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: ES-0.1'T1TLE: REACTOR TRIP RESPONSE REV: 10 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: ES-F 1 TITLE REACTOR TRIP RESPONSE REV: 10 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: ES-0.1 TITLE: REACTOR TRIP RESPONSE REV: 10 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 to Appendix l for Red Path Summary.)*1 Monitor RCS Tavg-STABLE AT OR TRENDING TO 547'F IF temperature less than 547'F and decreasing, THEN perform the following:

a.Stop dumping steam.b.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: ES-0.1 T11'LE: REACTOR TRIP RESPONSE REV 10 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 CLOSED~MFW regulating valves~MFW bypass valves c.Verify total AFW flow-GREATER THAN 200 GPM b.Place A and B MFW regulating valve and bypass valve controllers in MANUAL at 0%demand.c.Manually start both MDAFW pumps.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.d.Close MFW pump discharge valves~MOV-3977, A MFW pump~MOV-3976, B MFW pump 2)Go to step 3.d.Manually stop MFW pumps.e.Stop MFW pumps EOP: ES-0.1 REACTOR TRIP RESPONSE REV: 10 PAGE 5 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify MRPI ITIdicates

-ALL CONTROL AND SHUTDOWN RODS ON BOTTOM IF one or more control rods NOT fully inserted, THEN perform the 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: ES-0.1 LITLE: REACTOR TRIP RESPONSE REV: 10 PAGE 6 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Verify All AC Busses ENERGIZED BY OFFSITE POWER o Normal feed breakers to all 480 volt busses-CLOSED Perform the following:

a.IF any AC emergency bus normal feed breaker open, THEN ensure associated D/G breaker closed.o 480 volt bus voltage-GREATER THAN 420 VOLTS o Emergency D/G output breakers OPEN b.Perform the following as necessary:

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

6 Verify IA Available:

o At least 2 air compressors RUNNING o IA pressure-GREATER THAN 60 PSIG Dispatch AO to locally reset and start air compressors as necessary.

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

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: ES-0.1 REACTOR TRIP RESPONSE REV: 10 PAGE 8 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRZR Level Control: a.Verify charging pumps-ANY RUNNING a.Manually start charging pumps as 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 AS NECESSARY o PRZR heater control group o PRZR heater backup group e.Reset PRZR heaters and energize as necessary to restore PRZR pressure.

EOP: ES-0.1 REACTOR TRIP RESPONSE REV: 10 PAGE 9 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check PRZR Pressure Control: a.PRZR pressure-GREATER THAN 1750 PSIG b.PRZR pressure-GREATER THAN 2210 PSIG a.Perform the following:

1)Verify SI actuation.

IF NOT, THEN manually actuate SI.2)Go to E-O, REACTOR TRIP OR SAFETY INJECTION, Step l.b.IF pressure less than 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.

EOP: ES-0.1 REACTOR TRIP RESPONSE REV: 10 PAGE 10 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 8 continued from previous page)c.PRZR pressure-LESS THAN 2260 PSIG c.IF pressure greater than 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: ES-0.1 TITLE: REACTOR TRIP RESPONSE REV: 10 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 THAN 5%b.Control feed flow to maintain narrow range level between 17%and 39%.a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%in at least one S/G.b.IF narrow range level in any S/G continues to increase, THEN stop feed to that S/G.10 Check If TDAFW Pump Can Be Stopped: a.Both MDAFW pumps-RUNNING a.Go to Step 11.b.PULL STOP TDAFW pump steam supply valves~MOV-3504A~MOV-3505A EOP: ES-0.1 1'TLE: REACTOR TRIP RESPONSE REV: 10 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 o Annunciator G-15, STEAN DUMP ARMED-LIT 1)Place S/G ARV controller in AUTO at 1005 psig and verify proper operation.

