ML20205C442

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Rev 2 to Emergency Operating Procedure EOP 35 FR-C.1, Response to Inadequate Core Cooling
ML20205C442
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 06/15/1988
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-35-FR-C.1, NUDOCS 8810260497
Download: ML20205C442 (10)


Text

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STAT!6N PROCEDURE COVER SHF' g A. IDENTIFICATION Number; E0P 35 FR-C.1 Rev. 2,

Title:

RESPONSE TO INADEQUATE CORE COOLING 1

Prepared By: J. BUCKINGHAM/H. K. COVIN B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEAD No (,, fl J- \

C. SPECIFIC UNREVIEWE0 SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation of systems as described in design documents. YES [ ] NO [4 (If yes, perform written USQ determination and Safety ,

Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES [ ] NO C -7

0. SPECIFIC SAFETY FVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety system response. YES [ ] NO [-7 (If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

E. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] NO [ T F. PROCEDURE REQUIRE b /SORC REVIEW (In addition to rebiew, item with a YES response must be documented in the 50RC meeting minutes.) YES [ g NO [ ]

  • G. 50RC APPROVAL /$0RC Meeting Number 3 -8 7-/hf H. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:

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$~/S~~ Yb Station / Service / Unit Superintendent Effective Date SF301/9/s/SES/87-12/lofi 8910260497 001007 PDR ADOCK 05000213 P PDR

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E0P 35 FR-C.1 Page 1

. Rev. 2

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0 RESPONSE TO INADEQUATE C,')RE COOLING Paae No. Eff Jej.,

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RESPONSE TO INADEQUATE CORE COOLING E0P 35 FR-C.1 Page 2 L Rev. 2 V

A. PURPOSE This procedure provides actions to restore core cooling.

d B. ENTRY CONDITIONS This procedure was written for Modts 1, 2, and 3. Using this procedure when not in these modes requires a step by step evaluation to determine if the required action is s'ill applicable to current plant conditions.

This procedure is entered from EOP 35 F-0.2, CORE COOLING Critical Safety Function Status Tree, on the RED condition.

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r RESPONSE TO INADEQUATE CORE COOLING E0P 35 FR-C.1 Page 3 Rev. 2

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STEP ACTION /EXPECTF0 RESPONSE HESPONSE NOT OSTAINED l CAUTION

1. If RWST level decreases to < 520,000 gal, the ECCS systems should be aligned for cold leg recirculation using E0P 35 ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.
2. RHR pumps should not be run with RHR Hx inlet temperatures > 195*F without RPCCW to the RHR Hxs. g 1 Verify ECCS Valve Alignment - Manually align valves-PROPER EMERGENCY ALIGNMENT as necessary 2 Verify ECCS Flow In All e Trains
a. Charging pumps SI a. START pumps and align flow indicator - valves as necessary CHECK FOR FLOW

's b. SI pump flow b. START pumps and align indicators - CEECK valves as necessary FOR FLOW

c. RER pump flow c. START pumps and align indicators - CHECK valves as necessary FOR FLOW 3 Check RCP Support Conditions
a. Any 6.9 KV bus - a. Restore power to buses.

ENERGIZED

b. RPCCW to RCPs - b. Establish RPCCW to RCPs.

AVAILABLE

c. Seal injection to RCPs - c. Establish seal injection.

CHECK FOR FLOW

d. Seal water return d. Establish seal water from RCPs - CHECK leakoff.

FOR FLOW oPSO441 3-44 l

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RESPONSE TO INADEQUATE CORE COOLING EOP 35 FR-C.1 Peg 2 4 Rev. 2 STEP ACTION / EXPECTED RESPONSg RESPONSg NOT 08TAINED 4 Check SI Accumulator Isolation Valve Status

a. Isolation valves - OPEN a. Open isolation valves as follows
1) Restore power to isolation valves (32-2R-R5F, 32-2W-R3J, 32-2R-F4M, 32-2W-F4M)
2) OPEN isolation valves UNLESS closed after e accumulator discharge
3) Remove power from isolation valves.

5 Check Core Exit TCs < 1200*F Go to Step 7.

6 Check Core Exit TCs .

a. Temperature < 720'F a. IF decreasing THEN return to Step 1. IF NOT, THEN go to Step 7'.
b. Return to procedure f- g and step in effect '

7 Check Containment Hydrogen Concentration

a. Determine containment a. Have Chemistry obtain a hyrogen per OP 3313A, hydrogen sample per the NYDROGEN RECOMBINERS, POST ACCIDENT LIQUID HYDROGEN MONITORS AND SAMPLING SYSTEM RECOMBINER BLDO VENTILATION
b. Hydrogen concentration b. Consult Director of
< 5.0% Station Emergency l Organization (DSEO) for l tiditional recovery actions. Go to Step 8
c. Hydrogen concentration c. Turn on hydrogen

< 0.5% recombiner system per OP 3313A, NYDROGEN RECOMBINERS AND RECOMBINER BUILDING VENTILATION O

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RESPONSE TO INADEQUATE CORE C004}NG EOP 35 FR-C.1 Page 5 Rev. 2-(-

d STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED CAUTION

1. CST water source for AFW pumps will be necessary IF,DWST level decreases to < 80,000 gal.
2. A faulted or ruptured SG should NOT be used in subsequent steps UNLESS no intset SG is available.

