Similar Documents at Ginna |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999
Proposed Tech Specs,Consisting of 1999 Changes to TS Bases
ML17265A6941999-06-28028 June 1999
Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping
ML17265A6401999-05-12012 May 1999
Rev 11 to Technical Requirements Manual for Ginna Station.
ML17265A6261999-04-18018 April 1999
Rev 10 to Technical Requirements Manual (Trm), for Ginna Station
ML17311A0701999-04-14014 April 1999
Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
ML17309A6521999-04-14014 April 1999
Rev 14 to AP-RCS.1, Reactor Coolant Leak.
ML17309A6531999-04-13013 April 1999
Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr
ML17265A6111999-03-26026 March 1999
Rev 9 to Technical Requirements Manual for Ginna Station.
ML17265A5911999-03-0101 March 1999
Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6)
ML17265A5571999-02-25025 February 1999
Rev 4 to Technical Requirements Manual (Trm).
ML17265A5491999-02-12012 February 1999
to EOP FR-H.5, Response to SG Low Level.
ML17265A5481999-02-12012 February 1999
to EOP ATT-22.0, Attachment Restoring Feed Flow.
ML17265A5461999-02-12012 February 1999
0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required.
ML17309A6481999-01-25025 January 1999
Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr
ML17265A5151999-01-14014 January 1999
Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index
ML17265A5081999-01-0808 January 1999
Rev 7 to Technical Requirements Manual, for Ginna Station
ML17265A4961998-12-18018 December 1998
Rev 6 to Technical Requirements Manual.
ML20198C0361998-12-14014 December 1998
Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required
ML20198C0121998-12-14014 December 1998
Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow
ML20198C0581998-12-14014 December 1998
Rev 5 to FR-Z.1, Response to High Containment Pressure
ML20198C0411998-12-14014 December 1998
Rev 16 to FR-C.1, Response to Inadequate Core Cooling
ML20198C0521998-12-14014 December 1998
Rev 13 to FR-S.1, Response to Reactor Restart/Atws
ML17265A4661998-11-24024 November 1998
Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR
ML20155G0301998-10-30030 October 1998
Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop
ML17265A4091998-08-24024 August 1998
Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr
ML17265A3721998-07-16016 July 1998
Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr
ML17265A3151998-06-0404 June 1998
Proposed Tech Specs Basis Re Main Steam Isolation Setpoint
ML17265A2941998-05-21021 May 1998
Tech Specs Consisting of Submittal Changes for 1998
ML17265A2861998-05-0606 May 1998
Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr
ML17265A2461998-04-27027 April 1998
Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool
ML17265A1821998-02-20020 February 1998
Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria.
ML17265A1491997-12-31031 December 1997
Rev 1 to Inservice Testing Program.
ML17264B0731997-10-14014 October 1997
Rev 4 to Technical Requirements Manual (TRM) for Ginna Station.
ML17264B0671997-10-0808 October 1997
Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements
ML17264B0441997-09-29029 September 1997
Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept
ML17264B0391997-09-29029 September 1997
Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study
ML17265A1541997-09-16016 September 1997
Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification.
ML17264B0031997-08-19019 August 1997
Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3
ML17264A9991997-08-19019 August 1997
Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values
ML17264A9791997-08-0505 August 1997
Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
ML17264A9781997-08-0505 August 1997
Rev 12 to AP-RCS.1, Reactor Coolant Leak.
ML17264A9771997-08-0505 August 1997
Rev 11 to AP-RCP.1, RCP Seal Malfunction.
ML17264A9751997-08-0505 August 1997
Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
ML17264A9851997-08-0404 August 1997
Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
ML17264A9391997-07-0707 July 1997
Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
ML17264A9341997-07-0101 July 1997
to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624
ML17264A9461997-06-20020 June 1997
to Inservice Insp (ISI) Program.
ML17264A9241997-06-0303 June 1997
Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection
ML17311A0471997-05-22022 May 1997
Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr
ML17264A8671997-04-24024 April 1997
Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements
1999-06-28
[Table view]
Category:TEST REPORT
MONTHYEARML17263A3221993-04-30030 April 1993
Reactor Containment Bldg Integrated Leakage Rate Apr 1993, Ginna Nuclear Station.
ML17250B0221989-05-31031 May 1989
Reactor Containment Bldg Integrated Leakage Rate.
