ML17262A349
| ML17262A349 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/20/1990 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17262A347 | List: |
| References | |
| AP-RCS.3, NUDOCS 9102070081 | |
| Download: ML17262A349 (206) | |
Text
ECP: TITLE: REV: 5 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 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:
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REV: 5 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 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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TITLE: REV 5 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 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:
- b. RCS activity - GREATER THAN b. IP normal activity verified, NORMAL (Check with HP THEN direct I8C to check Department for normal activity) 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- a. Place AOV-244 in bypass DIVERT VLV CATION DEBOR DI position.
AOV-244 IN BYPASS POSITION
- b. Place PCV-135 to manual AND ad)ust as necessary - TO CONTROL LETDOWN PRESSURE
- 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
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EOP.: LITLE: REV' AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 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 Refer to EPIP 1-0, GINNA STATION Letdown Line LESS THAN EVENT EVALUATION AND 200 MR/HR ABOVE BACKGROUND 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 IF DI efficiency is NOT Letdown DI DECONTAMINATION acceptable, THEN place a new mixed FACTOR GREATER THAN 10 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:
IF shutdown is required, THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.
o Continued plant power operation
- ALLOWED, REFER TO TECHNICAL SPECIFICATION SECTION 3.1.4
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EOP:
REV: 5 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 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- b. IF Aux Bldg radiation levels NORMAL (Check with HP for indicate above normal, THEN normal readings) 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-
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EOP:
REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN 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:
T!TLE REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN 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, that a when natural circulation cooldown it has been determined is required.
- 2) ECA-0 when
', has been ALL it LOSS OF AC POWER RECOVERY WITHOUT determined that a SI REQUIRED/
natural circulation cooldown is required.
- 3) Other normal operating procedures 'when a natural circulation cooldown is required.
'r EOP: T1TLE:
REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN 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 a. Go to Step 2.
starting an RCP:
o Bus 11A or 11B energiz.ed o Refer to Attachment RCP START
- b. Start one RCP
- c. Any RCP - RUNNING c. Go to Step 2.
- d. Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITION
EOP s T!TLE:
REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN 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
o Level - GREATER THAN 20$
- 1) Ensure BA transfer pumps and
-OR- RMW pumps running.
o Level - STABLE OR INCREASING 2) Place RMW,flow control valve HCV-ill in MANUAL and increase RNW flow.
- 3) Increase boric acid flow as necessary.
EOP:
REV' ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 5 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check Charging Pump Suction Aligned To VCT:
- a. Check VCT level: a. IF VCT level can NOT be maintained greater than 5%, THEN o Level - GREATER THAN 20% perform the following:
o VCT makeup system - AVAILABLE 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: b. Manually align valves as necessary.
o LCV-112C - OPEN o LCV-112B - CLOSED 4 Borate RCS To Cold Shutdown Boron Concentration (Refer to Figure SDM) 5 Establish Maximum Rx Vessel Start fans as necessary.
Head Cooling:
o Check control rod shroud fans (45,kw) - BOTH RUNNING o Check one Rx compartment cooling fan (23 kw)- RUNNING
EOP:
REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 6 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Verify Adequate Shutdown Margin
~ RCS loop A
~ RCS loop B
~ PRZR
- b. Verify boron concentration- b. Perform the following:
GREATER -THAN REQUIREMENTS OF FIGURE SDM 1) Maintain RCS average temperature greater than 500'F until adequate SDM established.
- 2) Continue to borate as necessary.
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EOP: T]ILE:
REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN 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 a. Manually or locally dump steam using S/G ARVs.
- b. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 25'F/HR
- c. Maintain S/G narrow range level c. Control feed flow as necessary.
BETWEEN 17$ AND 39%
- 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 Return to Step 7.
Temperatures LESS THAN 550'F
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EOP t TlTLE:
REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN 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 AOV-294 and normal PRZR spray valves.
closing normal charging valve 9 Depressurize RCS To 1950 PSIG:
- a. Check letdown - IN SERVICE 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 10.
- b. Depressurize RCS using auxiliary b. IF auxiliary spray valve NOT spray valve (AOV-296) available, THEN use one PRZR PORV.
FOP: T!TLE.
REV: 5 ES-0 ' NATURAL CIRCULATION COOLDONN PAGE 9 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- * * * * * * * * * * * * * * * * * * * * * * * *
- 4' *************
CAUTION SI ACTUATION CIRCUITS WILL AUTOMATICALLYUNBLOCK IF PRZR PRESSURE INCREASES TO GREATER THAN 1992 PSIG.
- 10 Monitor SI Block Criteria:
- a. Check the following: a. Return to Step 9.
o PRZR pressure - LESS THAN 1950 PSIG
-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 c. Maintain PRZR pressure greater status light - LIT 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- a. Perform the following:
BOTH RUNNING
- 2) Go to Step 12.
l O' T1TLE!
