ML022130205

R. E. Ginna Nuclear Power Plant - Emergency Operating Procedures, Revision 33 to ES-1.3, Transfer to Cold Leg Recirculation - FR-S.1, Revision 14, Response to Reactor Restart/Atws

ML022130205
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
ES-1.3, Rev 33
Download: ML022130205 (145)

Text

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 3 RESPONSIBLE týNAGER

? - C-9,&()

EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides the necessary instructions for transferring the Safety Injection system and Containment Spray system to recirculation modes of operation.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure may be entered from:

a. E-1, LOSS OF REACTOR OR SECONDARY COOLANT, or,

b. ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, or,

c. ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, or,

d. FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, or,

e. FR-C.2, RESPONSE TO DEGRADED CORE COOLING, or,

f. FR-C.3, RESPONSE TO SATURATED CORE COOLING, or,

g. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, or,

h. FR-Z.1, RESPONSE TO HIGH CONTAINMENT PRESSURE, on low RWST level.

i. Other procedures whenever RWST level reaches the switchover setpoint (28%).

EOP: TITLE: REV: 33 ES-I.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 3 of 22

...... AI.... *....

X R*N ....O

• OO*AI ********

CAUTION 0 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 CONSULT WITH RADIATION PROTECTION BEFORE DISPATCHING PERSONNEL TO AUXILIARY BUILDING. SWITCHOVER TO RECIRCULATION MAY CAUSE HIGH RADIATION LEVELS.

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 Verify RWST level - GREATER IF sump recirculation NOT in THAN 15% progress, THEN pull-stop all pumps taking suction from RWST, EXCEPT one SI pump AND go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.

2 Verify CNMT Sump B Level - AT IF RWST level is less than 28% AND LEAST 113 INCHES CNMT sump B level is less than 113 inches, THEN go to ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.

NOTE: Steps 3 through 13 should be performed without delay. FR procedures should not be implemented prior to completion of these steps.

3 Reset SI

NOTE: IF D/Gs supplying emergency AC busses, THEN non-essential loads may be shed as necessary to allow start of additional SW pumps.

4 Establish Adequate SW Flow:

a. Verify at least two SW pumps a. Start additional SW pumps as RUNNING power supply permits (257 kw each). IF only 1 SW pump operable, THEN perform the following:

1) Ensure SW aligned to one CCW Hx per Attachment MIN SW.

2) Go to Step 5.

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

valves OPEN o MOV-4615 and MOV-4734

• MOV-4616 and MOV-4735

c. Dispatch AO to Check BOTH CCW c. Locally place BOTH CCW Hxs in Hxs IN SERVICE service

d. 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 This Step continued on the next page.

(Step 4 continued from previous page)

e. Direct AO to adjust SW flow to e. IF the required SW flow can NOT required value be obtained, THEN perform the following:

"o IF on normal SW discharge:

1) Isolate SW to screenhouse and

"* V-4619, CCW HX A air conditioning headers.

"* V-4620, CCW HX B

"* MOV-4609/MOV-4780 AT

-OR LEAST ONE CLOSED

"* MOV-4663/MOV-4733 AT "o IF on alternate SW discharge: LEAST ONE CLOSED

"* V-4619C. CCW HX A 2) Direct AO to locally adjust

"* V-4620B, CCW HX B SW flow to required value.

3) Direct AO to locally isolate SW return from SFP Hxs:

"* SFP Hx A (V-4622) (for alternate SW discharge use V-4622A)

"* SFP Hx B (V-8689)

4) Verify SW portions of Attachment SD-1 are complete.

EOP: TITLE: REV: 33 ES-I.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 6 of 22 E A CCW TD RE ERESPONSE NOTsOBTAINE:D 5 Establish CCW flow to RHR Hxs:

a. Check both CCW pumps - RUNNING a. Perform the following:

1) Start CCW pumps as power supply permits (122 kw each).

2) IF both CCW pumps are running, THEN go to step 5b.

3) IF only one CCW pump is running, THEN perform the following:

a) Direct AO to isolate CCW to boric acid evaporator o Close V-760A b) Manually open CCW MOV to only one operable RHR loop.

o Open MOV-738A

-OR o Open MOV-738B c) Go to step 6.

b. Open CCW valves to RHR Hxs b. Dispatch AO to locally open valves.

• MOV-738A e MOV-738B

EEOP: TITLE: REV: 33 I ES-1.3 TRANSFER TO COLD LEG RECIRCULATION R SPAGE 7 of 22

. . . . * . . . * * *.* .**. * *. .I*. . 0*AI.**I CAUTION o THE RHR HX OUTLET VALVES (HCV-624 AND HCV-625) WILL FAIL OPEN ON LOSS OF INSTRUMENT AIR PRESSURE.

o CONSULT WITH RADIATION PROTECTION BEFORE DISPATCHING PERSONNEL TO AUXILIARY BUILDING. SWITCHOVER TO RECIRCULATION MAY CAUSE HIGH RADIATION LEVELS.

6 Check RHR Flow: Manually adjust RHR Hx outlet valves equally to reduce flow to o RHR flow - LESS THAN 1500 GPM less than 1500 gpm per operating PER OPERATING PUMP pump

• RHR Hx A, HCV-625

• RHR Hx B, HCV-624 IF flow can NOT be reduced manually, THEN dispatch an AO with locked valve key to locally adjust RHR Hx outlet valve handwheels equally to reduce flow.

"* RHR Hx A, HCV-625 handwheel

"* RHR Hx B, HCV-624 handwheel

EOP: TITLE:

REV: 33 ES-I.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 8 of 22 7 Check IF Unnecessary Pumps Can Be Stopped:

a. Three SI pumps - RUNNING a. Go to Step 7c.

b. Stop SI pump C and place both switches in PULL STOP

c. Stop both RHR pumps and place in PULL STOP

d. Both CNMT spray pumps RUNNING d. Pull stop any idle CNMT spray pump and go to Step 7f.

e. Pull stop one CNMT spray pump

f. Check CNMT pressure - LESS THAN f. Go to Step 8.

28 PSIG.

g. Place NaOH Tank outlet valve controllers in manual, full open.

"*AOV-836A

"*AOV-836B

h. Reset CNMT spray

i. Close discharge valves for idle CNMT spray pump(s) o Pump A e MOV-860A o MOV-860B o Pump B o MOV-860C 9 MOV-860D

8 Verify RHR System Alignment:

a. Verify the following valves a. Ensure at least one suction CLOSED valve and one discharge valve closed.

"o RHR suction valves from loop A hot leg

"* MOV-700

"* MOV-701 "o RHR discharge valves to loop B cold leg

"* MOV-720

"* MOV-721

b. Verify RHR pump suction crosstie b. Manually open valves. If valves valves OPEN can NOT be opened, THEN dispatch AO to locally open valves.

e MOV-704A e MOV-704B

c. Verify the following valves c. Ensure at least one valve in OPEN each set open.

"o RHR pump discharge to Rx vessel deluge valves

"* MOV-852A

"* MOV-852B "o RHR suction from sump B (inside CNMT)

"* MOV-851A

"* MOV-851B

d. Verify RCDT pump suction valves d. Manually close valves.

from sump B CLOSED

.e MOV-1813A

• MOV-1813B

EOP: TITLE: REV: 33 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 10 of 22

-- .* *...*..........EP

....ATO TD E OS. R O NO .*.

OBTAINED CAUTION RHR FLOW INDICATED ON FI-626 SHOULD BE LIMITED TO 1500 GPM PER OPERATING PUMP TO ENSURE OPTIMUM PUMP PERFORMANCE.

9 Initiate RHR Sump Recirculation:

a. Close RWST outlet valve to RHR a. Dispatch AO to locally close pump suction. MOV-856 (turn on valve and continue with Step 9b.

DC power key switch)

b. Open both RHR suction valves b. IF only one valve will open, from sump B (outside CNMT) THEN perform the following:

"o MOV-850A - OPEN 1) Initiate only one train of RHR recirculation (Refer to "o MOV-850B - OPEN Attachment RHR NPSH for further guidance).

2) Go to 9e.

IF neither valve will open, THEN refer to Attachment RHR PRESS REDUCTION for further guidance.

c. Check MOV-738A AND MOV-738B c. Perform the following:

BOTH OPEN

1) IF MOV-738A open, THEN start RHR Pump A and go to step 9e.

2) IF MOV-738B open, THEN start RHR Pump B and go to step 9e.

d. Start both RHR pumps

e. Verify at least one RHR pump e. IF no RHR pump can be started, RUNNING THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.

_ATIOIEXPCTE

• RESONSI IRESPOýNSE NýOTOBTAINEýD CAUTION SUMP RECIRCULATION FLOW TO RCS MUST BE MAINTAINED AT ALL TIMES, EXCEPT DURING ALIGNMENT FOR HIGH HEAD RECIRCULATION.

NOTE: The TSC should be requested to establish periodic monitoring of the AUX BLDG sub-basement, as radiological conditions permit, to monitor RHR pump operation.

10 Check RWST Level - LESS THAN DO NOT continue with this procedure 15% until RWST level is less than 15%.

11 Stop All Pumps Supplied From RWST:

a. Stop all SI pumps and place in PULL STOP

b. Stop all charging pumps

c. Stop operating CNMT spray pump and place in PULL STOP

d. Check CNMT pressure LESS THAN d. Go to Step 12.

28 PSIG

e. Reset CNMT spray if necessary

f. Close CNMT spray pump discharge valves

"* MOV-860A

"*MOV-860B

"*MOV-860C

"*MOV-860D

EOP: TITLE:

REV: 33 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 12 of 22

. . . . .. . . . . *.. *O

. *O

. . 0**AI

.*I ..

CAUTION RHR FLOW MUST BE MAINTAINED LESS THAN 1500 GPM PER OPERATING RHR PUMP AS DETERMINED BY THE TOTAL OF FI-931A, FI-931B AND FI-626 INDICATIONS.

12 Align SI And CNMT Spray For Sump Recirculation:

a. Verify SI pump suction valves a. Ensure at least one valve in from BASTs - CLOSED each flowpath closed.

"*MOV-826A and MOV-826B

"*MOV-826C and MOV-826D

b. Close RWST outlet valves to SI b. Ensure at least one valve closed.

and CNMT spray pumps (turn on DC power key switches)

"* MOV-896A

"* MOV-896B

c. Close SI pump RECIRC valves c. Ensure at least one valve closed.

"* MOV-898

"*MOV-897

d. Verify SI pump suction valves d. Ensure at least one valve open.

from RWST - OPEN

"*MOV-825A

"*MOV-825B

e. Align operating RHR pump flow e. Ensure at least one flowpath path(s) to SI and CNMT spray aligned from RHR pump(s) to SI pump suction. and CS pump suction header (Refer to Attachment RHR SYSTEM).

o IF RHR Pump A operating.

THEN open MOV-857A and IF neither flow path can be MOV-857C aligned. THEN refer to Attachment RHR PRESS REDUCTION o IF RHR Pump B operating. for further guidance.

THEN open MOV-857B

CAUTION SI PUMPS SHOULD BE STOPPED IF RCS PRESSURE IS GREATER THAN THEIR SHUTOFF HEAD PRESSURE.

NOTE: Operation of SI pump C is preferred since it delivers to both RCS loops.

