ML17262A352
| ML17262A352 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/09/1991 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17262A347 | List: |
| References | |
| E, E-0, NUDOCS 9102070092 | |
| Download: ML17262A352 (56) | |
Text
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E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 1 of 26 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE
/
T SUPERI TE ENT
-9 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
9102070092 9i020i PDR ADOCK 05000244 P
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E-0 REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 2 of 26 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 require a reactor trip, if one has not occurred:
o Any plant parameter reaches a reactor trip setpoint and logic as listed in procedure P-l, REACTOR CONTROL AND PROTECTION SYSTEM.
o Operator discrection.
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 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 3 of 26 STEP ACTION/BXPECTED RBSPONSE RBSPONSE NOT OBTAINED NOTE:
o Steps 1 through 12 are IMMEDIATE ACTION steps.
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.
O 1
Verify Reactor Trip:
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 any power range channel greater than 5X OR MRPI indicates more than one control rod not fully
- inserted, THEN go to FR-S.1,
RESPONSE
TO REACTOR RESTART/ASS, Step 1
O 2
Verify Turbine Stop Valves CLOSED Manually trip turbine.
IF turbine trip can NOT be
- verified, THEN close both MSIVs.
3 Verify Both Trains Of AC Emergency Busses Energized To At Least 420 VOLTS:
~ Bus 14 and Bus 18
~ Bus 16 and Bus 17 Attempt to start any failed emergency D/G to restore power to all AC emergency busses.
IF power can NOT be restored to at least one train, THEN go to ECA-O.O, LOSS OF ALL AC POVER, Step 1.
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E-0 REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 4 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED O
4 Check If Any SI Annuciator LIT 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 Safeguards sequencing started
-OR-o Operator determines SI required IF SI is NOT required, THEN go to ES-0.1, REACTOR TRIP RESPONSE, Step l.
O 5
Verify SI and RHR Pumps Running:
- a. All SI-pumps - RUNNING
- b. Both RHR pumps - RUNNING
- a. Perform the following:
- 1) Ensure SI pump suction supply open from BASTs or RVST.
- 2) Manually start pumps.
- b. Manually start pumps.
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E-0 REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 5 of 26 STEP ACTION/EXPECTED RBSPONSE RESPONSB NOT OBTAINED 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 vith 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
O 7
Verify CNMT Spray Not Required:
o Annunciator A-27, CNMT SPRAY-EXTINGUISHED o
CNMT pressure
- LBSS THAN 28 PSIG Verify CNMT spray initiated.
IR CNMT spray NOT initiated, THEN perform the folloving:
- a. Depress manual CNMT spray pushbuttons (2 of 2).
- b. Ensure CNMT spray pumps running.
- c. Bnsure CNMT spray pump discharge valves open.
~ MOV-860A
~ MOV-860B
~ MOV-860C
~ MOV-860D
- d. Bnsure NaOH tank outlet valves open.
~ AOV-836A
~ AOV-836B
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E-0 REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 6 of 26 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 (3.6xlO~ lb/hr) from either S/G
- d. Verify MSIV closed on the affected S/G(s)
- d. Manually close valves.
O 9
Verify MFW Isolation:
a.
MFV pumps - TRIPPED b.
MFW flow control valves - CLOSED
~ MFV","r'egulating valves
~ MFV-",bypass valves c.
S/G blowdown and sample valves
- CLOSED
- a. Manually close MFV pump discharge valves and trip MFW pumps.
- b. Place A and B S/G MFV regulating valve and bypass valve controllers in MANUAL at OX demand.
- c. Place S/G blowdown and sample valve isolation switch to CLOSE.
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E-0 REACTOR TRIP OR SAFETY INJECTION REV 15, PAGE 7 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED O
10 Verify AFW Pumps Running:
a.
MDAFW pumps - RUNNING b.
TDAPW pump - RUNNING IF NECESSARY
- a. Manually start MDAFW pumps.
