ML17265A515

Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index

ML17265A515
Person / Time
Site:	Ginna
Issue date:	01/14/1999
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17265A517	List: ML17265A515 ML17311A067
References
PROC-990114, NUDOCS 9901220067
Download: ML17265A515 (159)

Text

EOP AP-SW.1 TITLE: SERVICE WATER LEAK REV 14 PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIB MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY: vv<nmoosv esoxxs PDR ADQCK 05000244 F PDR EOP: AP-SW.1 TITLE: SERVICE WATER LEAK REV: 14 PAGE 2 of 10 A.PURPOSE-This procedure provides the necessary instructions to respond to a service water system leak.B.ENTRY CONDITIONS/SYMPTOMS 1.SYMPTOMS-The symptoms of SERVICE WATER LEAK are: a.Service water header pressure low alarms on computer, or b.Sump pump activity increases in containment, the AUX BLDG@or INT BLDG@OR c.Unexplained increase in the waste hold-up tank, or d.Visual observation of a SW leak, or e.Annunciator C-2, CONTAINMENT RECIRC CLRS WATER OUTLET HI TEMP 217 F, lit, or f.Annunciator C-10, CONTAINMENT RECIRC CLRS WATER OUTLET LO FLOW 1050 GPM, lit, or g.Annunciator E-31, CONTAINMENT RECIRC FAN CONDENSATE HI-HI LEVEL alarm, exhibits an unexplained increase in frequency, or h.Annunciator H-G, CCW SERVICE WATER LO FLOW 1000 GPM, lit.

EOP AP-SW.1 TITLE: SERVICE WATER LEAK REV: 14 PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 l*0 l I I f 1 i f 0 t~~*i~1*1 1 1*1 0 t 1*I 4 t 1 4~~1~~CAUTION o IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION.

SHALL BE PERFORMED.

o IF EITHER D/G RUNNING WITHOUT SW COOLING AVAILABLE, THEN STOP THE AFFECTED D/G TO PREVENT OVERHEATING.

1 Verify 480V AC Emergency Busses 17 and 18-ENERGIZED Ensure associated D/G(s)running and attempt to manually load busses 17 and/or 18 onto the D/G(s)if necessary.

2 Verify At Least One SW Pump Running In Each Loop:~A or B pump in loop A~C or D pump in loop B IF a SW pump has tripped, THEN ensure other pump in the affected loop is running.

, y h 0 A~

EOP: AP-SW.1 SERVICE WATER LEAK REV: 14 PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Abnormally low pressure in either SW loop may indicate that the idle pump check valve is open.This may be corrected by restarting or isolating the idle pump.3 Check SW System Status: a.Check SW loop header pressures:

o Pressure in both loops-APPROXIMATELY EQUAL o PPCS SW low pressure alarm status-NOT LOW o Pressure in both loops STABLE OR INCREASING b.Check SW loop header pressures GREATER THAN 55 PSIG a.IF three SW pumps operating and either loop pressure less than 40 psig.THEN trip the reactor and go to E-0.REACTOR TRIP OR SAFETY INJECTION.

IF only two SW pumps operating and either loop pressure less than 45 psig, THEN start one additional SW pump (243 kw each pump).b.IF either SW loop pressure is less than 55 PSIG with three SW pumps running AND cause can NOT be corrected, THEN initiate a controlled shutdown while continuing with this procedure (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN).

~~

EOP: AP-SW.1 SERVICE WATER LEAK REV: 14 PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o If SW is lost to any safeguards equipment, the affected component should be declared inoperable and appropriate actions taken as required by ITS, Section 3.o CNMT sump A level of 10 feet is approximately 6 feet 6 inches below the bottom of the reactor vessel.4 Check For SW Leakage In CNMT: a.Check Sump A indication o Sump A level-INCREASING-OR-a.IF the SW leak is NOT in the CNMT, THEN go to Step 6.o Sump A pump start frequency-INCREASING (Refer to RCS Daily Leakage Log)b.Evaluate Sump A conditions:

1)Verify Leakage within capacity of one Sump A pump (50 gpm)2)Check Sump A level-LESS THAN 10 FEET b.Plant shutdown should be considered, consult plant staff.c.Direct RP to establish conditions for CNMT entry V&4 r-EOP: AP-SW.1 TITLE: SERVICE WATER LEAK REV 14 PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1~t 4 I*1'0 I*~4 1 1 4 1*1 0**4 t 1 1 4 4 0~I I 4*1 1 1 1 t~CAUTION BEFORE ISOLATING SW TO CNMT RECIRC FANS.REFER TO ITS SECTION 3.6.6 FOR OPERABILITY REQUIREMENTS.

NOTE: o One Reactor Compartment cooling fan should be running whenever RCS temperature is greater than 135 F.'CNMT recirc fan condensate collector level indicators may be helpful in identifying a leaking fan cooler.5 Check CNMT fan indications:

o CNMT recirc fan collector dump frequency-NORMAL (Refer to RCS Daily Leakage Log)o CNMT recirc fan SW flows APPROXIMATELY EQUAL (INTER BLDG basement by IBELIP)o Reactor compartment cooler SW outlet pressures-APPROXIMATELY EQUAL (INTER BLDG SAMPLE HOOD AREA)~Cooler A-PI 2232~Cooler B-PI 2141 Dispatch AO to perform Attachment SW LOADS IN CNMT as necessary.

WHEN CNMT SW leak location identified, THEN go to Step 9.

1 4~h't I k'l e~'s>~~~

EOP: AP-SW.1 SERVICE WATER LEAK REV: 14 PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Dispatch AO To Screenhouse To Perform The Following:

a.Verify idle SW pump check valve closed o Idle pump shaft stopped o Idle pump discharge pressure ZERO (unisolate and check local pressure indicator) b.Investigate for SW leak in Screenhouse

-NO EXCESSIVE LEAKAGE INDICATED a.Notify Control Room of any indication of check valve failure.b.Perform the following:

1)Identify leak location.IP increase in leakage from underground header indicated, THEN isolation of header should be considered (Refer to Attachment SW ISOLATION) 2)Notify Control Room of leak location.NOTE: Refer to Attachment SW ISOLATION for a list of the major non-safeguards loads supplied by each service water header.7 Check Indications For Leak Location: o AUX BLDG sump pump start frequency-NORMAL (Refer to RCS Daily Leakage Log)o Annunciator L-9.AUX BLDG SUMP HI LEVEL-EXTINGUISHED Dispatch AO to the specific area to investigate for leakage.o Annunciator L-17, INTER BLDG SUMP HI LEVEL" EXTINGUISHED I~'~

EOP: AP-SW.1 SERVICE WA'gER LEAK REV 14 PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Dispatch AO To Locally Investigate For SW Leakage And To Monitor Operating Equipment~Turbine BLDG~SAFW pump room I~~e~~(I'I~W 4\~~k fOP: AP-SW.1 SERVICE WATER LEAK REV: 14 PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If SW is lost to either D/G, refer to ER-D/G.2.ALTERNATE COOLING FOR EMERGENCY D/Gs.if cooling is required.9 Evaluate SW Leak Concerns a.Check SW pump status-AT LEAST THREE PUMPS RUNNING b.Intact SW loop header pressure GREATER THAN 45 PSIG a.IF either SW header pressure less than 45 psig, THEN start third SW pump.b.Dispatch AO to perform the following:

1)Split A and B SW headers: o Close V-4669 OR V-4760 in B D/G room.o Close V-4611 OR V-4612 in Screenhouse.

o Close V-4625 OR V-4626 in INT BLDG clean side.o Close V-4639 OR V-4756 in INT BLDG clean side.c.Verify leak location-IDENTIFIED d.Verify plant operating at power e.Leak isolation at power-ACCEPTABLE 2)IF plant at power, THEN initiate a controlled shutdown (Refer to 0-2.1.NORMAL SHUTDOWN TO HOT SHUTDOWN).

3)Go to Step 10.c.Return to Step 3.d.Verify SW system conditions appropriate for plant mode (Refer to ITS Section 3.7.8)and go to Step 10.e.IF plant shutdown required.THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.

'I I b EOP: AP-SW.1 SERVICE WATER LEAK REV: 14 PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Dispatch AO(s)To Locally Isolate SW Leak As Necessary ll Verify SW Leak Isolated a.Monitor SW System Operation o SW loop header pressure RESTORED TO PRE-EVENT VALUE Archive PPCS point,ID loop A P2160 OR loop B P2161)o Both SW loop header pressures STABLE a.IF SW leak can NOT be isolated within the affected header, THEN stop SW pumps in the affected loop and go to Step 12.b.Verify at least one SW pump available from each screenhouse AC Emergency bus~Bus 17 SW pumps B or D~Bus 18 SW pumps A or C b.Refer to ITS Section 3.7.8 for , limiting conditions for operation.

NOTE: o Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

o An Action Report, per IP-CAP.1, should be submitted for a SW leak in CNMT.12 Notify Higher Supervision-END-EOP: AP-SW.1 SERVICE WATER LEAK REV: 14 PAGE 1 of 1 AP-SW.1 APPENDIX LIST TITLE 1)ATTACHMENT SW ISOLATION (ATT-2.2)2)ATTACHMENT SW LOADS IN CNMT (ATT-2.3)

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV 27 PAGE 1 of 26 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBL MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: E-0 REACTOR TRIP OR SAFETY INACTION REV: 27 PAGE 2 of 26 A.PURPOSE-This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection and to assess plant conditions, and identify the appropriate recovery procedure.

