24
Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. James A. Fitzpatrick NPP RO. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan Site Vice President - JAF January 19, 2005 JAFP-05-0013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Subject: James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Inservice Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17) Reference: 1. Entergy letter to USNRC (JAFP-03-0 1I1), "Proposed Alternatives In Accordance With 10CFR50.55a(g)(6)(ii)(A)(5) and Relief From ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds Pursuant to I OCFR50.55a(g)(6)(i)," (Relief Request No. 30), dated August 4, 2003. 2. Letter, R. Laufer to M. Kansler, dated July 21, 2004, regarding "James A. FitzPatrick Nuclear Power Plant - Relief Request No. 30 for Third 10-Year Inservice Inspection (ISI) Program Interval" (TAC NO. MC0293) Dear Sir: This letter submits the James A. FitzPatrick (JAF) Owner's Activity Report, JAF-RPT- 05-00005, Rev. 0 (Enclosure 1) which contains a summary of the Inservice Inspection (ISI) examinations conducted during the plant's fall 2004 Refuel Outage (Reloadl6/Cycle 17). This Report is being submitted in accordance with JAF's approved Relief Request RR-6 (implementation of Code Case N-532) as modified by those requirements specified in Regulatory Guide 1.147, rev. 13, Section B, "Discussion", which approved the use of Code Case N-532-1. JAF was previously granted relief (Alternate to 10 CFR 50.55a(g)(6)(ii)(A)(2) Augmented RPV Examination) for the Third 10-Year ISI Interval (Reference 2). In its Request for Relief (Reference 1), Entergy stated that it planned to complete, to the AO

Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

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Page 1: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

EntergyEntergy Nuclear NortheastEntergy Nuclear Operations, Inc.James A. Fitzpatrick NPPRO. Box 110Lycoming, NY 13093Tel 315 349 6024 Fax 315 349 6480

T.A. SullivanSite Vice President - JAF

January 19, 2005JAFP-05-0013

U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555

Subject: James A. FitzPatrick Nuclear Power PlantDocket No. 50-333License No. DPR-59Inservice Inspection Summary Report2004 Refuel Outage (Reload 16/Cycle 17)

Reference: 1. Entergy letter to USNRC (JAFP-03-0 1I1), "ProposedAlternatives In Accordance With10CFR50.55a(g)(6)(ii)(A)(5) and Relief From ASMESection XI Code Regarding Inspection of RPV VerticalShell Welds Pursuant to I OCFR50.55a(g)(6)(i)," (ReliefRequest No. 30), dated August 4, 2003.

2. Letter, R. Laufer to M. Kansler, dated July 21, 2004,regarding "James A. FitzPatrick Nuclear Power Plant -Relief Request No. 30 for Third 10-Year InserviceInspection (ISI) Program Interval" (TAC NO. MC0293)

Dear Sir:

This letter submits the James A. FitzPatrick (JAF) Owner's Activity Report, JAF-RPT-05-00005, Rev. 0 (Enclosure 1) which contains a summary of the Inservice Inspection(ISI) examinations conducted during the plant's fall 2004 Refuel Outage(Reloadl6/Cycle 17). This Report is being submitted in accordance with JAF's approvedRelief Request RR-6 (implementation of Code Case N-532) as modified by thoserequirements specified in Regulatory Guide 1.147, rev. 13, Section B, "Discussion",which approved the use of Code Case N-532-1.

JAF was previously granted relief (Alternate to 10 CFR 50.55a(g)(6)(ii)(A)(2)Augmented RPV Examination) for the Third 10-Year ISI Interval (Reference 2). In itsRequest for Relief (Reference 1), Entergy stated that it planned to complete, to the

AO

Page 2: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

- |

maximum extent practical, the Phase II inspections (ID inspections) during the plant'sfall 2004 Refuel outage (RO16). Entergy also agreed to provide NRC notification aftercompletion of RO16 if any examination coverage was significantly different from thoseestimated.

Phase II inspections were not completed as anticipated due to unforeseen outagechallenges. However, all remaining examinations have been scheduled to be performedduring the plant's next Refuel Outage scheduled for Fall 2006. This will permit thecompletion of remaining Phase II examinations within the Third 10-Year ISI ProgramInterval which is scheduled to end December 31, 2006.

Enclosure II provides a summary of regulatory commitments made in this submittal.

Should you have any questions concerning this letter, please contact Mr. AndrewHalliday at (315) 349-6055.

This letter contains one new commitment.

Very truly yours,

TAS:GB

Enclosure I: JAF Owner's Activity Report (OAR), First Outage, Third Period, ThirdInterval (Report No. JAF-RPT-05-00005, rev.0)Attachment 1 - Abstract Of Examinations And Tests,Attachment 2 - Items With Flaws Or Relevant Conditions That

Required Evaluation For Continued Service,Attachment 3 - Abstract Of Repairs, Replacements Or Corrective

Measures Required For Continued Service.

Enclosure II: Summary of Regulatory Commitments

Page 3: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

cc: Regional Administrator, Region 1U.S. Nuclear Regulatory Commission475 Allendale RoadKing of Prussia, PA 19406-1415

Office of the Resident InspectorU.S. Nuclear Regulatory CommissionJames A. FitzPatrick Nuclear Power PlantP.O. Box 136Lycoming, NY 13093

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

Mr. Peter R. Smith, PresidentNYSERDA17 Columbia CircleAlbany, NY 12203-6399

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Enclosure I to JAFP-05-0013Entergy Nuclear Operations, Inc. - J. A. FitzPatrick

Docket No. 50-333

JAF Owner's Activity Report (OAR), First Outage, Third Period,Third Interval

(Report No. JAF-RPT-05-00005. Rev. 0)

Attachment 2 -Attachment 2 -

Attachment 3 -

Abstract of Examinations and Tests,Items with Flaws or RelevantConditions That Required Evaluationfor Continued Service,Abstract of Repairs, Replacements orCorrective Measures Required forContinued Service.

