Similar Documents at Ginna |
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Category:TECHNICAL SPECIFICATIONS
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
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)
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
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
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
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
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
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
ML17264A9241997-06-0303 June 1997
Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection
ML17264A8671997-04-24024 April 1997
Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements
ML17264A8491997-03-31031 March 1997
Proposed Tech Specs 3.7.12 Re Spent Fuel Pool Boron Concentration
ML17264A7601996-12-16016 December 1996
Proposed Annual TS Bases
ML17264A7131996-10-29029 October 1996
Proposed Tech Specs Re Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump
ML17264A6001996-09-13013 September 1996
Proposed Tech Specs Re RCS Pressure & Temp Limits Rept
ML17264A5301996-06-0303 June 1996
Proposed Tech Specs Re Update to Correction of Typographical Error Request
ML17264A5111996-05-29029 May 1996
Proposed Tech Specs Pages 3.3-18 & 3.3-19,reflecting Revs to LCO 3.3.1
ML17264A4711996-05-0808 May 1996
Proposed Tech Specs,Correcting Typos
ML17264A4081996-03-20020 March 1996
Proposed Tech Specs 3.9.3,Containment Penetrations Re Use of Roll Up Door & Associated Encl Building for LCO 3.9.3 Requirements
ML17264A4051996-03-15015 March 1996
Proposed Tech Specs Changing Section 5.6.6 Page 5.0-22 to Incorporate Methodology for Determining RCS P/T & LTOP Limits Into Administrative Controls Section for RCS P/T Limits Rept
ML17264A3451996-02-0909 February 1996
Proposed Tech Specs,Revising Setpoints for SG Water Level High Feedwater Isolation Function
ML17264A3401996-02-0909 February 1996
Proposed Tech Specs Re LTOP Limits Using Util Proposed Methodology
ML17264A3341996-02-0909 February 1996
Proposed Tech Specs Containment Requirements During Mode 6 Cost Beneficial Licensing Action
ML17264A3231996-01-26026 January 1996
Proposed Tech Specs Re Nuclear Fuel Cycle for NRC Approval
ML17264A2811995-12-0808 December 1995
Proposed Tech Specs Re Changes to Current RCS Pressure & Temp Limits for Heatup,Cooldown,Criticality & Hydrostatic Testing
ML17264A2531995-11-27027 November 1995
Proposed Tech Specs for Implementation of 10CFR50,App J, Option B
ML17264A2571995-11-20020 November 1995
Proposed Tech Specs,Discussing Changes to TS Instrumentation Requirements & Conversion to Improved TS
ML17264A2491995-11-20020 November 1995
Proposed Tech Specs Re Ventilation Filter Testing Program
ML17264A1511995-08-31031 August 1995
Proposed Tech Specs Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS
ML17263A9781995-03-13013 March 1995
Proposed Tech Specs to Revise TS 4.4.2.4.a,replacing Specific Leakage Testing Frequencies for Containment Isolation Valves
ML17263A7901994-09-27027 September 1994
Proposed TS Section 6.0, Administrative Controls.
ML17263A7281994-07-15015 July 1994
Proposed Tech Specs Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431
ML17263A6581994-05-23023 May 1994
Proposed Tech Specs,Increasing Allowable Reactor Coolant Activity Levels
ML17263A6431994-05-13013 May 1994
Proposed Tech Specs Administrative Section 6.0
ML17263A3701993-08-20020 August 1993
Corrected Proposed TS Page 5.1-1,changing Word Released to Leased
ML17263A3571993-08-0606 August 1993
Proposed Tech Specs Re Alternative Requirements for Snubber Visual Insp Intervals
ML17263A3191993-07-15015 July 1993
Proposed Tech Specs,Removing Containment Isolation Valve Table 3.6-1 from TS
ML17263A2101993-04-0505 April 1993
Proposed TS Table 3.6-1, Containment Isolation Valves.
ML17262B1191992-12-17017 December 1992
Proposed Tech Specs Sections 3.2 & 3.3 Re Acid Storage Tank Boron Concentration Reduction Study
ML17309A5021992-11-30030 November 1992
Proposed Tech Specs Reflecting Removal of Table of Containment Isolation Valves
ML17262B0441992-10-0808 October 1992
Proposed TS 3.7.1 Re Auxiliary Electrical Sys
ML17262B0211992-09-15015 September 1992
Proposed Tech Specs Sections 3.1.1.4,3.1.1.6 & 4.3.4, Addressing GL 90-06, Resolution of Generic Issue 70, 'Porv & Block Valve Reliability' & Generic Issues 94, 'Addl LTOP for Lwrs.'