REV 5 ES-0.2 NATURAL CIRCULATION COOLDOWN 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 $ TITLE$
REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN 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 AOV-294 and normal PRZR spray valves, closing normal charging valve 14 Initiate RCS Depressurization:
- a. Check letdown - IN SERVICE 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. Depressurize RCS using auxiliary b. IF auxiliary spray valve NOT spray valve (AOV-296) available, THEN use one PRZR PORV.
- c. Plot:" RCS temperature and pressure on curve selected in Step 11 hourly
EOP:
REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 12 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Continue Cooldown And Depressurization:
- a. Check RCS cold leg temperature- a. Stabilize RCS temperature and go GREATER THAN 335'F to Step 15c.
- b. Maintain cooldown rate in RCS cold legs - LESS THAN 25'F/HR
- c. Maintain RCS temperature and c. Control RCS pressure as pressure within limits of Figure neces'sary to restore pressure/
determined previously 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 Repressurize RCS within allowable Reactor Vessel: limits and continue cooldown.
o PRZR level - NO UNEXPECTED LARGE IF RCS depressurization must VARIATIONS continue, THEN go to ES-0.3, NATURAL CIRCULATION COOLDOWN WITH o RVLIS level (no RCPs) - GREATER STEAM VOID IN VESSEL.
THAN 95%
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EOP t REV: 5 ES-0 ' NATURAL CIRCULATION COOLDONN PAGE 13 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Check If SI Isolated:
ACCUMs Should Be
- a. RCS pressure - LESS THAN a. Continue with Step 19. WHEN RCS 1500 PSIG pressure is less than 1500 psig, THEN do Steps 18b through d.
~ 'MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- c. Close SI ACCUM discharge valves c. IF any valve can NOT be closed, THEN perform the following:
~ ACCUM A) MOV-841
~ ACCUM B, MOV-865 1) Dispatch personnel to locally close valves, as necessary.
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
- 2) Open HCV-945.
- d. Locally open breakers for MOV-841 and MOV-865
EOP:
REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN 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 Perform the following:
Injection Flow And Labyrinth Seal D/P: o Adjust charging flow to REGEN Hx (HCV-142) as necessary.
o Labyrinth seal D/P to each RCP-GREATER THAN 15 INCHES OF WATER -OR-o Seal injection flow to each RCP o Dispatch AO to adjust seal
- GREATER THAN 6 GPM injection needle valves if necessary.
~ RCP A, V-300A
~ RCP B, V-300B
4 EOP:
REV' ES-0 ' NATURAL CIRCULATION COOLDOWN 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 a. Return to Step 15.
THAN 350'F b, RCS pressure - LESS THAN b. Stabilize RCS temperature and 1500 PSIG return to Step 14.
- c. Lock out SI system as follows:
- 1) Place all SI pump switches in PULL STOP
- 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
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EOPt TITLE:
REV 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 16 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Check Can Be IfEstablished:
RHR Normal Cooling
- b. Verify all SI pump switches in b. Return to Step 21.
PULL STOP
- d. Place RCS overpressure d. IF RCS overpressure protection protection system in service system can NOT be placed in (Refer to 0-7, ALIGNMENT AND service, THEN consult Plant OPERATION OF THE REACTOR VESSEL staff to determine if RHR normal OVERPRESSURE PROTECTION SYSTEM) cooling should be established and go to Step 23.
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: T1TLE:
REV: 5 ES-O.' NATURAL CIRCULATION COOLDOWN 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:
~ Core exit T/Cs Return to Step 23.
~ Upper head T/Cs
~ RCS hot leg temperature
~ RCS cold leg temperature
- b. Check control rod shroud fan b. Consult Plant staff to determine status - BOTH RUNNING DURING wait period for upper head COOLDOWN cooling.
