ML080450391

Two Ltrs from Sutton to LB 1) Informing That Entergy Is Available for Oral Argument 3/10-3/14/08 and 2) Transmitting Letter That Pertains to Riverkeeper Proposed Contention TC-1 and New York State Proposed Contention 26

ML080450391
Person / Time
Site:	Indian Point
Issue date:	02/04/2008
From:	Bessette P Entergy Nuclear Operations, Morgan, Morgan, Lewis & Bockius, LLP
To:	Lathrop K, Lawrence Mcdade, Richard Wardwell Atomic Safety and Licensing Board Panel
SECY/RAS
References
07-858-03-LR-BD01, 50-247-LR, 50-286-LR, RAS 15064
Download: ML080450391 (33)

Text

-I5OA Morgan, Lewis & Bbckius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004 Tel: 202.739.3000 Fax: 202.739.3001 www.morganlewis.com Kathryn M. Sutton Partner 202.739.5738 ksuiton@rnorganlewis.com Paul M. Bessette Partner 202.739.5796 pbessette@morganlewis.com Morgan Lewis COUNSELORS AT LAW DOCKETED USNRC February 12, 2008 (8:47am)

OFFICF OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF February 4, 2008 Lawrence G. McDade, Chair Atomic Safety and Licensing Board Panel Mail Stop - T-3 F23 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Dr. Kaye D. Lathrop Administrative Judge Atomic Safety and Licensing Board Panel 190 Cedar Lane E.

Ridgway, CO 81432 Dr. Richard E. Wardwell Administrative Judge Atomic Safety and Licensing Board Panel Mail Stop - T-3 F23 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 In the Matter of Entergy Nuclear Operations, Inc.

(Indian Point Nuclear Generating Units 2 and 3)

Docket Nos.. 50-247-LR/50-286-LR

Dear Administrative Judges:

In response to the Licensing Board's Order dated January 24, 2008 concerning Preliminary Notification Regarding the Scheduling of Oral Arguments, Entergy Nuclear Operations, Inc. wishes to confirm in writing that it is available for oral argument, without restriction, during the week of March 10-14, 2008.

Sin Kathryn M. Sutton Paul M. Bessette Martin J. O'Neill Counsel for Entergy Nuclear Operations, Inc.

cc:

Service List William Dennis, Assistant General Counsel Entergy Nuclear Operations, Inc.

I-WA/2920749.1 P /a V/-t?/

'-3

Morgan, Lewis & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004 Tel: 202.739.3000 Fax: 202.739.3001 www.morganlewis.com Kathryn M. Sutton Partner 202.739.5738 ksutton@morganilewis.com Paul M. Bessette Partner 202:739.5796 pbessette@morganlewis.com MorgAn Lew CO.0U N S E.L ORS A T LA W February 4, 2008 Lawrence G. McDade, Chair Atomic Safety and Licensing Board Panel Mail Stop - T-3 F23 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Dr. Kaye D. Lathrop Administrative Judge Atomic Safety and Licensing Board Panel 190 Cedar Lane E.

Ridgway, CO 81432 Dr. Richard E. Wardwell Administrative Judge Atomic Safety and Licensing Board Panel Mail Stop - T-3 F23 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 In the Matter of Entergy Nuclear Operations, Inc.

(Indian Point Nuclear Generating Units 2 and 3)

Docket Nos. 50-247-LR/50-286-LR

Dear Administrative Judges:

Enclosed for your information is a copy of a January 22, 2008, letter from Fred R.

Dacimo, Vice President, License Renewal, Entergy Nuclear Operations, Inc., to the U.S. Nuclear Regulatory Commission (Entergy Letter NL-08-021, "Subjec't.:.License Application Amendment 2"). Entergy referenced the letter in its January 22, 2008, answers to the Riverkeeper and New York State petitions to intervene. See "Answer of Entergy Nuclear Operations, Inc. Opposing Riverkeeper, Inc.'s Request for Hearing and Petition to Intervene" (Jan. 22, 2008), at 35-36; "Answer of Entergy Nuclear Operations, Inc. Opposing New York State. Notice of Intention to Participate and Petition to Intervene" (Jan. 22, 2008), at 147-48.

The letter pertains to Riverkeeper Proposed Contention TC-1 and New York State Proposed Contention 26.

As Entergy explained in its January 22, 2008, answers, the referenced letter clarifies the relationship between Entergy License Renewal Commitment 33 regarding environmentally I-WA/2920295.1

Atomic Safety and Licensing Board Panel February 4, 2008 Page 2 Morgan Lewis COUNSELORS AT LAW assisted fatigue ("EAF") and the Fatigue Monitoring Program described in Section B.1.12 of Appendix B to the Indian Point license renewal application ("LRIA"). The attachments to the letter contain certain revisions to portions of the LRA germane to EAF and the Fatigue Monitoring Program, including Commitment 33 of the List of Regulatory Commitments. In its January 22, 2008, answers, Entergy included, verbatim, the text of revised Commitment 33.

Because it appears that the letter has yet to be-made publicly available through ADAMS. (at least as of this morning), Entergy is providing a courtesy copy of the letter to the Licensing Board, NRC Staff, Riverkeeper, New York State, as well as the other petitioners in this proceeding.

Sin Kathryn M. Sutton Paul M. Bessette Martin J. O'Neill Counsel for Entergy Nuclear Operations, Inc.

Enclosure:

cc w/ encl.:

As stated Service List William Dennis, Assistant General Counsel Entergy Nuclear Operations; Inc.

ntýr Entarov'Nudlaar Nort:6eas

Indlian Point Enejrgy Cnt r 450 Broadwaýy. GS9 S.

.:P.O: Box 249"'

-Bchanain. NY 10511-0249 Tl(14) 7825 ried Prscdniot January 22, 2008 Re:

Indian Point Units 2& 3 Docket"Nos. 50247&, 50A286 NL-08-02128 U.S. Nuclear Regulatory Commission ATTN: Document Controi Desk".-

Washington, DC 20555-0001

SUBJECT:

Entergy Nuclear Operations Inc.

Indian Point Nuclear Generating Unit Nos. 2 & 3 Docket Nos. 50-247 and 50-286 License Renewa" Applicatbon Amendment 2 REFEI*ENCES:

1. -Entergy Letter dated.April 23, 2007, F. R. Dacimo to Document Contro Desk, "LicenseRenewal Application" (NL-07-039)

2. EntIergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Bouindary Drawings",(NL-07-040)

3..Entergy' Letter dated April 23, 200.7, F. R. Dacimo to Document Control Desk, License Renewal Application Environmental Report References" (NL-07-041)

Dear Sir or Madam:

1n the referenced letters, Entergy Nuclear Operations, Inc. (Entergy) applied. for renewal of the Indian Point Energy Center operating licenses for Unit 2 and 3.

Based on discussions during license renewal audits, clarification to the LRA is provided in. This information clarifies the relationship between Commitment 33 regarding environmentally assisted fatigue and the Fatigue Monitoring Program described in LRA Section B.1.12. The Fatigue Monitoring Program includes the actions identified in Commitment 33 to address the evaluation of the effects of environmentally assisted fatigue in accordance with 10 CFR 54.21(c)(1)(iii).

The revised Regulatory Commitment List is provided in Attachment 2.

If you have any questions, or require additional information, please contact Mr. Robert Walpole at 914-734-6710.

NL-08-021 Docket Nos. 50-247 & 50-286 Page 2 of 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on

{--L2-(;8 Sincerely, fJ~1v~tr.

