ML17263A197

Rev 11 to EOP E-1, Loss of Reactor or Secondary Coolant.

ML17263A197
Person / Time
Site:	Ginna
Issue date:	03/24/1993
From:	Marlow T ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A191	List: ML17263A188 ML17263A193 ML17263A194 ML17263A197 ML17263A199 ML17263A200 ML17263A204
References
E-1, NUDOCS 9304080163
Download: ML17263A197 (194)

Text

EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 1 of 16 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE l v>>PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY: ,9304080163 930330"." PDRADOCK 05000244 P..""'PDR 1 P g'f EOP: E-1 TLTLE: LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 2 of 16 A.PURPOSE-This procedure provides actions to recover from a loss of reactor or secondary coolant.B.ENTRY CONDITIONS/SYMPTOMS l.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 0 g REACTOR TRI P OR SAFETY I N JECTION g ECA 2 1 g 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-1.1, 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 g LOSS OF ALL AC POWER RECOVERY WITH S I REQUIRED I 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 r established.

i.FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, if RCS pressure is less than all non-faulted S/G(s)pressure.j.FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs are close.

EOP: E-1 TITLE: 'LOSS OF REACTOR OR SECONDARY COOLANT REV: 11 PAGE 3 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************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'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+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 I E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: ll PAGE 4 of 16 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 IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN verify faulted S/G isolated unless needed for RCS cooldown: o Pressure in both S/Gs-GREATER THAN 100 PSIG~Steamlines

~Feedlines IF NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step l.*****************************************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).NOTE: TDAFW pump flow control valves fail open on loss of IA.*3 Monitor Intact S/G Levels: a.Narrow range level-GREATER THAN 58[258 adverse CNMT]b.Control feed flow to maintain narrow range level between 178[258 adverse CNMT]and 508 a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 58[258 adverse CNMT]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.

W 1 N EOP!E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV 11 PAGE 5 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check Secondary Radiation Levels-NORMAL o Steamline radiation monitor (R-31 and R-32)o Request HP 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.*****************************************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:~MOV-515, MCC C position 6C~MOV-516, MCC D 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 C position 6C~MOV-516, MCC D position 6C c.Open one block valve unless it was closed to isolate an open PORV.

K EOP!E-1 TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 6 of 16 ,STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************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.

6 Reset SZ 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 (258 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 I E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 11 PAGE 7 of 16 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 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'ECIRC 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.

f)

E-l.LOSS OF REACTOR OR SECONDARY COOLANT REV: 11 PAGE 8 of 16 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 LOSS OF REACTOR OR SECONDARY COOLANT REV 11 PAGE 9 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ll 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 RCP¹1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal in)ection needle valve(s)to affected RCP:~V-300A for RCP A~V-300B for RCP B b.Charging pump suction aligned to RWST'LCV-112B-OPEN o LCV-112C-CLOSED 2)Ensure HCV-142 open, demand at 0%.b.Manually align valves as necessary.

IF LCV-112B can NOT be opened, 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)Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).3)WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).

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EOP: E-1 T1TLE: LOSS OF REACTOR OR SECONDARY COOLANT REV 11 PAGE 10 of 16 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]o Pressure-STABLE OR INCREASING a.Do NOT stop SI pumps.Go to Step 14.b.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING b.Do NOT stop SI pumps.Go to Step 14.c.Secondary heat sink: o Total feed flow to intact S/Gs-GREATER THAN 200 GPM-OR-c.IF neither condition satisfied, THEN do NOT stop SI pumps.Go to Step 14.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]d;Do NOT stop SI pumps'erform the following:

1)IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.2)Go to Step 14.

EOP s E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: ll PAGE 11 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Go To ES-1.1, SI TERMINATION/

Step 1*14 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 15.b.Continue with Step 15.WHEN BOTH conditions satisfied, THEN do'Steps 14c 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 C

EOP: E-1 TITLE.LOSS OF REACTOR OR SECONDARY COOLANT REV: 11 PAGE 12 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************, 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 TO LESS THAN 250 PSIG[465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.*15 Monitor If RHR Pumps Should.Be Stopped: a.Check RCS pressure: 1)Pressure-GREATER THAN 250 psig[465 psig adverse CNMT]2)RCS pressure-STABLE OR~INCREASING b.Stop RHR pumps and place in AUTO 1)Go to Step 17.2)Go to Step 16.16 Check RCS And S/G Pressures a.Check pressures in both S/Gs STABLE OR INCREASING a.Return to Step 1.b.Check pressures in both S/Gs-GREATER THAN 100 PSIG c.Check RCS pressure-STABLE OR DECREASING b.Monitor RCS pressure.IF RCS pressure does NOT increase after faulted S/G dryout, THEN go to Step 17.c.Return to Step l.