13 Verify Adequate RCS Makeup Flow:

a. RCS pressure - LESS THAN a. Perform the following:

225 psig [425 psig adverse CNMT]

1) Check RCS conditions:

"o RCS subcooling based on core exit T/Cs greater than Figure MIN SUBCOOLING.

"o PRZR level greater than 5%

[30% adverse CNMT].

IF either condition NOT met, THEN start one SI pump.

2) Go to Step 14.

b. RHR injection flow adequate: b. Start one SI pump.

"o Core exit T/Cs LESS THAN REQUIREMENTS OF FIGURE RHR INJECTION "o Check RVLIS level (no RCPS)

GREATER THAN 52% [55% adverse CNMT]

EOP: TITLE:

REV: 33 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 14 of 22 CAUTION IF A CNMT SPRAY PUMP IS STARTED, THEN CNMT PRESSURE SHOULD BE CLOSELY MONITORED. CNMT PRESSURE SHOULD NOT BE REDUCED TO LESS THAN 22 PSIG.

• 14 Check If CNMT Spray Is Required:

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

28 PSIG

1) IF CNMT spray previously actuated and NaOH tank level greater than 55%. THEN consult TSC to determine if CNMT spray should be restarted.

2) Go to Step 15.

b. Verify CNMT spray pump discharge b. Manually open valve(s) for valves OPEN selected pump.

"*MOV-860A "* CS pump A, MOV-860A or MOV-860B

"*MOV-860B "* CS pump B, MOV-860C or MOV-860D

"*MOV-860C

"*MOV-860D

c. Start selected CNMT spray pump c. IF the selected CNMT spray pump will not start, THEN align and start the other CNMT spray pump.

IF neither pump will start, THEN continue with Step 15. WHEN a CNMT spray pump can be started, THEN do steps 14d, e and f.

d. Adjust RHR flow to maintain less than 1500 gpm per operating RHR pump as indicated by the total of FI-931A, FI-931B and FI-626 "indications.

This Step continued on the next page.

RESPONSE NOT OBTAINED (Step 14 continued from previous page)

e. Open NaOH tank outlet valves

• AOV-836A o AOV-836B

f. WHEN CNMT pressure decreases to 22 psig. THEN perform the following:

1) Reset CNMT spray

2) Check NaOH tank outlet valves 2) Place NaOH tank outlet valve

-CLOSED controllers to MANUAL and close valves.

o AOV-836A o AOV-836B

3) Stop CNMT spray pumps and place in PULL STOP

4) Close CNMT spray pump discharge valves

• MOV-860A o MOV-860B o MOV-860C o MOV-860D 15 Verify Adequate Core Cooling: IF both RHR pumps running. THEN ensure two SI pumps running.

"o Core exit T/Cs - STABLE OR DECREASING IF only one RHR pump running. THEN perform the following:

"o RVLIS level (no RCPs) STABLE OR INCREASING a. Ensure one SI pump running.

"o RVLIS level (no RCPs) - GREATER b. WHEN CNMT spray pumps stopped.

THAN 52% [55% adverse CNMT] THEN start one additional SI pump.

• 1AMn t I n ýta0R l EStP ONSE OT T AIvNe 0LB NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

"*16 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 CNMT1 in at least one S/G.

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

STEPH ACToN/xPETE RESoNSE RESPoNSE NoT OBTA INE 17 Establish Normal Shutdown Alignment:

a. Check condenser AVAILABLE a. Dispatch AO to perform 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

c. Verify adequate Rx head cooling:

1) Verify at least one control I) 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

18 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 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)

19 Check If SI ACCUMs Should Be Isolated:

a. Both RCS hot leg temperatures a. Continue with Step 20. WHEN LESS THAN 400°F both RCS hot leg temperatures less than 400°F, THEN do Steps 19b through d.

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:

e ACCUM A, MOV-841 1) Open vent valves for o ACCUM B, MOV-865 unisolated SI ACCUMs.

"* ACCUM A, AOV-834A

"*ACCUM B, AOV-834B

2) Open HCV-945.

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

EOP: TITLE: REV: 33 ES-I.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 20 of 22 dACTIN/EPECTD STP H RSPONEI RESPOýNSE NýOTOBýTAINEýD CAUTION IF FUEL DAMAGE IS SUSPECTED, MAINTAIN S/G PRESSURE SLIGHTLY GREATER THAN RCS PRESSURE.

20 Check If Intact S/Gs Should Be Depressurized To RCS Pressure:

a. RCS pressure LESS THAN INTACT a. Go to Step 21.

S/G PRESSURES

b. Direct RP to sample S/Gs for activity

c. Request TSC perform a dose projection on steaming S/Gs

d. Dose projection for each S/G d. Do NOT dump steam from a S/G ACCEPTABLE with an unacceptable dose projection.

e. Dump steam to condenser from e. IF steam dump to condenser NOT intact S/G(s) until S/G pressure available, THEN dump steam using less than RCS pressure intact S/G ARVs until S/G pressure less than RCS pressure.

21 Consult TSC to Determine If Rx Vessel Head Should Be Vented

EOP: TITLE: REV: 33 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 21 of 22 SACTO I PECTD REP0 SI ISPOýNSE NýOT OBTAINEDI NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 22.

22 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.

NOTE: The TSC should be consulted before changing recirculation lineups.

23 Check Event Duration Consult TSC to evaluate long term GREATER THAN 19 HOURS AFTER plant status.

EVENT INITIATION 24 Secure CNMT Spray

a. Reset CNMT spray

b. Place NaOH Tank outlet valve controllers in AUTO

• AOV- 836A

• AOV- 836B

c. Place CNMT spray pumps in PULL STOP

d. Close discharge valves for idle CNMT spray pumps "o Pump A e MOV- 860A o MOV- 860B "o Pump B e MOV-860C e MOV- 860D

STEPH ACTioN/xPECTE RESPONSE RESPONSE NOT oBTINED 25 Verify Two SI Pumps - RUNNING Manually start pumps.

26 Check Core Exit T/Cs - LESS Perform the following:

THAN REQUIREMENTS OF FIGURE RHR INJECTION a. Manually open both PRZR PORVs and block valves.

b. Verify core exit T/Cs decreasing to less than requirements of Figure RHR INJECTION. IF NOT, THEN dump steam from intact S/Gs until core exit T/Cs less than required.

27 Consult TSC To Evaluate Long Term Plant Status

- END

EOP: TITLE:

REV: 33 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 1 of 1 ES-1.3 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE RHR INJECTION (FIG 5.0)

3) FIGURE MIN SUBCOOLING (FIG-1.0)

4) ATTACHMENT D/G STOP (ATT-8.1)

5) ATTACHMENT SD-i (ATT- 17.0)

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

7) ATTACHMENT RHR NPSH (ATT 14.3)

8) ATTACHMENT RHR SYSTEM (ATT-14.5)

9) ATTACHMENT MIN SW (ATT 2.1)

10) ATTACHMENT RHR PRESS REDUCTION (ATT- 14.6)

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

12) 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 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F

e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE:

REV: 33 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE I of 1 FOLDOUT PAGE

1. ECA-1.1 TRANSITION CRITERIA IF emergency coolant recirculation is established and subsequently lost, THEN go to ECA-l.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.

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.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER ")3 RESPONSIB~g MANAGER

"? - 5-xCT DATE EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR. This recovery method depressurizes the ruptured S/G by draining it through the ruptured S/G tubes into the RCS.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-3, STEAM GENERATOR TUBE RUPTURE, if plant staff selects backfill method.

b. ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, when blowdown is not available and plant staff selects backfill method.

EOP: TITLE: REV: 14 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 3 of 10 RESPONSE....RESPONSE.NOT.OB A*CTION*EX.....CT*ED.*.

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

• * * * * * * * * * * * . * * * * * * * . * * * * * *t * * * * * * * * * * * *r *

• 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 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure

--ACTON/XPETEDRESONSI

• [RESPýONSE NýOT OBTAINEýD[

2 Check If SI ACCUMs Should Be Isolated:

a. Check the following: a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED "o RCS subcooling based on core RECOVERY DESIRED, Step 1.

exit T/Cs - GREATER THAN 0°F USING FIGURE MIN SUBCOOLING "o PRZR level - GREATER THAN 5%

[30% adverse CNMT]

b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves e MOV-841, MCC C position 12F

• MOV-865, MCC D position 12C

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

"*ACCUM A, MOV-841 1) Open vent valves for

"*ACCUM B, MOV-865 unisolated SI ACCUMs.

• ACCUM A, AOV-834A e ACCUM B, AOV-834B

2) Open HCV-945.

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

EOP: TITLE: REV: 14 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 5 of 10 NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

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

• 4 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 the 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 go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

EOP: TITLE: REV: 14 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 6 of 10 NOTE: Since ruptured SIG may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.

5 Initiate RCS Cooldown To Cold Shutdown:

a. Establish and maintain cooldown rate in RCS cold legs LESS THAN l00°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 SIG available and RHR system NOT in service, THEN perform the following:

"o Use faulted SIG.

-OR "oGo to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED.

Step 1.

EOP: TITLE: REV: 14 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 7 of 10

ýRESPOýNSE NýOTOBýTAINEýD

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

adverse CNMT] using feed flow.

Range Level - LEVEL GREATER THAN 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 SIG pressure increases to 1020 psig.

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

adverse CNMT].

• 7 Control Charging And Letdown Flow To Maintain PRZR Level:

a. PRZR level GREATER THAN 13% a. Increase charging flow as

[40% adverse CNMT] necessary and go to Step 8.

b. PRZR level - LESS THAN 75% [65% b. Decrease charging flow to adverse CNMT] decrease level and go to Step 10.

LOP: TITLE: REV: 14 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 8 of 10

-LJ--c ACTION/EXPECTED RESPONSE m I RESPONSE NOT OBTAINED w

NOTE: o The upper head region may void during RCS depressurization if RCPs are not running. This may result in a rapidly increasing PRZR level.

o RCS depressurization may be stopped when RCS pressure decreases to less than 400 psig [300 psig adverse CNMT] to maintain adequate RCP #1 seal D/P.

• 8 Depressurize RCS To Backfill From Ruptured S/G:

a. Depressurize using normal PRZR a. IF letdown is in service, THEN spray depressurize using auxiliary spray valve (AOV-296). IF NOT, THEN use one PRZR PORV.

b. Maintain PRZR level BETWEEN 13% AND 75% [BETWEEN 40% AND 65%

adverse CNMT]

c. Check ruptured S/G level c. Stop RCS depressurization.

GREATER THAN 5% [25% adverse CNMT]

d. Energize PRZR heaters as necessary

e. Maintain RCS subcooling based on core exit T/Cs - GREATER THAN 0°F USING FIGURE MIN SUBCOOLING 9 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 Or 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT)

EOP: TITLE: REV: 14 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 9 of 10 10 Check If RHR Normal Cooling Can Be Established:

a. RCS cold leg temperature - LESS a. Go to Step 11.

THAN 350°F

b. Go to Step 11.

b. RCS pressure - LESS THAN 400 psig [300 psig adverse CNMT]

c. IF RCS overpressure protection

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

OVERPRESSURE PROTECTION SYSTEM)

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

• 11 Monitor RCP Operation:

a. RCPs ANY RUNNING a. Go to Step 12.

b. Stop affected RCP(s).

b. Check the following:

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

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

EOP: TITLE: REV: 14 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 10 of 10

• STpH CTIN'EP*C*O *SPNS* IRESP0*NSEN0OTOBýTAINE 12 Check Core Exit T/Cs - LESS Return to Step 3.

