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| {{#Wiki_filter:BEFORETHEUNXTEDSTATESNUCLEARREGULATORY COMMISSSXON IntheMatterofROCHESTER GASANDELECTRICCORPORATION (R.E.GinnaNuclearPowerStation,UnitNo.1)CERTIFICATE OFSERVICEDocketNo.52-244IherebycertifythatIhaveservedadocumententitled"Application forAmendment toOperating License"withthree(3)documents, Attachments A,B,andC,attachedthereto,bymailingcopiesthereoffirstclass,postagepre-paid,toeach,ofthefollowing personsthis3rddayofAugust,1979:Mr.MichaelL.Slade12Trailwood CircleRochester, NewYork14618WarrenB.Rosenbaum, Esq.OneMainStreet707WilderBuildingRochester, NewYork14614EdwardG.Ketchen,Esp.OfficeoftheExecutive LegalDirectorU.S.NuclearRegulatory Commission Washington, D.C.20555Mr.RobertN.PickneySupervisor TownofOntario107RidgeRoadWestOntario,NewYork14519V908080Q/(p'- | | {{#Wiki_filter:BEFORE THE UNXTED STATES NUCLEAR REGULATORY COMMISSSXON In the Matter of ROCHESTER GAS AND ELECTRIC CORPORATION (R.E.Ginna Nuclear Power Station, Unit No.1)CERTIFICATE OF SERVICE Docket No.52-244 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 3rd day of August, 1979: Mr.Michael L.Slade 12 Trailwood Circle Rochester, New York 14618 Warren B.Rosenbaum, Esq.One Main Street 707 Wilder Building Rochester, New York 14614 Edward G.Ketchen, Esp.Office of the Executive Legal Director U.S.Nuclear Regulatory Commission Washington, D.C.20555 Mr.Robert N.Pickney Supervisor Town of Ontario 107 Ridge Road West Ontario, New York 14519 V 908080 Q/(p'- |
| JeffreyL.Cohen,Esq.NewYorkStateEnergyOfficeSwanStreetBuildingCore1,SecondFloorEmpireStatePlazaAlbany,NewYorkl2223EdwardLuton,Esq.AtomicSafetyandLicensing BoardU.S.NuclearRegulatory CommissionWashington, D.C.20555Dr.EmmethA.LuebkeAtomicSafetyandLicensing BoardU.S.NuclearRegulatory CommissionWashington, D.C.20555Dr.DixonCallihanUnionCarbideCorporation P.O.BoxYOakRidge,Tennessee 37830LxK.LarsonLeBoeuf,Lamb,Leiby6MacRaeAttorneys forRochester GasandElectricCorporation II'if UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant,UnitNo.l),)))Docket.No.50-244))APPLICATION FORAMENDMENT TOOPERATING LICENSE<iPursuanttoSection50.90'oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission"
| | Jeffrey L.Cohen, Esq.New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza Albany, New York l2223 Edward Luton, Esq.Atomic Safety and Licensing Board U.S.Nuclear Regulatory Commis sion Washington, D.C.20555 Dr.Emmeth A.Luebke Atomic Safety and Licensing Board U.S.Nuclear Regulatory Commis sion Washington, D.C.20555 Dr.Dixon Callihan Union Carbide Corporation P.O.Box Y Oak Ridge, Tennessee 37830 L x K.Larson LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation II'i f UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Rochester Gas and Electric Corporation (R.E.Ginna Nuclear Power Plant, Unit No.l),)))Docket.No.50-244))APPLICATION FOR AMENDMENT TO OPERATING LICENSE<i Pursuant to Section 50.90'of the regulations of the U.S.Nuclear Regulatory Commission (the"Commission"), Rochester Gas and Electric Corporation |
| ),Rochester GasandElectricCorporation | | ("RGB"), holder of Provisional Operating License No.DPR-18, hereby requests that the Technical Specifica-tions set forth in Appendix A to that license be amended to add requirements for undervoltage protection. |
| ("RGB"),holderofProvisional Operating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifica-tionssetforthinAppendixAtothatlicensebeamendedtoaddrequirements forundervoltage protection. | | This request for a change in the Technical Specifications revises and supersedes our request of December 22, 1977, and is submitted in response to a letter from A.Schwencer, Chief, Operating Reactors Branch 51, dated June 3, 1977.The proposed technical specification change is set forth in Attachment A to this Application. |
| ThisrequestforachangeintheTechnical Specifications revisesandsupersedes ourrequestofDecember22,1977,andissubmitted inresponsetoaletterfromA.Schwencer, Chief,Operating ReactorsBranch51,datedJune3,1977.Theproposedtechnical specification changeissetforthinAttachment AtothisApplication.
