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| | issue date = 03/04/1998 | | | issue date = 03/04/1998 |
| | title = Forwards Summary of Results of Any Change to or Error Discovered in Evaluation Models for Eccs,Or Application of Such Models,That Affect Fuel Cladding Temp Calculation.Info Submitted Per 10CFR50.46(a)(3)(ii) | | | title = Forwards Summary of Results of Any Change to or Error Discovered in Evaluation Models for Eccs,Or Application of Such Models,That Affect Fuel Cladding Temp Calculation.Info Submitted Per 10CFR50.46(a)(3)(ii) |
| | author name = STALL J A | | | author name = Stall J |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:CATEGORY1REGULATYINFORMATION DISTRIBUTIO SYSTEM(RIDS)P''ACCESSION NB/:9803100326 DOC.DATE: | | {{#Wiki_filter:CATEGORY 1 REGULAT Y INFORMATION DISTRIBUTIO SYSTEM (RIDS) |
| 98/03/04NOTARIZED: | | P |
| NO'FACIL:50-335 St.LuciePlant,Unit1,FloridaPower6LightCo."50-389St.LuciePlant,Unit2,Florida'ower SLightCo.AUTH.NAMEAUTHORAFFILIATION STALL,J.A.
| | '' ACCESSION NB/:9803100326 DOC.DATE: 98/03/04 NOTARIZED: NO DOCKET ¹ |
| FloridaPowerSLightCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET¹0500033505000389
| | 'FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power 6 Light Co. 05000335 "50-389 St. Lucie Plant, Unit 2, Florida'ower S Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION STALL,J.A. Florida Power S Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Forwardssummaryofresultsofanychangetoorerrordiscovered inevaluation modelsforECCS,orapplication ofsuchmodels,thataffectfuelcladdingtempcalculation.
| | Forwards summary of results of any change to or error discovered in evaluation models for ECCS,or application of such models, that affect fuel cladding temp calculation. Info A submitted per 10CFR50.46(a)(3)(ii). |
| Infosubmitted per10CFR50.46(a)(3)(ii).
| | DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: |
| DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: | | TITLE: OR Submittal: General Distribution E NOTES: |
| GeneralDistribution NOTES:AERECIPIENT IDCODE/NAME PD2-3LAGLEAVES,W COPIESLTTRENCL1111RECIPIENT IDCODE/NAME PD2-3PDCOPIESLTTRENCL11RINTERNAL:
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 LA 1 1 PD2-3 PD 1 1 R GLEAVES,W 1 1 INTERNAL: ACRS 1 1 FI E CE 1 1 NRR/DE/ECGB/A 1 1 NRR DE EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL:.'NOAC 1 1 NRC PDR 1 1 D |
| ACRSNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS31111111110FIECENRRDEEMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT 11111111EXTERNAL:.'NOAC 11NRCPDR11DENOTETOALL"RIDS"RECIPIENTS:
| | E NOTE TO ALL "RIDS" RECIPIENTS: |
| PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
| | PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13 |
| LTTR14ENCL13 FloridaPower5LightCompany,6351S.OceanDrive,JensenBeach,FL34957FPLMarch4,1998L-98-057'0 CFR50.46U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, DC20555Re:St.LucieUnits1and2DocketNos.50-335and50-389Acceptance CriteriaforEmergency CoreCoolingSystemsforLightWaterNuclearPowerReactors:
| |
| 10CFR50.46AnnualReortPursuantto10CFR50.46(a)(3)(ii),
| |
| thenatureofanychangetoorerrordiscovered intheevaluation modelsforEmergency CoreCoolingSystems(ECCS),orintheapplication ofsuchmodels,thataffectthefuelcladdingtemperature calculations forSt.LucieUnits1and2isreportedintheattachment tothisletter.Theestimated eFectfromanysuchchangeorerroronthelimitingECCSanalysisforeachunitisalsoaddressed.
| |
| ThedataintervalforthereportisfromJanuary1throughDecember31,1997.Shouldtherebeanyquestions, pleasecontactus.Verytrulyyours,J.A.StallVicePresident St.LuciePlantJAS/RLDAttachment cc:RegionalAdministrator, RegionII,USNRCSeniorResidentInspector, USNRC,St.LuciePlant9803'i0032 05000335PDRADQCKPDRPlllllllllilllllllllllllllllllllllllllll anFPLGroupcompany St.LucieUnits1and2DocketNos.50-335and50-38910CFR50.46AnnualReortL-98-057ATTACHMENT Page1of3Emergency corecoolingsystem(ECCS)analysesforSt.LucieUnit1andSt.LucieUnit2areperformed bySiemensPowerCorporation (SPC)andAseaBrownBoveri-Combustion Engineering (ABB-CE),
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| respectively.
