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| {{#Wiki_filter:AC(FLEA'l'Uu uL5i'KLUul'ION uM4OblhilMA'I'jOb! | | {{#Wiki_filter:AC(FLEA'l'Uu uL5i'KLUul'ION uM4OblhilMA'I'jOb! |
| SYSi'j'M~0REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9005110175 DOC.DATE:90/05/08NOTARIZED: | | SYSi'j'M~0 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 9005110175 DOC.DATE: 90/05/08 NOTARIZED: |
| NOFACIL:50-335 St.LuciePlant,Unit1,FloridaPower&LightCo.50-389St.Lu&ePlant,Unit2,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATION SAGER,D.A.
| | NO FACIL:50-335 St.Lucie Plant, Unit 1, Florida Power&Light Co.50-389 St.Lu&e Plant, Unit 2, Florida Power&Light Co.AUTH.NAME AUTHOR AFFILIATION SAGER,D.A. |
| FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKETPr0500033505000389
| | Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET Pr 05000335 05000389 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| RespondstoNRCBulletin88-010,"Nonconforming Molded-Case CircuitBreakers."
| | Responds to NRC Bulletin 88-010,"Nonconforming Molded-Case Circuit Breakers." DISTRIBUTION CODE: IE21D COPIES RECEIVED:LTR ENCL 0 SIZE: TITLE: Bulletin Response 88-10-Nonconforming Molded C se Circus,t Brea ers.NOTES: RECIPIENT ID CODE/NAME PD2-2 LA NORRIS,J INTERNAL: AEOD/DOA NRR DOEA/GCB 11 NRR GUILLEN,J NRR/DET/EMEB9H3 NRR/DOEA/OGCB11 NRR/DST 8E2 NRR/POTAPOVS,U RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD AEOD/DS P/TPAB NRR GILL,A.S.NRR STONE,J.C. |
| DISTRIBUTION CODE:IE21DCOPIESRECEIVED:LTR ENCL0SIZE:TITLE:BulletinResponse88-10-Nonconforming MoldedCseCircus,tBreaers.NOTES:RECIPIENT IDCODE/NAME PD2-2LANORRIS,JINTERNAL: | | NRR/DOEA/OEAB11 NRR/DREP/PEPB9D RGN2 FILE NRC PDR COPIES LTTR ENCL ,1 1'1 1 1 1 1 1 1 1 1 1 1 1 1 1.1 1 1 NOTE TO ALL"RIDS" RECIPIENIS: |
| AEOD/DOANRRDOEA/GCB11NRRGUILLEN,J NRR/DET/EMEB9H3 NRR/DOEA/OGCB11 NRR/DST8E2NRR/POTAPOVS,U RES/DSIR/EIB EXTERNAL: | | PLEASE HELP US TO REDUCE WASTEt CONTACT THE DOCUMENI'ONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISHUBUTION LISTS FOR DOCUMENIS YOU DON'T NEED)TOTAL NUMBER OF COPIES.REQUIRED: LTTR 22 ENCL 21 |
| LPDRNSICCOPIESLTTRENCL101111111111111111111111RECIPIENT IDCODE/NAME PD2-2PDAEOD/DSP/TPABNRRGILL,A.S.
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| NRRSTONE,J.C.
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| NRR/DOEA/OEAB11 NRR/DREP/PEPB9D RGN2FILENRCPDRCOPIESLTTRENCL,11'11111111111111.111NOTETOALL"RIDS"RECIPIENIS: | |
| PLEASEHELPUSTOREDUCEWASTEtCONTACTTHEDOCUMENI'ONTROL DESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISHUBUTION LISTSFORDOCUMENIS YOUDON'TNEED)TOTALNUMBEROFCOPIES.REQUIRED:
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| LTTR22ENCL21
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| P.O..l4000,Juno Beech,iL334080420@PLMAY,081990,L-90-16110CFR50.54(f)U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Gentlemen: | | P.O..l4000,Juno Beech,iL 33408 0420@PL MAY, 0 8 1990, L-90-161 10 CFR 50.54(f)U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen: |
| Re:St.LucieUnits1and2DocketNos.50-335and50-389NRCBulletinNo.88-10Nonconforming Molded-Case CircuitBreakersTACNos.71358and71359NRCBulletinNo.88-10,"Nonconforming Molded-Case CircuitBreakers", | | Re: St.Lucie Units 1 and 2 Docket Nos.50-335 and 50-389 NRC Bulletin No.88-10 Nonconforming Molded-Case Circuit Breakers TAC Nos.71358 and 71359 NRC Bulletin No.88-10,"Nonconforming Molded-Case Circuit Breakers", issued November 22, 1988, requested that licensees take actions to provide reasonable assurance that molded-case circuit breakers (CBs), including CBs used with motor controllers; purchased for use in safety-related applications without verifiable traceability to the CB manufacturers, perform their safety functions. |
| issuedNovember22,1988,requested thatlicensees takeactionstoprovidereasonable assurance thatmolded-case circuitbreakers(CBs),including CBsusedwithmotorcontrollers; purchased foruseinsafety-related applications withoutverifiable traceability totheCBmanufacturers, performtheirsafetyfunctions.
| | By letter L-89-120 dated April 3, 1989, Florida Power&Light Company (FPL)submitted a partial, response to NRC Bulletin No.88-10.The purpose of this submittal is to provide FPL's response to the remaining requirements of the bulletin.This completes FPL's response to NRC Bulletin No.88-10.Should there be any questions about this information, contact us.I please Very truly yours, D.A.ger Vice r sident St.L ie Plant DAS/MS D/gp Attachment cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St.Lucie Plant 5'005110175 5'00508 PDR ADOCK 05000335 O PDC an FPL Group company ATTACHMENT NRC BULLETIN No.88-10 Re ortin Re irement: 1.All holders of operating licenses are required to provide a written report by April 1, 1989, that: a~Confirms that only molded-case Circuit Breakers (CBs)that meet the criteria of item 7 of the actions requested are being maintained as stored spares for future use in safety-related applications. |
| ByletterL-89-120datedApril3,1989,FloridaPower&LightCompany(FPL)submitted apartial,responsetoNRCBulletinNo.88-10.Thepurposeofthissubmittal istoprovideFPL'sresponsetotheremaining requirements ofthebulletin.