Page 5: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

ENN Q-UuWRQAilED ENH4C14? Revisin3-sbuou NUCLEAR ADn<u~PFK=

MLANAGEM#ENTNUA WORMATONALUE Pap u d S._ . lg .USVEA! .. .C.4 R

ATTACHMENT98.1 RN~d E PO R5OT COVER BMWT

Shoot I of I

Eng RepwtNo. JAF-1T5OO Rev.hp cI of

EnterTERGYgNUCLEAR Rr EAS

EnglSerlugg Repor9Tkle:

IAP Owner's Acty Report (OAR) Frt Outeg, Tird Period, Third IrVal

Engoneering Repoit Tvpe

New Reviion 10 Canelled 0 S;erceded 03Appiabe SlSW)

IP1 0 IP2 0 IP3 0 JAF 1 PNPS 3 vW D

Quav-tyEetd: BYesa Biq/

AD.SmiW Date: 1/WIISO,55', - Reposible Engineer Mint Nmae%')

R by.ewedb Date: ( i&

*Rvewd by.D: 1//DueNucer b m~erm

Approved bT. Date: I/j l

Multiple Site Rew(10)sule Desin Veriflernuviewer (PritNamSign) sTpervisor (prht Name/in) Dal

_ _ __' For ASME Secdion Xl Code Program plans per ENNDOO-120, I requW-d.

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FORM OAR-I /rOWNER'S ACTMTY REPORT z t1

#moWhbvtapOwfdwAMComM= N Pw I \41f_m mA u/mfr

Rep fr, rE ELATo Rev. 0

Omw ENFSRGY NUCLEFAR NO FHAST-440 Hatn Ave, .Whfb PA, NmewYwk 10601parmmddorOm)

flw Jmu A Flt&P&M nuRge rBMmrPlmrti 268 Lala Rd .L. Lomk NewYatk 13D03(N.m ard Addmaa of PWM

wn UIR &... Curawdal Servio Dab Trim Raksat Outage Nwrbs IL_

Cairant kiaedlon kftvsi lid(UL 2nd, .d MN Man

Curave kwpeaon Period ard(lat, 2nd.3e

Elon ad Pddnda of Sedon )a appicabW b to bfaden Rian iOg EdaIt, No Admnd

Dat and RAvm ofnd'sd Pc . SI Pm; mrn JAF-SI4f2 Rea, 3 IO**br 1 2001

Edlloi mid Adda odASME Sedon Xa appIIbie to Repirs aud I Cpllamnw.. I dlbwt Inkw h CID!on Plan

CERT1FICATE OF CONFOfURANCE

I m, ta goe adanb me hHs Owmra AdMNy Rpor ae wc and wAO 3we*al. tests, repairs.plcaments. vadnt id conecd mn v, repmrted bytl rpowmtxm lon fmpquiaf daSeca Xl.

Cerilkte orAuftd=o No. Epiao Dafte _ _ _

t;_ _ _ _ _ _ _ _ __C_ _e,X44ndrZ p9vT),jW-: a 100

CERTIFICATE OF IfSERVICE INSPECT1ON

,1 m d hon a sid cnluun Isd by oa Pressure Vessel kupedzr mid VWSlt e of________of______________________________ db.e" hiepedd go am

decIbed hI Oft 0wia Actft Repou1 urxv the period to lrJjL m6 and aftle hu to to bed my ludgo and bewf n te rmw hI= peraoed a aciea repbord y §s rpopa I acodnc vth Aie eqkmetofSecdon I.

By slhgig i ceica rWwrthe kopactor r tids eaplfe makes an wmty. 6qrmsasd orknpimed. wcemhV ftexammaliora, t. efpalrs _ucer . evehietions aNd corrmv measure ducrIbd hI Ib rport Fuwme .nuierrtinpeoWr nor his eMlyer shD be fA Iny mer for any persoal kWy or propety dwnw or a lou of w knd asnbom or _t fb

.SoftirI Naon Board. Stae. Prnce, an EndouAema-' ,7,focs lo O ,H.§z,/,

Fde: CCN532FORJLWPD-L0

Page 7: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

THIRD INTERVAL ATTACHMENT I First Refueling OutageThird Period

D.h-a1ln. 4*

." * L~ I..X»~.k>:X>.>~~<<>.>( ................~.. >. :.-::<;::4 . >.~*::*. :.:...:»x:~>x2::.xc..> ~ .>&..-: . . .. .U

ABSTRACT OF EXAMINATIONS AND TESTSTobl- Total

ExaminatIons Examinations Tota Examin Total ExaminationsExamination Required for The Credited for TM Credited (%) For Credited (%) To Date for R rk

Category Interval Period The Period The Interd

Approved Relief Req RR-17 deletes (4) RPV C icumferentlal Shell Weld Enlnatoa RR-I8 defersB-A 39 17 43% 53 theRPVVeticl SheWd examInatonst R016 (Ye 2004) and RR-30 alows partil exmhtoncovere fbr welds W3A & W3C fom the RPV ID.- Remainder o exams are defeabl to End d Interbal

(Table IWB-2S00-1)

B-D 54 0 0 59% Table M-20-1 Noe 2) eowa a maximum credit of 50% for the itt Period

Examinations for components within as Category are perform d every Refuel Outaga R013, 14, 15, 1 S.6-E 47 47 100% 100% and R017 In acoordance 1la Presure Tat Program I Requirement Once Per It dervl

B-F 0 0 0% 0% CMMponw n tis category wre part of the Augmented K38W Inspection Program and Rlsk4rnformedInepecton Prg Extent and Frequency are In asordance with the IGSOC Inspeton Program Cateri.

.. ,_ ._ .... , y RefWence Code Cateory R-A RIsk4nfomed Inapedn Pgram for examinationsn aid _pr .* . .. 4. .y44..4 . .... "' "

6-0-1 312 0 0% 27% ExamsforItems 58180,'190, and 2O re required when disesnmbled?..Ai :44: 9:y * ' - ;4::;.:::4.?.C. ~ .>.4. . S S....... :?f. ffSS .

