L-PI-04-097, Corrections to ECCS Evaluation Models
| ML042300510 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/05/2004 |
| From: | Solymossy J Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-PI-04-097 | |
| Download: ML042300510 (11) | |
Text
Commied to Praie Island Nuclear Generating Plant Operated by Nuclear Management Company, LLC AUG 5 2004 L-PI-04-097 10 CFR 50.46 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 CORRECTIONS TO ECCS EVALUATION MODELS Attached is a report of changes to the Prairie Island Nuclear Generating Plant (PINGP)
Emergency Core Cooling System (ECCS) Evaluation Models. This report is being submitted in accordance with the provisions of 10 CFR 50, Section 50.46.
The report includes Large Break Loss of Coolant Accident (LBLOCA) and Small Break Loss of Coolant Accident (SBLOCA) changes reported by Westinghouse that are applicable from the beginning of Fuel Cycle 22, thus valid for the 2003 reporting year.
The non-plant specific changes are presented in Enclosure 1. All non-zero changes are summarized in Enclosure 2 and are LBLOCA Item A.11 (-19 IF for Broken Loop Nozzle Correction) and SBLOCA Item C.1 (35 IF for NOTRUMP Bubble Rise/Drift Flux Model Inconsistency Corrections). We consider these changes to constitute the 2003 annual report.
Inaddition, Enclosure 2 includes plant specific LBLOCA changes initiated as a result of PINGP's safety analysis transition from in-house analyses to Westinghouse analyses.
This transition was authorized by a license amendment issued by the Nuclear Regulatory Commission by letter dated April 28, 2004 and the transition was made effective July 6, 2004. These changes are summarized in Enclosure 2 and are Item A.10. (-47 IF for Sensitivity Study for FQ=2.5, Low Head Safety Injection Correction, PAD 4.0 Implementation, Steam Generator/Loop AP Re-tuning, and Core Power Restoration), and Item B.5. (+17 OF for Cycle 22 Safety Analysis Transition Program Core Average Burnup). These changes exceed 50 OF and, therefore, the 30-day reporting criterion is applicable for the LBLOCA analyses.
The analysis vendor has recently assessed the applicable LBLOCA changes and corrections noted in Enclosure 2. The assessment has concluded that all corrections are realistic estimates of the impacts on peak cladding temperature (PCT) and are independent of each other. Based on this, the LBLOCA analysis level of conservatism remains essentially the same. In addition, the resultant LBLOCA PCT has decreased from 2180 OF to 1994 "F. Since the analysis remains in compliance with 10 CFR 50.46, 1717 Wakonade Drive East . Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 Nuclear Management Cornpany, LLC (NMC) has concluded that no additional analysis is necessary at this time.
The summary sheets attached to this letter need not be withheld from public disclosure.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Please contact Jack Leveille (651-388-1121, Ext 4142) if you have any questions related to this letter.
Site ice Preside , P ie Island Nuclear Generating Plant CC Regional Administrator, USNRC, Region IlIl Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant Enclosures (2)
ENCLOSURE 2 LOCA Peak Clad Temperature Summary Prairie Island Nuclear Generating Plant (includes plant specific changes and non-zero non-plant specific changes) 8 Pages Follow (Prairie Island Unit 1 LBLOCA - 3 pages)
(Prairie Island Unit 2 LBLOCA - 3 pages)
(Prairie Island Unit I SBLOCA - I page)
(Prairie Island Unit 2 SBLOCA - I page)