- b. Manually open steam supply valves.
~ MOV-3505A
~ MOV-3504A Oll Verify At Least Two SW Pumps RUNNING Perform the following:
- a. Ensure one SV pump running on each energized screenhouse AC-.
emergency bus:
~ Bus 17
~ Bus 18
- b. IP offsite power NOT available, THEN ensure SV isolation.
- 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 c.
CNMT RECIRC fan coolers SV outlet valve status lights-BRIGHT
- b. Manually close CI and CVI valves.
IP valves can NOT be
- closed, THEN dispatch AO to locally close valves (Refer to Attachment CI/CVI).
- c. Dispatch AO to locally fail open valves.
~ FCV-4561
~ PCV-4562
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E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 8 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION RCP TRIP CRITERIA LISTED ON FOLDOUT PAGE SHOULD BE MONITORED PERIODICALLY.
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 b.
RHR flow indicator - CHECK FOR FLOW
- a. IF RCS pressure less than 1400 psig, THEN manually start pumps and align valves.
IF
- NOT, THEN go to Step 15.
- 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 5X (25X adverse CNMT) in any S/G, THEN control AFW flow to maintain narrow range level.
IF narrow range level less than 5X
[25X adverse CNMT] 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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I E-0 TIALE:
REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 9 of 26 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 Alignment:
a.
Check BAST level:
o Level - GREATER THAN 10X o
Annunciator B-23, BORIC ACID TANK LO LO LEVEL-EXTINGUISHED
- a. Perform the following:
~ 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
~ MOV-825A
~ MOV-825B 3)
Go to Step 18.
- b. Ensure both valves in either flow path open.
o MOV-826A and MOV-826B
-OR-o MOV-826C and MOV-826D
- c. Manually align valves as necessary.
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E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 10 of 26 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
- a. Ensure at least one valve open.
- b. Manually start pump on available bus.
- c. Perform the folloving:
- 1) Ensure SI pumps B and C
running.
- 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 folloving:
- 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 SI pump C discharge valves - OPEN
~ MOV-871A
~ MOV-871B 3)
Go to Step 19.
- e. Manually open valves as necessary.
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E-0 TlTLE:
REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 11 of 26 STBP ACTION/BXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF OFFSITE POWBR IS LOST AFTER SI RESET, SELECTED SV PUMPS AND ONE CCV PUMP VILL AUTO START ON EMERGENCY D/G.
MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMBNT.
19 Check CCW Flow to RCP Thermal Barriers:
o Annunciator A-7, RCP 1A CCV 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 CCV RETURN HI TEMP OR LO FLOV-EXTINGUISHED
- c. Verify adequate pover available to run one charging pump (75 kw).
- d. Start one charging pump at minimum speed for seal infection.
- e. Ad)ust HCV-142 to establish either of the folloving:
o Labyrinth seal D/P to each RCP greater than 15 inches of vater.
-OR-o RCP seal infection flov to each RCP greater than 6 gpm.
- f. IF large imbalance in seal infection flow exists, THEN consider local ad)ustment of V-300A and V-300B.
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15 PAGE 12 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 20 Check If TDAFW Pump Can Be Stopped:
- a. Both MDAFW pumps - RUNNING b.
PULL STOP TDAFW pump steam supply valves
~ MOV-3504A
~ MOV-3505A a.
Go to Step 21.
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. IF cooldovn continues, THEN control total feed flov greater than 200 gpm until narrov range level greater than 5X [25X adverse CNMT] in at least one S/G.
c.
WHEN S/G level greater than 5X
[25X adverse CNMT) in one S/G, THEN limit feed flov to that required to maintain level in at least one S/G.
- d. IF cooldovn 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.
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E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 13 of 26 STBP ACTION/EXPECTED RESPONSE RESPONSB NOT OBTAINBD 22 Check PRZR PORVs And Spray Valves:
a.
