ML17263A271

Rev 7 to EOP FR-C.2, Response to Degraded Core Cooling.

ML17263A271
Person / Time
Site:	Ginna
Issue date:	04/21/1993
From:	MARLOW T A ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A269	List: ML17263A268 ML17263A270 ML17263A271 ML17263A272 ML17263A273 ML17263A274 ML17263A275 ML17263A276
References
FR-C.2, NUDOCS 9305140049
Download: ML17263A271 (28)

Text

EOP: FR-CD 2 TITLE: RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 1 of 15 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY: 9305140049 930505 PDR'DOCK 05000244~F EOP: FR-C.2 RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 2 of 15 A.PURPOSE-This procedure provides actions to restore adequate core cooling.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS

-This procedure is entered from: a.F-0.2, CORE COOLING Critical Safety Function Status Tree, on any ORANGE condition.

FR-C.2 RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 3 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+"5 R/hr.1 Check RWST Level-GREATER THAN 284 Perform the following:

a.Ensure SI system aligned for cold leg recirculation using Steps 1 through 11 of ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.

b.Go to Step 4.

J EOP: FR-C.2 TITLE: RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 4 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Verify SI Pump And RHR Pump Emergency Alignment:

a.RHR pump discharge to Rx vessel deluge-OPEN~MOV-852A~MOV-852B a.Ensure at least one valve open.b.Verify SI pump C-RUNNING b.Manually start pump on available bus.c.Verify SI pump A-RUNNING d.Verify SI pump B-RUNNING c.Perform the following:

1)Ensure SI pumps B and C running.2)Ensure SI pump C aligned to discharge line A: o MOV-871B closed o MOV-871A open 3)Go to Step 3.d.Perform the following:

1)Ensure SI pumps A and C running.2)Ensure SI pump C aligned to discharge line B: o MOV-871B open o MOV-871A closed e.Verify both SI pump C discharge valves-OPEN~MOV-871A~MOV-871B 3)Go to Step 3.e.Manually open valves as necessary.

EOP: FR-C.2 TITLE: RESPONSE TO DEGRADED'CORE COOLING REV: 7 PAGE 5 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify SI Pump Suction Alignment a.Check BAST level: o Level-GREATER THAN 10%o Annunciator B-23, BORIC ACID TANK LO LO LEVEL-EXTINGUISHED a.Perform the following:

1)Ensure at least one SI pump suction valve from RWST open.~MOV-825A~MOV-825B 2)Ensure at least one valve in"'each SI pump suction line from BAST closed.~MOV-826A or MOV-826B~MOV-826C or MOV-826D b.Verify SI pump suction valves from BAST-OPEN~MOV-826A~MOV-826B~MOV-826C~MOV-826D 3)Go to Step 4.b.Ensure both valves in either flow path open.o MOV-826A and MOV-826B-OR-o MOV-826C and MOV-826D c.Verify SI pump suction from RWST CLOSED~MOV-825A~MOV-825B c.Manually align valves as necessary.

EOP: FR-C.2 RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 6 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Verify SI Flov In Both Trains: a.SI line loop A and B flow indicators

-CHECK FOR FLOW a.Perform the following:

1)Manually start SI pumps and align valves as necessary.

2)Establish maximum charging flow.b.RCS pressure-LESS THAN 250 psig[465 psig adverse CNMT]c.RHR loop flow indicator-CHECK FOR FLOW b.Go to Step 5.c.Manually start RHR pumps and align valves.

EOP: FR-C.2 TITLE: RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 7 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).5 Check RCS Vent Paths: a.Power to PRZR PORV block valves-AVAILABLE b.PORVs-CLOSED a.Restore power to block valves unless block valve was closed to isolate an open PORV:~MOV-515, MCC C position 6C~MOV-516, MCC D position 6C b.IF PRZR pressure less than 2335 psig, THEN manually close PORVs.IF any PORV can NOT be closed, THEN manually close its block valve.c.Block valves-AT LEAST ONE OPEN c.Open one block valve unless it was closed to isolate an open PORV..d.Rx vessel head vent valves CLOSED d.Manually close valves.~SOV-590~SOV-591~SOV-592~SOV-593 EOP: FR-C.2 RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 8 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Normal conditions for running RCPs are desired, but RCPs should not be tripped if normal conditions cannot be established or maintained.

6 Check RCP Status: a.At least one RCP-RUNNING b.Support conditions for the operating RCP(s)available (Refer to Attachment RCP START)a.Go to Step 9.b.Try to establish support conditions for the operating RCP.7 Check RVLIS Fluid Fraction a.Fluid fraction (any RCP on)GREATER THAN 60%a.IF increasing, THEN return to Step l.b.Return to procedure and step in effect.IF NOT, then go to Step 8.8 Check If One RCP Should Be Stopped: a.Both RCPs-RUNNING b.Stop one RCP c.Go to Step 10 a.Go to Step 10.