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| Thefollowing information pertaining totheevaluation modelsforsmallbreaklossofcoolantaccidents (SBLOCA)andlargebreaklossofcoolantaccidents (LBLOCA),
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| andtheapplication ofsuchmodelstoeachSt.Lucieunit,isprovidedpursuantto10CFR50.46(a)(3)(ii).
| |
| Asummaryofcalculated peakcladdingtemperature (PCT)changesisprovidedinTable1.ThedataintervalforthisreportisfromJanuary1throughDecember31,1997.1.ST.LUCIEUNIT1SBLOCA:Achangewasmadetotheevaluation modelassumptions involving highpressuresafetyinjection (HPSI)flowasymmetry.
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| Re-evaluation ofSBLOCAusingtherevisedHPSIflowasymmetry identified anewlimitingbreaksizeof0.05ft~,andresultedinaPCTincreaseof149'F(previously reportedinReference 3.1).Thecalculated PCTforthelimitingSBLOCAis1953'F.LBLOCA:AZ-equivalent modeldiscrepancy, whichwasreportedinthe1996AnnualReport(Reference 3.2),wascorrected andexplicitly evaluated fortheUnit1LBLOCAanalysisofrecord.Theimpact&omthiserrorhadbeenconservatively estimated asamaximumPCTincreaseof15'F.Following correction ofthediscrepancy, theactualchangeincalculated PCTis-1.0'F.Theevaluation modelwasalsoupdatedtoconservatively usetheminimumcontainment sprayandfancoolerinitiation time.Thischangeresultedina14'FPCTincrease.
| |
| Thecombination ofrevisions totheZ-equivalent modelandtheminimumcontainment sprayandfancoolerinitiation timeyieldsacalculated PCTof2040'FforthelimitingLBLOCA.SPCalsoidentified avariability inRELAP-4coderesultsthatmayaffectthepe'akcladdingtemperature calculated inLBLOCAanalyses.
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| Thevariability ischaracterized asalargechangeinthecodeoutputresultthatisproducedbysmallchangesinthecodeinput,andforwhichsignificantly largechangesshouldnotbeexpectedwhenconsidering physicalbehavior.
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| SPCisassessing thecause(s)andimpactofthisdeviation (Reference 3.3).Apreliminary assessment indicates thattheeffectoncalculated PCTisnotsignificant andthattheSt.LucieUnit1LBLOCAanalysisofrecordremainsincompliance withacceptance criteriaof10CFR50.46.Corrective actionshavenotbeenfinalized andquantified resultsarenotexpectedtobeavailable untillaterin1998.
| |
| St.LucieUnits1and2DocketNos.50-335and50-38910CFR50.46AnnualReortL-98-057ATTACHMENT Page2of32.ST.LUCIEUNIT2General:TheECCSperformance analysiscomputercodesforSBLOCAandLBLOCAwereconverted foruseonHewlettPackard(HP)workstations oper'ating undertheHP/UXoperating system.Thecodeswerepreviously usedwithHPApolloworkstations undertheDomainoperating system,andtheoverallimpactoftheconversion isestimated tohavenoeffectonthecalculated PCT(totheprecision ofprintedresults,i.e.,lessthan.01'F).Inadditiontothecomputerplatformchange,anoptionwasaddedtotheSBLOCAmethodswhichautomates thetransferofdata(coreboundaryconditions) betweentheCEFLASH-4AS blowdownhydraulics computercodeandthePARCHhotrodheatupcode.Previously, thisdatatransferwasperformed manually.