| | FPL Res onse Florida Power&Light Company (FPL)provided a response to Reporting Requirement 1.a.in letter L-89-120 dated April 3, 1989'e ortin Re irement: 1.b.Summarizes the total number, manufacturer, model number, and to the extent possible the procurement chain of those CBs that could not be traced to the CBM in items 1 and 4 of the actions requested. |
| Thiscompletes FPL'sresponsetoNRCBulletinNo.88-10.Shouldtherebeanyquestions aboutthisinformation, contactus.IpleaseVerytrulyyours,D.A.gerVicersidentSt.LiePlantDAS/MSD/gpAttachment cc:StewartD.Ebneter,RegionalAdministrator, RegionII,USNRCSeniorResidentInspector, USNRC,St.LuciePlant5'005110175 5'00508PDRADOCK05000335OPDCanFPLGroupcompany ATTACHMENT NRCBULLETINNo.88-10ReortinReirement:1.Allholdersofoperating licensesarerequiredtoprovideawrittenreportbyApril1,1989,that:a~Confirmsthatonlymolded-case CircuitBreakers(CBs)thatmeetthecriteriaofitem7oftheactionsrequested arebeingmaintained asstoredsparesforfutureuseinsafety-related applications.
| | For installed CBs, also identify each system in which they are/were installed. |
| FPLResonseFloridaPower&LightCompany(FPL)providedaresponsetoReporting Requirement 1.a.inletterL-89-120datedApril3,1989'eortinReirement:1.b.Summarizes thetotalnumber,manufacturer, modelnumber,andtotheextentpossibletheprocurement chainofthoseCBsthatcouldnotbetracedtotheCBMinitems1and4oftheactionsrequested.
| | Zf item 4 of the actions requested has not been completed by April 1, 1989, due to the schedule for tests in item 3 of the actions requested, this information should be updated within 30 days of the completion of item 4 to address those additional CBs that could not be traced to the CBM.FPL Res onse Florida Power&Light Company (FPL)provided a response to item 1 of the actions requested in letter L-89-120 dated April 3, 1989.For FPL's response to item 4 of the actions requested, refer to Reporting Requirement 1.c.below.Re ortin Re irement: 1.c.Confirms that items 1(2g 3I 4g 5 6 and 7 of the actions requested have.been completed or will be implemented as requested. |
| Forinstalled CBs,alsoidentifyeachsysteminwhichtheyare/wereinstalled.
| | Action Re ested: 1.All addresses are requested to perform the following review by March>, 1989: a~Identify all molded-case CBs purchased prior to August 1, 1988, that are being maintained as stored spares for safety-related (Class 1E)applications or commercial grade CBs that are being maintained as stored spares for future use in safety-related applications; this includes CBs purchased from a CBM or from any other source.If the number of these stored spare CBs is less than 50 at a nuclear plant site, then randomly select CBs purchased between August 1, 1983 and August 1, 1988 that have been installed in safety-related applications as replacements or modifications to form a minimum sample of 50 CBs per nuclear plant site.b.Verify the traceability of these CBs.c~Identify the number, manufacturer, model number, and to the extent possible the procurement chain for all those CBs identified in (la)that cannot be traced to the CBM.For installed CBs, also identify each system in which they are/were installed. |
| Zfitem4oftheactionsrequested hasnotbeencompleted byApril1,1989,duetotheschedulefortestsinitem3oftheactionsrequested, thisinformation shouldbeupdatedwithin30daysofthecompletion ofitem4toaddressthoseadditional CBsthatcouldnotbetracedtotheCBM.FPLResonseFloridaPower&LightCompany(FPL)providedaresponsetoitem1oftheactionsrequested inletterL-89-120datedApril3,1989.ForFPL'sresponsetoitem4oftheactionsrequested, refertoReporting Requirement 1.c.below.ReortinReirement:1.c.Confirmsthatitems1(2g3I4g56and7oftheactionsrequested have.beencompleted orwillbeimplemented asrequested.
| | FPL Res onse FPL provided a response to Actions Requested 1.a., 1.b., and 1.c.in letter L-89-120 dated April 3, 1989.Action Re ested: 2.All holders of operating licenses who identify installed CBs per item 1 above or item 4 below that cannot be traced to a CBM are requested to prepare, within 30 days of the completion of each item, an analysis justifying continued operation until items 1 through 5 of the actions requested in this bulletin have been completed. |
| ActionReested:1.Alladdresses arerequested toperformthefollowing reviewbyMarch>,1989:a~Identifyallmolded-case CBspurchased priortoAugust1,1988,thatarebeingmaintained asstoredsparesforsafety-related (Class1E)applications orcommercial gradeCBsthatarebeingmaintained asstoredsparesforfutureuseinsafety-related applications; thisincludesCBspurchased fromaCBMorfromanyothersource.IfthenumberofthesestoredspareCBsislessthan50atanuclearplantsite,thenrandomlyselectCBspurchased betweenAugust1,1983andAugust1,1988thathavebeeninstalled insafety-related applications asreplacements ormodifications toformaminimumsampleof50CBspernuclearplantsite.b.Verifythetraceability oftheseCBs.c~Identifythenumber,manufacturer, modelnumber,andtotheextentpossibletheprocurement chainforallthoseCBsidentified in(la)thatcannotbetracedtotheCBM.Forinstalled CBs,alsoidentifyeachsysteminwhichtheyare/wereinstalled.
| | FPL Res onse Following FPL's response to item 1 of the actions requested (see FPL letter L-89-120, dated April 3, 1989), an assessment of the acceptability for use of all installed safety related circuit breakers (CB)that were procured under the same purchase orders as the 22 nontraceable stored spare CBs was performed ( |
| FPLResonseFPLprovidedaresponsetoActionsRequested 1.a.,1.b.,and1.c.inletterL-89-120datedApril3,1989.ActionReested:2.Allholdersofoperating licenseswhoidentifyinstalled CBsperitem1aboveoritem4belowthatcannotbetracedtoaCBMarerequested toprepare,within30daysofthecompletion ofeachitem,ananalysisjustifying continued operation untilitems1through5oftheactionsrequested inthisbulletinhavebeencompleted.