B.ENTRY CONDITIONS/SYMPTOMS 1.The following are symptoms that require a reactor trip,'f one has-not occurred: o Any plant parameter reaches a reactor trip setpoint and logic as listed in procedure P-l, REACTOR CONTROL AND PROTECTION SYSTEM.o Operator discretion.

2.The following are symptoms of a reactor trip: o Any, First Out reactor trip annunciator lit.o A rapid decrease in core neutron level as indicated by nuclear instrumentation.

o MRPI Indicates all control and shutdown rods on bottom.o Reactor trip breakers indicate open.3.The following are symptoms that require a reactor trip and safety injection, if one has not occurred: o Any plant parameter reaches the Safety Injection setpoint and logic as listed in procedure P-l, REACTOR CONTROL AND PROTECTION SYSTEM.o Operator discretion.

4.The following are symptoms of a reactor trip and safety injection:

o Any SI annunciator lit.o Safeguards sequencing started.

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 3 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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 perform the following:

a.Open Bus 13 and-Bus 15 normal feed breakers.b.Verify rod drive MG sets tripped.c.Close Bus 13 and Bus 15 normal feed breakers.d.Reset lighting breakers.IF the reactor will NOT trip OR IF power range NIS indicates greater than 5'/., THEN go to FR-S.l, RESPONSE TO REACTOR RESTART/ATWS.

Step 1 2 Verify Turbine Stop Valves-CLOSED Manually trip turbine.IF turbine trip can NOT be verified.THEN close both MSIVs.3 Verify Both Trains Of AC Emergency Busses Energized To At Least 420 VOLTS: Attempt to start any failed emergency D/G to restore power to all AC emergency busses.~Bus 14 and Bus 18~Bus 16 and Bus 17 IF power can NOT least one train.ECA-O.O.LOSS OF Step 1.be restored to at THEN go to ALL AC POWER.

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV 27 PAGE 4 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED a.Any SI Annunciator

-LIT a.IF any of the following conditions are met, THEN manually actuate SI and CI: o PRZR pressure less than 1750 psig-OR-o Steamline pressure less than 514 psig-OR-o CNMT pressure greater than 4 psig-OR-o SI sequencing started'OR-b.SI sequencing

-BOTH TRAINS STARTED.o Operator determines SI required IF SI is NOT required, THEN go to ES-0.1, REACTOR TRIP RESPONSE, Step 1.b.Manually actuate SI and CI.

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 5 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should be open and monitored periodically.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+0>R/hr.5 Verify SI and RHR Pumps Running: a.All SI pumps-RUNNING b.Both RHR pumps-RUNNING a.Perform the following:

1)Ensure SI pump suction supply open from RWST.2)Manually start pumps.b.Manually start pumps.6 Verify CNMT RECIRC Fans Running: a.All fans-RUNNING b.Charcoal filter dampers green status lights-EXTINGUISHED a.Manually start fans.b.Dispatch personnel to relay room with relay rack key to locally open dampers by pushing in trip relay plungers.~AUX RELAY RACK RA-2 for fan A~AUX RELAY RACK RA-3 for fan C EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV 27 PAGE 6 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*7 Verify CNMT Spray Not Required: o Annunciator A-27.CNMT SPRAY-EXTINGUISHED o CNMT pressure-LESS THAN 28 PSIG Verify CNMT spray initiated.

IF CNMT spray NOT initiated, THEN perform the following:

a.Depress manual CNMT spray pushbuttons (2 of 2).b.Ensure CNMT spray pumps running.IF no CNMT spray pump available.

THEN go to Step 8.c.Ensure CNMT spray pump discharge valves open for operating pump(s).o CNMT spray pump A:~MOV-860A~MOV-860B o CNMT spray pump B: 0 MOV-860C~MOV-860D d.Ensure NaOH tank outlet valves open.~AOV-836A~AOV-836B EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV 27 PAGE 7 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check If Main Steamlines Should Be Isolated: a.Any MSIV-OPEN b.Check CNMT pressure-LESS THAN 18 PSIG c.Check if ANY main steamlines should be isolated: o Low Tavg (545 F)AND high steam flow (0.4xl06 lb/hr)from either S/G a.Go to Step 9.b~Ensure BOTH MSIVs closed and go to Step 9~c.Go to Step 9.-OR-o High-High steam flow (3.6x106 lb/hr)from either S/G d.Verify MSIV closed on the affected S/G(s)d.Manually close valves.9 Verify MFW Isolation:

a.MFW pumps-TRIPPED b.MFW flow control valves-CLOSED~MFW regulating valves~MFW bypass valves c.S/G blowdown and sample valves CLOSED 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 in MANUAL at 0%demand.c.Place S/G blowdown and sample valve isolation switch to CLOSE.

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 8 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Verify 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 11 Verify At Least Two SW Pumps RUNNING Perform the following:

a.Ensure one SW pump running on each energized screenhouse AC emergency bus:~Bus 17~Bus 18 b.IF offsite power NOT available, THEN ensure SW isolation.

EOP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 9 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Verify CI And CVI: a.CI and CVI annunciators

-LIT~Annunciator A-26.CNMT ISOLATION~Annunciator A-25.CNMT VENTILATION ISOLATION a.Depress manual CI pushbutton.

b.Verify CI and CVI valve status lights-BRIGHT c.CNMT RECIRC fan coolers SW outlet valve status lights BRIGHT b.Manually close CI and CVI valves as required'F valves can NOT be verified closed by MCB indication, THEN dispatch AO to locally close valves (Refer to Attachment CI/CVI for alternate isolation valves).c.Dispatch AO to locally fail open valves.~FCV-4561~FCV-4562~~~I I I~~~I~I I I~I I**I~I~I I~~~I I I I I I I I*~~I~CAUTION RCP TRIP CRITERIA LISTED ON FOLDOUT PAGE SHOULD BE MONITORED PERIODICALLY'3 Check CCW System Status: a.Verify CCW pump-AT LEAST ONE RUNNING b.Place switch for excess letdown AOV-310 to CLOSE a.IF offsite power available, THEN manually start one CCW pump.c.Verify CCW from excess letdown AOV-745-CLOSED c.Manually close valve.

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 10 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Verify SI And RHR Pump Flow: a.SI flow indicators

-CHECK FOR FLOW b.RHR flow indicator-CHECK FOR FLOW a.IF RCS pressure less than 1400 psig, THEN manually start pumps and align valves.IF NOT, THEN go to Step-15.b.IF RCS pressure less than 140 psig, THEN manually start pumps and align valves.IF NOT, THEN go to Step 15.15 Verify Total AFW Flow-GREATER THAN 200 GPM IF S/G narrow range level greater than 5%[25%adverse CNMT]in any S/G, THEN control AFW flow to maintain narrow range level.IF narrow range level less than 5%[25%adverse CNMT]in all S/Gs, THEN manually start pumps and align valves as necessary.

IF AFW flow greater than 200 gpm can NOT be established, THEN go to FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.Step 1.16 Verify AFW Valve Alignment:

a.AFW flow-INDICATED TO BOTH S/G(s)b.AFW flow from each MDAFW pump-LESS THAN 230 GPM Manually align valves as necessary.

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 11 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Verify SI Pump And RHR Pump Emergency Alignment:

a.RHR pump discharge to Rx vessel deluge-OPEN~MOV-852A~MOV-852B b.Verify SI pump C-RUNNING c.Verify SI pump A-RUNNING d.Verify SI pump B-RUNNING e.Verify SI pump C discharge valves-OPEN~MOV-871A~MOV-871B a.Ensure at least one valve open.b.Manually start pump on available bus.c.Perform the following:

1)Ensure SI pumps B and C running.IF either pump NOT.running, THEN go to Step 17e.2)Ensure SI pump C aligned to discharge line A: o MOV-871A open o MOV-871B closed 3)Go to Step 18.d.Perform the following:

1)Ensure SI pumps A and C running.IF either pump NOT, running, THEN go to Step 17e.2)Ensure SI pump C aligned to discharge line B: o MOV-871B open o MOV-871A closed 3)Go to Step 18.e.Manually open valves as necessary.

EOP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 12 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*0 4~~1 4~~1 1 4 1 i 1~0 I 4~1 1 4~~P 4*0 0 I 1 4 0~~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.

18 Check CCW Flow to RCP Thermal Barriers: o Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO FLOW-EXTINGUISHED o Annunciator A-15, RCP 1B CCW RETURN HI TEMP OR LO FLOW EXTINGUISHED IF CCW to a RCP is lost, THEN perform the following:

a.Stop affected RCPs.b.Reset SI.c.Verify adequate power available to run one charging pump (75 kw).d.Start one charging pump at minimum speed for seal injection.

e.Adjust HCV-142 to establish either of the following:

o Labyrinth seal D/P to each RCP greater than 15 inches of water.-OR-o RCP seal injection flow to each RCP greater than 6 gpm.f.IF large imbalance in seal injection flow exists, THEN consider local adjustment of V-300A and V-3008.

