ML022120533

R. E. Ginna Nuclear Power Plant - Emergency Operating Procedures, Revision 23 to ECA-3.1, SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired - ES-1.2, Revision 24, Post LOCA Cooldown and Depressurization

ML022120533
Person / Time
Site:	Ginna
Issue date:	07/25/2002
From:	Widay J Rochester Gas & Electric Corp
To:	Clark R Document Control Desk, NRC/NRR/DLPM/LPD1
References
ECA-3.1, Rev 23
Download: ML022120533 (179)

Text

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 1 of 36 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLO MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

~~TITLE:RE:2

- REV: 23 SGTR WITH LOSS OF REACTOR COOLANT CA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 2 of 36 A. PURPOSE - This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions while minimizing loss of RCS inventory and voiding in the RCS for an SGTR concurrent with a LOCA (i.e. Ruptured-Faulted S/G).

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-3, STEAM GENERATOR TUBE RUPTURE, if ruptured S/G can not be isolated from any intact S/G.

b. E-3, STEAM GENERATOR TUBE RUPTURE, if PRZR PORV can not be isolated by closing its block valve.

c. E-3, STEAM GENERATOR TUBE RUPTURE, if ruptured S/G is faulted.

d. E-3, STEAM GENERATOR TUBE RUPTURE, and ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, if no intact S/G is available for RCS cooldown.

e. E-3, STEAM GENERATOR TUBE RUPTURE, if minimum DIP between ruptured and intact S/G cannot be maintained.

f. E-3, STEAM GENERATOR TUBE RUPTURE, if RCS subcooling is less than required.

g. E-3, STEAM GENERATOR TUBE RUPTURE, if RCS pressure does not increase after closing PRZR PORV and block valve.

h. E-3, STEAM GENERATOR TUBE RUPTURE, and ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, if SI can not be terminated.

i. E-3, STEAM GENERATOR TUBE RUPTURE, and ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, if SI is reinitiated after termination.

j. E-3, STEAM GENERATOR TUBE RUPTURE, ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, and ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, if SI accumulators should not be isolated.

.1 REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 3 of 36

k. ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, and ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, if a non-ruptured S/G is not available for RCS cooldown.

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 4 of 36 I

ST- P ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

CAUTION o IF RWST LEVEL DECREASES TO LESS THAN 28%. THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.

o IF PRZR LEVEL IS LESS THAN 50% OR IF ADVERSE CNMT CONDITIONS EXIST, THEN PRZR HEATERS SHOULD NOT BE ENERGIZED UNTIL PRZR LEVEL IS EVALUATED BY THE TSC.

o IF OFFSITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER)

NOTE: 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+05 R/hr.

1 Reset SI 2 Reset CI:

a. Depress CI reset pushbutton

b. Verify annunciator A 26, CNMT b. Perform the following:

ISOLATION EXTINGUISHED

1) Reset SI.

2) Depress CI reset pushbutton.

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 5 of 36 3e ifOESPONSE NAOTdOeTAINEyo 3 Verify Adequate SW Flow:

a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (257 kw each).

IF less than two SW pumps running, THEN perform the following:

1) Ensure SW isolation.

2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1).

3) IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

4) IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

5) Go to Step 5.

h. Dispatch AC to establish normal shutdown alignment (Refer to Attachment SD-1)

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 6 of 36 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 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 e Bus 13 to Bus 14 tie e 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 if CNMT RECIRC fans should be stopped (Refer to Attachment CNMT RECIRC FANS).

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

turbine building - OPEN MNOV-4613 and MOV-4670

• MOV-4614 and MOV-4664

c. Verify adequate air c. Manually start air compressors compressor(s) RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.

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

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 5. WHEN IA restored, THEN do Steps 4e and f.

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

f. Verify IA to CNMT AOV-5392 OPEN

.1 REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 7 of 36 STEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED[

• 5 Monitor All AC Busses Perform the following:

BUSSES ENERGIZED BY OFFSITE POWER a. IF any AC emergency bus normal feed breaker open, THEN ensure o Normal feed breakers to all 480 associated D/G breaker closed.

volt busses CLOSED

b. Perform the following, as o 480 bus voltage GREATER THAN necessary:

420 VOLTS

1) Close non safeguards bus tie o Emergency D/G output breakers breakers:

OPEN

"*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) Restore power to MCCs.

"*A from Bus 13

"*B from Bus 15

"*E from Bus 15

"*F from Bus 15

4) Start HP seal oil backup pump.

5) Ensure D/G load within limits.

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

7) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.

c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 8 of 36 EDRESONSI IRESPýONSE ýNOT 0ýBTAINýEDIý SACTONJXP

• 6 Monitor If CNMT Spray Should Be Stopped:

a. CNMT spray pumps ANY RUNNING a. Go to Step 7.

b. Check the following: b. Continue with Step 7. WHEN BOTH conditions satisfied, THEN do "o CNMT pressure - LESS THAN Steps 6c through f.

4 PSIG "o Sodium hydroxide tank level LESS THAN 55%

c. Reset CNMT spray

d. Check NaOH tank outlet valves d. Place NaOH tank outlet valve CLOSED controllers to MANUAL and close valves.

• AOV-836A

• AOV-836B

e. Stop CNMT spray pumps and place in AUTO

f. Close CNMT spray pump discharge valves

• MOV 860A

• MOV-860B

• MOV-860C

• MOV 860D

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 9 of 36 STEPH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF ANY RUPTURED SIG IS FAULTED, FEED FLOW TO THAT S/G SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.

7 Check Ruptured S/G Level:

a. Narrow range level GREATER a. IF ruptured S/G NOT faulted, THAN 5% [25% adverse CNMT] THEN perform the following:

1) Maintain feed flow to ruptured S/G until level greater than 5% [25% adverse CNMT].

2) Continue with Step 8. WHEN ruptured S/G level greater than 5% [25% adverse CNMT],

THEN do Steps 7b through e.

b. Close MDAFW pump discharge valve b. Dispatch AO to locally close to ruptured S/G valve.

• S/G A, MOV-4007

• S/G B, MOV-4008

c. Pull stop MDAFW pump for ruptured S/G

d. Close TDAFW pump flow control d. Dispatch AO with locked valve valve to ruptured S/G key to locally close TDAFW pump manual feedwater isolation valve

• S/G A, AOV-4297 to ruptured S/G.

• S/G B, AOV-4298

• S/G A, V-4005

• S/G B, V-4006

e. Verify MDAFW pump crosstie e. Manually close valves.

valves CLOSED

• MOV-4000A

• MOV 4000B

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 10 of 36 STE ACTION/EXPECTED RESPONSEIi RESPONSE NOT OBTAINEDI CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT]. THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

v . .*

• v * * * * * * * "* * ******** .. * * * ***

8 Check If RHR Pumps Should Be Stopped:

a. Check RCS pressure: a. Go to Step 9.

o Pressure GREATER THAN 250 psig [465 psig adverse CNMT]

o Pressure STABLE OR INCREASING

b. Stop RHR pumps and place in AUTO

EOP: IJTLE:

REV: 23 ECA-3 SGTR WITH LOSS OF REACTOR COOLANT C SUBCOOLED RECOVERY DESIRED PAGE 11 of 36 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Evaluate Plant Status:

a. Check auxiliary building a. Notify RP and refer to radiation - NORMAL appropriate AR-RMS procedure.

• Plant vent iodine (R-10B)

• Plant vent particulate (R-13) o Plant vent gas (R-14)

• CCW liquid monitor (R-17)

• Letdown line monitor (R-9)

• CHG pump room (R-4)

b. Direct RP to obtain following samples:

• RCS boron

• RCS activity

• CNMT hydrogen

• CNMT sump boron

c. Verify adequate Rx head cooling:

1) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw).

2) Verify one Rx compartment 2) Perform the following:

cooling fan RUNNING "o Dispatch AO to reset UV relays at MCC C and MCC D.

"o Manually start one fan as power supply permits (23 kw).

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 12 of 36 7ý-

STEP ACTI ON /EXPECTED RESPONS RESPONSE NOT OBTAINED 10 Establish 75 GPM Charging Flow:

a. Charging pumps ANY RUNNING a. Perform the following:

1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high.

THEN dispatch AO with RWST area key to locally isolate seal injection to affected RCP.

• RCP A, V-300A e RCP B. V-300B

2) Ensure HCV-142 open.

b. Align charging pump suction to b. IF LCV-112B can NOT be opened.

RWST: THEN dispatch AO to locally open manual charging pump suction o LCV-112B OPEN from RWST (V 358 located in charging pump room).

o LCV-112C CLOSED IF LCV-112C can NOT be closed, THEN perform the following:

1) Verify charging pump A NOT running and place in PULL STOP.

2) 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 establish 75 gpm total charging flow

• Charging line flow

• Seal injection

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 13 of 36 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 11 Check If S/G Secondary Side _IF any SIG pressure decreasing in Is Intact: an uncontrolled manner OR completely depressurized. THEN o Pressure in both S/Gs STABLE verify faulted S/G isolated unless OR INCREASING needed for RCS cooldown:

o Pressure in both S/Gs - GREATER "* Steamlines THAN 110 PSIG "* Feedlines IF NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION. Step 1.

NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

"*12 Monitor Intact S/G Levels:

a. Narrow range level GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in intact S/G.

b. Control feed flow to maintain b. IF narrow range level in the narrow range level between 17% intact S/G continues to increase

[25% adverse CNMT] and 50% in an uncontrolled manner, THEN consider isolating unnecessary release paths:

"*TDAFW pump steam supply valves

"*S/G blowdown valves

"* Refer to Attachment RUPTURED S/G

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 14 of 36 SACIONEXECTD RSP SE IRESPOýN EOOBTAINEDI 0

NOTE: Shutdown margin should be monitored during RCS cooldown (Refer to Figure SDM).

13 Initiate RCS Cooldown To Cold Shutdown:

a. Establish and maintain cooldown rate in RCS cold legs LESS THAN 100°F/HR

b. Use RHR system if in service

c. Dump steam to condenser from c. Manually or locally dump steam intact S/G using intact S/G ARV.

IF no intact S/G available, THEN perform the following:

o Use faulted S/G.

-OR o IF RHR system NOT in service, THEN use ruptured S/G.

"*14 Monitor Conditions For Subcooled Recovery:

a. Check RWST level GREATER THAN a. IF CNMT sump B level is less 50% than 113 inches, THEN go to ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED, Step 1.

b. Check ruptured S/G narrow level b. Consult TSC to determine if LESS THAN 90% [80% adverse recovery should be completed CNMT] using ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED.

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 15 of 36 SACTION/EXPECTED RESPONSEII RESPONSE NOT OBTAINED 15 Check RCS Subcooling Based On Go to Step 28.

Core Exit T/Cs - GREATER THAN 00 USING FIGURE MIN SUBCOOLING 16 Check Safeguards Pump Status Go to Step 24.

0 SI pumps ANY RUNNING OR o RHR pumps - ANY RUNNING IN INJECTION MODE 17 Place PRZR Heater Switches In The Following Positions:

o PRZR heater control group PULL STOP o PRZR heater backup group OFF 18 Check PRZR level - LESS THAN Go to Step 20.

13% [40% adverse CNMT]

.1 REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 16 of 36 S ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

• a * * * * * * * * * * * * * * * * * * * * * * * * * * *

• a * * * * * * * *

• NOTE: o When using PRZR PORV, select one with an operable block valve.

0 If auxiliary spray is in use, then spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

19 Depressurize RCS To Refill PRZR:

a. Use normal PRZR spray valve a. Use one PRZR PORV. IF IA NOT associated with running RCP available, THEN refer to Attachment N2 PORVS.

• RCP A, PCV-431A

• RCP B, PCV-431B IF no PORV available, THEN use auxiliary spray valve.

b- PRZR level GREATER THAN 13% b. Continue with Step 20. WHEN

[40% adverse CNMT] level greater than 13% [40%

adverse CNMT], THEN stop RCS depressurization.

c. Stop RCS depressurization

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 17 of 36

_A*IOIEXPCT*

• RESONSI IRESPOýIIE NýOTOBTAINEýD CAUTION o IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

O INADVERTENT CRITICALITY MAY OCCUR FOLLOWING NATURAL CIRCULATION COOLDOWN IF THE RCP IN THE RUPTURED LOOP IS STARTED FIRST.

20 Check If An RCP Should Be Started:

a. Both RCPs STOPPED a. Stop all but one RCP and go to Step 21.

b. RCS subcooling based on core b. Go to Step 28.

exit T/Cs GREATER THAN 0°F USING FIGURE MIN SUBCOOLING

c. PRZR level GREATER THAN 13% c. Return to Step 18.

[40% adverse CNMT]

d. Try to start an RCP

1) Establish conditions for starting an RCP o Bus IIA or lB energized o Refer to Attachment RCP START

2) Start one RCP

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 18 of 36 I

SACTION/EXPECTED RESPONE 1 RESPONSE NOT OBTAINEDI 21 Check If One Of Three SI Pumps Should Be Stopped:

a. Three SI pumps RUNNING a. Go to Step 22.

b. RCS subcooling based on core b. IF RCS hot leg temperatures exit T/Cs GREATER THAN 35 0 F greater than 320'F [3100F CNMT] USING FIGURE adverse CNMT], OR IF RHR normal

[900F adverse MIN SUBCOOLING cooling in service. THEN go to Step 28.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 320'F

[310'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 21c. IF no RHR pump can be started in injection mode, THEN go to Step 28.

c. Check PRZR level GREATER THAN c. Do NOT stop SI pump. Return to 13% [40% adverse CNMT] Step 18.

d. Stop one SI pump

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 19 of 36 ST1EP . ACTION/EXPECTED RESONSE RESPONSE NOT OBTAINEDI 22 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps RUNNING a. Go to Step 23.

b. Determine required RCS subcooling from table:

Charging Pump RCS Subcooling Criteria Availability NONE 120°F [200°F adverse CNMT]

ONE 115°F [190°F adverse CNMT]

TWO 105OF [180°F adverse CNMT]

THREE 100'F [175°F adverse CNMT]

c. RCS subcooling based on core c. IF RCS hot leg temperatures exit T/Cs GREATER THAN VALUE greater than 320°F [30°OF FROM TABLE ABOVE USING FIGURE adverse CNMT]1 OR IF RHR normal MIN SUBCOOLING cooling in service. THEN go to Step 28.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 320'F

[310'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 22d. IF no RHR pump can be started in injection mode, THEN go to Step 28.

d. PRZR level GREATER THAN 13% d. Do NOT stop SI pump. Return to

[40% adverse CNMT] Step 18.

e. Stop one SI pump

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 20 of 36 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check If Last SI Pump Should Be Stopped:

a. One SI pump RUNNING a. IF any RHR pump running in injection mode, THEN go to Step 28. IF NOT. THEN go to Step 24.

b. Determine required RCS subcooling from table:

Charging Pump RCS Subcooling Criteria Availability NONE Insufficient subcooling to stop SI pump.

ONE 255°F [295°F adverse CNMT]

TWO 235°F [285°F adverse CNMT]

THREE 2101F [270'F adverse CNMT]

c. RCS subcooling based on core c. IF RCS hot leg temperatures exit T/Cs GREATER THAN VALUE greater than 320°F [310'F FROM TABLE ABOVE USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING cooling in service, THEN go to Step 28.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 320°F

[310'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 23d. IF no RHR pump can be started in injection mode, THEN go to Step 28.

d.' PRZR level GREATER THAN 13% d. Do NOT stop SI pump. Return to

[40% adverse CNMT] Step 18.

e. Stop running SI pump

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 21 of 36 SE ACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINED 24 Check If Charging Flow Should Be Controlled To Maintain PRZR Level:

a. Check RHR pumps - RUNNING IN a. Start charging pumps and control INJECTION MODE charging flow to maintain PRZR level and go to Step 25.

b. Go to Step 28

LOP: TITLE:RE:2 ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT - REV: 23

" SUBCOOLED RECOVERY DESIRED PAGE 22 of 36 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION "o IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

"o INADVERTENT CRITICALITY MAY OCCUR FOLLOWING NATURAL CIRCULATION COOLDOWN IF THE RCP IN THE RUPTURED LOOP IS STARTED FIRST.

