ML13311A527

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Loss of Secondary Coolant, Revision 0
ML13311A527
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 05/20/1982
From:
Southern California Edison Co
To:
Shared Package
ML13311A465 List:
References
SO1-1.2-1.2, NUDOCS 8205240483
Download: ML13311A527 (14)


Text

501-.2-1.2 LOSS OF SECONDARY COOLANT REV 0 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED EMERGENCY INSTRUCTION S01-1.2-1.2 LOSS OF SECONDARY COOLANT

1.

PURPOSE:

The purpose of this instruction is to provide the diagnostics to enable confirmation of a LOSS OF SECONDARY COOLANT, the assurance of an adequate heat sink, and the identification of SI reset criteria for the conditions present.

Additionally, this instruction directs the implementation of procedures to insure long term shutdown and cooling of the reactor.

8205240483 820520 PDR ADOCK 05000206 1 of 14 F

PDR_

501-1.2-1.2 LOSS OF SECONDARY COOLANT REV 0 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Foldout page should be open.

Check Motor Drive AFW Pump:

a.

Pump breaker -

CLOSED.

a. Return pump to service:
1) IF pump tripped on T5w discharge pressure, THEN lower AFW FT7w controllers to one half of their preset positions.
2) Go to MANUAL AND RESET.
3) Manually start pump.
4) Throttle AFW flow:

Total flow GREATER THAN 250 GPM.

AND Flow per SG -

LESS THAN 150 GPM.

b. Turbine driven pump:
b. Manually open valves.

Steam warmup valve OPEN.

OR Steam supply valve OPEN.

2 of 14

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2

Check If AFW Isolation To Une SG Is Required:

a. AFW flow - APPROXIMATELY
a. IF AFW flow to one SG EQUAL TO ALL SGs.

Tnormally high com compared to others, THE N isolate AFW to EFatSG.

Go to s tep 3.

b. AFW header flow
b. IF controller position controllers AT Vs siorifIcantly

- PRESET POSITION.

reduced to meet flow limit of 150 gpm to FCV -

2301 50%

one SG, THEN isolate FCV - 2300 100%

AW to tF FSG. Go to FCV -

3300 100y step 3.

FCY -

3301 50%

Steam flow -

APPROXIMATELY

c. IF one S steam flow EQUAL FOR ALL Su's.

T pegged downscale compared to others, THEN isolate AFW to 5 7 SS.Got 3

Check AFW Flow:

a. Total AEW flow -GREATER
a. Adjust flow as THAN 250 GPM.

required.

b. Each SG with established
b. Adjust flow as AFW f1ow ALEFSS THAN required.

150 GPM.

3 of 14

501-1.2-1.2 LOSS OF SECONDARY COOLANT REV 0 ACTION/EXPECTED RESPONSE -----

RESPONSE NOT OBTAINED 4

Check Level In SGs With Lstabilshed AFW Flow:

a.

Narrow range level

a. IF less than 26% in

- GREATER THAN 26%.

i-a SGs,THEN go to step 3.

b. Throttle AFW flow to
b. IF narrow range level maintain narrow range in one SG continues level at 50%.

increase, THEN:

l' Secure AFW to that SG

2) Request activity sample of that SG.

IF high activity resent, THEN go to 501-1.2-17, STEAM GENERATOR TUBE RUPTURE.

3) For a P.APID level increase in one SG, go to S01-1.2-1.3, STEAM GENERATOR TUBE RJPTURE.

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501-1.2-1.2 LOSS OF SECONDARY COOLANT REV 0 0 S ACTION/EXPECTED RESPONSE T OBTAINED CAUTI ON If RCS temperature is increasing, then control AFW flow to stabilize RCS temperature.

5 Check RCS Cooldown Rate:

a. Cooldown Rate - LESS
a. IF cooldown rate THAN 100 OF/HR.

greater than 100 oF/hr, THEN throttle fl wTo each SG with established AFW flow to 25 gpm.

5 of 14

S01-1.2-1.2 LOSS OF SECONDARY COOLANT REV 0 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6

Check Pressurizer PORVs And Block Valves:

a. Power available to block
a. Restore power to block valves.

valves.

b. PORVs -

CLOSED.

b. IF RCS pressure less t"an 2085 psig, THEN manually close PORVs.

