IR 05000244/1989018
| ML17250B023 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/18/1989 |
| From: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Rich Smith ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17250B024 | List: |
| References | |
| EA-89-177, NUDOCS 8910270041 | |
| Download: ML17250B023 (2) | |
Text
Docket No. 50-244 EA No.89-177
Rochester Gas and Electric Corporation ATTN:
Mr. Robert E.
Smith Senior Vice President Production and Engineering 49 East Avenue Rochester, New York 14649 Gentlemen:
Subject:
R.
E. Ginna Nuclear Power Plant Notice.of Violation and Enforcement Conference (Special Inspection No. 50-244/89-18)
This letter transmits a Notice of Violation and Enforcement Conference Meeting Summary for the enforcement conference held with you and members of your staff in the NRC Region I Office on October 3, 1989.
The meeting was held to discuss safety significance, root cause(s),
and corrective actions for the potential
'violations of NRC requirements and safety issues documented in Region I Special Inspection Report No. 50-244/89-18.
After evaluating the information you and your staff presented at the enforce-ment conference and Inspection Report No. 50-244/89-18, we have concluded that the measures you have applied to assure reliability of the identified elec-trical power distribution equipment are acceptable.
Also, we categorized the failure to release the waste gas decay tank within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of sampling and the erroneous intermediate range detector setpoints as having little safety sig-nificance and meeting the requirements of the NRC policy for not issuing Notices of Violation.
Therefore, no violation citations are being forwarded for these matters.
Our review concluded that the safety concerns identified in Enclosure 1 to this letter violated NRC requirements.
You are required to respond to these matters in accordance with Enclosure 1.. In your response you should include those ac-tions taken or planned to assure effectiveness of your quality assurance or-ganization and of the independent verification process.
Although the enclosed violation for modification control problems was categor-ized at Severity Level IV, we noted that NRC Report No. 50-244/89-18 documents multiple instances of lack of careful design control.
We regard careful and thorough design control for modifications as. important to assuring safe opera-tion.
In this regard, you should be particularly aware of the provision of the NRC enforcement policy (10 CFR 2, Appendix C, Section V.B) authorizing the im-position of civil penalties for Severity Level IV violations that are similar to prior violations for which you did not take effective corrective action.
OFFICIAL RECORD COPY
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EA 89-177 - 0001.0. 0 10/18/89
Rochester Gas and Electric Corporation
OCT 18 1988 Thank you for your cooperation.
Sincerely, 08IGIQL SIGNED BY William F.
Kane, Director Division of Reactor Projects cc w/encls:
Harry H. Voigt, Esquire Central Records (4 copies)
Director, Power Division Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New York, Department of Law State of New York, Division of Analysis 5 Planning bcc w/encls:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encls)
~ ORP Section 'Chief DRS Section Chief P. Drysdale, RI, DRS R. Laura, RI, NMP A. Johnson, PM, NRR Robert J.
Bores, DRSS J.
Lieberman, OE J. Partlow, NRR J. Goldberg, OGC DRP:RI Perry 10/K/89 l7 DRP:RI ce'cCabe iclI l J~ son JP OFFICIAL RECORD COPY EA 89-177 - 0002.0.0 10/16/89