ML17262A351
| ML17262A351 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/19/1990 |
| From: | Marlow T ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17262A347 | List: |
| References | |
| E, E-0, NUDOCS 9102070087 | |
| Download: ML17262A351 (60) | |
Text
EC" TITLE: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 26 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT E FECTI E DATE CATEGORY 1.0 REVIEWED BY:
9i02070087 9i020i PDR ADOCK 05000244 P PDR
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REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION 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 that require reactor trip, 1.
if onefollowing The are symptoms has not. occurred:
a o Any plant parameter reaches a reactor trip setpoint and logic as listed in procedure P-1, 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-l, 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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TITLE: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 3 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE 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.
O1 Verify Reactor Trip:
o At least one train of reactor Manually trip reactor.
IF reactor trip breakers NOT open, trip breakers - OPEN THEN perform the following:
o Neutron flux - DECREASING a. Open Bus 13 and Bus 15 normal feed breakers.
o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM 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.l, RESPONSE TO REACTOR RESTART/ATVS, Step 1 O2 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 Attempt to start any failed Emergency Busses Energized emergency D/G to restore power to To At Least 420 VOLTS: all AC emergency busses.
~ Bus 14 and Bus 18 IF power can NOT be restored to at
~ Bus 16 and Bus 17 least one train, THEN go to ECA-O.O, LOSS OF ALL AC POVER, Step l.
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EC9: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 4 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check LIT If Any SI Annuciator 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.
5 Verify SI
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and RHR Pumps Running:
~
- a. All SI pumps - RUNNING a. Perform the following:
- 1) Ensure SI pump suction supply open from BASTs or RVST.
- 2) Manually start pumps.
- b. Both RHR pumps - RUNNING b. Manually start pumps.
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EOP: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 5 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED O 6 Verify CNMT Running:
RECIRC Fans
- a. All fans - RUNNING a. Manually start fans.
- b. Charcoal filter dampers green b. Dispatch personnel to relay status lights - EXTINGUISHED 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 O 7 Verify Required:
CNMT Spray Not Verify CNMT spray IP CNMT spray NOT initiated.
initiated, THEN o Annunciator A-27, CNMT SPRAY- perform the following:
EXTINGUISHED
28 PSIG
- b. Ensure CNMT spray pumps running.
- c. Ensure CNMT spray pump discharge valves open.
~ MOV-860A
~ MOV-860B
~ MOV-860C
~ MOV-860D
- d. Ensure NaOH tank outlet valves open.'
AOV-836A
~ AOV-836B
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EQP: TITLE: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 6 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check If Main Steamlines Should Be Isolated:
- a. Any MSIV - OPEN a. Go to Step 9.
- c. Check if ANY main steamlines c. Go to Step 9.
should be isolated:
o Low Tavg (545'F) AND high steam flow (0.4x10~ lb/hr) from either S/G
-OR-o High-High steam flow (3.6xlO~ lb/hr) from either S/G
- d. Verify MSIV closed on the d. Manually close valves.
affected S/G(s) 9 Verify MFW Isolation:
- a. MFV pumps - TRIPPED a. Manually close MFV pump discharge valves and trip MPV pumps'.
- b. MFV flow control valves - CLOSED Place A and B S/G MFW
~
regulating valve and bypass
~ MFV regulating valves valve controllers in MANUAL at
~ MPV bypass valves OX demand.
- c. S/G blowdown and sample valves Place S/G blowdown and sample
- CLOSED valve isolation switch to CLOSE.
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EOP: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 7 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED O .-Verify 10 AFW Pumps Running:
- a. Manually start pumps.
- b. TDAFW pump - RUNNING IF b. Manually open steam supply NECESSARY valves.
~ MOV-3505A
~ MOV-3504A O11 Verify At Least RUNNING Two SW Pumps Perform the following:
~ Bus 17
~ Bus 18
- b. IF offsite power NOT available, THEN ensure SW isolation.
O12 Verify CI And CVI:
- a. CI and CVI annunciators - LIT a. Depress manual CI pushbutton.
~ Annunciator A-26, CNMT ISOLATION
~ Annunciator A-25, CNMT VENTILATION ISOLATION
- b. Verify CI and CVI valve status b. Manually close CI and CVI lights - BRIGHT valves. IF valves can NOT be closed, THEN dispatch AO to locally close valves (Refer to Attachment CI/CVI).
