ML17263A589
| ML17263A589 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/30/1994 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17263A585 | List:
|
| References | |
| E, E-0, NUDOCS 9404190109 | |
| Download: ML17263A589 (75) | |
Text
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E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE of 29 ROCHESTER GAS AND ELECTRIC CORPORATI N
GINNA STATION CONTROLLED COPY NUMBER ECHNICAL REV EW PORC REVIEW DAT P
T SUPERINTE ENT 7
~j EFFECTIVE DATE CATEGORY 1 0
REVIEW BY r
04190i0'P 9404i4 PDR ADOCK~05000244 P
1 J
~ ("
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E-0 REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 2 of 29 A.
PURPOSE This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection and to assess plant conditions, and identify the appropriate recovery procedure.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
The following are symptoms that requiie a reactor trip, if one has not occurred:
o Any plant parameter reaches a reactor trip setpoint and logic as listed in procedure P-1, REACTOR CONTROL AND PROTECTION SYSTEM.
o Operator discretion.
2.
The following are symptoms of a reactor trip:
o Any First. Out reactor trip annunciator lit.
o A rapid decrease in core neutron level as indicated by nuclear instrumentation.
o MRPI Indicates all control and shutdown rods on bottom.
o Reactor trip breakers indicate open.
3.
The following are symptoms that require a reactor trip and safety injection, if one has not occurred:
o Any plant parameter reaches the Safety Injection setpoint and logic as listed in procedure P-1, REACTOR CONTROL AND PROTECTION SYSTEM.
o Operator discretion.
4.
The following are symptoms of a reactor trip and safety injection:
o Any SI annunciator lit.
o Safeguards sequencing started.
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E-0 REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 3 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE" NOT OBTAINED NOTE:
o Steps 1 through 12 are IMMEDIATE ACTION steps' 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.
o At least one train of reactor trip breakers OPEN o
Neutron flux - DECREASING o
MRPI indicates
- ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Manually trip reactor.
IF reactor trip breakers NOT open, THEN perform the following:
a.
Open Bus 13 and Bus 15 normal feed breakers.
- b. Verify rod drive MG sets tripped.
- c. Close Bus 13 and Bus 15 normal feed breakers.
- d. Reset lighting breakers.
IF the reactor will NOT trip OR IF power range NIS indicates greater than 5%,
THEN go to FR-S.l,
RESPONSE
TO REACTOR RESTART/ATWS, Step 1
O 2
Verify Turbine Stop Valves CLOSED Manually trip turbine.
IF turbine trip can NOT be
- verified, THEN close both MSIVs ~
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REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 4 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 3
,Verify Both Trains Of AC Emergency Busses Energized To At Least 420 VOLTS:
Attempt to s tar t any failed emergency D/G to restore power to all AC emergency busses.
~ Bus 14 and Bus 18
~ Bus 16 and Bus 17 IF power can NOT least one train, ECA-O.O, LOSS OF Step 1.
be restored to at THEN go to ALL AC POWER, a.
Any SI Annunciator
- LIT
- a. IF any of the following conditions are met, THEN manually actuate SI and CI:
o PRZR pressure less than 1750 psig
-OR-o Steamline pressure less than 514 psig
-OR-o CNMT pressure greater than 4 psig
-OR-o SI sequencing started
-OR-o Operator determines SI required b.
SI sequencing BOTH TRAINS STARTED.
IF SI is NOT required, THEN go to ES-O.l, REACTOR TRIP
- RESPONSE, Step l.
- b. Manually actuate SI and CI.
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19 PAGE 5 of 29 STEP ACTION/EXPECTED RESPONSE
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NOT OBTAINED 5
Verify SI and RHR Pumps Running:
- a. All SI pumps RUNNING
- b. Both RHR pumps RUNNING a.
Perform the following:
l) Ensure SI pump suction supply open from RWST.
- 2) Manually start pumps.
- b. Manually start pumps.
O 6
Verify CNMT RECIRC Fans Running:
- a. All fans
- RUNNING
- b. Charcoal filter dampers green status lights
- EXTINGUISHED
- a. Manually start fans.
- b. Dispatch personnel to relay room with relay rack key to locally open dampers by pushing in trip relay plungers.
~ AUX RELAY RACK RA-2 for fan A
+ AUX RELAY RACK RA-3 for fan C
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RESPONSE
NOT OBTAINED O
7 Verify CNMT Spray Not Required:
o Annunciator A-27, CNMT SPRAY-EXTINGUISHED o
CNMT pressure
- LESS THAN 28 PSIG Verify CNMT spray initiated.
IF CNMT spray NOT initiated, THEN perform the following:
a.
Depress manual CNMT spray pushbuttons (2 of 2).
b.
Ensure CNMT spray pumps running.
IF no CNMT spray pump available, THEN go to Step 8.
