ML17055C648

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Forwards Safety Evaluation Verifying Conformance of Util Emergency Repsonse Capability to Reg Guide 1.97.Rev 1 to EGG-EA-6880, Conformance to Reg Guide 1.97,Nine Mile Point... Also Encl
ML17055C648
Person / Time
Site: Nine Mile Point 
Issue date: 11/19/1986
From: Zwolinski J
Office of Nuclear Reactor Regulation
To: Mangan C, Seibert C
NIAGARA MOHAWK POWER CORP.
Shared Package
ML17055C650 List:
References
RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-51109, NUDOCS 8611250550
Download: ML17055C648 (4)


Text

November 17, 1986 Docket No. 50-220 Niagara Mohawk Power Corporation ATTN:

Mr. C. V. Mangan Senior Vice President c/o Miss Catherine R. Seibert 300 Erie Boulevard West

Syracuse, New York 13202

Dear Mr. Mangan:

SUBJECT:

SAFETY EVALUATION -

EMERGENCY REGULATORY GUIDE 1.97, REV.

2 DISTRIBUTION NRC PDR JKelly Local PDR JZwolinski BWD1 Reading RStevens RBernero JJoyce EJordan JLezevnick BGrimes GHolahan JPartlow ACRS (10)

NThompson OGC-BETH (info only)

GLainas NMPl File

RESPONSE

CAPABILITY, CONFORMANCE TO (TAC 51109)

Re:

Nine Mile Point Nuclear Station, Unit No.

1 We have completed our review of your submittals dated April 2, 1984, October 18, 1985 and December 6, 1985 regarding your response to Emergency

Response

Capability, Conformance to Regulatory Guide 1.97 (R.G. 1.97), Revision 2.

A detailed review and technical evaluation was performed by the staff's contractor, EGSG Idaho, Inc., and is found in the attached Technical Evaluation Report.

We have reviewed this report and concur with the conclusion that you either conform to, or are justified in deviating from, the guidance of R.G. 1.97 for each post-accident monitoring variable except for neutron flux.

For this variable, a Category 1 system that meets all the criteria of R.G. 1.97 is an industry development item.

The existing instrumentation is acceptable for interim operation.

In the long term, you have committed to follow industry development of Category 1 Neutron Flux instrumentation, evaluate the acceptability of this instrumenta-tion and install such equipment when it becomes available.

The Safety Evaluation supporting our findings is enclosed.

Sincer ely, 86g1260650 >++

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Enclosure:

Safety Evaluation Ori gina 1 s igned by R, Auluck John A. Zwolinski, Director BWR Project Directorate II1 Division of BWR Licensing cc w/enclosure:

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Mr. C. V. Mangan Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station, Unit No.

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Washington, D. C.

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Oswego, New York 13126 Niaoara Mohawk Power Corporation ATTN:

Mr. Thomas Perkins Plant Superintendent Nine Mile Point Nuclear Station Post Office Box 32

Lycoming, New York 13093 Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 126
Lycoming, New York 13093 John W. Keib, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
Syracuse, New York 13202 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza
Albany, New York 12223