IF S/G ARV NOT controlling in AUTO, THEN control S/G ARV manually.b.Adjust condenser steam dump controller HC-484 to 1005 psig in AUTO 2)Go to Step lid.c.Place steam dump mode selector switch to MANUAL d.Verify RCS Tavg-STABLE AT OR TRENDING TO 547'F d.Return to Step 1.12 Check RCP Status-AT LEAST ONE RUNNING Perform the following:

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: ES-0.1 TITLE: REACTOR TRIP RESPONSE REV: 10 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 Range Detectors Should Be Energized:

a.Source range channels DEENERGIZED a.Go to Step 13e.b.Check intermediate range flux-EITHER CHANNEL LESS THAN 10 10 AMPS b.Perform the following:

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:

o Both intermediate range channels-LESS THAN 10 10 AMPS c.Continue with Step 14.When either condition met, THEN do Steps 13d and e.-OR-o Greater than 20 minutes since reactor trip d.Verify source range detectors ENERGIZED d.Manually energize source range detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).e.Transfer Rk-45 recorder to one source range and one intermediate range channel IF source ranges can NOT be restored, THEN refer to ER-NIS.l, SR MALFUNCTION, and go to Step 14.

EOP l ES-0.1 TITLE: REACTOR TRIP RESPONSE REV: 10 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 rod shroud fan-RUNNING 2)Manually start one fan as power supply permits (45 kw).3)Verify one Rx compartment cooling fan-RUNNING 3)Manually start one fan as power supply permits (23 kw).d.Dispatch AO to perform Attachment SD-1 EOP: ES-0'TITLE: REACTOR TRIP RESPONSE REV: 10 PAGE 15 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Maintain Stable Plant Conditions:

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

b.PRZR level-BETWEEN 20%AND 30%c.S/G narrow range levels BETWEEN 17%AND 39%d.RCS Tavg-GREATER THAN 540'F b.Control charging as necessary.

c.Control S/G feed flow as necessary.

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 o Level-GREATER THAN 20%-OR-V o Level-STABLE OR INCREASING b.Manually increase VCT makeup flow as follows: 1)Ensure BA transfer pumps and RMW pumps running.2)Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.3)Increase boric acid flow as necessary.

EOP: ES-0.1 REACTOR TRIP RESPONSE REV: 10'AGE 16 of 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 VCT o LCV-112C-OPEN o LCV-112B-CLOSED b.Manually align valves as necessary.

EOP: ES-0.1 REACTOR TRIP RESPONSE REV: 10 PAGE 17 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify TDAFW Pump Aligned For AUTO Start: a.Any MDAFW pump-AVAILABLE b.Verify AMSAC TRIPPED status light-EXTINGUISHED c.Verify both S/G levels-GREATER THAN 17%d.Verify the following:

1)TDAFW pump-OFF 2)TDAFW pump steam supply valve switches in AUTO a.Verify TDAFW pump operating if necessary and go to Step 20.b.Reset AMSAC.c.Continue with Step 20.WHEN S/G level greater than 17%, THEN do Steps 18d and 19.1)IF TDAFW pump NOT required to maintain S/G level, THEN stop pump if desired.2)Place TDAFW pump steam supply valve switches in AUTO.

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

a.Verify the following:

o Both S/G levels-STABLE OR INCREASING a.Continue with Step 20.WHEN conditions met, THEN do Steps 19b through f.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: ES-O.l REACTOR TRIP RESPONSE REV: 10 PAGE 19 of 19 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Determine If Cooldown Is Required: a.Consult Plant staff to determine if RCS cooldown is necessary a.IF cooldown NOT required, THEN go to 0-3, HOT SHUTDOWN WITH XENON PRESENT.b.At least one RCP-RUNNING c.Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN b.Perform the following:

')Ensure 2 control rod shroud fans running.2)Go to ES-0.2, NATURAL CIRCULATION COOLDOWN, Step 1,-END-EOP:.ES-0.1 REACTOR TRIP RESPONSE REV: 10 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:ES-.O.1 REACTOR TRIP RESPONSE REV: 10 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:ES-.O.1 TITLE: REACTOR TRIP RESPONSE REV 10 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature From Figure Below[-]Core Exit T/C Indication S PRESSURE (PSIG)RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 20 RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION INADEQUATE SUBCOOLING REGION ADV ERS E CNNT TEMPERATURE INCREMENTS 10'F NORMAL CNNT 0 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE

('F)

EOP:, ES,M.1 REACTOR TRIP RESPONSE REV: 10 PAGE 1 of 1 NOTE FOLDOUT PAGE 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: FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV: 13 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: FR-C.1 TITLE: RESPONSE TO INADEQUATE CORE COOLING REV: 13 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: FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV 13 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 THAN 28%Perform the following:

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 from RWST-OPEN~MOV-825A~MOV-825B a.Ensure at least one SI pump suction valve from RWST open.~MOV-825A~MOV-825B 0 Wlj\'k FOP: FR-C.1 T1TLF.: RESPONSE TO INADEQUATE CORE COOLING REV: 13 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 deluge-OPEN~MOV-852A~MOV-852B b.Verify both RHR pumps-RUNNING c.Verify SI pump C-RUNNING d.Verify SI pump A-RUNNING e.Verify SI pump B-RUNNING t f.Verify both SI pump C discharge valves-OPEN~MOV-871A~MOV-871B a.Ensure at least one valve open.b.Manually start pumps c.Manually start pump on available bus.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~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.Manually open valves as necessary.

E\

EOP: FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV: 13 PAGE 5 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Verify SI Flow In Bath Trains: o SI line loop A and B flow indicators

-CHECK FOR FLOW o RHR loop flow indicator-CHECK FOR FLOW Perform the following:

a.Manually start pumps and align valves as necessary.

b.Establish maximum charging flow.5 Check RCP Support Conditions:

a.Verify Bus 11A or llB-ENERGIZED b.Check other RCP support conditions (Refer to Attachment RCP START)Continue attempts to establish RCP support conditions.

6 Check, SI ACCUM Discharge Valves-OPEN~MOV-841~MOV-865 IF SI ACCUM discharge valves closed after ACCUM discharge, THEN go to Step 7.IF NOT, THEN perform the following:

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: FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV: 13 PAGE 6 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check Core Exit T/Cs-LESS THAN 1200'P Go to Step 10.8 Check RVLIS Indi.cation: a.RCPs-BOTH SECURED a.Return to procedure and step in effect b.RVLIS level-GREATER THAN 43%[46%adverse CNMT]c.Return to procedure and step in effect b.IF RVLIS increasing, THEN return to Step 1.IF NOT, THEN go to Step 9.9 Check Core Exit T/Cs: a.Temperature

-LESS THAN 700'F b.Return to procedure and step in effect a.IF decreasing, THEN return to Step 1.IF NOT, THEN go to Step 10.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: FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV: 13 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 ISOLATION-EXTINGUISHED b.Perform the following:

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 THAN 0.5$b.Consult TSC to determine if hydrogen recombiners should be placed in service.

I'1'\t e~

EOP: FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV: 13 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 THAN 5%[25%adverse CNMT]b.Control feed flow to maintain narrow range level between 17%[25%adverse CNMT]and 50%a.Maintain total feed flow greater 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.

EOP: FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV 13 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 AVAILABLE a.Restore power to block valves unless block valve was closed to isolate an open'ORV: b.PORVs-CLOSED~MOV-515, MCC D position 6C~MOV-516, MCC C position 6C 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 CLOSED d.Manually close valves.~SOV-590~SOV-591~SOV-592~SOV-593 EOP: FR-C.1 T1TLEE RESPONSE TO INADEQUATE, CORE COOLING REV'3 PAGE 10 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Estab19.sh Condenser Steam Dump Pressure Control: a.Verify condenser available:

o Intact S/G MSIV-OPEN o Annunciator G-15, STEAM DUMP ARMED-LIT a.Place intact S/G ARV controller in MAANUAL and go to Step 16.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 maximum rate b.Check S/G pressure-LESS THAN 200 PSIG a.Manually or locally dump steam at maximum rate using S/G ARVs.b.IF S/G pressure decreasing, THEN return to Step 13., IF NOT, THEN go to Step 23.c.Check RCS hot leg temperatures BOTH LESS THAN 400'F d.Stop S/G depressurization c.IF RCS hot leg temperatures decreasing, THEN return to Step 13.IF NOT, THEN go to Step 23.

