ML17264A144
| ML17264A144 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/30/1995 |
| From: | Andrea Johnson NRC (Affiliation Not Assigned) |
| To: | Mecredy R BALTIMORE GAS & ELECTRIC CO. |
| Shared Package | |
| ML17264A145 | List: |
| References | |
| TAC-M92188, NUDOCS 9509060275 | |
| Download: ML17264A144 (3) | |
Text
Dr. Robert C. Hecredp Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 August 30, 1995
SUBJECT:
SAFETY EVALUATION OF ROCHESTER GAS AND ELECTRIC'S PROPOSED CRITICALITY ANALYSIS OF THE GINNA NEW AND SPENT FUEL RACKS/CONSOLIDATED ROD STORAGE CANISTERS (TAC NO. H92188)
Dear Dr. Hecredy:
By letter dated Hay 5,
- 1995, Rochester Gas and Electric Corporation (RG&E) submitted proposed engineering calculations to increase the allowable Uranium-235 (U-235) enrichment of fuel to be stored in the new and spent fuel storage facilities of the Ginna plant.
The NRC staff finds the criticality aspects of the proposed enrichment increase to the Ginna new and spent fuel pool storage racks acceptable, and meet the requirements of General Design Criterion 62 for the prevention of criticality in fuel storage and handling.
Conclusions are summarized in the enclosed safety evaluation.
Sincerely, Original signed by:
Allen R. Johnson, Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation cc:
See next page DISTRIBUTION:
i, Docket Filer NRC & Local PDRs PDI-3 Reading JZwolinski LHarsh AJohnson SLittle GHolahan RJones EWeiss LKopp OGC ACRS (4)
JLinville, RI WLazaurus, RI DOCUMENT NAME:
G: iGINNAiG192188. LTR To rscolve s copy of this document, indlcste In the hoc C" a Copy w ut sttschmsnt/snciosure "E a Copy with s c
nt/ nciosure 'N e No copy OFFICE PDI-1: LA PDI-1: PM F
SRXB PDI-NAME DATE SLittl Q/
/95 AJohnson 95 Z.
95 LMg sh 95 9509060275 950830 PDR
'-'ADQCK 05000244 P
~"'r
- PDR, 0...:IC'IAL~.:'R. CQRD4COP,:Y
~'
~
~
~P,fl A/00 O
Ce 0
I R
o~
Cy
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 30, 1995 Dr. Robert C. Hecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
SAFETY EVALUATION OF ROCHESTER GAS AND ELECTRIC'S PROPOSED CRITICALITY ANALYSIS OF THE GINNA NEW AND SPENT FUEL RACKS/CONSOLIDATED ROD STORAGE CANISTERS (TAC NO. H92188)
Dear Dr. Hecredy:
By letter dated Hay 5,
- 1995, Rochester Gas and Electric Corporation (RGSE) submitted proposed engineering calculations to increase the allowable. Uranium-235 (U-235) enrichment of fuel to be stored in the new and spent fuel storage facilities of the Ginna plant.
The NRC staff finds the criticality aspects of the proposed enrichment increase to the Ginna new and spent fuel pool storage racks acceptable, and meet the requirements of General Design Criterion 62 for the prevention of criticality in fuel storage and handling.
Conclusions are summarized in the enclosed safety evaluation.
Sincerely, A
en R. Joh on, Project Hanager Pro
'torate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation cc:
See next page