ML17264A616
| ML17264A616 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/24/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17264A615 | List: |
| References | |
| 50-244-96-06, 50-244-96-6, NUDOCS 9610010117 | |
| Download: ML17264A616 (3) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Rochester Gas and Electric Corporation Robert E. Ginna Nuclear Power Plant Docket No. 50-244 License No. DPR-18 During an NRC inspection conducted between June 16 and July 20, 1996, two violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the violations are listed below:
A.
Technical Specifications Surveillance Requirement 3.7.8.3 requires that all service water loop header cross tie valves be locked in position and verified locked every 31 days.
Valves V-4610, V-4611, V-4612, and V-4779 are required to be locked closed, and valves V-4623, V-4639, V-4640, and V-4756 are required to be locked open when the plant is operating in Modes 1, 2, 3, and 4.
Contrary to the above, from February 24, 1996 to June 17, 1996, valves V-4610, V-4611, V-4612, V-4779, V-4623, V-4639, V-4640, and V-4756 were not locked.
The plant was in Modes 1, 2, 3, or 4 from February 24-April 2, and from June 3-June 17, 1996.
The plant was below Mode 4 during a refueling outage between April 2 and June 3, 1996.
Surveillance procedure S-30.8 required a monthly.
verification that these valves were in their correct positions, but it did not require a verification that the valves were also locked.
This is a Severity Level IV violation (Supplement I).
B.
10 CFR 50.59(b)(1) requires, in part, that the licensee maintain records of changes in the facility and of changes in procedures made pursuant to this section, to the extent that these changes constitute changes in the facility as described in the safety analysis report.
These records must include a written determination that the change, test, or experiment does not involve an unreviewed safety question.
Contrary to the above, in May 1994 the licensee modified service water valve MOV-4616 by making a significant change to its closing time without performing a safety evaluation.
This change created the potential for not meeting the assumed or design service water flows listed in the Updated Final Safety Analysis Report (UFSAR) for the diesel generator and containment recirculation fan coolers to perform their safety function and thereby operating the plant different from that described in the UFSAR. Specifically, in May 1994 the licensee changed the closing time of valve MOV-4616 from approximately 30 to approximately 120 seconds and operated the plant in this configuration until May 1996 when the closing time was changed to approximately 60 seconds, for which the licensee performed a safety evaluation.
This is a Severity Level IV violation (Supplement I) ~
9b10010117 Vb0'F24 PDR ADQCK 05000244 8
PDR OFFICIAL RECORP
(;OPY
'nclosure 1
0 Pursuant to the provisions of 10 CFR 2.201, Rochester Gas and Electric Corporation is hereby required to submit a written statement or explanation within 30 days of receipt of the letter transmitting this Notice of Violation (Notice) 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 if applicable, a copy to the NRC Resident Inspector at the facility that is the subject of this 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.
Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response.
If an adequate reply is not received within the required time specified in this Notice, an order or a 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.
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 24th day of September, 1996
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