Application for Amend to License DPR-18,changing Tech Specs to Reflect Overpressure Protection Sys Requirements.Safety Evaluation & Justification for Continued Operation EnclML17244A180 |
Person / Time |
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Site: |
Ginna ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
10/11/1978 |
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From: |
WHITE L D ROCHESTER GAS & ELECTRIC CORP. |
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Shared Package |
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ML17244A179 |
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References |
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TASK-05-03, TASK-5-3, TASK-RR NUDOCS 7810190069 |
Download: ML17244A180 (17) |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17265A6921999-06-28028 June 1999 Application for Amend to License DPR-18 to Revise ITS Associated with RCS Leakage Detection Instrumentation.Lar Proposed as Result of Commitment That Rg&E Submit as Part of Staff Review of Application of leak-before-break Status ML17265A5691999-03-0101 March 1999 Application for Amend to License DPR-18,proposing Change in ITS to Revise Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4651998-11-24024 November 1998 Application for Amend to License DPR-18,revising Improved Tech Spec Description of Fuel Cladding Matl (TS 4.2.1) & Updating References Provided in TS 5.6.5 for COLR ML17265A2431998-04-27027 April 1998 Application for Amend to License DPR-18,revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0431997-09-29029 September 1997 Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept ML17264B0381997-09-29029 September 1997 Application for Amend to License DPR-18,revising TS Re 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 Revised Setpoint Analysis ML17264B0021997-08-19019 August 1997 Application for Amend to License DPR-18,allowing Testing of Certain ECCS motor-operated Valves in Mode 4 Which Currently Requires Entry in LCO 3.0.3 ML17264A9981997-08-19019 August 1997 Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A8661997-04-24024 April 1997 Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements ML17264A8471997-03-31031 March 1997 Application for Amend to License DPR-18,revising Spent Fuel Pool Storage Requirements ML20134D9911996-10-29029 October 1996 Application for Amend to License DPR-18,requesting Change to Mode of Applicability for Auxiliary Feedwater Pump Actuation on Main Feedwater Pump ML17264A7121996-10-29029 October 1996 Application for Amend to License DPR-18 Requesting Change to Required Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A5991996-09-13013 September 1996 Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept ML17264A4701996-05-0808 May 1996 Application for Amend to License DPR-18,correcting Typos ML17264A4041996-03-15015 March 1996 Application for Amend to License DPR-18,revising TS to Incorporate Methodology for Determining RCS P/T Limits & LTOP Limits in Administrative Controls Section of RCS P/T Limits Rept ML17264A3441996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - 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ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17265A6921999-06-28028 June 1999 Application for Amend to License DPR-18 to Revise ITS Associated with RCS Leakage Detection Instrumentation.Lar Proposed as Result of Commitment That Rg&E Submit as Part of Staff Review of Application of leak-before-break Status ML17265A5691999-03-0101 March 1999 Application for Amend to License DPR-18,proposing Change in ITS to Revise Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4651998-11-24024 November 1998 Application for Amend to License DPR-18,revising Improved Tech Spec Description of Fuel Cladding Matl (TS 4.2.1) & Updating