EOP: E-1 TLTLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 11 PAGE 13 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 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)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)WHEN bus 15 restored, THEN reset control room lighting breaker.6)Refer to Attachment SI/UV for other equipment lost with loss of offsite power.7)Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).b.Stop any unloaded emergency D/G~and place in standby (Refer to Attachment D/G STOP)

EOP E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV'1 PAGE 14 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify CNMT Sump Recirculation Capability:

a.Check RHR system: 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 1.o MCC C-ENERGIZED o Bus 16 and bus 17-ENERGIZED o MCC D-ENERGIZED 2)RHR pumps and valves 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.

II E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV 11 PAGE 15 of 16 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 HP to obtain following samples:~RCS boron~RCS activity~CNMT hydrogen~CNMT sump boron~BASTs,boron a.Notify HP 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.c.Verify adequate Rx head cooling: 1)Check IA to CNMT-AVAILABLE 2)Verify at least one control rod shroud fan-RUNNING 3)Verify, one Rx compartment cooling fan-RUNNING 1)Go to Step 20.2)Manually start one fan as power supply permits (45 kw)3)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 11 PAGE 16 of 16 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, 21 Check If Transfer To Cold Leg Recirculation Is Required: a.RWST level-LESS THAN 28%b.Go to ES-1;3, TRANSFER TO COLD LEG RECIRCULATION, Step 1 a.Return to Step 18.-END-I EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 11 PAGE 1 of 1 E-1 APPENDIX LIST TITIZ PAGES 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLING 3)ATTACHMENT CNMT RECIRC 4)ATTACHMENT D/G STOP 5)ATTACHMENT SD-1 6)ATTACHMENT SI/UV 7)ATTACHMENT MIN SW 8)ATTACHMENT AUX BLDG SW 9)ATTACHMENT SW LOADS IN CNMT 10)FOLDOUT

EOP s E-1 T1TLE0 LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 1 of 1 RED PATH

SUMMARY

a.SUBCRITICALITY

-Nuclear power greater than 54 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'34[464 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.E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature From Figure Below[-]Core Exit T/C Indication RC 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 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVE E CNMT RS NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE

('F)

EOP: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV 11 PAGE 1 of 1 FOLDOUT PAGE 1.SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually operate SI pumps as necessary:

o RCS subcooling based on core exit T/Cs-LESS THAN O'F USING FIGURE MIN SUBCOOLING OR-o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%[30%adverse CNMT]2~SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, SI TERMINATION, Step 1: a.RCS subcooling based on core exit T/Cs-GREATER THAN 0 F USING FIGURE MIN SUBCOOLING b.Total feed flow to intact S/Gs-GREATER THAN 200 GPM OR-Narrow range level in at least one intact S/G-GREATER THAN 5%[25%adverse CNMT]c.RCS pressure: o GREATER THAN 1625 PSIG[1825 psig adverse CNMT]o STABLE OR INCREASING d.PRZR level-GREATER THAN 5%[30%adverse CNMT]3.SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.4.COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step.l.5.AFW SUPPLY SWITCHOVER CRITERION IF CST'evel decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).6.E-3 TRANSITION CRITERIA IF any S/G'level increases in an uncontrolled manner or any S/G has abnormal radiation, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.

EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 1 of 38 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW 1 PORC REVIEW DATE k'LANT SUPERINTENDENT EFFECTIV DATE CATEGORY 1.0 REVIEWED BY:

0 f IC K c A aJ pP,*t EOP: E-3 JITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 2 of 38 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 CONDITIONS/SYMPTOMS l.ENTRY CONDITIONS

-This procedure is entered from: a.E-O, REACTOR TRIP OR SAFETY INJECTION, when condenser air ejector radiation or blowdown radiation is abnormal, or b~E 0 g REACTOR TRIP OR SAFETY INJECTION/

E 1/LOSS OF REACTOR OR SECONDARY COOLANT g E-2, FAULTED STEAM GENERATOR ISOLATION, and FR HE 3 RESPONSE TO STEAM GENERATOR HIGH LEVELS when secondary radiation is abnormal, or c.E-O, REACTOR TRIP OR SAFETY INJECTION/

E 1 g LOSS OF REACTOR OR SECONDARY COOLANT g ES 1~2 g POST LOCA COOLDOWN AND DEPRESSURI ZATION g ECA 3~3 g SGTR WITHOUT PRESSURI ZER PRESSURE CONTROLS when an intact S/G narrow range level increases in an uncontrolled manner.d ECA 3~3~SGTR WITHOUT PRESSURI ZER PRESSURE CONTROL/when pressurizer pressure control is restored.e.E-1 series FOLDOUT page'whenever either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.

