefore, the Periodic Steveillane ad Pre-ertive irherfance (PSPI4 program will nrnage or confcirm Sm beosence of cracking dem otlherrnal fatigue The aging effect of taligus cracking is roerstivel y Idenified loh the fire pump desad egine R the athest componer were designed per AS0E 831.1 code, alimited rorber of cycles wodd be the threshold or suseptibility tocracking dem tof licot.

Since the system is normally in standby and used primarily during tust leg his riulikely to reach any legitimate thresheold toprodc heligue cracking Furthermore, through moetoring and trending of performanrce data edwo the Fire Protection Program, cracking of system oocrpornefs wilhbeidentified and corrected through thS norrectrieaction program As described insection B.lf3.1, dreestion of degraded performs e produted corrective actiorn icluding engine replacemenr in202 prior to les of Irtended furtiohe Coreestpsly, oorlirned irnplemerfaflon of the Fire Protection Program prosidus ressornle assurance aging effects will be managed for theedead fire perp eaheust s*nystem. In addition, PNPS performr f rprerp inspectiony testing and mairhenree in aocordheee with NFPA 25 which would also detect the presencef crackirg intm urheust systen prim Or teen of irtlended fumetio This ften is coued lo item 378.

NRC PNPS Lead Patel Erach Uoyd, Ldead Pael, Erach Frobeorger, Pap 42CI 77

James Davis - AMR - Report to the NRC.doc.pdf Page 43 Number Status Request 429 Closed T3`32-P-t12 In LRA section 33.227A PNPS states that the corbon sted deed exhaust piping axnt omporents in the lire protectio* system is marnaged by the Fire Protection Prograt The FireProtection Program uses visual inrs*ot of diesd eoheaust piping and coeponrens to manage Ices of material i FirePre"etion Program (LRABS.13`t) iscretited hoe rrereing aging of these cospos artss, piease emptibn Why thee system coeporerns we ntl included in the program desoriptiono0the FireProtection Prograes Furthermore, no etranoement is addressed Urat would irnlude Uhese oopn~o rer inthe Fire Protection Program.

430 Closed

[T.33.2-P-13]

Sutbsequees torestlon T.3.3Z1, the applioant hes credited Fire Protection Program in lieu of GALL AMP )X..13B, Instection of terrnal Surfaces 01 Mlsoclareoes Piping and Ducting Compoents as reomenaded for GALL item V.D2-16, wh is referenced by the applicant for these line items. The GALL AMP )(1.1M3 sates that visual inspection 01 internal nres of p0a1 nt ssrr ionrws iperlormed drirg mainrerese or euteillsrce activities for viblet

/idence 01

-orresiss to irdcase posible loss of malerial.

Siore PNPS is using the Fire Protection Program in lieu of GALL AMP tAMO8, please =rplaisn hew the Fire Protetios Program performs this vual irepectiro As written insOe LRA, the Fire Protection Program is nor adetuate to mnage loss of maoerial for these corponents 431 Closed

[T332-P-O1]

Table 3.2, question I The PNPPS B1.12 Fatigue Moritoring iscredited for manngneg th agin effect tCracking fatigue fon comporents in the RHR (TableaNumber 322-1), ADS (TeNe Number 322-3), HPIC (Tale Number 322 4). RCIC (Table Number 322 5) systres. In eset cases the components have been assigned Note "A or Note C'. H-oever, the PNPS a.1.12 Fatigue Monitorirg program hes esoep on tothe GALL prograr, X.Mi, Metai Fatigue of Resctor Coolant Pressure Boueonry. Therdoret Note "C'should beNote D"Dand Note "AW should be Note "wE as appropriate for tiese com:onens.

Response

NRC The program description listed in Section B.1.131 matches the Pald, Erach description oited in GALL saetion XISe6, Fire Protection which includes the desel driven fire pumpy The eheaust piping wnd components nrepart of me tire purp. Enhaerarorts for ag.g manraemrnr of the esheast subeystem wre described for aoritoles 3-parasoders montoredlit pec ted and 6-cceptaere criteria of the progres This item is dosed to item 378.

See She response to item 394 that addresses taem in Table 3.3.2-9.

ParM, Erach For the piping omnponent line item inTale 33.2-10 that has irdoor air (irs) as ae emirorerrer ft Fire Protection Program Iecludes avisual inspection of the esternal surfaces of the Hamon system piping and tsts. Since esteM srfaces are represenatiove of irered surfaces that ne eposed tothe esame environment, the Fire Protection Program is adequate for rnneging the agng dfects of oosrorta reposed to indor air.

Thie item is closed to item 378.

PNPS Lead Frornerger, Frorebager.

NUREG-181 dtoes not "pesily XM1, Metal Fatigue of Reactor Codast Pressure Boundary Inthe AP oolumdn for items Idetifying cumulative fatigue damage NUREG-t801 Idertifies fatigue as a TLAA and raers to guiudce In SRP Section 43 which inturn describes trestrnae of fatigue in a vasisty of ways deperndng on te component. Since NUREG-1801 does rot credit the Fatigue Monitoring Programr, teoeptiore in tSis program have no besring on the dection of rates.

Pavinic, Wayne Ungenrtntr, AW 431 77

James Davis - AMR - Report to the NRC.doc.pdf Page 44 Number Status Request

Response

NRC PNPS Lead 432 Closed

[TrZ2-P-O2 ABolting Integrity Progaam willbedtteloped tat willaddrees the Pavinlcht Wayne Fronkabger, aging management otbolting inthe scope ol license renewal.

Table 322 question 2 The Bolting integrity Program will be irplemnted primr totto period The PNPS B.1.31 System VWakdon Pirogran is used to of aetended operation tnaccdance withtoonmitment nuweber 32 dilect LOM tfo carbon steel bolting Instead of GALL X,.M18 Boting Integrity. X"M118 invokes visual VT-I eaarnriation for This retuires an amendment tothe LRA torinclude descriptions of boitng testhan 2 inches indiameter. It is net clear if VT I the Bolting Integrity Program inlApderobne-Aand Bead to identify Isn ed for boting that ics raeined in accordance with the where the program is appicablae.

System Wetkdbwn Programn What standard in teed for visual inspection of bolting under the System Walkltown Program The ite is closed to Ien 373.

43 Cloed

[T322-P-Ca]

Sit e the Onre-Time Inspection (OTI) Program is applicable to each Paiinich, Wayne Frotebarger, water cherristry control program, it is also applicable to each lire Table a2?2 question 3 ite*nt that credits a water cheristry control programn IRA Tben 121 indicates that the One-Time Inspection Prog-n is credited Stainless steel el steel components that we emposed to along with the water cheoistry control programs for line items for treated water in Table 322 do not specity ore-time which GALL renootmina a

aone-line inspection loorirm water itenotion to detect te of material although Thee 321 chesrnitry control. Table 2 credts the OTI program througt indcatre OTt Add OTtasA s for thesea omponetis for reference tolthe associated Table 1 line iten consistency with Table 3.21 no provide a justification for not perforning OTI This reuires anaerent tothe chenistry program desnriptionr in LRA Appentices A and B to clearly indicate that the One-Tirne Ienpetion Program willcontirm the ectivenes of the Water Chermistry Cootrol - BWR, Wter Cheeistry Contrd - Auxiliary Systems and the Water Chetistry Coetrol - Cloeed Cooling Water programs.

Thie Iten is olosed to hem 372 434 Cloeed jT322-P-O04 Table 3,2, questint, 4 Bt is he Clener if the Syatem bWtkdown Program provides for irspection interiom surfaces of carbon steel cornponosta egposed toei-tor air for LOMt Plea*e prmiide detais showing inpection of interior surfaces tot the ornponert 435 Closed

[TF122-P-CB]

Table 3.2.2 cuestion 5 JeM numbern3 122-4, a22-5, and 3.2-t4-tB6 westcnlese teld Ppiping ooponalne (e.g orifices, strainers). Please eslain why Note *C'wa assigned totheme components.

The Syste*n Walkdown Program is not Ireneded tolnIpect interiom piping and ocimpoaret surface unless they have been aepoed for Inpection during mnintenence and reiars. As indicated inthe tables in Section 3of the IRA, the Syctem Walkdown Prog-an menages agng for etterrel surfaces of coneree.

The progran alsoa nages Je of naterial trorn inter surfaces insituatione in which internal and etarne m nete and environment oonbitetionw are the same such thet noterea sarface condition is repirnotsalin a Od interhed surface condition The varioue piping components in tabes 3.22-4, a22-5, and a32-14-16, towhich Note "C'wamassigned. have steam as the enviroiment. The eysteam represented by these tables we all ESF systems; however NUREO-1801 does hot include the combination of stanless steof ina steam environment ftotary ESF compnent (Chqter V). Consequentlyy, omparisons were made to steaw ad power otnveriont systems comortentss (Chaper VIl) where the stairiness ste team oontirnat to is addressed Since the systems do woe match, a Note "C" is applied Pevinich Wayne From-nhger.

Pavioikh Wayn Ungerntster, PbIo 44d 27

James Davis - AMR,- Report to the NRC.doc.pdf Page 45 Number Status Request 436 Closed (Taa2-P-o6]

Tae 3.2Z question 6 les nurnter 3.32-4-16, wrested piping oor'porrws (eg orifices, strainers). Please atypain why Note "C"was assigned tothese cormporst.

437 Closed

[T32.2-P-07]

Table 32. question 7 SRP-LR,3 5528 Loss of rtosrial due General, Pltirce and Crevicorrosion, Iool 3 provides or the veriication of the efotiowveness o the luricating oil progam through ore-time inspection os0*edeot sled cesponents at susceptible locations. Carbon steel cotrponets are rKd, specifically or through arepresentative cornponeni, suijected toa ore-tine inspection for lw ot materi ad..Atdd OTl AM's fto these omponts for cooristeroy with Table 3.21 or provide a justifiaotion for not perfortring OTI.

Response

The various sled piping ooros intaotote 33.2-14-16, towoich Note "C'was assigned, have stea, assthe Osvironrnert withthe aging ofect f sither cracking -atigue or loss of rnaterial The system represerned by tis table is an ESF systemr however, the only aging sftedt identified inthe NUREG-1801 ESF tables (Chapter V) forIcorn-ination of sled ina etoem environment, is flow odeerated oorrosion Consequently, soroearlaoor were mads to stoea and power conrersion ayotens comrponents (Chapter VIII) where the st-eel/stern oornbt tiot includes oracking -fafigue art loss ol material as aging effects. Shnoe the systers do rte matchl a Note wC' is applied Durlng the petorrrcwse 0*rouine d

irsertsewe onoorortnots that olortin lubricating oil, vsisel irnpections of thsee ornponets would identity degraded =osotions thet sdld beattributed toan ineffective Oil Analysis Program The oorrective action program at PNPS has alow threshold Ifr the ioentietioro oe degraded oorditions suoh thet corrosioý ororaokingo of oponerns would he identified ase not o0*tis program The reviewr o operwting experience a PNPS fhe the last floe years did not idettity awt

-onditios reports tha inioaded an inreleotive oil aawlysis program or thst identified degraded orpornen I cotditions such as corrosion or crooking ins auticatirng oil4 iroreir. Thas reviet ol qoereting erperienoe at PNPS s-rve in lieu of a o-tim-irspection to provide confirmation oithe toectiveness of the Oil Arelysis Program During the past five years, many visual irnpeetioref 0*ompnorets cootiring lubricating oil have been performed during corrective and preventive murinenane soities. The visual iapections d* these epontrts wotld identify degraded oorotliore suoh as sorrosion or cracking thait ould be etfibued tose inofective Oil Arlysbs Progrtm PNPS has a low thresheld for the identification of degraded oondlions such tht coerrosion or cracking of crsponents woeld beidenitiied as entered idto the oenreotive action program Nooordihlon reports thalt identified degraded osrrrposent sordlions, such as --rosio or cracking in a lubricating oil envirorent, were initiated asa resolt f these inspections, These past inspectionr a PNPS serve in lies ofsa orltime irspection to provide sortirmatiof dthe tsfecventes sdftw OilArelysis Program This tern is *osed to Ken 376.

NRC PNPS Lead Pavinioiq Wayre Ungaoieter, Pavinich, W*yne Froabarger, FPE45d 27

James Davis - AMR - Report to the NRC.doc.pdf Page 46 Number Status Request 439 Closed fT322-P-09]

Tale a32 qusWtion 9 Th. GALL specifies )I.MU, Open-Cycle Cooling Water Systen Program for carbon steel piping and PNPS credits the plant-specific Perioc Suroeillalce atd Preventive Maintanarce Programl Athough the p~lt-specific progrant provides hor visual ardor UT inspection as in XIA.M, it does not provide for preventive actions. Whe is the justification for not inplerenting preverdive actions?

440 Closed

[Tapi1-t-P-Ot]

Table 221-1, qoestion I The PNPS LRA, Section 3.2221 indicates that cunulative fatigue denamge is aTLAA eaeus-ed ineo-ad-nce with ItCFR54.21t(). However, PNPS aging rnange-rn reciews do in consider oumulative heigue dearage a -one-n for ste, or eseriess steel unless system tenpeeature moceeds 223 degrees F or 270 degrees F, respectively which is not a codortion of the SAP LRA Secties 3222-1. Provide an anatysis int justifies the eoxon of evaluation for cunulative tatigee dhrge for steel or stairiess steel aornp:tes in syntems t*t peeate below 220 degrees F or 270 degrees F, respetively.

Response

htew 3 21-35 specifies Ute Periodic Surveillanre and Preve-dive tainterence Proprm instead 01 XMISM Open-Cycle Cooling Water System PrograM. because the ermiroroec indicated as raw water in tines a22-6 and 322-7 is ueed to idklrify water WHcO is

.ntreated but is not pert of the row cooing water system. Therefore, the prevetive actions front GL 89-13 Itht wredoscribed in NUREG-t801 X,[VI0) do nt apply. The rewnaning preetive action specified inXIM issnot actually anorgoing MAV element, bul is the design cinsideration that conpoents are constrtcted of appropriate neterials. The sitecorrective actiov proga prov does ressonare assurance that if appropriate iraterials were

-st provided in the orinal oonponvre design, any resulting proldese would be evaluated and appropriate corrective actiors would betaken to address those problems.

