ML20198S917

Notice of Violation from Insp on 981019-1106.Violation Noted:As of 981106,appropriate Quality Standards as Described in UFSAR Section 9.2.2.1 & in App 3.2A Not Specified & Included in Design Documents for Electrical

ML20198S917
Person / Time
Site:	San Onofre
Issue date:	01/04/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20198S894	List: IR 05000361/1998014 ML20198S890 ML20198S917
References
50-361-98-14, 50-362-98-14, NUDOCS 9901120039
Download: ML20198S917 (2)

Text

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l4 ENCLOSURE 1 NOTICE OF VlOLATION Southern California Edison Co. Docket Nos.: 50-361; 50-362 San Onofre Nuclear Generating Station License Nos.: NPF-10; NPF-15 During an NRC inspection conducted on October 19 through November 6,1998, a violation of NRC requirements was identified. In accordano with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:

i 10 CFR Part 50, Appendix B, Criterion lil, " Design Control," states, in part, " Measures shall be established to assure that applicable regulatory requirements and the design basis, as defined in 50.2 and as specified in the license application . . . are correctly translated into specifications, drawings, procedures, and instructions. These measures shall include provisions to assure that appropriate quality standards are specified and included in design documents.

Updated Final Safety Analysis Report Section 9.2.2.1, "[ Component Cooling Water]

Design Bases," stated that the component cooling water system and components are designed to the equipment classitation requirements indicated in Appendix 3.2A, "O-List."

t Updated Final Safety Analysis Report Appendix 3.2A defines Quality Class Il as those l structures, components, and systems not in Quality Class I that are provided to mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the Nblic.

Component Cooling Water Miniflow Control Valves 2(3) HY-6537, -6538, and -6539 perform a safety action necessary to provide essential auxiliary support to the engineered safety features that are provided to mitigate the consequences of postulated accidents. For postulated accidents involving a loss-of-offsite power, these valves must close after the component cooling water pumps are restarted, when flow is restored above 3000 gpm, to enable the component cooling water system to deliver required design basis flows.

l Contrary to the above:

l As of November 6,1998, appropriate quality standards as described in Updated Final

Safety Analysis Report Section 9.2.2.1,"[ Component Cooling Water] Design Bases,"

and in Appendix 3.2A were not specified and included in design documents for the electrical control of Component Cooling Water Miniflow Control Valves 2(3) HY-6537, -

6538, and -6539. Specifically, the electrical control circuits for these valves were not classified as Quality Class 11 and as a consequence these control circuits were not provided with Class 1E power and various circuit components, such as the controlling flow switches, were not Class 1E or Seismic Category 1.

L l l 9901120039 990104 1 PDR ADOCK 0 0

4 I This is a Severity Level IV violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Southern California Edison Co. 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 or severity level, (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.

If you contest this enforcement action, you should also provide a copy of your response, with the basis for your denial, to the Director, Office of E iforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.

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. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial ,

information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.

In accordance with 10 CFR 19.11, you may be required to post this Notice within two working days.

Dated at Arlington, Texas, this 4th day of Januaiy 1999 i

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