~A$r a.a EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 3 of 38 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+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 CNMTj d.Stop both RCPs a.Go to Step 2.b.Go to Step 2.c.Go to Step 2.

\

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 4 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Identify Ruptured S/G(s): o Unexpected increase in either S/G narrow range level-OR-Continue with Steps 6 through 11.WHEN ruptured S/G(s)identified, THEN do Steps 3, 4 and 5.o High radiation indication on main steamline radiation monitor~R-31 for S/G A~R-32 for S/G B-OR-o AO reports local indication of high steamline radiation-OR-o RP reports high radiation from S/G activity sample 4 WJ EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 5 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED************

x****x*%*********************

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'050 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 c.IF at least one MDAFW pump running, THEN 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.Verify ruptured S/G blowdown valve-CLOSED d.Place S/G blowdown and sample valve isolation switch to CLOSE.~S/G A, AOV-5738~S/G B, AOV-5737 IF blowdown can NOT be isolated manually, THEN dispatch AO to locally isolate blowdown..

~S/G A, V-5701~S/G B, V-5702 a1 Ill I't il U EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 6 of 38 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)Place condenser steam dump mode selector switch to MANUAL.4)Adjust condenser steam dump controller to 1050 psig in AUTO.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).b.Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G part A)IF the ruptured S/G can NOT be isolated from the intact S/G, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1 L~Qt J>;

EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 7 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**********

x*a***x x x x%*x x*****************

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

l)Maintain feed flow to ruptured S/G until level greater than 5%[25%adverse CNMT).2)Continue with Step 6.WHEN ruptured S/G level greater than 5%[25%adverse CNMT], THEN do Steps 5b through e.b.Close MDAFW pump discharge valv'e to ruptured S/G b.Dispatch AO to locally close valve.~S/G A, MOV-4007~S/G B, MOV-4008 c.Pull stop MDAFW pump for ruptured S/G d.Close TDAFW pump flow control 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 valve key to locally close TDAFW pump manual feedwater isolation valve to ruptured S/G.~S/G A, V-4005~S/G B, V-4006 e.Manually close valves.~MOV-4000A~MOV-4000B U~W~p*~ga t, r.g'1 EOP: E-3 ijiLE: STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 8 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**********

x*****x**%*********************

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 6B).**************

P***x 0 x*0***x**************

• 6 Monitor PRZR PORVs And 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.PORVs-CLOSED~MOV-515, MCC C position 6C~MOV-516, MCC D 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 go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.c.Open one block valve unless it was closed to isolate an open PORV.

P'>fg EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 9 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check If S/G Secondary Side Is Intact: o Pressure in both S/Gs-STABLE OR INCREASING IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN verify faulted S/G isolated unless needed for RCS cooldown: o Pressure in both S/Gs-GREATER THAN 100 PSIG~Steamlines

~Feedlines IF faulted S/G NOT isolated, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.**********

x%**x%x 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).*******x*4*%x*x**x**%********************

NOTE: TDAFW pump flow control valves fail open on loss of IA.*8 Monitor Intact S/G Level: 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.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 l.

%tk Cg gt EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 10 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED********x*x~*%x'.*x x*a*x x**x x***x*********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.

x x x**x x*x***x******************

9 Reset SI 10 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.

x x**x x x********************

CAUTION RCS PRESSURE SHOULD BE MONITORED.

IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG[465 PSIG ADVERSE CNMT), THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.**********%

• • • • • x x**x********************

11 Check If RHR Pumps Should Be Stopped: a.Check RCS pressure: a.Go to Step 12.o Pressure-GREATER THAN 250 psig[465 psig adverse CNMTj o Pressure-STABLE OR INCREASING b.Stop RHR pumps and place both in AUTO fA~m f+J g~'k EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 11 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If ruptured S/G needed for cooldown, isolation is not necessary.

12 Verify Ruptured S/G Isolated: a.Check ruptured MSIV-CLOSED b.Ruptured S/G pressure-GREATER THAN 300 PSIG a.IF only intact S/G MSIV can be closed, THEN ensure air ejector/gland steam supply and flange heating steam isolated.(Refer to ATTACHMENT RUPTURED S/G, part B).IF neither S/G MSIV can be closed THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1 b.Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.13 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 14.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

~s'I~l I c~i~g V W EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 12 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Following initiation of controlled cooldown or depressurization, RCP trip criteria is no longer applicable.

