ML17262A886

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Rev 8 to EOP ECA-3.1, SGTR W/Loss of Reactor Coolant Subcooled Recovery Desired
ML17262A886
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/06/1992
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262A884 List:
References
ECA-3.1, NUDOCS 9206160388
Download: ML17262A886 (74)


Text

EOP:

ECA-3.1 T!TLE:

SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 1 of 32 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT FFE IVE DATE CATEGORY 1.0 REVIEWED BY:

9206160388 92060S PDR ADOCK OS000244 P

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1

EOP I ECA-3.1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 2 of 32 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.

b ~

E 3 g STEAM GENERATOR TUBE RUPTURE g 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.

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.

f E

3 g STEAM GENERATOR TUBE RUPTURE g if RCS subcooling is less than required.

g E

3 g 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 'g SGTR WITHOUT PRESSURIZER PRESSURE CONTROLS if SI can not be terminated.

i.

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

j.

E-3, STEAM GENERATOR TUBE RUPTURE, ES 3

1g 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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EOP:

TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 3 of 32 3 ~ 1 g POST SGTR COOLDOWN USING BACKFILL/

ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, and 3'/

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

ftl p/

EOP:

ECA-3.1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 4 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 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 RECIRCULATION.

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.

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+ 5'/hr.

1 Reset SI 2

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.

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EOP:

ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 5 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 3 Verify Adequate SW Flow:

a.

Check at least two SW p'umps 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 5.

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EOP:

ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 6 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 4 Establish IA to CNMT:

a. Verify non-safeguards busses energized from offsite power o

Bus 13 normal feed CLOSED a.

Perform the following:

1) Close non-safeguards bus tie breakers:

-OR-o Bus 15 normal feed CLOSED

~ Bus 13 to Bus 14 tie

~ Bus 15 to Bus 16 tie

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

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

b. Verify SW isolation valves to turbine building -

OPEN

~ MOV-4613 and MOV-4670

~ MOV-4614 and MOV-4664

b. Manually align valves.

cd Verify at least two air compressors

- RUNNING

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.

Check IA supply:

d. Perform the following:

o Pressure GREATER THAN 60 PSIG o

Pressure STABLE OR INCREASING

1) Continue attempts to restore IA (Refer to AP-IA.l, LOSS OF INSTRUMENT AIR).
2) Continue with Step 5.

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

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

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EN>:

ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 7 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 5 Verify All AC Busses ENERGIZED BY OFFSITE POWER 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

~ B from B'us 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).

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EOP:

ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV 8

PAGE 8 of. 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 6

Check If CNMT Spray Should Be Stopped:

a.

CNMT spray pumps

- ANY RUNNING

b. Verify CNMT pressure LESS THAN 4 PSIG
c. Reset CNMT spray a.

Go to Step 7.

b. Continue with Step 7.

WHEN conditions satisfied, THEN do Steps 6c through f.

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

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EOP:

ECA-3.1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 9 of 32 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.

7 Check If RHR Pumps Should Be Stopped:

a.

Check RCS pressure:

o Pressure

- GREATER THAN 250 psig

[465 psig adverse CNMT]

o Pressure STABLE OR INCREASING a.

Go to Step 8.

b. Stop RHR pumps and place in AUTO

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EOP:

ECA-3.1 LITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 10 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 8

Evaluate Plant Status:

a.

Check auxiliary building radiation

- 'NORMAL

~ Plant vent iodine (R-10B)

~ Plant vent particulate (R-13)

~ Plant vent gas (R-14)

~ CCV liquid monitor (R-17)

~ Letdown 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.
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 9.

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).

I

EOP:

ECA-3. 1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRFD REV:

8 PAGE 11 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 9 Establish 75 GPM Charging Flow:

a. Charging pumps

- ANY RUNNING a.

