ML17263A271

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Rev 7 to EOP FR-C.2, Response to Degraded Core Cooling.
ML17263A271
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/21/1993
From: Marlow T
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A269 List:
References
FR-C.2, NUDOCS 9305140049
Download: ML17263A271 (28)
v • d • e


Text

EOP: TITLE:

REV: 7 FR-CD 2 RESPONSE TO DEGRADED CORE COOLING 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:

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 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.

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 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 Perform the following:

THAN 284

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: TITLE:

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 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 a. Ensure at least one valve open.

deluge - OPEN

~ MOV-852A

~ MOV-852B

b. Verify SI pump C - RUNNING b. Manually start pump on available bus.
c. Verify SI pump A - 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. Verify SI pump B - RUNNING 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

3) Go to Step 3.
e. Verify both SI pump C discharge e. Manually open valves as valves - OPEN necessary.

~ MOV-871A

~ MOV-871B

EOP: TITLE:

REV: 7 FR-C. 2 RESPONSE TO DEGRADED'CORE COOLING PAGE 5 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify SI Pump Suction Alignment

a. Check BAST level: a. Perform the following:

o Level - GREATER THAN 10% 1) Ensure at least one SI pump suction valve from RWST open.

o Annunciator B-23, BORIC ACID TANK LO LO LEVEL- ~ MOV-825A EXTINGUISHED ~ 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

3) Go to Step 4.
b. Verify SI pump suction valves b. Ensure both valves in either from BAST - OPEN flow path open.

~ MOV-826A o MOV-826A and MOV-826B

~ MOV-826B

~ MOV-826C -OR-

~ MOV-826D o MOV-826C and MOV-826D

c. Verify SI pump suction from RWST c. Manually align valves as CLOSED necessary.

~ MOV-825A

~ MOV-825B

EOP:

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 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 a. Perform the following:

indicators - CHECK FOR FLOW

1) Manually start SI pumps and align valves as necessary.
2) Establish maximum charging flow.
b. RCS pressure - LESS THAN b. Go to Step 5.

250 psig [465 psig adverse CNMT]

c. RHR loop flow indicator - CHECK c. Manually start RHR pumps and FOR FLOW align valves.

EOP: TITLE:

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 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 a. Restore power to block valves

- AVAILABLE unless block valve was closed to isolate an open PORV:

~ MOV-515, MCC C position 6C

~ MOV-516, MCC D position 6C

b. PORVs - CLOSED 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 d. Manually close valves.

CLOSED

~ SOV-590

~ SOV-591

~ SOV-592

~ SOV-593

EOP:

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 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 a. Go to Step 9.
b. Support conditions for the b. Try to establish support operating RCP(s) available conditions for the operating RCP.

(Refer to Attachment RCP START) 7 Check RVLIS Fluid Fraction

a. Fluid fraction (any RCP on) a. IF increasing, THEN return to GREATER THAN 60% Step l.

IF NOT, then go to Step 8.

b. Return to procedure and step in effect.

8 Check Stopped:

If One RCP Should Be

a. Both RCPs - RUNNING a. Go to Step 10.
b. Stop one RCP
c. Go to Step 10

CE' It I

i e

EOP:

REV: 7 FR-CD 2 RESPONSE TO DEGRADED CORE COOLING PAGE 9 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check Core Cooling:

a. RVLIS level (no RCPs) - GREATER a. IF increasing, THEN return to THAN 43% [46% adverse CNMT] Step 1. IF NOT, THEN go to Step 10.
b. Core exit T/Cs - LESS THAN 700'F b. IF decreasing,'HEN return to Step l. IF NOT, THEN go to Step 10.
c. Return to procedure and step in effect 10 Check SI ACCUM Discharge IF SI ACCUM discharge valves closed Valves OPEN after ACCUM discharge, THEN go to Step 11. IF NOT, THEN perform the

~ MOV-841 following:

~ MOV-865

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: TITLE:

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 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 a. Increase total feed flow to THAN 5% [25% adverse CNMT) restore narrow range level greater than 5% [25% adverse CNMT] in at least one S/G.
b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

12 Verify Condenser Steam Dump In Manual:

a. Verify condenser available: a. Place intact S/G ARV controller in MANUAL and go to Step 13.

o Intact S/G MSIV - OPEN o Annunciator G-15, STEAM DUMP ARMED - LIT

b. Place steam dump mode selector switch in MANUAL
c. Place steam dump controller in MANUAL

EOP: TITLE:

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 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 c. Return to Step 11.

