Similar Documents at Ginna |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999
Proposed Tech Specs,Consisting of 1999 Changes to TS Bases
ML17265A6941999-06-28028 June 1999
Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping
ML17265A6401999-05-12012 May 1999
Rev 11 to Technical Requirements Manual for Ginna Station.
ML17265A6261999-04-18018 April 1999
Rev 10 to Technical Requirements Manual (Trm), for Ginna Station
ML17311A0701999-04-14014 April 1999
Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
ML17309A6521999-04-14014 April 1999
Rev 14 to AP-RCS.1, Reactor Coolant Leak.
ML17309A6531999-04-13013 April 1999
Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr
ML17265A6111999-03-26026 March 1999
Rev 9 to Technical Requirements Manual for Ginna Station.
ML17265A5911999-03-0101 March 1999
Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6)
ML17265A5571999-02-25025 February 1999
Rev 4 to Technical Requirements Manual (Trm).
ML17265A5491999-02-12012 February 1999
to EOP FR-H.5, Response to SG Low Level.
ML17265A5481999-02-12012 February 1999
to EOP ATT-22.0, Attachment Restoring Feed Flow.
ML17265A5461999-02-12012 February 1999
0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required.
ML17309A6481999-01-25025 January 1999
Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr
ML17265A5151999-01-14014 January 1999
Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index
ML17265A5081999-01-0808 January 1999
Rev 7 to Technical Requirements Manual, for Ginna Station
ML17265A4961998-12-18018 December 1998
Rev 6 to Technical Requirements Manual.
ML20198C0361998-12-14014 December 1998
Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required
ML20198C0121998-12-14014 December 1998
Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow
ML20198C0581998-12-14014 December 1998
Rev 5 to FR-Z.1, Response to High Containment Pressure
ML20198C0411998-12-14014 December 1998
Rev 16 to FR-C.1, Response to Inadequate Core Cooling
ML20198C0521998-12-14014 December 1998
Rev 13 to FR-S.1, Response to Reactor Restart/Atws
ML17265A4661998-11-24024 November 1998
Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR
ML20155G0301998-10-30030 October 1998
Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop
ML17265A4091998-08-24024 August 1998
Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr
ML17265A3721998-07-16016 July 1998
Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr
ML17265A3151998-06-0404 June 1998
Proposed Tech Specs Basis Re Main Steam Isolation Setpoint
ML17265A2941998-05-21021 May 1998
Tech Specs Consisting of Submittal Changes for 1998
ML17265A2861998-05-0606 May 1998
Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr
ML17265A2461998-04-27027 April 1998
Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool
ML17265A1821998-02-20020 February 1998
Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria.
ML17265A1491997-12-31031 December 1997
Rev 1 to Inservice Testing Program.
ML17264B0731997-10-14014 October 1997
Rev 4 to Technical Requirements Manual (TRM) for Ginna Station.
ML17264B0671997-10-0808 October 1997
Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements
ML17264B0441997-09-29029 September 1997
Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept
ML17264B0391997-09-29029 September 1997
Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study
ML17265A1541997-09-16016 September 1997
Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification.
ML17264B0031997-08-19019 August 1997
Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3
ML17264A9991997-08-19019 August 1997
Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values
ML17264A9791997-08-0505 August 1997
Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
ML17264A9781997-08-0505 August 1997
Rev 12 to AP-RCS.1, Reactor Coolant Leak.
ML17264A9771997-08-0505 August 1997
Rev 11 to AP-RCP.1, RCP Seal Malfunction.
ML17264A9751997-08-0505 August 1997
Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
ML17264A9851997-08-0404 August 1997
Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
ML17264A9391997-07-0707 July 1997
Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
ML17264A9341997-07-0101 July 1997
to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624
ML17264A9461997-06-20020 June 1997
to Inservice Insp (ISI) Program.
