Revision as of 14:21, 7 July 2018

Text

Rev 5 to High Reactor Coolant Activity.
	ML17262A349
Person / Time
Site:	Ginna
Issue date:	11/20/1990
From:	WIDAY J A; ROCHESTER GAS & ELECTRIC CORP.
To:	;
Shared Package
ML17262A347	List: ML17262A346; ML17262A348; ML17262A349; ML17262A351; ML17262A352; ML17262A354; ML17262A356;
References
	AP-RCS.3, NUDOCS 9102070081
	Download: ML17262A349 (206)
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ECP: AP-RCS.3 TITLE: HIGH REACTOR COOLANT ACTIVITY REV: 5 PAGE 1 of 5 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE 40 P T SUPER NT NDENT-cgQ-9b EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY: 9i0207008i 9i020i l PDR ADDCK 050002m<PDR

/P Q'1II t 1~k EOP,: AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY REV: 5 PAGE 2 of 5 A.PURPOSE-This procedure provides guidance necessary to operate the plant with indication of high reactor coolant activity.B.ENTRY CONDITIONS/SYMPTOMS 1.SYMPTOMS-The symptoms of HIGH REACTOR COOLANT ACTIVITY are;a.Unexplained increase in letdown line monitor, R-9, or b.Sampling indicates I-131 equivalent GREATER THAN 0.2 uCi/gm, or c.Sampling indicates gross degassed activity GREATER THAN 20 uCi/gm, or d.Sampling indicates that total specific activity exceeds 84/E.

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AP-RCS.3 TITLE: HIGH REACTOR COOLANT ACTIVITY REV 5 PAGE 3 of 5 STEP ACTION/BXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************

CAUTION IF LETDOWN PLOW EXCEEDS 60 GPM WHEN USING AOV-202, D/P ACROSS THE CVCS DBMINERALIZERS SHOULD BE MONITORED TO VERIPY THAT FLOW IS CONTINUING THROUGH THE DI'S.HOWEVER, FLOW THROUGH THE DI'S SHOULD NOT EXCEED 90 GPM.1 Verify RCS Activity: a.Direct HP-TO SAMPLE RCS FOR ACTIVITY b.RCS activity-GREATER THAN NORMAL (Check with HP Department for normal activity)b.IP normal activity verified, THEN direct I8C to check operability of R-9, letdown line monitor, AND return to normal operations.

2 Increase Letdown Flow To 60 GPM a.Verify deborating DI i'solated-DIVERT VLV CATION DEBOR DI AOV-244 IN BYPASS POSITION b.Place PCV-135 to manual AND ad)ust as necessary-TO CONTROL LETDOWN PRESSURE a.Place AOV-244 in bypass position.c.Change orifices-CLOSE 40 GPM ORIPICE AND OPEN 60 GPM LTDN ORIFICE AOV-202 IMMBDIATELY d.Ad)ust letdown pressure-TO APPROXIMATELY 250 PSIG e.Return PCV-135-TO AUTO, IF DBSIRBD

+4 4 t, (,~V aa EOP.: AP-RCS.3 LITLE: HIGH REACTOR COOLANT ACTIVITY REV'PAGE 4 of 5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

3 Check Area Monitor R9 Letdown Line-LESS THAN 200 MR/HR ABOVE BACKGROUND Refer to EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.

- - - - CAUTION WHEN A NEW DI IS VALVED IN, THERE MAY BE A PLUS OR MINUS REACTIVITY ADDITION DUE TO A BORON CHANGE.(REFER TO S-3.2B TO PREVENT A REACTIVITY CHANGE.)4 Verify Proper Operation Of Letdown DI-DECONTAMINATION FACTOR GREATER THAN 10 IF DI efficiency is NOT acceptable, THEN place a new mixed bed in service.(Refer to S-4.5.7A, A LETDOWN MIXED BED DI RESIN REPLACEMENT, OR S-4.5.7B, B LETDOWN MIXED BED DI RESIN REPLACEMENT).

5.Check Sampling Requirements REFER TO TECHNICAL SPECIFICATION TABLE 4.1-4 6 Check If Continued Plant Power Operation Allowed: o Continued plant power operation-ALLOWED, REFER TO TECHNICAL SPECIFICATION SECTION 3.1.4 IF shutdown is required, THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.

8 lk'V$it EOP: AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY REV: 5 PAGE 5 of 5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check Aux Bldg For Increased Radiation Levels: a.Notify HP Department

-TO SURVEY AUX BLDG b.Aux Bldg radiation levels-NORMAL (Check with HP for normal readings)b.IF Aux Bldg radiation levels indicate above normal, THEN have HP Department establish controls for the higher radiation areas.8 Complete-NOTIFICATION TO HIGHER SUPERVISION AND THE REACTOR ENGINEER 9 Check Conditions For Offsite Reporting:

o Refer to-EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION-END-I~8 h 0 P4 h EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 17 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE 4P/7~PLANT SUPERINTENDENT 4-/1-5'8 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

ES-0.2 T!TLE NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 2 of 17 A.PURPOSE-This procedure provides actions to perform a natural circulation RCS cooldown and depressurization to cold shutdown, with no accident in progress, under requirements that will preclude any upper head void formation.

B.SYMPTOMS AND OR ENTRY CONDITIONS This procedure is entered from: 1)ES-0.1, REACTOR TRIP RESPONSE, when it has been determined that a natural circulation cooldown is required.2)ECA-0', LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED/when it has been determined that a natural circulation cooldown is required.3)Other normal operating procedures

'when a natural circulation cooldown is required.

'r EOP: ES-0'T1TLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 3 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION o IF SI ACTUATION OCCURS DURING THIS PROCEDURE, E-O, REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORMED.

o IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

NOTE: Foldout page should be open and monitored periodically.

1 Monitor Conditions For RCP Restart: a.Establish conditions for starting an RCP: o Bus 11A or 11B energiz.ed o Refer to Attachment RCP START b.Start one RCP c.Any RCP-RUNNING d.Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITION a.Go to Step 2.c.Go to Step 2.

.

EOP s ES-0'T!TLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 4 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check VCT Makeup System: a.Verify the following:

l)Boric acid flow control valve-SET FOR REQUIRED CSD CONCENTRATION 2)RMW mode selector switch in AUTO 3)RMW control armed-RED LIGHT LIT b.Check VCT level o Level-GREATER THAN 20$-OR-o Level-STABLE OR INCREASING b.Manually increase VCT makeup flow as follows: 1)Ensure BA transfer pumps and RMW pumps running.2)Place RMW,flow control valve HCV-ill in MANUAL and increase RNW flow.3)Increase boric acid flow as necessary.

EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV'PAGE 5 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check Charging Pump Suction Aligned To VCT: a.Check VCT level: o Level-GREATER THAN 20%o VCT makeup system-AVAILABLE a.IF VCT level can NOT be maintained greater than 5%, THEN perform the following:

1)Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed 2)Continue with Step 4.WHEN VCT level greater than 40$, THEN do Step 3b.b.Verify the following:

o LCV-112C-OPEN o LCV-112B-CLOSED b.Manually align valves as necessary.

4 Borate RCS To Cold Shutdown Boron Concentration (Refer to Figure SDM)5 Establish Maximum Rx Vessel Head Cooling: o Check control rod shroud fans (45,kw)-BOTH RUNNING o Check one Rx compartment cooling fan (23 kw)-RUNNING Start fans as necessary.

EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 6 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Verify Adequate Shutdown Margin a.Direct HP to sample the RCS for boron concentration

~RCS loop A~RCS loop B~PRZR b.Verify boron concentration-GREATER-THAN REQUIREMENTS OF FIGURE SDM b.Perform the following:

1)Maintain RCS average temperature greater than 500'F until adequate SDM established.

2)Continue to borate as necessary.

