ML20028G044
| ML20028G044 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/24/1983 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028G042 | List: |
| References | |
| 50-029-82-15, 50-29-82-15, NUDOCS 8302070346 | |
| Download: ML20028G044 (2) | |
Text
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APPENDIX A NOTICE OF VIOLATION Yankee Atomic Electric Company Docket No.
50-29 Yankee Nuclear Power Station Licensa No. DPR-3 As a result of the inspection conducted on November 16 - December 31, 1982, and in accordance with the NRC Enforcement Policy (10 CFR 2, Appendix C) published in the Federal Register on March 9, 1982 (47 FR 9987), the following violations were identified:
A.
10 CFR 50.59 states that the licensee may make changes in the facility as described in the safety analysis report without prior Commission approval unless the change involves an unreviewed safety question, and that records shall be maintained of changes to the system as described in the safety analysis report.
These records shall include written safety evaluations which provide the bases for determining that the changes do not involve unreviewed safety questions.
1.
Licensee approved procedure AP-0200, Design Changes and Alterations, Rev. 6, requires that changes to Safety Classified systems that require quality assurance, which are initiated by the plant, be processed as a Plent Design Change Request to include a safety evaluation if the changes render the systems unlike their description in the Final Hazards Summary Report (FHSR), including drawings.
Contrary to the above, the incore instrumentation flux thimble paths, a Safety Class 2 system as defined by Appendix D, Table D.1 of the approved Operational Quality Assurance Manual, at positions K-6 and A-5 were determined to be leaking and on December 15, 1982 the thimbles were isolated by valving out-of-service and plugged down-stream of the isolation valve.
Disconnection of the thimble tubing and installation of a plugged fitting constitutes a change mad: to a system component, as described in the Final Hazards Summary Report, Chapter 107, without the required evaluation or use of an approved Plant Design Change Request.
2.
Licensee approved procedure AP-0200, Design Changes and Alterations, Rev. 6, requires that changes to Non-Nuclear Safety systems not requiring quality assurance, which are initiated by the plent, be processed as a Plant Alteration to include a safety evaluation if the changes render the systems unlike their description in the Final Hazards Summary keport (FHSR). including drawings.
0FFICIAL RECORD COPY 8302070346 830124
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Aprasfix A 2
Contrary to the above, the Tank and Evaporator multi point indicator, WD-TI-300, a Non-Nuclear Safety system as defined by Appendix D,Section II of the approved Operational Quality Assurance Manual, was determined to be not operating on November 24, 1981, and was placed out-of-service and temporary indicators were installed.
This change was made to a system component, as described in the Final Hazards Summary Report, Chapter 209, without the required evaluation or use of an approved Plant Alteration.
The above findings constitute a Severity Level IV violation (Supplement I.D.)
8.
10 CFR 50.72, section (8), and Yankee Nuclear Power Station OP-MEMO No.
2A-1, require that the licensee shall notify the NRC Operations Center as soon as possible and in all cases within one hour, by telephone, of any accidental, unplanned, or uncontrolled radioactive release.
Contrary to the above, at 1:30 a.m. on November 16, 1982, the licensee determined that an accidental gaseous radioactive release from the Waste Gas Surge Drum had occurred and the NRC Operations Center was not notified until 7:40 a.m. that same day.
This is a Severity Level V violation (Supplement I.E.)
Pursuant to the provisions of 10 CFR 2.201, Yankee Atomic Electric Company is hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including:
(1) the corrective steps'which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.
OFFICIAL RECORD COPY
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