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| {{#Wiki_filter:EOP:AP-RCS.1REACTORCOOLANTLEAKREV:12PAGE1of11ROCHESTER GASANDELECTRICCORPORATION GINNASTATIONCONTROLLED COPYNUMBERRESPONSIB MANAGEREFFECTIVE DATECATEGORY1.0REVIEWEDBX:9708130%38 970805PDRADQCK05000244 EOP:AP-RCS.1REACTORCOOLANTLEAKREV:12PAGE2of11A.PURPOSE-Thisprocedure providestheinstructions necessary tomitigatetheconsequences ofareactorcoolantleak.B.ENTRYCONDITIONS/SYMPTOMS 1.ENTRYCONDITIONS | | {{#Wiki_filter:EOP: AP-RCS.1 REACTOR COOLANT LEAK REV: 12 PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIB MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BX: 9708130%38 970805 PDR ADQCK 05000244 EOP: AP-RCS.1 REACTOR COOLANT LEAK REV: 12 PAGE 2 of 11 A.PURPOSE-This procedure provides the instructions necessary to mitigate the consequences of a reactor coolant leak.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS |
| -Thisprocedure isenteredfrom:a.S-12.2,OPERATORACTIONINTHEEVENTOFINDICATION OFSIGNIFICANT INCREASEINLEAKAGE,whenasignificant increaseinRCSleakageisindicated. | | -This procedure is entered from: a.S-12.2, OPERATOR ACTION IN THE EVENT OF INDICATION OF SIGNIFICANT INCREASE IN LEAKAGE, when a significant increase in RCS leakage is indicated. |
| b.AP-CVCS.1, CVCSLEAK,whenleakcannotbeisolated. | | b.AP-CVCS.1, CVCS LEAK, when leak cannot be isolated.2.SYMPTOMS-The symptoms of REACTOR COOLANT LEAK are;a.Annunciator F-14, CHARGING PUMP, SPEED, lit, or b.Annunciator A-2, VCT LEVEL 144 86, lit, or c.Annunciator E-16, RMS PROCESS MONITOR HIGH ACTIVITY, lit, or d.Annunciator E-24, RMS AREA MONITOR HIGH ACTIVITY, lit, or e.Annunciator F-4, PRESSURIZER LEVEL DEVIATION-5 NORMAL+5, lit,'r f.Annunciator F-10, PRESSURIZER LO PRESS 2185 PSI, lit, or g.Annunciator F-11, PRESSURIZER LO LEVEL 134, lit. |
| 2.SYMPTOMS-ThesymptomsofREACTORCOOLANTLEAKare;a.Annunciator F-14,CHARGINGPUMP,SPEED,lit,orb.Annunciator A-2,VCTLEVEL14486,lit,orc.Annunciator E-16,RMSPROCESSMONITORHIGHACTIVITY, lit,ord.Annunciator E-24,RMSAREAMONITORHIGHACTIVITY, lit,ore.Annunciator F-4,PRESSURIZER LEVELDEVIATION | | EOP: AP-RCS.1 REACTOR COOLANT LEAK REV: 12 PAGE 3 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED. |
| -5NORMAL+5,lit,'rf.Annunciator F-10,PRESSURIZER LOPRESS2185PSI,lit,org.Annunciator F-11,PRESSURIZER LOLEVEL134,lit. | | NOTE:-Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION. |
| EOP:AP-RCS.1REACTORCOOLANTLEAKREV:12PAGE3of11STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINEDCAUTIONIF,ATANYTIMEDURINGTHISPROCEDURE, AREACTORTRIPORSIOCCURS,E-O,REACTORTRIPORSAFETYINJECTION, SHALLBEPERFORMED. | | 1 Check PRZR Level-STABLE AT PROGRAM LEVEL IF PRZR level decreasing, THEN start additional charging pumps and increase speed as necessary to stabilize PRZR level.IF PRZR level continues to decrease, THEN close loop B cold leg to REGEN Hx isolation valve, AOV-427.IF available charging pumps are running at maximum speed with letdown isolated, AND PRZR level is decreasing, THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION. |
| NOTE:-Conditions shouldbeevaluated forsitecontingency reporting (RefertoEPIP-1.0, GINNASTATIONEVENTEVALUATION ANDCLASSIFICATION. | | EOP: AP-RCS.1 T1TLE: REACTOR COOLANT LEAK REV: 12 PAGE 4 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF VCT level decreases to 5%, charging pump suction will swap to the RWST.This may require a load reduction. |
| 1CheckPRZRLevel-STABLEATPROGRAMLEVELIFPRZRleveldecreasing, THENstartadditional chargingpumpsandincreasespeedasnecessary tostabilize PRZRlevel.IFPRZRlevelcontinues todecrease, THENcloseloopBcoldlegtoREGENHxisolation valve,AOV-427.IFavailable chargingpumpsarerunningatmaximumspeedwithletdownisolated, ANDPRZRlevelisdecreasing, THENtripthereactorandgotoE-O,REACTORTRIPorSAFETYINJECTION.