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| Theautomated processprovidesamoreaccurateandeAicientmethodoftransferring thedata,andtheeffectontheECCSperformance analysisforSBLOCAisestimated tobeareduction incalculated PCTofapproximately 4'F.ThelimitingECCSanalysesofrecordhavenotbeenperformed withthechangesdescribed above.SBLOCA:NoerrorswerefoundintheSBLOCAanalysisforthisreporting period.Thepeakcladdingtemperature fortheanalysisofrecordremainsat1915'F.LBLOCA:Anerrorwasdiscovered andcorrected inthedecayheatenergyredistribution factor(ERF)usedintheECCSperformance evaluation modelforLBLOCA.Theimpactoncalculated peakcladdingtemperature wasconservatively estimated andpreviously reportedinReference 3.4.Correcting theERFerrorresultedina28'Fincrease, andthelimitingECCSanalysisPCTis2171'F.3.REFERENCES 1.FPLLetterL-97-313, J.A.StalltoUSNRC(DCD),"ErrorintheApplication ofSBLOCAEvaluation Model;30Day,10CFR50.46Report:"December17,1997.2.FPLLetterL-97-034, J.A.StalltoUSNRC(DCD),"Acceptance CriteriaforEmergency CoreCoolingSystemsforLightWaterNuclearPowerReactors:
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| 10CFR50.46AnnualReport:"March6,1997.3.SPCLetterNRC:98:001, J.S.HolmtoUSNRC,"InterimReportofEvaluation ofaDeviation Pursuantto10CFR21.21(a)(2):"
| |
| January15,1998.4.FPLLetterL-97-205, J.A.StalltoUSNRC(DCD),"ErrorintheUseofLBLOCAEvaluation Model;30Day10CFR50.46Report:"August8,1997.
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| St.LucieUnits1and2DocketNos.50-335and50-38910FR5046AnnualReortL-98-057ATTACHMENT Page3of3TableISt.LucieUnits1and21997SBLOCAandLBLOCAPCTSummaryUnit1SBLOCASumma199610CFR50.46AnnualReortnote1Chanedueto30% | | Florida Power 5 Light Company, 6351 S. Ocean Drive, Jensen Beach, FL34957 March 4, 1998 FPL L-98-057'0 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors: |
| SGtubeluinanalsisnote2ChaneduetorevisedHPSIflowasmmet199710CFR50.46AnnualReortPCT1765'F+39'F+149'F1953'FUnit1LBLOCASumma199610CFR50.46AnnualReortZ-euivalenterrorenaltestimated maximumimactonPCT+15'FChanefollowincorrection ofZ-euivalenterrorChaneduetorevisedcontainment sraandfancoolerminimumdelatime199710CFR50.46AnnualReort2027'F-1'F+14'F2040'FUnit2SBLOCASumma199610CFR50.46AnnualReortChanedurin1997199710CFR50.46AnnualReortPCT1915'F0'F1915'FUnit2LBLOCASumma199610CFR50.46AnnualReortERFerrorenaltestimated maximumimactonPCT+30'FChanefollowincorrection ofERFerror199710CFR50.46AnnualReortPCT2143'F+28'F2171'FNotes:(1)Calculated peakcladdingtcmpcraturc isforstcamgenerator (SG)tubeplugginglevelof25%.(2)Analysiswasperformed in1996,butdidnotbccomcanalysisofrecorduntilissuanceofAmendmcnt No.151(5/16/97) tothcfacilityoperating license.Thcvalueisincludedinthistabletoidentifycomponents contributing tothccumulative impacton1997PCTofrecord.}}
| | 10 CFR 50.46 Annual Re ort Pursuant to 10 CFR 50.46(a)(3)(ii), the nature of any change to or error discovered in the evaluation models for Emergency Core Cooling Systems (ECCS), or in the application of such models, that affect the fuel cladding temperature calculations for St. Lucie Units 1 and 2 is reported in the attachment to this letter. The estimated eFect from any such change or error on the limiting ECCS analysis for each unit is also addressed. The data interval for the report is from January 1 through December 31, 1997. |
| | Should there be any questions, please contact us. |
| | Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/RLD Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant 9803'i0032 05000335 PDR ADQCK PDR P |
| | lllllllllilllllllllllllllllllllllllllll an FPL Group company |
| | |
| | St. Lucie Units 1 and 2 L-98-057 Docket Nos. 50-335 and 50-389 ATTACHMENT 10 CFR 50.46 Annual Re ort Page 1 of 3 Emergency core cooling system (ECCS) analyses for St. Lucie Unit 1 and St. Lucie Unit 2 are performed by Siemens Power Corporation (SPC) and Asea Brown Boveri-Combustion Engineering (ABB-CE), respectively. The following information pertaining to the evaluation models for small break loss of coolant accidents (SBLOCA) and large break loss of coolant accidents (LBLOCA), and the application of such models to each St. Lucie unit, is provided pursuant to 10 CFR 50.46(a)(3)(ii). |