- c. Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD SHUTDOWN)
-END-
I EOP; T1TLE REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN 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:
REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN 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! TiTLE:
REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 OI woo SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOL ING 600 ADVERSE CNMT REGION 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0
200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
EOP: T!TLE:
REV 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPH) 1800 BORON INCREHENTS 20 PPH 1600 1400 ADEQUATE SDH 1200 100 PPH CONS ERVATISH INCLUDED 1000 8OO 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 T!TLE:
REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 FIGURE NAT CIRC C D WITHOUT SHROUD FANS RCS PRESSURE (PSIG) 2500 2400 RCS PRESSURE NORHAL INCREHENTS RCS temp RANGE 2300 20 PSIG for S/G SI 2200 (514 psig) 2100 SI UNBLOCK 2000 1900 1800 1700 1600 1500 [1] Wait 11 hrs before decreasing RCS pressure 1400 less than 1600 psig 1300 1200 1100 1000 900 800 700 [2] Wait 29 hrs before decreasing RCS pressure 600 less than 350 psig to prevent boiling in 500 upper head 400 300 200 TEHPERATURE 100 INCREHENTS 10'F 0 50 100 150 '200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEHPERATURE ('F)
EOP: TlTLE:
REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 1 of I FIGURE NAT CIRC C D WITH SHROUD FANS RCS PRESSURE (PSIG) 2500 2400 RCS PRESSURE INCREMENTS RCS temp 2300 for S/G SI 20 PSIG 2200 (514 psig) 2100 SI UNBLOCK 2000 1900 1800 A
1700 .V 0
1600 I
D 1500 1400 NORMAL 1300 RANGE 1200 1100 1000 900 800 700 600 500 400 300 200 TEMPERATURE ioo INCREMENTS 10'F 0 50 100 150 200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEMPERATURE ('F)
EOP: TlTLE:
REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 FOLDOUT PAGE 1~ 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 2 ~ 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: TITLE:
REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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: TITLE:
REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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: TITLE:
REV 10 ES-1s2 POST. LOCA COOLDOWN AND DEPRESSURIZATION 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 Be If RHR Stopped:
Pumps Should
- a. Check RCS pressure: a. Go to Step 2.
- 1) Pressure - GREATER THAN 250 psig [465 psig adverse CNMT]
- 2) Pressure - STABLE OR INCREASING
- b. Stop RHR pumps and place AUTO
EOP:
REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 4 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2 Monitor All AC Busses-BUSSES ENERGIZED BY OFFSITE POWER a. IF any AC emergency bus normal feed breaker open, THEN ensure o Normal feed breakers to all 480 associated D/G breaker closed.
volt busses - CLOSED
- b. Perform the following, as o 480 bus voltage - GREATER THAN necessary:
420 VOLTS
- 1) Close non-safeguards bus tie o Emergency D/G output breakers breakers:
OPEN
~ 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:
REV 10 ES-1 ' POST LOCA COOLDOWN AND DEPRESSURIZATION 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 RCP ¹1 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 b. IF LCV-112B can NOT be opened, RWST' THEN perform the following:
LCV-112B - OPEN 1) Verify charging pump A NOT running and place in PULL o LCV-112C - CLOSED STOP.
- 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).
- c. Start charging pumps as necessary (75 kw each) and establish 75 gpm total charging flow
~ Charging line flow
~ Seal injection flow
EOP! TITLE!
REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 6 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Establish Condenser Steam Dump Pressure Control:
- a. Verify condenser available: a. Place S/G ARV controllers in AUTO at desired pressure and go o Any MSIV - OPEN to Step 5.
o Annunciator G-15, STEAM DUMP ARMED - LIT
- 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 a. Maintain total feed flow greater THAN 5S [25$ adverse CNMT) than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT] in at least one S/G.
- b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase in an
[25% adverse CNMT] and 50% uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
EOP:
REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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 c. Manually or locally dump steam intact S/G(s) using intact S/Gs ARV.
7 Check RCS Subcooling'ased On Manually operate SI pumps as Core Exit T/Cs - GREATER THAN necessary and go to Step 19.
O'F USING FIGURE MIN SUBCOOLING 8 Check SI and RHR Pump Status: Go to Step 15.
o SI pumps - ANY RUNNING
-OR-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: TLTLE:
REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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 a. Depressurize using one PRZR spray if available PORV. IF IA NOT available, THEN refer to Attachment N2 PORVS.
IF no PORV available, THEN use auxiliary spray valve (AOV-296).
- b. PRZR level - GREATER THAN 13% b. Continue with Step ll. WHEN
[40$ adverse CNMT] level greater than 13% [40$
adverse CNMTJ, THEN stop RCS depressurization.
- c. Stop RCS depressurization
4 EOP: T1TLE:
REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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 Started:
If An RCP Should Be
- b. RCS subcooling based on core b. Go to Step 19, exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING
- c. PRZR level - GREATER THAN 13% c. Return to Step 10.
[40$ adverse CNMT]
- d. Try to start an RCP d. IF IA to CNMT available, THEN ensure at least one control rod
- 1) Establish conditions for shroud fan running (45 kw each).
starting an RCP o Bus 11A or 11B energized o Refer to Attachment RCP START
- 2) Start one RCP
I I EOP:
REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 10 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Pumps If One Of Three SI Should Be Stopped:
- a. Three SI pumps - RUNNING a. Go to Step 13.
- b. RCS subcooling based on core b. IF RCS hot leg temperatures exit T/Cs - GREATER THAN 35'F greater than 325'F [270'F
[90'F adverse CNMT] USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING 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. Check PRZR level - GREATER THAN c. Do NOT stop SI pump. Return to 13% [40% adverse CNMT] Step 10.
