ML20044C921

Rev 9 to EOP ECA-3.1, SGTR W/Loss of Reactor Coolant - Subcooled Recovery Desired

ML20044C921
Person / Time
Site:	Ginna
Issue date:	04/21/1993
From:	Marlow T ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A278	List: ML17263A277 ML17263A279 ML17263A280 ML17263A281 ML17263A282 ML17309A518 ML20044C921
References
ECA-3.1, NUDOCS 9305140067
Download: ML20044C921 (38)

Text

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i TR WITH MSS OF M COR COO W T -

-l ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 1 of 33 I

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i ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION y

I CONTROLLED COPY NUMBER v'

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TECHNICAL REVIEW

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r PORC REVIEW DATE

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PIANT SUPERINTENDENT P

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EFFECTIVE DATE-i

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CATEGORY 1.0

'l REVIEWED BY:_

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9305140067 930505 hDR ADOCK'05000244 PDR

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TITLE:

REV: 9 R WITH LOSS OF REACTOR COOLANT -

j ECA-3*1 SUBCOOLED RECOVERY DESIRED PAGE 2 of 33 A.

PURPOSE - This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions while minimizing loss of RCS inventory and voiding in the RCS for an SGTR concurrent with a LOCA (i.e. Ruptured-Faulted S/G).

B.

ENTRY CONDITIONS / SYMPTOMS 1.

ENTRY CONDITIONS - This procedure is entered from:

a.

E-3, STEAM GENERATOR TUBE RUPTURE, if ruptured S/G can not be isolated from any intact S/G.

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b.

E-3, STEAM GENERATOR TUBE RUPTURE, if PRZR PORV can not be isolated by closing its block valve.

c.

E-3, STEAM GENERATOR TUBE RUPTURE, if ruptured S/G is faulted.

l d.

E-3, STEAM GENERATOR TUBE RUPTURE, if no intact S/G is available for RCS cooldown.

e.

E-3, STEAM GENERATOR TUBE RUPTURE, if minimum D/P between ruptured and intact S/G cannot be maintained.

s f.

E-3, STEAM GENERATOR TUBE RUPTURE, if RCS subcooling is less than required.

g.

E-3, STEAM GENERATOR TUBE RUPTURE, if RCS pressure does not increase after closing PRZR PORV and block valve.

h.

E-3, STEAM GENERATOR TUBE RUPTURE, and ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, if SI can not be terminated.

i.

E-3, STEAM GENERATOR TUBE RUPTURE, and ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, if SI is reinitiated after termination.

j E-3, STEAM GENERATOR TUBE RUPTURE, ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, and ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, if SI accumulators should not be isolated.

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ECA-3*1 SUBCOOLED RECOVERY DESIRED PAGE 3 of 33 l

!i k.

ES-3.1, POST-SGTR COOLDOWN USING BACKFILL,

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ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, and

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ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, if a non-ruptured S/G is not available for RCS cooldown.

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R WITH MSS OF REACOR COON -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 4 of 33 l

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l

STEP f

CAUTION o 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 RECIRCUIATION.

o IF PRZR LEVEL IS LESS THAN 50% OR IF ADVERSE CNMT CONDITIONS EXIST, THEN PRZR HEATERS SHOULD NOT BE ENERGIZED UNTIL PRZR LEVEL IS EVALUATED BY THE TSC.

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

NOTE: o Foldout page should be open AND monitored periodically.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

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a 1 Reset SI 1

2 Reset CI:

a. Depress CI reset pushbutton l

b. Verify annunciator A-26, CNMT

b. Perform the following:

ISOLATION - EXTINGUISHED

1) Reset SI.

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2) Depress CI reset pushbutton.

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SGTR WITH LOSS OF REACTOR COOIJdiT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 5 of 33 0

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 3 Verify Adequate SW Flow:

f

a. Check at least two SU pumps -

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

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

1) Ensure SW isolation.

2) Dispatch AO to establish i

normal shutdown alignment (Refer to Attachment SD-1).

3) Go to Step 5.

b. Dispatch AO to establish normal i

shutdown alignment (Refer to Attachment SD-1)

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TITLE:

9 ACTOR COO N -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 6 of 33

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i ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP I

4 Establish 1A to CNMT:

a. Verify non-safeguards busses

a. Perform the following:

energized from offsite power

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

-OR-

• Bus 13 to Bus 14 tie

• Bus 15 to Bus 16 tie i

o Bus 15 normal feed - CLOSED I

2) Verify adequate emergency D/G

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capacity to run air compressors (75 kw each).

