ML17262A164

Rev 13 to EOP E-O, Reactor Trip or Safety Injection.

ML17262A164
Person / Time
Site:	Ginna
Issue date:	08/08/1990
From:	Marlow T ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262A163	List: ML17262A162 ML17262A164 ML17262A165
References
E, E-0, NUDOCS 9010020146
Download: ML17262A164 (60)

Text

EOP: TITLE: REV 13 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 F'o o EFF CT VE DATE GiNNA STA! lON S 'ART:

DATE CATEGORY 1.0 Tl iVjE REVIEWED BY: COSY PLETED.

DATE 90100 TlME PDR ~~ ~00921 P OCK P>0002yy PDC, )

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REV 13 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-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-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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EOP: TITLE: REV: 13 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 ROLDOUT 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: Manually trip reactor.

reactor trip breakers o At least one train of reactor IR 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 DOWN RODS ON BOTTOM b. Verify rod drive MG sets tripped:

c. Close Bus 13 and Bus 15 normal feed breakers.

d. Reset lighting breakers.

IR any power range channel greater than 5X OR MRPI indicates more than one control rod not fully inserted, THEN go to RR-S.1, RESPONSE TO REACTOR RESTART/ATWS, Step 1 O 2 Verify Turbine Stop Valves CLOSED Manually trip turbine.

IR turbine trip can NOT be verified, THEN close both MSIVs.

3 Verify Both Trains Of AC Attempt to start any failed Emergency Busses Energized To emergency D/G to restore power to At Least 420 VOLTS: all AC emergency busses.

~ Bus 14 and Bus 18 IR power can NOT be restored to at

~ Bus 16 and Bus 17 least one train, THEN go to ECA-O.O, LOSS OR ALL AC POWER, Step l.

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EOP) TITLE:

REV 13 E-'0 REACTOR TRIP OR SAFETY INJECTION PAGE 4 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED O 4 Check LIT If Any SI Annuciator IP 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 IP SI is NOT required, THEN go to ES-0.1, REACTOR TRIP RESPONSE, Step 1.

O 5 Verify SI Running:

and RHR Pumps

a. All SI pumps - RUNNING Manually start pumps.

b. Both RHR pumps - RUNNING b. Manually start pumps.

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REV: 13 E-D REACTOR TRIP OR SAFETY INJECTION PAGE 5 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED O 6 Verify Running:

CNMT RECIRC Fans

a. All fans - RUNNING a. Manually start fans.

b. Charcoal filter dampers green b. Dispatch personnel to relay room status lights - EXTINGUISHED 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 Res-CNMT

'=ed:

Spray Not Verify CNMT spray initiated.

IP CNMT spray NOT initiated, THEN o Annunciator A-27, CNMT SPRAY- perform the following:

EXTINGUISHED

a. Depress manual CNMT spray o CNMT pressure - LESS THAN 28 PSIG 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

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EOP:

REV 13 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 6 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED O 8 Check If Main Steamlines Should Be Isolated:

a. Any MSIV - OPEN a. Go to Step 9.

b. Check CNMT pressure - LESS THAN b. Ensure BOTH MSIVs closed and go 18 PSIG 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 (3.6x10~ lb/hr) from either S/G

d. Verify MSIV closed on the d. Manually close valves.

affected S/G(s)

a. MFW pumps - TRIPPED a. Manually close MFW pump discharge valves and trip MFW pumps.

b. MFW flow control valves - CLOSED b. Place A and B S/G MFV regulating valve and bypass valve

~ MFV regulating valves controllers in MANUAL at OX

~ MFV bypass valves demand.

c. S/G blowdown and sample valves- c. Place S/G blowdown and sample CLOSED valve isolation switch to CLOSE.

EOP: TITLE: REV: 13 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 7 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED O 10 Verify AFW Pumps Running:

- RUNNING a. Manually start pumps.

a. MDAFW pumps MDAFW

b. TDAFW pump - RUNNING IF b. Manually open steam supply NECESSARY valves.