ML17264A9241997-06-0303 June 1997
Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection
ML17311A0471997-05-22022 May 1997
Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr
ML17264A8671997-04-24024 April 1997
Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements
1999-06-28
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17265A6401999-05-12012 May 1999
Rev 11 to Technical Requirements Manual for Ginna Station.
ML17265A6261999-04-18018 April 1999
Rev 10 to Technical Requirements Manual (Trm), for Ginna Station
ML17309A6521999-04-14014 April 1999
Rev 14 to AP-RCS.1, Reactor Coolant Leak.
ML17311A0701999-04-14014 April 1999
Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
ML17309A6531999-04-13013 April 1999
Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr
ML17265A6111999-03-26026 March 1999
Rev 9 to Technical Requirements Manual for Ginna Station.
ML17265A5571999-02-25025 February 1999
Rev 4 to Technical Requirements Manual (Trm).
ML17265A5481999-02-12012 February 1999
to EOP ATT-22.0, Attachment Restoring Feed Flow.
ML17265A5491999-02-12012 February 1999
to EOP FR-H.5, Response to SG Low Level.
ML17265A5461999-02-12012 February 1999
0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required.
ML17309A6481999-01-25025 January 1999
Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr
ML17265A5151999-01-14014 January 1999
Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index
ML17265A5081999-01-0808 January 1999
Rev 7 to Technical Requirements Manual, for Ginna Station
ML17265A4961998-12-18018 December 1998
Rev 6 to Technical Requirements Manual.
ML20198C0581998-12-14014 December 1998
Rev 5 to FR-Z.1, Response to High Containment Pressure
ML20198C0361998-12-14014 December 1998
Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required
ML20198C0521998-12-14014 December 1998
Rev 13 to FR-S.1, Response to Reactor Restart/Atws
ML20198C0411998-12-14014 December 1998
Rev 16 to FR-C.1, Response to Inadequate Core Cooling
ML20198C0121998-12-14014 December 1998
Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow
ML20155G0301998-10-30030 October 1998
Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop
ML17265A4091998-08-24024 August 1998
Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr
ML17265A3721998-07-16016 July 1998
Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr
ML17265A2861998-05-0606 May 1998
Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr
ML17265A1821998-02-20020 February 1998
Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria.
ML17265A1491997-12-31031 December 1997
Rev 1 to Inservice Testing Program.
ML17264B0731997-10-14014 October 1997
Rev 4 to Technical Requirements Manual (TRM) for Ginna Station.
ML17265A1541997-09-16016 September 1997
Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification.
ML17264A9751997-08-0505 August 1997
Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
ML17264A9771997-08-0505 August 1997
Rev 11 to AP-RCP.1, RCP Seal Malfunction.
ML17264A9791997-08-0505 August 1997
Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
ML17264A9781997-08-0505 August 1997
Rev 12 to AP-RCS.1, Reactor Coolant Leak.
ML17264A9851997-08-0404 August 1997
Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
ML17264A9391997-07-0707 July 1997
Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
ML17264A9341997-07-0101 July 1997
to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624
ML17264A9461997-06-20020 June 1997
to Inservice Insp (ISI) Program.
ML17311A0471997-05-22022 May 1997
Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr
ML20140B8291997-03-24024 March 1997
Rev 3 to EOP ATT-12.0, Attachment N2 Porvs
ML17264A8221997-02-0606 February 1997
Rev 15 to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.
ML17264A8201997-02-0606 February 1997
Rev 7 to AP-RCC.2, Rcc/Rpi Malfunction.
ML17264A8081997-01-23023 January 1997
Revised Emergency Operating Procedures,Including Rev 14 to E-1,Rev 19 to E-3,Rev 14 to ECA-2.1,Rev ECA-3.3,Rev 20 to ES-1.3,Rev 13 to FR-C.1,Rev 12 to FR-C.2 & Rev 14 to FR-P.1
ML20133N3351997-01-10010 January 1997
Rev 7 to FR-C.3, Response to Saturated Core Cooling
ML17264A8881996-10-10010 October 1996
Rev 9 to ODCM for Ginna Station.
