ML17037B641
| ML17037B641 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/02/1977 |
| From: | Rhode G Niagara Mohawk Power Corp |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037B641 (4) | |
Text
NRC FDRM 195 (2-76)
U.S. NUCLEAR REGULATORY C ISSION DOCKET NUMBER 50>> 220 NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL FILE NUMBER TO:
Mr; George Lear; FROM:
Niagara Mohawk Power Corp.
- Syracuse, New York Mr. Gerald K, Rhode DATE OF DOCUMENT 2/2/77 DATE RECEIVED 2/7/77
@LETTER PkiR IGINAL
~QCOPY DESCRIPTION
'C3NOTORIZED PkNC LASSIFI ED PROP INPUT FORM ENCLOSURES NUMBER OF COPIES RECEIVED
.One si,gn0d f
'f Ltr..re our 1/18/77 Ltr.~,'.concerning refueling accident inside the reactor containment building and its effects on the potential site boundary radiation exposures.
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ACKNOWLEDGED DO NjT REMOVE PLANT NAME Nine Mile Point Unit No.l (1-P)
SAFETY ASSIGNED AD:
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LIC ASST Lear Parrish-FOR ACTION/INFORMATION PROJECT MANAGER LIC ASST 2877 RJL REG FILE I & E OELD GOSSICK & STAFF MIPC CASE-HANAUER HARLESS PROJECT MANAGEMENT BOYD P,
COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPDR e o N
Y TIC:
NSIC:
NRC FORM 196 (2.76)
INTERNALD SYSTEMS SAFETY HEINEMAN SCHROEDER
" ENGINEERING.
MACARR
- KNIGHT-SIHWEIL PAWLICK REACTOR SAFE ROSS NOVAK ROSZTOCZY CHECK AT& I SALTZMAN RUTBERG EXTERNALDISTRIBUTION NAT LAB REG V.IE LA PDR CONSULTANTS:
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ISTRl BUTION PLANT SYSTEMS TEDESCO IPPOLITO.
OPERATING REACTORS STELLO OPERATING TECH EISENHUT BUTLE B
ULR KSON OR Sl SAF ERNST BALLARD SPANGLER SITE TECH GAMMILL STEPP HULMAN SITE ANALYSIS
" VOLLMER BUNCH J,
COLLINS KREGER CONTROL NUMBER JSS/,.
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NIAGARAMOHAWKPOWER CORPORATION 4lII~,
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MOHAWK 300 ERIE BOULEVARD. WEST SYRACUSE, N. Y. I3202
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'ebruary 2, 1977 Director of Nuclear Reactor Regulation Attn:
Mr. George Lear, Chief Operating Reactors - Branch ¹3 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Re:
Nine Mile Point Unit 1 Docket No. 50-220 DPR-63
Dear Mr. Lear:
Four letter of January 18, 1977 stated that, based upon the Nuclear Regulatory Commission's preliminary review, a refueling accident inside the reactor containment building and its effects on the potential site boundary radiation exposures has been considered during the licensing review for the Nine Mile Point Unit 1 facility.
Upon review, we also conclude that such an accident has been considered and potential site boundary radiation exposures would be within 10 CFR Part 100 guidelines.
CL'EAIl'REGV AMATORY CO)hlAIj'5'le tAollSodlon Si ncerel y, r
NIAGARA MORAWK POWER CORPORATZON Nq.
GERALD K. R ODE Vi'ce President Engineering
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