References Provided in TS 5.6.5 for COLR ML17265A2431998-04-27027 April 1998 Application for Amend to License DPR-18,revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0431997-09-29029 September 1997 Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept ML17264B0381997-09-29029 September 1997 Application for Amend to License DPR-18,revising TS Re 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 Revised Setpoint Analysis ML17264B0021997-08-19019 August 1997 Application for Amend to License DPR-18,allowing Testing of Certain ECCS motor-operated Valves in Mode 4 Which Currently Requires Entry in LCO 3.0.3 ML17264A9981997-08-19019 August 1997 Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A8661997-04-24024 April 1997 Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements ML17264A8471997-03-31031 March 1997 Application for Amend to License DPR-18,revising Spent Fuel Pool Storage Requirements ML20134D9911996-10-29029 October 1996 Application for Amend to License DPR-18,requesting Change to Mode of Applicability for Auxiliary Feedwater Pump Actuation on Main Feedwater Pump ML17264A7121996-10-29029 October 1996 Application for Amend to License DPR-18 Requesting Change to Required Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A5991996-09-13013 September 1996 Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept ML17264A4701996-05-0808 May 1996 Application for Amend to License DPR-18,correcting Typos ML17264A4041996-03-15015 March 1996 Application for Amend to License DPR-18,revising TS to Incorporate Methodology for Determining RCS P/T Limits & LTOP Limits in Administrative Controls Section of RCS P/T Limits Rept ML17264A3441996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] |
Text
UNITEDSTATESOFAMERICANUCIEARREGULATORYCOMMISSIONIntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant.,UnitNo.l))))DocketNo.50-244))APPLICATIONFORAMENDMENTTOOPERATINGLICENSEPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(the"Commission"),RochesterGasandElectricCorporation("RG&E"),holderofProvisionalOperatingLicenseNo.DPR-18,herebyrequeststhattheTechnicalSpecifica-tionssetforthinAppendixAtothatlicensebeamendedtoincludereactoroverpressureprotectionsystemrequirements.Theproposedtechnicalspecificationchangeisset.forthinAttachmentAtothisApplication.AsafetyevaluationissetforthinAttachment,B.Thisevaluationalsodemonstratesthattheproposedchangedoesnotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.Justifi-cationforclassificationoftheamendmentpursuantto10C.F.R.Section170.22isincludedasAttachment,C.AcheckfortheappropriatefeeaccompaniesthisApplication.lS(o]qoo6q WHEREFORE,Applicantrespectfullyrequeststhat.AppendixAtoProvisionalOperatingLicenseNo.DPR-l8beamendedintheformattachedheretoasAttachmentA.RochesterGasandElectricCorporationByL.D.Whxe,Jr.VicePresident,ElectricandSteamProductionSubscribedandsworntobeforemeonthis///FLBayofOctober,1978.GARYL.REISSNOTARYPUBLIC,StatoofN.Y.MonroeCo.MyCommtssiooExpiresMarchpp,19,./yg AttachmentAFigure3.10-2isnotmet,theplantshallbetakentothehotshutdownconditionandtheoneloopshutdownmarginshallbemet.d.AtleastonereactorcoolantpumpshallbeinoperationforaplannedtransitionfromoneReactorOperatingModetoanotherinvolvinganincreaseintheboronconcentrationofthereactorcoolant.e.AreactorcoolantpumpshallnotbestartedwithoneormoreoftheRCScoldlegtemperatures<330'Funless1)thepressurizerwatervolume7slessthan324cubicfeet(38%level)or2)thesecondarywatertemperatureofeachsteamgeneratorislessthan50'FaboveeachoftheRCScoldlegtemperatures.3.1.1.2SteamGeneratora.Onesteamgeneratorshallbecapableofperformingitsheattransferfunctionwhenevertheaveragecoolanttemperatureisabove350'F.b.Thetemperaturedifferenceacrossthetubesheetshallnotexceed100'F.3.1.1.3SafetValvesa~Atleastonepressurizercodesafetyvalveshallbeoperablewheneverthereactorheadisonthevessel.b.Bothpressurizercodesafetyvalvesshallbeoperablewheneverthereactoriscritical.Basis:Whentheboronconcentrationofthereactorcoolantsystemistobereducedtheprocessmustbeuniformtopreventsuddenreactivitychangesinthereactor.Mixingofthereactorcoolantwillbesufficient3+12Proposed
