ML17264A135

Rev 10 to ES-0.1, Reactor Trip Response.

ML17264A135
Person / Time
Site:	Ginna
Issue date:	08/09/1995
From:	White T ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264A134	List: ML17264A133 ML17264A135
References
PROC-950809, NUDOCS 9508150178
Download: ML17264A135 (101)

Text

EOP: T1TLE:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 1 of 19 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW RES N IBLE MANAGER P-O'-A EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

9508150178 950810 PDR ADOCK 05000244 F PDR

EOP: TITLE REV: 10 ES-F 1 REACTOR TRIP RESPONSE PAGE 2 of 19 A. PURPOSE This procedure provides the necessary instructions to stabilize and control the plant following a reactor trip without a safety injection.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS This procedure is entered from:

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

EOP: TITLE:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 3 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• • • • • • • • • • • x** x ***** x x CAUTION IF SI ACTUATION OCCURS DURING THIS PROCEDURE, THEN E-O, REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORMED.

• • • • • • • • • • • • • x****% ******************x x x

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

Critical Safety Function Status Trees should be monitored. (Refer l

to Appendix for Red Path Summary.)

• 1 Monitor RCS Tavg STABLE AT IF temperature less than 547'F and OR TRENDING TO 547'F decreasing, THEN perform the following:

a. Stop dumping steam.

b. Rotate reheater steam supply controller cam to close reheater steam supply valves.

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

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

e. IF cooldown continues, THEN close both MSIVs.

IF temperature greater than 547'F and increasing, THEN perform the following:

o Place condenser steam dump mode control to.MANUAL

-OR-o Manually dump steam using S/G ARVs.

EOP: T11'LE:

REV 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 4 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF A MFW PUMP IS LEFT RUNNING ON RECIRC FOR EXTENDED PERIODS OF TIME, OVERHEATING MAY OCCUR.

• • • • • • • x*% ***x********************x*x  % ***

2 Check S/G Feed Flow Status:

a. Check RCS Tavg - LESS THAN 554'F a. Continue with Step 3. WHEN temperature less than 554'F, THEN do Steps 2b, c, d and e.

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

~ MFW regulating valves demand.

~ MFW bypass valves

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

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

o Manually start TDAFW pump.

-OR-o Perform the following:

1) Establish MFW on bypass valves.

2) Go to step 3.

d. Close MFW pump discharge valves d. Manually stop MFW pumps.

~ MOV-3977, A MFW pump

~ MOV-3976, B MFW pump

e. Stop MFW pumps

EOP:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 5 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify MRPI ITIdicates ALL IF one or more control rods NOT CONTROL AND SHUTDOWN RODS ON fully inserted, THEN perform the BOTTOM following:

a. Place RMW mode selector switch to BORATE.

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

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

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

EOP: LITLE:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 6 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Verify All AC Busses Perform the following:

ENERGIZED BY OFFSITE POWER

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

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

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

OPEN

2) Close non-safeguards bus tie breakers:

~ Bus 13 to Bus 14 tie

~ Bus 15 to Bus 16 tie

3) Reset Bug 13 and Bus 15 lighting breakers,

4) Dispatch AO to locally reset and start two IA compressors.

5) Place the following pumps in PULL STOP' EH pumps

~ Turning gear oil pump

~ HP seal oil backup pump

6) Restore power to MCCs.

~ A from Bus 13

~ B from Bus 15

~ E from Bus 15

~ F from Bus 15

7) Start CNMT RECIRC fans as necessary.

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

EOP:

REV 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 7 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify At Least Two SW Pumps Manually start SW pumps as RUNNING necessary.

6 Verify IA Available: Dispatch AO to locally reset and start air compressors as necessary.

o At least 2 air compressors RUNNING IF IA pressure can NOT be maintained, THEN perform the o IA pressure - GREATER THAN following:

60 PSIG

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

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

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

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

EOP:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 8 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRZR Level Control:

a. Verify charging pumps - ANY a. Manually start charging pumps as RUNNING necessary.

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

1) Place loop B cold leg isolation valve to REGEN Hx (AOV-427) switch to close.

2) Verify excess letdown iso'lation valve (AOV-310) closed.

3) Ensure PRZR heaters off.

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

5) Continue with Step 8. WHEN PRZR level greater than 13%,

THEN do Steps 7c through e.

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

d. PRZR level - TRENDING TO 20% d. Control charging and letdown to maintain PRZR level at 20%.

e. Check PRZR heaters - ENERGIZED e. Reset PRZR heaters and energize AS NECESSARY as necessary to restore PRZR pressure.

o PRZR heater control group o PRZR heater backup group

EOP:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 9 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check PRZR Pressure Control:

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

1750 PSIG

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

2) Go to E-O, REACTOR TRIP OR SAFETY INJECTION, Step l.

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

1) Ensure PRZR PORVs closed.

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

~ PCV-430, MOV-516

~ PCV-431C, MOV-515

2) Ensure normal PRZR spray valve controller, demand at 0%.