Fred R. D~i~~ -d4 i¥ ft/ean Vice President

/

License Renewal

I NSL-08-021:

D.cket Nos. 50-247 5286

.Pag*3 of 3 Attachments:

I.Fatigue Monitqrin*g* Prgrami Cldrification0 2.Regulato ryConmitrnint List, Revision3 cc:

Mr. S:amnuel JCollins, Regional Ad'inistrator,- NRC R I

C

.-h i

.ý t

j Mr.-Kenneth Chang, NRC Branch Chief, Engineering. Review Banch I Mr. Ba M. Pham NRC E~nvironmnrieta :Proje6t Man'ager'.

Mr. John Boskak NRR RSenior Project M. na er Mr. Paul Eddy, New Y-ork State.Departhiehtof Public Sevice NRC Resident Inspectors "ffie- '

Mr. Paul D."Tonko. Ptesident; New York.State Eher'gy, Research, & Development Authority

ATTACHMENT" 1TO NIL'08021 Fatigue Monitoring.Pro 'ram 'Clarification ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286

"ý-08-021 Atchmeint I Docket Nosi 50-247 & 5646286 P

-of q

License Ren'ewazl-Applica~tio Amendment 2-:

Fatigue Monitoring Program Clarificatin LRA and'commitment list revisions are provided below. (u6nderline.- added, striketihrough.-

deleted)

LRA Table 4.1-1, List of IP2TLAA and Resolution, line item titled "Effects of reactor water environment on fatigue life",: is revised as foows.

Effects of reactor Water environhent Anly,.erom.in..

lid 4.3.3 on fatigue life 1

4 R

0 r5R.()(,..

Agingf, fect managed.

10 CFR 54;21(c)(1)(iii)

LRA Table 4.1-2, List of IP3 TLAA and Resolution, line item titled "Effects of reactor Water environment on fatigue life", is revised as~foillws:..

Effects of reactor water environment A"nalysc r*emainin valid 4.3.3 on-fatigue life In0 CF 54214

,U%,1 "OR.

Aging-effect managed 10 CFR 54.2.1 (c)(!)(iii)

LRA Section 4.33, paragraph 10 is revised as follows.

At least 2 years prior to entering the period of extended operation, for the locations identified in LRA Table 4.3-13 (P2) and-LRA Table 4.3-14 (IP3)NUR.G.. R 6260 f...r inghouse PDAIR* of t IPEr vint.g,, under the Fatigue Monitoring Proqram IPEC will implement one or more of the following.

(1) Consistent with the Fatigue Monitoring Program, Detection of Apqinq Effects, update the fatique usage calculations using Rfefined the fatigue analyses to determine valid CUFs less than 1.0 when accounting for the effects of reactor water environment. This includes applying the appropriate Fe, factors to valid CUFs determined in accordance with one of the following.

For locations in LRA Table 4.3-13, (0P2) and LRA Table 4.3-14 ([Pe3)imni'di*g NUREGCR 6260 lo..ations, with existing fatigue analysis valid for the period of

-NL-08-021

'Attachment 1 D.d~

2

.Docket Nos.50-247 & 50-"286 extended operation, use the existingh CUFns oA*dster th c Inveionmenthy.dPEd Moe iniin PE dditional planta-specific locations wit ai U my b de~

An analysis using an NRC,-approved version of theiASMEcode orNRC-approved' alternative (e.g., NRC-approved code case)v ay be peifrmet t determinesauvalid

~ Manage te cffcetc f aging1du the--

fatiguz att e

rfemtd!ctosb hie~to progdramhet hill bec reviewed t

aend" pprOvd: by-I-aip tho R

eg.

pciodici n~one RdpretruciVc oxamination fof r othe Olffec ajuted loa~n t 1n ctor enveloping toe bo~

dIc"ah.i 'c d-e

e.

'r" l'ad,..m":

6ýý6

'y*

" '* brst.

by a bct.

j.cceta;ble to. thP

.)

An, anConsistent with the Fatigue Monitorin". Prooram. Corrective Actiors' RCepair or

,ite* "replace the affected locations before exceeding a CUF 0*.i:0:*

of t

e 1.0.lid fatgu durin lho pcgo of-edtidc oprtontico gn ac ont rga AeW-h ac

hepe, qualifiation, ofthod, anf~td f'-onpa ilb cbidt theoCa cc yre prior to theL per jiod f et e oprthion (3)

SCtonsitn A

With

.11 Fatigue Monitoring Progrm, isrrrevised as folows.,Re ro

ýThei Fai Pgusl~ýe MoioigPogram is, anexs ing programtha ýtrak th ie numbe ofiials t l ad p

r tsents o e d

reactr c n

t fat igu tansts byasurng thsat th actua e eiv e

nube of trnie-d es not theFanal*zie number of trn

,*set The

,roaram(-prv

,(;i d

fohe Ifatiu usage environmentally assistedfatigue Will be manpged per x

e 10CFR54.21(c)(1)(iii). F LRA Section A.2.1.1i1, F tigue onitoring P'gam, cacuaions willou ts The Fatigue Monitoring Program is'an existing program that tra-cks the number of critical thermal and pressure transients for selected reactor colant. system-compvnents. The program ensures the validity of analyces that explicitly analyzed a specified number of fatigue transients by assuring that the actualeffective number of transients doesnot exceed the analyzed number of transients.vTiherromraen provides for update of the fatioue usaede calculations to maintain a CUF of < 1.0 for thepberi~d of extended ý6peration..For the" locations identified in Section A.2.2.2.3,updated calculations-Will account for the effects of the reactor water environment. These calculation updates :are,governed by Enter-gy's 10 CFR 50 Appendix B Quality Assurance.(QA) P~ro-gram~ and include desi-ý,n input verification and indepedent review's ensuring that valid assumpf, ons, transients, Cycles, external Ioadinos.-

analysis methods. and environmental fatiolue life correction factors"will be used in

NL-08-ý021 Afttchmnirt I

--Docket Nos. 5,-0-247 &5-8 Page 3o the fatigue analyses.

D The roram requiresCorrectiv a'ctions including repair6or replace6meit of aff'cted c'omponents 'befoire fatig.ue usgecatculations deterine the CUF exceeds 1.0. Specific corcive actions are inmpeemehted iniaccordanre with the iPEC coirective action rogrqaim.: Repair or repl*acement ofthe? affectedc6mp'on-et(s), if necessary.

-will be inaccordance` wiit I

etblished-pt p'rocedures goverigrpi n6elcmn iactivties. These established precdres are governed by Enterqy's 10 CFR 50 Appendix B QA prboaram and meet the' applicable *r&air or replacemeit equirements of the ASME-Code LRA Section A.2.2.2.3. Env i.tonmental Effects on Fatigu.týis revised a -s follows.

The effects of renatr water environment on fatiguedwere evaated foricense renewal.

Projected umulative usage factors (CFs)were6calculated fqr the limiting lýcations

ýidentifed-i. based on NUREG/CR-6260. The identified 1P2-locations are those listed in the license renewal applicaation, Table 4. 3-13. For

• lcat.ions

• ,tCUG-,lo than1.0 th.

JLAA

• has benpro-jected through the p Aiiod oMnýr6de;- operationper I140 CFR 54*.24(e)(1)(ii).-Several locations may exceed a CUF-of 1.0 with, cnsideration of henvironmental effects during the period of extended.6peration. The.Fatique Monitoring.

tPrgram requires that Aat leasttwo years prior t6o entering the period of extended operation,.

the site wilimplement one or'more of the fowingl (1) Consistent with the.Fatigue Monitoring Pro-gram. Detection of AginqgEffects, update the fatigueusage, calcUlations u ting Rrefined #hfatigue analyses to determine valid CUFs less than 1.0 when accounting ofr the effects of reactor water environment. This includes applying the appropriate Fen factors to valid CUFs deterrnined in accordance with one of the following.