THAN 2000F 13 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions (Refer to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS)

b. Consult TSC END

EOP: TITLE: REV: 14 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 ES-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 RHR COOL (ATT-14.1)

6) FOLDOUT

EOP: TITLE:

REV: 14 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL 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 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 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F

e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE:

REV: 14 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 FOLDOUT PAGE

1. SI REINITIATION CRITERIA Following SI termination, IF either condition listed below occurs, THEN start SI pumps manually 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 T/Cs - LESS THAN 0°F USING REQUIREMENTS OF 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, UNLESS faulted S/G needed for RCS cooldown.

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).

4. MULTIPLE S/G TUBE RUPTURE CRITERIA I

IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

EOP: TITLE: REV: 15 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN "PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBXI MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:.

EOP: TITLE:

REV: 15 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 2 of 10 A. PURPOSE - This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR. This recovery method depressurizes the ruptured S/G by draining via S/G blowdown.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-3, STEAM GENERATOR TUBE RUPTURE, if plant staff selects the blowdown method.

EOP: TITLE:RE  : 1 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 3 of 10 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 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 2 Check If SI ACCUMs Should Be Isolated:

a. Check the following: a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED "o RCS subcooling based on core RECOVERY DESIRED, Step 1.

exit T/Cs GREATER THAN 0°F USING FIGURE MIN SUBCOOLING "o PRZR level GREATER THAN 5%

[30% adverse CNMT1

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 outlet valves c. Vent any unisolated ACCUMs:

• ACCUM A, MOV-841 1) Open vent valves for

• ACCUM B, MOV-865 unisolated SI ACCUMs.

"*ACCUM A, AOV 834A

"*ACCUM B, AOV-834B

2) Open HCV-945.

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

EOP: TITLE:

REV: 15 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 4 of 10 TE ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

3 Verify Adequate Shutdown Margin

a. Direct RP to sample RCS and ruptured SIG for boron concentration

b. Verify boron concentration b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

• 4 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 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 go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED. Step 1.

EOP: TITLE: REV: 15 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 5 of 10 NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.

5 Initiate RCS Cooldown To 3500 F:

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

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

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

"o Use faulted S/G.

-OR

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

LEOP: TITLE: REV: 15 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 6 of 10

• -*- ** * *.................. R N OBTAINED CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.

• 6 Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondary Leakage:

a. Perform appropriate action(s) from table:

PRZR RUPTURED S/G NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13% o Increase Increase o Increase

[40% ADVERSE CNMT] charging flow charging charging flow flow o Depressurize o Maintain RCS RCS using and ruptured Step 6b. S/G pressure equal BETWEEN 13% Depressurize Energize Maintain RCS

[40% ADVERSE CNMT] RCS using PRZR and ruptured AND 50% Step 6b. heaters S/G pressure equal BETWEEN 50% AND 75% o Depressurize Energize Maintain RCS

[65% ADVERSE CNMT] RCS using PRZR and ruptured Step 6b. heaters S/G pressure equal o Decrease charging flow GREATER THAN 75% o Decrease Energize Maintain RCS

[65% ADVERSE CNMT] charging flow PRZR and ruptured heaters S/G pressure equal

b. Use normal PRZR spray to obtain b. IF letdown is in service, THEN desired results for Step 6a use auxiliary spray (AOV-296).

IF NOT, THEN use one PRZR PORV.

7 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 8 Check If RCS Cooldown Should Be Stopped:

a. RCS cold leg temperatures LESS a. Return to Step 3.

THAN 350°F

b. Stop RCS cooldown

c. Maintain RCS cold leg temperature LESS THAN 350°F

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

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

THAN 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 SIG level greater than 5% [25%

adverse CNMT].

EOP: TITLE: REV : 1 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 8 of 10 SACTON/XPETEDRESONSI [RESPýONSE NýOT0BýTAINEýD NOTE: Blowdown from ruptured S/G may be stopped when RCS pressure decreases to less than 400 psig [300 psig adverse CNMT] to maintain adequate RCP #1 seal AP.

10 Consult TSC To Determine IF blowdown can NOT be initiated, Appropriate Procedure To THEN go to alternate post-SGTR Establish Blowdown From cooldown procedure, ES-3.1, Ruptured S/G POST-SGTR COOLDOWN USING BACKFILL, Step 1. OR ES-3.3., POST-SGTR COOLDOWN USING STEAM DUMP, Step 1.

• 11 Control Charging And Letdown Flow To Maintain PRZR Level:

a. PRZR level - GREATER THAN 13% a. Increase charging flow as

[40% adverse CNMT] necessary and go to Step 12.

b. PRZR level LESS THAN 75% [65% b. Decreases charging flow to adverse CNMT] decrease level and go to Step 13.

NOTE: The upper head region may void during depressurization if RCPs are not running. This may result in a rapidly increasing PRZR level.

"*12 Depressurize RCS To Minimize RCS-To-Secondary Leakage:

a. Depressurize using normal PRZR a. IF letdown is in service, THEN spray depressurize using auxiliary spray valve (AOV-296). IF NOT, THEN use one PRZR PORV.

b. Energize PRZR heaters as necessary

c. Maintain RCS pressure at ruptured S/G pressure

d. Maintain RCS subcooling based on core exit T/Cs GREATER THAN 0°F USING FIGURE MIN SUBCOOLING

CT OPETRESPONSE NnOTOBTAINED

"*13 Monitor RCP Operation:

a. RCPs ANY RUNNING a. Go to Step 14.

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

"o RCP #1 seal DIP - GREATER THAN 220 PSID

" Check RCP seal leakage WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF 14 Check If RHR Normal Cooling Can Be Established:

a. RCS cold leg temperature LESS a. Return to Step 9.

THAN 350°F

b. RCS pressure LESS THAN b. Return to Step 9.

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)

LEOP: TITLE: REV: 15 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 10 of 10

-- CTIO/EXECTE

• REPONS] IRESPOýNSE NýOTOBýTAINEýD 15 Continue RCS Cooldown To Cold Shutdown:

a. Maintain cooldown rate in RCS cold legs LESS THAN 1000F/HR

b. Use RHR System

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

IF no intact S/G available and RHR system NOT in service, THEN perform the following:

"o Use faulted S/G.

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

16 Check Core Exit T/Cs - LESS Return to Step 9.

THAN 2000F 17 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions (Refer to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS)

b. Consult TSC

-END

EOP: TITLE: REV: 15 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1 of 1 ES-3.2 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 RHR COOL (ATT-14.1)

6) FOLDOUT

EOP: TITLE:

REV: 15 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN 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: 15 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1 of 1 FOLDOUT PAGE

1. SI REINITIATION CRITERIA Following SI termination, IF either condition listed below occurs, THEN start SI pumps manually 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 T/Cs - LESS THAN 0'F USING REQUIREMENTS OF 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, UNLESS faulted S/G needed for RCS cooldown.

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.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

4. MULTIPLE S/G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER ___

RESPONSIBL" NAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 2 of 12 A. PURPOSE - This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR. This recovery method depressurizes the ruptured S/G by dumping steam.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-3, STEAM GENERATOR TUBE RUPTURE, if plant staff selects steam dump method.

b. ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, when blowdown is not available and plant staff selects steam dump method.

EOP: TITLE:

REV: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 3 of 12 CAUTION o STEAM SHOULD NOT BE RELEASED FROM ANY RUPTURED S/G IF WATER MAY EXIST IN ITS STEAMLINE.

o AN OFFSITE DOSE EVALUATION SHOULD BE COMPLETED PRIOR TO USING THIS PROCEDURE.

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 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure

EOP: TITLE:

REV: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM~ DUMP PAGE 4 of 12 2 Check If SI ACCUMs Should Be Isolated:

a. Check the following: a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED "o RCS subcooling based on core RECOVERY DESIRED, Step 1.

exit T/Cs - GREATER THAN 0°F USING FIGURE MIN SUBCOOLING "o PRZR level GREATER THAN 5%

[30% adverse CNMT]

b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves e MOV-841, MCC C position 12F

• MOV-865, MCC D position 12C

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

"*ACCUM A, MOV-841 1) Open vent valves for

"*ACCUM B. 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

OP: TITLE: REV: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 5 of 12 NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

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

• 4 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 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 go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.

5 Initiate RCS Cooldown To 3500 F:

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

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

IF no intact SIG available, THEN perform the following:

o Use faulted S/G.

-OR o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.

. *-ACTION/EXPECTED.....*..*

RSN* R N OBTAINED...[. *.

CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.

• 6 Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondary Leakage:

a. Perform appropriate action(s) from table:

PRZR RUPTURED SIG NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13% o Increase Increase o Increase

[40% ADVERSE CNMT] charging flow charging flow charging flow o Depressurize o Maintain RCS RCS using and ruptured Step 6b. S/G pressure equal BETWEEN 13% Depressurize Energize Maintain RCS

[40% ADVERSE CNMT] RCS using PRZR and ruptured AND 50% Step 6b. heaters S/G pressure equal BETWEEN 50% AND 75% o Depressurize Energize Maintain RCS

[65% ADVERSE CNMT] RCS using PRZR and ruptured Step 6b. heaters S/G pressure equal o Decrease charging flow GREATER THAN 75% o Decrease Energize Maintain RCS

[65% ADVERSE CNMT] charging flow PRZR and ruptured heaters S/G pressure equal

b. Use normal PRZR spray to obtain b. IF letdown is in service, THEN desired results for Step 6a use auxiliary spray (AOV-296).

IF NOT. THEN use one PRZR PORV.

OP: TITLE: REV: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 8 of 12 7 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 8 Check If RCS Cooldown Should Be Stopped:

a. RCS cold leg temperatures LESS a. Return to Step 3.

THAN 350°F

b. Stop RCS cooldown

c. Maintain RCS cold leg temperature LESS THAN 350'F

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

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

THAN 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 SIG 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].

S .* .

ST*IN.XETDREP.E**....*.........*

.. RSO E NOT OBTAINED CAUTION RUPTURED S/G PRESSURE MAY DECREASE RAPIDLY WHEN STEAM IS RELEASED.

NOTE: Steam release from ruptured S/G may be stopped when RCS pressure decreases to less than 400 psig [300 psig adverse CNMT1 to maintain adequate RCP #1 seal AP.

10 Initiate Cooldown Of Ruptured S/G:

a. Verify condenser available: a. Manually or locally dump steam using ruptured S/G ARV and go to o Intact SIG MSIV OPEN Step 11.

o Annunciator G-15, STEAM DUMP ARMED LIT

b. Dispatch AO to locally align steam traps associated with the ruptured SIG.

c. Dispatch AO to locally open ruptured S/G MSIV bypass valve

d. Dump steam to condenser using steam dump pressure controller

• 11 Control Charging And Letdown Flow To Maintain PRZR Level:

a. PRZR level GREATER THAN 13% a. Increase charging flow as

[40% adverse CNMT] necessary and go to Step 12.

b. PRZR level LESS THAN 75% [65% b. Decrease charging flow to adverse CNMT] decrease level and go to Step 13.

EOP: TITLE: REV: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 10 of 12

. .q STEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED[

NOTE: The upper head region may void during depressurization if RCPs are not running. This may result in a rapidly increasing PRZR level.