The te of 220 degrees (carbon steel) and 270 degrees (stainless steel) as a creening citeria below which there is no oisideration 01 meheical fatigue s an aging rneheunie is docutreared in Apperdi H to EPRI 10036, "Non-Ctsos t Meoharerd Inplrrerelation Guideine and Malhani cal Tods,t usually relerred to as the Mhchanical Toeol. Ths docvuena takes the sreering linmits o12702 degress front t EPRI Fatigue IMangerent Hatdbook, TR-t54534. Fatigue isbesed onthermal cycles sen by the cowponert, and ifte ooeoponenr doesn't go above these tearperatures it is nol seeing thermal cycles large enough to ontrdode totatigue.

NRC PNPS Lead Pasvirnic Wayne Ivy, Ted Paviric% Wayne Firnin, Ron PAW 46d 77

James Davis -,AMR - Report to the NRC.doc.pdf Page 47 I Number Status Request 441 Closed ff321-3-P-01O Table 3.21-3, -5, -6, -8, -9, -10, -14, 16 -18, question 2 These item rerts's specify One-Time Inspection along with arther program such en Water Chernistry or L.tcatting Oil Anlysis. Howeer. Tabte 3.22 components that correspfrd to thee Table 32.1 items do not specify one Ume inspection to detect leos of material. PMesssag sarnC errt fine items loinrelae Oe-Time Inspection or provide the basis for eclairng OTI

Response

since the Ore-Times Inspectin (OTI) Program is appticable toeach water chsrnistry cotrol progran, it is also applicable to each line iten that credits a water chemistry control program ILRA Talle 3.2s1 Injcates that the One-Timn Inspectio' Program is crelted elong with the water chemistry control prograne for line items Is' which GALL recomernae aset-ltime inspection tosconfirm water chemistry soatrol. Table 2creits Whe OTI program through ederence towth esseiehed Tale t lire itma.

During thepererte oflrone rer-inen ane csomponents Wet contain hbricating oil, visual Itspection of these components woud dentify degraded cordtions that soad be atriberd.tan ireftstiee Oil Analysis Progran The corrective action prograe at PNP$ has atow threhodhfos the identition of degraded oadltions suh that corroeion or srcking oe components womld be idenified ase prt d this program The review o operating eeps'eren at PNPS for the last woe yewrs did not identity any condition reports that indicated an ineffective sit aralyhs progsam or that ids'titied degradedl carpotren I snditions such as corrosion or cracking ina lubricating oil er*iroanent.

This resiewrooperating experierce st PNPS serves in lieu of a ss-tire inspection to proide sondirmetion of the effectivenes osthe 0I Analysis Program This reires nam-enoert tothe chafrstry program decriptiones in LRA Apperdices Asnd BAto clearly indicate that the Oe-Tioe Itpectire Program willcoteirm the effs'tiveness of the Water Chemistry Control - BWR, Water Chieriatry Coatroi - Auiliary Systems aed the Waser Chenistry Cortrd - Closed Cooling Water programs.

Thes is Isoed to tem 372 During the past hWe yeMs. mav sisual inspections otlcomponers containing lubrisahtng ol hQen been performed dtring onrectie and preventive renirferene ctivities. The viesul ispections oi thns components woad idetity degraded conditions sh as corrosion aor saking Ahwt colad bealtribtded toe lIneffective Gil Analysis Progr-m PNPP has elow threshodd for the We ntitifiati of degsaded cosditionw such 1hf corrosion a orrking of comtponents woad beidertified and ensered into the cfrective action program Nocondition reprls that idet ifed degreded comporet oredtions, such as orroesion s crahking ins isicelne oil erlironmert, were inr taled as a remit of these inrpections. Thee past inspecaiow, sa PNPS sev In leu of a one-tim r

Inspection to provide cosfiration d the fectivesres of the Ol Arrlysis Program This item is olosed to hem 376 NRC PNPS Lead Peinich, Wayne Froaberger, Pag 47d ?7

James Davis - AMR - Report to the NRC.doc.pdf Page48 Number Status Request 442 Clcsed

[T3Zat-35-P-01t Table 321-ni, question 3 The GALL specifies XIMAW, Open Cycle Cooing Walter System Program and PNPS credits the plaot specific Periodic Surveillace eand Preceltaive Mainsesoe Progra*i Attho4u the plant specific program presides for visual arslor UT inspection as in VIAPO, it d-es n procide tfr presive actions. Preside justification for rl adhering to X,.W*0.

443 Closed IGererel-P-0St In gere*.at System Welkdown is cradled for bren ng LOM for boftirt However. other aging eftects may beactive for halting and System Wtlkdown does n proeide for prevertive actions. Agng Effects for bottitg should bemanaged unde the lcrla of a Bolting Ineegrity Program inaccordance wkthGALL program XIM18.

444 Ctosed

[Genera-P-02 Compars innthe SGT system that we exposed to Instrumnt airaremanged withthe plart-specific Instrutt Air Quality Program (PNPS APW BI.17). This prog*m only mneitors fie air quality. However, the GALL Compressed Air lonitoring Programt XI.1434, additioaly requires testing for leakage rates, inspection for tcorosion, and perfortnece testing comaporents. What prograrn(s) provide for these editioral requirements? It these

.ad tsl requiremrnal OfXtI.4 se runt c ertd by anothal program, piease proeide ju*litifclis for not incluting them Thisenmeat isapplict.e to1fite IAsystem aswmelt

Response

hem 321-35 specifies tie Periccic Smosllanceasd Prme-tive cirtnenacoe (PSPt4 Program inste a XIO.M2, Open-Cycle Cooling Water System Program. became the emvirorymer indicated as rm Mte intables 322-6 and a22-7 is usd to ideaity water which is uitreated but is no pert af the raw cooling water system Therdore, the prevesive actions fom GL89-13 thet te described in NUREG-1801 XI.M20 do rot apply The remaining preventive action specified inXSINGS isml actually anongoing AiP demet, but is the design osnsalation that compornets wre corstrulted of appropriate materials. The site corrective action prgram preoides resonase as surance thaet approprite mnterials were rot providel inthe original coponent dWigr% any resulting problems would be evatuated and appropriate =orecttie actions would betaken to atdres those problems.

A Bolting Integrity Program will bedeveloped het will address the aging management oa btiing inthe scope oflicems ranewal.

The BoltingI kitgity Prcgram will be inrdemerted prior to the period l extended operation incacordance with conmtmn'st rnumbt 32 This requires anraneanent tothe LRA to inclide descriptlios of the Bolting Integrity Program inApprdoioes Aand BSanm to idnify whee the program is applicable This itest is aomed to Item 373.

Through moritoring of air quality, the Instrument Air Quality Program maintains instrument air fres ateignificant cortarrinsrns and water, thereby preventing s

of material. This appro*e* to msprng loss of mmteriai Is acre effective them leakage mositoring and repetitive inspection for sornesiac Performance noritoring udler ths rnatnenance ruleaddresses actlie conponaers thia womd be Included inperformeane testing Noadditionas agsg esfects were dentified whose ngemet required these other atributes of the Compressed Airhorttoring Program, X[.W14. Recent inlerral inspections th sir reieir tks anid aosture checks of the inmtr.rnent air system have not detectel significan comeison or moisture in the system These peat inspections at PNPS seve In ieus a ona-tiUe inspection to provide confirmation d the eSfectienees of the Instrurett Air Quality program innmaning aging effects acoompArs eexposed to instrurrtr air without the additional program attributes recornmended bc GALL XI.5 4.

NRC PNPS Lead Psviricf, Way-Icy, Ted Pavirih, Wayne Frorelbarger, Pecinich Wayne Nichols. BiiI P4P44CUd 77

James Davis - AMR,-,Report to the NRC.doc.pdf Page 49 Number Status Request

Response

NRC PNPS Lead 445 Closed

[31 t-J-0it The asted roiroenarne for these unparesa are all nessetally Jackson, Wlbur Firin. Ron the sarne regardless a the listed taemerature. The environnerts Sore at the ete-thet rl tp to ItetN 3.1. 1-2 we described specifying the two tempesture ranges indicate thet the systen inLRA Table 3.1.2-1 as inenrirornnet cf Treated Water terparature is aboe the threshold vnalue thst can resuAt inaeracki*g

>220 dog F, and sotne we described as in Treated Water >

de tofatigue for the specficTi carponel resteriat. The rnramal 270 deg F.

Itdiue theshold fotr stainless sted is 270iF and for acrbon steel, 227tF as stated in the EPRI Mechanical Toots (EPRI Report Please justify the med two terterntalr ranlges todescribe 1003056).

the etrirormerts for the earnptnerts that rail W to Nm 3.It-Z 446 Closed

[1l.1-J-0 Drawings were available for NRC review dtring the sitevisei Jackeon, Wilbur ChearLt4ri ta-care Housings; Nazzles - Head Seal Leak-al (NI. N13).

447 Closed 13.1-0-310 The license renewad lation of these ooenportts (ynneesre Jackson, Wilbe Finnin, Ran bouhdary) correns tOre wed between the ID attachrnet and the In LRA Table 3.t-.2I, the COponer Type ID Atta ent ceal. Bmanae these aoatp are diretly attached to the Weld, (are Way, dryer hold down pads, ec) we indicated preeser-hebrdary, they were aernnvatiedy given an intended as heving the intended Itstion at "paessure bonrdary.

l futncion of presre boundary. Th is iconistent with the treearelt d vessel ID ettachma wteds innNUREG-1801 Sections IVAt-12 Please justify the these coortnerts provide a pressure and 51.M.

bo-ary lunction 448 Closed (3t.t-J-Oq4 These attachmert welds ae nrt specifically listed inthe reactor Jackson, Wilber Flran Roan versel drees report hewever, tay eae boanded by the resedl ofthet LRA Table 3.12-1 indicates thet for t Altlac t Welds, report. Any vessel stress report done per ASE Secton III contains the aging ffect t "Crackirg-fat igadu is an-aged bya TLAM CUF only for teane locations that the desigrer felt cauld betafigsn liniting While wnly these liniting areas ea actually calelated, the stress report orerathe entire vessed Please dise-wahetth Wese canporneis are explicitly addressed in the TLAA e

brded by the reecitas i the Acopy fthe vessel stress report (Corabustio Engin ing TLAA.

t isthe specific TIAA tht rnaragee the airg CENC-1139) wan ranidedolohe irpector.

effett o "CrackJrJ-at igie" inthese corpnaeras?

Pai 49od 77

James Davis - AMR - Report to the NRC.doc.pdf Page 50 Number Status Request 449 Closed t3.1.1-J-051 In LRATable 31.2-3, carbon steed piping and littings aid valves ina treated water eAtuironrot awe shown as having the agng sfect di ves of riWerial The aging vrageveed progan* reornevedid byvorreepodirg GALL fineiten Vd.r1

1. Table 1, Nest 13. is Water Chertistry and Ova-Time Inpectiov.

For piping aid ratings aid valves with daveder -= r NPS, the aging anargwavert program is shown as "Water Chernistry Conltro - BWWR aid 1rserevce Itrpectiorr in LRA Table 3.1.2-3. For piping and fittings aid valves with Snidear* < 4" NPS, the agigrng an ret proegaw isrshown as "Wter Chemistry Control - BWR* InLRA Table 3.1.2-3.

The.le asseised with the Iliv itae in IRA Table 3t.2-3 is Note IC:

For the carbon steel piping and fittings ad valves with dnamer >=C NPS, please provide jelificafion thld Note C is the covret voe to apply for these eveponvets.

For carbon steed piping ad filtings and valvee with dameer

• 4-NPS, pl"ase proesde jstilication that Note C is the wre note toappily for these coaprteers. Ales, lot these comrpoents please provide justification for ret perloring a

.er-hew itpefties as re.e-nt.ded by GALL Il-itet Vol-d 1.Tables thiem 13t

Response

As idenlified inthe dscussion colurn entry d Taie 31.1 Itel 13 (31.1-13), Water Cheanistry Cerard -BWR isaugrqerted bytIe Ow-Time Iransption Prngra Io assure eftectivenwss od the water chehistry progra,. This is try whorevr the water chenistry prograw is crdued The Water Charristry Control -BWVR aid On-Time Irepetion Programe, by themdves, satiefy the NUREG-t801 rewotnrerdationv.

The ISI Proeam spIplermnts the Water Cheaistry aid One Time Inspetion Program, bid is rMt recessary tosatisty the NUREG-I18I recvemerdafioera since the Water Chetistry Contrd -BWR and One-Time Inepestioe Progame awe vonsistent with the NUREG-1801 programe, a Note A or C is appropriate since he roly viable soerparison for these piping aid valve tines isto IV.CI-6 for isolation conldenser war s er s, Note C' vet he used For soerpereens with dawdaer < 4NPS, the answer is the saver Both Water Cherristry Centrol -BVWR and Ore-Time Iasetion Program apply tothese corponents, whichis ooesisntw with the resnsTiawa tiose d NUREG-1te1. Sine theorty vale oornparison for these piping ard valveline istoIV,Ci-6 for isolation cordenser sotoroneots, Note "Cm vest be vead NRC PMPS Lead Jackson WlbWa Finrin, Ron Pap c7f 277

'James Davis,- AMR - Report to the NRC.doc.pdf Page 51 Number Status Request 450 Closed

[31t V

-0J-O In I.RATable 3.1.2-1, sone, olihe conponts withaeing efect "Loss di WMar' that roll up to LRA Table I line iten 4.1.1-14 sho thi aegng neragernt is provided by 'Watr Chenistry Coreor-BWR and Inseavice Inspectio*r'; olers cd the cornponents with aging elect "Loss of haeial thao roll up to IRA Table I line tean 41.1-14 show that aging naran is provided by 'War Cheristry Conrol -

SM.' Th. -oreepoding line item in GALL -Une 14in Vduee 1, Table I - shows tIne Aging Mrnagotert Progras as

-'Waer Cheristry" and 'One-Timn Inspection" IRA Note 31.222 paragra

3. indicates that Ora-Tiwe inspection Sropresertativ eesaenyle willbeued toconfirm the etectivenes dns oeA Water Chemistry Conard progean

Oujetion, Please distas the criteria he adecting the sorple points hot the Or-Tine Irpoti.

Will the Thernrl Slea OW rdl up t o IRATable I line itan 41.1-14 bespecifically inmpected? Or, will they be included In the poplation from which componerts ae seected ton ora-lnie Inspecorla tot not specifically irnepanld?