EOP: FR-CD 1 TITLE: RESPONSE TO INADEQUATE CORE COOLING REV: '13 PAGE 11 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check If SI ACCUMs Should Be Isolated: a.RCS hot leg temperatures

-BOTH LESS THAN 400'F a.Go to Step 23.b.,Verify SI reset c.Close SI ACCUM discharge valves~ACCUM A, MOV-841~ACCUM B, MOV-865 b, Manually reset SI.c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.~ACCUM A, AOV-834A~ACCUM B, AOV-834B d.Locally reopen breakers for MOV-841 and MOV-865 2)Open HCV-945.18 Stop Both RCPs 19 Dump Steam to Condenser At.Maximum Rate To Depressurize All Intact S/Gs To Atmospheric Pressure Manually or locally dump steam at maximum rate using S/G ARVs.20 Verify SI Plow: 'SI line loop A and B flow indicators

-CHECK FOR FLOW Perform the following:

a.Continue efforts to establish SI flow.-OR-o RHR loop flow indicator-CHECK FOR FLOW b.Try to establish charging flow c.IF core exit T/Cs less than 1200'F, THEN return to Step 19.IF NOT, THEN g'o to Step 23.

EOP: FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV: 13 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 LESS THAN 320'F b.Return to Step 19.c.RVLIS level (no RCPs)-GREATER THAN 68%[73%adverse CNMT]cd Return to Step*19'2 Go to Appropriate Plant Procedure a.Check RWST level-GREATER THAN 28'.Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 18 a.Go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

't~I'a"'~

EOP: FR-C.1 T!TLE!RESPONSE TO INADEQUATE CORE COOLING REV: 13 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 If RCPs Should Be Started: a.Core Exit T/Cs-GREATER THAN 1200'F a.Go to Step 24.b.Check if an idle RCS cooling loop is available o Narrow range S/G level-GREATER THAN 5%[25%adverse CNMT]o RCP in associated loop-AVAILABLE AND NOT OPERATING b.Perform t'e following:

1)Open all PRZR PORVs and block valves IF any block valve can NOT be opened, THEN ensure power supplied to block valve.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 c.Start RCP in one idle RCS cooling loop d.Return to Step 23a 3)Go to.Step 24.

EOP: FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV: 13 PAGE 14 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 Try To Locally Depressurize All Intact S/Gs To Atmospheric Pressure: o Use intact S/G(s)ARVs-OR-Use faulted or ruptured S/G.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 If SI ACCUMs Should Be Isolated: a.RHR loop flow indicator-AT LEAST INTERMITTENT FLOW a, Return to Step 23.b.Close SI ACCUM discharge valves~ACCUM A, MOV-841~ACCUM B, MOV-865 b.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.c.Locally reopen breakers for MOV-841 and MOV-865~ACCUM A, AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.

II h'I l r, t EOP.FR-C.1 TITLE 0 RESPONSE TO INADEQUATE CORE COOLING REV 13 PAGE 15 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check Zf RCPs Should Be Stopped: a.Both RCS hot leg temperatures LESS THAN 320'F a.Go to Step 27.b.Stop all RCPs 27 Verify SI Plov: o SI line loop A and B flow indicators

-CHECK FOR FLOW Perform the following:

a.Continue efforts to establish SI flow.-OR-o RHR loop flow indicator-CHECK FOR FLOW b.Try to establish charging flow.c.Return to Step 23.28 Check Core Cooling: a.RCPs-BOTH SECURED b.RCS hot leg temperatures

-LESS THAN 320'F a.Return to Step 23.b.Return to Step 23.c.RVLIS level-GREATER THAN 68%[73%adverse CNMT]c.Return to Step 23.

