ML20024H920
| ML20024H920 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/16/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20024H919 | List: |
| References | |
| 50-443-93-80, NUDOCS 9308270235 | |
| Download: ML20024H920 (2) | |
Text
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4 APPENDIX A NOTICE OF VIOLATION North Atlantic Energy Service Corporation Docket No. 50-443 i
Seabrook Station, Unit 1 License No. NPF-86 l
As a result of the inspection conducted on April 26 through May 21,1993, and in accordance with the " General Statement of Policy and Procedure for NRC Enforcement i
Actions," 10 CFR Part 2 Appendix C (Enforcement Policy) (1993), the following violations were identified:
A.
Part 50 of Title 10 of the Code of Federal Regulations, Section 50.55 (b)(1) requires that the licensee shall maintain records of changes in the facility and of changes in procedures made pursuant to this section, to the extent that these changs constitute changes in the facility as described in the safety analysis report or to the extent that they constitute changes in procedures as described in the safety analysis report. These records must include a written safety evaluation which provides the bases for the determination that the charge, test, or experiment does not involve an unreviewed i
I safety question.
Section 8.3.2.1.f(2) of the Seabrook Updated Final Safety Analysis Report states that, i
".. a loss-of-current relay (Device No. 37/62) is provided which senses loss-of-charger output current. This relay provides an alarm locally at the charger and a computer alarm."
l Contrary to the above, no written safety evaluation was performed for a change to the plant as described in the FSAR in that, in March 1991, the loss-of-charger output current computer alarm described above was deleted with no written safety evaluation.
B.
Part 50 of Title 10 of the Code of Fcderal Regulations, Appendix B, Criterion III, Design Control, requires that design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program.
Contrary to the above, prior to initial licensing on March 15, 1990, the plant design review failed to provide a verification that the design of the emergency diesel generator system was adequate in that the control air system was not seismically qualified, and therefore, the unexpected failure of the diesel engine could occur when the diesel engine cooling control valves go to the as-designed, full open, position upon the loss of the control air supply. This could result in excess cooling of the diesel engine and subsequent engine failure This is a Severity Izvel IV Violation (Supplement II).
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Appendix A 2
Pursuant to the provisions of 10 CFR 2.201, the North Aaantic Energy Service Corporation is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATFN: Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator, Region I, and a copy to the NRC Resident Inspector within 30 days of the date of the letter transmitting this Notice of Violation. This reply should include: (1) the reason for the violation, if admitted, or if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violation, and (4) the date when full compliance will be achieved. If an adequate reply is not received within the time specitled in this Notice, an order or a Demand for Information may be issued to show cause why the license should not be modified, suspended, revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given l
to extending the response time.
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