Please describe how the therrrl slanven provide GhA iotended urticsl S' Pressure Borodary.' Doe 'pressur.

hmtt

- in this con* - rnea RPVpreastre boundary.

451 Closed 13.1.WJ-07 Please olarhy thGA fnion othe coetorant inTale ai.2-3 identified s 'Detector (CRD)? Is this t rod position Indttoal assenaly, or

,Anhinrg Sea?

452 Cloeed

[3.1.1-J-068 Pleas make walacble dtring the site visit acopy the BWRVIP recoanendations related loaging e orargernm S

GA steam dry..

Response

1) A.ephraned inSection B.1.23 dlthe LRA.

'The elemenr S the progran includa (a) daterninalion od the arnpae size based m an eassessaont d mSatmerias oS lbrication, areircora, pleauible aging ealects, and operating eaperience, (b) ideatification d the inspection locahions inthe systea or oonponenl based orthe aing elaect (o)doterninetien cithe anerinalhon techniqute includngo acceplta criteriaitat would be elective in mnaging the aging elect tor which the coponert is carrined and (d) ealeation Sf the need for lollow-up easninatiora to tietor the progesion d any aging degrattion*

In atdtirt. guidance o NUREG-1801 for XiM32 and XI.M35 willbe cned toseaect sample poirts.

2) They will be included in the population frow whch the samples we selected Which specifi itera willbe irpected willhe doternined by applying Ghe guidance ftwn NUREG-1801, Section

.M32 and XI.MM, when PNPS inpaements ths program

3) These coar nt ea aewded lothe reator coolat presure boutdary.

Consera trly, tnese coaryonan were coneoratively givean 0irntended fnction S pressure boundary. Therma sleees ae conaidered udjaent to aing tnrragenend review in NUREG-180t tarn I.AI-7.

The ddeactrs Indicated as 0D0 ector (CRD)'*we dalectors Ior presuare and ltwan inthescraan accumulators.

A copy dtW IP-139 was provided lothe inspector.

NRC PNPS Lead Jackwoo,

lWto Fiimn, Ron Jackson, Wilbur Firnin, Ron Jackso.

• • ltor Chanr Weria PRo1 Sof 77

James Davis - AMR-Report to the NRC.doc.pdf Page 52 Number Status Request 453 Acoepted

[3t1-J-0e1 The GALL. rooommernd ag*g mnnagegren program t the steer, dryer is -A pdart-spocifit aging enoagrmer program is to beevaluated.-

In Tale 3&12-2 the Aging Mkagement Progeam identified to, the steear dyer is -BWR Vaessel treorres" and Note E' is apied Please explain why Note E (rather than Note A) is applied for this line itemr The disosiono d"Note" on LRA pages aO.-4 ard 3.0-5 stats that etter designa oone we standard rote based on Apperdox Fof NE 95-10 (Rawerace 30-3)." The roteer-a a.

to NEt 95-t10. Reision & Howewer, remiew of the raterence finds that Apperdx F is aoot tIrdustry Guidarce onRevised 54.(a)(2) Sooping Criteiae; and Notes We disussedt in Table 4.2-2 o that docrrl.

Please correct this admnristrative eror inthe ISA 454 Closed

[31.t-J-t0 GALL it-e VI.AI-5 frdicales thal penotrations for fhe moinite and fhthe drain tinerolltpto GAULL Vo*urer 1, Table I, Iter 40. The LRA does not irdcate that penrrationr hoe the Sdran line ard for fle mroritor roml ip to IRA Table a.1t, htem 40. Please juatify why the drain line perotratroe at the Star menitor partaratiors we not 455 Cloted (3A.1--I11)

In tRATable1.2-1 the aging effect dooraking for CRD SWib Titas and kr-Core Housing N. shown as ranaged by Water ChOtistry Contrl erd Wan t Vessel treratds AMPS.

In GALL 0. aging ottect of oachlng for these oompon-r e iN sahwn as maeged by Wter C seriatry Control ard BWR Peatratione.

Please discuss wty PNPS has included these oroponert inthe BAR Vessel Irlernas program rather than inthe BAR Penleratiore program as recommendede by GALL

Response

Note NE iusemd rather than Note A became the NRC ald NEI agreed to use Note *E* rather than Note A when GALL specifies a plart-spaoitic program This irdcates the need for the staf to review the acceptability ot the progoram, while Note A would irdeate that the oe ao the program had alreary been accepted as drouenrted inthe GALL report The appropriate reference for the LRA standrod forral is NEI 95-10, Revision 6, AppenKx D rather tean Appendix F. This reruires an arrnertrt to the LRA.

This response requires antametdment totte LRA Aportlor vofhe. queslion rerpiree clarification. Taile 3.12-t does rot Itlude a comorn en type 4

peificalty nrmed arrur moritor penetration'" The irore hoar inge, which prmoide vessal paeratretioror te fledetectors, we mtde dostainsess sted and for the agng affect ot orackIg% the posnter to Table 3.3.1 aa tsea 40.

The drain erozle inTable a 1.2-, which presrneably isOre drain line perntration irdocated inthe questi on, iscomposed of carbon aleal, so rol4,c to Tae 3.1.1 itemn 40, for stainless steel cooponoeat, would be irnppropriate.

The PNPS BAR Petaratiors Program isN onsistent with the NUREG-1t Seetion XAMB, which covers only SLCIDP notle and instruntas penrtratiorr as discussed inBWRVIP-27 ewd BARVIP-49. PNPS Includes the CRD stub ttbean rd irntrument hoiurings infire BWR Vessel IIternals Program as they wer overed by BARVIP-47, Lower Plenum, whiohis included inNUREG-1801 program Xt.M. This slightly ircoasistaer withNUREG-1901 Sectlion IV, hod PNPS ftal it was better tobe oorsistert with the programs in Section XA tha the one line item in Section IV At PNPS, both the BAR Perntrations Program asd the BWR Vessal Ihternals Program we irnrplrererld by the eamm pis4 prooeturer NRC PNPS Lead Jacksoo% WIbr Finnin, Ron Jackson, WAbtw Finrin, Roa Jackson, W tbur Finrin, Ron PAW 5Wd 77

James Davis - AMR - Report to the NRC.doc.pdf Page 53 Number Status Request 456 Cltosed 3.t.1-J-121 In LRATable 3.12-2 the C-poneni Type 'Conrd rod guide tubes - rtie" is in ane wirore-l c "Treated watert > 270 deg-F, and the Goeraresi Type Contr rod guide tues howee isin sosrcirorteesr oh Treated weter >482 deg-F".

PlFse clarity what is mest by 'Control rod guide tubas -

heed asd expain why its ervirerrel is ditferes-fron the

• otteld rod gide lubas - tuba' 457 Closed 13.1.t-J-13r In LRATable 3 1.2-3 theeols y csornqwis idetifiedtas htwiJ the aging affect of Loss of theridl [dr to FACG sod included tnthe Flow Accdarated Cs-roion MP are carbon steel piping ast fittings -= 4 NPS. The GALL descriplion of the FAG SAW ()I.MI7) does rat litit applicability of this progras baed anpipe damser. ptease justify why onsy e large-daer-thr piping inTable a1.2-3 isincluded inlthe FAC prorarn Please identify the piping seg-ms-s tha are incrlsded in the FAC prosam in IRA Table 3 1.2-3.

45B Closed 13.1.1-J-141 In LRA Table 31.2-Z tor corbseerta with agng edecd roe ci saterial that roll uqpto LRA Table I Ihan 3.1.1-47, the AMW Is Idetified as "Water Cheistry Control - BWR."

Howener, in the GALL the agng affect od Loss o I tlsial hoe these corronerts is rwmgwd by both Water Cheristry asd Inservies Inspection (IWB IWC, and IMD). Plesse justify why Wtser Chemistry Csntrol - BWR with noassociated irepection is sdeguate to nonwge the agng cffect of Loss of Materiad hoe these crorsn-res.

Response

NRC PNPS Lead The CRGT base is located nest the bottom of the guide tube and Jacksor Wilbur Finnirn Ron suptpole the conltd rot stahn t drive is dtsco-nrected asd removd for ervice The control rod guide tube is esedo of slariess steel. Os wnviror'net is given a >270 'F because that is the threshold for fatigue f sainhless steel per the EPRI Macharical Tols

((100305). The gude tube base is tade of CASS asd consequerAty its eroiros-erst was quoted as >482 "F as this is the threahold for therIn enl ittsileert in CASS The lieiting Isrserature was listed for each.o.rposn Both srponirrs see the sees tengrsatsres.

Flow-e*deradted corrosion (FAC) is not expeced to be a significant Jackson, Wilbt Finnrki Ron aging trechanism for the rwjority of the reactor coolast system.

(including piping asd JIM rge <cC NPS) as the lines we seithe seldot wsed (suchas, scrarn dscharge header, corsprasy, HPCI. rnlear systes pressure rehie, PASS, RCIC, RHR,aod SLC) os -Oere is little flow while inause (CRD,NBVI, RWCU). In LRA Table 3.1.2-3Z carbon sled piping segtares

-=4 NPS (such as feldwats-piping) we included inthe FAC Progrant PNPS hWs reviewed the FAC progra-asd destertined that 8 ittludes a portion d the reactor vessel drain piping that supplies RWCU, and the is mnall bare - esrbon steel piping PNPS willt-id toss of rwats-r due to flow accelerated corrsalon to the time ewiry for se)l bore piping (<4" NPS) inLRA table 312-3 (page 3.1-63).

Th. new entry willidentily Flow accelerated corrosion asa separate asing daect as dote for the large bore carbon steel piping entry on page 3.1-65, The GALL oosparison will be Voluns 2 itne IV.C 1-7 which rails up to Tabe 3,1.1-4&.

This reuires an aaenr*trant to the IRA The its inTaele &1.2-2 *1 rodl upto Une twM &1.1-47 (GALL Jackson, Wlbur Finnin, Ron red V twe o IV.AI-)

s for eose of.ateial due to pitting and roice corrosalon NUREG-180i repeatedly credits Wter Cherstry Control - BaW sutnewted by the One-Time Inspection pogsar-i to saage loss of rrwteridl due to pilling and crevice os-rosion (for earplets IV.AI-E VA1-Il). Thisproerra continleion is-dequape to this aging eWfact In that the loss of rts-rial due to pitting arI colevice corrosin Ios the irsr-ons is no dsfferent than the loss of material due topitting od wroesion fIs oher stairless steel cornponents aeposed tonreact-I oolac. As nrted inTable 31,1 the Oas-Time Inspection Prog-rer willveriy effetiveaes of the Weter Chenistry Contrd -SBWR Progra-e Pa 531d 77

i James Davis 7 AMR - Report to the NRC.doc.pdf Page 54 I Number Status Request 459 Accepted [31.t,-151 to [RATle 3.1.1, ite Numbte 3.1.1-48 Discuss-io includes the stoernmer, 'Inseriice inpetion iso,*

sppiicale toooprronats

< 4NPS." ASIVE Section Xl, Taens IW5 25O0-t. Exnrafation Category B-J, reqires Srftee (bta not Volunmetris) etarination for pressure retaining welds in Class 1 pipe that is. 4 NPS. Please refordle the statemeni in itern 3I.1-48 Discussionaith lt ASWiE Section Xl recpiremerls stated above-48D Accepted 13.111-J-16t inLRA Table 3t1.1, Item Ntmtr. 3t1.1-48 Disssion ritled tee statemaert. Crackinginsteel compoertrs due to thermal sad mtechle.ia loedirn is net directly dependet on water chemistry, so orly fte One-Timt Inspection Program is credited. However, there arnetli items inetle 1X2 Tabes where One-Tie Inspection' by itself rolls p to hare hmbere Pt.1-48. Please eingain the sapparert inconreistery betwees the IRA statecart an the way the the roit-up to hein Number a3.t1-48 wre done in the IRA

Response

While ASME Code tabe tW250-1I (Category B-N-1) does require VT-1 or VT.3 inspection sithe irnersor Htchm7n*s and core srtport etructures, it does ret rerpire inspection at the nliorily of the irterats. Therefore, cradting ISI or managng est fmaterial at the irlretals in grenal is irnppropriate The PNPS One-Time Itepection Program will incorporate the rasot other inspections that are pernormed inchodig IS irepections done per ASIE A iW-2500-1 Wt-N-2and! other opporttcs-itio insprections.

Perhtate the statnear Sat ISI doees no apply is nisleading. We shoe d tone said the PNPS does ret credit ISI tr aging tnagement d piping <4". ISI typically only -eqpres surface ecaintation of ti-se onqonera r and the aring effects reaupring tanagernet initiate onthe ID, theretore we did not credit ISI for manedng these attests.

AnrLRA antired i required PNPS will am-at the LRA to delete the statement "lnsemie inspection is no applicable to ooeiorirts < 4" NPS" from the discussion in line item 3.1.1-4 Thes will require an amendment tahe lIRA For dlarificatiorn the statement "Crackirg insteel componnts ue to theral and rnecheral loading Is nt drertly dependent on water cheristry, soedy the Oem-Time Inspection Program is credited" should be ddaled.

An LRA armenenta is required PNPS willeamend the LRA to delete testatement "Crackinrginsted oomponeats due tothermel and mchaenical soeling Ileot directly dependert on water ohesistry, sooedy the One-Time Inspection Program is creadted' from the discussion in line item 3.1.1-A&

ThIswill recireanamecdrxent tothe LRA NRC PNPS Lead JaclsMo Witbl, FirPrin, Ron Jackson, WIb Ungedter.

Ag 54Cd 7

James Davis-AMR-Report to the NRC.doc.pdf P...

'Page 55 Number Status Request 461 AOcWed 13t.t-J-17]

In GALL Volume 1, Table 1, hew 49.n naugented inspeotion using UT or other demonstrated aooeptable inspection is renommercleeo for BWs with acrevioe in the access hoe eomes.

Doee PNPS he-a orevoe inthl acess tote noner-?

Does PNPS perform an inspention of the aoe hoe hone.s using UTorodhe-demonstrated ecceptable inspection tecnniqlues?