For locations, including N.REGICR. 6260location., with exstng fatigue analysis valid for the period of extended operation, use the existing CUF to determ.ine the eni.onmentally in addition. to the NUREGR 6260.atie.s..,

more.Fe i.itingLdditional plant-specific locations with a valid CUF maybe evaluated. In particular, the pressurizer lowershell will be reviewed to ensure the surge nozzle remains the limiting component.

Representative CUF values from other plants, adjusted to or enveloping the plant-specific external loads may be used if demonstrated applicable.

An analysis using an NRC-approved version of the ASME code or NRC-approved:

alternative (e.g., NRC-approved code case) may be performed to determine a valid CUF.

(2) Manage the effects Of agin du oftgue at the affected locations by an iseto programA that has been riewed and approved by the NRC (e.g., periodic nOR

ýNL-08-02 1.

ý:,.DockletNos& 50-247 & 50-286 Piage '4 of 6 detorincd by amtd t

(32) Consistent"with the Fatiaue Monitoring, Program,' Corrective Acrions. Rrepair or replace the affected'0locations before.exceeding"_a CUE(JOF io.0:+!-'::__:.:--'

o 0

Sho0uld IPEC colect' th pint aaete gn fet u ocv Ronctal aceited years pIR0rortthprodoexcddortin LRA Section A.3.1. 1. 1, Fatigue Monitoring Program',is reVised as follows.

'The Fatigue Monitoring Program is an existing program that tracks the number' of critical thermal and pressure trnsi*e"*nits"fr* se'ectled acto colant system compone.

The program ensures the validityqof ana!ysesthat explicitly analyzed a specified number of

.fatigue transients by assuring that the actual effectiveinumber of transients'does not exceed

-he analyzed number of transients. The program provides for u fdate f the fatique.usage

-calculations to-maintain a CUF of < 1.0 for0the period of extended operation. For the l6o..cations ident ified in SectionbA.3.2 2.3.uidated calculations will accountfor the effects of

ý,the reactor water environment. These calcrulation udates are goveried by Enteriy's 10

• • CFR 50.Appendix B Quality Assurahce (QA) program 'and includedes6Jin irn u verification land independent reviewsi ensuring that valid &ssurnptions. tran*ient,.,cycles, external 71loadings,: analysis methods, and environmental.fatigue*life correction factors:will be used in

,the6fatique analyses. ýThe programreguires cbrrective actionrs -inclu'dingq repai or

'replacement of affected components before fatigue' usage calculations determine the CUF exceeds 1.0.0 Specific corrective actions arie.implemented in accordance with the IPEC cor rective actibn program. Repair or replacemnt of the affected compodnent(s),f if necessary.

will be in accordance with established plant procedures governihg riep'air and replacement activities. These established proceduires are' govermed by" Entergly's :10"CFR 50 Apiýendix B QA program and meet the applicable reipairor reolacementireguiremrents'of the ASME Code Section Xl.

LRA Section A.3.2.2.3, Environmental Effects on Fatigue, is revised as follows.

The effects of reactor water environment on fatigue were evaluated for license renewal.

Projected cumulative usage factors (CUFs) Were calculated for the iimiting locations ident! ed based on NUREG/CR-6260. The identified IP3 locations are those listed in the license renewal application, Table 4.3-14. Frth o

N,,,

ith'CUF, leo§ than 1.0, te' TLAhas been projected through the pcried of. etended orainper 10 GFR 64,24(6)(4)(ii)7 Several locations may exceed a CUF of 1.0 with consideration of environmental effectsduring the period of extended operation. The Fatigue Monitorinq Program requires that Aat least two years prio" to entering the period.of extended operation, for the locatins ideIntified in NUREG!CIR 6260 for VWstinghouse WRs of this viitage, the site will implement one or more of the following:

NL-08-02 1 Attachment I Docket Nos.50247&'50-286 Pae 5of 6 (1) Consisteht with the'Fatigue M6nitoing Program e, tec ion of Ain Effects., 'edate the fatiiue usaqecalculiation usin e'ine*

-*t*atig-e a

6Jyse to'det*rminevalid CUFs less' than 1.0 when ac*ounting for the.effectsof reactor water envirorime.t This includes applying the'approprqiate.Fe factqors ovaid CUFs determined in accordance.

with one of the followingd.

For1locations, includin, g IUREG!CR 6260 catincv with.existing fatige analysis valid for the period of extended operation," use the e6xisting CUF to-dotenin.the environmentally acptded-Gyý.

In addition tob the. NUaCr t

6ý2601 6 at;o.nmoe. limtingAdditional,lan*-*secific locations with a valid CUF may be evaluated. In particular, the pressurizer. lower shell will be,ý reviewed to ensure the surge nozzle' remains the Imii!ng compe*oint Representative.CUF values from othier plants;:djtie to. o-.-r enveloping the plant-specific external-loads may be used if demonstrated applicable An analysis.using an NRC-approVed version of the ASME code or NRC-approved.

Iaternative (eIg., NRC-approved pode"case) may be performed to determine a valid CUF.

(2*Maag te ffects-oagndutoftuetth ffected loca-tions by an inspection mthat h:; bo id apppoved by.the NR

.g

p.

non docruive examiatio oA f the affected locaion t npeto itr4l ob deteirmind b0 M method AGacceptble tin thia 1R)2

()Consistent with the Fatigue.Moniltoring Program, Corrective Actions. "repair or repla'ce' the affec'r ted 'locations befo6r"e.e.

• ex*

6din* 6. CUF of 1.0.

Shud sCeclect the optin to Mmianaete gn offect duo toen6ViRironental acciSted fatigue during theperod of externded operaion 6dti of th Ogn aagmn rogrFAm such aI hcpqaiiain ehd n rqec ib um itdotoNC atrleast 2 years pro o h eriod of extended oeain LRA Section B.s1. 12, Fatigue Monitoring, Program Description, is revised as follows.

The Fatigue Monitoring Program is an existing program that tracks the number of critical thermal and. pressure transients for selected reactor coolant system' components. The program ens.ures the validity of analyses that explicitly analyzed -a specified number of fatigue transients by assuring that the actual effective number of transients does not exceed the analyzed number of transients.

The program provides for update of the fatigue usage calculationS to maintain a CUF of <

1.0 for the period of extended-operation". For the locations* identified in LRA Table"4.3-13

• P2) and LRA Table 4.3-14 (P3). updated calculations will account for the effects of the reactor water environument. These calculation ug dtes are governed by Entergy's 10 CFR 50 Appendix B Quality Assurance (OA) program and include design input verification and

NL-08-021 AiiimenI Docket-Nos. 50-247 &` 50-8 Page 6of 6 independent reviews ensuing that vaid' as-umoina nsients, cycles, external.loadings.

analysis methods, 'and environmental fatiue life correctioi faictrs wi, be 'used in the fati6ue The analysis'methodsfor determination of stressesad fatigue usacie will be in accordance with 'an NRC endors--ed E-'d'i-tion ofteiirii FoiW6~ehii~

Eni

'i6jsASME)_

Boiler and PreOssure VeseCo.Sctn IRus for Crituto of 1'

Nular Pwr'ý6 Plant Coimpone nts Divisionh 1 Subseci6n N BClass I Components. Sb ariciies NBi3200 or NB-g 3600 as applicable to, the specific com6onient.

PECwil utiliz.design'transients from IPEC Desig n. Sldecifications; to-bounhd all1 oerational trnsient-Thenumbers :of cies Used for

.evaluation will-b based othdeinnubrfcclsand -acuaIp C

nl count proiected out to the-e'n-d o'f the. license renewal 6i erio' d_ (60 v64 4:

Environmentaleffects: on fatigu6e udsage will be assessed usinjgqethodol

consbistent with; the G*enferic Agingq Lessoniis: Lear~ned: Rep'ortt;. NU(R EG1 *801,; Re*v.: 1. ;(GALL th!