EOP: ,FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV: 13 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 28%c.Go to E-l, LOSS OF REACTOR OR'ECONDARY COOLANT, Step 18.b.'Go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step l.-END-EOP: FR-C.1 RESPONSE TO INADEQUATE CORE COOLING REV: 13 PAGE 1 of 1 FR-C.1 APPENDIX LIST TITLE 1)ATTACHMENT RCP START 2)ATTACHMENT N2 PORVS PAGES EOP FR-P.1, T1ILE0 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 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: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 16 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: FR-P.1 T1TLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 16 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 THAN 250 PSZG[465 PSIG adverse CNMT]IF RHR flow greater than 475 gpm, THEN return to procedure and step in effect.

EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV'6 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 Temperatures

-STABLE OR INCREASING Try to stop RCS cooldown: 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.This Step continued on the next page.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.

EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 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 AVAILABLE a.Restore power to block valves unless block valve was closed to isolate an open PORV: b.Block valves-AT LEAST ONE OPEN~MOV-515, MCC D position 6C~MOV-516, MCC C position 6C 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: FR-P.1 1'!TLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 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 Overpressure Protection System-IN SERVICE a.Go to Step 4d.b.Check RCS pressure-LESS THAN 410 PSIG c.Go to Step 4e d.PRZR pressure-LESS THAN 2335 PSIG e.Verify PRZR PORVs-CLOSED b..Perform the following:

1)Ensure at least one PRZR PORV open.2)Continue with Step 5.WHEN pressure less than setpoint, THEN do Step 4e.d.Perform the following:

1)Ensure at least one PRZR PORV open.2)Continue with Step 5.WHEN pressure less than setpoint, THEN do Step 4e.e.Manually close valve.IF any valve can NOT be closed, THEN manually close its block valve.

J~EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 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:

o RCS subcooling based on core exit T/Cs-GREATER THAN 50'F USING FIGURE MIN SUBCOOLING o.Check RVLIS indication:

Perform the following:

a.IF RCS subcooling based on core exit T/Cs greater than O'F using Figure MIN SUBCOOLING and no RCP running, THEN attempt to start an RCP: o Level (no RCPs)-GREATER THAN 68%[73%adverse CNMT]-OR-o Fluid fraction (any RCP running)-GREATER THAN 80%1)Establish conditions for starting an RCP: o Bus 11A or 11B energized o Refer to Attachment RCF 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: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 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 ISOLATION-EXTINGUISHED b.Perform the following:

1)Reset SI.2)Depress CI reset pushbutton.

10 Verify Adequate SW Flow: a.Check at least two SW pumps RUNNING a.Manually start SW pumps as power 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).b.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.

I~EOP: FR-P.1 T!TLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 16 PAGE 9 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Establish IA ta CNMT: a.Verify non-safeguards busses energized from offsite power o Bus 13 normal feed-CLOSED-OR-o Bus 15 normal feed-CLOSED b.Verify SW isolation valves to turbine building-OPEN~MOV-4613 and MOV-4670~MOV-4614 and MOV-4664 c.Verify at least two air compressors

-RUNNING d.Check IA supply: o Pressure-GREATER THAN 60 PSIG o Pressure-STABLE OR INCREASING e.Reset both trains of XY relays for IA to CNMT AOV-5392 f.Verify IA to CNMT AOV-5392-OPEN a.Perform the following:

1)Close non-safeguards bus tie breakers:~Bus 13 to Bus 14 tie~Bus 15 to Bus 16 tie 2)Verify adequate emergency D/G capacity to run air compressors (75 kw'each).IF NOT, THEN evaluate if CNMT RECIRC fans should be stopped (Refer to Attachment CNMT RECIRC FANS).3)WHEN bus 15 restored, THEN reset control room lighting.b.Manually align valves'.Manually start air 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.Perform the following:

1)Continue attempts to restore IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).2)Continue with Step 12.WHEN IA restored, THEN do Steps lie and f.

EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 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 RWST: o LCV-112B-OPEN o LCV-112C-CLOSED b.IF LCV-112B can NOT be opened, THEN perform the following:

1)Verify charging pump A NOT running and place in PULL STOP.2)Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).c.Start charging pumps as necessary to establish charging line flow to REGEN HX-GREATER THAN 20 GPM 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).

p~EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 PAGE 11 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*13 Monitor SI Reinitiation Criteria: o RCS subcooling based on core exit T/Cs-GREATER THAN FIGURE MIN SUBCOOLING o RVLIS indication:

Manually operate SI pumps as necessary and perform the following:

a.IF RCS subcooling based on core exit T/Cs greater than Figure MIN SUBCOOLING and no RCP running, THEN attempt to start a RCP: o Level-GREATER THAN 68%[73%adverse CNMT]-OR-o Fluid fraction (any RCP running)-GREATER THAN 80%1)Establish conditions for starting an RCP: o Bus llA or 11B energized o Refer to Attachment RCP START 2)IF conditions established, THEN start one RCP.b.Go to Step 26'4 Check RCS Hot Leg Temperatures

>>STABLE IF increasing, THEN control feed 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: FR-P.1 T!TLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 PAGE 12 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Check If SI ACCUMs Should Be Isolated: a.Check the following'.

o RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Return to Step 13.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+MOV-841~MOV-865 c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.~ACCUM A, AOV-834A~ACCUM B, AOV-834B d.Locally reopen breakers for MOV-841 and MOV-865 2)Open HCV-945.3)Continue with Step 16.Do NOT decrease RCS pressure to less than unisolated ACCUM pressure.

EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 16 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 spray if available a.IF normal spray NOT available, THEN use one PRZR PORV.IF IA NOT available, THEN refer to Attachment N2 PORVS.b.Depressurize RCS until one of the following conditions satisfied:

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

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 FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 16 PAGE 14 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*17 Monitor RCP Operation:

a.RCPs-ANY RUNNING b.Check the following:

o RCP¹1 seal D/P-GREATER THAN 220 PSID a.Go to Step 18.b.Stop affected RCP(s).o RCP¹1 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 THAN 13%[40%adverse CNMT]Try to restore level with charging while maintaining stable RCS pressure.IF level can NOT be restored, THEN go to Step 25.

EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 PAGE 15 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Check If Normal CVCS Operation Can Be Established a.Verify IA restored: , o IA to CNMT (AOV-5392)

-OPEN o IA pressure-GREATER THAN 60 PSIG a.Continue with Step 23.WHEN IA restored, THEN do Steps 19 through 22.b.CCW pumps-ANY RUNNING c.Verify instrument bus D-ENERGIZED d, Charging pump-ANY RUNNING b.Perform the following:

1)IF any RCP¹1 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.Energize MCC B.IF MCC B NOT available, THEN perform the following:

1)Verify MCC A energized.

2)Place instrument bus D on maintenance supply.d.Continue with Step 24.WHEN any charging pump running, THEN do Steps 20 through 24.

EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 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: a.Establish charging line flow to REGEN Hx-GREATER THAN 20 GPM be Place the following switches to CLOSE:~Letdown orifice valves (AOV-200A, AOV-200B, and AOV-202)~AOV-371, letdown isolation valve~AOV-427, loop B cold leg to REGEN Hx c.Place letdown controllers in MANUAL at 40%open~TCV-130~PCV-135 d.Reset both trains of XY relays for AOV-371 and AOV-427 e.Open AOV-371 and AOV-427 IF RCP seal return has been established, THEN establish excess letdown as follows:, o Place excess letdown divert valve, AOV-312, to NORMAL.o Ensure CCW from excess letdown open, (AOV-745).

o Open excess letdown isolation valve AOV-310.o Slowly open HCV-123 to maintain excess letdown temperature less than 195'F and pressure less than 100 psig.o Adjust charging pump speed as necessary.

IF RCP seal return NOT established, THEN consult TSC to determine, if excess letdown should be placed in service.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 FR-P.1 TlTLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 16 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:

1)RMW mode selector switch in AUTO c.Adjust controls as necessary.

