ML20205B151

Rev 1 to Emergency Operating Procedure EOP 35 ES-0.0, Rediagnosis

ML20205B151
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-ES-.0, EOP-35-ES-0.0, NUDOCS 8810260194
Download: ML20205B151 (5)

Text

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E. J. Mroc.  ?-1-85 '

Form Approved by Station Superintendent Effe'ctive Date 7y STATION PROCEDURE COVER SHEET t i ~

V A. IDENTIFICATION Number E0P 35 ES-0.0 Rev. 1 i Title REDIAGNOSIS Prepared By H. K. COVIN B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURL DATE DEPARTMENT H2A0 C. UNREVIEWED SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED:

(Significant change in procedure method or scope YES [ ] NO [ ]

as described in FSAR)

- (If yes, document in PORC/50RC meeting minutes)

ENVIRONMENTAL IMPACT (Adverse environmental impact) YES [ ] NO [ ]

(If yev, document in PORC/50RC meeting minutes)

D. INTEGRATED SAFETY REVIEW REQUIRED (Af fects response of Safety Systems, performance YES [ ] NO [ ]

of safety-related control system.s or performance of control systems which may indirectly affect safety system response.)

(If yes, document in PORC/50RC meeting minutes.)

~

E. PROCEDURE REQUIRES /SORC REVIEW YES N N0 [ ]

F. h SORC APPROVAL h/50RCMeetingNumber Y M~d2l G. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:

,.rL M l' I~ s'.

p Station /5eryfce/ Unit Superintendent Effective Date

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SF 301 Rev. 7 9'

0010260194 DR 001007 p ADOCM 0500o213 PDR

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REDIAGNOSIS E0P 35 ES-0.0 Page 2  ;

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,%.J A. PURPOSE This procedure provides a mechanism to allow the operator to  !

determine or confirm the most appropriate post accident recovery procedure.

B. ENTRY CORDITIONS This procedure is entered based on' operator judgement with an SI condition existing,.

This procedure was written for Modes 1, 2, 3 and 4 when R11R is not in service. 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 condition.

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• REDIAGNOSIS E0P 35 ES-0.0 Page 3 Rev. 1

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE

1. Foldout page should be open.

2. This procedure should only be used if S1 is in service or is required.

___1 Check If Any SG Is Not Faulted

a. Check pressures in all a. IF a controlled cooldown is SGs - ANY STABLE OR in progress, THEN go to INCREASING Step 2. IF NOT, TifEN the following applies

1) IF main steamlines NOT isolated, THEN you ahould be in E0P 35 E-2, FAULTED STEAM GENERATOR ISOLATION.

- OR -

2) IF main steamlines isolated. THEN you should be in E0P 35 ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL l

[\~-)\ STEAM GENERATORS.

___2 Check If All SGs ate Not Faulted

a. Check pressure in all a. Verify all faulted SG(s)

SGs - isolated

1) NO SG PRESSLE DECREASING IN AN 1) Steamlines UNCONTROLLED MANNER 2) Feedlines

2) NO SG COMPLETELY IF NOT, T11Eli you should DEPRESSURIZED be in E0P 35 E-2, FAULTED STEAM GENERATOR ISOLATION.

~~~3 Check if SG Tubes Are You should be in an E0P 35 E-1 '

Ruptured LOSS OF REACTOR OR SECONDARY COOLANT or E0P 35 ECA-1 LOSS OF EMERGENCY COOLANT CIRCULATION series procedure.

a. ANY SG LEVEL INCREASING IN AN UNCONTROLLED MANNER

- OR -

b. ANY SG WITli llIGil RADIATION CPM 441 3 44

• REDIAGNOSIS E0P 35 ES-0.0 Page 4 Rev. 1 7ms I \

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT CflTAINED

_4 You Should Be In An E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE Or E0P 35 ECA-3, SGTR CONTINGENCIES series procedure

-FINAL-f)J Ct l CPE641 3 44