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| FPLResonseFollowing FPL'sresponsetoitem1oftheactionsrequested (seeFPLletterL-89-120, datedApril3,1989),anassessment oftheacceptability foruseofallinstalled safetyrelatedcircuitbreakers(CB)thatwereprocuredunderthesamepurchaseordersasthe22nontraceable storedspareCBswasperformed
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| ==Reference:== | | ==Reference:== |
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| NRCBulletinNo.88-10Supplement 1,Position4).Theresultsrevealedoneuntraceable CBwasinstalled in.theSt.LucieUnit2Qualified SafetyParameter DisplaySystem.Thisbreakerhassincebeenreplacedwithatraceable CBinaccordance with.thecriteriaofitem7ofthe actionsrequested.
| | NRC Bulletin No.88-10 Supplement 1, Position 4).The results revealed one untraceable CB was installed in.the St.Lucie Unit 2 Qualified Safety Parameter Display System.This breaker has since been replaced with a traceable CB in accordance with.the criteria of item 7 of the actions requested. |
| Theinformation concerning thisnontraceable breaker,asrequested initem4.c.oftheactionsrequested, isprovidedinAttachment 1(item1).Additionally, seeFPL'sresponses toitems3,4and5oftheactionsrequested fortheremaining information requested inActionRequested 2.ActionReested:3.Alladdressees whoidentify80percentormoreCBstraceable totheCBMperitem1abovearerequested totest.theCBsthatarenottraceable totheCBMinaccordance withthetestprogramdescribed inAttachment 1.Anyinstalled CBsthatfailanyofthesetestsshouldbereplacedwithCBsthatmeetthecriteriaofitem7oftheactionsrequested orCBsthatpassalltestsinaccordance withthetestingprogramdescribed inAttachment 1.Ifmorethan10percentoftheCBstestedfailanyofthetestsdescribed inAttachment 1,continuewithitem4;otherwise, proceedtoitem6oftheactionsrequested.
| | The information concerning this nontraceable breaker, as requested in item 4.c.of the actions requested, is provided in Attachment 1 (item 1).Additionally, see FPL's responses to items 3, 4 and 5 of the actions requested for the remaining information requested in Action Requested 2.Action Re ested: 3.All addressees who identify 80 percent or more CBs traceable to the CBM per item 1 above are requested to test.the CBs that are not traceable to the CBM in accordance with the test program described in Attachment 1.Any installed CBs that fail any of these tests should be replaced with CBs that meet the criteria of item 7 of the actions requested or CBs that pass all tests in accordance with the testing program described in Attachment 1.If more than 10 percent of the CBs tested fail any of the tests described in Attachment 1, continue with item 4;otherwise, proceed to item 6 of the actions requested. |
| Holdersofoperating licensesarerequested tocompletethistestingprogrambeforestartupfromthefirstrefueling outagebeginning afterMarch1,1989.Holdersofconstruction permitsarerequested tocompletethistestingprogrambeforefuelload.FPLResonseFPLdetermined thattwenty-two (22)outofonehundredandtwenty-four (124)CBsweremaintained asstoredspareswhichcouldnotbetracedtotheoriginalCBmanufacturers (seeFPLletterL-89-120, datedApril3,1989).Therefore, FPLhaddetermined that80percentormoreofthestoredspareCBsweretraceable totheCBM.InanNRCmemorandum datedJanuary5,1989(CharlesE.RossitoStevenA.VargaandGaryMHolahan,"Interpretation/Clarification ofBulletinNo.88-10:Nonconforming Molded-Case CircuitBreakers"
| | Holders of operating licenses are requested to complete this testing program before startup from the first refueling outage beginning after March 1, 1989.Holders of construction permits are requested to complete this testing program before fuel load.FPL Res onse FPL determined that twenty-two (22)out of one hundred and twenty-four (124)CBs were maintained as stored spares which could not be traced to the original CB manufacturers (see FPL letter L-89-120, dated April 3, 1989).Therefore, FPL had determined that 80 percent or more of the stored spare CBs were traceable to the CBM.In an NRC memorandum dated January 5, 1989 (Charles E.Rossi to Steven A.Varga and Gary M Holahan,"Interpretation/Clarification of Bulletin No.88-10: Nonconforming Molded-Case Circuit Breakers"), the NRC Staff agreed that testing of the nontraceable spares need not be performed provided the utility performs Bulletin No.88-10 items 4 and 5 of the actions requested, regardless of the traceability results of item 1 of the bulletin.Following a review of the Bulletin No.88-10 CB test program, FPL elected not to test the twenty-two nontraceable CBs, but instead elected to perform items 4 and 5 of the actions requested in accordance with the January 5, 1989, NRC memorandum. |
| ),theNRCStaffagreedthattestingofthenontraceable sparesneednotbeperformed providedtheutilityperformsBulletinNo.88-10items4and5oftheactionsrequested, regardless ofthetraceability resultsofitem1ofthebulletin. | | Action Re ested: 4.All addresses who identify less than 80 percent of the CBs traceable-+to the CBM per item 1 above or who identify a failure rate of more than 10 percent for the CBs tested per item 3 above are requested to perform the following actions: a~Identify all molded-case CBs that have, been purchased between August 1, 1983 and August 1, 1988, and installed in safety-related applications as replacements or installed during modifications. |
| Following areviewoftheBulletinNo.88-10CBtestprogram,FPLelectednottotestthetwenty-two nontraceable CBs,butinsteadelectedtoperformitems4and5oftheactionsrequested inaccordance withtheJanuary5,1989,NRCmemorandum. | | b.Verify the traceability of these CBs.c~Identify the number, manufacturer, model number, system in which they are/were installed, and to the extent possible, the procurement chain for all those CBs identified in (4a)that cannot be traced to the CBM.FPL Res onse FPL identified all St.Lucie plant molded-case CBs purchased between August 1, 1983 and August 1, 1988 and installed in safety-related applications. |
| ActionReested:4.Alladdresses whoidentifylessthan80percentoftheCBstraceable-+to theCBMperitem1aboveorwhoidentifyafailurerateofmorethan10percentfortheCBstestedperitem3abovearerequested toperformthefollowing actions:a~Identifyallmolded-case CBsthathave,beenpurchased betweenAugust1,1983andAugust1,1988,andinstalled insafety-related applications asreplacements orinstalled duringmodifications.
