IR 07100120/2012007
| ML16161A934 | |
| Person / Time | |
|---|---|
| Site: | Oconee, 07100120  |
| Issue date: | 12/29/1987 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16161A933 | List: |
| References | |
| 50-269-87-49, 50-270-87-49, 50-287-87-49, NUDOCS 8801110408 | |
| Download: ML16161A934 (2) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-269, 270, and 287 Oconee Units 1, 2, and 3 License Nos. DPR-38, DPR-47, and DPR-55 During the Nuclear Regulatory Commission (NRC)
inspection conducted November 20 - December 7, 1987, a violation of NRC requirements was identifie In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986), the violation is listed below:
Oconee Nuclear Station Technical Specification (TS) 3.8.6 states "During the handling of irradiated fuel in the reactor building, at least one door on the personnel and emergency hatches shall be close The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing surface."
An Oconee Nuclear Station Technical Specification interpretation for TS 3.8 explains that, in addition to the requirements of TS 3.8.6, any other pathway other than the hatches listed shall be covered, sealed or isolated with the intent to prevent air flow from inside the Reactor Building at normal atmospheric pressur CFR 50, Appendix B, Criterion III, Design Control states that design changes shall be subject to design control measures commensurate with those applied to the original design and be approved by the organization that performed the original design unless the licensee designates another responsible organizatio Technical Specification 6.4.1 states that the station shall be operated and maintained in accordance with approved procedure Contrary to the above requirements:
a. In the periods of September 24-28 and October 10-12, 1987, refueling operations were conducted at Oconee Unit 1 with gaps totalling 3 to 4 square inches in the emergency hatch seals-and equalization valv Also in the periods of February 23 to March 13, 1986, (Unit 1),
August 19 to February 27, 1986, (Unit 2) and December 30, 1986, to March 9, 1987, (Unit 3) refueling operations were carried out with the one-inch equalizing valves open in the emergency hatches, thus negating containment integrit The Emergenty Hatch Temporary Modification ONTM-0297 was not adequately prepared nor reviewed, in that it was not taken into consideration that unlocking the equipment hatch doors automatically cammed open the one-inch equalization valve PDR ADOCK 05000269
Duke Power Company
Docket Nos. 50-269, 270, and 287 Oconee Units 1, 2, and 3 License Nos. DPR-38, DPR-47., and DPR-55 The procedure for foaming closed penetrations through the emergency hatch was not adequate in that it did not adequately describe how the job was to be performed and was not provided to the workmen performing the jo This is a Severity Level IV Violation (Supplement I).
This violation applies to Units 1, 2 and Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Oconee, within 30 days of the date of the letter transmitting this Notic This reply should be clearly marked as a "Reply to a Notice of Violation" and should include:
(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time. If an 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, suspended, or revoked or why such other action as may be proper should not be take It is noted that the above violation was identified by the licensee, was promptly reported to NRC, and resulted in immediate and proper corrective action. Also, an extensive study was made to determine cause and actions to prevent recurrence, which is reported in Licensee Event Report 50-269/87-0 FOR THE NUCLEAR REGULATORY COMMISSION Original Signed by Luis A. Reyes Luis A. Reyes, Director Division of Reactor Projects Dated at Atlanta, Georgia this 29th day of De