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| | issue date = 08/30/1994 | | | issue date = 08/30/1994 |
| | title = Requests Enforcement Discretion W/Respect to TS 3.4.2.1.a. Request Background Info & Justification Encl | | | title = Requests Enforcement Discretion W/Respect to TS 3.4.2.1.a. Request Background Info & Justification Encl |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = MARTIN T T | | | addressee name = Martin T |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | docket = 05000244 | | | docket = 05000244 |
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| =Text= | | =Text= |
| {{#Wiki_filter:tI'u7($@<j~IIWZROCHESTERGASANDELECTRICCORPORATION~8944P'<<EASTAVENUE,ROCHESTER,N.Y.14649.0001August30,1994TCLEPHONCi~rAcoo@.vie546.2700U.S.NuclearRegulatoryCommissionRegionalAdministrator,RegionIMr.ThomasT.Martin475AllendaleRoadKingofPrussia,PA19406 | | {{#Wiki_filter:I'u7($@<j~IIWZ t |
| | 4 4P'<< |
| | ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649.0001 TCLEPHONC i~rA coo@. vie 546.2700 August 30, 1994 U.S. Nuclear Regulatory Commission Regional Administrator, Region I Mr. Thomas T. Martin 475 Allendale Road King of Prussia, PA 19406 |
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| ==Subject:== | | ==Subject:== |
| RequestForEnforcementDiscretionR.E.GinnaNuclearPowerPlantDocketNo.50-244
| | Request For Enforcement Discretion R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
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| ==DearMr.Martin,== | | ==Dear Mr. Martin,== |
| Inaccordancewith10CFRPart2,AppendixC,andusingtheguidancecontainedinNRCInspectionManualPart9900,RG&ErequestsEnforcementDiscretionwithrespecttoGinnaStationTechnicalSpecification3.4.2.1.a.Therequest,backgroundinformation,andjustificationisattached.ThisrequestwasinitiallydiscussedwiththeNRCduringaconferencecallonAugust20,1994at1600EST.RG&EreceivedverbalapprovaloftheenclosedEnforcementDiscretionduringaphoneconversationbetweenMr.WilliamLazarusNRC,RegionI,andRobertMecredy,VicePresident,NuclearProductionatapproximately1720ESTonthatsamedate.Thisletterprovidesallnecessaryinformationrequestedduringthesetwophoneconversations.Verytrulyyours,RobertC.MecryXC:U.S.NuclearRegulatoryCommissionOfficeofNuclearReactorRegulationAssistantDirectorforRegionIReactorsMr.JoseA.CalvoWashington,D.C.20555GinnaStationSeniorResidentInspector'P4ll03036094i027PDRADaCK05000244PPDR~T~
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| I.-DCRIPTIONFTECHNICALPECIFICATINREUIREMENTGinnaStationTechnicalSpecification(TS)3.4.2.1requiresthatbothmotor-drivenAuxiliaryFeedwater(MDAFW)pumpsbeoperablewiththeRCStemperatureM350'F.ActionStatement3.4.2.1.astatesthatifoneMDAFWpumpisinoperable,thepumpmustberestoredtooperablestatuswithin7daysortheplantshallbeinatleastHotShutdownwithin6hoursandatanRCStemperature<350'Fwithinthefollowing6hours.2.DCRIPTINOFREOnAugust24,1994at0530hours,MDAFWPumpBwasremovedfromservicetoperformscheduledtestingandmaintenanceoftheassociatedservicewatercoolingsupplystrainerandtheAClubeoilpump(ProceduresEM-785andM-44.13,andWorkOrder¹19400838).ThemaintenanceactivitieswerecompletedonAugust25,1994andalimitedtestwassubsequentlyperformedonMDAFWPumpBbeginningat1430hourstoverifytheoperabilityoftheAClubeoilpumpbreaker.At1432hours,theoperatorsnoticedthatthenormallyclosedrecirculationlineair-operatedvalve(AOV4310)forMDAFWPumpBdidnotopenasrequired.ThepumpwasthensecuredandatroublecardwasinitiatedforAOV4310at1435hours.PreparationsweretheninitiatedtoperformtherepairofAOV4310.Thevalvewasrepairedandafullpumptest(ProcedurePT-16Q-B)wasthenperformedonAugust26,1994toverifypumpandvalveoperability.At2220hours,itwasdeterminedthattheMDAFWpumpdidnotmeetthe~prequirementsandatroublecardwasinitiatedforthepump.MajorrepairsonMDAFWPumpBweresubsequentlyinitiatedwhichincludedcompletedisassemblyofthepump.ItisnotedthatProcedurePT-16Q-BwassuccessfullyperformedonMDAFWPumpBonAugust18th.RGB'asconservativelyassumedthatMDAFWPumpBhasbeeninoperablesinceAugust24,1994at0530hourswheninitialworkactivitiesbeganandtheLCOwasentered.However,sincerepairactivitiesofthepumpwerenotinitiateduntillateonAugust26,1994,andduetotheleadtimeforreplacementpartsandtheneedtoperformpost-maintenancetesting,RG&Edoesnotanticipatethatthenecessaryrepairs'andtestingcanbeaccomplishedwithintheTSrequired7days.EnforcementDiscretionisthereforerequestedtograntRGB'elieffromcompliancewiththerequirementsofTS3.4.2.1.a.ThisEnforcementDiscretionisrequestedtobeginonAugust31,1994at0530hourswhenthecurrentLCOforTS3.4.2.l.awillexpire.TheEnforcementDiscretionisrequestedtoendonSeptember2at0800hourswhenallnecessaryrepairandtestingactivitieswillbecompleted.Thisisanextensionof50.5hours. 3..BASTFORRKTThereareatotaloffiveAFWpumpsinstalledatGinnaStation.ThepreferredAFWsystemhastwo100%capacityMDAFWpumpsandone200%capacityturbinedriven(TDAFW)pump.TheStandbyAuxiliaryFeedwater(SAFW)systemhastwo100%capacityMDAFWpumpswhicharemanuallystartedbytheoperatorsifnormalAFWislost(e.g.,highenergylinebreaksintheIntermediateBuilding).Thesafety-relatedfunctionoftheAFWsystematGinnaStationistomitigatethefollowingaccidentsorevents(UFSARSection10.5.2.1):a.b.C.d.e.f.g.h.Lossofmainfeedwater(MFW)withoffsitepoweravailableLossofMFWwithoutoffsitepoweravailableMFWlineruptureMainSteamlineruptureLossofallACpower(onsiteandoffsite)LOCASteamGeneratorTubeRupture(SGTR)CooldownItemscanddhavebeenevaluatedforGinnaStationassumingthatonlytheredundantSAFWsystemisavailable(UFSARSection15.2.7.3)whileitemeonlyrequirestheTDAFWpump(UFSARSection15.2.5).ItemsaandbareboundedbytheanalysisforthehighenergylinebreaksintheIntermediateBuilding(i.e.,itemscandd)duetotheavailablewaterinventoryintheintactSGs.TheSAFWsystemcanalsobeusedforcooldownevents(itemg)duetothetimewhichwouldbeavailableasaresultoflowdecayheatlevels.Consequently,onlyLOCAsandSGTRs(i.e.,itemsfandg)mustbeconsideredwithrespecttotheinoperableMDAFWpump.FollowingaLOCAorSGTR,thepreferredAFWsystemwillreceiveanautomaticstartsignaltoprovidecoolingwatertothesteamgenerators.However,forallLOCAs,boththeTDAFWpumpandMDAFWPumpAwillbeavailabletoprovidethenecessarycoolingwater.ThereisnosinglefailurewhichcanresultinthelossofbothofthesepumpsduringaLOCA.InthecaseofaSGTR,itcanbepostulatedthataruptureoccursinSGAwhichwouldresultintheisolationofautomaticAFWflowfromMDAFWPumpAandtheTDAFWpump(toS/GAonly).OnlyautomaticflowfromtheTDAFWpumpto'GBwouldbeavailableinthisinstance.OperatoractionisalreadyrequiredforaSGTReventtodepressurizetheRCS.Sincethistenminutedelayisalreadyassumedintheaccidentanalysis,itcanbeassumedthattimeisalsoavailabletousetheSAFWsystemorcross-tieMDAFWAtoSGBiftheTDAFWpumpweretofail.Inaddition,itisnotedthattheincreasedSGlevelintherupturedSGprovidesadditionaltimebeforeAFWwouldberequired. AreviewoftheGinnaStationPRAindicatesthatatuberuptureinSGAwithasubsequentfailureoftheTDAFWpump,thusrequiringtheneedforSAFW,isofverylowprobability(-1.4E-06fortheadditional2dayMDAFWPumpoutage).Inaddition,theAFWsystemisinstandbyduringnormalpoweroperations.ItisnotconsideredprudenttorequireaplantshutdownthroughmodesinwhichthepreferredAFWsystemisusedtoprovidenormalSG'coolingwaterneedswithoneMDAFWpumpinoperable.ThepotentialforplanttransientsandthesubsequentneedforAFWduringthesemodetransitionsisalsoincreased.MPENSATRYACTINRG&EwillnotperformanytestingormaintenancerelatedtotheremainingAFWandSAFWpumpsandtheirnecessarysupportsystemsduringtherequestedtwodayextension.Inaddition,operatorawarenessofRCSleakagehasbeenincreasedsinceleakagecanbeusedasanindicationofapotentialLOCAorSGTR.TheOperationsPlanoftheDay(POD)hasalsobeenrevisedtoenhanceoperatorawarenessoftheuseoftheMDAFWpumpcross-tielinesifrequired.TIFICATINFRDURATINOFREUESTTherequestedtwodayLCOextensionisnecessarytoensurecompletionrepairsonMDAFWPumpBandtoperformtherequiredtesting.Thetwodayextensionisbasedontheneedtocompletethealignmentofthepumpincludingthespeedincreaser.Basedonpreviousexperience,theseactivitiesmayrequiremultipleiterations.Duringthisrequestedextension,three100%capacityAFWpumpsandone200%capacityTDAFWpumpareavailabletoprovidethenecessarycoolingwatertotheSGsfordecayheatremoval.AsdiscussedinSection3,theprobabilityofanaccidentwhichrequirestheAFWpumpsduringthetwodayextensionisverysmall.MDAFWPumpAwassuccessfullytestedonAugust16,1994(ProcedurePT-16Q-A)~TestingoftheTDAFWpumpwasalsosuccessfullyperformedonAugust22,1994(ProcedurePT-16Q-T)providingadditionalassurancethecontinuedoperabilityofthesepumps.AttachmentAprovidesasummaryofthemostrecentAFWandSAFWpumptests.IGNIFICANTHAZARDSEVALUATIONRG&EhasevaluatedtheEnforcementDiscretionrequestandconcludedthatthereisnopotentialdetrimenttothepublichealthandsafetyandthatasignificantsafetyhazardisnotinvolved.Thisbasisforthisconclusionissummarizedbelow: | | In accordance with 10 CFR Part 2, Appendix C, and using the guidance contained in NRC Inspection Manual Part 9900, RG&E requests Enforcement Discretion with respect to Ginna Station Technical Specification 3.4.2.1.a. The request, background information, and justification is attached. |
| -4,a"ExtendingthecurrentoutageofMDAFWPumpBforapproximatelytwodaysdoesnotresultinasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheremainingAFWandSAFWpumpsprovidesufficientredundancytomitigateallpotentialaccidents.b.ExtendingthecurrentoutageofMDAFWPump8forapproximatelytwodaysdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluated.TheonlyaccidentwhichcanbeinitiatedbyAFWisanovercoolingeventcausedbyspuriousactuation.SinceMDAFWPumpBisnotoperable,thisaccidentisnotcredibleduringtherequestedextension.Noothernewordifferentkindsofaccidentarecreatedbytheplantconditionduringthetwodayextension.C.ExtendingthecurrentoutageofMDAFWPump3forapproximatelytwodaysdoesnotinvolveasignificantreductioninamarginofsafety.TheremainingAFWandSAFWpumpsprovidesufficientredundancytomitigateallpotentialaccidents.Inaddition,operatorsaresufficientlytrainedandproceduresaddresstheresponsetoalossofMFW.7.NVIRNMKNTALIMPACTTherearenoenvironmentalreleasesassociatedwiththecurrentplantcondition.TheprobabilityofrequiringuseoftheinoperableMDAFWpumpisverysmall.Inaddition,sufficientguidanceiscurrentlyavailabletotheoperatorstorespondtoany,postulatedscenariowhichwouldrequireAFWortheSAFWsystem.Therefore,therearenoenvironmentalconsequencesassociatedwiththisrequest.8.REVIEWBYRCTheGinnaStationPORChasreviewedandapprovedthisrequestforEnforcementDiscretion.ThomasMarlowGinnaStationPORCChairmanDate OVERALLAFWPUMPSTATUSCEMENT4P/4PLIMITVIBRATIONS"A"MDAFWP1150/1120<'>NoAdverseTrends"B"MDAFWP(PendingRebaselineTestFollowingCorrectiveMaintenance-8/30/94)TurbineAFWP1160/1131">NoAdverseTrends"C"SBAFWP1250/1122~~NoAdverseTrends"D"SBAFWP1267/1152NoAdverseTrends(1)-BasedonNSSLDesignAnalysis(2)-BasedonASMESectionXZCodeFormula | | This request was initially discussed with the NRC during a conference call on August 20, 1994 at 1600 EST. RG&E received verbal approval of the enclosed Enforcement Discretion during a phone conversation between Mr. William Lazarus NRC, Region I, and Robert Mecredy, Vice President, Nuclear Production at approximately 1720 EST on that same date. |
| ~/~N4 | | This letter provides all necessary information requested during these two phone conversations. |
| }} | | Very truly yours, Robert C. Mecr y XC: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Assistant Director for Region I Reactors Mr. Jose A. Calvo Washington, D.C. 20555 Ginna Station Senior Resident Inspector |