200 PSIG

d. Stop S/G depressurization

EOP: TITLE:

REV: 7 FR-C. 2 RESPONSE TO DEGRADED CORE COOLING 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 Isolated:

If SI ACCUMs Should Be

a. RCS hot leg temperatures - BOTH a. Go to Step ECA-3.1, SGTR WITH LESS THAN 400'F LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
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 c. Vent any unisolated ACCUMs:

~ MOV-841 1) Open vent valves for

~ 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

TITLE:

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 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: TITLE:

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 14 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify SI Flow: Perform the following:

o SI line loop A and B flow a. Continue efforts to establish SI indicators - CHECK FOR FLOW flow.

-OR- b. Try to establish maximum

.charging flow.

o RHR loop flow indicator - CHECK FOR FLOW c. Return to Step 17.

19 Isolate Both SI ACCUMs:

a. Close SI ACCUM discharge valves a. Vent any unisolated ACCUMs:

~ MOV-841 1) Open vent valves for

~ MOV-865 unisolated SI ACCUMs.

~ ACCUM A, AOV-834A

~ ACCUM B, AOV-834B

2) Open HCV-945.
b. Locally reopen breakers for MOV-841 and MOV-865 20 Stop All RCPs 21 Check Core Cooling: Return to Step 17.

o RVLIS level (no RCPs) - GREATER THAN,68% [73% adverse CNMTj o Both'RCS hot leg temperatures LESS THAN 320'F

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 15 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Go to Appropriate Plant Procedure

a. Check RWST level - GREATER THAN a. Go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

28'.

Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 17

-END-

EOP:

REV: 7 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 1 of 1 FR-C.2 APPENDIX LIST T1TLE PAGES

1) ATTACHMENT RCP START

EOP: TITLE REV: 7 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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: TITLE: REV 7 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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 Go to Step 11.

(R-17) INCREASING 2 Check CCW Radiation Monitor Go to Step 4.

(R-17) IN ALARM 3 Verify CCW Surge Tk Vent Close CCW surge tk vent RCV-017.

RCV-017 -- CLOSED 4 Check RCS Leakage GREATER Go to Step 11.

THAN NORMAL (Leakage found on latest RCS Leakage Surveillance Sheet)

EOP:

REV 7 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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 IP either pump has indication of a Indications: thermal barrier leak, THEN: .

o Labyrinth seal D/Ps - NORMAL a. Verify seal injection flow (Both D/Ps reading approximately the same value) b. Close CCW from lA (1B) thermal barrier MOV-754A (754B).

o RCP fl seal leak off flows-NORMAL (Check fl seal leak-off c. IF CCW surge tank level stable, charts for normal indication) THEN go to Step 19.

o Annunciator A-7 (15) RCP 1A (1B) d. IP CCW surge tank level CCW RETURN HI TEMP OR LO PLOW continues to increase, THEN go 165 GPM 125'P ALARM- to Step 6.

EXTINGUISHED

r+r EOP: TITLE: REV 7 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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 a. IP excess letdown inservice, THEN go to Step 10.
b. Letdown indications b. Isolate letdown as follows:

o Letdown line flow - NORMAL 1) Close letdown loop B cold leg (approximately 40 GPM) to RHx AOV-427.

o Low press LTDN pressure- 2) Close LTDN orifices AOVs NORMAL (approximately 250 200A, 200B, and 202.

psig)

3) Place low press LTDN press o NRHX CCW outlet (local PI-135 PCV-135 in manual AND TI-600) - LESS THAN 190'P close (at 100X DEMAND signal).
4) Close HCV-142 and reduce charging as necessary.
5) Go to Step 7.
c. Go to Step ll

EOP: TITLE:

REV 7 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 6 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check If Stopped:

CCW Inleakage Has Restore normal letdown:

a. Establish charging line flow to o CCW surge tank level - STABLE 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:

REV: 7 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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 a. Reduce charging as necessary to REFERENCE LEVEL control PRZR level.
b. Go to Step 18
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