Similar Documents at Ginna |
---|
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/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17265A6401999-05-12012 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 ML17309A6521999-04-14014 April 1999 Rev 14 to AP-RCS.1, Reactor Coolant Leak. ML17311A0701999-04-14014 April 1999 Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure. 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. ML17265A5571999-02-25025 February 1999 Rev 4 to Technical Requirements Manual (Trm). ML17265A5481999-02-12012 February 1999 to EOP ATT-22.0, Attachment Restoring Feed Flow. ML17265A5491999-02-12012 February 1999 to EOP FR-H.5, Response to SG Low Level. 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. ML20198C0581998-12-14014 December 1998 Rev 5 to FR-Z.1, Response to High Containment Pressure ML20198C0361998-12-14014 December 1998 Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required ML20198C0521998-12-14014 December 1998 Rev 13 to FR-S.1, Response to Reactor Restart/Atws ML20198C0411998-12-14014 December 1998 Rev 16 to FR-C.1, Response to Inadequate Core Cooling ML20198C0121998-12-14014 December 1998 Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow 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 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 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. ML17265A1541997-09-16016 September 1997 Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification. ML17264A9751997-08-0505 August 1997 Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses. ML17264A9771997-08-0505 August 1997 Rev 11 to AP-RCP.1, RCP Seal Malfunction. 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. 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. 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 ML20140B8291997-03-24024 March 1997 Rev 3 to EOP ATT-12.0, Attachment N2 Porvs ML17264A8221997-02-0606 February 1997 Rev 15 to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition. ML17264A8201997-02-0606 February 1997 Rev 7 to AP-RCC.2, Rcc/Rpi Malfunction. ML17264A8081997-01-23023 January 1997 Revised Emergency Operating Procedures,Including Rev 14 to E-1,Rev 19 to E-3,Rev 14 to ECA-2.1,Rev ECA-3.3,Rev 20 to ES-1.3,Rev 13 to FR-C.1,Rev 12 to FR-C.2 & Rev 14 to FR-P.1 ML20133N3351997-01-10010 January 1997 Rev 7 to FR-C.3, Response to Saturated Core Cooling ML17264A8881996-10-10010 October 1996 Rev 9 to ODCM for Ginna Station. ML20128N0681996-10-0303 October 1996 Revised Emergency Operating Procedures,Including Rev 5 to Att-10.0, Attachment Faulted S/G & Rev 6 to Att-16.0, Attachment Ruptured S/G ML17264A5311996-05-31031 May 1996 Revised Emergency Operating Procedures,Including Rev 10 to AP-RCP.1,Rev 12 to ECA-0.1,Rev 12 to ECA-2.1,Rev 3 to FR-H.2,Rev 3 to FR-H.4,Rev 7 to FR-I.1,Rev 12 to FR-P.1,Rev 10 to FR-S-1 & Rev 6 to FR-S.2 ML17264A5161996-05-22022 May 1996 Rev 2 to Technical Requirements Manual (TRM) ML17264A4581996-04-0808 April 1996 Rev 7 to ODCM for Ginna Station. ML17264A4371996-04-0101 April 1996 Rev 1 to Technical Requirements Manual (TRM) ML17264A4391996-04-0101 April 1996 Rev 1 to Updated Technical Requirements Manual (TRM) ML17264A4191996-02-24024 February 1996 Rev 0 to Technical Requirements Manual (Trm). ML17264A6901996-02-23023 February 1996 Rev 0 to Inservice Testing Program. 1999-05-12
[Table view] |
Text
EOP:ES-3'POST-SGTR COOLDOWNUSINGBACKFILLREV:5PAGE1of8ROCHESTER GASANDELECTRICCORPORATION GINNASTATIONCONTROLLED COPYNUMBERD3TECHNICAL REVIEWPORCREVIEWDATEPLANTSUPERINTENDENT EFECIVEDATECATEGORY1.0REVIEWEDBY:-9206Lb0403 920b05PDRADOCK05000244PPDR
'glE%'.tA EOP:ES-3'TITLE:POST-SGTR COOLDOWNUSINGBACKFILLREVS5PAGE2of8A.PURPOSE-Thisprocedure providesactionstocooldownanddepressurize theplanttocoldshutdownconditions following aSGTR.Thisrecoverymethoddepressurizes therupturedS/GbydrainingitthroughtherupturedS/GtubesintotheRCS.B.ENTRYCONDITIONS/SYMPTOMS 1.ENTRYCONDITIONS
-Thisprocedure isenteredfrom:a.E-3STEAMGENERATOR TUBERUPTURE,ifplantstaffselectsbackfillmethod.b~ES3~2/POSTSGTRCOOLDOWNUSINGBLOWDOWNgwhenblowdownisnotavailable andplantstaffselectsbackfillmethod.