(8) -Valves, /I(S) ) Valves, I (4) ... To~s In ExamInations Required column for bodling per Interval is that of Components ., bolts. This_ . . Valve 33%,RPVCH & Piping Inlu Flane, Vahes, RPV Closure Head & PipIno Flangs., Pumps, and CRD Flangs CRs examhB-G-2 RPV & P RPVCH & PN 0% I S 10 Flangs Pumps 100% I CRD(a) only when dbassembled. Bolting In Pressure Sedl Vlves are ecluded. One RPVCH Piping Flange & Flange

Pump 7/ CRD Flange, 1(1) Pump 14% S9% Bolting was deleted alter l t Period Inpedt n Deletion ocoured during 1 t Peiod Remaining RPVCH &s _ 17 2ping Flange Bofling 5

.:{:eAio~y6:f r r>: .,..>.. ~ ~...,.~ S~ r . 8g'.'. >' gl ? S.t:S. ...:?¾2X.:flŽ8?,, aY'S>.,:.:tB-K (BH) 5 1 20% 80%

.SSr r?~zg ' ^ S i ~i og.x y,' 8 8 'S f>,: >s -4,.: >:. ?S. ? ,s*:X.4..>.C .4.2...-. .4..................'4.:XC ':.C.:.4:-y 4C4>,> 4 ~ r .v. '.?? :

Components wIthIn thi Category are pdt of the RIk4nformed Inspection Program andtor the AugmentedIGSOC Inspection Program. Exent and Frequency requirements ae conducted In accordance with the

B-i 0 0 0% 0% apple program for tht component let Period (R013 & R014) aquaement blr Exent end Frequencyam required to meet Riak4nbfrmed Progmallstbc acrie and when required the iGSCC Programrequirements Reference Code Category R-A Rlskc-4noirmed Inspection Program for examinations and

_ _ _ _p a.

Page 1 of7

Page 8: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

THIRD INTERVAL ATTACHMENT 1 First Refueling OutageThird Period

D.a n.fl- 4*

CLASS I "continued'... . v u. :: . < u

ABSTRACT OF EXAMINATIONS AND TESTSr Total TotalExaminations Examinations Total Examination Total Examinations .

ExamInation Required for The Credited for Thi Credited (%) For Crdited (%) To Data kwr| Cetegoy Intl | | Period The Period | The Interval

B-K (S-K-I) 13 3 23*4 xmnbncnuldI sormsihCd aeN59 Alternate Rulintorthe Selection and

SK(O________ 0332%8N_ _ __ _I_ fn d:r a. ,ar I...sen .... on.B-L-1 O O O O N15 C to Amfd d

B-L-2 Once per Interval 0 0 0 Exam reud only when a pump Is disaesembled for matrisrm, wpair, or volumetricew. Exams are________ __u__ __ limited to at least one pump hI each group of pumps perfornk; Similar functions iths

5-EF14 0 0 0 0 aNot a oplio l tobJAF (VaS do not hav veo Weidsa)5fA><vv#. >N ';ft 2-:$<.>:Y:3344<3:

4.4 *. ,i :, S". ''"'' '

i412 Once per Interval 0 0% 33% Exam requid only when a vale is disassembled for maintenanoe repair, or volurinitc exaf Exams are(18) lemIted t one valve wlhin each groupof vate tha an of the same size, conscI deoignmanufac method and tht Peibr similar hfnons in the watem.

BM :y~~S: I8 "'IV :._ f Examinations and Tess Is eutitd under a separate Entery emitl lt, JAFP-04-01 90,

BN-N1 As Required As Required As Required As Required dated December 15. 2004. JAFNPP Dodet No. 50-333. In-Vernal Visual Inspection Summary Report 2004Rehei Outge (Reload I eb 17)..t. /~. -' g.. <.:yy.5<i c v4vjys s.z;<y.4Z S..,,.~i;ss''< ..,~y ~ .*iy :'4y . i{ty

A ct aminations and Tests Is submitted under a separate Entegy trsntti etter, JAFP-441 90,8-N-2 As Required As Required As Required As Required datd Decembr 15, 2004, JAFNPP Docet No. 50-333, In-Veasa Visual Inspecton Summary Report 2004

_ ReMel Outage (Reload I1Cyole 17)

8-0 1 (3) 4 1DO% 100% Peipheral CRD ibusing Q8% Tots! yfswral to the End of Intervalas perwmibe-

B-P 5 1 20% 80% Each Reuelir, Ou R013, 14,15, 18, and 17 (AWCode CsesN48-1s~- S i f S f a......- .:> i *.C ~ . 3' 44. 844 <4g f ±4433ffifyso>,

Page 2 of 7

Page 9: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

THIRD INTERVAL ATTACHMENT 1 First Refueling OutageThird Period

Da&.aU -l.. Or .*

m m m .... ..... 7-77,7.7 77,Ao uSI I I ur cXAMirtoA I InnAlU M ato1

I Examinatons Examinations Totl Examil Total ExaminationsExamination Required for The Credited for Ti Credited (%) For Credited (%) To Date for Remarks

Cateory | intrval Period The Period The lnteral

... ' ' 'ite LA S:x . . ... .. ... 44cx4. . .. .40.4>.00 ..C-A 5 1 20% 80%

CeB 4 2 50% 100°A~-,77.77m~

C-D O O O O% Not Applibie to AF

C-F-1 0 0 O O No Applib o JAF

The totals de d ih i ctegory represent Sactn Xi requrenlemets forthe lst Perlod Exnlna otncon d durkV R014 (2nd Refuel Outage) are required tI meet Secton Xl percentages and RWi-

C-F-2 0 0 0% 0% Innnd Prognmaticterha The Extent and Frequcy r f caegoy meet th t end Frequencycriteon st ed hi Seon Xl, and the Riek-lrtn Inspectin Progr. Reference Code Ctory RA Risk-nformed Inpeion Program for exnmnations and percenteget

C-G 0 0 0 0 Not Applielbe to JAF

Each Refueling Outage (lAW Code Cae N-49d-1) Percentages and Tod *mm performed arid creditedC-H 447 (5) 149 20% 80% rer t Period requeme only nd do nt indude me required App JAest

