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| | issue date = 07/17/1979 | | | issue date = 07/17/1979 |
| | title = Application for Amend to License DPR-18 Changing Reactor Overpressure Protection Sys Requirements.W/Certificate of Svc & Related Info | | | title = Application for Amend to License DPR-18 Changing Reactor Overpressure Protection Sys Requirements.W/Certificate of Svc & Related Info |
| | author name = WHITE L D | | | author name = White L |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = | | | addressee name = |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 8 | | | page count = 8 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant,UnitNo.l))))DocketNo.50-244))APPLICATIONFORAMENDMENTTOOPERATINGLICENSEPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(the"Commission"),RochesterGasandElectricCorporation("RG&E"),holderofProvisionalOperatingLicenseNo.DPR-l8,herebyrequeststhattheTechnicalSpecifica-tionssetforthinAppendixAtothatlicensebeamendedtochangereactoroverpressureprotectionsystemrequirements.TheproposedtechnicalspecificationchangeissetforthinAttachmentAtothisApplication.AsafetyevaluationissetforthinAttachmentB.Thisevaluationalsodemonstratesthat,theproposedchangedoesnotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.Justifi-cationforclassificationoftheamendmentpursuantto10C.F.R.Section170.22isincludedasAttachmentC.AcheckfortheappropriatefeeaccompaniesthisApplication. | | {{#Wiki_filter:UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of ) |
| WHEREFORE,ApplicantrespectfullyrequeststhatAppendixAtoProvisionalOperatingLicenseNo.DPR-18beamendedintheformattachedheretoasAttachmentA.RochesterGasandElectricCorporationByL.D.Who.,Jr.VicePresident,ElectricandSteamProductionSubscribedandsworntobeforeme'nthisI7dayofJuly,1979.STEPHENKOWBANOTARYPUBLlC,StateofN.Y,MonroeCountyftyCommissionExpiresMarch30,19/17 BEFORETHEUNITEDSTATESNUCLEARREGULATORYCOMMISSIONIntheMatterofROCHESTERGASANDELECTRXCCORPORATION(R.E.GinnaNuclearPowerStation,Unit,No.1))))))DocketNo.50-244)CERTIPXCATEOFSERVICEIherebycertifythatIhaveservedadocumententitled"Applicationfor'AmendmenttoOperatingLicense"withthree(3)documents,AttachmentsA,BandC,attachedthereto,bymailingcopiesthereoffirstclass,postagepre-paid,toeachofthefollowingpersonsthis19thdayofJuly1979:Mr.MichaelL.Slade1250CrownPointDriveWebster,NewYork14580WarrenB.Rosenbaum,EsquireOneMainStreet707WilderBuildingRochester,NewYork14614EdwardG.Ketchen,EsquireOfficeoftheExecutiveLegalDirectorU.S.NuclearRegulatoryCommissionWashington,D.C.20555Mr.RobertN.PickneySupervisorTownofOntario197RidgeRoadWestOntario,NewYork14519 JeffreyL.Cohen,EsquireNewYorkStateEnergyOfficeSwanStreetBuildingCorel,SecondFloorEmpireStatePlazaAlbany,NewYorkl2223EdwardLuton,EsquireAtomicSafetyandLicensingBoardU.S.NuclearRegulatoryCommissionDr.EmmethA.LuebkeAtomicSafetyandLicensingBoardU.S.NuclearRegulatoryCommissionDr.DixonCallihanUnionCarbideCorporationP.O.BoxYOakRidge,Tennessee37830oertS.FaronLeBoeuf,Lamb,Leiby6MacRaeAttorneysforRochesterGasandElectricCorporation ATTACHMENTAOveressureProtectionSstem~ld>>ApplieswheneverthetemperatureofoneormoreoftheRCScoldlegsis<330'F.Ob'ectiveToprevent,overpressurizationofthereactorcoolantsystem.Secification/3.15.1Exceptduringsecondarysidehydrostatictests,atleastoneofthefollowingoverpressureprotectionsystemsshallbeoperable:a~b.Twopressurizerpoweroperatedreliefvalves(PORVs)'ithaliftsettingof<435psig,orAreactorcoolantsystemventof>1.1squareinches.3.15.1.13.15.1.23.15.1.3WithonePORVinoperable',eitherrestoretheinoperablePORVtooperablestatuswithin7daysordepressurizeandventtheRCSthrougha1.1squareinchvent(s)withinthenext8hours;maintaintheRCSinaventedconditionuntilbothPORVshavebeenrestoredtooperablestatus.WithbothPORVsinoperable,depressurizeandventtheRCSthrougha1.1squareinchvent(s)within8hours;maintaintheRCSinaventedconditionuntilbothPORVshavebeenrestoredtooperablestatus.UseoftheoverpressureprotectionsystemtomitigateaRCSpressuretransientshallbereportedinaccordancewith6.9.3.BasisTheoperabilityoftwopressurizerPORVsoranRCSventopeningofgreaterthan1.1squareinchesensuresthattheRCSwillbeprotectedfrompressuretransientswhichcouldexceedthelimitsofAppendixGto10CFRPart50whenoneormoreoftheRCScoldlegsare<330'F.EitherPORVhasadequaterelievingcapabilitytoprotect;theRCSfromoverpressurizationwhenthetransientislimitedtoeither(1)thestartofanidleRCPwiththesecondarywatertemperatureofthesteamgenerator<50'FabovetheRCScoldlegtemperatureor(2)thestartofpsafetyinjectionpumpanditsinjectionintoawatersolidRCS. | | ) |