"*12 Depressurize RCS To Minimize RCS-To-Secondary Leakage:

a. Depressurize using normal PRZR a. IF letdown is in service, THEN spray associated with running RCP depressurize using auxiliary spray valve (AOV-296). IF NOT, THEN use one PRZR PORV.

b. Energize PRZR heaters as necessary

c. Maintain RCS pressure at ruptured SIG pressure

d. Maintain RCS subcooling based on core exit T/Cs - GREATER THAN 0°F USING FIGURE MIN SUBCOOLING

"*13 Monitor RCP Operation:

a. RCPs ANY RUNNING a. Go to Step 14.

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

o RCP #1 seal DIP GREATER THAN 220 PSID

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

EOP: TITLE: REV: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 11 of 12 14 Check If RHR Normal Cooling Can Be Established

a. RCS cold leg temperature LESS a. Return to Step 9.

THAN 350°F

b. RCS pressure - LESS THAN b. Return to Step 9.

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) 15 Continue RCS Cooldown To Cold Shutdown:

a. Maintain cooldown rate in RCS cold legs LESS THAN 100°F/HR

b. Use RHR System

c. Dump steam to condenser from c. Manually or locally dump steam intact S/C using intact S/G ARV IF no intact SIG available and RHR system NOT in service, THEN perform the following:

"o Use faulted SIG.

-OR

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

LOP: TITLE:

REV: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 12 of 12

• STEPH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 16 Check Core Exit T/Cs - LESS Return to Step 9.

THAN 2000F 17 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions (Refer to 0-2.2.

PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS)

b. Consult TSC END

EOP: TITLE:

REV: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 ES-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 RHR COOL (ATT 14.1)

6) FOLDOUT

EOP: TITLE:

REV: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 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: 15 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FOLDOUT PAGE

1. SI REINITIATION CRITERIA Following SI termination, IF either condition listed below occurs, THEN start SI pumps manually 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 T/Cs - LESS THAN 00 F USING REQUIREMENTS OF 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, UNLESS faulted S/G needed for RCS cooldown.

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.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

4. MULTIPLE S/G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

EOP: TITLE:

REV: 19 RESPONSE TO INADEQUATE CORE COOLING FR-C.1 PAGE 1 of 18 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONS IBL 'MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE: REV: 19 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 2 of 18 A. PURPOSE - This procedure provides actions to restore core cooling.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. F-0.2, CORE COOLING Critical Safety Function Status Tree, on a RED condition.

SACIONEXPCTE REPONEI[RESPýONSE ýNOTOýBTAINED[ý NOTE: 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 RWST Level - GREATER Perform the following:

THAN 28%

a. Ensure SI system aligned for cold leg recirculation using Steps 1 through 13 of ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.

b. WHEN the SI system is aligned for sump recirculation, THEN go to Step 4.

2 Verify SI Pump Suction Aligned to RWST:

a. Verify SI pump suction valves a. Ensure at least one SI pump from RWST - OPEN suction valve from RWST open.

"*MOV-825A

• MOV-825A

"*MOV-825B

• MOV-825B

.................... *... * *.... * .T OA.O...O..O CAUTION RHR PUMPS SHOULD NOT BE RUN LONGER THAN 1 HOUR WITHOUT CCW TO THE RHR HEAT EXCHANGERS.

3 Verify SI Pump And RHR Pump Emergency Alignment:

a. RHR pump discharge to Rx vessel a. Ensure at least one valve open.

deluge OPEN

"*MOV-852A

"*MOV-852B

b. Verify both RHR pumps - RUNNING b. Manually start pumps

c. Verify SI pump C - RUNNING c. Manually start pump on available bus.

d. Verify SI pump A - RUNNING d. Perform the following:

1) Ensure SI pumps B and C running.

2) Ensure SI pump C aligned to discharge line A:

"o MOV-871B closed "o MOV-871A open

3) Go to Step 4.

e. Verify SI pump B - RUNNING e. Perform the following:

1) Ensure SI pumps A and C running.

2) Ensure SI pump C aligned to discharge line B:

"o MOV-871B open "o MOV-871A closed

3) Go to Step 4.

f.,*Verify both SI pump C discharge f. Manually open valves as valves OPEN necessary.

• MOV-871A

• MOV-871B

EOP: TITLE: REV: 19 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 5 of 18 P ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED1 4 Verify SI Flow In Both Trains: Perform the following:

o SI line loop A and B flow a. Manually start pumps and align indicators - CHECK FOR FLOW valves as necessary.

o RHR loop flow indicator CHECK b. Establish maximum charging flow.

FOR FLOW 5 Check RCP Support Conditions:

a. Verify Bus I1A or liB - ENERGIZED a. Restore power to Bus IIA or 1lB (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).

b. Check other RCP support b. Continue attempts to establish conditions (Refer to Attachment RCP support conditions.

RCP START) 6 Check SI ACCUM Discharge IF SI ACCUM discharge valves closed Valves - OPEN after ACCUM discharge, THEN go to Step 7. IF NOT, THEN perform the

"*MOV- 841 following:

"*MOV- 865

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

• MOV-841. MCC C position 12F e MOV-865, MCC D position 12C

b. Open SI ACCUM discharge valves.

• ACCUM A, MOV-841

• ACCUM B, MOV-865

EOP: TITLE:

REV: 19 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 6 of 18 SSTEPH ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 7 Check Core Exit T/Cs - LESS Go to Step 10.

THAN 12000F 8 Check RVLIS Indication:

a. RCPs BOTH SECURED a. Return to procedure and step in effect

b. RVLIS level GREATER THAN 52% b. IF RVLIS increasing, THEN return

[55% adverse CNMT] to Step 1. IF NOT, THEN go to Step 9.

c. Return to procedure and step in effect 9 Check Core Exit T/Cs:

a. Temperature LESS THAN 700°F a. IF decreasing, THEN return to Step 1. IF NOT, THEN go to Step 10.

b. Return to procedure and step in effect 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) 10 Reset SI

dACTIN/EPECTD STP H RSPONEI RESPýONSE ýNOTOýBTAINED[

11 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.

NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 12.

12 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.

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

. . X*0* . . .**. *. OT

• OA* . . . . ..

CAUTION o IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).

o A FAULTED OR RUPTURED S/G SHOULD NOT BE USED IN SUBSEQUENT STEPS UNLESS NO INTACT S/G IS AVAILABLE.

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

"*13 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.

IF total feed flow greater than 200 gpm can NOT be established, THEN perform the following:

1) Continue attempts to establish a heat sink in at least one S/G (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

2) Go to Step 23.

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

EoP: TITLE: REV: 19 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 9 of 18

• *A* **O** X............. *** ..

0 O**A .......

CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 14B).

14 Check RCS Vent Paths:

a. Power to PRZR PORV block valves a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:

"*MOV-515, MCC D position 6C

"*MOV-516, MCC C position 6C

b. PORVs CLOSED b. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.

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

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

d. Rx vessel head vent valves d. Manually close valves.

CLOSED

• SOV- 590

• SOV-591

• SOV-592

• SOV-593

REPONE [RESPýONSE ýNOTOýBTAINýED [ SACIONEXPCTE 15 Establish Condenser Steam Dump Manual Control

a. Verify condenser available: a. Place intact S/G ARV controller in MANUAL and go to Step 16.

o Intact S/G MSIV - OPEN o Annunciator G-15, STEAM DUMP ARMED - LIT

b. Place steam dump mode selector switch in MANUAL

c. Place steam dump controller in MANUAL NOTE: Partial uncovering of SIG tubes is acceptable in the following steps.

16 Depressurize All Intact S/Gs To 200 PSIG:

a. Dump steam to condenser at a. Manually or locally dump steam maximum rate at maximum rate using SIG ARVs.

b. Check S/G pressure LESS THAN b. IF S/G pressure decreasing, THEN 200 PSIG return to Step 13.

IF NOT, THEN go to Step 23.

c. Check RCS hot leg temperatures c. IF RCS hot leg temperatures BOTH LESS THAN 400°F decreasing, THEN return to Step 13.

IF NOT, THEN go to Step 23.

d. Stop S/G depressurization

dACTON/XPETEDRESONSI STP H IRESPýONSE NýOT OBTAINEýD 17 Check If SI ACCUMs Should Be Isolated:

a. RCS hot leg temperatures - BOTH a. Go to Step 23.

LESS THAN 400°F

b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves if necessary o MOV-841 MCC C position 12F o MOV-865 MCC D position 12C

c. Verify SI reset c. Manually reset SI.

d. Close SI ACCUM discharge valves d. Perform the following:

• ACCUM A, MOV-841 1) Reset CI.

• ACCUM B, MOV-865

2) Ensure adequate air compressor(s) running.

3) Establish IA to CNMT.

4) Open vent valves for unisolated SI ACCUMs.

"* ACCUM A, AOV-834A

"* ACCUM B, AOV-834B

5) Open HCV-945.

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

EOP: TITLE: REV: 19 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 12 of 18 18RESPONSE NOT OBBTAINEDo 18 Stop Both RCPs 19 Dump Steam to Condenser At Manually or locally dump steam at Maximum Rate To Depressurize maximum rate using SIG ARVs.

All Intact S/Gs To Atmospheric Pressure Flow: Perform the following:

20 Verify SI "o SI line loop A and B flow a. Continue efforts to establish SI indicators CHECK FOR FLOW flow.

-OR b. Try to establish charging flow.

"o RHR loop flow indicator - CHECK c. IF core exit T/Cs less than FOR FLOW 1200'F, THEN return to Step 19.

IF NOT, THEN go to Step 23.

21 Check Core Cooling:

a. Core exit T/Cs LESS THAN 1200°F a. Go to Step 23.

b. RCS hot leg temperatures BOTH b. Return to Step 19.

LESS THAN 320°F

c. RVLIS level (no RCPs) - GREATER c. Return to Step 19.

THAN 77% [82% adverse CNMT]

22 Go to Appropriate Plant Procedure

a. Check RWST level GREATER THAN a. Go to ES-1.3. TRANSFER TO COLD 28% LEG RECIRCULATION, Step 1.

b. Go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT, Step 17

NOTE: Normal conditions are desired but not required for starting the RCPs.

23 Check If RCPs Should Be Started:

a. Core Exit T/Cs - GREATER THAN a. Go to Step 24.

1200°F

b. Check if an idle RCS cooling b. Perform the following:

loop is available

1) Reset SI.

"o Narrow range SIG level GREATER THAN 5% [25% adverse 2) Reset CI.

CNMT]

3) Ensure adequate air "o RCP in associated loop compressor(s) running.

AVAILABLE AND NOT OPERATING

4) Establish IA to CNMT.

5) Open all PRZR PORVs and block valves a) IF any block valve can NOT be opened, THEN ensure power supplied to block valve.

b) IF IA NOT available, THEN refer to Attachment N2 PORVS.

6) IF core exit T/Cs remain greater than 1200'F, THEN open Rx vessel head vent valves.

"* SOV-590

"* SOV-591

"* SOV-592

"* SOV-593

7) Go to Step 24.

c. Start RCP in one idle RCS cooling loop

d. Return to Step 23a

STEPH ACTioN/xPETE RESoNSE REsPoNS NoT oBTA INE 24 Try To Locally Depressurize Use faulted or ruptured S/G.

