IR 07100109/2012020
| ML20198A918 | |
| Person / Time | |
|---|---|
| Site: | 07100109, San Onofre  |
| Issue date: | 12/30/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20198A904 | List: |
| References | |
| 50-361-97-25, 50-362-97-25, NUDOCS 9801060133 | |
| Download: ML20198A918 (2) | |
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ENCLOMlRE_1 NOTICE OF VIOLATION Southem California Edison Co.
Docket Nos.:
50-361 San Ontefre Nuclear Generating Stati.m 50-362 License Nos.:
NPF-10 NPF 15 During an NRC inspection conducted on November 9 'brough December 20,1997, ene violation of NRC requirements was identified. In acco dance with the ' General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation, listed below:
10 CFR Part 50, Appendix B, Criterion XI, states that "a test program sha" be established to assure that all testing required to demonstrate that structures, systems, arid components will perform satisfactorily in se/vice is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents...."
Units 2 and 3 Technical Specifications Bases, Section 3.5.2, states that "considering si,yle failure,44 percent (15.9 gpm) of the value (362 gpm) assumed in the analysis for the injection flow rate of one charging pump is required for loss of coolant accident...."
Contrary to the above, Valves S2(3)1201MUO21, the Units 2 and 3 charging to Loop 1 A check valves, installed in 1985 and 1993, respectively, w~ not tested adequately to demonstrate that they would perform satisfactorily in service in accordance with acceptance limits contained in Technical Specifications bases, an applicable design document, until June 1997. During June 1997, when Valves S2(3)1201MUO21 were tested, they were found to have limited open disk travel, and unable to provide 15.9 gpm injection flow rate for all analyzed loss of coolant accident locations, when operated in parallel with Valves S2(3)1201MUO20, the Units 2 and 3 charging to Loop 2A check valves, a condition assumed in the Technical Specification bases.
This is a Severity Level IV violation (Supplement I ) applicable to Units 2 and 3 (Violation 361; 362/97025-03).
The NRC has concluded that information regarding the reason for the violation, the corrective actions taken and planned to correct the violation and prevent recurrences, and the date when full compliance was achieved are already adequately addressed on the docket in Licensee Event Report 50-361/97 010 dated August 13,1997, and NRC inspectior Report 50-361; 362/9719, dated October 10,1997. However, you are required to submit a written statement or explanation pursuant to 10 CFR Part 2.201 if the description therein does not accurately reflect your corrective actions or your position. In that case, or if you choose to respond, clearly mark your response as a " Reply to a Notice of Violation," and tend it to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.
20555 with a copy te the Regional Administrator, Region IV, and a copy to the NRC Resident 9001060133 971230 PDR ADOCK 05000361 G
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. inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter
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transmitting this Notice of Violation (Notice).
Because your response, if any, will be placed in the NRC Public Document Room (PDR), to the
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extent possible, it should not include any personal privacy, proprietary, rar safeguards i
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 th6 legal basis to support your request for withholding the information from the public.
Dat t Walnut Creek, California i
thi ay of December 1997_
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