- d. Stop one SI pump
EOP! TlTLE~
REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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 a. Go to Step 14.
- b. Determine required RCS subcooling from table:
Charging Pump RCS Subcooling Criteria Availability NONE 120'F [200'F adverse CNMT]
ONE 115'F [190'F adverse CNMT]
105'F [180'F adverse CNMT]
THREE 100'F [175'F adverse CNMT)
- c. RCS subcooling based on core c. IF RCS hot leg temperatures exit T/Cs - GREATER THAN VALUE greater than 325'F [270'F FROM TABLE ABOVE USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING 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 13d. IF no RHR pump can be operated in injection mode, THEN go to Step 19.
- d. PRZR level - GREATER THAN 13% d. Do NOT stop SI pump. Return to
[40% adverse CNMT] Step 10.
- e. Stop one SI pump
1 TITLEt EOP:
REV'0 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 12 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check Be If Last Stopped:
SI Pump Should
- a. One SI pump - RUNNING a.'F any RHR pump running in injection mode, THEN go to Step 19. IF NOT, THEN go to Step 15.
- b. Determine required RCS subcooling from table:
Charging Pump RCS Subcooling Criteria Availability NONE Insufficient subcooling to stop SI pump.
ONE 255'F [295'F adverse CNMT]
TWO 235'F [285'F adverse CNMT]
THREE 210'F [270'F adverse CNMT]
- c. RCS subcooling based on core c. IF RCS hot leg temperatures exit T/Cs - GREATER THAN VALUE greater than 325'F [270'F FROM TABLE ABOVE USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING 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% d. Do NOT stop SI pump. Return to
[40% adverse CNMT] Step 10.
- e. Stop running SI pump
EOP: TITLE$
REV 10 ES-1 ' POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 13 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Check If Charging Maintain Be Controlled To Flow Should PRZR Level:
- a. Check RHR pumps - RUNNING IN a. Start charging pump and control INJECTION MODE charging flow to maintain PRZR level and go to Step 16.
- b. Go to Step 19 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:
REV: 10 ES-1 ' POST LOCA COOLDOWN AND DEPRESSURIZATION 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 AOV-294 and normal PRZR spray valves.
closing normal charging valve 17 Depressurize RCS To Minimize RCS Subcooling:
- a. Depressurize using normal PRZR a. IF normal spray NOT available, spray if available THEN use one PRZR PORV.
NOT available, THEN IF IA refer to Attachment N2 PORVS.
IF no PRZR PORV available, THEN use auxiliary spray valve (AOV-296).
- b. Energize PRZR heaters as necessary
- c. Depressurize RCS until EITHER of the following conditions satisfied:
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: T!TLE REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 15 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify Adequate Shutdown Margin
- b. Verify boron concentration- b. Borate as necessary.
GREATER THAN REQUIREMENTS OF FIGURE SDM
- 19 Monitor SI Reinitiation Criteria:
- a. RCS subcooling based on core a. Manually operate SI pumps as exit T/Cs - GREATER THAN O' necessary and go to Step 20.
USING FIGURE MIN SUBCOOLING b, PRZR level - GREATER THAN 5% b. Manually operate SI pumps as
[30% adverse CNMT] necessary and return to Step 10.
EOP $ T1TLE$
REV 10 ES-1. 2 . POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 16 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check Isolated:
If SI ACCUMs Should Be
- a. RCS subcooling based on core a. IF both RCS hot leg temperatures exit T/Cs - GREATER THAN O' less than 400'F, THEN go to USING FIGURE MIN SUBCOOLING Step 20c.
IF NOT, THEN go to Step 21.
- b. PRZR level - GREATER THAN 5% b. Return to Step 10.
[30% adverse CNMT]
~ MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- d. Close SI ACCUM discharge valves d. Vent any unisolated ACCUMs:
~ ACCUM A, MOV-841 1) Open vent valves for
~ ACCUM B, MOV-865 unisolated SI ACCUMs.
~ ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
- e. Locally reopen breakers for MOV-841 and MOV-865
EOP:
REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 17 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check If Emergency Should Be Stopped:
D/Gs
- a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).
o Emergency D/G output breakers OPEN 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- a. Manually start pumps as power RUNNING supply permits (258 kw per pump). IF less than two SW pumps can be operated, THEN go to Step 23.
- b. Verify AUX BLDG SW isolation b. Establish SW to AUX BLDG (Refer valves - OPEN to Attachment AUX BLDG SW).
~ MOV-4615 and MOV-4734
~ MOV-4616 and MOV-4735
- c. Verify CNMT RECIRC fan c. Dispatch AO to locally throttle annunciator C-2, HIGH flow to CCW Hx to between TEMPERATURE ALARM - EXTINGUISHED 5000 gpm and 6000 gpm total flow.
