ML16148A522
| ML16148A522 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/13/1991 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16148A521 | List: |
| References | |
| 50-270-91-09, 50-270-91-9, 50-287-91-09, 50-287-91-9, EA-91-052, EA-91-52, NUDOCS 9107160165 | |
| Download: ML16148A522 (2) | |
Text
NOTICE OF VIOLATION Duke Power Company Docket Nos.
50-270 and 50-287 Oconee Nuclear Station License Nos.
DPR-47 and DPR-55 Units 2 and 3 EA 91-052 During an NRC inspection conducted on March 24 - April 27, 1991, 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 (1991), the violation is listed below:
Technical Specification 3.3.1.c(1) requires valves HP-409 and HP-410 to be operable whenever reactor power is greater than 60 percent of full power.
Technical Specification 3.3.1.c(2) requires that if the above valves are inoperable and are not restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, reactor power shall be reduced to below 60 percent of full power within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Technical Specifications define operable as all essential instrumentation required in order to assure performance of the safety function being capable of performing its related support functions.
Contrary to the above, valves 3HP-409 and 2HP-410 were inoperable for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as described below, and during numerous periods of reactor operations reactor power was not reduced below 60 percent of full power within an additional 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
- 1. Valve 3HP-409 was inoperable from May 1984 until March 1991, due to the fact that the High Pressure Injection crossover flow instrument to the "B" High Pressure Injection Header was inoperable as a result of modifications to the flow instrumentation that resulted in the impulse lines being reversed.
- 2. Valve 2HP-410 was inoperable from initial installation in 1980 until March 1991 due to the fact that the High Pressure Injection crossover flow instrument to the "A" High Pressure Injection header was inoper able as a result of the orifice plate in the flow element being installed in the reverse direction.
This is a Severity Level III 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, 101 Marietta Street, N.W.,
Suite 2900, Atlanta, GA 30323, 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). 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 OSan 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, 9107160165 910613 PDR ADOCK 0500269 Q
-2 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. Under the authority of Section 182 of the Act, 42 U.S.C. 2232, this response shall be submitted under oath or affirmation.
FOR THE NUCLEAR REGULATORY COMMISSION JLMilhoan/for Stewart D. Ebneter Regional Administrator Dated at Atlanta, Georgia this /l4, day of June 1991 0II