- c. Ensure CNMT spray pump discharge valves open for operating pump(s).
o CNMT spray pump A:
~ MOV-860A
~ MOV-860B o
CNMT spray pump B:
~ MOV-860C
~ MOV-860D d.
Ensure NaOH tank outlet valves open.
~ AOV-836A
~ AOV-836B
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19 PAGE 7 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED O
8 Check If Main Steamlines Should Be Isolated:
a.
Any MSIV -
OPEN b.
Check CNMT pressure
- LESS THAN 18 PSIG c.
Check if. ANY main steamlines should be isolated:
.o Low Tavg (545'F)
AND high steam flow (0.4x10 lb/hr) from either S/G a.
Go to Step 9.
b.
Ensure BOTH MSIVs closed and go to Step 9.
c.
Go to Step 9.
-OR-o High-High steam flow (3.6x10~ lb/hr) from either S/G
- d. Verify MSIV closed on the affected S/G(s)
- d. Manually close valves.
a.
MFW pumps
- TRIPPED b.,MFW flow control valves CLOSED
+ MFW regulating valves
~
MFW bypass valves c.
S/G blowdown and sample valves CLOSED
- b. Place A and B S/G MFW regulating valve and bypass valve controllers in MANUAL at 0%
demand.
- c. Place S/G blowdown and sample valve isolation switch to CLOSE.
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19 PAGE 8 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED a.
MDAFW pumps
- RUNNING b.
TDAFW pump
- RUNNING IF NECESSARY
- a. Manually start MDAFW pumps.
, b. Manually open steam supply valves.
~ MOV-3505A
~ MOV-3504A O
11 Verify At Least Two SW Pumps RUNNING Perform the following:
a.
Ensure one SW pump running on each energized screenhouse AC emergency bus:
~ Bus 17
~ Bus 18
- b. IF offsite power NOT available, THEN ensure SW isolation.
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E-0 REACTOR TRIP OR SAFETY INJECTION REV 19 PAGE 9 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
'2 Verify CI And CVI:
a.
CI and CVI annunciators
- LIT
~ Annunciator A-26, CNMT ISOLATION
~ Annunciator A-25, CNMT VENTILATION ISOLATION a.
Depress manual CI pushbutton.
- b. Verify CI and CVI valve status lights
- BRIGHT
- b. Manually close CI and CVI valves as required.
IF valves can NOT be closed, THEN dispatch AO to locally close valves (Refer to Attachment CI/CVI for alternate isolation valves).
c.
CNMT RECIRC fan coolers SW outlet valve status lights BRIGHT
- c. Dispatch AO to locally fail open valves.
~ FCV-4561
~ FCV-4562
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REACTOR TRIP OR SAFETY INJECTION REV 19 PAGE 10 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
- x*********x x**xx x*x***x***************
CAUTION RCP TRIP CRITERIA LISTED ON FOLDOUT PAGE SHOULD BE MONITORED PERIODICALLY.
- * * * * * * * * * * *
- 4 * * * * * * * * * * * * * * * * * * * * * * * * * *
- 13 Check CCW System Status:
- a. Verify CCW pump
- AT LEAST ONE RUNNING
- b. Verify CCW from excess letdown (AOV-745)
CLOSED
- a. IF offsite power available, THEN manually start one CCW pump.
- b. Manually close valve.
14 Verify SI And RHR Pump Flow:
a.
SI flow indicators CHECK FOR FLOW
- a. IF RCS pressure 1400 psig, THEN pumps and align THEN go to Step less than manually start valves.
IF NOT, 15 RHR flow indicator CHECK FOR FLOW
- b. IF RCS pressure less than 140 psig, THEN manually start pumps and align valves.
IF NOT, THEN go to Step 15.
15 Verify Total AFW Flow GREATER THAN 200 GPM IF S/G narrow range level greater than 5%
[25% adverse CNMT] in any S/G, THEN control AFW flow to maintain narrow range level.
IF narrow range level less than 5%
[25% adverse CNMTj in all S/Gs, THEN manually start pumps and align valves as necessary.
IF AFW flow greater than 200 gpm can NOT be established, THEN go to FR-H.1,
RESPONSE
TO LOSS OF SECONDARY HEAT SINK, Step 1.
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19 PAGE 11 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 16 Verify AFW Valve Alignment:
a.
AFW flow - INDICATED TO BOTH S/G(s) b.
AFW flow from each MDAFW pump LESS THAN 230 GPM Manually align valves as necessary.
17 Verify SI Pump Suction Aligned to RWST:
~ MOV-825A
~ MOV-825B a.
Ensure at least one SI pump suction valve from RWST open.
~ MOV-825A
~ MOV-825B
- b. Verify SI pump suction valves from BASTs CLOSED
~ MOV-826A
~ MOV-826B
~ MOV-826C
~ MOV-826D b.
Ensure at least one valve in each SI pump suction line from BAST closed.