| | Traceability to the original CB manufacturer has been determined for all but four (4)CBs.Attachment 1 lists the information requested in item 4.c.for'hose four installed (items 2-5 of Attachment 1)CBs which were not traced to the original CB manufacturer. |
| b.Verifythetraceability oftheseCBs.c~Identifythenumber,manufacturer, modelnumber,systeminwhichtheyare/wereinstalled, andtotheextentpossible, theprocurement chainforallthoseCBsidentified in(4a)thatcannotbetracedtotheCBM.FPLResonseFPLidentified allSt.Lucieplantmolded-case CBspurchased betweenAugust1,1983andAugust1,1988andinstalled insafety-related applications. | | Action Re ested: 5.All addressees who identify installed CBs that cannot be traced to the CBM per item 4 above are requested to replace these CBs with components that meet the criteria of item 7 of the actions requested or to test them in accordance with the program described in Attachment 1;CBs that fail any of these tests should be replaced with CBs that meet the criteria of item 7 of the actions requested or CBs that pass all tests in accordance with the test program described in Attachment 1.Holders of operating licenses are requested to replace or to~test at least one-half, or all if the total number is less than 75, of these installed CBs before startup from the first refueling outage beginning after March 1, 1989.The remaining CBs should be replaced or tested before startup from the second refueling outage beginning after March 1, 1989.Holders of construction permits are requested to replace or to test these installed CBs before fuel load. |
| Traceability totheoriginalCBmanufacturer hasbeendetermined forallbutfour(4)CBs.Attachment 1liststheinformation requested initem4.c.for'hosefourinstalled (items2-5ofAttachment 1)CBswhichwerenottracedtotheoriginalCBmanufacturer. | | FPL Res onse FPL has elected to replace those CBs listed in Attachment 1 with breakers that meet the criteria of item 7 of the actions requested. |
| ActionReested:5.Alladdressees whoidentifyinstalled CBsthatcannotbetracedtotheCBMperitem4abovearerequested toreplacetheseCBswithcomponents thatmeetthecriteriaofitem7oftheactionsrequested ortotesttheminaccordance withtheprogramdescribed inAttachment 1;CBsthatfailanyofthesetestsshouldbereplacedwithCBsthatmeetthecriteriaofitem7oftheactionsrequested orCBsthatpassalltestsinaccordance withthetestprogramdescribed inAttachment 1.Holdersofoperating licensesarerequested toreplaceorto~testatleastone-half, orallifthetotalnumberislessthan75,oftheseinstalled CBsbeforestartupfromthefirstrefueling outagebeginning afterMarch1,1989.Theremaining CBsshouldbereplacedortestedbeforestartupfromthesecondrefueling outagebeginning afterMarch1,1989.Holdersofconstruction permitsarerequested toreplaceortotesttheseinstalled CBsbeforefuelload.
| | Three of the five breakers listed in Attachment 1 have already been replaced.The other two breakers are scheduled to be replaced as shown in Attachment 1 (Replacement Status)as required by Bulletin No.88-10.For the breakers to be replaced, a justification for continued operation for each breaker has been developed in accordance with item 2 of the actions requested. |
| FPLResonseFPLhaselectedtoreplacethoseCBslistedinAttachment 1withbreakersthatmeetthecriteriaofitem7oftheactionsrequested.
| | Action Re ested: 6.Information generated while performing the actions requested in items 1, 2, 3, 4, and 5 above should be documented and maintained for a period of 5 years after the completion of all requested actions.'PL Res onse FPL provided a response to Action Requested 6.in letter L-89-120 dated April 3, 1989.Action Re ested: 7 With the exception of actions taken in response to items 3 and 5 of the actions requested above, molded-case CBs installed in safety-related applications after August 1, 1988 should be: a~b.Manufactured by and procured from a CBM under a 10 CFR 50, Appendix B, program;or Procured from a CBM or others with verifiable traceability to the CBM, in compliance with applicable industry standards, and upgraded to safety-related by the licensee or others using an acceptable dedication program.The NRC encourages addresses to significantly upgrade their dedication programs through a joint industry effort to ensure their adequacy and consistency. |
| ThreeofthefivebreakerslistedinAttachment 1havealreadybeenreplaced.
| | The NRC will monitor these industry initiatives and if they are not sufficient or not timely, or if problems with the dedication of commercial grade equipment for safety-related use continue, the NRC will take appropriate regulatory actions. |
| Theothertwobreakersarescheduled tobereplacedasshowninAttachment 1(Replacement Status)asrequiredbyBulletinNo.88-10.Forthebreakerstobereplaced, ajustification forcontinued operation foreachbreakerhasbeendeveloped inaccordance withitem2oftheactionsrequested.
| | FPL Res onse Molded case CBs to be installed in safety-related applications are manufactured and procured from a CB manufacturer under a 10 CFR 50, Appendix B program.Additionally, statements have been added to procurement documents for all molded case CBs requiring that certification of traceability to the breaker manufacturer be provided with, the breakers.Re ortin Re irement: 2~All holders of operating licenses are required to submit a report that summarizes available results of tests conducted in accordance with items 3 and 5 of the actions requested within 30 days after startup from the first and second refueling obtages beginning after March 1, 1989.For CBs that pass these tests, the only information required is the number, manufacturer, model number and to the extent possible the procurement chain of CBs tested (summary report format is acceptable). |
| ActionReested:6.Information generated whileperforming theactionsrequested initems1,2,3,4,and5aboveshouldbedocumented andmaintained foraperiodof5yearsafterthecompletion ofallrequested actions.'PL ResonseFPLprovidedaresponsetoActionRequested 6.inletterL-89-120datedApril3,1989.ActionReested:7Withtheexception ofactionstakeninresponsetoitems3and5oftheactionsrequested above,molded-case CBsinstalled insafety-related applications afterAugust1,1988shouldbe:a~b.Manufactured byandprocuredfromaCBMundera10CFR50,AppendixB,program;orProcuredfromaCBMorotherswithverifiable traceability totheCBM,incompliance withapplicable industrystandards, andupgradedtosafety-related bythelicenseeorothersusinganacceptable dedication program.TheNRCencourages addresses tosignificantly upgradetheirdedication programsthroughajointindustryefforttoensuretheiradequacyandconsistency.