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EOP: ES-0.2 T]ILE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 7 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION o IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW WILL BE NECESSARY (REFER TO ER-AFW.1)ALTERNATE WATER SUPPLY TO AFW PUMPS).o SI MUST BE BLOCKED BEFORE S/G PRESSURE DECREASES TO 514 PSIG.o THE hT BETWEEN PRZR LIQUID AND THE HOT LEG TEMPERATURE SHOULD NOT BE PERMITTED TO EXCEED 200'F.IF THIS LIMIT IS EXCEEDED, THEN NOTIFY TECHNICAL ENGINEERING OF THE MAXIMUM hT OBSERVED.7 Initiate RCS Cooldown To Cold Shutdown: a.Dump steam to condenser b.Establish and maintain cooldown rate in RCS cold legs-LESS THAN 25'F/HR c.Maintain S/G narrow range level BETWEEN 17$AND 39%a.Manually or locally dump steam using S/G ARVs.c.Control feed flow as necessary.

d.Plot RCS cold leg temperatures and PRZR temperature twice per hour (Refer to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN, for plot paper)8 Check:RCS Hot Leg Temperatures

-LESS THAN 550'F Return to Step 7.

I H-I EOP t ES-0.2 TlTLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 8 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o If charging line to PRZR vapor hT exceeds 320'F, then plant staff should be consulted before using auxiliary spray.o WHEN using a PRZR PORV, THEN select one with an operable block valve.o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.9 Depressurize RCS To 1950 PSIG: a.Check letdown-IN SERVICE a.Try to establish letdown (Refer to Attachment LETDOWN).b.Depressurize RCS using auxiliary spray valve (AOV-296)IF letdown can NOT be established, THEN depressurize RCS using one PRZR PORV and go to Step 10.b.IF auxiliary spray valve NOT available, THEN use one PRZR PORV.

FOP: ES-0'T!TLE.NATURAL CIRCULATION COOLDONN REV: 5 PAGE 9 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**************************4'*************CAUTION SI ACTUATION CIRCUITS WILL AUTOMATICALLY UNBLOCK IF PRZR PRESSURE INCREASES TO GREATER THAN 1992 PSIG.******************************************10 Monitor SI Block Criteria: a.Check the following:

o PRZR pressure-LESS THAN 1950 PSIG a.Return to Step 9.-OR-o LOW PRZR PRESS BLOCK SAF INJEC status light-LIT h b.Place SI block switches to BLOCK~Train A~Train B c.Verify SAFETY INJECTION BLOCKED status light-LIT c.Maintain PRZR pressure greater than 1750 psig and S/G pressure greater than 514 psig until SI blocked.11 Determine RCS Pressure And Temperature Limits-.a.Check control rod shroud fans-BOTH RUNNING b.Maintain RCS pressure-WITHIN LIMITS OF FIGURE NAT CIRC C/D WITH SHROUD FANS a.Perform the following:

1)Maintain RCS pressure within limits of Figure NAT CIRC C/D WITHOUT SHROUD FANS.2)Go to Step 12.

l O' ES-0.2 T1TLE!NATURAL CIRCULATION COOLDOWN REV 5 PAGE 10 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*12 Maintain PRZR Level Between 204 And 304*13 Monitor RCS Cooldown: o Core exit T/Cs-DECREASING o RCS hot leg temperatures-DECREASING o RCS subcooling based on core exit T/Cs-INCREASING o Cooldown rate in RCS cold legs-LESS THAN 25'F/HR

EOP$ES-0.2 TITLE$NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 11 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.

THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.NOTE: o If at any time it is determined that a natural circulation cooldown and depressurization must be performed at a rate that may form a steam void in the vessel, then procedure ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAN VOID IN VESSEL, should be used.o If charging line to PRZR vapor AT exceeds 320'F, then plant staff should be consulted before using auxiliary spray.o WHEN using a PRZR PORV, THEN select one with an operable block valve.o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves, 14 Initiate RCS Depressurization:

a.Check letdown-IN SERVICE b.Depressurize RCS using auxiliary spray valve (AOV-296)c.Plot:" RCS temperature and pressure on curve selected in Step 11 hourly a.Try to establish letdown (Refer to Attachment LETDOWN).IF letdown can NOT be established, THEN depressurize RCS using one PRZR PORV and go to Step 15.b.IF auxiliary spray valve NOT available, THEN use one PRZR PORV.

EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 12 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Continue Cooldown And Depressurization:

a.Check RCS cold leg temperature-GREATER THAN 335'F b.Maintain cooldown rate in RCS cold legs-LESS THAN 25'F/HR c.Maintain RCS temperature and pressure within limits of Figure determined previously a.Stabilize RCS temperature and go to Step 15c.c.Control RCS pressure as neces'sary to restore pressure/temperature relationship to within limits of approprite Figure.16 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT)17 Check For Steam Void In Reactor Vessel: Repressurize RCS within allowable limits and continue cooldown.o PRZR level-NO UNEXPECTED LARGE VARIATIONS o RVLIS level (no RCPs)-GREATER THAN 95%IF RCS depressurization must continue, THEN go to ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL.

C I, V l t 4 l EOP t ES-0'NATURAL CIRCULATION COOLDONN REV: 5 PAGE 13 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Check If SI ACCUMs Should Be Isolated: a.RCS pressure-LESS THAN 1500 PSIG b.Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves~'MOV-841, MCC C position 12F~MOV-865, MCC D position 12C c.Close SI ACCUM discharge valves~ACCUM A)MOV-841~ACCUM B, MOV-865 a.Continue with Step 19.WHEN RCS pressure is less than 1500 psig, THEN do Steps 18b through d.c.IF any valve can NOT be closed, THEN perform the following:

1)Dispatch personnel to locally close valves, as necessary.

2)Maintain RCS pressure greater than 1000 psig until both SI ACCUMs isolated.IF any SI ACCUM can NOT be isolated AND RCS depressurization to less than 1000 psig is required, THEN;1)Open vent valves for unisolated SI ACCUMs,~ACCUM A, AOV-834A~ACCUM B, AOV-834B d.Locally open breakers for MOV-841 and MOV-865 2)Open HCV-945.3)Maintain RCS pressure greater than SI ACCUM pressure.

EOP: ES-0.2 NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 14 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*19 Maintain Letdown Flow: a.Open letdown orifice valves as necessary b.Adjust low pressure letdown control valve setpoint as necessary*20 Maintain Required RCP Seal Injection Flow And Labyrinth Seal D/P: o Labyrinth seal D/P to each RCP-GREATER THAN 15 INCHES OF WATER Perform the following:

o Adjust charging flow to REGEN Hx (HCV-142)as necessary.-OR-o Seal injection flow to each RCP-GREATER THAN 6 GPM o Dispatch AO to adjust seal injection needle valves if necessary.

~RCP A, V-300A~RCP B, V-300B 4

EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV'PAGE 15 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check If SI System Normal Shutdown Alignment Should Be Established:

a.RCS cold leg temperature

-LESS THAN 350'F a.Return to Step 15.b, RCS pressure-LESS THAN 1500 PSIG c.Lock out SI system as follows: 1)Place all SI pump switches in PULL STOP b.Stabilize RCS temperature and return to Step 14.2)Locally close breakers for SI.pump discharge valves to cold legs~MOV-878B, MCC D position 8C~MOV-878D, MCC D position 8F 3)Close SI pump discharge to cold legs~MOV-878B~MOV-878D 4)Locally open breakers for MOV-878B and MOV-878D Pt EOPt ES-0.2 TITLE: NATURAL CIRCULATION COOLDOWN REV 5 PAGE 16 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Check If RHR Normal Cooling Can Be Established:

a.RCS pressure-LESS THAN 400 PSIG b.Verify all SI pump switches in PULL STOP a.Stabilize RCS temperature and return.to Step 14.b.Return to Step 21.c.Sample the RHR system to ensure adequate boron concentration (Refer to Attachment RHR SAMPLE)d.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)e.Establish RHR normal cooling (Refer to Attachment RHR COOL)d.IF RCS overpressure protection system can NOT be placed in service, THEN consult Plant staff to determine if RHR normal cooling should be established and go to Step 23.23 Continue RCS Cooldown To Cold.Shutdown*****************************************CAUTION DEPRESSURIZING THE RCS BEFORE THE ENTIRE RCS IS LESS THAN 200'F MAY RESULT IN ADDITIONAL VOID FORMATION IN THE RCS.24 Continue Cooldown Of Inactive Portion Of RCS: a.Cool upper head region using control rod shroud fans b.Cool S/G U-tubes by dumping steam from all S/Gs