| | Rochester Gas and Electric Corporation ) Docket No. 50-244 (R. E. Ginna Nuclear Power Plant, ) |
| | Unit No. l) ) |
| | APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S. |
| | Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RG&E"), holder of Provisional Operating License No. DPR-l8, hereby requests that the Technical Specifica-tions set forth in Appendix A to that license be amended to change reactor overpressure protection system requirements. |
| | The proposed technical specification change is set forth in Attachment A to this Application. A safety evaluation is set forth in Attachment B. This evaluation also demonstrates that, the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility. Justifi-cation for classification of the amendment pursuant to 10 C.F.R. |
| | Section 170.22 is included as Attachment C. A check for the appropriate fee accompanies this Application. |
| | |
| | WHEREFORE, Applicant respectfully requests that Appendix A to Provisional Operating License No. DPR-18 be amended in the form attached hereto as Attachment A. |
| | Rochester Gas and Electric Corporation By L.D. Who., Jr. |
| | Vice President, Electric and Steam Production Subscribed and sworn to before me'n this I 7 day of July, 1979. |
| | STEPHEN KOWBA NOTARY PUBLlC, State of N. Y, Monroe County fty Commission Expires March 30, 19/17 |
| | |
| | BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of ) |
| | ) |
| | ROCHESTER GAS AND ELECTRXC ) |
| | CORPORATION ) |
| | (R. E. Ginna Nuclear Power Docket No. 50-244 |
| | ) |
| | Station, Unit, No. 1) ) |
| | CERTIPXCATE OF SERVICE I hereby certify that I have served a document entitled "Application for 'Amendment to Operating License" with three (3) documents, Attachments A, B and C, attached thereto, by mailing copies thereof first class, postage pre-paid, to each of the following persons this 19th day of July 1979: |
| | Mr. Michael L. Slade 1250 Crown Point Drive Webster, New York 14580 Warren B. Rosenbaum, Esquire One Main Street 707 Wilder Building Rochester, New York 14614 Edward G. Ketchen, Esquire Office of the Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Robert N. Pickney Supervisor Town of Ontario 197 Ridge Road West Ontario, New York 14519 |
| | |
| | Jeffrey L. Cohen, Esquire New York State Energy Office Swan Street Building Core l, Second Floor Empire State Plaza Albany, New York l2223 Edward Luton, Esquire Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Dr. Dixon Callihan Union Carbide Corporation P.O. Box Y Oak Ridge, Tennessee 37830 o ert S. Faron LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation |
| | |
| | ATTACHMENT A Ove ressure Protection S stem |
| | ~ld>> |
| | Applies whenever the temperature of one or more of the RCS cold legs is < 330'F. |
| | Ob 'ective To prevent, overpressurization of the reactor coolant system. |
| | S ecification |
| | / 3.15.1 Except during secondary side hydrostatic tests, at least one of the following overpressure protection systems shall be operable: |
| | a pressurizer power operated relief valves |
| | ~ Two (PORVs)'ith a lift setting of < 435 psig, or |
| | : b. A reactor coolant system vent of > 1.1 square inches. |
| | 3.15.1.1 With one PORV inoperable', either restore the inoperable PORV to operable status within 7 days or depressurize and vent the RCS through a 1.1 square inch vent(s) within the next 8 hours; maintain the RCS in a vented condition until both PORVs have been restored to operable status. |
| | 3.15.1.2 With both PORVs inoperable, depressurize and vent the RCS through a 1.1 square inch vent(s) within 8 hours; maintain the RCS in a vented condition until both PORVs have been restored to operable status. |
| | 3.15.1.3 Use of the overpressure protection system to mitigate a RCS pressure transient shall be reported in accordance with 6.9.3. |
