ML16342D490
| ML16342D490 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 12/04/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML16342D489 | List: |
| References | |
| 50-275-96-21, 50-323-96-21, EA-96-467, NUDOCS 9612100270 | |
| Download: ML16342D490 (4) | |
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ENCLOSURE 1 NOTICE OF VIOLATION Pacific Gas and Electric Company Diablo Canyon Nuclear Power Plant Docket No.:
License No.:
50-275 50-323 DPR-80 DPR-82 EA 96-467 During an NRC inspection conducted on September 29, 1996, through November 9, 1996, a violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions, "NUREG-1600, the violation is listed below:
A.
10 CFR 50.65(a)(2) states, in part, that monitoring under (a)(1) is not required where it has been demonstrated that the performance or condition of a structure, system, or component has been effectively controlled through the performance of appropriate preventive maintenance of the structure, system, or component, and that the structure, system, or component remains capable of performing its intended function.
Regulatory Guide 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," Revision 1, endorses NUMARC 93-01, "Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," as an acceptable method for implementing the requirements of 10 CFR 10.65.
Regulatory Guide 1.160 states that the methods described in the guide will be used in the evaluation of the effectiveness of maintenance activities of licensees who are required to comply with 10 CFR 50.65 unless a licensee has proposed an acceptable alternative method for compliance.
The licensee subscribed to the NUMARC 93-01 methodology in Administrative Procedure MA1 ~ID17, Revision 1, "Maintenance Rule Monitoring Program," Section 1.2.
NUMARC 93-01, Section 9.3.2, states, in part, that performance criteria for.
evaluating structures, systems or components (SSCs) are necessary to identify the standard against which performance is to be measured.
Criteria are established to provide a basis for determining satisfactory performance and the need for goal setting.
Section 9.3.2 also states, in part, that specific performance criteria are established for all risk significant SSCs that are in a standby (not normally operating) mode.
Contrary to the above, the performance criteria established for the main steam safety valves (MSSVs) did not provide reasonable assurance that they were capable of fulfillingtheir intended safety function, in that the criteria were based solely on turbine steam supply system functionality and not functionality of the MSSVs, which comprised a key component of the turbine steam supply system.
This is a Severity Level IV violation (Supplement 1).
96i2i00270 961204 PDR ADOCK 05000275 8
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Pursuant to the provisions of 10 CFR 2.201, Pacific Gas and Electric Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission,,ATTN:
Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, 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 violations, and (4) the date when full compliance will be achieved.
Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response.
If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction.
However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.
Dated at Arlington, Texas this 4th day of December 1996
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