Iat 'state S: "The sam ple of cditical cmpo6nents can be evalua*i@te d byaippling environmental i5f6e correction facotor to the' existkin ASME Code ftigu 6 nls Fomlefrcluaing Othe,

'.environmental life 6correctioh factors a6re 6cntained in-NOREG-/CR-6583 fr fciarb6n arnd low-

.lloy steeis arnd. in NUREG/CR-5704 for austenit-ic stainless steels."-.:

The Fatique Monitorinq Prorm tra cks actual plantltransients a nd evaluates these against

• the desigqn transients. Cyclee ounitsshown'o limits-arýe-x-p'ectb'd to be: apipoadhed 'forthe current license" term. The.Fatique Mohitorin_ Pirarýa Will, ensure that the'numbers-of transient cycles exlerienced by theiolaInt Temain:within :theanalyzedjniubers of c6yces and

.hence, the com-ponent.CUFsr-emain below thevalues calculated inthe design basisefatigue

!evaluations. Ifeonoingmonitoring indicates the potentialiforja condition outside that analyzed above, IPEC may. perfom further'reahalsis 6

of the i*entified configuration usingq I established confiquration ranaanqement rocess6es as-described above-.

The program requires corrective actions including repair or replacement of affected components before fatigue.'usage calculations determine the:CUF exceeds 1.0. Specific corrective actions are implemented in accordance with the 'PEC corrective action program. Repair oi-relacement of the affected component(s), if necessar, will be in accordanýce withfestablished plant procedures goveming repair and replacem6nt activities. These established pir6cedures are governed by, Entergy's 10 CFR 50 AppendixBOA program A meet theapplieable reairorreplacement requirements r

apr rl

ATTACHMENT 2 TO NL-08-021.

Regulatory'commitiment-List,.Revision-3, -!

ENTERGY.NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286

Nl_-08-021 Docket No6s. 50-24.7;& 50-286 PageP 1,of 16 List of"Regulaory: Commitments' The following table id~entifies those actions-.6ommitted to'by Entergy in this*doc6ment.'....

_Any other statements in this submitta -are provided for informationpurposes and-are not----

considered to be regulatory commitments.

COMMITMENT IMPLEMENTATION SOURCE'"

RELATED' SCHEDULE LRA SECTION

• AUDIT ITEM Enhance the Aboveground Steel Tanks Program for 1P2 NL-07-039 1P2 and 1P3 to perform thickness m:easurements Iof eptember 28, A.3.1.1 ane013 B.1.1 the bottom surfaces of-the condensate storage tanks,..

city water tank, and fire water tanks onceduringthe.i 1P3:

first ten years of the period of extended operation*

Dcme12 Enhance the Aboveground Steel Tanks Program for 2'015 lP2 and IP3 to require trending of thickness measurements when material loss is detected..

2 Enhance the.Bolting Integrity Program fori..P2 and lP3 P2.

r NL-039 A.2..2 to.- clarify that actual yield strength is used in selecting..

p 2

A.3. 12 materials for low susceptibility tod CGCan'dclarify thle '0..

B.2 prohibition on use of lubricants containing0 MS 2 for botng P3:

NL-07-153 Audit Items bolting.

December 12, 201, 241,

-The Bolting Integrity Program manages loss of.

.2015 "270 preload and loss of material for all external bolting.

3 Implement the Buried Piping and Tanks Inspection 1P2:

NL-07-039 A.2.1.5 LRASecion eptember 28, A.3.1.5

Program for IP2 and IP3 as described in LRA Section

.1.

B. 1.6 2013

-B.1.6 B.1.6..NL-07-153 Audit Item This new program will be implemented consistent with* iP3:.

173

.the corresponding program described in NUREG-December 12, 1801 Section XI.M34, Buried Piping and Tanks 015 Inspection.

"f.

&L0-021:

Docket Nos.`50-247, & 50-;286 Page of16:

COMMITMENT IIMPLEMENTATION SOURCE

RELAELATvP__

":SCHEDULE-I LRA SECTION j

j_______ I UDIT ITEM 4

Enhance the Diesel Fuel Monitoring Pr6gram to.

include cleaning and inspection ofthe.P2 GT-1 gas' turbine fue oil storge tanksg, P2 and lP3 EDG fuel-oil

,day tanks., iP2 SBOlApOpendix R.diesel generator fuel oil day tank, andPippendix R ful-oil storage taank and day tank once every en years-.

Enhance the Diesel Fuel Monitoring Progrm to-i; t o include quar'erly sampling and analysis of the 1P2 sBO/APpfendix R diesel generator Ifuel oil day tank, iP2 security"diesel fueloil day tarnk, and IP3 Appendix, R fuel oil storage tank. Particulates,- qterand.

sediment checks will-beý performed on the samples.-

FiIterabIe sliIds acceptance c iteriohnwill.l be. ess§ than' or equal to 10mg/I. Water and sediment acceptance criterion will be. less thann equ'ai to.05%::.--

EnhNance the Diesel Fuel Monitoring Program to.

include thicknesS measurement of the bottom surface ofjite following tanks once every ten yeaýsrs.- lP2: EDG fuel oil storage tanks, EDG fuel oil day tanks,.

SBO/Appendix R diesel generator fuel oil day tank, GT-I gas turbine fuel oil Storage tanks, and diesel fire

pump fuel oil storage tank; IP3: EDQGfue oilday taniks, Appendix R fuel -oil storage tank, and diesel fire pump fuel oil storage.tank.

Enhance the Diesel Fuel Monitoring Program to change the analysis for water and particulates to a quarterly frequency for the following tanks. IP2: GT-i gas turbine, fuel.oil storage tanks and diesel fire pump fuel oil storage tank; !P3: Appendix R fuel oil day tank and diesel fire pump fuel oil storage tank.

Enhance the Diesel Fuel Monitoring Program to specify acceptance criteria for thickness.

measurements of the fuel oil storage tanks within the scope of the program.

Enhance the Diesel Fuel Monitoring Program to direct samples be taken near the tank bottom and. include direction to remove water when detected.

Enhance the Diesel Fuel Monitoring Program to direct the addition of chemicals including biocide when the presence of biological activity is confirmed.

1P2:

7' Septemnber 28, 2013 D1ecemberI 2,ý.

2015 NL-07-039

ýNL-07-1 53_

..;*A:.2.1:.8 8.

Audit items 8 129,'

132 I

U U

J

.NL-8-,021 Attachmment2 Docket No 50-247 & 50286

• ~

".-COMMITMN'

'RELATED- :

COMMITMENT"-

IMPLEMENTATION SOURCE.

