ML16148A774
| ML16148A774 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/07/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16148A773 | List: |
| References | |
| 50-269-93-02, 50-269-93-2, 50-270-93-02, 50-270-93-2, 50-287-93-02, 50-287-93-2, NUDOCS 9305170155 | |
| Download: ML16148A774 (2) | |
Text
ENCLOSURE 2 NOTICE OF DEVIATION Duke Power Company Docket Nos.: 50-269, 50-270, 50-287 Oconee License Nos.: DPR-38, DPR-47, DPR-55 During an NRC inspection conducted on January 25 - March 5, 1993, deviations from written commitments were identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Action," 10 CFR Part 2, Appendix C, the deviations are listed below:
A.
Final Safety Analysis Report, section 8.3.1.3, "Physical Identification of Safety-Related Equipment," states in part that motor control center 1XS1 protective systems power and control cables are color coded gray and motor control center 1XS2 protective systems power and control cables are color coded yellow to identify their use and/or channel association.
Contrary to the above, as of March 2, 1993, power cables 1XS2 and 1XS48 from 600 Volts Alternating Current (VAC) motor control centers 1XS1 and 1XS2 respectively to the safety related transformer CT-4 cooling fans were color coded black.
B.
Final Safety Analysis Report, section 8.3.1.4.6.2, "Cable Separation,"
states in part that mutually redundant safety related cables are run in separate trays.
Contrary to the above, as of February 24, 1993, the power cables for the mutually redundant emergency core cooling recirculation sump isolation valves 2LP-19 and 2LP-20 were run in the same cable trays.
C.
Final Safety Analysis Report, section 3.2.2.2, System Piping Classification states in part that Table 3-1 applies uniformly to all piping except auxiliary systems in the Reactor Building. The Keowee piping classification of table 3-1 is F and the design Criteria is USAS B31.1.
USAS B31.1 section 101.4.2, "Fluid Expansion Effects," states that where the expansion of a fluid may increase the pressure, the piping system shall be designed to withstand the increased pressure or provision shall be made to relieve the excess pressure.
Contrary to the above, from February 6, 1973 to present, thermal expansion effects for the Keowee Turbine Guide Bearing Oil Cooler, Generator Thrust Bearing Cooler, and Generator Air Coolers were not properly designed to withstand the increased pressure in an isolation mode.
9305170155 930507 PDR ADOCK 05000269 G
Duke Power Company 2 Docket Nos. :50-269,50-270, and 50-287 Oconee License Nos.: DPR-38, DPR-47, DPR-55 Please provide to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator, Region II, a copy to the NRC Resident Inspector, in writing within 30 days of the date of this Notice, the reason for the deviation, the corrective steps which have been taken and the results achieved, the corrective steps which will be taken to avoid further deviations, and the date when your corrective actions will be completed. Where good cause is shown, consideration will be given to extending the response time.
Dated at Atlanta, Georgia this 07th day of May 1993 0II 0I