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

RECIRC FANS).

b. Verify SW isolation valves to

b. Manually align valves.

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turbine building - OPEN

• MOV-4613 and MOV-4670 i

• MOV-4614 and MOV-4664

c. Verify at least two air

c. Manually start air nempresscrs compressors - RUNNING as power supply peruics (75 kw l

each). If air compressors can NOT be started, THEN dispatch A0 to locally reset compressors as necessary.

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d. Check IA supply:

d. Perform the following:

o Pressure - GREATER TRAN

1) Continue attempts to restore l

60 PSIG 1A (Refer to AP-IA.1, LOSS OF 1NSTRUMENT AIR).

o Pressure - STABLE OR INCREASING

2) Continue with Step 5.

VHEN IA restored, THEN do Steps 4e and f.

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e. Reset both trains of XY relays for IA to CNMT A0V-5392 j

f. Verify IA to CNMT ADV-5392 - OPEN l

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SGTR WITH LOSS OF REACTOR COOLANT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 7 of 33 1

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ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP

• 5 Monitor All AC Busses -

Perform the following:

BUSSES ENERGIZED BY OFFSITE POWER

a. 1F any AC emergency bus normal feed breaker open, THEN ensure o Normal feed breakers to all 480 associated D/G breaker closed.

volt busses - CLOSED

b. Perform the following, as 7

o 480 bus voltage - CREATER THAN necessary:

420 VOLTS

1) Close non-safeguards bus tie Emergency D/G output breakers -

breakers:

o OPEN

• Bus 13 to Bus 14 tie

• Bus 15 to Bus 16 tie f

2) Place the following pumps in PULL STOP:

• EH pumps

/ '

• Turning gear oil pump

• HP seal oil backup pump k

3) Restore power to MCCs.

• A from Bus 13 I

• B from Bus 15

• E from Bus 15

• F from Bus 15

4) VMEN 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).

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SGTR WITH LOSS OF REACTOR COOLANT -

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SUBCOOLED RECOVERY DESIRED PAGE 8 of 33 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP

• 6 Monitor If CimT Spray Should Be Stopped:

a. Ch3T spray pumps - ANY RUNNING

a. Go to Step 7.

b. Check the following:

b. Continue with Step 7.

WHEN BOTH conditions satisfied, THEN do o CNMT pressure - LESS THAN Steps 6c through f.

4 PSIG o Sodiu:n hydroxide tank level -

LESS THAN 55%

c. Reset CNMT spray

d. Check NaOH tank outlet valves -

d. Place NaOH tank outlet valve I

CLOSED controllers to MANUAL and close valves.

• A0V-8 36 A

• A0V-836B

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e. Stop CNMT spray pumps and place in AUTO

f. Close CNMT spray pump discharge valves

• MOV-860A

• MOV-860B

• MOV-860C

• MOV-860D i

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• 9 SGTR WITH LOSS OF REACTOR COOIANT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 9 of 33 i

l ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP f

CAUTION t

RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES TO LESS THAN

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250 PSIG [465 PSIC ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY k'ATER TO THE RCS.

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7 Check If RHR Pumps Should Be Stopped:

a. Check RCS pressure:

a. Go to Step 8.

o Pressure - CREATER THAN 250 psig [465 psig adverse l

CNMT]

o Pressure - STABLE OR INCREASING

b. Stop RHR pumps and place in AUTO t

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9 SGTR WITH LOSS OF REACTOR COOLANT -

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ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 10 of 33 O

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP CAUTION IF ANY RUPTURED S/G IS FAULIED, FEED FLOW TO THAT S/G SHOULD REMAIN IS01ATED DUx1NG SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS C00LDOWN.

• 8 Monitor Ruptured S/G Level:

a. Narrow range level - GREATER

a. IF ruptured S/G NOT faulted, THAN 5% [25% adverse CNMT)

THEN perform the following:

1) Maintain feed flow to ruptured S/G until level greater than 5% [25% adverse CNMT].

2) Continue with Step 9.

VHEN ruptured S/G level greater than St [25% adverse CNMT),

THEN do Steps Eb through e.

b. Close MDAW pump discharge valve

b. Dispatch A0 to locally close to ruptured S/G valve.

• S/G A, MOV-4007

• S/G B, MOV-4008

c. Pull stop MDAW pump for ruptured S/G

d. Close TDAW pump flow control

d. Dispatch A0 with locked valve valve to ruptured S/G key to locally close TDAW pump manual feedwater isolation valve

• S/G A, A0V-4297 to ruptured S/G.