~ MOV-826A or MOV-826B
~ MOV-826C or MOV-826D
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REACTOR TRIP OR SAFETY INJECTION REV 19 PAGE 12 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 18 Verify SI Pump And RHR Pump Emergency Alignment:
a.
RHR pump discharge to Rx vessel deluge OPEN
~ MOV-852A
~ MOV-852B
- b. Verify SI pump C - RUNNING
- c. Verify SI pump A -
RUNNING
- d. Verify SI pump B -
RUNNING
- e. Verify SI pump C discharge valves OPEN
~ MOV-871A
~ MOV-871B a.
Ensure at least one valve open.
- b. Manually start pump on available bus.
- c. Perform the following:
- 1) Ensure SI pumps B and C
running.
IF either pump
- NOT, running, THEN go to Step 18e.
- 2) Ensure SI pump C aligned to discharge line A:
o MOV-871A open o
MOV-871B closed 3)
Go to Step 19.
- d. Perform the following:
- 1) Ensure SI pumps A and C
running.
IF either pump
- NOT, running, THEN go to Step 18e.
- 2) Ensure SI pump C aligned to discharge line B:
o MOV-871B open o
MOV-871A closed 3)
Go to Step 19.
- e. Manually open valves as necessary.
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REACTOR TRIP OR SAFETY INJECTION REV 19 PAGE 13 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
- * * * * * * * * * * * *
- x
- x *
- x * *
- x * * * * * *
- x x *
- x * * * *
- CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN SELECTED SW PUMPS AND ONE CCW PUMP WILL AUTO START ON, EMERGENCY D/G.
MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
x ****x *****
x ****x *******
19 Check CCW Flow to RCP Thermal Barriers:
o Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO FLOW EXTINGUISHED IF CCW to a RCP is lost, THEN perform the following:
a.
Stop affected RCPs.
- b. Reset SI.
o Annunciator A-15, RCP 1B CCW RETURN.HI TEMP OR LO FLOW EXTINGUISHED
- c. Verify adequate power available to run one charging pump (75 kw).
- d. Start one charging pump at minimum speed for seal injection.
- e. Adjust HCV-142 to establish either of the following:
o Labyrinth seal D/P to each RCP greater than 15 inches of water.
-OR-o RCP seal injection flow to each RCP greater than 6 gpm
- f. IF large imbalance in seal injection flow exists, THEN consider local adjustment of V-300A and V-300B.
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E-0 REACTOR TRIP OR SAFETY INJECTION REV 19 PAGE 14 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 20 Check If TDAFW Pump, Can Be Stopped:
a.
Both MDAFW pumps
- RUNNING b.
PULL STOP TDAFM pump steam supply valves
~ MOV-3504A
~ MOV-3505A a.
Go to Step 21.
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REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 15 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 21 Check RCS Tavg STABLE AT OR TRENDING TO 547'F IF temperature, less than 547'F and decreasing, THEN perform the following:
a.
Stop dumping steam.
- b. Rotate reheater steam supply controller cern to close reheater steam supply valves.
- c. IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level greater'han 5%
[25%
adverse CNMT) in at least one S/G.
d.
VHEN S/G level greater than 5%
[25% adverse CNMT) in one S/G, THEN limit feed flow to that required to maintain level in at least one S/G.
- e. IF cooldown.continues, THEN close both MSIVs.
IF temperature greater than 547'F and increasing, THEN perform the following:
o Dump steam to condenser.
-OR-o Control RCS temperature manually using S/G ARVs.
I
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REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 16 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 22 Check PRZR PORVs And Spray Valves:
a.
PORVs CLOSED
- a. IF PRZR pressure less than 2335 psig, THEN manually clo'se PORVs.
IF any valve can NOT be closed, THEN manually close its block valve.
~ MOV-516 for PCV-430
~ MOV-515 for PCV-431C
- b. Auxiliary spray valve (AOV-296)
CLOSED IF block valve can NOT be
- closed, THEN go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- b. Manually close auxiliary spray valve.
IF valve can NOT be
- closed, THEN perform the following:
- 1) Decrease charging pump flow to minimum.
c.
Check PRZR pressure
- LESS THAN 2260 PSIG
- d. Verify normal PRZR spray valve controllers DEMAND AT 0%
- 2) Ensure charging valve to loop B cold leg open (AOV-294).
- c. Continue with Step 23.
WHEN pressure less than 2260 psig, THEN do Steps 22d.
- d. Place controllers in MANUAL at 0% demand.
IF valves can NOT be
- closed, THEN stop associated RCP(s).
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REACTOR TRIP OR SAFETY INJECTION REV 19 PAGE 17 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
- 23 Monitor RCP Trip Criteria:
a.
RCP status
- ANY RCP RUNNING
- b. SI pumps
- AT LEAST TWO RUNNING c.
RCS pressure minus maximum S/G pressure LESS THAN 175 psig
[400 psig adverse CNMT]
d.
Stop both RCPs a.
Go to Step 24.
b.