EOP: ES-O.'T1TLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 17 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION IF LESS THAN TWO CONTROL ROD SHROUD FANS ARE RUNNING, THE UPPER HEAD REGION MAY REMAIN ABOVE 200'F FOR UP TO 29 HOURS AFTER REACHING CSD.25 Determine If RCS Depressurization Is Permitted:

a.Entire RCS-LESS THAN 200'F~Core exit T/Cs~Upper head T/Cs~RCS hot leg temperature

~RCS cold leg temperature b.Check control rod shroud fan status-BOTH RUNNING DURING COOLDOWN c.Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD SHUTDOWN)a.Do NOT depressurize RCS.Return to Step 23.b.Consult Plant staff to determine wait period for upper head cooling.-END-I EOP;ES-0'T1TLE NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 1 ES-0.2 APPENDIX LIST TITLE PAGES 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLING 3)FIGURE SDM 4)FIGURE NAT CIRC C/D WITHOUT SHROUD FANS 5)FIGURE NAT CIRC C/D WITH SHROUD FANS 6)ATTACHMENT RCP START 7)ATTACHMENT LETDOWN 8)ATTACHMENT RHR COOL 9)ATTACHMENT RHR SAMPLE 10)FOLDOUT

EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 1 RED PATH

SUMMARY

a.SUBCRITICALITY

-Nuclear power greater than 5%b.CORE COOLING-Core exit T/Cs greater than 1200'F-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs)less than 43%[46%adverse CNMT]c.HEAT SINK-Narrow range level in all S/Gs less than 5%[25%adverse CNMT]AND total feedwater flow less than 200 gpm d.INTEGRITY-Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F e.CONTAINMENT

-CNMT pressure greater than 60 psig

EOP!ES-0'TiTLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature From Figure Below[-]Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 OI woo 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVERSE CNMT NORMAL CNMT INADEQUATE SUBCOOL ING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE

('F)

EOP: ES-0.2 T!TLE: NATURAL CIRCULATION COOLDOWN REV 5 PAGE 1 of 1 BORON CONCENTRATION (PPH)1800 FIGURE SDM 1600 BORON INCREHENTS 20 PPH 1400 1200 1000 ADEQUATE SDH 100 PPH CONS ERVATISH INCLUDED8OO 600 400 BORATE 200 BURNUP INCREHENTS 100 HWD/HTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)NOTE: To obtain core burnup, use PPCS turn on code BURNUP.

h, A" EOP0 ES-0'T!TLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 1 RCS 2500 PRESSURE (PSIG)FIGURE NAT CIRC C D WITHOUT SHROUD FANS 2400 2300 2200 2100 2000 1900 1800 1700 1600 RCS PRESSURE INCREHENTS 20 PSIG RCS temp for S/G SI (514 psig)SI UNBLOCK NORHAL RANGE 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200100[2]Wait 29 hrs before decreasing RCS pressure less than 350 psig to prevent boiling in upper head[1]Wait 11 hrs before decreasing RCS pressure less than 1600 psig TEHPERATURE INCREHENTS 10'F 0 50 100 150'200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEHPERATURE

('F)

EOP: ES-0.2 TlTLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of I RCS PRESSURE (PSIG)2500 FIGURE NAT CIRC C D WITH SHROUD FANS 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200ioo RCS PRESSURE INCREMENTS 20 PSIG RCS temp for S/G SI (514 psig)SI UNBLOCK A.V 0 I D NORMAL RANGE TEMPERATURE INCREMENTS 10'F 0 50 100 150 200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEMPERATURE

('F)

EOP: ES-0'TlTLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 1 1~2~FOLDOUT PAGE RC T I CR TERIA IF BOTH conditions listed below occur, THEN trip both RCPs: a.SI pumps-AT LEAST TWO RUNNING b.RCS pressure minus maximum S/G pressure-LESS THAN 175 PSIG SI PUMP AUTO SWITCHOVER CRITERION WHEN BAST level decreases to 104, THEN ensure SI pump automatic switchover to RWST.3~SI ACTUATION CRITERIA IF EITHER condition listed below occurs, THEN actuate SI and go to E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1.o RCS subcooling based on core exit T/Cs-LESS THAN O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING OR-o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54 AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

"Sy EOP: ES-1.2 TITLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 1 of 23 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0.REVIEWED BY:

P EOP: ES-1.2 TITLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 2 of 23 A.PURPOSE-This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions following a loss of reactor coolant inventory.

B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS

-This procedure is entered from: E 1 g LOSS OF REACTOR OR SECONDARY COOLANT g when RCS pressure is greater than the shutoff head pressure of the RHR pumps.

EOP: ES-1s2 TITLE: POST.LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 3 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION o IF RWST LEVEL DECREASES TO LESS THAN 28%, THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, STEP l.o IF PRZR LEVEL IS LESS THAN 50%OR IF ADVERSE CNMT CONDITIONS EXIST, THEN PRZR HEATERS SHOULD NOT BE ENERGIZED UNTIL PRZR LEVEL IS EVALUATED BY THE TSC.o RCS PRESSURE SHOULD BE MONITORED.

IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG[465 PSIG ADVERSE CNMT], THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.NOTE: o Foldout page should be open and monitored periodically.

1 o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+R/hr.*I Monitor If RHR Pumps Should Be Stopped: a.Check RCS pressure: 1)Pressure-GREATER THAN 250 psig[465 psig adverse CNMT]2)Pressure-STABLE OR INCREASING a.Go to Step 2.b.Stop RHR pumps and place AUTO

EOP: ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 4 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*2 Monitor All AC Busses-BUSSES ENERGIZED BY OFFSITE POWER o Normal feed breakers to all 480 volt busses-CLOSED o 480 bus voltage-GREATER THAN 420 VOLTS o Emergency D/G output breakers OPEN a.IF any AC emergency bus normal feed breaker open, THEN ensure associated D/G breaker closed.b.Perform the following, as necessary:

1)Close non-safeguards bus tie breakers:~Bus 13 to Bus 14 tie~Bus 15 to Bus 16 tie 2)Place the following pumps in PULL STOP'EH pumps~Turning gear oil pump~HP seal oil backup pump 3)Restore power to MCCs.~A from Bus 13~B from Bus 15~E from Bus 15~F from Bus 15 4)WHEN bus 15 restored, THEN reset control.room lighting.5)Refer to Attachment SI/UV for other equipment lost with loss of offsite power.c.Try to restore offsite power to all AC busses (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

EOP: ES-1'POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 5 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Establish 75 GPM Charging Flaw: a.Charging pumps-ANY RUNNING a.Perform the following:

1)IF CCW flow is lost to any RCP thermal barrier OR any RCP¹1 seal outlet temperature offscale high, THEN dispatch AO with RWST area key to locally isolate seal injection to affected RCP'V-300A for RCP A~V-300B for RCP B 2)Ensure HCV-142 open, demand at 0%.b.Align charging pump suction to RWST'LCV-112B-OPEN o LCV-112C-CLOSED b.IF LCV-112B can NOT be opened, THEN perform the following:

1)Verify charging pump A NOT running and place in PULL STOP.c.Start charging pumps as necessary (75 kw each)and establish 75 gpm total charging flow 2)Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).3)WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).~Charging line flow~Seal injection flow

EOP!ES-1.2 TITLE!POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 6 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Establish Condenser Steam Dump Pressure Control: a.Verify condenser available:

o Any MSIV-OPEN o Annunciator G-15, STEAM DUMP ARMED-LIT a.Place S/G ARV controllers in AUTO at desired pressure and go to Step 5.b.Ad)ust condenser steam dump controller HC-484 to desired pressure and verify in AUTO c.Place steam dump mode selector switch to MANUAL*****************************************CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS), NOTE: TDAFW pump flow control valves fail open on loss of IA.*5 Monitor Intact S/G Levels: a.Narrow range level-GREATER THAN 5S[25$adverse CNMT)b.Control feed flow to maintain narrow range level between 17%[25%adverse CNMT]and 50%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT]in at least one S/G.b.IF narrow range level in any S/G continues to increase in an uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

EOP: ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 7 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Shutdown margin should be monitored during RCS cooldown (Refer to Figure SDM).6 Initiate RCS Cooldown To Cold Shutdown: a.Establish and maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Use RHR system if in service c.Dump steam to condenser from intact S/G(s)c.Manually or locally dump steam using intact S/Gs ARV.7 Check RCS Subcooling'ased On Core Exit T/Cs-GREATER THAN O'F USING FIGURE MIN SUBCOOLING Manually operate SI pumps as necessary and go to Step 19.8 Check SI and RHR Pump Status: o SI pumps-ANY RUNNING-OR-Go to Step 15.o RHR pumps-ANY RUNNING IN INJECTION MODE 9 Place PRZR Heater Switches In The Following Positions:

o PRZR'eater control group-PULL STOP'PRZR heater backup group-OFF "i

EOP: ES-1.2 TLTLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 8 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.

THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.NOTE: o WHEN using a PRZR PORV, THEN select one with an operable block valve.o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.10 Depressurize RCS To Refill PRZR: a.Depressurize using normal PRZR spray if available a.Depressurize using one PRZR PORV.IF IA NOT available, THEN refer to Attachment N2 PORVS.b.PRZR level-GREATER THAN 13%[40$adverse CNMT]c.Stop RCS depressurization IF no PORV available, THEN use auxiliary spray valve (AOV-296).

b.Continue with Step ll.WHEN level greater than 13%[40$adverse CNMTJ, THEN stop RCS depressurization.

4 EOP: ES-1.2 T1TLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 9 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

- - - - 11 Check If An RCP Should Be Started: a.Both RCPs-STOPPED b.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Stop all but'one RCP and go to Step 12.b.Go to Step 19, c.PRZR level-GREATER THAN 13%[40$adverse CNMT]c.Return to Step 10.d.Try to start an RCP 1)Establish conditions for starting an RCP o Bus 11A or 11B energized o Refer to Attachment RCP START d.IF IA to CNMT available, THEN ensure at least one control rod shroud fan running (45 kw each).2)Start one RCP I I EOP: ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 10 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If One Of Three SI Pumps Should Be Stopped: a.Three SI pumps-RUNNING b.RCS subcooling based on core exit T/Cs-GREATER THAN 35'F[90'F adverse CNMT]USING FIGURE MIN SUBCOOLING c.Check PRZR level-GREATER THAN 13%[40%adverse CNMT]d.Stop one SI pump a.Go to Step 13.b.IF RCS hot leg temperatures greater than 325'F[270'F adverse CNMT]OR IF RHR normal cooling in service, THEN go to Step 19.IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F[270'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 12c.IF no RHR pump can be operated in injection mode, THEN go to Step 19.c.Do NOT stop SI pump.Return to Step 10.

EOP!ES-1.2 TlTLE~POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 11 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Check If One Of Two SI Pumps Should Be Stopped: a.Two SI pumps-RUNNING b.Determine required RCS subcooling from table: a.Go to Step 14.Charging Pump Availability NONE ONE THREE RCS Subcooling Criteria 120'F[200'F adverse CNMT]115'F[190'F adverse CNMT]105'F[180'F adverse CNMT]100'F[175'F adverse CNMT)c.RCS subcooling based on core exit T/Cs-GREATER THAN VALUE FROM TABLE ABOVE USING FIGURE MIN SUBCOOLING c.IF RCS hot leg temperatures greater than 325'F[270'F adverse CNMT]OR IF RHR normal cooling in service, THEN go to Step 19.d.PRZR level-GREATER THAN 13%[40%adverse CNMT]e.Stop one SI pump IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F[270'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 13d.IF no RHR pump can be operated in injection mode, THEN go to Step 19.d.Do NOT stop SI pump.Return to Step 10.

1 EOP: ES-1.2 TITLEt POST LOCA COOLDOWN AND DEPRESSURIZATION REV'0 PAGE 12 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If Last SI Pump Should Be Stopped: a.One SI pump-RUNNING b.Determine required RCS subcooling from table: a.'F any RHR pump running in injection mode, THEN go to Step 19.IF NOT, THEN go to Step 15.Charging Pump Availability NONE ONE TWO THREE RCS Subcooling Criteria Insufficient subcooling to stop SI pump.255'F[295'F adverse CNMT]235'F[285'F adverse CNMT]210'F[270'F adverse CNMT]c.RCS subcooling based on core exit T/Cs-GREATER THAN VALUE FROM TABLE ABOVE USING FIGURE MIN SUBCOOLING c.IF RCS hot leg temperatures greater than 325'F[270'F adverse CNMT]OR IF RHR normal cooling in service, THEN go to Step 19.IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F[270'F adverse CNMT], THEN ,ensure at least one RHR pump running in injection mode and go to Step 14d.IF no RHR pump can be operated in injection mode, THEN go to Step 19.d.PRZR level-GREATER THAN 13%[40%adverse CNMT]e.Stop running SI pump d.Do NOT stop SI pump.Return to Step 10.

EOP: ES-1'TITLE$POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 13 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Check If Charging Flow Should Be Controlled To Maintain PRZR Level: a.Check RHR pumps-RUNNING IN INJECTION MODE b.Go to Step 19 a.Start charging pump and control charging flow to maintain PRZR level and go to Step 16.*****************************************CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

16 Check RCP Status: a.RCPs-AT LEAST ONE RUNNING a.Perform the following:

1)Establish conditions for starting an RCP: o Verify Bus 11A or 11B energized.

o Refer to Attachment RCP START.2)Start one RCP.IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).IF natural circulation NOT verified, THEN increase dumping steam.b.Stop all but one RCP-w EOP: ES-1'POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 14 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.

THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.NOTE: o WHEN using a PRZR PORV, THEN select one with an operable block valve.o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.17 Depressurize RCS To Minimize RCS Subcooling:

a.Depressurize using normal PRZR spray if available a.IF normal spray NOT available, THEN use one PRZR PORV.IF IA NOT available, THEN refer to Attachment N2 PORVS.b.Energize PRZR heaters as necessary c.Depressurize RCS until EITHER of the following conditions satisfied:

IF no PRZR PORV available, THEN use auxiliary spray valve (AOV-296).

o RCS subcooling based on core exit T/Cs-LESS THAN 10'F USING FIGURE MIN SUBCOOLING-OR-o PRZR level-GREATER THAN.75%[65%adverse CNMT]

EOP: ES-1.2 T!TLE POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 15 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify Adequate Shutdown Margin a.Direct HP to sample RCS for boron concentration b.Verify boron concentration-GREATER THAN REQUIREMENTS OF FIGURE SDM b.Borate as necessary.

19 Monitor SI Reinitiation Criteria: a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Manually operate SI pumps as necessary and go to Step 20.b, PRZR level-GREATER THAN 5%[30%adverse CNMT]b.Manually operate SI pumps as necessary and return to Step 10.

EOP$ES-1.2.T1TLE$POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 16 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check If SI ACCUMs Should Be Isolated: a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING b.PRZR level-GREATER THAN 5%[30%adverse CNMT]c.Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves~MOV-841, MCC C position 12F~MOV-865, MCC D position 12C d.Close SI ACCUM discharge valves~ACCUM A, MOV-841~ACCUM B, MOV-865 e.Locally reopen breakers for MOV-841 and MOV-865 a.IF both RCS hot leg temperatures less than 400'F, THEN go to Step 20c.IF NOT, THEN go to Step 21.b.Return to Step 10.d.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.~ACCUM A, AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.