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 13 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Check If TDAFW Pump Can Be Stopped: a.Both MDAFW pumps-RUNNING b.PULL STOP TDAFW-pump steam supply valves~MOV-3504A~MOV-3505A a.Go to Step 20.*20 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.Ensure reheater steam supply valves are closed.c.IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level greater than 5'5[25/adverse CNMT]in at least one S/G.d.WHEN S/G level greater than 5%[251o adverse CNMT]in one S/G.THEN limit feed flow to that required to maintain level in at least one S/G.e.IF cooldown continues, THEN close both MSIVs.IF temperature greater than 547'F and increasing, THEN dump steam to stabilize and slowly decrease temperature to 547'F.

fop: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 14 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check PRZR PORVs And Spray Valves: a.PORVs-CLOSED a.IF PRZR pressure less than'2335 psig, THEN manually close PORVs.IF any valve can NOT be closed, THEN manually close its block valve.~MOV-516 for PCV-430~MOV-515 for PCV-431C b.Auxiliary spray valve (AOV-296)CLOSED c.Check PRZR pressure-LESS THAN 2260 PSIG d.Normal PRZR spray valves-CLOSED~PCV-431A~PCV-431B IF block valve can NOT be closed.THEN go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT.'tep 1~b.Manually close auxiliary spray valve.IF valve can NOT be closed.THEN perform the following:

1)Decrease charging pump flow to minimum.2)Ensure charging valve to loop B cold leg open (AOV-294).

c.Continue with Step 22.WHEN pressure less than 2260 psig.THEN do Steps 21d.d.Place controllers in MANUAL at 0/.demand.IF valves can NOT be closed, THEN stop associated RCP(s).

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 15 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*22 Monitor RCP Trip Criteria: a.RCP status-ANY RCP RUNNING b.SI pumps-AT LEAST TWO RUNNING c.RCS pressure minus maximum S/G pressure-LESS THAN 175 psig[400 psig adverse CNMT]d.Stop both RCPs a.Go to Step 23'.Go to Step 23.c.Go to Step 23.23 Check If S/G Secondary Side Is Intact: o Pressure in both S/Gs-STABLE OR INCREASING o Pressure in both S/Gs-GREATER THAN 110 PSIG IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.24 Check If S/G Tubes Are Intact: o Air ejector radiation monitors (R-15 or R-15A)-NORMAL o S/G blowdown radiation monitor (R-19)-NORMAL o Steamline radiation monitors (R-31 and R-32)-NORMAL Go to E-3.STEAM GENERATOR TUBE RUPTURE, Step 1.

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 16 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check If RCS Is Intact: a.CNMT area radiation monitors NORMAL Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT.Step l.~R-2~R-7~R-29~R-30 b.CNMT pressure-LESS THAN 0.5 PSIG c.CNMT sump B level-LESS THAN 8 INCHES d.CNMT sump A level o Level-STABLE o Annunciator C-19.CONTAINMENT SUMP A HI LEVEL-EXTINGUISHED

,

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 17 of,26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check If SI Should Be Terminated:

a.RCS pressure: o Pressure-GREATER THAN 1625 PSIG o Pressure-STABLE OR INCREASING b.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING c.Secondary heat sink: o Total feed flow to S/Gs GREATER THAN 200 GPM a.Do NOT stop SI pumps.Go to Step 27.b.Do NOT stop SI pumps.Go to Step 27.c.IF neither condition met, THEN do NOT stop SI pumps.Go to Step 27.-OR-o Narrow range level in at least one S/G-GREATER THAN 5%d.PRZR level-GREATER THAN 5%e.Go to ES-l.l.SI TERMINATION.

Step 1.d.Do NOT stop SI pumps.Perform the following:

1)IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.2)Go to Step 27.

EOP: E-0 REACTOR TRIP OR SAFETY IN JECTION REV: 27 PAGE 18 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o The Critical Safety Function Red Path Summary is available in APPENDIX 1.27 Initiate Monitoring of Critical Safety Function Status Trees*28 Monitor S/G Levels: a.Narrow range level-GREATER THAN 5%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%in at least one S/G.b.Control feed flow to maintain narrow range level between 17%and 50%b.IF narrow range level in any S/G continues to increase in an uncontrolled manner.THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.29 Check Secondary Radiation Levels-NORMAL o Steamline radiation monitor (R-31 and R-32)o Dispatch AO to locally check steamline radiation o Request RP sample S/Gs for activity Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

EOP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 19 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*~~0 1 I 1~0 I*I l l**0~I~1 I 1 0~1 0*~~4 1 1*4 4 1~1 4~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.

• 0 i 1 4~f 0 4 1 4 4 1 4 4 0 1 I~j 1 i 1~1 I*4~~30 Reset SI 31 Reset CI: a.Depress CI reset pushbutton b.Verify annunciator A-26.CNMT ISOLATION-EXTINGUISHED b.Perform the following:

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

32 Verify Adequate SW Flow: a.At least three SW pumps-RUNNING b.Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)a.Manually start SW pumps as power supply permits (257 kw each).IF less than three pumps running, THEN ensure SW isolation.

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 20 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 Establish IA to 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 adequate air compressor(s)

-RUNNING d.'heck 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'ontrol 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 34.WHEN IA restored, THEN do Steps 33e and f.

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 21 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 Check Auxiliary Building Radiation-NORMAL~Plant vent iodine (R-10B)~Plant vent particulate (R-13)~Plant vent gas (R-14)~CCW liquid monitor (R-17)~LTD line monitor (R-9)~CHG pump room (R-4)Evaluate cause of abnormal conditions.

IF the cause is a loss of RCS inventory outside CNMT.THEN go to ECA-1.2.LOCA OUTSIDE CONTAINMENT, Step 1.35 Check PRT Conditions o PRT level (LI-442)-LESS THAN 84%o PRT temperature (TI-439)-LESS THAN 120 F Evaluate the following flowpaths for cause of abnormal conditions:

~RCP seal return relief~PRZR PORVs~PRZR safeties~Letdown line relief o PRT pressure (PI-440A)-LESS THAN 3 PSIG IF excess letdown previously in service, THEN close AOV-310, excess letdown isolation valve from loop A cold.

EOP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 22 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED~*4~4 4~l 4~i 1~~I~1 1~~4 4 4 1 I*~*1 4*~I 1~1~4~CAUTION RCS PRESSURE SHOULD BE MONITORED.

IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG.THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.36 Check If RHR Pumps Should Be Stopped: a.Check RCS pressure: 1)Pressure-GREATER THAN 250 PSIG 2)Pressure-STABLE OR INCREASING 1)Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.2)Go to Step 37.b.Stop both RHR pumps and place in AUTO 37 Check Normal Power Available To Charging Pumps: o Bus 14 normal feed breaker-CLOSED o Bus 16 normal feed breaker-CLOSED Verify adequate emergency D/G capacity to run charging pumps (75 kw each).IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer to Attachment CNMT RECIRC FANS).

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 23 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 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 gl seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s)to affected RCP:~V-300A for RCP A~V-300B for RCP B 2)Ensure HCV-142 open, demand at 0/o.b.Charging pump suction aligned to RWST: o LCV-112B-OPEN o'CV-112C-CLOSED b.Manually align valves as necessary.

IF LCV-112B can NOT be opened, THEN dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).IF LCV-112C can NOT be closed.THEN perform the following:

1)Verify charging pump A NOT running and place in PULL STOP.c.Start charging pumps as necessary and adjust charging flow to restore PRZR level 2)Direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).

EOP: E-0 REACTOR TRIP OR SAFETY IN JECTION REV: 27 PAGE 24 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 39 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG o Reset PRZR heaters o Use normal PRZR spray

EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 25 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 40 Check If Emergency D/Gs Should Be Stopped: a.Verify AC emergency busses energized by offsite power: o Emergency D/G output breakers OPEN o AC emergency bus voltage-GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers-CLOSED a.Perform the following:

1)Verify non-safeguards bus tie breakers closed:~Bus 13 to Bus 14 tie~Bus 15 to Bus 16 tie 2)Place the following pumps in PULL STOP:~EH pumps~Turning gear oil pump~HP seal oil backup pump 3)Ensure condenser steam dump mode control in MANUAL.4)Restore power to MCCs:~A from Bus 13~B from Bus 15~E from Bus 15~F from Bus 15 5)Start HP seal oil backup pump.6)Ensure D/G load within limits.7)Refer to Attachment SI/UV for other equipment lost with loss of offsite power.8)Try to restore offsite power (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).b.Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)

E-0 REACTOR TRIP OR SAFETY IN JECTION REV: 27 PAGE 26 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 41 Return to Step 20-END-

E-0 REACTOR TRIP OR SAFETY IN JECTION REV 27 PAGE 1 of 1 E-0 APPENDIX LIST TITLE 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLXNG (FIG-1.0)3)ATTACHMENT CX/CVX (ATT-3.0)4)ATTACHMENT SD-1 (Arr-17.0) 5)ATTACHMENT CNMT RECIRC FANS (ATT-4.0)6)ATTACHMENT D/G STOP (ATT-8.1)7)ATTACHMENT SI/UV (Arr-s.a)8)FOLDOUT EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 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'AND RVLIS level (no RCPs)less than 52%[55%-adverse CNMT]c.HEAT SINK-Narrow range level in all S/Gs less than 5%[25%adverse CNMT]AND total feedwater flow less than 200 gpm d.INTEGRITY-Cold leg temperatures decrease greater than 100'in last 60 minutes AND RCS cold leg temperature less than 285 F e.CONTAINMENT