Go to Step 24.
c.
Go to Step 24.
24 Check If S/G Secondary Side Is Intact:
o Pressure in both S/Gs STABLE OR INCREASING IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
o Pressure in both S/Gs GREATER THAN 100 PSIG 25 Check If S/G Tubes Are Intact:
o Air ej ector radiation monitors (R-15 or R-15A)
NORMAL o
S/G blowdown radiation monitor (R-19)
NORMAL Go to E-3, STEAM GENERATOR TUBE
- RUPTURE, Step 1.
o Steamline radiation monitors (R-31 and R-32)
NORMAL
I
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E-0 LITLE:
REACTOR TRIP OR SAFETY INJECTION REV'9 PAGE 18 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 26 Check, If RCS Is Intact:
a.
CNMT area radiation monitors NORMAL Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
~ R-2
~ R-7
~ R-29
~ R-30 b.
CNMT pressure LESS THAN 0.5 PSIG c.
INCHES t
d.
Level -
STABLE o
Annunciator C-19, CONTAINMENT SUMP A HI LEVEL -
EXTINGUISHED NOTE:
The following is an attempt to determine whether a
PRZR spray valve has failed.
27 Check RCS Pressure STABLE OR INCREASING IF RCS pressure decreasing with PRZR level stable or increasing, THEN stop both RCPs.
~,
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REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 19 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 28 Check If SI Should Be Terminated:
a.
RCS pressure:
o Pressure GREATER THAN 1625 PSIG o
Pressure STABLE OR INCREASING a.
Do NOT stop SI pumps.
Go to Step 30.
b.
RCS subcooling based on core exit T/Cs GREATER THAN O' USING FIGURE MIN SUBCOOLING b.
Do NOT stop SI pumps.
Go to Step 30.
\\
c.
Secondary heat sink:
o Total feed flow to S/Gs GREATER THAN 200 GPM
- c. IF neither condition met, THEN do NOT stop SI pumps.
Go to Step 30.
-OR-o Narrow range level in at least one S/G GREATER THAN 5S d.
PRZR level
- GREATER THAN 5%
d.
Do NOT stop SI pumps.
Perform the following:
- 1) IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.
2)
Go to Step 30 '
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REACTOR TRIP OR SAFETY INJECTION REV 19 PAGE 20 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 29 Go To ES-1 '@ SI TERMINATION'tep 1
NOTE:
o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
o The Critical Safety Function Red Path Summary is available in APPENDIX 1.
30 Initiate Monitoring of Critical Safety Function Status Trees
- +***************x x*x*************x****
CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).
- 31 Monitor S/G Levels:
a.
Narrow range level GREATER THAN 5%
- b. Control feed flow to maintain narrow range level between 17%
and 50%
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5% in at least one S/G.
- b. IF narrow range level in any S/G continues to increase in an uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE
- RUPTURE, Step l.
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REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 21 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 32 Check Secondary Radiation Levels NORMAL o
Steamline radiation monitor (R-31 and R-32)
Go to E-3, STEAM GENERATOR TUBE
- RUPTURE, Step 1.
o Dispatch AO to locally check steamline radiation o
Request HP sample S/Gs for activity CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN SELECTED SW PUMPS AND ONE CCW PUMP WILL AUTO START ON EMERGENCY D/G.
MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
x x *%
33 Reset SI 34 Reset CI:
a.
Depress CI reset pushbutton
- b. Verify annunciator A-26, CNMT ISOLATION -
EXTINGUISHED
- b. Perform the following:
- 1) Reset SI.
- 2) Depress CI reset pushbutton.
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19 PAGE 22 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 35 Verify Adequate SW Flow:
- a. At least three SW pumps
- RUNNING
- a. Manually start SW pumps as power supply permits (258 kw each).
IF less than three pumps
, running, THEN ensure SW isolation.
- b. Dispatch AO to establish normal shutdown alignment (Refer to
. Attachment SD-1)
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REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 23 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 36 Establish IA to CNMT:
- a. Verify non-safeguards busses energized from offsite power
~
o Bus 13 normal feed CLOSED
-OR-o Bus 15 normal feed CLOSED
- b. Verify SW isolation valves to turbine building -
OPEN
~ MOV-4613 and MOV-4670
~ MOV-4614 and MOV-4664
- c. Verify at least two air compressors RUNNING d.
Check IA supply:
o Pressure GREATER THAN 60 PSIG o
Pressure STABLE OR INCREASING e.
Reset both trains of XY relays for IA to CNMT AOV-5392
Perform the following:
- 1) Close non-safeguards bus tie breakers:
~ Bus 13 to Bus 14 tie
~ Bus 15 to Bus 16 tie
- 2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).
IF NOT, THEN evaluate if CNMT RECIRC fans should be stopped (Refer to Attachment CNMT RECIRC FANS).
3)
WHEN bus 15 restored, THEN reset control room lighting.
- b. Manually align valves.