25 Check RCP Status:

a. RCPs AT LEAST ONE RUNNING a. Try to start one RCP

1) IF RVLIS level (no RCPs) less than 95%, THEN perform the following:

"o Increase PRZR level to greater than 65% [82%

adverse CNMT]

" Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20'F using Figure MIN SUBCOOLING "o Energize PRZR heaters as necessary to saturate PRZR water

2) Establish conditions for starting an RCP:

"o Verify bus 11A or liB energized.

"o Refer to Attachment RCP START.

3) Start one RCP.

IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).

IF natural circulation NOT verified. THEN increase dumping steam.

b. Stop all but one RCP

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 23 of 36

• * **A.TION..X.........ON**O**O*TAI .........

CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

NOTE: o WHEN using a PRZR PORV, THEN select one with an operable block valve.

o If auxiliary spray is in use, then spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

26 Depressurize RCS To Minimize RCS Subcooling:

a. Depressurize using normal PRZR a. Depressurize using one PRZR spray if available PORV. IF IA NOT available, THEN refer to Attachment N2 PORVS.

IF no PORV available, THEN use auxiliary spray valve (AOV 296).

b. Energize PRZR heaters as necessary

c. Depressurize RCS until EITHER of the following conditions satisfied:

"o RCS subcooling based on core exit T/Cs LESS THAN 10°F USING FIGURE MIN SUBCOOLING

-OR "o PRZR level GREATER THAN 75%

[65% adverse CNMT]

I REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 24 of 36 STE ACTION/EXPECTED RESPONSEI!I RESPONSE NOT OBTAINEDI NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

27 Verify Adequate Shutdown Margin

a. Direct RP to sample RCS and ruptured S/C for boron concentration

b. Verify boron concentration b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM

• 28 Monitor SI Reinitiation Criteria:

a. RCS subcooling based on core a. Manually start SI pumps as exit T/Cs - GREATER THAN 0°F necessary and go to Step 29.

USING FIGURE MIN SUBCOOLING

b. PRZR level GREATER THAN 5% b. Manually start SI pumps as

[30% adverse CNMT] necessary and return to Step 18.

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 25 of 36 S ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED1 29 Check If SI ACCUMs Should Be Isolated:

a. RCS subcooling based on core a. IF both RCS hot leg temperatures exit T/Cs GREATER THAN 0°F less than 400'F, THEN go to USING FIGURE MIN SUBCOOLING Step 29c.

IF NOT, THEN go to Step 30.

b. PRZR level GREATER THAN 5% b. Return to Step 18.

[30% adverse CNMT]

c. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves

• MOV-841, MCC C position 12F

• MOV-865, MCC D position 12C

d. Close SI ACCUM discharge valves d. Vent any unisolated ACCUMs:

• MOV-841 1) Open vent valves for

• MOV-865 unisolated SI ACCUMs.

o ACCUM A, AOV-834A o ACCUM B, AOV-834B

2) Open HCV-945.

e. Locally reopen breakers for MOV-841 and MOV-865

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 26 of 36

• • O*****o.

~~ ~ ~ ýEPýS o*.NoBoAINEI 30 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

"o Emergency DIG output breakers OPEN "o AC emergency bus voltage GREATER THAN 420 VOLTS "o AC emergency bus normal feed breakers CLOSED

b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP) 31 Minimize Secondary System Contamination:

a. Isolate reject from hotwell to a. IF hotwell level increasing, CST: THEN direct RP to sample hotwells for activity.

"o Place hotwell level controller (HC-107) in MANUAL at 50%

"o Verify hotwell level - STABLE

b. Verify local actions to complete isolation of ruptured S/G (Refer to Attachment RUPTURED S/G)

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 27 of 36 TACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 32 Verify Adequate SW Flow To CCW Hx:

a. Verify at least two SW pumps a. Manually start pumps as power RUNNING supply permits (257 kw per pump). IF less than two SW pumps can be operated, THEN perform the following:

1) IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

2) IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

3) Go to Step 33.

b. Verify AUX BLDG SW isolation b. Manually align valves.

valves OPEN

• MOV 4615 and MOV-4734

• MOV-4616 and MOV-4735 This Step continued on the next page.

EOP: TITLE: R 2 ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT - REV: 23 E SUBCOOLED RECOVERY DESIRED PAGE 28 of 36 (Step 32 continued from previous page)

-h f win

c. Verify U1NMI REIRnui fdan I . - - 6 annunciator C-2, HIGH TEMPERATURE ALARM - EXTINGUISHED 1) Determine required SW flow to CCW HXs per table:

SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2 Total of 5000 6000 gpm equally divided to both HXs Normal 1 5000 - 6000 gpm to in-service HX Alternate 2 30-33" d/p across each HX Alternate 1 95-100" d/p across in-service HX

2) Direct AO to adjust SW flow to required value.

o IF on normal SW discharge:

0 V-4619, CCW Hx A o V-4620. CCW Hx B

-OR o IF on alternate SW discharge:

• V-4619C, CCW Hx A o V-4620B, CCW Hx B

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 29 of 36 SE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 Check RCP Cooling Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).

a. Check CCW to RCPs o Annunciator A-7, RCP IA CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED o Annunciator A-15, RCP IB CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED

b. Check RCP seal injection o Labyrinth seal D/Ps GREATER THAN 15 INCHES OF WATER

-OR o RCP seal injection flow to each RCP GREATER THAN 6 GPM

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 30 of 36 SACI0 EXECTD RSPNSE [RESPýON ENO OýTAINEDI 34 Check If Seal Return Flow Should Be Established:

a. Verify instrument bus D a. Perform the following:

ENERGIZED

1) Ensure steam dump mode control in MANUAL.

2) Restore power to instrument bus D from MCC B or MCC A (maintenance supply).

b. Verify RCP #1 seal outlet b. Go to Step 35.

temperature LESS THAN 235°F

c. Verify RCP seal outlet valves c. Manually open valves as OPEN necessary.

• AOV 270A

• AOV 270B

d. Reset both trains of XY relays for RCP seal return isolation valve MOV-313

e. Open RCP seal return isolation e. Perform the following:

valve MOV-313

1) Place MOV-313 switch to OPEN.

2) Dispatch AO with key to RWST gate to locally open MOV-313.

f. Verify RCP #1 seal leakoff flow f. Perform the following:

LESS THAN 6.0 GPM

1) Trip the affected RCP

2) Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve

"* RCP A, AOV-270A

"* RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 35.

g. Refer to AP-RCP.l, RCP SEAL

g. Verify RCP #1 seal leakoff flow GREATER THAN 0.8 GPM MALFUNCTION.

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 31 of 36 111111

-ACTI ON/ EXPECTED RESPONSE[ I11ý RESPONSE NOT OBTAINEDI NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

35 Check If Source Range Detectors Should Be Energized:

a. Source range channels a. Go to Step 35e.

DEENERGIZED

b. Check intermediate range flux b. Perform the following:

EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing, THEN initiate boration.

2) Continue with Step 36. WHEN flux is LESS THAN 10-10 amps on any operable channel, THEN do Steps 35c, d and e.

c. Check the following: c. Continue with Step 36. WHEN either condition met, THEN do o Both intermediate range Steps 35d and e.

channels LESS THAN 10-10 AMPS

-OR o Greater than 20 minutes since reactor trip

d. Verify source range detectors d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can NOT be restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 36.

e. Transfer Rk-45 recorder to one source range and one intermediate range channel

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 32 of 36 7ý-

S ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINEDI 36 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.

b. Perform the following:

"o Open generator disconnects e IC13A71 e 9X13A73 "o Place voltage regulator to OFF "o Open turbine drain valves "o Rotate reheater steam supply controller cam to close valves "o Place reheater dump valve switches to HAND "o Stop all but one condensate pump

c. Verify Attachment SD- COMPLETE

.1 REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 33 of 36 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED)

CAUTION FEED FLOW SHOULD NOT BE ESTABLISHED TO ANY RUPTURED S/G WHICH IS ALSO FAULTED UNLESS IT IS NEEDED FOR RCS COOLDOWN.

• 37 Monitor Ruptured S/G(s) Refill ruptured S/G to 80% [60%

Narrow Range Level - GREATER adverse CNMTI using feed flow.

THAN 17% [25% adverse CNMT]

IF either of the following conditions occurs. THEN stop feed flow to ruptured S/G unless needed for RCS cooldown:

"o Ruptured S/G pressure decreases in an uncontrolled manner.

-OR "o Ruptured S/G pressure increases to 1020 psig.

• 38 Monitor RCP Operation:

a. RCPs ANY RUNNING a. Go to Step 39.

b. Check the following: b. Stop affected RCP(s).

o RCP #1 seal D/P GREATER THAN 220 PSID o Check RCP seal leakage WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 34 of 36 STEP ACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINED 39 Check Condenser Steam Dump Manually or locally dump steam Available - CONDENSER VACUUM using intact S/G ARV.

GREATER THAN 20 INCHES HG IF no intact S/G available, THEN:

o Use faulted SIG.

-OR o IF RHR system NOT in service, THEN use ruptured SIG.

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 35 of 36 SACTON/XPETEDRESONSI IRESPýONSE ýNOT OýBTAINýED[ý 40 Check If RHR Normal Cooling Can Be Established:

a. RCS cold leg temperature - LESS a. Go to Step 41.

THAN 350°F

b. RCS pressure - LESS THAN b. Go to Step 41.

400 psig [300 psig adverse CNMT]

c. Place letdown pressure controller in MANUAL CLOSED

d. Check following valves OPEN d. Perform the following:

"*AOV 371, letdown isolation 1) Reset both trains of XY valve relays for AOV-371 and

"*AOV-427, loop B cold leg to AOV-427.

REGEN Hx

"*At least one letdown orifice 2) Open AOV-371 and AOV-427.

valve (AOV-200A, AOV-200B, or AOV-202) 3) Open one letdown orifice valve.

e. Verify pressure on PI 135 LESS e. Go to Step 41.

THAN 400 PSIG

f. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)

g. Consult TSC to determine if RHR normal cooling should be established using Attachment RHR COOL

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 36 of 36 NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 41.

41 Check CNMT Hydrogen Concentration:

a. Direct RP to start CNMT hydrogen monitors as necessary

b. Hydrogen concentration LESS b. Consult TSC to determine if THAN 0.5% hydrogen recombiners should be placed in service.

42 Check Core Exit T/Cs - LESS Return to Step 8.

THAN 2000 F 43 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions

b. Consult TSC END

REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 1 of 1 ECA-3.1 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG 1.0)

3) FIGURE SDM (FIG 2.0)

4) FIGURE RCP SEAL LEAKOFF (FIG -4.0)

5) ATTACHMENT CNMT RECIRC FANS (ATT 4.0)

6) ATTACHMENT SI/UV (ATT 8.4)

7) ATTACHMENT RUPTURED S/G (ATT- 16.0)

8) ATTACHMENT N2 PORVS (ATT 12.0)

9) ATTACHMENT RCP START (ATT -15.0)

10) ATTACHMENT D/G STOP (ATT 8.1)

11) ATTACHMENT SEAL COOLING (ATT 15.2)

12) ATTACHMENT SD-i (ATT 17.0)

13) ATTACHMENT SD-2 (ATT 17.1)

14) ATTACHMENT RHR COOL (ATT 14.1)

15) ATTACHMENT NC (ATT 13.0)

16) ATTACHMENT NO SW PUMPS (ATT 2.4)

17) ATTACHMENT LOSS OF OFFSITE POWER (ATT 8.5)

17) FOLDOUT

--- m" REV: 23 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED PAGE 1 of 1

• 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%

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 52% [55%

adverse CNMT]

C. HEAT SINK - Narrow range level in all S/Gs less than 5%

[25% 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 2850F

e. CONTAINMENT - CNMT pressure greater than 60 psig

I ILt:

SGTR WITH LOSS OF REACTOR COOLANT - REV: 23 SUBCOOLED RECOVERY DESIRED PAGE 1 of 1 FOLDOUT PAGE

1. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start SI pumps as necessary:

"o RCS subcooling based on core exit TCs - LESS THAN 0 0 F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING "o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT]

2. SATURATED RECOVERY CRITERIA IF ruptured S/G narrow range level increases to greater than 90% [80% adverse CNMT], THEN consult TSC to determine if recovery should be completed using ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED.

3. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1, UNLESS faulted S/G needed for RCS cooldown.

4. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-I.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

5. 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)

REV:2 6 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 1 of 27 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER O2I3 RESPNI MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

TITLE: REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 2 of 27 A. PURPOSE - This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions while minimizing loss of RCS inventory and voiding in the RCS.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, when RWST level is low without a corresponding increase in containment sump level.

b. ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, when the ruptured S/G level is high and plant staff selects saturated recovery method.

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 3 of 27 SACION XECTO RSPNSE IREIP0 NE OOBTAINEýD 0

CAUTION IF RWST LEVEL DECREASES TO LESS THAN 28%, THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-l.3, TRANSFER TO COLD LEG RECIRCULATION.

. . . . I * . * * * .* * * * * .* *

• v * * * * . * * * * * * ** * ** * * * **

• NOTE: o Steps 1 through 14 of ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, should be performed before continuing with this procedure.

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+05 R/hr.

1 Add Makeup To RWST As Necessary:

"o Refer to S-9J. BLENDING TO RWST

-OR "o Refer to S-3.2D. TRANSFERRING WATER FROM CVCS HUT(S) TO RWST TO SFP

-OR-0 Refer to Attachment SFP-RWST

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 4 of 27 SACTONJXPETEDRESONSI iRESPOýNSE NýOT OBTAINEýD CAUTION IF ANY RUPTURED S/G IS FAULTED, FEED FLOW TO THAT S/G SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.

2 Check Ruptured S/G Level:

a. Narrow range level GREATER a. IF ruptured S/G NOT faulted, THAN 5% [25% adverse CNMT] THEN perform the following:

1) Maintain feed flow to ruptured S/G until level greater than 5% [25% adverse CNMT].

2) Continue with Step 3. WHEN ruptured S/G level greater than 5% [25% adverse CNMT],

THEN do Steps 2b through e.

b. Close MDAFW pump discharge valve b. Dispatch AO to locally close to ruptured S/G valve.

S/G A, MOV 4007 S

• S/G B, MOV-4008

c. Pull stop MDAFW pump for ruptured S/G

d. Close TDAFW pump flow control d. Dispatch AO with locked valve valve to ruptured S/G key to locally close TDAFW pump manual feedwater isolation valve

• S/G A. AOV-4297 to ruptured S/G.

• S/G B, AOV-4298

• S/G A, V-4005

• S/G B, V-4006

e. Verify MDAFW pump crosstie e. Manually close valves.

valves CLOSED

• MOV 4000A

• MOV 4000B

.1 REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 5 of 27

.. A......*. X * .*. . . .* *O*

CAUTION

. O.. ........

OO ....

o IF OFFSITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER) o RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

3 Check If RHR Pumps Should Be Stopped:

a. Check RCS pressure: a. Go to Step 4.

1) Pressure GREATER THAN 250 psig [465 psig adverse CNNT]

2) RCS pressure STABLE OR INCREASING

b. Stop RHR pumps and place in AUTO 4 Check If S/G Secondary Side IF any S/G pressure decreasing in Is Intact: an uncontrolled manner OR completely depressurized, THEN "o Pressure in both S/Gs STABLE verify faulted S/G isolated unless OR INCREASING needed for RCS cooldown:

"o Pressure in both S/Gs GREATER "* Steamlines THAN 110 PSIG "* Feedlines IF NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION. Step 1.

