ML20234C571

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Notice of Violation from Insp on 870709-0825.Violations Noted:Channel Check of Auxiliary Feedwater Flow Rate Inadequate & Failure to Demonstrate Operability of Ac Offsite Sources within Required Time Frames
ML20234C571
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 09/15/1987
From: Reyes L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20234C552 List:
References
50-413-87-25, 50-414-87-25, NUDOCS 8709210339
Download: ML20234C571 (2)


Text

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o ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-413'and 50-414 Catawba 1 and 2 License Nos. NPF-35 and NPF-52 During the Nuclear Regulatory Commission (NRC) inspection conducted on July 9, 1987 through August 25, 1987, violations of NRC requirements were identified specified acceptance criteria and failure to demonstrate operability of offsite power sources within required time frames.

In accordance with the

" General Statement of Policy and Procedure for NRC Enforcement Actions,"

10 CFR Part 2, Appendix C (1987), the violations are listed below:

A.

Technical Specification 6.8.1 requires that written procedures shall be established, implemented, and maintained. covering the applicable procedures recommended in Appendix A to Regulatory Guide 1.33, Revision. 2, February 1978.

PT/2/A/4600/03, Monthly Surveillance Items, requires. a channel check to be performed on Auxiliary Feedwater Flow Rate. channels with a specified acceptance criteria that remote indications agree with control room indications within 30 gallons per minute (gpm).

Contrary to the above, on August 26, 1986, January 4, 1987 and March 1, 1987, the licensee failed to perform an adequate Channe1 ~ Chsck of Auxiliary Feedwater Flow Rate in that under existing plant conditions, remote indications and control room indications could not be compared for the specified acceptance criteria of 30 gpm due to all gauges being offscale high.

This is a Severity Level IV violation applicable to ' Unit 2 only.

(Supplement I)

B.

Technical Specification 3.8.1.1 requires two separate and independent diesel generators to be operable when in operational modes 1, 2, 3 and 4.

With one diesel generator inoperable, the A.C. offsite sources shall be demonstrated operable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter by verifying correct breaker alignments and Indicated power availability.

8709210339 870915 PDR ADOCK 05000413 G

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I Duke Power Company 2

Docket Nos'. 50-413 and 50-414 Catawba 1 and 2 License Nos. NPF-35 and NPF-52 Contrary to the above, the licensee failed to demonstrate operability of the A.C.

offsite sources within the required time frames when one diesel-generator was inoperable on the following separate occasions:

1.

On June 8, 1987 with the 1A Diesel Generator inoperable at 11:00 a.m.,

the A.C.

offsite sources were not demonstrated operable until 12:50 p.m., 50 minutes late.

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1 2.

On June 17, 1987 with the 18 Diesel Generator inoperable at 6:00 a.m.

and the A.C. offsite sources having been -demonstrated operable at 5:55 a.m., the A.C. o.ffsite sources were not demonstrated operable J

until 3:40 p.m., one hour and 45 minutes late.

3.

On July 20, 1987 with the 2B Diesel Generator inoperable at 8:30 p.m.

and the A.C. offsite sources having been demonstrated operable at 7:50 p.m., the A.C. offsite sources were not demonstrated operable until 5:00 a.m. on July 21, 1987, one hour and 10 minutes late.

i This is a Severity Level IV Violation (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit to this Office within thirty (30) days of the date of the letter transmitting this Notice a written statement' or explanation in reply.

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including:

(1) admission or denial of 'the! violations, (2) the reason for the violations if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved. Where good 1

cause is shown, consideration will be given to extending the response time.

i FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY

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VIRGIL L. BROM/NLEE-Luis A. Reyes, Director Division of Reactor Projects Dated at Atlanta, Georgia this 15 day of Sept.

1987

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