Response

NRC PNPS Lead TIhELINE OF SHROUD ACCESS HOLE COVER EXAAMNATIONS: Janksor W,1b Parde, Rich

- 19B6 -GE issues SIL 462

- 1991 (RFO-8) - UTI both none-r (tor I

ni. naews only)

-1993 (RFO-9)- UT d both eooers (for irm. ard racial flaws)

-1996 (RFO-t0) - UT of -e-c degree woe-only

- 193 (RFO-10) - VT-I of both ows

-2001 -GE i.-es SIt 462 Ren.t on-=t

-2003 (RFO-14)-EVT-I oboih woers

-205 (RFO-15) -

w ecras

-200? (RFO-t16)- Pan to irepet tf80 degrees by VT-I

-2009 (RFO-t7)-Pwan toinspent aSO degees byVT-1 Pilgrim will oortirce t inrpent he woe.s hole 9

we-a S degroe and 0 degrees visuallyet 4 awd 6pyer inrterae.

respestovely during the nwrdwt licensing period I new BWRVIP gnideaoe is ued on these componenda, PNPS will per-trw iepentio inawordcne-. withthat grideanoe Within the first 6yesr 6

dthe petlod o tenoel opleration and ewry 12 yearse thersher. PNPS willtinpent the access hole oers-with UT methods. Alteretiody, PNPS wilt inspect the aocess hole wove-in oondenree withBWRVtP guideline should suah gdancne boon-e available.

This Is comnitment Item 34.

462 Closed

[3.1.1-J-181 RATle 3.1.2-f lists the ISI program as lee AMP uwed to ew-ging the agng effect of oracking in '01hr Pressuro Boundtry Boning - Upper head flange bolts and nuds -CRD flange bolting Please ddenfly the ASIVE Exanination Category aod Requiremerb that wre apdicatle lor these comoponents.

Category 6-0-f1 ol th ASME X) nde neonins the repirerente for Jwkksoc Motwr Packe, Rich allpreosure-rtairingbdtling >c"da Inthe ISt Progrant The code rec-ires a vltumeric (utirasonic) tene-for all RPV closure stIds (aarrined inplace) ard aVT-I viseal dacn for all RPV closure rods eery tlOyear.

Category B-3-2 o6 the ASKEXl node wonrains the re-pirements hoe pressure-retning ibdting <=2 dia inthe IEl Progam The code req-ires a VT-f visual aarn wery thyeors or dboling Intnis category (iritudes CRD flange boling, RPV head N7& Nltnonzle flange boting).

PeWp 77

James Davis - AMR - Report to the NRC.doc.pdf Page 56 1 Number Status Request 463 A.ccpted fa3l.14-J-9l LRATable 3.1.2-2 Identifies "Therral Agng Erittlerb int of CASSB as the AMP totinage the aing effect of "reduction in oractue toughness' for three, coror typo.

Control Rod Luide TUbes - Basne' -Fuel Support Pieces -

Poor Lcbe, and "Je Ptirp Asseeblies (venoi cornponro]f."

However LRA Table B-2 says thtie NUREG-1801 Prograr "Thtornm Aging Embrintloerl of CASS* is rno applicable at PN PS. Please correct or cutify this opparent inoweistercy inthe LRA Also, i an IRA orrection in r9 pf.oo atio.e that ths Notc for each of the three co.mponert line ierno -oe vajidated or changd to becoeisterl with eny changes trade in the IRA 464 closed

[3l.1-J-2q GALL Voluwe 1, Tabe 1, Uns 52 Idenrifes the aging effects for RCPB flosue blting as 4Cracking ctue to 9CC, lcoe ol mtratrial dito wear, eossof dp toad die tostherml eflects, gakel creep end self-looseing.

OGy the aging aftect of "Crackig is identified inLRA Tale 31.2-1 for coriwonai fhat rolup to LRAUine Vean 3.1.1-52 The "Disomsniod'in the IRA for Une kern 3.1.1-52 provides discustion io wly thes oher arg tootes lieted in GALL eve cn flitiuded applicable at PNPS.

O'eaftion, PMae provide PNPS basis for the Diseccuion siatefent Us fIndustry operating afeeierce indicate taf to*os of material dMe towaIr nter asignificant aging effect for this botting' Mlease ef.rIfy what is aed.. by "rd a sig-ificant aring tffoot."

Plesse provide copy oftechntica rolerenve(s) csuporting the IRA staterrei that "Loes of preload due tostress relaxedio (creep) wcUd only boa cornon invery high teperaturre applioationr (o 700deg-F).

Response

NRC PNPS Lead NUREG-1WI prograem XI.M12 TTherirl A*ing Embruttleses of Cast Jacksort Wib" Finrinr Ron Acte-tito Stainless Sted (CASS)" applies to CASS pressoe boendcary compones In the RCS This progain isno applicable to PNPS, as we hvoe im CASS preaue boundary corponeaes.

NUREG-1801 prograi XLMt3, 'Thermal Agng aid Nedtron Irradiation Enbrittlevfef s

a Cast Astentic StaBlress Sted (CASS)"

applies toreator vessd irternads (non-presa e botiniary) pieces trnac Of CASS. The seniioned cornpones above werall reactor vessd irlerrels and are covered by thie prograsn In nons istaeres, the LRA rsers toTher rea Aging Errtinviierent of CASS frogran as a ehortened roaoe for and with a fMprlir*. to the Theait Aging m*d Nhgron Irradiation Eribrfif*ierirt of Cast Astenitic Stainless Sted (CASS) Progran For clariftior* those Instanoes willbe revised tolearly indicate ths appropriate progran Thispreqirw aneamneraro tothe IRA Toclarily the IRA discussion inline item 3ff.-s2, the phrase *not a Jackaorn Wit.,

FiPrnun Ron

.ig.iticat aging alecr sawos nott nagng tofect ren rrn treragenent. This isonorsifted with the EPRI Mcheaical Tools that do ino consider loa of material di to wear s

aaging fect for boled olosira. In additiorn tos. of a riia ctue to wear was not Identified as an eat ofonosrnn tnhe raeldion of GSI-29 for bolting The ger'al systean bdfirg toswlich this lineiteci appliei is no roditrioy ioassettbled Occasional thrtad failrae die to wear nisolhisire sud as galling are not age related bui we evend-dven oot*ionue Us ert resolved whan they ocor.

Bitting at PNPS is standard grad. B7o arbon steel, or inilar raferiel, *co* in epecilized appdifationals where etaianess steel boiling ic utilized Loes of preload due to or.s. relaxation (creep) woud only bea cncoern invery high tarpeore applications (>

70F) as stated inthe ASIE Code, Seotion f1, Part D, Table 4. No PNPS bolting operates at >70WF. Therefore, Iea of preload d to stress relaxation (creep) ie rot an epplicabl ani effect for theUs reactor oxolani systemn Aoopy d this setiton if the code waS mailatbe cuing the audmt.

P4P 5f d77

James Davis - AMR - Report to the NRC-doc.pdf.

Page 57 Number Status Request 4

Closed

[3.1.1-J-211 The LRADiscussion for Une Item 3i.1-52 includes the atternswi.

sTo atdess these bolting qoeratlion conca-ts, PNPS Iu taken tiors Ioeaddress NUREG-1339.

lese.ion i ofeneric Saety is--

29: Bolting Degradation on Failure in. Nulear Power Plarts" Pleso idertify and provide a ospy f mny pre*nus, dOCkoled conrespondene in which PNPS describes its actions and o:rnsiternere (I1a1.) withreardItNURE-1239 a4 Closed I3.1.1-J-221 In LRA Table 31.2-1 a lone Iteu identilies the aging alfect od "Less of lerien" for the oeylporimi type "Closureflanga etuds, reuts, hers., " bshing." Ndot"Hiseapplied for this lins iter', indiealing ghat the agng elfect is not in NUREG-1B01 IonlhIs acrrcmurt, rnsterial asd areirosrnaee cosednftiont Plese Idekify and discuss theg echarism tha cretles the aging effect d'Loeof kMtterial insthese onaperenes.

Please identify and describe PNPS-spcific or industry sqpriese mwhe the aging effect of "*Los of Mlateriai" has been observed instese oorponess.

Pletse inlude asdiscussion of why "Loss of Material" isan aging zlfact applicable for the. ceorrrturis but not for conponena ghut rolluipto LRA Table Unse KOertiaI-S

Response

GL-9117. Generic Saelty Issue 29, Brlting degradation o failure in nroleer pewer plants is dated 1I/17t91. The 0L required no response and no docketed correspondence was subcitted PNPS did racis GS-91-17 in 1991 and areview suemary was provided to Ihe NRC aulit teen turing the site visit Partly as a result o the PNPS review d GL 91-17, Station tainrenace procedlure for bolting, 3.M4-92 mac devdoped based on EPRI NP-5SE7, "Goodl Bolting Practicee".

Inthe Nos-Class I Mcchtrical Iplenenmation Geideline and Mechanical Tools, Revision 3, EPRI, Palo Alto, CA 2D01. 1003056 (TIhe hitecto Tools) Areordix E. kow alloy sted exposed So indoor air oortairing roisture (huimidity) is suAbl t loss of reterial due tothe aging mchati sm di general corrosir This bolling item has thie rnmtial and aerirornurti conrbination wmd theralore the acing taect Is applicable. In acoorderoe with the operating experierce provided inthe Reactor Heed Closure Stuos Progrank aornirtion i IS r1a8tor hed closure studs ai visuel arrinislion of 18 nuts and mS a-sh during RFOtS found no nen recordrtee indications oi loss ofr sertai LRA Table Une smsr 3.1.1-B2 is based onNUREG-1801. Vo.1e-I.

Table I which addresses loss d niderta doe only to wser for carbon and ctiaess steal bolting. Since Ste NURE-t1801 ine, tentr does rotd adens other aging rrlaharisms that result in lose of remted-M, it sas deermed tha tle lne item is ot applicable for lose oitrniia clue to general conrosnim NRC PNPS Lead Jackson Wibhr Chan Usis Jackson, Wilbur Finrn, Ron PrSdW50 77

James Davis - AMR - Report to the NRC.doc.pdf Page 58 Number Status Request 467 Closed 13.1.1-J-z2 LRATable 3.1.2-3 incrldes alima iten for tin Steamline Flow Restrictor. wd.W di CASS, in an environrnet of Treated Watle > 482 dog-F, aging dfect of Reduction in Fractura Toughness. For Class I piping cornrpreets "rde othis treriatl, inths e,.ironenrt and with tls aging afWont.

the GALL reamrenduds the AW Xi.M1Z "Thernal AZng E iltremritlrr of Cast Aulatnilin Stairleas Stoet (CABS)." In lieu d the recommented AJ.

PNPS proposes to uea aOne-Ti-Inspection The GALL-reaownrnrne APW Imtldes screering criteria to determine winch CASS otrponrets are poentially suceptible totherat aging eanbrittlrert and requre cugmered Inspection Has PNPS applied the screening crifteria to the tin Stearnfine Flow Restritolts? Is., what were th restlte?

Please describe what statirnt ion requdrernests, sethots and stondards willbeosad inPNPSe proposed On-Time Inepa of tithe Main Steanlise Flow Restrico*rs.

Pieeso juatify that e ons-Ti n Inapetion provides ad equate aging eragenel tdthe Min Sleerline Flow Reatrictors during the period of citaded opweation, 468 Closed

[Si&.-J-24q LRA Ien Netter 11.1-53 Dieuoion sles, "Thereere he stedl anron -in* ltre Class 1 reector vesel, Veessel irterals or reactor coolart prencue boundary sipoeed to closed cyclesonoling water." However, LRA Toble a1.2-3 (pae 3.1-8) imlmudes lire Itors for Pwrp oane - Thermal barrier (FIR) made od CASS where e eging renigerliei progrew are identified e

"Water Chenistry Cowtlr -Closed Cooling Water" and "Inserice Inpection" These line iteta appear tobe Inconsisterl withthe Dituwssion in.1.1-53.

PFease eytplain why these Inearera Ircorsistent withits Discusion, in 351.1-53 or correct the inconsistency.

Response

The eain steam line flow restrictors we rno pressee rtatinng conporents (an presuoe btondary lurolirn). They we acast piece that is reeed inside the rr-in slam-pipirg The meN sat-n piping is the pressure boundry. Conreaqoey, lhe tain steamr flow reotrictors warero a good canodate tot GALL programn XiM12.

a) No, PNPS has rut done the scresptng for e rdns steam line hfow restrictors.

b) While the inepectio proWe-h, hss nrt yot been developed. ihe planned inspectio is acvisuan statirraion peorormed by inserting a canerw into the wain steam tire-

.) Reduction at Fractre Toughness (Cracking) and Lass di Material o the rwin latmo line flow reitrotora eae not onrsidered likely aefects dtring the period oifte.1-d operation (No aging of ties restritoareis identified hyNUREGA1t01). Lens olrnatria wilhbe Mitigated by M: - Water Chernistry Cotred. Nornthels.

PNPS hes ommorioted todo aone-tirme inspection tovsify thet these aging effects anr not oceuring Since the flow restrictors are rno pressure relaiting oorrpo*ents, the One-Time Itpection Progven is adequite to mnage the efWects of agirn NRC PNPS Lead Jacksoo Wilblo Finrrn, Ron As easted inthe qutesorn, itemn1.1-53 raterstosted cosponents.

Janksorn Wilbtr Ungenrtelr, CASS isooreidered stainless sled. The material and environmet comrinatioe ofatanloiees steel inclosed oyclecodling water does rnt appee inthe RCS (Chaite" IV) Wtas oNUREO-1831; threreore, the line it8m for the punp 0o1er -thernel barrier is orepared tothe ESF tbles of NUREG-I01.

Pfa od 77

James Davis - AMR - Report to the NRC.doc.pdf Page 59 1 Number Status Request 469 Closed

[3.1.1-J-251 PNPS IRA Table 3.1.2-3 includes antries Ior piping and fittins made of carbon te01..n oifonnw c Ar-itonkot (e~t). Sowe cthese entries have anaging efteI of oses of atherial; sote of these entries have anaging e=fect of

-on'e For the elaries withaging affect of-noneW, Note 101

, aplied andte 1e "Highcontoned nurfact tpenaltene ntec oisture alcumolaton thei to.d rest in Please lari thy the high tlper afire oonditions that ore mnotioned inthe rote What is the "high terrPeratud" threshlod? For piping thal eqweienoss significant tstetotee chaes dening opetion. -Rotimntety what p..e-tage ofperation at topetatune be*ow U. Ngh tomeeatune fteshold is assumned r anticipated toe those piping and fitligs where the agng ftfect isn tonr'?

Please diseoo the mnhodlology hat PNPS wase to identify whNch piping is classified as 1-Ing aging affect of 'loss of rn

.0d wrdWhih has aging dfet of "none.

