ML16161A974
| ML16161A974 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/03/1988 |
| From: | Brownlee V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16161A973 | List: |
| References | |
| 50-269-88-08, 50-269-88-8, 50-270-88-08, 50-270-88-8, NUDOCS 8805100033 | |
| Download: ML16161A974 (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, 55 During the Nuclear Regulatory Commission (NRC) inspection conducted March 17 April 18, 1988, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR, Part 2, Appendix C (1987), the violation is listed below:
Oconee Nuclear Station Technical Specification 6.4.1 states that the station shall be operated and maintained in accordance with approved procedures and that these procedures shall contain appropriate check-off lists and instructions. Station Directive 2.2.2, Independent Verification identifies the methods used to perform component verification to assure applicable components being removed from service are the correct compo nent.
Contrary to the above, the method used to perform component verification to assure the correct component is identified prior to performing maintenance was inadequate as indicated in the following examples:
- 1.
On February 11, 1988, a spill of 400-600 gallons of radioactive water occurred because SD 2.2.2 did not adequately detail how an unlabeled component was to be verified as the correct component prior to performing maintenance.
A Unit 1 valve under normal pressure was worked upon in lieu of a Unit 2 valve.
- 2.
On February 25, 1988, 2 MS-83, a 6 inch Main Steam valve, was removed from service instead of 2 MS-85 due to inadequate method of verifica tion that the work being performed was being done on the correct component.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D. C. 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Oconee, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include:
(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the 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 8805100033 880503 PDR ADOCK 05000269 DCD
Duke Power Company 2
Docket Nos. 50-269, 270, 287 Oconee Units 1, 2 and 3 License Nos. DPR-38, 47, 55 will be achieved. Where good cause is shown, consideration will be given to extending the response time. If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects Dated at Atlanta, Georgia this ".'
day of 4-1988