| | 2 Check VCT Makeup System: a.Verify VCT level-GREATER THAN 5a a.Ensure charging pump suction aligned to RWST.~LCV-112B-OPEN~LCV-112C-CLOSED b.Verify the following: |
| EOP:AP-RCS.1T1TLE:REACTORCOOLANTLEAKREV:12PAGE4of11STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINEDNOTE:IFVCTleveldecreases to5%,chargingpumpsuctionwillswaptotheRWST.Thismayrequirealoadreduction. | | 1)RMW mode selector switch in AUTO b.Adjust controls as necessary. |
| 2CheckVCTMakeupSystem:a.VerifyVCTlevel-GREATERTHAN5aa.EnsurechargingpumpsuctionalignedtoRWST.~LCV-112B-OPEN~LCV-112C-CLOSEDb.Verifythefollowing:
| | 2)RMW control armed-RED LIGHT LIT c.Check VCT-level: o Level GREATER THAN 20$-OR-o Level-STABLE OR INCREASING c.Check letdown divert valve, LCV-112A, closed.IF VCT makeup flow NOT adequate, THEN perform the following: |
| 1)RMWmodeselectorswitchinAUTOb.Adjustcontrolsasnecessary. | | 1)Ensure BA transfer pumps and RMW pumps running.2)Adjust RMW flow control valve, HCV-111, to increase RMW flow.3)Increase boric acid flow as necessary to maintain required concentration. |
| 2)RMWcontrolarmed-REDLIGHTLITc.CheckVCT-level:oLevelGREATERTHAN20$-OR-oLevel-STABLEORINCREASING c.Checkletdowndivertvalve,LCV-112A, closed.IFVCTmakeupflowNOTadequate, THENperformthefollowing: | | IF VCT level can NOT be maintained, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION, if necessary. |
| 1)EnsureBAtransferpumpsandRMWpumpsrunning.2)AdjustRMWflowcontrolvalve,HCV-111,toincreaseRMWflow.3)Increaseboricacidflowasnecessary tomaintainrequiredconcentration. | | EOP: AP-RCS.l TITLE: REACTOR COOLANT LEAK REV: 12 PAGE 5 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check If RCS Leakage In CNMT: o Check CNMT radiation monitors-NORMAL~R-2~R-7~R-lOA~R-11~R-12 o CNMT sump A pump run frequency-NORMAL (Refer to RCS Daily Leakage Log)IF leakage is indicated in CNMT, THEN perform the following: |
| IFVCTlevelcanNOTbemaintained, THENrefertoER-CVCS.1, REACTORMAKEUPCONTROLMALFUNCTION, ifnecessary.
