ML20206B589
| ML20206B589 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/26/1988 |
| From: | Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20206B587 | List: |
| References | |
| 50-312-88-32, NUDOCS 8811150498 | |
| Download: ML20206B589 (2) | |
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APPENDIX A NOTICE OF VIOLATION Sacramento Municipal Utility District Docket No. 50-312 P. O. Box 15830 License No. DPR-54 T
Sacramento, California 95813 1
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During an NRC inspection conducted on September 19, 1938 through October 7 1988 a violation of NRC requirements was identified.
In accordance with the i
4 "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below:
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10 CFR 50.59 provides that:
(1) Changes in the facility as described in the safety analysis i
report may be made without prior Comission approval, unless the proposed change, test or experiment involves a chaage in i
the technical specifications incorporated in the license or an
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unreviewed safety question, j
f (2) 10 CFR 50.59 further requires that:
i The licensee shall maintain records or changes in the facility
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and of changes in procedures made pursuant to this section, to l
the extent that these changes constitute changes in the l
facility as described in the safety analysis report or to the l
extent that they constitute changes in procedures as described i
in the safety analysis report. These records must include a
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written safety evaluation which provides the bases for the f
determination that the change, test, or experiment does not i
involve an unreviewed safety question.
Rancho Seco Updated Safety Analysis Report (USAR' Section 9.5.2.1 I
states that "The decay heat removal system is shown schematically in
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Figure 9.5-1."
Figure 9.5-1 shows relief valves PSV-26101 and PSV 26110 providing pressure relief protection for portions of the DHR
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system.
Contrary to the above, on March 28, 1988, relief valves PSV-26101 r
and PSV 26110 were made inoperable. A written safety evaluation was not completed to provide the bases for a determination that the j
change did not involve an unreviewed safety question.
This is a Severity Level IV violation (Supplement I).
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Pursuant to the provisions of 10 CFP. 2.201, the Sacramento Municipal Utility District is hereby required to submit a written statement or explanation to I
the U.S. Nuclear Regulatory Comission, ATTN: Document Control Desk, Washington, DC 20555 with a copy to the NRC Resident Inspector, Anthony D'Angelo, within 30 days of the date of the letter transmitting this Notice.
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I This reply should be clearly marked as a "Reply to a Notice of Violation" and
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should include for each violation:
(1) the reason for the violation if i
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i admitted, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
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, i
suspended, or revoked or why such other action as may be proper should not be taken.
Consideration may be given to extending the response time for good cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION 44 K h,R. ~hymerman, Chief Rea t'or Projects Branch California Dated at yalnut Creek,[cher 1988 l
this 76ht day of dc l
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