IR 05000333/1981011
| ML20004F424 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/26/1981 |
| From: | Kister H, Linville J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20004F421 | List: |
| References | |
| 50-333-81-11, NUDOCS 8106180326 | |
| Download: ML20004F424 (3) | |
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llh U.S. NUJLEAR REGULATORY CCMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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Region I
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Report No. 50-333/81-11
Docket No. _50-333 Category C
Licensa No. OPR-59 Priority
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Licensee: Power Authority nf the State of New York P.O. Box 41 Lycoming, New York 13093 Facility Name: James A. FitzPatrick Nuclear Power Station r
Meeting at: USNRC, Region I, King of Prussia, Pennsylvania i
Meeting conducted: April 29,1981
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NRC Personne
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Q Jf C. LinviMe, Acting Senior d(te st(ned
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Resident Inspector j
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Approved by:
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H. B. Ki ster, Chief, Reactor dayh sigfe Projects Section 1C Meeting Summary:
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Enforcement Conference on Acril 29, 1981 (Report No. 50-333/81-11)
I Summary:
Special enforcement conference convened by NRC Region I management to discuss NRC concerns regarding a recent inspection finding (50-333/81-07) which identified that G safety relief valve
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(SRV) was replaced with an SRV having a different setpoint following its failur? to lift in response to a manual signal without performing
a nuclear safety evaluation as required by 10 CFR 50.59.
Senior licensee i
and NRC Region I management attended the meeting in the NRC Region I
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office. The meeting was one hour in duration.
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8106180326
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DETAILS i
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Attendees-Power Authe-ity of the State of New York
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J. W. Boston, Executive Vice Presidant and Director of Power Operations i
J. P. Bayne, Senior Vice President - Nuclear Generation
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A. Kiausmann, Director, Quality Assurance
B. W. Diest, Manager of Nuclear Operations R. Ram, Project Nuclear Operations Engineer
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R. J. Pasternak, Resident Manager
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R. Baker, Superintendent of Power M. C. Cosgrove, Site Quality Assurance Engineer
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V. Childs, Assistant to the Resident Manager
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U.S. Nuclear Regulatory Commission B. H. Grier, Director. Region I J. A. Allan, Deputy Director, Region I f
E. J. Brunner, Acting Director, Division of Resident and l
Project Inspection t
R. T. Carlson, Director, Enforcement and Investigation Staff i
H. B. Kister, Chief, Reactor Projects Sectico IC J. C. Linville, Acting Senior Resident Inspector, J. A. FitzPatrick Station
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Discussions l
NRC Region I Management opened the meeting by sr',marizing their
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concerns regarding the failure to perform a saf.cy evaluation and request a change in Technical Specifications as required by 10 CFR
50.59; and the failure of the Plant Operations Review Committee and the Quality Assurance personnel to assure that the change in G SRV
setpoint received adequate evaluation.
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The licensee attributed this incident to errors in judgmer.t on the
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part of plant management personnel caused by management practices
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which led to insufficient independence between the decision making i
and technical review processes.
In order to ensure that this type
of incident does not recur, the licensee stated that he is changing
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procedures for the control of maintenance and modifications, reviewing the Safety Evaluations associated with all Technical Specification Amendments to assure all commitments have been identified and
adhered to, establishing an independent onsite review committee,
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conducting a Quality Assurance audit to identify similar situations, and directing plant management to participate less actively in the problem solution efforts of department superintendents thereby enabling them to review these proposals more independently.
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Results The licensee stated that he would complete the following actions:
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Change the procedures for the control of Maintenance and
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Modifications by providing a form to give department superintendents
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guidance in determir.ing whether changes are modifications and to document this decision.
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Establish an independent onsite review committee staffed by
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four engineers.
Complete a six man-week review by the' Quality Assurance department
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to identify similar situations.
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Complete a review of the Safety Evaluations for all Technical
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Specification Amendments to ensure that all commitments have been identified, adhered to, and incorporated in the Technical i
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Specifications as required.
Region I Management acknowledged and coninented on the licensee's corrective actions.
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