EXsZzsss- : : _ _:_ _ _ _ :'_'f _ _ _ _ _ _ _ _ '>' - t..t s " 0~i .i s, i , ss:.ss$Us;s$s s

Pag 3 of 7

Page 10: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

THIRD INTERVAL ATTACHMENT I First Refueling OutageThird Period

Refuel Outane 16. .,:_,:. _ _ t.. _ I

I1>o%:I01TDT iYMI--t i'ni~ I

At -I -;It1 A I AI U: N It§It

- rotal 1 otal -Iro alExacihations Examinations Examinations Total Examinations

Examination Required for Credited for Credited (%) For Credited (%) To Date ho RemarklsCategroy The nerval This Period The Period The Interval

CL,. . . ......i i - ', ,, ~~~~~. .. .-. . - o -R-Ef. -E.. X' .......... :.,

Tots and percenages are based on Code Case N-509, Code Category 0-A, RemNumbers D1.1 0, 01.20, D1.30 & D1.40 have hcorporated exams performed underASME 1989 Edition Code Category D-B, Items Numbers D2.20, D2.40, D2.50 & Code

D-A (CC N-509) 16 2 13% 81% Categoy D-C. ItemNmbers 03.2D3.40 & 0350.

D- 0 0 0% 0% Based on Coda Case N-509 this Code Cagory Is no longer applicable.

________ ________ S_ _ _ _ _ _ _ _ _ ;.':.:<..<i ' ' "Q ' , Y y S. ' SS. 2.@S, SSSS'S. yA Sa. ySS '44S0-C 0 0 0% 0% Based on Code Cam N-SOS thi Code Category Is no longs appl~cble.

Page 4 of 7

Page 11: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

THIRD INTERVAL ATTACHMENT I First Refueling OutageThird Period

.. ~ ~ Refel OutageP

__________ ~~ABSTRACT OF EXAMINATIONS AND TESTS . .A~$~_ T Io-al To'a'Examinations Exarninations Tot Examinaton Total Examinafions

Examination Required for The Credited for Thi Credited (%) For Credited (%) To Date for RemarksCategory Interval , Perod The Peiod The Interva l

F: .C^v~ +S .N: . . . .. . :; .S .. . .S ,S . . ..'S '' .: . ..\ .. . . . .... .. ........4 .: kor:t: x . .: ...

Class 1 23 3 13% 69% Exams pefomied In acrdarnce wt Code Come N491-1Chas 1 Snubber

Claws 5 0 0% 80%

Cl 2 48 9 19% 76% mformed n acrne WM Code Co N4mi-1Class 2 Snubber

Claws 9 0 0% 66%

Class 3 39 6 15% 87% Exas Peformd In ac rda cewith Ode Ce N491-1Class 3 Snubber

Clamps S 0 0% 100%

Suppoeta other

than PipingSuports 21 4 1S% 81% ExamN petftred In accordance wIth Cod Co" N-S1-1

Total Category F-

A 148 22 15% 81%

Page S of 7

Page 12: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

THIRD INTERVAL ATTACHMENT 1 First Refueling OutageThird Period

Refuel Outane IS S fSf S f >.s i n s.s; :i @.4 f f S4, 'B.'.. $. s..k ... c'

4 ............-.*......~. T > J~ . . : .:,i.........:

___ _ ABSTRACT OF EXAMINATIONS AND TESTSTotal Total

Exwmlne n Examinations Tohl Examinalon Total Examint ioneExamination Required for Credited for Thi Credited (%) For Credited (I) To Date r Remarkos

Category Interl Period Theisedod The Inted -_

E-A 100% Per Period 2 5% 100% The 2nd Period for WE Includes Refuel Ouages 15 &6. i m are performed In eccordanwith ASME Section Xl 1998 EdItion no Add Reief Rquest RR-27

. .11..,W , 4, " 'U'%:v.4 . s s , s

E * Based on ASME Section 1998 Edition this Cod Cgory is no nr applicable.

E-C N/A N/A NIA N/A

E-Dr-s rd on ASME Swctlon 1998 Edition this Code Category is no bngo ap ble.:KanS g 5E= - M

E-F * .* 4-:::s'n

E-P .* *

E-0 _____ :4 :s:.'r..' ,~,Based on ASME Section 1996 Edition tiCoeCaofIsno onger appliceble.

E-* Based on ASME Section 1996 Edition this Code C 0n I no longer Welcable.. .. .... .. ........ S:T: 44

'i . '':4

B

Pages of?

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- I

THIRD INTERVAL ATTACHMENT I First Refueling OutageThird Period

P&fIlml fOtne 1it

ABSTRACT OF EXAMINATIONS AND TESTSTotal TotalF

Emtninsdons Exmnination |eb Examinkons Total ExaminoatinsExamination Required for The Credited for Thl Credited (%) For Credited (%) To Date for Rwnarks

Ctego. Patedd -L. Poldod The IntAa j

Class i 33 T -I_1Cless 28 __ ___

Cim 3 1 4- Inspection Credited form Augmented Inwedtion Programs

RA 47 11 23% 76%

Page 7 of 7

Page 14: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

THIRD INTERVAL ATTACHMENT 2 First Refueling OutageThird Period

Refuel Outage 16

1_ I

Flaw Characterlzstlon (WA-3300)

Faw or RelevantCondition FoundDuring Scheduled

Section Xl Exaninationor Test (Yes I No)

Results

*1 r

Integrally Welded

The pressure boundry weld which joins RHR line Acceptable for Continued Service - Per CR-JAF-2004-03826 / CA-10-20.-VW20-302-SA to the pipe support is only 00001 evaluation -The 'as-builr weld configuration has been

welded in two places rather than four as required evaluated in MCC# DRN-04-06127 for calculation no. PFSK-1991,by the controlled drawing. This results in a Rev. 0, which determined the weld to be acceptable. Additionally,reduction of weld length from the drawing ORN-04-06204 has been generated against pipe support drawing #

requirement of 48 inches to the field condition of 24 PFSK-1991 sht 2 of 3, Rev.1, to document the 'as-buitr integralinches. Yes attachment weld.