ML17251A7911986-03-31031 March 1986
Reactor Containment Bldg Integrated Leakage Rate Test.
ML17309A3531984-08-15015 August 1984
1984 Steam Generator Eddy Current Exam Summary Rept. W/850306 Ltr
ML17254A8901984-06-26026 June 1984
Startup Physics Testing Program.
ML17255A7181984-01-31031 January 1984
Containment Vessel Tendons, 1983 Surveillance Final Rept
ML17255A7191983-12-31031 December 1983
Containment Vessel Tendons Stress Relaxation Properties of Retensioned Wires.
ML17256A6831983-04-15015 April 1983
Level Control Valve 427 Fuse Coordination - Ginna Station.
ML17256A4281982-12-15015 December 1982
Reactor Containment Bldg Integrated Leak Rate Test,May 1982.
ML17255A6891982-11-16016 November 1982
Dynamic Collapse of Steam Generator Tubes.
ML17256A9771982-05-18018 May 1982
Addendum 1, Lab Collapse Tests, Revision 0,to Steam Generator Evaluation,Ginna Steam Tube Failure Incident, 820125,RE Ginna Nuclear Power Plant.
ML17256A9811982-05-18018 May 1982
Addendum 3, Phase II Metallurgical Exams, Revision 0,to Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125,RE Ginna Nuclear Power Plant.
ML17256A9831982-05-18018 May 1982
Addendum 4, External Tube Loading Test, Revision 1 to Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125,RE Ginna Nuclear Power Plant.
ML17256A9791982-05-18018 May 1982
Addendum 2, Lab Fatigue Testing, Revision 0,to Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125,RE Ginna Nuclear Power Plant.
ML17256A8541982-04-26026 April 1982
Steam Generator Evaluation,Ginna Steam Tube Rupture Incident,820125,RE Ginna Nuclear Power Plant.
ML17258A2041981-09-21021 September 1981
Adequacy of Station Electric Distribution Sys Voltages.
ML17258A7461981-01-29029 January 1981
to App C-Ginna Station Inservice Pump & Valve Testing Program for 810101 Through 901230.
ML17250A5991980-07-31031 July 1980
Piping Stress Analysis Rept,Rhr Sys,Section 200.
ML17250A5901980-07-31031 July 1980
Re Ginna Nuclear Power Plant,Seismic Upgrading Program Piping Stress Analysis,Main Steam Sys,Section 200. Main Steam Containment Drawing Encl
ML17250A5861980-07-31031 July 1980
Piping Stress Analysis Rept,Rhr Sys,Section 250.
ML17249A9101980-04-11011 April 1980
Revised Pages 4,6 & I-2,Table 3 & Figure 1-A for Evaluation of Prestressed Tendon Forces.
ML17249A3371979-11-20020 November 1979
Evaluation of Prestressed Tendon Forces.
ML20081C0311976-02-28028 February 1976
Reactor Containment Bldg Integrated Leak Rate Test
ML17258A1351973-11-12012 November 1973
Qualification Tests for Modular Penetration 5 Diameter (Prototype B1).
