ML17264A573
| ML17264A573 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/26/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17264A572 | List: |
| References | |
| 50-244-96-05, 50-244-96-5, NUDOCS 9608050251 | |
| Download: ML17264A573 (3) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Rochester Gas and Electric Corporation Ginna Station Docket No. 50-244 License No. DPR-18 As a result of an inspection conducted on May 5 - June 15, 1996, the following violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the violation is listed below:
10 CFR 50, Appendix B, Criterion V requires that activities affecting quality be prescribed and accomplished in accordance with documented procedures, and that these procedures include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
Operations procedure 0-15.2, "Valve Alignment for Reactor Head Lift, Core Component Movement, and Periodic Status Checks," required that containment penetration P-2 be"adequately sealed" prior to refueling, and be independently verified by two operating personnel.
Station Modification procedure SM-10034-10.01, "Temporary Service Air System For SGRP," contained a requirement to maintain the temporary service air line (in penetration P-2) pressurized or its isolation valves closed during fuel movement in containment.
Contrary to the above, on May 21, 1996, Procedures 0-15.2, and SM-10034-10.01 were not adequately accomplished, and did not contain appropriate acceptance criteria, in that containment penetration P-2 was not adequately sealed during the movement of irradiated fuel inside containment.
The temporary service air line was removed such that penetration P-2 contained one approximate 3 inch diameter hole and one approximate 1-1/2 inch diameter hole passing through its entire length from the inside to the outside of containment.
This condition persisted for approximately 3 and 1/2 hours during the movement of irradiated fuel inside containment.
This is a Severity Level IV violation. (Supplement I)
Pursuant to the provisions of 10 CFR 2.201, Rochester Gas and Electric Corporation 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 I, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of receipt of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as "Reply to a Notice of Violation" and should include:
(1) the reason for the violations, or, if contested, the basis for disputing the violations; (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 may be issued to show cause why the license should not be modified, suspended, or revoked, or why such action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time.
'P608050251 960726 PDR ADOCK 05000244 6
Notice of Violation Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction.
However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.
Dated at King of Prussia, Pennsylvania this 26th day of July 1996