Westinghousc LOCA Peak Clad Temperature Summary ror SECV Ul'l Large B~rcak Plant Name: Prairic Island Unit I Utility Name: Nuclear Management Company. LIC Revision D6aie: 7/12104 A nalvsic Inrormat ion EM: SECY UP[ WCIT Analysis Date: 3/1195 Lim1ining BrakSizc: Cd=0.4 FQ: 2.4 Fdll: 1.77 Fuel: OFA SGTP(%): I5 Not es: ZirIo6. OSG SGTP Evaluated up In 24.64%f (see also Note f!; Fqitcreatsed to2.5 Item A.10)
Clad Temp (0 F) Rct. Notes LICENSING BASIS 2180 2.3 (2)
Analysis-Of-Record PCT MARGIN ALLOCATIONS (Delta PCT)
A. PRIOR PERMANENT ECCS 111ODEL ASSESSMENTS I . Fixled 1c1 Trnstcfr odc Assignment ErrorfAccumulator Water Ijxlinn -17S 3 Error (199$ Rcpcwt) 2 .I *DTransition cOiling lett Transfer Error ( 1997 RepCtr) 5 S
- Vewi thannel DX Error I199J Reporte .14 5 t Input Consistency ('997 Reponl 5
- 5. Noltemsfor 1996. 199SReptrts n 4.6 6 AccumuLutor Une 'ressurizer Sur.- Lnc DLtnt I'bnt Specific 113 7 ,b)
AcL%;umuLtw LcsId & Line Vtlumneti'ani SpeicifLc ltenn Efnov-Reanalysis (I999 Rcjxa) 7 . dltelinq-iphtbus and Unhe-ateCondunicot Input Corractions I MnI .147 8.10 IC)
Specific. 2000 Repon) 8 . Accunubtor Pressure t )li
.V. Rptnge tPla nt Specifi. 2001 Reporta a 1'.13 (di
) . IHISI FJmr Evrtnation (lMnt Specific. 2002 Report) 34) 2J. 15 (h) 10 Sensitivity Study for FQr2.5. UISI Correction etc. (as listed in nece qW)} .47 17.192(0 (gi)
I Plat Specific. 20n3 Report) 11 . Broken Lnop Nozzle Correction (Pmnt Specific) (2003 RcportI .19 20.22 ti)
B. PLANNED IPLANT CHANGE EVALUATIONS I . Sensitisitv Stud* for Steam Gcncrtwor Tube Plugging Increase h7 25', 52 S 2 Accumnulator Waler Volumae s- 25 r,3 Range 12 12
- . Accumnutwor Pressure Extended to +1-55 psi RangC 21 12 4 . S Rconvtitutcd fnxlsEBaluation 0 9.11 IC) 5 . Cyk 22 SATI'COwe Avtrac Burnup 17 21 C. 2004 PERMANENT ECCS MODEL ASSESSMENTS I. None I)
D. TEMPORARY ECCS MODEL ISSUES*
I. None (I E. OTHER
Westinghouse LOCA Peak Clad Temperaturc Summary for SECY UPI Large Break Plant Name: Prairie Island Unit I Utility Name: Nuclear Manacement Company, ULC Rcvision [iae: '.7112104 I . RovalorRcfcren. e4LHSlEror Evaluxatizm .3 17 (h) lICENSING BASIS PcT + lMARGIN ALLOCATIONS PC'C 1994 It is rfCCrmcnddlithat these tmporary l rrarlcadouM Ahich addrss eurrent LOCA nicdl issues nut hv considered with respect to 10 CFR 50.46 reportinq requirerncnts.
Rererences:
I . 95NS-C-002R. tlpdjtcd 1LPS USI.OCA. Madr124. 1995.
2 . WCAIP-I3919. Addendum 1. 'Pnlrie Istod Units I and 2 WCOIIKAtIXAC Btest Estimtine UPI Large Break LOCA Analysis Enrineering R-.prt Addkndirn 1: Updatcd Results.- rcecnher 19'96 3 %SPl-96-202. Nothen States Powcr Company P'rixitc bland Units I and 2 10 LTM 50.46 Annual tNotilicaiion and Rpvnling: Fhbruary 20. 1996.
4 NSPI97-201. Northern States Pr3 er Company Prairik Isind Units I and 2 ID CFR 50.46 Annual Netifimation and Rcurxting. Arit 17.1997.
5 . NSIP9 12. N1rthern States PlwerCownpany Prairie bLand U',its I and 2 IOCFR 50.46 Annutl Notification and Reponing fir 1997." Vebruasry 27.1998.
6 NSP-99-0l0.-Northem States Pmcrt omripny Prairie sbland Unit I and 2 1OCR K50.46 Annual Notification and Itclsiting for 1998." April 29. 1999.
7 .NSPl-OMi. Northcm States PtnwtrCompany vPririe Wand t:nits I and 2 I f CFR 5046 Annual Notification and Reporting frw 1999.Afieruarv 2000.
S . NSP4Xt-037. Nuonhcm States Pouwer Company Prairie land IVnits I and 2 LOCA Evaluation .f :5q SG1TP %ith Othvr Mmdkling ULpdatcs. December It. 2000.
I 0.04S-G.-007WCA8-00-390. Prairie Island Unit I Cvcle 'I LOCA RerloadConflrmitkirnand MCEP CbcktlisC PDcoembr I5.
21100.
10 . NSPI01406. othern Statcs Poer C pany Prairie labnd naitsI and 2 ID CTR 50.46 Annual Notification and Xcportin for 2000.- 1jrdh 6.200l.