EOP: T!TLE0 REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 18 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check RCP Cooling Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).
- a. Check CCW to RCPs 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:
REV 10 ES-1 ' POST LOCA COOLDOWN AND DEPRESSURIZATION 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- a. Restore power to instrument bus ENERGIZED D from MCC B or MCC A (maintenance supply).
- b. Verify RCP ¹1 seal outlet b. Go to Step 25.
temperature - LESS THAN 235'F
- c. Verify RCP seal outlet valves c. Manually open valves as OPEN necessary.
~ AOV-270A
~ AOV-270B
- d. Reset both trains of XY relays for RCP seal return isolation valve MOV-313
- e. Open RCP seal return isolation e. Perform the following:
valve MOV-313
- 1) Place MOV-313 switch to OPEN,
- LESS THAN 5.5 GPM 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
EOP: TITLE:
REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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 a. Go to Step 25e.
DEENERGIZED b, Check intermediate range flux- b. Perform the following:
EITHER CHANNEL LESS THAN 10 10 AMPS 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: c. Continue with Step 26. WHEN either condition met, THEN do o Both intermediate range Steps 25d and e.
channels - LESS THAN 10 AMPS
-OR-o Greater than 20 minutes since reactor trip
- d. Verify source range detectors- d. Manually energize source range ENERGIZED 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$ TITLE$
REV 10 ES-1 ' POST LOCA COOLDOWN AND DEPRESSURIZATION 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:
- 2) Verify at least one control 2) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
- 3) Verify one Rx compartment 3) Perform the following:
cooling fan - RUNNING 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 COMPLETE
EOP: TITLE:
REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 22 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Check If RCPs Must Be Stopped:
- a. RCPs - ANY RUNNING a. Go to Step 28.
- b. Check the following: b. Go to Step 28.
o RCP ¹1 seal D/P - LESS THAN 220 PSID
-OR-o RCP ¹1 seal leakoff - LESS THAN 0.25 GPM
- c. Stop affected RCP(s) 28 Check Condenser Steam Dump Use intact S/G 'ARV for RCS Available CONDENSER VACUUM temperature control.
GREATER THAN 20 INCHES HG 29 Check Can Be IfEstablished:
RHR Normal Cooling
- a. RCS cold leg temperature - LESS a. Return to Step 1.
THAN 350'F
- b. RCS pressure - LESS THAN b. Go to Step 30.
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)
EOP:, T!TLE:
REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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:
)
- b. Hydrogen concentration - LESS b. Consult TSC to determine if THAN 0.5% hydrogen recombiners should be placed in service.
31 Check Core Exit T/Cs - LESS Return to Step l.
THAN 200'F 32 Evaluate Long Term Plant Status:
- a. Maintain cold shutdown conditions
- b. Consult TSC
-END-
EOP T!TLEI REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 1 ES-1.2 APPENDIX LIST TITLE PAGES
- 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
EOP: TITLE!
REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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: T!TLE:
REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core .Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOLING 600 ADVERSE CNMT REGION 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0
200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
1t EOP: TITLE:
REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPM) 1800 BORON INCREMENTS 20 PPM 1600 1400 ADEQUATE SDM 1200 100 PPM CONSERVATISM INCLUDED 1000 800 600 400 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: T!TLE0 REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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 TITLE:
REV: 6 ES-3 ~ 1 POST-SGTR COOLDOWN USING BACKFILL 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-REV 6 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL 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&,
staff selects backfill method.
if plant
- 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: T!TLE0 REV: 6 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL 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 TITLE:
REV: 6 ES-3.1- POST-SGTR COOLDOWN USING BACKFILL PAGE 4 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check Isolated:
If SI ACCUMs Should Be
- a. Check the following: a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED o RCS subcooling based on core RECOVERY DESIRED, Step 1.
exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 5S
[30% adverse CNMT)
~ MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- c. Close SI ACCUM outlet valves c. Vent any unisolated ACCUMs:
~ ACCUM A, MOV-841 1) Open vent valves for
~ ACCUM B, MOV-865 unisolated SI ACCUMs.
~ ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
- d. Locally reopen breakers for MOV-841 and MOV-865
I t EOP: TlTLE:
REV: 6 ES-F 1 POST-SGTR COOLDOWN USING BACKFILL E
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
- b. Verify boron concentration- b. Borate as necessary.
GREATER THAN REQUIREMENTS OF FIGURE SDM 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 a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT] in the intact S/G.
- b. Control feed flow to maintain b. IF narrow range level in the narrow range level between 17% intact S/G continues to increase
[25% adverse CNMT) and 50% in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.