| | Basis The operability of two pressurizer PORVs or an RCS vent opening of greater than 1.1 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are < 330'F. Either PORV has adequate relieving capability to protect; the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator < 50'F above the RCS cold leg temperature or (2) the start of p safety injection pump and its injection into a water solid RCS. |
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| ==References:== | | ==References:== |
| (1)L.D.White,Jr.lettertoA.Schwencer,NRC,datedJuly29,19773.15-1Proposed AttachmentBAreactorcoolantsystemOverpressureProtectionSystem(OPS)hasbeeninstalledatR.E.GinnatomitigatepressuretransientsthatmightotherwiseexceedthoselimitswhicharebaseduponAppendixGto10CFRPart50.Thesystemisdesignedtomitigatetransientswhichmayresultfrompersonnelerror,equipmentmal-functionorproceduraldeficiencies.AdescriptionofthissystemwasprovidedinlettersfromMr.L.D.White,Jr.,RochesterGasandElectricCorporation,toMr.A.Schwencer,U.S.NuclearRegulatoryCommission,datedFebruary24,1977,March31,1977,andJuly29,1977.TheOPSwillpreventawatersolidreactorcoolantsystemfromexceedingapressureof535psigforasafetyinjectionpumpdischargingtothereactorcoolantsystem,areactorcoolantpumpstartdischargingtothereactorcoolantsystem,areactorcoolantpumpstartwitha50'Ftemperaturedifferentialbetweentheprimaryandsecondarysystemsorlessseveremassinputorheatinputtransients.Specification3.15requiresthatanoverpressureprotectionsystembeoperablewhenoneormoreoftheRCScoldlegtemperaturesislessthanorequalto330'F.Fortemperaturesgreaterthan330'FtheallowableRCSpressureisgreaterthanthenormalreliefpressureofthetwopressurizerpoweroperatedreliefvalvessothatnootheroverpressureprotectionisrequired.Below330'FeachofthePORVs,usingalowpressuresetpointof435psig,willmitigatethelimitingmassinputandheatinputpressuretransientsinawater-solidRCS.ThesinglesetpointwasestablishedtopreventexceedingtheallowableRCSpressureat100'Fanddoesnotprovideforpressureincreaseswhichwouldnormallybeacceptablewithincreasingtemperature.GinnaStationhasadministrativelylimitedthepressuredif-ferentialfromthesecondarysidetotheprimarysideofthesteamgeneratorsto800psid.Thislimithasbeenimposedtolimitstressesplacedonthesteamgeneratorwhichmaycausecladdingintheprimarychannelheadtoseparatefromthebasemetal.AlthoughGinnahasneverexperiencedcladdingseparation,severalotherplantsofthesamevintagedidintheirearlyoperatinghistory.The800psidpressurelimitationisconsideredawiseandprudentprecautiontolimitthepotentialfordifficultrepairsinahighradiationarea.Duringsecondarysidehydrostatictestingtherequirementsforhighsecondarysidepressure,limitedRCSpressureduetoOPSopera-tionandamaximum800psidifferentialpressurearemutuallyexclusive.TheOPSisneededonlyintheunlikelyeventofapressuretransient.DuringinfrequentsecondarysidehydrostatictestsextraprecautionscanbeimplementedtopreventpressuretransientswiththeOPSdeactivatedandtoallowcompliancewiththeotherconstraintsplaceduponthesteamgenerators. | | |
| DuringnormaloperationwhentheOPSisrequiredtobeoperable,amaximumofonesafetyinjectionpumpisallowedtobeoperabletoassurethatamassadditionpressuretransientcanberelievedbyasinglePORV.Duringthesecondarysidehydrostatictestnosafetyinjectionpumpswillbeallowedtooperate.TheOPSwillmitigatetheeffectsofareactorcoolantpumpstartwiththesecondarysideofthesteamgeneratorsatleast50'Fwarmerthanthereactorcoolantsystem.Priortothesecondarysidehydrostatictestthetemperaturedifferentialwillbeminimizedbothtoaidintheperformanceofthetestandtopreventapressuretransientintheeventofaninadvertentreactorcoolantpumpstart.TheexistinglimitationsontheoperationofthechargingpumpswhentheRCSisbeingcooledbytheRHRsystemwithouttheOPSoperablewillbefollowed.Theselimitationswillpreventin-advertentoverpressurizationoftheRHRsystemshouldletdownbeterminated.TheOPShasnotbeenchallengedatGinnaStation.EtwillbeoperablebeforeandafterthesecondarysidehydrostatictestasrequiredbytheRCStemperature.DuringthehydrostatictestwhentheOPSisnotoperablethenormaloperationsshiftwillbesupplementedbyanadditionallicensedoperator.Thisoperatorwillbechargedwiththeresponsibilityofassuringthatalltheadministrativecontrolsandprecautionsnecessarytopreventoverpressuretransientswillbeobserved.Thus,thereisadequateassurancethatapressuretransientwillnotoccurduringasecondarysidehydrostatictestandthatthetestcanbesafelyperformedwithouttheOPSoperable.
