ML17249A727
| ML17249A727 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/14/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 8003050158 | |
| Download: ML17249A727 (5) | |
Text
Docket No, 50-244
'MMT0IIIl000fKT FlLF IPIt DISTRIBUTION WITH ENCLOSURE:
oc e
GW c or e,
ACRS (1)
W/0 ENCLOSURE:
NRC PDR Local PDR Mr. Leon D. White, Jr.
ORB P2 Reading p~~
Vice President NRR'Reading Electric and Steam Production
'Eisenhut Rochester Gas and Electric Corporation
"'HVollmer
89 East Avenue
'L'Ziemann Rochester, New York 14649 HSmith'"
FPagano
Dear Hr. Whfte:
JMil1er
- JEnnis, MNSS NSIC TERA Enclosed for your information and action are the results of the NRC-sponsored vital area analysis for the Gfnna Nuclear Station.
Thyrse results have been previously discussed with Nr. George Daniels 'of Rochester Gas and Electric Corporation.
As indicated during the revfeIt of your Physical Security Plan submitted in response to the requorements of 10 CFR ?3.55, some modification of your plan may be required as a result of the vital area analysis.
Please undertake the appropriate revisions and advise the NRC of those 1evfsfons within 60 days of your recefpt of this letter.
We have determined that the enclosure to this letter contains information of a type specified in 10 CFR 2.?90(d).
Accordingly, it fs deemed to be comoercfal or" financial information within the meaning of 10 CFR 9.5(a)(4) and.shall;:he subject to disclosure only fn accordance with the provisions of'D CFR 9.12.
Sincerely,
Enclosure:
As stated (Withheld from Public Disclosure) cc w/o enclosur e:
See next page Dennis L. Zfemann, Chief Operating Reactors Branch 82 Division of Operating Reactors 8OO3O5 O
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Mr. Leon D. White, Jr.
cc w/o enclosure:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby 8 MacRae 1757 N Street, N.
W.
Washington, D. C.
20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Rochester Committee for Scientific Information Robert E. Lee, Ph.D.
P. 0. Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza
- Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontario 107 Ridge Road West
- Ontario, New York 14519 Director, Techni cal Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall f2 Arlington, Virginia 20460 U. S. Environmental Protection Agency Region II Office ATTN:
EIS COORDINATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555
GINNA NUCLEAR STATION VITAL AREA ANALYSIS
SUMMARY
The Ginna plant was determined to have the following Type I vital areas:
1.
Control Room 2.
Reactor Containment 3.
Relay Room 4.
Intermediate building sub-basement 5.
Intermediate building 253'evel, north side (location of reactor trip breakers) 6.
Upper level spent fuel area (for up to 28 days after shutdown for refueling)
This determination is based on the following assumptions:
1.
The standby auxiliary feedwater,building will be included within the vital area perimeter.
2.
The turbine driven auxiliary feedwater pump will have a self-cooling feature, added to make it independent of the AC and DC lube oil cooler pumps.
3.
The DC distribution supplying power to the turbine driven AFMS DC lube oil pump will'be relocated to a vital area.
4.
The condensate storage tank with associated valves and piping will be incorporated within the vital area perimeter.,
(Note:
This includes the small 900 Section of CST piping in the Intermediate Building at the 253'evel.)
5.
The ability for unimpeded movement of personnel between NCClC and HCC1D will be prevented.
6.
The remainder of the plant will be compartmentalized as shown on Drawing 33013-703, Revision 2, "Ginna Station Controlled Access Plan."
SECURI TX-RELATED IN>'ORhQ.TIOR 10 CFR 2. F90(d) INFORMATION
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