ML17265A177
| ML17265A177 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/02/1998 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M95759, NUDOCS 9803090278 | |
| Download: ML17265A177 (6) | |
Text
Dr. Robert C. Mecredy Vice President, Nuclear (~rations
~ Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 March 2, 1
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONON THE RADIATIONEFFECTS ASPECTS OF THE SPENT FUEL POOL STORAGE RACK MODIFICATIONAT R.
E. GINNANUCLEAR POWER PLANT (TAC NO. M95759)
'ear Dr. Mecredy:
The NRC staff has reviewed the report with respect to the application for the modification of the spent fuel pool storage racks submitted by the Rochester Gas and Electric Corporation for R. E.
Ginna Nuclear Power Plant.
Based on the review, we need additional information as shown in the enclosure to complete our review.
Please provide your response as soon as you can to support your schedule for completion of this action.
Sincerely, ORIGINAL SIGNED BY:
Docket No. 50-244
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Guy S. Vissing, Senior Project Manager Project Directorate 1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 2, 1998 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rocheste~ Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONON THE RADIATIONEFFECTS ASPECTS OF THE SPENT FUEL POOL STORAGE RACKMODIFICATIONAT R. E. GINNANUCLEAR POWER PLANT (TAC NO. M95759)
Dear Dr. Mecredy:
The NRC staff has reviewed the report with respect to the application for the modification of the spent fuel pool storage r'acks submitted by the Rochester Gas and Electric Corporation for R. E.
Ginna Nuclear Power Plant.
Based on the review, we need additional information as shown in the enclosure to complete our review.
Please provide your response as soon as you can to support your schedule for completion of this action.
Sincerely, Docket No. 50-244 G y S. Vissing, Senior P ject Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information ccw/encl: See next page
II
Dr. Robert C. Mecredy Rochester Gas and Electric Company R.E. Ginna Nuclear Power Plant Peter D. Drysdale, Sr. Resident Inspector R.E., Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road Ontario, NY 14519 Regional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. F. WilliamValentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Lalw 120 Broadway New York, NY 10271 Nicholas S. Reynolds Winston 8 Strawn 1400 S Street N.W.
Washington, DC 20005-3502 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Falls Road, Room 11 Rochester, NY 14620 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223
RE UEST FOR ADDITIONALINFORMATION RELATEDTO THE GINNASPENT FUEL POOL EXPANSION DOCKET NO. 50-244 In Chapter 6.0,'adiological Evaluation of the Spent Fuel Pool Re-Racking Lice'nsing Report (Februaty 1997), you,address the offsite dose consequences at the EAB and LPZ for both a fuel handling and tornado missile accident.
For these same-two accidents, provide a discussion of the thyroid and whole body dose consequences to the'control room operator.
These dose consequences should be within the acceptance'criteria of 30 rem thyroid and 5 rem whole body In Table 6.5-1 of your February 1997 SFP re-racking report, you list the auxiliary building gaseous rele'ases for 1994 and 1995. This table does not show any contribution from Kr-85, which has been identified as one of the radionuclides released from other plants.
Provide your reasoning for not seeing any Kr-85 in the auxiliary building releases.
Enclosure
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