• S/G B, A0V-4298

• S/G A, V-4005

• S/G B, V-4006

e. Verify MDA W pump crosstie

e. Manually close valves.

valves - CIDSED

• MOV-4000A

• MOV-40005

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IITLE:

S OR COO N -

ECA-3*1 SUBCOOLED RECOVERY DESIRED PAGE 11 of 33 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 1

h 9 Evaluate Plant Status:

a. Check auxiliary building

a. Notify HP and refer to radiation - NORMAL appropriate'AR-RMS procedure.

• Plant vent iodine (R-10B)

• Plant vent particulate (R 13)

+

• Plant vent gas (R-14)

• CCW liquid monitor (R-17)

• Letdown line monitor (R-9)

• CHG pump room (R-4)

b. Direct HP to obtain following i

samples:

• RCS boron I

• RCS activity

• CNMT hydrogen f

CNMT sump boron o

• BASTS boron

c. Verify adequate Rx head cooling:

1

1) Check IA to CNMT - AVAIIABLE

1) Go to Step 10.

2) Verify at least one control

2) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kv).

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3) Verify one Rx comparcment

3) Perform the following:

cooling fan - RUNNING i

o Dispatch A0 to reset UV relays at MCC C and MCC D.

Manually start one fan as l

o power supply permits (23 kv).

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SGTR WITH LOSS OF REACTOR COOLANT -

ECA-3.2 SUBCOOLED RECOVERY DESIRED PAGE 12 of 33 0

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 10 Establish 75 GPM Charging Flour-

a. Charging pumps - ANY RUNNING

a. Perform the following:

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1) 1E CCW flow is lost to any RCP thermal barrier _0.R any RCP #1 seal outlet temperature offseale high, THEN dispatch AO with RUST area key to locally isolate seal injection to affected RCP.

• RCP A. V-300A

• RCP B, V-300B

2) Ensure HCV-142 open.

b. Align charging pump suction to

b. IE LCV-112B can NOT be opened, RWST:

THEN perform the following:

o LCV-112B - OPEN

1) Verify charging pump A HOI running and place in PULL o LCV-ll2C - CLOSED STOP.

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

3) VHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from l

VCT (V-268 located in charging pump room).

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c. Start charging pumps as necessary and establish 75 gpm total charging flow l

• Charging line flow

• Seal injection O

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EOP2 IllLE:

": S SGrR wira toss or REACron cootAnr -

3,_3*1 f

SUBCOOLED RECOVERY DESIRED PAGE 13 of 33 O

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP l

I 11 Check If S/G Secondary Side If any S/G pressure decreasing in Is Intact:

an uncontrolled manner OR completely depressurized. THEN o Pressure in both S/Cs - STABLE verify faulted S/G isolated unless OR INCREASING needed for RCS cooldown:

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o Pressure in both S/Cs - GREATER

• Steamlines i

THAN 100 PSIG

= Feedlines l

l' IF NOT, THEN go to E-2, FAULTED STEAM CENERATOR IS01ATION, Step 1.

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

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L NOTE: TDAW pump flow control valves fail open on loss of IA.

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• 12 Monitor Intact S/G Levels:

a. Narrow range level - CREATER

a. Maintain total feed flow greater THAN 5% [25% adverse CNMT) than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in intact S/G.

b. Control feed flow to maintain

b. lE narrow range level in the narrow range level between 17%

intact S/G continues to increase

[25% adverse CNMT) and 50%

in an uncontrolled manner, THEN l

consider isolating unnecessary release paths:

• TDAW pump steam supply valves

• S/G blowdown valves

• Refer to Attachment RUPTURED S/G 1

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SGTR WITH LOSS OF REACTOR COOLANT -

CA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 14 of 33 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i

NOTE: Shutdowm margin should be monitored during RCS cooldosm (Refer to Figure SDM).

13 Initiate RCS Cooldown To Cold Shutdown:

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a. Establish and maintain cooldowm rate in RCS cold legs - LESS THAN 100'F/HR t

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b. Use RER system if in service

c. Dump steam to condenser from

c. Manually or locally dump steam intact S/G using intact S/G ARV.

l H no intact S/G available.

THEN perform the following:

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r o Use faulted S/C.

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-OR-o E RER system NOT in service, j

THEN use ruptured S/G.

i 14 Check RCS Subcooling Based On Go to Step 28.