- c. Manually start air compressors as power supply permits (75 kw each).
IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
- d. Perform the following:
- 1) Continue attempts to restore IA (Refer to AP-IA.l, LOSS OF INSTRUMENT AIR).
- 2) Continue with Step 37.
WHEN IA restored, THEN do Steps 36e and f.
EOP:
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RESPONSE
NOT OBTAINED 37 Check Auxiliary Building Radiation NORMAL Evaluate cause of abnormal conditions.
~ Plant vent iodine (R-10B)
~ Plant vent particulate (R-13)
~ Plant vent gas (R-14)
~
CCW liquid monitor (R-17)
~ LTD line monitor (R-9)
~
CHG pump room (R-4)
IF the cause is a loss of RCS inventory outside
38 Check PRT Conditions o
PRT level (LI-442)
LESS THAN 84%
o PRT temperature (TI-439)
LESS THAN 120'F Evaluate the following flowpaths for cause of abnormal conditions:
~ RCP seal return relief
~ PRZR PORVs
~ PRZR safeties
~ Letdown'ine relief o
PRT pressure (PI-440A)
- LESS THAN 3 PSIG IF excess letdown previously in
- service, THEN close AOV-310, excess letdown isolation valve from loop A cold.
EOP:
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REACTOR TRIP OR SAFETY INJECTION REV 19 PAGE 25 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED x x **x********%
- x
- x x *x******
CAUTION RCS PRESSURE SHOULD BE MONITORED.
IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG
[465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
x **********
39 Check If RHR Pumps Should Be Stopped:
a.
Check RCS pressure:
- 1) Pressure GREATER THAN 250 PSIG
- 2) Pressure STABLE OR INCREASING 1)
Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step l.
2)
Go to Step 40.
b.
Stop both RHR pumps and place in AUTO 40 Check Normal Power Available To Charging Pumps:
o Bus 14 normal feed breaker CLOSED o
Bus 16 normal feed breaker CLOSED Verify adequate emergency D/G capacity to run charging pumps (75 kw each).
IF NCT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer to Attachment CNMT RECIRC FANS).
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REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 26 of 29 STEP ACTION/EXPECTED RESPONSE
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NOT OBTAINED 41 Check If Charging Flow Has Been Established:
a.
Charging pumps
- ANY RUNNING a.
Perform the following:
- 1) IF CCW flow is lost to any RCP thermal barrier OR any RCP 51 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s) to affected RCP:
~ V-300A for RCP A
~ V-300B for RCP B
- 2) Ensure HCV-142 open, demand at OS.
- b. Charging pump suction aligned to RWST:
o LCV-112B -
OPEN o
LCV-112C -
CLOSED
- b. Manually align valves as necessary.
IF LCV-112B can NOT be opened, THEN perform the following:
- 1) Verify charging pump A NOT running and place in PULL STOP.
- 2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).
- c. Start charging pumps as necessary and adjust charging flow to restore PRZR level 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).
E-0 REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 27 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 42 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG o
Reset PRZR heaters o
Use normal PRZR spray
e Il Ih
EOP:
E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 28 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 43 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses energized by 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 a.
Perform the following:
- 1) Verify non-safeguards bus tie breakers closed:
~ 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) Ensure condenser steam dump mode control in MANUAL.
- 4) Restore power to MCCs:
~ A from Bus 13
~
B from Bus 15
~
E from Bus 15
~ F from Bus 15
- 5) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.
- b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)
~ 6) Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
EOP:
E-0 REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 29 of 29 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 44 Return to Step 21
-END-
EOP:
E-0 REACTOR TRIP OR SAFETY INJECTION REV:
19 PAGE 1 of 1 E-0 APPENDIX LIST TITLE PAGES 1)
RED PATH
SUMMARY
2)
FIGURE MIN SUBCOOLING 3)
ATTACHMENT CI/CVI 4)
ATTACHMENT SD-1 5)
ATTACHMENT CNMT RECIRC FANS 6)
ATTACHMENT D/G STOP 7)
ATTACHMENT SI/UV 8)
FOLDOUT
EQPI AP-CCW.2 LOSS OF CCW DURING POWER OPERATION REV:
11 PAGE 1 of 8 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
ECP:
AP-CCW.2 TITLE:
LOSS OF CCW DURING POWER OPERATION REV:
11 PAGE 2 of 8
A.
PURPOSE This procedure provides the steps necessary to respond to a loss of CCW while the plant is at power.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
ENTRY CONDITIONS This procedure may be entered from:
a.
AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING SYSTEM, when CCW surge tank level decrease indicated at power.
2.
SYMPTOMS The symptoms of LOSS OF CCW DURING POWER OPERATION are; a
~
Annunciator A-13, CCW SURGE TANK LO LEVEL 41.24, lit, or b.
Annunciator A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI, lit, or c ~
d.
e.
g, h.