ML20128N0681996-10-0303 October 1996
Revised Emergency Operating Procedures,Including Rev 5 to Att-10.0, Attachment Faulted S/G & Rev 6 to Att-16.0, Attachment Ruptured S/G
ML17264A5311996-05-31031 May 1996
Revised Emergency Operating Procedures,Including Rev 10 to AP-RCP.1,Rev 12 to ECA-0.1,Rev 12 to ECA-2.1,Rev 3 to FR-H.2,Rev 3 to FR-H.4,Rev 7 to FR-I.1,Rev 12 to FR-P.1,Rev 10 to FR-S-1 & Rev 6 to FR-S.2
ML17264A5161996-05-22022 May 1996
Rev 2 to Technical Requirements Manual (TRM)
ML17264A4581996-04-0808 April 1996
Rev 7 to ODCM for Ginna Station.
ML17264A4371996-04-0101 April 1996
Rev 1 to Technical Requirements Manual (TRM)
ML17264A4391996-04-0101 April 1996
Rev 1 to Updated Technical Requirements Manual (TRM)
ML17264A4191996-02-24024 February 1996
Rev 0 to Technical Requirements Manual (Trm).
ML17264A6901996-02-23023 February 1996
Rev 0 to Inservice Testing Program.
1999-05-12
[Table view] |
Text
CATEGORYj.REGULATINFORMATIONDISTRIBUTIONOZSTEM(RIDE)ACCUS(IONNBR:9610180150DOC.DATE:96/02/23NOTARIZED:NODOCKETFA(:IL:50-244RobertEmmetGinnaNuclearPlant,Unit1,RochesterG05000244AUTH.NAMEAUTHORAFFILIATIONMULLER,K.A.RochesterGas&ElectricCorp.RECIP.NAMERECIPIENTAFFILIATION
SUBJECT:
Rev0to"InserviceTestingProgram."DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLTITLE:ORSubmittal:GeneralDistributionSIZE:NOTES:LicenseExpdateinaccordancewith10CFR2,2.109(9/19/72).A'5000244TiRECIPIENTIDCODE/NAMEPD1-1LAVISSINGFG.INTERNA.-CENTER1NRR/SR'/HICBNRR/DSSA/SRXBOGC/HDS3EXTERNAL:NOACCOPIESLTTRENCL11111111111011RECIPIENTIDCODE/NAMEPD1-1PDNRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDRCOPIESLTTRENCL1111111111DENOTETOALLMRIDSNRECIPIENTS:PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083TOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCL11' 4Iv'<
TO:FROM:Cnty,GuyKissing,NRC(301)415-2102MarkI'laherty,RAFF.(716)724-8512ci1&al¹'I.i)i'.elllg<(~ggpssIamEaringyouthefollowinginforination:One-ItnedtagramsoftheSafutyInicctrongJ)andConrarnnrenthpnry(CS)sv~Ccrns~Hdchrhombirhesirblocth&t.s(8o;andb'28),ThmcvalvesarcrequiredtobeopenduringpoweroperationsincethcPSPASsignaiwithrespecttoRCSpressurecanactuatetheSipumpspriortorcachiigtheshtttoft'eadofthcSIpuaps(1700iisigveiiuis14tlnpsig').Thercforc,nutintainingthcMOVsopenensuresthattheSIpimpsarenotdcadltcadcdduringthetimeframeittakesfnrtheR('.Sprvssuietodropfrotn1700psigto1400paid.Thevalveareabriieiiilhediob>>capableofclosingduringuseoftheSIsystemforhigh-lieadiechimitationTheii:,closureoftheMOVspreventstheadditionofliighlpiadhm:livesiimliiluiritotheRNST.PerTechnicalSpwificationsLCO'3.5,2and3S'1,atlealoiieSIiiiunniustbeoperableabove2009.