14 Initiate RCS Cooldown: a.Determine required core exit temperature from below table RUPTURED SG PRESSURE 1100 PSIG 1000 PSIG 900 PSIG 800 PSIG 700 PSIG 600 PSIG 500 PSIG 400 PSIG 300 PSIG REQUIRED CORE EXIT TEMPERATURE

('F)525[505 adverse CNMT)510[490 adverse CNMT)500[475 adverse CNMT]485[460 adverse CNMT)465[440 adverse CNMT)450[420 adverse CNMT)425[395 adverse CNMT]405[370 adverse CNMT)375[330 adverse CNMT)b.Initiate dumping steam to condenser from intact S/G at maximum rate 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-c.Core exit T/Cs-LESS THAN REQUIRED TEMPERATURE d.Stop RCS cooldown and maintain core exit T/Cs less than required temperature o IF both S/Gs ruptured, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1 c.Continue with Step 15.WHEN core exit T/Cs less than required, THEN do Step 14d.

+k~f EOP: E-3 TtTLE: STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 13 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*15 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 CNMT RECIRC fans as necessary.

5)WHEN bus 15 restored, THEN reset control room lighting.c.Try to restore offsite power to all AC busses (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

pffft'Ill p%~I 4, r l~

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV'5 PAGE 14 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 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: 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 18.

<,1$y 4 4s jf-Qy'"9,, t 4'X;i EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 26 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 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~MOV-4615 and MOV-4734~MOV-4616 and MOV-4735 a.Manually start pumps as power supply permits (258 kw each).IF less than two SW pumps can be operated, THEN go to Step 37.b.Establish SW to AUX BLDG (Refer to Attachment AUX BLDG SW).c.Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE ALARM-EXTINGUISHED c.Dispatch AO to locally throttle flow to CCW Hx to between 5000 gpm and 6000 gpm total flow.

4 I P EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 27 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 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 37.WHEN IA restored, THEN do Steps 31 through 36.b.Verify instrument bus D ENERGIZED c.CCW pumps-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 tl seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected RCP(s).d.Charging pump-ANY RUNNING~RCP A, MOV-749A and MOV-759A~RCP B, MOV-749B and MOV-759B 2)Manually start one CCW pump.d.Continue with Step 37.WHEN any charging pump running, THEN do Steps 32 through 36.

I'1'r I V I IWg EOP: E-3 JIZLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 28 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 Check If Seal Return Flow Should Be Established:

a.Verify RCP¹1 seal outlet temperature

-LESS THAN 235'F b.Verify RCP seal outlet valves OPEN~AOV-270A~AOV-270B a.Go to Step 33.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 d.Perform the following:

1)Place MOV-313 switch to OPEN.e.Verify RCP¹1 seal leakoff flow LESS THAN 5.5 GPM 2)Dispatch AO with key to RWST gate to locally open MOV-313.e.IF any RCP seal leakoff flow greater than 5.5 gpm, THEN: o Close the affected RCP seal discharge valve~RCP A, AOV-270A~RCP B, AOV-270B f.Verify RCP¹1 seal leakoff flow GREATER THAN 0.25 GPM o Trip the affected RCP IF both RCP seal discharge valves are shut, THEN go to Step 33.f.Refer to AP-RCP.1, RCP SEAL MALFUNCTION.

I.'~I~.4 Al tg~Ck EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 29 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 Verify PRZR Level-GREATER THAN 13%[40: adverse CNMT]Continue with Step 35.WHEN PRZR level increases to greater than 13%[40%adverse CNMT], THEN do Step 34.34 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-200B, 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 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 i.Adjust charging pump speed and HCV-142 as necessary A h EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 30 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Check VCT Makeup System: a.Adjust boric acid flow control valve in AUTO to 9.5 gpm b.Verify the following:

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

2)RMW control armed-RED LIGHT LIT c.Check VCT level: o Level-GREATER THAN 20%-OR-o Level-STABLE OR INCREASING c.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.

I>~M t~, M.lt Cg~a~4~I P h~4 EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 31 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 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 37.WHEN VCT level greater than 40%, THEN do Step 36b.b.Verify charging pumps aligned to VCT o LCV-112C-OPEN o LCV-112B-CLOSED b.Manually align valves as necessary.

Pp<<4.ig%1EP EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 32 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**************

x**x*x x x*******************

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

• 37 Control RCS Pressure And Makeup 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 CNMTJ BETWEEN 13%[40%ADVERSE CNMT)AND 50%BETWEEN 50%AND 75%[65%ADVERSE CNMTj GREATER THAN 75%[65%ADVERSE CNMT]o Increase RCS makeup flow o Depressurize RCS using Step 37b Depressurize RCS using Step 37b o Depressurize RCS using Step 37b o Decrease RCS makeup flow o Decrease RCS makeup flow Increase RCS makeup flow Energize PRZR heaters Energize PRZR heaters Energize PRZR heaters o Increase RCS makeup 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 37a b.IF letdown is in service, THEN use auxiliary spray (AOV-296).