11 . RothrockOJNC 1oSWipl SW).7r*Iiric Islnd Unit I LUCA PC .NMay3o.2001.
I2 . NSPI02-9. 'Nuclear Manzgement Coimpany Prairie Mlind I niis I and 2 LBLOWA AccuniulaurlPrr-isrue and Volunm Ranies Evaluatiov.' Friruary 15. 20)2.
13 . NSP-02-S. 'Nuclear Man tnentCompany Paine Iland Unit I and 2 10CF2R 50.46 Annual Notificztion and Reporting for 2001." March 2002.
14 . NSP-02-59LTR-ESI-02-194. 'Final Esaluation of Larle ltreaI LOCA Erns." M)exnrher 2002.
15 . NSP4]t13l9. "Nuclear Manageient Company Prairic Island Units I and 2 10 CFl 50.46 Annual Notification and Reporting for 20M2. %lardc 2003.
16 . MP02-TAII-0394 I ETNSL.Ott1-9.2-5 IS. 'NStC Itairik Island Units I and 2. SG Tube Flow Area ReduKction under LOCA/
SSE - Fnatl Krirt-. October 21. 1992.
17 . NSP I0 Safcty Analysis Trannsition Program Transmittal of Engineerin Re rport. Febnuary 20. 2004.
I . NSP-93-513. Kcv 1JET. HSl0O1,1-93-313, Rev. 1. Iester rnro T. A Hawley (NV)lo X. E. tliar (NSP). FinalTTransmtutl or Assumptlins, LbI1USed for the Large and Small Break LOCA Antlyscs. Rev. I'. Julv 7. 1903. M 'onfirred by: Letter from K.
E. llipr MSP) o kMr.T. Hawky IVJ. 'Acceptance ofNSI' 93 -513. Rev. 1. Juhr 30. 1993.
19 . NSI'-04-3S. 'SuclearManagement IOCFR 50D46 Annual Notificatimn and Reporting for Connpany Prairiesland IInits I anid 210 2003. March 200.1 20 . WCAP.1620ti-P.-SATP ngincetring Report for Prairie bland. rvtxuary 2004.
21 NFrNMc-04.4-9. 'Nuclar NlanaSemcn Company Prairie IsLind Unit I Cycle 22 Final RSC:-April 200 2' . NSP.(t4 5. "Suikar MAnpgeln21C24 ny PairieIsland Untns I & 2 Sates AnalpisTransition l'rogra tcgromnvtn In CFR 50 46 Inhjuiry." April ' I.2tO 4.
Westinghouse LOCA Peak Clad Temperature Summary for SECY UPI large Break Plant Name: Prairie Island Unit I Utility Name: Nucicar Managcmcnt Company. LLC Revision Date: 7115/04 Notes:
(a) I'-bar-llA incrnsc t rrt 1.57 In I.59) tb) RcKnalvsis for all Gsld issues Iel R1rnalysi~fv Ioth issues (dj Rcltcd JCO in exissence (NS 034-Ojo;0 NMCcognizntofuncertainy aprlictsion and lM'rshcet catcgorization.
(CS Reennstitutimn for C)rk 21 recanted per Reference 11.
I) It is assuni d Oiut NMC is appl!inr the 0.36% SOrTlawtnce faJCt brancis of the S( UXt A I SSE issue MRcfentmv Ih!.
Thus the 25% SGT!P Study threm i 1 supports a net SCTP linsis of t24.64.
(g) Scnsi insStudy fIcEFQ 42.0. PAD 4.1)IMPkrIenta'ic. Restontion Of UISI to ReWesence Il sVahles.
SGiIAXIp A' Re.
tuning. Cce r^Ae Rest ation.
thl mie note tFi sensitivity study allows for the rrmovaI or the Reference 14 enrinerrin; assemsment.
ti ItermsA.10 and A.1 I prnscnted as aOMe- .66Fentryprior to Reference 22 eonspnsition.