| | a.Direct HP to sample CNMT for entry.b.Continue'with Step 4.WHEN CNMT cleared for entry, THEN dispatch personnel to investigate CNMT for RCS leakage./CAUTION RADIATION PROTECTION TECHNICIAN SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.4 Dispatch AO To AUX BLDG To Investigate For CVCS Leak (locked area keys required)5 Check For Leak To CCW System: o CCW surge tank level-APPROXIMATELY 50%AND'TABLE Go to AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP.o CCW radiation monitor, R-17-NORMAL EOP: AP-RCS.1 TITLE: REACTOR COOLANT LEAK REV: 12 PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check CVCS Conditions: |
| EOP:AP-RCS.lTITLE:REACTORCOOLANTLEAKREV:12PAGE5ofllSTEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED3CheckIfRCSLeakageInCNMT:oCheckCNMTradiation monitors-NORMAL~R-2~R-7~R-lOA~R-11~R-12oCNMTsumpApumprunfrequency-NORMAL(RefertoRCSDailyLeakageLog)IFleakageisindicated inCNMT,THENperformthefollowing: | | a.Letdown indication: |
| a.DirectHPtosampleCNMTforentry.b.Continue'with Step4.WHENCNMTclearedforentry,THENdispatchpersonnel toinvestigate CNMTforRCSleakage./CAUTIONRADIATION PROTECTION TECHNICIAN SHOULDBECONSULTED PRIORTOENTERINGAHIGHAIRBORNEAREA.4DispatchAOToAUXBLDGToInvestigate ForCVCSLeak(lockedareakeysrequired) 5CheckForLeakToCCWSystem:oCCWsurgetanklevel-APPROXIMATELY 50%AND'TABLE GotoAP-CCW.1, LEAKAGEINTOTHECOMPONENT COOLINGLOOP.oCCWradiation monitor,R-17-NORMAL EOP:AP-RCS.1TITLE:REACTORCOOLANTLEAKREV:12PAGE6of11STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED6CheckCVCSConditions: | | o Letdown flow-APPROXIMATELY 40 GPM o Low pressure LTDN pressure-APPROXIMATELY 250 PSIG a.IF letdown isolated, THEN continue with Step 6b.IF NOT isolated, THEN go to AP-CVCS.1, CVCS LEAK, Step 6.o Letdown pressure control valve, PCV-135, demand-APPROXIMATELY 35%OPEN b.Charging indication: |
| a.Letdownindication: | | o Seal injection flows GREATER THAN 6 GPM AND STABLE b.Go to AP-CVCS.1, CVCS LEAK, Step 6.o RCP Labyrinth seal D/Ps GREATER THAN 15 INCHES AND APPROXIMATELY EQUAL o Charging pump discharge pressure-GREATER THAN RCS PRESSURE c.AUX BLDG radiation levels NORMAL~R-4~R-9~R-10B~R-13~R-14 c.Go to AP-CVCS.1, CVCS LEAK, Step 6 and refer to CVCS piping diagrams for further guidance. |
| oLetdownflow-APPROXIMATELY 40GPMoLowpressureLTDNpressure-APPROXIMATELY 250PSIGa.IFletdownisolated, THENcontinuewithStep6b.IFNOTisolated, THENgotoAP-CVCS.1, CVCSLEAK,Step6.oLetdownpressurecontrolvalve,PCV-135,demand-APPROXIMATELY 35%OPENb.Chargingindication:
| |
| oSealinjection flowsGREATERTHAN6GPMANDSTABLEb.GotoAP-CVCS.1, CVCSLEAK,Step6.oRCPLabyrinth sealD/PsGREATERTHAN15INCHESANDAPPROXIMATELY EQUALoChargingpumpdischarge pressure-GREATERTHANRCSPRESSUREc.AUXBLDGradiation levelsNORMAL~R-4~R-9~R-10B~R-13~R-14c.GotoAP-CVCS.1, CVCSLEAK,Step6andrefertoCVCSpipingdiagramsforfurtherguidance.