IF NOT, THEN use one PRZR PORV.

I')~4 N 1g'0'1I+S EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 33 of 38 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.1, 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'.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) l I h EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 34 of 38 STEP ACTION/EXPECTED'ESPONSE 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

EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 35 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED******xx x*0 xxxxx%xx'xx%'*x 4***x****x*******

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

• • • • • • • • • • • • 4*4 x x w*~************'*********42 Check RCP Status: a.RCPs-AT LEAST ONE RUNNING b.Stop all but one RCP a.Perform the following:

1)Try to start one RCP: a)Ensure conditions for starting an RCP.o Bus llA or 11B energized.

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

o Increase PRZR level to greater than 65%(80%adverse CNMTj.o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20'F using Figure MIN SUBCOOLING.

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.

ig$V J~w II'gl e EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 36 of 38 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.2)Continue with Step 44.WHEN flux is LESS THAN 10 amps on any operable channel, THEN do Steps 43c through e.c.Check the following:

o Both intermediate range channels-LESS THAN 10 10 AMPS 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).IF source ranges can'OT be restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 44.e.Transfer Rk-45 recorder to one source range and one intermediate range channel I 4Q A~

EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 37 of 38 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:

i 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)Check IA to CNMT-AVAILABLE 2)Verify at least one control rod shroud fan-RUNNING 3)Verify one Rx compartment cooling fan-RUNNING 1)Go to Step 45.2)Manually start one fan as power supply permits (45 kw)3)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

~m ,~~l~l, EOP: E-3 LITLE: STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 38 of 38 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-

~lt 4 elhi 7 X EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 1 of 1 E-3 APPENDIX LIST TITLE 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLING 3)ATTACHMENT CNMT RECIRC FANS 4)ATTACHMENT D/G STOP 5)ATTACHMENT N2 PORVS 6)ATTACHMENT NC 7)ATTACHMENT SEAL COOLING 8)ATTACHMENT RCP START 9)ATTACHMENT RUPTURED S/G 10)ATTACHMENT SD-1 11)ATTACHMENT SD-2 12)ATTACHMENT AUX BLDG SW 13)FOLDOUT PAGES 4

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV 15 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~~[464 adverse CNMT]c.HEAT SINK-Narrow range level in all S/Gs less than 54[25<adverse CNMT]AND total feedwater flow less than 200 gpm d.INTEGRITY-Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F e.CONTAINMENT

-CNMT pressure greater than 60 psig

'p V',II Ijf r'-Il+~" I'~f c I, I~4 EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV 15 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature From Figure Below t'-]Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION E C DV ERS NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE

(')

J'-

EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 15 PAGE 1 of 1 SI REINITIATION CRITERIA FOLDOUT PAGE IF either condition listed below occurs, THEN operate SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1: o RCS subcooling based on core exit T/Cs-LESS THAN 0 F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.

OR 2 4 o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%[304 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 1.3~COLD LEG RECIRCULATION SWITCHOVER CRITERION 4.5.IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step l.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.

tel 5t EOP: ECA-2'T1TLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 1 of 31 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RES 0 SIBLE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY

EOP: ECA-2-1 TLTLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 2 of 31 A.PURPOSE-This procedure provides actions to mitigate and minimize a loss of secondary coolant from both steam generators.

B.ENTRY CONDITIONS/SYMPTOMS 1-ENTRY CONDITIONS

-This procedure is entered from: a.E-2, FAULTED STEAM GENERATOR ISOLATION, when an uncontrolled depressurization of both steam generators occurs.

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATZON OF BOTH STEAM GENERATORS REV: 12 PAGE 3 of 31 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: o FOLDOUT page should be open AND monitored periodically.

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+R/hr.1 Check Secondary Pressure Boundary: o MSIVs-CLOSED o MFW flow control valves-CLOSED~MFW regulating valves~MFW bypass valves o MFW pump discharge valves CLOSED V o S/G blowdown and sample valves CLOSED Manually close valves one loop at a time.IF valves can NOT be closed, THEN dispatch AO to locally isolate flowpaths, as necessary, one loop at a time.o TDAFW pump steam supply valves PULL STOP o TDAFW pump flow control valves CLOSED o S/G ARVs-CLOSED o Dispatch AO to locally isolate S/Gs (Refer to Attachment FAULTED S/G)

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 4 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION A MINIMUM FEED FLOW OF 50 GPM MUST BE MAINTAINED TO EACH S/G WITH A NARROW RANGE LEVEL LESS THAN 5%[25%ADVERSE CNMT].*****************************************2 Control Feed Flow To Minimize RCS Cooldown: a.Check cooldown rate in RCS cold legs-'ESS THAN 100'F/HR b.Check narrow range level in both S/Gs-LESS THAN 50%a.Decrease feed flow to 50 gpm to each S/G and go to Step 2c.b.Control feed flow to maintain narrow range level less than 50%in both S/Gs.c.Check RCS hot leg temperatures STABLE OR DECREASING c.Control feed flow or dump steam to stabilize RCS hot leg temperatures.