All Intact S/Gs To Atmospheric Pressure:

"o Use intact S/G(s) ARVs

-OR "o Open TDAFW pump steam supply valve from intact S/G(s)

"* S/G A. MOV-3505A

"* SIG B, MOV-3504A

-OR 0 Perform the following:

a. Open intact SIG MSIV bypass valves

b. Open both priming air ejector steam inlet valves

"* V-3580

"* V-3581 25 Check Core Exit T/Cs LESS IF core exit temperatures THAN 1200°F decreasing, THEN return to step 23.

IF core exit temperatures increasing, THEN go to SACRG-1.

SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE, step 1.

EOP: TITLE: REV: 19 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 16 of 18 SP ACTION/EXPECTED RESPONSE [RESPONSE NOT OBTAINED 26 Check If SI ACCUMs Should Be Isolated:

a. RHR loop flow indicator AT a. Return to Step 23.

LEAST INTERMITTENT FLOW

b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves if necessary o MOV-841 MCC C position 12F e MOV-865 MCC D position 12C

c. Reset SI.

d. Close SI ACCUM discharge valves d. Perform the following:

"*ACCUM A, MOV-841 1) Reset CI.

"*ACCUM B, MOV-865

2) Ensure adequate air compressor(s) running.

3) Establish IA to CNMT.

4) Open vent valves for unisolated SI ACCUMs.

"* ACCUM A, AOV-834A

"* ACCUM B, AOV-834B

5) Open HCV-945.

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

STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 27 Check If RCPs Should Be Stopped:

a. Both RCS hot leg temperatures a. Go to Step 28.

LESS THAN 320°F

b. Stop all RCPs 28 Verify SI Flow: Perform the following:

o SI line loop A and B flow a. Continue efforts to establish SI indicators - CHECK FOR FLOW flow.

-OR- b. Try to establish charging flow.

o RHR loop flow indicator CHECK c. Return to Step 23.

FOR FLOW 29 Check Core Cooling:

a. RCPs BOTH SECURED a. Return to Step 23.

b. RCS hot leg temperatures - LESS b. Return to Step 23.

THAN 320°F

c. RVLIS level - GREATER THAN 77% c. Return to Step 23.

[82% adverse CNMT]

30 Go to Appropriate Plant Procedure

a. IF PRZR PORVs and head vents were opened in Step 23. THEN consult TSC to evaluate long term status AND continue with transitions.

b. Check RWST level GREATER THAN b. Go to ES-1.3, TRANSFER TO COLD 28% LEG RECIRCULATION, Step 1.

c. Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 17.

-END-

EOP: TITLE:

REV: 19 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 1 of 1 FR-C.1 APPENDIX LIST TITLE I) ATTACHMENT RCP START (ATT 15.0)

2) ATTACHMENT N2 PORVS (ATT-12.0)

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

EOP: TITLE: REV: 16 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 1 of 14 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBL NAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:___________

A. PURPOSE - This procedure provides actions to restore adequate core cooling.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. F-0.2, CORE COOLING Critical Safety Function Status Tree, on any ORANGE condition.

STP ACTION/EXPECTED RESPONSE[ RESPONSE NOT OBTAINEDI NOTE: 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.

o Normal conditions for running RCPs are desired, but RCPs should NOT be tripped if normal conditions cannot be established or maintained.

• 1 Monitor RWST Level - GREATER Perform the following:

THAN 28%

a. Ensure SI system aligned for cold leg recirculation using Steps 1 through 13 of ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.

b. Go to Step 4.

2 Verify SI Pump Suction Aligned To RWST:

a. SI pump suction valves from RWST a. Ensure at least one SI pump OPEN suction valve from RWST open

• MOV-825A o MOV-825A

• MOV-825B o MOV-825B

EOP: TITLE:

REV: 16 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 4 of 14 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED 3 Verify SI Pump And RHR Pump Emergency Alignment:

a. RHR pump discharge to Rx vessel a. Ensure at least one valve open.

deluge - OPEN

"*MOV-852A

"*MOV-852B

b. Verify SI pump C - RUNNING b. Manually start pump on available bus.

c. Verify SI pump A RUNNING c. Perform the following:

1) Ensure SI pumps B and C running.

2) Ensure SI pump C aligned to discharge line A:

"o MOV-871B closed "o MOV-871A open

3) Go to Step 4.

d. Verify SI pump B RUNNING d. Perform the following:

1) Ensure SI pumps A and C running.

2) Ensure SI pump C aligned to discharge line B:

o MOV-871B open o MOV-871A closed

3) Go to Step 4.

e. Verify both SI pump C discharge e. Manually open valves as valves OPEN necessary.

0 MOV-871A e MOV 871B

EOP: TITLE: REV: 16 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 5 of 14 STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ý 4 Verify SI Flow In Both Trains:

a. SI line loop A and B flow a. Perform the following:

indicators CHECK FOR FLOW

1) Manually start SI pumps and align valves as necessary.

2) Establish maximum charging flow.

b. RCS pressure - LESS THAN b. Go to Step 5.

250 psig [465 psig adverse CNMT]

c. RHR loop flow indicator - CHECK c. Manually start RHR pumps and FOR FLOW align valves.

EOP: TITLE: REV 16 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 6 of 14 X

..* .................. O* * *O O **...*..

• 0T **

... *SOE CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE. IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).

5 Check RCS Vent Paths:

a. Power to PRZR PORV block valves a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:

"*MOV-515, MCC D position 6C

"*MOV-516, MCC C position 6C

b. PORVs CLOSED b. IF PRZR pressure less than 2335 psig. THEN manually close PORVs.

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

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

d. Rx vessel head vent valves d. Manually close valves.

CLOSED

"* SOV-590

"*SOV-591

"*SOV-592

"*SOV-593

EOP: TITLE: REV FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 7 of 14 6 Check RCP Status:

a. At least one RCP - RUNNING a. Go to Step 9.

b. Support conditions for the b. Try to establish support operating RCP(s) available conditions for the operating RCP.

(Refer to Attachment RCP START) 7 Check RVLIS Fluid Fraction

a. Fluid fraction (any RCP on) a. IF increasing. THEN return to GREATER THAN 64% Step 1.

IF NOT, then go to Step 8.

b. Return to procedure and step in effect.

8 Check If One RCP Should Be Stopped:

a. Both RCPs RUNNING a. Go to Step 10.

b. Stop one RCP

c. Go to Step 10 9 Check Core Cooling:

a. RVLIS level (no RCPs) -GREATER a. IF increasing, THEN return to THAN 52% [55% adverse CNMT] Step 1. IF NOT, THEN go to Step 10.

b. Core exit T/Cs - LESS THAN 700'F b. IF decreasing, THEN return to Step 1. IF NOT, THEN go to Step 10.

c. Return to procedure and step in effect

EOP: TITLE: REV: 16 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 8 of 14 S~ACTI ON/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check SI ACCUM Discharge IF SI ACCUM discharge valves closed Valves - OPEN after ACCUM discharge, THEN go to Step 11. IF NOT, THEN perform the

"*MOV-841 following:

"*MOV-865

a. 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

b. Open SI ACCUM discharge valves.

"*ACCUM A, MOV-841

"*ACCUM B, MOV-865 CAUTION "o IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).

"o A FAULTED OR RUPTURED SIG SHOULD NOT BE USED IN SUBSEQUENT STEPS UNLESS NO INTACT S/G IS AVAILABLE.

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

• 11 Monitor Intact S/G Levels:

a. Narrow range level - GREATER a. Increase total feed flow to THAN 5% [25% adverse CNMT] restore narrow range level greater than 5% [25% adverse CNMT] in at least one S/G.

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

12 Establish Condenser Steam Dump Manual Control

a. Verify condenser available: a. Place intact S/G ARV controller in MANUAL and go to Step 13.

"o Intact SIG MSIV - OPEN "o Annunciator G-15. STEAM DUMP ARMED - LIT

b. Place steam dump mode selector switch in MANUAL

c. Place steam dump controller in MANUAL

EOP: TITLE: REV: 16 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 10 of 14 SE*AT **.............

NE ECE.SOS. R O .*

NO OBTAINED CAUTION THE FOLLOWING STEP WILL CAUSE SI ACCUMULATOR INJECTION WHICH MAY RESULT IN A RED PATH CONDITION IN F-0.4, INTEGRITY STATUS TREE. THIS PROCEDURE SHOULD BE COMPLETED BEFORE TRANSITION TO FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK.

13 Depressurize All Intact S/Gs To 200 PSIG:

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

b. Dump steam to condenser b. Manually or locally dump steam from intact S/Gs:

o Use S/G ARVs.

-OR "o Open TDAFW pump steam supply valve(s) for affected SIG(s):

"*SIG A. MOV-3505A

"* S/G B, MOV-3504A

-OR "o Locally perform the following:

"o Open intact S/G MSIV bypass valve.

"o Open priming air ejector steam isolation valves.

o V-3580

• V-3581

c. Check S/G pressures LESS THAN c. Return to Step 11.

200 PSIG

d. Stop S/G depressurization

STP ACTION/EXPECTEDE RESPONSE NOT OBTAINEDI CAUTION RHR PUMPS SHOULD NOT BE RUN LONGER THAN 1 HOUR WITHOUT CCW TO THE RHR HEAT EXCHANGERS.

• * * * * * * * * * * * * * * * * * * * * *

• a * * * * * * * * * * * * * * * *

• 14 Check RHR Pumps - RUNNING Manually start pumps as necessary.

15 Check If SI ACCUMs Should Be Isolated:

a. RCS hot leg temperatures BOTH a. Go to Step 17.

LESS THAN 400°F

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

• MOV-841, MCC C position 12F

• MOV-865, MCC D position 12C

c. Reset SI

d. Close SI ACCUM discharge valves d. Perform the following:

• MOV-841 1) Reset CI

• MOV-865

2) Ensure adequate air compressor(s) running

3) Establish IA to CNMT

4) Open vent valves for unisolated SI ACCUMs.

e ACCUM A. AOV-834A e ACCUM B, AOV-834B

5) Open HCV-945.

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

STEP ACTION/XPECTED RESPONSE. RESPONSE NOT OBTAINED CAUTION SYMPTOMS FOR FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, SHOULD BE CLOSELY MONITORED DURING SUBSEQUENT STEPS.

16 Stop All RCPs 17 Depressurize All Intact S/Gs To Atmospheric Pressure:

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

b. Dump steam to condenser b. Manually or locally dump steam from intact S/Gs:

1) Use S/G ARVs.

2) Open TDAFW pump steam supply valve(s) for affected SIG(s):

"* S/G A, MOV-3505A

"* S/G B, MOV-3504A

3) Locally perform the following:

"o Open intact S/G MSIV bypass valve.

"o Open priming air ejector steam isolation valves.

e V-3580

• V-3581

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED1 18 Verify SI Flow: Perform the following:

"o SI line loop A and B flow a. Continue efforts to establish SI indicators - CHECK FOR FLOW flow.

-OR b. Try to establish maximum charging flow.

"o RHR loop flow indicator CHECK FOR FLOW c. Return to Step 17.

19 Isolate Both SI ACCUMs:

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

• MOV-841, MCC C position 12F

• MOV-865, MCC D position 12C

b. Reset SI

c. Close SI ACCUM discharge valves c. Perform the following:

• MOV-841 1) Reset CI.

• MOV-865

2) Ensure adequate air compressor(s) running.

3) Establish IA to CNMT.

4) Open vent valves for unisolated SI ACCUMs.

