ML20059K689

Notice of Violation from Insp on 930905-1002.Violation Noted:Instrumentation & Electrical Technicians Failed to Adequatley Implement Catawba Nuclear Site Directive 4.2.2 & Procedure IP/O/A/3890/01

ML20059K689
Person / Time
Site:	Catawba
Issue date:	10/29/1993
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20059K688	List: IR 05000413/1993026 ML20059K687 ML20059K689
References
50-413-93-26, 50-414-93-26, NUDOCS 9311160150
Download: ML20059K689 (2)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-413, 414 Catawba Units 1 and 2 License No. NPF-35, NPF-52 During an NRC inspection conducted on September 5, 1993 - October 2, 1993, 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, the violations are listed below:

A.

Technical Specification 6.8.1, Procedures and Programs, requires, in part, that written procedures be established, implemented and maintained covering the activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, which includes licensee procedures controlling maintenance and the plant independent verification process.

Catawba Nuclear Site Directive 4.2.2, Independent Verification, and procedure IP/0/A/3890/01, Controlling Procedure for Troubleshooting and Corrective Maintenance, each require that, before an action is performed that involves independent verification, both individuals will verify that the component on which action is to be performed is the correct component.

Contrary to the above:

1.

On September 25, 1993, Instrumentation and Electrical technicians failed to adequately implement Catawba Nuclear Site Directive 4.2.2 and procedure IP/0/A/3890/01. The technicians failed to properly independently verify that sliding link A-5, associated with the Containment Floor and Equipment Sump Pump 2A start circuit, was located in electrical cabinet 2ATC14, and erroneously opened sliding link A-5 in cabinet 2ATC16. This caused the closure of the "A" Steam Generator Main Steam-Isolation Valve, 2SM-7, resulting in a Unit 2 reactor trip.

2.

On September 23, 1993, Instrumentation and Electrical technicians failed to adequately implement Catawba Nuclear Site Directive 4.2.2.

The technicians failed to properly independently verify a wire that was to. be removed and inadvertently caused the "A" train Control Room Ventilation chiller to trip. This resulted in inoperability of the "A" train and entry into Technical Specification 3.0.3.

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

B.

10 CFR 50.73(a)(2)(i)(B) requires that the licensee submit to the NRC a Licensee Event Report for any operation or condition prohibited by the plant's Technical Specification within 30 days after the event has been discovered.

9311160150 931029 PDR ADOCK 05000413 G

PDR

Duke Power Company 2

Docket Nos. 50-413,-414

~ Catawba Units-1 and 2 License Nos. NPF-35, NPF-52 10 CFR 50.73(a)(2)(iv) requires that the licensee submit to.the NRC an LER for any event or condition that resulted in a manual or automatic actuation of any engineered safety feature. The opening of the Ice Condenser lower inlet doors during a containment pressurization event is considered an automatic actuation of an engineered safety feature.

Contrary to the above:

1.

On August 18, 1992, the licensee's failure to perform portions of the outside containment leakage testing at the required frequency required by Technical Specification 6.8.4.a. was identified. The licensee failed to submit a Licensee Event Report for this violation of Technical Specification 6.8.4.a, Primary Coolant Sources Outside Containment, within 30 days of discovering the violation.

2.

On January 31, 1993, with Unit 1 in Mode 4, a water hammer event occurred in the Residual Heat Removal System suction piping and caused a pipe break in a vent line connected.in the RHR suction piping inside containment.

The subsequent containment pressure incream caused the Ice Condenser lower inlet doors to open. The licensee failed to submit an LER for this event within 30 days.

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

Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby rc:pired to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector at the Catawba Nuclear Station, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation:

(1) the reason for the violation, or, if cu.. tested, the basis for disputing the violation,-(2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations,.and (4) the date when full compliance will be achieved.

If an adequate reply is not received within the time specified in this Notice, an order or demand for information may be issued so as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

Dated at Atlanta, Georgia this 29ttday of October 1993 o