ML16148A741
| ML16148A741 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/22/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16148A740 | List: |
| References | |
| 50-269-93-03, 50-269-93-3, 50-287-93-03, 50-287-93-3, NUDOCS 9303020124 | |
| Download: ML16148A741 (2) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-269 and 287 Oconee 1 and 3 License Nos. DPR-38 and 55 During an NRC inspection conducted on January 3 - 30, 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 6.4.1 requires that the station be operated and maintained in accordance with approved procedures.
Operating Procedures OP/1/A/1502/07, Refueling Procedure, required that Fuel Assemblies 6DT and 5R4 be placed in core locations F-05 and M-13 respectively during core reload.
Contrary to the above, Unit 1 was not maintained in accordance with Procedure OP/1/A/1502/07 in that:
- 1.
On December 31, 1992, Fuel Assembly 6DT was placed in core location E-05 instead of the required core location F-05.
- 2.
On December 31, 1992, Fuel Assembly 4MU was placed in core location M-13 instead of Fuel Assembly 5R4.
This is a severity level IV violation and is applicable to Unit 1 only.
(Supplement I).
B.
Oconee Technical Specification 6.4.1 requires that the station be operated and maintained in accordance with approved procedures.
Step 1.12, Enclosure 6.5 of Abnormal Procedure AP/3/A/1700/19, Loss of Main Feedwater, requires that Emergency Feedwater Control Valves 3 FDW 315 and 3FDW-316 be placed in "Auto" following restart of Main Feedwater system.
Step 2.3, Enclosure 4.2 of Operations Procedure OP/1/A/1102/10, Controlling Procedure for Unit Shutdown, requires Safety Rod Group 1 to be inserted when Reactor Coolant System (RCS) pressure reaches 1900 to 1850 psig.
Contrary to the above, these requirements were not met in that:
- 1.
Following a Unit 3 reactor trip on January 26, 1993, valves 3FDW 315 and 3FDW-316 were not placed in "Auto" after restarting the Main Feedwater System. The unit was in hot shutdown during this period.
9303020124 930222 PDR ADOCK 05000269 Q
Duke Power Company 2
Docket Nos. 50-269 and 287 Oconee 1, and 3 License Nos. DPR-38 and 55
- 2.
During the Unit 1 RCS cooldown and de-pressurization on January 29, 1993, Safety Rod Group 1 was not inserted into the core prior to an automatic Reactor Protection System (RPS) actuation at RCS pressure of 1810 psig.
This is a severity level IV violation and is applicable to Units 1 and 3 (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 Oconee 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 contested, 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 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 22ndday of Februaryl 993