RELATED SLRA SECTION

___________________________________I

____IUDIT ITEM 5

Enhance: the -External Suurfaces Monitotring P* ogram 1P:

r 3

.2.1.1O

-for P2 and IP3 to include periodic inspections-of eptemer"2-A

• -'.1 systems in scope and subject to aging management -

1

.1 review for-license renewal in accordance with.10CFR "

54.4(a)(1) and (a)(3)i. "lnipeictions s al inc lude areas-:.

surrounding the subject systemsto identi hazardsto ecemer 1, those systems. Inspectionrs of'nearbysystemrsthat 015 could impact the subject sýystems will include SSCs

.that are in scope and subjectto aging management revie~ for icense renewal in accoran*ewith 10 CFR 6

Enhance the FatiuýeMonitoring Programi for IP2 to'2NL-07-039

.2. 111 monitor steady state cycles and feedwater cycles or.

eptmbe-28, A.3.1.1' perform an evaluation to determine monitoring is not 013 i..12, "N

L 'B/-153, A*udit Ite m required,. Review the number of alflowed events'and 16-5 Audit Item resolve discrepancies betweenmreference documents 164 arid monitoring procedures.,

Enhance the Fatigue Monitoring Program for -P3 to lP3:,

include all the transients identified. Assure all fatigue December, 12, analysis transients are included with the lowest 2015 limiting numbers. Update the number of design transients accumulated to date.ý

.__..___I

NL 21, Attachm~ent 2, Dpcke.t Not, 507-247A &50-ý286:

1. COMMITMENT JIPEETTOJSOURCEIRLAE I CHEDULE.

LRA SECTION I

~AUDIT. ITEtM 7

Enhance the Fire Protection Program to inspect external surfaces of the 1P3 RCP oil coiiection' systems.for loss of'materia each refuelinhgccle.-

Enhance the. Fire* Protectio -Pro'gram.t to. ex plic'itly:

state that the !P2 and IP3 diesel fire"pump engine, sub-systems (including t*hefuedlsupply. line).shal be observed while the 0pump. is-ru ning. Acceptance criteria will be revised to verify tihatthe diesel. ngine does not exhibit signs of degradation while4running; such as fuel oil, lube oil,"coolant, or exhaust gas leakage.,

Enhance the Fire Protection Program to-specqfy that the 1P2 and IP3 diesel fire pump'engine arbon stee!l exhaust components are inrspected for 'evidence of corrosion and cracking at least once each operating cycle."

-Enhance the Fire Protection Program for 1P3 to

isually inspect. the: cable spreading room, 480V.

switchgear room, and EDG room CO 2 fire suppression System for signs of degradation, such as corroIsion and mechanical damage at least once every six months.

Septembelr28, 2

• 13'.

P3:-----

20151ý NL 07 -039 3

A.2. 1.12 A.3A.1.2 B.1.13 I......

.

*.*.,:: *. -*ii.=i

'. :'*".. : '='i

.:N L-08-021 Attachmnent 2 Docket Nos. 50-247 & 50-286 Page 5 of:16' v

-COMMITMENT' IMPLEMENTATION

-SOURCE

'-RELATED-.

SCHEDULE LRA SEC-TION I AUDIT ITEM 1P:

-N-07-0-39 A.2;.:18'T.

8 Enhance the Fire Water Program t..o include,inspection oNL..

.13 of IP2 and IP3 hose reels for e Vidence ofqcorosion

,4,

,!2013 B.1,14 Acceptance criteriawillbe revwsed to verify no NL'07-153. Audit Items unacceptable sgns of dgradt*ion.

105 10.

Enhance the Fire Water Program to replace a'llrtest ecember,12, NL-08-014,.

a sample of !P2 and JP3 spr'ijnkler headsirequiped for e015 10 CFR 50.48,using guidance ofP 20(21 edition), Section 5.3.1.1.1 beforethe end of the 50-..

year sprinkfer head serviceifýeand at1 0-year inteirvalýsthe'eafterýduring the ie*pnded perod of operation to ensure that signs of degradation, such as corrosion, are detected in a timelyimanner" Enha'nce the Fire'Wa'ter Progr-am toperform wall thickness evaluations of IP2a'nd P3fire; protection piping on system componentis using non-int*usive.

techniques (e.g., volumetric6testing) to identify evidence of loss of material duelto corrosion. These inspections will be" performed before the end of.the current operating term andat intervals thereafter during the period of extendedl-operation. Results of the :initial evaluations will be used todetermine the appropriate inspection interval to. ensure aging effects; are identified pior to0loss of intended function.

Enhance the FireWater Program to inspect the internal surface of foam based fire suppression tanks.

Acceptance criteria will be enhanced to verify no

_ 1 significant corrosion.

Atachment 2 Docket Nos.. 5027&5-6 Page 6s of 16

1. COMMITMENT IMPLEMENTATION SOURCE RELATED

-SCHEDULE L RA "S'EICTION

______________________________________A "UbIT ITEM:

9 Enhance the Flux Thimble Tube Inspection Pr og am

-L-07-03, A-2.^."5 for IP2 and 1P3 to implement compansons to wear-:

0September 28, A.1" rates identified in WCAP-12866.. Include.Provisions to 013 BA

.1"

-compare data.tatothe previous prmanoes'a b'n..

perform evaluations regarding change to test P:

frequency and scope..

Decembr 2,:

2015.

Enhance the Flux Thirmble&Ubelnspectio r"

Program for IP2 and1P3 t'ospecify the acceptance'.crieriaas-outlined in WCAP-12866 or other pant-specific va.ues based on eva'luation ofprevi`u,-9 test results.

Enhance the Flux Thimble Tu"be inispection Program for! P2 and lP3to direct evaltuation! and-performance, of corrective actions baýSed on'tubes thatexcee'd or..

are projected to exceed'the acceptance criteria. Also stipulate that flux thimble tubes'that cannot be inspected'over the tube length ard cannotrit be shown

,by analysis to be satisfactory for continued service.

Imust be removed from service to ensure the integrity

' lof the reactor coolant system pressure loundary. '

L-08-021'

'Afttchment 2 Docket'Nos.

4O-47& 50-8 Pag 7,.of 16

'COMMITMENT IMPLEMENTATION,-SOURCE,

RELATED' HEDULE

,LRA SECTION IAUDIT ITEM I"'*

-" ;," IP2

• 7-3

2 16 :

10 Enhance the Heat Exchanger Monitoring Program for 1P2:

.L--..,..

.2.1...

.......-,:... 00 ýe~

m e 28 :,ý.- ;

A 3.1.16 IP2 and IP3 to include the following heat exchangers--

etb3 28,

.1.,.

in the scope of the program

03.

8N B.1.17, "NL-07-1 53 Audit itelm

• Safety injection pump lube oil heat-exchangr IP3:~-----5

,*. RHR.heat exchangers emb.r 12

• RHR pump seal coolers

. Non-regenerative heat exchangers Charging pump seal wateri heat exchangers

• Charging pup flVui~d drive coolers

• Charging pump crankcase'oil co~olers

. Spent fuel pit heat exchangers

• Secondary system steam generator sample:.

coolers.:.

Waste gas compressor heat exchangers SBO/Appendix R diesel jacket water heat exchanger (!P2 only),

Enhance the Heat Exchanger Monitoring Program for IP2 and IP3 to perform visual inspection on heat.

exchangers where non-destructive examination, such as eddy cu'rrent inspection, is not possible due to heat exchanger design limitations.-

Enhance the. Heat Exchanger Monitoring Program for IP2 and iP3 to include considerati6n of material-environment combinations when detetmining sample population of heat exchangers.

Enhance the Heat Exchanger Monitoring Program for IP2 and IP3 to establish minimum tube wall thickness for the new heat exchangers identified in the scope of the program. Establish acceptance criteria for heat exchangers visually inspected to include no unacceptable. signs of degradation.

/NL-0oM-21 Dokt N9S. "50-247 &'507286 Page 8:of 16 COMMITMENT IMPLEMENTATION SOURCE RELATED".

-SCHEDULE LRA SECTION

" -AUDIT ITEM 1P2:

NL-07-303 A...7 11 Enhance the ISI Program for.IP? andlP3 to provide

,' epteNbe072,

'A,2117 periodic visual inspections to confirm the absence of 013 B.

.,1 aging effects for lubrite sliding supports used in the:':.N3-071 A

item steam generator and reactor coolant pumLpSupport-.5 AP3:-t.

i59

systems, e50be 2 015ý 12 Enhance the Masonry Wall Progranmfor iP2 and lP3 1P2:

NL-07-039 A.2"118 to specify that the !P1 intake structure is included in e

r1 the program 013 B.1.19 IP3:

• December 12.

