ML20205C465

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Rev 2 to Emergency Operating Procedure EOP 35 FR-C.2, Response to Degraded Core Cooling
ML20205C465
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.2, NUDOCS 8810260506
Download: ML20205C465 (9)
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  • St'ph n E. ace 3-31-87 87-12 Fcrm Apprsved by Stativ.r SuperintCnd;nt Effective D ho 50RC Mtg. No.

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STATION PROCEDURE COVER SHEET

( A. IDENTIFICATION V

Number: E0P 35 FR-C.2 4ev. 2

Title:

R.oPONSE TO DEGRADED CORE COOLING Prepared By: H. K. COVIN B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE 6 s7l DEPARTMENT HEAD A7 b, @,v 3 / if 17 v j l C. SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED: '

Modifies intent of pr3cedure and changes operation of systems as described in design documents. YES [ ] NO [-1" (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 [@

0. SPECIFIC SAFETY EVALUATION PFOUIRED 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 [Jr (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(-Y F. PROCEDURE REQUIRE h SORC REVIEW (In addition to rs W 6 ite with a YES response must be documented in the; OR SORC meeting minutes.) YES [-T NO [ ]

G. 50RC APPROVAL SORC Meeting Number 3-8 7-///f H. APPROVAL AND IMPLEMENTATION The attached r e eby approved, and effective on the date below:

./ f dl - pr W StatT6n/ Service / Unit Superintendent Effective Date ~

SF 301  ;

Rev. 9 age 1 M 1 8910260506 001007 PDR ADOCK 05000213 P PDR

E0P 35 FR 2 Page 1

. Rev. 2 i

l RESPONSE TO DEGRADED CORE COOLING Page No. Eff. Rev.

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9 e RESPONSE TO DEGRADED CORE COOLING E0P 35 FR-C.2 Pege 2 Rev. 2

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

B. ENTRY CONDITIONS This procedure was written for Modes 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 still applicable to current plant conditions.

This procedure is entered from E0P F-0.2, CORE COOLING Critical Safety Function Status Tree, on any ORANGE condition.

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RESPONSE TO DEGRADED CORE COOLING- E0P 35 FR-C.2 Page 3 Rev. 2

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OETAINEO CAUTION If RWST level decreases to <520,000 gal, the ECCS Systems j should be aligned for cold leg recirculation using E0P 35 ES-1.3. TRANSFER TO COLD LEO RECIRCULATION, 1 Verify ECCS Valve Alignment - Manually align valves as PROPER EMERGENCY ALIGNMENT necessary 2 Verify ECCS Flow In All Trains

a. Charging pump SI flow a. START pumps and align ,

indicator - CHECK FOR FLOW valves as necessary

b. SI pump flow indicators - b. START pumps and align CHECK FOR FLOW valves as necessary
c. RCS pressure < 300 psia c. Go to Step 3.

(450 psia FOR l O d.

ADVERSE CONTAINMENT)

RHR pump flow indicators - d. START pumps and align CHECK FOR FLOW valves as necessary 3 Check RCS Vent Paths

a. PZR PORVs - CLOSED a. Manually CLOSE PZR PORVs.

IF any valve can NOT be closed, M manually CLOSE its olock valve,

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

an open PZR PORV.

c. Reactor vessel head vent c. CLOSE reactor vessel isolation valves - CLOSED head vent isolation valves.
d. PZR vapor space sample d. CLOSE PZR vapor space isolation valves - CLOSED sample isolation valves.

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RESPONSE TO DEGRADED CORE COOLING EOP 35 FR-C.2 Peg 2 4 Rev. 2 STEP ACTION / EXPECTED NESPONSE RESPONSg NOT OSTAINED NOTE Normal conditions for running RCPs are desired BUT RCPs should NOT be tripped IF normal conditions can NOT be established or maintained.

4 Check RCP Status

a. At least one RCP - RUNNING a. Go to step 7.
b. RPCCW to RCPs - AVAILABLE b. Establish RPCCW to RCPs.
c. Seal injection to RCPs - c. Establish seal injection.

CHECK FOR FLOW

d. Seal water return from d. Establish seal water .

RCPs - CHECK FOR FLOW 1e a ko f f .