| | A summary of calculated peak cladding temperature (PCT) changes is provided in Table 1. The data interval for this report is from January 1 through December 31, 1997. |
| | : 1. ST. LUCIE UNIT 1 SBLOCA: A change was made to the evaluation model assumptions involving high pressure safety injection (HPSI) flow asymmetry. Re-evaluation of SBLOCA using the revised HPSI flow asymmetry identified a new limiting break size of 0.05 ft~, and resulted in a PCT increase of 149 'F (previously reported in Reference 3.1). The calculated PCT for the limiting SBLOCA is 1953 'F. |
| | LBLOCA: A Z-equivalent model discrepancy, which was reported in the 1996 Annual Report (Reference 3.2), was corrected and explicitly evaluated for the Unit 1 LBLOCAanalysis of record. |
| | The impact &om this error had been conservatively estimated as a maximum PCT increase of 15 'F. |
| | Following correction of the discrepancy, the actual change in calculated PCT is -1.0 'F. The evaluation model was also updated to conservatively use the minimum containment spray and fan cooler initiation time. This change resulted in a 14 'F PCT increase. The combination of revisions to the Z-equivalent model and the minimum containment spray and fan cooler initiation time yields a calculated PCT of 2040 'F for the limiting LBLOCA. |
| | SPC also identified a variability in RELAP-4 code results that may affect the pe'ak cladding temperature calculated in LBLOCAanalyses. The variability is characterized as a large change in the code output result that is produced by small changes in the code input, and for which significantly large changes should not be expected when considering physical behavior. SPC is assessing the cause(s) and impact of this deviation (Reference 3.3). A preliminary assessment indicates that the effect on calculated PCT is not significant and that the St. Lucie Unit 1 LBLOCA analysis of record remains in compliance with acceptance criteria of 10 CFR 50.46. Corrective actions have not been finalized and quantified results are not expected to be available until later in 1998. |
| | |
| | St. Lucie Units 1 and 2 L-98-057 Docket Nos. 50-335 and 50-389 ATTACHMENT 10 CFR 50.46 Annual Re ort Page 2 of 3 |
| | : 2. ST. LUCIE UNIT 2 General: The ECCS performance analysis computer codes for SBLOCA and LBLOCA were converted for use on Hewlett Packard (HP) workstations oper'ating under the HP/UX operating system. The codes were previously used with HP Apollo workstations under the Domain operating system, and the overall impact of the conversion is estimated to have no effect on the calculated PCT (to the precision of printed results, i.e., less than .01 'F). In addition to the computer platform change, an option was added to the SBLOCA methods which automates the transfer of data (core boundary conditions) between the CEFLASH-4AS blowdown hydraulics computer code and the PARCH hot rod heatup code. Previously, this data transfer was performed manually. The automated process provides a more accurate and eAicient method of transferring the data, and the effect on the ECCS performance analysis for SBLOCA is estimated to be a reduction in calculated PCT of approximately 4 'F. The limiting ECCS analyses of record have not been performed with the changes described above. |
| | SBLOCA: No errors were found in the SBLOCA analysis for this reporting period. The peak cladding temperature for the analysis of record remains at 1915 'F. |
| | LBLOCA: An error was discovered and corrected in the decay heat energy redistribution factor (ERF) used in the ECCS performance evaluation model for LBLOCA. The impact on calculated peak cladding temperature was conservatively estimated and previously reported in Reference 3.4. |
| | Correcting the ERF error resulted in a 28 'F increase, and the limiting ECCS analysis PCT is 2171 'F. |
| | : 3. REFERENCES |
