ML13311A467
| ML13311A467 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/20/1982 |
| From: | Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13311A465 | List: |
| References | |
| SO1-1.2-1-01, SO1-1.2-1-1, NUDOCS 8205240440 | |
| Download: ML13311A467 (14) | |
Text
S ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED EMERGENCY INSTRUCTION S01-1.2-1.01 REACTOR TRIP RESPONSE I.
PURPOSE:
The purpose of this instruction is to provide direction for a REACTOR TRIP RECOVERY to assure reactor shutdown, establish stable plant control to prevent a return to criticality and ensure decay heat removal.
Additionally this instruction directs the implenentation of procedures that provide for subsequent plant operation.
8205240440 820520 PDR ADOCK 05000206 P
ACTION/EXPECTED
RESPONSE
RESPONSE NOT OBTAINED Note:
Foldout page should be o pen.
CAUTION If SI actuation occurs at any time, inTediately go to 501-1.2-1.0, REACTOR TRIP OR SAFETY INJECTION, step 5.
Verify RCS Heat Removal:
- a. Verify RCS temperature DECREASING TO 535 0F.
- b. Place steam dump mode selector switch to PRESSURE CONTROL ATMOS AND CONDENSER.
C. Verify steam dump
- c. Set steam dump controller -
SET AT controller to 930 PSIG.
930 psig.
- d. IF AFW NOT initiated, THREN use main
- 1) Auxiliary feedwater Teedwater regulator initiated.
bypass CVs to establish flow to SGs.
- 2) Flow indication on aux.
2 Isolate Main Feedwater Flowpath:
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S01-1.2-1.01 REACTOR TRIP RESPONSE REV 0 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3
Check Steam Generator Levels:
- a. Narrow range level
- a. IF LESS than 261, GREATER TMAN 261.
TREN maintain:
- 1) Total SG feed flow
- GREATER THAN 250 GPM.
- 2) Feed flow per SG LESS THAN 150 GPM.
- b. Throttle SG feed flow to maintain narrow range level at 501.
4 Verify All Control Rods Fully Inserted:
- a. Rod bottom lights -
ON.
- a. Verify rod positon from LVDT indication.
IF two or more control rods NOT fully inserted, THEN go to 501-1.2-16, ANTICIPATED TRANSIENT WITHOUT SCRAM, step 6.
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ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5
Check Pressurizer Level Control:
- a.
Level GREATER THAN 10%.
- a. IF level less than TU%,
THEN:
- 1) Verify letdown isolation; IF NOT, THEN manually iioate letdown.
- 2) Verify heaters OFF; IF NOT, THEN manualIyTrn off heaters.
- 3) Manually control charging to restore pressurizer level.
- b. Verify charging and
- b. Manually place in letdown in service.
service.
- c.
Level - TRENDNG
- c. Control charging and TO 15%.
letdown to maintain level at 15%.
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S01-1.2-1.01 REACTOR TRIP RESPONSE REV 0 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6
Check Pressurizer Pressure Control:
a., Pressure - GREATER THAN
- a. IF pressure LESS than 1735 PSIG.
T735 PSIG, THEN verify or initiate-T actuation AND go to S01-1.2-1.0, REACTOR TRIP OR SAFETY INJECTION, step 5.
- b.
Pressure - STABLE AT OR
- b. TF pressure less than TRENDING TO 2085 PSIG.
k85 PSIG AND decreasingEHEN:
- 1) Verify pressurzzer POR~s closed; IF NOT closed, THr9 manually cloF Nthe POR~s.
- 2) Verify pressurizer spray valves closed; IF NOT, closed, TREN manuallyTT-ose the valvyes.
- 3) Verify pressurizer heaters on; IF NOT on THEN anuTy turn aon the heaters.
- c.
IF pressure GREATER THAN M~5 PSIG AND increasing, TIHE N:
)I e Verify pressurizer heaters off; IF NOT, manually turn the hauyters off.
- 2) Control pressure using pressurizer spray, auxiliary spray, or PORt in this preferred order, as necessary.
- d. Pressurizer heaters
- d. Reset pressurizer AVAILABLE.
heaters.
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STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7
Check Intermediate Range Flux:
- a.
Flux - LESS THAN
- a. IF power NOT 2x10- 9 AMPS.
Tecreasing, THEN go to Sol-1.1-27, EMERGENCY BORATION.
AND Continue with step
- 9. WHEN flux decreases below 2x10-9 amps, THEN perform steps 7F7 AND 7c.
- b.
Verify source range detectors high voltage ON.
- c. Transfer nuclear recorders to source range scale.
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S01-1.2-1.01 REACTOR TRIP RESPONSE REV 0 ACTION/EXPECTED
RESPONSE
RESPONSE NOT OBTAINED 8
Verify Termination Of Generator Coastdown:
- a.
Coastdown terminated - AT 40% of NOMINAL TERMINAL VOLTAGE (7200 VOLTS).
- b.
ACB l1AO4 -
OPEN.
- b. Manually open ACB 11804 -
OPEN.
breakers.
Generator Field Breaker OPEN.
9 Restore Power to 4 KV busses ]A AND 1B From Auxiliary Transrormer C:
- a.
Verify RCP breakers:
- a. Manually open ACB 11A01 -
OPEN.
breakers.
ACB 11A03 -
OPEN.
ACB 11803 -
OPEN.
- b. Close ACB 11CO1,
- b. IF neither bus can be AND ACB 12C01..
Tuxiliary transformer C, THEN:
- 1) Reset the lockup bus.
- 2) Verify open OR open the generator motor operated disconnect switch.
- 3) Close Unit 1 CB CB 4012 OR CB 6012.
- 4) Close ACB 11A04 AND ACB 11B04.