gfy'ler EOP:ES-3.1POST-SGTR COOLDOWNUSINGBACKFILLREV:5PAGE3of8STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINEDNOTE:oFOLDOUTpageshouldbeopenANDmonitored periodically.
AdverseCNMTvaluesshouldbeusedwheneverCNMTpressureisgreaterthan4psigorCNMTradiation isgreaterthan10+R/hr.1EnergizePRZRHeatersAsNecessary ToSaturatePRZRWaterAtRupturedS/GPressure2CheckIfSIACCUMsShouldBeIsolated:
a.Checkthefollowing:
oRCSsubcooling basedoncoreexitT/Cs-GREATERTHANO'USINGFIGUREMINSUBCOOLING a.GotoECA-3.1,SGTRWITHLOSSOFREACTORCOOLANT-SUBCOOLED RECOVERYDESIRED,Step1.oPRZRlevel-GREATERTHAN5%[30%adverseCNMT]b.DispatchAOwithlockedvalvekeytolocallyclosebreakersforSIACCUMdischarge valves~MOV-841,MCCCposition12F~MOV-865,MCCDposition12Cc,CloseSIACCUMoutletvalves~ACCUMA,MOV-841~ACCUMB)MOV-865c.Ventanyunisolated ACCUMs:1)Openventvalvesforunisolated SIACCUMs.~ACCUMA,AOV-834A~ACCUMB,AOV-834Bd.LocallyreopenbreakersforMOV-841andMOV-8652)OpenHCV-945.
l~'sJA&
EOP:ES-3.1TITLE:POST-SGTR COOLDOWNUSINGBACKFILLREV:5PAGE4of8STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINEDNOTE:LeakagefromrupturedS/GintoRCSwilldiluteRCSboronconcentration.
3VerifyAdequateShutdownMargina.DirectHPtosampleRCSandrupturedS/Gforboronconcentration b.Verifyboronconcentration-GREATERTHANREQUIREMENTS OFFIGURESDMb.Borateasnecessary.
- CAUTIONIFCSTLEVELDECREASES TOLESSTHAN5FEET,THENALTERNATE WATERSOURCESFORAFWPUMPSWILLBENECESSARY (REFERTOER-AFW.1)
ALTERNATE WATERSUPPLYTOAFWPUMPS).NOTE:TDAFWpumpflowcontrolvalvesfailopenonlossofIA.4CheckIntactS/GLevel:a.Narrowrangelevel-GREATERTHAN5%[25%adverseCNMT)Ib.Controlfeed'flowtomaintainnarrowrangelevelbetween17%[25%adverseCNMT]and50%a.Maintaintotalfeedflowgreaterthan200gpmuntilnarrowrange~levelgreaterthan5%[25%adverseCNMT]intheintactS/G.b.IFnarrowrangelevelintheintactS/Gcontinues toincreaseinanuncontrolled manner,THENgotoECA-3.1,SGTRWITHLOSSOFREACTORCOOLANT-SUBCOOLED RECOVERYDESIRED,Step1.
~tn,~A-Wriep.el:l~Ir(+I EOP:ES-3~1TITLE:POST-SGTR COOLDOWNUSINGBACKFILLREV:5PAGE5of8STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINEDNOTE:SincerupturedS/Gmaycontinuetodepressurize tolessthantheminimumRCSpressurenecessary forcontinued RCPoperation, cooldowntocoldshutdownshouldbecompleted asquicklyaspossible, nottoexceed100'F/hr.