470 AoWopd 131.W-J-261 PNPS IRA Thabe 31.2-3 contains two line itet for t

Bolting (flanges. "Iln,-.

di)r whene the matneial is either low alloy elen or stainle slted, the e.irornert Is Alr-irdoor (external), and ths aging affect is crackingy Plase. identify t.

nheanhwm hst causes this aging dfect in these noenflbnnes. Please justify that the inseevioe inspection p etn provides aging n

of thie.

oon~ponets admelte to enre that they cntinue to perlorm thleir irnended trction during the period of etended

,.-to Pl

'Oee lify whether PNPS willbedvelping a boling nlte*fity progan mnodeled n

Selietion XMI to include these onpornets.

Response

The *eilction of the aging dfecnt o lss of ratetial e of no aging dfect was dependent upon the lenperalwre ofthe ornopone dcring nornal operatic' Conots withaternperaere above the boiling rponit o water will precnude onistuwe

• o*urnlaton As a mrtter ofoonene, the transition point wasoan udo at the teperatusre thresholdd of Plot crenking due to fatigou in stel.

Although these oopornints can be below this threshod dcring Stoi nc ondit, orxc.

eaci sorn. c-oorcne-nt cooed possibly one tepratutsres boh above and below this threshoId during nonal openaoino, time ncon-neo shotAd rely, if ever, beat a tempeatunre balow the lenl dew point Caonsedluely, even tduring nhuldwon con*itios, noistwre accumulation should beneuigible, The PNPS poslition on lose of nmlerial mo wteiot surfacel of etoed piping grew o00 of earlier ticense rerewal application enpenonro Loss of nmterial on aeetnal aenees isnonmally mtnage by systen walkdowns; howener, nystn walkctowns dont inmpect the Wt10erior srface of Irntiaed pipi ng unoess the insuatlion is renoet lnf reirtenonae, Thee intsno d ned torer inslation and direnly Inpect pipe mternat elnraces as the beef that renuires the itotion prevents roisture aocumnulation which in ton prtweets lossof rnlerial. PNPS's plan isto impenct ofiuatood stnw pipng for loo of rateidal via system walkdowns and noo renone any i-usallon Table S.1.1 hen rn mxib 31.1-52 specifies the agng edfect of noacking due to stires corrosion cracking toe carbon and stirnlens tend reactor coolant system proseure blondary closune bolting Intnrvice inspection of bSling erponeM s IS ispecified in GALL XIM18, Bolting Intogity, Ior rontegonni of oraoking and hens of rmtoera of preousre retaining bolting impacted inonandnece with ASME Section X. Therfooe, "itmeroiceinspection is acceptfole for ranoegng crcking in reactor coolan prt nure boonday hbolti However, a Boling Irt-gity Progrann that credits ioerince impecttons willhedeveloped thV willtaddress the ang treotendof Solting inth. scope of li-en rfenwal.

This reduires anWenirhnen tothe LRA to Inclue description of the Boling Integrity Progran inAppedloes Awnd Baind tot1Ideniy whre. the progran iapplincable TNs Itto is closed lo ltrn 373.

NRC PNPS Lead Jackson Wilbur Unget ldt, Jackso% Wilbuw Finnirt, Ron Pao 5Pd 77

James Davis - AMR - Report to the NRC.doc.pdf Page 609 Number Status Request

Response

NRC PNPS Lead 471 Closed 131 1-J-.71 The gng dffect drerackirn due tofatigue dpernds ounthe thermal Jackson Wilbur UrLngerfter, and mechanical Iuoedng of the uunponl and is eufectively In IRATabte 3.12.-3, EAP cobination Boluting stainless irdeprden, d uthe awirsrnert trthe surface of the u

.rricsl.

steea. Air-irdoor, Crecking-ftigue, TLAA -the Was e e'A The taees in NUREG-1801, V.ur-. CqAt IV (ot"Vide of 105." Pies. Mplain why note 105 is applicude tothis line Stubection Al) incltude oennycrals with antair osiroeriert ad an iten.

aging effect of cranling due tofatigue. 7hilere ofwthed e lines soaid have hoea wed as a substitution, the choice d a line within the cresponding system tabe (Taobe IV.C1 inthis cae) was prelered Plant sixecfic Note 106 rplainsr thie the difference in a!win ts is accWqree for the evaluation df cracking due to tstig-e 472 Closed 131.14J-211 The aging eduect f cracking due tofatigue doperlds onthe thenral Jackson, Wtlbur Lirtrselter, and techanrical loaing cfthe conponard and Is efctively InLRATat*e3.12-1, hAPuoornbinftios CClosu erflange iroIepndwt d the aervirontere at the surface ofdthe oorinp*netr stud' or tthr pres.u.e bounmary bolting, Low alloy sted, Thitables InNUREG-1801, Volume 2Chiepr IV (outside Air-irdoor. Cracking-fatigue, TIAA -the notes are C, 105.6 Subsection At) include owponerts with a' air envirnmet ard an PRiase agiain why rnoe 105 is appliuae to these line iters.

• • ng ffect dcrachitn e thfatnieo. While one olthese ires soud hwve ben netd aa substitution, the chce of a line within the uorresporlirg systen ratle (Tabe V.At lnoths we) was preferred Plaro specific Note 105 erplainn the the iftere"0o in eZrrirerts is cceptale for the evaluation drclking due to ftigue.

F WVU 77

I James Davis - AMR - Report to the, NRC.doc.pdf

.Page 61. 1 Number Status Request 473 Closed

[ V.1J-291 In LRAT e 312-1. the following coorponents me identifiedt s having tthe ang lect 4 'crmkig" arnd Note H Is applied Doer (Bctom Head); Oone (Upper Chosue Head); Flanges (Shell I

.rs Range and Upper head closure Range); Vesaed Shell (Bdtlin shehl); Vesel shall (Irferrnadiahe nozzle sheP1, lowe. hl, upwer shelf), Nozzles (Mien steas).

Table 3-I in BWRVIP-74-A (Reactor poresos Vessal Inspection and Flaw Evaluation Guidelines for Ucerne Renewal) addresses varolos potendia age related nrlthonsms and indicates the cormorents to which the mnantsmoio aply. EXrcept for the ineoherfanm oltfatigu which sppiios to eon, of the crponmens listed in the paragraph above, there Ism nomchanion, InTeabe 3-10 BWRVIP-74-A that

-.sos cracking and that BWRVIP-74-A idetifies as applioble for the c sompore listed above, COestion Please provide adescussion of the hedotogi that PNPS used toddetndrs OW the agng efect di-crackingr is aploable for the cnponers listed in the first paragraph, abovn, Please identify the nechenismt(s) that cause cracking Inthese oonpoets.

Plesse qys*in how or whother PNPS incorporated the Information contained in BWRVIP-74-A !no its daterninetion that cracking Is, aging effect applicable for these Plese discus he pla--spepoi to or industry erxpeience reviewed by PNPS innak.,g the deterrihtion that cracking Is anging effect appiciable for, hese -opoenm.

Response

NRC PNPS Lead The cracking referred to in these erries is stress corrosion cracking Jackson, fVAllbe Finin, Ron da the stahniess sled cladding This was rot entered based on BWRVIP-74, btl was based onthe necherical lods and indstiry operating experience. NUREG-1th1 also specifies cracking du to SCC ms ae aing effct eor tnary stainless sled neterial enrire Note that for enies such as Nozzle, Drain (Nh 1) which is uclad carbon steel there is mo cracking entry other thn crackng-fatligm.

Bie 61d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 62 Number Status Request 474 Acepted 13.11-J-3oj In LRATabde 3.1.2-1, the cseponent Stabilizer Pade (part a Support. - Stablizer pads, d.pport skirt) is dlertified as htving aneaglng test of'loss of material' ard the MPis Inservee Inspection Csesti.sM W-at Is Ste -echarism that causes the aging aftect of loes et msterial?

Please describe th Itrervise Inspection fle the Stabilizer pacs: What is tte eearriretion frequecy? Exaeniration repcirenree-Eeaee ion rnetroti ? Acceptaeee astdrd?

Are there tay serrenty approved radid requests applicable for thes ssrreeri' 475 Closeed (TIAA-H-01t The apptlcert Is requested to provide the design codes for the iner plat% torus down chs arivert header erd tons-attached piping, and SRV piping for review.

Response

The entry intable 3t1.2-t is for both the suppcrt skirt atd the stabilizer pacs The support skirt was oersativaly considered suscepitile to loss of Wraler as it rreiras below 2 2DFP The stabiizer pads we located as the aiche of the

-essel, arn are typically greeter than 220 P. Coreistent with other LRA eoiptre*s., these peds shoeld hot be subject to loss o naterial The LRA will beslerified to indicate that the less of material aty applies orty tothe suppot skirt The respires areanenernrnt toethe LRA The stabilizer pads ara inspected per ASKE Section X0 Table IWB-2500-1 cstegory B-K The code (fotlnte 7to Table tWB-25CO-1 category B-K) allows surlace earination froe an accessible acde of the wed. At PNPS the top aidc of the Wead is cessible ard PNPS pertores trngretic particle testing ed the top side da each bracket wed inwery tOyear interv.

PNPS mseels the oode repuireserts and therfeore has ra*te request for thae irpections.

[I) The design code tsr the dryWcll finer plate le AShE Cock, Section Ill. The ce includes Code Case 1330-1 and Cede Case t177-5, and the latest ealtion as of June 9,1967. [Refererce Ctieago Bridge ad Iron (CB&t) docueet 9-314). For the tons shtll, the design cede is ASKE Coae, Section IlL The csde ircludee Code Cese 1*-1 art Code Case 1177-5, atd the latest edition as ot June 9, 96"7. h was later evaluated to the requirewerts eo ASME Section sll Oachionr with adlenda through Sueneer It177 ard Code Case N-197 as pert of the MWrk I Torus Program (Reference Teledyne E-nseerirg Services (TES) docuent TR-5i10-1].

121 The origirl design code for te torus dowroarneivert header is ANSI B31.1, t167 ediasm Itwas later ecaluated tothe requirerents et ASWE Section III Division I lwth addends through Sumrmeer i97?

and Code Case N-197 as part of the Mark I Torus Progran

[Rerernce TES documert TR-t310-1].

(31 The originld design ate for thetorua attached piping Is ANSI MIt.A, 1967 elion. It was latr ertalted to the requirements of ASkE Section II1, 1977 editior, withAcerelea through Suarerrr 1977 a pert dathe Mark ITorus Program Pipe support analyst. was performed to Section III Subsect On NF [Rfaterener TES docukarrt TR-S310-21.

14, The origial design de for the SRV piping li ANSI B31.1, 1967 editionr twas later eluael letothe first anchor fron the torus tothe requirements of ASME Section III, 1977 elitioer with addend.

through Summer 1977 as pert at the Mark I Tora Program (Reference TES docunat TR-5310-2). The SRV/DL piping was alyzel for higher discharge flow as pall of the Thar..) Power Chetleizalion (TPO) Prograe tolhe fatrn design cafe NRC PNPS Lead Jacksoa5 Wilbur Firnin, Ron Hoang, Dan Chean

,arns awd 7

t James Davis - AMR - Report to the NRC.doc.pdf Page 63 1 Number Status Request 476 Closed CTLAA-H-02 The applTicant is reqes'et to provitde a statemnet ind'sting thet the estinete of the total merrb. of 60-yeer SthV actuationse used in the design lteigue analysis roeratr valid ar01 consr'vative, based on the acotua S3W actumarions noowfe0 tthrowh2W

Response

NRC PNPS en tracked SPV actteios front 1992 to 2005 Atolal oC 14 Hoang Dan ctuatiots have been recorded on valvsA, ard 13 sah on-valv-B.

C ard D. Using the t4actuations in tle thirteen year period, the projected actuation for the rest of 60 yeses wre 31 lifts. The narr60 of liftt inthe first 21 years of pla t

tile(1972 -1993).e.re n recorded These lifts were mrore frequt inathe esrly years. so PNP estirnttled these 21 yer.s at5 trnes the recorded rej. The yields120 lifts inthe first 21 years. Corbitring Itheearly period, the recorded periot, and the projected period, ther will be-n estirneted 165 lifts in60 years.

PNPS plant specific tnloysis (Teledyno Engineering services dtoouert TR-53t0-2) states th. t fth SRVpenetratitee aretpeiild

,or 75DD cycles of mrrsaim lead Based a Mthe, the projected CUF for 60 years is cacufoated en 0.O2M PNPS Lead Chert, Letis PA Wof 77

James Davis-AMR - Reporttothe NRC.doc.pdf Page 64 Number Status Request

Response

NRC PNPS Lead Firsin, Flon 477 Closed jTLAA-H-W3]

Tel.d e Engineerirg Services docuenwt TR-5310-2 dtcneross Hoanr Dan stres evaluatios or the SFRV ppi rig for various loud cosrnatiare, Please proide Fatigue, alysis of the SRV dischtge but does rot Include a fatigue anal ysis. (The fatigue analysis of piping and Fatigue selysis d other Tots attached piping the SRV piping along with all the othw torus attached pipirny) (TAP Is boended by lsPR-751, the GE0 ark I cortainreot pmrogram WPR-751 -onluded shet ler all plars and piping systesre oosidened, in all cases the fatigue usage factrs loe an assu-ed 4O-year pant life wasless than 05. Inaworet-case swenriw o oWtarding pIlat lfeot eanaddlti coa 20 yes would prodte usage ateters balem o75 Sinre this is less than I.0, the fatigue criteria ae satisfie The lA-751 gane rio taligue analysis is thus proteted for the period d extenrded operation in accordan-a with 10 CFR54.21t()(et)ii).

APNPSd0aot specific arnaysis adftses the SRVd lsherge Ppipng and its supports, as wel as the msin vowe penetration Ihrongh whichthe SflRVdscherg enteore ts thorus Tse analysis states that Ihe SAVpweltrafin we qualified le 750 cycles of mxiusn load while the SRVs wre epscted tbsee less than 5D cyese at main-mn leat an less then 4530 cycles a partial toad The rqwpt ooludees "Sinos the 75DO cycles d t-inluj load bends both ud these by sorh alarge 1rmrgin and ss m cno"w igniicawt lod we lopoeed on the ine, the pse-taion was asounred acceptaek for fatigue withe urther eealualioc " Increesing the 40eayer cycles by 1.5 let the period of outnted epesalio would still beoly 75 rsain loed cycles asd 6750 low loed cycles fet sot al 5630 rioxed load cycles, les than the 7500 roxrinum loud cycles permitsed The fatigue arnlysis for torus perlleatior thus rsransi valid for the poerd do etsleeed oseratio in -dor-tree with 10 CFP 54.21(c)(tfi).

