ML20149H357

Notice of Violation from Insp on 871226-880125.Violation Noted:Failure to Maintain Automatic Valve in Flow Path in Open Position When Above 10% Rated Thermal Power

ML20149H357
Person / Time
Site:	Catawba
Issue date:	02/04/1988
From:	Brownlee V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20149H352	List: IR 05000413/1987044 ML20149H349 ML20149H357
References
50-413-87-44, 50-414-87-44, NUDOCS 8802190230
Download: ML20149H357 (2)

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ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket No. 50-413 and 50-414 Catawba 1 and 2 License No. NPF-35 and NPF-52 During the Nuclear Regulatory Commission (NRC) inspection conducted on December 26, 1987 through January 25, 1988, violations of NRC requirements were identified. .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 3.7.1.2. requires three -independent steam generator auxiliary feedwater pumps and associated flow paths to be operable. With one auxiliary feedwater pump inoperable restore the required auxiliary feedwater pump to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Technical Specification 4.7.1.2.1.a.4 requires that each auxiliary.

feedwater pump be demonstrated operable at least once per 31 days by verifying that each automatic valve in the flow path is in the fully open position when above 10% Rated Thermal Power.

Contrary to the above, the licensee failed to maintain automatic valves in the flow path in the fully open position when above 10%

Rated Thermal Power constituting inoperability of the associated auxiliary feedwater pump in that enclosures 4.9 and 4.10 of procedure OP/1 (2)/A/6250/02, Auxiliary Feedwater System - required the automatic flow control valves to be fully closed or throttled during operations to cool auxiliary feedwater piping. The enclosures were implemented routinely on both units, including one instance where the Unit 2 "A" train automatic valves were fully closed or throttled continuously from November 10 to November 23, 1987 and the licensee did not maintain the units in an Operational Mode in which the Technical Specification did not apply.

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

B. 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. Enclosure 4.13 of procedure OP/1/A/6350/02, Diesel Generator Operations, requires that if Diesel Generator IB is removed from service, the operator is to transfer the power supply for "B" train Control Room Area Ventilation System (VC/YC) to Unit 2 "B" train emergency bus 2ETB or declare "B" train VC/YC inoperable.  ;

8802190230 880204 PDR ADOCK 05000413 J DCD

I Duke Power Company 2 Docke : No. 50-413 and 50-414 Catawba 1 and 2 License No. NPF-35 and NPF-52 Contrary to the above, on December 1,1987 with Diesel Generator 1B removed from service, the licensee failed to transfer the power supply for "B" train to emergency bus 2ETB or declare "B" train VC/YC inoperable. Since "A" train VC/YC was inoperable, this resulted in both trains of VC/YC without an operable source of emergency power for approximately five (5) hours, with Unit 2 in Mode 1.

This is a Severity Level IV Violation (Supplement 1) (applicable to Unit 2 only).

Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector within thirty (30) days of the date of the letter transmitting this Notice.

This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation: (1) admission or denial of the violation, (2) the reason for the violation 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 cause is shown, consideration will be given to.

extending the response time. 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, suspended, or revoked or why such other action as may be proper siould not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION

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Virgil L. Brownlee, Chief Reactor Projects Bran-5 3 Division of Reactor Projects DatedatAtlanta,hutGeorgia thisq6dayof6e

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