Perform the following:

1) IF CCW flow is lost to any RCP thermal barrier OR any RCP 51 seal outlet temperature offscale high, THEN dispatch AO with RWST area key to locally isolate seal injection to affected RCP.
b. Align charging pump suction to RWST:

o LCV-112B -

OPEN o

LCV-112C -

CLOSED

~ RCP A, V-300A

~ RCP B, V-300B

2) Ensure HCV-142 open.
b. IF LCV-112B can NOT be opened, THEN perform the following:
1) Verify charging pump A NOT running and place in PULL STOP.
2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).
c. Start charging pumps as necessary and establish 75 gpm total charging flow

~ Charging line flow

~ Seal injection 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:

ECA-3.1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 12 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 10 Check If S/G Secondary Side Is Intact:

o Pressure in both S/Gs STABLE OR INCREASING o

Pressure in both S/Gs GREATER THAN 100 PSIG IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN verify faulted S/G isolated unless needed for RCS cooldown:

~ Steamlines

~ Feedlines IF NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step l.

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,'LTERNATE WATER SUPPLY TO AFW PUMPS).

NOTE:

TDAFW pump flow control valves fail open on loss of IA.

11 Check Intact. S/G Levels:

a. Narrow range level GREATER THAN 5%

[25% adverse CNMT]

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT) and 50%

a. Maintain total feed flow greater than 200 gpm until narrow range level greater tha'n 5%

[25%

adverse CNMT] in intact S/G.

b. IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN consider isolating unnecessary release paths:

~ TDAFW pump steam supply valves

~ S/G blowdown valves

~ Refer to Attachment RUPTURED S/G

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EOP:

ECA-3.1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 13 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED NOTE:

Shutdown margin should be monitored during RCS cooldown (Refer to Figure SDM).

12 Initiate RCS Cooldown To Cold Shutdown:

a. Establish and maintain cooldown rate in RCS cold legs

- LESS THAN 100'F/HR b.

Use RHR system if in service c.

Dump steam to condenser from intact S/G

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

IF no intact S/G available, THEN perform the following:

o Use faulted S/G.

-OR-o IF RHR system NOT in service, THEN use ruptured S/G.

II 13 Check RCS,-Subcooling Based On Core Exit T/Cs GREATER THAN O'F USING FIGURE MIN SUBCOOLING Go to Step 26.

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EOP:

ECA-3 ~ 1 T!TLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 14 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 14 Check If Subcooled Recovery Is Appropriate:

a.

Check RWST level GREATER THAN 50%

b.

Check ruptured S/G narrow level

- LESS THAN 90%

[85% adverse CNMT)

a. IF CNMT sump B level is less than 113 inches, THEN go to ECA-3.2>

SGTR WITH LOSS OF REACTOR COOLANT -

SATURATED RECOVERY DESIRED, Step 1.

b. Consult TSC to determine if recovery should be completed using ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT -

SATURATED RECOVERY DESIRED.

15 Check Safeguards Pump Status o

SI pumps

- ANY RUNNING

-OR-Go to Step 22.

o RHR pumps

- ANY RUNNING IN INJECTION MODE 16 Place PRZR Heater Switches In The Following Positions:

o PRZR heater control group PULL STOP o

PRZR heater backup group OFF

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EOP:

ECA-F 1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV 8

PAGE 15 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.

THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

  • *
  • 4 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
  • NOTE:

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

17 Depressurize RCS To Refill PRZR:

a.

Use normal PRZR spray valve associated with running RCP

~ RCP A, PCV-431A

~ RCP B, PCV-431B b.

PRZR level

- GREATER THAN 13%

[40% adverse CNMT]

c. Stop RCS depressurization a.

Use one PRZR PORV.

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

IF no PORV available, THEN use auxiliary spray valve.

b. Continue with Step 18.

WHEN level greater than 13%

[40%

adverse CNMT), THEN stop RCS depressurization.

Air x

4

EOP:

ECA-3. 1 T!TLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 16 of 32 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 EVALUATION.

18 Check RCP Status:

a. Both RCPs STOPPED b.