| | For CBs that fail these test(s)these reports should indicate the test(s)and the values of test parameter(s) at which the failure(s) occurred, as well as the corresponding manufacturer, model number, and to the extent possible, the procurement chain.FPL Res onse As stated in response to item 4 of the actions requested, FPL elected not to test the twenty-two nontraceable breakers, and instead elected to perform items 4 and 5 of actions requested. |
| TheNRCwillmonitortheseindustryinitiatives andiftheyarenotsufficient ornottimely,orifproblemswiththededication ofcommercial gradeequipment forsafety-related usecontinue, theNRCwilltakeappropriate regulatory actions.
| | Since FPL did not test, a report that summarizes the results of these test is not applicable. |
| FPLResonseMoldedcaseCBstobeinstalled insafety-related applications aremanufactured andprocuredfromaCBmanufacturer undera10CFR50,AppendixBprogram.Additionally, statements havebeenaddedtoprocurement documents forallmoldedcaseCBsrequiring thatcertification oftraceability tothebreakermanufacturer beprovidedwith,thebreakers.
| | PROCUREMENT 1)GE/Solidstate Unknown ATTACHMENT 1 MODEL PART THFK224150 UNIT SYSTEM REPLACEMENT STATUS Qualified Safety Replaced Parameter Display (9/25/89)System Inverter 2), West/CGD*Unknown FB3125L 1A Battery Charger Replaced (1/3/90)3)SQ.D./Whiting* |
| ReortinReirement:2~Allholdersofoperating licensesarerequiredtosubmitareportthatsummarizes available resultsoftestsconducted inaccordance withitems3and5oftheactionsrequested within30daysafterstartupfromthefirstandsecondrefueling obtagesbeginning afterMarch1,1989.ForCBsthatpassthesetests,theonlyinformation requiredisthenumber,manufacturer, modelnumberandtotheextentpossibletheprocurement chainofCBstested(summaryreportformatisacceptable).
| | Unknown QOU120 Fuel Cask Crane Replaced (12/15/89) 4)GE/GESCO Unknown THED136070 Breaker Feeds Power Panel 220 from Motor Control Center 2A6 Scheduled Replacement (Fall 1990)5)West/L&D Unknown QC1030 Breaker for Limit Scheduled Switch to 2B DC Replacement Bus Tie Breaker (Fall 1990)Motor Operated*A final determination on the traceability of this breaker was not made since a traceable replacement breaker was available. |
| ForCBsthatfailthesetest(s)thesereportsshouldindicatethetest(s)andthevaluesoftestparameter(s) atwhichthefailure(s)
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| : occurred, aswellasthecorresponding manufacturer, modelnumber,andtotheextentpossible, theprocurement chain.FPLResonseAsstatedinresponsetoitem4oftheactionsrequested, FPLelectednottotestthetwenty-two nontraceable
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| : breakers, andinsteadelectedtoperformitems4and5ofactionsrequested.
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| SinceFPLdidnottest,areportthatsummarizes theresultsofthesetestisnotapplicable.
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| PROCUREMENT 1)GE/Solidstate UnknownATTACHMENT 1MODELPARTTHFK224150 UNITSYSTEMREPLACEMENT STATUSQualified SafetyReplacedParameter Display(9/25/89) | |
| SystemInverter2),West/CGD*
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| UnknownFB3125L1ABatteryChargerReplaced(1/3/90)3)SQ.D./Whiting*
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| UnknownQOU120FuelCaskCraneReplaced(12/15/89) 4)GE/GESCOUnknownTHED136070 BreakerFeedsPowerPanel220fromMotorControlCenter2A6Scheduled Replacement (Fall1990)5)West/L&DUnknownQC1030BreakerforLimitScheduled Switchto2BDCReplacement BusTieBreaker(Fall1990)MotorOperated*Afinaldetermination onthetraceability ofthisbreakerwasnotmadesinceatraceable replacement breakerwasavailable.
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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]
Category:UTILITY TO NRC
MONTHYEARML17223A9401990-09-13013 September 1990
Forwards Evaluation of Potential Safety Impact of Failed Control Element Assemblies on Limiting Transients for Facility
ML17223A9341990-09-10010 September 1990
Forwards Addl Info Re Generic Implications & Resolution of Control Element Assembly (CEA) Failure at Facility,Per NRC Request.Description of Testing Program for Old Style CEAs in Unit 1 Core Encl
L-90-315, Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 81990-08-30030 August 1990
Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 8
ML17223A9201990-08-28028 August 1990
Forwards Forms NIS-1 & NIS-2, Owners Rept for Inservice Insps as Required by Provisions of ASME Code Rules, Per 900725 Ltr
ML17223A8911990-08-20020 August 1990
Forwards Corrected Monthly Operating Repts for Jul 1990 for St Lucie Units 1 & 2 & Summary of Operating Experience
ML17348A5041990-08-17017 August 1990
Forwards fitness-for-duty Program Performance Data for Jan-June 1990
L-90-301, Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant1990-08-16016 August 1990
Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant
ML17223A8751990-08-0909 August 1990
Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor
IR 05000335/19900141990-08-0909 August 1990
Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor
ML17348A4701990-07-27027 July 1990
Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing
ML17223A8621990-07-25025 July 1990
Advises That NIS-1 & NIS-2 Forms,As Part of Inservice Insp Rept,Will Be Submitted by 900831
ML17348A4281990-07-25025 July 1990
Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b)
ML17223A8631990-07-25025 July 1990
Submits Addl Info Re Implementation of Programmed Enhancements Per Generic Ltr 88-17, Loss of Dhr. All Mods for Unit 1 Completed & Operational.Mods for Unit 2 Schedule for Upcoming Refueling Outage
L-90-271, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders1990-07-20020 July 1990
Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders
ML17223A8581990-07-19019 July 1990
Forwards Implementation Status of 10CFR50.62 Mod at Facility Re Requirements for Reduction of Risk from ATWS Events for Light Water Cooled Nuclear Power Plants
ML17223A8491990-07-18018 July 1990
Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Transmitters Models 1153 Series B,1153 Series D & 1154 Mfg Prior to 890711 Supplied by Different Vendor
ML17223A8521990-07-17017 July 1990
Forwards Addl Info Requested Re Generic Implications & Resolution of Control Element Assembly Failure at Plant.Encl Confirms Util Intent to Follow C-E Regulatory Response Group Action Program
IR 05000335/19900131990-07-0909 July 1990
Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements
ML17223A8421990-07-0909 July 1990
Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements
ML17348A3881990-07-0505 July 1990
Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs
ML17223A8391990-07-0303 July 1990
Forwards Results of Beach Survey Procedure & Reduction of Field Survey Data,Per Tech Spec 4.7.6.1.1.Unit 1 Updated Fsar,Section 2.4.2.2,concluded That Dune Condition Acceptable Per Tech Spec 5.1.3
ML17223A8381990-07-0202 July 1990
Requests Termination of Operator License for s Lavelle.Util Also Requests That Ltr Be Withheld (Ref 10CFR2.790)
L-90-239, Forwards Rev 6 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990
Forwards Rev 6 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)
ML17223A8371990-06-27027 June 1990
Provides Details of Implementation Plan Re Recommendations & Schedular Requirements in Generic Ltr 89-10,per 891228 Ltr.Design Basis Review of safety-related motor-operated Valves & Determination of Switch Settings in Progress
ML17308A4981990-06-27027 June 1990
Responds to Generic Ltr 90-04 Re Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions
ML17223A8341990-06-19019 June 1990
Forwards Corrected Proposed Tech Spec Figure 3.4-2 Per 900207 Application for Amend to License NPF-16,incorporating Revised Pressure/Temp Limits & Results of Revised Low Temp Overpressure Protection Analysis Into Tech Specs
ML17223A8241990-06-18018 June 1990
Forwards Revised Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1988.