5InitiateRCSCooldownToColdShutdown:
a.Establish andmaintaincooldownrateinRCScoldlegs-LESSTHAN100'F/HRb.UseRHRsystemifinservicec.Dumpsteamtocondenser fromintactS/Gc.ManuallyorlocallydumpsteamusingintactS/GARV.IFnointactS/Gavailable andRHRsystemNOTinservice,THENperformthefollowing:
oUsefaultedS/G.-OR-oGotoECA-3.1,SGTRWITHLOSSOFREACTORCOOLANTSUBCOOLED RECOVERYDESIRED,Step1.6CheckRupturedS/GNarrowRangeLevel-GREATERTHAN174[254adverseCNMT]I'efillrupturedS/Gto67%[55%adverseCNMT)usingfeedflow.IFeitherofthefollowing conditions occurs,THENstopfeedflowtorupturedS/G:oRupturedS/Gpressuredecreases inanuncontrolled manner.-OR-oRupturedS/Gpressureincreases to1020psig.
QLckk<W4IS EOP:ES-3'POST-SGTR COOLDOWNUSINGBACKFILLREV:5PAGE6of8STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED7ControlRCSMakeupFlowAndLetdownToMaintainPRZRLevel:a.PRZRlevel-GREATERTHAN13%[40$adverseCNMT]b.PRZRlevel-LESSTHAN75%[65%adverseCNMT]a,IncreaseRCSmakeupflowasnecessary andgotoStep8.b.DecreaseRCSmakeupflowtodecreaselevelandgotoStep10.NOTE:TheupperheadregionmayvoidduringRCSdepressurization ifRCPsarenotrunning.Thismayresultinarapidlyincreasing PRZRlevel.8Depressurize RCSToBackfillFromRupturedS/G:a.Depressurize usingnormalPRZRspraya.IFletdownisinservice,THENdepressurize usingauxiliary sprayvalve(AOV-296).
IFNOT,THENuseonePRZRPORV~b.MaintainPRZRlevel-BETWEEN13%AND75%[BETWEEN40%AND65%adverseCNMT]c.CheckrupturedS/GlevelGREATERTHAN5%[25%adverseCNMT]c.StopRCSdepressurization.
d.EnergizePRZRheatersasnecessary e.MaintainRCSsubcooling basedoncoreexitT/Cs-GREATERTHANO'FUSINGFIGUREMINSUBCOOLING IIt,.Jfg4CK~
EOP:ES-3~1POST-SGTR COOLDOWNUSINGBACKFILLREV:5PAGE7of8STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED9Establish RequiredRCSHydrogenConcentration (RefertoS-3.3C,H2Or02REMOVALFROMPRIMARYSYSTEMBYBURPINGVCT)10CheckIfRHRNormalCoolingCanBeEstablished:
a.RCScoldlegtemperature
-LESSTHAN350'Fa.GotoStep11.b.RCSpressure-LESSTHAN400psig[300psigadverseCNMT]c.PlaceRCSoverpressure protection systeminservice(Referto0-7,ALIGNMENT ANDOPERATION OFTHEREACTORVESSELOVERPRESSURE PROTECTION SYSTEM)d.Establish RHRnormalcooling(RefertoAttachment RHRCOOL)b.'otoStep11.c.IFRCSoverpressure protection systemcanNOTbeplacedinservice,THENnotifyTSCofpotential TechSpecviolation ifRHRsystemisplacedinservice.llCheckIfRCPsMustBeStopped:a.RCPs-ANYRUNNING"b.Checkthefollowing:
oRCP¹1sealD/P-LESSTHAN220PSIDa.GotoStep12.b.GotoStep12.-OR-oCheckRCPsealleakage-LESSTHAN0.25GPMc.StopaffectedRCP(s)