S
-r
EOP: T1TLE!
REV: 6 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL 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 c. Manually or locally dump steam intact S/G 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 Refill ruptured S/G to 67% [55%
Range Level LEVEL GREATER adverse CNMT] using feed flow.
THAN 174 [254 adverse CNMT]
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:
REV: 6 ES-3 ' POST-SGTR COOLDOWN USING BACKFILL 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% a. Increase RCS makeup flow as
[40% adverse CNMT] .necessary and go to Step 8.
- b. PRZR level - LESS THAN 75% [65% b. Decrease RCS makeup flow to adverse CNMT] level and go to Step 10.
'ecrease 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 a. IF letdown is in service, THEN spray 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- c. Stop RCS depressurization.
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
EOP:
REV: 6 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL 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 Can Be IfEstablished:
RHR Normal Cooling
- a. RCS cold leg temperature - LESS a. Go to Step 11.
THAN, 350'F
- b. RCS pressure - LESS THAN b. Go to Step 11, 400 psig [300 psig adverse CNMT]
- c. Place RCS overpressure c. IF RCS overpressure protection protection system in service system can NOT be placed in (Refer to 0-7, ALIGNMENT AND service, THEN notify TSC of OPERATION OF THE REACTOR VESSEL potential Tech Spec violation if OVERPRESSURE PROTECTION SYSTEM) RHR system is placed in service.
- ll'onitor RCP Operation:
- a. RCPs - ANY RUNNING a. Go to Step 12.
- b. Check the folloving: b. Go to Step 12.
o RCP ¹1 seal D/P - LESS THAN 220 PSID
-OR-o Check RCP seal leakage - LESS THAN 0.25 GPM
- c. Stop affected RCP(s)
EOP:
REV: 6 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 9 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Core Exit T/Cs LESS Return to Step 3.
THAN 200'F 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:
REV' ES-3 ' POST-SGTR COOLDOWN USING BACKFILL
,PAGE 1 of 1 ES-3.1 APPENDIX LIST TITLE PAGES
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING
- 3) FIGURE SDM
- 4) ATTACHMENT RHR COOL
- 5) FOLDOUT
I a,g
EOP:
REV 6 ES-3 ' POST-SGTR COOLDOWN USING BACKFILL 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 exit T/Cs greater than 700'F AND
-OR-'ore 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:
REV: 6 ES-3 ' POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOL ING 600 ADVERSE CNHT REGION 500 400 300 200 NORMAL CNHT TEMPERATURE INCREMENTS 10'F 100 0
200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
l'~
~ ~
tl
EOP t T1TLE:
REV: 6 ES-F 1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPH) 1800 BORON INCREMENTS 20 PPM 1600 1400 ADEQUATE SDH 1200 100 PPH CONSERVATISM INCLUDED 1000 80O 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! TITLE:
REV: 6 ES-3 ~ 1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 FOLDOUT PAGE 1~ SI REINITIATION CRITERI 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].
2 ~ 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 IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
4 ~ 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).
- 5. 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 REV: 7 ES-3. 2 POST-SGTR COOLDOWN USING BLOWDOWN 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, selects the blowdown method.
if plant staff
E
~ as
EOP T1TLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN 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 Isolated:
If SI ACCUMs Should Be
- a. Check the following: a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED o RCS subcooling based on core RECOVERY DESIRED, Step 1.
exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 5%
[30% adverse CNMT]
~ MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- c. Close SI ACCUM outlet valves c. Vent any unisolated ACCUMs:
~ ACCUM A, MOV-841 1) Open vent valves for
~ ACCUM B) MOV-865 unisolated SI ACCUMs.
~ ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
- d. Locally reopen breakers for MOV-841 and MOV-865
% ~
'I e ~
EOP: T1TLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN 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
- b. Verify boron concentration- b. Borate as necessary.
GREATER THAN REQUIREMENTS OF FIGURE SDM 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 a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT] in intact S/G.
- b. Control feed flow to maintain b. IF narrow range level in the narrow, range level between 17% intact S/G continues to increase
[25%,. adverse CNMT] and 50% in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1,
a 4 EOP! T!TLK:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN 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 b. Manually or locally dump steam intact S/G ~
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.
P 0
T1TLE:
REV: 7 ES-3 2
~ POST-SGTR COOLDOWN USING BLOWDOWN 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 RUPTURED S/G NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13% o Increase RCS Increase RCS o Increase RCS
[40% ADVERSE CNMT] makeup flow makeup flow makeup flow o Depressurize o Maintain RCS RCS using and ruptured Step 6b, S/G pressure equal BETWEEN 13% Depressurize Energize Maintain RCS
[40% ADVERSE CNMT] RCS using PRZR and ruptured AND 50% Step 6b. heaters S/G pressure equal.