CE'It I i e EOP: FR-CD 2 RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 9 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check Core Cooling: a.RVLIS level (no RCPs)-GREATER THAN 43%[46%adverse CNMT]b.Core exit T/Cs-LESS THAN 700'F c.Return to procedure and step in effect a.IF increasing, THEN return to Step 1.IF NOT, THEN go to Step 10.b.IF decreasing,'HEN return to Step l.IF NOT, THEN go to Step 10.10 Check SI ACCUM Discharge Valves-OPEN~MOV-841~MOV-865 IF SI ACCUM discharge valves closed after ACCUM discharge, THEN go to Step 11.IF NOT, THEN perform the following:

a.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 b.Open SI ACCUM discharge valves.~ACCUM A, MOV-841~ACCUM B, MOV-865 EOP: FR-C.2 TITLE: RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 10 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION o 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).o A FAULTED OR RUPTURED S/G SHOULD NOT,BE USED IN SUBSEQUENT STEPS UNLESS NO INTACT S/G IS AVAILABLE.

NOTE: TDAFW pump flow control valves fail open on loss of IA.*ll Monitor Intact S/G Levels: 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.Increase total feed flow to restore narrow range level greater than 5%[25%adverse CNMT]in at least one S/G.12 Verify Condenser Steam Dump In Manual: a.Verify condenser available:

o Intact S/G MSIV-OPEN o Annunciator G-15, STEAM DUMP ARMED-LIT a.Place intact S/G ARV controller in MANUAL and go to Step 13.b.Place steam dump mode selector switch in MANUAL c.Place steam dump controller in MANUAL EOP: FR-C.2 TITLE: RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 11 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION THE FOLLOWING STEP WILL CAUSE SI ACCUMULATOR INJECTION WHICH MAY RESULT IN A RED PATH CONDITION IN F-0.4, INTEGRITY STATUS TREE.THIS PROCEDURE SHOULD BE COMPLETED BEFORE TRANSITION TO FR-P.l, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK.13 Depressurize All Intact S/Gs To 200 PSIG: a.Maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Dump steam to condenser b.Manually or locally dump steam from intact S/Gs: o Use S/G ARVs.-OR-o Open TDAFW pump steam supply valve(s)for affected S/G(s):~S/G A, MOV-3505A~S/G B, MOV-3504A-OR-o Locally perform the following:

o Open intact S/G MSIV bypass valve.o Open priming air ejector steam isolation valves.~V-3580~V-3581 c.Check S/G pressures-LESS THAN 200 PSIG c.Return to Step 11.d.Stop S/G depressurization EOP: FR-C.2 TITLE: RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 12 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION't RHR PUMPS SHOULD NOT BE RUN LONGER THAN 1 HOUR WITHOUT CCW TO THE RHR HEAT EXCHANGERS

.14 Check RHR Pumps-RUNNING Manually start pumps as necessary.

15 Check If SI ACCUMs Should Be Isolated: a.RCS hot leg temperatures

-BOTH LESS THAN 400'F b.Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves if necessary~MOV-841, MCC C position 12F~MOV-865, MCC D position 12C c.Close SI ACCUM discharge valves~MOV-841~MOV-865 a.Go to Step ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.~ACCUM A, AOV-834A~ACCUM B, AOV-834B d.Locally reopen breakers for MOV-841 and MOV-865 2)Open HCV-945.

FR-C.2 TITLE: RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 13 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION SYMPTOMS FOR FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, SHOULD BE CLOSELY MONITORED DURING SUBSEQUENT STEPS.16 Stop All RCPs 17 Depressurize All Intact S/Gs To Atmospheric Pressure: a.Maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Dump steam to condenser b.Manually or locally dump steam from intact S/Gs: 1)Use S/G ARVs, 2)Open TDAFV pump steam supply valve(s)for affected S/G(s):~S/G A, MOV-3505A~S/G B, MOV-3504A 3)Locally perform the following:

o Open intact S/G MSIV bypass valve.o Open priming air effector steam isolation valves.~'V-3580~V-3581 EOP: FR-C.2 TITLE: RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 14 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify SI Flow: o SI line loop A and B flow indicators

-CHECK FOR FLOW Perform the following:

a.Continue efforts to establish SI flow.-OR-o RHR loop flow indicator-CHECK FOR FLOW b.Try to establish maximum.charging flow.c.Return to Step 17.19 Isolate Both SI ACCUMs: a.Close SI ACCUM discharge valves~MOV-841~MOV-865 b.Locally reopen breakers for MOV-841 and MOV-865 a.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.~ACCUM A, AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.20 Stop All RCPs 21 Check Core Cooling: o RVLIS level (no RCPs)-GREATER THAN,68%[73%adverse CNMTj o Both'RCS hot leg temperatures LESS THAN 320'F Return to Step 17.