| | 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.Attachment C describes why no fee under 10 CFR 170.22 is required. |
| Asafetyevaluation issetforthinAttachment B.Thisevaluation alsodemonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.
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| Attachment Cdescribes whynofeeunder10CFR170.22isrequired. | |
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| WHEREFORE, Applicant respectfully requeststhatAppendixAtoProvisional Operating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment A.Rochester GasandElectricCorporation ByL.D.White,Jr.VicePresident, ElectricandSteamProduction Subscribed andsworntobeforemeonthis3IdayofJuly1979.ROSEMARIEPERROHEIIQTftIIY PUBLIC,StateofII.Y.,MonroeCountyMyCommission ExpiresMarch30,Qg~ | | 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.White, Jr.Vice President, Electric and Steam Production Subscribed and sworn to before me on this 3I day of July 1979.ROSE MARIE PERROHE IIQTftIIY PUBLIC, State of II.Y., Monroe County My Commission Expires March 30, Qg~ |
| Attachment A1.Removepages2.3-4,2.3-8,3.5-4,3.5-4a,and4.1-7.2.Inserttheenclosedrevisedpages2.3-4,2.3-8,2.3-9,3.5-4aand4.1-7. | | Attachment A 1.Remove pages 2.3-4, 2.3-8, 3.5-4, 3.5-4a, and 4.1-7.2.Insert the enclosed revised pages 2.3-4, 2.3-8, 2.3-9, 3.5-4a and 4.1-7. |
| f.Lowreactorcoolantflow->90%ofnormalindicated flow~g.Lowreactorcoolantpumpfrequency | | f.Low reactor coolant flow->90%of normal indicated flow~g.Low reactor coolant pump frequency->57.5 Hz.2.3.1.3 Other reactor tri s 2.3.2 a.High pressurizer water level-<92%of span b.Low-low steam generator water level->5%of narrow range instrument span Protective instrumentation settings for reactor trip inter-locks shall be as follows: 2.3.2.1 Remove bypass of"at power" reactor trips at high power (low pressurizer pressure and low reactor coolant flow)for both loops: Power range nuclear flux-<8.'5%of rated power (1)(Note: During cold rod drop tests, the pressurizer high level trip may be bypassed.) |
| ->57.5Hz.2.3.1.3Otherreactortris2.3.2a.Highpressurizer waterlevel-<92%ofspanb.Low-lowsteamgenerator waterlevel->5%ofnarrowrangeinstrument spanProtective instrumentation settingsforreactortripinter-locksshallbeasfollows:2.3.2.1Removebypassof"atpower"reactortripsathighpower(lowpressurizer pressureandlowreactorcoolantflow)forbothloops:Powerrangenuclearflux-<8.'5%ofratedpower(1)(Note:Duringcoldroddroptests,thepressurizer highleveltripmaybebypassed.) | | 2.3.2.2 Remove bypass of single loss of flow trip at, high power: 2.3.3 Power range nuclear flux-<50%of rated power Relay settings for 480 volt safeguards bus protection shall be as follows: 2.3.3.1 Loss of voltage relay operating time<8.5 seconds for 480 volt safeguards bus voltages<368 volts 2.3.3.2 Acceptable degraded voltage relay operating times and setpoints, for 480 volt safeguards bus voltages<414 volts'and>368 volts are defined by the safeguard equip-ment thermal capability curve shown in Figure 2.3-1.Basis: TTTe Eigh flux reactor trip (low set point)provides redundant pro-tection in the power range for a power excursion beginning fop low power.This trip value was used in the safety analysis.2.3-4 PROPOSED e 0 the minimum DNB ratio increases at lower flow because the maximum enthalpy rise does not increase.For this reason the single pump loss of flow trip can be bypassed below 50%power.The loss of voltage and degraded voltage trips ensure opera-bility of safeguards equipment during a postulated design basis (9)(10)(11) event concurrent with a degraded bus voltage condition. |