Acceptable for Continued Sefivce - Per CR-JAF-2004-04094 / CA-00001 evaluation - Support calculation indicates that the latest designload in the vertical direction is seismic and the balance Is a thermal

ISI VT-3 examination of pipe support 13-4A-NS-9 load. This loading breakdown indicates that there will be no netidentified clearances exceeding the drawing positive force in the positive vertical direction and therefore, no

specifications Drawing H13-10 specifies 108" upward movement of the pipe, Since the pipe will not move upwardclearances where a 5/16" clearance was identified under any loading condition the restraint gap above is irrelevant and i

at the top of the seismic constraint. Yes not required to restrain the pipe in that direction.Constraint Type

L .1.

Page 1 of 5

Page 15: Entergy Nuclear Northeast Entergy James A. Fitzpatrick NPP · Should you have any questions concerning this letter, please contact Mr. Andrew Halliday at (315) 349-6055. This letter

THIRD INTERVAL ATTACHMENT 2 First Refueling OutageThird Period

Refuel Outage 16

ExamninatonCategory

Item Number Itm Descriptpon Ftaw Charactertzatron (IWA-3300)

Flaw or RelevaintCondition FoundDuring Scheduled

Section Xl Examinationor Test (Yes I No)

Results

R-A (B-J) 99.11 Acceptable for Continued Senvce - Per CR-JAF-2004-04472 - TheUltrasonic examination of weld 18-34-389 per the examination results were correlated to conditions accepted by theClass 1 -Circumferential ISI program identified a subsurface planer construction radiographs and is acceptable per ASME Section Xl IWB

Weld indication for evaluation Yes 3112 (b). CR generated for documentation and trending.

Acceptable for Continued Serivce - Per CR-JAF-2004-035961 CA-00001- Snubber 10-32B-HS-278 was changed out with a rebuilt unit

O&M Standard N/A Hydraulic / Snubber as stated in the Condition Description of this CR. A engineeringOne of the two existing extension piece jam nuts evaluation concluded that the loose jam nut did not Impact the

on pipe support PFSK-2366 1I0-32B-HS-278 structural integrity of the snubber/extension assembly. Therefore,(snubber) were found loose during a VT-3 In- snubber 10-321-HS-278 would have been capable of performing its

service Inspection. Yes safety-related function for all design conditions.

Acceptable for Continued Servce - Per CR-JAF-2004-647 -Engineering examined the condition of the rigid strut in contact with arexisting tube tray. The sway strut is in touching the top edges of thetube tray and is in contact with the top face of the two (2) cablesinside the tray. There were no signs of damage or degradation to the

F-A F1.20e Rigid Sw Strut Cable tray with two armored cables was found cables, the tube tray, or the sway strut The centerine of the piperesting on the horizontal member. clamp was found to be approximately 3" lower in elevation than the

centerline elevation of the support base plate and beam attachment.Engineering recommend raising the centerline of the pipe clamp to thfsame centerline elevation of the base plate and beam attachment.Raising the clamp upward a minimum of 3" would allow sufficientclearance between the bottom of the sway strut and the top of the

Yes tube tray and the cables.

Page 2 of 5

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THIRD INTERVAL ATTACHMENT 2 First Refueling OutageThird Period

Refuel Outage 16

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ ~~ ~~~~Table 2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

----- ---------------------------------- - - - --------- ---- . . ... . ..... ...... ...... ..... ............... .... .. . . . . . . ........

[ Flaw or RelevantExamnaton II I Cond Wion Found

Exatnation Rom Nunber Item Description Flaw Characterization (IWA-3300) Duing Schedu led Results

or Test (Yes No)

Vr-3 examination of pipe support 10-1 1A-NS-83PFSK-64 found the following rejectable Acceptable for Continued Serivce - Per CR-JAF-2004-03717 - The 'as

conditions: 1) Pipe Line 10-24"-W20-302-1 1A builr configuration discrepancies have been evaluated In calculationtouches the house steel at the top of the support. #JAF-CALC;4400503 Rev. 0 and were determined to be acceptable.

F-A F1 .20b Vertical Constraint 2) Plate to trunion weld has slag inclusion. 3) Yes Additionally, DRN-04405872 has been generated against pipe supportVertical support member at the top of the support drawing # PFSK-864, Rev.2. to document the 'as-built discrepancieshas weld rod imbedded in the weld area. 4) The These actions complete the requirements of CA-00001 and the

trunion support plate is half off of the support beam corrective action is ready for closure.and not fully resting on the support

ISI VT-3 examination identified missing or Acceptable for Continued Serivce - Per CR-JAF-2004-03755 - Theseincomplete welds on the pipe support structure. 1) deficiencies were previously identified when the support was

No weld exists at the top east end of lower TS inspected under the pipe support program (F1-84-091) (11/1989). TheF-A F1.20b Constraint Type 6x6x1iT x1-1-3/4" lg. 2) The ? fillet weld between Yes as-built configuration has not been reconciled through the pipe

. Support the top TS 6x6x1/x2W-4-1/2" and the 1" base plate support program. Two calculations have been performed (Cakc. 0226Eis incomplete at west side. 3) The 1/4k fillet EM-38-815, Rev. 0 & Calc. JAF-CALC-MULTI-04056 Rev. 0) and an

between top TS 6x6x1/2"x3'- and plate 1x23x2- ECN (F1-84-091-2562) has been drafted to document the deficiencies1/2' is omitted for 1" at the hilti bol but has not been approved or issued.

Llsega snubber from location 02-2-2B-HS-4functionally tested by VO JF-030388701 achieved Acceptable for Continued Serivce - Per CR-JAF-2004-04226 - Afterlockup rate of 1 .03ipm in the tension direction. The review of the snubber test data results show that the snubber is SAT.

O&M Standard N/A Hydraulic Snubber temperature compensated operability acceptance Yes Problem is difference between Interpretation of Bergen Patterson testrange contained in MST-100.01 Is 1.80 to 19.30 Ysdata and This snubber manufactured by Lisega. See attached writeipm; the performance acceptance range is 6.30 to up from Maintenance Supervisor which was reviewed and concurred13.30 ipm. As found is below both acceptance to by Snubber Engineer. jpccriteria.