-CNMT pressure greater than 60 psig E-0 REACTOR TRIP OR SAFETY INJECTION REV 27 PAGE 1 of 1 FOLDOUT PAGE 2.RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs: a.SI pumps--AT LEAST TWO RUNNING b.RCS pressure minus maximum S/G pressure-LESS THAN 175 PSIG[400 psig adverse CNMT]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).

t EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 1 of 21 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER OI+RESPONSI E MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

I EOP: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 2 of 21 A.PURPOSE-This procedure provides actions to recover from a loss of reactor or secondary coolant.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS

-This procedure is entered from: a.E-O, REACTOR TRIP OR SAFETY INJECTION, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when a PRZR PORV is stuck open and its block valve can not be closed.b.E-O, REACTOR TRIP OR SAFETY INJECTION, with any of the following symptoms: high containment radiation, high containment pressure, or high containment recirculation sump level.c.E-O, REACTOR TRIP OR SAFETY INJECTION, ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when RCS pressure is less than the shutoff head pressure of the RHR pumps or is decreasing.

d.ES-l.l, SI TERMINATION, and FR-I.2, RESPONSE TO LOW PRESSURIZER LEVEL, if SI has to be reinitiated.

e.E-2, FAULTED STEAM GENERATOR ISOLATION, after identification and isolation of a faulted S/G.f.ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, after normal injection mode conditions are established.

g.ECA-1.2, LOCA OUTSIDE CONTAINMENT, when a LOCA outside containment is isolated.h.FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, and FR-C.2, RESPONSE TO DEGRADED CORE COOLING, after core cooling has been reestablished.

FR-H.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs are closed.

EOP: TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 3 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I*I I I I I I I~~~I~~*I I~I I I I~I I I I I*I*I*I I I~CAUTION IF RWST LEVEL DECREASES TO LESS THAN 28%, THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3.TRANSFER TO COLD LEG RECIRCULATION, STEP 1.NOTE: o FOLDOUT page should be open AND monitored periodically.

o Critical Safety Function Status Trees should be monitored.(Refer to Appendix 1 for Red Path Summary.)o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.1 Monitor RCP Trip Criteria: a.RCP status-ANY RCP RUNNING b.SI pumps-AT LEAST TWO RUNNING c.RCS pressure minus maximum S/G pressure-LESS THAN 175 psig[400 psig adverse CNMT]d.Stop both RCPs a.Go to Step 2.b.Go to Step 2.c.Go to Step 2.

EOP: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 4 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check If S/G Secondary Side Is Intact: o Pressure in both S/Gs-STABLE OR INCREASING o Pressure in both S/Gs-GREATER THAN 110 PSIG IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN verify faulted S/G isolated unless needed for RCS cooldown:~Steamlines

~Feedlines IF NOT, THEN go to E-2.FAULTED STEAM GENERATOR ISOLATION, Step l.NOTE: TDAFW pump flow control valves fail open on loss of IA.*3 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 CNMTl and 50%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT1 in at least one S/G.b.IF narrow range level in any S/G continues to increase in an uncontrolled manner, THEN go to E-3.STEAM GENERATOR TUBE RUPTURE, Step l.*4 Monitor If Secondary Radiation Levels Are Normal o Steamline radiation monitor (R-31 and R-32)o Request RP sample S/Gs for activity IF steamline radiation monitors NOT available, THEN dispatch AO to locally check steamline radiation.

IF abnormal radiation levels detected in any S/G, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.

~I EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 5 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED~*l~0 4 0 t~1 1 I 0 1~4 0 4 0 1 1***l 1*i*4 1*4 0 I 4~1~~CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE.IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).*5 Monitor PRZR PORV Status: a.Power to PORV block valves AVAILABLE b.PORVs-CLOSED a.Restore power to block valves unless block valve was closed to isolate an open PORV: o MOV-515, MCC D position 6C~MOV-516, MCC C position 6C b.IF PRZR pressure less than 2335 psig, THEN manually close PORVs.c.Block valves-AT LEAST ONE OPEN IF any PORV can NOT be closed.THEN manually close its block valve.IF block valve can NOT be closed, THEN dispatch AO to locally check breaker.~MOV-515, MCC D position 6C~MOV-516.MCC C position 6C c.Open one block valve unless it was closed to isolate an open PORV.

U I'~4 EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 6 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED~i i*0 4~0 1 0 l i l 0 1 t~**1~l~~1 P~4 4~4 4*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.

~~P t 4 I*l 1*4 4 0~~~4 0~I 1*4 4 0 1 1~i~4 1 4 4 0 t I 1~~6 Reset SI 7 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.

8 Verify Adequate SW Flow: a.Check at least two SW pumps RUNNING b.Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)a.Manually start SW pumps as power supply permits (257 kw each).IF less than two SW pumps running, THEN perform the following:

1)Ensure SW isolation.

2)Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)3)Go to Step 10.

• ~

EOP: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 7 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish IA to 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 turbine building SW isolation valves-OPEN~MOV-4613 and MOV-4670~MOV-4614 and MOV-4664 c.Verify adequate 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.c.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 10.WHEN IA restored, THEN do Steps 9e and f.

EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 8 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check Normal Power Available To Charging Pumps: o Bus 14 normal feed breaker CLOSED o Bus 16 normal feed breaker CLOSED Verify adequate emergency D/G capacity to run charging pumps (75 kw each).IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer to Attachment CNMT RECIRC FANS).

EOP: E-1 TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 9 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 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 81 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s)to affected RCP:~V-300A for RCP A~V-300B for RCP B 2)Ensure HCV-142 open.demand at 0/o.b.Charging pump suction aligned to RWST: o LCV-112B-OPEN o LCV-112C-CLOSED b.Manually align valves as necessary.

IF LCV-112B can NOT be opened, THEN dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).IF LCV-112C can NOT be closed.THEN perform the following:

1)Verify charging pump A NOT running and place in PULL STOP.2)Direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).c.Start charging pumps as necessary and adjust charging flow to restore PRZR level

EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 FAGE 10 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If SI Should Be Terminated:

a.RCS pressure: o Pressure-GREATER THAN 1625 psig[1825 psig adverse CNMT]a.Do NOT stop SI pumps.Go to Step 13.o Pressure-STABLE OR INCREASING b.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FXGURE MIN SUBCOOLING b.Do NOT stop SI pumps.Go to Step 13.FI c.Secondary heat sink: o Total feed flow to intact S/Gs-GREATER THAN 200 GPM c.IF neither condition satisfied.

THEN do NOT stop SI pumps.Go to Step 13.-OR-o Narrow range level in at least one intact S/G GREATER THAN 5%[25%adverse CNMT]d.PRZR level-GREATER THAN 5%[30%adverse CNMT]e.Go to ES-l.l, SI TERMINATION, Step l.d.Do NOT stop SX pumps.Perform the following:

1)IF normal PRZR spray available'HEN try to stabilize RCS pressure with PRZR spray.2)Go to Step 13.

h EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE ll of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*13 Monitor If CNMT Spray Should Be Stopped: a.CNMT spray pumps-RUNNING b.Check the following:

o CNMT pressure-LESS THAN 4 PSIG a.Go to Step 14.b.Continue with Step 14.WHEN BOTH conditions satisfied, THEN do Steps 13c through f.o Sodium hydroxide tank level LESS THAN 55'/c.Reset CNMT spray d.Check NaOH tank outlet valves CLOSED~AOV-836A~AOV-836B d.Place NaOH tank outlet valve controllers to MANUAL and close valves.e.Stop CNMT spray pumps and place in AUTO f.Close CNMT spray pump discharge valves~MOV-860A~MOV-860B~MOV-860C~MOV-860D EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 12 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED~4 0 I 4 t*0 I 4*4~0 0 1 1 1 0 1 1 1 1*I 4 1 4 I t 0 0 0 4 I~0 4~CAUTION o 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.

o.RCS PRESSURE SHOULD BE MONITORED.

IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG[465 PSIG ADVERSE CNMT7, THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.*14 Monitor If RHR Pumps Should Be Stopped: a.Check RCS pressure: 1)Pressure-GREATER THAN 250 psig[465 psig adverse CNMT7 2)RCS pressure-STABLE OR INCREASING 1)Go to Step 16.2)Go to Step 15.b.Stop RHR pumps and place in AUTO 15 Check RCS And S/G Pressures a.Check pressures in both S/Gs STABLE OR INCREASING b.Check pressures in both S/Gs-GREATER THAN 110 PSIG c.Check RCS pressure-STABLE OR DECREASING a.Return to Step 1.b.Monitor RCS pressure.IF RCS pressure does NOT increase after faulted S/G dryout, THEN go to Step 16.c.Return to Step l.

EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 13 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check If Emergency D/Gs Should Be Stopped: a.Verify AC emergency busses energized by offsite power: o Emergency D/G output breakers OPEN o AC emergency bus voltage-GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers-CLOSED b.Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)a.Perform the following:

1)Close non-safeguards bus tie breakers as necessary:

~Bus 13 to Bus 14 tie~Bus 15 to Bus 16 tie 2)Place the following pumps in PULL STOP:~EH pumps~Turning gear oil pump~HP seal oil backup pump 3)Ensure condenser steam dump mode control in MANUAL.4)Restore power to MCCs:~A from Bus 13~,B from Bus 15~E from Bus 15~F from Bus 15 5)Start HP seal oil backup pump.6)Ensure D/G load within limits.7)WHEN bus 15 restored, THEN reset control room lighting breaker.8)Refer to Attachment SI/UV for other equipment lost with loss of offsite power.9)Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

EOP: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 14 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check If RHR Should Be Throttled:

a.Check RHR Pumps-ANY RUNNING b.Check RWST level-LESS THAN 70%c.RHR flow-LESS THAN 1500 GPM PER OPERATING PUMP a.Go to step 18.b.Continue with Step 18.WHEN RWST level less than 70%, THEN perform step 17b.c.Manually adjust RHR Hx outlet valves equally to reduce flow to less than 1500 gpm per operating pump~RHR Hx A, HCV-625~RHR Hx B.HCV-624 IF flow can NOT be reduced manually, THEN dispatch an AO with locked valve key to locally adjust RHR Hx outlet valve handwheels equally to reduce flow.~RHR Hx A, HCV-625 handwheel~RHR Hx B.HCV-624 handwheel I

EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 15 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify CNMT Sump Recirculation Capability:

a.Check RHR and CCW systems: 1)Power available to emergency AC busses and MCCs required for CNMT sump recirculation o Bus 14 and bus 18 ENERGIZED a.Restore power to at least one train of emergency AC busses.IF at least one train of cold leg recirculation capability can NOT be verified, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step l.o MCC C-ENERGIZED o Bus 16 and bus 17 ENERGIZED o MCC D-ENERGIZED 2)RHR pumps and valves OPERABLE 3)CCW pumps and Hx-OPERABLE b.Check SW pumps-AT LEAST 2 PUMPS AVAILABLE c.Dispatch AO to check AUX BLDG sub-basement for RHR system leakage (AUX BLDG sub-basement key may be required)b.Attempt to restore at least 2 SW pumps to operable.IF only 1 SW pump available, THEN refer to Attachment MIN SW for additional guidance.c.IF any RHR pump seal leakage indicated, THEN leakage should be evaluated and isolated if necessary.

l a ll-~ll~'0 1 I~

EOP: LOSS OP REACTOR OR SECONDARY COOLANT REV: 21 PAGE 16 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Evaluate Plant Status: a.Check auxiliary building radiation-NORMAL~Plant vent iodine (R-10B)~Plant vent particulate (R-13)~Plant vent gas (R-14)~CCW liquid monitor (R-17)~LTDN line monitor (R-9)~CHG pump room (R-4)b.Direct RP to obtain following samples:~RCS boron~RCS activity~CNMT hydrogen~CNMT sump boron c.Verify adequate Rx head cooling: 1)Verify at least one control rod shroud fan-RUNNING 2)Verify one Rx compartment cooling fan-RUNNING a.Notify RP and refer to appropriate AR-RMS procedure.

IF the cause is a loss of RCS inventory outside CNMT, THEN go to ECA-1.2.LOCA OUTSIDE CONTAINMENT.

Step 1.1)Manually start one fan as power supply permits (45 kw)2)Perform the following:

o Dispatch AO to reset UV relays at MCC C and MCC D.o Manually start one fan as power supply permits (23 kw)

EOP: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 17 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check If RCS Cooldown And Depressurization Is Required: a.RCS pressure-GREATER THAN 250 psig[465 psig adverse CNMT]b.Go to ES-1.2.POST LOCA COOLDOWN AND DEPRESSURIZATION.

Step 1 a.IF RHR pump flow greater than 475 gpm, THEN go to Step 21.

EOP: E-1 LOSS 05'EACTOR OR SECONDARY COOLANT REV: 21 PAGE 18 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF D/Gs supplying emergency AC busses.THEN non-essential loads may be shed as necessary to allow start of additional SW pumps.21 Establish Adequate SW Flow: a.Verify at least two SW pumps-RUNNING b.Verify AUX BLDG SW isolation valves-OPEN a.Start additional SW pumps as power supply permits (257 kw each).IF only 1 SW pump operable, THEN perform the following:

1)Ensure Attachment MIN SW is in progress.2)Go to Step 22.b.Manually align valves.~MOV-4615 and MOV-4734~MOV-4616 and MOV-4735 This Step continued on the next page.

EOP: E-1 T1TLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 19 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 21 continued from previous page)c.Dispatch AO to perform the following:

1)Check BOTH CCW Hx-INSERVICE 1)Perform the following:

a)Locally place BOTH CCW Hxs in service 2)Verify total SW flow to CCW Hxs-GREATER THAN 5000 GPM b)Locally adjust total SW flow equally to available CCW Hxs to between 5000 gpm and 6000 gpm 0 V-4619~V-4620 2)Perform the following:

a)Isolate SW to screenhouse and air conditioning headers.~MOV-4609/MOV-4780

-AT LEAST ONE CLOSED~MOV-4663/MOV-4733

-AT LEAST ONE CLOSED b)Direct AO to locally adjust total SW flow equally to available CCW Hxs to between 5000 gpm and 6000 gpm (V-4619 and V-4620).c)Direct AO to locally isolate SW return from SFP Hxs: SFP Hx A (V-4622)~SFP Hx B (V-8689)d)Verify SW portions of Attachment SD-1 are complete.

EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 20 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Establish CCW flow to RHR Hxs: a.Check both CCW pumps-RUNNING b.Manually open CCW valves to RHR Hxs a.Perform the following:

1)Start CCW pumps as power supply permits (124 kw each)2)IF both CCW pumps are running, THEN go to step 22b.3)IF only one CCW pump is running, THEN perform the following:

a)Direct AO to isolate CCW to boric acid evaporator o Close V-760A b)Manually open CCW MOV to only one operable RHR Loop o Open MOV-738A-OR-o Open MOV-738B c)Go to step 23.b.Dispatch AO to locally open valves.~MOV-738A~MOV-738B

EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 21 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check If Transfer To Cold Leg Recirculation Is Required: a.RWST level-LESS THAN 28'/o b.Go to ES-1.3.TRANSFER TO COLD LEG RECIRCULATION, Step 1 a.Return to Step 17.-END-

EOP: TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 1 of 1 E-1 APPENDIX LIST TITLE 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLING (FIG-1.0)3)ATTACHMENT CNMT RECIRC FANS (A'rr-4.0)4)ATTACHMENT D/G STOP (Arr-s.I)5)ATTACHMENT SD-1 (ATr-17.0) 6)ATTACHMENT SI/UV (nor-s.ii) 7)ATTACHMENT MIN SW (Arr-2.1)8)FOLDOUT EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 1 of 1 RED PATH

SUMMARY

a.SUBCRITICALITY

-Nuclear power greater than 5%b.CORE COOLING-Core exit T/Cs greater than 1200'-OR-Coze exit T/Cs greater than 700'AND RVLIS level (no RCPs)less than 52%[55%adverse CNMT]c.HEAT SINK-Narrow range level in all S/Gs less than 5%[25%adverse CNMT]AND total feedwater flow less than 200 gpm d.INTEGRITY-Cold leg temperatures decrease greater than 100'in last 60 minutes AND RCS cold leg temperature less than 285'e.CONTAINMENT

-CNMT pressure greater than 60 psig EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 1 of 1 1.RCP TRIP CRITERIA FOLDOUT PAGE IF BOTH conditions listed below occur, THEN trip both RCPs: a.Sl pumps-AT LEAST TWO RUNNING b.RCS pressure minus maximum S/G pressure-LESS THAN 175 PSIG[400 psig adverse CNMT]2..SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start Sl pumps as necessary:

o RCS subcooling based on core exit T/Cs-LESS THAN 0 F USING FIGURE MIN SUBCOOLING-OR-o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%[30%adverse CNMTJ 3.SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, Sl TERMINATION, Step 1: a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING b.Total feed flow to intact S/Gs-GREATER THAN 200 GPM-OR-Narrow range level in at least one intact S/G-GREATER THAN 5%[25%adverse CNMT]c.RCS pressure: o GREATER THAN 1625 PSIG[1825 psig adverse CNMT]o STABLE OR INCREASING d.PRZR level-GREATER THAN 5%[30%adverse CNMT]4.SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.5.E-3 TRANSITION CRITERIA IF any S/G level increased in an uncontrolled manner or any S/G has abnormal radiation, THEN manually start SI pumps as necessary AND go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.6.COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.7.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: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 1 of 41 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONS LE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV 27 PAGE 2 of 41 A.PURPOSE-This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture (SGTR), this procedure should also be used for a SGTR in one S/G and a fault in the other S/G.B.ENTRY CONDXTIONS/SYMPTOMS l.ENTRY CONDITIONS

-This procedure is entered from: a.E-O, REACTOR TRXP OR SAFETY INJECTXON, when condenser air ejector radiation or blowdown radiation is abnormal, or b E 0 g REACTOR TRI P OR SAFETY IN JECTION g E-l, LOSS OF REACTOR OR SECONDARY COOLANT, E-2, FAULTED STEAM GENERATOR ISOLATION, and FR-H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL, when secondary radiation is abnormal, or c.E-O, REACTOR TRIP OR SAFETY INJECTION, E-1, LOSS OF REACTOR OR SECONDARY COOLANT, E 2~FAULTED STEAM GENERATOR ISOLATION ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, when an intact S/G narrow range level increases in an uncontrolled manner.d.ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, when pressurizer pressure control is restored.e.Any FOLDOUT page that has E-3 transition criteria whenever either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.