2)RMW control armed-RED LIGHT LIT d, Check VCT level;o Level-GREATER THAN 20%-OR-o Level-STABLE OR INCREASING d.Manually increase VCT makeup flow as follows: 1)Ensure BA transfer pumps and RMW pumps running, IF NOT, THEN reset MCC C and MCC D UV lockouts as necessary.

2)Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.3)Increase boric acid flow as necessary.

FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 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 b.Verify charging pumps aligned to VCT o LCV-112C-OPEN o LCV-112B-CLOSED 2)Continue wi'th Step 23.WHEN VCT level greater than 40%, THEN do Step 22b.b.Manually align valves as necessary.

23 Check PRZR Level-LESS THAN 75%[65%adverse CNMT]Control charging and letdown as 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: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV'6 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 Temperature (TZ-424)-AT SATURATION FOR DESIRED PRESSURE IF PRZR liquid temperature low, THEN energize PRZR heaters as necessary to establish desired temperature.

25 Check RCS Subcooling Based On Core Exit T/Cs-LESS THAN 10'F USING FIGURE MZN SUBCOOLZNG IF RCS pressure less than 160 psig[200 psig adverse CNMT], THEN go to Step 26.IF NOT, THEN depressurize 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 Cold Legs-GREATER THAN 100'F ZN ANY 60 MINUTES PERIOD Return to procedure and step in effect.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: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 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: o RCS subcooling based on core exit T/Cs-GREATER THAN FIGURE MIN SUBCOOLING o RVLIS indication:

o Level-GREATER THAN 68%[73%adverse CNMT]-OR-o Fluid fraction (any RCP running)-GREATER THAN 80%Manually operate SI pumps as necessary.

IF RCS subcooling based'on core exit T/Cs greater than Figure MIN SUBCOOLING and no RCP running, THEN perform the following:

a.Establish conditions for starting an RCP: o Bus llA or 11B energized o Refer to Attachment RCP START b.IF conditions established, THEN start one RCP.

EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 PAGE 21 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Return To Procedure And Step In Effect-END-EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 PAGE 1 of 1 FR-P.1 APPENDIX LIST TITLE 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 PAGES EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 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 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED'EGION ADVERSE CNMT NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE

('F)

EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 16 PAGE 1 of 1 RCS 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG FIGURE SOAK LIMITS REMAIN BELOW CURVE TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEMPERATURE

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EOP: FR-P.1 TITLE: RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV: 16 PAGE 1 of 1 FIGURE RCP SEAL LEAKOFF¹I 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 2500¹1 SEAL DP (RCS PRESS-VCT PRESS)PSI EOP I FR-S~1 RESPONSE TO REACTOR RESTART/ATWS REV 10 PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RE ONSIBLE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS REV: 10 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: FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS REV: 10 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 1 Verify Reactor Trip: o At least one train of reactor trip breakers-OPEN o Neutron flux-DECREASING o MRPI indicates-ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Manually trip reactor.IF reactor trip breakers NOT open, THEN manually insert control rods.O 2 Verify Turbine Stop Valves-CLOSED Manually trip turbine.IF turbine trip can NOT be verified, THEN close both MSIVs.3 Check AFW Pumps Running: a.MDAFW pumps-RUNNING b.TDAFW pump-RUNNING IF NECESSARY a.Manually start MDAFW pumps.b.Manually open steam supply valves.~MOV-3505A~MOV-3504A

EOP: FR-S.l T1TLE: RESPONSE TO REACTOR RESTART/ASS REV 10 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: o All SI annunciators EXTINGUISHED o All SI pumps-OFF IN AUTO b.Verify at least one charging pump-RUNNING c.Align boration path: 1)Start two BA transfer pumps 2)Open MOV-350 3)Verify BA flow d.Verify charging flow path: o Charging valve to loop B cold leg (AOV-294)-OPEN o Charging flow control valve (HCV-142)-DEMAND AT 0%a.Perform the following:

1)Complete steps 1 through 12 of E-O, REACTOR TRIP OR SAFETY INJECTION, while continuing with this procedure 2)IF SI flow indicated, THEN go to'Step 5.IF NOT, THEN go to Step 4b.b.Perform the following:

1)Reset SI if necessary.