ML17244A5781966-09-16016 September 1966
Submits Info Re Seismic Qualification of Mechanical & Electrical Equipment & Fluid & Electric Distribution Sys. Includes Test Repts,Tech Specs & Oversized Drawings
1993-04-30
[Table view] |
Text
1aJune26,1984StartupPhysicsTestingProgramCycle14StartupPhysicsTestingProgramwasconductedduringtheperiodfromMay11,1984toJune88,1984.Thestateddatesspanfrominitialcriticalitytoattainmentof188%power.Theresultsofthephysicstestingprogramshowedthatallmeasureddatawaswithintheboundsoftheacceptancecriteriatoleranceswithexceptionsasnotedbelow.ThePT-34seriesofprocedureswasusedtoperformthelowpowerphysicstestingmeasurementsinconjunctionwiththeS-15seriesforfluxmapping.Theprogramconsistedofdeterminingthefollowingparameters:l.Allrodsoutcriticalboronconcentration2.IsothermalTemperaturecoefficient3.ControlRodWorthsforBanks"D","C"and"B"4.Boronendpoints5.Coresymmetryandpowerdistributionmeasurements6.Criticalboronconcentration-FullPowerInitialcriticalitywasachievedon85/12/84at8458hours.TheHotZeroPowerparametersaslistedin1thru4abovewerethenmeasured.Thefluxsymmetrymappingandsubsequentpowerescalationandmeasurementofpowerdistributionandhotchannelfactorswasdelayeduntil5/23/84duetotheplantreturntocoldshutdownforsecondarychemistryconcerns.Thefollowingdatasummarizestheresultsofthetestingprogram.CriticalMeasurementsa~NuclearH~etDetermination:Nuclearheatwasobservedat~4x18ampsonChannelN-41.ItwasdeterminedfromthisthatalLreactivitymeasurementswouldbeperformedbelow2x18FullScaleampstostaybelownuclearheat.b.Reactiv~itComputerCheckout:Thereactorwasplacedonvaryingperiodstoprovideacomparisonofindicatedreactivitywiththatderivedfromperiodmeasurements.Thefollowingtablesummarizesthecomputercheckout:ControlBankTMeasured1Reactivity(PCM)TtDifferenceDStepsIReactorIl(M-P)x188WithdrawnIPeriod/SecondslMeasured(M)IPredicted(P)lP61826268'3157.298'523.1635.S652.5223~4536.153.1-1.25%.665-1.11%8408070526840709.PDRADOCK05000244PPDR
)(ttIt~St'ItItr,IItIlJII4IJt qc~'IsothermalTempatureCoefficient:Heatpandcooldownratesofapproximately18P7hr.wereestablishedtodeterminetheisothermaltemperaturecoefficient.Thefollowingdatasummarizestheresultsoftheaverageoftwoacceptabletraces.TAccetanceIMTCIsARO-4.9INotPositiveI-2.215+2.685IICore~MTCpDifferenceConfigurationIPredicted(P)ICriteriaIMeasured(M)I(M-P)1lrNOTE:ModeratorTemperatureCoefficient=ITC-(-1.66)d.ControlRodWorth:ControlRodworthwasmeasuredbyadjustingrodpositiontocompensatefordilution.Thefollowingtablesummarizestheintegralrodworthdata.PredictMeasuredDifferenceCtrlI(P)BankI(PCM)PPMIM-P(PCM)ICriter.PPPM(M)IAccept.I(M-P)x188IPredictIMeasureIDiffDC*BSum946184218822998914.5995.5827.52737.5+15%+15%+15%+18%3~334.46-17.428.4418211418331912318398324+21-ll5+5AcceptanceCriteria:Theacceptancecriteriaisthatthemeasuredindividualbankintegralworthbewithin15%ofthepredictedvaluesandthatthetotalworthofthreebanksbewithin185ofthepredictedvalue.Ifthecriteriononindividualbankworthisnotmet,anevaluationwillbeperformedtodeterminethecauseandanypotentialimpacts.Ifthecriterionintotalworthofthethreebanksisnotmet,additionalbankswillbemeasureduntilthemeasurementiswithin18%oftheprediction.Thiswillbecontinued,ifnecessary,tomeasurementatanN-1rodinsertedcondition.TheresultofanN-lmeasurement,withappropriateallowanceformeasurementuncertainty,willbecomparedtothevalueassumedintheSafetyAnalyses.Assummarizedabove,Bank"B"indicatedadeviationofpredictedrodworththatexceededtheacceptancecriteriaof+15%.Thetotalrodworthforthethreebankshowever,didsatisfytheacceptancecriteriaof+18' 0J~~fD