| | : 1. FPL Letter L-97-313, J.A. Stall to USNRC (DCD), "Error in the Application of SBLOCA Evaluation Model; 30 Day, 10 CFR 50.46 Report:" December 17, 1997. |
| | : 2. FPL Letter L-97-034, J.A. Stall to USNRC (DCD), "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors: 10 CFR 50.46 Annual Report:" |
| | March 6, 1997. |
| | : 3. SPC Letter NRC:98:001, J.S. Holm to USNRC, "Interim Report of Evaluation of a Deviation Pursuant to 10 CFR 21.21(a)(2):" January 15, 1998. |
| | : 4. FPL Letter L-97-205, J.A. Stall to USNRC (DCD), "Error in the Use of LBLOCAEvaluation Model; 30 Day 10 CFR 50.46 Report:" August 8, 1997. |
| | |
| | St. Lucie Units 1 and 2 L-98-057 Docket Nos. 50-335 and 50-389 ATTACHMENT 10 FR 50 46 Annual Re ort Page3 of 3 Table I St. Lucie Units 1 and 2 1997 SBLOCA and LBLOCAPCT Summary Unit 1 SBLOCA Summa PCT 1996 10 CFR 50.46 Annual Re ort note 1 1765 'F Chan edueto30% SGtube lu in anal sis note2 +39 'F Chan e due to revised HPSI flow as mmet +149 'F 1997 10 CFR 50.46 Annual Re ort 1953 'F Unit 1 LBLOCA Summa 1996 10 CFR 50.46 Annual Re ort 2027 'F Z-e uivalent error enalt estimated maximum im act on PCT +15 'F Chan e followin correction of Z-e uivalent error -1 'F Chan e due to revised containment s ra and fan cooler minimum dela time +14 'F 1997 10 CFR 50.46 Annual Re ort 2040 'F Unit 2 SBLOCA Summa PCT 1996 10 CFR 50.46 Annual Re ort 1915 'F Chan e durin 1997 0'F 1997 10 CFR 50.46 Annual Re ort 1915 'F Unit 2 LBLOCA Summa PCT 1996 10 CFR 50.46 Annual Re ort 2143 'F ERF error enalt estimated maximum im act on PCT +30 'F Chan e followin correction of ERF error +28 'F 1997 10 CFR 50.46 Annual Re ort 2171 'F Notes: (1) Calculated peak cladding tcmpcraturc is for stcam generator (SG) tube plugging level of 25%. |
| | (2) Analysis was performed in 1996, but did not bccomc analysis of record until issuance of Amendmcnt No. 151 (5/16/97) to thc facility operating license. Thc value is included in this table to identify components contributing to thc cumulative impact on 1997 PCT of record.}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17241A5001999-10-21021 October 1999
Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C
ML17309A9981999-10-19019 October 1999
Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points
ML20217F6171999-10-0808 October 1999
Forwards Insp Repts 50-335/99-11 & 50-389/99-11 on 990827 & 990907-09.No Violations Identified.Matl Encl Contained Safeguards Info as Defined by 10CFR73.21 & Disclosed to Unauthorized Individuals Prohibited by Section 147 of AEA
ML17241A4811999-10-0101 October 1999
Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a
ML20212M1601999-09-28028 September 1999
Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl
ML17241A4701999-09-25025 September 1999
Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant
ML17241A4721999-09-24024 September 1999
Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999
ML17241A4681999-09-22022 September 1999
Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17241A4671999-09-20020 September 1999
Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams.
ML17241A4581999-09-13013 September 1999
Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program
ML17241A4531999-08-31031 August 1999
Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006
ML17241A4521999-08-31031 August 1999
Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval
ML17241A4501999-08-26026 August 1999
Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached
ML17241A4371999-08-13013 August 1999
Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d)
ML17241A4461999-08-11011 August 1999
Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure
L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999
Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)
ML17309A9911999-07-26026 July 1999
Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified
ML17241A4471999-07-22022 July 1999
Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure
ML17241A4221999-07-22022 July 1999
Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates.