1 Enhance the Metal-Enclosed Bus Inspection Program iP2-NL-07-039 A.2.1.19 to add IP2 480V bus associated with substation A to September 28-A.3.1.19 the scope of bus inspected.

2013 B.1.20 enh eN-07153 Audit Item Eihance the Metal-Enclosed Bus Inspection Program. IP3:

124 frlP2 and IP3to visually inspect the external surface December 12, Audit Item of-MEB enclosure assemblies for loss' of material at 2015 133 least once every 10 years. The firsi inspection wilil occur prior to the period of ektended operation and the acceptance criterion will be no significant loss of material.

Enhance the Metal-Enclosed Bus Inspection Program for IP2 and IP3 to inspect bolted connections at least.

once every five, years if performed visuallyor at least once every ten years using quantitative measurements such as thermography or contact resistance measurements. The first inspection will occur prior to the period'of extended operation, The plant will process a change to applicable site procedure to remove the reference to "re-torquing" connections for phase bus maintenance and bolted connection maintenance.

" "IP2:

NL-07 1-039 A.2.1.21 14 Implement the Non-EQ Bolted Cable Connections Program for IP2 and IP3 as described in LRA Section September 28, A.3.1.21

.1.22.

2013 B.1.22 IP3:

December 12, S015

'NL-08-ý02 I Afttchment

.Doketý Nos. 50-247: & 50-286'.

Page 9 of 16 COMIMETIMPLEMENTATION SOURCE-RELATED SCHEDULE LRA SECTION

____I AUDIT ITEM 15

-Implement the Non-EQ Inaccessible Medium-Voltage W-07,0: 3-

""3 '.2.1.22 Cable Program forl1P2 and 1P3as described in LRA September 28, A.3.1.2 Section B.1.23.

013 B.'..3 NL-7-7-*

udit item This-new program will beiimplemented consistent with-IP3: -.:.

173 the corresponding program described in N'REG-December 12, 1801 Section XI.E3,Inacce6sible Medium-Voltage-2015 Cables Not Subject To, 10 CFR50.49 Environmental Qualification Requirements.

16 Implement the Non-EQ Instrumentation Circuits Test pteber 2807039 A.1.1.23 Review Program for IP2 and lP3 as described in LRA 0

'3

-1..

4 Section.B; 1.24.

• -.2 1"""

B -1.2 Section....24...NL-07-153 Audit item This new programWill be, impremented consistent with 1P3:,

173 the corresponding program described in NUREG-December 12, 1801 Section X!.E2,-ElectI6cai Cablesand

.015 Connections Not Subject to 10 CFR'50.49-Environmental Qualification Requirements Used in

_Instrumentation Cir cuits. -_

17 Implement the Non-EQ Insulated Cables and IP2:

NL-07-039 A.2.1.24

!Connections Program for IP2 and IP3 as described in September 28, A.3.1.24 LRASection B.1.25.

2013 B.1.25 NL-07-153-Audit item

!!T~his new program-will be implemented consistent with iP3:.

173 the corresponding program described in NUREG-December 12,.

1801 Section XI.E1, Electrical Cables and 2015 Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements.

NL-08-021 1 Attachmenit 2 Doc:ke Nos. 50-247 &501286 ag 10 o( 16 COMMITMENT IMPLEMENTATION SOURCE:

- RELATED" S:CHEDULE LRA SECTION

_______I AUDIT ITEM.

ce " :

• 1Pr' vnrts ie-'2 NL-07-039 A2"1.25 18 Enhance the Oi! Analysis ProgramiforP2to sample e*pemb0er 28,.

3...2.

and analyze lubricating oil.used in the SBO/Appendix 013 B..,

R diesel generato* consistent with oil analysis for-

• other site dieselgenerator I s.-

Enhance the Oil Analysis Program for 1P2 and IP3 to December12, sample and analyze generato seal oi and turbine 2015 hydraulic contro oil.

Enhance the Oii Analysis Program for iP2and iP3 to.-.

formalize preliminary oil screening for water..and..-

particulates and laboratory analyses includinge acceptance criteria for all components included in the scope of this program. The program will specify:'

corrective actions in the eve ntacceptance criteria'are not met.

Enhance the Oil Aalysis Program for,P2 and 1P3 to formalize trending of preliminary oil screening results aswell as data provided from independent laboratories.

19 IP2met tPiNL-07-039 A.2.1.26 19 rplement the One-Time Inspection Program for 1P2 epS br8 A.3.1.26 and 1P3 as described in LA ection B.1.27.

.1.2 LPLeci1 3

B..27.2 This new program will be implemented consistent with NL-07-153 Audit item th~e corresponding program described in NUREG-IP3:

173 1801,Section XI.M32, One-'Time.Inspection.

December 12, 2015 IP2:

NL-07-039 A.2.1.27 20 Implement the One-Time Inspection -Small Bore Piping Program for IP2 and 1P3 as described in LRA e

.2 2013 B.1. 28

.Section B.1.28.

03

.12 NL-07-153 Audit item' This new program will be implemented consistent-with IP3:

173

.the corresponding program described in.NUREG-:..

December 12, 1801,Section XI.M35, One-Time Inspection of ASME 2015

.Code Class I Small-Bore Piping.

12:

.NL-07-039 A.2.1.28" 21 Enhance the Periodic Surveillance and Preventive,

" S2 A..1.28 Maintenance Program for IP2 and IP3 as necessary 013 2.1.29 to assure that the effects of aging will be managed, such that applicable components will continue to perform their intended functions consistent with the 1P3:

current licensing basis through the period of extended December 12, 2015 operation.

.NL-08-02 1 Pocket Nos. 160-247.& 50-2.8T6.

Pag 11 oflW

-:J COMMITMENT IMPLEMENTATION SOURCE RELATED scHEbuLE LRA SECTION,

_ - I AUDIT ITEM

-22:

Enhance-the Reactor6.essel Sýryreillance P.rogram for*N..

NL-07-039

.A.2.1.:31.ý witdr~ SIeptember 28,-

JA31.31 1P2 and 1P3 reisn th scien capsule.

013 i1.3 schedules to dr and test a standby capsule to cover the6.peakk reactor vessel fluence expected through the end of the period of extended operation' - De3..

12, Enhance the.Reactor Vessel Surveillance Program for 2015 IP2 and 1P3 to requirethat tested and untested`.. --

specimens from all'ca'psules pulled from the reactor vessel are maintained in storage.

23 Implement the Selective Leachig' Program for1P2?.

P2:

NL 07-039 A;2.1.32 and IP3 as described in ERA.Section'B.-1.33.

eptember 28,.

A.3.1.32 03 Bý.1.33 This new program will be imp'lemented consistent with

'NL-07-1 53 Audit item' the corresponding program describ-d inNUREG-.

P3:

173 1801, Section XlIM33 Selective Leaching of Materials.- December12,.

24 Enhance the Steam Generator Integrity Program for 1P2.

N--07

.39 A.2.1.34

`1

.. I.... eptem ber 28,A

..1 3 1P2 and 0P3 to r'equire that the results of the condition

-eptmbe 28-A.3.-.34 monitoring assessment are compared to the oerational assessment performed for the prior013 B

o~ertioaI pior 1173:

operating cycle with differences evaluated.

December,

. December 1,,

2015*

Enhance theStructures Monitoring Program to'.

IP2:

NL-07-039 A.2.1.35 explicitly specify that the following structures are September 28, A.3.1.35 included inthe program.

2013 1B.1.36

• Appendix R diesel generator foundation (IP3)

NL-07-153 0 Appendix R diesel generator fuel oil tank vault IP3:

Audit item

(!P3)

December 12, 86 e Appendix R diesel generator switchgear and 015 enclosure (iP3)

Audit item city water storage tank foundation 88 condensate storage tanks foundation (IP3)

• containment access facility and annex (IP3).