| 2.3.2.2Removebypassofsinglelossofflowtripat,highpower:2.3.3Powerrangenuclearflux-<50%ofratedpowerRelaysettingsfor480voltsafeguards busprotection shallbeasfollows:2.3.3.1Lossofvoltagerelayoperating time<8.5secondsfor480voltsafeguards busvoltages<368volts2.3.3.2Acceptable degradedvoltagerelayoperating timesandsetpoints, for480voltsafeguards busvoltages<414volts'and | |
| >368voltsaredefinedbythesafeguard equip-mentthermalcapability curveshowninFigure2.3-1.Basis:TTTeEighfluxreactortrip(lowsetpoint)providesredundant pro-tectioninthepowerrangeforapowerexcursion beginning foplowpower.Thistripvaluewasusedinthesafetyanalysis. | |
| 2.3-4PROPOSED e0theminimumDNBratioincreases atlowerflowbecausethemaximumenthalpyrisedoesnotincrease. | |
| Forthisreasonthesinglepumplossofflowtripcanbebypassedbelow50%power.Thelossofvoltageanddegradedvoltagetripsensureopera-bilityofsafeguards equipment duringapostulated designbasis(9)(10)(11) eventconcurrent withadegradedbusvoltagecondition.
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| ==References:== | | ==References:== |
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| (1)FSAR14.1.1(2)FSAR,Page14-3(3)FSAR14.3.1(4)FSAR14.1.2(5)FSAR72I 7~3(6)FSAR3.2.1(7)FSAR14.1.6(8)FSAR14.1.9(9)LetterfromL.D.White,Jr.toA.Schwencer, NRC,datedSeptember 30,1977(10)LetterfromL.D.White,Jr.toA.Schwencer, NRC,datedSeptember 301977(11)LetterfromL.D.White,Jr.toD.Ziemann,NRC,datedJuly24,19782.3-8PROPOSED o.016001400IISecondLevelI~I.'UnderVoltageProtection LIFigure2.3-11200~ltdI88d001000800600-+-'I'I~I~I~~I"I~1400I+.AllowaI"blIlaOeReyperI'IlatingI200~iReion0Secondary Volts(120Volts).PrimaryVolts(480Volts)t240PercentVolts(460VoltBase)5287080909232036870%80%103.5'1490%120=480104%ISafeguards BusVoltage'.3-9 PROPOSEDs~I Page3of312356NO.ofMIN.MIN.PERMISSIBLE OPERATORACTIONNO.ofCHANNELSOPERABLEDEGREEOFBYPASSIFCONDITIONS OFCHANNELSTOTRIPCHANNELSREDUNDANCY CONDITIONS COLUMN3or5CANNOTBEMET17.Circulating WaterFloodProtection a.Screenhouse 2b.Condenser 18.LossofVoltage/DegradedVoltage480VoltSafe-guardsBus4/bus2/bus2/busNOTE1:Whenblockcondition exists,maintainnormaloperation. | | (1)FSAR 14.1.1 (2)FSAR, Page 14-3 (3)FSAR 14.3.1 (4)FSAR 14.1.2 (5)FSAR72I 7~3 (6)FSAR 3.2.1 (7)FSAR 14.1.6 (8)FSAR 14.1.9 (9)Letter from L.D.White, Jr.to A.Schwencer, NRC, dated September 30, 1977 (10)Letter from L.D.White, Jr.to A.Schwencer, NRC, dated September 30 1977 (11)Letter from L.D.White, Jr.to D.Ziemann, NRC, dated July 24, 1978 2.3-8 PROPOSED o.0 1600 1400 I I Second Level I~I.'Under Voltage Protection L I Figure 2.3-1 1200~l td I 8 8 d 0 0 1000 800 600-+-'I'I~I~I~~I"I~1 400 I+.All owa I" bl I la O e Re y per I'I l ating I 200~iRe ion 0 Secondary Volts (120 Volts).Primary Volts (480 Volts)t 240 Percent Volts (460 Volt Base)528 70 80 90 92 320 368 70%80%103.5'14 90%120=480 104%ISafeguards Bus Voltage'.3-9 PROP OSED s~I Page 3 of 3 1 2 3 5 6 NO.of MIN.MIN.PERMISSIBLE OPERATOR ACTION NO.of CHANNELS OPERABLE DEGREE OF BYPASS IF CONDITIONS OF CHANNELS TO TRIP CHANNELS REDUNDANCY CONDITIONS COLUMN 3 or 5 CANNOT BE MET 17.Circulating Water Flood Protection a.Screenhouse 2 b.Condenser 18.Loss of Voltage/Degraded Voltage 480 Volt Safe-guards Bus 4/bus 2/bus 2/bus NOTE 1: When block condition exists, maintain normal operation. |