| | (1) L. D. White, Jr. letter to A. Schwencer, NRC, dated July 29, 1977 3.15-1 Proposed |
| AttachmentCTheproposedAmendmenttotheProvisionalOperatingLicensehasbeenevaluatedanddeterminedtofallwithinthedefinitionofClassIIIof10C.F.R.Section170.22therebyrequiringafeeof$4,000.Theproposedamendmentdealswithasinglesafetyissue,over-pressureprotectionofthereactorvessel.TheissuehasbeenclearlyidentifiedbyanNRCposition.}}
| | |
| | Attachment B A reactor coolant system Overpressure Protection System (OPS) has been installed at R. E. Ginna to mitigate pressure transients that might otherwise exceed those limits which are based upon Appendix G to 10 CFR Part 50. The system is designed to mitigate transients which may result from personnel error, equipment mal-function or procedural deficiencies. A description of this system was provided in letters from Mr. L. D. White, Jr., Rochester Gas and Electric Corporation, to Mr. A. Schwencer, U. S. Nuclear Regulatory Commission, dated February 24, 1977, March 31, 1977, and July 29, 1977. The OPS will prevent a water solid reactor coolant system from exceeding a pressure of 535 psig for a safety injection pump discharging to the reactor coolant system, a reactor coolant pump start discharging to the reactor coolant system, a reactor coolant pump start with a 50'F temperature differential between the primary and secondary systems or less severe mass input or heat input transients. |
| | Specification 3.15 requires that an overpressure protection system be operable when one or more of the RCS cold leg temperatures is less than or equal to 330'F. For temperatures greater than 330'F the allowable RCS pressure is greater than the normal relief pressure of the two pressurizer power operated relief valves so that no other overpressure protection is required. Below 330'F each of the PORVs, using a low pressure setpoint of 435 psig, will mitigate the limiting mass input and heat input pressure transients in a water-solid RCS. |
| | The single setpoint was established to prevent exceeding the allowable RCS pressure at 100'F and does not provide for pressure increases which would normally be acceptable with increasing temperature. |
| | Ginna Station has administratively limited the pressure dif-ferential from the secondary side to the primary side of the steam generators to 800 psid. This limit has been imposed to limit stresses placed on the steam generator which may cause cladding in the primary channel head to separate from the base metal. |
| | Although Ginna has never experienced cladding separation, several other plants of the same vintage did in their early operating history. The 800 psid pressure limitation is considered a wise and prudent precaution to limit the potential for difficult repairs in a high radiation area. |
| | During secondary side hydrostatic testing the requirements for high secondary side pressure, limited RCS pressure due to OPS opera-tion and a maximum 800 psi differential pressure are mutually exclusive. The OPS is needed only in the unlikely event of a pressure transient. During infrequent secondary side hydrostatic tests extra precautions can be implemented to prevent pressure transients with the OPS deactivated and to allow compliance with the other constraints placed upon the steam generators. |
| | |
| | During normal operation when the OPS is required to be operable, a maximum of one safety injection pump is allowed to be operable to assure that a mass addition pressure transient can be relieved by a single PORV. During the secondary side hydrostatic test no safety injection pumps will be allowed to operate. |
| | |
| | The OPS will mitigate the effects of a reactor coolant pump start with the secondary side of the steam generators at least 50'F warmer than the reactor coolant system. Prior to the secondary side hydrostatic test the temperature differential will be minimized both to aid in the performance of the test and to prevent a pressure transient in the event of an inadvertent reactor coolant pump start. |
| | The existing limitations on the operation of the charging pumps when the RCS is being cooled by the RHR system without the OPS operable will be followed. These limitations will prevent in-advertent overpressurization of the RHR system should letdown be terminated. |
| | The OPS has not been challenged at Ginna Station. Et will be operable before and after the secondary side hydrostatic test as required by the RCS temperature. |