Core Exit T/Cs - GREATER THAN 0*F USING FIGURE MIN SUBCOOLING t

• 15 Monitor Conditions For i

Subcooled Recovery:

a. Check RWST level - GREATER THAN

a. E CNMT sump B level is less 50%

than 113 inches THEN go to ECA-3.2, SGTR VITH IDSS OF REACTOR COOLANT - SATURATED L

RECOVERY DESIRED, Step 1.

b. Check ruptured S/G narrow level

b. Consult TSC to determine if

- LESS THAN 90% [85% adverse recovery should be completed CNMT]

using ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED.

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SGTR WITH LOSS OF REACTOR COOIANT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 15 of 33 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 16 Check Safeguards Pur.p Status Go to Step 24.

I o SI pu:tps - ANY RUNNING

-OR-l o RHR pu:rps - ANY RiiNNING IN INJECTION MODE i

17 Place PRZR Heater Switches In The Following Positions:

i o PRZR heater control group - PULL STOP o PRZR heater backup group - OFF 18 Check PRZR level - LESS THAN Go to Step 20.

13% [40% adverse CNMT) i i

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SGTR WITH LOSS OF REACTOR COOIANT -

l SUBCOOLED RECOVERY DESIRED i

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PAGE 16 of 33 f

i ACTION / EXPECTED RESPONSE RESPOSSE NOT OBTAINED STEP j

CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION, THIS L'ILL RESULT i

j IN A RAPIDLY INCREASING PRZR LEVEL.

f i

b k' hen using PRZR PORV, select one with an operable block valve.

NOTE: o l

o If auxiliary spray is in use, then spray flow may be increased by I

closing normal charging valve ADV-294 and normal PRZR spray valves, f

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19 Depressurize RCS To Refill l

PRZR:

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a. Use normal PRZR spray valve

a. Use one PRZR PORV. H IA EDT associated with running RCP available, THEN refer to f

i Attachment N2 PORVS.

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• RCP A, PCV-431A E

• RCP B, PCV-431B H no PORV available, THEN use I

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auxiliary spray valve.

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b. PRZR level - CREATER THAN 13%

b. Continue with Step 20.

L' HEN

[40% adverse CNMT]

level greater than 13% [40%

adverse CNMT), THEN stop RCS depressurization.

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c. Stop RCS depressurization I

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REV* 9 SGTR WITH LOSS OF REACTOR COOIANT -

SUBCOOLED RECOVERY DESIRED PAGE 17 of 33 i

f ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED I

STEP L

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j CAUTION I

IF RCP SEAL COOLING HAD PREVIOUSLY BEEN IDST, FAEN THE AFFECTED RCP SHOULD

'f NOT BE STARTED PRIOR TO A STATUS EVALUATION.

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20 Check If An RCP Should Be Started:

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a. Both RCPs - STOPPED

a. Stop all but one RCP and go to

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Step 21.

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b. RCS subcooling based on core

b. Go to Step 28.

f exit T/Cs - CREATER THAN O'F j

j USING FIGURE MIN SUBC00 LING i

c. PRZR level - GREATER THAN 13%

c. Return to Step 18.

[40% adverse CNMT) i l

d. Try to start an RCP

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3 I

1) Establish conditions for starting an RCP i

o Bus llA or llB energized

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t' o Refer to Attachment RCP START l

2) Start one RCP l

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R WITH MSS OF RDCTOR COO N -

ECA-3*1 SUBCOOLED RECOVERY DESIRED PAGE 18 of 33 O

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ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 21 Check If One Of Three SI Pumps Should Be Stopped:

a. Three SI pumps - RUNNING

a. Go to Step 22.

b. RCS subcooling based on core

b. H RCS hot leg temperatures exit T/Cs - GREATER THAN 35*F greater than 320*F [310*F

[90*F adverse CNMT] USING FIGURE adverse CNMT), DE E RHR normal MIN SUBC00 LING cooling in service, THEN go to Step 28.

E RHR normal cooling NOT in service AND RCS hot leg temperatures less than 320*F

[310*F adverse CNMT), THEN ensure at least one RHR pump running in injection mode and go i

to Step 21c. E no RHR pump can be operated in injection mode, THEN go to Step 28.