Westinghouse LOCA Peak Clad Temperature Summary for SECY UPI Large Brcak Plant Name: Prairie Island Unit 2 Utilith Name: Nuclear Management Company. LLC Revision Yate: 7 /112/04 Analvsis Inrornation Ewd: SECY UI'l WCIT Analysis Date: 311195 LIrnitingBreakSize: Cd=0.4 FQ: 2.4 FdII: 1.77 Fuel: OFA SGTl(): IS Notes: Zidonm. SGTP Evaluated up to 24.14'6(see also Nutc el: Fq increased to 2.5 (item A.10 Clad Tentp ('F) Rer. Notes LICENSING BASIS Analysis-Or-Record PCT 2180 1' (a)
MARGIN ALLOCATIONS (Delta PCT)
A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS I . Fixed I lIat Traisfer Nodc Assignscnt EnurfAccumulawo Water Iv1tsTiron -175 3 EmittI995 Rerott) 2 . l-trtansinon Iloiling lcat TnnsfkrError v1997 Report) 59 5 3 v.oi-e OCnisul DX Error (1997 Rcp") .11 5 4 . Input C.mnistcncy (1997 RrpxwlU -06 5
- 5. No limis for 19)6, 1998 cTuYtS. 0 4.(.
( . Aecunulbmt trncflrcssurizc Surge Line DmtaIr Pnt specific 11'. 7 qth Acumututr Letl &kUin Volume I Plant spmifc Restart Enror:
Reanalysis (1999 Reprn) 7 . htlodcdiap Updates and Unhated Colductor Input Corrections Ipbnt .147 9.0 tel specifict ;2000 Report) 8 . Accumubtor Ptreare 41-30 psi Range (Plant Speciic.) (2001 Repont) 8 10.11 (d) 9 . WMSI Fnmr EAtuation (Nlan Specific) (2002 RIpt) 't0 121.3 (SI 10 . Seasitihil) Study for FQ=2.5. UISI Currection. cte. tas listed in note tVI -47 15.17.18 (..h t1'aus Spclinc) (2003 Rcprto I . Iimken loxp Notzkl Correction (Plant Specific) (H)03 Report) -19 2018 Ih)
B. PLANNED PLANT CHIANGE EVALUATIONS I .Sensitivity Studyft Sateam Gener tcr Tube Pluaang increasc to 25b 52 S 2 . Aeunulitor Water olumn t 25 N3Rante 12 10 3 . Aecunstibtor Prssure Extended lo41-55 psi Range 21 10
- 4. Cyckc22SATfrCoreAeagc llumup 17 19 C. 2004 PERMANENT ECCS MODEL ASSESSMENTS I . None 1)
D.TEMPORARY ECCS MODEL ISSUES*
I . None 0 E. OTHER I . ResvalofXrecenf e 5l2lElSlEo*Evaluation .30 15 fs'
Westinghouse LOCA leak Clad Temperatute Summary for SFCY UPI Large Break Plant Name: Prairic Island Unit 2 Utilitv Name: Nud ear Manaiement Company. LLC Revision Date: 7/11204 LICENSING BASIS PCT+ MARGIN ALLOCATIONS PCT= 1994
- htis iycinumtiirkd that uheoe teniporatry PCT aIllocatio~ns ichich address eurrent LOCA model issues not be ermsidceda with reslect to I0 'CFR50.46 reporting requirements.
Referenees:
I 't5NS.-r.0tt21. 'IdatcdUtP Lll LOC'A.Mallrch 2J. 1995.
2 . wV(CAP-IP119..Addcndun I. 'rir Island Units I and? WCOI3RAtfRAC Ocst Estim3te Un Larre Dreak LOCA Analysis bigineerin Report Addendum 1: tpdated Results,' Ctcemhcr 1996.
J NSI'.9h-202. Nothern SLttes l'owe tCompany ratirieIsland Units I and 210 CFR 5046 AnnuaI Noti fiation and Repning.' vbruaq 20. 199C.
4 NSI'.97.201.'NorthernStates PowcrConmasiy PrairkieIlnd Units I and2 10CFR50.46 AnnualNutireaticniand Reporxing. April 17. 1997.
5 . NSP-98-0?.'Nordmhen States power Company Prtirk Island tnits I and 2 10 CFR 50.46 Annual Notificatkn and Reporting for 1907n.Rbrnary 27.1993.
C . NSP.99-0 10. 'Northern Stats Power Company Prairie band I'nits I and2 10 CR 5(0.46 Annual Notification and Reporting for 199S.' April 29. 1999.
7 NSI'4W-.(Xj5. 'Northern Stales l'racr Company lrairie Island Units I and 2 10 CFR 50.46 Annual Notificraion and Reporting
'.f 199'7.' F-lruary 2000.
S . SP-0A4t57. 'Northern States PomcrCampanyftriric blatnd Units I and 2 LOCA Evaitation of 25 , SGm'I ith Other
%lMerling t;pdates Dekcember 11. 2000.