EOP:ES;3~1POST-SGTR COOLDOHNUSINGBACKFILLREV'PAGE8of8STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED12CheckCoreExitT/Cs-LESSTHAN200'FReturntoStep3.13EvaluateLongTermPlantStatus:a.Maintaincoldshutdownconditions (Referto0-2.3,PLANTATCOLDORREFUELING SHUTDOWN) b.ConsultTSC-END-
EOP:ES-3'POST-SGTR COOLDOWNUSINGBACKFILLREV:5PAGE1of1ES-3.1APPENDIXLISTTITLEPAGES1)REDPATHSUMMARY2)FIGUREMINSUBCOOLING 3)FIGURESDM4)ATTACHMENT RHRCOOL5)FOLDOUT 9h$~$
EOP:ES-3.1POST-SGTR COOLDOWNUSINGBACKFILLREV:5PAGE1of1REDPATHSUMMARYa.SUBCRITICALITY
-Nuclearpowergreaterthan5%b.CORECOOLING-CoreexitT/Csgreaterthan1200'F-OR-CoreexitT/Csgreaterthan700'FANDRVLISlevel(noRCPs)lessthan43%[46%adverseCNMT)c.HEATSINK-NarrowrangelevelinallS/Gslessthan54[25%adverseCNMT]ANDtotalfeedwater flowlessthan200gpmd.INTEGRITY
-Coldlegtemperatures decreasegreaterthan100'Finlast60minutesANDRCScoldlegtemperature lessthan285'Fe.CONTAINMENT
-CNMTpressuregreaterthan60psig sJIAy1PjL%~
EDP:ES-3'TITLE:POST-SGTR COOLDOWNUSINGBACKFILLREV'PAGE1of,1FIGUREMINSUBCOOLING NOTE:Subcooling Margin=Saturation Temperature FromFigureBelow[-]CoreExitT/CIndication RC25002400230022002100200019001800170016001500140013001200110010009008007006005004003002001000SPRESSURE(PSIG)RCSPRESSUREINCREMENTS 20PSIGSUBCOOLED REGIONCNMTDVRSENORMALCNMTINADE(UATE SUBCOOLING REGIONTEMPERATURE INCREMENTS 10'F200250300,350400450500550600650'00COREEXITSATURATION TEMPERATURE
('F)
~IhIJVt4aAk~2V94+eDi EOP:ES-3.1TITLE:POST-SGTR COOLDOWNUSINGBACKFILLREV:5PAGE1of1BORONCONCENTRATION (PPH)1800FIGURESDM1600BORONINCREMENTS 20PPH140012001000ADEQUATESDH100PPHCONSERVATISH INCLUDEDSOO600400BO200BURNUPINCREMENTS 100HWD/HTU01000200030004000500060007000800090001000011000CYCLE22BURNUP(MWD/HTU)
NOTE:Toobtaincoreburnup,usePPCSturnoncodeBURNUP.
EOP:ES-3'T1TLE:POST-SGTR COOLDOWNUSINGBACKFILLREV:5PAGE1of1FOLDOUTPAGE1~SIREINITIATION CRITERIAIFeithercondition listedbelowoccurs,THENoperateSIpumpsmanuallyasnecessary andgotoECA-3.1,SGTRWITHLOSSOFREACTORCOOLANT-SUBCOOLED RECOVERYDESIRED,Step1:oRCSsubcooling basedoncoreexitT/Cs-LESSTHANO'FUSINGREQUIREMENTS OFFIGUREMINSUBCOOLING.
OR2~oPRZRlevel-CHARGINGCANNOTCONTROLLEVELGREATERTHAN5%[304adverseCNMT]SECONDARY INTEGRITY CRITERIAIFanyS/Gpressureisdecreasing inanuncontrolled manneroriscompletely depressurized ANDhasnotbeenisolated, THENgotoE-2,FAULTEDS/GISOLATION, Step1.3~COLDLEGRECIRCULATION SWITCHOVER CRITERION 4~IFRWSTleveldecreases tolessthan284,THENgotoES-1.3,TRANSFERTOCOLDLEGRECIRCULATION, Step1.AFWSUPPLYSWITCHOVER CRITERION IFCSTleveldecreases tolessthan5feet,THENswitchtoalternate AFWwatersupply(RefertoER-AFW.l, ALTERNATE WATERSUPPLYTOAFWPUMPS).
1