ML20098H026

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Responds to Violations Noted in Insp Rept 50-244/84-16. Corrective Actions:Shift Supervisors Advised to Give Close Scrutiny to Independent Verification of Reconnection Procedure
ML20098H026
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/28/1984
From: Kober R
ROCHESTER GAS & ELECTRIC CORP.
To: Starostecki R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8410090269
Download: ML20098H026 (2)


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$ "*" A ROCHESTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE,- ROCHESTER, N.Y.146kb001 kh ROGER W. MOBER vtCE PRE 5fDENT Tf LIP"ONE ELEctnic a STEAM FHODUCTON -

amE A CODE 716 546 2700 September 28, 1984 Mr. Richard-W. Starostecki, Director

. Division of Projects and Resident Programs U. S. Nuclear Regulatory Commission Region I 631 Park Avenue

. King of Prussia, Pennsylvania 19406

Subject:

I& E Inspection Report 84-16 Notice of Violations Control Of Limitino Conditions for Operating Equipment R..E.

Ginna Nuclear Power Plant, Unit No. 1 Docket No. Eb-244

Dear Mr.' Starostecki:

In accordance with the above subject which stated

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"As a result of the inspection conducted on June 9,1984, and in accordance with the NRC Enforcement Policy, (10 CFR 2, Appendix C) published in the Federal Register on March 8, 1984 (49 FR 8583) the following violation was identified:

Technical Specification 6.8, "Proccdures" requires written procedures be established, implemented, and maintained covering activities referenced in Appendix "A" of Regulatory Guide'l.33, November 1972.-

$r Ginna Station Administrative Procedure ( A)-52.4, " Control of Limiting Conditions for Operating Equipment", Revision to No. 45, June 19, 1984, written pursuant to Technical

'*o Specification 6.8, requires Attachment I to A-52.4 to

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be ' utilized to document safeguards equipment which is no removed from and restored to service, and to ensure the SO Operations Department is aware of the Limiting Conditions

'84 for Operation imposed by Technical Specifications to gg meet minimum system operability requirements.

ma.e Contrary to the above, on July 25, 1984, Attachment I to A-52.4 was not. utilized to identify the incperability of Automatic Deluge System S-29."

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s i.the following is submitted in response.

. Corrective action-to-address this violation is as follows:

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The event was discussed at the Shift Supervisor's

.I cMeeting on-August 28, 1984.

.It was recognized that valve isolation for the Fire Suppression System was an "off-normal" activity._-The routine being, to disable.

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the' detection system by disconnection procedure SC-3.16.2.4, and initiate an-A-52.4 Attachment I, " Control of Limiting Conditions for Operating Equipment."'

The Liaison Engineer for,the modification work elected to have-isolation valves closed in the same system and a separate A-52.4 attachment should have been utilized, but was'not.

Clarification was determined necessary for both the A-52.4 Attachment I and SC-3.16.2.4 procedures.

A procedure change has been submitted to A-52.4 Attachment I - that states: "For fire. suppression systems, if more

'than one component is-deemed inoperable in the'same system,-use separate A-52.4 attachments".

An addition to the SC-3.16.2.4 procedure directs the operator 3to list any valves. isolated during the dis-connection of the-fire signaling system.

'A specific step in the reconnection portion of the pr'ocedure.

--directs him to restore the valves listed earlier to normal position, holds removed.

A letter was addressed 'to the Shift Supervisors advising them to give close scrutiny to an independent verification-of the reconnection procedure. Also to personally examine the ' indications on the Gamewell panel that'the detection systems'are operable subsequent,to reconnection and

. prior'to dismissing ~the firewatch personnel.

Truly Yours, Y,

'R r W. Kober--

Subscribed and sworn to me on:this-28th day f Se tomber, 1984.

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