Annunciator A-17, MOTOR OFF RCP CCWP, lit, or Annunciator A-9, RHR PUMP COOLING WATER OUTLET LO FLOW 15 GPM, lit or Annunciator A-6, CONT SPRAY PUMP COOLING WATER OUT LOW FLOW 15 GPM, lit or Annunciator A-14, SAFETY INJ PUMPS COOLING WATER OUT LO FLOW 25 GPM, lit or Annunciator A-7 (A-15),
RCP A (B)
CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F, lit or Annunciator A-24 (A-"32),
RCP A (B) OIL LEVEL + 1.25, lit.
EQP:
AP-CCW.2 TITLE:
LOSS OF CCW DURING POWER OPERATION REV:
11 PAGE 3 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
- xx*xxx*xxA*xxxx*x**xk*x*x*x ex xxx*x*
CAUTION o
IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 200'F, THEN TRIP THE AFFECTED RCP.
o IF CCW IS LOST, THEN SEAL INJECTION SHOULD BE MAINTAINED TO THE RCP(S)
UNTIL RCS TEMPERATURE IS LESS THAN 200'F, OR UNTIL CCW IS RESTORED.
xxx*x%%x**xxxxxwxxxxxxx**x*x****x***xx**
NOTE: If leakage from the CCW system is indicated, then refer to ER-SC.5, HAZARDOUS AND MIXED WASTE MANAGEMENT AND CONTROL, for guidance.
1 Check CCW Pump Status:
o Both CCW pump breaker white disagreement lights EXTINGUISHED o
Annunciator A-17, MOTOR OFF RCP CCWP EXTINGUISHED Perform the following:
a.
Ensure standby CCW pump running.
- b. IF annunciator A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI, lit, THEN check closed CCW to RHR HXs (MOV-738A and MOV-738B).
r I
EOP AP-CCW.2 ilLEE:
S LOSS OF CCW DURING POWER OPERATION REV 11 PAGE 4 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
CCW surge tank level should be verified locally in the AUX BLDG, if possible.
2 Verify CCW Surge Tank Level APPROXIMATELY 50~o AND STABLE Perform the following:
a.
Open RMW to CCW surge
- tank, HOV-823.
- b. Start RMW pump(s).
- c. IF surge tank level stable or increasing, THEN go to Step 3.
IF CCW surge tank level can NOT be maintained greater than 10%,
THEN perform the following:
- 1) Trip the reactor.
- 2) Trip the RCPs.
- 3) Place both CCW pumps in pull stop.
4)
Go to E-O, REACTOR TRIP OR SAFETY INJECTION.
EOP:
AP-CCW.2 TITLE:
LOSS OF CCW DURING POWER OPERATION REV 11 PAGE 5 of 8
STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED x**x***x
- x x*****x****x**********
CAUTION IF ANY RCP IS TRIPPED, THEN SHUTDOWN MARGIN REQUIREMENTS SHOULD BE VERIFIED (REFER TO 0-3.1, BORON CONCENTRATION FOR XENON FREE ALL RODS IN MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN).
- x****
x x**x****x*********x***
o Annunciator A-7 (A-15),
RCP 1A (1B)
CCW return Hi temp or low flow 165 gpm 125'F alarm-EXTINGUISHED o
RCP motor bearings temperature (PPCS address GD-RCPS OR RCP temperature monitor RK-30A recorder) 5 200'F IF CCW lost to RCP(s),
THEN perform the following:
- a. Trip the Rx.
- b. Trip affected RCP(s).
c.
Go to E-O, REACTOR TRIP OR SAFETY INJECTION.
4 Check CCW Valve Alignment NORMAL (Refer to Attachment AT POWER CCW ALIGNMENT)
Align CCW valves as necessary.
EOP:
AP-CCW.2 TITLE:
LOSS OF CCW DURING POWER OPERATION REV:
11 PAGE 6 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
o An evaluation must be made to determine if operation may continue while investigating a
CCW leak in containment.
o Operation may continue with the reactor support coolers isolated.
If this occurs, notify higher supervision.
5 Check For CCW Leakage In CNMT:
a.
o Level STABLE o
Sump A pumps
- OFF a..IF abnormal increase in CNMT sump level, THEN perform the following:
b.
RCP oil levels STABLE
- b. IF any RCP oil level increasing uncontrollably, THEN perform the following:
- 1) Trip Reactor.
- 2) Trip affected RCP(s).
~ RCP A, MOV.-749A and MOV-759A
~ RCP B, MOV-749B and MOV-759B 4)
Go to E-O, REACTOR TRIP OR SAFETY INJECTION.
H)P:
AP-CCW.2 TlTLE:
LOSS OF CCW DURING POWER OPERATION REV 11 PAGE 7 of 8
STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 6
Check for CCW Leakage In AUX BLDG:
o Start frequency of AUX BLDG sump pump(s)
NORMAL (Refer to RCS daily leakage log) o Waste holdup tank level STABLE OR INCREASING AS EXPECTED Dispatch AO to investigate AUX BLDG for CCW leakage.