| | 'P4ll030360 94i027 PDR ADaCK 05000244 P PDR |
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| | I. - D CRIPTION F TECHNICAL PECIFICATI N RE UIREMENT Ginna Station Technical Specification (TS) 3.4.2.1 requires that both motor-driven Auxiliary Feedwater (MDAFW) pumps be operable with the RCS temperature M 350'F. Action Statement 3.4.2.1.a states that ifone MDAFW pump is inoperable, the pump must be restored to operable status within 7 days or the plant shall be in at least Hot Shutdown within 6 hours and at an RCS temperature < 350'F within the following 6 hours. |
| | : 2. D CRIPTI N OF RE On August 24, 1994 at 0530 hours, MDAFW Pump B was removed from service to perform scheduled testing and maintenance of the associated service water cooling supply strainer and the AC lube oil pump (Procedures EM-785 and M-44.13, and Work Order ¹19400838). The maintenance activities were completed on August 25, 1994 and a limited test was subsequently performed on MDAFW Pump B beginning at 1430 hours to verify the operability of the AC lube oil pump breaker. At 1432 hours, the operators noticed that the normally closed recirculation line air-operated valve (AOV 4310) for MDAFW Pump B did not open as required. The pump was then secured and a trouble card was initiated for AOV 4310 at 1435 hours. |
| | Preparations were then initiated to perform the repair of AOV 4310. The valve was repaired and a full pump test (Procedure PT-16Q-B) was then performed on August 26, 1994 to verify pump and valve operability. At 2220 hours, it was determined that the MDAFW pump did not meet the ~p requirements and a trouble card was initiated for the pump. Major repairs on MDAFW Pump B were subsequently initiated which included complete disassembly of the pump. It is noted that Procedure PT-16Q-B was successfully performed on MDAFW Pump B on August 18th. |
| | RGB'as conservatively assumed that MDAFW Pump B has been inoperable since August 24, 1994 at 0530 hours when initial work activities began and the LCO was entered. However, since repair activities of the pump were not initiated until late on August 26, 1994, and due to the lead time for replacement parts and the need to perform post-maintenance testing, RG&E does not anticipate that the necessary repairs |
| | 'and testing can be accomplished within the TS required 7 days. Enforcement Discretion is therefore requested to grant RGB'elief from compliance with the requirements of TS 3.4.2.1.a. |
| | This Enforcement Discretion is requested to begin on August 31, 1994 at 0530 hours when the current LCO for TS 3.4.2.l.a will expire. The Enforcement Discretion is requested to end on September 2 at 0800 hours when all necessary repair and testing activities will be completed. This is an extension of 50.5 hours. |
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| | 3.. BAST FOR RK T There are a total of five AFW pumps installed at Ginna Station. The preferred AFW system has two 100% capacity MDAFW pumps and one 200% capacity turbine driven (TDAFW) pump. The Standby Auxiliary Feedwater (SAFW) system has two 100% capacity MDAFW pumps which are manually started by the operators if normal AFW is lost (e.g., high energy line breaks in the Intermediate Building). |
| | The safety-related function of the AFW system at Ginna Station is to mitigate the following accidents or events (UFSAR Section 10.5.2.1): |
| | : a. Loss of main feedwater (MFW) with offsite power available |
| | : b. Loss of MFW without offsite power available C. MFW line rupture |
| | : d. Main Steam line rupture |
| | : e. Loss of all AC power (onsite and offsite) |
| | : f. LOCA |
| | : g. Steam Generator Tube Rupture (SGTR) |