ML17241A4151999-07-22022 July 1999
Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2
ML17241A4101999-07-16016 July 1999
Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants
ML17309A9881999-07-0707 July 1999
Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager
ML20209F1541999-07-0606 July 1999
Informs That NRC in Process of Conducting Operational Safeguards Response Evaluations at Nuclear Power Reactors. Plant Chosen for Such Review Scheduled for Wk of 990823-26
ML17241A4011999-06-30030 June 1999
Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604
ML17241A3971999-06-30030 June 1999
Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr
ML17355A3661999-06-30030 June 1999
Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998
ML17241A3951999-06-29029 June 1999
Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl
ML17241A3731999-06-17017 June 1999
Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16)
ML17241A3641999-06-14014 June 1999
Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139
ML20195F3871999-06-11011 June 1999
Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)
IA-99-247, Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)1999-06-11011 June 1999
Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)
L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999
Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)
ML17241A3561999-06-0707 June 1999
Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209
ML17241A3601999-06-0707 June 1999
Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998
ML20195F3941999-05-27027 May 1999
FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR
ML17241A3461999-05-24024 May 1999
Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage
ML17241A3391999-05-20020 May 1999
Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F
ML17241A3371999-05-20020 May 1999
Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225
ML20207C7531999-05-17017 May 1999
Discusses Issue Identified by FPL in Feb 1998 Involving Potential for Fire to Cause Breach of Rc Sys High/Low Pressure Interface Boundary & NRC Decision for Exercise of Enforcement Discretion
ML17241A3301999-05-17017 May 1999
Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted
ML17309A9821999-05-10010 May 1999
Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl
IR 05000335/19980141999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
ML17241A3221999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
ML17229B1071999-04-28028 April 1999
Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120
ML17229B1051999-04-22022 April 1999
Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices
ML17229B1061999-04-21021 April 1999
Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17309A9851999-04-15015 April 1999
Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick
ML20205M0431999-04-13013 April 1999
Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR
ML17229B0951999-04-0808 April 1999
Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program
ML17229B0821999-04-0707 April 1999
Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl
1999-09-28
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17241A5001999-10-21021 October 1999
Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C
ML17309A9981999-10-19019 October 1999
Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points
ML17241A4811999-10-0101 October 1999
Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a
ML17241A4701999-09-25025 September 1999
Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant
ML17241A4721999-09-24024 September 1999
Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999
ML17241A4681999-09-22022 September 1999
Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17241A4671999-09-20020 September 1999
Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams.
ML17241A4581999-09-13013 September 1999
Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program
ML17241A4531999-08-31031 August 1999
Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006
ML17241A4521999-08-31031 August 1999
Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval
ML17241A4501999-08-26026 August 1999
Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached
ML17241A4371999-08-13013 August 1999
Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d)
ML17241A4461999-08-11011 August 1999
Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure
L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999
Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)
ML17309A9911999-07-26026 July 1999
Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified
ML17241A4221999-07-22022 July 1999
Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates.
ML17241A4471999-07-22022 July 1999
Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure
ML17241A4151999-07-22022 July 1999
Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2
ML17241A4101999-07-16016 July 1999
Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants
ML17309A9881999-07-0707 July 1999
Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager
ML17241A4011999-06-30030 June 1999
Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604
ML17241A3971999-06-30030 June 1999
Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr
ML17355A3661999-06-30030 June 1999
Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998
ML17241A3951999-06-29029 June 1999
Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl
ML17241A3731999-06-17017 June 1999
Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16)
ML17241A3641999-06-14014 June 1999
Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139
L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999
Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)
ML17241A3601999-06-0707 June 1999
Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998
ML17241A3561999-06-0707 June 1999
Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209
ML20195F3941999-05-27027 May 1999
FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR
ML17241A3461999-05-24024 May 1999
Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage
ML17241A3371999-05-20020 May 1999
Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225
ML17241A3391999-05-20020 May 1999
Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F
ML17241A3301999-05-17017 May 1999
Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted
ML17309A9821999-05-10010 May 1999
Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl
ML17241A3221999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
IR 05000335/19980141999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
ML17229B1071999-04-28028 April 1999
Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120
ML17229B1051999-04-22022 April 1999
Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices
ML17229B1061999-04-21021 April 1999
Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17309A9851999-04-15015 April 1999
Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick
ML17229B0951999-04-0808 April 1999
Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program
ML17229B0821999-04-0707 April 1999
Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl
ML17229B0851999-04-0505 April 1999
Requests Approval of Encl Relief Request 25 Which Proposes to Use Alternative Requirements of ASME Code Case N-613 in Lieu of Requirements of ASME Section XI Figures IWB-2500-7(a) & IWB-2500-7(b).Action Requested by Aug 1999
ML17309A9791999-03-31031 March 1999
Forwards Revised EPIPs Including Rev 2 to EPIP-00,rev 2 to EPIP-09,rev 2 to EPIP-10 & Rev 10 to HP-207.Summary of Revs Listed
ML17309A9761999-03-23023 March 1999
Forwards Revised Epips,Including Rev 4 to EPIP-03, Er Organization Notification/Staff Augmentation, Rev 3 to EPIP-05, Activation & Operation of OSC & Rev 14 to HP-200, HP Emergency Organization. Changes to Epips,Discussed
ML17229B0691999-03-19019 March 1999
Transmits TS Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity,Per Soluble Boron Credit
ML17229B0721999-03-16016 March 1999
Requests Approval of Enclosed Relief Requests 23 & 24 Re ISI Plan for Second ten-year Interval.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage
ML17355A2631999-03-12012 March 1999
Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit
ML17229B0481999-03-10010 March 1999
Informs That Util Delivered Matls Requested in Encl 1 of NRC Ltr by Hand on 990308,as Requested by NRC Ltr Dtd 990218
1999-09-25
[Table view] |
Text
CATEGORY 1 REGULAT Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)
P
ACCESSION NB/:9803100326 DOC.DATE: 98/03/04 NOTARIZED: NO DOCKET ¹
'FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power 6 Light Co. 05000335 "50-389 St. Lucie Plant, Unit 2, Florida'ower S Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION STALL,J.A. Florida Power S Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards summary of results of any change to or error discovered in evaluation models for ECCS,or application of such models, that affect fuel cladding temp calculation. Info A submitted per 10CFR50.46(a)(3)(ii).