ML17223A8271990-06-18018 June 1990
Forwards Ma Smith 900601 Ltr to WR Cunningham of EPA Requesting Mod to Plant NPDES Permit to Permit Cleaning of Facility & to Establish Discharge Limits for Chemical Cleaning Wastes
ML17348A2981990-06-12012 June 1990
Forwards Rev 16 to Topical QA Rept.
ML17223A6761990-05-31031 May 1990
Advises That Air Operated safety-related Components Will Perform All Design Basis Events,Per 881227 Ltr.All Actions Required by Generic Ltr 88-14 Complete for Plant
ML17348A2651990-05-29029 May 1990
Submits Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per 10CFR26,App A.2.8(e)(4)
ML17223A6741990-05-22022 May 1990
Forwards Info Re Status of 10CFR50.62 Mods to Meet ATWS Requirements as of 900515.Plant Change/Mod Package Necessary for Installing ATWS Will Be Issued by 900630.Hardware Procurement for Diverse Scram Sys Approx 90% Complete
ML17223A6361990-05-0808 May 1990
Forwards Final Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. One Untraceable Circuit Breaker Installed in Unit 2 Qualified SPDS & Replaced W/Traceable Breaker
ML17223A6281990-04-21021 April 1990
Forwards St Lucie Unit 2 Annual Environ Operating Rept, Vol 1 1989.
ML17223A6081990-04-13013 April 1990
Responds to Violations Noted in Insp Repts 50-335/90-02 & 50-389/90-02.Corrective Actions:Nuclear Plant Supervisor Required to Remain in Control Room During Significant Changes in Power Operation & Preventive Maint Upgraded
ML17223A6071990-04-0505 April 1990
Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. Removal & Replacement of Cold Leg Side Plugs of Heat Number 3513 for Unit 1 Completed During Refueling Outage
ML17308A4911990-04-0202 April 1990
Forwards Description & Summary of Safety Evaluations of Plant Changes/Mods Reportable Per 10CFR50.59.Repair &/Or Replacement of Protective Coatings on Surfaces Inside Bldg Pose No Unreviewed Safety Question
ML17223A5931990-03-30030 March 1990
Forwards Status of 10CFR50.62, Requirements for Reduction of Risk from ATWS Mods at Plant as of 900315.Diverse Scram Sys Module Prototype Fabrication in Progress
ML17223A5921990-03-27027 March 1990
Forwards Addl Info on Proposed License Amend Re Increased Max Allowable Resistance Temp Detector Delay Time,Per 891219 Telcon & Advises That Util Request to Increase Plant Resistance Temp Detector Response Time Remain Unchanged
ML17223A5831990-03-19019 March 1990
Forwards Response to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implications of Control Sys in LWR Nuclear Power Plants,' Per 10CFR50.54(f)
ML17347B6191990-03-13013 March 1990
Provides Listing of Property Insurance Programs
ML17223A5531990-03-0909 March 1990
Submits Results of Investigation of Error Detected in Dose Assessment During 900124 NRC Evaluated Exercise at Plant. Operator Error Caused Keyboard Hangup Requiring Computer Restart
ML17223A5451990-03-0808 March 1990
Forwards Revised Tech Specs Re Steam Generator Tube Repairs, Per 890602 Telcon & Subsequent Discussions W/Nrc
ML17308A4871990-03-0707 March 1990
Forwards Response to Eight Audit Questions & Licensing Bases Criteria to Resolve Station Blackout Issue.Util Currently Has Procedures to Mitigate Effects of Hurricanes & Tornados Which Meet or Exceed NUMARC 87-00 Guidelines
ML17347B5881990-03-0101 March 1990
Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits
ML17347B6031990-02-27027 February 1990
Requests Approval to Use Code Case N-468 at Plants
ML17223A5321990-02-26026 February 1990
Forwards CEN-396 (L)-NP, Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2.
ML20012A0011990-02-26026 February 1990
Notifies That Followup Actions Completed on Schedule & Incorporated Into Rev 25 to Plant Physical Security Plan,Per NRC 890605 Request
ML17223A5411990-02-26026 February 1990
Provides Addl Info Re Proposed License Amends Re Moderator Temp Coefficient Surveillance Requirements,Per 891026 & 900109 Telcons
IR 05000335/19890241990-02-22022 February 1990
Responds to Violations Noted in Insp Repts 50-335/89-24 & 50-389/89-24.Corrective Actions:Applicable Procedures Changed to Clarify Which Spaces & Blocks Required to Be Completed on Plant Work Order & QC Supervisor Counseled
1990-09-13
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AC(FLEA'l'Uu uL5i'KLUul'ION uM4OblhilMA'I'jOb!
SYSi'j'M~0 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 9005110175 DOC.DATE: 90/05/08 NOTARIZED:
NO FACIL:50-335 St.Lucie Plant, Unit 1, Florida Power&Light Co.50-389 St.Lu&e Plant, Unit 2, Florida Power&Light Co.AUTH.NAME AUTHOR AFFILIATION SAGER,D.A.
Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET Pr 05000335 05000389
SUBJECT:
Responds to NRC Bulletin 88-010,"Nonconforming Molded-Case Circuit Breakers." DISTRIBUTION CODE: IE21D COPIES RECEIVED:LTR ENCL 0 SIZE: TITLE: Bulletin Response 88-10-Nonconforming Molded C se Circus,t Brea ers.NOTES: RECIPIENT ID CODE/NAME PD2-2 LA NORRIS,J INTERNAL: AEOD/DOA NRR DOEA/GCB 11 NRR GUILLEN,J NRR/DET/EMEB9H3 NRR/DOEA/OGCB11 NRR/DST 8E2 NRR/POTAPOVS,U RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD AEOD/DS P/TPAB NRR GILL,A.S.NRR STONE,J.C.
NRR/DOEA/OEAB11 NRR/DREP/PEPB9D RGN2 FILE NRC PDR COPIES LTTR ENCL ,1 1'1 1 1 1 1 1 1 1 1 1 1 1 1 1.1 1 1 NOTE TO ALL"RIDS" RECIPIENIS:
PLEASE HELP US TO REDUCE WASTEt CONTACT THE DOCUMENI'ONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISHUBUTION LISTS FOR DOCUMENIS YOU DON'T NEED)TOTAL NUMBER OF COPIES.REQUIRED: LTTR 22 ENCL 21
P.O..l4000,Juno Beech,iL 33408 0420@PL MAY, 0 8 1990, L-90-161 10 CFR 50.54(f)U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
Re: St.Lucie Units 1 and 2 Docket Nos.50-335 and 50-389 NRC Bulletin No.88-10 Nonconforming Molded-Case Circuit Breakers TAC Nos.71358 and 71359 NRC Bulletin No.88-10,"Nonconforming Molded-Case Circuit Breakers", issued November 22, 1988, requested that licensees take actions to provide reasonable assurance that molded-case circuit breakers (CBs), including CBs used with motor controllers; purchased for use in safety-related applications without verifiable traceability to the CB manufacturers, perform their safety functions.
By letter L-89-120 dated April 3, 1989, Florida Power&Light Company (FPL)submitted a partial, response to NRC Bulletin No.88-10.The purpose of this submittal is to provide FPL's response to the remaining requirements of the bulletin.This completes FPL's response to NRC Bulletin No.88-10.Should there be any questions about this information, contact us.I please Very truly yours, D.A.ger Vice r sident St.L ie Plant DAS/MS D/gp Attachment cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St.Lucie Plant 5'005110175 5'00508 PDR ADOCK 05000335 O PDC an FPL Group company ATTACHMENT NRC BULLETIN No.88-10 Re ortin Re irement: 1.All holders of operating licenses are required to provide a written report by April 1, 1989, that: a~Confirms that only molded-case Circuit Breakers (CBs)that meet the criteria of item 7 of the actions requested are being maintained as stored spares for future use in safety-related applications.
FPL Res onse Florida Power&Light Company (FPL)provided a response to Reporting Requirement 1.a.in letter L-89-120 dated April 3, 1989'e ortin Re irement: 1.b.Summarizes the total number, manufacturer, model number, and to the extent possible the procurement chain of those CBs that could not be traced to the CBM in items 1 and 4 of the actions requested.
For installed CBs, also identify each system in which they are/were installed.
Zf item 4 of the actions requested has not been completed by April 1, 1989, due to the schedule for tests in item 3 of the actions requested, this information should be updated within 30 days of the completion of item 4 to address those additional CBs that could not be traced to the CBM.FPL Res onse Florida Power&Light Company (FPL)provided a response to item 1 of the actions requested in letter L-89-120 dated April 3, 1989.For FPL's response to item 4 of the actions requested, refer to Reporting Requirement 1.c.below.Re ortin Re irement: 1.c.Confirms that items 1(2g 3I 4g 5 6 and 7 of the actions requested have.been completed or will be implemented as requested.
Action Re ested: 1.All addresses are requested to perform the following review by March>, 1989: a~Identify all molded-case CBs purchased prior to August 1, 1988, that are being maintained as stored spares for safety-related (Class 1E)applications or commercial grade CBs that are being maintained as stored spares for future use in safety-related applications; this includes CBs purchased from a CBM or from any other source.If the number of these stored spare CBs is less than 50 at a nuclear plant site, then randomly select CBs purchased between August 1, 1983 and August 1, 1988 that have been installed in safety-related applications as replacements or modifications to form a minimum sample of 50 CBs per nuclear plant site.b.Verify the traceability of these CBs.c~Identify the number, manufacturer, model number, and to the extent possible the procurement chain for all those CBs identified in (la)that cannot be traced to the CBM.For installed CBs, also identify each system in which they are/were installed.
FPL Res onse FPL provided a response to Actions Requested 1.a., 1.b., and 1.c.in letter L-89-120 dated April 3, 1989.Action Re ested: 2.All holders of operating licenses who identify installed CBs per item 1 above or item 4 below that cannot be traced to a CBM are requested to prepare, within 30 days of the completion of each item, an analysis justifying continued operation until items 1 through 5 of the actions requested in this bulletin have been completed.
FPL Res onse Following FPL's response to item 1 of the actions requested (see FPL letter L-89-120, dated April 3, 1989), an assessment of the acceptability for use of all installed safety related circuit breakers (CB)that were procured under the same purchase orders as the 22 nontraceable stored spare CBs was performed (
Reference:
NRC Bulletin No.88-10 Supplement 1, Position 4).The results revealed one untraceable CB was installed in.the St.Lucie Unit 2 Qualified Safety Parameter Display System.This breaker has since been replaced with a traceable CB in accordance with.the criteria of item 7 of the actions requested.
The information concerning this nontraceable breaker, as requested in item 4.c.of the actions requested, is provided in Attachment 1 (item 1).Additionally, see FPL's responses to items 3, 4 and 5 of the actions requested for the remaining information requested in Action Requested 2.Action Re ested: 3.All addressees who identify 80 percent or more CBs traceable to the CBM per item 1 above are requested to test.the CBs that are not traceable to the CBM in accordance with the test program described in Attachment 1.Any installed CBs that fail any of these tests should be replaced with CBs that meet the criteria of item 7 of the actions requested or CBs that pass all tests in accordance with the testing program described in Attachment 1.If more than 10 percent of the CBs tested fail any of the tests described in Attachment 1, continue with item 4;otherwise, proceed to item 6 of the actions requested.