3) IF PRZR pressure decreasing AND PRZR level increasing, THEN stop RCPs one at a time until PRZR pressure stabilizes.

4) Ensure PRZR heaters energized.

This Step continued on the next page.

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REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 10 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 8 continued from previous page)

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

1) Verify demand on PRZR pressure controller PCV-431 greater than 50$ . IF NOT, THEN place controller in MANUAL and increase as necessary.

2) Ensure PRZR heaters off.

3) Control pressure using normal PRZR spray.

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

a) Verify spray line fluid to PRZR hT less than 320'F.

IF NOT, THEN use one PORV.

b) IJse auxiliary spray.

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

EOP: TITLE:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 11 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• • • • • • • • • • • • • • x x***x****x*************

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).

• • • • • • • • • • • • • • • • 4 ************************

• 9 Monitor S/G Levels:

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

b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase, THEN stop and 39%. feed to that S/G.

10 Check Stopped:

If TDAFW Pump Can Be

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

b. PULL STOP TDAFW pump steam supply valves

~ MOV-3504A

~ MOV-3505A

EOP: 1' TLE:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 12 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ll Establish Condenser Steam Dump Pressure Control:

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

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

2) Go to Step lid.

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

c. Place steam dump mode selector switch to MANUAL

d. Verify RCS Tavg - STABLE AT OR d. Return to Step 1.

TRENDING TO 547'F 12 Check RCP Status AT LEAST Perform the following:

ONE RUNNING

a. Establish conditions for starting an RCP:

o Verify bus 11A or 11B energized.

o Refer to Attachment RCP START.

b. Start one RCP.

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

IF natural circulation NOT verified, THEN increase dumping steam.

EOP: TITLE:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 13 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE; Loss of forced air cooling may result in failure of NIS detectors.

13 Check If Source Detectors Should Range Be Energized:

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

DEENERGIZED

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

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

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

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

channels - LESS THAN 10 10 AMPS

-OR-o Greater than 20 minutes since reactor trip

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

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

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

EOP l TITLE:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 14 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Establish Normal Shutdown Alignment:

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

b. Perform the following:

o Open generator disconnects

~ 1G13A71

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

c. Verify adequate Rx head cooling:

1) Check IA to CNMT - AVAILABLE 1) Go to Step 15.

2) Verify at least one control 2) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw).

3) Verify one Rx compartment 3) Manually start one fan as cooling fan - RUNNING power supply permits (23 kw).

d. Dispatch AO to perform Attachment SD-1

EOP: TITLE:

REV: 10 ES-0 ' REACTOR TRIP RESPONSE PAGE 15 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Maintain Stable Plant Conditions:

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

b. PRZR level - BETWEEN 20% AND 30% b. Control charging as necessary.

c. S/G narrow range levels c. Control S/G feed flow as BETWEEN 17% AND 39% necessary.

d. RCS Tavg - GREATER THAN 540'F d. Control dumping steam as necessary. IF cooldown continues, THEN close both MSIVs.

16 Check VCT Makeup System:

a. Verify the following:

1) Adjust boric acid flow control valve to 9.5 gpm

2) RMW mode selector switch in AUTO

3) RMW control armed - RED LIGHT LIT

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

o Level - GREATER THAN 20%

1) Ensure BA transfer pumps and

-OR- RMW pumps running.

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

3) Increase boric acid flow as necessary.

EOP:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE 16 of

'AGE 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check Charging Pump Suction Aligned To VCT:

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

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

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

THEN do Step 17b.

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

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

EOP:

REV: 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 17 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify TDAFW Pump Aligned For AUTO Start:

a. Any MDAFW pump - AVAILABLE a. Verify TDAFW pump operating if necessary and go to Step 20.

b. Verify AMSAC TRIPPED status b. Reset AMSAC.

light - EXTINGUISHED

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

d. Verify the following:

1) TDAFW pump - OFF 1) IF TDAFW pump NOT required to maintain S/G level, THEN stop pump if desired.

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

EOP:

REV 10 ES-0.1 REACTOR TRIP RESPONSE PAGE 18 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Establish Normal AFW Pump Shutdown Alignment:

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

INCREASING o Total AFW flow - LESS THAN 200 GPM

b. Close MDAFW pump discharge valves

~ MOV-4007

~ MOV-4008

c. Place AFW bypass switches to DEF

d. Stop all but one MDAFW pump

e. Open AFW discharge crossover valves

~ MOV-4000A

~ MOV-4000B

f. Open AFW bypass valves as necessary to control S/G levels

~ AOV-4480

~ AOV-4481

EOP:

REV: 10 ES-O.l REACTOR TRIP RESPONSE PAGE 19 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Determine Required:

If Cooldown Is

a. Consult Plant staff to determine a. IF cooldown NOT required, THEN if RCS cooldown is necessary go to 0-3, HOT SHUTDOWN WITH XENON PRESENT.