| Poweroperation maybecontinued foraperiodofupto7dayswith1channelinoperable orforaperiodof24h~withtwochannelsin~operable.
| | Power operation may be continued for a period of up to 7 days with 1 channel inoperable or for a period of 24 h~with two channels in~operable.Power operation may be continued for a period of up to 7 days with 1 channel inoperable or for a period of 24 hrs.with two channels inoperable. |
| Poweroperation maybecontinued foraperiodofupto7dayswith1channelinoperable orforaperiodof24hrs.withtwochannelsinoperable.
| | Maintain hot shut-down or place bus on diesel generator. |
| Maintainhotshut-downorplacebusondieselgenerator.
| | F.P.***Full Power Not Applicable If both rod misalignment monitors (a and b)inoperable for 2 hours or more, the nuclear overpower trip shall be reset to 93%of rated power in addition to the in-creased surveillance noted.If a functional unit is operating with the minimum operable channels, the number of channels to trip the reactor will be column 3 less column 4.A channel is considered operable with 1 out of 2 logic or 2 out of 3 logic. |
| F.P.***FullPowerNotApplicable Ifbothrodmisalignment monitors(aandb)inoperable for2hoursormore,thenuclearoverpower tripshallberesetto93%ofratedpowerinadditiontothein-creasedsurveillance noted.Ifafunctional unitisoperating withtheminimumoperablechannels, thenumberofchannelstotripthereactorwillbecolumn3lesscolumn4.Achannelisconsidered operablewith1outof2logicor2outof3logic. | | TABLE 4.1-1 (CONTINUED) |
| TABLE4.1-1(CONTINUED)
| | Channel Check Calibrate Test Remarks 25.Containment Pressure 26.Steam Generator Pressure Narrow range containment pressure (-3.0,+3 psig excluded)27.Turbine First Stage Pressure S 28.Emergency Plan Radiation Instruments 29.Environmental Monitors N.A.N.A.30.Loss of Voltage/Degraded Voltage 480 Volt Safe-guards Bus.N.A.S-Each Shift D-Daily B/N-Biweekly Q-Quarterly M-Monthly P-Prior to each startup if not done previous week R.-Each Refueling Shutdown N.A.-Not applicable Attachment B By letter dated June 3;1977, the NRC requested that RG&E assess the susceptibility of safety related electrical equipment with regard to (1)sustained degraded voltage conditions at the offsite power sources and (2)interaction between the offsite and onsite emergency power sources.An analysis of undervoltage protection at Ginna Station was performed and submitted to the NRC in a letter dated July 21, 1977.This analysis reviewed the current undervoltage protection and described the basis for a modification which would reduce the Station's susceptibility to a sustained degraded voltage.However, due to lack of specific information regarding equipment, setpoints for the additional undervoltage protection were not established at that time.Following receipt of additional information, RG&E submitted setpoints in a letter to the NRC dated September 30, 1977.The proposed specifications are identical to those presented in the September 30 letter.These Specifications will provide protection for a complete loss of 480 volt.bus voltage as well as for degraded voltage conditions. |
