ML20236Q495
| ML20236Q495 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/13/1987 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20236Q480 | List: |
| References | |
| 50-333-87-21, NUDOCS 8711200091 | |
| Download: ML20236Q495 (2) | |
Text
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APPENDIX A NOTICE OF VIOLATION Power Authority of the State of New York Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant License No. DRP-59 As a result of the inspection conducted September 1, 1987 to October 20, 1987, and in accordance with the General Statement of Policy and Procedure for Enforcement Actions (Enforcement Policy),10 CFR 2, Appendix C, the following violations were identified:
A.
10 CFR 50.59, Changes, Tests and Experiments, states in parts (a)(1),
"The holder of a license.. may make changes in the facility as described in the safety analysis report... without Commission approval, unless the proposed change, test or experiment involves a change in the technical specifications incorporated in the license or i
an unreviewed safety question; and (b)(1) "The licensee shall maintain records of the changes in the facility... These records must include a written safety evaluation which provides the bases for the determination that the change does not involve an unreviewed safety question."
i Contrary to the above, on October 9,1987, the high vibration trip of the A reactor feed pump turbine, described in Final Safety Analysis Report section 10.8.3, was disabled without a written safety evaluation to determine that the change does not involve an unreviewed safety question.
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Also contrary to the above, since 1979, the reactor recirculation speed control system, described in Final Safety Analysis Report
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section 14.5.5.3, has been routinely operated with the speed limiters disabled without a written safety evaluation to determine that the change does not involve an unreviewed safety question.
This is a Severity Level IV Violation.
(Supplement I).
B.
Technical Specification 6.8(A) requires that written procedures and administrative policies be implemented that meet or exceed the requirements and recommendations of section 5 " Facility Administrative Policies and Procedures of ANSI N18.7-1972". ANSI N18.7-1972, section 5 requires procedures and policies for plant standing orders.
Plant Standing Order 51, Erection of Scaffolds Near Safety-related Equipment, Revision 1, dated July 29, 1987, requires scaffold planks to be tied or wood stops provided against slippage and scaffolds exceeding seven feet in height to be rigidly tied-off to existing structural steel in each horizontal direction.
8711200091 871113 PDR ADOCK 05000333 G
PDR OFFICIAL RECORD COPY IR FITZ 87 0003.0.0 11/10/87
Appendix A 2
I Contrary to the above, on September 30, 1987, scaffolding was erected approximately 20 feet above three of the four Emergency Diesel Generators and was not rigidly tied-off and had planks which were not secured against slippage.
This is a Severity Level V Violation.
(Supplement I).
l Pursuant to the provisions of 10 CFR 2.201, the Power Authority of the d
State of New York is hereby required to submit to this office within thirty days of the date of the letter which transmitted 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; (3) the date when full compliance will be achieved.
Where good cause is shown, consideration will I
be given to extending this response time.
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OFFICIAL RECORD COPY IR FITZ 87 0003.1.0 11/10/87