ML20205C805

Rev 2 to Emergency Operating Procedure EOP 35 FR-P.2, Response to Anticipated PTS Condotion

ML20205C805
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	06/15/1988
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467	List: A07413, Forwards Specific Emergency Operating Procedures for Use During Incident Response Ctr Activation ML20204H704 ML20204H734 ML20204H868 ML20204H928 ML20204H963 ML20204J027 ML20204J039 ML20204J092 ML20204J109 ML20204J115 ML20204J120 ML20204J128 ML20204J133 ML20204J139 ML20204J147 ML20204J497 ML20204J543 ML20204J565 ML20204J627 ML20204J633 ML20204J638 ML20204J642 ML20204J659 ML20204J669 ML20204J685 ML20204J707 ML20204J733 ML20204J739 ML20204J746 ML20204J767 ML20204J781 ML20204J786 ML20204J814 ML20204J824 ML20204J849 ML20204J853 ML20204J865 ML20204J878 ML20204J902 ML20204J914 ML20204J920 ML20204J939 ML20204J947 ML20204J954 ML20204J958 ML20204J965 ML20204J975 ML20204J982 ML20204J994 ... further results
References
EOP-35-FR-P.2, NUDOCS 8810260576
Download: ML20205C805 (8)

Text

- __ _ ________ _ - __________-_ _______ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

STATION PROCEDURE COVER SHEET A.

IDENTIFICATION Number: E0P 35 FR-P.2 Rev.

2

Title:

RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SH0CK CON 0! TION Preparcd By: H.

K. COVIN/J.

L. BUCKINGHAM 8.

REVIEW

! have reviewed the above procedure and have found it to be satisfactory.

TI T L_E

$!GNATURE DATE DEPARTMENT HEAD db fa,!f,If g

g C.

SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation

/

YES [ ]

NO [9 of systems as described in design documents.

(If yes, perform writtan 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 [ 'j NO [

0.

SPECIFIC SAFETY EVALUATION 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 [ 4 (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 [ 'J PROCEDURE REQUIRES b S0RC REVIEW F.

YES((]

(In addition to revT W, it with a YES response NO [ ]

must be documented in th R /SORC meeting minutes.)

G.

50RC APPROVAL SORC Meeting Number

_1 - f 3 -/o 3 H.

APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:

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11.1 7 Station / Service / Unit Superintendent Effective Date SF301/9/s/SES/87-12/lof1 8910260576 001007 gDR ADOCK 050fg

l E0P 35 FR-P.2 Pago 1 Rav. 2 r

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RESPONSE TO ANTICIPATED PRESSURIZE 0 i

THERMAL SHOCK CONDITION Page No.

Eff. Rev.

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RESPONSE TO ANTICIPATED PRESSURIZED E0P 35 FR-P.2 Pago 2 THERMAL SHOCK CONDITION Rev. 2 A.

PURPOSE This procedure provides actions to respond to a limited overcooling condition or to an overpressure condition at low temperature.

B.

ENTRY CONDTIONS This procedure was written for Modes 1, 2, 3 and 4.

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 35 F-0.4, INTEGRITY Critical Safety Function Status Tree, on either YELLOW condition.

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RESPONSE TO ANTICIPATED PRESSURIZED E0P 35 FR-P,2 Peg 2 3 THERMAL SHOCK CORDITION Rev. 2

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STEP ACTION / EXPECTED RESPONSE RESPONet NOT 00TAINED NOTE A faulted SG is any SG that is depressurizing in an uncontrolled manner or is completely depressurized.

1 Check RCS Cold Leg Temperatures Try to stop RCS cooldown

- STABLE OR INCREASING a.

Verify SG atmospheric dump valves and safeties

closed, b.

Verify condenser steam dump valves closed, c.

IF RER system in service, THEN stop any,

cooldown from RRR system.

d.

Control feed flow to non-faulted SG(s) to stop RCS cooldown.

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Maintain total feed i

j flow > 525 gpm until narrow ratte level >4%

(34% FOR ADVERSE CONTAlWF.NT) in at least one non-faulted SG.

e.

Minimize cooldown from I

faulted SG(s).

1. CLOSE the following Main Steam Line Isolation and Bypass Valves Main Feed Line Isolation Chemical Feed Blowdown and Sampling Lines Steam Supply to TDAFW Pump SG Atmospheric Dump Valves Main Steam Line Low Point Drains TDAFW Pump Low

N Point Drains oPKSS 1 3-44

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RESPONSE TO ANTICIPATED PRESSURIZED E0P 35 FR-P.2 Pag] 6 THERMAL SHOCK CONDITION Rev. 2

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STEP ACTION /tXPECTED RESPONSE RESPONSE NOT 08TAINED n/

2) IF all SGs faulted, THEN control feed flow at 75 gpm to each SG.

3) IF any SG not faulted. THEN isolate all feedwater to faulted SG(s) unless necessary for RCS temperature control.

IF a faulted SG is necessary for RCS temperature control, THEN control feed flow at 75 gpa to that SG.

2 Check If ECCS Has Been Go to Step 5.

Te rmina ted a.

SI pumps - ALL STOPPED

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b.

Charging Pump to Reactor x- /

Cold f.eg Isolation Valves -

CLOSED 3

Check RCS Pressure - WITHIN Lower RCS pressure to TECH SPEC PRESSURE-TEMPERATURE within tech spec limits LIMITS FOR 100*F/HR COOLDOWN using normal PIR spray.

RATE IF normal spray NOT available and letdown is in service, THEN use auxiliary spray.

IF NOT, THEN use one PZR PORV.

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o RESPONJE TO ANTICIPATED PRESSURIZED E0P 35 FR-P.2 Pege 5 THERMAL SHOCK CONDITION Rev. 2

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STEP ACTION /IXPECTED RE SPONSE RESPCNSE NOT CSTAINED

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x-4 Determine If Additional RCS Cooldown Restrictions Are Required a.

Cooldown rate in any RCS a.

Additional cooldown cold leg >100'F IN ANY restrictions are not 60 MINUTE PERIOD required. Go to Step 5.

b.

RCS cooldown is permitted with the following restrictions

1) Maintain RCS pressure and cold leg temperatures within the limits of OPS Form E0P 35 FR-P.2-1 (OPS Form E0P 35 FR-P.2-2 FOR ADVERSE CONTAINMENT)

2) Maintain cooldown rate in RCS cold legs <100*F in any 60 minute period.

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5 Return to Procedure and Step (d

In Effect

-FINAL-CPhy41 344

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