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

') Ensure 2 control rod shroud fans running.

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

c. Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN

-END-

EOP:

REV: 10

. ES-0.1 REACTOR TRIP RESPONSE PAGE 1 of 1 ES-O.1 APPENDIX LIST TITLE PAGES

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING

3) ATTACHMENT LETDOWN

4) ATTACHMENT RCP START

5) ATTACHMENT NC

6) ATTACHMENT SD-1

7) ATTACHMENT SD-2

8) FOLDOUT

EOP:

REV: 10 ES-.O. 1 REACTOR TRIP RESPONSE 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 43% [46~

adverse CNMT]

c. HEAT SINK Narrow range level in all S/Gs less than 54

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

d. INTEGRITY Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F

e. CONTAINMENT CNMT pressure greater than 60 psig

EOP: TITLE:

REV 10 ES-.O. 1 REACTOR TRIP RESPONSE PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOLING 600 REGION ADVERS E CNNT 500 400 300 200 NORMAL CNNT TEMPERATURE INCREMENTS 10'F 100 0

20 0 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)

EOP:

REV: 10

, ES,M. 1 REACTOR TRIP RESPONSE PAGE 1 of 1 FOLDOUT PAGE NOTE The Critical Safety Function Red Path Summary is available in APPENDIX l.

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

o RCS subcooling based on core exit T/Cs LESS THAN O' USING FIGURE MIN SUBCOOLING OR o PRZR level LESS THAN 5% [30% adverse CNMT]

AND RCS subcooling based on core exit T/Cs LESS THAN 20'F USING FIGURE MIN SUBCOOLING OR o Any automatic SI setpoint is reached

2. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

EOP:

REV: 13 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 1 of 16 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER CN RESPONSIBLE AGER

/-43-0 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 13 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 2 of 16 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.

EOP:

REV 13 FR-C. 1 RESPONSE TO INADEQUATE CORE COOLING PAGE 3 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT values should be used whenever CNMT ~ressure is greater than 4 psig or CNMT radiation is greater than 10+ R/hr.

1 Check EST Level - GREATER Perform the following:

THAN 28%

a. Ensure SI system aligned for cold leg recirculation using Steps 1 through 12 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 Sucti.on

~

Aligned to EST:

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

0 Wlj \ ' k

FOP: T1TLF.:

REV: 13 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 4 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RHR PUMPS SHOULD NOT BE RUN LONGER THAN 1 HOUR WITHOUT CCW TO THE RHR HEAT EXCHANGERS.

E 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:

t

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

E \

EOP:

REV: 13 FR-C. 1 RESPONSE TO INADEQUATE CORE COOLING PAGE 5 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Verify SI Flow In Bath 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: Continue attempts to establish RCP support conditions.

a. Verify Bus 11A or llB - ENERGIZED

b. Check other RCP support conditions (Refer to Attachment 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

~ MOV-865; MCC D position 12C

b. Open SI ACCUM discharge valves.

~ ACCUM A) MOV-841

~ ACCUM B, MOV-865

EOP:

REV: 13 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 6 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check Core Exit T/Cs - LESS Go to Step 10.

THAN 1200'P 8 Check RVLIS Indi. cation:

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

b. RVLIS level - GREATER THAN 43% b. IF RVLIS increasing, THEN return

[46% 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 SELECTED SW PUMPS AND ONE CCW PUMP WILL AUTO START ON EMERGENCY D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

10 Reset SI

EOP:

REV: 13 FR-C. 1 RESPONSE TO INADEQUATE CORE COOLING PAGE 7 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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 should be THAN 0.5$ hydrogen recombiners placed in service.

I' 1 '\t e ~

EOP:

REV: 13 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 8 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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.1, 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.

• • • • • • • • • • • • • • • • • • • • • • 4 ******************

NOTE: TDAFW pump flow control valves fail 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:

REV 13 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 9 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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'ORV:

~ 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: T1TLEE REV'3 FR-C.1 RESPONSE TO INADEQUATE, CORE COOLING PAGE 10 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Estab19.sh Condenser Steam Dump Pressure Control:

a. Verify condenser available: a. Place intact S/G ARV controller in MAANUAL 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 S/G tubes is acceptable in the following steps.

16 Depressurize All Intact 8/Gs To 200 PSIG

a. Dump steam to condenser at a. Manually or locally dump steam maximum rate at maximum rate using S/G 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

EOP: TITLE:

REV: '13 FR-CD 1 RESPONSE TO INADEQUATE CORE COOLING PAGE 11 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check If SI Isolated:

ACCUMs Should Be

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

LESS THAN 400'F b.,Verify SI reset b, Manually reset SI.

c. Close SI ACCUM discharge 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 18 Stop Both RCPs 19 Dump Steam to Condenser At. Manually or locally dump steam at Maximum Rate To Depressurize maximum rate using S/G ARVs.