8 Check Intact SG Levels

a. Narrow range level a. Raise total feed flow

> 4% (34% FOR ADVERSE to restore narrow range CONTAINMENT) level > 4% (34% FOR

' ADVERSE CONTAINMENT).

IF total feed flow

< 525 gps, TNEN go to Step 17. OBSERVE NOTE l PRIOR TO STEP 17.

b. Control feed flow to maintsin narrow range level between 4%

(34% FOR ADVERSE CONTAINMENT) and 50%

9 Check RCS Vent Paths

a. PZR PORVs - CLOSED a. Manually close PZR PORVs.

IF any valve can NE be closed, THEN manually close its block valve.

! b. Block valves - AT b. Open block valve UNLESS LEAST ONE OPEN it was closed to isolate

an open PZR PORV.
c. Reactor vessel head vent c. Manually close reactor isolation valves - vessel head vent CLOSED isolation valves.
d. PZR vapor space d. Manually close PZR vapor sample isolation space sample isolation valves - CLOSED valves.

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, RESPONSE TO INADEQUATE CORE COOLING EOP 35 FR-C.1 Page 6 Rev. 2 0 -

eTEP ACTION / EXPECTED RESPONSE RESPONSE NOT OETAINEO NOTE

1. Partial uncovery of SG tubes is acceptable in the following steps.
1. Bypass Low Low Tavg interlock at 553*F to maintain steam dump operation.
3. Block steamline isolation when P-11 light lit.

10 Depressurize All Intact SGs To 134 psig

a. Dump steam to the a. Dump steam at maximma condenser at maximum rate to atmosphere rate
b. Check SG pressures b. IF SG pressure

< 231 psig decreasing, THEN return to Step 8. IF NOT, THEN go to Step 17. OBSERVE NOTE PRIOR TO STEP 17..

c. Check RCS hot leg c. IF RCS hot leg temperatures - AT temperatures decreasing, ps LEAST TWO < 375*F THEN return to Step 8.

\ ,) IF NOT, THEN go to Step

17. OBSERVE NOTE PRIOR TO STEP 17.
d. Stop SG depressurization 11 Check If SI Accumulators Should Be Isolated
a. At least two RCS a. Go to Step 17. OBSERVE hot leg temperatures NOTE PRIOR TO STEP 17.

< 375'F

b. Restore power to isolation valves (32-2R-R5F, 32-2W-R3J, 3?-2R-F4M, 32-2W-F4M)
c. CLOSE isolation valves c. Vent any unisolated accumulator
d. Remove power from isolation valves.

12 STOP All RCPs O

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 13 Depressurize All Intact SGs To Atmospheric Pressure

a. Dump steam to condenser a. Dump steam at maximum at maximum rate rate to atmosphere 14 Verify ECCS Flow
a. Charging pump SI flow a. Continue efforts to indicator - CHECK establish ECCS flow.

FOR FLOW IF core exit TCs

< 1200*F, THEN OR return to Step 13. IF NOT, THEN go to Step 17.

SI pump flow OBSERVE NOTE PRIOR TO indicators - CHECK STEP 17.

FOR FLOW OR .

RHR pump flow indicators - CHECK FOR FLOW 15 Check Core Cooling

a. Core exit TCs < 1200*F a. Go to Step 17. OBSERVE NOTE PRIOR TO STEP 17.
b. At least two RCS hot b. Return to Step 13.

leg temperatures < 350'F

c. RVLMS plenum level > 19% c. Return to Step 13.

16 Go To EOP 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 12 O

CP50641 3-44

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RESPONSE TO INADEQUAIE CORE COOLING E0P 35 FR-C.1 Pega 8 Rev. 2

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Normal conditions are desired but not required for starting the RCPs.

17 Check Core Exit TCs < 1200*F Start RCPs as necessary until core exit TCs < 1200*F IF core exit TCs > 1200*F and all available RCPs running, THEN open all PZR PORVs and block valves. IF-core exit TCs > 1200*F and all PZR PORVs and block valves are open, THEN open all other RCS vent paths to containment.

18 Try To Locally Depressurize ,

All Intact SGs to Atmospheric Pressure

a. Locally open steam a. Use faulted OR ruptured dump valves OR SG.

Atmospheric Dumps OR

~ ~ , Atmospheric Dump

( ') bypass valves.

U 19 Check If SI Accumulators Should Be Isolated

a. RHR pump flow a. Return to Step 17.

indicators - AT LEAST INTERMITTENT FLOW

b. Restore power to isolation valves (32-2R-RSF, 22-2W-R3J, 32-2R-F4M, 32-2W-F4M)
c. CLOSE isolation valves c. Vent any unisolated accumulator
d. Remove power from isolation valves.

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RESPONSE TO INADEQUATE CORE COOLING E0P 35 FR-C.1 Pags 9 Rev. 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 20 Check If RCPs Should Be Stopped .

a. At least two RCS hot a. Go to Ste; 21.

temperatures < 350*F

b. STOP all RCPs 21 Verify ECCS Flow
a. Charging pump SI a. Continue efforts to flow indicator - establish ECCS flow.

CHECK FOR FLOW Return to Step 17.

EE SI pump flow indicators - CHECK ,

FOR FLOW .

9E RKR pump flow indicators - CHECK FOR FLOW 22 Check Core Cooling

a. RVLMS plenum level a. Return to Step 17.

> 19% AND at least two RCS hot leg temperatures

< 350'F 23 Go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 12

-FINAL-O OPS 0041 3 44