ML17262A351

Rev 14 to Reactor Trip or Safety Injection.

ML17262A351
Person / Time
Site:	Ginna
Issue date:	12/19/1990
From:	Marlow T ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262A347	List: ML17262A346 ML17262A348 ML17262A349 ML17262A351 ML17262A352 ML17262A354 ML17262A356
References
E, E-0, NUDOCS 9102070087
Download: ML17262A351 (60)

Text

EC" E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 14 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 8'~V E-0 REACTOR TRIP OR SAFETY INJECTION REV: 14 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-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.

4 Cl 4 h E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV 14 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.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.l, RESPONSE TO REACTOR RESTART/ATVS, 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 l.

P Pp C>>~u i' EC9: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 14 PAGE 4 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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.5 Verify SI and RHR Pumps~~Running: a.All SI pumps-RUNNING a.Perform the following:

1)Ensure SI pump suction supply open from BASTs or RVST.b.Both RHR pumps-RUNNING 2)Manually start pumps.b.Manually start pumps.

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EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 14 PAGE 5 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE 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 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 CNMT Spray Not Required: o Annunciator A-27, CNMT SPRAY-EXTINGUISHED o CNMT pressure-LESS THAN 28 PSIG Verify CNMT spray initiated.

IP CNMT spray NOT initiated, THEN perform the following:

a.Depress manual CNMT spray pushbuttons (2 of 2).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 F h f 444>>

EQP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 14 PAGE 6 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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: a.Go to Step 9.b.Ensure BOTH MSIVs closed and go to Step 9.c.Go to Step 9.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 affected S/G(s)d.Manually close valves.9 Verify MFW Isolation:

a.MFV pumps-TRIPPED b.MFV flow control valves-CLOSED~MFV regulating valves~MPV bypass valves c.S/G blowdown and sample valves-CLOSED a.Manually close MFV pump discharge valves and trip MPV pumps'.Place A and B S/G MFW~regulating valve and bypass valve controllers in MANUAL at OX demand.'.Place S/G blowdown and sample valve isolation switch to CLOSE.

k 1Q l IW I'~,1, EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV 14 PAGE 7 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED O 10.-Verify AFW Pumps Running: 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.

O 12 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 c.CNMT RECIRC fan coolers SW outlet valve status lights-BRIGHT b.Manually close CI and CVI valves.IF 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~FCV-4562 I cg (P'r+4, 1 ESP: E-0 T!TLE: REACTOR TRIP OR SAFETY INJECTION REV 14 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 RUNNING b.Verify CCW from excess letdovn (AOV-745)-CLOSED a.IF offsi,te power available, THEN manually start one CCW pump b.Manually close valve.14 Verify SI And RHR Pump Flow: a.SI flov indicators

-CHECK FOR FLOW b.RHR flov 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, THBN go to Step 15.15 Verify Total AFW Flow-GREATER THAN 200 GPM IF S/G narrov range level greater 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: E-0'TITLE: REACTOR TRIP OR SAFETY INJECTION REV 14 PAGE 9 of 26 STEP ACTION/BXPECTED RESPONSE RESPONSB NOT OBTAINBD 16 Verify AFW Valve Alignment:

a.AFW flow-INDICATED TO BOTH S/G(s)b.AFW flow from each MDAFW pump-LBSS 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:

1)Bnsure at least one SI pump suction valve from RWST open.~MOV-825A~MOV-825B 2)Ensure at least one valve in each SI pump suction line from BAST closed.~MOV-826A or MOV-826B~MOV-826C or MOV-826D b.Verify SI pump suction valves from BAST-OPEN~MOV-826A~MOV-826B~MOV-826C~MOV-826D c.Verify SI pump suction from RWST-CLOSED~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'ecessary.

k t ar k'l ECO: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 14 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, 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.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.2)Ensure SIi 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.

h ig't!.'4 E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV 14 PAGE 11 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************

CAUTION IP OPFSITE 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 SAPEGUARDS EQUIPMENT.

19 Check CCW Flow to RCP Thermal Barriers: o Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO PLOV-EXTINGUISHED o Annunciator A-15, RCP 1B CCW RETURN HI TEMP OR LO PLOW-EXTINGUISHED IP CCV to a RCP is lost, THEN perform the following:

a.Stop affected RCPs.b.Reset SI.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.IP large imbalance in seal injection flow exists, THEN consider local adjustment of V-300A and V-300B.

