ML20205C544

Rev 1 to Emergency Operating Procedure EOP 35 FR-H.2, Response to Steam Generator Overpressure

ML20205C544
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	12/13/1985
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-H.2, NUDOCS 8810260524
Download: ML20205C544 (6)

Text

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E. J. Mroci

• 1-1-85 Form Apprcved by St; tion Superintendent Effective Date STATION PROCEDURE COVER SHEET A. IDENTIFICATION Number E0P 35 FR-H.2 Rev. 1 Title RESPONSE TO STEAM GENERATOR OVERPRESSURE Prepared By J. D. Catlig B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEAD I -

k /2 /d C. UNREVIEWE0 SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED:

(Significant change in procedure method or scope YES ( ) NO ){

as described in FSAR)

(If yes, document in PORC/SORC meeting minutes)

ENVIRONMENTAL IMPACT (Adverse environmental impact) YES [ ] NO M (If yes, document in PORC/SORC meeting minutes)

D. INTEGRATED SAFETY REVIEW REQUIRED (Affects response of Safety Systems, performance YES [ ] NO k of safety-related control systems or performance of control systems which may indirectly affect safety system response.)

(If yes, document in PORC/SORC meeting minutes.)

E. PROCEDURE REQUIRES M ORC REVIEW YES}Q NO ( )

F. 66R260RCAPPROVAL

@ 0RC Meeting Number 3 -85' Mk G. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:

V-W V I2 -134_C hv Station /Ser#ce/ Unit Superintendent Effective Date SF 301 Rev. 7

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E0P 35 FR-H.2 Page 1

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RESPONSE TO STEAM GENERATOR OVERPRESSURE i i l Page No. Eff. Rev.

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RESPONSE TO STEAM GENERATOR OVERPRESSURE E0P 35 FR-il.2 Pag 2 2 Rev. 1

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A. PURPOSE This procedure provides actions for an overpressure condition affecting any steam generator where pressure has increased above the highest steamline safety valve setpoint.

B. ENTRY CONDITIONS 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-0.3, HEAT SINK Critical Safety Function Status Tree on a YELLOW condition. .

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f 7sPon5E To STEAM or.nr.KAf0K OVLKYKL55 UKE EOP 35 FR-H.2 Pega 3 Rev. 1 O - SYtp ACTION /SEPECTED RESPO94SE R8SPONSE NOT OSTAltetO NOTE Throughout this procedure, "affected" refers to any i SG in which pressure is greater than 1225 psis, i

1 Identify Affected SG(s)

a. Any SG pressure - a. Return to procedure and GREATER THAN 1225 ?SIG step in effect. l 2 Verify FW Isolation To Manually close valves Affected SG(s)

a. Flow control valves -

CLOSED  ;

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b. Flow control bypass l valves - CLOSED , l

c. FW trip valves -

CLOSED

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3 Check Affected SG(s) Go to E0P 35 FR-H.3, RESPONSE  !

Narrow Range Level - TO STEAM GENERATOR HIGH LESS THAN 92% LEVEL, Step 1. i O (77% FOR ADVERSE CONTAINMENT)

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CAUTION If affected SG narrow range level increases to l greater than 92% (77% for adverse containment),  !

steam should not be released from the affected SG(s),

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i RESPONSE TO STEAM GENERATOR OVERPRESSURE E0P 35 FR-H.2 Pegs 4 Rev. 1

!. - STEP ACTION /EEPECTED RESPONSE RESPONSE NOT OSTMNEO i i

4 Try To Dump Steam From The Go to Step 6.

Affected SG(s)  ;

a. SG Atmospheric Dumps

b. SG Atmospheric Dump Bypass valves 0

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c. Main steamline isolation bypass valves .

OR

) d. Steam supply valves to e i turbine-driven AW pump  ;

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5 Check Affected SG(s) Pressure

a. Pressure - DECREASING a. Go to Step 6. (

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b. Pressure - LESS THAN b. Return to Step 3.  !

l 1225 PSIG j 1  !

! c. Control steam release to i maintain SG pressure less than 1225 PSIG i

d. Return to procedure and j step in effect.  ;

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CAUTION I AW flow should remain isolated to affected SG(s)  !

i until a steam release path is established.

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i 6 Isolate AW Flow To t

Affected SG(s) l J ,

i 7 Check RCS Hot Les cool down RCS to less than  !

Temperatures - LESS THAN 539'T (539'T for adverse  !

539'F (539'T FOR containment) by dimping l steam from the unaffected SG(s)

. ADVERSE CONTAINMENT) l

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RESPONSE TO STEAM UENERATOR QVLKrKr.55 UMP EOF 33 FR-H.Z Paga 3 Rev. 1

- tTap ACTIONitXPECTRO RSSPONSE R88POM48 NOT 00TAIN80 8 Continue Attempts To Manually Or Locally Dump Steam From Affected SG(s)

a. SG Atmospheric Dumps

b. SG Atmospheric Dump Bypass valves

c. Main steamline isolation bypass valves

d. Steam supply valves to turbine-driven AFV Pump 9 Return to Procedure And Step In Effect

-FINAL-O CP50641 3 04