~ MOV-3505A

~ MOV-3504A ll Verify At Least Two SW Pumps Perform the following:

RUNNING

a. Ensure one SW pump running on each energized screenhouse AC emerg ncy bus:

~ Bus 17

~ Bus 18 E

b. IF offsite power NOT available, THEN ensure SW isolation.

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 open outlet valve status lights- valves.

BRIGHT

~ FCV-4561

~ FCV-4562

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REV: 13 E-0 REACTOR TRIP OR SAFETY INJECTION 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 a. IF offsite power available, THEN RUNNING manually start one CCW pump.

b. Verify CCW from excess letdown b. Manually close valve.

(AOV-745) - CLOSED 14 Verify SI And RHR Pump Flow:

a. SI flow 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 flow indicator - CHECK FOR b. IF RCS pressure less than FLOW 140 psig, THEN manually start pumps and align valves. IF NOT, THEN go to Step 15.

15 Verify Total AFW Flow IF S/G narrow range level greater GREATER THAN 200 GPM 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 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.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.

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REV 13 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 9 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Verify AFW Valve Alignment: Manually align valves as necessary.

a. AFW flow - INDICATED TO BOTH S/G(s)

b. AFW flow from each MDAFW pump-LESS THAN 230 GPM 17 Verify SI Pump Suction Alignment:

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

o Level - GREATER THAN 10X 1) Ensure at least one SI pump su"tion valve from RWST open; o Annunciator B-23, BORIC ACID TANK LO LO LEVEL- ~ MOV-825A EXTINGUISHED ~ MOU-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

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

- CLOSED necessary.

~ MOV-825A

~ MOV-825B

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REV 13 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 folloving:

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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 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

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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REV 13 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 11 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IP OPPSITE POWER IS LOST APTER SI RESET, SELECTED SW PUMPS AND ONE CCV PUMP WILL AUTO START ON EMERGENCY D/G. MANUAL ACTION VILL BE REQUIRED TO RESTART SAPEGUARDS EQUIPMENT.

19 Check CCW Flow to RCP Thermal IP CCW to a RCP is lost, THEN Barriers: perform the following:

o Annunciator A-7, RCP 1A CCW a. Stop affected RCPs.

RETURN HI TEMP OR LO PLOW-EXTINGUISHED b. Reset SI.

o Annunciator A-15, RCP 1B CCV c. Verify adequate power available RETURN HI TEMP OR LO PLOV- to run one charging pump (75 kw).

EXTINGUISHED

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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REV'3 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 MDAFW pumps - RUNNING a. Go to Step 21.

b. PULL STOP TDAFW pump steam supply valves

~ MOV-3504A

~ MOV-3505A 21 Check RCS Tavg STABLE AT OR IF temperature less than 547'F and 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 5% [25%

adverse CNMT] in at least one S/G.

c. WHEN 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.

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.

EOP: TITLE:

REV 13 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:

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-431C IF block valve can NOT be closed, THEN go to E-l, LOSS OF ~

REACTOR OR SECONDARY COOLANT, Step 1.

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. @HEN 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 0% 0% demand. IF valves can NOT be closed, THEN stop associated RCP(s).

I 1 EOP: TITLE: REV'3 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

a. RCP status - ANY RCP RUNNING a. Go to Step 24.

b. SI pumps - AT LEAST TVO 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 Is If S/G

=;'ct: Secondary Side IR any S/G pressure decreasing an uncontrolled manner OR in completely depressurized, THEN go o Pressure in both S/Gs - STABLE to E-2, RAULTED STEAM GENERATOR OR INCREASING ISOLATION, Step, 1.

o Pressure in both S/Gs - GREATER THAN 100 PSIG 25 Check If S/G Tubes Are Intact: Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

o Air ejector radiation monitors (R-15 or R-15A) - NORMAL o S/G blovdovn radiation monitor (R-19) - NORMAL o Steamline radiation monitors (R-31 and R-32) - NORMAL

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REV: 13 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

c. CNMT sump B level - LESS THAN 78 IN.

d. C .: '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.