3 Check If RCPs Should Be Stopped: 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 4.b.Go to Step 4.'.Go to Step 4.

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 5 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check CST Level-GREATER THAN 5 FEET'witch to alternate AFW suction supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).*****************************************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 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 C position 6C~MOV-516, MCC D 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 C position 6C~MOV-516, MCC D position 6C c.'Open one block valve unless it was closed to isolate an open PORV.

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 6 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check Secondary Radiation Levels-NORMAL o Steamline radiation monitor (R-31 and R-32)o Dispatch AO to locally check steamline radiation Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.o Request RP sample S/Gs for activity*****************************************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: ECA-2~1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV 12 PAGE 7 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION RCS PRESSURE SHOULD BE MONITORED.

IF.RCS PRESSURE DECREASES TO LESS THAN 250 PSIG[465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.*8 Monitor If RHR Pumps Should Be Stopped: a.RHR pumps-ANY RUNNING b.Check RCS Pressure: a.Go to Step 9.1)Pressure-GREATER THAN 250 psig[465 psig adverse CNMT]2)Pressure-STABLE OR INCREASING 1)Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.2)Go to Step 9.c.Stop RHR pumps and place in AUTO

EOP: ECA-2~1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 8 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*9 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 10.b.Continue with Step 10.WHEN BOTH conditions satisfied, THEN do Steps 9c 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.~AOV-836A~AOV-836B e.Stop CNMT spray pumps and place in AUTO f.Close CNMT spray pump discharge valves~MOV-860A~MOV-860B~MOV-860C~MOV-860D, l~

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 9 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check RWST Level-GREATER THAN 284 Go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step l.ll 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.

12 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:

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 14.

EOP: ECA-2.1 T!TLE: UNCONTROLLED DEPRESSURXZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 10 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 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 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.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)C'ontinue attempts to restore IA (Refer,to AP-IA.1, LOSS OF INSTRUMENT AIR).2)Continue with Step 14.WHEN IA restored, THEN do Steps 13e and f.

EOP: ECA-2'T!TLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 11 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If SI ACCUMs Should Be Isolated: a.Both RCS hot leg temperatures LESS THAN 400'F a.Go to Step 15.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-945.15 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;ECA-2.1 T!TLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 12 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 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 RCP¹1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s)to affected RCP:~RCP A, V-300A~RCP B, V-300B 2)Ensure HCV-142 open, demand at 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.c.Start charging pumps as'ecessary and adjust charging flow to restore PRZR level 2)Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).3)WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 13 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*17 Monitor SI Termination Criteria: a.SI pumps-ANY RUNNING b.Check RCS pressure: o Pressure-GREATER THAN 1625 psig[1825 psig adverse CNMT]o Pressure-STABLE OR INCREASING a.Go to Step 19.b.DO NOT stop SI pumps'~, Perform the following:

1)Energize PRZR heaters and operate PRZR spray as necessary to stabilize RCS pressure greater than 1625 psig[1825 psig adverse CNMT)c.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING 2)Return to Step 2.c.DO NOT stop SI pumps.Return to Step 2.d.PRZR level-GREATER THAN 5%[30%adverse CNMT)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)Return to Step 17a.NOTE: Foldout Page E-2 transition criteria does not apply while performing steps 18 and 19.18 Stop SI and RHR Pumps And Place In Auto

EOP: ECA 2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 14 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*19 Monitor SI Reinitiation Criteria: a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Manually operate SI pumps as necessary and return to Step 2.b.PRZR level-GREATER THAN 5%[30%adverse CNMT]b.Control charging flow to maintain PRZR level.IF PRZR level can NOT be maintained, THEN manually operate SI pumps as necessary and return to Step 2.20 Check RCS Hot Leg Temperatures

-STABLE OR DECREASING Control feed flow or dump steam to stabilize RCS hot leg temperatures.