4 EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 3 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should be open AND monitored periodically.

o Critical Safety Function Status Trees should be monitored (Refer to Appendix 1 for Red Path Summary).o Personnel should be available for sampling during this procedure.

o Conditions should be evaluated for Site Contingency Reporting (EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.*1 Monitor RCP Trip Criteria: a.RCP status-ANY RCP RUNNING b.SI pumps-AT LEAST TWO RUNNING c.RCS pressure minus maximum S/G pressure-LESS THAN 175 psig[400 psig adverse CNMT]d.Stop both RCPs a.Go to Step 2.b.Go to Step 2.c.Go to Step 2.

EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV 27 PAGE 4 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED~I~~~1*4*1 I 1 l*~i~1*1 0 4~0 I i 4 I 0 0 4 0 0 I~~j~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.

2 Identify Ruptured S/G(s): o Unexpected increase in either S/G narrow range level-OR-o High radiation indication on main steamline radiation monitor~R-31 for S/G A~R-32 for S/G B Perform the following:

a.Reset SI b.Continue with Steps 10 through 16.WHEN ruptured S/G(s)identified.

THEN do Steps 3 through 9.-OR-o AO reports local indication of high steamline radiation-OR-o RP reports high radiation from S/G activity sample EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 5 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 4~~1 4 4 l 4 I 0~~~~0 0 0 I 0 0 I 4~~4 l~*0 1 1 4 l 4 i 1 CAUTION o IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G.o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.3 Isolate Flow From Ruptured S/G (s): a.Adjust ruptured S/G ARV controller to 1050 psig in AUTO b.Check ruptured S/G ARV-CLOSED b.WHEN ruptured S/G pressure less than 1050 psig, THEN verify S/G ARV closed.IF NOT closed, THEN place controller in MANUAL and close S/G ARV.IF S/G ARV can NOT be closed, THEN dispatch AO to locally isolate.c.Close ruptured S/G TDAFW pump steam supply valve and place in PULL STOP~S/G A, MOV-3505A~S/G B.MOV-3504A d.Verify ruptured S/G blowdown valve-CLOSED~S/G A, AOV-5738~S/G B, AOV-5737 c.Dispatch AO with locked valve key to locally isolate steam from ruptured S/G to TDAFW pump.~S/G A, V-3505~S/G B, V-3504 d.Place S/G blowdown and sample valve isolation switch to CLOSE.IF blowdown can NOT be isolated manually, THEN dispatch AO to locally isolate blowdown.~S/G A, V-5701~S/G B.V-5702 0~g 4 I EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 6 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Complete Ruptured S/G Isolation:

a.Close ruptured S/G MSIV-RUPTURED S/G MSIV CLOSED a.Perform the following:

1)Close intact S/G MSIV.2)Place intact S/G ARV controller at 1005 psig in AUTO.3)Adjust condenser steam dump controller to 1050 psig in AUTO.b.Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G part A)4)Place condenser steam dump mode selector switch to MANUAL.5)Adjust reheat steam supply controller cam to close reheat steam supply valves.6)Ensure turbine stop valves CLOSED.7)Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G.parts A and B).

1 EOP: TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 7 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*1 i f*~1*I 1 t 4 1 1*1 l t I*****4 1 1 0 4~f t 1 1 t~4 l***CAUTION IF ANY RUPTURED S/G IS FAULTED.FEED FLOW TO THAT S/G SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.S Check Ruptured S/G Level: a.Narrow range level-GREATER THAN 5%[25%adverse CNMT]b.Close MDAFW pump discharge valve to ruptured S/G~S/G A, MOV-4007~S/G B, MOV-4008 a.IF ruptured S/G NOT faulted.THEN perform the following:

l)Maintain feed flow to ruptured S/G until level greater than 5%%d[25%adverse CNMT].2)Continue with Step 6.WHEN ruptured S/G level greater than 5%[25%%d adverse CNMT], THEN do Steps 5b through e.b.Dispatch AO to locally close valve.c.Pull stop MDAFW pump for ruptured S/G d.Close TDAFW pump flow control valve to ruptured S/G~S/G A, AOV-4297~S/G B.AOV-4298 e.Verify MDAFW pump crosstie valves-CLOSED d.Dispatch AO with locked'alve key to locally close TDAFW pump manual feedwater isolation valve to ruptured S/G.~S/G AD V-4005~S/G B.V-4006 e.Manually close valves.~MOV-4000A~MOV-4000B EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 8 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Verify Ruptured S/G Isolated: a.Check ruptured MSIV-CLOSED b.Check TDAFW pump steam supply from ruptured S/G-ISOLATED c.Ruptured S/G pressure-GREATER THAN 300 PSIG a.Ensure air ejector/gland steam supply and flange heating steam isolated.(Refer to ATTACHMENT RUPTURED S/G, part B).b.Continue efforts to isolate steam supply from ruptured S/G:~S/G A, MOV-3505A OR V-3505~S/G B, MOV-3504A OR V-3504 c.Go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.7 Establish Condenser Steam Dump Pressure Control: a.Verify condenser available:

o Intact S/G MSIV-OPEN o Annunciator G-15.STEAM DUMP ARMED-LIT a.Adjust S/G ARV controllers to maintain intact S/G pressure in AUTO and go to Step 8.b.Adjust condenser steam dump controller HC-484 to maintain intact S/G pressure and verify in AUTO c.Place steam dump mode selector switch to MANUAL EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 9 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I~0~1 0~4 1 0~*~1~f 1~0~~4 I I*1 1 1 1 1 1 4~~~4 1 i~~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.

8 Reset SI EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 10 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED~~1\1~1 1 1 1~*1*1 1 1 1 1 1 1 1~~~1 1 1 1*1*1**1 1 1 1~CAUTION RUPTURED S/G LEVEL SHALL BE MAINTAINED GREATER THAN 5%[25%ADVERSE CNMT]DURING THE RCS COOLDOWN, UNLESS THE RUPTURED S/G IS ALSO FAULTED.NOTE: Following initiation of controlled cooldown or depressurization, RCP trip criteria is no longer applicable.

9 Initiate RCS Cooldown: a.Determine required core exit temperature from below table RUPTURED SG PRESSURE REQUIRED CORE EXIT TEMPERATURE

('F)1100 PSIG 1000 PSIG 900 PSXG 800 PSIG 700 PSXG 600 PSIG 500 PSIG 400 PSIG 300 PSIG 525 510 500 485 465 450 425 405 375 505 adverse CNMT]490 adverse CNMT]475 adverse CNMT]460 adverse CNMT]440 adverse CNMT]420 adverse CNMT]395 adverse CNMT]370 adverse CNMT 330 adverse CNMT b.IF ruptured S/G MSIV closed, THEN initiate dumping steam to condenser from intact S/G at maximum rate c.Core exit T/Cs-LESS THAN REQUIRED TEMPERATURE d.Stop RCS cooldown and stabilize core exit T/Cs less than required temperature b.Manually or locally initiate steam dump from intact S/G at maximum rate using S/G ARV.IF no intact S/G available, THEN perform the following:

o Use faulted S/G.-OR-o IF a ruptured S/G must be used.THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.c.Continue with Step 10.WHEN core exit T/Cs less than required, THEN do Step 9d.

EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE ll of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: TDAFW pump flow control valves fail open on loss of IA.10 Monitor Intact S/G Level: a.Narrow range level'-GREATER THAN 5%[25%%d 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.b.IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.

II 4 EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 12 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 f 1 4 1 1 4 4~*~~~~*1 4*1*~4 1~~4 0 I~f 0 I t~0~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 11B).ll Monitor PRZR PORVs And Block Valves: a.Power to PORV block valves AVAILABLE b.PORVs-CLOSED a.Restore power to block valves unless block valve was closed to isolate an open PORV:~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.IF block valve can NOT be closed.THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.Step 1.c.Block valves-AT LEAST ONE OPEN~c.Open one block valve unless it was closed to isolate an open PORV.

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 13 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 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.

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 14 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Monitor All AC Busses BUSSES ENERGIZED BY OFFSITE POWER o Normal feed breakers to all 480 volt busses-CLOSED o 480 volt bus voltage-GREATER THAN 420 VOLTS o Emergency D/G output breakers OPEN Perform the following:

a.IF any AC emergency bus normal feed breaker open, THEN ensure associated D/G breaker closed.b.Perform the following as necessary:

1)Close non-safeguards bus tie breakers:~Bus 13 to Bus 14 tie~Bus 15 to Bus 16 tie 2)Place the following pumps in PULL STOP:~EH pumps~Turning gear oil pump~HP seal oil backup pump 3)Restore power to MCCs.~A from Bus 13~B from Bus 15~E from Bus 15~F from Bus 15 4)Start HP seal oil backup pump.i 5)Start CNMT RECIRC fans as necessary.