EOP: TITLE:

REV: 13 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

a. RCS pressure: a. Do NOT stop SI pumps. Go to Step 30.

o Pressure - GREATER THAN 1625 PSIG o Pressure - STABLE OR INCREASING

b. RCS subcooling based on core b. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN O' Step 30.

USING FIGURE MIN SUBCOOLING c.,"'. ~ndary 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 5%

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.

29 Go To ES-l.l, SI TERMINATION, Step 1

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REV 13 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 Function 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

'" VILL BE NECESSARY (REFER TO ER-AFV.l, ALTERNATE VATER SUPPLY TO AFV AFV PUl PUMPS).

31 Check S/G Levels:

a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% than 200 gpm until narrow range level greater than 5% in at least one S/G.

b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase in an and 50% uncontrolled manner, THEN go to E-3) STEAM GENERATOR TUBE RUPTURE, Step l.

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REV 13 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 1.

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 IF OFF." "" POWER IS LOST AFTER SI RESET, SELECTED SW PUMPS AND ONE CCW PUMP'ILL AUTO START ON EMERGENCY D/G. MANUAL ACTION WILL 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 13 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 - 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)

EOP TITLE: 13 REV 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 folloving:

energized from offsite power

1) Close non-saf'eguards 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 evaluate RECIRC fans should be if CNMT stopped (Refer to Attachment CNMT RECIRC PANS).

3) WHEN bus 15 restored, THEN reset control room lighting.

b. Verify SW isolation valves to b. Manually align valves.

turbine building - OPEN

~ MOV-4613 and MOV-4670

~ MOV-4614 and MOV-4664

c. Verify at least tvo air c. Manually start air compressors compressors - RUNNING as power supply permits (75 kv each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.

d. Check IA supply: d. Perform the folloving:

o Pressure - GREATER THAN 1) Continue attempts to restore 60 PSIG IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).

o Pressure - STABLE OR INCREASING 2) Continue with Step 37. WHEN IA restored, THEN do Steps 36e and f.

e. Reset both trains of XY relays for IA to CNMT AOV-5392

f. Verify IA to CNMT AOV-5392 - OPEN

EOP: REV 13 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 (LI-442) -

o t'" level PRT LESS THAN

~ 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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REV: 13 E-0 REACTOR TRIP OR SAFETY, INJECTION PAGE 22 of 26 STEP 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 MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

39 Check Stopped:

If RHR Pumps Should Be

a. Check RCS pressure:

1) Pressure - GREATER THAN 1) Go to E-l, LOSS OF REACTOR OR 250 PSIG SECONDARY COOLANT, Step 1.

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 kw 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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EOP: LITLE: REV 13 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) IF CCW flow is lost to any RCP thermal barrier OR any RCP gl seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal infection 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 to b. Manually align valves as RWST: necessary.

"o LCV-112B - OPEN IF 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 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).

c. Start charging pumps as necessary and adjust charging flow to restore PRZR level

EOP:

REV'3 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 223S PSIG o Reset PRZR heaters o Use normal PRZR spray

E EOP: TITLE: \

REV 13 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

a. Verify AC emergency busses a. Perform the following:

energized by offsite power:

1) Verify non-safeguards bus tie o Emergency D/G output breakers breakers closed:

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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REV 13 E-O 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 13 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

EOP:

REV 13 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 5%

[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. C~'AINMENT CNMT pressure greater than 60 psig

EOP: TITLE:

REV: 13 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 2200 g INCREMENTS 20 PSIG 2100 2000 1900 I

1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 700 INADEQUATE SUBCOOLING 600 REGION ADVERSE CNMT 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10~P 100 0

200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('P)

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REV 13 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 l.

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 to and'o 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'evel LESS THAN 5c [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 10%, THEN ensure SI pump automatic switchover to RWST.

AFW SUPPLY SWITCHOVER CRITER10N 1F 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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