5 Check RVLMS Indication

a. Plenum Indication 1 19% a. Go to Step 6.

s g b. Return to procedure and step in effect 6 Check if One RCP Should Be Stopped

a. All Operable RCPs - a. Go to Step 8.

RUNNING

b. STOP one RCP using the following order as a guide (RCP 2, 1 THEN 3, 4)
c. Go to Step 8 7 Check Core Cooling
a. RVLMS plenum indication a. Go to Step 8.

1 19%

! b. Core exit TCs < 720'F b. IF decreasing, THEN return to Step 1. 1F E

N , THEN go to Step 8.

c. Return to procedure and step in effect.

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s e RESPONSE TO DEGRADED CORE COOLING E0P 35 FR-C.2 Page 5 Rev. 2

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED l

l 0 Check SI Accumulator Isolation Valve Status ,

a. Isolation valves - OPEN a. Open isolation valves {

as follows

1) Restore power to isolation valves (32-2R-RSF, 32-2W-R3J, 32-2R-F4M, i

32-2W-F4M) ,

2) OPEN isolation valves i UNLESS closed after 6 accumulator discharge.
3) Remove power from l isolation valves. ,

u CAUTION

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

i 9 Check Intact SG Levels

a. Narrow range level a. Raise total feed flow i > 4% (34% FOR ADVERSE to restore narrow range CONTAINMENT) level > 4% (34% FOR ADVERSE CONTAINMENT) in i at least one SG I b. Control feed flow to

! maintain narrow range

! level l'etwe en 4%

} (34% FOR ADVERSE

! CONTAINMENT) and 50%

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RESPONSE TO DEGRADED CORE COOLING E0P 35 FR-C.2 Page 6 Rev. 2 N

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINEO CAUTION The following step may cause a red path condition in E0P 35 F-0.4, INTEGRITY CRITICAL SAFETY FUNCTION STATUS TREE. This procedure should be completed before transition of E0P ?.5 FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK.

10 Depressurize All Intact SGs To 134 psig

a. Maintain cooldown rate in -

RCS cold legs < 100*F/HR

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b. Dump steam to condenser b. Manually OR locally 1

dump steam from SGs to i Atmosphere 1

c. Check SG pressures c. Return to Step 9.

J O < 134 psig

d. Stop SG depressurization I

l CAUTION

195'F without RPCCW to the RHR HXs.

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I 11 Check RHR Pumps - RUNNING START pumps as necessary.

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RESPONSE TO DEGRADED CORE COOLING EOP 35 FR-C.2 Page 7 Rev. 2

- sTap AcT10N/expeciso RespoNas assPONas NOT OsTAINED 12 Check If SI Accumulators Should Be Isolated

a. At least two RCS hot leg a. Go to Step 14.

temperatures < 375'F

b. Restore power to isolation valves i

(32-2R-RSF, 32-2W-R3J, ,

32-2R-F4M, 32-2W-F4M)

c. CLOSE all SI accumulator c. Vent any unisolated isolation valves accumulator l
d. Remove power from isolation valves .

CAUTION Symptoms for E0P 35 FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, should be closely monitored during subsequent steps.

O 13 STOP All RCPs 14 Depressurize All Intact SGs To Atmospheric Pressure

a. Maintain cooldown rate in RCS cold legs < 100*F/HR
b. Dump steam to condenser b. Manually OR_ locally dump steam from SGs to Atmosphere O

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, RESPONSE TO DEGRADED CORE COOLING E0P 35 FR-C.2 Paga 8 Rev. 2 f )

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED

___15 Verify ECCS Flow Continue efforts to establish ECCS flow. Return to Step 14.

a. Charging pump SI flow indicator - CHECK FOR FLOW SE
b. SI pump flow indicators -

CIIECK FOR FLOW 93

c. RHR pump flow indicators -

CHECK FOR FLOW 16 Isolate SI Accumulators *

a. Restore power to isolation valves (32-2R-R5F, 32-2W-R3J, 32-2R-F4M, 32-2W-F4H) q q ,,) b. CLOSE All SI Accumulator b. Vent any unisolated Isolation Valves accumulator
c. Remove power from isolation valves 17 STOP All RCPs

___18 Check Core Cooling Return to Step 14.

a. RVLMS plenum level

> 19%

b. At least two RCS hot leg temperatures <350'F l

___19 Go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 12

-FINAL-(">

OPK441 1 44

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