- c. CNMT RECIRC fan coolers SW c. Dispatch AO to locally fail outlet valve status lights- open valves.
BRIGHT
~ FCV-4561
~ FCV-4562
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ESP: T!TLE: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 8 of 26 STBP 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 a. IF offsi,te power available, RUNNING THEN manually start one CCW pump
- b. Verify CCW from excess letdovn b. Manually close valve.
(AOV-745) - CLOSED 14 Verify SI And RHR Pump Flow:
- a. SI flov indicators - CHECK FOR a. IF RCS pressure less than FLOW 1400 psig, THEN manually start pumps and align valves. IF NOT, THEN go to Step 15.
- b. RHR flov indicator - CHECK FOR b. IF RCS pressure less than FLOW 140 psig, THEN manually start pumps and align valves. IF NOT, THBN go to Step 15.
15 Verify Total AFW Flow IF S/G narrov range level greater GREATER THAN 200 GPM than 5X [25X adverse CNMT] in any S/G, THEN control AFW flow to maintain narrov range level.
IF narrov range level less than 5X
[25X adverse CNMT] in all S/Gs, THEN manually start pumps and align valves as necessary. IF AFW flov greater than 200 gpm can NOT be established, THEN go to FR-H.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step l.
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EGP: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 9 of 26 STEP ACTION/BXPECTED RESPONSE RESPONSB NOT OBTAINBD 16 Verify AFW Valve Alignment: Manually align valves as necessary.
- a. AFW flow - INDICATED TO BOTH S/G(s)
- a. Check BAST level: a. Perform the following:
o Level - GREATER THAN 10X 1) Bnsure 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 18.
- 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
~ MOV-825A
~ MOV-825B
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ECO: TITLE: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION 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 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-871A open o MOV-871B closed
- 3) Go to Step 19.
- d. Verify SI pump B - RUNNING, d. Perform the following:
- 1) Ensure SI pumps A and C running.
- 2) Ensure SIi pump C aligned to discharge line B:
o MOV-871B open o MOV-871A closed
- 3) Go to Step 19.
- e. Verify SI pump C discharge e. Manually open valves as valves - OPEN necessary.
~ MOV-871A
~ MOV-871B
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TITLE: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 11 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
19 Check CCW Flow to RCP IP CCV to a RCP is lost, THEN Thermal Barriers: perform the following:
o Annunciator A-7, RCP 1A CCW a. Stop affected RCPs.
RETURN HI TEMP OR LO PLOV-EXTINGUISHED b. Reset SI.
o Annunciator A-15, RCP 1B CCW c. Verify adequate power available RETURN HI TEMP OR LO PLOW- ~
to run one charging pump EXTINGUISHED (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. IP large imbalance in seal injection flow exists, THEN consider local adjustment of V-300A and V-300B.
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ESP: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 12 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check Stopped:
If TDAFW Pump Can Be
- a. Both MDAFV pumps - RUNNING a. Go to Step 21.
- b. PULL STOP TDAFV pump steam supply valves
~ MOV-3504A
~ MOV-3505A 21 Check RCS Tavg STABLE AT IF temperature less than 547'F and OR TRENDING TO 547'F decreasing, THEN perform the following:
- a. Stop dumping steam.
- b. IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level greater than 5X [25%
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 flow to that required to maintain level in at least one S/G.
- d. 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.
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EOP: TITLE: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 13 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Check PRZR PORVs And Spray Valves:
IF any valve can NOT be closed, THEN manually close its block valve.
~ MOV-516 for PCV-430
~ MOV-515 for PCV-'31C IF block valve can NOT be closed, THEN go to E-l, LOSS OF.
REACTOR OR SECONDARY COOLANT, Step l.
- b. Auxiliary spray valve (AOV-296) b. Manually close auxiliary spray
- CLOSED valve. IF 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. Check PRZR pressure - LESS THAN c. Continue with Step 23. VHEN 2260 PSIG pressure less than 2260 psig, THEN do Steps 22d.
- d. Verify normal PRZR spray valve d. Place controllers in MANUAL at controllers - DEMAND AT OX OX demand. IF valves can NOT be closed, THEN stop associated RCP(s).