7 Verify CCW System Leak IDENTIFIED AND ISOLATED Perform the following:
- b. Return to Step 2.
8 Verify CCW Surge Tank Level APPROXIMATELY 50+o AND STABLE Perform the following:
a.
Open RMW to CCW surge
- tank, MOV-823.
- b. Start RMW pump(s).
- c. Restore CCW surge tank level to 50'.
d.
Stop RMW pump and close MOV-823.
9 Direct RP To Sample CCW System For Chromates
EDP:
AP-CCW.2 LOSS OF CCW DURING POWER OPERATION REV:
11 PAGE 8 of 8
STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 10 Evaluate Plant Conditions:
a.
CCW system malfunction-IDENTIFIED AND CORRECTED
- a. Return to Step 1.
b.
CCW system status adequate for power operation (Refer to Tech Spec Section 3.3.3).
- b. IF shutdown required, THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.
NOTE:
Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
11 Notify Higher Supervision 12 Return To Procedure Or Guidance In Effect
-END-
EOP AP-CCW.2 TITLE:
LOSS OF CCW DURING POWER OPERATION REV:
11 PAGE 1 of 1
AP-CCW.2 APPENDIX LIST TITLE PAGES 1)
ATTACHMENT AT POWER CCW ALIGNMENT
EOP:
AP-CCW.3 TITLE:
LOSS OF CCW PLANT SHUTDOWN REV 9
PAGE 1 of 9
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLAN SUPERINTENDENT EFFECTI DATE CATEGORY 1.0 REVIEWED BY:
EOP AP-CCW.3 TITLE:
LOSS OF CCW PLANT SHUTDOWN REV:
9 PAGE 2 of 9
A.
PURPOSE This procedure provides the steps necessary to respond to a loss of CCW while the plant is shut down.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
ENTRY CONDITIONS This procedure may be entered from:
a.
AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP, or b ~
AP ELEC ~ 3
~
LOSS OF 1 2A AND/OR 1 2B TRANSFORMER (BELOW 350'F), or c.
AP-RHR.1, LOSS OF RHR, or d
AP RHR ~ 2 g LOSS OF RHR WHILE OPERATING AT REDUCED RCS INVENTORY CONDITIONS, when CCW malfunction indicated.
2.
SYMPTOMS
The symptoms of LOSS OF CCW
PLANT SHUTDOWN are:
a.
Annunciator A-6, CONT SPRAY PUMP COOLING WATER OUT LO FLOW 15 GPM, lit, or b.
Annunciator A-7, (A-15),
RCP A (B)
CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F, lit, or c.
Annunciator A-9, RHR PUMP COOLING WATER OUTLET LO FLOW 15 GPM, lit, or d.
Annunciator A-13, CCW SURGE TANK LO LEVEL 41.2'.,
lit, or e.
Annunciator A-14, SAFETY INJ PUMPS COOLING WATER OUT LO FLOW 25 GPM, lit, or f.
Annunciator A-17, MOTOR OFF RCP CCWP, lit, or g.
Annunciator A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI, lit, or h.
Annunciator A-24, (A-32),
RCP A (B)
OIL LEVEL
+/- 1.25, lit, or i.
Annunciator A-31, CCW SYSTEM LO FLOW 1800 GPM, lit.
I
COP:
AP-CCW.3 TITLE:
LOSS OF CCW PLANT SHUTDOWN REV 9
PAGE 3 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED x ***x ***********************
CAUTION o
IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 200'F, THEN TRIP THE AFFECTED RCP.
o IF CCW IS LOST, THEN SEAL INJECTION SHOULD BE MAINTAINED TO THE RCP(S)
UNTIL RCS TEMPERATURE IS LESS THAN 200'F, OR UNTIL CCW IS RESTORED.
x ******
x x *********************
NOTE:
o If leakage from the CCW system is indicated, then refer to ER-SC.5, HAZARDOUS AND MIXED WASTE MANAGEMENT AND CONTROL, for guidance.
o If CCW is lost to operating CS, RHR, or SI pumps, they may be left running for brief periods while isolating a CCW leak.
1 Check CCW Pump Status:
o Both CCW pump breaker white disagreement lights EXTINGUISHED o
Annunciator A-17, MOTOR OFF, RCP CCWP EXTINGUISHED IF a CCW pump has tripped, THEN perform the following:
a.
Ensure the other CCW pump is running.
- b. Attempt to reset and start the affected CCW pump if required for cooling.
- c. IF no CCW pumps available, THEN go to Step 4.
EOP:
AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN REV:
9 PAGE 4 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 2 Verify CCW Surge Tank Level Normal:
o Annunciator A-13, CCW SURGE TANK LO LEVEL 41.2%
EXTINGUISHED o
Level STABLE IF CCW surge tank level is decreasing, THEN perform the following:
a.
