ML20205B735

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Forwards Insp Rept 50-309/85-27 on 850903-04.Apparent Violation Re Inoperability of Steam Generator Pressure Channels Will Be Discussed at Enforcement Conference Scheduled for 850909
ML20205B735
Person / Time
Site: Maine Yankee
Issue date: 09/04/1985
From: Starostecki R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Randazza J
Maine Yankee
Shared Package
ML20205B742 List:
References
NUDOCS 8509120211
Download: ML20205B735 (2)


See also: IR 05000309/1985027

Text

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SEP 0 41985

Docket / License: 50-309/DPR-36

Maine Yankee Atomic Power Company

ATTN: Mr. J. B. Randazza

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Vice President

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Nuclear Operations

83 Edison Drive

Augusta, Maine 04336

Gentlemen:

Subject:

Inspection 50-309/85-27

This transmits the September 3-4, 1985 special inspection findings of Messrs.

C. Holden and J. Robertson at the Maine Yankee Atomic Power Plant, Wiscasset, Maine.

The inspection was conducted to determine the circumstances surrounding the dis-

covery of.the inoperability of Steam Generator Pressure Channels for the Reactor

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Protective System.

Those findings were based on observations of activities, in-

terviews and document reviews, and have been discussed with Mr. Boulette of your

,

staff.

'

An apparent violation of NRC requirements is cited in the enclosed inspection re-

port. We are considering this violation for appropriate enforcement action which

will be addressed under separate correspondence at a later date.

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We consider this event to be serious and request that you include the discussion

of this event in the Enforcement Conference scheduled for September 9,1985, on

the mispositioned root valves for associated Steam Generator Pressure Transmitters.

2

Even though the cause of this event is different from the mispositioned root valve

event, it indicates that two different control mechani.sms failed to assure that

the steam generator pressure instruments were operable during Cycle 8.

At the

conference, in addition to those items identified in my letter of August 28, 1985,

you should also be prepared to discuss:

,

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The cause of this event.

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Disposition of EDCR 83-32 modifications.

The adequacy of your post maintenance testing requirement and return to ser-

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vice criteria.

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Actions you have taken to assure all necessary plant safety related equipment

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will be operaticaal for startup at the end of this current outage.

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Your cooperation with us is appreciated.

Sincerely,

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8509120211 850904

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ADOCK 05000 309

Richard W. Starostecki, Director

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PDR

Division of Reactor Projects

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SEP 0 41985

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Enclosure:

Region I Report 50-209/85-27

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C. E. Monty, President

C. D. Frizzle, Assistant Vice President / Manager of Operations

J. H. Garrity, Plant Manager

P. L. Anderson, Project Manager

G. D. Whittier, Licensing Section Head

J. A. Ritsher, Attorney (Ropes and Gray)

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Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector

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