| | During the hydrostatic test when the OPS is not operable the normal operations shift will be supplemented by an additional licensed operator. This operator will be charged with the responsibility of assuring that all the administrative controls and precautions necessary to prevent overpressure transients will be observed. |
| | Thus, there is adequate assurance that a pressure transient will not occur during a secondary side hydrostatic test and that the test can be safely performed without the OPS operable. |
| | |
| | Attachment C The proposed Amendment to the Provisional Operating License has been evaluated and determined to fall within the definition of Class III of 10 C.F.R. Section 170.22 thereby requiring a fee of |
| | $ 4,000. |
| | The proposed amendment deals with a single safety issue, over-pressure protection of the reactor vessel. The issue has been clearly identified by an NRC position.}} |
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[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
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
)
Rochester Gas and Electric Corporation ) Docket No. 50-244 (R. E. Ginna Nuclear Power Plant, )
Unit No. l) )
APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.
Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RG&E"), holder of Provisional Operating License No. DPR-l8, hereby requests that the Technical Specifica-tions set forth in Appendix A to that license be amended to change reactor overpressure protection system requirements.
The proposed technical specification change is set forth in Attachment A to this Application. A safety evaluation is set forth in Attachment B. This evaluation also demonstrates that, the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility. Justifi-cation for classification of the amendment pursuant to 10 C.F.R.
Section 170.22 is included as Attachment C. A check for the appropriate fee accompanies this Application.
WHEREFORE, Applicant respectfully requests that Appendix A to Provisional Operating License No. DPR-18 be amended in the form attached hereto as Attachment A.
Rochester Gas and Electric Corporation By L.D. Who., Jr.
Vice President, Electric and Steam Production Subscribed and sworn to before me'n this I 7 day of July, 1979.
STEPHEN KOWBA NOTARY PUBLlC, State of N. Y, Monroe County fty Commission Expires March 30, 19/17
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of )
)
ROCHESTER GAS AND ELECTRXC )
CORPORATION )
(R. E. Ginna Nuclear Power Docket No. 50-244
)
Station, Unit, No. 1) )
CERTIPXCATE OF SERVICE I hereby certify that I have served a document entitled "Application for 'Amendment to Operating License" with three (3) documents, Attachments A, B and C, attached thereto, by mailing copies thereof first class, postage pre-paid, to each of the following persons this 19th day of July 1979:
Mr. Michael L. Slade 1250 Crown Point Drive Webster, New York 14580 Warren B. Rosenbaum, Esquire One Main Street 707 Wilder Building Rochester, New York 14614 Edward G. Ketchen, Esquire Office of the Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Robert N. Pickney Supervisor Town of Ontario 197 Ridge Road West Ontario, New York 14519
Jeffrey L. Cohen, Esquire New York State Energy Office Swan Street Building Core l, Second Floor Empire State Plaza Albany, New York l2223 Edward Luton, Esquire Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Dr. Dixon Callihan Union Carbide Corporation P.O. Box Y Oak Ridge, Tennessee 37830 o ert S. Faron LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation
ATTACHMENT A Ove ressure Protection S stem
~ld>>
Applies whenever the temperature of one or more of the RCS cold legs is < 330'F.
Ob 'ective To prevent, overpressurization of the reactor coolant system.
S ecification
/ 3.15.1 Except during secondary side hydrostatic tests, at least one of the following overpressure protection systems shall be operable:
a pressurizer power operated relief valves
~ Two (PORVs)'ith a lift setting of < 435 psig, or
- b. A reactor coolant system vent of > 1.1 square inches.
3.15.1.1 With one PORV inoperable', either restore the inoperable PORV to operable status within 7 days or depressurize and vent the RCS through a 1.1 square inch vent(s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both PORVs have been restored to operable status.
3.15.1.2 With both PORVs inoperable, depressurize and vent the RCS through a 1.1 square inch vent(s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both PORVs have been restored to operable status.