Audit Item

• discharge canal (IP2/3) 87 emergency lighting poles and foundations (IP2/3) fire pumphouse (IP2) fire protection pumphouse (IP3) 0 fire water storage tank foundations (IP2/3) 0 gas turbine 1 fuel storage tank foundation maintenance and outage building-elevated passageway (IP2)

L new station security building (IP2)

NL-08-021 DoktNos. 247 & 50-286,

-P glofi COMMITMENT

.IMPLEMENTATION SOURCE"

-RELATED HiDULE

,LRASECTiON I AUDIT ITEM

. nuclear Service building (IPI).

primary water storagetank foundation (iP3) refueling wate!r storage tnk foundation (IP3) security access and oftce building (0P3)

service water p hse( P2/3) service water valve pit (IP3) o superheater stack transformer/switchyard support structures (IP2) waste holdup tank pits (P2/13)

Enhance the Structures! Monitoring Program for lP2 and IP3 to clarify that in addition to structural steel and concrete, the following commodities (including their anchorages) are inspected for eachstr ucture as applicable.

cable trays and supports concrete portion of reactor vessel Supports conduits and supports.

c Cranes, rails and girders equipment pads and foundations fire proofing (pyrocrete) 4 HVAC duct supports jib cranes-manholes and duct banks manways, hatches and hatch covers monorails new fuel storage racks sumps, sump screens, strainers and flow barriers Enhance the Structures Monitoring Program for IP2 and 1P3 to inspect inaccessible concrete. areas that are exposed by excavation for any reason. IP2 and IP3 will also inspect inaccessible concrete areas in environments where observed conditions in accessible areas exposed to.the same environment indicate that significant concrete degradation is occurring.

Enhance the Structures Monitoring Program for IP2 and IP3 to perform inspections of elastomers (seals, gaskets, seismic joint filler, and roof elastomers) to identify cracking and change in material properties and for inspection of aluminum vents and louvers to identify loss of material.

NL-08-ý02 1 Attacihment 2

-,DocketNos.502-47,&50-286 Page..13of1 COMMITMENT IMPLEMENTATION SOURCE' RELATED

.;ýSCHED LE LR SEC ION I AUDIT ITEM Enhance the Structures Monitoring Program for IP2 and IP3 to perform an engineerng evaluation of ground~water'samples to assess aggressiveness of Sgroundwater to 0cncrete on a periodic basis (atleast.-

once every five years). :iPEC will obtain samples from at least 5 wells that are representative. f the ground water surrounding below-grade site structures.

Samples will be monitored forsulfa.tes, pH and chlorides.

Enhancethe'Structures Monitoring Program for iP2 and 1P3 to perform inspection of normally submerged concrete portions of the intake structures 'at least once every 5Eyears..

26 Implement the Thermal Aging Embrittlement of Cast 9

• ~tme 28

-A.

3.1.36, Ajstenitic Stainless Steel (CASS) Program for IP2 eptember 28, A.3.1.36 ahd IP3 as described in LRA Section B.1.37, 013 1.37 NL-07-153 Audit item This new program will be implemented consistent with IP3:

173 tqe corresponding program described in NUREG-December 12, 1801,Section X!IM12, Thermal Aging Embrittlement 2015 of Cast Austenitic Stainle'ssSteel:(CASS) Program.

27 Implement the Thermal Aging and Neutron Irradiation.P2 NL-07-039 A.2.1.37 Embnttlement of Cast Austenitic Stainless Steel September 28, A.3.1.37 I

ý..1..:.1.0 1

B.1.3 8 (CASS) Program for iP2 and IP3 as described in LRA 013 8N1538 Section B.1.38..

dP3:.

173.

This new program will be implemented consistent with December 12, the corresponding program described in NUREG-2015 1801 Section XIM1 3, Thermal Aging and Neutron Embrittlement of Cast Austenitic Stainless Steel (CASS) Program.

28 Enhance the Water Chemistry Control - Closed IP2; NL-07-039 A.2.1.39 September 28, A.3.1.39 Cooling Water Program to maintain water chemistry of013 1.40 the IP2 SBO/Appendix R diesel generator cooling system per EPRI guidelines.

IP3:

Enhance the Water Chemistry Control - Closed December 12, Cooling Water Program to maintain the IP2 and'lP3 2015 security generator cooling water system pH within limits specified by EPRI guidelines.

.. NL-08-021 Attac'h ment 2 Docket'Nos.50_247'& 50:-286 jae 14 of. 16.

COMMITIMENT -

IMPLEMENTATION SOURCE, -j. RELATED SCDULE LA SECTION I AUDIT.ITEM iP2 ~~~ýNL-07-09

.214 29 Enhance the Water Chemistry Control - Primaryand

-039 Secondary Program for IP2 to test sulfates monthly in Peptmber 28" 1B..41 the RWST with a limit-of <.150 ppb.

iP2..

NL-07039 A.21.41 -

30 Foraging management-of the reactor.vessel intern.als, IPEC will (1) participate in theihndustry prograrms for

'r*,tem"er 28,-

A.3.-.,.

investigating and mianaging aging effects on reactor internals; (2) evaluate and implement the results-of lP3:

Ithe industr program -as applicableto the reactor Decmbe 12, internals; and (3) upon compietion'of thesepr.ograms, 013 but not less than 24 months before entering the p erio&d

" of extended operation, submit an inspection plan for reactor internals to the NRC for review and approval.

• ~~

0 N :O7-03 9, ý.A. 2.2.1:2:

31 Additional P-T curves will be subrmitted as required 1P2:.N-,-3.A.,...

"per 10 CFR 50, Appendix Gpror to the period of September 28,

-A.3.21.2 extended operation as part of the Reactor Vessel

1.

4.2.3

.Surveillance Program.

D ecembe.12,

'.. :2015:

2 As required by 10 CFR 50.61 (b)(4), iP3 will submit a iP3:

NL-07-039 A.3.2.1.4 p -lant-specific safety analysis for plateB2803-3;to the. December 12, 4.2.5 NRC three years prior to reaching the RTps P

..2015

• .Screening criterion. Alternatively, the site may choose.

to implement the revised. PTS (10 CFR 50.61) rule when approved, which would permit use of Regulatory Guide 1.99, Revision 3.

NL-0-021:

AttachMenit 2 Docket Nos. 50-247, & 5-286 Pag _15 of 16-COMMITMENT IMPLEMENTATION

SOURCE"

, :RELATED, SCHEDULE "

R-SECTION

______D'__

tI UDITITE 33*

33 At least 2 yeais prior to entering the period :of extended operation, for the locations identified, in LRA Table 4.3-13 (IP2) and LRA-Table 4.3-14 (1P3), under the Fatigue Mon itoring Program. 1P2and1P3 will implement one o'rmore of the-following:

(1) Consistent withth'e Fati'ue Monitorin 0

Program'.

Detection of Aging Effectsi UiJdate the fatigu6e6sage.e IP2:

September 28, December.12, 2013

• NL-'07-039 NL-07-1-53

-NL-08-021

,A.2.223.

4.3.3 Audit item 146 Calculations u'sihg re'finedth fatigue hanalyses -to-determine via~l CUjFs less than 1. whenac'counting for the effects of reactor water environment. This includes applying the appropriate Fen factors to valid CUFs determined in accordance with one of the, following:

1. For locations in LRA Table 4.3-13 (IP2) and.LRA Table 4.3-14 (1P3) includi-g N REG!C r

R.6260

• 06atine, -with existing fatigue analysis valid for the perod of extended operation, use the existing CUF.-t determ~ine thc cnvironmentalhi Adi-stC14 Cf.-

2.

n addi*oin to. tiho NUREhl62ID60 Jo't I, n;n more, li*/fing Additional plant-specific locations with a valid CUF may be evaluated. In particular, the pressurizer lower shell Will be reviewed to ensure the surge nozzle remains the limiting component.