21 Check Narrow Range Level In Both S/Gs-LESS THAN 504 Control feed flow to maintain narrow range level less than 50%in both S/Gs.22 Verify Adequate SW Flow To CCW Hx: a.Verify at least two SW pumps RUNNING b.Verify AUX BLDG SW isolation valves-OPEN~MOV-4615 and MOV-4734~MOV-4616 and MOV-4735 a.Manually start pumps as power supply permits (258 kw per pump).IF less than two SW pumps can be operated, THEN go to Step 28'.Establish SW to AUX BLDG (Refer to Attachment AUX BLDG SW).c.Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE AIARM-EXTINGUISHED c.Dispatch AO to locally throttle flow to CCW Hx to between 5000 gpm and 6000 gpm total flow.

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 15 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 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 28.WHEN IA restored, THEN do Steps 23 through 27.b.Verify instrument bus D-ENERGIZED b.Energize MCC B.IF MCC B NOT available, THEN perform the following:

c.CCW pumps-ANY RUNNING d.Charging pump-ANY RUNNING 1)Verify MCC A energized.

2)Place instrument bus D on maintenance supply.c.Perform the following:

1)IF any RCP¹1 seal outlet temperature of f scale 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 28.WHEN any charging pump running, THEN do Steps 24 through 27.

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 16 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 Verify PRZR Level-GREATER THAN 134[40%adverse CNMT]Continue with Step 26.WHEN PRZR level increases to greater than 13%[40%adverse CNMT], THEN do Step 25.25 Establish Normal Letdown: a.Verify charging line flow to REGEN Hx-GREATER THAN 20 GPM b.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'alve 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 i.Adjust charging pump speed and HCV-142 as necessary

EOP: ECA-2.1 T1TLE UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 17 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 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.

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURXZATION OF BOTH STEAM GENERATORS REV 12 PAGE 18 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 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 28.WHEN VCT level greater than 40%, THEN do'tep'7b.

b.Verify charging pumps aligned to VCT: o LCV-112C-OPEN o LCV-112B-CLOSED b.Manually align valves as necessary.

EOP: ECA-'2.1 TITLES UNCONTROLLED DEPRESSURXZATZON OF BOTH STEAM GENERATORS REV 12 PAGE 19 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check RCP Cooling: a.Check CCW to RCPs: Establish normal cooling to RCPs~(Refer to Attachment SEAL COOLING).o Annunciator A-7, RCP lA 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 flov to each RCP-GREATER THAN 6 GPM

EOP: ECA-2.1 T1TLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 20 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 Check If Seal Return Flow Should Be Established:

a.Verify RCP¹1 seal outlet temperature

-LESS THAN 235'F b.Verify RCP seal outlet valves OPEN a.Go to Step 30.b.Manually open valves as necessary.

~AOV-270A~AOV-270B c.Reset both trains of XY relays for RCP seal return isolation valve MOV-313 d.Open RCP seal return isolation valve MOV-313 e.Verify RCP¹1 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 RWST 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 RCP¹1 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 30.f.Refer to AP-RCP.1, RCP SEAL MALFUNCTION.

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 21 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.o When using PRZR PORV, select one with an operable block valve.30 Energize Heaters And Operate Normal Spray As Necessary To Maintain RCS Pressure Stable IF normal'pray NOT available and letdown is in service, THEN use auxiliary spray valve (AOV-296).

IF PRZR spray NOT'vailable', THEN use one PRZR PORV.IF IA NOT available, THEN refer to Attachment N2 PORVS.

C EOP: ECA-2.1'1ILE:

UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV 12 PAGE 22 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Verify All, AC Busses-ENERGIZED BY OFFSITE PONER o Normal feed breakers to all 480 volt busses-CLOSED o 480 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 4 B from Bus 15~E from Bus 15~F from Bus 15 4)WHEN bus 15 restored, THEN reset control room lighting..

5)Refer to Attachment SI/UV for other equipment lost with loss of offsite power.c.Try to restore offsite power to all AC busses (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

I EOP: ECA-2 1 T!TLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 23 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATIONS 32 Check RCP Status-'T LEAST ONE RUNNING Try to start one RCP: a.Establish conditions for starting an RCP.o Bus 11A or 11B energized I 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 can NOT be verified, THEN increase feed flow or dumping steam.

ilk EOP: ECA-2~1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 24 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

33 Check If Source Range Detectors Should Be Energized:

a.Source range channels DEENERGIZED a.Go to Step 33e.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 34.WHEN flux is LESS THAN 10 amps on any operable channel, THEN do Steps 33c, d and e.c.Check the following:

o Both intermediate range channels-LESS THAN 10-10 AMPS c.Continue with step 34.WHEN either condition met, THEN do Steps 33d 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 34.

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 25 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 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.1, 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)

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 26 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 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 1)Manually start one fan as power supply permits (45 kw)2)Verify one Rx compartment cooling fan-RUNNING 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: ECA-F 1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 27 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 Maintain Plant Conditions-STABLE Control plant systems as necessary to maintain conditions stable.o RCS pressure o PRZR level o RCS temperatures

• 37 Monitor SI Reinitiation Criteria: a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Manually operate SI pumps as necessary.