IF any PORV cannot be closed, THEN manually close itT FTock valve. IF block valve caFhot be closed, THEN go to 501-1.2-T, LOSS OF REACTOR COOLANT.

c. Block valves -

OPEN.

c. Open block valve unless it was closed to isolate a faulty PORV.

CAUTION If any pressurizer PORY opens because of high RCS pressure, repeat step 6 after pressure drops below PORV setpoint.

6 of 14

501-1.2-1.2 LOSS OF SECONDARY COOLANT REV 0 0 STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7

Check CST Level:

a. CST level - GREATER
a. IF CST level low, THEN THAN 4 FT.

I ansfer to alternRf AFW water supply per SO1-7-3, AUXILIARY FEEDWATER SYSTEM.

8 Check Containr)ent Spray System:

a. Refueling water pump
a. IF pumps NOT running, breakers - CLOSED.

77EN go to step 9.

b. Containment pressure
b. IF pressure high, THEN LESS THAN 1.4 PSIG.

maintain containmeM~

spray until contain ment pressure is less than 1.4 psig.

c.

Stop containment spray and place in standby.

1) Reset CSAS Trains A AND B.
2) Stop both hydrazine additive pumps.
3) Close spray additive pump discharge valves SV 600 AND SV 601.
4) Close spray valves CV 82 AND CV 114.
5) Stop both refueling water pumps.

7 of 14

0 STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If containment pressure increases above 10 PSIG, containment spray must be reinitiated.

9 Check RWST Level

a.

RWST level -

GREATER

a. IF less than 213, THEN THAN 2l1.

ITign SI system for cold leg recirculation per 501-1.2-1.22, CONTAINMENT SPRAY RECIRCULATION FOLLOWING LOSS OF SECONDARY COOLANT.

CAUTION If RCS cold leg tenperature is less than 350 oF, it is important to Reactor Vessel Integrity that Si be terminated immediately when SI termination criteria is met.

10 Check RCS Cold Leg Iemperatures:

a. ALL RCS cold leg
a. IF any RCS cold leg temperatures temperature less than GREATER THAN 350 OF.

350 OF THEN go to step 8 of 14

50.1-2-1.2 LOSS OF SECONDARY COOLANT REV 0 0 STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Check Containment Conditions:

a. Containment pressure
  • IF ANY condition high LESS TNAN 1.4 PSIG T increasing, THEN AND NOT INCREASING.

go to step 14.

b.

Containment radiation on ARS 1232 -

LESS THAN ALARM SET POINT AND NOT INCREASNG.

c.

Containment sump level LESS THiAN ALARM SET POINT AND NOT INCREASING.

9 of 14

501-1.2-1.2 LOSS OF SECONDARY COOLANT REV 0 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If containment conditions of step 11 exhibit high or increasing readings while doing step 12, go to step 14.

12 Check If SI Can Be Terminated Under NORMAL Oontanment Lond to ons:

a. RCS pressure -

GREATER

a. DO NOT TERMINATE SI, THAN 1400 PSIG AND return to step 9.

INCREASING.

b. Pressurizer level
b. D0 NOT TERMINATE SI, GREATER THAN 20C.

return to step 9.

c. RCS subcooling - GREATER
c. DO NOT TERMINATE SI, THAN 40 OF.

return to step 9.

d. Secondary heat sink:
d. IF neither condition Ts satisfied, ThEN DO Flow to each SG with NOT TERMINATE ST7 established AFW flow return to step 9.

- GREATER THAN 25 GPM.

AND RCS hot leg temperatures STABLE OR DECREASING.

13 Terminate SI:

a.

Go to S01-1.2-1.21, SI TERMINATION FOLLOWING LOSS OF SECONDARY COOLANT.

0 10 of 14

ACTION/EXPECTED

RESPONSE

RESPONSE NOT OBTAINED 14 Check If SI Can Be Terminated

- under ABRORMAL Conta-inment Conditions:

a.

RCS pressure -

GREATER

a. DO NOT TERMINATE SI, THAN 1400 PSIG AN return to step 9.