All Intact S/Gs To Atmospheric Pressure 20 Verify SI Plow: Perform the following:

' 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 g'o to Step 23.

EOP:

REV: 13 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 12 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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 cd Return to Step *19 THAN 68% [73% adverse CNMT]

'2 Go to Appropriate Plant Procedure

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

28'.

Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 18

't ~ I ' " '

a ~

EOP: T!TLE!

REV: 13 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 13 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Normal conditions are desired but not required for starting the RCPs.

23 Check Started:

If RCPs Should Be

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

1200'F

b. Check if an idle RCS cooling b. Perform t'e following:

loop is available

1) Open all PRZR PORVs and block o Narrow range S/G level- valves GREATER THAN 5% [25% adverse CNMT] IF any block valve can NOT be opened, THEN ensure power o RCP in associated loop- supplied to block valve.

AVAILABLEAND NOT OPERATING IF IA NOT available, THEN refer to Attachment N2 PORVS.

2) IF core exit'/Cs remain greater than 1200'F, THEN open Rx vessel head vent valves.

~ SOV-590

~ SOV-591

~ SOV-592

~ SOV-593

3) Go to. Step 24.

c. Start RCP in one idle RCS cooling loop

d. Return to Step 23a

EOP:

REV: 13 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 14 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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

~ S/G B, MOV-3504A

-OR-o Perform the following:

a. Open intact S/G MSIV bypass valves

b. Open both priming air ejector steam inlet valves

~ V-3580

~ V-3581 25 Check Isolated:

If SI ACCUMs Should Be

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

LEAST INTERMITTENT FLOW

b. Close SI ACCUM discharge valves b. 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.

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

II h

'I l r,

t

EOP. TITLE0 REV 13 FR-C. 1 RESPONSE TO INADEQUATE CORE COOLING PAGE 15 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check Zf RCPs Should Be Stopped:

a. Both RCS hot leg temperatures a. Go to Step 27.

LESS THAN 320'F

b. Stop all RCPs 27 Verify SI Plov: 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 28 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 68% c. Return to Step 23.

[73% adverse CNMT]

EOP:

REV: 13

,FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 16 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 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 l.

c. Go to E-l, LOSS OF REACTOR OR COOLANT, Step 18. 'ECONDARY

-END-

EOP:

REV: 13 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 1 of 1 FR-C.1 APPENDIX LIST TITLE PAGES

1) ATTACHMENT RCP START

2) ATTACHMENT N2 PORVS

EOP T1ILE0 RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P. 1, SHOCK CONDITION PAGE 1 of 21 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIB MANAGER

+-~+-v EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

0 EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV 16 FR-P.1 SHOCK CONDITION PAGE 2 of 21 A. PURPOSE This procedure provides actions to avoid, or limit, thermal shock or pressurized thermal shock to the reactor pressure vessel, or overpressure conditions at low temperature.

B. ENTRY CONDITIONS/SYMPTOMS

l. ENTRY CONDITIONS This procedure is entered from:

a. F-0.4, INTEGRITY Critical Safety Function Status Tree, on either a RED or ORANGE condition.

EOP: T1TLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV 16 FR-P. 1 SHOCK CONDITION PAGE 3 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF. CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN SWITCH TO ALTERNATE AFW WATER SUPPLY (REFER TO ER-AFW.l, ALTERNATE WATER SUPPLY TO THE AFW PUMPS).

NOTE: Adverse CNMT values should be used whenever CNMT ~ressure is greater than 4 psig or CNMT radiation is greater than 10+ R/hr.

1 Check RCS Pressure - GREATER IF RHR flow greater than 475 gpm, THAN 250 PSZG [465 PSIG THEN return to procedure and step adverse CNMT] in effect.

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV'6 FR-P. 1 SHOCK CONDITION PAGE 4 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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 S/G.

NOTE: A faulted S/G is any S/G that is depressurizing in an uncontrolled manner or is completely depressurized.

2 Check RCS Cold Leg Try to stop RCS cooldown:

Temperatures - STABLE OR INCREASING a. Ensure S/G ARVs closed.

b. Close both S/G MSIVs.

c. Ensure MFW flow control valves closed.

~ MFW regulating valves

~ MFW bypass valves

d. Ensure MFW pumps tripped.

e. Rotate reheater steam supply controller cam to close reheater steam supply valves.

f. IF S/G pressure less than condensate pressure, THEN stop all condensate pumps.

g. IF RHR system in service, THEN stop any cooldown from RHR system.

h. Control total feed flow to non-'faulted S/G(s) greater than 200 gpm until narrow range level greater than 5% [25% adverse CNMT] in at least one non-faulted S/G. WHEN S/G level greater than 5% [25% adverse CNMT] in one non-faulted S/G, THEN limit feed flow to stop RCS cooldown.

This Step continued on the next page.

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 5 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 2 continued from previous page)

i. Minimize cooldown from faulted S/G(s):

1) Close faulted S/G(s) TDAFV pump steam supply valve(s).