EOP: ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 17 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check If Emergency D/Gs Should Be Stopped: a.Verify AC emergency busses energized by offsite power: o Emergency D/G output breakers OPEN a.Try to restore offsite power (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).o AC emergency bus voltage-GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers-CLOSED b.Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)22 Verify Adequate SW Flow To CCW Hx: a.Verify at least two SW pumps-RUNNING b.Verify AUX BLDG SW isolation valves-OPEN~MOV-4615 and MOV-4734~MOV-4616 and MOV-4735 c.Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE ALARM-EXTINGUISHED a.Manually start pumps as power supply permits (258 kw per pump).IF less than two SW pumps can be operated, THEN go to Step 23.b.Establish SW to AUX BLDG (Refer to Attachment AUX BLDG SW).c.Dispatch AO to locally throttle flow to CCW Hx to between 5000 gpm and 6000 gpm total flow.

'

EOP: ES-1.2 T!TLE0 POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 18 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check RCP Cooling a.Check CCW to RCPs Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).o Annunciator A-7, RCP lA CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED o Annunciator A-15, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED b.Check RCP seal in)ection o Labyrinth seal D/Ps-GREATER THAN 15 INCHES WATER-OR-o RCP seal injection flov to each RCP-GREATER THAN 6 GPM 3 It EOP: ES-1'POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 19 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 Check If Seal Return Flow Should Be Established:

a.Verify instrument bus D-ENERGIZED b.Verify RCP¹1 seal outlet temperature

-LESS THAN 235'F c.Verify RCP seal outlet valves OPEN~AOV-270A~AOV-270B a.Restore power to instrument bus D from MCC B or MCC A (maintenance supply).b.Go to Step 25.c.Manually open valves as necessary.

d.Reset both trains of XY relays for RCP seal return isolation valve MOV-313 e.Open RCP seal return isolation valve MOV-313 f.Verify RCP¹1 seal leakoff flow-LESS THAN 5.5 GPM g.Verify RCP¹1 seal leakoff flow GREATER THAN 0.25 GPM e.Perform the following:

1)Place MOV-313 switch to OPEN, 2)Dispatch AO with key to RWST gate to locally open MOV-313.f.IF any RCP seal leakoff flow greater than 5.5 gpm, THEN perform the following:

o Close the affected RCP seal discharge valve~RCP A, AOV-270A~RCP B, AOV-270B o Trip the affected RCP IF both RCP seal discharge valves are shut, THEN go to Step 25'.Refer to AP-RCP.l, RCP SEAL MALFUNCTION.

EOP: ES-1.2 TITLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 20 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

25 Check Xf Source Range Detectors Should Be Energized:

a.Source range channels DEENERGIZED a.Go to Step 25e.b, Check intermediate range flux-EITHER CHANNEL LESS THAN 10 10 AMPS b.Perform the following:

1)IF neither intermediate range channel is decreasing, THEN initiate boration.2)Continue with Step 26.WHEN flux is LESS THAN 10 amps on any operable channel, THEN do Steps 25c, d and e.c.Check the following:

o Both intermediate range channels-LESS THAN 10 AMPS c.Continue with Step 26.WHEN either condition met, THEN do Steps 25d and e.-OR-o Greater than 20 minutes since reactor trip d.Verify source range detectors-ENERGIZED d.Manually energize source range detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).IF source ranges can NOT be restored, THEN refer to ER-NIS.l, SR MALFUNCTION and go to Step 25.e.Transfer Rk-45 recorder to one source range and one intermediate range channel

EOP$ES-1'TITLE$POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 21 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Establish Normal Shutdown.Alignment:

a.Check condenser-AVAILABLE a.Dispatch AO to perform Attachment SD-2.b.Perform the following:

o Open generator disconnects

~1G13A71~9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cern to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump c.Verify adequate Rx head cooling: 1)Check IA to CNMT-AVAILABLE 1)Go to Step 26d.2)Verify at least one control rod shroud fan-RUNNING 3)Verify one Rx compartment cooling fan-RUNNING 2)Manually start one fan as power supply permits (45 kw)3)Perform the following:

o Dispatch AO to reset UV relays at MCC C and MCC D.o Manually start one fan as power supply permits (23 kw)d.Verify Attachment SD-1-COMPLETE

EOP: ES-1.2 TITLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 22 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Check If RCPs Must Be Stopped: a.RCPs-ANY RUNNING b.Check the following:

o RCP¹1 seal D/P-LESS THAN 220 PSID a.Go to Step 28.b.Go to Step 28.-OR-o RCP¹1 seal leakoff-LESS THAN 0.25 GPM c.Stop affected RCP(s)28 Check Condenser Steam Dump Available-CONDENSER VACUUM GREATER THAN 20 INCHES HG Use intact S/G'ARV for RCS temperature control.29 Check If RHR Normal Cooling Can Be Established:

a.RCS cold leg temperature

-LESS THAN 350'F a.Return to Step 1.b.RCS pressure-LESS THAN 400 psig[300 psig adverse CNMT]c.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)d.Consult TSC to determine if RHR normal cooling should be established using Attachment RHR COOL b.Go to Step 30.

EOP:, ES-1.2 T!TLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 23 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 30.30 Check CNMT Hydrogen Concentration:

a.Direct HP to start CNMT hydrogen monitors as necessary)b.Hydrogen concentration

-LESS THAN 0.5%b.Consult TSC to determine if hydrogen recombiners should be placed in service.31 Check Core Exit T/Cs-LESS THAN 200'F Return to Step l.32 Evaluate Long Term Plant Status: a.Maintain cold shutdown conditions b.Consult TSC-END-

EOP ES-1.2 T!TLEI POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 1 of 1 ES-1.2 APPENDIX LIST TITLE 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLING 3)FIGURE SDM 4)ATTACHMENT SEAL COOLING 5)ATTACHMENT RCP START 6)ATTACHMENT NC 7)ATTACHMENT D/G STOP 8)ATTACHMENT SD-1 9)ATTACHMENT SD-2 10)ATTACHMENT SI/UV 11)ATTACHMENT N2 PORVS 12)ATTACHMENT RHR COOL 13)ATTACHMENT AUX BLDG SW 14)FOLDOUT PAGES

EOP: ES-1.2 TITLE!POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 1 of 1 RED PATH SUMhG&Y a.SUBCRITICALITY

-Nuclear power greater than 5%b.CORE COOLING-Core exit T/Cs greater than 1200'F-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs)less than 43%[46%adverse CNMT]c.HEAT SINK-Narrow range level in all S/Gs less than 5%[25%adverse CNMT]AND total feedwater flow less than 200 gpm d.INTEGRITY-Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F e.CONTAINMENT

-CNMT pressure greater than 60 psig

EOP: ES-1.2 T!TLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature From Figure Below[-]Core.Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVERSE CNMT NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE

('F) 1t EOP: ES-1.2 TITLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 1 of 1 BORON CONCENTRATION (PPM)1800 FIGURE SDM 1600 BORON INCREMENTS 20 PPM 1400 1200 1000 ADEQUATE SDM 100 PPM CONSERVATISM INCLUDED800 600 400 BORATE 200 BURNUP INCREMENTS 100 MWD/MTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (MWD/HTU)NOTE: To obtain core burnup, use PPCS turn on code BURNUP.

8 EOP: ES-1.2 T!TLE0 POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 1 of 1 FOLDOUT PAGE 1.SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually operate SI pumps as necessary:

o RCS subcooling based on core exit T/Cs-LESS THAN O'F USING FIGURE MIN SUBCOOLING

-OR-o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54[304 adverse CNMT]2~SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, SI TERMINATION, Step 1: a.RCS subcooling based on core exit T/Cs-GREATER THAN O'F USING FIGURE MIN SUBCOOLING b.Total feed flow to intact-S/Gs

-GREATER THAN 200 GPM-OR-Narrow range level in at least one intact S/G-GREATER THAN 54[254 adverse CNMT]c.RCS pressure: o GREATER THAN 1625 PSIG[1825 psig adverse CNMT]o STABLE OR INCREASING d.PRZR level-GREATER THAN 54[304 adverse CNMT]3.SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.4.COL LEG CIRCULATION SWITCHOVER CRITERION IF RpST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.5.AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS)~6.E-3 TRANSITION CRITERIA IF any S/G level increases in an uncontrolled manner or any S/G has abnormal radiation, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

EOPo ES-3~1 TITLE: POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 1 of 9 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC'EVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE'ATEGORY 1.0 REVIEWED BY:

ps-ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV 6 PAGE 2 of 9 A.PURPOSE-This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR.This recovery method depressurizes the ruptured S/G by draining it through the ruptured S/G tubes into the RCS.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS

-This procedure is entered from: a.E-3 STEAM GENERATOR TUBE RUPTURE&, if plant staff selects backfill method.b.ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWNg when blowdown is not available and plant staff selects backfill.method.