(2)CuopoftheGinnaStationISTPro@amMrhRespecttoMOV~8PCfroid'8>6',Asshownontheone-linediagrams,hdOVs896Aand8'rovidesuctiontotheSIend'CSsystems.PerColdShutdown1ustificationCS.I",Nil;8onlycxccrciscsthesevalves.duringcoldshutdownsinceclosureoftheMVVsrendersbothSlandCBinnpersh1e,ThisisverysimilartothcN7and898valves.{3)(,'osoftheMCSZR1PhichAp~ovcdth>>CarrantICTPnigncmFurCiilma,Thereisonlyasinglesentencevhichapilrove%CS17.BasedontLieabove,llieieisiu~~enfantforonlynerclslng897and898atcoldshutdove,ThenextIeilulleiltali.i>ftheievalvesis11(11/96(incJudes25",oextension).Ifthealternatetestingf'reyiencyicnotluovidedbyIbisdate,R68rEwouldbeforcedtoenterLCO3.0.3toperfortnianAShKtequiradtestorshutdownGinna.Cng$0cCigill"'8003.39bi0280i50960223PDRADGCK05000244PPDR' GINNAPSASYSTEMV/ORKPACKAGEPSA-06CONTAINlVlENTSPRAYSYSTEMTSI01IRVfST)FigureA-1REVISION0APPENOIXA'AGE2OF2oIILDlOQll9GlCVCSRHRRMRIc~~LRUlg~t'do~+QDSSSA$88$(~C$8I~t&CASI831A856AUpperOorrraInnrantSprayRIny180NcnloeI9pomAzmzAcrzOI+931)1SIO8IN~5N)881C1$Sl8DWEdrrclor841A&l788318$600CharooelFootACharooalRherB-QyrSA-Qy8$.P76$888--tovrer=----"-"rOMlQCVlHhJPSI01$A880CConlelnrneraSprayRlnpI88Hanleel882$
913814iS2182P.83lS4OINSERYICETESTING.PROGRAMRevision0Page1of87j~,I\II~<I~I~!XNSERVXCE'XXST1NGPROGRAMEffectiveDate:Preparedhy:Date:a1~QualityAssuranceReviewhy:l~iJApprovedby:Date:~Co!AT<OLL~'gCuPY.NO 913814152182P.84INSERV(CETESTlNGPROGRAMRevision0Page19'of87CS-15aValves852Aa8areResidualHeatRemoval(RHR)dischargemotoroperatedvalvestotheroactorvessel.Thosevalvesopentoprovidesafetyinjectionflowto%hereactorvs~eel.Thesevalvesshouldnotbcexercisedduringno'rmalpoweroperationasthiswouldreducethesystemtosingle-valve-protectionbetweentheRCSandRHRsystemandcouldresultinanintersystemLOCAoutsideofcohtainmont.Testingwillboperformeddurhsgauldshutdown.IC-16:Deleted(663A/BaraaddressedlhVR-3}<<~ceoCS-17:Valves896A0BareRefuelingRaterStorageTank(RWSoutlet.isolationvalves.Exercisingthesevalvesduringpoweroperationisimpractical.Pai3.ureofoneofthesevalvesintheclvsedpositionduringpoweroperationwouldrenderbothcontainmentsprayandsafetyin)ectiontrainsinoperablewhichwouldrequireshuttingdownthereactorsTestingwillbeperformedduringcoldshutdown.CS-18CS19:Valve702providesaflowpathfromtheResidualHeatRemoval(RHR)dischargelinetotheletdownheadeijurorpressurerelief,Exercisingthischeckvalvedurj.ngpoweroperationwouldrequireisolatingletdownwhichcouldresultinlossofpressurizerlevelcontroland,causeareactortrip.Testingwillbeperformedduringcoldshutdown.Valves1819AthruGarecontainmentpressuretv.ansmitterisolationvalves.Thesenormallyopenvalvesarecontainmentisolationvalves.Rxazcisingthesavalvesduringpoweroperationcandisableassociatedpressurechannelsandcauseaplanttripfunctionto;beinoperable.Testingwillbeperformedduringcoldshutdown.CS-20:Deleted(A4'fq)