~,J'Thedeviationhabeenevaluatedbynuclear'engineering,and,ithasbeendeterminedthatproceedingtofullpowerisacceptableforthefollowingreasons.Thetotalrodworthforthethreebanksmeasurediswithin+18%ofpredictedvalues,therefore,satisfyingtheassumptionsoutlinedintheshutdownmargincalcu-lation.2~Theshutdownmargincalculation(Table6.3oftheNuclearDesignReport)indicatesthatexcessshutdownmarginof818pcmexiststotherequiredshutdownmarginof1888pcmatBOL.3~ThemeasuredARO,D,D+Cand,estimatedD+C+BboronendpointdatacomparewelltothepredictedvaluesindicatingthattheBbankdeviationdoesnotrepresentanunanticipatedcorereactivityanomaly.TheWestinghousenucleardesignerisconductinghisownevaluationtodeterminethecauseofthedeviation.Basedonthisevaluation,additionalfluxmapdataandcomparisonofoverallcoreperformanceversuspredictedthroughthecycle,itcanbedeterminedatalaterdatewhethertoimposeahigherDbankinsertionlimittowardendofcyclewheretheshutdownmarginisattheminimum.e.BoronEnd~oint:Thefollowingtablesummarizestheboronendpointdata.rrTDifferenceCon~icauration(predicated(p)(acceptance(Measured(M)((M-p)ARODInsertedD+CInserted*D+C+BInsertedl1329122711131818+75+75+75.+7513291286118318858-21-185AcceptanceCriteria:Theaveragecriticalboronconcentrationforagivenconfigurationwillbecomparedtothepredictedconcentrationforthatconfiguration.Theacceptancecriterionwillbe+75ppm.Ifthisacceptancecriterionisnotmet,themeasurementdatawillbereviewedandthefuelsupplierwillbeaskedtoreviewhispredictions.Concurrentwiththisreviewtheremainderofthezeropowerphysicstestingwillbecompletedtoseeifanyotherdifferencesarepresentthatcouldaidindeterminingthecauseofnotmeetingtheacceptancecriteria.Ifaftertheaboveactions,theacceptancecriterionstillcannotbemetanevaluationwillbeperformedontheeffectofthisdifferenceonparametersusedintheaccidentanalysis'ftheaccidentanalysisisunaffectedbythisdifference,thecorewillbeallowedtogoabove5%ratedpower.
t~II~IJ8II-IIlJttIIJ4ltttLIftIftCIIII'
~~~.~NOTE:AlthoughthetestingprogramdidnotspecifymeasurementofControlBank"B"PPMBoronNorthortheBoronEndpointforD+C+BInserted,sufficientacquiredboronsampledataexistedtoincludethestatedvaluewithreasonableconfidence.FluxSymmetryandPowerDistribution:Thefluxsymmetryfluxmapwasperformedat23.6%ratedpower.Alllocationswereevaluatedtotheacceptancecriteriaaslistedbelow.Theonlylocationstofalloutoftheacceptancebounds,werelocationsI-5andI-6,whichrecorded-14.231%and-14.233%respectively.ThethimbleusedtopredicttheselocationsisI-5.ThisspecificassemblylocationisaMixedOxideAssembly(Plutoniumenriched).Theresultswereevaluatedanditwasdeterminedthatmodelingofthepowerdistributionforthisassemblywasthereasonforthedifference.Theremainderofthemapwasingoodagreementwithpredictionsandverifiedthecorewasproperlyloaded.AllNuclearHotChannelfactorswerewellwithintheboundsofPlantTechnicalSpecifications.Duringsubsequentpowerescalation,fluxmapsweregeneratedat46$,71.5%withIncore/Excorecalibrationperformedat83%power.Followingareactor/turbinetripduetoanexciterfailure,powerescalationto188%wasachieved.The188%mapwasthentakenon6/8/84,withallHotChannelFactorswellwithintheboundsofPlantTechnicalSpecifi-cations.A~ccetanceCriteria:TheacceptancecriterionforafluxmapisthattheplantTechnicalSpecificationonpeakingfactorsbemet.Asanaidinevaluatingthepowerdistributionmaps,thedifferencesbetweenmeasuredandpredictedassemblypowerlevelsarereviewed.Generalcriteriaforthesecomparisonsarethatthedifferenceforassemblieswithrelativepower<1'belessthan15%andthedifferenceforassemblieswithrelativepower>1.8belessthan18%.Ifthesedifferencesareexceeded,anevaluationshallbeperformedtoensurethatthepeakingfactorTechnicalSpecificationswillbemet.Ifsuchanevaluationindicatesthatthepeakingfactorlimitswillbemet,nofurtheractionisnecessary.geCriticalBoronConcentration-FullPower:Duetothenumerousdelaysasaresultofsecondaryconcernsencounteredduringstartup,HotFullPowerSteadystateconditionswerenotattaineduntil6/8/84,whichrepresentsanexposureof"388MWD/MTU.Thecalculatedboronconcentrationatthatpointwas888PPMwithapredicatedvalueof828PPM.SubsequentBoronmeasurementstodateindicatethepredicatedtocloselyapproximatetheactualvaluesobtained.
RECElVEO-REGlON1$85JULl2Plill:52~gfi~,~r~~~~~