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| EOP:AP-RCS.1TlTLE:REACTORCOOLANTLEAKREV:12PAGE7of11STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED7CheckPRTIndications: | | EOP: AP-RCS.1 TlTLE: REACTOR COOLANT LEAK REV: 12 PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRT Indications: |
| a.Level->BETWEEN61%AND84%b.Pressure-APPROXIMATELY 1.5PSIGANDSTABLEc.Temperature | | a.Level->BETWEEN 61%AND 84%b.Pressure-APPROXIMATELY 1.5 PSIG AND STABLE c.Temperature |
| -ATCNMTAMBIENTTEMPERATURE ANDSTABLEChecktailpipeandvalveleakofftemperatures forthePRZRsafetyvalvesandPORVsforindication ofleakage.IFnoPORV,orsafetyvalveleakageisindicated, THENcheckotherleakpathsfromtheRCStothePRT.~Letdownreliefvalve,RV-203~Sealreturnreliefvalve,RV-314CAUTIONSTEAMGENERATOR TUBELEAKAGEINONES/GSHALLNOTEXCEED0.1GPMWHENAVERAGEDOVER24HOURS.8CheckS/GsForLeakage:oAirejectorradiation monitors-~NORMALIFS/Gtubeleakindicated, THENreferto0-6.10,PLANTOPERATION WITHAS/GTUBELEAKINDICATION. | | -AT CNMT AMBIENT TEMPERATURE AND STABLE Check tailpipe and valve leakoff temperatures for the PRZR safety valves and PORVs for indication of leakage.IF no PORV,or safety valve leakage is indicated, THEN check other leak paths from the RCS to the PRT.~Letdown relief valve, RV-203~Seal return relief valve, RV-314 CAUTION STEAM GENERATOR TUBE LEAKAGE IN ONE S/G SHALL NOT EXCEED 0.1 GPM WHEN AVERAGED OVER 24 HOURS.8 Check S/Gs For Leakage: o Air ejector radiation monitors-~NORMAL IF S/G tube leak indicated, THEN refer to 0-6.10, PLANT OPERATION WITH A S/G TUBE LEAK INDICATION. |
| ~R-15~R-15AoS/Gblowdownradiation monitor(R-19)-NORMALoSteamline radiation monitorsNORMAL~R-31~R-32oS/Gsampleactivity-NORMAL(CheckwithRPDepartment fornormal) | | ~R-15~R-15A o S/G blowdown radiation monitor (R-19)-NORMAL o Steamline radiation monitors NORMAL~R-31~R-32 o S/G sample activity-NORMAL (Check with RP Department for normal) |
| EOP:AP-RCS.1REACTORCOOLANTLEAKREV:12PAGE8of11STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED9CheckSIAccumulator Levels-STABLECalculate inleakage toSIaccumulators (RefertoS-16.11,MONITORING INLEAKAGE TOSIACCUMULATORS). | | EOP: AP-RCS.1 REACTOR COOLANT LEAK REV: 12 PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check SI Accumulator Levels-STABLE Calculate inleakage to SI accumulators (Refer to S-16.11, MONITORING INLEAKAGE TO SI ACCUMULATORS). |
| 10CheckRCPSealLeakoffFlows:oLeakoffflows-WITHINTHENORMALOPERATING RANGEOFFIGURERCPSEALLEAKOFFGotoAP-RCP.l, RCPSEALMALFUNCTION.
| | 10 Check RCP Seal Leakoff Flows: o Leakoff flows-WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF Go to AP-RCP.l, RCP SEAL MALFUNCTION. |
| oLeakoffflows-STABLE11CheckRCDTLeakRate-NORMAL(RefertoRCSDailyLeakageLogandPPCSpointIDL1003)CheckothersourcesofinleakagetoRCDT:a.IFRxvesselflangeleakofftemperature hasincreased, THENcloseRxVESSFLANGESEAL'EAKOFF VLV,AOV-521.b.Verifyexcessletdownisolated.
| | o Leakoff flows-STABLE 11 Check RCDT Leak Rate-NORMAL (Refer to RCS Daily Leakage Log and PPCS point ID L1003)Check other sources of in leakage to RCDT: a.IF Rx vessel flange leakoff temperature has increased, THEN close Rx VESS FLANGE SEAL'EAKOFF VLV, AOV-521.b.Verify excess letdown isolated.IF NOT, THEN ensure RCDT divert valve, AOV-312, in the VCT position.c.IF source of leakage NOT determined, THEN suspect loop drains. |
| IFNOT,THENensureRCDTdivertvalve,AOV-312,intheVCTposition.