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 6 of 27 NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

• 5 Monitor Intact S/G Level:

a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in at least one S/G.

b. Control feed flow to maintain b. IF narrow range level in the narrow range level between 17% intact S/G continues to increase

[25% adverse CNMT] and 50% in an uncontrolled manner, THEN consider isolating unnecessary release paths:

o TDAFW pump steam supply valves o S/G blowdown valves o Refer to Attachment RUPTURED S/G NOTE: Shutdown margin should be monitored during RCS cooldown. Refer to Figure SDM.

6 Initiate RCS Cooldown To Cold Shutdown:

a. Establish and maintain cooldown rate in RCS cold legs LESS THAN ]00°F/HR

b. Use RHR system if in service

c. Dump steam to condenser from c. Manually or locally dump steam intact S/G using intact S/G ARV.

IF no intact S/G available, THEN perform the following:

o Use faulted S/G.

-OR o IF RHR system NOT in service, THEN use ruptured S/G.

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 7 of 27 STEPH ACTION/xPETE RESPONS REPOS NOT OBT0AINED 7 Check RCS Subcooling Based On Go to Step 19.

Core Exit T/Cs - GREATER THAN 0 0 F USING FIGURE MIN SUBCOOLING 8 Check Safeguards Pump Status Go to Step 15.

o SI pumps ANY RUNNING

-OR-o RHR pumps ANY RUNNING IN INJECTION MC 9 Place PRZR Heater Switches In The Following Positions:

o PRZR heater control group PULL STOP o PRZR heater backup group OFF

.1 REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 8 of 27 CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

o When using PRZR PORV, select one with an operable block valve.

10 Depressurize RCS To Refill PRZR:

a. Use normal PRZR spray valve a. Use one PRZR PORV. IF IA NOT associated with running RCP available, THEN refer to Attachment N2 PORVS.

"* PCV-431A for A RCP

"* PCV-431B for B RCP IF no PORV available, THEN use auxiliary spray valve.

b. PRZR level GREATER THAN 13% b. Continue with Step 11. WHEN

[40% adverse CNMT] level greater than 13% [40%

adverse CNMT], THEN stop RCS depressurization.

c. Stop RCS depressurization

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 9 of 27 S11111ACTI ON/EXPECTED RE POSIIRESPONSE NOT 0BTAINEI.

CAUTION o IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST. THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

o INADVERTENT CRITICALITY MAY OCCUR FOLLOWING NATURAL CIRCULATION COOLDOWN IF THE RCP IN THE RUPTURED LOOP IS STARTED FIRST.

11 Check If An RCP Should Be Started:

a. Both RCPs - STOPPED a. Stop all but one RCP and go to Step 12.

b. RCS subcooling based on core b. Go to Step 19.

exit T/Cs - GREATER THAN 0°F USING FIGURE MIN SUBCOOLING

c. PRZR level GREATER THAN 13% c. Return to Step 10.

[40% adverse CNMT]

d. Try to start an RCP

1) Establish conditions for starting an RCP "o Bus 11A or liB energized "o Refer to Attachment RCP START

2) Start one RCP

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 10 of 27 ONIXPET ORESONSI IRSP0 NSE 1ýOT OBTAINEýI 12 Check If One Of Three SI Pumps Should Be Stopped:

a. Three SI pumps RUNNING a. Go to Step 13.

b. RCS subcooling based on core b. IF RCS hot leg temperatures exit T/Cs GREATER THAN 10°F greater than 320'F [310°F

[10°F adverse CNMT] USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING cooling in service, THEN go to Step 19.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 320'F

[310°F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 12c. IF no RHR pump can be started in injection mode, THEN go to Step 19.

c. Check PRZR level GREATER THAN c. Do NOT stop SI pump. Return to 13% [40% adverse CNMT] Step 10.

d. Stop one St pump

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 11 of 27 13 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps - RUNNING a. Go to Step 14.

b. RCS subcooling based on core b. IF RCS hot leg temperatures exit T/Cs GREATER THAN 35°F greater than 320'F [310'F

[35°F adverse CNMT] USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING cooling in service, THEN go to Step 19.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 320'F

[310'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 13c. IF no RHR pump can be started in injection mode, THEN go to Step 19.

c. PRZR level GREATER THAN 13% c. Do NOT stop SI pump. Return to

[40% adverse CNMT] Step 10.

d. Stop one SI pump

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 12 of 27 rý-

STP ACT ION/ EXPECTED RESPONSE1 RESPONSE NOT OBTAINEDý1 14 Check If Last SI Pump Should Be Stopped:

a. One SI pump RUNNING a. IF any RHR pump running in injection mode, THEN go to Step 19. IF NOT, THEN go to Step 15.

b. Determine required RCS subcooling from table:

Charging Pump RCS Subcooling Criteria Availability NONE Insufficient subcooling to stop SI pump.

ONE 215°F [215°F adverse CNMT]

TWO 150°F [150OF adverse CNMT]

THREE 80°F [80°F adverse CNMT]

c. RCS subcooling based on core c. IF RCS hot leg temperatures exit T/Cs GREATER THAN VALUE greater than 320°F [310'F FROM TABLE ABOVE USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING cooling in service, THEN go to Step 19.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 320'F

[3100F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 14d. IF no RHR pump can be started in injection mode, THEN go to Step 19.

d. PRZR level GREATER THAN 13% d. Do NOT stop SI pump. Return to

[40% adverse CNMT] Step 10.

e. Stop running SI pump

___________________________________________________________________________________ I REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 13 of 27 15 Check If Charging Flow Should Be Controlled To Maintain RCS Inventory:

a. Check RHR pumps - RUNNING IN a. Perform the following:

INJECTION MODE

1) Control charging flow to maintain RCS inventory:

"o RVLIS level (no RCPs)

BETWEEN 77% AND 82% [82%

AND 85% adverse CNMT]

-OR "o RVLIS fluid fraction (any RCP running) BETWEEN 84%

AND 90%

2) Go to Step 16.

b. Go to Step 19

I FOP: TITLE:

ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT - REV: 26

" SATURATED RECOVERY DESIRED PAGE 14 of 27 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI CAUTION "o IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST. THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

"o INADVERTENT CRITICALITY MAY OCCUR FOLLOWING NATURAL CIRCULATION COOLDOWN IF THE RCP IN THE RUPTURED LOOP IS STARTED FIRST.

16 Check RCP Status:

a. RCPs AT LEAST ONE RUNNING a. Try to start one RCP

1) IF RVLIS level (no RCPs) less than 95%, THEN perform the following:

"o Increase PRZR level to greater than 65% [82%

adverse CNMT]

"o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20'F using Figure MIN SUBCOOLING "o Energize PRZR heaters as necessary to saturate PRZR water

2) Establish conditions for starting an RCP:

"o Verify bus 11A or liB energized.

"o Refer to Attachment RCP START.

3) Start one RCP.

IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).

IF natural circulation NOT verified, THEN increase dumping steam.

b. Stop all but one RCP

.1 REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 15 of 27 CAUTION o VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

o IF SI HAS BEEN TERMINATED. THE ACCUMS SHOULD BE ISOLATED PRIOR TO DEPRESSURIZING THE RCS TO LESS THAN 1000 PSIG.

NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

o When using PRZR PORV, select one with an operable block valve.

17 Depressurize RCS To Saturation At Core Exit:

a. Determine saturation pressure for core exit T/Cs using Figure TSAT

b. Use normal PRZR spray valves b. Use one PRZR PORV. IF IA NOT associated with running RCP available, THEN refer to Attachment N2 PORVS.

e PCV-431A for A RCP

• PCV-431B for B RCP IF PORV NOT available. THEN use auxiliary spray valve (AOV-296).

c. Energize PRZR heaters as necessary

d. Depressurize RCS until EITHER of the following conditions satisfied:

"o PRZR level GREATER THAN 75%

[65% adverse CNMT]

-OR "o RCS pressure - AT SATURATION FROM STEP 17a

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 16 of 27 IRESPOýNSE NýOTOBýTAINEýD 18 Verify Adequate Shutdown Margin

a. Direct RP to sample RCS and ruptured S/G for boron concentration

b. Verify boron concentration b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM

"*19 Monitor SI Reinitiation Criteria:

a. Core exit T/Cs - DECREASING a. Manually start SI pumps as necessary.

b. Check RVLIS indication: b. Manually start SI pumps as necessary.

"o Level (no RCPs) GREATER THAN 77% [82% adverse CNMT]

-OR "o Fluid Fraction (any RCP running) GREATER THAN 84%

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 17 of 27 rý-

d TPH ACTION/EXPECTED RESPONSE[I RESPONSE NOT OBTAINEDIý 20 Check If SI ACCUMs Should Be Isolated:

a. RCS subcooling based on core a. IF both RCS hot leg temperatures exit T/Cs - GREATER THAN O F 0 less than 4000F, THEN go to USING FIGURE MIN SUBCOOLING Step 20c.

IF NOT, THEN go to Step 21.

b. PRZR level - GREATER THAN 5% b. Return to Step 10.

[30% adverse CNMT]

c. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves

• MOV-841, MCC C position 12F

• MOV-865, MCC D position 12C

d. Close SI ACCUM discharge valves d. Vent any unisolated ACCUMs:

• MOV-841 1) Open vent valves for

• MOV 865 unisolated SI ACCUMs.

"*ACCUM A, AOV-834A

"*ACCUM B, AOV-834B

2) Open HCV-945.

e. Locally reopen breakers for MOV-841 and MOV-865

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 18 of 27

-I 21 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.I. RESTORATION OF OFFSITE POWER).

"o Emergency DIG output breakers OPEN "o AC emergency bus voltage GREATER THAN 420 VOLTS "o AC emergency bus normal feed breakers CLOSED

b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP) 22 Minimize Secondary System Contamination:

a. Isolate reject from hotwell to a. IF hotwell level increasing, CST: THEN direct RP to sample hotwells for activity.

"o Place hotwell level controller (HC-107) in MANUAL at 50%

"o Verify hotwell level STABLE

b. Verify local actions to complete isolation of ruptured S/G (Refer to Attachment RUPTURED S/G)

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 19 of 27 STEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 23 Verify Adequate SW Flow To CCW Hx:

a. Verify at least two SW pumps a. Manually start pumps as power RUNNING supply permits (257 kw per pump). IF less than two SW pumps can be operated, THEN perform the following:

1) IF IO SW pumps running. THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

2) IF only one SW pump running.

THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

3) Go to Step 24.

b. Verify AUX BLDG SW isolation b. Manually align valves.

valves - OPEN

• MOV-4615 and MOV-4734 a MOV-4616 and MOV-4735 This Step continued on the next page.

REV:2 6 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 20 of 27 (Se 3CTIO N uTEDRRESPONSE p NfOTrOBTAINEvDi (Step 23 continued from previous page)

c. Verify CNMT RECIRC fan c. Perform the following:

annunciator C-2, HIGH TEMPERATURE ALARM - EXTINGUISHED 1) Determine required SW flow to CCW HXs per table:

SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2 Total of 5000 6000 gpm equally divided to both HXs Normal 1 5000 - 6000 gpm to in-service HX Alternate 2 30-33" d/p across each HX Alternate 1 95-100" d/p across in-service HX

2) Direct AO to adjust SW flow to required value.

o IF on normal SW discharge:

"* V-4619, CCW Hx A

"* V-4620. CCW Hx B

-OR o IF on alternate SW discharge:

o V-4619C. CCW Hx A o V-4620B. CCW Hx B

.1 REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 21 of 27 SE ACTION/ EXPECTED RESPONSE]RESPONSE NOT OBTAINEýD

]

H OBTAINED NOT 24 Check RCP Cooling Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).

a. Check CCW to RCPs "o Annunciator A-7, RCP 1A CCW RETURN HIGH TEMP OR LOW FLOW

- EXTINGUISHED "o Annunciator A-15, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED

b. Check RCP seal injection "o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER

-OR "o RCP seal injection flow to each RCP GREATER THAN 6 GPM

---

m" SGTR WITH LOSS OF REACTOR COOLANT REV: 26 SATURATED RECOVERY DESIRED PAGE 22 of 27 25 Check If Seal Return Flow Should Be Established:

a. Verify instrument bus D a. Perform the following:

ENERGIZED

1) Ensure steam dump mode control in MANUAL.

2) Restore power to instrument bus D from MCC B or MCC A (maintenance supply).

b. Verify RCP #1 seal outlet b. Go to Step 26.

temperature LESS THAN 235°F

c. Verify RCP seal outlet valves c. Manually open valves as OPEN necessary.

"*AOV-270A

"*AOV-270B

d. Reset both trains of XY relays for RCP seal return isolation valve MOV-313

e. Open RCP seal return isolation e. Perform the following:

valve MOV-313

1) Place MOV-313 switch to OPEN.

2) Dispatch AO with key to RWST gate to locally open MOV-313.

f. Verify RCP #1 seal leakoff flow f. Perform the following:

LESS THAN 6.0 GPM

1) Trip the affected RCP

2) Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve e RCP A, AOV-270A

• RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 26.

g. Verify RCP #1 seal leakoff flow g. Refer to AP-RCP.1, RCP SEAL GREATER THAN 0.8 GPM MALFUNCTION.

SGTR WITH LOSS OF REACTOR COOLANT REV: 26 SATURATED RECOVERY DESIRED PAGE 23 of 27 II sTEP 1' A77 ON /EXPECTED 111 RESPONS: RESPONSE NOT OBTAINEDM NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

26 Check If Source Range Detectors Should Be Energized:

a. Source range channels a. Go to Step 26e.

DEENERGIZED

b. Check intermediate range flux b. Perform the following:

EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing, THEN initiate boration.

2) Continue with Step 27. WHEN flux is LESS THAN 10-10 amps on any operable channel, THEN do Steps 26c, d and e.

c. Check the following: c. Continue with Step 27. WHEN either condition met, THEN do "o Both intermediate range Steps 26d and e.

channels - LESS THAN 10-10 AMPS

-OR "o Greater than 20 minutes since reactor trip

d. Verify source range detectors d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can NOT be restored, THEN refer to ER-NIS.l, SR MALFUNCTION and go to Step 27.

e. Transfer Rk-45 recorder to one source range and one intermediate range channel

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 24 of 27 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 27 Establish Normal Shutdown Alignment:

a. Check condenser AVAILABLE a. Dispatch AO to perform Attachment SD-2.

b. Perform the following:

"o Open generator disconnects

"* 1G13A71

"* 9X13A73 "o Place voltage regulator to OFF "o Open turbine drain valves "o Rotate reheater steam supply controller cam to close valves "o Place reheater dump valve switches to HAND "o Stop all but one condensate pump

c. Verify adequate Rx head cooling:

1) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)

2) Verify one Rx compartment 2) Perform the following:

cooling fan RUNNING "o Dispatch AO to reset UV relays at MCC C and MCC D.

"o Manually start one fan as power supply permits (23 kw).

d. Verify Attachment SD-1 COMPLETE

-I REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 25 of 27 1

-I ST.ACTION/EXPECTED RESPONSE. RESPONSE NOT OBTAINED CAUTION FEED FLOW SHOULD NOT BE ESTABLISHED TO ANY RUPTURED S/G WHICH IS ALSO FAULTED UNLESS IT IS NEEDED FOR RCS COOLDOWN.

• 28 Monitor Ruptured S/G(s) Refill ruptured S/G to 80% [60%

Narrow Range Level - GREATER adverse CNMT] using feed flow.

THAN 17% [25% adverse CNMT]

IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G unless needed for RCS cooldown:

"o Ruptured S/G pressure decreases in an uncontrolled manner.

-OR "o Ruptured S/G pressure increases to 1020 psig.

• 29 Monitor RCP Operation:

a. RCPs ANY RUNNING a. Go to Step 30.

b. Check the following: b. Stop the affected RCP(s).