| ChannelCheckCalibrate TestRemarks25.Containment Pressure26.SteamGenerator PressureNarrowrangecontainment pressure(-3.0,+3psigexcluded) 27.TurbineFirstStagePressureS28.Emergency PlanRadiation Instruments 29.Environmental MonitorsN.A.N.A.30.LossofVoltage/Degraded Voltage480VoltSafe-guardsBus.N.A.S-EachShiftD-DailyB/N-BiweeklyQ-Quarterly M-MonthlyP-PriortoeachstartupifnotdonepreviousweekR.-EachRefueling ShutdownN.A.-Notapplicable Attachment BByletterdatedJune3;1977,theNRCrequested thatRG&Eassessthesusceptibility ofsafetyrelatedelectrical equipment withregardto(1)sustained degradedvoltageconditions attheoffsitepowersourcesand(2)interaction betweentheoffsiteandonsiteemergency powersources.Ananalysisofundervoltage protection atGinnaStationwasperformed andsubmitted totheNRCinaletterdatedJuly21,1977.Thisanalysisreviewedthecurrentundervoltage protection anddescribed thebasisforamodification whichwouldreducetheStation's susceptibility toasustained degradedvoltage.However,duetolackofspecificinformation regarding equipment, setpoints fortheadditional undervoltage protection werenotestablished atthattime.Following receiptofadditional information, RG&Esubmitted setpoints inalettertotheNRCdatedSeptember 30,1977.Theproposedspecifications areidentical tothosepresented intheSeptember 30letter.TheseSpecifications willprovideprotection foracompletelossof480volt.busvoltageaswellasfordegradedvoltageconditions.
| | Both relaying systems will assure that assumptions of all safety analysis are met.Specifically, equipment will be loaded onto the diesel generators within the time assumed in the safety analyses.The undervoltage relay protection, which was identified as"second-level protection" in the June 3, 1977 NRC letter and in our two subsequent letters, will protect equipment against a bus voltage which is greater than the loss of voltage relay setpoint but.less than the voltage guaranteed by equipment manufacturers for continuous duty for Ginna safeguards equipment. |
| Bothrelayingsystemswillassurethatassumptions ofallsafetyanalysisaremet.Specifically, equipment willbeloadedontothedieselgenerators withinthetimeassumedinthesafetyanalyses.
| | The proposed undervoltage setpoints will provide the required protection while also assuring that, spurious trips will not occur while equipment is being sequenced onto the diesel generators. |
| Theundervoltage relayprotection, whichwasidentified as"second-level protection" intheJune3,1977NRCletterandinourtwosubsequent letters,willprotectequipment againstabusvoltagewhichisgreaterthanthelossofvoltagerelaysetpointbut.lessthanthevoltageguaranteed byequipment manufacturers forcontinuous dutyforGinnasafeguards equipment.
| | The NRC Staff requested that the proposed system be modified to provide"coincident logic" as described in position 1, part b of their June 3, 1977 letter.Provision for"coincident, logic" does not.effect the setpoint information contained in the December 16, 1977 Application for Change to Operating License and re-submitted herewith.However, it has changed the required number of relays necessary to trip.The coincident logic scheme is described in our July 24, 1978 letter (ref.11 to the Technical Specification Basis).Loss of voltage and degraded voltage conditions simulated during the refueling shutdown are performed to verify both system performance and relay calibration. |
| Theproposedundervoltage setpoints willprovidetherequiredprotection whilealsoassuringthat,spurioustripswillnotoccurwhileequipment isbeingsequenced ontothedieselgenerators.