ML17262A9141992-06-22022 June 1992
Proposed TS 4.3.1 Re Reactor Vessel Matl Surveillance Testing
ML17262A8321992-04-23023 April 1992
Proposed Tech Specs Re Snubber Visual Insp Schedule
ML17262A8221992-04-21021 April 1992
Proposed Tech Specs Re Fire Protection Program
ML17262A7871992-03-23023 March 1992
Proposed Tech Spec Revising Section 6.5.1 Re Plant Operations Review Committee Function
ML17262A7911992-03-20020 March 1992
Proposed Tech Specs Revising 6.9.1.2 & 6.9.2.5
1999-06-28
[Table view]
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] |
Text
Attachment IVR.E.GinnaNuclearPowerPlantIncludedpages:4.0-15.0-205.0-21Mark-upofExistingGinnaStationTechnical Specifications 98i2070083 98ii24PDRADQCK05000244PPGR J
DesignFeatures4.04.0DESIGNFEATURES4.1SiteLocationThesitefortheR.E.GinnaNuclearPowerPlantislocatedonthesouthshoreofLakeOntario,approximately 16mileseastofRochester, NewYork.Theexclusion areaboundarydistances fromtheplantshallbeasfollows:Direction N(including offshore)
NNENEENEEESESESSESSSWSWWSWWWNW'WNNWDistancem800080008000,8000747640503450450450503915945701800080004.2ReactorCore4.2.1FuelAssemblies cHo<z.irc~loyjZ%<~~>~c"~ANThereactorshallcontain121fuelasseblies.Eachassemblyshallconsistofamatrixofzircalloy cladfuelrodswithaninitialcomposition ofnaturalorslightlyenricheduraniumdioxide(UO,)asfuelmaterial.
Limitedsubstitutions ofzircon~urn aoorstainless steelfillerrodsforfuelrods,inaccorancewithapprovedapplications offuelrodconfigurations, mayeuse.Fuelassemblies shallbelimitedtothosefueldesignsthathavebeenanalyzedwithapplicable NRCstaffapprovedcodesandmethodsandshownbytestsoranalysestocomplywithallfuelsafetydesignbases.Alimitenumberofleadtestassemblies thathavenotcompleted reprsentative testingmaybeplacedinnonlimiting core.regions.eyeesp~(continued)
R.E.GinnaNuclearPowerPlant4.0-1Amendment No.61 11 Reporting Requirements 5.65.6Reporting Requirements 5.6.5COLR(continued) b.Theanalytical methodsusedtodetermine thecoreoperating limitsshallbethosepreviously reviewedandapprovedbytheNRC,.specifically thosedescribed inthefollowing documents:"
1.WCAP-9272-P-A, "Westinghouse ReloadSafetyEvaluation Methodology,"
July1985.(Methodology forLCO3.1.1,LCO3.1.3,LCO3.1.5,LCO3.1.6,LCO3.2.1,LCO3.2.2,LCO3.2.3,andLCO3.9.1.)2.3.WCAP-9220-P-A, "Westinghouse ECCSEvaluation Model-1981 Version,"
Revision1,February1982.(Hethodolog forLCO3.2.1.)WCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures
-TopicalReport,"'September 1974.(Methodology forLCO3.2.3.)4.WCAP-8567-P-A, "Improved ThermalDesignProcedure;"
February1989.(Hethodology forLCO3.4.1wheusinP.5.WCAP11397-P-A, "RevisedThermalDesignProcedure,"
April1989.(Methodology forLCD3.4.1'henusingRTDP.)~n6.'CAP-'10054-P-A andWCAP-1008+
"Westinghouse SmallBreakECCSEvaluation ModelUsingtheNOTRUMPCode,"August1985.(Methodology forLCO3.2.1)p~U~'"~c.i>>.WCAP-10924-P-A, Volume1,.1,andAdden1,2,3,"Westinghouse Large-Break LOCABest-Estimate Methodology, Vo1:ModelDescription anda>aso,"December1988.(Hethodology forLCO3.2;1)C.t.l8.WCAP-10924-P-A, Volume2,.2,andnda"Westinghouse Large-Break LOCABest-stimateMethodology, Volume2:Application toTwo-LoopPWRsEquippedwithUpperPlenumInjection,"
December8.(Methodology forLCO3.2.1)(continued)
R.E.GinnaNuclearPowerPlant5.0-20Amendment No.61 eportingRequirements 5.65.6Reporting, Requirements.
