ML20245G298

Notice of Violation from Insp on 890226-0325.Violation Noted:Licensee Failed to Implement Procedure in That While Attempting to Close 1SV-27A,operator Inadvertently Closed 1SM-7,Steam Generator 1A MSIV

ML20245G298
Person / Time
Site:	Catawba
Issue date:	04/20/1989
From:	Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20245G264	List: IR 05000413/1989007 ML20245G259 ML20245G298
References
50-413-89-07, 50-413-89-7, 50-414-89-07, 50-414-89-7, NUDOCS 8905030113
Download: ML20245G298 (2)

Text

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ENCLOSURE 1 N_0TICE OF VIOLATION Duke Power Company Docket Nos. 50-413, 50-414 Catawba 1 and 2 License Nos. NPF-35 and NPF-52 During the Nuclear Regulatory Commission (NRC) inspection conducted on l February 26,198f through March 25, 1989, a violation of NRC requirements was l identified. In accordance with the " General Statement of Policy and Procedure l for NRC Enforcement Actions", 10 CFR Part 2, Appendix C (1989), the violation is listed below: i l

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

1. PT/1/A/4200/09A, Auxiliary Safeguards Test Cabinet Periodic Test, Step 8.1.2.5 of enclosure 13.1 requires the operator to close ISV-27A, Steam Generator 1A Power Operated Relief Isolation Valve as a test prerequisite.

Contrary to the above, on March 5,1989 the licensee failed to implement {

the procedure in that while attempting to close ISV-27A, the operator j inadvertently closed ISM-7, Steam Generator 1A Main Steam Isolation Valve, '

which resulted in a reactor trip and a safety injection.

2. IP/0/A/3890/01, Controlling Procedure for Troubleshooting and Corrective I Maintenance, requires the maintenance technician to determine specific  ;

limitations for anticipated work to be performed and to determine the effect of planned activities on plant operations. '

Contrary to the above, on February 21, 1989, maintenance technicians I

failed to adequately perform this step in that the effects of placing an electrical jumper between terminal points F-11 and F-12, as shown on electrical drawing CNEE 0270-01.03, were not adequately evaluated which resulted in an inadvertent main steam isolation valve closure, a reactor

' rip and a safety injection.

3. Operations Management Procedure 1-8, Authority and Responsibility of Licensed Operators, section 7.2.B requires that the Operator at the Controls (0ATC) be knowledgeable of unit status at all times.

Contrary to the above, on February 21, 1989, the 0ATC was not knowledgeable of the unit status in that at 1:20 p.m. the 0ATC initiated steps to reduce reactor plant temperature, however, failed to recognize the ensuing excessive cooldown rate which resulted in a safety injection six minutes later.

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

8905030113 890420 DR ADOCK0500g3

Duke Power Company 2 Docket Nos. 50-413, 50-414 Catawba 1 and 2 License Nos. NPF-35 and NPF-52 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 wFich 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 should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION 10 $$

Alan R. Herdt, Chief Reactor Projects, Branch 3 Division of Reactor Projects Dated at Atlanta, Georgia this 20 day of April 1989