05000219/LER-1982-058, Forwards LER 82-058/03L-0.Detailed Event Analysis Encl

Forwards LER 82-058/03L-0.Detailed Event Analysis Encl

ML20028C795
Person / Time
Site:	Oyster Creek
Issue date:	12/29/1982
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20028C796	List: 05000219/LER-1982-058, Forwards LER 82-058/03L-0.Detailed Event Analysis Encl 05000219/LER-1982-058-03, /03L-0:on 821128,main Steam Line Drain Valves V-1-106 & V-1-110 Failed to Close Fully.Cause Unknown. Investigation Will Continue During Next Outage
References
NUDOCS 8301140135
Download: ML20028C795 (3)

LER-1982-058, Forwards LER 82-058/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191982058R00 - NRC Website

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GPU Nuclear Ng g7 P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number:

December 29, 1982 Mr. Ronald C. Haynes, Administrator Region I U.S. Nuclear Regulatory Commission 531 Park Avenue King of Prussia, PA 19406

Dear Mr. Haynes:

Subj ect: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/82-58/03L This letter forwards three copies of a Licensee Event Report (LER) to report Reportable Occurrence No. 50-219/82-58/03L in compliance with paragraph 6.9.2.b.2 of the Technical Specifications.

Very truly yours, A

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Peter B. Fiedler Vice President and Director Oyster Creek PBF:Ise Enclosure s cc: Director (40 copies)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Director (3)

Of fice of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C.

20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 8301140135 821229 PDR ADOCK 05000219 S

PDR GPU Nuclear is a part of the General Public Utilities System p@

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10YSTER CREEK NUCLEAR GENERATING STATION-Forked ~ River, New Jersey 08731;

~ Licensee Event Report

-. Reportable-Occurrence No. 50-219/82-58/03L '

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Report Date t

' December - 29, 1982.

Occurrence Date-November 28,- 1982-

. Identification of Occurrence L During surveillance testing, main steam drain valves V-1-106 and V--l-110. failed to fully close when given the closed. signal with its control' switch. - The valves were both secured and deactivated in the isolation position, which is a

- limiting condition for operation permitted by the Technical. Specifications,~

paragraph 3.5.A.3.a.1.b.

This event is considered to be a reportable occurrence as defined in the" Technical Specifications, paragraph 6.9.2.b.2.

Conditions Prior to Occurrence The event occurred during routine startup operations.

3 Major Parameters Reactor Power - 753 MWt i

Generator Load - 218 MWe Reactor Coolant Temperature - 5250F 1

Description of Occurrence During performance of the "MSIV Closure and IST Test", main steam drain valves V-1-106 and V-1-110 failed the acceptance criteria in the closing direction.

Both valves would not fully close when given the appropriate signals. The two i

remaining main steam drain valves, V-1-107 and V-1-111, were both operable.

Valves V-1-106 and V-1-110 were closed by bypassing the control circuitry, deactivated, and secured in their isolation position as required by the Technical Specifications.

I Apparent cause of Occurrence The apparent cause of the occurrence is unknown at this time. The valves were stroked several times and current checks were performed in an attempt to discover the problem. Both valve operators did not exhibit their full' load amperage values upon closing, and the charts taken during these readings were evaluated with no abnormalities noted. These checks were made with the reactor 0

depressurized and reactor coolant temperature 1er,s than 212 F.

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Licensee Event Report Page.2

- Reportable' Occurrence No. 50-219/82-58/03L'-

Analysis'of Occurrence

~.The Main Steam drain valves are primary, containment isolation valves, and, as such, are required to close when reactor isolatio t signals-are present.

In-this case, valves V-1-106 and. V-1-110 would not have fuliy closed. - It was demonstrated, however,. that the valver were capable of being closed.by bypassing the control. circuitry. Additionally, these valves are maintained in the closed position during power operation... Based on this, the safety significance of the event is considered minimal.

' Corrective Action Valves V-1-106 and V-1-110 were closed and tagged out of service, as required by the Technical Specifications. At ' the present. time, all-- four. (4) main steam drain valves are tagged in the closed (normal) position. An-investigation as

'I to the cause of this event will be continued during the upcoming refueling

- outage.

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