ML20127E836
| ML20127E836 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/06/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20127E815 | List: |
| References | |
| 50-413-92-29, 50-414-92-29, NUDOCS 9301200062 | |
| Download: ML20127E836 (2) | |
Text
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O{ CLOSURE 1 NOTICE OF VIOLATION Duke Power Company Catawba Units 1 and 2 Docket Nos. 50-413 and 50-414 License Nos. NPf-35 and NPF-52 During an NRC inspection conducted on November 8, 1992 - December 12, 1992, a violation of NRC requirements was identified.
in accordance with the
" General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, (1992), the violation is listed below:
10 CFR 50, Appendix B, Criterion III, Design Control, and the licensee's accepted Quality Assurance Program (Duke-1-A, Section 17.3.2.2) collectively require that measures be established to assure that applicable regulatory requirements and the design basis specified in the license application for the facility be correctly translated into specifications, drawings, procedures, and instructions.
Further, design control measures are to provide for verifying the adequacy of design, by the performance of design reviews, the use of alternate or simplified calculational methods, or the performance of a suitable testing program.
Technical Specification 3,7.1.2 requires at least three Auxiliary Feedwater (CA) pumps and associated flow paths be operable in Modes 1-3.
Operability includes the capability of the system to perform its intended safety function during design basis events, assuming a single active failure, and with no credit taken for non-safety equipment toward mitigating the event.
Contrary to the above, design control measures associated with the CA System were inadequate in that design deficiencies existed on both units since startup which rendered the systems inoperable in that they were not capable of performing their intended safety functions. The design deficiencies involve the interaction of non-safety related equipment with safety related control circuitry affecting the operation of both units' Turbine Driven Auxiliary feedwater Pumps (TDAFWPs) such that during certain design basis events, malfunction of the non-safety related equipment, coupled with a single active failure would have prevented the CA Systems of both units from delivering the reqaired flow to two intact S/Gs as designed.
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 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 facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
Violation" and should include for each violation:This reply should be clearly mar (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the 9301200062 930106 PDR ADOCK 03000413 G
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Duke Power Company 2
Docket Nos. 50-413 and 50-414 Catawba Units 1 and 2 License Nos. NPF-35 and NPF-52 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 6thday of January 1993
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