"o RCP #1 seal D/P GREATER THAN 220 PSID

" Check RCP seal leakage WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF

REV:2 6 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 26 of 27 STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Check Condenser Steam Dump Use intact S/G ARV for RCS Available - CONDENSER VACUUM temperature control.

GREATER THAN 20 INCHES HG 31 Check If RHR Normal Cooling Can Be Established:

a. RCS cold leg temperature - LESS a. Go to Step 32.

THAN 350°F

b. RCS pressure LESS THAN b. Go to Step 32.

400 psig [300 psig adverse CNMT]

c. Place letdown pressure controller in MANUAL CLOSED

d. Check following valves - OPEN d. Perform the following:

"*AOV-371. letdown isolation 1) Reset both trains of XY valve relays for AOV-371 and

"*AOV-427. loop B cold leg to AOV-427.

REGEN Hx

"*At least one letdown orifice 2) Open AOV-371 and AOV-427.

valve (AOV-200A, AOV-200B, or AOV-202) 3) Open one letdown orifice valve.

e. Verify pressure on PI-135 LESS e. Go to Step 32.

THAN 400 PSIG

f. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)

g. Consult TSC to determine if RHR normal cooling should be established using Attachment RHR COOL

a REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 27 of 27 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED[

NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 32.

32 Check CNMT Hydrogen Concentration:

a. Direct RP to start CNMT hydrogen monitors as necessary

b. Hydrogen concentration LESS b. Consult TSC to determine if THAN 0.5% hydrogen recombiners should be placed in service.

33 Check Core Exit T/Cs - LESS Return to Step 3.

THAN 2000 F 34 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions

b. Consult TSC

-END

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED PAGE 1 of 1

--I ECA-3.2 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG 1.0)

3) FIGURE SDM (FIG -2.0)

4) FIGURE TSAT (FIG -8.0)

5) FIGURE RCP SEAL LEAKOFF (FIG-4.0)

6) ATTACHMENT SFP-RWST (ATT- 18. 0)

7) ATTACHMENT N2 PORVS (ATT- 12.0)

8) ATTACHMENT NC (ATT- 13.0)

9) ATTACHMENT SEAL COOLING (ATT 15.2)

10) ATTACHMENT RCP START (ATT 15.0)

11) ATTACHMENT D/G STOP (ATT 8.1)

12) ATTACHMENT RUPTURED S/G (ATT 16.0)

13) ATTACHMENT SD-I (ATT 17.0)

14) ATTACHMENT SD-2 (ATT 17.1)

15) ATTACHMENT RHR COOL (ATT 14.1)

16) ATTACHMENT NO SW PUMPS (ATT 2.4)

17) ATTACHMENT LOSS OF OFFSITE POWER (ATT -8.5)

18) FOLDOUT

-- m-"

TITLE:

REV: 26 SGTR WITH LOSS OF REACTOR COOLANT -

,CA-3.2 SATURATED RECOVERY DESIRED PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%

b. CORE COOLING - Core exit T/Cs greater than 1200'F

-OR Core exit T/Cs greater than 7000F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 5%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F

e. CONTAINMENT - CNMT pressure greater than 60 psig

SGTR WITH LOSS OF REACTOR COOLANT REV: 26 SATURATED RECOVERY DESIRED PAGE 1 of 1 FOLDOUT PAGE

1. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start SI pumps as necessary:

o Core exit T/Cs - INCREASING

-OR o Check RVLIS indication:

Level (no RCPs) - LESS THAN 77% [82% adverse CNMT]

Fluid fraction (any RCP running) - LESS THAN 84%

2. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized, and has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1, UNLESS faulted S/G needed for RCS cooldown.

3. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

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.I, ALTERNATE WATER SUPPLY TO AFW PUMPS).

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER S RESPONS IBIy- MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides actions for a SGTR with coincident loss of normal and auxiliary PRZR sprays and PORVs.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-3, STEAM GENERATOR TUBE RUPTURE, when PRZR pressure control is not available.

NOTE: 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+05 R/hr.

1 Check Ruptured S/G Narrow Go to Step 8.

Range Level - LESS THAN 80%

[60% adverse CNMT]

2 Check RCP Status - AT LEAST Try to start one RCP:

ONE RUNNING

a. Establish conditions for starting RCP.

"o Bus 11A and Bus 1iB energized "o Refer to Attachment RCP START

b. Start one RCP. IF no RCP can be started, THEN go to Step 4.

3 Check IF Normal PRZR Spray Available:

a. Verify the following: a. Perform the following:

1) Verify IA to CNMT - AVAILABLE 1) Place PRZR heater control group to PULL STOP.

2) Verify spray valve associated with running RCP - OPERABLE 2) Place PRZR heater backup group to OFF.

3) Place normal spray valve controllers to MANUAL at 0%.

4) Go to Step 4.

b. Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 21

4 Try To Restore PRZR PORV:

a. Block valves - AT LEAST ONE OPEN a. Open one block valve unless it was closed to isolate an open

"*MOV-516 for PCV-430 PORV.

"*MOV-515 for PCV-431C If block valves can NOT be opened, THEN dispatch AO to locally ensure breakers to block valves closed.

"*MOV-515, MCC D position 6C

"*MOV-516, MCC C position 6C

b. Check IA to CNMT - AVAILABLE b. Refer to Attachment N2 PORVS to operate PORVs.

c. Verify at least one PRZR PORV c. Go to Step 5.

flow path - AVAILABLE

d. Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 22

SE ACTION/EXPECTED RE PONSE RESPONSE NOT OBTAINEDI NOTE: If auxiliary spray is the only means of RCS pressure control, THEN the 320°F AT limit between the spray line and PRZR does not apply.

5 Try To Establish Auxiliary Spray:

a. Charging pumps - AT LEAST ONE a. Perform the following:

RUNNING

1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high, THEN locally isolate seal injection to affected RCP.

"*RCP A, V-300A

"*RCP B, V-300B

2) Ensure HCV-142 demand at 0%.

3) Start charging pumps as necessary.

IF charging not available, THEN go to Step 6.

b. Establish auxiliary spray flow: b. IF auxiliary spray can NOT be established, THEN go to Step 6.

1) Open auxiliary spray valve (AOV-296)

2) Close charging valve to loop B cold leg (AOV-294)

c. Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 21b

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

• 6 Monitor Intact S/G Level:

a. Narrow range level GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in at least one SIG.

b. Control feed flow to maintain b. IF narrow range level in intact narrow range level between 17% S/G continues to increase in an

[25% adverse CNMT] and 50% uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

7 Check PRZR Level - GREATER Return to Step 1.

THAN 5% [30% adverse CNMT]

STEP ACTION /EXPECTED RESPONSE NOT OBTAINEDI 8 Check If SI Can Be Terminated:

a. RCS subcooling based on core a. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN 0°F ECA-3.1, SGTR WITH LOSS OF USING FIGURE MIN SUBCOOLING REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

b. Secondary heat sink: b. IF neither condition satisfied THEN do NOT stop SI pumps. Go "o Total feed flow to intact to ECA-3.1, SGTR WITH LOSS OF S/Gs GREATER THAN 200 GPM REACTOR COOLANT - SUBCOOLED AVAILABLE RECOVERY DESIRED, Step 1.

-OR "o Narrow range level in intact S/G GREATER THAN 5% [25%

adverse CNMT]

c. RVLIS indication c. Do NOT stop SI pumps. Go to ECA-3.1, SGTR WITH LOSS OF "o Level (no RCPs) GREATER REACTOR COOLANT - SUBCOOLED THAN 77% [82% adverse CNMT] RECOVERY DESIRED. Step 1.

-OR "o Fluid fraction (any RCP running) GREATER THAN 84%

d. Any ruptured S/G narrow range d. Do NOT stop SI pumps. Return to level INCREASING IN AN Step 2.

UNCONTROLLED MANNER OR OFFSCALE HIGH

9 Stop SI Pumps and Place In AUTO

STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check If Charging Flow Has Been Established:

a. Charging pumps ANY RUNNING a. Perform the following:

1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s) to affected RCP:

"* RCP A, V-300A

"* RCP B. V-300B

2) Ensure HCV-142 open, demand at 0%.

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 dispatch AO to locally open "o LCV-112C - CLOSED manual charging pump suction from RWST (V-358 located in charging pump room).

IF LCV-112C can NOT be closed, THEN perform the following:

1) Verify charging pump A NOT running and place in PULL STOP.

2) 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 perform the following:

o Restore PRZR level o Maintain RCS subcooling based on core exit T/Cs - GREATER THAN 0°F USING FIGURE MIN SUBCOOLING

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• 11 Monitor RCS Inventory: Perform the following:

"o RCS subcooling based on core a. Manually start SI pumps as exit T/Cs GREATER THAN 0°F necessary.

USING FIGURE MIN SUBCOOLING

b. Go to ECA-3.1, SGTR WITH LOSS OF "o RVLIS indication REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

o Level (no RCPs) GREATER THAN 77% [82% adverse CNMT]

-OR o Fluid fraction (any RCP running) - GREATER THAN 84%

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Verify Adequate SW Flow To CCW Hx:

a. Verify at least two SW pumps - a. Manually start pumps as power RUNNING supply permits (257 kw per pump). IF less than two SW pumps can be operated, THEN perform the following:

1) IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

2) IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

3) Go to Step 20.

b. Verify AUX BLDG SW isolation b. Manually align valves.

valves OPEN

• MOV-4615 and MOV-4734

• MOV-4616 and MOV-4735 This Step continued on the next page.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDK (Step 12 continued from previous page)

c. Verify CNMT RECIRC fan c. Perform the following:

annunciator C-2, HIGH TEMPERATURE ALARM - EXTINGUISHED 1) Determine required SW flow to CCW HXs per table:

SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2 Total of 5000 6000 gpm equally divided to both HXs Normal 1 5000 6000 gpm to in-service HX Alternate 2 30-33" d/p across each HX Alternate 1 95-100" d/p across in-service HX

2) Direct AO to adjust SW flow to required value.

o IF on normal SW discharge:

"*V-4619, CCW Hx A

"* V-4620. CCW Hx B

-OR o IF on alternate SW discharge:

e V-4619C. CCW Hx A o V-4620B. CCW Hx B

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Check If Normal CVCS Operation Can Be Established

a. Verify IA restored: a. Continue with Step 17. WHEN IA restored, THEN do Steps 13 o IA to CNMT (AOV-5392) OPEN through 16.

o IA pressure GREATER THAN 60 PSIG

b. Verify instrument bus D b. Energize MCC B. IF MCC B NOT ENERGIZED available, THEN perform the following:

1) Verify MCC A energized.

2) Place instrument bus D on maintenance supply.

C. CCW pumps ANY RUNNING c. Perform the following:

1) IF any RCP #1 seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected RCP(s).

"*RCP A, MOV-749A and MOV-759A

"*RCP B, MOV-749B and MOV-759B

2) Manually start one CCW pump.

d. Charging pump ANY RUNNING d. Continue with Step 20. WHEN any charging pump running, THEN do Steps 14 through 17.

NOTE: If PRZR level is less than 13%. letdown may be established by placing AOV-427 to OPEN.

14 Establish Normal Letdown: IF RCP seal return has been established, THEN establish excess

a. Establish charging line flow to letdown as follows:

REGEN Hx GREATER THAN 20 GPM "o Place excess letdown divert

b. Place the following switches to valve, AOV-312. to NORMAL.

CLOSE:

"o Ensure CCW from excess letdown e Letdown orifice valves open. (AOV-745).

(AOV-200A. AOV-200B. and AOV-202) "o Open excess letdown isolation e AOV-371, letdown isolation valve AOV-310.

valve e AOV-427, loop B cold leg to " Slowly open HCV-123 to maintain REGEN Hx excess letdown temperature less than 195°F and pressure less

c. Place letdown controllers in than 100 psig.

MANUAL at 40% open "o Adjust charging pump speed as

"*TCV- 130 necessary.

"*PCV- 135 IF RCP seal return NOT established.

d. Reset both trains of XY relays THEN consult TSC to determine if for AOV-371 and AOV-427 excess letdown should be placed in service.

e. Open AOV-371 and AOV-427

f. Open letdown orifice valves as necessary

g. Place TCV-130 in AUTO at 105°F

h. Place PCV-135 in AUTO at 250 psig

i. Adjust charging pump speed and HCV-142 as necessary

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Check VCT Makeup System:

a. Adjust boric acid flow control valve in AUTO to 9.5 gpm

b. Adjust RMW flow control valve in AUTO to 40 gpm

c. Verify the following: c. Adjust controls as necessary.

1) RMW mode selector switch in AUTO

2) RMW control armed - RED LIGHT LIT

d. Check VCT level: d. Manually increase VCT makeup flow as follows:

"o Level - GREATER THAN 20%

1) Ensure BA transfer pumps and

-OR RMW pumps running. IF NOT, THEN reset MCC C and MCC D UV "o Level - STABLE OR INCREASING lockouts as necessary.

2) Place RMW flow control valve HCV-111 in MANUAL.

3) Increase RMW flow.

STE ACTION/EXPECTED RESPONSE[ RESPONSE NOT OBTAINED[

16 Check Charging Pump Suction Aligned To VCT:

a. VCT level - GREATER THAN 20% a. IF VCT level can NOT be maintained greater than 5%, THEN perform the following:

1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed

2) Continue with Step 17. WHEN VCT level greater than 40%,

THEN do Step 16b.

b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.

o LCV-112C - OPEN o LCV-112B - CLOSED

qSTEPH ACT ION/ EXPECTED RSOE RESPONSE NOT OBTAINEDI 17 Check RCP Cooling: Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).

a. Check CCW to RCPs:

"o Annunciator A-7, RCP 1A CCW RETURN HIGH TEMP OR LOW FLOW

- EXTINGUISHED "o Annunciator A-15, RCP lB CCW RETURN HIGH TEMP OR LOW FLOW

- EXTINGUISHED

b. Check RCP seal injection:

"o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER

-OR "o RCP seal injection flow to each RCP GREATER THAN 6 GPM

18 Check If Seal Return Flow Should Be Established:

a. Verify RCP #1 seal outlet a. Go to Step 19.

temperature - LESS THAN 2350F

b. Verify RCP seal outlet valves b. Manually open valves as OPEN necessary.

• AOV-270A

• AOV-270B

c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313

d. Open RCP seal return isolation d. Perform the following:

valve MOV-313

1) Place MOV-313 switch to OPEN.

2) Dispatch AO with key to RWST gate to locally open MOV-313.

e. Verify RCP #1 seal leakoff flow e. Perform the following:

LESS THAN 6.0 GPM

1) Trip the affected RCP

2) Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve

"*RCP A, AOV-270A

"*RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 19.

f. Verify RCP #1 seal leakoff flow f. Refer to AP-RCP.1, RCP SEAL GREATER THAN 0.8 GPM MALFUNCTION.

19 Equalize Charging And Letdown Flows:

a. Verify charging pump controllers in manual

b. Control charging and seal injection flows to equal letdown and seal leakoff flows 20 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

"o Emergency DIG output breakers OPEN "o AC emergency bus voltage GREATER THAN 420 VOLTS "o AC emergency bus normal feed breakers - CLOSED

b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP) 21 Minimize Secondary System Contamination:

a. Isolate reject from hotwell to a. IF hotwell level increasing, CST: THEN direct RP to sample hotwells for activity.

o Place hotwell level controller (HC-107) in MANUAL at 50%

o Verify hotwell level - STABLE

b. Verify local actions to complete isolation of ruptured S/G (Refer to Attachment RUPTURED SIG)

STE ACTION/EXPECTED RESPONSEI i RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

22 Check If Source Range Detectors Should Be Energized:

a. Source range channels a. Go to Step 22e.

DEENERGIZED

b. Check intermediate range flux b. Perform the following:

EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing, THEN initiate boration.