STABLE OR INCREXITNG.

b. Pressurizer level
b. DO NOT TERMINATE SI,

- GREATER THAN 50-.

return to step 9.

c. RCS subcooline -

GREATER

c. 0O NOT TERMINAE SI, THAN 40 oF.

return to step 9.

d. Secondary heat sink:
d. IF neither condition T

satisfied, THEN DO Total flow to SGs with NOT TERM:NATE T,

established AFW flow return to step 9.

GREATER THAN 250 GPM.

OR Narrow ranace level in at least one SG with established AFW flow GREATER THAN 26%.

15 Terminate SI:

a.

Go to 501-1.2-1.21, SI TERMINATION FOLLOWING LOSS OF SECONDARY COOLANT.

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501-1.2-1.2 LOSS OF SECONDARY COOLANT REV 0 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If RCS cold leg temperature is less than 350 OF it is important to Reactor Vessel Integrity that Si be terminated immediately when SI termination criteria is met.

16 Check If SI Can Be Terminated RLS Cold Leg Temperature Beow 350 uF:

a. RCS pressure -

GREATER

a. DO NOT TERMINATE SI, THAN 700 PSIG AND return to step 9.

STABLE OR INCREASING.

b. Pressurizer level
b. DO NOT TERMINATE SI,

- GREATER THAN 20%.

return to step 9.

c.

RCS subcooling -

GREATER

c. DO NOT TERMINATE SI, THAN 40 OF.

return to step 9.

d. Secondary heat sink:
d. IF neither condition Tf satisfied, THEN DO Total flow to SGs with NOT TERMINATE 3T, established AFW flow return to step 9.

GREATER THAN 10 GPM.

OR Narrow range level in at least one SG with established AFW flow GREATER THAN 26%.

12 of 14

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Terminate SI:

a. Go to SO1-1.2-1.1, SI TERMINATION FOLLOWING LOSS OF SECONDARY COOLANT.

H. E. MORGAN MANAGER, STATION OPERATICNS 13 of 14

SO1-1.2-1.2 Rev 0 MTOR DRIVEN AF' PUMP REST-AT CR!TERIA

a.

IF a motor driven AF pump trips on low discharge pressure, THEN:

1)

Lower AFW flow controllers.

2)

Reset AMD restart pump.

SI REINITIATION CRITERIA FOLLOWING LOSS OF SECONDARY COOLANT

a.

Reinitiate SI if ANY ONE of the parameters listed below occurs:

1)

RCS Pressure-tEWEASES BY 200-PSI AFTER SI TERMINATION.

2)

RCS Subcooling -

LESS THAN 40 -F.

3) Pressurizer Level - DECREASES BY 10' AFTER SI TERMINATION.

AFW SUPPLY 5 ITCHOVER CRITERION

a. IF CST level less than 4 FEET, THEN switch to alternate AFW supply.

COLD LEG RECRCULAION SWICHOER CRITERIA

a. IF RWST level less than 211, THEN align SI system for cold leg injectioni and recirculation per S01-1.2T.T3, TRANSFER TO COLD LEG INJECTION AND RECIRCULATI ON.

SYMPTYS FOR RESPONSE TO IRADEQUATE CORE COOLING

a. Go to S01-1.2-14, RESPONSE TO INADEQUATE CORE COOLING, when ANY ONE of the following symptoms occur:
1) Five of more core exit TCs -

GREATER THAN 1200 OF.

OR

2)

RCS hot leg temrperatures -

GREATER THAN 700 OF.

SYMPTOMS FOR RESPONSE TO LOSS OF SECONDARY HEAT SINK

a. Go to S01-1.2-15, RESPONSE TO LOSS OF SECONDARY HEAT SINK, if AFW Flow is NOT AVAILABLE.

IF EVE TS REQUIRE IMLEMENTATION OF THIS PROCEDURE:

a. Notify Shift Technical Advisor.
b. Notify Shift Communicator.

C. Determine if event is classified as an emergency and requires notification of offsite agencies and implementation of the Emergency Plan per S0123-V1II-11, RECOGNITION AND CLASSIFICATION OF EMERGENCIES.

d. IF event is NOT classified as an emergency in c above THEN determine if ntification7To the NRC is required within one hour per 501-14-13, NOTIFICATION TO NRC OF SIGNIFICANT EVENTS.

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