| | EOP: AP-RCS.1 TITLE REACTOR COOLANT LEAK REV: 12 PAGE 9 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Valve Leakoff Temperatures |
| c.IFsourceofleakageNOTdetermined, THENsuspectloopdrains. | | -NORMAL (Refer to Pressurizer Valve Leak-Off Temperature Record Log)IF any valve leakoff temperature is abnormally high, THEN initiate investigation of that leakage path.13 Establish Stable Plant Conditions: |
| EOP:AP-RCS.1TITLEREACTORCOOLANTLEAKREV:12PAGE9ofllSTEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED12CheckValveLeakoffTemperatures | | a.PRZR level-TRENDING TO PROGRAM b.Check PRZR pressure control: o Pressure-TRENDING TO 2235 PSIG o PRZR backup heaters-OFF a.Control charging and letdown flows to restore PRZR level to program.b.Verify proper operation of PRZR heaters and spray or take manual control of PRZR pressure controller 431K.IF pressure can NOT be controlled, THEN refer to AP-PRZR,l, ABNORMAL PRESSURIZER PRESSURE, 14 Evaluate RCS Leakage: a.Leakage within limits (Refer to leakage surveillance sheet and ITS section 3.4.13)b.Leak location identified a.IF leak NOT isolable, but PRZR level and seal injection can be maintained, THEN shut the plant down (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN or AP-TURB.5, RAPID LOAD REDUCTION). |
| -NORMAL(RefertoPressurizer ValveLeak-OffTemperature RecordLog)IFanyvalveleakofftemperature isabnormally high,THENinitiateinvestigation ofthatleakagepath.13Establish StablePlantConditions: | | b.Return to Step l. |
| a.PRZRlevel-TRENDINGTOPROGRAMb.CheckPRZRpressurecontrol:oPressure-TRENDINGTO2235PSIGoPRZRbackupheaters-OFFa.ControlchargingandletdownflowstorestorePRZRleveltoprogram.b.Verifyproperoperation ofPRZRheatersandsprayortakemanualcontrolofPRZRpressurecontroller 431K.IFpressurecanNOTbecontrolled, THENrefertoAP-PRZR,l, ABNORMALPRESSURIZER | | AP-RCS.1 REACTOR COOLANT LEAK REV: 12 PAGE 10 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements. |
| : PRESSURE, 14EvaluateRCSLeakage:a.Leakagewithinlimits(Refertoleakagesurveillance sheetandITSsection3.4.13)b.Leaklocationidentified a.IFleakNOTisolable, butPRZRlevelandsealinjection canbemaintained, THENshuttheplantdown(Referto0-2.1,NORMALSHUTDOWNTOHOTSHUTDOWNorAP-TURB.5, RAPIDLOADREDUCTION).
| | 15 Notify Higher Supervision-END-EOP: REACTOR COOLANT LEAK REV: 12 PAGE 11 of ll AP-RCS.1 APPENDIX LIST TITLE PAGES 1)FIGURE RCP SEAL LEAKOFF EOP: AP-RCS.1 TITLE: REACTOR COOLANT LEAK REV: 12 PAGE 1 of 1 FIGURE RCP SEAL LEAKOFF kl SEAL LEAK RATE (GPH)6 LEAK RATE INCREHENTS 0.2 GPH 3 NORHAL OPERATING RANGE DP INCREHENTS 50 PSI 250 500 750 1000 1250 1500 1750 2000 2250 2500 81 SEAL DP (RCS PRESS-VCT PRESS)PSI J}} |
| b.ReturntoStepl. | |
| AP-RCS.1REACTORCOOLANTLEAKREV:12PAGE10ofllSTEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINEDNOTE:Referto0-9.3,NRCIMMEDIATE NOTIFICATION, forreporting requirements. | |
| 15NotifyHigherSupervision
| |
| -END-EOP:REACTORCOOLANTLEAKREV:12PAGE11ofllAP-RCS.1APPENDIXLISTTITLEPAGES1)FIGURERCPSEALLEAKOFF EOP:AP-RCS.1TITLE:REACTORCOOLANTLEAKREV:12PAGE1of1FIGURERCPSEALLEAKOFFklSEALLEAKRATE(GPH)6LEAKRATEINCREHENTS 0.2GPH3NORHALOPERATING RANGEDPINCREHENTS 50PSI250500750100012501500175020002250250081SEALDP(RCSPRESS-VCTPRESS)PSI J}} | |
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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
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EOP: AP-RCS.1 REACTOR COOLANT LEAK REV: 12 PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIB MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BX: 9708130%38 970805 PDR ADQCK 05000244 EOP: AP-RCS.1 REACTOR COOLANT LEAK REV: 12 PAGE 2 of 11 A.PURPOSE-This procedure provides the instructions necessary to mitigate the consequences of a reactor coolant leak.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS
-This procedure is entered from: a.S-12.2, OPERATOR ACTION IN THE EVENT OF INDICATION OF SIGNIFICANT INCREASE IN LEAKAGE, when a significant increase in RCS leakage is indicated.