The PNPS plard-speifit analysis (TR-5310-2) ralede.es the gensec GE Mark I Corninees progrea hoe othrw torus athed piping The results al the genwic GE Merk I cortalneort progrs (bteed ou pesrs Ya dparstio-) wore that 92% l the TAP would here curnulative usage factor of less thn 0.3, and thM 160%

would have usge factrs lessthEn 05. Coorvasively rustiplying the CUFs by 1.5 shaos that for ee yeas d operatin 92% l the TAP would have CUFabaos 0.45, and 100% would hweo CUFs below 075. These calcelatieos have owue been projected throueg the period l 'tesnded operation in ccordance wth 10 CFR 54.21(c)(1ii).

Pao Wod 77

James Davis - AMR - Report to the NRC.doc.pdf Page 65 Number Status Request 490 CIo N

Wt't Is the operatring hitoy fto buried pipe. inlern othe nmber of inspectione aeid any leks"d their cause, (ioniem o eterenal caused leeks)? Hee any buried pipes been replaced due tocorronion or oeting pronem's? If the phased arrsy UT technique is used, how will it be qualified and oe will the operalors bectualified?

Response

In the past 5yeWa there as been limited ewpeierne with the inspection of buried piping atPNPS. The experiere has occurred mainly on the fire water uderground distribultion systerm, This systern is approxirrmaly 35 years old ed onists of cment lined tlletble inch pipe with mecharical joints. There tes been no history o lgnificanti leeks other than during two instanres, onr in 2001 and one in 205. In the firet verl the Ir underground fine down stretm of 8-L-22 bled. The probable cause of failure was most ikely induced by minor tabrication aeonmaies oonmould.ed by marr$nal installation techniiques. When this piping wae Wsoeamed it was lourd to be overall invery good condition eternally excepty r

a emall aree of surface correioer attributed to nrgfirml irnlstlation techniqupes In the second ewer the 8r underground pipe failed in the ea of the N2 tb* edrqacrm tothe EDG bdiidingt Due to congestion nld the presence ofIte t"a", Whichwno installed ebseqeent tothe iretalatitot of the pipin,, it was toE poesible to dg upthe piping to mnins it atnd determine the cause of the bailure buWy tberelated tothe installation of the lark-Inaddtion to these two instancee there have been a nuber ofvalves enoavaled during rnineereane whichlonld the valvee ard piping tobe in rerktkaey good condition, Fro an addlitionl historical perspective, the eOl service water (SSW) eystel at PNPS has emperelnced leaks onthe buried trial (screenhtuse toeaeitiary boys) piping en a reeult of internl corroeion The riginral piping material was rubler lined carbon etedl wrapped with renforeed fibonjlass wrapping aerd coal tar saturted felt and heavy Kralt pacer. The leaks were derrieneed to be the result of the degraded rubber lining being in contact with sea water. Theme pipee here mimee been replaced with udiined Titoanum wrapped with the same externl coating me the oriinal pipe. The pipe rplacemenrinenurred in 1995 arid 1997. In addition, ;W SSW buried disclharge piping (also rubber lined carbon steal with eaternal pipe wrapping, same as einme piping) from the autiliary bays tothe discharge canal also etperienced aewre ilnteral corrosion due totaluiree of the rube liring. Two 40P lorghe of 2 -dameter pipe. (on ea. oh loop) werbrepiaced in 1999 as a reeuit of the failed euber liring ard iniernal orrosion. Theme spooln we replaced withoarben steel coaled internaly ard miterrenly withaneoty coaeting The piping bth was removed was eronined after le wrapping we. remo-ed and ite emternal sucaceo was found lobe ingood cordtio, Since that U-6e the entire lengh of both SSW burled disharge toope here been lined itnernelly with oured-in-place pipe linings, "B" Loop in2001 and "A Loop In2001 The pleeld array Inspectlon technique, was provided merely a an amerple of aypotenrial future earninarton tshnilqo Itaeld other remote techeiquee will potentially beetlle to.asess the conrdition ol tdenwive portions of buried piping without the nerd for mecavatiort This eception was taken to allow the ipoterial wee of thIe oeheique r onthers in lie. of etonoting piping in order to provide a more eteotine aseessesment oiorenall piping condition while alimirting the potential for damag ing the piping during excvotion.

P4W 65d 77 NRC PNPS Lead Davis, Jim try, Ted

James Davis - AMR - Report to the NRC.doc.pdf Page 66 Number Status Request 494 Closed Five liielt-si iTabe 332.24-l (LRApages33-134 through I37)

Mrence Table 3.4.1 item 3.4.1-8 and credit PSPM Progar to menage tie aging efect of LOM for eteel piping piping components. and piping demente aiposed to taw water Please identity the specific components inthe CirculatingPatin Syster" Val aer represented by these Table 2 lIn items and prs idle procedures under which PSPM willbeisplemented tormanage the aging elft of LOM due to general, pitting crevice, PiC, adl louling.

Response

Since a superior inspection teafrcnia is red yd available, epecitics regarding qualification of the process and tlnticistaw ner atilable The circulatirg water system consists primreily of two circulating water pumps and associated piping and vaiet as shown primarily on WMt1. The reaiewtodnternine the 10CFR 54.4(a)(2) componts used a spaces approach ftt Identified ailrpoe types and nonae-a cobinaionsi inthe system th were in scope he did rno list Individual comrporent nubiers. As ideatliied inULtA Table 23314-B, the only areas of the turbine building fhat waem escluded were the components inside the main condenser and the only portions do w intake etructusre Oh were ckluded weretbe ineakte stra typsetteait pimp rosm "l chtvrailon n The components included btiing, circulating water pump casings, the above ground piping, tutbing therowedls, the condense inhe oulet and croescorrect salvo, ipansion joints and the associated sent, drain, and instrument valve bodies. The water box scaesring yet-shown -fi WshI area

-ons in use,p te ow portions "at still form a pressure bounary for the watn boxes we included As idntiied ons l12 Shed t, an r1sitidl tHorine saMipe pump ise longer usied, bud portione sow eyemt weri included the still ftem otw pressure beurdeay.

As ieicated inAMttachnoa 3do LRPO-OZ Agrg Management Program Evaluation Report (AMPER), procedures do roe mist le the Irnspection of these cosp*or*s, and acomplee listing of components ant willbeincluded inthe procedbem is not eatlable.

As stated inLRA Appendex Ball Comritment

21. program activity implementing dmumetse will be wnced prior the period of eatended opnration to ireorporde oieattribute odthis inspecticn dascribed In the A/tPER. Tie will assure thatan effects of agng willbe managei such the applicable ocirponttus will continue to perform their intended functions conistedt withthe current licensing besis for tie period of eadended operati-n NRC PNPS Lead Wen, Pent tY, Ted PAW 6d 77

1James Davis-AMR-Report tothe NRC.Pdoc.Pdf Page 67 Number Status Request 495 Cloasd Four line items inTable 332-t4-1 (LRA pages 3.3-134 rald 1t5), PNPS claimed that Circuating Water System, corrspont of plping and tarts whchare rmade ofplastic, have noagng effect rdr wonentation eternat a raw water irntrnal enviro'nralnts. What kind of plastic material ae they. Why are they not auAdect to aging dgect?

495 Closed Four line ittem inTable s32-14-1 with note F(LRfApage 33-t1M), the applicant proposed to mrage cracking aid change in materiad propertles of the elastome ar frcoldenser ecernsion joint arpesed to raw water aid condensation in ertarrt ecirorner ruing AMP at Pariode Survaillaro and Prenetiva ral areae-e (PSPt4. Please proeide techical justificatior as why PSPM alre is suffitent to manage the aging effects of cracking and change ina materia properties.

Response

Sonre o0 the circulating water system piling in scope tor

[Maintenance Rule 10CFR 50651 (a)(2)shown onthe piping &

iratret diagrams is piping codes JE aid JF. Pipe class JE is ffiowillass rainorced plastic As kdernified inthe PNPS Specification tar Piping M30t, piping code JF allows the uwe of PVC plping Per Nde 3aon K1t1. some of the piping is PVC The 55 gallon drum shown onlW12 Shedl I whch is the tank inths line tean is eso PVC Aging affects were identfied for (a)(2) components included in AMM-3 usaing the Non-Class I Mecheiocal Irnplem'tafsion Guiddine and Mechanical Tools, Revision 3, EPRI, Palo Alto, CA 2flt, t00306 (The Mechnnical Tiols). In acaardane with the Mechetncal Toois, Section2 t.8 of Appendix A, PVC and thermoplestice are relatively unaffected by water ar humidyi.t The components inquisition we installed irdoors aid contain raw walar.

Tharefe, based onthe Mecharical Toole and industry operating espedince, dig piping has no agng edfects requiring mneagemarer In raw water a condensation environments.

As indicated in Attachment 304 LRPD-0., Aging IMansrgerre Program Evaluation Reporl t(AWER), Irepectior. willheparormad to delerrine the sueace condition aid flerrbility oa the circulating water aseraason Joints As indicated inathe AMPSE, a representative samnpe of the eap reion joints willbe vsually inspected aid ranuly flted every 5 years toVerin y nosigntieanr arkeng or ither abnortralites while flteing elasioner "on ar"s A visual inspection and physia *areipulation of this aomponart aurea het the elatomar lai craeking aid that the retarial propertiee of felteritoty are still adequate for the erperalon Joirn to maintain its pressure boundary ad rot affect safety-rdated ooaponaset.

Industry operating experience tor copronerts of iths type has scown that the fre rencyp of inspection should beadqale to manage thPee aging etfects.

While thee aomponents are managed by the sedetive heching program tar the interal surfaten the saelctive leachng program Is rot credited witihe mranagement of loss of mtatermat for enterral surfaces that are oay waited by aontnsationa N thesea componaens were to wpenriwe selective heaching, the aging didec willocLrs on aid he identified bythe seleotive Leacdng Program foP the naineal surtace Pat is eoposed to ran water baorea/

aignifrit o

alecive leaching is eiaperiened on the mdernal r

urfate o

at is wetted only bytppanda ordensalionr Ths is due tothe minimal amourt Oat electrolyte that is preseng in a periodic candensation eanvironment.

Thereare, the System Waikdown Program alone is epected to be a adetate prograe for the mistraitl rfacn of time corriponees.

NRC PNPS Lead Wen, Peter Ivy, Ted Wen, Peter Ivy, Ted 497 Closed Three lineirems in Table3.12-14-1 (LRA pages33-134, 13t, aid t36), the applicant proposed to manage LOM of coppi alloy >1c5% Znlor piping, strainer housing and valve body enposed tocrdentaation ertearal envirarenrl ruing AMP of system Watkdown PreRse pronide technicao Justitcation as why Spastem aIkdown dae is suffioietr to rrege the aging affect of LOM Do you consder the aging dfent at loss of mateaia cue to selective leaching for these tire titers Wag Pdar Ivy, Ted Pa& 671 ;7

James Davis,- AMR,- Report to the NRC.doc.pdf Page 68 Number Status Request 49 Closed Eleven tire item i Table 3.32-14-9 with sets G (Eitraction Staem System thS applicant proposel totrnaege cracking, LOC and cracking-latigue d nickel alloy for exypansion join eag-sed otasted water usirg water chetistry oorerol BWR and TLAA Metal fattgue, Two line Aetna related toTLAA netal fatigae will be krpedt to Question 341 -W-01 for dissu*sior For the oher 9 line iter, pleae preido technical justification as why Water Cheristry Control BWR alone is stficien! St menag the aging cfteets of cracking and LO 499 Closed

[T.S3&?144 In Table 11.2-9, Fire Protection - Water System, FPNPS credits IRA AMP B1.1.,

FireProtection Prograeo to ranage aods of material and toding of gray iron ad opper ally >15% Znshed exshager sael and tkbes. However., the Fire Protection progr-w deser ilpion does nre irclude these corrqeenes nor has the prograni been enarsed toinclude t1heasertOpsrerts Ptess sarity how the FireProtectson Prograt will mrawge, thee aging affects for theae rripnrs.

Response

NRC As can be seen in seation 424.2 of LRPD-OS, Agrig Mrrgerert Werk PeteP Program Evaluation Report (AWMER), the water chaeistry consrod-OVIR progrew includes peWods Mronitoring and conrrol d knownsdetrirrnetl onramrirets suachehetorides, dissolved oxygen, and sultate W

orNeW ttiore below the leels known to reuit in loss of raterial or crackirg As Idetified insAtachmett 2 of the AMER, aOrr-Tirns Inspection Progra-will be eornpldtd toveity the aefecttvehess i the water cheyistry corerc-BWR programs to manage the aging effects of ioss of materidl and craskr*g-Theciore, the orrrbination of hese two progaene is wdticianl to Manage te aging esfeats of creking and loss of material for nickel alloy coregonerts nsyposed to reated water, ThisreqUiresansers me tothe certristry program descriptiorn in IRA Apperdies A and B to slety reIate that the Cm-Tire Irspection Fyogase willcondirm the ottestinenese of the Water Cherestry Control. SB, Wter Cheristry Contrro - Ailtiary Systemnn and the Water Chadistry Cortrof. Closed Cooling Water proga This itat is closed to Itm 372 PNPS Lead toy, Ted Ivy. Ted Inaccordance with AMe B1.13.1, procedures wilt hbeetretd (astribuoe 3 and 6) to verity I hat the dead &V m does not ashitit aigns of degradation waile runrtninr, sach s foci oil,.ube oal, coolant Gacket water), or exheost gae leakage. Through monitoring a nd heeing of perlorswce dda, specfically jacke sooling

water, forling and loss of maserial for the fire punp diesel jacket water hest mehenger willbe eitieidd and orrected through the orrectwse action prog-a As described inoperatitng experience fol AP 11.13.1, Obseevation ocdegraded p.Iforrncne produced correative actiorn irhluaing eng n replaerensrl ln20 prior todoes of irtended terntior. Conrseartly. contireed isapletentation of the FirseProlection Prog-sw provides reasonable asserane aging effects will be mnaged h the diesd fire petp jackat water hael twohetge. In adolifort, PNPS pert*wa Sfireypup inpectior, tesling ad nmirtere loacoerdawe with NPFPA25whoih would elso deaed the preese o agng effects in the acket water systes prior to aode od inrewded teIion.