| | : h. Cooldown Items c and d have been evaluated for Ginna Station assuming that only the redundant SAFW system is available (UFSAR Section 15.2.7.3) while item e only requires the TDAFW pump (UFSAR Section 15.2.5). Items a and b are bounded by the analysis for the high energy line breaks in the Intermediate Building (i.e., items c and d) due to the available water inventory in the intact SGs. The SAFW system can also be used for cooldown events (item g) due to the time which would be available as a result of low decay heat levels. Consequently, only LOCAs and SGTRs (i.e., items f and g) must be considered with respect to the inoperable MDAFW pump. |
| | Following a LOCA or SGTR, the preferred AFW system will receive an automatic start signal to provide cooling water to the steam generators. However, for all LOCAs, both the TDAFW pump and MDAFW Pump A will be available to provide the necessary cooling water. There is no single failure which can result in the loss of both of these pumps during a LOCA. |
| | In the case of a SGTR, it can be postulated that a rupture occurs in SG A which would result in the isolation of automatic AFW flow from MDAFW Pump A and the TDAFW pump (to S/G A only). Only automatic flow from the TDAFW pump to 'G B would be available in this instance. Operator action is already required for a SGTR event to depressurize the RCS. Since this ten minute delay is already assumed in the accident analysis, it can be assumed that time is also available to use the SAFW system or cross-tie MDAFW A to SG B if the TDAFW pump were to fail. In addition, it is noted that the increased SG level in the ruptured SG provides additional time before AFW would be required. |
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| | A review of the Ginna Station PRA indicates that a tube rupture in SG A with a subsequent failure of the TDAFW pump, thus requiring the need for SAFW, is of very low probability (- 1.4E-06 for the additional 2 day MDAFW Pump outage). In addition, the AFW system is in standby during normal power operations. It is not considered prudent to require a plant shutdown through modes in which the preferred AFW system is used to provide normal SG'cooling water needs with one MDAFW pump inoperable. The potential for plant transients and the subsequent need for AFW during these mode transitions is also increased. |
| | MPENSAT RY ACTI N RG&E will not perform any testing or maintenance related to the remaining AFW and SAFW pumps and their necessary support systems during the requested two day extension. In addition, operator awareness of RCS leakage has been increased since leakage can be used as an indication of a potential LOCA or SGTR. The Operations Plan of the Day (POD) has also been revised to enhance operator awareness of the use of the MDAFW pump cross-tie lines if required. |
| | TIFICATI N F R DURATI N OF RE UEST The requested two day LCO extension is necessary to ensure completion repairs on MDAFW Pump B and to perform the required testing. The two day extension is based on the need to complete the alignment of the pump including the speed increaser. Based on previous experience, these activities may require multiple iterations. During this requested extension, three 100% capacity AFW pumps and one 200% capacity TDAFW pump are available to provide the necessary cooling water to the SGs for decay heat removal. As discussed in Section 3, the probability of an accident which requires the AFW pumps during the two day extension is very small. |
| | MDAFW Pump A was successfully tested on August 16, 1994 (Procedure PT-16Q-A) Testing of the TDAFW pump was also successfully performed on August 22, |
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| | 1994 (Procedure PT-16Q-T) providing additional assurance the continued operability of these pumps. Attachment A provides a summary of the most recent AFW and SAFW pump tests. |