~ S/G A, MOV-3505A

~ S/G B, MOV-3504A

2) IF both S/G(s) faulted, THEN control feed flow at 50 gpm to each S/G.

3) IF any S/G NOT faulted, THEN isolate all feedwater to faulted S/G unless necessary for RCS temperature control.

IF a faulted S/G is necessary for RCS temperature control, THEN control feed flow at 50 gpm to that S/G.

3 Check PRZR PORV Block Valves:

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

IF at least one block valve can NOT be opened, THEN dispatch AO to locally check breaker.

~ MOV-515, MCC D position 6C

~ MOV-516, MCC C position 6C

~ ~

~ ~

EOP: 1'!TLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 6 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, THEN STEP 4 SHOULD BE PERFORMED AFTER PRESSURE DECREASES TO LESS THAN THE APPLICABLE PORV SETPOINT.

4 Check PRZR PORV Status:

a. Check Reactor Vessel a. Go to Step 4d.

Overpressure Protection System-IN SERVICE

b. Check RCS pressure - LESS THAN b.. Perform the following:

410 PSIG

1) Ensure at least one PRZR PORV open.

2) Continue with Step 5. WHEN pressure less than setpoint, THEN do Step 4e.

c. Go to Step 4e

d. PRZR pressure - LESS THAN d. Perform the following:

2335 PSIG

1) Ensure at least one PRZR PORV open.

2) Continue with Step 5. WHEN pressure less than setpoint, THEN do Step 4e.

e. Verify PRZR PORVs - CLOSED e. Manually close valve.

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

~

J EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 7 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check SI Pumps - ANY RUNNING Go to Step 13 ~

6 Check If SI Can Be Terminated: Perform the following:

o RCS subcooling based on core a. IF RCS subcooling based on core exit T/Cs - GREATER THAN 50'F exit T/Cs greater than O'F using USING FIGURE MIN SUBCOOLING Figure MIN SUBCOOLING and no RCP running, THEN attempt to start

o. Check RVLIS indication: an RCP:

o Level (no RCPs) - GREATER 1) Establish conditions for THAN 68% [73% adverse CNMT] starting an RCP:

-OR- o Bus 11A or 11B energized o Fluid fraction (any RCP o Refer to Attachment RCF running) - GREATER THAN 80% START

2) IF conditions established, THEN start one RCPT

b. Go to Step 26.

CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN SELECTED SW PUMPS AND ONE CCW PUMP WILL AUTO START ON EMERGENCY D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

7 Reset SI

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 8 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 8top 8I And RHR Pumps And Place In AUTO 9 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.

10 Verify Adequate SW Flow:

a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (258 kw each).

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

') Ensure SW isolation.

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

3) Go to Step 12. WHEN adequate SW available, THEN do Step 11.

b. Dispatch AO to establish normal=

shutdown alignment (Refer to Attachment SD-1)

I ~

EOP: T!TLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV 16 FR-P.1 SHOCK CONDITION PAGE 9 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Establish IA ta CNMT:

a. Verify non-safeguards busses a. Perform the following:

energized from offsite power

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR- ~ Bus 13 to Bus 14 tie

~ Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED

2) Verify adequate emergency D/G capacity to run air compressors (75 kw 'each).

IF NOT, THEN evaluate RECIRC fans should be if CNMT stopped (Refer to Attachment CNMT RECIRC FANS).

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

b. Verify SW isolation valves to b. Manually align turbine building - OPEN valves'.

~ MOV-4613 and MOV-4670

~ MOV-4614 and MOV-4664

c. Verify at least two air

- RUNNING Manually start air compressors compressors 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 12. WHEN IA restored, THEN do Steps lie and f.

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

f. Verify IA to CNMT AOV-5392 - OPEN

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 10 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 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 Cl 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 Oa.

b. Align charging pump suction to b. IF LCV-112B can NOT be opened, RWST: THEN perform the following:

o LCV-112B - OPEN 1) Verify charging pump A NOT running and place in PULL o LCV-112C - CLOSED STOP.

2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).

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

c. Start charging pumps as necessary to establish charging line flow to REGEN HX - GREATER THAN 20 GPM

~

p EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P. 1 SHOCK CONDITION PAGE 11 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• 13 Monitor SI Reinitiation Manually operate SI pumps as Criteria: necessary and perform the following:

o RCS subcooling based on core a. IF RCS subcooling based on core exit T/Cs - GREATER THAN FIGURE exit T/Cs greater than Figure MIN SUBCOOLING MIN SUBCOOLING and no RCP running, THEN attempt to start a o RVLIS indication: RCP:

o Level - GREATER THAN 68% [73% 1) Establish conditions for adverse CNMT] starting an RCP:

-OR- o Bus llA or 11B energized o Fluid fraction (any RCP o Refer to Attachment RCP running) - GREATER THAN 80% START

2) IF conditions established, THEN start one RCP.

b. Go to Step 26

'4 Check RCS Hot Leg IF increasing, THEN control feed Temperatures >> STABLE flow and dump steam to stabilize RCS hot leg temperatures.

