ML17250B100

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Rev 9 to E-1, Loss of Reactor or Secondary Coolant
ML17250B100
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/09/1990
From: Widay J
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17250B096 List:
References
E-1, NUDOCS 9004200634
Download: ML17250B100 (38)


Text

EOP:

E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV:

9 PAGE 1 of 15 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE P

NT SUPERINT DE T EFF CTIVE DATE

~ fl W,'Tt QA NON QA CATEGORY 1. 0 REVIEWED BY:

c 9004200634 9004i0 PDR'DOCK 05000244 P,

PNU IC c

'i

EOP:

E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV:

9 PAGE 2 of 15 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 1g

RESPONSE

TO LOSS OF SECONDARY HEAT SINKS when a

PRZR PORV is stuck open and its block valve can not be closed.

b ~

E 0

REACTOR TRXP OR SAFETY INJECTXONg with any of the following symptoms:

high containment radiation, high containment-pressure, or high containment recirculation sump level.

c.

E-O, REACTOR TRIP OR SAFETY INJECTION, and ECA 2

~ 1g UNCONTROLLED DEPRESSURXZATION OF BOTH STEAM GENERATORS, when RCS pressure is less than the shutoff head pressure of the RHR pumps.

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 ISOLATXON, after identification and isolation of a faulted S/G.

f ECA 0

~ 2 g LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, after normal injection mode conditions are established.

g.

ECA-1.2, LOCA OUTSIDE CONTAINMENT, when a LOCA outside containment is isolated.

h.

FR-C.l,

RESPONSE

TO INADEQUATE CORE COOLING, and FR-C.2,

RESPONSE

TO DEGRADED CORE COOLING, after core cooling has been reestablished.

i ~

FR H 1 ~

RESPONSE

TO LOSS OF SECONDARY HEAT S INK/

if RCS pressure is less than all,non-faulted S/G(s)

'pressure.

~

FR H 1 g

RESPONSE

TO LOSS OF SECONDARY HEAT S INK/

after secondary heat sink has been reestablished and all PRZR PORVs are closed.

EOP:

E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV:

9 PAGE 3 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION IF RVST LEVEL DECREASES TO LESS THAN 28X, THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCUL'ATION, STEP 1.

NOTE:

o FOLDOUT page should be open AND monitored periodically.

o Critical Safety Function Status Trees should be monitored.

(Refer to Appendix 1 for Red Path Summary.)

o Conditions should be evaluated for Site Contingency Reporting (Refer to SC-100, 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 If RCPs Should Be Stopped:

a.

RCP status

- ANY RCP RUNNING

b. SI pumps - AT LEAST TVO RUNNING c.

RCS pressure minus maximum S/G pressure

- LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs a.

Go to Step 2.

b.

Go to Step 2.

c.

Go to Step 2.

EOP:

E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV 9

PAGE 4 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 2

Check If S/G Secondary Side Is Intact:

o Pressure in both S/Gs - STABLE OR INCREASING o

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

~ Steamlines

~ Peedlines IP NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.

CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 PEET, THEN ALTERNATE WATER SOURCES POR AFV PUMPS VILL BE NECESSARY (REFER TO ER-APW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

NOTE:

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

3 Check Intact S/G Levels:

a. Narrow range level - GREATER THAN 5X [25X adverse CNMT]
a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5X [25X adverse CNMT] in at least one S/G.
b. Control feed flow to maintain narrow range level between 17X

[25X adverse CNMT] and 50X

b. IF narrow range level in any S/G continues to increase in an uncontrolled
manner, THEN go to E-3, STEAM GENERATOR TUBE
RUPTURE, Step 1.

EOP:

E-1 TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV:

9 PAGE 5 of 15 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 1.

CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR

PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5b).

5 Check PRZR PORVs And Block Valves:

a.

Power to PORV block valves-AVAILABLE b.

PORVs - CLOSED

c. Block valves - AT LEAST ONE OPEN
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.

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:

E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV 9

PAGE 6 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION IP OFPSITE POWER IS LOST APTER SI RESET, SELECTED SW PUMPS AND ONE CCV PUMP WILL AUTO START ON EMERGENCY D/G.

MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

6 Reset SI 7

Reset CI:

a.

Operate CI reset key switch

b. Verify annunciator A-26, CNMT ISOLATION - EXTINGUISHED
b. Perform the following:
1) Reset SI.
2) Operate CI reset key svitch.

8 Verify Adequate SW Flow:

a.

Check at least two SV pumps-RUNNING

b. Dispatch AO to establish normal shutdovn alignment (Refer to Attachment SD-1)
a. Manually start SV pumps as power supply permits (258 kv each).

IR less than tvo SW pumps

running, THEN perform the folloving:
1) Ensure SV isolation,
2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1) 3)

Go to Step 10.

EOP:

LOSS OF REACTOR OR SECONDARY COOLANT REV 9

PAGE 7 of 15 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 ZY relays for IA to CNMT AOV-5392

f. Verify IA to CNMT AOV-5392-OPEN a.

Perform the folloving:

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 PANS).