2) Continue with Step 23. WHEN flux is LESS THAN 10-10 amps on any operable channel, THEN do Steps 22c through e.

c. Check the following: c. Continue with Step 23. WHEN either condition met. THEN do "o Both intermediate range Steps 22d and e.

channels LESS THAN 10-10 AMPS

-OR "o Greater than 20 minutes since reactor trip

d. Verify source range detectors d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can NOT be restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 22.

e. Transfer Rk-45 recorder to one source range and one intermediate range channel

TACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 23 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.

b. Perform the following:

"o Open generator disconnects o 1G13A71 a 9X13A73 "o Place voltage regulator to OFF "o Open turbine drain valves "o Rotate reheater steam supply controller cam to close valves "o Place reheater dump valve switches to HAND "o Stop all but one condensate pump

c. Verify adequate Rx head cooling:

1) Manually start one fan as

1) Verify at least one control rod shroud fan - RUNNING power supply permits (45 kw)

2) Verify one Rx compartment 2) Perform the following:

cooling fan RUNNING "o Dispatch AO to reset UV relays at MCC C and MCC D.

"o Manually start one fan as power supply permits (23 kw)

d. Verify Attachment SD-1 COMPLETE

STEP ACTION/EXPECTED RESPO S I RESPONSE NOT OBTAINEDI NOTE: Plant staff should decide whether to repair PRZR pressure control systems or continue with this procedure. If PRZR pressure control is established, PRZR level should be restored to greater than 5% [30%

adverse CNMT] and then further recovery should continue with E-3, STEAM GENERATOR TUBE RUPTURE, Step 32.

24 Check If SI ACCUMs Should Be Isolated:

a. Check the following: a. Return to Step 11.

"o RCS subcooling based on core exit T/Cs GREATER THAN 0°F USING FIGURE MIN SUBCOOLING "o RVLIS indication "o Level (no RCPs - GREATER THAN 77% [82% adverse CNMT]

-OR "o Fluid fraction (any RCP running) GREATER THAN 84%

b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves

• MOV-841, MCC C position 12F

• MOV-865, MCC D position 12C

c. Close SI ACCUM discharge valves c. Vent any unisolated ACCUMs:

• MOV-841 1) Open vent valves for

• MOV-865 unisolated SI ACCUMs.

e ACCUM A, AOV-834A

• ACCUM B, AOV-834B

2) Open HCV-945.

d. Locally reopen breakers for MOV-841 and MOV-865

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

25 Verify Adequate Shutdown Margin

a. Direct RP to sample RCS and ruptured S/G for boron concentration

b. Verify boron concentration b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM 26 Maintain Required RCP Seal Perform the following:

Injection Flow And Labyrinth Seal D/P: "o Adjust charging flow to REGEN Hx, HCV-142 as necessary.

"o Labyrinth seal D/P to each RCP GREATER THAN 15 INCHES OF WATER -OR "o RCP seal injection flow "o Dispatch AO to adjust seal GREATER THAN 6 GPM injection needle valves V-300A and V-300B if necessary.

27 Initiate RCS Cooldown to 3500F In RCS Cold Legs:

a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN ]00OF/HR

b. Dump steam to condenser from b. Manually or locally dump steam intact S/G using intact S/G ARV.

IF no intact S/G available, THEN use faulted S/G.

SACTONIXPETEDRESONSI IRESPýONSE NýOT OBTAINEOI CAUTI ON RCS AND RUPTURED SIG PRESSURES MUST BE MAINTAINED LESS THAN THE RUPTURED S/G ARV SETPOINT.

28 Control Charging Flow To Maintain RCS Subcooling:

a. RCS subcooling based on core a. Increase charging flow to exit T/Cs GREATER THAN 2 0 °F maintain subcooling greater than USING FIGURE MIN SUBCOOLING 20°F using Figure MIN SUBCOOLING and go to Step 29.

b. Ruptured S/G narrow range level b. Control charging flow to

- LESS THAN 90% [80% adverse maintain RCS pressure at CNMT] ruptured S/G pressure and go to Step 29.

c. Ruptured S/G narrow range level c. IF ruptured SIG level STABLE OR DECREASING increasing, THEN decrease charging flow to stabilize level. Maintain RCS subcooling greater than 20°F using Figure MIN SUBCOOLING.

29 Check If RCS Cooldown Should Be Stopped:

a. RCS cold leg temperatures LESS a. Return to Step 25.

THAN 350°F

b. Stop RCS cooldown

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

30 Check RCS Pressure - GREATER Go to Step 33.

THAN 400 PSIG [300 PSIG adverse CNMT]

• 31 Monitor Ruptured S/G Narrow Refill ruptured S/C to 80% [60%

Range Level - GREATER THAN adverse CNMT] using feed flow.

17% [25% adverse CNMT]

IF any of the following conditions occurs, THEN stop feed flow to ruptured S/G:

"o Ruptured S/G pressure decreases in an uncontrolled manner.

-OR "o Ruptured S/G pressure increases to 1020 psig.

-OR

" Ruptured S/G pressure decreases to 350 psig psig AND ruptured S/G level greater than 5% [25%

adverse CNMT]

STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI CAUTION o STEAM SHOULD NOT BE RELEASED FROM A RUPTURED S/G IF WATER MAY EXIST IN ITS STEAMLINE.

o RUPTURED SIG PRESSURE MAY DECREASE RAPIDLY WHEN STEAM IS RELEASED.

32 Depressurize RCS And Ruptured S/G To 400 PSIG [300 PSIG adverse CNMT]

a. Perform the following:

o Decrease charging and increase letdown to initiate backfill

-OR o Initiate blowdown from ruptured S/G

-OR o Dump steam from ruptured S/G

b. Check RCS pressure LESS THAN b. Return to Step 31.

400 psig [300 psig adverse CNMT]

c. Stop RCS depressurization

33 Check If RHR Normal Cooling Can Be Established:

a. RCS cold leg temperature - LESS a. Return to Step 27.

THAN 350°F

b. RCS pressure - LESS THAN b. Return to Step 31.

400 psig [300 psig adverse CNMT]

c. Place RCS overpressure c. IF RCS overpressure protection protection system in service system can NOT be placed in (Refer to 0-7, ALIGNMENT AND service, THEN notify TSC of OPERATION OF THE REACTOR VESSEL potential Tech Spec violation if OVERPRESSURE PROTECTION SYSTEM) RHR system is placed in service.

d. Establish RHR normal cooling (Refer to Attachment RHR COOL)

NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

34 Verify Adequate Shutdown Margin

a. Direct RP to sample RCS and ruptured S/G for boron concentration

b. Verify boron concentration b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Initiate RCS Cooldown To Cold Shutdown:

a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100°F/HR

b. Use RHR system if in service

c. Dump steam to condenser from c. Manually or locally dump steam intact S/G from intact S/G using ARVs.

IF no intact SIG available and RHR system NOT in service, THEN use faulted SIG.

36 Control Charging Flow To Maintain RCS Subcooling:

a. RCS subcooling based on core a. Increase charging flow to exit T/Cs GREATER THAN 20°F maintain subcooling greater than USING FIGURE MIN SUBCOOLING 20'F using Figure MIN SUBCOOLING and go to Step 37.

b. Ruptured S/G narrow range level b. Control charging flow to

- LESS THAN 90% [80% adverse maintain RCS pressure at CNMT] ruptured S/G pressure and go to Step 37.

c. Ruptured S/G narrow range level c. IF ruptured S/G level STABLE OR DECREASING increasing. THEN decrease charging flow to stabilize level. Maintain RCS subcooling greater than 20°F using Figure MIN SUBCOOLING.

STEP ACTIOr/EXPECTED r RSPONSE RESPONSENOT OBTAINEC

• 37 Monitor RCP Operation:

a. RCPs ANY RUNNING a. Go to Step 39.

b. Check the following: b. Stop the affected RCP(s).

"o RCP #1 seal D/P - GREATER THAN 220 PSID "o Check RCP seal leakage WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF 38 Check Core Exit T/Cs - LESS Return to Step 34.

THAN 2000 F 39 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions

b. Consult TSC

-END-

ECA-3.3 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG- 1.0)

3) FIGURE SDM (FIG -2.0)

4) FIGURE RCP SEAL LEAKOFF (FIG -4.0)

5) ATTACHMENT RCP START (ATT- 15.0

6) ATTACHMENT N2 PORVS (ATT 12.0)

7) ATTACHMENT RUPTURED S/G (ATT -16.0)

8) ATTACHMENT D/G STOP (ATT -8. 1)

9) ATTACHMENT SD-i (ATT 17.0)

10) ATTACHMENT SEAL COOLING (ATT 15.2)

11) ATTACHMENT SD-2 (ATT -17.1)

12) ATTACHMENT RHR COOL (ATT- 14.1)

13) ATTACHMENT NO SW PUMPS (ATT- 2.4)

14) FOLDOUT

RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%

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 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 5%

[25% 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 2850F

e. CONTAINMENT - CNMT pressure greater than 60 psig

FOLDOUT PAGE

1. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:

"o RCS subcooling based on core exit TCs - LESS THAN 0°F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING

- OR "o Check RVLIS indication:

Level (no RCPs) - LESS THAN 77% [82% adverse CNMT]

Fluid Fraction (any RCP running) - LESS THAN 84%

2. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1, UNLESS faulted S/G needed for RCS cooldown.

3. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

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.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).

LoP: TITLE: REV: 20 ES-0.1 REACTOR TRIP RESPONSE PAGE 1 of 19 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER '3 RESPONSIBLEMANAGER S_?o2,5- -YcDATE EFFECTIVE (o

CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 20 ES-0.1 REACTOR TRIP RESPONSE PAGE 2 of 19 A. PURPOSE - This procedure provides the necessary instructions to stabilize and control the plant following a reactor trip without a safety injection.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-0, REACTOR TRIP OR SAFETY INJECTION, when SI is neither actuated nor required.

EOP: TITLE:

REV: 20 ES-0.1 REACTOR TRIP RESPONSE PAGE 3 of 19 CAUTION IF SI ACTUATION OCCURS DURING THIS PROCEDURE, THEN E-0, REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORMED.

NOTE: o FOLDOUT page should be open and monitored periodically.

"o Critical Safety Function Status Trees should be monitored. (Refer to Appendix I for Red Path Summary.)

" Refer to AP(s) that were in effect prior to the reactor trip.

• 1 Monitor RCS Tavq - STABLE AT IF temperature less than 547°F and OR TRENDING TO 5470 F decreasing, THEN perform the following:

a. Stop dumping steam.

b. Ensure S/G blowdown and sample valves closed.

c. Ensure reheater steam supply valves are closed.

d. IF MDAFW pumps supplying greater than 200 gpm, THEN ensure TDAFW pump steam supply valves in PULL STOP.

e. IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level greater than 5% in at least one S/G. WHEN S/G level greater than 5% in one S/G, THEN limit feed flow to that required to maintain S/G level.

f. IF cooldown continues below 540 0 F, THEN close both MSIVs.

IF temperature greater than 547°F and increasing. THEN dump steam to stabilize and slowly decrease temperature to 547°F.

SE ACTION/EXPECTEDoS SRESPONSE NOT OBTAIND 2 Check S/G Feed Flow Status:

a. Check RCS Tavg LESS THAN 554°F a. Continue with Step 3. WHEN temperature less than 554°F.

THEN do Steps 2b through f.

b. Verify MFW flow control valves b. Place A and B MFW regulating CLOSED valve and bypass valve controllers in MANUAL at 0%

"* MFW regulating valves demand.

"* MFW bypass valves

c. Verify total AFW flow - GREATER c. Manually start both MDAFW pumps.

THAN 200 GPM IF total AFW flow greater than 200 gpm can NOT be established.

THEN perform the following:

"o Manually start TDAFW pump.

-OR "o Perform the following:

1) Establish MFW on bypass valves.

2) Go to step 3.

d. Close MFW pump discharge valves

• MOV-3977, A MFW pump

• MOV-3976, B MFW pump

e. Stop MFW pumps and place in PULL STOP

f. WHEN both MFP pumps are stopped, THEN place A and B MFW regulating valve and bypass valve controllers in MANUAL at 0% demand.

3 - ees.: R RioOxS NOT OMnAitrSC 3 Monitor 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, THEN stop and 52%. feed to that SIG.

4 Verify MRPI Indicates - ALL IF one or more control rods NOT CONTROL AND SHUTDOWN RODS ON fully inserted, THEN perform the BOTTOM following:

a. Place RMW mode selector switch to BORATE.

b. Adjust boric acid flow control valve, FCV-I1OA, for desired flowrate.

c. Set boric acid integrator to desired amount (650 gallons for each control rod not fully inserted).

d. Place RMW control to start and verify flow. IF flow can NOT be established, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION.

EOP: TITLE: REV: 20 ES-0.1 REACTOR TRIP RESPONSE PAGE 6 of 19 SON/EXPECTED RESPONSE NOT OBTAINED 5 Verify All AC Busses Perform the following:

ENERGIZED BY OFFSITE POWER

a. IF any AC emergency bus normal o Normal feed breakers to all 480 feed breaker open, THEN ensure volt busses - CLOSED associated D/G breaker closed.

o 480 volt bus voltage GREATER b. Perform the following as THAN 420 VOLTS necessary:

o Emergency D/G output breakers 1) Ensure one CCW pump running.

OPEN

2) Close non-safeguards bus tie breakers:

"* Bus 13 to Bus 14 tie

"* Bus 15 to Bus 16 tie

3) Reset Bus 13 and Bus 15 lighting breakers.

4) Dispatch AO to locally reset and start adequate air compressors.

5) Place the following pumps in PULL STOP:

"*EH pumps

"*Turning gear oil pump

"* HP seal oil backup pump

6) Restore power to MCCs.

"*A from Bus 13

"*B from Bus 15

"*E from Bus 15

"*F from Bus 15

7) Start HP seal oil backup pump

8) Establish 2 CNMT RECIRC fans in service (205 kw each).

9) Ensure D/G load within limits.

c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

EOP: TITLE:

ES-0.1 REACTOR TRIP RESPONSE PAGE 7 of 19 STP ATONEPCE REPOS RESONEOTOT INE 6 Verify At Least Two SW Pumps Manually start SW pumps as

- RUNNING necessary.

IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

7 Verify IA Available: Dispatch AG to locally reset and start adequate air compressors.

"o Adequate air compressor(s)

RUNNING IF adequate electric air compressor(s) can NOT be operated, "o IA pressure GREATER THAN THEN use diesel air compressor.

60 PSIG (Refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)

IF IA pressure can NOT be maintained, THEN perform the following:

a. Refer to AP-IA.1, LOSS OF INSTRUMENT AIR.

b. Verify charging pump A NOT running and place in PULL STOP.

c. Dispatch AO to locally open V-358, manual charging pump suction from RWST (charging pump room).

d. WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (charging pump room).

EOP: TITLE: REV: 20 ES-0.1 REACTOR TRIP RESPONSE PAGE 8 of 19 I

STEP ACTION/EXPECTED RESPONS RESPONSE NOT OBTAINEDI 8 Check PRZR Level Control:

a. Verify charging pumps ANY a. Perform the following:

RUNNING

1) Close letdown isolation, AOV-427.

2) Manually start one charging pump.

b. PRZR level GREATER THAN 13% b. Perform the following:

1) Place letdown isolation AOV-427 switch to close.

2) Verify excess letdown isolation valve AOV-310 closed.

3) Ensure PRZR heaters off.

4) Control charging to restore PRZR level greater than 13%.

5) Continue with Step 9. WHEN PRZR level greater than 13%,

THEN do Steps 8c through e.

c. Verify letdown IN SERVICE c. Verify excess letdown in service. IF NOT, THEN manually place letdown in service (Refer to ATT-9.0, ATTACHMENT LETDOWN).

d. PRZR level TRENDING TO 35% d. Control charging and letdown to maintain PRZR level at 35%.

e. Check PRZR heaters - ENERGIZED e. Reset PRZR heaters and energize to restore PRZR pressure.

o PRZR proportional heaters o PRZR heater backup group

EOP: TITLE: REV: 20 ES-0.1 REACTOR TRIP RESPONSE PAGE 9 of 19 9 Check PRO PE ssurE1"I Control:o*o Ro I 9 Check PRZR Pressure Control:

a. PRZR pressure - GREATER THAN a. Perform the following:

1750 PSIG

1) Verify SI actuation. IF NOT, THEN manually actuate SI and CI.