RCS subcooling based on core exit T/Cs GREATER THAN O' USING FIGURE MIN SUBCOOLING a.

Stop all but one RCP and go to Step 19.

b.

Go to Step 26.

c.

PRZR level

- GREATER THAN 13%

[40%,adverse CNMT]

d. Try to start an RCP
1) Establish conditions for starting an RCP o

Bus 11A or llB energized o

Refer to Attachment RCP START

c. Return to Step 17.
2) Start one RCP

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EOP:

ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV 8

PAGE 17 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 19 Check If One Of Three SI Pumps Should Be Stopped:

a. Three SI pumps

- RUNNING b.

RCS subcooling based on core exit T/Cs GREATER THAN 35'F

[90'F adverse CNMT] USING FIGURE MIN SUBCOOLING c.

Check PRZR level -

GREATER THAN 13%

[40% adverse CNMT]

d. Stop one SI pump a.

Go to Step 20.

b. IF RCS hot leg temperatures greater than 325'F [270'F adverse CNMT], OR IF RHR normal cooling in service, THEN go to Step 26.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F

[270'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 19c.

IF no RHR pump can be operated in injection mode, THEN go to Step 26.

c.

Do NOT stop SI pump. Return to Step 17.

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EOP:

ECA-3. 1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 18 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 20 Check If One Of Two SI Pumps Should Be Stopped:

a.

Two SI pumps

- RUNNING

b. Determine required RCS subcooling from table:

a.

Go to Step 21.

Charging Pump Availability NONE ONE TWO THREE RCS Subcooling Criteria 120'F [200'F adverse CNMT) 115'F [190'F adverse CNMT]

105 'F [180'F adverse CNMT]

100'F [175'F adverse CNMT]

c.

RCS subcooling based on core exit T/Cs GREATER THAN VALUE FROM TABLE ABOVE USING FIGURE MIN SUBCOOLING cd IF RCS hot leg temperatures greater than 325'F [270'F adverse CNMT], OR IF RHR normal cooling in service, THEN go to Step 26.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F

[270'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 20d.

IF no RHR pump can be operated in injection mode, THEN go to Step 26.

d.

PRZR level -

GREATER THAN 13%

[40% adverse CNMT]

e.

Stop one SI pump d.

Do NOT stop SI pump. Return to Step 17.

EOP:

ECA-3.1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 19 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 21 Check If Last SI Pump Should Be Stopped:

a.

One SI pump

- RUNNING

b. Determine required RCS subcooling from table:
a. IF any RHR pump running in injection mode, THEN go to Step 26.

IF NOT, THEN go to Step 22.

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

255'F [295'F adverse CNMT]

235 'F [285'F adverse CNMT]

210'F [270'F adverse CNMT]

c.

RCS subcooling based on core exit T/Cs GREATER THAN VALUE FROM TABLE ABOVE USING FIGURE MIN SUBCOOLING d.

PRZR level GREATER THAN 13%

[40% adverse CNMT) e.

Stop running SI pump

c. IF RCS hot leg temperatures greater than '325'F [270'F adverse CNMT] OR IF RHR normal cooling in service, THEN go to Step 26

'F RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F

[270'F adverse CNMT], THEN ensure at least one RHR pump running'in injection mode and go to Step 21d.

IF no RHR pump can be operated in injection mode, THEN go to Step 26.

d.

Do NOT stop SI pump.

Return to Step 17.

EOP:

ECA-3.1 T1TLE:

SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 20 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 22 Start Charging Pumps As Necessary And Control Charging Flow To Maintain PRZR Level CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

23 Check RCP Status:

a.

RCPs

- AT LEAST ONE RUNNING a.

Perform the following:

1) Establish conditions for starting an RCP:

o Verify bus 11A or 11B energized.

o Refer to Attachment RCP START.

2) Start one RCP.

IF an RCP can NOT be started,

. THEN verify natural circulation (Refer to Attachment NC).