"*ACCUM A, AOV-834A

"*ACCUM B, AOV-834B

5) Open HCV-945.

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

20RESPONSE NOT OSBTAINEDlC 20 Stop All RCPs 21 Check Core Cooling: Return to Step 17.

o RVLIS level (no RCPs) - GREATER THAN 77% [82% adverse CNMT]

o Both RCS hot leg temperatures LESS THAN 320°F 22 Go to Appropriate Plant Procedure

a. Check RWST level GREATER THAN a. Go to ES-1.3. TRANSFER TO COLD 28% LEG RECIRCULATION, Step 1.

b. Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 17 END -

EOP: TITLE:

REV: 16 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 1 of 1 FR-C.2 APPENDIX LIST TITLE

1) ATTACHMENT RCP START (ATT- 15.0)

EOP: TITLE: REV: 26 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 1 of 30 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER_ _ _

RESPONS IBL%1ANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE: REV: 26 FR-H.I RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 2 of 30 A. PURPOSE - This procedure provides actions for responding to a loss of secondary heat sink in both S/Gs.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-0, REACTOR TRIP OR SAFETY INJECTION, when minimum AFW flow is not verified AND normal range level in both S/Gs is less than 5% [25% adverse CNMT]

b. F-0.3, HEAT SINK Critical Safety Function Status Tree on a RED condition.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED J

• ~~~ ~~~~~~ . . . . . . . . . . . * . . * . . * . . * . . .

CAUTION "o IF TOTAL FEED FLOW IS LESS THAN 200 GPM DUE TO OPERATOR ACTION, THIS PROCEDURE SHOULD NOT BE PERFORMED.

"o FEED FLOW SHOULD NOT BE REESTABLISHED TO A FAULTED S/G IF A NON-FAULTED S/G IS AVAILABLE.

NOTE: 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 If Secondary Heat Sink Is Required:

a. RCS pressure GREATER THAN ANY a. IF RWST level greater than 28%,

NON-FAULTED S/G PRESSURE THEN return to procedure and step in effect.

IF RWST level less than 28%,

THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

This Step continued on the next page.

(Step 1 continued from previous page)

b. Check RCS cold leg temperature b. IF RCS pressure less than GREATER THAN 3500 F 400 psig [300 psig adverse CNMT], THEN try to place RHR System in service while continuing with this procedure:

1) Reset SI.

2) Place letdown pressure controller in MANUAL CLOSED.

3) Open the following valves (reset xy relays):

• AOV-371. letdown isolation valve e AOV-427. loop B cold leg to REGEN Hx

• At least one letdown orifice valve (AOV-200A, AOV-200B, or AOV-202)

4) IF pressure on PI-135 less than 400 psig. THEN establish RHR normal cooling (Refer to ATT-14.1, ATTACHMENT RHR COOL).

5) IF adequate cooling with RHR system established, THEN return to procedure and step in effect.

STEP* ACTION/EXPECTED RESONSEI RESPONSE NOT OBTAINEDI

• 2 Monitor Secondary Heat Sink: IF a loss of heat sink is indicated, THEN perform the "o Verify either S/G level WIDE following:

RANGE GREATER THAN 50 inches

[100 inches adverse CNMT] a. Trip both RCPs.

"o Verify PRZR pressure - LESS THAN b. Go to Step 13 to initiate bleed 2335 PSIG and feed cooling.

CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET. THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

3 Try to Establish AFW Flow To At Least One S/G:

a. Check S/G blowdown and samples a. Place S/G blowdown and sample valves CLOSED valve isolation switch to CLOSE.

b. Check MCB indications for cause of AFW failure:

1) Verify CST level - GREATER 1) Refer to ER-AFW.1, ALTERNATE THAN 5 FEET WATER SUPPLY TO AFW PUMPS.

2) Verify busses supplying power 2) Continue attempts to restore to MDAFW pumps ENERGIZED power to MDAFW pumps.

a Bus 14

• Bus 16

3) Determine AFW flow requirements per ATT-22.0.

ATTACHMENT RESTORING FEED FLOW

4) Check AFW valve alignment 4) Dispatch AO to locally align valves.

o AFW pump discharge valves OPEN

"*MOV-4007

"*MOV-4008

"*MOV-3996 o TDAFW pump flow control valves - OPEN

"*AOV-4297

"* AOV-4298 This Step continued on the next page.

EOP: TITLE:

REV: 26 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 7 of 30 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 3 continued from previous page)

c. Check AFW pumps ALL RUNNING c. Perform the following:

1) Manually start MDAFW pumps.

2) Check TDAFW pump steam supply valves OPEN.

e MOV-3504A e MOV-3505A

3) If necessary dispatch AO to locally reset TDAFW pump governor valve.

4) IF NO AFW pumps operable, THEN go to Step 4.

d. Control AFW flow per requirements of ATT-22.0, ATTACHMENT RESTORING FEED FLOW

e. Check total flow to S/Gs e. Continue attempts to restore AFW GREATER THAN 200 GPM flow and go to Step 4.

f. Return to procedure and step in effect 4 Stop Both RCPs 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) 5 Reset SI If Actuated

EOP: TITLE:

REV: 26 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 8 of 30 STE ACTION/EXPECTED RESPONSEl RESPONSE NOT OBTAINEDl 6 Try To Establish MFW Flow To At Least One S/G:

a. Check any MFW pump - AVAILABLE a. Go to Step 7.

b. Check condensate system: b. IF offsite power available. THEN try to place condensate system "o Condensate pump - ANY RUNNING in service.

"o MFW pump suction pressure IF NOT, THEN go to Step 7.

GREATER THAN 185 PSIG

c. Establish MFW flow: c. IF MFW flow can NOT be established, THEN go to Step 7.

1) Check MFW pump discharge valves CLOSED

2) Verify MFW regulating or bypass valves OPERABLE

3) Place A and B MFW regulating valve and bypass valve controllers in MANUAL at 0%

demand.

4) Dispatch AO to restore MFW pump SW cooling

5) Verify SIG blowdown key switches in NORMAL

6) Ensure Annunciator H-4,MAIN FEED PUMP OIL SYSTEM EXTINGUISHED

7) Close Condensate Bypass valve, AOV-3959.

8) Ensure Annunciator H-I1, FEED PUMP SEAL WATER LO DIFF PRESS 15 PSI EXTINGUISHED

9) Ensure one MFW pump recirc valve - OPEN

10) Start selected MFW pump This Step continued on the next page.

EOP: TITLE: REV: 26 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 9 of 30 STE ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDi (Step 6 continued from previous page)

11) Open MFW pump discharge valve

12) Adjust MFW regulating or bypass valves to control MFW flow per requirements of ATT-22.0, ATTACHMENT RESTORING FEED FLOW

d. Go to Step 11 7 Establish SAFW Flow:

a. Perform the following: a. IF greater than 200 gpm total SAFW flow can NOT be

1) Align SAFW system for established, THEN go to Step 8.

operation (Refer to ATT-5.1.

ATTACHMENT SAFW)

2) Determine SAFW flow requirements per ATT-22.0, ATTACHMENT RESTORING FEED FLOW

3) Start both SAFW pumps

4) Control SAFW flow per requirements of ATT-22.0, ATTACHMENT RESTORING FEED FLOW

5) Verify SAFW total flow GREATER THAN 200 GPM

b. Go to Step 11

SACTIONIEXPECTED RESPONSE1 RESPONS NOT OBTAINED CAUTION IF WIDE RANGE LEVEL IN BOTH S/GS DECREASES TO LESS THAN 50 INCHES [100 INCHES ADVERSE CNMT] OR IF PRZR PRESSURE INCREASES TO GREATER THAN 2335 PSIG DUE TO LOSS OF HEAT SINK, THEN STEPS 13 THROUGH 15 SHOULD BE IMMEDIATELY INITIATED FOR BLEED AND FEED.

8 Establish Conditions to Feed S/G(s) From Condensate System:

a. Check condensate pumps - ANY a. IF offsite power available, THEN RUNNING manually start at least one condensate pump. IF a condensate pump can NOT be started, THEN go to Step 12.

b. Establish condensate flowpath (Refer to ATT-5.0, ATTACHMENT COND TO S/G)

c. De-energize PRZR heaters 9 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 10.

"o Annunciator G-15, STEAM DUMP ARMED - LIT

b. Adjust condenser steam dump controller HC-484 to highest S/G pressure

c. Verify condenser steam dump controller HC-484 in AUTO

d. Place steam dump mode selector switch to MANUAL

EOP: TITLE: REV: 26 FR-H.l RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 11 of STEP ACTION/EXPECTED RESPONSE' . RESPONSE NOT OBTAINED[

CAUTION FOLLOWING BLOCK OF AUTOMATIC SI ACTUATION, MANUAL SI ACTUATION MAY BE REQUIRED IF CONDITIONS DEGRADE.

• r

• dr . * . * . * * *r . * * * * * * * * * * * * *r * * * * * * * * * * *r * *r *r

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

10 Establish Condensate Flow to S/G:

a. Check RCS pressure - GREATER a. Go to Step 10c.

THAN 1950 PSIG

b. Depressurize RCS to less than 1950 psig:

1) Check letdown IN SERVICE 1) Use one PRZR PORV. IF IA to CNMT, AOV-5392, NOT open, THEN refer to ATT-12.0.

ATTACHMENT N2 PORVS.

a) IF PORV NOT available, THEN use auxiliary spray valve, AOV-296 and go to step 10c.

2) Depressurize using auxiliary 2) Use one PRZR PORV. IF IA to spray valve (AOV-296) CNMT. AOV-5392, NOT open, THEN refer to ATT-12.0, ATTACHMENT N2 PORVS.

c. WHEN PRZR pressure less than 1950 psig, THEN place SI block switches to BLOCK

• Train A

• Train B

d. Verify SAFETY INJECTION BLOCKED status light LIT This Step continued on the next page.

EOP: TITLE: REV: 26 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 12 of 30

• STEPH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI (Step 10 continued from previous page)

e. Stop depressurizing RCS and maintain RCS pressure less than 1950 psig

f. Manually adjust MFW regulating or bypass valves to control feed flow per requirements of ATT-22.0, ATTACHMENT RESTORING FEED FLOW

g. Dump steam to condenser at g. Manually or locally dump steam maximum rate to depressurize at using intact SIG ARV at maximum least one S/G to less than rate to depressurize at least 380 psig one SIG to less than 380 psig.

h. Verify condensate flow to S/Gs h. Go to Step 12.

11 Check S/G Levels:

a. Narrow range level in at least a. IF feed flow verified and level one S/G - GREATER THAN 5% [25% increasing in at least one S/G, adverse CNMT] THEN maintain flow to restore narrow range level greater than 5% [25% adverse CNMT]. IF NOT verified. THEN go to Step 12.

b. Return to procedure and step in effect 12 Verify Secondary Heat Sink:

a. Check the following: a. IF loss of heat sink is indicated, THEN perform the "o Either S/G level WIDE RANGE following:

GREATER THAN 50 inches

[100 inches adverse CNMT] 1) Go to Step 13 to initiate bleed and feed cooling.

"o PRZR pressure - LESS THAN 2335 PSIG

b. Return to Step 1

STEP ACTION/EXPECTED RESPONSE NOT OBTAINEDI CAUTION STEPS 13 THROUGH 15 MUST BE PERFORMED QUICKLY IN ORDER TO ESTABLISH RCS HEAT REMOVAL BY RCS BLEED AND FEED.

