ML20236Q559

Directs Recipient to Perform Insp of Causes,Safety Implications & Associated Operator Actions During Radioactive Coolant Spill & Actions Taken Resulting in Safety Limit Violation on 870911

ML20236Q559
Person / Time
Site:	Oyster Creek
Issue date:	09/15/1987
From:	Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20236Q524	List: IR 05000219/1987029 ML20236Q522 ML20236Q531 ML20236Q535 ML20236Q559 ML20236Q567
References
NUDOCS 8711200127
Download: ML20236Q559 (3)

Text

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APPENDIX B

SEP 151987 MEMORANDUM FOR

William F. Kane, Director-Division of Reactor Projects FROM: William T. Russell Regional Administrator

SUBJECT:

AUGMENTED INSPECTION TEAM - SAFETY LIMIT VIOLATION AT OYSTER CREEK You are directed to perform a prompt inspection of the causes, safety implica-tions, and associated operator actions during a radioactive coolant spill and subsequent actions which resulted in a Safety Limit Violation at Oyster Creet on September 11, 1987. 'The inspection shall be in accordance with NRC Manual Chapter 0513, Part III, and additional instructions in this memorandum.

I DRP is assigned to conduct this inspection and Dr. L. H. Bettenhausen is designated as the Team Leader. The team wiil also include the provisien fer participation by the Office of Investigation and NRR.

1 OBJECTIVE The general objectives of the AIT are to:

a. Conduct a timely, thorough, and systematic inspection related to the circumstances surrounding the Safety Limit Violation. 1

b. Assess the safety significance of the events and communicate to Regic al '

and Heac:;uarters ranagement the facts and safety concerns relate: to t"e problems identifiec.

c. Collect, analyze, and document all relevant data and factual infermatior to determine the causes, conditions and circumstances pertaining to the  ;

events,

d. Evaluate the adequacy of the licensee's internal review of the event.

SCOPE OF THE INSPECTION The AIT response should identify and document the relevant facts and determine the probable causes and should be limited to the issues directly related to the Safety Limit Violation event and operator responses.

8711200127 871106 PDR ADOCK 00000219 P PDR

I

, Memorandum for William F. Kane 2 SEP 151987 Specifically, the AIT should:

a. Develop a chronology of the event.

b. Determine the scope and quality of licensee's internal review of the event.

c. Develop a history of the Safety Limit and why it exists.

d. Review the maintenance activities leading to the event.

e. Determine operator response.

SCHEDULE The AIT shall be dispatched toithe Oyster Creek Nuclear Generating Station not later than September 12, 1987, and shall remain there as long as necessary tc accomplish the objectives of this inspection'. It is expected that this will take no longer than five working days.

A written report of this inspection will be provided to me by SeptemOer 3C, 1987.

It may be necessary to report on operator integrity issues at a later date as they are explored anc identified.

TEAM COMPOSITION Tre assignec tear memoers are as follows:

L. Bettenhausen, DRP, RI C. Cowgill, DRP, RI W. Bateman, SRI - Oyster Creek J. Wechselberger, RI - Oyster Creek D. Alsopp, RI - Hope Creek A. Dromerick, NRR h3 -

William T. Russell Regional Administrator

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KINO 0F PnUB51A, PENNsVLVANlA 19408 11 SEP 1987  ;

i Docket No. 50-219 Confirmatory Action Letter No. 87-12 EA No.87-185 GPU Nuclear Corporation ATTN: Mr. P. R. Clark '

President 100 Interpace Parkway Parsippany, New Jersey 07054 Gentlemen:

Subject:

Confirmatory Actioh Letter 87 Violation of Technical Specification Safety Limit and Subsequent Operator Actions 1

Pursuant to the telephone conversation on September 11, 1987 between Mr. Samuel Collins of rny staf f and Mr. Ed Kintner of your staf f, it is our understanding that you will:

1. Maintain the plant in a shut down condition per the requirements of IC CFR 50.36 which requires Commission approval for restart.

2.

Estab'.15h and raintain as foLrd cercitions for relevant Fa-dwarr. a r.:

prccess systers which pertain to analysis of the event. These conditiers will be maintained until released by the NRC.

1

3. Condset an independent review of the circumstances surrounding the events and forward a report to the Commission per the requirernents of Technical Specification Section 6.7.

It is our understanding that upon completion of formulation of your methodo'cg>

to assess the violation of Technical Specification Safety Limit events and subsequent operator actions, these plans will be discussed with the NRC prior to implementation.

If your understanding of the actions to be taken differs from the above description, please contact this office within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of receipt of this letter and before restarting the plant from its current outage.

Sincerely.

W,

'1111am T. Russell Regional Administrator f lt)0 l

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t GPU Nuclear Corporation 2 11 SEP 1987 0

CC:

P.B. Fiedler, Vice President and Director M. Laggart, BWR Licensing Manager Licensing Manager, Oyster Creek Public Document Room (PDR) local Public Document Room (LPOR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector State of New Jersey

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