| | IGNIFICANT HAZARDS EVALUATION RG&E has evaluated the Enforcement Discretion request and concluded that there is no potential detriment to the public health and safety and that a significant safety hazard is not involved. This basis for this conclusion is summarized below: |
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| | -4 |
| | ,a" Extending the current outage of MDAFW Pump B for approximately two days does not result in a significant increase in the probability or consequences of an accident previously evaluated. The remaining AFW and SAFW pumps provide sufficient redundancy to mitigate all potential accidents. |
| | : b. Extending the current outage of MDAFW Pump 8 for approximately two days does not create the possibility of a new or different kind of accident from any previously evaluated. The only accident which can be initiated by AFW is an overcooling event caused by spurious actuation. Since MDAFW Pump B is not operable, this accident is not credible during the requested extension. No other new or different kinds of accident are created by the plant condition during the two day extension. |
| | C. Extending the current outage of MDAFW Pump 3 for approximately two days does not involve a significant reduction in a margin of safety. The remaining AFW and SAFW pumps provide sufficient redundancy to mitigate all potential accidents. In addition, operators are sufficiently trained and procedures address the response to a loss of MFW. |
| | : 7. NVIR NMKNTALIMPACT There are no environmental releases associated with the current plant condition. The probability of requiring use of the inoperable MDAFW pump is very small. In addition, sufficient guidance is currently available to the operators to respond to any, postulated scenario which would require AFW or the SAFW system. Therefore, there are no environmental consequences associated with this request. |
| | : 8. REVIEW BY RC The Ginna Station PORC has reviewed and approved this request for Enforcement Discretion. |
| | Thomas Marlow Ginna Station PORC Chairman Date |
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| | OVERALL AFW PUMP STATUS CEMENT 4 P/4 P LIMIT VIBRATIONS "A" MDAFWP 1150/1120<'> No Adverse Trends "B" MDAFWP (Pending Rebaseline Test Following Corrective Maintenance - 8/30/94) |
| | Turbine AFWP 1160/1131"> No Adverse Trends "C" SBAFWP 1250/1122~~ No Adverse Trends "D" SBAFWP 1267/1152 No Adverse Trends (1)-Based on NSSL Design Analysis (2)-Based on ASME Section XZ Code Formula |
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Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30
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ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649.0001 TCLEPHONC i~rA coo@. vie 546.2700 August 30, 1994 U.S. Nuclear Regulatory Commission Regional Administrator, Region I Mr. Thomas T. Martin 475 Allendale Road King of Prussia, PA 19406
Subject:
Request For Enforcement Discretion R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Martin,
In accordance with 10 CFR Part 2, Appendix C, and using the guidance contained in NRC Inspection Manual Part 9900, RG&E requests Enforcement Discretion with respect to Ginna Station Technical Specification 3.4.2.1.a. The request, background information, and justification is attached.
This request was initially discussed with the NRC during a conference call on August 20, 1994 at 1600 EST. RG&E received verbal approval of the enclosed Enforcement Discretion during a phone conversation between Mr. William Lazarus NRC, Region I, and Robert Mecredy, Vice President, Nuclear Production at approximately 1720 EST on that same date.
This letter provides all necessary information requested during these two phone conversations.
