ML15224A581

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Notice of Violation from Insp on 890717-0819.Violation Noted:Corrective Actions to Preclude Repetition of Significant Conditions Adverse to Quality Not Adequate
ML15224A581
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 09/08/1989
From: Herdt A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML15224A580 List:
References
50-269-89-25, 50-270-89-25, 50-287-89-25, NUDOCS 8909150063
Download: ML15224A581 (2)


Text

ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-269, -270, -287 Oconee Units 1, 2 and 3 License Nos. DPR-38, -47, -287 During the Nuclear Regulatory Commission (NRC) inspection conducted July 17, 1989 - August 19, 1989, a violation of NRC requirements was identified.

The violation involved two examples of inadequate corrective actions to prevent recurrence of events. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions."

10 CFR Part 2, Appendix C (1989), the violation is listed below:

10 CFR 50 Appendix B, Criterion XVI and Section 17.2.16 of the Accepted Quality Assurance Program require that measures be established to assure that significant conditions adverse to quality are promptly identified, corrected and action be taken to preclude repetition.

Contrary to the above, the corrective actions to preclude repetition of significant conditions adverse to quality were not adequate, in that:

a.

Instrument Procedure (IP)

O/A/0301/003U:

Procedure to Reset the Flux/Imbalance/Flow and High Flux Trips for Operation With Excessive Power Tilt or Other Conditions, was not revised sufficiently to address performance with dummy bistables installed after a previous reactor trip under similar conditions.

This contributed to a subsequent reactor trip.

b.

Improvements to Maintenance Work Request directives and specific work groups methods of implementing those directives taken as a result of inadequate testing of a containment isolation valve (as identified in LER 269/88-01) were not adequate to prevent a second incident of an Engineered Safeguards Containment Isolation valve being returned to service with inadequate testing.

This is a Severity Level IV Violation (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement of explanation in reply including:

(1) admission or denial of the violation, (2) the reason for the violation if Sj:Vk 5

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Duke Power Company 2

Docket Nos. 50-269, -270, -287 Oconee Units 1, 2 and 3 License Nos. DPR-38, -47, -287 admitted, (3) corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance wi.11 be achieved. Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION Al R. Herdt, Chief Reactor Projects Branch 3 Division of Reactor Projects Dated at Atlanta, Georgia this 8th day of Sept.1989