3. Representative CUF values from other plants, adjusted to or enveloping the IPEC plant specifiC external loads may, be used if demonstrated applicable to'IPEC.

4. An analysis using an NRC-approved version of the ASME code or NRC-approved alternative (e.g., NRC-approved code case) may be performed to determine'a valid. CUF, affncptd locations by an i'spe teion p*ogpra*

thAt has been rev"o cdiano appf"rvd by the PRG (eag., peizr*dic nn decrst~iic yexamination of the affeccted 1ocationcsat insectonintr.al~tobo detrmpined by a mnethod.

accepbz to. he NRC.).,

R (2) Consistent with the Fatigue Monitoring Program.

Corrective Actions, Rrepair or replace the affected locations before exceeding a CUF of 1.0.

.Should !PECG select thc option to mnanage-thc aging *:effts due to enViron..ental assiste fatigue d-ring th e pcrid of e*tended

operaion, d...i.. of the aging management program such as scope, qualification, mnethod, and frequency will. be sub.mitted to the NRC at least-2 yeTrsrior to the period of c ded. pefati

4L-708--021, Attachment'2 Docket Nos. 50-247 & 50-286.

-Page 16 of 16 COMMITMENT IMPLEMENTATION

-SOURCE

'RELATED SCHEDULE' LRA SECTION

___I AUDIT ITEM

34.

1P2 SBOIAppendix R diesel generato~rwil b lApril30, 2008, NL-07-078 21.3.5 installed and operational by April'30, 2008.This.

committed change to the fadility meets the

-:requirementsof 10.C-FR,50.59(c)(1) andi thereforte,-a*:

license amendment pursuant:to 10 CFR 50.90 is not

_ required. '

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges:..

Lawrence G. McDade, Chair Dr. Richard E. Wardwell Dr. Kaye D. Lathrop In the Matter of ENTERGY NUCLEAR OPERATIONS, INC.

(Indian Point Nuclear Generating Units 2 and 3)

)

Docket Nos. 50-247-LR and 50-286-LR

)"

)

ASLBP No. 07-858-03-LR-BD01

))

February 4, 2008 CERTIFICATE OF SERVICE I hereby certify that copies of two letters from counsel for Entergy Nuclear Operations, Inc. to the Atomic Safety and Licensing Board, both dated February 4,'2008, were served this 4th day of February 2008 upon the persons listed below, by first -class mail and e-mail as shown below. The. first letter concerns the availability of counsel for Entergy Nuclear Operations, Inc.

for oral argument during the week of March 10-14, 2008. The second letter transmits a courtesy copy of a letter from Entergy Nuclear Operations, Inc. to the NRC (Entergy Letter NL-08-021) dated January 22, 2008.

Office of Commission Appellate Adjudication U.S. Nuclear Regulatory Commission Mail Stop: O-16G4 Washington, DC 20555-.0001 (E-mail: ocaamail(cnrc.-gov)

Administrative Judge Richard E. Wardwell Atomic Safety and Licensing Board Panel Mail Stop: T-3 F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 (E-mail: rew6cnrc.gov)

Administrative Judge Lawrence G. McDade, Chair Atomic Safety and Licensing Board Panel Mail Stop: T-3 F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 (E-mail: lgml @,nrc.gov)

Administrative Judge Kaye D. Lathrop Atomic Safety and Licensing Board Panel 190 Cedar Lane E.

Ridgway, CO 81432 (E-mail: kdl2(@nrc.gov)

I -WA/2920769.1

Office of the Secretary

• Attn: Rulemaking and Adjudications Staff U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 (E-mail: hearingdocket(@nrc.gov)

Zachary S. Kahn Law Clerk Atomic&Safety and Licensing Board Panel Mail Stop: T-3 F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 (E-mail: zxkl (@nrc.gov)

Manna Jo Greene Environmental Director Hudson River Sloop Clearwater, Inc.

112 Little Market Street Poughkeepsie, NY 12601 (E-mail: mannajo(dclearwater.org)

Stephen C. Filler, Board Member Hudson River Sloop Clearwater, Inc.

303 South Broadway, Suite 222 Tarrytown, NY 10591 (E-mail: sfiller(Onylawline.com)

Sherwin E. Turk, Esq.

Lloyd B. Subin, Esq.

Beth N. Mizuno, Esq.

Kimberly A.: Sexton, Esq.

Christopher C. Chandler, Esq.

David E. Roth, Office of the General Counsel Mail Stop: 0-15 D21 U.S. Nuclear.Reaulatory Commission Washington,*DC 20555-0001 (E-mail: setanrc.gov)

(E-mail: lbs3 (anrc.gov)

(E-mail: bnml nrc.gov)

(E-mail: kim',berly.sexton(inrc.gov)

(E-mail: christopher.chandler(inrc. gov)

(E-mail: David.Roth(@nrc.gov)

Nancy Burton 1*47 Cross Highway Redding Ridge, CT 06876 (E-mail: NancyBurtonCTPaol.com)

Justin D. Pruyne, Esq.

Assistant County Attorney, Litigation Bureau of Counsel to Charlene M. Indelicato, Esq.

Westchester County Attorney 148 Martine Avenue, 6th Floor White Plains, NY 10601 (E-mail: jdp3(iwestchestergov.com)

Diane Curran, Esq.

Harmon, Curran, Spielberg, & Eisenberg, L.L.P.

1726 M Street N.W., Suite 600 Washington, D.C. 20036 (E-mail: dcurran(aharmoncurran.com)

Phillip Musegaas, Esq.

Victor M. Tafur, Esq.

Riverkeeper, Inc.

828 South Broadway Tarrytown, NY 10591 (E-mail: phillip(riverkeeper.org)

(E-mal: vtafur(iriverkeeper.org)

Thomas F. Wood, Esq.

Daniel Riesel, Esq.

Ms. Jessica Steinberg, J.D.

Sive, Paget & Riesel, P.C.

460 Park Avenue New York, NY 10022 (E-mail: driesel(chsprlaw.com)

(E-mail: j steinberg(ai)sprlaw.com) 2

Robert D. Snook, Esq.

Office of the Attorney General State of Connecticut Assistant Attorney General 55 Elm Street P.O. Box 120 Hartford, CT 06141-0120 (E-mail: Robert.Snook(ipo.state.ct.us)

Andrew M. Cuomo,-Esq.

Attorney General of the State of New York John J. Sipos, Esq..

Charlie Donanldson Esq.

Assistants Attorney General The Capitol Albany, NY 12224-0341 (E-mail: john.sipos(@,6agstate.nv.us)

Joan Leary Matthews, Esq.

Senior Attorney for Special Projects Office of the General Counsel New. York State Department of Environmental Conservation 625 Broadway, 14th Floor Albany, NY 12207 (E-mail: ihmatthe(zgw. dec.state.ny.us)

Susan H. Shapiro, Esq.

21 Perlman Drive Spring.Valley, NY 10977 (E-mail: Palisadesart()aol.com mbs8 ourrocklandoffice.com)

Richard L-.Brodskyv 5 West Main St.

Elmsford, NY 10523 (E-mail: brodskr(@assembly.state.nV.us richardbrodskv(omsn.com)

Janice A. Dean Office of the, Attorney General of the State. of New York Assistant Attorney General 120 Broadway, 26th Floor New York, New York 10271 (E-mail: Janice.Dean(aoag.state.ny.us)

• Original and 2 copies A 6e2 Martin J. O'NeillV 3