Eachofthepressurizercodesafetyvalvesisdesignedtorelieve288,000lbs.perhr.ofsaturatedsteamatthevalvesetpoint.Below350'Fand350psiginthereactorcoolantsystem,theresidualheatremovalsystemcanremovedecayheatandtherebycontrolsystemtemperatureandpressure.Ifnoresidualheat.wereremovedbyanyofthemeansavailabletheamountofsteamwhichcouldbegeneratedatsafetyvalvereliefpressurewouldbelessthanhalfthevalves'apacity.Onevalvethereforeprovidesadequatedefenseagainstoverpressurization.ProhibitingreactorcoolantpumpstartswithoutalargevoidinthepressurizerorwithoutalimitedRCStemperaturedifferentialwillpreventRCSoverpressurizationduetoexpansionofcoolerRCSwaterasitentersawarmersteamgenerator.A38%levelinthepressurizerwillaccommodatetheswellresultingfromareactorcoolantpumpstartwithaRCStemperatureof140'Fandsteamgeneratorsecondarysidetemperatureof340'F,orthemaximumtemperaturewhichusuallyexistspriortocoolingthereactorwiththeRHRsystem.Thespecificationpermitsanorderlyreductioninpowerifareactorcoolant(gampislostduringoperationbetween130MWTand50%ofratedpower.Above50%power,anautomaticreactortripwilloccurifeitherpumpislost.Thepower-to-flowratiowillbemaintainedequaltoorlessthanonewhichensuresthattheminimumDNBratioincreasesatlowerflowsincethemaximumenthalpyrisedoesnotincrease.Temperaturerequirementsforthesteamgenerator'correspondwithmeasuredNDTfortheshellandallowablethermalstressesinthetubesheet.References(1)FSARSection14.1.6(2)FSARSection7.2.3Proposed c~Oneboricacidtankmaybeoutofserviceprovidedaminimumof2,000gallonsofa12%to13%byweightboricacidsolutionatatemperatureofatleast145'Fiscontainedintheoperabletankandprovidedthatthetankisrestoredtooperablestatuswithin24hours.d.Onechannelofheattracingmaybeoutofserviceprovideditisrestoredtooperablestatuswithin24hours.3.2.4Basis:Wheneverthereactorcoolantsystemis>200'FandisbeingcooledbytheRHRsystemandtheoverpressureprotectionsystemisnotoperable,atleastonechargingpumpshallbedemonstratedinoperableat,leastonceper12hoursbyverifyingthatthecontrolswitchisinthepull-stopposition.Thechemicalandvolumecontrolsystemprovidescontrolofthereactorcoolantsystemboroninventory.Thisisnormallyaccomplishedbyusingeitheroneofthethreechargingpumpsinserieswithoneofthetwoboricacidpumps.Analternatemethodofborationwillbetousethechargingpumpsdirectlyfromtherefuelingwaterstoragetank.Athirdmethodwillbetodepressurizeandusethesafetyinjectionpumps.Therearetwosourcesofboratedwateravailableforinjectionthroughthreedifferentpaths.(1)Theboricacidtransferpumpscandelivertheboricacidtankcontents(12%concentrationofboricacid)tothechargingpumps.(2)Thechargingpumpscantakesuctionfromtherefuelingwaterstoragetank.(2,000ppmboronsolution)(3)Thesafetyinjectionpumpscantaketheirsuctionsfromeithertheboricacidtanksortherefuelingwaterstoragetank.Thequantityofboricacidinstoragefromeithertheboricacidtanksortherefuelingwaterstoragetankissufficienttoborate.thereactorcoolant.inordertoreachcoldshutdownatanytimeduringcorelife.Approximately1800gallonsofthe12%to13%solutiqy)ofboricacidare.requiredtomeetcoldshutdowncondi-tions.'hus,aminimumof2000gallonsintheboricacidtanksisspecified.Anupperconcentrationlimitof13%boricacidinthetankisspecifiedtomaintainsolutionsolubilityatthespeci-fiedlowtemperaturelimitof145'F.Twochannelsofheattracingareinstalledonlinesnormallycontainingconcentratedboricacidsolutiontomaintainthespecifiedlowtemperaturelimit,.3~23Proposed Placingachargingpumpinpull-stopwheneverthereactorcoolantsystemtemperatureis>200'FandisbeingcooledbyRHRwithout,theoverpressureprotectionsystemoperablewillpreventinadvertayP)overpressurizationoftheRHRsystemshouldletdownbeterminated.