2)Start one charging pump.c.Initiate normal boration at magimum rate using the boric acid flow control valve, FCV-llOA.IF flow can NOT be established, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION.

d.Manually align valves and verify flow.

EOP: FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS REV 10 PAGE 5 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 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.b.Turbine trip o Open reactor trip breakers locally.b.Dispatch operator to locally trip turbine using manual trip lever on west end of HP turbine.6 Check PRZR PORV Status: o RCS pressure-LESS THAN 2335 PSIG o PORVs-CLOSED Verify CNMT ventilation isolation.

IF dampers NOT closed, THEN momentarily deenergize CNMT particulate monitor, R-ll, to actuate CVI.o Annunciator F-19, PRZR PORV OUTLET HI TEMP-EXTINGUISHED EOP: FR-ST 1 TITLE: RESPONSE TO REACTOR RESTART/ATWS REV 10 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 one S/G-GREATER THAN 5%[25%adverse CNMT]b.Control feed flow to maintain narrow range level between 17%[25%adverse CNMT]and 50%'.Perform the following:

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 at least one S/G.8 Verify Dilution Paths-, ISOLATED Manually isolate dilution paths.o Place RMW'mode switch to BORATE o Verify RMW to blender (HCV-111)CLOSED o Verify RMW pumps-OFF tl EOP: FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS REV 10 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:

o Core exit T/Cs-STABLE OR INCREASING b., IF RCS cooldown can NOT be controlled, THEN close both MSIVs and go to Step 10.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 b.MFW flow control valves-CLOSED~MFW regulating valves~MFW bypass valves 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.11 Identify Faulted S/G: o Any S/G Pressure-DECREASING IN AN, UNCONTROLLED MANNER Go to Step 14.-OR-o Any S/G-COMPLETELY DEPRESSURIZED l'

EOP: FR-S 1 TITLE: RESPONSE TO REACTOR RESTART/ATWS REV 10 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 S/G: o Close faulted S/G MDAFW pump discharge valve~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 Manually close valves.IF valves can NOT be closed, THEN dispatch AO to locally isolate flowpaths as necessary.

~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: FR-ST 1 RESPONSE TO REACTOR RESTART/ATNS REV: 10 PAGE 9 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Isolate Steam Flow From Faulted S/G: o Verify faulted S/G ARV-CLOSED~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 Manually close valves.IF valves can NOT be closed, THEN dispatch AO to locally isolate flowpaths as necessary.

~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!FR-S 1 RESPONSE TO REACTOR RESTART/ATWS REV 10 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:

o Power range channels-LESS THAN 5s o Intermediate range channels STABLE OR DECREASING o Intermediate range channels startup rate-NEGATIVE o Core exit T/Cs-STABLE Perform the following:

a.Stabilize RCS temperature.

b.Continue to inject boric acid, c.Direct RP to sample RCS and PRZR for boron concentration.

d, Verify boron concentration greater than Figure SDM.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: FR-ST 1.RESPONSE TO REACTOR RESTART/ATWS REV 10 PAGE ll of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Return to Procedure And Step In Effect-END-EOP: FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS REV: 10 PAGE 1 of 1 FR-S.1 APPENDIX LIST TITLE PAGES 1)FIGURE SDM 2)ATTACHMENT FAULTED S/G

't EOP: FR-S 1 RESPONSE TO REACTOR RESTART/ATWS REV 10 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 1200 1000 ADEQUATE SDM 100 PPH CONS ERVATISH INCLUDED 800 600 400 BORATE 200 BURNUP INCREMENTS 200 HWD/HTU 2000 4000 6000 8000 10000 12000 14000 16000 18000 CYCLE 26 BURNUP (HWD/MTU)