This itar is losed toiter 378.

Patd, Erach P'P 6 77

James Davis - AMR - Report to the NRC.doc.pdf Page 69 I Number Status Request Soo Closed IT3Z.15]

In the tRA, PNPS has indicaed tNon-Nord for A-JAM ocomb*ration in swwae Table Zs in section 3.3, ton plastic ocnvoneres invarious erwironrts.

Piease identify whet Win(s) d plastic material is (we) uwed at PNPS.

B0I AccepAt

[Tr.3.a216 Is sonm Taele Za, PNPS hms stated "None-Nore Won AE/AiP ontbrlnion for stainless stae boiting Inan air-otlc envira-sent, however, inTables 3.3.2-5 and 1.2-9 PNPS identified loss oi rntwites anon aging eifect for the saen rnaterial/enyiron mnut comnetntion nd oredlted the system walkdown prograin torneage this aging effect In an oitdoar enwirornent, sdnlesw feel materiwi said be ssceplible to ces o msetwisl Please clarityti tiscrepeany.

Response

At PNPS piping codes JE, JF, J3 and HT ase plastic a fiberglass As identified in the PNPS Specification tor Piping M3)0. pipe clo JEis hfiberglss reintorced plastic, piping cade JF allows the weed polyvinyl chloide (PVC) piping. and olms HT piping is PVC. Pwr note 3on

-W11, om d ithe pipe ode JO is PVCý Some specific nonioent.s swe also identified as plastic in the IRA that waenot ineltled inthe piping class sunsary sheets wmich required couonet* specitic rniews to identify the-aerial FPm instance some omponents stich as the tok shdwn on M212 sheet I is identitied on the drawing as a 55 galon PVC d-and some piping likethe piping onI&73 shed 3tis idenlified onthe drawing an othirinated p-yninyl

.htenide (CPVC)ý The fuel il system table 332-7 ateo identifies a plastic filter hewing weed onthe stalion hblacota desel fuel l tiftw X-176.

These we plastic bowls at the battn d the filter hasing that oollect water and sedmnent. The esact type odplastic is not known Wt wasseloected fornme by the wrginrd anesdactu in ntis applicatimIn eaddition, sinnri to all the platic nalerials described above it is rt exposed to direct scnlight and was designed Ihbe oned with fued oil. Therdore, as stated in th EPRI Mtheaenial Tooes tene d these conpanant Is expected to experience aging effctns ta repuire anwagwnent inthe wvroniornts to which they wre aipnetd.

The only tasle that dd rd itketify losh ed mnlerial for stainless tede boilng inan air-Andicr envirornant was Tale 3.3.2-7 fh the fh-ol syste Loss dl rterial is an aging effect requiring nnagerent ftin sheuid have been idene ied for the san rnlen sed belting with an envirorernt d o-artdoor. This aging effect is masnaged by the Sytemn Wadkdown Program, Thisrerpiraeanarn tnrt toan eLRA NRC Paid, Erach Paid, Erach PNPS Lead tNp, Ted ivy, Ted Pap F 9 77

James Davis - AMR - Report to the NRC.doc.pdf I Page 70b Number Status Request SM Closed T.332t7 In Table 33.2-14-21, PNPS has credited the Water Chesistry Control - Aueiliary Systems program to manage the aging elect d loss of marial for coopones inthe potable and saritary water system, However, the program description and the scope of the program only address stator cooilng water cheraistry The only dement where potatle aid earltny water is merioned isinothe closetst tr detection of aging offects.

Please justity why potable and seanitary water Is nrt identified inthe program description and scope a werk er syplhmest the progm toricalude it.

50 Ope, -

Ouection 4.3-4Identify wtichooogoreriamno city Plait groupa inAMR Tables 3.1.2-1, -Z aid -3weredesigned to ASW Section It1 Clarityw wich ortiponeis*como o city groups a1ce-d ernAStEW Section III CUF calocuation, and identity whih comowdity group listing in LRA Table 4.3-1 provides tw applicable CUF result. I no CUF satiouation was perfor-4 justity the basis for exclusion and propose as acceptable AP to aage the aging effect 'cracking fatvgud in accordance with the criterion in 10 CFR 5421(s)(1)(iii). Ift -eclusison from perforning aCUF caloati*n is based onan A.SME Section III, provide the paragraph In the Code.

504 Closed Quection 4.3-2 Idedfy whiohcomponents inAMRl Tables 31.2-1, -2. Zad -3were dsigned inacoerdooce withthe A.SKE B31t1 Cols. Clarity whether the cmodity groage were esaluated for nallowables atrsc re-t&ion seasceer hss ea osthe 7d_. thermal cycles in aoordeise with the B31.1 Code. Idetfy whether:

(1) the allowable strecs rerchtios acnflyss remtai bounded unier toCFR 54.2t(o)(1)(i),

(2) the alowable stress range needs tobe redsaed In accordance withthe atreas redtction criteria inthe 831.1 Code tocomply with 10CFR 54.21(e)(I)(ii). r (3) the ging effect "cracking - fatig needs to be maneged

,or the period oi ente-ded (EPO) operation in ecoordaroe with IOCFR 54.21(c)(1)(iii) and propose anacsplable AMP to. maage the aging affect.

Response

NRC The 'Scope of Prograre section otB.t.321 dthe LRA states city Patel. Erach water is taken from the Town it Ptymoith water nain and distlritLAt WhrouOn the potte and sanitary water system at town water pressue City water is moritored and treated by Ohe Town of Plymoath to1 mst the reggtstioer it the Commonwealth of Massachusetts As stated i.the DDetection of.Aing Etfects" section of a1.321 of the LRA, veoiatiorl that the water monitoring and treat*r*t by the Town of Ptyrestr is efsctine will occe under the Csc-Timn Inspectocn Prog'am, which enleds inspections toverity the affectiveness of water cheristry control programs to ensre thset significart degradation is noe ocurring and component intended tertion is rreienraned dtring the period oi esterdaid operation Therdeore poable and earitery water ia incruded inthe program The response addireees Quesfion 504 and QOesilon MS.

MeW t, Jim Answered in~oeftion SM.

MeW., Jim PNPS Lead Ivy, Ted Firiri Ron Finrrir Ron PA lOd ?77

James Davis -AMR - Report to the NRC.doc.pdf Page71 Number Status Request 65*

Closed Q

sestion 43-a. For rnt-piping somponenrs/ommo Alty groups inLRATables 3.1.2-1, -Zand -3t1ha werenol designed to ASME Section III o AMSE B31.1, identify which design code applies toll.the pricdar commodity grou and clarity whethtr th design code required a metal taotgue alyosis.

oea t m

t"ig.s analysis was reqired, summerize whet typo ot *sa" mtalysu Caoculation was rairesd tobe prtormred ard diseas how (1) the anasysis remsir baouding ndere 10CFR 542t(o)(1)i), (2) has been projected tolhf expiration ot the EPO end *as acceptable pursuant to 10 CFR 54.21(o)(1)(ii), or (3) whlerh an AMP reeds to be proposed to mang the aging ttfect of cracking -fatge for the EPO and state which AMW will be wsed to mtrega Whe agng effect-s e metal latigue oresyols was not performed and 'cracking -fatigwe reeds tohe swags for the EPO, propose anaccepoeble M*P tor the weeyrnl ofathe aging effect ineacordanee with the criterion in 10 CFR 54.21()(t)(iii) 5We Open -

Oestion 43-4.

For na-piping oomponentslcommo dity plano groupa inD LTIAbT]'

3.22-K a3.2-X and 3.42-l( identify which design sods aplies tothe parlisular corrnmoity group and clarity wheher the dcsign ode reqired a metal fatigue sreysis.

s eata ftat lysg welpis was reuiresd, sesum rize whet type o n*t faltiue calculation was reqired lobhe perforrme sid discuss how:

(t)the anrlysis rernre bosnding under tOCFR 54.t1(s)(t)(l),

(2) hts been projected tothe eypiraoe oft the EFO and remains a`eopable pursatn tot10 CFAS4.21(c)(1)(ii), or (3) whether anAP' needs tobe proposed to ennage We aging esect of cracking - tsflgdW fr the EPO and stole wioh AW' willbewaed torranrgs the argng etfect f a wtal tslue analysis was tar pertamed and cracking

-faligue needas tobe manage for the EPO, propose an aceptable AMP fo the maetgered ofhe aging aefect in

-seordance with the ritelron in 10 CFR 54.21 (c)(1)(iii).

Response

Answered inQuestion 5o.

NRC PNPS Lead M.o"f, Jim Firrin, Ron Mednd, Jim Firnsrn Ron PaW 71 d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 72 Number Status 507 Open-NRC Request Question 43-5: The application stales tha. while rot mandatory, the design of the RPV interre comnens is in aco-r:arnce with the intent of ASKE Section Ill Please claeity from both a regilatory and technical point of view what istrean byydesigned i Iaccordance withthe 'intern ASfE Section Ill." ordnity which Edition of ASKE Section III is bsing rederred towith respect tothe design o the RPV hternas.

Response

The statermet tht the reactor vessel internals wereboilt to the irnel of ASIE section Xl came fronm the FSAR. GE made t~S staterent inunay c the FSARs for BVsNofPilgrimfs vintage This statemnit cwr tat the design of the reactor intoerns was better than commercial grade quality. IMaterials, wall thickness, constrclion techniques (ircliding welding) were what wouLd have been used for an AS5E comn rt Howecer aerlyses and testing weree oi pelorrec* or doeclatti as reqdLred tor a onportent designed 'inaccordnce,owith We ASW code As no specific code was adhered to, rspecifa code year was specified; hwecer, es the internals were designed as pert of the plant design Ican beassumed the

-arrn code year (19OS) was

_d for general guidance LRA Section 43.t.2 willtberevised to delate Whe statement tWt the interrlos wce designed to the Intent of the ASKE code as faooos:

'43.1.2 Reactor VeWel Internacn A review cithe design basi rdouaent redeas the the Orly inrerold co*pwnert hoe whch Owe le ta ftig analysis is the coe sheoed emtaizer (tie rods), the reasit of a repair to strhurally replace cirountererlial saraid weld' atrrourlng the core The aatlysis is sTLAA. The trnoism CUF idetitfied ior the shroeid for 40 years of pewaion is 033. The CUF is included in Section 4.3.1.

The Fatigue Monitoring Program -e.res tetig.e a'eyses remain valid by monitoring the eatal nsmrbes of cycles ard evaluating them aoalnst the design valuon he ruates of allowable cycles. Timt-linited aging analyses (ttigue alyses) for the core sWhoud stablize will remein valid for the peiod of eatended operation inaccordance with 10CFR 54.21(cX1)(i)or the effects of aging onthe intended r

unctksr(s) will he edeualdy mcnaged for the period of e*tended operation inaccordance with 10 CFR 54.21()(1) (iii).*

The repres aneesadment tothe LRA PNPS idetified nontrctree mechantes (flaw gowth) enalyses Inh were TLAAI The results of the PNPS review of these nalyses ae oeatd in Section 24 of PNPS documetn LIPD-06, -Ucited Aging Analyses

-Mecharical FaPlige Three Saw growth eanlyses were lurd (Whe CR0 nozle toend cap weld, the Reactor Recirculation nozzle therna sleeves, acd Reestor Recirnoation nozzle N12). None of these antlysm were TLAA.

NRC PNPS Lead Medoff, Jim Finrin, Ron 5ir Open -

Question 43-The first h*l paragraph on pege 4.3-2 states NRC tha fracture mnchaecs analyses or flaw growth analyses are TLAs for PNPS if the altyses we based on itre-lirnited cssurwqtlh. Identity all fracture mechanics orfla growth safely esassents that meet the criteria for TLAAs in 10 CFR 54.3 IN ery maist, ecamnd Section 4.0 of the LRA to nclude them as TIAs lor the Wepplication and ealuate lhem inaccordance withthe redUremetns of 10 CFR 54.211()(1). Inckde enough techrical iniormotinion ojestity acceptability i the fracture mechaeocs or fn growth rleys-e. kgy fracture mechanecs cr flaw gronth analyses that med these TLAAofllcriawihlbeecalUated byte NRC's technical staff inthe Diolsionci Component Integrity, Office of Nuclear Reactor Regiatior Msdl, Jim Firnnin Ron FPW 72d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 73 Number Status Request 509 Accepted

[36.22-N-07j In LRASection 36 2Z you hae stated thaI reýh*wenl wear is an aging effcdt for etreinand stapension Irnseators in thal they are subjeat toorvenert.

Wear has rot beear apparad during rotina iapaectionsr. i fell -Wgd for the period d eutaeded operiora, surface rumt would rot cnute a Ices of inended lunction ard thus, is nri a signifi c ona ernart Provide a teahrinat justification of wiy ken aterelrief due to reencrd waee caused by wind blowing d supporled traenar isioneoonductos is nre an agng edect reqoiring rg for te gt-vo*tags insulators. Also, provide a tehnical justilication ofwhy surface rust would no ce a loes of irderned function ee is rno a significanlt *rnarn Eor Ngf-voltage itefators if left tmnegal for the period neolftended operation 510 Cloedal 13.622-N-08 Valous airborne materials such as enust and industrial eifluenl can eattarinate Inulator surfaces. A large builcdp of oertainabon enaaleae lh econductor voltage totrack along the stface noa easily and can lead to Inrator flathwer. Explain cy surface conrarrir1etin suchdaselst and rinustial effluent is rot asignificant aginr defa reqiring anegenert for hii-vdtago insulators at PNPS.