O-

c. Check PRZR level - GREATER THAN

c. Do EDT stop SI pump. Return to 13% [40% adverse CNMT}

Step 18.

d. Stop one SI pump r

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R M TH MSS OF M CTOR COO N -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 19 of 33 0

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 22 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps - RUNNING

a. Go to Step 23.

b. Determine required RCS

{

subcooling from table:

Charging Pump RCS Subcooling Criteria Availability NONE 120*F [200*F adverse CNMT]

ONE 115'F [190*F sdverse CNMT]

TWO 105'F [180*t adverse CNMT]

i THREE 100*F [175'F adverse CNMT]

f]

c. RCS subcooling based on core

c. H RCS hot leg temperatures

\\, f exit T/Cs - GREATER THAN VALUE greater than 320*F [310*F FROM TABLE ABOVE USING FIGURE adverse CNMT), OR IF PRR normal MIN SUBCOOLING cooling in service, THEN go to Step 28.

H RHR normal cooling (LOI in service AND RCS hot leg temperatures less than 320*F

[310*F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 22d. E no PSR pump can be operated in injection mode.

THEN go to Step 28.

d. PRZR level - GREATER THAN 13%

d. Do NOT stop SI pump. Return to

[40% adverse ChMT]

Step 18.

e. Stop one SI pump e

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9 SGTR WITH LOSS OF REACTOR COOLANT -

A" SUBCOOLED RECOVERY DESIRED PAGE 20 of 33

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O ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 23 Check If Last SI Pump Should Be Stopped:

a. One SI pump - RUNNING

a. E any RHR pump running in inj ection mode, THEN go to Step 28.

IF NOT, THEN go to Step 24

b. Determine required RCS subcooling from table:

Charging Pump RCS Subcooling Criteria Availability NONE Insufficient subcooling to stop SI pump.

ONE 255'F [295'F adverse CNMT)

(

TWO 235'F [285'F adverse CNMT]

THREE 210*F [270*F adverse CNMT)

c. RCS subcooling based on core

c. E RCS hot leg temperatures exit T/Cs - GREATER TdAN VALUE greater than 320*F [310*F FROM TABLE ABOVE USING FIGURE adverse CNMT) OPP JJE PdIR normal MIN SUBCOOLING cooling in service, THEN go to Step 28.

E RUR normal cooling HOI in service AND RCS hot leg temperatures less than 320*F

[310*F adverse CNMT), THEN ensure at least one RHR pump running in injection mode and go to Step 23d. E no RHR pump can be operated in injection mode, i

THEN go to Step 28.

d. PRZR level - GREATER THAN 13%

d. Do NOT stop SI pump. Return to

[40% adverse CNMT]

Step 18.

e. Stop running SI pump

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9 SGTR MTH MSS OF EACTOR COONT '-

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 21 of 33 3

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ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l

STEP t

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24 Check If Charging Flow Should l

Be Controlled To Maintain i

PRZR Level:

a. Check RHR pumps - RUNNING IN

a. Start charging pumps and control I

INJECTION MODE charging flow to maintain PRZR level and go to Step 25.

b. Go to Step 28 i

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

i-I 25 Check RCP Status:

j 1

a. RCPs - AT LEAST ONE RUNNING a.

Perform the following:

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1) Establish conditions for starting an RCP:

I o-Verify bus llA or 11B energized.

l E

o Refer to Attachment RCP START.

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2) Start one RCP.

E an RCP can NQI be started, THEN verify natural circulation (Refer to Attachment NC),

j E natural circulation NOT f

verified, EM incre se dumping

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steam.

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b. Stop all but one RCP i

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SGTR M TH wSS OF R M OR COO W T -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 22 of 33 I

i ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED f

STEP i

f CAUTION 3

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i VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

l F

f WHEN using a PRZR PORV, THEN select one with an operable block f

NOTE: o valve.

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

26 Depressurize RCS To Minimize RCS Subcooling:

a. Depressurize using normal PRZR

a. Depressurize using one PRZR spray if available PORV. H IA NOT available THEN refer to Attachment N2 PORVS.

E no PORV available, THEN use auxiliary spray valve (A0V-296).

[

t

b. Energize PRZR heaters as necessary

c. Depressurize RCS until EITHER of the following conditions satisfied:

o RCS subcooling based on core exit T/Cs - LESS THAN 10*F USING FIGURE MIN SUBCOOLING t-

-OR-o PRZR level - GREATER THAN 75%

l

[65% adverse CNMT]

f b

i

Lop ilILE:

E ECA-3*1

~

SUBCOOLED RECOVERY DESIRED PAGE 23 of 33 r-

?

RESPONSE NOT OBTAINED ACTION / EXPECTED RESPONSE STEP t

[

NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

27 Verify Adequate Shutdown Margin

a. Direct HP to sample RCS and ruptured S/G for boron concentration T

b. Verify boron concentration -

b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM

• 28 Monitor SI Reinitiation Criteria:

a. RCS subcooling based on core

a. Manually operate SI pumps as exit T/Cs - GREATER THAN O'F necessary and go to Step 29.