Open RMW to CCW surge tank, MOV-823.
- b. Start both RMW pumps.
- c. Dispatch AO to AUX BLDG to investigate for CCW leak 3 Verify Annunciator A-22, CCW PUMP DISCHARGE LO PRESS 60 PSIG EXTINGUISHED Dispatch AO to the AUX BLDG to perform the following:
~ MOV-738A
~ MOV-738B
- b. Investigate for CCW leaks.
KOP AP-CCW.3 TIILE:
LOSS OF CCW PLANT SHUTDOWN REV' PAGE 5 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED w *****
x
- x **% *% **********
CAUTION IF ANY RCP IS TRIPPED, THEN SHUTDOWN MARGIN REQUIREMENTS SHOULD BE VERIFIED (REFER TO 0-3.1, BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN).
% **4
% **% x x x A 4 x*********%
- x***4*%
- 4 Check RCS Temperature STABLE OR DECREASING IF S/G cooling available, THEN control S/G ARVs to stabilize RCS temperature.
IF S/G ARVs do NOT provide adequate
- cooling, THEN perform the following:
a.
Stop all but one RCP.
- b. Initiate S/G blowdown from both S/Gs.
- c. Maintain both S/G levels stable by controlling AFW flow.
5 Verify CCW Surge Tank Level GREATER THAN 104 Perform the following:
a.
Stop any running RCP.
- b. Pull stop both CCW pumps.
.c. Verify natural circulation (Refer to Attachment NC).
)h
EOP:
AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN REV 9
PAGE 6 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 6
a.
RCPs ANY RUNNING b.
Check RCP indications:
o Annunciator A-7 (A-15),
RCP A (B)
CCW RETURN HI TEMP OR LOW FLOW 165 GPM 125'F EXTINGUISHED o
Verify RCP motor bearing temperatures (PPCS GD RCPS or RK-30A recorder)
LESS THAN 200'F a.
Go to Step 7.
THEN perform the following:
- 1) Stop the affected RCP(s).
- 2) IF no RCPs running, THEN
- verify natural circulation (Refer to Attachment NC).
7 Check CCW System Leakage-ANY LEAKAGE INDICATED Go to Step 11.
EOP:
AP-CCW.3 TITLE:
LOSS OF CCW PLANT SHUTDOWN REV 9
PAGE 7 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 8
Check For CCW Leakage In CNMT:
a.
o Level STABLE o
Sump A pumps OFF
l) Direct RP Tech to sample sump A for chromates.
b.
RCP oil levels STABLE
- b. IF any RCP oil level increasing uncontrollably, THEN perform the following:
l) Stop affected RCP.
~ RCP A, MOV-749A and MOV-759A
~ RCP B, MOV-749B and MOV-759B
- 3) IF no RCPs running, THEN verify natural circulation (Refer to Attachment NC).
9 Check for CCW Leakage In AUX BLDG:
o Start frequency of AUX BLDG sump pump(s)
NORMAL (Refer to RCS daily leakage log) o Waste holdup tank level STABLE OR INCREASING AS EXPECTED Dispatch AO to investigate AUX BLDG for CCW leakage.
COP:
AP-CCW.3 Tl TLE:
LOSS OF CCW PLANT SHUTDOWN REV:
9 PAGE 8 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 10 Verify CCW System Leak IDENTIFIED AND ISOLATED Perform the following:
- b. Return to Step 2.
ll Check CCW Valve Alignment-AS REQUIRED FOR PLANT CONDITIONS'ealign valves as necessary to restore CCW to individual components.
12 Evaluate Plant Conditions:
a.
RHR normal cooling
- IN SERVICE b.
Check RCS Cooling:
o RCS temperature STABLE OR DECREASING o
CCW system status
- ADEQUATE FOR RHR NORMAL COOLING
- a. Adjust S/G ARVs as necessary to
'stabilize RCS temperature and go to Step 13.
- cooling, THEN go to AP-RHR.2, LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS or AP-RHR.2, LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.
NOTE; Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
13 Notify Higher Supervision
EOP AP-CCW.3 TITLE:
LOSS OF CCW PLANT SHUTDOWN REV' PAGE 9 of 9
STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 14 Return To Procedure Or Guidance In Effect
-END-
C 0
r0
COP:
AP-CCW ~ 3 LOSS OF CCW PLANT SHUTDOWN REV 9
PAGE 1 of 1 AP-CCW.3 APPENDIX LIST TITLE PAGES 1)
FIGURE MIN SUBCOOLING 2)
ATTACHMENT NC
OP:
AP-CCW.3 TITLE:
LOSS OF CCW PLANT SHUTDOWN REV:
9 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE:
Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0
S PRESSURE (PSIG)
SUBCOOLED REGION ADVERSE CNMT RCS PRESSURE INCREMENTS 20 PSIG NORMAL CNMT INADE(UATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
~
~
C