b.AP-CVCS.1, CVCS LEAK, when leak cannot be isolated.2.SYMPTOMS-The symptoms of REACTOR COOLANT LEAK are;a.Annunciator F-14, CHARGING PUMP, SPEED, lit, or b.Annunciator A-2, VCT LEVEL 144 86, lit, or c.Annunciator E-16, RMS PROCESS MONITOR HIGH ACTIVITY, lit, or d.Annunciator E-24, RMS AREA MONITOR HIGH ACTIVITY, lit, or e.Annunciator F-4, PRESSURIZER LEVEL DEVIATION-5 NORMAL+5, lit,'r f.Annunciator F-10, PRESSURIZER LO PRESS 2185 PSI, lit, or g.Annunciator F-11, PRESSURIZER LO LEVEL 134, lit.
EOP: AP-RCS.1 REACTOR COOLANT LEAK REV: 12 PAGE 3 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.
NOTE:-Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.
1 Check PRZR Level-STABLE AT PROGRAM LEVEL IF PRZR level decreasing, THEN start additional charging pumps and increase speed as necessary to stabilize PRZR level.IF PRZR level continues to decrease, THEN close loop B cold leg to REGEN Hx isolation valve, AOV-427.IF available charging pumps are running at maximum speed with letdown isolated, AND PRZR level is decreasing, THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION.
EOP: AP-RCS.1 T1TLE: REACTOR COOLANT LEAK REV: 12 PAGE 4 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF VCT level decreases to 5%, charging pump suction will swap to the RWST.This may require a load reduction.
2 Check VCT Makeup System: a.Verify VCT level-GREATER THAN 5a a.Ensure charging pump suction aligned to RWST.~LCV-112B-OPEN~LCV-112C-CLOSED b.Verify the following:
1)RMW mode selector switch in AUTO b.Adjust controls as necessary.
2)RMW control armed-RED LIGHT LIT c.Check VCT-level: o Level GREATER THAN 20$-OR-o Level-STABLE OR INCREASING c.Check letdown divert valve, LCV-112A, closed.IF VCT makeup flow NOT adequate, THEN perform the following:
1)Ensure BA transfer pumps and RMW pumps running.2)Adjust RMW flow control valve, HCV-111, to increase RMW flow.3)Increase boric acid flow as necessary to maintain required concentration.
IF VCT level can NOT be maintained, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION, if necessary.
EOP: AP-RCS.l TITLE: REACTOR COOLANT LEAK REV: 12 PAGE 5 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check If RCS Leakage In CNMT: o Check CNMT radiation monitors-NORMAL~R-2~R-7~R-lOA~R-11~R-12 o CNMT sump A pump run frequency-NORMAL (Refer to RCS Daily Leakage Log)IF leakage is indicated in CNMT, THEN perform the following:
a.Direct HP to sample CNMT for entry.b.Continue'with Step 4.WHEN CNMT cleared for entry, THEN dispatch personnel to investigate CNMT for RCS leakage./CAUTION RADIATION PROTECTION TECHNICIAN SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.4 Dispatch AO To AUX BLDG To Investigate For CVCS Leak (locked area keys required)5 Check For Leak To CCW System: o CCW surge tank level-APPROXIMATELY 50%AND'TABLE Go to AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP.o CCW radiation monitor, R-17-NORMAL EOP: AP-RCS.1 TITLE: REACTOR COOLANT LEAK REV: 12 PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check CVCS Conditions:
a.Letdown indication:
o Letdown flow-APPROXIMATELY 40 GPM o Low pressure LTDN pressure-APPROXIMATELY 250 PSIG a.IF letdown isolated, THEN continue with Step 6b.IF NOT isolated, THEN go to AP-CVCS.1, CVCS LEAK, Step 6.o Letdown pressure control valve, PCV-135, demand-APPROXIMATELY 35%OPEN b.Charging indication:
o Seal injection flows GREATER THAN 6 GPM AND STABLE b.Go to AP-CVCS.1, CVCS LEAK, Step 6.o RCP Labyrinth seal D/Ps GREATER THAN 15 INCHES AND APPROXIMATELY EQUAL o Charging pump discharge pressure-GREATER THAN RCS PRESSURE c.AUX BLDG radiation levels NORMAL~R-4~R-9~R-10B~R-13~R-14 c.Go to AP-CVCS.1, CVCS LEAK, Step 6 and refer to CVCS piping diagrams for further guidance.