2) Go to E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1.

b. PRZR pressure GREATER THAN b. IF pressure less than 2210 PSIG 2210 PSIG and decreasing, THEN perform the following:

1) Ensure PRZR PORVs closed.

IF any valve can NOT be closed, THEN manually close its block valve.

o PCV-430, MOV-516 o PCV-431C, MOV-515

2) Ensure normal PRZR spray valves closed.

"*PCV-431A

"*PCV-431B IF valves can NOT be closed, THEN stop associated RCP(s).

3) Ensure PRZR heaters energized.

This Step continued on the next page.

EOP: TITLE:

REV: 20 ES-0.1 REACTOR TRIP RESPONSE PAGE 10 of 19 (Step 9 continued from previous page)

c. PRZR pressure - LESS THAN c. IF pressure greater than 2260 PSIG 2260 psig and increasing, THEN perform the following:

1) Verify demand on PRZR pressure controller 431K greater than 50%. IF NOT, THEN place controller in MANUAL and adjust to restore PRZR pressure to approximately 2235 psig.

2) Ensure PRZR heaters off.

3) Control pressure using normal PRZR spray.

IF normal PRZR spray NOT available and letdown is in service, THEN perform the following:

a) Verify spray line fluid to PRZR AT less than 320 0 F.

IF NOT, THEN use one PORV.

b) Use auxiliary spray.

IF PRZR spray NOT available, THEN use one PRZR PORV.

SACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINEDI 10 Check If TDAFW Pump Can Be Stopped:

a. Both MDAFW pumps RUNNING a. Go to Step 11.

b. PULL STOP TDAFW pump steam supply valves

• MOV- 3504A

• MOV- 3505A 11 Establish Condenser Steam Dump Pressure Control:

a. Verify condenser available: a. Perform the following:

"o Any MSIV - OPEN 1) Place S/G ARV controller in AUTO at 1005 psig and verify "o Annunciator G-15, STEAM DUMP proper operation. IF S/G ARV ARMED LIT NOT controlling in AUTO. THEN control S/G ARV manually.

2) Go to Step lid.

b. Adjust condenser steam dump controller HC-484 to 1005 psig in AUTO

c. Place steam dump mode selector switch to MANUAL

d. Verify RCS Tavg - STABLE AT OR d. Adjust steam dump to restore TRENDING TO 547°F Tavg. IF steam dumps not available. THEN use ARVs.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check RCP Status - AT LEAST Perform the following:

ONE RUNNING

a. Establish conditions for starting an RCP:

"o Verify bus 11A or 1iB energized.

"o Refer to ATT-15.0, ATTACHMENT RCP START.

b. Start one RCP.

IF an RCP can NOT be started, THEN verify natural circulation (Refer to ATT-13.0, ATTACHMENT NC).

IF natural circulation NOT verified, THEN increase dumping steam.

STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

NOTE: Loss of forced air cooling may result in failure of NIS detectors.

13 Check If Source Range Detectors Should Be Energized:

a. Source range channels a. Go to Step 13e.

DEENERGIZED

b. Check intermediate range flux b. Perform the following:

EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing THEN initiate boration.

2) Continue with Step 14. WHEN flux is less than 10-10 amps on any operable channel, THEN do Steps 13c, d and e.

c. Check the following: c. Continue with Step 14. When either condition met, THEN do "o Both intermediate range Steps 13d and e.

channels LESS THAN 10 10 AMPS

-OR "o Greater than 20 minutes since reactor trip

d. Verify source range detectors d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can NOT be restored, THEN refer to ER-NIS.1, SR MALFUNCTION, and go to Step 14.

e. Transfer Rk-45 recorder to one source range and one "intermediate range channel

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Establish Normal Shutdown Alignment:

a. Check condenser AVAILABLE a. Dispatch AO to perform ATT-17.1, ATTACHMENT SD-2.

b. Perform the following:

"o Open generator disconnects

"* IG13A71

"*9X13A73 "o Place voltage regulator to OFF "o Open turbine drain valves "o Rotate reheater steam supply controller cam to close valves "o Place reheater dump valve switches to HAND "o Stop all but one condensate pump (Refer to T-5F, STARTING OR STOPPING THE CONDENSATE PUMPS)

c. Verify adequate Rx head cooling:

1) Verify at least one control 1) Manually start one fan as rod shroud fan RUNNING power supply permits (45 kw).

2) Verify one Rx compartment 2) Manually start one fan as cooling fan - RUNNING power supply permits (23 kw).

d. Dispatch AO to perform ATT-17.0, ATTACHMENT SD-1

SACTION/EXPECTED RESPONSE i RESPONSE NOT OBTAINED[

15 Maintain Stable Plant Conditions:

a. PRZR pressure - BETWEEN a. Control PRZR heaters and spray 1800 PSIG AND 2260 PSIG as necessary.

b. PRZR level BETWEEN 35% AND 40% b. Control charging as necessary.

c. SIG narrow range levels c. Control S/G feed flow as BETWEEN 17% AND 52% necessary.

d. RCS Tavg GREATER THAN 540'F d. Close both MSIVs.

16 Check VCT Makeup System:

a. Verify the following:

1) Adjust boric acid flow control valve to 9.5 gpm

2) Adjust RMY flow control valve to 40 gpm

3) RMW mode selector switch in AUTO

4) RMW control armed - RED LIGHT LIT

b. Check VCT level b. Manually increase VCT makeup flow as follows:

"o Level GREATER THAN 20%

1) Ensure BA transfer pumps and

-OR RMW pumps running.

"o Level STABLE OR INCREASING 2) Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check Charging Pump Suction Aligned To VCT:

a. VCT level GREATER THAN 20% a. IF VCT level can NOT be maintained greater than 5%, THEN perform the following:

1) Ensure charging pump suction aligned to RWST "o LCV-112B open "o LCV-112C closed

2) Continue with Step 18. WHEN VCT level greater than 40%,

THEN do Step 17b.

b. Align charging pumps to VCT o LCV-112C OPEN o LCV-112B - CLOSED

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify TDAFW Pump Aligned For AUTO Start:

a. Any MDAFW pump - AVAILABLE a. Verify TDAFW pump operating to maintain required SIC level and go to Step 20.

b. Verify AMSAC TRIPPED status b. Reset AMSAC.

light EXTINGUISHED

c. Verify both S/G levels GREATER c. Continue with Step 20. WHEN S/G THAN 17% level greater than 17%, THEN do Steps 18d, e and 19.

d. Verify Bus 11A and Bus 1lB AT d. Perform the following:

LEAST ONE ENERGIZED

1) IF TDAFW pump NOT required to maintain S/G level, THEN pull stop TDAFW pump steam supply valves:

o MOV-3504A

• MOV-3505A

2) Go to Step 19.

e. Verify the following:

1) TDAFW pump OFF 1) Perform the following:

a) IF TDAFW pump required to maintain S/G level. THEN go to Step 20.

b) Stop TDAFW pump.

2) TDAFW pump steam supply valve 2) Place TDAFW pump steam supply switches in AUTO valve switches in AUTO.

3) Verify TDAFW flow control 3) Open TDAFW flow control valves OPEN, DEMAND AT 0 valves.

"* AOV-4297

"* AOV-4298

EOP: TITLE:

REV: 20 ES-0.1 REACTOR TRIP RESPONSE PAGE 18 of 19 STEP ACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINED 19 Establish Normal AFW Pump Shutdown Alignment:

a. Verify the following: a. Continue with Step 20. WHEN conditions met, THEN do Steps "o Both S/G levels - GREATER 19b through f.

THAN 17% AND STABLE OR INCREASING "o Total AFW flow - LESS THAN 200 GPM

b. Close MDAFW pump discharge valves

"*MOV-4007

"*MOV-4008

c. Place AFW bypass switches to DEF

d. Stop all but one MDAFW pump

e. Open AFW discharge crossover valves

• MOV-4000A o MOV-4000B

f. Adjust AFW bypass valves to control S/G levels "aAOV-4480

"*AOV-4481

-TEP ACTION/EXPECTED RESPONSE NOT OBTAINEDI 20 Determine If Cooldown Is Required:

a. Consult Plant Staff - COOLDOWN a. Go to 0-3, HOT SHUTDOWN WITH REQUIRED XENON PRESENT.

b. At least one RCP RUNNING b. Perform the following:

1) Ensure 2 control rod shroud fans running.

2) Go to ES-0.2, NATURAL CIRCULATION COOLDOWN, Step 1.

c. Go to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN

- END

EOP: TITLE:

REV: 20 ES-0.1 REACTOR TRIP RESPONSE PAGE 1 of 1 ES-O.1 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG-1.0)

3) ATTACHMENT LETDOWN (ATT-9.0)

4) ATTACHMENT RCP START (ATT 15.0)

5) ATTACHMENT NC (ATT 13.0)

6) ATTACHMENT SD-I (ATT 17.0)

7) ATTACHMENT SD-2 (ATT -17. 1)

8) ATTACHMENT NO SW PUMPS (ATT -2.4)

9) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

10) FOLDOUT

RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%

b. CORE COOLING - Core exit T/Cs greater than 1200*F

-OR Core exit T/Cs greater than 7000F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 5%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F

e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE:

REV: 20 ES-0.1 REACTOR TRIP RESPONSE PAGE 1 of 1 FOLDOUT PAGE

1. SI ACTUATION CRITERIA IF ANY condition listed below occurs, THEN actuate SI and CI and go to E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1:

"o RCS subcooling based on core exit T/Cs - LESS THAN 0°F USING FIG-1.0, FIGURE MIN SUBCOOLING

- OR "o PRZR level - LESS THAN 5% [30% adverse CNMT]

AND RCS subcooling based on core exit T/Cs - LESS THAN 20 0 F USING FIG-1.0, FIGURE MIN SUBCOOLING

- OR "o Any automatic SI setpoint is reached

2. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RES PON s IB'L MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides the necessary instructions to terminate safety injection and stabilize plant conditions.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-0, REACTOR TRIP OR SAFETY INJECTION, and E-1, LOSS OF REACTOR OR SECONDARY COOLANT, when specified termination criteria are satisfied.

b. FR-H.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and SI has been terminated.

STEP, ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER)

NOTE: o FOLDOUT page should be open AND monitored periodically.

"o Critical Safety Function Status Trees should be monitored (Refer to Appendix I for Red Path Summary).

" Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

1 Reset SI 2 Reset CI:

a. Depress CI reset pushbutton

b. Verify annunciator A-26, CNMT b. Perform the following:

ISOLATION EXTINGUISHED

1) Reset SI.

2) Depress CI reset pushbutton.

3 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG "o Reset PRZR heaters "o Use normal PRZR spray

_TEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Verify Adequate SW Flow:

a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (257 kw each).

IF less than two SW pumps running, THEN perform the following:

1) Ensure SW isolation.

2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD 1).

3) IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

4) IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

5) Go to Step 7.

b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD 1)

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 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 e 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 if CNMT RECIRC fans should be stopped (Refer to Attachment CNMT RECIRC FANS).

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 adequate air c. Manually start air compressors compressor(s) - RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.

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

"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 6. WHEN IA restored, THEN do Steps 5e and f.

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

f. Verify IA to CNMT AOV-5392 OPEN

SACTION/EXPECTED RESPONSE 1 RESPONSE NOT OBTAINED[

6 Check If Charging Flow Has Been Established:

a. Charging pumps ANY RUNNING a. Perform the following:

1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s) to affected RCP:

"*RCP A. V-300A

"*RCP B, V-300B

2) Ensure HCV-142 open, demand at 0%.

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 dispatch AO to locally open o LCV 112C CLOSED manual charging pump suction from RWST (V-358 located in charging pump room).

IF LCV-112C can NOT be closed, THEN perform the following:

1) Verify charging pump A NOT running and place in PULL STOP.

2) 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

S ACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINEDI 7 Stop SI And RHR Pumps And Place In AUTO

• 8 Monitor SI Reinitiation Criteria:

a. RCS subcooling based on core a. Manually start SI pumps as exit T/Cs - GREATER THAN 0°F necessary and go to E-1, LOSS OF USING FIGURE MIN SUBCOOLING REACTOR OR SECONDARY COOLANT, Step 1.

b. PRZR level GREATER THAN 5% b. Control charging flow to

[30% adverse CNMT] maintain PRZR level.

IF PRZR level can NOT be maintained, THEN manually start SI pumps as necessary and go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

E STEP ACTION/EXPECTED RESPONSE[

1 RESPONSE NOT OBTAINED

• 9 Monitor If CNMT Spray Should Be Stopped:

a. CNMT spray pumps RUNNING a. Go to Step 10.

b. Check CNMT pressure - LESS THAN b. Continue with Step 10. WHEN 4 PSIG CNMT pressure less than 4 psig, THEN do Steps 9c through f.

c. Reset CNMT spray

d. Check NaOH tank outlet valves d. Place NaOH tank outlet valve CLOSED controllers to MANUAL and close valves.

• AOV-836A

• AOV-836B

e. Stop CNMT spray pumps and place in AUTO

f. Close CNMT spray pump discharge valves S MOV 860A S

MOV 860B S

MOV 860C S

MOV 860D

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

10 Verify MRPI Indicates - ALL IF one or more control rods NOT CONTROL AND SHUTDOWN RODS ON fully inserted, THEN perform the BOTTOM following:

a. Place RMW mode selector switch to BORATE.

b. Adjust boric acid flow control valve, FCV-110A, for desired flowrate.

c. Set boric acid integrator to desired amount (650 gallons for each control rod not fully inserted).

d. Place RMW control to start and verify flow. IF flow can NOT be established, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION.

11 Establish Condenser Steam Dump Pressure Control:

a. Verify condenser available: a. Place S/C ARV controllers in AUTO at desired pressure and go "o Any MSIV - OPEN to Step 12.

"o Annunciator C 15, STEAM DUMP ARMED LIT

b. Adjust condenser steam dump controller HC-484 to desired pressure and verify in AUTO.

c. Place steam dump mode selector switch to MANUAL.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

12 Verify Adequate SW Flow To CCW Hx:

a. Verify at least two SW pumps a. Manually start pumps as power RUNNING supply permits (257 kw each).

IF less than two SW pumps can be operated, THEN perform the following:

1) IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

2) IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

3) Go to Step 18.

b. Verify AUX BLDG SW isolation b. Manually align valves.

valves OPEN

• MOV-4615 and MOV-4734

• MOV-4616 and MOV-4735

c. Verify CNMT RECIRC fan c. Manually start an additional SW annunciator C-2, HIGH pump as power supply permits TEMPERATURE ALARM EXTINGUISHED (257 kw each).

'TEPACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

13 Check If Normal CVCS Operation Can Be Established

a. Verify IA restored: a. Continue with Step 18. WHEN IA can be restored,THEN do Steps o IA to CNMT (AOV-5392) OPEN 13 through 17.

o IA pressure GREATER THAN 60 PSIG

b. Verify instrument bus D b. Energize MCC B. IF MCC B NOT ENERGIZED available, THEN perform the following:

1) Verify MCC A energized.

2) Place instrument bus D on maintenance supply.

C. CCW pumps ANY RUNNING c. Perform the following:

1) IF any RCP #1 seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected RCP(s).

"*RCP A, MOV 749A and MOV 759A

"*RCP B, MOV-749B and MOV 759B

2) Manually start one CCW pump.

d. Charging pump ANY RUNNING d. Continue with Step 18. WHEN any charging pump running, THEN do Steps 14 through 17.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 14 Verify PRZR Level - GREATER Continue with Step 16. WHEN PRZR THAN 13% [40% adverse CNMT] level increases to greater than 13%

[40% adverse CNMT], THEN do Step 15.