9 . NSP4-1 0K1t. 'Northern Staites Pwer Company Prairi Island Units I and 2 10 CFR 5046 Annual Notification and Repmrting f2r XN.'March 6. 2001.
In . NINP2-9. 'Nucklar Managecment Conpany Pratrie vIland units I and?2 LBLOCA Accumulator Pressureand Volume Raneset Evhluation.' Fetmriy 15. 202.
11 . NSP-02 5.'Nucekar Itanaremnent Company Prairie Island Units I and 2 10 CFR 50.46 AnnuAl No'tification and Rerwwting ror 21UOI.- March 2002.
12 . NS1'-02-59iLTR-ES12-194. 'final Eyaluaiut or Large liral LOCA Error.' DVmcmbec 2002.
13 . NSr.o *.19.'NuclearMana nwent Company Prairie bland Units I and 2 t0 CFR 50.46 Annual .oigfication and Reporting For 2002.' March 20X03.
14 NIM)2-TAH-US9J4 EI NSIOPIA-')2-5IS. 'NSPC Prairie Klind Units I and 2. St rubc Fkow Area Reduaion unJdc LOCA/
SSE - F'ina Re ort'. October 21, 1992.
- 15. NSP-04-lo Safly AnalysisTransition ogramTransmiitalof Enginecring Rcprtr' rcbrua20.2004 Ifi . NS P93-513. Rev IIET.NSL.OP1--93-313. Rev. 1.Lcttcr frmn T. A. Hawley 1W) to K. E Higar IMP). 'Minal Tranmittal or Assumptiont lobe used forthe Lrgeand SdmaIl Brcal LOCA Analyses. Rev. I'.July?7.193. Cm',firncd by: Letttrr(rnm t.
E tligtar(NSP) to Mr.T. Ilawley(Wi. 'Acccptance o(NSP 93 513, RCv. I'.July 30. I993.
It . NSP-04.3s. 'Nucekar Management Company Prairie Island Units I and 2 10 tl:R 50.46 Annual Notification and Repwing for 200t. MIrch 2004.
IS. WCAP.16206-P. 'SATP Engineering Report r Prairke blanI.' Ftbrury 2004.
- 19. Nr-NMCA 4-50. 'Nucklar tanageunDt Company Prairi kbnd Unit 2 Cyc 2 Final RSE' April 2004 20 NSP-0445. 'Nuclear Managcment Company Prairie Island Units I & 2 Safely Analysis Transition Program Rerseonse to It (t-R 50.46 Inquiry.' April 21. 2004.
Notes:
(a) I'-bar-HA increased from 1.57 to 1.59 01 Reanatlysis Forall bsted issues tel Retanalysis rf.. lh h issues
Westinghouse LOCA Peak- Clad Temperature Summary for SECY' UPI Large Break Plant Name: Prairie Island Unit 2 Utility Name: Nuclear Managemenz Company, LLC Revision Date: 7112104 Id) RclAtcd IC' in ceistencc INSr-Ol-O030.NMC cXInin7nt of uncertaintyapplicaolin and lCT shmt c-aitcalicon.
(c) It is assunled that NMC is aI'Vbin; Vtc0.36 SCf'allowance factm I'rnch f lhc SU LOCA I SSE imute 1{KccremL-e 14).
"hus the 251 S l]' Study (item Bl.) supprits a nt SCI.' irnit of 24N'A.
tfJ Sensitivity Study for FQ,2.50. I'AD 4.0 Implemctnation. Restoration of UISI to Refrencc 16 values, sCn V. Re.
tuning. Cme rtmr Restoation-r.) Mhy ntcwe (0 sensitihity study atIkO for the rctnoil of the Reftrence 12 engiDccrinCassc1ssentL (h) Items A.lh ;tnd A.l I prcercntcd as aygrerptc -6 IFcntry prior to Rcfrcntv 20 doenmpusition.
Westinghouse Proprietary Class 2 Attachment 2 - PCT Sheets Page 5 of 10 Our ref: NSP-04-38 March 16,2004 Westingbotuse LOCA Peak Clad Temperature Summary for Small Break Plant Name: Prairie Island Unit I Utility Nttfne: Nuclear Management Company, LLC Revision Date: 3/3/04 Analysis Inrormation EM: NOTRUMP Analysis Date: 9/1/00 LinmtingBreakSize: 3 inch FQ: 2.8 Fdll: 2 Fuel: OFA SGT (%): 25 Notes: Zirlnom(14X14)
Clad Temp (0F) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1142 1 (a)
MARGIN ALLOCATIONS (Delta PCI)
A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS I . No Items for 2000, 2001 & 2002 Reports 0 2,6.7 B. PLANNED PLANT CHANGE EVALUATIONS I .5 Reconstituted Rods Evaluation N/A o 3,4 (b)
C. 2003 PERMANENT ECCS MODEL ASSESSMENTS I NOTRUMP Bubble Rise / Drift Flux Model Inconsistency Corrections 35 8 D. TEMPORARY ECCS MODEL ISSUES*
I .None 0 E. OTHER I Evaluation for Reduced Auxilary Feedwater Flow Rate o 5 LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT = 1177 eIt is recommended that these temporary PCT allocations which address current LOCA model issues not be considered with respect to 10 CFR 50.46 reporting requirements.