IF natural circulation NOT

verified, THEN increase
dumping, steam.
b. Stop all but one RCP

A 2

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ECA 1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 21 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.

THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

NOTE:

o WHEN using a PRZR

PORV, THEN select one with an operable block 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.

24 Depressurize RCS To Minimize RCS Subcooling:

a. Depressurize using normal PRZR spray if available
a. Depressurize using one PRZR PORV.

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

b. Energize PRZR heaters as necessary
c. Depressurize RCS until EITHER of the following conditions satisfied:

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

o RCS subcooling based on core exit T/Cs

- LESS THAN 10'F USING FIGURE MIN SUBCOOLING

-OR-o PRZR level

- GREATER THAN 758

[658 adverse CNMT]

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EOP:

ECA-3. 1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV' pAGE 22 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED NOTE:

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

25 Verify Adequate Shutdown Margin

a. Direct HP to sample RCS and ruptured S/G for boron concentration
b. Verify boron concentration-GREATER THAN REQUIREMENTS OF FIGURE SDM
b. Borate as necessary.

26 Verify SI Flow Not Required:

a.

RCS subcooling based on core exit T/Cs GREATER THAN O' USING FIGURE MIN SUBCOOLING

a. Manually operate SI pumps as necessary and go to Step 27.

b.

PRZR level GREATER THAN 5%

[30% adverse CNMT]

b. Manually operate SI pumps as necessary and return to Step 17.

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EOP:

ECA-3. 1 SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 23 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 27 Check If SI ACCUMs Should Be Isolated:

a.

RCS subcooling based on core exit T/Cs GREATER THAN O' USING FIGURE MIN SUBCOOLING b.

PRZR level

- GREATER THAN 5%

[30% adverse CNMT]

c. 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

d. Close SI ACCUM discharge valves

~ MOV-841

~ MOV-865

a. IF both RCS hot, leg temperatures less than 400'F, THEN go to Step 27c.

IF NOT, THEN go to Step 28.

b. Return to Step 17.
d. Vent any unisolated ACCUMs:
1) Open vent valves for unisolated SI ACCUMs.
e. Locally reopen breakers for MOV-841 and MOV-865

~ ACCUM A, AOV-834A

~ ACCUM B, AOV-834B

2) Open HCV-945.

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ECA-3.1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 24 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 28 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

a. Try to restore offsite power (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).

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) 29 Minimize Secondary System Contamination:
a. Isolate reject from hotwell to CST:

o Place hotwell level controller (HC-107) in MANUAL at50'.

IF hotwell level increasing, THEN 'direct HP to sample hotwells for activity.

o Verify hotwell level STABLE

b. Verify local actions to complete isolation of ruptured S/G (Refer to Attachment RUPTURED S/G)

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EOP:

ECA-3.1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV 8

PAGE 25 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 30 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 31.

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.

31 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

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8 PAGE 26 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 32 Check If Seal Return Flow Should Be Established:

a. Verify instrument bus D-ENERGIZED
b. Verify RCP Pl seal outlet temperature

- LESS THAN 235'F

c. Verify RCP seal outlet valves OPEN

~ AOV-270A

~ AOV-270B

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

Open RCP seal return isolation valve MOV-313

f. Verify RCP 51 seal leakoff flow LESS THAN 5.5 GPM
g. Verify RCP tl seal leakoff flow GREATER THAN 0.25 GPM a.

Perform the following:

1) Ensure steam dump mode control in MANUAL.
2) Restore power to instrument bus D from MCC B or MCC A (maintenance supply).

b.

Go to Step 33.

c. Manually open valves as necessary.

e.

Perform the following:

1) Place MOV-313 switch to OPEN.
2) Dispatch AO with key to RWST gate to locally open MOV-313.
f. 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 o

Trip the affected RCP IF both RCP seal discharge valves are shut, THEN go to Step 33.

g. Refer to AP-RCP.1, RCP SEAL MALFUNCTIONS

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8 PAGE 27 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED NOTE:

Adverse CNMT condit'ions 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 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 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).

