ML20151U388

Notice of Violation from Insp on 880502-0610.Violation Noted:As of 880610,licensee Failed to Rept Listed Conditions & Design of Valve motor-operated Control Circuits for Surge Tank Outlet Valve Did Not Include Analyses of Earthquakes

ML20151U388
Person / Time
Site:	San Onofre
Issue date:	08/03/1988
From:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20151U382	List: ML20151U379 ML20151U388 ML20151U394 ML20151U409
References
50-361-88-10, 50-362-88-10, NUDOCS 8808190068
Download: ML20151U388 (2)

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APPENDIX A NOTICE OF VIOLATION

t Southern California Edison Company San Onofre Units 2 and 3 P. O. Box 800 Docket Nos. 50-361, 50-362 ,

Rosemead, California 91770 License Nos. NPF-10, NPF-15 As a result of the inspection conducted during the period of May 2 to June 10,

1988, and in accordance with the NRC Ersforcement Policy 10 CFR Part 2, ,

Appendix C, the following violations were identified:

A. 10 CFR 50.73 requires, in part, that licensees shall report any event or condition that resulted in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded; that resulted in the nuclear power plant being in an unanalyzed condition that 3

Significantly compromised plant safety; that resulted in the nuclear ,

, power plant being in a condition that was outside the design basis of the plant; or any event or condition that alone coald have prevented the -

i fulfillment of the safety function of systems needed to mitigate the consequences of an accident.

Contrary to the above, as of June 10, 1988, the licensee failed to report ,

the following conditions: i (1) The High Energy Line Break Accident (HELBA) analysis not having  !

been adequately performed for the CCW system during plant licensing.

(2) The combination of CCW 1eakage and valve closure time which could have prevented the CCW system from functioning during a HELBA.

(3) The CCW system had leakage in excess of the design leakage and  !

had no capability for seismically qualified makeup to the system prior to 1984, as reported in delinquent Licensee Event  ;

Report 88-008.  !

This is a severity level IV violation (Supplement I).

j B. 10 CFR 50, Appendix A Criterion 2 and 44, requires, in part, that systems important to safety shall be designed to withstand the effects of {

natural phenomena such as earthquakes, and further requires that the '

design bases for these systems reflect appropriate combinations of the i effects of accident conditions with the effects of the natural phenomena, j i

j Contrary to the above, at the time of the inspection, (1) the design of '

the valve motor operator control circuits for the surge tank outlet valve

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of the Component Cooling Water (CCW) system did not include analyses of adverse effects of earthquakes; and (2) the design bases of the CCW system did not reflect the combination of the effects of the surge tank outlet valves for both trains souriously closing in conjunction with a i safe shutdown earthquake. '

i 8808190068 880803 PDR ADOCK 05000361 Q PDC l

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This is a severity level IV violation (Supplement I).

C. San Onofre Nuclear Generating Station (SONGS) Technical Specification 4.0.5 requires in part that inservice testing of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (Code).

The ASME Code,Section XI, requires, in part, that Category B valves be exercised every 3 months and that a record of test results be maintained. 2 Contrary to the above, as of June 10, 1988, Salt Water Cooling system valves HV6494 and HV6496 were not included in the Unit 2/3 inservice testing program..

This is a severity level IV violation (Supplement I).

1 Pursuant to the provisions of 10 CFR 2.201, Southern California Edison Company i is hereby required to submit a written statement or explanation to the U.S. I Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC )

20555 with a copy to the Regional Administrator, Region V, and a copy of the NRC Resident Inspector, within 30 days of the date of the letter transmitting 1

this Notice. This reply should be clearly marked as a "Reply to a Notice of j Violation" and should include for each violation: (1) the reason for the

violation, if admitted (2) the corrective steps that have been taken and the l 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, j 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. l 1

i FOR NUCLEAR REGULATORY Copti!SSION i l

J. B. Martin

. Regional Administrator I

Dated at Walnut Cr , California j

this f day of , 1988 1

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