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution E NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 LA 1 1 PD2-3 PD 1 1 R GLEAVES,W 1 1 INTERNAL: ACRS 1 1 FI E CE 1 1 NRR/DE/ECGB/A 1 1 NRR DE EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL:.'NOAC 1 1 NRC PDR 1 1 D
E NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13
Florida Power 5 Light Company, 6351 S. Ocean Drive, Jensen Beach, FL34957 March 4, 1998 FPL L-98-057'0 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors:
10 CFR 50.46 Annual Re ort Pursuant to 10 CFR 50.46(a)(3)(ii), the nature of any change to or error discovered in the evaluation models for Emergency Core Cooling Systems (ECCS), or in the application of such models, that affect the fuel cladding temperature calculations for St. Lucie Units 1 and 2 is reported in the attachment to this letter. The estimated eFect from any such change or error on the limiting ECCS analysis for each unit is also addressed. The data interval for the report is from January 1 through December 31, 1997.
Should there be any questions, please contact us.
Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/RLD Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant 9803'i0032 05000335 PDR ADQCK PDR P
lllllllllilllllllllllllllllllllllllllll an FPL Group company
St. Lucie Units 1 and 2 L-98-057 Docket Nos. 50-335 and 50-389 ATTACHMENT 10 CFR 50.46 Annual Re ort Page 1 of 3 Emergency core cooling system (ECCS) analyses for St. Lucie Unit 1 and St. Lucie Unit 2 are performed by Siemens Power Corporation (SPC) and Asea Brown Boveri-Combustion Engineering (ABB-CE), respectively. The following information pertaining to the evaluation models for small break loss of coolant accidents (SBLOCA) and large break loss of coolant accidents (LBLOCA), and the application of such models to each St. Lucie unit, is provided pursuant to 10 CFR 50.46(a)(3)(ii).
A summary of calculated peak cladding temperature (PCT) changes is provided in Table 1. The data interval for this report is from January 1 through December 31, 1997.
- 1. ST. LUCIE UNIT 1 SBLOCA: A change was made to the evaluation model assumptions involving high pressure safety injection (HPSI) flow asymmetry. Re-evaluation of SBLOCA using the revised HPSI flow asymmetry identified a new limiting break size of 0.05 ft~, and resulted in a PCT increase of 149 'F (previously reported in Reference 3.1). The calculated PCT for the limiting SBLOCA is 1953 'F.
LBLOCA: A Z-equivalent model discrepancy, which was reported in the 1996 Annual Report (Reference 3.2), was corrected and explicitly evaluated for the Unit 1 LBLOCAanalysis of record.
The impact &om this error had been conservatively estimated as a maximum PCT increase of 15 'F.
Following correction of the discrepancy, the actual change in calculated PCT is -1.0 'F. The evaluation model was also updated to conservatively use the minimum containment spray and fan cooler initiation time. This change resulted in a 14 'F PCT increase. The combination of revisions to the Z-equivalent model and the minimum containment spray and fan cooler initiation time yields a calculated PCT of 2040 'F for the limiting LBLOCA.
SPC also identified a variability in RELAP-4 code results that may affect the pe'ak cladding temperature calculated in LBLOCAanalyses. The variability is characterized as a large change in the code output result that is produced by small changes in the code input, and for which significantly large changes should not be expected when considering physical behavior. SPC is assessing the cause(s) and impact of this deviation (Reference 3.3). A preliminary assessment indicates that the effect on calculated PCT is not significant and that the St. Lucie Unit 1 LBLOCA analysis of record remains in compliance with acceptance criteria of 10 CFR 50.46. Corrective actions have not been finalized and quantified results are not expected to be available until later in 1998.