15 Establish Normal Letdown: IF RCP seal return has been established, THEN establish excess

a. Establish charging line flow to letdown as follows:

REGEN Hx GREATER THAN 20 GPM "o Place excess letdown divert

b. Place the following switches to valve, AOV-312. to NORMAL.

CLOSE:

"o Ensure CCW from excess letdown

"*Letdown orifice valves open, (AOV-745).

(AOV-200A, AOV-200B, and AOV-202) "o Open excess letdown isolation

"*AOV 371, letdown isolation valve AOV-310.

valve

"*AOV-427, loop B cold leg to " Slowly open HCV-123 to maintain REGEN Hx excess letdown temperature less than 195°F and pressure less

c. Place letdown controllers in than 100 psig.

MANUAL at 40% open "o Adjust charging pump speed as

• TCV-130 necessary.

• PCV 135 IF RCP seal return NOT established.

d. Reset both trains of XY relays THEN consult Plant Staff to for AOV 371 and AOV-427 determine if excess letdown should be placed in service.

e. Open AOV 371 and AOV 427

f. Open letdown orifice valves as necessary

g. Place TCV-130 in AUTO at 105'F

h. Place PCV-135 in AUTO at 250 psig

i. Adjust charging pump speed and HCV-142 as necessary to control PRZR level

STEP ACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINEDI 16 Check VCT Makeup System:

a. Adjust boric acid flow control valve in AUTO to 9.5 gpm

b. Adjust RMW flow control valve in AUTO to 40 gpm

c. Verify the following: c. Adjust controls as necessary.

1) RMW mode selector switch in AUTO

2) RMW control armed - RED LIGHT LIT

d. Check VCT level: d. Manually increase VCT makeup flow as follows:

o Level GREATER THAN 20%

1) Ensure BA transfer pumps and

-OR- RMW pumps running. IF NOT.

THEN dispatch AO to locally o Level STABLE OR INCREASING reset MCC C and MCC D UV lockouts as necessary.

2) Place RMW flow control valve HCV 111 in MANUAL and increase RMW flow.

3) Increase boric acid flow as necessary.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINE 17 Check Charging Pump Suction Aligned To VCT:

a. VCT level GREATER THAN 20% a. IF VCT level can NOT be maintained greater than 5%, THEN perform the following:

1) Ensure charging pump suction aligned to RWST "o LCV-112B open "o LCV-112C closed

2) Continue with Step 18. WHEN VCT level greater than 40%.

THEN do Step 11b.

b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.

"o LCV-112C OPEN "o LCV-112B CLOSED 18 Check RCS Hot Leg Control steam dump and total feed Temperatures - STABLE flow as necessary to stabilize RCS temperature.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDF NOTE: o WHEN using a PRZR PORV, THEN select one with an operable block valve.

o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

19 Control PRZR Heaters And IF normal spray NOT available and Operate Normal Spray To letdown is in service, THEN perform Stabilize RCS Pressure the following:

a. Verify Regen Hx Chg outlet temp to PRZR Vapor temp AT less than 320'F. IF NOT, THEN control pressure using one PRZR PORV and go to Step 20.

b. Control pressure using auxiliary spray.

IF auxiliary spray NOT available, THEN use one PRZR PORV.

NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

• 20 Monitor Intact S/G Levels:

a. Narrow range level GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] 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, THEN stop

[25% adverse CNMT] and 50% feed flow to that S/G.

dTpH ACTION/EXPECTED `1POSE

.... RESPONSE NOT 1I. OBTAINED NOTE: SW should be aligned to CCW Hxs before restoring RCP seal cooling.

21 Check RCP Cooling: Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).

a. Check CCW to RCPs:

"o Annunciator A-7. RCP IA CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED "o Annunciator A-15, RCP lB CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED

b. Check RCP seal injection:

o Labyrinth seal D/Ps - GREATER THAN 15 INCHES WATER

-OR-o RCP seal injection flow to each RCP GREATER THAN 6 GPM

STEP ACTION/EXPECTED RESPONSE' s RESPONSE NOT OBTAINEDK 22 Check If Seal Return Flow Should Be Established:

a. Verify RCP #1 seal outlet a. Go to Step 23.

temperature LESS THAN 235°F

b. Verify RCP seal outlet valves b. Manually open valves as OPEN necessary.

• AOV-270A

• AOV 270B

c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313

d. Open RCP seal return isolation d. Perform the following:

valve MOV-313

1) Place MOV-313 switch to OPEN.

2) Dispatch AO with key to RWST gate to locally open MOV 313.

e. Verify RCP #1 seal leakoff flow e. Perform the following:

LESS THAN 6.0 GPM

1) Trip the affected RCP

2) Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve.

"* RCP A, AOV-270A

"* RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 23.

f. Verify RCP #1 seal leakoff flow f. Refer to AP-RCP.1, RCP SEAL GREATER THAN 0.8 GPM MALFUNCTION.

STE ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 23 Verify All AC Busses Perform the following:

ENERGIZED BY OFFSITE POWER

a. IF any AC emergency bus normal o Normal feed breakers to all 480 feed breaker open, THEN ensure volt busses CLOSED associated D/G breaker closed.

o 480 volt bus voltage - GREATER b. Perform the following as THAN 420 VOLTS necessary:

o Emergency D/G output breakers 1) Close non-safeguards bus tie OPEN breakers:

"*Bus 13 to Bus 14 tie

"*Bus 15 to Bus 16 tie

2) Reset Bus 13 and Bus 15 lighting breakers.

3) Dispatch AO to locally reset and start two IA compressors.

4) Place the following pumps in PULL STOP:

"*EH pumps

"*Turning gear oil pump

"*HP seal oil backup pump

5) Restore power to MCCs.

• A from Bus 13 o B from Bus 15 e E from Bus 15 o F from Bus 15

6) Start HP seal oil backup pump.

7) Start CNMT RECIRC fans as necessary.

8) Ensure D/G load within limits.

9) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.

c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED7 NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

24 Check If Source Range Channels Should Be Energized:

a. Source range channels a. Go to Step 24e.

DEENERGIZED

b. Check intermediate range flux b. Perform the following:

EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing, THEN initiate boration.

2) Continue with Step 25. WHEN flux is LESS THAN 10-10 amps on any operable channel, THEN do Steps 24c, d and e.

c. Check the following: c. Continue with step 25. WHEN either condition met, THEN do "o Both intermediate range Steps 24d and e.

channels LESS THAN 10 10 AMPS

-OR "o Greater than 20 minutes since reactor trip

d. Verify source range detectors d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can NOT be restored, THEN refer to ER-NIS.l, SR MALFUNCTION, and go to Step 25.

e. Transfer Rk-45 recorder to one "source range and one intermediate range channel

TE H CTON /EXPECTED fl RESPNE J RESPONSE NOT OBTAINEI 25 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.l, RESTORATION OF 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

b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)

• • • ACTIO* EXPECTED O*

• RE SPOS E NOT O TAIN' '

CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

26 Check RCP Status - AT LEAST Perform the following:

ONE RUNNING

a. IF RVLIS level (no RCPs) less than 95%, THEN perform the following:

o Increase PRZR level to greater than 65% (82% adverse CNMT).

o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20'F using Figure MIN SUBCOOLING.

o Energize PRZR heaters as necessary to saturate PRZR water.

b. Establish conditions for starting an RCP:

"o Verify bus IIA or liB energized.

"o Refer to Attachment RCP START.

c. Start one RCP.

IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).

IF natural circulation NOT verified, THEN increase dumping steam from intact S/Gs.

ST*E ACTION/EXPECTED RESPoNSE RESPONSE NOT OBTAINED 27 Establish Normal Shutdown Alignment:

a. Check condenser AVAILABLE a. Dispatch AO to perform Attachment SD-2.

b. Perform the following:

"o Open generator disconnects o 1G13A71 o 9X13A73 "o Place voltage regulator to OFF "o Open turbine drain valves "o Rotate reheater steam supply controller cam to close valves "o Place reheater dump valve switches to HAND "o Stop all but one condensate pump

c. Verify adequate Rx head cooling:

1) Verify at least one control 1) Manually start one fan as rod shroud fan RUNNING power supply permits (45 kw)

2) Verify one Rx compartment 2) Perform the following:

cooling fan RUNNING "o Dispatch AO to reset UV relays at MCC C and MCC D.

"o Manually start one fan as power supply permits (23 kw)

d. Verify Attachment SD-1 COMPLETE

STEP ACTION/EXPECTED RESPONSE [ FRESPONSE NOT OBTAINED 28 Maintain Plant Conditions Stable:

a. RCS pressure BETWEEN 1800 PSIG a. Control PRZR heaters and spray AND 2235 PSIG as necessary.

b. PRZR level - BETWEEN 35% AND 40% b. Control charging as necessary.

c. Intact S/G narrow range levels c. Control S/G feed flow as BETWEEN 17% AND 52% necessary.

d. RCS cold leg temperature STA BLE d. Control dumping steam as necessary. IF cooldown continues, THEN close both MSIVs.

• 29 Monitor SI Reinitiation Criteria:

a. RCS subcooling based on core a. Manually start SI pumps as exit T/Cs GREATER THAN 0°F necessary and go to E-1, LOSS OF USING FIGURE MIN SUBCOOLING REACTOR OR SECONDARY COOLANT, Step 1.

b. PRZR level GREATER THAN 5% b. Control charging flow to

[30% adverse CNMT] maintain PRZR level.

IF PRZR level can NOT be maintained, THEN manually start SI pumps as necessary and go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Implement Plant Recovery Procedures:

a. Review plant systems for realignment to normal conditions (Refer to ATT-26.0, ATTACHMENT RETURN TO NORMAL OPERATIONS)

b. Go to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN END-

ES-1-1 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG-1.0)

3) ATTACHMENT CNMT RECIRC FANS (ATT 4.0)

4) ATTACHMENT D/G STOP (ATT-8. 1)

5) ATTACHMENT NC (ATT- 13.0)

6) ATTACHMENT SEAL COOLING (ATT- 15.2)

7) ATTACHMENT RCP START (ATT- 15.0)

8) ATTACHMENT SD-1 (ATT- 17.0)

9) ATTACHMENT SD-2 (ATT- 17.1)

10) ATTACHMENT SI/UV (ATT -8.4)

11) ATTACHMENT NO SW PUMPS (ATT-2.4)

12) ATTACHMENT RETURN TO NORMAL OPERATIONS (ATT -26.0)

13) ATTACHMENT LOSS OF OFFSITE POWER (ATT -8.5)

14) FOLDOUT

LOP: TITLE:

REV: 22 ES-I.1 SI TERMINATION PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%

b. CORE COOLING - Core exit T/Cs greater than 1200'F

-OR Core exit T/Cs greater than 7000F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 5%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F

e. CONTAINMENT - CNMT pressure greater than 60 psig

FOLDOUT PAGE

1. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start SI pumps as necessary and go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:

"o RCS subcooling based on core exit T/Cs - LESS THAN 0 0 F USING FIGURE MIN SUBCOOLING

- OR "o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%

[30% adverse CNMT]

2. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.

3. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.I, ALTERNATE WATER SUPPLY TO AFW PUMPS).

EoP: TITLE: REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 26 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSI6 MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

FOP: TITLE: REV: 24 ES-I.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 2 of 26 A. PURPOSE - This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions following a loss of reactor coolant inventory.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

E-1, LOSS OF REACTOR OR SECONDARY COOLANT, when RCS pressure is greater than the shutoff head pressure of the RHR pumps.

EOP: TITLE:

REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 3 of 26 SE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI

• v * * * * * * * * . .

CAUTI ON o IF RWST LEVEL DECREASES TO LESS THAN 28%, THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, STEP 1.

"o IF PRZR LEVEL IS LESS THAN 50% OR IF ADVERSE CNMT CONDITIONS EXIST, THEN PRZR HEATERS SHOULD NOT BE ENERGIZED UNTIL PRZR LEVEL IS EVALUATED BY THE TSC.

"o RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

NOTE: 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+05 R/hr.

• 1 Monitor If RHR Pumps Should Be Stopped:

a. Check RCS pressure: a. Go to Step 2.

1) Pressure GREATER THAN 250 psig [465 psig adverse CNMT]

2) Pressure STABLE OR INCREASING

b. Stop RHR pumps and place AUTO

T ACTION/ EXPECTED RESPONSEI I RESPONSE NOT OBTAINEDI

• 2 Monitor All AC Busses Perform the following:

BUSSES ENERGIZED BY OFFSITE POWER a. IF any AC emergency bus normal feed breaker open. THEN ensure o Normal feed breakers to all 480 associated D/G breaker closed.

volt busses CLOSED

b. Perform the following, as o 480 bus voltage GREATER THAN necessary:

420 VOLTS

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

OPEN

"* 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) Restore power to MCCs.

"*A from Bus 13

"*B from Bus 15

"*E from Bus 15

"*F from Bus 15

4) Start HP seal oil backup pump.

5) Ensure D/G load within limits.

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

7) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.

c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

EOP: TITLE:RE  : 2 ES-I.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 5 of 26 STEP -ACTION/EXPECTED 1 RESPONSE] RESPONSE NOT OBTAINED 3 Establish 75 GPM Charging Flow:

a. Charging pumps ANY RUNNING a. Perform the following:

1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high, THEN dispatch AO with RWST area key to locally isolate seal injection to affected RCP:

o V-300A for RCP A o V-300B for RCP B

2) Ensure HCV-142 open, demand at 0%.

b. Align charging pump suction to b. IF LCV-112B can NOT be opened, RWST: THEN dispatch AO to locally open manual charging pump suction "o LCV 112B OPEN from RWST (V-358 located in charging pump room).

"o LCV-112C CLOSED IF LCV-112C can NOT be closed, THEN perform the following:

1) Verify charging pump A NOT running and place in PULL STOP.

2) 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 (75 kw each) and establish 75 gpm total charging flow

• Charging line flow

• Seal injection flow

EOP: TITLE: REV: 24 ES-l.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 6 of 26 STP ACTION/EXPECTED RESP SEI RESPONSE NOT OBTAINEDI 4 Establish Condenser Steam Dump Pressure Control:

a. Verify condenser available: a. Place S/G ARV controllers in AUTO at desired pressure and go o Any MSIV OPEN to Step 5.

o Annunciator G-15, STEAM DUMP ARMED LIT

b. Adjust condenser steam dump controller HC-484 to desired pressure and verify in AUTO

c. Place steam dump mode selector switch to MANUAL NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

• 5 Monitor Intact S/G Levels:

a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in at least one SIG.

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

[25% adverse CNMT] and 50% uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

[OP : TITLE: REV: 24 ES-I.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 7 of 26 SACTON/XPETEDRESONSI IRESPOýNSE NýOTOBýTAINEýD NOTE: Shutdown margin should be monitored during RCS cooldown (Refer to Figure SDM).

6 Initiate RCS Cooldown To Cold Shutdown:

a. Establish and maintain cooldown rate in RCS cold legs LESS THAN 1OOOF/HR

b. Use RHR system if in service

c. Dump steam to condenser from c. Manually or locally dump steam intact S/G(s) using intact S/Cs ARV.

7 Check RCS Subcooling Based On Manually start SI pumps as Core Exit T/Cs - GREATER THAN necessary and go to Step 19.

0°F USING FIGURE MIN SUBCOOLING 8 Check SI and RHR Pump Status: Go to Step 15.

"o SI pumps ANY RUNNING

-OR "o RHR pumps ANY RUNNING IN INJECTION MODE 9 Place PRZR Heater Switches In The Following Positions:

"o PRZR heater control group PULL STOP "o PRZR heater backup group OFF

[OP: TITLE: REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 8 of 26 SACTION/EXPECTED RESPN RESPONSE NTOBTAIN11i)

. . *t *.. * * * * * * * * * *v * * * * * * * * * * * * * * * **

CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

NOTE: o WHEN using a PRZR PORV, THEN select one with an operable block valve.

o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

10 Depressurize RCS To Refill PRZR:

a. Depressurize using normal PRZR a. Depressurize using one PRZR spray if available PORV. IF IA NOT available, THEN refer to Attachment N2 PORVS.