13 Actuate SI and CI 14 Verify RCS Feed Path: Manually start pumps and align valves as necessary to establish

a. Check SI pumps - AT LEAST ONE RCS feed path.

RUNNING IF a feed path can NOT be

b. Check valve alignment for established, THEN continue attempts operating SI pumps PROPER to establish feed flow. Return to EMERGENCY ALIGNMENT Step 3.

STEP ACTION/EXPECTED RESPONSEI 1 RESPONSE NOT OBTAINED 15 Establish RCS Bleed Path:

a. Open both PRZR PORV block valves a. Ensure power to MCCs supplying block valves.

• MCC D for MOV-515 e MCC C for MOV-516 IF any block valve can NOT be opened, THEN dispatch AO to locally check breaker:

e MOV-515, MCC D position 6C e MOV-516. MCC C position 6C

b. Place both PRZR PORV switches to OPEN

c. Align RCS overpressure protection system to open both PRZR PORVs (Refer to ATT-12.0, ATTACHMENT N2 PORVS)

d. Verify PORVs - BOTH OPEN d. IF BOTH PRZR PORVs can NOT be opened, THEN ensure both PORV switches in OPEN.

EOP: TITLE:

REV: 26 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 15 of 3 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) 16 Check If SI Can Be Reset:

a. Check SI blocked status light a. Place SI block switches to EXTINGUISHED UNBLOCK

b. Check the following: b. IF PRZR pressure stable or increasing, THEN reset SI and go "o PRZR pressure - LESS THAN to Step 17.

1750 PSIG IF PRZR pressure decreasing,

-OR THEN perform the following:

"o Either steamline pressure 1) WHEN PRZR pressure less than LESS THAN 514 PSIG 1750 psig, THEN reset SI.

2) Go to Step 17.

c. Reset SI 17 Reset CI:

a. Depress CI reset pushbutton

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

CONTAINMENT ISOLATION EXTINGUISHED 1) Reset SI.

2) Depress CI reset pushbutton

EOP: TITLE: REV: 26 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 16 of 30 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify Adequate SW Flow:

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 21.

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

valves - AT LEAST ONE SET OPEN

• MOV-4615 and MOV-4734

• MOV-4616 and MOV-4735

EOP: TITLE: REV: 26 FR-H.I RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 17 of 30 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

19 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

• 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 ATT-4.0, ATTACHMENT CNMT RECIRC FANS).

3) Start HP seal oil backup pump.

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

b. Verify turbine building SW b. Manually align valves.

isolation valves - OPEN

• MOV-4613 and MOV-4670 e 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 21. WHEN IA restored, THEN do Steps 19e, f and 20.

e. Reset both trains of XY relays for IA to CNMT AOV-5392 f.**Verify IA to CNMT AOV-5392 - OPEN f. Continue with Step 21. WHEN IA restored to CNMT, THEN do Step 20.

STEP 1 ACTION/EXPECTED RESPONSE1 RESPONSE NOT OBTAINED[

NOTE: PRZR PORVs may close temporarily until adequate IA pressure is restored in CNMT.

20 Restore RCS Overpressure Protection System To Standby:

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. Place PORV PCV-430 and PCV-431C I N2 arming switches to BLOCK

• SOV-8619A

• SOV-8619B

c. Close PORV PCV-430 and PCV-431C I N2 SURGE TK VLVs I

• SOV-8616A a SOV 8616B

SE ACTION/EXPECTED RSPNS RESPONSE NOT OBTAINEDI 21 Verify Adequate RCS Bleed Perform the following:

Path:

a. Open Rx head vent valves.

o Core exit T/Cs - STABLE OR DECREASING "* SOV-590

"* SOV-591 o RVLIS Level (no RCPs) - GREATER "* SOV-592 THAN 77% [82% adverse CNMT] "* SOV-593

b. Align any available low pressure water source to intact S/Gs.

IF no low pressure water source can be aligned, THEN go to Step 22.

c. Depressurize at least one intact S/G to atmospheric pressure using S/G ARV.

CAUTION ACTIONS TAKEN TO INITIATE RCS BLEED AND FEED SHALL NOT BE REVERSED WHEN PERFORMING STEPS I THROUGH 12 OF E-0, REACTOR TRIP OR SAFETY INJECTION.

22 Complete Steps 1 through 12 Of E-0, REACTOR TRIP OR SAFETY INJECTION, While Continuing With This Procedure

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION THE RCS BLEED PATH MUST BE MAINTAINED EVEN IF RCS PRESSURE REMAINS GREATER THAN SI PUMP SHUTOFF HEAD.

23 Maintain RCS Heat Removal:

"o Maintain SI flow "o Maintain both PRZR PORVs and block valves - OPEN 24 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).

"o Bus 14 normal feed breaker CLOSED IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer "o Bus 16 normal feed breaker to ATT-4.0, ATTACHMENT CNMT RECIRC CLOSED FANS).

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

25 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 locally 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. 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 to establish maximum charging flow

STEP 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 STEPS 1 THROUGH 14 OF ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.

"o IF CONTAINMENT PRESSURE INCREASES TO GREATER THAN 28 PSIG, CONTAINMENT SPRAY SHOULD BE VERIFIED.

"o RHR PUMPS SHOULD NOT BE RUN LONGER THAN 1 HOUR WITHOUT CCW TO THE RHR HEAT EXCHANGERS.

• 26 Monitor If CNMT Spray Should Be Stopped:

a. CNMT spray pumps RUNNING a. Go to Step 27.

b. Check the following: b. Continue with Step 27. WHEN BOTH conditions satisfied, THEN do "o CNMT pressure LESS THAN Steps 26c through 26f.

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

EOP: TITLE:

REV: 26 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 23 of 30 SACTION/EXPECTED RESPONSE

... RESPONSE NOT OBTAINED 27 Continue Attempts To Establish Secondary Heat Sink In At Least One S/G:

a. Attempt to restore one or more of the following:

"* AFW flow

"* Main FW flow

• Standby AFW flow

• Condensate flow

b. WHEN a feed source is available, THEN control feed flow per requirements of ATT-22.0, ATTACHMENT RESTORING FEED FLOW 28 Check For Adequate Secondary Heat Sink:

a. Check narrow range level in at a. Return to Step 27.

least one SIG - GREATER THAN 5%

[25% adverse CNMT]

b. Adjust S/G ARV controllers to existing S/G pressure CAUTION IF THE RCS IS WATER SOLID, THEN ANY INCREASE IN RCS TEMPERATURE MAY RESULT IN A SIGNIFICANT RCS PRESSURE INCREASE. RCS HEATUP SHOULD BE PREVENTED.

29 Monitor RCS Temperatures: Perform the following:

o Core exit T/Cs - DECREASING a. Control steam dump and feed flow to establish natural circulation o RCS hot leg temperatures and stabilize RCS temperature.

"DECREASING

b. Return to Step 27.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Check CCW Pumps - ANY RUNNING Perform the following:

a. 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

b. Manually start one CCW pump (122 kw).

CAUTION IF RCS IS SOLID, CLOSURE OF HEAD VENTS MAY RESULT IN RAPID RCS PRESSURE INCREASE UNLESS RCS TEMPERATURE AND RCS INFLOW AND OUTFLOW ARE CAREFULLY CONTROLLED.

31 Verify Reactor Head Vent Manually close valves.

Valves - CLOSED

• SOV-590

• SOV-591 e SOV 592 e SOV-593

EOP: TITLE: REV: 26 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 25 of 30 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI CAUTION IF RCS IS SOLID, THEN TERMINATION OF BLEED AND FEED MAY RESULT IN RAPID RCS PRESSURE INCREASE UNLESS RCS TEMPERATURE AND RCS INFLOW AND OUTFLOW ARE CAREFULLY CONTROLLED.

32 Check If One Of Three SI Pumps Should Be Stopped:

a. Three SI pumps - RUNNING a. Go to Step 33.

b. RCS subcooling based on core b. Check the following:

exit T/Cs GREATER THAN 35°F

[90'F adverse CNMT] USING "o RCS pressure greater than FIG-1.0, FIGURE MIN SUBCOOLING 1625 psig [1825 psig adverse CNMT]

"o RCS subcooling based on core exit T/Cs greater than 0°F using FIG-1.0, FIGURE MIN SUBCOOLING IF NOT, THEN go to Step 35.

c. Check PRZR level - GREATER THAN c. Do NOT stop SI pump. Go to 13% [40% adverse CNMT] Step 35.

d. Stop one SI pump

LOP: TITLE: REV 2 6 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 26 of 30 STEP ACTION/EXPECTED RES PON RESPONSE NOT OBTAINED 33 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps - RUNNING a. Go to Step 34.

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 100'F [175°F adverse CNMT]

c. RCS subcooling based on core c. Check the following:

exit T/Cs GREATER THAN VALUE FROM TABLE ABOVE USING FIG-1.0. "o RCS pressure greater than FIGURE MIN SUBCOOLING 1625 psig [1825 psig adverse CNMT]

"o RCS subcooling based on core exit T/Cs greater than 0°F using FIG-1.0. FIGURE MIN SUBCOOLING IF NOT. THEN go to Step 35.

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

[40% adverse CNMT] Step 35.

e. Stop one SI pump

• TEH CTON/ EXPECTED RESPONSEI RESPONSE NOT OBTAINED1[ý[

34 Check If Last SI Pump Should Be Stopped:

a. One SI pump - RUNNING a. Go to Step 37.

b. Check the following: b. Go to Step 35.

" RCS subcooling based on core exit T/Cs greater than 0°F using FIG-1.0, FIGURE MIN SUBCOOLING "o RCS pressure greater than 1625 psig [1825 psig adverse CNMT]

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

[40% adverse CNMT] Step 35.

d. Stop running SI pump

e. Go to Step 37 NOTE: After closing a PORV, it may be necessary to wait for RCS pressure to increase to permit stopping SI pumps in SI reduction steps.

35 Check PRZR PORVs And Go to appropriate plant procedure:

Associated Block Valves - ANY BLEED PATH OPEN "o IF RWST level greater than 28%,

THEN go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

-OR "o IF RWST level less than 28%,

THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.

-TE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

CAUTION IF RCS IS SOLID, CLOSURE OF PORVS WILL RESULT IN RAPID RCS PRESSURE INCREASE UNLESS RCS TEMPERATURE AND RCS INFLOW AND OUTFLOW ARE CAREFULLY CONTROLLED.

36 Isolate PRZR Bleed Paths:

a. PRZR PORVs BOTH OPEN a. Perform the following:

1) Stop all but one charging pump.

2) Control charging flow as necessary to maintain RCS pressure and PRZR level.

3) Establish excess letdown as follows:

a) Place AOV-312 to NORMAL.

b) Ensure CCW pump running.

c) Manually open CCW from excess letdown Hx open (AOV-745).

d) Ensure excess letdown flow control valve, HCV-123 is closed, demand at 0.

e) Reset both trains of XY relays for MOV-313.

f) Open MOV-313.

g) Open excess letdown isolation valve AOV-310.

h) Slowly open HCV-123.

This Step continued on the next page.

