IR 05000029/1987016

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Enforcement Conference Rept 50-219/87-16 on 870610.Licensee Presented Background & Supplemental Info Re Violations Identified in Insp Rept 50-029/87-16
ML20234E710
Person / Time
Site: Oyster Creek, Yankee Rowe
Issue date: 06/30/1987
From: Baunack W, Blough A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20234E663 List:
References
50-219-87-16-EC, NUDOCS 8707070655
Download: ML20234E710 (3)


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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No.

87-16 Docket No.

50-219 License No.

DPR-16 _

Priority

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Category C

Licensee:

GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Facility Name:

Oyster Creek Nuclear Generating Station Meeting At:

Region I Office, King of Prussia, Pennsylvania Meeting Conducted: June 10, ISQ/

Prepareci By:

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O WT Baunack, Project Engineer Date

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Approved By:

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A. Bloug W Chief, Reactor Projects Date Section 1A, DRP Inspection Summary:

An Enforcement Conference was held at the NRC Region I Office on June 10, 1987, to discuss the findings of NRC Region I Inspection No. 50-219/87-16.

This meeting was attended by NRC and licensee management.

The licensee presented background and supplemental information relating to the apparent violations identified in special Inspection Report No. 50-219/87-16.

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8707070655 070630 PDR ADOCK 05000219 G

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DETAILS 1.

Meeting Attendees GPU Nuclear Corporation G. W. Busch, Dyster Creek Licensing Engineer P. B. Fiedler, Vice President and Director, Dyster Creek l

J. P. Kowalski, Dyster Creek Licensing Manager M. W. Laggart, Manager, Dyster Creek Licensing

R. L. Long, Vice President and Director, Planning and Nuclear Safety i

P. S. Smith, Engineer, Safety Analysis l

NRC i

J. M. Allan, Deputy Regional Administrator W. H. Bateman, Senior Resident Inspector W. H. Baunack, Project Engineer L. H. Bettenhausen, Acting Deputy Director, Division of Reactor

~1 Safety (DRS)

A. R. Blough, Chief, Reactor Projects Section 1A, Division of Reactor Projects (DRP)

S. J. Collins, Deputy Director, DRP D. J. Florek, Acting Chief, Test Programs Section, DRS J. M. Gutierrez, Regional Counsel D. J. Holody, Enforcement Officer W. F. Kane, Director, DRP J. F. Wechselberger, Resident Inspector L. J. Wink, Reactor Engineer, DRS l

2.

Discussion Following introduction of personnel at the conference, the NRC presented a brief discussion of the event, identified the apparent violations, and stated the purpose of the meeting. The licensees views of the description of the event and apparent violations identified in Inspection Report No.

50-219/87-16 were also requested.

i 3.

Licensee Presentation

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The licensee basically accepted the violations as preseated. Also, the licensee described certain mitigating factors and described the corrective actions which have been taken and the longer term actions which are con-templated.

The primary mitigating f actors presented by the licensee were that they recognized the error during the same shift on which it occurred, that they reported the event to t'ne resident inspectors, that they co-operated with the inspection team to determine root causes and corrective actions, and that problems with temporary variations had been previously noted during an audit and procedural changes had been initiated, f

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A number of corrective actions which had been taken or planned by the licensee had been previously identified in a letter to Mr. W. Russell, NRC from P. Fiedler, GPUN dated May 7,1987.

During this meeting, some addi-tional corrective actions were described.

This additional action in-cluded: (1) providing a date (July 31, 1987) by which a Management Over-sight Risk Tree (MORT) review would be completed; (2) a review of proced-ures which has been undertaken to determine a need for additional safety evaluations; (3) plans to formulate additional training for safety re-viewers and for those who need additional understanding of the FSAR; and, (4) a personal reinforcement by management of safety objectives to opera-tions department personnel.

The potential safety consequences associated with the event were also discussed.

4.

Conclusion Region I management summarized the items discussed during the meeting.

These included:

(1) the identified violations including the licensee's position on each; (2) the root causes of the violations; (3) the safety consequences; and, (4) the mitigating circumstances.

Also, Region I management stated that the licensee would be informed of any appropriate i

enforcement action. At this point, the meeting was adjourned.