3.15.1.3 Use of the overpressure protection system to mitigate a RCS pressure transient shall be reported in accordance with 6.9.3.
Basis The operability of two pressurizer PORVs or an RCS vent opening of greater than 1.1 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are < 330'F. Either PORV has adequate relieving capability to protect; the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator < 50'F above the RCS cold leg temperature or (2) the start of p safety injection pump and its injection into a water solid RCS.
References:
(1) L. D. White, Jr. letter to A. Schwencer, NRC, dated July 29, 1977 3.15-1 Proposed
Attachment B A reactor coolant system Overpressure Protection System (OPS) has been installed at R. E. Ginna to mitigate pressure transients that might otherwise exceed those limits which are based upon Appendix G to 10 CFR Part 50. The system is designed to mitigate transients which may result from personnel error, equipment mal-function or procedural deficiencies. A description of this system was provided in letters from Mr. L. D. White, Jr., Rochester Gas and Electric Corporation, to Mr. A. Schwencer, U. S. Nuclear Regulatory Commission, dated February 24, 1977, March 31, 1977, and July 29, 1977. The OPS will prevent a water solid reactor coolant system from exceeding a pressure of 535 psig for a safety injection pump discharging to the reactor coolant system, a reactor coolant pump start discharging to the reactor coolant system, a reactor coolant pump start with a 50'F temperature differential between the primary and secondary systems or less severe mass input or heat input transients.
Specification 3.15 requires that an overpressure protection system be operable when one or more of the RCS cold leg temperatures is less than or equal to 330'F. For temperatures greater than 330'F the allowable RCS pressure is greater than the normal relief pressure of the two pressurizer power operated relief valves so that no other overpressure protection is required. Below 330'F each of the PORVs, using a low pressure setpoint of 435 psig, will mitigate the limiting mass input and heat input pressure transients in a water-solid RCS.
The single setpoint was established to prevent exceeding the allowable RCS pressure at 100'F and does not provide for pressure increases which would normally be acceptable with increasing temperature.
Ginna Station has administratively limited the pressure dif-ferential from the secondary side to the primary side of the steam generators to 800 psid. This limit has been imposed to limit stresses placed on the steam generator which may cause cladding in the primary channel head to separate from the base metal.
Although Ginna has never experienced cladding separation, several other plants of the same vintage did in their early operating history. The 800 psid pressure limitation is considered a wise and prudent precaution to limit the potential for difficult repairs in a high radiation area.
During secondary side hydrostatic testing the requirements for high secondary side pressure, limited RCS pressure due to OPS opera-tion and a maximum 800 psi differential pressure are mutually exclusive. The OPS is needed only in the unlikely event of a pressure transient. During infrequent secondary side hydrostatic tests extra precautions can be implemented to prevent pressure transients with the OPS deactivated and to allow compliance with the other constraints placed upon the steam generators.
During normal operation when the OPS is required to be operable, a maximum of one safety injection pump is allowed to be operable to assure that a mass addition pressure transient can be relieved by a single PORV. During the secondary side hydrostatic test no safety injection pumps will be allowed to operate.
The OPS will mitigate the effects of a reactor coolant pump start with the secondary side of the steam generators at least 50'F warmer than the reactor coolant system. Prior to the secondary side hydrostatic test the temperature differential will be minimized both to aid in the performance of the test and to prevent a pressure transient in the event of an inadvertent reactor coolant pump start.
The existing limitations on the operation of the charging pumps when the RCS is being cooled by the RHR system without the OPS operable will be followed. These limitations will prevent in-advertent overpressurization of the RHR system should letdown be terminated.
The OPS has not been challenged at Ginna Station. Et will be operable before and after the secondary side hydrostatic test as required by the RCS temperature.
During the hydrostatic test when the OPS is not operable the normal operations shift will be supplemented by an additional licensed operator. This operator will be charged with the responsibility of assuring that all the administrative controls and precautions necessary to prevent overpressure transients will be observed.
Thus, there is adequate assurance that a pressure transient will not occur during a secondary side hydrostatic test and that the test can be safely performed without the OPS operable.
Attachment C The proposed Amendment to the Provisional Operating License has been evaluated and determined to fall within the definition of Class III of 10 C.F.R. Section 170.22 thereby requiring a fee of
$ 4,000.
The proposed amendment deals with a single safety issue, over-pressure protection of the reactor vessel. The issue has been clearly identified by an NRC position.