References:
(1)FSAR,Section9.2(2)FSAR,Page9.2-37(3)L.D.White,Jr.lettertoA.Schwencer,NRC,datedFebruary24,19773.2-4Proposed (ii)Thetworeactorcoolantdraintankpumpsshallbetestedandtheiroperabilitydemon-stratedpriortoinitiatingrepairsoftheinoperableresidualheatremovalpump.d.Oneresidualheatexchangermaybeoutofserviceforaperiodofnomorethan24hours.e.Anyvalverequiredforthefunctioningofthesafetyinjectionorresidualheatremovalsystemsmaybeinoperableprovidedrepairsarecompletedwithin12hours.Priortoinitiatingrepairs,allvalvesinthesystemsthatprovidetheduplicatefunctionshallbetestedtodemonstrateoperability.3.3.1.3f.Powermayberestoredtoanyvalvereferencedin3.3.1.1gforthepurposesofvalvetestingprovidingnomorethanonesuchvalvehaspowerrestoredandprovidedtestingiscompletedandpowerremovedwithin12hours.ExceptduringdieselgeneratorloadandsafeguardsequencetestingorwhenthevesselheadisremovedorthesteamgeneratormanwayisopenamaximumofonesafetyinjectionpumpshallbeoperablewheneverthetemperatureofoneormoreoftheRCScoldlegsis<330'F.3.3.1.3.13.3.23.3.2.1Wheneveramaximumofonesafetyinjectionpumpmaybeoperableby3.3.1.3atleasttwoofthesafetyinjectionpumpsshallbedemonstratedinoperableatleastoncepertwelvehoursbyverifyingthatthecontrolswitchesareinthepull-stopposition.ContainmentCoolinandIodineRemovalThereactorshallnotbemadecriticalexceptforlowtemperaturephysicstests,unlessthefollowingcondi-tionsaremet:a~b.c~Thesprayadditivetankcontainsnotlessthan4500gallonsofsolutionwithasodiumhydroxideconcentrationofnotlessthan30%byweight.Atleasttwocontainmentspraypumpsare'perable.Atleastthreefancoolerunitsareoperable.3.3-4Proposed
'untilrepairswereeffected.Thefacilityhasfourservicewaterpumps.Onlyoneisneededduringtheinjectionphase,andtwoarerequiredduringtherecirculationphaseofapostulatedloss-of-coolantaccident.(8)Thelimitsfortheaccumulatorpressureandvolumeassurethere-quiredamountofwaterinjectionduringanaccident,andarebasedonvaluesusedfortheaccidentanalyses.Theindicatedlevelof50%correspondsto1108cubicfeetofwaterintheaccumulatorandtheindicatedlevelof82%correspondsto1134cubicfeet.Thelimitationforamaximumofonesafetyinjectionpumptobeoperableandthesurveillancerequirementtoverifythattwosafetyinjectionpumpsareinoperablebelow330'FprovidesassurancethatamassadditionpressuretransientcanberelievedbytheoperationofasinglePORV.3~312Proposed 3.15OveressureProtectionSstem~lb1ApplieswheneverthetemperatureofoneormoreoftheRCScoldlegsis<330'F.Ob'ctiveTopreventoverpressurizationofthereactorcoolantsystem.Secification3.15.1Atleastoneofthefollowingoverpressureprotectionsystemsshallbeoperable:a.Twopressurizerpoweroperatedreliefvalves(PORVs)withaliftsettingof<435psig,orb.Areactorcoolantsystemventof>1.1squareinches.3.15.1.1WithonePORVinoperable,eitherrestoretheinoperablePORVtooperablestatuswithin7daysordepressurizeandventtheRCSthrougha1.1squareinchvent(s)withinthenext8hours;maintaintheRCSinaventedconditionuntilbothPORVshavebeenrestoredtooperablestatus.3.15.1.23.15.1.3WithbothPORVsinoperable,depressurizeandventtheRCSthrougha1.1squareinchvent(s)within8hours;maintaintheRCSinaventedconditionuntilbothPORVshavebeenrestoredtooperablestatus.UseoftheoverpressureprotectionsystemtomitigateaRCSpressuretransientshallbereportedinaccordancewith6.9.3.BasisTheoperabilityoftwopressurizerPORVsoranRCSventopeningofgreaterthan1.1squareinchesensuresthattheRCSwillbeprotectedfrompressuretransientswhichcouldexceedthelimitsofAppendixGto10CFRPart50whenoneormoreoftheRCScoldlegsare<330'F.EitherPORVhasadequaterelievingcapabilitytoprotecttheRCSfromoverpressurizationwhenthetransient,islimitedtoeither(1)thestartofanidleRCPwiththesecondarywatertemperatureofthesteamgenerator<50'FabovetheRCScoldlegtemperatureor(2)thestartof~1~afetyinjectionpumpanditsinjectionintoawatersolidRCS.