USING FIGURE MIN SUBCOOLING

b. PRZR level - GREATER THAN 56

b. Manually operate SI pumps as

[30% adverse CNMT) necessary and return to Step 18.

b 9

6

top:

iliLE' SGTR WITH LOSS OF REACTOR COOLANT -

+

A-3.1 SUBCOOLED RECOVERY DESIRED PAGE 24 of 33 i

9 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 29 Check If SI ACCUMs Should Be Isolated:

I

a. RCS subcooling based on core

a. 1F both RCS hot leg temperatures i

exit T/Cs - GREATER THAN 0*F less than 400*F, THEN go to USING FIGURE MIN SUBCOOLING Step 29c.

l IF NOT, THEN go to Step 30.

b. PRZR level - GREATER THAN 5%

b. Return to Step 18.

l

[30% adverse CNMT]

c Dispatch A0 with locked valve key to locally close breakers for SI ACCUM discharge valves j

• MOV-841, MCC C position 12F

• MOV-865, MCC D position 12C

d. Close SI ACCUM discharge valves

d. Vent any unisolated ACCUMs:

• MOV-841

1) Open vent valves for.

• MOV-865 unisolated SI ACCUMs.

• ACCUM A. A0V-834A

• ACCUM B, A0V-834B

{

t

2) Open HCV-945.

[

e. Locally reopen breakers for

-l MOV-841 and MOV-865 l

i i

i i

i i

I l

i i

i

+

.~

l top:

1 Ta:

REV*'9 SGTR WITH I4SS OF REACTOR COOI. ANT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 25 of 33 i-ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 30 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses

a. Try to restore offsite power energized by offsite power:

(Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

o Emergency D/C output breakers

- OPEN AC emergency bus voltage -

o CREATER THAN 420 VOLTS AC emergency bus normal feed o

breakers - CLOSED

b. Stop any unloaded emergency D/G and place in standby (Refer to AttacFaent D/G STOP) 31 Minimize Secondary System Contamination:

a.

Isolate reject from hotwell to

a. lE hotwell level increasing, CST:

ThEN direct HP to sample hotwells for activity.

o Place hotwell level controller (HC-107) in MANUAL at 50%

Verify hotwell level - STABLE o

b. Verify local actions to complete isolation of ruptured S/G (Refer i

to Attachment RUPTURED S/G) i i

r O

r

'EOP IIILEt t

REV: 9 SGTR WITH LOSS OF REACTOR COOLANT -

^~

~

SUBCOOLED RECOVERY DESIRED PAGE 26 of 33 O

l ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP i

i l

32 Verify Adequate SW Flow To t

CCW Hx:

a. Verify at least two SW pumps -

a. Manually start pumps as power l

RUNNING supply permits (258 kw per pump). IF less than two SW pumps can be operated, THEN go to Step 33.

b. Verify AUX BLDG SW isolation

b. Establish SW to AUX BLDG (Refer valves - OPEN to Attachment AUX BLDG SW).

i

• MOV-4615 and MOV-4734

• MOV-4616 and MOV-4735

c. Verify CNMT RECIRC fan

c. Dispatch AO to locally throttle annunciator C-2, HIGH flow to CCW Hx to between TEMPERATURE ALARM - EXTINGUISHED 5000 gpm and 6000 gpm total flow.

33 Check RCP Cooling Establish normal cooling to RCPs

\\

(Refer to Attachment SEAL COOLING).

a. Check CCW to RCPs o Annunciator A-7, RCP 1A CCW l

RETURN HIGH TEMP OR LOW FIDW

- EXTINGUISHED o Annunciator A-15. RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED

b. Check RCP seal injection Labyrinth seal D/Ps - CREATER o

THAN 15 INCHES OF WATER

-OR-o RCP seal injection flow to each RCP - GREATER THAN 6 GPM i

o l

j i

EDP:

IIILE2 SGTR WITH LOSS OF REACTOR COOIANT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 27 of 33

.p V

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 34 Check If Seal Return Flow Should Be Established:

a. Verify instrument bus D -

a. Perform the following:

ENERGIZED

1) Ensure steam dump mode control in MANUAL.

2) Restore power to instrument bus D from MCC B or MCC A (maintenance supply).

b. Verify RCP #1 seal outlet

b. Go to Step 35.

temperature - LESS THAN 235'F

c. Verify RCP seal outlet valves -

c. Manually open valves as OPEN necessary.

