IR 05000244/1996003
| ML17264A767 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/12/1996 |
| From: | Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| EA-96-386, NUDOCS 9612230275 | |
| Download: ML17264A767 (3) | |
Text
SUBJECT:
NRC INSPECTION REPORT NO. 50-244/96-03 (NOTICE OF VIOLATION-REPLY)
Dear Dr. Mecredy:
This refers to your July 15, 1996, correspondence in response to the subject Inspection Report and Notice of Violation (NOV) dated June 6, 1996.
We apologize for the delay in replying to your response.
The NOV and your response dealt with two violations identified during an NRC inspection conducted in accordance with NRC Inspection Module 83750 at the R. E. Ginna Nuclear Station.
The first violation involved an inadequate design review and justification for the reduction in the number of continuous air monitors (CAMs)
provided in the Auxiliary Building. The second violation involved inadequacies in radioactive contamination surveys that failed to detect radioactive contamination on material released from the station.
You contested the first violation and accepted the second.
We have reviewed your response in accordance with NRC Inspection Procedure 92904,
"Plant Support-Followup."
Your response
=nd described corrective actions are considered acceptable for Violation No. 2. We concur with your assessment of the root causes for that violation and accept the validity of the proposed corrective actions.
We will review the effectiveness of these actions in a future inspection.
Regarding your disagreement with the validity of Violation No.
1 (reduction in the number of CAMs within the Auxiliary Building), we have reviewed your response.
Based on your further efforts to improve the original 50.59 evaluation, your corrective actions regarding continued placement of CAMs within the Auxiliary Building, and the low safety consequence of the violation, after consultation with NRR and OE, we have decided to reclassify this violation as a Non-Cited Violation. Notwithstanding, you should assure that your UFSAR describes how NUREG 0737,Section III.D.3.3 iodine monitoring requirements are met since your safety evaluation did not address how the removal of the CAMs affects this action item.
9612230275 961212 PDR ADQCK 05000244
Dr. Robert No response to this letter is required.
We appreciate your cooperation.
Sincerely, James T. Wiggins, Director Division of Reactor Safety Docket No. 50-244 CC:
R. Smith, Senior Vice President, Customer Operations Central Records (7 copies)
P. Eddy, Director, Electric Division, Department of Public Service, State of New York State of New York, Department of Law N. Reynolds, Esquire F. William Valentino, President, New York State Energy Research and Development Authority J. Spath, Program Director, New York State Energy Research and Development Authority
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Dr. Robert Distribution:
Region I Docket Room (with concurrences)
PUBLIC NRC Resident Inspector Nuclear Safety Information Center (NSIC)
D. Screnci, PAO J. White, DRS J. Noggle, DRS T. Moslak, DRP R. Correia, NRR W. Dean, OEDO R. Frahm, Jr., NRR G. Vissing, NRR A. Dromerick, NRR Inspection Program Branch, NRR (IPAS)
M. Campion, ORA D. Holody, ORA OE (2)
DRS File-3-DOCUMENT NAME:
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E RI/DRS DATE JNOGGLE 07/29/96 J WHITE 09/'96 JWIGGINS
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