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ESP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 14 PAGE 12 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check If TDAFW Pump Can Be Stopped: a.Both MDAFV pumps-RUNNING b.PULL STOP TDAFV 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 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: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 14 PAGE 13 of 26 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 close PORVs.IF any valve can NOT be closed, THEN manually close its block valve.~MOV-516 for PCV-430~MOV-515 for PCV-'31C 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 IF block valve can NOT be closed, THEN go to E-l, LOSS OF.REACTOR OR SECONDARY COOLANT, Step l.b.Manually close auxiliary spray 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.Continue with Step 23.VHEN pressure less than 2260 psig, THEN do Steps 22d.d.Place controllers in MANUAL at OX demand.IF valves can NOT be closed, THEN stop associated RCP(s).

I 4+Y 1 r<q~A es 0 EGP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV 14 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 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 o Pressure in both S/Gs-GREATER THAN 100 PSIG IP any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step l.25 Check If S/G Tubes Are Intact: 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 Go to E-3, STEAM GENERATOR TUBE RUPTURE;Step l.

'ki ECP: E-0 REACTOR TRIP OR SAFETY INJECTION REV'4 PAGE 15 of 26 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 l.~R-2~R-7~R-29~R-30 b.CNMT pressure-LESS THAN.5 PSIG c.CNMT sump B level-LESS THAN 10 FEET 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 OR INCREASING IF RCS pressure decreasing with PRZR level stable or increasing, THEN stop both RCPs.

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ECP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 14 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 gl P l'lg 4>>, I t J E l' ESP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV 14 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 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.IP narrow range level in any S/G continues to increase in an uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

1 gl J+if:+t I~ECP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV 14 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 I***=**************************************

CAUTION 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 ISOLATION-EXTINGUISHED b.Perform the following:

1)Reset SI.2)Operate CI reset key switch.

E-0 REACTOR TRIP OR SAFETY INJECTION REV: 14 PAGE 19 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Verify Adequate SW Flow: a.At least three SW pumps-RUNNING b.Dispa'tch AO to establish normal shutdown alignment (Refer to Attachment SD-1)a.Manually start SW pumps as power supply permits (258 kw each).IF less than three pumps running, THEN ensure SW isolation.

P w V ,rq C J ECP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 14 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 395'F o Pressure-STABLE OR INCREASING e.Reset both trains of XY relays for IA to CNMT AOV-5392 f.Verify IA to CNMT AOV-5392-OPEN 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 REClRC FANS)~3)VHRN bus 15 restored, THEN reset control room ligKting.b.Manually align valves.c.Manually start air compressors 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.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.

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E"P: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 14 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 l.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 TlTLE: REACTOR TRIP OR SAFETY INJECTION REV: 14 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: 1)Pressure-GREATER THAN 250 PSIG 2)Pressure-STABLE OR INCREASING 1)Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1'.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 kv each).IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer to Attachment CNMT RECIRC FANS).

l m.S' E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV 14 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 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: b.Charging pump suction aligned to RWST: o LCV-112B-OPEN o LCV-112C-CLOSED c.Start charging pumps as necessary and adjust charging flow to restore PRZR level~V-300A for RCP A~V-300B for RCP B 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.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).

0 EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 14 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 Cy 7i I C C 4 lv<c 44 EOP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV 14 PAGE 25 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 43 Check If Emergency D/Gs Should Be Stopped: '.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.b.Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)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).

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EO~: E-0 REACTOR TRIP OR SAFETY INJECTION REV 14 PAGE 26 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 44 Return to Step 21-END-I%4 E-0 REACTOR TRIP OR SAFETY INJECTION REV 14 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 14 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 4 1 I'C0 Oq 4 h~" II I'g 1 EIII: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV 14 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)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300, 350 400 , 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE

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E Ql lg 1 ll 4 EC)E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 14 PAGE 1 of 1 NOTE: FOLDOUT PAGE The Critical Safety Function Red Path Summary is available in APPENDIX 1.RCP TRIP CRITERIA 2~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]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 3~-OR-o Any automatic SI setpoint reached 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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