• A0V-270A

• A0V-270B

d. Reset both trains of XY relays for RCP seal return isolation valve MOV-313

e. Open RCP seal return isolation e.

Perform the following:

valve MOV-313

1) Place MOV-313 switch to OPEN.

2) Dispatch A0 with key to RUST gate to locally open MOV-313.

f. Verify RCP #1 seal leakoff flow

f. IE any RCP seal leakoff flow

- LESS THAN 5.5 GPM greater than 5.5 gpm THEN:

o Close the affected RCP seal discharge valve

• RCP A, A0V-270A

• RCP B, A0V-270B o Trip the affected RCP JJE both RCP seal discharge valves are shut, THEN go to t

Step 35.

i t

g. Verify RCP #1 seal leakoff flow

g. Refer to AP RCP.1, RCP SEAL

- GREATER THAN 0.25 GPM MALFUNCTION.

f

)

/

(

. -. ~.. - -,

~

E0Ps 111LE:

SGTR WITH LOSS'OF REACTOR COOLANT -

EG-3

• 1 SUBCOOLED RECOVERY DESIRED PAGE 28 of 33 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP t

NOTE: Adverse CNMT conditions or loss of forced air cooling may result in

[

failure of NIS detectors.

}

35 Check If Source Range Detectors Should Be Energized:

I

a. Source range channels -

a. Go to Step 35e.

DEENERGIZED l

b. Check intermediate range flux -

b. Perform the following:

EITHER CHANNEL LESS THAN 10-10 AMPS

1) If neither intermediate range channel is decreasing, THEN initiate boration.

2) Continue with Step 36.

WHEN flux is LESS THAN 10-10 amps on any operable channel, THEN do Steps 35c, d and e.

O.

c. Check the following:

c. Continue with Step 36.

WHEN either condition met, THEN do o Both intermediate range Steps 35d and e.

channels - LESS THAN 10-10 AMPS

-OR-o Greater than 20 minutes since reactor trip

d. Verify source range detectors -

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

If source ranges can E0I be restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 36.

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

e EOP:

H RE:

SGTR WITH LOSS OF REACTOR COOLANT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 29 of 33 k

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 36 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 0FF o Open turbine drain valves Rotate reheater steam supply o

controller cam to close valves Q

o Place reheater dump valve kJ switches to HAND o Stop all but one condensate P2P f

c. Verify Attachment SD COMPLETE

/

k 4

e EOP IllLEX SGTR WITH LOSS OF REACTOR COOLANT -

+

ECA-3.1 SUCCOOLED RECOVERY DESIRED PAGE 30 of 33 l

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED t

f CAUTION FEED FLO'.i SHOULD NOT BE ESTABLISHED TO ANY RUPTURED S/G VHICH IS ALSO FAULTED UNLESS IT IS NEEDED FOR RCS COOLDOWN.

i

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • n*

• 37 Monitor Ruptured S/G(s)

Refill ruptured S/G to 67% [55%

l A

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

THAN 17% [25% adverse CNMT]

JfF either of the following conditions occurs, THEN stop feed flow to ruptured S/G unless needed for RCS cooldown:

Ruptured S/C pressure decreases l

o in an uncontrolled manner.

r

-OR-f o Ruptured S/G pressure increases to 1020 psig.

• 38 Monitor RCP Operation:

l

a. RCPs - ANY RUNNING

a. Go to Step 39.

b. Check the following:

b. Go to Step 39, o RCP #1 seal D/P - LESS THAN 220 PSID

-OR-o Check RCP seal leakage - LESS THAN 0.25 GPM

c. Stop affected RCP(s)

L

1 e

EOP:

iliLf.:

SGTR WITH IDSS OF REACTOR COOIANT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 31 of 33 i

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED' STEP 39 Check Condenser Steam Dur:p Manually or locally dump steam

{

Available - CONDENSER VACUUM using intact S/G ARV,

~

GREATER THAN 20 INCHES HG E no intact S/G available, THEN:

o Use faulted S/G.

-OR-H RHR system NOT in service, o

THEN use ruptured S/G.

l I

P IOP3 IllLE:

SG R UTH MSS OF RMOR COOWT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 32 of 33 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 40 Check If RHR Normal Cooling Can Be Established:

a. RCS cold leg temperature - LESS

a. Go to Step 41.

THAN 350'F

b. RCS pressure - LESS THAN

b. Go to Step 41.

400 psig [300 psig adverse CNMT]

c.