Response

Loss od rraterial due to rean cail wear is an aging effect for srain and suspension insulators it they are subject tosignificarl

-e-ent. Apoanibs nouse far mener orthe irseadtors in wird toiing the supported transrission condlutor, allowing the onrductor toIwing brem side toside. Pthoadi thIe rnachiism is possible, inaustry eaparience has shon transamission cornductors dt nor normaily wniog and thai when they de, due to a subtantial iind, they de not continuee o swirng fo very long one the wind he subsided. PNPS has noetrarerni ssionic.onutors supported by hligl-voltage insulators in-sope df license r-nan and threfore koes d rnealrial due toweat of Nghvolta-e inseuators is eot a-aging dffect requiring rranagernedt for lt pearkod exteneded oepratiore Various airborne mralcies such asndtst, salt and industrial diluaels can nortarrinale insulator sulaces. The buildup d surface ontardnratok is gradeual and Inerrot areas washed away by raint wklt*e glabzed and -oated insulator sturfaces s PNPS aide innortavrennn rennet PNPS applied Slygard (RTVsilicne) catirnge tosore, switchyard insulators to reduce flhver. Sutare ooarnaination can be a prbemn in arees where then are grete oeneersalions of airberne perticles such as nar facilities that deahb-ge sea. PNPS is nt r

cd ated ner any lecilitien teW prodece airborne perlinle such as so.

Therednre s, ans cnra'taireioan is red anapp Ibao aging techariee for hft-olntoae inslators aS PNPS.

LIRA Section 36.222 bee a typo In the fourth paragraph. The peragraph stadd read as fdlows: "Meatenican wea is an agiog edfect for strain aed suspension iruiators In lda they are subject to no Anent We-Fee not been apparent during routine i-pant-e IN Wt urmarged for the period of eastended operatiorn airfare eondreinleion would not caus a a hees of intended function end u,. Is nor aeignificarf oercerr, The requires anarerdrea to the LRA

• Sine vaious airbrne rteriats such as duet, sat and irduefid edfluents can contarrrinte Idelator surfaces The buildup of surface eolareiretion is gradual and Inmost areas washed aney by ran, wlIathe gla azed doated insulatot surfaces la PNPS side In nartarriction reefnnal. PNPS applied Slygard (RTVsilicone) coatings to sorne swilchyard insulators to rede flashover. Surface cornarainefion can bea pralern inareas wchar thle are greater eoncertrelione d airborne parlidae such as new facilities that desharge seoa. PNPS is la loeated tar any facilitis that paodece airborne parlicnle much an dust oar sot. Ther-ore, aurface nortarrination isan app licable aging rnecharern for Nght-vltage insuators at PNPS.

NRC PNPS Lead NgvLar Dn Stroud, Mike Ngiger Duc Sfroul, tWke P4X 23d 77

James Davis - AMR - Report to the NRC.doc.pdf Page 74 1 Number Status Request 511 Closed (36.22-N-091 Provide a technical justificat ion of why ircreased resistance of switclyard bus nor-rections de toboxidetion is not an aging dffect requiring reregurt 512 Accepted

[3.1.1 LRA Table 3A.1, Item Nutsr i48, is appicable for OsGl s piplrf littirgs and branch lines <NPS 4" esyosed Ib raeet

.o.i.s The GALL Report irdicates Is the aging effects of cracking die to lerrrnl and mecheracal loading apply lor both carbon led e staintes sled o nr.

Howve.r. no CiO-s piping -=oonis made of arbon sled ar rolled pjto lids line item, Pleas e*plian why ro crhon sleet piping ourjponents wre reied Lpto tlds line. Aethein noClass I carbon sted piping asrpenis

<NPS 4=at PNPS? I there we Class I rbon stle Piping mponwets <NPS 4 at PNPS, than piesse justify why theyare not rolled p. lir-ite 3.1.1-40, 513 Accepted Asa folow-upr loqesltion T32-1-35-P-O1 (itern 442) one d the line iters thai olls upto Ites 321-35 only credits the Corotainmert Lea Rale program lor snafng the aeing effect o sles of materisl. In asordrace with GALL X154 lids progamn by itself does not decldt in aging degradation has itiated. Plesase expiain how As use dtfbe Containrenl Leak Rali program is acceptable by Itself to an.,.

aging effects.

Response

Apolorsial nehsnian oortibrding toagng a switchyardbin oonnections is surface osidatiorn which can lead to inoreased or-act or onneclion resistance Connection sioace esidetion is not significanl for swilchyard bui norections at PNPS ales the switchyard bus ovrvneutione awe wadded Therefore, noagng effects due tsoi-1se oxidation we required lobe ranaged for the period of a*ltded

Zerstion.

The torrection toactive dvices we impeoted undet the itenanse Re programs In edditnor, thermoraphy is perflmed at leaest every 6 mrlshs toonaireain the irtegrity of the conn__tons. This program will cortirse iro the peried of eWended operation As stated In PNPS AlM-3%. "cracking die toflaw growth is managed bythe inspecaion requirernr*s for Class I ornqoner-s In noordarco with ASIE seclion XI, Siksection M8B Bacause lmeroioeinspection per ASKE Sation XI is reqlured ineaocomance with I0 CFR 5b.55a, cracking die to flaw growth is nK identified on the tables inAltachment I. Cracldng die Io flaw growth is oonsredeed epivatsnd toithe NUREG-1801 ertry of cracking due to thermal and mecharical loading The SI Program applieIs GoCls I carbon stedl piping oompovnerts at PNPS The IRA willbeclarified loshow thn oracking is an aging eafect relgiring rangeres for Class I wrbon sted piping cosponents

<NPS rat PNPS and in the qpriopriate aging manegemerit programs Include the ISI Progran and lhe One-Time Inspecties Program The discuseiol oolu hr RuIm 3.1.1-48 will be revised to be consiste with this changs. The credited aging managemnt programs will be the same as thsee listed for A NLUREG-IbOl line Itens orresponding toLRA Tab*e 31.1, hen s

48.

Thes reires anemerdrnati lobie LRA The Periodic S-veillance and Preventiove itereroe (PSPl4 Program is more appropriate o flanage lssa dmaterial hor piping aet valve body in a raw water inerrnal ernvironie in Taels 322-7.

The IRA willberevised bocredit this program instead d Corisinatn Leak late Program bo rege aging dlet of loss of material. In addition, the discussion in Iten 3.221-35 of Talle 321I will bhe ised toread as follows: The Petiodi Suvdllance and Preventive Mkeirteraroe Prograrn neaeges the oes of nwerisl for sdel oomponens exyosed tobraw ater."

Thie rescirese anardnenlbs lothe iRAborevise Table 322-7, 32aI andAppenix B.

NRC PNPS Lead NgrrV, D-a Stroud, Wke Jackson, Wilbe, Firsin, Rid Pavinich inyrs

&y, Ted Pe 741 IF77

James Davis - AMR - Report to the NRC.doc.pdf Page 75 1 Number Status Request 514 Accepted

[31A-321 LRATabee fites 3.1.1-14 3.11-15 and 31.1-47 all include discussions saying this agng ofthe compotts rolling up to those li-will be by Water Chemistry augmented by the Ors Time Inspction Program Attachernt 2 of LPRO-OZ RevisionOZ proides a list of AnMRMs aeoclted by the One-Time Inspection Acti*ities. However, Aftachtesrl 2 does not Include AMRM-31 (Reactor Pressure Vessel) or AWRMM32 (Reactor Vessel Interrals) inte list dltected AWVl

,s Please protidt an peanati - d Vy AWIM-31 and AMRM-32 ace not included inA tacretent 2od LRPD-02 Revision M How will PNPS ensure that appropriate sm-lime inpectlias are pertormedl the RPVI ed RVI osporwats shere such inspections ae credited for Aging Mehagemen-t tring te period of Wtended operation?

Response

NRC PNPS Lead Throughout the appicatiort the One-Time Inspection (OTI) Program Jacksono Wilbur Finrero Ron has beea treated as a support program for the water aesistry program for the purposes of verilying water cheristry program tafectiveness. The Om-Time Irspaction Program has not been treated asans alg magasent prograr directlyapplicable tothe systelm thet credit water chemistry for agng manaement Ths treatmern was considered appropriate since the veritication of water olerristry progrrt etfctiveness willheone integrated task OW serifies eatectaveress o the program for all system that credit wmat chemistry; the watert chemiatry program effectivesess willnot be verified sepsrately for each system. For the cases where Pne Om-Time Inspection Program addresses componern specific inspectonls, it is listed in P LRA a as aging sergwit program drectly applicaloe tothe oatpotes.

The first row of Attachnetl 2do LRPDC2 Identifies the activitis do Pre One-Time trapectiat Program thPt willteily water chemistry program effectiveness for all systems tt credit water chemislry.

This line applies to the water chemistry prog-ram, inludig Water Cheatistry Corterol -BWVR, which Intuarn applies toemwy of the system listed inthe applicatio The reactor prearure vessel and reactor vessed iretnaes cmponeras credit the Water Chesistry Control -BWFR programr, soth limeapplies toAMtM-31 and AMRM-32 The renanltng lines of Attachment 2of LRPD-02 iderstiy activities of Pt OCm-Time Inspection Program that address omponornt specific inspections. Appqicab! a system se identified for these inspectiors.

Pft 75d 77

James Davis - AMR - Report to the NRC.doc.pdf...

Page 76 I Number Status 515 Open -

Plant Request IRA Table 43-I provides the limitirg 40-yew cunulative usage factors (CUFs) for the RPV, RPV internal comporners, and reactor cooarnt pressure boundary (RCPS) piping that were designed toAStE Section Ill. Wth the exception of the CUFval,.e fortRPV feedwaler nozzee, PNPS has accepted the TLAA Metal fatigue CUFenaly.e. and stated that the 40-yew CUF corclusion renains valid for the period d extended operation (EPO) inaecordanee with tOCFR 54.21(c)(I)(i)or that the effect d 'cracking - fatigue" will be mnaged for the EPO.

The last paragraph on Page ItI o LRPD-06 states that more the tf othe design basis tansions dedined in the UFSAR projections show thO the allowable timit, ae defined by the RPV cyclicload analysis, wiltbeenoewtre bdore the enod 0 the period of emterded operationse The paragraph further sta-es that "Adetailed analysis beyond tve scpoe o this report would be required to r..ne-euhed the CUFs if the trwsient linit are in tact -eede.,"

and tShai he

'Tisting cynIe mnetoring program wniltnmonitor the cycles ard reorpre corrective actio upon approaching alieit."

Please explain how the 40-year CUF conclusion will remain valid tor the EPO when PNPS Report No. LRPO-05 inplies the the CUFs ahould herea ouldated and projected oen OD years. Plense take inacounot the fact that Drat Co-nmitmn-t 31 requiree corrective action when the CUFs emooeed IA, and ret when the implenentation of AM B.I.t2 "Fatigue Mntoritedng Program-datermnen thea the actual transient cycles will approach the number 01 design transient cycle that we allowed in the design basis. It the CUF.

shoed have been prcoected and recalculated fot 60-years. as irdcated In LRPD-SM provide aconnmitnder when the 60-yea-CUFs vounn for the RCPBoeomponents will be provided to 0v NRC tor review ed approval unter either 10 CFR 54,21(c)(1)(ii) er (ii). The resporns tothle npqetion mey require amendment of Commitment 3t er.

UFSAR Supplement Summerny Description AS52.1, Cteasen I Ae Fatigu*e THe itemn goe withitem,4AI

Response

NRC LAPD-06 was rd intended to imply that the CUFs shonld beprojected Medoft, Jim ol 1oG yearsts incordarce with 10CFR 5421(c)(1)(ii). CUFs in Table 4,3-1 mebased en assuned nurim oern otransient cycles, not ona tember 01 yenrs. Thea CUFsare red necessarily dO-yent timting values. As long as the cycles are not eceeded, the CUFs donord need to be recalculated. While some of the nurhmers of yles projected tor 60years in Table 43-2 meooed the design basis assumpliots Inr numbers of cycles, the Fatigue Monitoring Prograsn assures the the aralyses will be renised to imrease the allowable nu erd cylen before e teeing the design basis assumptions.

VIle LRPD-06 projects number s that mcoed the denign bhesi eeasurrpions, the projections are corservative and the acnuoe tnrnerS of cycles moy not exceed the design bhsis assurrptions on the han=s of cycles. CUFswillrequire recalculation if the tumbers of actue tranients approach the design beess values.

Because the CUFeinTeble 4.3-1, withtexceptaon o 0he taedwater nozzle, awe well below 1, the allowable ranuters of cycles oen be increesed through renetsis assumring Nhghe rurnbers 01 cycles.

PNPS Lead Finnin, Ron 516 Open -

The TPO project documenoted the results 01 reactor vessel Plaet fatigue usage factors 01 limiting noenarnw Intable 3-2 in GE report GE-NE-0000-(00-. 1898-C0, RA.0 Math 2O In the summary Table, it staten that for CRD nonze -stub tube, the existing PNPS CUF value was 0.8, and is now changed to 0.870 for TPO. H-ower, the LRA Table 4.3.1, which Identifies clses I CUFvaluee, the CROnozle value o01.8 was tot identifed Please jusify why this value was nt included inthe iRA PatI, Erach Finnir% Ron PW 25d 77

James Davis - AMR -Report to the NRC.doc.pdf Page, 77 1 Number Status 517 Open -

Plant Request Ouetion 43-8 PNPS provided the project teas withthe stress1. elyses a cunulative uage lactor caculations for the PNPS recirorstiort tiaoeam piping systems ard sore shroud statilizers !nthE tlowing docosers:

• OC23A4O84 &23A4DB4, Re.l. PilgrimReciroruation Piping Repiaoeorut Jun 27, 1905

• GE Report 2SA568, Revision i. Stress Reqort - Shted Stajilizors Vessel, June 19, 1995

• GE Report GENE-771-79-t194, Revision 2, Strood Repair Hardware Stress Arnlysis, June 19, 1995.

LRATable 4.3-1 lists 9Wel the limiting 40-yest CUFfo the recircdatlon pipi*g is 0.110 and OWat the lieiting C0y" CUP for the sorestorsd stabilizos is 0330. The lirriting 43 yesr CUFP -ues provided in lihon reports for these cOonaroets.re 09 and 0e00t, respectively. These vates donr correlate tothe 40-yesr CUF values prosided In LRA Tate 43-1. Explsen wha the 43-year CUF values in these design bass docuenarts ciffer front Ie 40-ye ealues providie i.LRA Taite 43-1.

EIthes design heats docurnetr do rot constitute twnost cuorel design basis CUF bases fo the repsamerrt reciroolation piping systes, and oe shrToud stabilizers, clarity whochdocreals do c

tahe latest design basis CUF calcultlonsr for these cornponest conmodity grots, Shoud this bethe case this question will reasin open unil tGE stalf can review GtE approprieate design basis calsotiamns for thlesa corponert onernodity grous..

Response

NRC PNPS Lead Med", Jim Finin, Ron Pahae 77d 77