IF decreasing, THEN verify that actions of Step 2 have been performed before continuing with procedure.

EOP: T!TLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 12 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Check If SI Isolated:

ACCUMs Should Be

a. Check the following'. a. Return to Step 13.

o RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o RVLIS indication:

o Level - GREATER THAN 68%

(73% adverse CNMTj

-OR-o Fluid fraction (any RCP running) - GREATER THAN 80%

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

~ MOV-841, MCC C position 12F

~ MOV-865, MCC D position 12C

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

+ MOV-841 1) Open vent valves for

~ MOV-865 unisolated SI ACCUMs.

~ ACCUM A, AOV-834A

~ ACCUM B, AOV-834B

2) Open HCV-945.

3) Continue with Step 16. Do NOT decrease RCS pressure to less than unisolated ACCUM pressure.

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

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV 16 FR-P.1 SHOCK CONDITION PAGE 13 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION THE RCS SHOULD NOT BE DEPRESSURIZED TO LESS THAN SI ACCUM PRESSURE UNTIL SI ACCUMS ISOLATED.

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

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

16 Depressurize RCS To Decrease RCS Subcooling:

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

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

b. Depressurize RCS until one of the following conditions satisfied:

o RCS subcooling based on core exit T/Cs - LESS THAN 10'F USING FIGURE MIN SUBCOOLING

-OR-o PRZR level - GREATER THAN 75%

{65% adverse CNMT]

-OR-o RCS pressure - LESS THAN 160 psig (200 psig adverse CNMT]

c. Stop RCS depressurization

TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV 16 FR-P. 1 SHOCK CONDITION PAGE 14 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• 17 Monitor RCP Operation:

a. RCPs - ANY RUNNING a. Go to Step 18.

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

o RCP ¹1 seal D/P - GREATER THAN 220 PSID o RCP ¹1 seal leakoff - WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF CAUTION AN INCREASE IN RCS PRESSURE MAY RESULT IN EXCESSIVE REACTOR VESSEL STRESS. RCS PRESSURE AND TEMPERATURE SHOULD BE MAINTAINED STABLE WHILE PERFORMING SUBSEQUENT STEPS IN THIS PROCEDURE.

I 18 Check PRZR Level - GREATER Try to restore level with charging THAN 13% [40% adverse CNMT] while maintaining stable RCS pressure. IF level can NOT be restored, THEN go to Step 25.

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 15 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Check Operation If Normal CVCS Can Be Established

a. Verify IA restored: a. Continue with Step 23. WHEN IA restored, THEN do Steps 19

, o IA to CNMT (AOV-5392) - OPEN through 22.

o IA pressure - GREATER THAN 60 PSIG

b. CCW pumps - ANY RUNNING b. Perform the following:

1) IF any RCP ¹1 seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected RCP(s).

~ RCP A, MOV-749A and MOV-759A

~ RCP B, MOV-749B and MOV-759B

2) Manually start one CCW pump.

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

1) Verify MCC A energized.

2) Place instrument bus D on maintenance supply.

d, Charging pump - ANY RUNNING d. Continue with Step 24. WHEN any charging pump running, THEN do Steps 20 through 24.

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P. 1 SHOCK CONDITION PAGE 16 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF RCS PRESSURE LESS THAN 250 PSIGI THEN PCV-135 SHOULD BE ADJUSTED TO ESTABLISH DESIRED LETDOWN FLOW, NOT TO INCREASE PRESSURE.

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

a. Establish charging line flow to letdown as follows:,

REGEN Hx - GREATER THAN 20 GPM o Place excess letdown divert be Place the following switches to valve, AOV-312, to NORMAL.

CLOSE:

o Ensure CCW from excess letdown

~ Letdown orifice valves open, (AOV-745).

(AOV-200A, AOV-200B, and AOV-202) o Open excess letdown isolation

~ AOV-371, letdown isolation valve AOV-310.

valve

~ AOV-427, loop B cold leg to o Slowly open HCV-123 to maintain REGEN Hx excess letdown temperature less than 195'F and pressure less

c. Place letdown controllers in than 100 psig.

MANUAL at 40% open o Adjust charging pump speed as

~ TCV-130 necessary.

~ PCV-135 IF RCP seal return NOT established,

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

e. Open AOV-371 and AOV-427

f. Open letdown orifice valves as necessary

g. Place TCV-130 in AUTO at 105 F

h. Place PCV-135 in AUTO at 250 psig Adjust charging pump speed and HCV-142 as necessary

TlTLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV 16 FR-P.1 SHOCK CONDITION PAGE 17 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check VCT Makeup System:

a, Adjust boric acid flow control valve in AUTO to 9.5 gpm b, Adjust RMW flow control valve in AUTO to 40 gpm

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

1) RMW mode selector switch in AUTO

2) RMW control armed - RED LIGHT LIT d, Check VCT level; d. Manually increase VCT makeup flow as follows:

o Level - GREATER THAN 20%

1) Ensure BA transfer pumps and

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

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

3) Increase boric acid flow as necessary.

TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 18 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

'2 Check Charging Pump Suction Aligned To VCT:

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

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

2) Continue wi'th Step 23. WHEN VCT level greater than 40%,

THEN do Step 22b.

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

o LCV-112C - OPEN o LCV-112B - CLOSED 23 Check PRZR Level - LESS THAN Control charging and letdown as 75% [65% adverse CNMT] necessary-to reduce PRZR level to less than 75% (65% adverse CNMT).

If necessary establish excess letdown.

IF no letdown available AND CCW to RCPs established, THEN cycle charging pumps as necessary to control PRZR level.

~ y 4 EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV'6 FR-P. 1 SHOCK CONDITION PAGE 19 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: For optimum long term pressure control, saturated conditions should be restored in the PRZR.

24 Verify PRZR Liquid - IF PRZR liquid temperature low, Temperature (TZ-424) AT THEN energize PRZR heaters as SATURATION FOR DESIRED necessary to establish desired PRESSURE temperature.

25 Check RCS Subcooling Based On IF RCS pressure less than 160 psig Core Exit T/Cs - LESS THAN [200 psig adverse CNMT], THEN go to 10'F USING FIGURE MZN Step 26. IF NOT, THEN depressurize SUBCOOLZNG using normal spray. Return to step 16b.

IF normal spray NOT available and letdown is in service, THEN use auxiliary spray for any further depressurization. Return to Step 16b.

IF auxiliary spray NOT available, THEN return to Step 16a.

26 Check Cool Down Rate In RCS Return to procedure and step in Cold Legs - GREATER THAN effect.

100'F ZN ANY 60 MINUTES PERIOD 27 Maintain RCS Pressure And Temperature Stable For At Least 1 Hour

a. Control steam dump and feed flow as necessary

b. Perform actions of other procedures in effect which do not cool down the RCS or increase RCS pressure until the RCS temperature soak has been completed

4 EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 20 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The following pressure, temperature and cooldown rate limits remain applicable in subsequent procedures.

28 WHEN 1 HOUR Soak Is Complete, THEN Continue RCS Cooldown And Depressurization As Necessary

a. Maintain RCS pressure -and cold leg temperature within the limits of Figure SOAK LIMITS

b. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 50'F IN ANY 60 MINUTES PERIOD 29 Verify SI Flow Not Required: Manually operate SI pumps as necessary.

o RCS subcooling based on core exit T/Cs - GREATER THAN FIGURE IF RCS subcooling based 'on core MIN SUBCOOLING exit T/Cs greater than Figure MIN SUBCOOLING and no RCP running, THEN o RVLIS indication: perform the following:

o Level - GREATER THAN 68% [73% a. Establish conditions for adverse CNMT] starting an RCP:

-OR- o Bus llA or 11B energized o Fluid fraction (any RCP o Refer to Attachment RCP START running) - GREATER THAN 80%

b. IF conditions established, THEN start one RCP.

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 21 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Return To Procedure And Step In Effect

-END-

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 1 of 1 FR-P. 1 APPENDIX LIST TITLE PAGES

1) FIGURE MIN SUBCOOLING

2) FIGURE SOAK LIMITS

3) FIGURE RCP SEAL LEAKOFF

4) ATTACHMENT RCP START

~

5) ATTACHMENT SD-1

6) ATTACHMENT CNMT RECIRC FANS

7) ATTACHMENT N2 PORVS

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P.1 SHOCK CONDITION PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RCS PRESSURE (PSIG) 2500 2400 2300 RCS PRESSURE INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED'EGION 1300 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOLING 600 REGION ADVERSE CNMT 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0

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

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV 16 FR-P. 1 SHOCK CONDITION PAGE 1 of 1 FIGURE SOAK LIMITS RCS PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 REMAIN 1300 BELOW 1200 CURVE 1100 1000 900 800 700 600 500 400 300 200 TEMPERATURE INCREMENTS 10'F 100 0

200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEMPERATURE ('F)

EOP: TITLE:

RESPONSE TO IMMINENT PRESSURIZED THERMAL REV: 16 FR-P. 1 SHOCK CONDITION PAGE 1 of 1 FIGURE RCP SEAL LEAKOFF

¹I SEAL'LEAK RATE (GPM) 6 LEAK RATE INCREMENTS 0.2 GPM NORMAL OPERATING RANGE DP INCREMENTS. 50 PSI 250 500 750 1000 1250 1500 1750 2000 2250 2500

¹1 SEAL DP (RCS PRESS - VCT PRESS) PSI

EOP I REV 10 FR-S ~ 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RE ONSIBLE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

REV: 10 FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 2 of 11 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-O, REACTOR TRIP OR SAFETY INJECTION, when reactor trip is not verified and manual trip is not effective.

