ML20205C634

Rev 1 to Emergency Operating Procedure EOP 35 FR-H.4, Response to Loss of Normal Steam Release Capabilities

ML20205C634
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	12/13/1985
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
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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.4, NUDOCS 8810260545
Download: ML20205C634 (4)

Text

0 E. J. Mrset

• 1-1-85 Form Approved by Station Superintendent Effe'ctivo Dato

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STATION PROCEDURE COVER SHEET

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w A. IDENTIFICATION Number E0P 35 FR-H.4 Rev. 1 Title RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES Prepared By J. D. Catlin

8. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEAD /2!I [5 C. UNREVIEWED SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED:

(Significant change in procedure method or scope YES [ ] NO M as described in FSAR)

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

ENVIRONMENTAL IMPACT (Adverse environmental impact) YES [ ] N0 g (If yes, document in PORC/SORC meeting minutes)

D. INTEGRATED SAFETY REVIEW REQUIRED (Affects response of Safety Systems, performance YES [ ] NO N 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 REQUIP,EefP M SORC REVIEW YES ><1 NO [ ]

F. (P6lIC'/50RCAPPROVAL h 0RC Meeting Number P86 c72A G. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approvt', and effective on the date below:

L v4 W Station /S@Ee/ Unit Superindndent l .) ~ l Effect ve Date

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SF 301 Rev. 7 8810260545OyO[ht:3 Page 1 of 1 PDR ADOCK PDR P

E0P 35 FR-H.4 Page 1 Rev. 1 RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES Pale No. Eff. Rev.

1-3 1 O

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RESPONSE TO LOSS OF NORMAL ST2AM E0P 35 FR-H.4 Page 2 RELEASE CAPABILITIES Rev. 1 O\_ /

A. PURPOSE This procedure provides actions to respond to a failure of the steam generator atmospheric dump valves and condenser dump valves.

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, KEAT SINK Critical Safety Function Status Tree on a YELLOW conditiot.

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• RESPONSE TO LOSS OF NORMAL STEAM E0P 35 FR-H.4 Pags 3 RELEASE CAPABILITIES Rev. 1 V -

STEP ACTION /EX*ECTED RESPONSE RESPONSE NOT OSTAINED NOTE Throughout this procedure, "affected" refers to any SG in which pressure is greater than 1185 psig.

CAUTION If affected SG(s) narrow range level increases to greater than 92% (77%

for adverse centainment), steam should not be released from the affected SG(s).

1 Try To Restore Normal Steam '

Release capability Of Affected ,

SG(s)

a. Atmospheric dumps QR

b. Condenser steam dump

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2 Check SG Pressures - LESS THAN Manually or locally dump steam 1185 PSIG from SG(s) with pressure greater than 1185 psig.

3 Return to Procedure And Step In Effect

-FINAL-4 O

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