IF no PORV available, THEN use auxiliary spray valve (AOV-296).

b. PRZR level GREATER THAN 13% b. Continue with Step 11. WHEN

[40% adverse CNMT] level greater than 13% [40%

adverse CNMT], THEN stop RCS depressurization.

c. Stop RCS depressurization

EOP: TITLE: REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 9 of 26

• A *

• O 0EXPECTED RE' O'

• I RESPONSE NOT

• O AI** *I*

CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST. THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

11 Check If An RCP Should Be Started:

a. Both RCPs STOPPED a. Stop all but one RCP and go to Step 12.

b. RCS subcooling based on core b. Go to Step 19.

exit T/Cs - GREATER THAN 0°F USING FIGURE MIN SUBCOOLING

c. PRZR level - GREATER THAN 13% c. Return to Step 10.

[40% adverse CNMT]

d. Try to start an RCP d. Ensure at least one control rod shroud fan running (45 kw each).

1) Establish conditions for starting an RCP "o Bus 11A or liB energized "o Refer to Attachment RCP START

2) Start one RCP

SEOP. TITLE: REV 2 I ES-1.2 I

POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 24 PAGE 10 of 26 SACTON/XPETEDRESONSI IRESPOýNSE NýOT OBTAINEýD 12 Check If One Of Three SI Pumps Should Be Stopped:

a. Three SI pumps - RUNNING a. Go to Step 13.

b. RCS subcooling based on core b. IF RCS hot leg temperatures exit T/Cs GREATER THAN 35°F greater than 320'F [310'F

[90°F adverse CNMT] USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING cooling in service, THEN go to Step 19.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 3200F

[310'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 12c. IF no RHR pump can be started in injection mode, THEN go to Step 19.

c. Check PRZR level GREATER THAN c. Do NOT stop SI pump. Return to 13% [40% adverse CNMT] Step 10.

d. Stop one SI pump

-- CTIO/EXECTE

• REPONSI IRESPOýNSE NýOTOBýTAINEýD 13 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps - RUNNING a. Go to Step 14.

b. Determine required RCS subcooling from table:

Charging Pump RCS Subcooling Criteria Availability NONE 120°F [200°F adverse CNMT]

ONE 115°F [190°F adverse CNMT]

TWO 105 0 F [180°F adverse CNMT]

THREE 1001F [175°F adverse CNMT]

c. RCS subcooling based on core c. IF RCS hot leg temperatures exit T/Cs - GREATER THAN VALUE greater than 320'F [310°F FROM TABLE ABOVE USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING cooling in service, THEN go to Step 19.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 320 0 F

[310'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 13d. IF no RHR pump can be started in injection mode, THEN go to Step 19.

d. PRZR level GREATER THAN 13% d. Do NOT stop SI pump. Return to

[40% adverse CNMT] Step 10.

e. Stop one SI pump

--ACTON/XPETEDRESONS[

• [RESPOýNSE NýOT OBTAINEýD[

14 Check If Last SI Pump Should Be Stopped:

a. One SI pump RUNNING a. IF any RHR pump running in injection mode, THEN go to Step 19. IF NOT. THEN go to Step 15.

b. Determine required RCS subcooling from table:

Charging Pump RCS Subcooling Criteria Availability NONE Insufficient subcooling to stop SI pump.

ONE 255 0 F [295°F adverse CNMT]

TWO 235'F [285°F adverse CNMT]

THREE 2101F [270'F adverse CNMT]

c. RCS subcooling based on core c. IF RCS hot leg temperatures exit T/Cs GREATER THAN VALUE greater than 320°F [310°F FROM TABLE ABOVE USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING cooling in service, THEN go to Step 19.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 320'F

[310'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 14d. IF no RHR pump can be started in injection mode, THEN go to Step 19.

d. PRZR level GREATER THAN 13% d. Do NOT stop SI pump. Return to

[40% adverse CNMT] Step 10.

e. Stop running SI pump

EOP : TITLE: REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 13 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED!

15 Check If Charging Flow Should Be Controlled To Maintain PRZR Level:

a. Check RHR pumps RUNNING IN a. Start charging pump and control INJECTION MODE charging flow to maintain PRZR level and go to Step 16.

b. Go to Step 19

EOP: TITLE: REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 14 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

16 Check RCP Status:

a. RCPs AT LEAST ONE RUNNING a. Perform the following:

1) Try to start one RCP:

a) IF RVLIS level (no RCPs) less than 95%, THEN perform the following:

"o Increase PRZR level to greater than 65% [82%

adverse CNMT].

" Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20°F using Figure MIN SUBCOOLING.

"o Energize PRZR heaters as necessary to saturate PRZR water.

b) Establish conditions for starting an RCP:

"o Verify Bus 11A ro 1IB energized.

"o Refer to Attachment RCP START.

c) Start one RCP.

2) IF an RCP can NOT be started.

THEN verify natural circulation (Refer to Attachment NC).

IF natural circulation can NOT be verified. THEN increase dumping steam.

b. Stop all but one RCP

EOP: TITLE: REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 15 of 26

• • • *** ***ON/EX*PE*CTED** REPOSE*REPOS NOT***BTA ***ED**

CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

NOTE: o WHEN using a PRZR PORV, THEN select one with an operable block valve.

0 If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

17 Depressurize RCS To Minimize RCS Subcooling:

a. Depressurize using normal PRZR a. IF normal spray NOT available.

spray if available THEN use one PRZR PORV. IF IA NOT available, THEN refer to Attachment N2 PORVS.

IF no PRZR PORV available, THEN use auxiliary spray valve (AOV-296).

b. Energize PRZR heaters as necessary

c. Depressurize RCS until EITHER of the following conditions satisfied:

"o RCS subcooling based on core exit T/Cs LESS THAN 10°F USING FIGURE MIN SUBCOOLING

-OR "o PRZR level GREATER THAN 75%

[65% adverse CNMT]

EOP: TITLE: REV: 24 ES-I.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 16 of 26 STEP -ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify Adequate Shutdown Margin

a. Direct RP to sample RCS for boron concentration

b. Verify boron concentration b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM

"*19 Monitor SI Reinitiation Criteria:

a. RCS subcooling based on core a. Manually start SI pumps as exit T/Cs GREATER THAN 0°F necessary and go to Step 20.

USING FIGURE MIN SUBCOOLING GREATER THAN 5% b. Manually start SI pumps as

b. PRZR level necessary and return to Step 10.

[30% adverse CNMT]

EOP: TITLE: REV: 24 ES-I.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 17 of 26

• CTIN/EPECED STPH ESPNSE[ IRESPOýNSE NýOT OBTAINEýD[

20 Check If SI ACCUMs Should Be Isolated:

a. RCS subcooling based on core a. IF both RCS hot leg temperatures exit T/Cs - GREATER THAN 0°F less than 400'F, THEN go to USING FIGURE MIN SUBCOOLING Step 20c.

IF NOT, THEN go to Step 21.

b. PRZR level GREATER THAN 5% b. Return to Step D0.

[30% adverse CNMT]

c. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves

"*MOV-841, MCC C position 12F

"* MOV-865, MCC D position 12C

d. Close SI ACCUM discharge valves d. Vent any unisolated ACCUMs:

• ACCUM A, MOV-841 1) Open vent valves for

• ACCUM B, MOV-865 unisolated SI ACCUMs.

o ACCUM A. AOV 834A e ACCUM B, AOV-834B

2) Open HCV 945.

e. Locally reopen breakers for MOV 841 and MOV-865

EOP: TITLE: REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 18 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.I. RESTORATION OF 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

b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)

FOP: TITLE: REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 19 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Verify Adequate SW Flow To CCW Hx:

a. Verify at least two SW pumps a. Manually start pumps as power RUNNING supply permits (257 kw per pump). IF less than two SW pumps can be operated. THEN perform the following:

1) IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

2) IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

3) Go to Step 23.

b. Verify AUX BLDG SW isolation b. Manually align valves.

valves OPEN

• MOV 4615 and MOV-4734 MOV-4616 and MOV 4735 This Step continued on the next page.

EOP: TITLE: REV: 24 ES-I.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 20 of 26 (STEP 2O/EXPECTED RESPONSE NOT OBTAINE (Step 22 continued from previous page)

c. Verify CNMT RECIRC fan c. Perform the following:

annunciator C-2, HIGH TEMPERATURE ALARM - EXTINGUISHED 1) Determine required SW flow to CCW HXs per table:

SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2 Total of 5000 6000 gpm equally divided to both HXs Normal 1 5000 6000 gpm to in-service HX Alternate 2 30-33" d/p across each HX Alternate 1 95-100" d/p across in-service HX

2) Direct AO to adjust SW flow to required value.

"o IF on normal SW discharge:

0 V-4619, CCW Hx A e V-4620. CCW Hx B

-OR "o IF on alternate SW discharge:

e V-4619C, CCW Hx A e V-4620B, CCW Hx B

EOP: TITLE: REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 21 of 26 I

rRESPONSE NOT O BTAI NE OBTAINED STEP ACTION/EXPECTED RESPONSE 1 NOT 23 Check RCP Cooling Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).

a. Check CCW to RCPs "o Annunciator A-7, RCP 1A CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED "o Annunciator A-15, RCP lB CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED

b. Check RCP seal injection "o Labyrinth seal D/Ps GREATER THAN 15 INCHES WATER

-OR "o RCP seal injection flow to each RCP - GREATER THAN 6 GPM

EOP: TITLE: REV: 24 ES-I.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 22 of 26

-- CTIN/EXECTD

• REPONEI RESPOýNSE NýOTOBýTAINEýD 24 Check If Seal Return Flow Should Be Established:

a. Verify instrument bus D a. Restore power to instrument bus ENERGIZED D from MCC B or MCC A (maintenance supply).

b. Verify RCP #1 seal outlet b. Go to Step 25.

temperature - LESS THAN 235°F

c. Verify RCP seal outlet valves c. Manually open valves as OPEN necessary.

"*AOV-270A

"*AOV-270B

d. Reset both trains of XY relays for RCP seal return isolation valve MOV-313

e. Open RCP seal return isolation e. Perform the following:

valve MOV-313

1) Place MOV-313 switch to OPEN.

2) Dispatch AO with key to RWST gate to locally open MOV-313.

f. Verify RCP #1 seal leakoff flow f. Perform the following:

LESS THAN 6.0 GPM

1) Trip the affected RCP

2) Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve

"* RCP A, AOV-270A

"* RCP B, AOV-270B IF both RCP seal discharge valves are shut. THEN go to Step 25.

g. Refer to AP-RCP.1. RCP SEAL

g. Verify RCP #1 seal leakoff flow GREATER THAN 0.8 GPM MALFUNCTION.

LOP: ITILE: REV: 24 ES-I.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 23 of 26 STEP ACTION/EXPECTED RESPONSEI i RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

25 Check If Source Range Detectors Should Be Energized:

a. Source range channels a. Go to Step 25e.

DEENERGIZED

b. Perform the following:

b. Check intermediate range flux EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing, THEN initiate boration.

2) Continue with Step 26. WHEN flux is LESS THAN 10-10 amps on any operable channel, THEN do Steps 25c, d and e.

c. Continue with Step 26. WHEN

c. Check the following:

either condition met, THEN do Steps 25d and e.

o Both intermediate range channels LESS THAN 10-10 AMPS

-OR o Greater than 20 minutes since reactor trip

d. Verify source range detectors d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can NOT be restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 25.

e. Transfer Rk-45 recorder to one source range and one intermediate range channel

STEP ACTION/EXPECTED RESPONSE[3 RESPONSE NOT OBTAINED 26 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.

b. Perform the following:

"o Open generator disconnects

"* 1G13A71

"*9X13A73 "o Place voltage regulator to OFF "o Open turbine drain valves "o Rotate reheater steam supply controller cam to close valves "o Place reheater dump valve switches to HAND "o Stop all but one condensate pump

c. Verify adequate Rx head cooling:

1) Verify at least one control 1) Manually start one fan as rod shroud fan RUNNING power supply permits (45 kw)

2) Verify one Rx compartment 2) Perform the following:

cooling fan - RUNNING "o Dispatch AO to reset UV relays at MCC C and MCC D.

"o Manually start one fan as power supply permits (23 kw)

d. Verify Attachment SD-1 COMPLETE

• 27 Mon tOr RCP OperOatiIon

• 27 Monitor RCP Operation:

a. RCPs ANY RUNNING a. Go to Step 28.

b. Stop affected RCP(s).

b. Check the following:

"o RCP #1 seal DIP - GREATER THAN 220 PSID "o RCP #1 seal leakoff - WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF Use intact S/G ARV for RCS 28 Check Condenser Steam Dump temperature control.

Available - CONDENSER VACUUM GREATER THAN 20 INCHES HG 29 Check If RHR Normal Cooling Can Be Established:

a. RCS cold leg temperature LESS a. Go to Step 30.

THAN 350°F

b. RCS pressure LESS THAN b. Go to Step 30.

400 psig [300 psig adverse CNMT]

c. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)

d. Consult TSC to determine if RHR normal cooling should be established using Attachment RHR COOL

SSTEP H ACTION/EXPECTED RESPONSEI IRESPONSE NOT OBTAINED NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 30.

30 Check CNMT Hydrogen Concentration:

a. Direct RP to start CNMT hydrogen monitors as necessary LESS b. Consult TSC to determine if

b. Hydrogen concentration should be hydrogen recombiners THAN 0.5%

placed in service.

Return to Step 1.

31 Check Core Exit T/Cs - LESS THAN 2000 F 32 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions

b. Consult TSC END

ES-1.2 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG- 1.0)

3) FIGURE SDM (FIG 2.0)

4) FIGURE RCP SEAL LEAKOFF (FIG -4.0)

5) ATTACHMENT SEAL COOLING (ATT 15.2)

6) ATTACHMENT RCP START (ATT 15.0)

7) ATTACHMENT NC (ATT 13.0)

8) ATTACHMENT D/G STOP (ATT 8.1)

9) ATTACHMENT SD-I (ATT 17.0)

10) ATTACHMENT SD-2 (ATT 17.1)

11) ATTACHMENT SI/UV (ATT 8.4)

12) ATTACHMENT N2 PORVS (ATT 12.0)

13) ATTACHMENT RHR COOL (ATT- 14. 1)

14) ATTACHMENT NO SW PUMPS (ATT 2.4)

15) FOLDOUT

EOP: TITLE: REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%

b. CORE COOLING - Core exit T/Cs greater than 1200'F

-OR Core exit T/Cs greater than 7000F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 5%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F

e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE:

REV: 24 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 1 FOLDOUT PAGE

1. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start SI pumps as necessary:

o RCS subcooling based on core exit T/Cs - LESS THAN 0°F USING FIGURE MIN SUBCOOLING

- OR o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%

[30% adverse CNMT]

2. SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, SI TERMINATION, Step 1:

a. RCS subcooling based on core exit T/Cs - GREATER THAN 0 0 F USING FIGURE MIN SUBCOOLING

b. Total feed flow to intact S/Gs - GREATER THAN 200 GPM

- OR Narrow range level in at least one intact S/G - GREATER THAN 5% [25% adverse CNMT]

c. RCS pressure:

o GREATER THAN 1625 PSIG [1825 psig adverse CNMT]

o STABLE OR INCREASING

d. PRZR level - GREATER THAN 5% [30% adverse CNMT]

3. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.

4. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-I.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

5. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.I, ALTERNATE WATER SUPPLY TO AFW PUMPS).

6. E-3 TRANSITION CRITERIA IF any S/G level increases in an uncontrolled manner or any S/G has abnormal radiation, THEN manually start SI Pumps as necessary AND go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.