ML17264A603
| ML17264A603 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/19/1996 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 9609230236 | |
| Download: ML17264A603 (6) | |
Text
septE r 19, 1996 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
RESOLUTION OF SPENT FUEL STORAGE POOL SAFETY ISSUES:
ISSUANCE OF FINAL REPORT, R.
E.
GINNA NUCLEAR POWER PLANT (TAC NO. M88094)
Dear Dr. Mecredy:
The Nuclear Regulatory Commission staff recently completed a detailed review of spent fuel storage pool safety issues.
The results of the staff's review are documented in a report to the Commission which. is enclosed for your information.
In the report, the staff concludes that existing structures,
- systems, and components related to the storage of irradiated fuel provide adequate protection of public health and safety.
Notwithstanding this finding, the. staff,has also, identified certain design features that reduce the reliability of spent. fuel,'ool,.decay heat'.removal, increase the potential for loss'of,spent fuel coolant, inventory, or increase the potential for consequential'---loss of essential safety functions.at'n operating reactor.
The staff 'intends to conduct plant-specific regulatory analyses to evaluate potential sa'fety.,enha'ncement backfits pursuant to 10 CFR
- 50. 109(a)(3) at a number of operating plants that possess one or more of these design features.
Although the R.
E. Ginna Nuclear Power Plant is not identified, for a plant-specific safety enhancement backfit analysis by the staff, it is requested that you review the enclosed report for.applicability to your facility and consider actions, as appropriate, related to the design of spent fuel pool decay heat removal systems at your facility. This,letter does not require any response.
fl If you have any questions regarding this matter, 'please do not hesitate to contact me at 301-415-1441.
Docket No. 50-244 Sincerely,
/S/)
Guy S. Vissing, Senior Project Manager Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
Memo to the Commission, from J. Taylor, "Resolution of Spent Fuel Storage Pool Action Plan Issues,"
dated July 26, 1996 cc w/encl:
See next page DOCUMENT NAME:GIM88094.SFP To receive a copy of this document, indicate in the box:
"C" = Copy without attachment enclos re "E" = Co y with attachment/enclosure "N" = No co y OFFICE LA:PDI"-1 E
PH:PDI-1 IIAHE SLittle Gvissing:
r'ATE 09/ I /96 09/
96 09
/96 09/
/96 09/
/96
. 0
>cia Recor Copy 9lf09230236 lf60lfflf I
mg KE C8]IR MV
l 1
I I g lk i
'J I
(
f J
C I
C'.
hAq M<~ "ik
~OIBTRIBOTIO
/
Docket File PUBLIC PDI-I Reading SVarga JZwolinski ADromerick SLittle GVissing OGC ACRS LDoerflein, RGN-I DISTRIBUTION w/o encl:
JShea
I t
I>>
ll l
f
g~R R500g
~o Cy i~
O I
e
~O
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Septembex 19, 1996 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
RESOLUTION OF SPENT FUEL STORAGE POOL SAFETY ISSUES'SSUANCE OF FINAL REPORT, R.
E.
GINNA NUCLEAR POWER PLANT (TAC NO. M88094)
Dear Dr. Mecredy:
The Nuclear Regulatory Commission staff recently completed a detailed review of spent fuel storage pool safety issues.
The results of the staff's review
,are documented in a report to the Commission which is enclosed for your information.
In the report, the staff concludes that existing structures,
- systems, and components related to the storage of irradiated fuel provide adequate protection of public health and safety.
Notwithstanding this finding, the staff has also identified certain design features that reduce the reliability of spent fuel pool decay heat removal, increase the potential for loss of spent fuel coolant inventory, or increase the potential for consequential loss of essential safety functions at an operating reactor.
The staff intends to conduct plant-specific regulatory analyses to evaluate potential safety enhancement backfits pursuant to 10 CFR
- 50. 109(a)(3) at a number of operating plants that possess one or more of these design features.
Although the R.
E. Ginna Nuclear Power Plant is riot identified for a plant-specific safety enhancement backfit analysis by the staff, it is requested that you review the enclosed report for applicability to your facility and consider
- actions, as appropriate, related to the design of spent fuel pool decay heat removal systems at your facility.
This letter does not require any response.
If you have any questions regarding this matter, please do not hesitate to contact me at 301-415-1441.
Docket No. 50-244 Guy
. Vissing, Senior roject Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
Memo to the Commission, from J. Taylor, "Resolution of Spent Fuel Storage Pool Action Plan Issues,"
dated July 26, 1996 cc w/encl:
See next page
Dr. Robert C.
Mecr edy R.E.
Ginna Nuclear Power Plant CC:
Peter D. Drysdale, Senior 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. William Valentino, President New York State
- Energy, Research, and Development Authority 2 Rockefeller Plaza
- Albany, NY 12223-1253 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S.
Reynolds Winston 5 Strawn 1400 L St.
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 Fall Road, Room 11 Rochester, NY 14620