| | The safeguards 480 volt loss of voltage and degraded voltage protection systems are not part of the reactor protection system.It is not practical to simulate these conditions during plant operation to satisfy a monthly test requirement. |
| TheNRCStaffrequested thattheproposedsystembemodifiedtoprovide"coincident logic"asdescribed inposition1,partboftheirJune3,1977letter.Provision for"coincident, logic"doesnot.effectthesetpointinformation contained intheDecember16,1977Application forChangetoOperating Licenseandre-submitted herewith.
| | Based on the analyses provided in our letters of July 21, 1977, September 30, 1977, and July 24, 1978 the proposed Technical Specification will provide protection against 480 volt bus under-voltage. |
| However,ithaschangedtherequirednumberofrelaysnecessary totrip.Thecoincident logicschemeisdescribed inourJuly24,1978letter(ref.11totheTechnical Specification Basis).Lossofvoltageanddegradedvoltageconditions simulated duringtherefueling shutdownareperformed toverifybothsystemperformance andrelaycalibration. | |
| Thesafeguards 480voltlossofvoltageanddegradedvoltageprotection systemsarenotpartofthereactorprotection system.Itisnotpractical tosimulatetheseconditions duringplantoperation tosatisfyamonthlytestrequirement.
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| BasedontheanalysesprovidedinourlettersofJuly21,1977,September 30,1977,andJuly24,1978theproposedTechnical Specification willprovideprotection against480voltbusunder-voltage.
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| AsstatedinourletterofJuly21,1977,weexpectthat,following receiptofapprovalofthemodification designbytheNRC,detailedengineering andprocurement ofequipment willrequireapproximately 9months.Installation mustbeperformed at.acoldorrefueling shutdownandwouldrequireapproximately twoweeks..Theeffective dataofaTechnical Specification shouldbesetconsistent withthisschedule.
| | As stated in our letter of July 21, 1977, we expect that, following receipt of approval of the modification design by the NRC, detailed engineering and procurement of equipment will require approximately 9 months.Installation must be performed at.a cold or refueling shutdown and would require approximately two weeks..The effective data of a Technical Specification should be set consistent with this schedule. |
| Attachment CTheTechnical Specification changeproposalrevisesaproposaloriginally submitted December22,1977whichwasfiledpriortotheeffective dateof10CPR170.22.Therevisionisnecessary toincorporate achangeindesignwhichwasrequested bytheNRCStaff.Thedesignchangewasdescribed inoursubmittal ofJuly24,1978.BecauseitisarevisionwhichtheStaffrequested andisnowreviewing, andisnotanewrequest,nofeeisrequired. | | Attachment C The Technical Specification change proposal revises a proposal originally submitted December 22, 1977 which was filed prior to the effective date of 10 CPR 170.22.The revision is necessary to incorporate a change in design which was requested by the NRC Staff.The design change was described in our submittal of July 24, 1978.Because it is a revision which the Staff requested and is now reviewing, and is not a new request, no fee is required. |
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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] 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
BEFORE THE UNXTED STATES NUCLEAR REGULATORY COMMISSSXON In the Matter of ROCHESTER GAS AND ELECTRIC CORPORATION (R.E.Ginna Nuclear Power Station, Unit No.1)CERTIFICATE OF SERVICE Docket No.52-244 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 3rd day of August, 1979: Mr.Michael L.Slade 12 Trailwood Circle Rochester, New York 14618 Warren B.Rosenbaum, Esq.One Main Street 707 Wilder Building Rochester, New York 14614 Edward G.Ketchen, Esp.Office of the Executive Legal Director U.S.Nuclear Regulatory Commission Washington, D.C.20555 Mr.Robert N.Pickney Supervisor Town of Ontario 107 Ridge Road West Ontario, New York 14519 V 908080 Q/(p'-
Jeffrey L.Cohen, Esq.New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza Albany, New York l2223 Edward Luton, Esq.Atomic Safety and Licensing Board U.S.Nuclear Regulatory Commis sion Washington, D.C.20555 Dr.Emmeth A.Luebke Atomic Safety and Licensing Board U.S.Nuclear Regulatory Commis sion Washington, D.C.20555 Dr.Dixon Callihan Union Carbide Corporation P.O.Box Y Oak Ridge, Tennessee 37830 L x K.Larson LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation II'i f UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Rochester Gas and Electric Corporation (R.E.Ginna Nuclear Power Plant, Unit No.l),)))Docket.No.50-244))APPLICATION FOR AMENDMENT TO OPERATING LICENSE90%of normal indicated flow~g.Low reactor coolant pump frequency->57.5 Hz.2.3.1.3 Other reactor tri s 2.3.2 a.High pressurizer water level-<92%of span b.Low-low steam generator water level->5%of narrow range instrument span Protective instrumentation settings for reactor trip inter-locks shall be as follows: 2.3.2.1 Remove bypass of"at power" reactor trips at high power (low pressurizer pressure and low reactor coolant flow)for both loops: Power range nuclear flux-<8.'5%of rated power (1)(Note: During cold rod drop tests, the pressurizer high level trip may be bypassed.)