Holders of operating licenses are requested to complete this testing program before startup from the first refueling outage beginning after March 1, 1989.Holders of construction permits are requested to complete this testing program before fuel load.FPL Res onse FPL determined that twenty-two (22)out of one hundred and twenty-four (124)CBs were maintained as stored spares which could not be traced to the original CB manufacturers (see FPL letter L-89-120, dated April 3, 1989).Therefore, FPL had determined that 80 percent or more of the stored spare CBs were traceable to the CBM.In an NRC memorandum dated January 5, 1989 (Charles E.Rossi to Steven A.Varga and Gary M Holahan,"Interpretation/Clarification of Bulletin No.88-10: Nonconforming Molded-Case Circuit Breakers"), the NRC Staff agreed that testing of the nontraceable spares need not be performed provided the utility performs Bulletin No.88-10 items 4 and 5 of the actions requested, regardless of the traceability results of item 1 of the bulletin.Following a review of the Bulletin No.88-10 CB test program, FPL elected not to test the twenty-two nontraceable CBs, but instead elected to perform items 4 and 5 of the actions requested in accordance with the January 5, 1989, NRC memorandum.
Action Re ested: 4.All addresses who identify less than 80 percent of the CBs traceable-+to the CBM per item 1 above or who identify a failure rate of more than 10 percent for the CBs tested per item 3 above are requested to perform the following actions: a~Identify all molded-case CBs that have, been purchased between August 1, 1983 and August 1, 1988, and installed in safety-related applications as replacements or installed during modifications.
b.Verify the traceability of these CBs.c~Identify the number, manufacturer, model number, system in which they are/were installed, and to the extent possible, the procurement chain for all those CBs identified in (4a)that cannot be traced to the CBM.FPL Res onse FPL identified all St.Lucie plant molded-case CBs purchased between August 1, 1983 and August 1, 1988 and installed in safety-related applications.
Traceability to the original CB manufacturer has been determined for all but four (4)CBs.Attachment 1 lists the information requested in item 4.c.for'hose four installed (items 2-5 of Attachment 1)CBs which were not traced to the original CB manufacturer.
Action Re ested: 5.All addressees who identify installed CBs that cannot be traced to the CBM per item 4 above are requested to replace these CBs with components that meet the criteria of item 7 of the actions requested or to test them in accordance with the program described in Attachment 1;CBs that fail any of these tests should be replaced with CBs that meet the criteria of item 7 of the actions requested or CBs that pass all tests in accordance with the test program described in Attachment 1.Holders of operating licenses are requested to replace or to~test at least one-half, or all if the total number is less than 75, of these installed CBs before startup from the first refueling outage beginning after March 1, 1989.The remaining CBs should be replaced or tested before startup from the second refueling outage beginning after March 1, 1989.Holders of construction permits are requested to replace or to test these installed CBs before fuel load.
FPL Res onse FPL has elected to replace those CBs listed in Attachment 1 with breakers that meet the criteria of item 7 of the actions requested.
Three of the five breakers listed in Attachment 1 have already been replaced.The other two breakers are scheduled to be replaced as shown in Attachment 1 (Replacement Status)as required by Bulletin No.88-10.For the breakers to be replaced, a justification for continued operation for each breaker has been developed in accordance with item 2 of the actions requested.
Action Re ested: 6.Information generated while performing the actions requested in items 1, 2, 3, 4, and 5 above should be documented and maintained for a period of 5 years after the completion of all requested actions.'PL Res onse FPL provided a response to Action Requested 6.in letter L-89-120 dated April 3, 1989.Action Re ested: 7 With the exception of actions taken in response to items 3 and 5 of the actions requested above, molded-case CBs installed in safety-related applications after August 1, 1988 should be: a~b.Manufactured by and procured from a CBM under a 10 CFR 50, Appendix B, program;or Procured from a CBM or others with verifiable traceability to the CBM, in compliance with applicable industry standards, and upgraded to safety-related by the licensee or others using an acceptable dedication program.The NRC encourages addresses to significantly upgrade their dedication programs through a joint industry effort to ensure their adequacy and consistency.
The NRC will monitor these industry initiatives and if they are not sufficient or not timely, or if problems with the dedication of commercial grade equipment for safety-related use continue, the NRC will take appropriate regulatory actions.
FPL Res onse Molded case CBs to be installed in safety-related applications are manufactured and procured from a CB manufacturer under a 10 CFR 50, Appendix B program.Additionally, statements have been added to procurement documents for all molded case CBs requiring that certification of traceability to the breaker manufacturer be provided with, the breakers.Re ortin Re irement: 2~All holders of operating licenses are required to submit a report that summarizes available results of tests conducted in accordance with items 3 and 5 of the actions requested within 30 days after startup from the first and second refueling obtages beginning after March 1, 1989.For CBs that pass these tests, the only information required is the number, manufacturer, model number and to the extent possible the procurement chain of CBs tested (summary report format is acceptable).
For CBs that fail these test(s)these reports should indicate the test(s)and the values of test parameter(s) at which the failure(s) occurred, as well as the corresponding manufacturer, model number, and to the extent possible, the procurement chain.FPL Res onse As stated in response to item 4 of the actions requested, FPL elected not to test the twenty-two nontraceable breakers, and instead elected to perform items 4 and 5 of actions requested.
Since FPL did not test, a report that summarizes the results of these test is not applicable.
PROCUREMENT 1)GE/Solidstate Unknown ATTACHMENT 1 MODEL PART THFK224150 UNIT SYSTEM REPLACEMENT STATUS Qualified Safety Replaced Parameter Display (9/25/89)System Inverter 2), West/CGD*Unknown FB3125L 1A Battery Charger Replaced (1/3/90)3)SQ.D./Whiting*
Unknown QOU120 Fuel Cask Crane Replaced (12/15/89) 4)GE/GESCO Unknown THED136070 Breaker Feeds Power Panel 220 from Motor Control Center 2A6 Scheduled Replacement (Fall 1990)5)West/L&D Unknown QC1030 Breaker for Limit Scheduled Switch to 2B DC Replacement Bus Tie Breaker (Fall 1990)Motor Operated*A final determination on the traceability of this breaker was not made since a traceable replacement breaker was available.
7