BETWEEN 50% AND 75% o Depressurize Energize Maintain RCS
[65% ADVERSE CNMT] RCS using PRZR and ruptured Step 6b. heaters S/G pressure equal o Decrease RCS makeup flow GREATER THAN 75% o Decrease RCS Energize Maintain RCS
[65% ADVERSE CNMT] makeup flow PRZR and ruptured heaters S/G pressure equal
- b. Use normal PRZR spray to obtain b. IF letdown is in service, THEN desired results for Step 6a use auxiliary spray (AOV-296).
IF NOT, THEN use one PRZR PORV.
EOP: TITLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN 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 Be If Stopped:
RCS Cooldown Should
- a. RCS cold leg temperatures - LESS a. Return to Step 3.
THAN 350'F
- b. Stop RCS cooldown
- c. Maintain RCS cold leg temperature - LESS THAN 350'F
- 9 Monitor Ruptured S/G Narrow Refill ruptured S/G to 67% [55%
Range Level - LEVEL GREATER adverse CNMT] using feed flow.
THAN 174 [254 adverse CNMT]
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 IF blowdown can NOT be initiated, Appropriate Procedure To THEN go to alternate post-SGTR Establish Blowdown From cooldown procedure, ES-3.1, Ruptured S/G POST-SGTR COOLDOWN USING BACKFILL, Step 1, OR ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1.
EOPs TITLE~
REV: 7 ES-3. 2 POST-SGTR COOLDOWN USING BLOWDOWN 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% a. Increase RCS makeup flow as
[40% adverse CNMT] necessary and go to Step 12.
- b. PRZR level - LESS THAN 75% [65% b. Decreases RCS makeup flow to adverse CNMT] 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 a. IF letdown is in service, TBEN spray 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: T!TLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13 Monitor RCP Operation:
- a. RCPs - ANY RUNNING a. Go to Step 14.
- b. Check the following: b. Go to Step 14.
o RCP ¹1 seal D/P - LESS THAN 220 PSID
-OR-o Check RCP seal leakage - LESS THAN 0.25 GPM
- c. Stop affected RCP(s) 14 Check Can Be IfEstablished:
RHR Normal Cooling
- a. RCS cold leg temperature - LESS a. Return to Step 9.
THAN 350'F
- b. RCS pressure - LESS THAN b. Return to Step 9.
400 psig [300 psig adverse CNMT]
- c. Place RCS overpressure c. IF RCS overpressure protection protection system in service system can NOT be placed in (Refer to 0-7, ALIGNMENT AND service, THEN notify TSC of OPERATION OF THE REACTOR VESSEL potential Tech Spec violation if OVERPRESSURE PROTECTION SYSTEM) RHR system is placed in service.
I' EOP: TITLE:
REV: 7 ES-3 ~ 2 POST-SGTR COOLDOWN USING BLOWDOWN 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 c. Manually or locally dump steam intact S/G 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 Return to Step 9.
THAN 200'F 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:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1 of 1 ES-3.2 APPENDIX LIST TITLE PAGES
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING
- 3) FIGURE SDM
- 4) ATTACHMENT RHR COOL
- 5) FOLDOUT
I.
EOP:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN.
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: TITLE:
REV: 7 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature Fro'm Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700
'1600 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 700 INADEQUATE SUBCOOLING 600 REGION ADVERSE GNAT 500 400 300 200 NORNL CNNT TEMPERATURE INCREMENTS 10'F 100 0
200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
I
~
EOP: T1TLE:
REV: 7 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPH) 1800 BORON INCREMENTS 20 PPH 1600 1400 1000'DEQUATE SDH 1200 100 PPM CONSERVATISM INCLUDED SOO 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: TiTLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN 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 o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54 [304 adverse CNMT].
2 ~ 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 IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
4 ~ 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).
5~ 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: T!TLE$
REV: 7 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 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: TITLE:
REV: 7 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 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 staff selects GENERATOR TUBE RUPTURE, steam dump method.
if plant b ~ ES 3 ~ 2 POST SGTR COOLDOWN US ING BLOWDOWNg plant staff g
when blowdown is not available and selects steam dump method.
~ 4
- P ~ I EOP: T!TLE!
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP 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:
REV: 7 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 4 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check Isolated:
If SI ACCUMs Should Be
- a. Check the following: a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED o RCS subcooling based on core RECOVERY DESIRED, Step l.
exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 5%
[30% adverse CNMT]
~ MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- c. Close SI ACCUM outlet valves c. Vent any unisolated ACCUMs:
~ ACCUM A, MOV-841 1) Open vent valves for
~ ACCUM B, MOV-865 unisolated SI ACCUMs.
~ ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
- d. Locally reopen breakers for MOV-841 and MOV-865
EOP: T!TLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP 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
- b. Verify boron concentration- b. Borate as necessary.