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STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Start At Least One RCP:
- a. Establish conditions for
ITarted, THEN monitor natural cTFiulation per step 11.
- b. Start RCP B.
- minutes, staFFRCP C.
- c. Go to step 12.
11 Monitor For RCS Natural Circulaton Usrng trended Values:
- a. RCS subcooling
- Attempt to establish GREATER THAN natural circulation 400F.
by increasing steam dump.
- b. Steam header pressure STABLE.
- c.
RCS cold leg temperature -
STABLE OR SLOWLY DECREASING 70DN NEAR SATURATION TEPERATURE FOR STEAM HEADER PRESSURE.
- d.
Core exit TCs STABLE OR SLOWLY DECREASING.T
- e.
Refer to S01-3-6, PLANT OPERATION WITH NATURAL CIRCULATION.
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S0l -1
.2-1.01 REACTOR TRIP RESPONSE REV 0 0STEP ACTION/EXPECTED RESPONSE.
RESPONSE NOT OBTAINED 12 Maintain Stable Plant Conditions:
- a. Pressurizer pressure - AT 2085 PSIG.
- b. Pressurizer level -
AT 15%.
- c.
SG narrow range level -
AT 50%.
13 Align Turbine Drains:
- a. Open turbine drain valves.
14 Align Reheater Steam Supply:
- a. Close reheater steam supply MOVs.
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S01-1.2-1.01 REACTOR TRIP RESPONSE REY 0 ST ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 SG Level Control Transfer With Feed Pump Operation:
- a.
One feed pimp breaker
- a. IF both feed pimps are
- CLOSED.
NT available, THEN go to step 17.
- b.
AFW system -
INITIATED.
- c. Establish flow through CV 142, CV 143, AND CV 144.
- d. Reduce flow thrcuah FCV 3300, FCV 3301, FCV 2301, AND FCV 2300, while increasing flow through CV 142, CV 143, AND CV 144.
16 Reset Auto AF initiation:
- a.
Place AFW system in - MANUAL AND depress RESET pushbuttons.
C. Stop motor driven pimp.
- d.
Close turbine driven pump AFW header discharge valve.
- e. Stop the turbine driven pump.
- f. Go to step 18.
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501-1.2-1.01 REACTOR TRIP RESPONSE REV 0 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINE 17 SG Level Control Transfer With AEW Pump Operation:
- a.
Place AFW system in - MANUAL.
- b.
Open motor driven pump main FW header discharge valve.
- c. Establish flow through CV 142, CV 143, AND CV 144.
- d. Reduce flow through FCV 3300, FCV 3301, FCV 2301, AND FCV 2300 while increasing flow through CV 142, CV 143, AND CV 144.
- e.
Close motor driven pump AFW header discharge.
- f.
Close turbine driven pump AFW header discharge valve.
- g. Shutdown steam driven AFW pump.
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S01-1.2-1.01 REACTOR TRIP RESPONSE REV 0 STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify Start of Turbine Auxiliary Oil Pump:
- a. Pump breaker - CLOSED.
- a. Manually start.
19 Verify Automatic Turbine Turning Gear Engagement:
- a.
Turning gear motor
- a. Manually engage indicating light -
ON.
A NL Zero speed alarm RESET.
20 Investigate Cause Of Reactor Trip:
- a. Evaluate alarm indications and monitor Plant status.
21 Inspect Containment:
- a. Check for fluid system leakage.
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501-1.2-1 01 REACTOR TRIP RESPONSE REV 0 STEPEACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Establish Plant Status:
- a. IF plant is to remain
- a. IF plant is to be Th hot standby, THEN:
Zoled down, THEN:
1 ) Borate RCS to Xenon - free
S01-3-5, FTN COLD SHUTDOWN.
- 2) Maintain stable plant
- 2) IF NO RCPs are contions per step 9.
r.nn:ring, THEN go to SO-3-6, P77 OPERATION WITH NATURAL CIRCULATION.
- b. Go to S01-3-4, PLANT SHUTDOWN FROM FULL POWER TO HOT STANDBY.
-E N D H. E. MORGAN MANAGER, STATION OPERATIONS 13 of 14
UI-i.L-
.U.L r
V U
MWTQR DRIVEN AFR' PUMP RESTART CRITERIA
- a. IF a motor driven AFW pump trips on low discharge pressure, THEN:
- 1) Lower AFW flow controllers.
- 2) Reset AND restart pump.
SI REINITIATION CRITERIA FOLLOWING SPURIOUS.SI
- a. Reinitiate SI if ANY ONE of the parameters listed below occurs:
') -RCS -Pressure
-LESS THAN 1735 PS1G.
- 2) Containment Pressure
- GREATER THAN 1.4 PSIG.
SYMPTOMS FOR RESPONSE TO INADEQUATE CORE COOLING
- a. Go to S01-1.2-14, RESPONSE TO INADEQUATE CORE COOLING, when ANY ONE of the following symptoms occur:
- 1) Five or more core exit TCs -
GREATER THAN 1200 oF.
- 2)
RCS hot leg temperatures -
GREATER THAN 700 OF.
SYMPTOMS FOR RESPONSE TO LOSS OF SECONDARY HEAT SINK
- a. Go to SO-1.2-15, RESPONSE TO LOSS OF SECONDARY HEAT SINK IF AFW Flow is NOT AVAILABLE.
IF EVENTS REQUIRE IMPLEMENTATION 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 inplementation of the Emergency Plan per S0123-VIII-11, RECOGNITION AND CLASSIFICATION OF EMERGENCIES.
- d. IF event is NOT classified as an emergency in c above THEN determine if Wtification-oT the NRC is required within one hour per 501-14-13, NOTIFICATION TO NRC OF SIGNIFICANT EVENTS.
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