IF source ranges can NOT be

restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 34.
e. Transfer Rk-45 recorder to one source range and one intermediate range channel

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ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 28 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 34 Establish Normal Shutdown Alignment:

a.

Check condenser

- AVAILABLE

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

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 Attachment SD-1 COMPLETE

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TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 29 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION FEED FLOW SHOULD NOT BE ESTABLISHED TO ANY RUPTURED S/G WHICH IS ALSO FAULTED UNLESS NEEDED FOR RCS COOLDOWN.

35 Check Ruptured S/G (s)

Narrow Range Level GREATER THAN 174 t'254 adverse CNMT]

Refill ruptured S/G to 67%

[55%

adverse CNMT] using feed flow.

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

o Ruptured S/G pressure decreases in an uncontrolled manner.

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

36 Check If RCPs Must Be Stopped:

a.

RCPs

- ANY RUNNING b.

Check the following'.

o RCP 41 seal D/P -

LESS THAN 220 PSID a.

Go to Step 37.

b.

Go to Step 37.

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

c. Stop affected RCP(s)

~

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8 PAGE 30 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 37 Check Condenser Steam Dump Available CONDENSER VACUUM GREATER THAN 20 INCHES HG Manually or locally dump steam using intact S/G ARV.

IF no intact S/G available THEN.

o Use faulted S/G.

-OR-o IF RHR system NOT in service, THEN use ruptured S/G.

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PAGE 31 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 38 Check If RHR Normal Cooling Can Be Established:

a.

RCS cold leg temperature LESS THAN 350'F a.

Go to Step 39.

b.

RCS pressure

- LESS THAN 400 psig

[300 psig adverse CNMT]

c. Place letdown pressure controller in MANUAL CLOSED b.

Go to Step 39.

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.
2) Open AOV-371 and AOV-427.
3) Open one letdown orifice valve.
e. Verify pressure on PI-135 LESS THAN 400 PSIG e.

Go to Step 39 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

II 11'P

ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 32 of 32 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 39 Check Core Exit T/Cs LESS THAN 200'F Return,to Step 11.

40 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions
b. Consult TSC

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ECA-3. 1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 1 of 1 ECA-3. 1 APPENDIX LIST TITLE PAGES 1)

RED PATH

SUMMARY

2)

FIGURE MIN SUBCOOLING 3)

FIGURE SDM 4)

ATTACHMENT CNMT RECIRC FANS 5)

ATTACHMENT SI/UV 6)

ATTACHMENT RUPTURED S/G 7)

ATTACHMENT N2 PORVS 8)

ATTACHMENT RCP START 9)

ATTACHMENT D/G STOP 10)

ATTACHMENT SEAL COOLING 11)

ATTACHMENT SD-1 12)

ATTACHMENT SD-2 13)

ATTACHMENT RHR COOL 14)

ATTACHMENT NC 15)

ATTACHMENT AUX BLDG SW 16)

FOLDOUT

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ECA-F 1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV 8

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 434

[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

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ECA-3. 1 TITLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 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 ERSE DV NMT NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)

q

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ECA-3.1, TITLE:

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8 PAGE 1 of 1 BORON CONCENTRATION (PPH) 1800 FIGURE SDM 1600 BORON INCREHENTS 20 PPH 1400 1200 1000 ADEQUATE SDH 100 PPH CONS ERVATISH INCLUDED BOO 600 400 TE 200 BURNUP INCREHENTS 100 HWD/HTU 0

1000'000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)

NOTE: To obtain core burnup, use PPCS turn on code BURNUP.

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ECA-3.1 TlTLE:

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED REV:

8 PAGE 1 of 1 FOLDOUT PAGE SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually operate SI pumps as necessary:

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 ~

SATURATED RECOVERY CRITERIA IF ruptured S/G narrow range level increases to greater than 904

[854 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.

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 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)