References:
(1)L.D.White,Jr.lettertoA.Schwencer,NRC,datedJuly29,19773.15-1Proposed OveressureProtectionSstemAlicabilit:Appliestothereactorcoolantsystemoverpressureprotectionsystem.Ob'ective:Toverifythattheoverpressureprotectionsystemwillfunctionproperlyifneeded.SecificationEachPORVshallbedemonstratedoperableby:a~PerformanceofachannelfunctionaltestonthePORVactuationchannel,butexcludingvalveopera-tion,within31dayspriortoenteringaconditioninwhichthePORVisrequiredoperableandatleastonceper31daysthereafterwhenthePORVisrequiredoperable.b.PerformanceofachannelcalibrationonthePORVactuationchannelat,leastonceper18months.c.VerifyingthePORVisolationvalveisopenatleastonceper72hourswhentheoverpressureprotectionsystemisrequiredtobeoperable.TheRCSvent(s)shallbeverifiedtobeopenatleastonceper12hourswhenthevent(s)isbeingusedforoverpressureprotectionexceptwhenthevent,pathwayisprovidedwithavalvewhichislocked,sealed,orotherwisesecuredintheopenposition.Thenverifythesevalvesopenatleastonceper31days.Proposed (2)Annually:Atabulationonanannualbasisofthenumberofstation,utilityandotherper-sonnel(includingcontractors)receivingex-posuresgreaterthan200mrem/yrandtheirassociatedmanremexposureaccordingtoworkandjobfunctions,e.g.,reactoroperationsandsurveillance,inserviceinspection,routinemaintenance,specialmaintenance(describemaintenance),wasteprocessing,andrefueling.Thedoseassignmenttovariousdutyfunctionsmaybeestimatesbasedonpocketdosimeter,TU),orfilmbadgemeasure-ments.Smallexposurestotallinglessthan20%oftheindividualtotaldoseneednotbeaccountedfor.Intheaggregate,atleast80%ofthetotalwholebodydosereceivedfromexternalsourcesshallbeassignedtospecificmajorworkfunctions.(NOTE:Thistabulationsupplementsthere-quirementsofSection20.407of10CFRPart20.)ReactorOverpressureProtectionSystemOperationIntheeventeitherthePORVsortheRCSvent(s)areusedtomitigateaRCSpressuretransient,aSpecialReportshallbepreparedandsubmittedtotheCommissionwithin30days.Thereportshalldescribethecircumstancesinitiatingthetransient,theeffectofthePORVsorvent(s)onthetransientandanyothercorrectiveactionnecessarytopreventrecurrence.6.9-10Proposed AttachmentBAreactorcoolantsystemoverpressureprotectionsystemhasbeeninstalledatR.E.GinnatomitigatepressuretransientsthatmightotherwiseexceedthoselimitswhicharebaseduponAppendixGto10CFRPart50.Thesystemisdesignedtomitigatetransientswhichmayresultfrompersonnelerror,equipmentmalfunctionorproceduraldeficiencies.AdescriptionofthissystemwasprovidedinlettersfromMr.L.D.White,Jr.,RochesterGasandElectricCorporation,toMr.A.Schwencer,U.S.NuclearRegulatoryCommission,datedFebruary24,1977,March31,1977,andJuly29,1977.Theoverpressureprotectionsystemwillpreventawatersolidreactorcoolantsystemfromexceedingapressureof535psigforasafetyinjectionpumpdischargingtothereactorcoolantsystem,areactorcoolantpumpstartwitha50'Ftemperaturedifferentialbetweentheprimaryandsecondarysystemorlessseveremassinputorheatinputtransients.Thespecificationprohibitingreactorcoolantpumpstartsunlessthefilledpressurizervolumeislessthan324ft(38%level)orunlessthetemperaturedifferentialbetweentheprimaryandsecondarysystemsislessthan50'Fwillproperlylimitheatinput,transients.Apressurizerlevelof38%willaccommodatetheswellresultingfromareactorcoolantpumpstartwithareactortemperatureof140'Fandsteamgeneratortemperatureof340'Fwithouttheneedforoperationoftheoverpressureprotec-tionsystem.Relieffromthepressurizerpoweroperatedreliefvalves(PORVs)would,however,increasethemarginbetweenthepeaktransientpressureandthelimitofTechnicalSpecification3.1.2.Withnogasorsteambubbleinthepressurizertheover-pressureprotectionsystemwillbyitselfpregytthepressurefromexceedingTechnicalSpecification3.1.2.Thespecificationtolimitthenumberofchargingpumpswhichmaybeoperablewhenthereactorcoolantsystemtemperatureisgreaterthan200'Fandtheoverpressureprotectionsystemisinoperablewillpreventapotentialoverpressurizationoftheresidualheatremovalsystem(RHR)shouldletdownbeisolated.AnalysishasshownthattheRHRsystemcanrelievetheinputfromthreechargingpumpswhenthereactorcoolantsystemtemperatureislessthan200'Fandcanrelievetheinputoftwocyygingpumpsattemperaturesgreaterthanorequalto200'F.Thecombinedcapacityof3chargingpumpsislessthanthat,ofonesafetyinjectionpumpandwillnotproducetransientpressuresgreaterthanthosewhichcanbemitigatedbytheoverpressureprotectionsystemwhenthatsystemisoperable.Proposedspecification3.3.1.3willprohibitmorethanonesafetyinjectionpumpfrombeingoperablewhenoneormoreoftheRCScoldlegtemperaturesislessthanorequalto330'Fexceptduringdieselgeneratorloadandsafeguardsequencetestingorwhenthevesselheadisremovedorthesteamgeneratormanwayisopen.Theshutoffheadofthesafetyinjectionpumpsislessthan1500psig,apressurewellbelowtheallowablepressurefor RCStemperaturesof330'Fandabove.Allsafetyinjectionpumpsmaybeoperablefortemperaturesabove330'F;onepumpmaybeoperablebelow330'F,whenthepotentialforoverpressuretransientsexists,becauseof~)emitigatingeffectoftheoverpressureprotectionsystem.Whenthereactorheadisremovedorwhenasteamgeneratormanwayisopenapotentialforoverpressurizationdoesnotexistandthereisnorestrictiononsafetyinjectionpumpoperation.Duringdieselgeneratorloadandsafeguardsequencetestingextraprecautionsaretakentopreventsafetyinjectionpumpdischargetothereactorcoolantsystem.Thepumpdischargevalvesareclosed,thevalvebreakersareopenedandtheDCcontrolfusesareremoved.Theseprecautionsreducethepotentialforoverpressurizationtoanacceptablelevelduringthetestperiod.Surveillanceofthepumpcontrolsoncepertwelvehourswhenonlyonepumpmaybeoperableisappropriatetopreventinadvertentpumpstarts.Proposedspecification3.15requiresthatanoverpressureprotectionsystembeoperablewhenoneormoreoftheRCScoldlegtemperaturesislessthanorequalto330'F.Fortemperaturesgreaterthan330'FtheallowableRCSpressureisgreaterthanthenormalreliefpressureofthetwopressurizerpoweroperatedreliefvalvessothatnootheroverpressureprotectionisrequired.Below330'FeachofthePORVs,usingalowpressuresetpointof435psig,willmitigatepressuretransientsinawater-solidRCSresultingfromthedischargeofasinglesafetyinjectionpumporthestartingofareactorcoolantpumpwitha50'Ftemyy~aturedifferentialbetweenthereactorandsteamgenerators.A1.1squareinchventistheorificeareaequivalenttothatofasinglePORV.BecauseeachofthePORVswillprovideoverpressureprotec-tion,7daysisanacceptabletimeduringwhichoneofthePORVsmaybeinoperable.Aftersevendays,orintheeventthatbothPORVsareinoperable,8hoursisanacceptableperiodoftimetoestablishaRCSventandisarelativelyshortperiodoftimetobewithoutadditionaloverpressureprotection.Proposedspecification4.16requiresappropriateactiontoassurethattheoverpressureprotectionsystemfunctionsproperly.Achannelfunctionaltestwillbeperformedpriortothetimethatthesystemisrequiredtobeoperableandatleastonceevery31daysthereafterwhenit,isoperable.Achannelcalibra-tionwillbeperformedatleastonceevery18months.Thesetestsandcalibrationsaresimilarinnatureandfrequencytothosewhichareperformedonplantprotectionsystemseventhoughthissystemdoesnotperformwhat,isconsideredtobeasafetyfunction.VerificationthatthePORVisolationvalveisopenatleastonceevery72hourswhentheoverpressureprotectionsystemisrequiredtobeoperablewillprovideappropriateassurancethattheoverpressureprotectionfunctionhasnotbeeninadvertentlydefeated.
(1)LetterfromL.D.White,Jr.,RochesterGas6ElectricCorporation,toA.Schwencer,NuclearRegulatoryCommission,July29,1977.(2)LetterfromL.D.White,Jr.,RochesterGas&ElectricCorporation,toA.Schwencer,NuclearRegulatoryCommission,February24,1977 AttachmentCTheproposedAmendment.totheProvisionalOperatingLicensehasbeenevaluatedanddeterminedtofallwithinthedefinitionofClassIIIof10C.F.R.Section170.22therebyreguiringafeeof94,000.Theproposedamendmentdealswithasinglesafetyissue,over-pressureprotectionofthereactorvessel.TheissuehasbeenclearlyidentifiedbyanNRCposition.
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