References:
I . NSP-O0-045, "SBLOCA Re-analysis with Revised NOTRUMP Code,' October 2,2000.
2 . NSP-O-006, 'Northem States PowerCompany Prairie Island Units I and 2 10 CFR 50.46 Annual Notification and Reporting for 2000,' March 6,2001.
3 . 0ONS--0076/CAB-0-390, Prairie Island Unit I Cycle 21 LOCA Reload Confirmation and FCEP Checklist,' December 15,2000.
4 . Rothrock (NMC) to Swigat (W), 'Prairie Island Unit I LOCA PCTr'. May 30,2001.
5 . NSP.02-36, SBLOCA Limited FSAR Update and Evaluation for Revised Auxilary Feedwater Flow Rate,' October 2002.
6 NSP-02-5, 'Nuclear Management Company Prairie Island Units I and 2 10 CFR 50.46 Annual Notification and Reporting for 2001,' March2002.
7 . NSP.03-19, 'Nuclear Management Company Prairie Island Units I and 2 10 CFR 50.46 Annual Notification and Reporting for 2002,' March 2003.
8 . NSP.03-68, '10 CFR 50.46 Mid-Year Notification and Reporting for 2003,' November 2003.
Notes:
(a) Accumulator water volume sensitivity of+/-30 cubic feet included.
(b) Reconstitution for Cycle 21, recanted per Reference 4.
A BNFL Group company
Westinghouse Proprietary Class 2 Attachment 2 - PCT Sheets Page lOof 10 Our ref: NSP-04-38 March 16,2004 Westinghouse LOCA Peak Clad Temperature Summary for Small Break Plant Name: Prairie Island Unit 2 Utility Name: Nuclear Management Company, LLC Revision Date: 3 /3/04 Analysis Information EM: NOTRUMP Analysis Date: 911/00 LimitingBreakSize: 3inch FQ: 2.8 Fdll: 2 Fuel: OFA SGTP (%): 25 Notes: Zirlo1l (14X14)
Clad Temp (OjF) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1142 1 (a)
MARGIN ALLOCATIONS (Delta PCI)
A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS I . No Iems for 2000,2001 & 2002 Reports 0 2.4,5 B. PLANNED PLANT CHANGE EVALUATIONS I . None 0 C. 2003 PERMANENT ECCS MODEL ASSESSMENTS I . NOTRUMP Bubble Rise/Drif Flux Model Inconsistency Corrections 35 6 D. TEMPORARY ECCS MODEL ISSUES*
I . None 0 E. OTHER I . Evaluation for Reduced Auxilary Feedwater Flow Rate 0 3 LICENSING BASIS PCT + MARGIN ALLOCATIONS PCTI= 1177 0 It is recommended that these temporary PCr allocations which address current LOCA model issues not be considered with respect to 10 CFR 50.46 reporting requirements.
References:
I NSP-00045. SBLOCA Re-analysis with Revised NOTRUMP Code," October 2,2000.
2 . NSP-01-006, Northern States Power Company Prairie Island Units I and 2 10 CFR 50.46 Annual Notification and Reporting for 2000. March 6,2001.
3 . NSP.02-36. "SBLOCA Limited FSAR Update and Evaluation for Revised Auxilary Feedwater Flow Rate. October 2002.
4 . NSP-02-5, Nuclear Management Company Prairie Island Units I and 2 10 CFR 50.46 Annual Notification and Reporting for 2001." March2002.
5 . NSP-03.19, Nuclear Management Company Prairie Island Units I and 2 10 CFR 50.46 Annual Notification and Reporting for 2002." March 2003.
6 . NSP-0386.'10 CFR 50.46 Mid-Year Notification and Reporting for2003," November2003.
Notes:
(a) Accumulator water volume sensitivity of +/.-30 cubic fee included A BNFL Group company