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EGP: TITLE: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 14 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check Stopped:
If RCPs Should Be
- b. SI pumps - AT LEAST TWO RUNNING b. Go to Step 24.
- c. RCS pressure minus maximum S/G c. Go to Step 24.
pressure - LESS THAN 175 psig
[400 psig adverse CNMT]
- d. Stop both RCPs 24 Check If S/G Is Intact:
Secondary Side IP any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN go o Pressure in both S/Gs - STABLE to E-2, FAULTED STEAM GENERATOR OR INCREASING ISOLATION, Step l.
o Pressure in both S/Gs - GREATER THAN 100 PSIG 25 Check Intact:
If S/G Tubes Are Go to E-3, STEAM GENERATOR TUBE RUPTURE; Step l.
o Air ejector radiation monitors (R-15 or R-15A) - NORMAL o S/G blowdown radiation monitor (R-19) - NORMAL o Steamline radiation monitors (R-31 and R-32) - NORMAL
'ki ECP: REV'4 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 15 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check If RCS Is Intact: Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step l.
- a. CNMT area radiation monitors-NORMAL
~ R-2
~ R-7
~ R-29
~ R-30
- b. CNMT pressure - LESS THAN
.5 PSIG
- d. CNMT sump A level o 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 IF RCS pressure decreasing with OR INCREASING PRZR level stable or increasing, THEN stop both RCPs.
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- ECP: TITLE: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 16 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check If Terminated:
SI Should Be
o Pressure - GREATER THAN 1625 PSIG o Pressure - STABLE OR INCREASING
USING FIGURE MIN SUBCOOLING
- c. Secondary heat sink: c. IF neither condition met, THEN do NOT stop SI pumps. Go to o Total feed flow to S/Gs- Step 30.
GREATER THAN 200 GPM
-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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ESP: TITLE: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION 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 Punction Red Path Summary is available in APPENDIX 1.
30 Initiate Monitoring of Critical Safety Function Status Trees CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO APW PUMPS).
31 Check S/G Levels:
- a. Narrow range level - GREATER a. Maintain total feed flow THAN 5X greater than 200 gpm until narrow range level greater than 5X in at least one S/G.
- b. Control feed flow to maintain b. IP narrow range level in any narrow range level between 17X S/G continues to increase in an and 50X uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
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ECP: TITLE: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 18 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 Check Secondary Radiation Go to E-3, STEAM GENERATOR TUBE Levels NORMAL RUPTURE, Step l.
o Steamline radiation monitor (R-31 and R-32) o Dispatch AO to locally check steamline radiation o Request HP sample S/Gs for activity
- =******************************* CAUTION I
IF OFFSITE POVER IS LOST AFTER SI RESET, SELECTED SW PUMPS AND ONE CCV PUMP VILL 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 b. Perform the following:
ISOLATION - EXTINGUISHED
- 1) Reset SI.
- 2) Operate CI reset key switch.
REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 19 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Verify Adequate SW Flow:
- a. At least three SW pumps- a. Manually start SW pumps as RUNNING power supply permits (258 kw each).
IF less than three pumps running, THEN ensure SW isolation.
- b. Dispa'tch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
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ECP: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 20 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 Establish IA to CNMT:
- a. Verify non-safeguards busses a. Perform the following:
energized from offsite power
- 1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:
-OR- ~ Bus 13 to Bus 14 tie
~ Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED
- 2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).
IF NOT, THEN CNMT RECIRC evaluate if fans should be stopped (Refer to Attachment CNMT REClRC FANS) ~
- 3) VHRN bus 15 restored, THEN reset control room ligKting.
- b. Verify SV isolation valves to b. Manually align valves.
turbine building - OPEN
~ MOV-4613 and MOV-4670
~ MOV-4614 and MOV-4664
- c. Verify at least two air c. Manually start air compressors compressors - RUNNING as power supply permits (75 kw each). IR air compressors can
~N T be started, THEN dispatch AO to locally reset compressors as necessary.
- d. Check IA supply: d. Perform the following:
o Pressure - GREATER THAN 395'F 1) Continue attempts to restore IA (Refer to AP-IA.l, LOSS o Pressure - STABLE OR OF INSTRUMENT AIR).
INCREASING
- 2) Continue with Step 37. WHEN IA restored, THEN do Steps 36e and f.