St. Lucie Units 1 and 2 L-98-057 Docket Nos. 50-335 and 50-389 ATTACHMENT 10 CFR 50.46 Annual Re ort Page 2 of 3
- 2. ST. LUCIE UNIT 2 General: The ECCS performance analysis computer codes for SBLOCA and LBLOCA were converted for use on Hewlett Packard (HP) workstations oper'ating under the HP/UX operating system. The codes were previously used with HP Apollo workstations under the Domain operating system, and the overall impact of the conversion is estimated to have no effect on the calculated PCT (to the precision of printed results, i.e., less than .01 'F). In addition to the computer platform change, an option was added to the SBLOCA methods which automates the transfer of data (core boundary conditions) between the CEFLASH-4AS blowdown hydraulics computer code and the PARCH hot rod heatup code. Previously, this data transfer was performed manually. The automated process provides a more accurate and eAicient method of transferring the data, and the effect on the ECCS performance analysis for SBLOCA is estimated to be a reduction in calculated PCT of approximately 4 'F. The limiting ECCS analyses of record have not been performed with the changes described above.
SBLOCA: No errors were found in the SBLOCA analysis for this reporting period. The peak cladding temperature for the analysis of record remains at 1915 'F.
LBLOCA: An error was discovered and corrected in the decay heat energy redistribution factor (ERF) used in the ECCS performance evaluation model for LBLOCA. The impact on calculated peak cladding temperature was conservatively estimated and previously reported in Reference 3.4.
Correcting the ERF error resulted in a 28 'F increase, and the limiting ECCS analysis PCT is 2171 'F.
- 3. REFERENCES
- 1. FPL Letter L-97-313, J.A. Stall to USNRC (DCD), "Error in the Application of SBLOCA Evaluation Model; 30 Day, 10 CFR 50.46 Report:" December 17, 1997.
- 2. FPL Letter L-97-034, J.A. Stall to USNRC (DCD), "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors: 10 CFR 50.46 Annual Report:"
March 6, 1997.
- 3. SPC Letter NRC:98:001, J.S. Holm to USNRC, "Interim Report of Evaluation of a Deviation Pursuant to 10 CFR 21.21(a)(2):" January 15, 1998.
- 4. FPL Letter L-97-205, J.A. Stall to USNRC (DCD), "Error in the Use of LBLOCAEvaluation Model; 30 Day 10 CFR 50.46 Report:" August 8, 1997.
St. Lucie Units 1 and 2 L-98-057 Docket Nos. 50-335 and 50-389 ATTACHMENT 10 FR 50 46 Annual Re ort Page3 of 3 Table I St. Lucie Units 1 and 2 1997 SBLOCA and LBLOCAPCT Summary Unit 1 SBLOCA Summa PCT 1996 10 CFR 50.46 Annual Re ort note 1 1765 'F Chan edueto30% SGtube lu in anal sis note2 +39 'F Chan e due to revised HPSI flow as mmet +149 'F 1997 10 CFR 50.46 Annual Re ort 1953 'F Unit 1 LBLOCA Summa 1996 10 CFR 50.46 Annual Re ort 2027 'F Z-e uivalent error enalt estimated maximum im act on PCT +15 'F Chan e followin correction of Z-e uivalent error -1 'F Chan e due to revised containment s ra and fan cooler minimum dela time +14 'F 1997 10 CFR 50.46 Annual Re ort 2040 'F Unit 2 SBLOCA Summa PCT 1996 10 CFR 50.46 Annual Re ort 1915 'F Chan e durin 1997 0'F 1997 10 CFR 50.46 Annual Re ort 1915 'F Unit 2 LBLOCA Summa PCT 1996 10 CFR 50.46 Annual Re ort 2143 'F ERF error enalt estimated maximum im act on PCT +30 'F Chan e followin correction of ERF error +28 'F 1997 10 CFR 50.46 Annual Re ort 2171 'F Notes: (1) Calculated peak cladding tcmpcraturc is for stcam generator (SG) tube plugging level of 25%.
(2) Analysis was performed in 1996, but did not bccomc analysis of record until issuance of Amendmcnt No. 151 (5/16/97) to thc facility operating license. Thc value is included in this table to identify components contributing to thc cumulative impact on 1997 PCT of record.