EOP: AP-RCS.1 TlTLE: REACTOR COOLANT LEAK REV: 12 PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRT Indications:
a.Level->BETWEEN 61%AND 84%b.Pressure-APPROXIMATELY 1.5 PSIG AND STABLE c.Temperature
-AT CNMT AMBIENT TEMPERATURE AND STABLE Check tailpipe and valve leakoff temperatures for the PRZR safety valves and PORVs for indication of leakage.IF no PORV,or safety valve leakage is indicated, THEN check other leak paths from the RCS to the PRT.~Letdown relief valve, RV-203~Seal return relief valve, RV-314 CAUTION STEAM GENERATOR TUBE LEAKAGE IN ONE S/G SHALL NOT EXCEED 0.1 GPM WHEN AVERAGED OVER 24 HOURS.8 Check S/Gs For Leakage: o Air ejector radiation monitors-~NORMAL IF S/G tube leak indicated, THEN refer to 0-6.10, PLANT OPERATION WITH A S/G TUBE LEAK INDICATION.
~R-15~R-15A o S/G blowdown radiation monitor (R-19)-NORMAL o Steamline radiation monitors NORMAL~R-31~R-32 o S/G sample activity-NORMAL (Check with RP Department for normal)
EOP: AP-RCS.1 REACTOR COOLANT LEAK REV: 12 PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check SI Accumulator Levels-STABLE Calculate inleakage to SI accumulators (Refer to S-16.11, MONITORING INLEAKAGE TO SI ACCUMULATORS).
10 Check RCP Seal Leakoff Flows: o Leakoff flows-WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF Go to AP-RCP.l, RCP SEAL MALFUNCTION.
o Leakoff flows-STABLE 11 Check RCDT Leak Rate-NORMAL (Refer to RCS Daily Leakage Log and PPCS point ID L1003)Check other sources of in leakage to RCDT: a.IF Rx vessel flange leakoff temperature has increased, THEN close Rx VESS FLANGE SEAL'EAKOFF VLV, AOV-521.b.Verify excess letdown isolated.IF NOT, THEN ensure RCDT divert valve, AOV-312, in the VCT position.c.IF source of leakage NOT determined, THEN suspect loop drains.
EOP: AP-RCS.1 TITLE REACTOR COOLANT LEAK REV: 12 PAGE 9 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Valve Leakoff Temperatures
-NORMAL (Refer to Pressurizer Valve Leak-Off Temperature Record Log)IF any valve leakoff temperature is abnormally high, THEN initiate investigation of that leakage path.13 Establish Stable Plant Conditions:
a.PRZR level-TRENDING TO PROGRAM b.Check PRZR pressure control: o Pressure-TRENDING TO 2235 PSIG o PRZR backup heaters-OFF a.Control charging and letdown flows to restore PRZR level to program.b.Verify proper operation of PRZR heaters and spray or take manual control of PRZR pressure controller 431K.IF pressure can NOT be controlled, THEN refer to AP-PRZR,l, ABNORMAL PRESSURIZER PRESSURE, 14 Evaluate RCS Leakage: a.Leakage within limits (Refer to leakage surveillance sheet and ITS section 3.4.13)b.Leak location identified a.IF leak NOT isolable, but PRZR level and seal injection can be maintained, THEN shut the plant down (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN or AP-TURB.5, RAPID LOAD REDUCTION).
b.Return to Step l.
AP-RCS.1 REACTOR COOLANT LEAK REV: 12 PAGE 10 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
15 Notify Higher Supervision-END-EOP: REACTOR COOLANT LEAK REV: 12 PAGE 11 of ll AP-RCS.1 APPENDIX LIST TITLE PAGES 1)FIGURE RCP SEAL LEAKOFF EOP: AP-RCS.1 TITLE: REACTOR COOLANT LEAK REV: 12 PAGE 1 of 1 FIGURE RCP SEAL LEAKOFF kl SEAL LEAK RATE (GPH)6 LEAK RATE INCREHENTS 0.2 GPH 3 NORHAL OPERATING RANGE DP INCREHENTS 50 PSI 250 500 750 1000 1250 1500 1750 2000 2250 2500 81 SEAL DP (RCS PRESS-VCT PRESS)PSI J