~aI+Coy+(sa~ypgODocket/to.JO-R44t~eggCOPYUNTKOSTATNVCLEARREGULATORYCOQMNSNNWAQiIICANoc~April55,1991%&A%(JgQ'lfl~gIS11CertifiedBy-ZAQefZlir.Robertc,liacredy,YicePresidentpinnaNuclearProductionPV5LIIRepeatereas$ClectricCOrporation89KastAvenueRochester,NewYork1%Say
DearNr,
5(ccredyiswamir..x.ewewcl.sepoutspueIascavlcsTuTue(IsTlpeeawfORP(95PSNDYALYES,NltI1999THIRD10VKARIKKRYAL(TACNO.73380)lyletterdatedHay23,1989,andsuhsayentlettersdatedOctober,27,3989;Februaryl5,Marchla,Anril6~Aprillie1990>andJanuaryRt,IMIROCheaterOasandDectHcCorporation.subiaittedtotheNRC'thaISTPvagraaeduMitionalinforiationforthe1STPmiai,thi&ID-yearinterval,atthe0,K.NnnaNuclearpmcrPlant.TheMAChasreviewedandevaluatedthepro9raaandadditionalinfor¹atienprovided.TheenclosedsafetyKvaluation(sE)uaspreparedbytheNcto'providetheresultsofthestaffreeien.'heCOdeofFederalRe9ulations,IbCFR'N,55a(g).~virescabinClassI,2,and3pu¹psandvalvesiauater~ledauclear.NicerfacilitiestoeieettheinservtcetestingraqairweatsstatedihtaaAs¹KBoiledandpressureYasselcode(code)sectionRl>specificallysahsectfonLo.'Ia-serviteTestingofPuiapsin%ac'fearposerplants~andSuhaeCtionIltvg"InserviceTestinyofYalves<nlluclearPeerPlanta.'acilfac111>1steqelredtoestablishapro9raaforthe<nservicetestia9of~sandvalves1555thfaopdŽaiedevarftenyearsto¹aotthetequircmaisiathelatestagewHe4100aandaddm4toSection0oftheCode.Thearogranissuh¹ittadtotheMforrivfNSedaPPrevalOfthereliefreqaaata.TheraVtauaaQilaVerifyingtlatthePrONra¹iSbasedantheapplicablecodeeditionaadaddenda,varigiaItaatall~sandve'ivesincludedintheprogramarasubfaete4toiatapetio45csessions+4verifyin9tseeacceptabilityoftherequestsfarri5free~reqe5~tsofSubsectionsIlIPandIN.TheISTproaraiai54ad41tionalfnfor¹atioaaddressedinthisevalwt1eeceVerstheintervalfro¹JanuaryI1990throu9hOeceetiel31~I%8404suliersedesallpreV5NSISTPPOgraasabait4ls.aasaestQAo1104thmmCI(iale9PY3)J~~IICgeNA55E~~r5eewoseear~k:Aboheson.~oe'a7,+ftiSShan/act;iv)q~anat+oeeosorsss<<roeRe~$osooo~sesssees]seeiso<<+i/9155$O/91g4/91+/i/91~ibocuninnt8aeie:TAC73380 913814152182P.86testingrendu)rementsapplyonlytocomponenttesting().e.~Pumpsandvalves)andarenotintendedtoprovidethebasistochangethe1)censee'scurrentTechnicalSpecificationsforsysteltestrequireients.Section8ofthisreportpresentstheRochesterSasandE>ect&cCorporationbasesforrequestingrelieffroltheSectionNlrequirementsfortheRobertE.GonnaNuclearPowerplantpulptestingprograaandtherev)ewer'sevaluat)onsandconclusionsregardingtheserequests.Sim)laiinformation)spresentedinSection3forthevalvetestingprogram.!!.!