V I i l 4 EOP: ES-3.1 T!TLE0 POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 3 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION INADVERTANT CRITICALITY MAY OCCUR FOLLOWING NATURAL CIRCULATION COOLDOWN IF THE RCP IN THE RUPTURED LOOP IS STARTED FIRST.J NOTE: o FOLDOUT page should be open AND monitored periodically.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+O R/hr.1 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure.

J~8 I EOP ES-3.1-TITLE: POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 4 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check If SI ACCUMs Should Be Isolated: a.Check the following:

o RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.o PRZR level-GREATER THAN 5S[30%adverse CNMT)b.Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves~MOV-841, MCC C position 12F~MOV-865, MCC D position 12C c.Close SI ACCUM outlet valves~ACCUM A, MOV-841~ACCUM B, MOV-865 d.Locally reopen breakers for MOV-841 and MOV-865 c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.~ACCUM A, AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.

I t EOP: ES-F 1 E TlTLE: POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 5 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

3 Verify Adequate Shutdown Margin a.Direct HP to sample RCS and ruptured S/G for boron concentration b.Verify boron concentration-GREATER THAN REQUIREMENTS OF FIGURE SDM b.Borate as necessary.

- - - - CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).NOTE: TDAFW pump flow control valves fail open on loss of IA.*4 Monitor Intact S/G Level: a.Narrow range level-GREATER THAN 5%[25%adverse CNMT]b.Control feed flow to maintain narrow range level between 17%[25%adverse CNMT)and 50%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT]in the intact S/G.b.IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.

S-r EOP: ES-3.1 T1TLE!POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 6 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.5 Initiate RCS Cooldown To Cold Shutdown: a.Establish and maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Use RHR system if in service c.Dump steam to condenser from intact S/G c.Manually or locally dump steam using intact S/G ARV.IF no intact S/G available and RHR system NOT in service, THEN perform the following:

o Use faulted S/G.-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.*6 Monitor Ruptured S/G Narrow Range Level-LEVEL GREATER THAN 174[254 adverse CNMT]Refill ruptured S/G to 67%[55%adverse CNMT]using feed flow.IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G: o Ruptured S/G pressure decreases in an uncontrolled manner.-OR-o Ruptured S/G pressure increases to 1020 psig.

g l EOP: ES-3'POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 7 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*7 Control RCS Makeup Flow And Letdown To Maintain PRZR Level: a.PRZR level-GREATER THAN 13%[40%adverse CNMT]b.PRZR level-LESS THAN 75%[65%adverse CNMT]a.Increase RCS makeup flow as.necessary and go to Step 8.b.Decrease RCS makeup flow to'ecrease level and go to Step 10.NOTE: The upper head region may void during RCS depressurization if RCPs are not running.This may result in a rapidly increasing PRZR level.*8 Depressurize RCS To Backfill From Ruptured S/G: a.Depressurize using normal PRZR spray a.IF letdown is in service, THEN depressurize using auxiliary spray valve (AOV-296), IF NOT, THEN use one PRZR PORV.b.Maintain PRZR level-BETWEEN 13%AND 75%[BETWEEN 40%AND 65%adverse CNMT]c.Check ruptured S/G level-GREATER THAN 5$[25%adverse CNMT]d.Energize PRZR heaters as necessary e.Maintain RCS subcooling based on core exit T/Cs-GREATER THAN O'F USING FIGURE MIN SUBCOOLING c.Stop RCS depressurization.

EOP: ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 8 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish Recpxired RCS Hydrogen Concentration (Refer to S-3.3C, H2 Or 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT)10 Check If RHR Normal Cooling Can Be Established:

a.RCS cold leg temperature

-LESS THAN, 350'F b.RCS pressure-LESS THAN 400 psig[300 psig adverse CNMT]c.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)d.Establish RHR normal cooling (Refer to Attachment RHR COOL)a.Go to Step 11.b.Go to Step 11, c.IF RCS overpressure protection system can NOT be placed in service, THEN notify TSC of potential Tech Spec violation if RHR system is placed in service.*ll'onitor RCP Operation:

a.RCPs-ANY RUNNING b.Check the folloving:

o RCP¹1 seal D/P-LESS THAN 220 PSID a.Go to Step 12.b.Go to Step 12.-OR-o Check RCP seal leakage-LESS THAN 0.25 GPM c.Stop affected RCP(s)

EOP: ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 9 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Core Exit T/Cs-LESS THAN 200'F Return to Step 3.13 Evaluate Long Term Plant Status: a.Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)b.Consult TSC'END-

EOP: ES-3'POST-SGTR COOLDOWN USING BACKFILL REV',PAGE 1 of 1 ES-3.1 APPENDIX LIST TITLE 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLING 3)FIGURE SDM 4)ATTACHMENT RHR COOL 5)FOLDOUT PAGES I a,g EOP: ES-3'POST-SGTR COOLDOWN USING BACKFILL REV 6 PAGE 1 of 1 RED PATH

SUMMARY

a.SUBCRITICALITY

-Nuclear power greater than 54 b.CORE COOLING-Core exit T/Cs greater than 1200'F-OR-'ore exit T/Cs greater than 700'F AND RVLIS level (no RCPs)less than 434[46%adverse CNMT]c.HEAT SINK-Narrow range level in all S/Gs less than 54[254 adverse CNMT)AND total feedwater flow less than 200 gpm d.INTEGRITY-Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F e.CONTAINMENT

-CNMT pressure greater than 60 psig I'

EOP: ES-3'POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature From Figure Below[-]Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVERSE CNHT NORMAL CNHT INADEQUATE SUBCOOL ING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE

('F) l'~~~tl EOP t ES-F 1 T1TLE: POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 1 of 1 BORON CONCENTRATION (PPH)1800 FIGURE SDM 1600 BORON INCREMENTS 20 PPM 1400 1200 1000 ADEQUATE SDH 100 PPH CONSERVATISM INCLUDED80O 600 400 BORATE 200 BURNUP INCREMENTS 100 HWD/MTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)NOTE: To obtain core burnup, use PPCS turn on code BURNUP.

EOP!ES-3~1 TITLE: POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 1 of 1 1~SI REINITIATION CRITERI FOLDOUT PAGE 2~IF either condition listed below occurs, THEN operate SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1: o RCS subcooling based on core exit T/Cs-LESS THAN O'USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.

OR o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54[30%adverse CNMT].SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.3.COLD LEG RECIRCULATION SWITCHOVER CRITERION 4~5.IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go'tO,.ECA-3

'<SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.

i' EOP: ES-3'POST-SGTR COOLDOWN USING BLOWDOWN'EV: 7 PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE LANT SUPERINTENDENT 4-i0-9G EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

l~i F.OP ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 2 of 10 A.PURPOSE-This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR.This recovery method depressurizes the ruptured S/G by draining via S/G blowdown.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS

-This procedure is entered from: a.E-3 STEAM GENERATOR TUBE RUPTURE, if plant staff selects the blowdown method.

E~as EOP ES-3'T1TLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should.be open AND monitored periodically.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+R/hr.1 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 2 Check If SI ACCUMs Should Be Isolated: a.Check the following:

o RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.o PRZR level-GREATER THAN 5%[30%adverse CNMT]b.Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves~MOV-841, MCC C position 12F~MOV-865, MCC D position 12C c.Close SI ACCUM outlet valves~ACCUM A, MOV-841~ACCUM B)MOV-865 c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.d.Locally reopen breakers for MOV-841 and MOV-865~ACCUM A, AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.

