ML20127N712

Notice of Violation from Insp on 850401-30

ML20127N712
Person / Time
Site:	Summer
Issue date:	05/23/1985
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127N706	List: ML20127N703 ML20127N712 ML20127N738
References
50-395-85-15, NUDOCS 8507020092
Download: ML20127N712 (2)

Text

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.5 ENCLOSURE 1 NOTICE OF VIOLATION South Carolina Electric and Gas Company Docket No. 50-395 V. C. Summer License No. NPF-12 1

I The following violations were identified during an inspection conducted on

, April 1 - 30, 1985. The Severity Levels were assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

! 1. Technical Specification 3.3.1, Table 3.3-1, Item 2.A. requires that with one power range nuclear flux channel inoperable, power operation may proceed provided the inoperable channel is placed in the tripped condition within 1

, hour and either Thermal Power is restricted to less than or equal to 75 i percent of Rated Thermal Power and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to 85 percent of Rated Thermal

Power within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the Quadrant Power Tilt Ratio (QPTR) is monitored

! at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2. Technical ~Specifica-tion 4.2.4.2 requires that with one Power Range Channel inoperable, QPTR be j determined to be within the limit when above 75 percent of Rated Thermal j Power by using the movable incore detectors to confirm that the normalized j symmetric power distribution, obtained from 2 sets of 4 symmetric thimble locations or a full-core flux map, is consistent with the indicated QPTR at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Contrary to the above, the licensee failed to implement the required i compensatory actions for an inoperable power range nuclear flux channel in

! that power range channel NI-41 was inoperable from 1:30 p.m. on April 9, 1985 until 9:00 a.m. on April 10, 1985, yet, reactor power remained at 100 percent and the movable incore detectors were not utilized to confirm that

the normalized symmetric power distribution was consistent with the j indicated Quadrant Power Tilt Ratio. '

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

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2. 10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power l Plants, Criterion 17 - Electrical Power Systems requires that onsite

! electrical power supplies, including the batteries, shall have sufficient i independence to perform their safety functions assuming a single failure.

The facility Final Safety Analysis Report (FSAR) Section 8.3.1.4.1, Criteria for Independence of Redundant Electrical Systems, references The Institute of Electrical and Electronics Engineers (IEEE) Standard 384, 1974, as modified by Regulatory Guide 1.75, Revision 1, as the basis for meeting the i criteria for independence. IEEE'384 requires that non-Class IE circuits be electrically isolated from Class IE circuits and associated circuits by the use of isolation devices.

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, 6507020092 850523 PDR ADOCK 05000395

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l South Carolina Electric and Gas Co. Docket No. 50-395 V. C. Summer License No. NPF-12 Contrary to the above, during the period of May 10 - 15, 1984, a non-Class IE individual cell battery charger, power from a non-Class 1E source, was connected to the Class IE battery XBA1A without the use of an isolation device. The unit was at power during this period and battery XBA1A was not removed from service.

This is a Severity Level IV 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 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.

Date:

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