Return to Step 2.b.PRZR level-GREATER THAN 5%[30%adverse CNMT)b.Control charging flow to maintain PRZR level.IF PRZR level can NOT be maintained, THEN manually operate SI pumps as necessary.

Return to Step 2~

'I'4 EOP: ECA-F 1 T1TLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 28 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 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.Go to Step 39.o PRZR level-GREATER THAN 5%[30%adverse CNMT]b.Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves~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.d.Locally reopen breakers for MOV-841 and MOV-865~ACCUM A;AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.

EOP: ECA-2~1 T!TLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 29 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 39 Check RCS Hot Leg Control feed flow and dump steam to Temperatures

-LESS THAN 350'F.establish RCS cooldown rate less than 100'F/hr in RCS cold legs.NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.o When using PRZR PORV, select one with operable block valve.40 Check RCS Pressure-LESS THAN 400 PSIG[300 PSIG adverse CNMT]e Use normal PRZR spray.IF normal spray NOT available and letdown is in service, THEN use auxiliary spray.IF NOT, THEN use one PRZR PORV.IF IA NOT available, THEN refer to Attachment N2 PORVS.

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 30 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 41 Check If RHR Normal Cooling Can Be Established:

a.RCS cold leg temperature

-LESS THAN 350'F a.Return to Step 37'.RCS pressure-LESS THAN 400 psig[300 psig adverse CNMT]c.Place letdown pressure controller (PCV-135)in MANUAL CLOSED b.Return to Step 40.d.Check following valves-OPEN~AOV-371, letdown isolation valve~AOV-'427, loop B cold leg to REGEN Hx~At least one letdown orifice valve (AOV-200A, AOV-200B, or AOV-202)d.Perform the following:

1)Reset both trains of XY relays for AOV-371 and AOV-427')Open AOV-371 and AOV-427.3)Open one letdown orifice valve.e.Verify pressure on PI-135-LESS THAN 400 PSIG e.Return to Step 40.f.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)g.Establish RHR normal cooling (Refer to Attachment RHR COOL)f.IF RCS overpressure protection system can NOT be placed in service, THEN notify TSC of potential Tech Spec violation if RHR system is placed in service.

EOP: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 31 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 42 Continue RCS Cooldown To Cold Shutdown: a.Maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR ,b.Check narrow range level in both S/Gs-LESS THAN 50%b.Control feed flow to maintain narrow range level less than 50%'n both S/Gs.43 Check Core Exit T/Cs-LESS THAN 200'F Return to Step 42.44 Evaluate Long Term Plant Status: a.Maintain cold shutdown conditions b.Consult TSC-END-

EOP: TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 1 of 1 ECA-2.1 APPENDIX LIST TITLE 1)RED PATH

SUMMARY

2)FIGURE MIN SUBCOOLING 3)ATTACHMENT FAULTED S/G 4)ATTACHMENT CNMT RECIRC FANS 5)ATTACHMENT NC 6)-ATTACHMENT RCP START 7)ATTACHMENT N2 PORVS 8)ATTACHMENT SEAL COOLING 9)ATTACHMENT SI/UV 10)ATTACHMENT D/G STOP 11)ATTACHMENT SD-1 12)ATTACHMENT SD-2 13)ATTACHMENT RHR COOL 14)ATTACHMENT AUX BLDG SW 15)FOLDOUT PAGES

EOP: ECA-2.1 T!TLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 1 of 1 RED PATH

SUMMARY

a.SUBCRITICALITY

-Nuclear power greater than 54 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%[464 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: ECA-2.1 TITLE: UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 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 1900'800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 20 RCS PRESSURE INCREHENTS 20 PSIG SUBCOOLED REGION INADEQUATE SUBCOOLING REGION ADVERSE CNHT TEHPERATURE INCREHENTS 10'F NORHAL CNHT 0'50 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEHPERATURE

('F)

EOP!ECA-2.1 TITLE!UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS REV: 12 PAGE 1 of 1 FOLDOUT PAGE 1.SI REINITIATION CRITERIA Manually operate SI pumps as necessary if EITHER condition listed below occurs: o RCS subcooling based on core exit TCs-LESS THAN O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54[304 ADVERSE CNMT]2.E-2 TRANSITION CRITERIA IF any S/G pressure increases at any time (except while performing SI termination in Steps 18 and 19), THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.3.COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.4.LOSS OF EMERGENCY COOLANT RECIRCULATION CRITERION IF emergency coolant recirculation is established and subsequently lost, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION,'Step 1.5.AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).