3)

WHEN bus 15 restored, THEN reset control room lighting.

b. Manually align valves.
c. Manually start air compressors as pover supply permits (75 kv 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 vith Step 10.

WHEN IA restored, THEN do Steps 9e and f.

EOP:

E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV' PAGE 8 of 15 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).

EOI" E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV:

9 PAGE 9 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 11 Check If Charging Flow Has Been Established:

a. Charging pumps

- ANY RUNNING

a. Perform the folloving:
1) IF CCV flov is lost to any RCP thermal barrier OR any RCP fl seal outlet temperature offscale high, THEN dispatch AO vith key to EST gate to close seal in)ection needle valve(s) to affected RCP:

~ V-300A for'CP A

~ V-300B for RCP B

b. Charging pump suction aligned to RVST:

o LCV-112B - OPEN o

LCV-112C - CLOSED

c. Start charging pumps as necessary and ad)ust charging flow to restore PRZR level
2) Ensure HCV-142 open, demand at OX.
b. Manually align valves as necessary.

IF LCV-112B can NOT be opened, THEN perform the folloving:

1) Verify charging pump A NOT running and place in PULL STOP.

V

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

3)

VHBN 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:

E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV 9

PAGE 10 of 15 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

c. Secondary heat sink:

o Total feed flow to intact S/Gs

- GREATER THAN 200 GPM b.

Do NOT stop SI pumps.

Go to Step 14.

c. IF neither condition satisfied, THEN do NOT stop SI pumps.

Go to Step 14.

-OR-o Narrow range level in at least one intact S/G-GREATER THAN 5X [25X adverse CNMT]

d.

PRZR level - GREATER THAN 5X

[30X 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)

Go to Step 14.

EOP:

E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV 9

PAGE 11 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 13 Go To ES 1 ~ 1 g SI TERMINATIONg Step 1

14 Check If CNMT Spray Should Be Stopped:

a.

CNMT spray pumps

- RUNNING

b. Check CNMT pressure

- LESS THAN 4 PSIG

c. Reset CNMT spray
d. Check NaOH tank outlet valves-CLOSED

~ AOV-836A

~ AOV-836B a.

Go to Step 15.

b. Continue with Step 15.

VHEN CNMT pressure less than 4 psig, THEN do Steps 14c through f.

d. Place NaOH tank outlet valve controllers to MANUAL and close valves.

e.

Stop CNMT spray pumps and place in AUTO

f. Close CNMT spray pump discharge valves

~ MOV-860A

~ MOV-860B

~ MOV-860C

~ MOV-860D

EOP E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV 9

PAGE 12 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION o

IP OPPSITE POWER IS LOST AFTER SI RESET, 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], THE RHR PUMPS MUST BE MANUALLYRESTARTED TO SUPPLY WATER TO THE RCS.

15 Check 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 l.

b.- Check pressures in both S/Gs-GREATER THAN 100 PSIG

c. Check RCS pressure

- STABLE OR DECREASING

b. Monitor RCS pressure.

IP RCS pressure does NOT increase after faulted S/G dryout, THEN go to Step 17.

c. Return to Step l.

0

EOP:

E-1 TITLE:

LOSS OF REACTOR.OR SECONDARY COOLANT REV 9

PAGE 13 of 15 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)

%HEN bus 15 restored, THEN reset control room lighting breaker.

b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)
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 POVER).

EOP:

E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV 9

PAGE 14 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 18 Evaluate Plant Status:

a. Verify sump B recirculation capability:
1) Power available to busses and MCCs supplying RHR pumps and valves
a. 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 Bus 14 and MCC C-ENERGIZED o

Bus 16 and MCC D-ENERGIZED 2)

RHR pumps - OPERABLE

b. Dispatch AO to check AUX BLDG sub-basement for RHR system leakage (AUX BLDG sub-basement key required) c.

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)

d. Direct HP to obtain following samples:

~ RCS boron

~ RCS activity

~ CNMT hydrogen

~ CNMT sump boron

~ BASTs boron

b. IF any RHR pump seal leakage indicated, THEN leakage should be evaluated and isolated if necessary.
c. 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 l.

This Step continued on the next page.

EOP:

TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV 9

PAGE 15 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED (Step 18 continued from previous page)

e. 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 19.

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) 19 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 20.

20 Check If Transfer To Cold Leg Recirculation Is Required:

a.

RWST level - LESS THAN 28X b.

Go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1

a. Return to Step 18.

-END-

EOP I E-1 TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV 9

PAGE 1 of 1 E-1 APPENDIX LIST TITLE 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)

FOLDOUT

EOP:

E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV:

9 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

EOP:

E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV' 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 E CNMT ADVERS NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)

EOP:

E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV' 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 54

[30~ adverse CNMT]

2.

SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-l.l, SI TERMINATION, Step 1:

a.

RCS subcooling based on core exit T/Cs GREATER THAN O'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 54 [304 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 l.

4.

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.

5.

AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5'eeti THEN switch to alternate AFW water supply (Refer to ER-AFW.1, 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 1.