%~'I e~

EOP: ES-3'T1TLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

3 Verify Adequate Shutdown Margin a.Direct HP to sample RCS and ruptured S/G for boron concentration b.Verify boron concentration-GREATER THAN REQUIREMENTS OF FIGURE SDM b.Borate as necessary.

- - - - CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).NOTE: TDAFW pump flow control valves fail open on loss of IA.*4 Monitor Intact S/G Level: a.Narrow range level-GREATER THAN 5%[25%adverse CNMT]b.Control feed flow to maintain narrow, range level between 17%[25%,.adverse CNMT]and 50%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT]in intact S/G.b.IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1, a 4 EOP!ES-3'T!TLK: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.5 Initiate RCS Cooldown To 350'F: a.Establish and maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Dump steam to condenser from intact S/G b.Manually or locally dump steam~from intact S/G using S/G ARV.IF no intact S/G available, THEN perform the following:

o Use faulted S/G.-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step l.

P0 ES-3~2 T1TLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.*6 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage: a.Perform appropriate action(s)from table: PRZR LEVEL RUPTURED S/G NARROW RANGE LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13%[40%ADVERSE CNMT]o Increase RCS makeup flow o Depressurize RCS using Step 6b, Increase RCS o Increase RCS makeup flow makeup flow o Maintain RCS and ruptured S/G pressure equal BETWEEN 13%[40%ADVERSE CNMT]AND 50%BETWEEN 50%AND 75%[65%ADVERSE CNMT]GREATER THAN 75%[65%ADVERSE CNMT]Depressurize RCS using Step 6b.o Depressurize RCS using Step 6b.o Decrease RCS makeup flow o Decrease RCS makeup flow Energize PRZR heaters Energize PRZR heaters Energize PRZR heaters Maintain RCS and ruptured S/G pressure equal.Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal b.Use normal PRZR spray to obtain desired results for Step 6a b.IF letdown is in service, THEN use auxiliary spray (AOV-296).

IF NOT, THEN use one PRZR PORV.

EOP: ES-3'TITLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT)8 Check If RCS Cooldown Should Be Stopped: a.RCS cold leg temperatures

-LESS THAN 350'F a.Return to Step 3.b.Stop RCS cooldown c.Maintain RCS cold leg temperature

-LESS THAN 350'F*9 Monitor Ruptured S/G Narrow Range Level-LEVEL GREATER THAN 174[254 adverse CNMT]Refill ruptured S/G to 67%[55%adverse CNMT]using feed flow.IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G: o Ruptured S/G pressure decreases in an uncontrolled manner.-OR-o Ruptured S/G pressure increases to 1020 psig.NOTE: Blowdown from ruptured S/G may be stopped when RHR system is placed in service.10 Consult TSC To Determine Appropriate Procedure To Establish Blowdown From Ruptured S/G IF blowdown can NOT be initiated, THEN go to alternate post-SGTR cooldown procedure, ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, Step 1, OR ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1.

EOPs ES-3.2 TITLE~POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*11 Control RCS Makeup Flow And Letdown To Maintain PRZR Level: a.PRZR level-GREATER THAN 13%[40%adverse CNMT]b.PRZR level-LESS THAN 75%[65%adverse CNMT]a.Increase RCS makeup flow as necessary and go to Step 12.b.Decreases RCS makeup flow to decrease level and go to Step 13.NOTE: The upper head region may void during depressurization if RCPs are not running.This may result in a rapidly increasing PRZR level.*12 Depressurize RCS To Minimize RCS-To-Secondarjj Leakage: a.Depressurize using normal PRZR spray a.IF letdown is in service, TBEN depressurize using auxiliary spray valve (AOV-296).

IF NOT, THEN use one PRZR PORV~b.Energize PRZR heaters as necessary c.Maintain RCS pressure at ruptured S/G pressure d.Maintain RCS subcooling based on core exit T/Cs-GREATER THAN O'F USING FIGURE MIN SUBCOOLING

EOP: ES-3'T!TLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*13 Monitor RCP Operation:

a.RCPs-ANY RUNNING b.Check the following:

o RCP¹1 seal D/P-LESS THAN 220 PSID a.Go to Step 14.b.Go to Step 14.-OR-o Check RCP seal leakage-LESS THAN 0.25 GPM c.Stop affected RCP(s)14 Check If RHR Normal Cooling Can Be Established:

a.RCS cold leg temperature

-LESS THAN 350'F a.Return to Step 9.b.RCS pressure-LESS THAN 400 psig[300 psig adverse CNMT]c.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)d.Establish RHR normal cooling (Refer to Attachment RHR COOL)b.Return to Step 9.c.IF RCS overpressure protection system can NOT be placed in service, THEN notify TSC of potential Tech Spec violation if RHR system is placed in service.

I' EOP: ES-3~2 TITLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED'I 15 Continue RCS Cooldown To Cold Shutdown: a.Maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Use RHR System c.Dump steam to condenser from intact S/G c.Manually or locally dump steam using intact S/G ARV.IF no intact S/G available and RHR system NOT in service, THEN perform the following:

o Use faulted S/G.-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOIANT-SUBCOOLED RECOVERY DESIRED, Step l.16 Check Core Exit T/Cs-LESS THAN 200'F Return to Step 9.17 Evaluate Long Term Plant Status: a.Maintain cold shutdown conditions

-(Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)b.Consult TSC-END-I; EOP: ES-3'POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 1 of 1 ES-3.2 APPENDIX LIST TITLE 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLING 3)FIGURE SDM 4)ATTACHMENT RHR COOL 5)FOLDOUT PAGES I.

EOP: ES-3'POST-SGTR COOLDOWN USING BLOWDOWN.REV: 7 PAGE 1 of 1 RED PATH

SUMMARY

a.SUBCRITICALITY

-Nuclear power greater than 54 b.CORE COOLING-Core exit T/Cs greater than 1200'F-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs)less than 434[464 adverse CNMT]c.HEAT SINK-Narrow range level in all S/Gs less than 54[254 adverse CNMT]AND total feedwater flow less than 200 gpm d.INTEGRITY-Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temper'ature less than 285'F e.CONTAINMENT

-CNMT pressure greater than 60 psig

EOP: ES-3.2 TITLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature Fro'm Figure Below[-]Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700'1600 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVERSE GNAT NORNL CNNT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE

('F)

~I EOP: ES-3.2 T1TLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 1 of 1 BORON CONCENTRATION (PPH)1800 FIGURE SDM 1600 BORON INCREMENTS 20 PPH 1400 1200 1000'DEQUATE SDH 100 PPM CONSERVATISM INCLUDEDSOO 600 400 BORATE 200 BURNUP INCREMENTS 100 HWD/HTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)NOTE: To obtain core burnup, use PPCS turn'n code BURNUP.

l' EOP: ES-3'TiTLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 1 of 1 FOLDOUT PAGE 1~SI REINITIATION CRITERIA IF either condition listed below occurs, THEN operate SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1: o RCS subcooling based on core exit T/Cs-LESS THAN O'USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.

OR 2~o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54[304 adverse CNMT].SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.3.COLD LEG RECIRCULATION SWITCHOVER CRITERION 4~5~IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner~O IF any intact S/G has abnormal radiation,'HEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.

k/~V EOP: ES-3.3 T!TLE$POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 12 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: ES-3.3 TITLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 2 of 12 A.PURPOSE-This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR.This recovery method depressurizes the ruptured S/G by dumping steam.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS

-This procedure is entered from: a.E-3 STEAM GENERATOR TUBE RUPTURE, if plant staff selects steam dump method.b~ES 3~2 g POST SGTR COOLDOWN US ING BLOWDOWN g when blowdown is not available and plant staff selects steam dump method.

~4*P~I EOP: ES-3'T!TLE!POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 3 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION o STEAM SHOULD NOT BE RELEASED FROM ANY RUPTURED S/G IF WATER MAY EXIST IN ITS STEAMLINE.

o AN OFFSITE DOSE EVALUATION SHOULD BE COMPLETED PRIOR TO USING THIS PROCEDURE.