PORVs -
CLOSED
- b. Auxiliary spray valve (AOV-296)
- CLOSED
- c. Check PRZR pressure
- LESS THAN 2260 PSIG
- d. Verify.'normal PRZR spray valve controllers -
DEMAND AT OX
- a. IP PRZR pressure less than 2335 psig, THEN manually close PORVs.
IP any valve can NOT be closed, THEN manually close its block valve.
~ MOV-516 for PCV-430
~ MOV-515 for PCV-431C IF block valve can NOT be
- closed, THBN go to E-l, LOSS OP REACTOR OR SECONDARY COOLANT'tep l.
- b. Manually close auxiliary spray valve.
IP valve can NOT be
- closed, THEN perform the following:
- 1) Decrease charging pump flow to minimum.
- 2) Ensure charging valve to loop B cold leg open (AOV-294).
- c. Continue with Step 23.
@HEN pressure less than 2260 psig, THEN do Steps 22d.
- d. Place controllers in MANUAL at OX demand.
IP valves can NOT be closed, THEN stop associated RCP(s).
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E-0 T1TLE:
REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 14 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 23 Check If RCPs Should Be Stopped:
a.
RCP status
- ANY RCP RUNNING
- b. SI pumps - AT LEAST TVO 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 o
Pressure in both S/Gs - GREATER THAN 100 PSIG IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
25 Check If S/G Tubes Are Intact:
o Air ejector radiation monitors (R-15 or R-15A) - NORMAL o
S/G blovdown radiation monitor (R-19) - NORMAL o
Steamline radiation monitors (R-31'~and R-32) - NORMAL Go to E-3, STEAM GENERATOR TUBE
- RUPTURE, Step 1.
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E-O REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 15 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 26 Check If RCS Is Intact:
a.
CNMT area radiation monitors-NORMAL
~ R-2
~ R-7
~ R-29
~ R-30 Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step l.
b.
CNMT pressure
- LESS THAN
.5 PSIG c.
CNMT sump B level - LESS THAN 10 FEET 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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E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 16 of 26 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 b.
RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING
- c. Secondary heat sink:
o Total feed flow to S/Gs-GREATER THAN 200 GPM a.
Do NOT stop SI pumps.
Go to Step 30.
b.
Do NOT stop SI pumps.
Go to Step 30.
- 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 5X d.
PRZR level - GREATER THAN 5X 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.
29 Go To ES-1. 1, SI TERMINATION, Step 1
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E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 17 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
o Conditions should be evaluated for Site Contingency Reporting (Refer to SC-100, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
o The Critical Safety Function Red Path Summary is available in APPENDIX l.
30 Initiate Monitoring of Critical Safety Function Status Trees CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFV PUMPS VILL BE NECESSARY (REFER TO ER-AFV.l, ALTERNATE VATER SUPPLY TO AFV PUMPS).
31 Check S/G Levels:
- a. Narrow range level - GREATER THAN 5X
- b. Control feed flow to maintain narrow range level between 17X and 50X
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5X 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-15 PAGE 18 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 32 Check Secondary Radiation Levels NORMAL o
Steamline radiation monitor (R-31 and R-32) o Dispatch AO to locally check steamline radiation Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.
o Request HP sample S/Gs for activity CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, SELECTED SV PUMPS AND ONE CCW PUMP WILL AUTO START ON EMERGENCY D/G.
MANUAL ACTION VILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
33 Reset SI 34 Reset CI:
- a. Operate CI reset key switch
- b. Verify annunciator A-26, CNMT ISOLATION - EXTINGUISHED
- b. Perform the following:
- 1) Reset SI.
- 2) Operate CI reset key switch.
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E-0 REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 19 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 35 Verify Adequate SW Flow:
- a. At least three SW pumps-RUNNING
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
- a. Manually start SW pumps as power supply permits (258 kw each).
IP less than three pumps
- running, THEN ensure SW isolation.