6)Ensure D/G load within limits.i 7)WHEN bus 15 restored, THEN reset control room lighting.c.Try to restore offsite power to all AC busses (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).

l EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 15 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Verify Adequate SW Flow: a.Check at least two SW pumps-RUNNING a.Manually start SW pumps as power supply permits (257 kw each).IF less than two SW pumps running, THEN: 1)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 16.

EOP: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 16 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish IA to CNMT: a.Verify non-safeguards busses energized o Bus 13 normal feed-CLOSED a.Perform the following:

1)Close non-safeguards bus tie breakers:-OR-o Bus 15 normal feed-CLOSED b.Verify turbine building SW isolation valves-OPEN~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).b.Manually align valves.~MOV-4613 and MOV-4670~MOV-4614 and MOV-4664 c.Verify adequate air compressors

-RUNNING d.Check IA supply: o Pressure-GREATER THAN 60 PSIG o Pressure-STABLE OR INCREASING

, c.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 16.WHEN IA restored, THEN do Steps 15e and f.e.Reset both trains of XY relays for IA to CNMT AOV-5392 Verify IA to CNMT AOV-5392-OPEN(

EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 17 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**I*I**I I I t*I I*I I I*~t I I I I I t I I I t I I t I I I~~CAUTION RCS PRESSURE SHOULD BE MONITORED.

IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG[465 PSIG ADVERSE CNMT].THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.~I I~I I******I***~~*I I I I I I I~I~~*~I*~*~~~16 Check Xf RHR Pumps Should Be Stopped: a.Check RCS pressure-GREATER THAN 250,psig[465 psig adverse CNMT]b.Stop RHR pumps and place both in AUTO a.Go to Step 17.

y'S&~1~I'~~~.~~"%~I I EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 18 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Establish Charging Flow: a.Charging pumps-ANY RUNNING a.Perform the following:

1)IF CCW flow is lost to any RCP thermal barrier OR any RCP gl seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to locally close seal injection needle valves to affected RCP.~V-300A for RCP A~V-300B for RCP B 1 2)Ensure HCV-142 demand at 0%.b.Align charging pump suction to RWST: o LCV-112B-OPEN o LCV-112C-CLOSED c.Start charging pumps as necessary and establish 75 gpm total charging flow~Charging line flow~Seal injection b.IF LCV-112B can NOT be opened, THEN dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).IF LCV-112C can NOT be closed, THEN perform the following:

1)Verify charging pump A NOT running and place in PULL STOP.2)Direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).

0~I IL t Hl k$~

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 19 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Check If RCS Cooldown Should Be Stopped: a.Core exit T/Cs-LESS THAN REQUIRED TEMPERATURE b.Stop RCS cooldown c.Stabilize core exit T/Cs-LESS THAN REQUIRED TEMPERATURE a.Do NOT proceed until core exit T/Cs less than required temperature.

19 Check Ruptured S/G Pressure-STABLE OR INCREASING IF pressure continues to decrease to less than 250 psi above the pressure of the intact S/G, THEN go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.Step 1.20 Check RCS Subcooling Based On Core Exit T/Cs-GREATER THAN 20 F USING FIGURE MIN SUBCOOLING Go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1

\~" f W 5'~

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 20 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: SI ACCUMs may inject during RCS depressurization.

21 Depressurize RCS To Minimize Break Flow And Refill PRZR: a.Check the following:

o Ruptured S/G level-LESS THAN 90%[80%adverse CNMT]o Any RCP-RUNNING o IA to CNMT-AVAILABLE b.Spray PRZR with maximum available spray until ANY of the following conditions satisfied:

o PRZR level-GREATER THAN 75%[65%adverse CNMT]-OR-o RCS pressure-LESS THAN SATURATION USING FIGURE MIN SUBCOOLING-OR-o BOTH of the following:

1)RCS pressure-LESS THAN RUPTURED S/G PRESSURE 2)PRZR level-GREATER THAN 5%[30%adverse CNMT]c.Close normal PRZR spray valves: 1)Adjust normal spray valve controller to 0%DEMAND 2)Verify PRZR spray valves CLOSED~PCV-431A~PCV-431B d.Verify auxiliary spray valve (AOV-296)-CLOSED e.Go to Step 24 a.Go to Step 22.c.Stop associated RCP(s).d.Decrease charging speed to minimum and ensure charging valve to loop B cold leg open (AOV-294).

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 21 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o THE PRT MAY RUPTURE IF A PRZR PORV IS USED TO DEPRESSURIZE THE RCS.THIS MAY RESULT IN ABNORMAL CNMT CONDITIONS.

o CYCLING OF THE PRZR PORV SHOULD BE MINIMIZED.

o THE UPPER HEAD REGION MAY VOID DURING RCS DEPRESSURIZATION IF RCPS ARE NOT RUNNING.THIS MAY RESULT IN A RAPIDLY INCREASING PRZR LEVEL.NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.o When using a PRZR PORV select one with an operable block valve.22 Depressurize RCS Using PRZR PORV To Minimize Break Flow And Refill PRZR: a.Verify IA to CNMT-AVAILABLE b.PRZR PORVs-AT LEAST ONE AVAILABLE a.Refer to Attachment N2 PORVS to operate PORVs.b.IF auxiliary spray available, THEN return to Step 21b.IF auxiliary spray can NOT be established, THEN go to ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL.Step 1.This Step continued on the next page.

~e~&'4~4~ll k"e II I.'h' EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 22 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 22 continued from previous page)c.Open one PRZR PORV until ANY of the following conditions satisfied:

o PRZR level-GREATER THAN 75%[65%adverse CNMT]-OR-o RCS pressure-LESS THAN SATURATION USING FIGURE MIN SUBCOOLING c.IF auxiliary spray available, THEN return to step 21b.1)IF auxiliary spray can NOT be established, THEN go to ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 1.-OR-o BOTH of the following:

1)RCS pressure-LESS THAN RUPTURED S/G PRESSURE 2)PRZR level-GREATER THAN 5%[30%adverse CNMT]d.Close PRZR PORVs d.IF either PRZR PORV can NOT be closed, THEN close associated block valve.

!n"1 EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 23 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check RCS Pressure-INCREASING Close block valve for the PRZR PORV that was opened.IF pressure continues to decrease, THEN perform the following:

a.Monitor the following conditions for indication of leakage from PRZR PORV: o PORV outlet temp (TI-438)NOT decreasing.

o PRT pressure, level or temperature continue t'o increase.b.Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.

EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 24 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED~0 t 1 1*~**1**~0 4*1 I 1 4 1 1~~0 1 I*t 1~f I*4 I 4 1*~CAUTION SI MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVENT OVERFILLING OF THE RUPTURED S/G.24 Check If SI Flow Should Be Terminated:

a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING b.Secondary heat sink: o Total feed flow to S/G(s)GREATER THAN 200 GPM AVAILABLE-OR-a.Do NOT stop SI pumps.Go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.b.IF neither condition satisfied, THEN do NOT stop SI pumps.Go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED'tep 1.o Narrow range level in at least one intact S/G-GREATER THAN 5%[25%adverse CNMT]c.RCS pressure-STABLE OR INCREASING d.PRZR level-GREATER THAN 5%[30%adverse CNMT]c.Do NOT stop SI pumps.Go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.Step 1.d.Do NOT stop SI pumps.Return to Step 6.

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 25 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Stop SI Pumps And Place In AUTO 26 Establish Required Charging Line Flow: a.Charging pumps-ANY RUNNING a.Perform the following:

1)IF CCW flow is lost to any RCP thermal barrier OR any RCP gl seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to locally isolate seal injection to affected RCP: b.Establish 20 gpm charging line flow~RCP A, V-300A~RCP B.V-3008 2)Ensure HCV-142 open.3)Start one charging pump.

E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 26 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*27 Monitor SI Reinitiation Criteria: a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING b.PRZR level-GREATER THAN 5%[30%adverse CNMT]a.Manually start SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.b.Control charging flow to maintain PRZR levels IF PRZR level can NOT be maintained, THEN manually start SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.Step 1.

1.I~

EOP: E-3 STEAM GENERATOR TUBE RUPl'URE REV: 27 PAGE 27 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check If SI ACCUMs Should Be Isolated: a.Check the following:

o RCS subcooling based on core exit T/Cs-GREATER THAN 0 F USING FIGURE MIN SUBCOOLING o PRZR level-GREATER THAN 5'/o[30%%d adverse CNMT]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 a.Manually operate SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.d.Locally reopen breakers for MOV-841 and MOV-865~ACCUM A.AOV-834A~ACCUM B.AOV-834B 2)Open HCV-945.

EOP: E-3 STEAM'GENERATOR TUBE RUPTURE REV: 27 PAGE 28 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 Verify Adequate SW Flow To CCW Hx: a.Verify at least three SW pumps RUNNING b.Verify AUX BLDG SW isolation valves-AT LEAST ONE SET OPEN a.Manually start pumps as power supply permits (257 kw each).IF less than two SW pumps can be operated, THEN go to Step 36.b.Manually align valves.~MOV-4615 and MOV-4734~MOV-4616 and MOV-4735 c.Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE ALARM-EXTINGUISHED c.Dispatch'O to locally throttle flow to CCW Hx to between 5000 gpm and 6000 gpm total flow.