Very truly yours, Robert C. Mecr y XC: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Assistant Director for Region I Reactors Mr. Jose A. Calvo Washington, D.C. 20555 Ginna Station Senior Resident Inspector
'P4ll030360 94i027 PDR ADaCK 05000244 P PDR
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I. - D CRIPTION F TECHNICAL PECIFICATI N RE UIREMENT Ginna Station Technical Specification (TS) 3.4.2.1 requires that both motor-driven Auxiliary Feedwater (MDAFW) pumps be operable with the RCS temperature M 350'F. Action Statement 3.4.2.1.a states that ifone MDAFW pump is inoperable, the pump must be restored to operable status within 7 days or the plant shall be in at least Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and at an RCS temperature < 350'F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- 2. D CRIPTI N OF RE On August 24, 1994 at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />, MDAFW Pump B was removed from service to perform scheduled testing and maintenance of the associated service water cooling supply strainer and the AC lube oil pump (Procedures EM-785 and M-44.13, and Work Order ¹19400838). The maintenance activities were completed on August 25, 1994 and a limited test was subsequently performed on MDAFW Pump B beginning at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> to verify the operability of the AC lube oil pump breaker. At 1432 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.44876e-4 months <br />, the operators noticed that the normally closed recirculation line air-operated valve (AOV 4310) for MDAFW Pump B did not open as required. The pump was then secured and a trouble card was initiated for AOV 4310 at 1435 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.460175e-4 months <br />.
Preparations were then initiated to perform the repair of AOV 4310. The valve was repaired and a full pump test (Procedure PT-16Q-B) was then performed on August 26, 1994 to verify pump and valve operability. At 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />, it was determined that the MDAFW pump did not meet the ~p requirements and a trouble card was initiated for the pump. Major repairs on MDAFW Pump B were subsequently initiated which included complete disassembly of the pump. It is noted that Procedure PT-16Q-B was successfully performed on MDAFW Pump B on August 18th.
RGB'as conservatively assumed that MDAFW Pump B has been inoperable since August 24, 1994 at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> when initial work activities began and the LCO was entered. However, since repair activities of the pump were not initiated until late on August 26, 1994, and due to the lead time for replacement parts and the need to perform post-maintenance testing, RG&E does not anticipate that the necessary repairs
'and testing can be accomplished within the TS required 7 days. Enforcement Discretion is therefore requested to grant RGB'elief from compliance with the requirements of TS 3.4.2.1.a.
This Enforcement Discretion is requested to begin on August 31, 1994 at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> when the current LCO for TS 3.4.2.l.a will expire. The Enforcement Discretion is requested to end on September 2 at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> when all necessary repair and testing activities will be completed. This is an extension of 50.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
3.. BAST FOR RK T There are a total of five AFW pumps installed at Ginna Station. The preferred AFW system has two 100% capacity MDAFW pumps and one 200% capacity turbine driven (TDAFW) pump. The Standby Auxiliary Feedwater (SAFW) system has two 100% capacity MDAFW pumps which are manually started by the operators if normal AFW is lost (e.g., high energy line breaks in the Intermediate Building).
The safety-related function of the AFW system at Ginna Station is to mitigate the following accidents or events (UFSAR Section 10.5.2.1):
- a. Loss of main feedwater (MFW) with offsite power available
- b. Loss of MFW without offsite power available C. MFW line rupture
- d. Main Steam line rupture
- e. Loss of all AC power (onsite and offsite)
- f. LOCA
- g. Steam Generator Tube Rupture (SGTR)
- h. Cooldown Items c and d have been evaluated for Ginna Station assuming that only the redundant SAFW system is available (UFSAR Section 15.2.7.3) while item e only requires the TDAFW pump (UFSAR Section 15.2.5). Items a and b are bounded by the analysis for the high energy line breaks in the Intermediate Building (i.e., items c and d) due to the available water inventory in the intact SGs. The SAFW system can also be used for cooldown events (item g) due to the time which would be available as a result of low decay heat levels. Consequently, only LOCAs and SGTRs (i.e., items f and g) must be considered with respect to the inoperable MDAFW pump.
Following a LOCA or SGTR, the preferred AFW system will receive an automatic start signal to provide cooling water to the steam generators. However, for all LOCAs, both the TDAFW pump and MDAFW Pump A will be available to provide the necessary cooling water. There is no single failure which can result in the loss of both of these pumps during a LOCA.
In the case of a SGTR, it can be postulated that a rupture occurs in SG A which would result in the isolation of automatic AFW flow from MDAFW Pump A and the TDAFW pump (to S/G A only). Only automatic flow from the TDAFW pump to 'G B would be available in this instance. Operator action is already required for a SGTR event to depressurize the RCS. Since this ten minute delay is already assumed in the accident analysis, it can be assumed that time is also available to use the SAFW system or cross-tie MDAFW A to SG B if the TDAFW pump were to fail. In addition, it is noted that the increased SG level in the ruptured SG provides additional time before AFW would be required.