Page 3 of 5

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THIRD INTERVAL ATTACHMENT 2 First Refueling OutageThird Period

Refuel Outage 16____________ ~~~~~Table 2 __________________

S w a -S in -

Flew or Relevant

Exarnnatlon FlewCondItion FoundRItom Nurmber Rom DescriptonFlw Charctertratlon (IA-33) During Scheduled Resultscaeoy Seton Xi Exarninstlon

or Test (Yes / No)

Acceptable for Continued Serivce - Per CR-JAF-2004-04191 - Thespherical bearing was freed up once the performance test load was

During the ISI VT-3 inspection of snubber #23-19A- placed on the snubber body. The performance load was higher thanO&M Standard N/A Hydraulic / Snubber H the pipe damp spherical bearing was bound Yes the initial load applied by the mechanic (in the field) where the bound

up condition was identified. The performance test demonstrated thatup. the stainless steel spherical bearing allowed the snubber paddle to

move freely about the bearing. The snubber remained to be operableand functional as intended

The as found piston rod length of snubber JAF-306at location 10-1-HS-207 inspected under WOJF-030391900 was 2". The replacement snubber

as Installed has a piston rod length of 2". This does Acceptable for Continued Servce - Per CR-JAF-2004-04269 - Basednot meet the snubber preset piston rod length as on review of pipe stress calculation C/S:JAF-C.5 Rev 0, the thermal

O&M Standard N/A Hydraulic / Snubber called out In PFSK-4647(DCR 98-338) Yes movements of the piping for all plant design conditions will result inwhich is 3-3/4" to 4-1/2" +1- 1/4" negligible movement of the snubber as it moves from its cold to hot

position. Therefore the piston rod length os 2" is acceptable.

The existing piston rod length of snubber JAF-347at location 10-1-HS 209 was 5-3/8" wheninspected underW -F030392100. The

acceptable snubber setting per PFSK- Acceptable for Continued Serivce - Per CR-JAF-2004-04268 -Based4647(DCR_98338) is 1-7/8" to 3" +/- 114". The on review of pipe stress calculation CJS:JAF-C5 Rev. 0, the thermal

O&M Standard N/A Hydraulic / Snubber replacement snubber JAF-345 has an Installed Yes movements of the piping for all plant design conditions will result inpiston rod length of negligible movement of the snubber as it moves from its cold to hot

5-1/4". this is not within the limits of PFSK4647. position. Therefore, the piston rod length of 2" is acceptable.

Page 4 of 5

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THIRD INTERVAL ATTACHMENT 2 First Refueling OutageThird Period

Refuel Outage 16

I I

Flaw Characterization (IWA4300)

Flaw or RelevantCondition Found

During ScheduledSection Xl ExamInatIon

or Test (Yes I No)

Results

I C

Hydraulic / SnubberDuring the performance of replacing snubber 10-2C-HS-187 under WO JF-030401200 the piston

setting were found out of tolerance.Yes

Acceptable for Continued Sertvce - Per CR-JAF-2004-3810 - Thesnubber was not Inoperable. The piston setting of 3-3/8" Isacceptable. CR-JAF-2002-03065 addressed this same issue exceptthe piston setting was 3-1/2". The Engineering Evaluation to supportDperability (attached to CR-JAF-2002-03065) provides justification forthe 'as-found" piston setting. Since the current piston setting Is 3-3/8", the snubber will extend 2-1/14 to 5-5/8" as it moves from its.cold' to "hot" position. Therefore, the snubber will continue toperform its design function with no limitation since its range of travelfor all plant conditions is within the acceptable stroke (i.e. 0" to 6") ofthe snubber.

An engineering walkdown identified two conduits inthe vicinity of the snubber extension piece. Oneconduit having a clearance of 1/8" as Identified in

this Condition Report and the other conduit havinga clearance of 1". The configuration was

determined to be acceptable since the 1/8" gap willincrease as the pipe moves approximately 1 W

thermally (i.e., delta X = -0.434" and delta Z = -0. 195") from its cold to hot position during plantoperation. The 1" gap between the extension

piece and the second conduit will decreaseapproximately 12" from its cold to hot position

during plant operation. Seismic displacement ofthe pipe at the snubber location is negligible since

the pipe is located below grade in the ReactorBuilding V"st Crescent (minimal seismic

response) and the pipe is anchored approximately30 It. from the snubber.

Acceptable for Continued Serivce - Per CR-JAF-2004.03839 -Drawing No. PFSK-2243, Rev. 1, will be revised per DRN #04-06285to show the clearance between the two (2) existing conduits and thesnubber extension piece.

Hydraulic / Snubber No

Reference: ER #JAF-04-34781, Rev. 0

Page 5 of 5

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ATTACHMENT 3Third Intervd FlftIst Refueling Outage

Third PeriodR18

TABLE 3

&T .~ £I _A FPltrrt P1W i _tS PfdfWf S ff# II lWI I-- -,,::M:..-..._::::::......,s:::s.:s, ~~.:W. '.:.Sc.:: s:s.:: Blt9 .1:::..::; ,S c ... . .......... - B .:: .... .. ......... s " mI S ;Ss" S'

CODE Recur t . Item Description and Description of Work Flaw or Relevant Close Date Repar I Work OrderCLASS Repbetment or Condition Found During Repabement Number

Corrective Scheduled Examination Plan NumberMeaur, or Test (YeoNo)

3 Replr Saher Wan ThIcess Weld Patch Yes 3/23204 04-001 JF-030618500

3 R ir Strainer Wall Thickless Weld Patch Yes 9/2/2004 04-002 JF-030618600HEMUVE SNUBBER JAF-L-504 FROM LICATION 02-2-Za-

1 Repce HS-4 AND INSTALL JAF-L-W01 PER MP-100.03. No 10/712004 04-003 JF-030388700

Replcm CRDU Bot plcement due to missing washers Yes 10114/20M 0 044004 JF-020806300