Place letdown pressure controller in HANUAL CLOSED

d. Check following valves - OPEN

d. Perform the following:

• A0V-371, letdown isolation

1) Reset both trains of XY valve relays for A0V-371 and

• A0Ve427, loop B cold leg to A0V-427.

REGEN Hx

• At least one letdown orifice

2) Open A0V-371 and A0V-427.

valve (A0V-200A, AOV-200B, or O

A0V-202)

3) Open one letdown orifice

valve,

e. Verify pressure on PI-135 - LESS

e. Go to Step 41.

THAN 400 PSIG

f. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)

g. Consult TSC to determine if RHR normal cooling should be established using Attachment RHR COOL t

s O

EOP:

11TLE:

REV: 9 SGTR WITH LOSS OF REACTOR COOLANT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 33 of 33 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 41, 41 Check CNMT Hydrogen Concentration:

a. Direct HP to start CNMT hydrogen monitors as necessary

b. Hydrogen concentration - LESS

b. Consult TSC to determine if THAN 0.5%

hydrogen recombiners should be placed in service.

42 Check Core Exit T/Cs - LESS Return to Step 7.

THAN 200*F 43 Evaluate Long Term Plant Status:

O

a. Maintain cold shutdown conditions

b. Consult TSC

-END-

t&:

ilTLE:

SGTR WITH MSS OF RMCTOR COO N T -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 1 M 1 a

ECA-3.1 APPENDIX LIST TITLE PAGES 1)

RED PATH

SUMMARY

1 2)

FIGURE MIN SUBCOOLING 1

3)

FIGURE SDM 1

4)

ATTACHMENT CNMT RECIRC FANS 1

5)

ATTACHMENT SI/UV 1

6)

ATTACHMENT RUPTURED S/G 2

7)

ATTACHMENT N2 PORVS 1

8)

ATTACHMENT RCP START 1

9)

ATTACHMENT D/G STOP 1

10)

ATTACHMENT SEAL COOLING 2

11)

ATTACHMENT SD-1 1

12)

ATTACHMENT SD-2 1

13)

ATTACHMENT RHR COOL 2

14)

ATTACHMENT NC 1

1 15)

ATTACHMENT AUX BLDG SW 1

16)

FOLDOUT 1

O

EOP IIILE:

l SGTR WITH LOSS OF REACTOR COOLANT -

l ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 1 of 1 O

RED PATH

SUMMARY

l a.

SUBCRITICALITY - Nuclear power greater than 5%

b.

CORE COOLING - Core exit T/Cs greater than 1200*F I

-OR-i Core exit T/Cs greater than 700*F AND

.I RVLIS level (no RCPs) less than 43% [46%

adverse CNMT) l i

c.

HEAT SINK - Narrow range level in all S/Gs less than 5%

[25% adverse CNMT) AND total feedwater flow l

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 i

I O

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EOP:

YlTLE:

I GTR WITH MSS OF REACTOR COO N -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE:

Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication i

RCS PRESSURE (PSIG) 2500 i

/

2400

' l-c RCS PRESSURE 2300 g INCREMENTS 20 PSIG M S/

2200

~

~'

2100 2000 Y*!

i=r 1900

' ~, '

1800

./ ;

1. -/-

1700

'-E i

1600 fy; i

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1500

". r##-

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O 1400 I*I' SUBC00 LED

1. -=;f =

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900

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. : I" INADEQUATE 700 600 -

'/

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SUBC00 LING REGION i ADVERSE CNMT s

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300 200

_dp '

NORMAL CNMT l i

TEMPERATURE INCREMENTS 10*F 100

~-

0 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE (*F)

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T11LE:

REV: 9 SGTR WITH LOSS OF REACTOR COOLANT -

ECA-3.1 SUBCOOLED RECOVERY DESIRED PAGE 1 of 1 FOLDOUT PAGE 1.

SI REINITIATION CRITERIA IF EITHER condition listed below occure, THEN manually operate SI pumps as necessary:

RCS subcooling based on core exit TCs -

LESS THAN O'F USING o

REQUIREMENTS OF FIGURE MIN SUBCOOLING o

PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%

j

[30% adverse CNMT]

2.

SATURATED RECOVERY CRITERIA lE ruptured S/G narrow range level increases to greater than 90% [85% adverse CNMT), THEN consult TSC to determine if recovery should be completed using ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED.

l 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, unless faulted S/G needed for RCS cooldown.

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 1.

5.

AFW SUPPLY SWITCHOVER CRITERION IE 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)

O