A review of the Ginna Station PRA indicates that a tube rupture in SG A with a subsequent failure of the TDAFW pump, thus requiring the need for SAFW, is of very low probability (- 1.4E-06 for the additional 2 day MDAFW Pump outage). In addition, the AFW system is in standby during normal power operations. It is not considered prudent to require a plant shutdown through modes in which the preferred AFW system is used to provide normal SG'cooling water needs with one MDAFW pump inoperable. The potential for plant transients and the subsequent need for AFW during these mode transitions is also increased.
MPENSAT RY ACTI N RG&E will not perform any testing or maintenance related to the remaining AFW and SAFW pumps and their necessary support systems during the requested two day extension. In addition, operator awareness of RCS leakage has been increased since leakage can be used as an indication of a potential LOCA or SGTR. The Operations Plan of the Day (POD) has also been revised to enhance operator awareness of the use of the MDAFW pump cross-tie lines if required.
TIFICATI N F R DURATI N OF RE UEST The requested two day LCO extension is necessary to ensure completion repairs on MDAFW Pump B and to perform the required testing. The two day extension is based on the need to complete the alignment of the pump including the speed increaser. Based on previous experience, these activities may require multiple iterations. During this requested extension, three 100% capacity AFW pumps and one 200% capacity TDAFW pump are available to provide the necessary cooling water to the SGs for decay heat removal. As discussed in Section 3, the probability of an accident which requires the AFW pumps during the two day extension is very small.
MDAFW Pump A was successfully tested on August 16, 1994 (Procedure PT-16Q-A) Testing of the TDAFW pump was also successfully performed on August 22,
~
1994 (Procedure PT-16Q-T) providing additional assurance the continued operability of these pumps. Attachment A provides a summary of the most recent AFW and SAFW pump tests.
IGNIFICANT HAZARDS EVALUATION RG&E has evaluated the Enforcement Discretion request and concluded that there is no potential detriment to the public health and safety and that a significant safety hazard is not involved. This basis for this conclusion is summarized below:
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,a" Extending the current outage of MDAFW Pump B for approximately two days does not result in a significant increase in the probability or consequences of an accident previously evaluated. The remaining AFW and SAFW pumps provide sufficient redundancy to mitigate all potential accidents.
- b. Extending the current outage of MDAFW Pump 8 for approximately two days does not create the possibility of a new or different kind of accident from any previously evaluated. The only accident which can be initiated by AFW is an overcooling event caused by spurious actuation. Since MDAFW Pump B is not operable, this accident is not credible during the requested extension. No other new or different kinds of accident are created by the plant condition during the two day extension.
C. Extending the current outage of MDAFW Pump 3 for approximately two days does not involve a significant reduction in a margin of safety. The remaining AFW and SAFW pumps provide sufficient redundancy to mitigate all potential accidents. In addition, operators are sufficiently trained and procedures address the response to a loss of MFW.
- 7. NVIR NMKNTALIMPACT There are no environmental releases associated with the current plant condition. The probability of requiring use of the inoperable MDAFW pump is very small. In addition, sufficient guidance is currently available to the operators to respond to any, postulated scenario which would require AFW or the SAFW system. Therefore, there are no environmental consequences associated with this request.
- 8. REVIEW BY RC The Ginna Station PORC has reviewed and approved this request for Enforcement Discretion.
Thomas Marlow Ginna Station PORC Chairman Date
OVERALL AFW PUMP STATUS CEMENT 4 P/4 P LIMIT VIBRATIONS "A" MDAFWP 1150/1120<'> No Adverse Trends "B" MDAFWP (Pending Rebaseline Test Following Corrective Maintenance - 8/30/94)
Turbine AFWP 1160/1131"> No Adverse Trends "C" SBAFWP 1250/1122~~ No Adverse Trends "D" SBAFWP 1267/1152 No Adverse Trends (1)-Based on NSSL Design Analysis (2)-Based on ASME Section XZ Code Formula
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