2.3.2.2 Remove bypass of single loss of flow trip at, high power: 2.3.3 Power range nuclear flux-<50%of rated power Relay settings for 480 volt safeguards bus protection shall be as follows: 2.3.3.1 Loss of voltage relay operating time<8.5 seconds for 480 volt safeguards bus voltages<368 volts 2.3.3.2 Acceptable degraded voltage relay operating times and setpoints, for 480 volt safeguards bus voltages<414 volts'and>368 volts are defined by the safeguard equip-ment thermal capability curve shown in Figure 2.3-1.Basis: TTTe Eigh flux reactor trip (low set point)provides redundant pro-tection in the power range for a power excursion beginning fop low power.This trip value was used in the safety analysis.2.3-4 PROPOSED e 0 the minimum DNB ratio increases at lower flow because the maximum enthalpy rise does not increase.For this reason the single pump loss of flow trip can be bypassed below 50%power.The loss of voltage and degraded voltage trips ensure opera-bility of safeguards equipment during a postulated design basis (9)(10)(11) event concurrent with a degraded bus voltage condition.
References:
(1)FSAR 14.1.1 (2)FSAR, Page 14-3 (3)FSAR 14.3.1 (4)FSAR 14.1.2 (5)FSAR72I 7~3 (6)FSAR 3.2.1 (7)FSAR 14.1.6 (8)FSAR 14.1.9 (9)Letter from L.D.White, Jr.to A.Schwencer, NRC, dated September 30, 1977 (10)Letter from L.D.White, Jr.to A.Schwencer, NRC, dated September 30 1977 (11)Letter from L.D.White, Jr.to D.Ziemann, NRC, dated July 24, 1978 2.3-8 PROPOSED o.0 1600 1400 I I Second Level I~I.'Under Voltage Protection L I Figure 2.3-1 1200~l td I 8 8 d 0 0 1000 800 600-+-'I'I~I~I~~I"I~1 400 I+.All owa I" bl I la O e Re y per I'I l ating I 200~iRe ion 0 Secondary Volts (120 Volts).Primary Volts (480 Volts)t 240 Percent Volts (460 Volt Base)528 70 80 90 92 320 368 70%80%103.5'14 90%120=480 104%ISafeguards Bus Voltage'.3-9 PROP OSED s~I Page 3 of 3 1 2 3 5 6 NO.of MIN.MIN.PERMISSIBLE OPERATOR ACTION NO.of CHANNELS OPERABLE DEGREE OF BYPASS IF CONDITIONS OF CHANNELS TO TRIP CHANNELS REDUNDANCY CONDITIONS COLUMN 3 or 5 CANNOT BE MET 17.Circulating Water Flood Protection a.Screenhouse 2 b.Condenser 18.Loss of Voltage/Degraded Voltage 480 Volt Safe-guards Bus 4/bus 2/bus 2/bus NOTE 1: When block condition exists, maintain normal operation.
Power operation may be continued for a period of up to 7 days with 1 channel inoperable or for a period of 24 h~with two channels in~operable.Power operation may be continued for a period of up to 7 days with 1 channel inoperable or for a period of 24 hrs.with two channels inoperable.