FR-C.2 RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 15 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Go to Appropriate Plant Procedure a.Check RWST level-GREATER THAN 28'.Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 17-END-a.Go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

EOP: FR-C.2 RESPONSE TO DEGRADED CORE COOLING REV: 7 PAGE 1 of 1 FR-C.2 APPENDIX LIST T1TLE 1)ATTACHMENT RCP START PAGES EOP: AP-CCW.1 TITLE LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 7 PAGE 2 of 11 A.PURPOSE-This procedure provides the actions required to identify and isolate leakage into the CCW system and to control the plant during the course of the event.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS

-This procedure is entered from;a.AP-CVCS.1, CVCS LEAK, when conditions indicate LEAKAGE INTO THE COMPONENT COOLING LOOP.2.SYMPTOMS-The symptoms of LEAKAGE INTO THE COMPONENT COOLING LOOP are;a.Annunciator A-5, COMP COOLING SURGE TANK HI LEVEL 58.84, or b.CCW radiation monitor (R-17)alarm, or c.Annunciator A-7 (15), RCP 1A (1B)CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F, or d.Erratic RCP labyrinth seal D/P.

EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 7 PAGE 3 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS'-Op REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • NOTE: Letdown diversion to CVCS HUT may cause R-17 increase or alarm.1 Check CCW Radiation Monitor (R-17)-INCREASING Go to Step 11.2 Check CCW Radiation Monitor (R-17)-IN ALARM Go to Step 4.3 Verify CCW Surge Tk Vent RCV-017--CLOSED Close CCW surge tk vent RCV-017.4 Check RCS Leakage-GREATER THAN NORMAL (Leakage found on latest RCS Leakage Surveillance Sheet)Go to Step 11.

EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV 7 PAGE 4 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: RCPs may be safely operated without CCW to the thermal barrier if seal injection flow is maintained.

5 Check RCP Thermal Barrier Indications:

o Labyrinth seal D/Ps-NORMAL (Both D/Ps reading approximately the same value)o RCP fl seal leak off flows-NORMAL (Check fl seal leak-off charts for normal indication) o Annunciator A-7 (15)RCP 1A (1B)CCW RETURN HI TEMP OR LO PLOW 165 GPM 125'P ALARM-EXTINGUISHED IP either pump has indication of a thermal barrier leak, THEN:.a.Verify seal injection flow b.Close CCW from lA (1B)thermal barrier MOV-754A (754B).c.IF CCW surge tank level stable, THEN go to Step 19.d.IP CCW surge tank level continues to increase, THEN go to Step 6.

r+r EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 7 PAGE 5 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION CLOSELY MONITOR PRZR LEVEL WHILE LETDOWN IS ISOLATED.*****************************************6 Check NRHX For Leakage: a.Normal letdown-INSERVICE b.Letdown indications a.IP excess letdown inservice, THEN go to Step 10.b.Isolate letdown as follows: o Letdown line flow-NORMAL (approximately 40 GPM)o Low press LTDN pressure-NORMAL (approximately 250 psig)o NRHX CCW outlet (local TI-600)-LESS THAN 190'P c.Go to Step ll 1)Close letdown loop B cold leg to RHx AOV-427.2)Close LTDN orifices AOVs 200A, 200B, and 202.3)Place low press LTDN press PI-135 PCV-135 in manual AND close (at 100X DEMAND signal).4)Close HCV-142 and reduce charging as necessary.

5)Go to Step 7.

EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 7 PAGE 6 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check If CCW Inleakage Has Stopped: o CCW surge tank level-STABLE Restore normal letdown: a.Establish charging line flow to REGEN Hx greater than 20 GPM.b.Place letdown controllers TCV-130 and PCV-135 in manual at 25X open.c.Open AOV-427.d.Open letdown orifice valves as necessary.

e.Place TCV-130 in auto at 105'P.f.Place PCV-135 in auto at 250 Psigo g.Ad)ust charging speed and HCV-142 as necessary.

h.Go to Step 11.

EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 7 PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Establish Excess Letdown: a.Place excess letdown divert valve, AOV-312, to NORMAL , b.Verify RCP seal return isolation valve, MOV-313, OPEN c.Ensure CCV from excess letdown open, (AOV-745)d.Open excess letdown isolation valve, AOV-310 e.Slowly open HCV-123 to maintain excess letdown temperature less than 195'F and pressure less than 100 psig f.Adjust charging pump speed as necessary 9 Check PRZR Level: a.PRZR level-TRENDING TO REFERENCE LEVEL b.Go to Step 18 a.Reduce charging as necessary to control PRZR level.