5:6.5(g~d~Revs'Sia~)~wcWCAP-10924-P olume1,1,Addenum4,"WethousOCABest-stimateMethodology Modelascription andValidation ModelRevisions,"
~ugus990Pldrdkl1%I(ethodology forLCO3.2.1)COLR(continue 9.WCAP-10924-P-A, Rev.2andWCAP-12071, "Westinghouse Large-Break LOCABestEstimateMethodology, Volume2:Application toTwo-LoopPWRsEquippedWithUpperPlenumInjection, Addendum1:Responses toNRCguestions,"
December1988.Hethodolo yforLCO3.2.1)C.Thecoreoperating limitsshallbedetermined suchthatall'pplicable limits(e.g.,fuelthermalmechanical limits,corethermalhydraulic limits,Emergency CoreCoolingSystems(ECCS)limits,nuclearlimitssuchasSDH,transient analysislimits,andaccidentanalysislimits)ofthesafetyanalysisaremet.d.TheCOLR,including anymidcyclerevisions orsupplements, shallbeprovideduponissuanceforeachreloadcycleto"theNRC.5.6.6ReactorCoolantSstemRCSPRESSUREANDTEMPERATURE LIMITS~RTPLa~b.RCSpressureandtemperature limitsforheatup,cooldown, criticality, andhydrostatic testingaswellasheatupandcooldownratesshallbeestablished anddocumented inthePTLRforthefollowing:
LCO3.4.3,"RCSPressureandTemperature (P/T)Limits"ThepoweroperatedreliefvalveliftsettingsrequiredtosupporttheLowTemperature Overpressure Protection (LTOP)System,andtheLTOPenabletemperature shallbeestablished ariddocumented inthePTLRforthefollowing:
LCO3.4.6,"RCSLoops-MODE4";LCO3.4.7,"RCSLoops-MODE5,LoopsFilled";LCO3.4.10,"Pressurizer SafetyValves";andLCO3.4.12,"LTOPSystem."(continued)
R.E.GinnaNuclearPowerPlant5.0-21Amendment No.61 Ik INSERT1WCAP-13677-P-A, "10CFR50.46Evaluation ModelReport:WCOBRA/TRAC Two-LoopUpperPlenumInjection ModelUpdatestoSupportZIRLOCladdingOption,"February1994.(Methodology forLCO3.2.1).INSERT2WCAP-12610-P-A, "VANTAGE+FuelAssemblyReference CoreReport,"April1995.(Methodology forLCO3.2.1).
'1f iAttachment VR.E.GinnaNuclearPowerPlantProposedGinnaStationTechnical Specifications DesignFeatures4.04.0DESIGNFEATURES4.1SiteLocationThesitefortheR.E.GinnaNuclearPowerPlantislocatedonthesouthshoreofLakeOntario,approximately 16mileseastofRochester, NewYork.Theexclusion areaboundarydistances fromtheplantshallbeasfollows:Direction N(including offshore)
NNENEENEEESESESSESSSWSWWSWWWNWNWNNWDistancem8000800080008000747640503450450450503915945701800080004.2ReactorCore4.2.1FuelAssemblies Thereactorshallcontain121fuelassemblies.
EachassemblyshallconsistofamatrixofzircaloyorZIRLOcladfuelrodswithaninitialcomposition ofnaturalorslightlyenricheduraniumdioxide(UO,)asfuelmaterial.