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E"P: TITLE: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 21 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 37 Check Auxiliary Building Evaluate cause of abnormal Radiation NORMAL conditions.
~ Plant vent iodine (R-10B) IF the cause is a loss of RCS
~ Plant vent particulate (R-13) inventory outside CNMT, THEN go to
~ Plant vent gas (R-14) ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step l.
~ CCV liquid monitor (R-17)
~ LTD line monitor (R-9)
~ CHG pump room (R-4) 38 Check PRT Conditions Evaluate the following flowpaths for cause of abnormal conditions:
o PRT level (LI-442) - LESS THAN 84X ~ RCP seal return relief
~ PRZR PORVs o PRT temperature (TI-439) - LESS ~ PRZR safeties THAN 120'F ~ Letdown line relief o PRT pressure (PI-440A) - LESS IF excess letdown previously in THAN 3 PSIG service, THEN close AOV-310, excess letdown isolation valve from loop A cold.
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TlTLE: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 22 of 26 STEP ACTION/EXPECTED RESPONSE 'RESPONSE NOT OBTAINED
- * * * * * * * * * * * * * * 'k * * * * * * * * * * * * * * * * * * * * * * * *
- CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG, THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
39 Check If RHR Pumps Should Be Stopped:
- a. Check RCS pressure:
- 2) Pressure - STABLE OR 2) Go to Step 40.
INCREASING
- b. Stop both RHR pumps and place in AUTO 40 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kv each).
o Bus 14 normal feed breaker-CLOSED IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker- to Attachment CNMT RECIRC FANS).
CLOSED
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TITLE: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 23 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 41 Check Been If Charging Established:
Flow Has
- a. Charging pumps - ANY RUNNING a. Perform the following:
- 1) IP CCV flow is lost to any RCP thermal barrier OR any RCP fl seal outlet temperature offscale high, THEN dispatch AO with key to RVST 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 OX.
- b. Charging pump suction aligned b. Manually align valves as to RWST: necessary.
o LCV-112B - OPEN IP LCV-112B can NOT be opened, THEN perform the following:
o LCV-112C - CLOSED
- 1) Verify charging pump A NOT running and place in PULL STOP.
- 2) Dispatch AO to locally open manual charging pump suction from RVST (V-358 located in charging pump room).
- 3) VHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
- c. Start charging pumps as necessary and adjust charging flow to restore PRZR level
0 EOP: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION 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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EOP: TITLE: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 25 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 43 Check If Emergency Should Be Stopped:
D/Gs Verify AC emergency busses a. Perform the following:
energized by offsite power:
- 1) Verify non-safeguards bus o Emergency D/G output tie breakers closed:
breakers - OPEN
~ Bus 13 to Bus 14 tie o AC emergency bus voltage- ~ Bus 15 to Bus 16 tie GREATER THAN 420 VOLTS
- 2) Place the following pumps in o AC emergency bus normal feed PULL STOP:
breakers - CLOSED
~ 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.
- 6) Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POVER).
- b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)
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EO~: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 26 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 44 Return to Step 21
-END-
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REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION 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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REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION 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 2)5'F
- e. CONTAINMENT CNMT pressure greater than 60 psig
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EIII: TITLE: REV 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 2300 RCS PRESSURE INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOLING 600 REGION 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0
200 250 300, 350 400 , 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
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EC) TITLE: REV: 14 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 FOLDOUT PAGE NOTE: The Critical Safety Function Red Path Summary is available in APPENDIX 1.
RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:
- a. SI pumps AT LEAST TWO RUNNING
- b. RCS pressure minus maximum S/G pressure LESS THAN 175 psig
[400 psig adverse CNMT]
2 ~ SI ACTUATION CRITERIA IF ANY condition listed below occurs, THEN actuate SI and go to E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o RCS subcooling based on core exit T/Cs LESS THAN O' USING FIGURE MIN SUBCOOLING
-OR-o PRZR level LESS THAN 54 [304 adverse CNMT]
AND RCS subcooling based on core exit T/Cs LESS THAN 20'F USING FIGURE MIN SUBCOOLING
-OR-o Any automatic SI setpoint reached 3 ~ SI PUMP AUTO SWITCHOVER CRITERION WHEN BAST level decreases to 104, THEN ensure SI pump automatic switchover to RWST.
4 ~ AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
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