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| ML17264A405 |
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| Site: |
Ginna  |
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| Issue date: |
03/15/1996 |
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| From: |
ROCHESTER GAS & ELECTRIC CORP. |
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| To: |
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| Shared Package |
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| ML17264A403 |
List: |
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| NUDOCS 9603210240 |
| Download: ML17264A405 (7) |
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Proposed Tech Specs Re Ventilation Filter Testing Program
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Proposed Tech Specs Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS
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Proposed Tech Specs to Revise TS 4.4.2.4.a,replacing Specific Leakage Testing Frequencies for Containment Isolation Valves
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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
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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.'
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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
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Rev 11 to Technical Requirements Manual for Ginna Station.
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Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
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Rev 9 to Technical Requirements Manual for Ginna Station.
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Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6)
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Rev 4 to Technical Requirements Manual (Trm).
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Rev 6 to Technical Requirements Manual.
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Rev 13 to FR-S.1, Response to Reactor Restart/Atws
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Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop
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ML17265A3721998-07-16016 July 1998
Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr
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Proposed Tech Specs Basis Re Main Steam Isolation Setpoint
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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
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Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool
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Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria.
ML17265A1491997-12-31031 December 1997
Rev 1 to Inservice Testing Program.
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Rev 4 to Technical Requirements Manual (TRM) for Ginna Station.
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Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values
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Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
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Rev 12 to AP-RCS.1, Reactor Coolant Leak.
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Rev 11 to AP-RCP.1, RCP Seal Malfunction.
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Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
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Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
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Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
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to Inservice Insp (ISI) Program.
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Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection
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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
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1999-06-28
[Table view] |
Text
AttachmentIIMarkedUpCopyofR.E.GinnaNuclearPowerPlantTechnicalSpecificationsIncludedPages:5.0-22,96032102409603i5aDOCV,0Soooae4PPDR
~If ReportingRequirements5.65.6ReportingRequirements5.6.6PTLR(continued)C.TheRCSpressureandtemperatureandLTOPlimitsshallbethosepreviouslyreviewedandapprovedbytheRCinmen~menAo.48.1heaccepa~ityoeTandLTOPlimitsaredocumentedinNRCletter,"R.E.Ginna-AcceptanceforReferencing.ofPressureLimitsReport,"December26,1995.Speciically,thelimitsandmethodologyaredescribedieoow>ngocumens:i.iamenmentAo.45~aci>yOperatingLLicenseio.DPR-18,R.E.GinnaNuclearPowerPlant,Harch6,1992.2.LetterfromC.I.Grimes,NRC,toR.A.Newton,MestinghouseElectricCorporation,"AcceptanceforReferencingTopicalReportMCAP-14040,'evision1,'HethodologyusedtoDevelopColdOverpressureHitigatingSystemSetpointsandRCSHeatupandCooldownLimitCurves','"October16,1995.3.LetterfromR.C.Mecredy,RochesterGasandElectricCorporation(RG8E),toDocumentControlDesk,NRC,AttentionA.R.Johnson,"TechnicalSpecificationsImprovementProgram,ReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR),"December8,1995.d.ThePTLRshallbeprovidedtotheNRCuponissuanceforeachreactorvesselfluencyperiodandforrevisionsorsupplementthereto.R.E.GinnaNuclearPowerPlant5.0-22AmendmentNo.61 41' AttachmentIIIProposedTechnicalSpecificationsIncludedPages:5.0-22 eportingRequirements~~5.65.6ReportingRequirements5.6.6PTLR(continued)C.d.TheanalyticalmethodsusedtodeterminetheRCSpressureandtemperatureandLTOPlimitsshallbethosepreviouslyreviewedandapprovedbytheNRCinthefollowingdocuments:1.(NRCapprovaldocument>2.LetterfromC.I.Grimes,NRC,toR.A.Newton,WestinghouseElectricCorporation,"AcceptanceforReferencingTopicalReportWCAP-14040,Revision1,'HethodologyusedtoDevelopColdOverpressureHitigatingSystemSetpointsandRCSHeatupandCooldownLimitCurves',"October16,1995.3.LetterfromR.C.Hecredy,RochesterGasandElectricCorporation(RGSE),toDocumentControlDesk,NRC,AttentionA.R.Johnson,"TechnicalSpecificationsImprovementProgram,ReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR),"December8,1995.ThePTLRshallbeprovidedtotheNRCuponissuanceforeachreactorvesselfluencyperiodandforrevisionsorsupplementthereto.R.E.GinnaNuclearPowerPlant5.0-22AmendmentNo.Q lf