ML20215K300

Notice of Violation from Insp on 870505-31

ML20215K300
Person / Time
Site:	Summer
Issue date:	06/16/1987
From:	Verrelli D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20215K277	List: IR 05000395/1987014 ML20215K275 ML20215K300 ML20215K329
References
50-395-87-14, NUDOCS 8706250287
Download: ML20215K300 (1)

Text

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NOTIC FV LATION~

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South Carolina Electric & Gas' Docket No. 50-395 V. C. Summer Nuclear Station License No. NPF-12 The following . violations were identified during an inspection conducted on May 5-31,; 1987. The . Severity Level was assigned in accordance with the

~ Enforcement Policy.(10 CFR Part 2, Appendix C).

'A. 10.CFR 50.54(q) requires.the licensee to follow and maintain in effect an

. Emergency P_lan. 'The licensee's Radiation Emergency Plan and Emergency.

Preparedness Procedures. implements this requirement.

Contrary to the above, on May 26, 1987 the licensee failed to follow  ;

p procedures and did not promptly classify Reactor Coolant System Pressure Boundary-Leakage as an Unusual Event. This resulted in at least a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> delay in implementing .the Emergency Plan and making required notifica-tions.

This is a Severity Level V violation, (Supplement VIII).  !

B. Technical Specification 6.8.1.a requires that station procedures be established, implemented and maintained.

Contrary to the above, on May 12, 1987 the licensee's operating procedures

'for the Service Water System were deficient in that they failed to include the-special steps required to insure that the Service Water Booster Pumps would operate under accident . conditions, i .e. , a loss of offsite power followed by a safety injection, with the pumps running prior to the event.

This is a Severity Level V violation, (Supplement I).

Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of 'this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged violations; (2) the reasons for the violations if-admitted; (3) the corrective steps which have been taken j and the results achieved; (4) corrective steps which will be taken to avoid  ;

further violations; and (5) the date when full compliance will be achieved.  ;

Security or safeguards information should be submitted as an enclosure to facilitate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.

FOR THE NUCLEAR REGULATORY COMMISSION i OHGINM SIC UY l I

g 62 g g g 6 5 DAVID M. VERRELLI G David M. Verrelli, Chief Reactor Projects Branch 1 Division of Reactor Projects  ;

Dated at Atlanta, Georgia this16th day of June 1987

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