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E-0 REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 20 of 26 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 SV 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
- a. 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 RECRRC PANS).
3)
WHEN bus 15 restored, THEN reset control room ligKting.
- 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.1, LOSS OF INSTRUMENT AIR).
- 2) Continue with Step 37.
WHEN IA restored, THEN do Steps 36e and f.
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E-0 REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 21 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 37 Check Auxiliary Building Radiation NORMAL
~ Plant vent iodine (R-10B)
~ Plant vent particulate (R-13)
~ Plant vent gas (R-14)
~ CCV liquid monitor (R-17)
~ LTD line monitor (R-9)
~ CHG pump room (R-4)
Evaluate cause of abnormal conditions.
IF the cause is a loss of RCS inventory outside CNMT, THEN go to ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
38 Check PRT Conditions o
PRT level (LI-442) - LESS THAN 84X o
PRT temperature (TI-439) - LESS THAN 120'F o
PRT pressure (PI-440A) - LESS THAN 3 PSIG Evaluate the following flowpaths for cause of abnormal conditions:
~ RCP seal return relief
~ PRZR PORVs
~ PRZR safeties
~ Letdown line relief IF excess letdown previously in
- service, THEN close AOV-310, excess letdown isolation valve from loop A cold.
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E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 22 of 26 STBP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION RCS PRESSURE SHOULD BE MONITORED.
IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG, THE RHR PUMPS MUST BE MANUALLYRESTARTED TO SUPPLY WATER TO THE RCS.
39 Check If RHR Pumps Should Be Stopped:
a.
Check RCS pressure:
- 1) Pressure
- GRBATER THAN 250 PSIG
- 2) Pressure
- STABLE OR INCREASING
- b. Stop both RHR pumps and place in AUTO 1)
Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
2)
Go to Step 40.
40 Check Normal Power Available To Charging Pumps:
o Bus 14 normal feed breaker-CLOSED o
Bus 16 normal feed breaker-CLOSBD Verify adequate emergency D/G capacity to run charging pumps (75 kw each).
IF NOT, THBN evaluate if CNMT RECIRC fans can be stopped (Refer to Attachment CNMT RECIRC FANS).
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E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 23 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 41 Check If Charging Flow Has Been Established:
- a. Charging pumps - ANY RUNNING
- a. Perform the following:
- 1) IP CCW flow is lost to any RCP thermal barrier OR any RCP fl 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
- b. Charging pump suction aligned to RWST:
o LCV-'112B - OPEN o
LCV-112C - CLOSED
- 2) Ensure HCV-142 open, demand at OX.
- b. Manually align valves as necessary.
Ip LCV-112B can NOT be opened, THEN perform the following:
- 1) Verify charging pump A NOT running and place in PULL STOP.
- c. Start charging pumps as necessary and ad)ust charging flow to restore PRZR level
- 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).
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E-0 REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 24 of 26 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
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E-0 TITLE:
REACTOR TRIP OR SAFETY INJECTION REV 15 PAGE 25 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 43 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses energized by offsite pover:
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 folloving:
- 1) Verify non-safeguards bus tie breakers closed:
~ Bus 13 to Bus 14 tie
~ Bus 15 to Bus 16 tie
- 2) Place the folloving 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 pover to MCCs:
~ A from Bus 13
~ B from Bus 15
~ E from Bus 15
~
R from Bus 15
- b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)
- 5) Refer to Attachment SI/UV for other equipment lost vith loss of offsite power.
- 6) Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OR ORRSITE POWER).
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E-0 REACTOR TRIP OR SAFETY INJECTION REV:
15 PAGE 26 of 26 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 44 Return to Step 21
-END-
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E-0 REACTOR TRIP OR SAFETY INJECTION REV:
15 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
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E-0 REACTOR TRIP OR SAFETY INJECTION REV 15 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 temperature less than 285'F e.
CONTAINMENT CNMT pressure greater than 60 psig
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