3 Repsir BFSK-1 084 Yes 5/4/2004 04-005 JF-020228000

1 Repcerent: CRDU Bolt Yes 10/14/2000 04-007 JF-030419300

1 Repacemn Srnbber Replacement (02-2-2B-HS4) No 10/15/2004 04.008 JF-030388700

2 Repceent Snubber Replacement (1 0-1-8-8) No 8/1O2004 04-009 JF-030395000

Replacement Snubber R acement a 14-9A-HS-14) No 9/2/2004 04-011 JF-030400900KlMOV2: SUbrK JAj-130 FKUOM LOA I ION 10-1 -is-

2 Replacement 20 AND INSTALL JAF-127 No 8/17/2004 04-013 JF-030395200.KMOVtZ SNUBBEtKRJAF-15Z FRUM LOQUIAWN 1Q-18i-HS-

2 Replacement 17 AND INSTALL JAF-810 No 8117/2004 04-014 JF.030400700

2 Replacement 3 AND INSTALL JAF-8423 No 8Q2/2004 04-015 JF-030401800U1)IkA55h~ibI±JUIlQ" AND KtFAIR UNIT UWOI±R ANUD

3Sp ASSOCIATED PIPING AND VALVES PER MAINTENANCE No 822004 04-017 JF-031007300

3 Rephema 67ICu1; hms a btbe Wk.I Yes 10/25/2004 04-018 JAF-04-18338

3 Repceent Snubber Repament (10-30BHs-102) No 1014/2004 04-020 .JF-030395800

Page 1 of 5

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ATTACHMENT 3Third Interal FFrst Refueling Outage

Third PeriodRiB

TABLE 3

m ~

CODE RepadrI itm Description and Description of Work Flaw or Relevent Close Date Repair I Work OrderCLASS Repluomentor Condition Found During Rep mcnent Number

Correctie Scheduled Examination Plan NumberMeasure or Test (YesiNo)

Snubber Replacementl (emove snubber JAF-J7b trom2 Replnent location 10-17-56 ) No a111W004 04021 JAF-03-27015

3 Replacement REPLACE 46SWS-127 RETURN VALVE No 10/15/2004 04-022 JAF-04-10058

2 Replacement Replace snubber JAF-125 with snubber JAF-1i4. No 10/13/2004 04-023 JF-0303966REMOVE SNUBBER JAF-286 PERFORM FUNCTIONAL TEST

2 Relcmn & rebuild, wan reinstall. NO 91280004 04-025 JF.030401 300REMOVE SNUBBER JAF-408/PERFORM FUNCTIONAL

2 Replacement TEST/buld, ad reinsl No 10/1212004 04-028 JF-030401700

2 Replacement & rebuld, and reinstll. No 91/e004 04-033 JF-030401800AEM V SNBE A-209 FROM LOCATION 11-8-H= 3

2 Replacement FUNCTIONAL TEST & INSTALL JAF-229 PER MP-100.03. No 10/19/2004 04-034 JF-030401400REMOVES5NUBBER JAF-23 PERFORM FUNCTIONAL TEST

2 Replacement & rebuild, and reinstall. No 10121/2004 04-035 JF-030401200Repair Areas ot Localized Wan Thinning on 10501 utreiner

3 Repair Basket Houshg Yes 12/1/2004 04-037 JAF-04-21896

3 Replacement Replace quantity one nut on 16 AOV-132A Bonnet of valve Yes 11/9P2004 04-039 JAF-03-27262

Page 2 of 5

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ATTACHMENT 3Third Interval PlIt Refueling Outage

Third PeriodRIB

TABLE 3

CODE Repd/ Item Description and Description of Work Flaw or Relevant Close Date Repair I Work OrderCLASS Repleamentor Condition Found During Replacment Number

Con ntlve Scheduled Examination Plan NumberMeasure or Test (YoeNo)

Reeplace uownstream Seat nng Intemal seal wela on pressure2 Reps boudary yes 12/22004 04-040 JAF-04-3959

REMOVE SNUBBER JAF.144 FROM LOCATION 23-19A-HS-4 101r004 03-00002-34I Replacement AND INSTALL JAF-145 PER MP-100.03. No 03-03898-00

REMOVE SNUBBER JAF-532 FROM LOCATION 29-TBHS-16 No 107/20 03-002-38 0I Replacement AND INSTALL JAF-53 PER MP-100.03. No 101712004 03-00002-21 03-03883-00

REMOVE SNUBBER JAF-508 FROM LOCATION 02-2-1 B-HN0S-I Redscement 17 AND INSTALL JAF-S08 PER MP-100.03. No 10/7/2004 03-00002-1 03-03927-00

REMOVE SNUBBER JAF-313 FROM LOCATION 02.2-1A-HS- No 1012004 03-00002-11 Replacement 12 AND INSTALL JAF-309 PER MP-100.03. No11/040 00-7 03-03900-00

1 REMOVE SNUBBER JAF-412 FROM LOCATION 02-2-1B-HS- No 10/102004 03-0002-23I Replacement 12 AND INSTALL JAF-417 PER MP-100.03. No10/7/2004030 9 03-0392300

REMOVE SNUBBER JAF-413 FROM LOCATION 02-2-1B-HS-3 JF-030392500I Replacement 19 AND INSTALL JAF-419 PER MP-100.03. No 10h 0 0 03-03925-00

REMOVE SNUBBER JAF-515 FROM LOCATION 29-IB-HS39N JF-030392900 03-Replacement AND INSTALL JAF-515 PER MP-1 00.03. No 10/10Q0U 03-00002-0 03739-00

REMOVE SNUBBER JAF-315 FROM LOCATION 02-2-IB-HS- No 10/2004 0340002 20 JF-030387500 03-1 Replacement 13 AND INSTALL JAF-304 PER MP-100.03. 0103875-00

REMOVE SNUBBER JAF-315 FROM LOCATION OZ 2-1B-HS- JF-030387500 03-I Repleement 13 AND INSTALL JAF-304 PER MP-100.03. No 10110R004 03-00002-21 03875-01

