B11409, Responds to IE Bulletin 80-06, ESF Reset Control. Trip Signal to Containment Air Activity Pump & Containment Sump Pump Provided.Removal of Safety Injection Actuation Signals from RHR Valves Being Evaluated

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Responds to IE Bulletin 80-06, ESF Reset Control. Trip Signal to Containment Air Activity Pump & Containment Sump Pump Provided.Removal of Safety Injection Actuation Signals from RHR Valves Being Evaluated
ML20197B804
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 04/28/1986
From: Opeka J
CONNECTICUT YANKEE ATOMIC POWER CO.
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
B11409, IEB-80-06, IEB-80-6, NUDOCS 8605130134
Download: ML20197B804 (2)


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  • CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N. CONNECTICUT P o Box 270 HARTFORD CONNECTCUT 06141-0270 TELEPHONE 203-665-5000 April 28, 1986 Docket No. 50-213 B11409 Dr. Thomas E. Murley Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

References:

(1) W. G. Counsil letter to T. E. Murley dated January 24, 1985 Gentlemen :

Haddam Neck Plant I&E Bulletin 80-06: Engineered Safety Features Reset Control The purpose of this letter is to provide updated information and close out commitments made in Reference (1). These commitments included two plant modifications: (1) modify the circuitry associated with the Containment Air Recirculation (CAR) Fan Danpers to preclude their automatic return to normal operating position upon reset of the ESF ectuation signal; and (2) provide a trip signal, meeting I&E Bulletin 80-06 criteria, for both the containment air activity pump and the containment sump pump. Both of these modifications were recently completed.

CYAPCO also commited to evaluate the need to remove Safety Injection (SI) actuation signals f rom Residual Heat Removal (R1id) heat exchanger flow control valves RH-FCV-602 and RF-FCV-786. These valcas are manually blocked and locked in their required accident

  • panition and the air supply to the valves is removed negating any moverdent upon receipt of a SI signal. The SI signal will be removed before the end of the 1987 refueling outage. Since the system as presently configured poses no safety concern, this is not an urgent change.

8605130134 860425 PDR ADOCK 05000213 .

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- . .} **A n We trust that the above information satisf actorily resolves all remaining aspects of the subject Bull ~etin.

Very truly yours,

.f i- CONNECTICUT YANKEE ATOMIC POWER COMPANY J. F 4peka O f\&4_

Senior Vice President I

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