~!!JustiBeat)onsforexercisingCategoryA,B,andCvalvesduringcoldshutdownsandrefuelingautagesinsteadofquarterlydur)ngpoweroperationswerereviewedandfoundacceptableexceptasnotedinAppendixA.Inconsistenciesandomissionsinthelicensee'sISTprogramnoteddu~ingtheCOurSeOfthiSreViewareliStedinAppends@A.TheliCenseeSheuldresolvetheseitemsinaccordancewiththeevaluations,conclusions,andguidelinespresentedinthfsreport, TO913814152182P.87~~rAprillS,1991TheHRCstaffwithtechnicalassistancefroidF656IdahoInc.{E616),hasreviewedandevaluatedtheISTProgralandrequestsforreliefsubafttedfortheRobertE.GfnnaNuclearPowerplant.Thestaffadoptstheevaluatfonsand,conclusionscontainedintheTechnicalEvaluationReport(TER)preparedbyKCLC.TheenclosedSKincorporatestheTERwhichisattachedtothisSK.Nearerecasaendfngthatrelfefbegrantedfrythetestfngrtaufresentswhfchwehavedeter3afnedwouldbefipracticaltoperform,wherecoap1(ancewouldresultinahardshipwithoutac~ensatfngincreaseinsafetyandwheretheproposed*alternativetestingprovidesanacceptablelevelofqualityandsafety.Me.havedeterminedthattheISTProgramreliefrequestsareacceptableforfipleiantatfonprovidedtheitems(dentfffedfnAppendixAoftheTER(Attachaent2OftheEnclosure)areaddressedwithinthetimefraoespecifiedintheenclosedSE.ThelicenseeisrequiredtocomplywiththeISTProgramdefinedintheabovereferencedletterswherereliefhasbeengrantedintheenclosedSE.ESTprogramchangessuchesadditionalreliefrequestsorchangestoapprovedreliefrequestsshouldbesubmfttcdforstaffreviewbutshou1dnotbeimp'leaentedPriortorevfewandapprovalbytheNRC.NeworrevisedreliefrequestsaeetfngtheposftfonsinGenericletter(GL)89-04(6L89-04Enclosure1),shouldbesubinfttedtotheNRCstaffbutcanbeimplementedprovidedtheguidancein6LSS44,Section6,isfollowed.1STProgramchangesthatinvolveadditionsordelationsofconsonantsfromtheISTProgramshouldbeprovidedtotheNRC.ThissubmittalcompletesthetechnicalreviewperformedbytheNRCstaffunderTACNumber73380.Sincerely,
Enclosure:
AsStated,ccwfenclosur'e:SeenextpageQrfgfnalsignedhyAllenR.Johnson,Pro5ectHanagerProjectDfrectorateI-3DivisionofReactionPro5ectsI/IIOfficeofNuclearReactorRegulatfon0:D-rrrrrrrrrrvSLHFok<<rvrr~rrrrrroorrrrDATE:P/NmDocumentName:TAG73380~ravrvrvovrooorrvrrrrrrr~rrroorrrrrrrrvrchaohoooo.~hoooOg,g/oNhoolooo:~~rrrrvrrvrrrrr+rrrrrrrrrrrroroorrvprrorrrrrorrrrsoorkrsrroor:L8>lot:$4III+l(5/l'L
~.t GINNAPSASYSTEMWORKPACKAGEPSA-08SAFETYINJECTIONSYSTEM1REVISION0*APPENDIXA:PAGE2OF8Xf~~0Pi~maA-1TSIOSA{Aoeuor.lRWSTStyOtOAPSNIA3116116nS$TASo7CstrrA)69IA7SFSI$IICSloop8HotlryRCSloop8CddbyTram81StSS1$16A$9IB$$6T810$8(Aooarn.)5858258'FIe691C66180(9..IBOB)g<e3MB95IOteSTm3788Iys'PCSloctrA-Not.log.37RCSlootharidbg