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 29 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 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 36.WHEN IA restored, THEN do Steps 30 through 35.b.Verify instrument bus D-ENERGIZED c.CCW pumps-ANY RUNNING d.Charging pump-ANY RUNNING b.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.c.Perform the following:

1)IF any RCP gl seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected RCP(s).~RCP A, MOV-749A and MOV-759A~RCP B, MOV-749B and MOV-759B 2)Manually start one CCW pump.d.Continue with Step 36.WHEN any charging pump running, THEN do Steps 31 through 35.

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 30 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Check If Seal Return Flow Should Be Established:

a.Verify RCP gl seal outlet temperature

-LESS THAN 235 F b.Verify RCP seal outlet valves-OPEN~AOV-270A~AOV-270B a.Go to Step 32.b.Manually open valves as necessary.

c.Reset both trains of XY relays for RCP seal return isolation valve MOV-313 d.Open RCP seal return isolation valve MOV-313 e.Verify RCP$1 seal leakoff flow-LESS THAN 6.0 GPM d.Perform the following:

1)Place MOV-313 switch to OPEN.2)Dispatch AO with key to RMST gate to locally open MOV-313.e.Perform the following:

1)Trip the affected RCP 2)Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve f.Verify RCP tl seal leakoff flow GREATER THAN 0.8 GPM~RCP A.AOV-270A~RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 32.f.Refer to AP-RCP.l, RCP SEAL MALFUNCTION.

Ji tet fOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 31 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 Verify PRZR Level-GREATER THAN 13%[40%adverse CNMT]Continue with Step 34.WHEN PRZR level increases to greater than 13%[40%adverse CNMT], THEN do Step 33.33 Establish Normal Letdown: a.Establish charging line flow to REGEN Hx-GREATER THAN 20 GPM b.Place the following switches to CLOSE:~Letdown orifice valves (AOV-200A, AOV-2008, and AOV-202)~Letdown isolation valve AOV-371~Loop B cold leg to REGEN Hx AOV-427 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 f.Open letdown orifice valves as necessary g.Place TCV-130 in AUTO at 105'F h.Place PCV-135 in AUTO at 250 psig i.Adjust charging pump speed and HCV-142 as necessary 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.

~I\~~

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 32 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 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 2)RMW control armed-RED LIGHT LIT c.Adjust controls as necessary.

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.

A'f~I~'4 (~wc~I~

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 33 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 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 with Step 36.WHFN VCT level greater than 40%, THEN do Step 35b.b.Manually align valves as necessary.

iV, EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 34 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED~0 4~4 1 I 1 I 1't I 4 4 1~4~f f I~1 1 4 4 I 4~~4~*~****~~CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.*36 Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondary Leakage: a.Perform appropriate action(s)from table: PRZR LEVEL RUPTURED S/G NARROW RANGE LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13%[40%ADVERSE CNMT]BETWEEN 13%[40%ADVERSE CNMT]AND 50%BETWEEN 50%AND 75%[65%ADVERSE CNMT]GREATER THAN 75%[65%ADVERSE CNMT]o Increase charging flow o Depressurize RCS using Step 36b Depressurize RCS using Step 36b o Depressurize RCS using Step 36b o Decrease charging flow o Decrease charging flow Increase charging flow Energize PRZR heaters Energize PRZR heaters Energize PRZR heaters o Increase charging flow o Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal b.Control pressure using normal PRZR spray.if available, to obtain desired results for Step 36a b.IF letdown is in service, THEN use auxiliary spray (AOV-296).

IF NOT, THEN use one PRZR PORV.

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 35 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 37 Monitor If CNMT Spray Should Be Stopped: a.CNMT spray pumps-ANY RUNNING b.Verify CNMT pressure-LESS THAN 4 PSIG c.Reset CNMT spray d.Check NaOH tank outlet valves CLOSED~AOV-836A~AOV-836B a.Go to Step 38 b.Continue with Step 38.WHEN CNMT pressure less than 4 psig.THEN do Steps 37c through f.d.Place NaOH tank outlet valve controllers to MANUAL and close valves.e.Stop CNMT spray pumps and place in AUTO f.Close CNMT spray pump discharge valves~MOV-860A~MOV-860B~MOV-860C~MOV-860D

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 36 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 Check If Emergency D/Gs Should Be Stopped: a.Verify AC emergency busses energized by offsite power: o Emergency D/G output breakers OPEN a.Try to restore offsite power (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).o AC emergency bus voltage GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers-CLOSED b.Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)39 Minimize Secondary System Contamination:

a.Isolate reject from hotwell to CST: o Place hotwell level controller (LC-107)in MANUAL at 50/o a.IF hotwell level increasing.

THEN direct RP to sample hotwells for activity.o Verify hotwell level-STABLE b.Check status of local actions to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G)

~i I~-4.'5 k EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 37 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 40 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 41 Check RCP Cooling: a.Check CCW to RCPs: Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).o Annunciator A-7.RCP 1A CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED o Annunciator A-15, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED b.Check RCP seal injection:

o Labyrinth seal D/Ps-GREATER THAN 15 INCHES OF WATER-OR-o RCP seal injection flow to each RCP-GREATER THAN 6 GPM I t EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 38 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 I 1 I 1 4 4 1 4 0~1 i 0 0 I*4**0*1 4 1 0~0 4~1 P I~0~~4**CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

42 Check RCP Status: a.RCPs-AT LEAST ONE RUNNING b.Stop all but one RCP a.Perform the following:

l)Try to start one RCP: a)Ensure conditions for starting an RCP.o Bus llA or llB energized.

o Refer to Attachment RCP START.')IF RVLIS level (no RCPs)less than 95%.THEN perform the following:

o Increase PRZR level to greater than 65%[82%adverse CNMT].o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20 F using Figure MIN SUBCOOLING.

o Energize PRZR heaters as necessary to saturate PRZR water c)Start one RCP.2)IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).IF natural circulation can NOT be verified.THEN increase dumping steam.

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 39 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

43 Check If Source Range Detectors Should Be Energized:

a.Source range channels DEENERGIZED a.Go to Step 43e.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.c.Check the following:

o Both intermediate range channels-LESS THAN 10 10 AMPS 2)Continue with Step 44.WHEN flux is LESS THAN 10 10 amps on any operable channel, THEN do Steps 43c through e.c.Continue with Step 44.WHEN either condition met, THEN do Steps 43d 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 44.

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 40 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 44 Establish Normal Shutdown Alignment:

a.Check condenser-AVAILABLE a.Dispatch AO to perform Attachment SD-2.b.Perform the following:

o Open generator disconnects

~1G13A71~9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump c.Verify adequate Rx head cooling: 1)Verify at least one control rod shroud fan-RUNNING 2)Verify one Rx compartment cooling fan-RUNNING 1)Manually start one fan as power supply permits (45 kw)2)Perform the following:

o Dispatch AO to reset UV relays at MCC C and MCC D.o Manually start one fan as power supply permits (23 kw)d.Verify Attachment SD-1-COMPLETE EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV 27 PAGE 41 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 45 Consult TSC To Determine Appropriate Post-SGTR Cooldown Procedure:

o Go to ES-3.1.POST-SGTR COOLDOWN USING BACKFILL, Step 1-OR-o Go to ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, Step 1-OR-o Go to ES-3.3.POST-SGTR COOLDOWN USING STEAM DUMP, Step 1-END-

EOP: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 1 of 1 E-3 APPENDIX LIST TITLE 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLING (FIG-I.O)3)ATTACHMENT CNMT RECIRC FANS (ATT-4.0)4)ATTACHMENT D/G STOP (ATT-8.1)S)ATTACHMENT N2 PORVS (Arr-12.0) 6)ATTACHMENT NC (Arr-13.0) 7)ATTACHMENT SEAL COOLING (Arr-15.2) 8)ATTACHMENT RCK" START (Arr-Is.o) 9)ATTACHMENT RUPTURED S/G (Arr-16.0) 10)ATTACHMENT SD-1 (Arr-17.0) 11)ATTACHMENT SD-2 (Arr-17.1) 12)FOLDOUT

E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 1 of 1 RED PATH

SUMMARY

a~b.C.d.e.SUBCRXTXCALITY

-Nuclear power greater than 5%CORE COOLING-Core exit T/Cs greater than 1200'-OR-Core exit T/Cs greater than 700 F AND RVLIS level (no RCPs)less than 52%[55%adverse CNMT]HEAT SINK-Narrow range level in all S/Gs less than 5-:[25%adverse CNMT]AND total feedwater flow less than 200 gpm INTEGRITY-Cold leg temperatures decrease greater than 100'in last 60 minutes AND RCS cold leg temperature less than 285'CONTAINMENT

-CNMT pressure greater than 60 psig E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 1 of 1 FOLDOUT PAGE SI REINITIATION CRITERIA Following SI termination, IF either condition listed below occurs, THEN start SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1: o RCS subcooling based on core exit T/Cs-LESS THAN O'USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.

OR 2.o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%[30%adverse CNMT].SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1, UNLESS faulted S/G needed for RCS cooldown.3.4.5.COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.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).MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.