GREATER THAN REQUIREMENTS OF FIGURE SDM 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 a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT] in intact S/G.
- b. Control feed flow to maintain b. IF narrow range level in the narrow range level between 17% intact S/G continues to increase
[25%'dverse CNMT] and 50$ in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.
t =, ~
EOP:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM'UMP 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 b. Manually or locally dump steam intact S/G 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$ ZLTLE$
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP 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 RUPTURED S/G NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13$ o Increase RCS Increase RCS o Increase RCS
[40% ADVERSE CNMT] makeup flow makeup flow makeup flow o Depressurize o Maintain RCS RCS using and ruptured Step 6b. S/G pressure equal BETWEEN 13% Depressurize Energize Maintain RCS
[40% ADVERSE CNMT] RCS using PRZR and ruptured AND 50% Step 6b. heaters S/G pressure equal BETWEEN 50% AND 75% o Depressurize Energize Maintain RCS
[65% ADVERSE CNMT] RCS using PRZR and ruptured Step 6b. heaters S/G pressure equal o Decrease RCS makeup flow GREATER THAN 75% o Decrease RCS Energize Maintain RCS
[65% ADVERSE CNMT] makeup flow PRZR and ruptured heaters S/G pressure equal
- b. Use normal PRZR spray to obtain b. IF letdown is in service, THEN desired results for Step 6a use auxiliary spray (AOV-296).
IF NOT, THEN use one PRER PORV.
1 EOP: T!TLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP 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 Be If Stopped:
RCS Cooldown Should
- a. RCS cold leg temperatures - LESS a. Return to Step 3, THAN 350'F
- b. Stop RCS cooldown
- c. Maintain RCS cold leg temperature - LESS THAN 350'F
- 9 Monitor Ruptured S/G Narrow Refill ruptured S/G to 67% [55%
Range Level - LEVEL GREATER adverse CNMT] using feed flow.
THAN 174 [254 adverse CNMT]
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! TITLE!
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP 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: a. Manually or locally dump steam using ruptured S/G ARV and go to o Intact S/G MSIV - OPEN Step 11.
o Annunciator G-15, STEAM DUMP ARMED - LIT
- 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% a. Increase RCS makeup flow as
[40% adverse CNMT] necessary and go to Step 12.
- b. PRZR4~level - LESS THAN 75% [65% b. Decrease RCS makeup flow to adverse'CNMT] decrease level and go to Step 13.
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EOP TITLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 10 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The upper head region may void during depressurization if RCPs are level.
not running. This may result in a rapidly increasing PRZR
- 12 Depressurize RCS To Minimize RCS-To-Secondary Leakage:
- a. Depressurize using normal PRZR a. IF letdown is in service, THEN spray associated with running RCP 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 a. Go to Step 14.
- b. Check the following: b. Go to Step 14.
o RCP ¹1 seal D/P - LESS THAN 220 PSID
-OR-o Check RCP seal leakage - LESS THAN 0.25 GPM
- c. Stop affected RCP(s)
EOP: T!TLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 11 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check Can Be IfEstablished RHR Normal Cooling
- a. RCS cold leg temperature - LESS a. Return to Step 9.
THAN 350'F
- b. RCS pressure - LESS THAN b. Return to Step 9.
400 psig [300 psig adverse CNMTj
- c. Place RCS overpressure c. IF RCS overpressure protection protection system in service system can NOT be placed in (Refer to 0-7, ALIGNMENT AND service, THEN notify TSC of OPERATION OF THE REACTOR VESSEL potential Tech Spec violation if OVERPRESSURE PROTECTION SYSTEM) RHR system is placed in service.
- d. Establish RHR normal cooling (Refer to Attachment RHR COOL) 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 c. Manually or locally dump steam intact S/G 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.
TLTLE0 REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 12 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check Core Exit T/Cs LESS Return to Step 9.
THAN 200'F 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! TITLE!
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 ES-3.3 APPENDIX LIST TITLE PAGES
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING
- 3) FIGURE SDM
- 4) ATTACHMENT RHR COOL
- 5) FOLDOUT
REV: 7 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 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: T!TLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Suhcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOLING 600 REGION ADVERSE CNMT 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0
200 250 300 350 400 450 500 550 600 650 700 CORE EXIT. SATURATION TEMPERATURE ('F)
EOP!
REV: 7 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPH) 1800 BORON INCREMENTS 20 PPH 1600 1400 ADEQUATE SDH 1200 100 PPH CONSERVATISM INCLUDED 1000 800 600 400 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: TITLE:
REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP 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 RE{}UIREMENTS OF FIGURE MIN SUBCOOLING.
OR o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT].
2 ~ 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 IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
4 ~ 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).
- 5. 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.
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