No IO1=00 03- 2-53 JF-020209700 02.2 Repair REPAIR H10-42A PER F1-84-091 No 10/102004 03-0002-53 02097-00

REMOVE SNUBBER JAF-421 FROM LOCATION 34-4A-HS-17 JF-030392600 03-t Repacmr* AND INSTALL JAF-420 PER MP-1 00.03. No 10/10/2004 03-00002-41 03928-00

REMOVE SNUBBER JAF-323 FROM LOCATION 02-2-1A-HS- No 10112004 030002-18 JF-03039 03-1 Repleoment IS AND INSTALL JAF-327 PER MP-100.03. No1/1R08 0390200

REMOVE SNUBBER JAF-526 FROM LOCATION 29-IA-HS-8A No 101112004 -00002-35 JF-030388100 03I Replnent AND INSTALL JAF-541 PER MP-1 00.03. 01/1045 3881-0

REMOVE SNUBBER JAF-521 FROM LOCATION 29-1D--HS-35 1011/004 0- 39 JF-030388500 031 Replapment AND INSTALL JAF-518 PER MP-100.03. N__ o _0/___ _ _ 03_00002_39 03885-00

REMOVE SNUBBER JAF-529 FROM LOCATION 02-2-2A-HS- JF-030387900 03-I Repe t 8 AND INSTALL JAF-536 PER MP-100.03. No 10/11/24 03-00002-24 03879-00

REMOVE SNUBBER JAF-306 FROM LOCATION 10-1-HS-207 JF-030391 900 03-2 Repacemenl AND INSTALL JAF-310 PER MP-100.03. No 10/12/2004 03-00002-2 39100

RIEMOVE SNUBB1ER JAF-W4 FROM LOCATION 1O-1..S-21 Repbcement AND INSTALL JAF-345 PER MP-100.03. No 10/1212004 03002-32 03921-00

Page 3 of 5

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ATTACHMENT 3Third Interval First Refueling Outage

Third Period- RIB

TABLE 3

CODE Repair / Item.Description and Description of Work Flaw ot Relevant Close Daft Repair Work OrderCLASS Replacnmnt or Condition Found During Replucment Number

Correctinv Scheduled Examination Plan NumberMesure or Test (Y/sINo)

No 10112004 03-00002-28 JF-2013590 02-3 Replacement 4EXJ-1D _ _ __ _ _ _ __ _ _ _ _ 01359-00

3 Replcement 46EW-10D No 10112t2004 03-00002-30 JF-02013610002-Replace snubber SIN JAF-135 with SIN JAF-126.10-30B-HS- JF-030396000 03-

3 Replacement 1003 No 10122004 030002-72 0390-00REMOVE SNUBBER JAF-298 FROM LOCATION 10-15A-HS- JF-030401100 03-

2 Replacement 103 AND INSTALL JAF-278 PER MP- 100.03. No 10/12t2004 03-00002-78 04011-00REMOVE SNUBBER JAF-298 FROM LOCATION 10-15A-HS- No 1 JF-030401100 03-

2 Replacement 103 AND INSTALL JAF-278 PER MP-100.03. No_10/12t2004_03-00W2-79_040114"1

No 10/13t2004 03 00002-29 JF-020136000 02-3 Replacement 46EXJ-IOC _ _______ ____01380-00

No 1113rM 03)000-27 JF-020135800 02-3 Replacement 48EXJ-1OA No 1 U0000227 01358-00

REMOVE SNUBBER JAF-298 FROM LOCATION 10-15A-HS- No 10/13/2004 03-00002-78 JF-030401100 03-2 Replacement 103 AND INSTALL JAF-278 PER MP-100.03. No____________03-00002-78 04011-00

REMOVE SNUBBER JAF-161 FROM LOCATION 12-1-HS-20A JF-030387300 03-1 Replcement AND INSTALL JAF-120 PER MP-100.03. No 10/14/2004 03-00002-33 03873-00

new body (JAF 110) on 0ZRV-71G See Rome WR 02-08203-I Replacement 00 No 12122004 03-00002-e0 JAF0437003

Page 4 of 5

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ATTACHMENT 3Third Interval Firet Reftielcng Outage

Third Period-. R16

TABLE 3

CODE Repair I Item Decription and Description of Work Flaw or Relevant Close Date Repair I Work OrderCLASS Repfacment or Condition Found During Replacment Number

Corrective Scheduled Examination Plan NumberMeasure or Test (YOsINo)

No 1/gAM 3-000256 JF2-027-71=0 2-1 Replacement 02RV-71C Relbf Valve Replacement of Min Body Boltng No 11/9/2004 03-00002-58 07712-01

No 119r2 000000-12 JF-030527100 03-1 Replacement 02V-1 ADS Reactor Vessel Replacment of Bolting No 11/912004 00 412 O271-00

No IIMM 0-0002-61 JF-020820201 02-_ Replacement 02RV-71H Relief Valve Replacement of Main Body Boling No 11/92004 0000021 08202-013 Replacement 46-SWS-127J Replacement ofVale V No 1211/2004 03-00002-91 JF-030908700I Replacement I1SV-74A/ RHR Heat ExchngerW Steam Inlet Safety Yes 10.14.04 0402 JAF-0010933003 Replacement 46-SvvS-127KReaVeameM tOf Valv No 121112004 03-00002-52 UF795700

Page 5 of 5

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Enclosure II to JAFP-05-0013Entergy Nuclear Operations, Inc. - J. A. FitzPatrick

Docket No. 50-333

REGULATORY TYPE SCHEDULEDCOMMITMENT One Time Continuing COMPLETION DATE

Action Compliance

This letter contains JAFNPP Fall 2006 RefuelOne (1) new commitment. Outage

XEntergy Nuclear

Operations (ENO) willcomplete all remainingrequired Third 10-Year

Inservice Inspection (ISI)Program Interval reactor

pressure vessel (RPV)weld examinations at the

James A. FitzPatrickNuclear Power Plant(JAFNPP) during the

plant's Fall 2006 RefuelOutage