Limitedsubstitutions ofzircaloy, ZIRLO,orstainless steelfillerrodsforfuelrods,inaccordance withNRCapprovedapplications offuelrodconfigurations, maybeused.Fuelassemblies shallbelimitedtothosefueldesignsthathavebeenanalyzedwithapplicable NRCstaffapprovedcodesandmethodsandshownbytestsorcyclespecificanalysestocomplywithallfuelsafetydesignbases.Alimitednumberofleadtestassemblies thathavenotcompleted representative testingmaybeplacedinnonlimiting coreregions.I(continued)
R.E.GinnaNuclearPowerPlant4.0-1Amendment No.Q 4
eportingRequirements 5.65.6Reporting Requirements 5.6.5COLR(continued) b.Theanalytical methodsusedtodetermine thecoreoperating limitsshallbethosepreviously reviewedandapprovedbytheNRC,specifically thosedescribed inthefollowing documents:
1.WCAP-9272-P-A, "Westinghouse ReloadSafetyEvaluation Methodology,"
July1985.(Methodology forLCO3.1.1,LCO3.1.3,LCO3.1.5,LCO3.1.6,LCO3.2.1,LCO3.2.2,LCO3.2.3,andLCO3.9.1.)2.WCAP-13677-P-A, "10CFR50.46Evaluation ModelReport:WCOBRA/TRAC Two-LoopUpperPlenumInjection ModelUpdatestoSupportZIRLOŽCladdingOption,"February1994.(Methodology forLCO3.2.1.)3.WCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures
-TopicalReport,"September 1974.(Hethodology forLCO3.2.3.)4.WCAP-12610-P-A, "VANTAGE+FuelAssemblyReference CoreReport,"April1995.(Methodology forLCO3.2.1).5.WCAP11397-P-A, "RevisedThermalDesignProcedure,"
April1989.(Methodology forLCO3.4.1whenusingRTDP.)6.WCAP-10054-P-A andWCAP-10081-A, "Westinghouse SmallBreakECCSEvaluation ModelUsingtheNOTRUMPCode,"August1985.(Methodology forLCO3.2.1)7.WCAP-10924-P-A, Volume1,Revision1,"Westinghouse Large-Break LOCABest-Estimate Methodology, Volume1:ModelDescription andValidation Responses toNRCguestions,"
andAddenda1,2,3,December1988.(Hethodology forLCO3.2.1)(continued)
R.E.GinnaNuclearPowerPlant5.0-20Amendment No.g lirI eportingRequirements 5.65.6Reporting Requirements 5.6.5COLR(continued) 8.WCAP-10924-P-A, Volume2,Revision2,"Westinghouse Large-Break LOCABest-Estimate Methodology, Volume2:Application toTwo-LoopPWRsEquippedwithUpperPlenumInjection,"
andAddendum1,December1988.(Methodology forLCO3.2.1)9.WCAP-10924-P-A, Volume1,Revision1,Addendum4,"Westinghouse Large-Break LOCABest-Estimate Methodology, Volume1:ModelDescription andValidation, Addendum4:ModelRevisions,"
March1991.(Methodology forLCO3.2.1)c~Thecoreoperating limitsshallbedetermined suchthatallapplicable limits(e.g.,fuelthermalmechanical limits,corethermalhydraulic limits,Emergency CoreCoolingSystems(ECCS)limits,nuclearlimitssuchasSDH,transient analysislimits,andaccidentanalysislimits)ofthesafetyanalysisaremet.d.TheCOLR,including anymidcyclerevisions orsupplements, shallbeprovideduponissuanceforeachreloadcycletotheNRC.5.6.6ReactorCoolantSstemRCSPRESSUREANDTEMPERATURE LIMITSREPORTPTLRa0b.RCSpressureandtemperature limitsforheatup,cooldown, criticality, andhydrostatic testingaswellasheatupandcooldownratesshallbeestablished anddocumented inthePTLRforthefollowing:
LCO3.4.3,"RCSPressureandTemperature (P/T)Limits"ThepoweroperatedreliefvalveliftsettingsrequiredtosupporttheLowTemperature Overpressure Protection (LTOP)System,andtheLTOPenabletemperature shallbeestablished anddocumented inthePTLRforthefollowing:
LCO3.4.6,"RCSLoops-MODE4";LCO3.4.7,"RCSLoops-MODE5,LoopsFilled";LCO3.4.10,"Pressurizer SafetyValves";andLCO3.4.12,"LTOPSystem."(continued)
R.E.GinnaNuclearPowerPlant5.0-21Amendment No.g
.0~51J~(((,