Maintain hot shut-down or place bus on diesel generator.
F.P.***Full Power Not Applicable If both rod misalignment monitors (a and b)inoperable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or more, the nuclear overpower trip shall be reset to 93%of rated power in addition to the in-creased surveillance noted.If a functional unit is operating with the minimum operable channels, the number of channels to trip the reactor will be column 3 less column 4.A channel is considered operable with 1 out of 2 logic or 2 out of 3 logic.
TABLE 4.1-1 (CONTINUED)
Channel Check Calibrate Test Remarks 25.Containment Pressure 26.Steam Generator Pressure Narrow range containment pressure (-3.0,+3 psig excluded)27.Turbine First Stage Pressure S 28.Emergency Plan Radiation Instruments 29.Environmental Monitors N.A.N.A.30.Loss of Voltage/Degraded Voltage 480 Volt Safe-guards Bus.N.A.S-Each Shift D-Daily B/N-Biweekly Q-Quarterly M-Monthly P-Prior to each startup if not done previous week R.-Each Refueling Shutdown N.A.-Not applicable Attachment B By letter dated June 3;1977, the NRC requested that RG&E assess the susceptibility of safety related electrical equipment with regard to (1)sustained degraded voltage conditions at the offsite power sources and (2)interaction between the offsite and onsite emergency power sources.An analysis of undervoltage protection at Ginna Station was performed and submitted to the NRC in a letter dated July 21, 1977.This analysis reviewed the current undervoltage protection and described the basis for a modification which would reduce the Station's susceptibility to a sustained degraded voltage.However, due to lack of specific information regarding equipment, setpoints for the additional undervoltage protection were not established at that time.Following receipt of additional information, RG&E submitted setpoints in a letter to the NRC dated September 30, 1977.The proposed specifications are identical to those presented in the September 30 letter.These Specifications will provide protection for a complete loss of 480 volt.bus voltage as well as for degraded voltage conditions.
Both relaying systems will assure that assumptions of all safety analysis are met.Specifically, equipment will be loaded onto the diesel generators within the time assumed in the safety analyses.The undervoltage relay protection, which was identified as"second-level protection" in the June 3, 1977 NRC letter and in our two subsequent letters, will protect equipment against a bus voltage which is greater than the loss of voltage relay setpoint but.less than the voltage guaranteed by equipment manufacturers for continuous duty for Ginna safeguards equipment.
The proposed undervoltage setpoints will provide the required protection while also assuring that, spurious trips will not occur while equipment is being sequenced onto the diesel generators.
The NRC Staff requested that the proposed system be modified to provide"coincident logic" as described in position 1, part b of their June 3, 1977 letter.Provision for"coincident, logic" does not.effect the setpoint information contained in the December 16, 1977 Application for Change to Operating License and re-submitted herewith.However, it has changed the required number of relays necessary to trip.The coincident logic scheme is described in our July 24, 1978 letter (ref.11 to the Technical Specification Basis).Loss of voltage and degraded voltage conditions simulated during the refueling shutdown are performed to verify both system performance and relay calibration.
The safeguards 480 volt loss of voltage and degraded voltage protection systems are not part of the reactor protection system.It is not practical to simulate these conditions during plant operation to satisfy a monthly test requirement.
Based on the analyses provided in our letters of July 21, 1977, September 30, 1977, and July 24, 1978 the proposed Technical Specification will provide protection against 480 volt bus under-voltage.
As stated in our letter of July 21, 1977, we expect that, following receipt of approval of the modification design by the NRC, detailed engineering and procurement of equipment will require approximately 9 months.Installation must be performed at.a cold or refueling shutdown and would require approximately two weeks..The effective data of a Technical Specification should be set consistent with this schedule.
Attachment C The Technical Specification change proposal revises a proposal originally submitted December 22, 1977 which was filed prior to the effective date of 10 CPR 170.22.The revision is necessary to incorporate a change in design which was requested by the NRC Staff.The design change was described in our submittal of July 24, 1978.Because it is a revision which the Staff requested and is now reviewing, and is not a new request, no fee is required.
I