ML20137W395
| ML20137W395 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/07/1986 |
| From: | Mangan C NIAGARA MOHAWK POWER CORP. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| (NMP2L-0605), (NMP2L-605), NUDOCS 8602200130 | |
| Download: ML20137W395 (2) | |
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7 M Y NIAGARA
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R UMOHAWK NIAGARA MOHAWK POWER CORPORATl0N/300 ERIE BOULEVARD WEST, SYRACUSE. N.Y.13202/ TELEPHONE (315) 474-1511 February 7, 1986 (NMP2L 0605)
Mr. R. H. Starostecki, Director U.S. Nuclear Regulatr < Comission Region I Division of Reactor Pro 3ects 631 Park Avenue King of Prussia, PA ~ 19406 Re: Nine tMle Point Unit 2 Docket No. 50-410
Dear Mr. Starostecki:
The following is submitted in response to your letter dated August 7, 1985 concerning the apparent violation identifled in Inspection Report No.
50-410/83-06.
Subsequent to our response to the Nuclear Regulatory Commission on September 26, 1983, the Management Analysis Company independent assessment team, which was reviewing violations and discrepancies, issued a Corrective Action Request with respect to the apparent violation identified in Inspection Report 83-06.
Niagara ibhawk responded to the Corrective Action Request by indicati ng that an independent Final Safety Analysis Report veri fication program had been instituted to help ensure the accuracy of the Final Safety Analysis Report at the time of licensing.
The Management Analysis Lampany assessment tean accepted the Niagara Mohawk resolution of this Corrective Action Request.
Since the initial discrepancy has been corrected, and Niagara ibhawk has instituted a specific program to help ensure the accuracy of the Final Safety Analysis Report, Niagara Mohawk does not believe that any further discussion regardi ng the interpretation of the apparent violation would enhance the resolution of this issue.
As we have discussed at several meetings with your
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Mr. R. W. Stamstecki, Director Page 2 staff, the Final Safety Analysis Report verification progran has identified a ntriber of changes which have been incorporated into the Final Safety Analysis Report to reflect the design of Unit 2.
For this reason, Niagara Mohawk believes that this issue can be resolved.
Very truly yours, C. V. Mangan Senior Vice President CVM/GG/cla xc: Director of Inspection and Enfomement U.S. Nuclear Regulatory Comission Washington, DC 20555 R. A. Gravi, NRC Senior Resident Inspector Project File (2)
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