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

EOP:

REV: 10 FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 3 of 11 STEP 'CTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: 'o Steps 1 through 3 are IMMEDIATE ACTION steps.

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

O Verify 1

o Reactor Trip:

At least one train of reactor Manually trip reactor.

IF reactor trip breakers NOT open, trip breakers - OPEN THEN manually insert control rods.

o Neutron flux - DECREASING o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM O Verify Turbine Stop Valves 2

CLOSED Manually trip turbine.

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

3 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

EOP: T1TLE:

REV 10 FR-S. l RESPONSE TO REACTOR RESTART/ASS PAGE 4 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION ACTIONS TAKEN TO INITIATE RCS BORATION SHALL NOT BE REVERSED WHEN PERFORMING STEPS 1 THROUGH 12 OF E-O, 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-O, 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 magimum rate using the boric

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

2) Open MOV-350 established, THEN refer to ER-CVCS.1, 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:

REV 10 FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 5 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check If The Following Have Occurred:

Trips

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

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

o Open reactor trip breakers locally.

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

6 Check PRZR PORV Status: Verify CNMT ventilation isolation.

IF dampers NOT closed, THEN o RCS pressure - LESS THAN momentarily deenergize CNMT 2335 PSIG particulate monitor, R-ll, to actuate CVI.

o PORVs - CLOSED o Annunciator F-19, PRZR PORV OUTLET HI TEMP - EXTINGUISHED

EOP: TITLE:

REV 10 FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION

'F 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).

7 Check S/G Level:

a. Narrow range level in at least 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.

2) Maintain total feed flow greater than 400 gpm until narrow range level greater than 5% [25% adverse CNMT) in 50%'.

b. Control feed flow to maintain at least one S/G.

narrow range level between 17%

[25% adverse CNMT] and 8 Verify Dilution Paths Manually isolate dilution paths.

ISOLATED o Place RMW 'mode switch to BORATE o Verify RMW to blender (HCV-111)

CLOSED o Verify RMW pumps - OFF

tl EOP:

REV 10 FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 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 10.

INCREASING o Pressure in both S/Gs STABLE OR INCREASING o Pressure in both S/Gs GREATER THAN 100 PSIG

c. Go to Step 14 10 Verify MFW Isolation:

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

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

~ MFW regulating valves controllers to MANUAL at 0%

~ MFW bypass valves demand.

11 Identify Faulted S/G: Go to Step 14.

o Any S/G Pressure - DECREASING IN AN,UNCONTROLLED MANNER

-OR-o Any S/G - COMPLETELY DEPRESSURIZED

l' EOP: TITLE:

REV 10 FR-S 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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.

12 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.

~ S/G 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

~ S/G 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 Close faulted S/G SAFW pump discharge valve

~ S/G A, MOV-9701A

~ S/G B, MOV-9701B

EOP:

REV: 10 FR-ST 1 RESPONSE TO REACTOR RESTART/ATNS PAGE 9 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 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.

~ S/G 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 o Verify faulted S/G blowdown and, sample valves - CLOSED

~ S/G A, AOV-5738 and AOV-5735

~ S/G B, AOV-5737 and AOV-5736 o Dispatch AO to complete faulted S/G isolation (Refer to Attachment FAULTED S/G)

1i EOP!

REV 10 FR-S 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 10 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION BORATION SHOULD CONTINUE TO OBTAIN ADEQUATE SHUTDOWN MARGIN DURING SUBSEQUENT ACTIONS.

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

14 Verify Reactor Subcritical: Perform the following:

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

5s

b. Continue to inject boric acid, o Intermediate range channels STABLE OR DECREASING c. Direct RP to sample RCS and PRZR for boron concentration.

o Intermediate range channels startup rate - NEGATIVE d, Verify boron concentration greater than Figure SDM.

o Core exit T/Cs - STABLE IF adequate shutdown margin verified, THEN return to procedure and step in effect.

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 5.

EOP:

REV 10 FR-ST 1 .RESPONSE TO REACTOR RESTART/ATWS PAGE ll of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Return to Procedure And Step In Effect

-END-

EOP:

REV: 10 FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 1 FR-S.1 APPENDIX LIST TITLE PAGES

1) FIGURE SDM

2) ATTACHMENT FAULTED S/G

't EOP:

REV 10 FR-S 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 1 FIGURE SDM NOTE: o Curve includes allowance for one stuck rod. Add 100 ppm for each additional stuck rod.

o To obtain core burnup, use PPCS point ID BURNUP.

BORON CONCENTRATION (PPH) 1800'600 BORON INCREMENTS 20 PPM 1400 ADEQUATE SDM 1200 100 PPH CONS ERVATISH INCLUDED 1000 800 600 400 BORATE BURNUP 200 INCREMENTS 200 HWD/HTU 2000 4000 6000 8000 10000 12000 14000 16000 18000 CYCLE 26 BURNUP (HWD/MTU)