NOTE: o FOLDOUT page should be open AND monitored periodically.

o Adverse CNMT value's should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+R/hr.1 Energy.ze PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure

EOP: ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 4 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check If SI ACCUMs Should Be Isolated: a.Check the following:

o RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.o PRZR level-GREATER THAN 5%[30%adverse CNMT]b.Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves~MOV-841, MCC C position 12F~MOV-865, MCC D position 12C c.Close SI ACCUM outlet valves~ACCUM A, MOV-841~ACCUM B, MOV-865 d.Locally reopen breakers for MOV-841 and MOV-865 c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.~ACCUM A, AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.

EOP: ES-3'T!TLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 5 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

=3 Verify Adequate Shutdown Margin a.Direct HP to sample RCS and ruptured S/G for boron concentration b.Verify boron concentration-GREATER THAN REQUIREMENTS OF FIGURE SDM b.Borate as necessary.

- - - - CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).NOTE: TDAFW pump flow control valves fail open on loss of IA.*4 Monitor Intact S/G Level: a.Narrow range level-GREATER THAN 5%[25%adverse CNMT]b.Control feed flow to maintain narrow range level between 17%[25%'dverse CNMT]and 50$a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT]in intact S/G.b.IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.

.t=,~

EOP: ES-3'POST-SGTR COOLDOWN USING STEAM'UMP REV: 7 PAGE 6 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.5 Initiate RCS Cooldown To 350'F: a.Establish and maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Dump steam to condenser from intact S/G b.Manually or locally dump steam from intact S/G using S/G ARV.IF no intact S/G available, THEN perform the following:

o Use faulted S/G.-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.

4 EOP$ES-3'ZLTLE$POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 7 of 12-STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.*6 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage: a.Perform appropriate action(s)from table: PRZR LEVEL RUPTURED S/G NARROW RANGE LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13$[40%ADVERSE CNMT]o Increase RCS makeup flow o Depressurize RCS using Step 6b.Increase RCS o Increase RCS makeup flow makeup flow o Maintain RCS and ruptured S/G pressure equal BETWEEN 13%[40%ADVERSE CNMT]AND 50%BETWEEN 50%AND 75%[65%ADVERSE CNMT]GREATER THAN 75%[65%ADVERSE CNMT]Depressurize RCS using Step 6b.o Depressurize RCS using Step 6b.o Decrease RCS makeup flow o Decrease RCS makeup flow Energize PRZR heaters Energize PRZR heaters Energize PRZR heaters Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal b.Use normal PRZR spray to obtain desired results for Step 6a b.IF letdown is in service, THEN use auxiliary spray (AOV-296).

IF NOT, THEN use one PRER PORV.

1 EOP: ES-3'T!TLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 8 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY.BURPING VCT)8 Check If RCS Cooldown Should Be Stopped: a.RCS cold leg temperatures

-LESS THAN 350'F a.Return to Step 3, b.Stop RCS cooldown c.Maintain RCS cold leg temperature

-LESS THAN 350'F*9 Monitor Ruptured S/G Narrow Range Level-LEVEL GREATER THAN 174[254 adverse CNMT]Refill ruptured S/G to 67%[55%adverse CNMT]using feed flow.IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G: o Ruptured S/G pressure decreases in an uncontrolled manner.-OR-o Ruptured S/G pressure increases to 1020 psig.

C EOP!ES-3'TITLE!POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 9 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION RUPTURED S/G PRESSURE MAY DECREASE RAPIDLY WHEN STEAM IS RELEASED.NOTE: Steam release from ruptured S/G may be stopped when RHR System is in service.10 Initiate Cooldown Of Ruptured S/G: a.Verify condenser available:

o Intact S/G MSIV-OPEN o Annunciator G-15, STEAM DUMP ARMED-LIT a.Manually or locally dump steam using ruptured S/G ARV and go to Step 11.b.Dispatch AO to locally open ruptured S/G MSIV bypass valve c.Dump steam to condenser using steam dump pressure controller

ll Control RCS Makeup Flow And Letdown To Maintain PRZR Level: a.PRZR level-GREATER THAN 13%[40%adverse CNMT]b.PRZR4~level

-LESS THAN 75%[65%adverse'CNMT]

a.Increase RCS makeup flow as necessary and go to Step 12.b.Decrease RCS makeup flow to decrease level and go to Step 13.

'I~

EOP ES-3'TITLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 10 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The upper head region may void during depressurization if RCPs are not running.This may result in a rapidly increasing PRZR level.*12 Depressurize RCS To Minimize RCS-To-Secondary Leakage: a.Depressurize using normal PRZR spray associated with running RCP a.IF letdown is in service, THEN depressurize using auxiliary spray valve (AOV-296).

IF NOT, THEN use one PRZR PORV.b, Energize PRZR heaters as necessary c.Maintain RCS pressure at ruptured S/G pressure d.Maintain RCS subcooling based on core exit T/Cs-GREATER THAN O'F USING FIGURE MIN SUBCOOLING

13 Monitor RCP Operation:

a.RCPs-ANY RUNNING b.Check the following:

o RCP¹1 seal D/P-LESS THAN 220 PSID a.Go to Step 14.b.Go to Step 14.-OR-o Check RCP seal leakage-LESS THAN 0.25 GPM c.Stop affected RCP(s)

EOP: ES-3'T!TLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 11 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If RHR Normal Cooling Can Be Established a.RCS cold leg temperature

-LESS THAN 350'F a.Return to Step 9.b.RCS pressure-LESS THAN 400 psig[300 psig adverse CNMTj c.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)d.Establish RHR normal cooling (Refer to Attachment RHR COOL)b.Return to Step 9.c.IF RCS overpressure protection system can NOT be placed in service, THEN notify TSC of potential Tech Spec violation if RHR system is placed in service.15 Continue RCS Cooldown To Cold Shutdown: a.Maintain co'oldown rate in RCS cold legs-LESS THAN 100'F/HR b.Use RHR System c.Dump steam to condenser from intact S/G c.Manually or locally dump steam using intact S/G ARV IF no intact S/G available and RHR system NOT in service, THEN perform the following:

o Use faulted S/G.-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.

ES-3'TLTLE0 POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 12 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check Core Exit T/Cs-LESS THAN 200'F Return to Step 9.17 Evaluate Long Term Plant Status: a.Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)b.Consult TSC-END-e EOP!ES-3'TITLE!POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 1 ES-3.3 APPENDIX LIST TITLE 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLING 3)FIGURE SDM 4)ATTACHMENT RHR COOL 5)FOLDOUT PAGES

ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 1 RED PATH SUMl6&Y a.SUBCRITICALITY

-Nuclear power greater than 54 b.CORE COOLING-Core exit T/Cs greater than 1200'F-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs)less than 434[464 adverse CNMT]c.HEAT SINK-Narrow range level in all S/Gs less than 54[254 adverse CNMT]AND total feedwater flow less than 200 gpm d.INTEGRITY-Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F e.CONTAINMENT

-CNMT pressure greater than 60 psig Cl EOP: ES-3'T!TLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Suhcooling Margin=Saturation Temperature From Figure Below[-]Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVERSE CNMT NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT.SATURATION TEMPERATURE

('F)

EOP!ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 1 BORON CONCENTRATION (PPH)1800 FIGURE SDM 1600 BORON INCREMENTS 20 PPH 1400 1200 1000 ADEQUATE SDH 100 PPH CONSERVATISM INCLUDED800 600 400 BORATE 200 BURNUP INCREMENTS 100 HWD/HTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (MWD/HTU)NOTE: To obtain-core burnup, use PPCS turn on code BURNUP.

EOP: ES-3'TITLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 1 FOLDOUT PAGE 1~2~SI REINITIATION CRITERIA IF either condition listed below occurs, THEN operate SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1: o RCS subcooling based on core exit T/Cs-LESS THAN O'USING RE{}UIREMENTS OF FIGURE MIN SUBCOOLING.

OR o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%[30%adverse CNMT].SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has.not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.3~COLD LEG RECIRCULATION SWITCHOVER CRITERION 4~5.IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled maniier~O IF any intact S/G has abnormal radiation, THEN go.,to'ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.

, jL P t~~

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