ML17264A727
| ML17264A727 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/06/1996 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-M95759, NUDOCS 9611140205 | |
| Download: ML17264A727 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055$ 4001 November 6, 1996 Sea-l(~P~+>
LICENSEE: Rochester Gas and Electric Corporation FACILITY: R.
E. Ginna Nuclear Power Plant
SUBJECT:
SUMMARY
OF MEETING WITH REPRESENTATIVES OF ROCHESTER GAS AND ELECTRIC CORPORATION JULY 10,
- 1996, CONCERNING A PROPOSED RERACKING OF THE SPENT FUEL STORAGE POOL WITH BORATED STAINLESS MATERIALS (TAC NO. N95759)
In preparation for the planned reracking of the Ginna Spent Fuel Storage Pool (SFSP),
representatives of Rochester Gas and Electric Corporation (RGS.E) together with representatives of RGSE vendors, Framatome Technologies, Inc.
(FTI), Framatome Cogema Fuels (FCF) and Societe Atlantique de Techniques Avancees (ATEA) presented plans for expanding the storage capacity of the Ginna SFSP.
The meeting discussed proprietary issues.
This summary addresses the non-proprietary issues.
Enclosure 1 provides the agenda of the meeting, Enclosure 2 provides the list of attendees of the meeting, and Enclosure 3
provides the viewgraphs of the presentation materials.
Enclosure 4 provides the proposed schedule for the total project.
The current configuration of the Ginna SFSP consists of two regions.
Region 1
consists of stainless steel racks with 176 storage locations in a checker board pattern.
Region 2 consists of stainless steel racks with boraflex and with 840 storage locations.
It is proposed to replace the Region 1 racks with borated stainless steel racks.
Two locations are proposed in Region l.
One with borated stainless steel that would accommodate 187 storage locations and one with borated stainless steel in a checker board pattern that would accommodate 292 storage locations.
These would be installed during this reracking.
There would be additional borated stainless steel racks that would be placed along sides of the present Region 2 racks.
The construction of these racks would be at a later date.
Several concerns were discussed including (1) potential loading conditions for future spent fuel casks designs as they affect the dropping of heavy loads
- analyses, (2) adequacy of the number of feet per rack, (3) provisions for preventing tipping of a rack during a seismic event, (4) concern for thermal expansion that could cause buckling of the borated stainless steel plates in the lateral direction, and (5) concern for the corrosion resistance of the material thr ough all temperature ranges that the material would experience.
Of prime concern was adequacy of the stiffness of the racks.
The staff would like to see a demonstration test that would verify the adequacy of the stiffness of the structures.
96iii40205 96ii06 PDR ADOCK 05000244 PDR
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November 6, 1996 The submittal for a license amendment is planned for early January 1997 with completion of NRC review by early November 1997.
This would accommodate fabrication, construction at the site and completion by late December 1998 which would accommodate the refueling of the reactor in March 1999.
/s/
Docket No. 50-244 Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
l.
Agenda 2.
List of Attendees 3.
Viewgraphs of Presentation Materials 4.
Project Schedule cc w/encls:
See next page DOCUMENT NAME: GI95759.MTN To receive a copy of this document, indicate in the box:
"C" = Copy without attachment enclosure "E" = Co y ith attachment enclosure "N" = No co y OFFICE NAME DATE PH:PDI-1 Gvissing:
11/
/96 E
LA:PDI-1 SLICCI 11/
/96 D:PDI-1 SBajwa 11/
/96 0
icosa Recor Copy 11/
/96 11/
/96
The submittal for a license amendment is planned for early January 1997 with completion of NRC review by early November 1997.
This would accommodate fabrication, construction at the site and completion by late December 1998 which would accommodate the refueling of the reactor in March 1999.
Gu
. Vissing, Seni r Project Manager Project Directorate I-l Division of Reactor Pr'ojects I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosures:
1.
.Agenda 2.
List of Attendees 3.
Viewgraphs of Presentation Materials 4.
Project Schedule cc w/encls:
See next page
Rochester Gas and Electric Corporation 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 Hr.
F. William Valentino, President New York State
- Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension
- Albany, NY 12203-6399 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S.
Reynolds Winston
& Strawn 1400 L St.
N.W.
Washington, DC 20005-3502 Hs.
Thelma Wideman
- Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31
- Lyons, NY 14489 Ms. Hary Louise Heisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Fall
- Road, Room 11 Rochester, NY 14620 Dr. Robert C. Hecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 Hr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza Tenth Floor
- Albany, NY 12223
I