EOP: TITLE:

REV: 26 FR-H.I RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 29 of 30 P ACTIO/ EXPECTD RESPONSEd ESPONSE NOT O TAINEDg (Step 36 continued from previous page)

b. Close one open PRZR PORV b. Close PORV block valve. IF block valve can NOT be closed, THEN go to appropriate plant procedure:

"o IF RWST level greater than 28%. THEN go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

-OR "o IF RWST level less than 28%,

THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.

c. Return to Step 32 37 Check PRZR PORVs - BOTH CLOSED Close both PRZR PORVs. IF any PRZR PORV can NOT be closed, THEN manually close its block valve.

38 Check If RHR Pumps Should Be Stopped:

a. RHR pumps ANY RUNNING IN a. Go to Step 39.

INJECTION MODE

b. Check RCS pressure: b. Go to appropriate plant procedure:

1) Pressure - GREATER THAN 250 psig [465 psig adverse "o IF RWST level greater than CNMT] 28%, THEN go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT,

2) Pressure - STABLE OR Step 1.

INCREASING OR "o IF RWST level less than 28%,

THEN go to ES-I.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

c. Stop RHR pumps and place in AUTO

STEPH ACTION/EXPECTED RSPONSE RESPONSE NOT OBTAINEDt 39 Start Charging Pumps As Necessary And Control Charging Flow To Maintain PRZR Level 40 Go To ES-1.1, SI TERMINATION, Step 8

-END-

Eop: TITLE:

REV: 26 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 1 of 1 FR-H.1 APPENDIX LIST TITLE I) FIGURE MIN SUBCOOLING (FIG-1.0)

2) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)

3) ATTACHMENT COND TO S/G (ATT-5.0)

4) ATTACHMENT N2 PORVS (ATT*12.0)

5) ATTACHMENT RHR COOL (ATT-14.1)

6) ATTACHMENT SAFW (ATT-5.1)

7) ATTACHMENT RESTORING FEED FLOW (ATT-22.0)

8) ATTACHMENT NO SW PUMPS (ATT -2.4)

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

EOP: TITLE: REV: 14 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 13 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER_ _ _

RESPONSIBL %MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides actions to add negative reactivity to a core which is observed to be critical when expected to be shut down.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-0, REACTOR TRIP OR SAFETY INJECTION, when reactor trip is not verified and manual trip is not effective.

b. F-0.1, SUBCRITICALITY, Critical Safety Function Status Tree on either a RED or ORANGE condition.

EOP: TITLE: REV: 14 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 3 of 13 SE ACTION/EXPECTED RESPONSEI RESPONS NOT OBTAINEDI NOTE: Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

Manually trip reactor.

o Verify Reactor Trip:

IF reactor trip breakers NOT open, "o At least one train of reactor trip breakers OPEN THEN manually insert control rods.

"o Neutron flux DECREASING "o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Manually trip turbine.

SVerify CLOSED Turbine Stop Valves IF turbine trip can NOT be verified, THEN close both MSIVs.

0 Check AFW Pumps Running:

a. MDAFW pumps RUNNING a. Manually start MDAFW pumps.

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

"* MOV-3505A

"* MOV-3504A

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDi CAUTION ACTIONS TAKEN TO INITIATE RCS BORATION SHALL NOT BE REVERSED WHEN PERFORMING STEPS 1 THROUGH 12 OF E-0, REACTOR TRIP OR SAFETY INJECTION.

NOTE: If offsite power is lost coincident with SI, then MCC C and MCC D lockout relays must be reset to restore BA and RMW pumps.

4 Initiate Emergency Boration Of RCS:

a. Check SI status: a. Perform the following:

o All SI annunciators 1) Complete steps 1 through 12 EXTINGUISHED of E-0, REACTOR TRIP OR SAFETY INJECTION, while o All SI pumps - OFF IN AUTO continuing with this procedure

2) IF SI flow indicated, THEN go to Step 5. IF NOT, THEN go to Step 4b.

b. Verify at least one charging b. Perform the following:

pump RUNNING

1) Reset SI if necessary.

2) Start one charging pump.

c. Align boration path: c. Initiate normal boration at maximum rate using the boric

1) Start two BA transfer pumps acid flow control valve, FCV-IIOA. IF flow can NOT be

2) Open MOV-350 established. THEN refer to ER-CVCS.I, REACTOR MAKEUP

3) Verify BA flow CONTROL MALFUNCTION.

d. Verify charging flow path: d. Manually align valves and verify flow.

o Charging valve to loop B cold leg (AOV-294) OPEN o Charging flow control valve (HCV-142) DEMAND AT 0%

EOP: TITLE:

REV: 14 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 5 of 13 STEP ACTION/E.XPECTED RESPONSEI RESPONSE NOT OBTAINED I NOT OBTAINED H-I RESPONSE 5 Check PRZR PORV Status:

a. RCS pressure LESS THAN a. Verify PRZR PORVs and block 2335 PSIG valves open. IF NOT, THEN open PRZR PORVs and block valves as necessary until PRZR pressure less than 2335 psig.

b. Check PORVs BOTH CLOSED b. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.

IF any PORV can NOT be closed, THEN manually close its block valve. IF block valve can NOT be closed, THEN dispatch AO to locally check breaker.

"*MOV-515, MCC D position 6C

"*MOV-516, MCC C position 6C 6 Verify CNMT Ventilation Isolation

a. CVI annunciator LIT a. Momentarily deenergize CNMT particulate monitor, R-11, to

• Annunciator A-25, CNMT actuate CVI.

VENTILATION ISOLATION

b. Verify CVI valve status lights b. Manually close CVI valves as BRIGHT required IF valves can NOT be verified closed by MCB indication, THEN dispatch AO to locally close valves (Refer to Attachment CI/CVI FOR ALTERNATE ISOLATION VALVES).

LOP: TITLE: REV: 14 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 6 of 13 SE ACTION/EXPECTED RESPONSE[ RESPONSE NOT OBTAINEDI 7 Check If The Following Trips Have Occurred:

a. Reactor trip a. Dispatch AO to locally trip reactor:

o Trip MG set breakers at bus 13 and bus 15.

-OR o Open reactor trip breakers locally.

b. Turbine trip b. Dispatch AO to locally trip turbine using manual trip lever on west end of HP turbine.

EOP: TITLE: REV: 14 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 7 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED!

CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET. THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

• 8 Monitor S/G Level:

a. Narrow range level in at least a. Perform the following:

one S/G - GREATER THAN 5% [25%

adverse CNMT] 1) Verify total feed flow greater than 400 gpm.

IF NOT. THEN manually start pumps and align valves as necessary.

IF AFW can NOT be established, THEN establish SAFW (Refer to ATT-5.1, ATTACHMENT SAFW)

2) Maintain total feed flow greater than 400 gpm until narrow range level greater than 5% [25% adverse CNMT] in at least one S/G.

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

STEPH ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 9 Verify Dilution Paths ISOLATED

a. Place RMW mode switch to BORATE

b. Stop RMW pumps b. Perform the following: I

1) Close RMW to blender (AOV-111)1

2) Direct AO to locally open RMW pump breaker I e RMW Pump A, MCC C Pos 13B e RMW Pump B. MCC D Pos 1B I 10 Stabilize RCS Temperature:

a. Control steam dump as necessary

b. Verify the following: b. IF RCS cooldown can NOT be controlled, THEN close both "o Core exit T/Cs STABLE OR MSIVs and go to Step 11.

INCREASING "o Pressure in both S/Gs STABLE OR INCREASING "o Pressure in both S/Gs GREATER THAN 110 PSIG

c. Go to Step 15

SSTEPH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[

11 Verify MFW Isolation:

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

b. Place A and B S/G MFW regulating valve and bypass valve controllers to MANUAL at 0%

demand.

12 Identify Faulted S/G: Go to Step 15.

"o Any SIG Pressure DECREASING IN AN UNCONTROLLED MANNER

-OR "o Any S/G Pressure LESS THAN 110 PSIG

EoP: TITLE: REV:14 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 10 of 13 CAUTION o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.

o IF BOTH S/GS ARE FAULTED, AT LEAST 50 GPM FEED FLOW SHOULD BE MAINTAINED TO EACH S/G.

13 Isolate Feed Flow To Faulted Manually close valves.

S/G:

IF valves can NOT be closed, THEN "o Close faulted S/G MDAFW pump dispatch AO to locally isolate discharge valve flowpaths as necessary.

o SIG A, MOV-4007

• S/G B, MOV-4008 "o Pull stop faulted S/G MDAFW pump "o Close faulted S/G TDAFW flow control valve

"* SIG A, AOV-4297

"* S/G B, AOV-4298 "o Verify faulted S/G MFW regulating valve and bypass valve - CLOSED

• S/G A. HCV-466 and HCV-480

• S/G B, HCV-476 and HCV-481 "o Verify MDAFW pump crosstie valves BOTH CLOSED

"*MOV-4000A

"*MOV-4000B 0 Close faulted S/G SAFW pump discharge valve 0 S/G A, MOV-9701A o S/G B, MOV-9701B

SACTION/EXPECTED Rl flONSE RESP0 SE NOT 0BTAIN E

ýý-

CAUTION IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, THEN STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE SIG.

14 Isolate Steam Flow From Manually close valves.

Faulted S/G:

IF valves can NOT be closed, THEN "o Verify faulted S/G ARV CLOSED dispatch AO to locally isolate flowpaths as necessary.

e SIG A, AOV-3411

• S/G B, AOV-3410 "o Close faulted S/G TDAFW pump steam supply valve and place in PULL STOP

• S/G A, MOV-3505A S/G B, MOV-3504A S

"o Verify faulted S/G blowdown and sample valves CLOSED

• S/G A, AOV-5738 and AOV-5735 S I/G B, AOV-5737 and AOV-5736 "o Dispatch AO to complete faulted S/G isolation (Refer to Attachment FAULTED S/G)

EOP: TITLE:

REV: 14 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 12 of 13 flSTEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED 15 Check Core Exit T/Cs - LESS IF core exit temperatures greater THAN 12000F than 1200°F and increasing, THEN go to SACRG-1, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE, step 1.

NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

16 Verify Reactor Subcritical: Perform the following:

o Power range channels - LESS THAN a. Stabilize RCS temperature.

5%

b. Continue to inject boric acid.

o Intermediate range channels STABLE OR DECREASING c. Perform actions of other FR procedures in effect which do o Intermediate range channels NOT cooldown or otherwise add startup rate - NEGATIVE positive reactivity to the core.

o Core exit T/Cs - STABLE d. Direct RP to sample RCS and PRZR for boron concentration.

e. Verify boron concentration greater than Figure SDM.

IF adequate shutdown margin verified, THEN go to Step 17.

IF NOT, THEN perform the following:

a. Allow RCS to heat up.

b. Perform actions of other FR procedures in effect which do NOT cooldown or otherwise add positive reactivity to the core.

c. Return to Step 4.

EOP: TITLE:

REV: 14 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 13 of 13 I ..................................................... %

CAUTI ON BORATION SHOULD CONTINUE TO OBTAIN ADEQUATE SHUTDOWN MARGIN DURING SUBSEQUENT ACTIONS.

• S * *

• 17 Return to Procedure And Step In Effect

-END -

EOP: TITLE:

REV: 14 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 1 FR-S.1 APPENDIX LIST TITLE

1) FIGURE SDM (FIG-2.0)

2) ATTACHMENT FAULTED S/G (ATT-10.0)

3) ATTACHMENT CI/CVI (ATT-3.0)

4) ATTACHMENT SAFW (ATT-5.1)