ML17264A869

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Forwards RAI Re License Amend Request of 970331 Relating to Proposed Mod of Plant Sfsp
ML17264A869
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/30/1997
From: Vissing G
NRC (Affiliation Not Assigned)
To: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
References
TAC-M95759, NUDOCS 9705020250
Download: ML17264A869 (7)


Text

Apri 1 30, 1997 Dr. Robert C. Hecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING YOUR LICENSE AMENDMENT REQUEST OF MARCH 31,

1997, RELATING TO A PROPOSED MODIFICATION OF THE GINNA SPENT FUEL STORAGE POOL (TAC NO. H95759)

Dear Dr. Hecredy:

The NRC staff has reviewed your request of March 31, 1997, for a license amendment relating to a proposed spent fuel storage pool modification and has identified the need for additional information.

Enclosed is a request for additional information.

Please provide your response within 45 days from the receipt of this request.

Sincerely, ORIGINAL SIGNED BY:

Docket No. 50-244

Enclosure:

Request for Additional Information, cc w/encl:

See next page Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation DISTRIBUTION:

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DOCUMENT NAME:G: iGINNAiH95759.RAI To receive a copy of this document,,indicate in the box:

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 April 30, 1997 Dr. Robert C. Hecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING LICENSE AMENDMENT REQUEST OF MARCH 31,

1997, RELATING TO A PROPOSED MODIFICATION OF THE GINNA SPENT FUEL STORAGE POOL (TAC NO. H95759)

Dear Dr. Hecredy:

The NRC staff has reviewed your request of March 31, 1997, for a license amendment relating to a proposed spent fuel storage pool modification and has identified the need for additional information.

Enclosed is a request for additional information.

Please provide your response within 45 days from the receipt of this request.

Sincerely, Docket No. 50-244

Enclosure:

Request for Additional Information cc w/encl:

See next page Guy S. Vissing, Senior Project Manager Project Directorate I-l Division of Reactor Projects ; I/II Office of Nuclear Reactor Regulation

Dr. Robert C. Mecredy 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 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 Yor k, NY 10271 Nicholas S.

Reynolds Winston

& 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 ill West Fall
Road, Room 11 Rochester, NY 14620 Mr. Paul Eddy New York State Department of Public Service

'3 Empire State

Plaza, Tenth Floor
Albany, NY 12223

RE UEST FOR ADDITIONAL INFORMATION CONCERNING RE VEST FOR A LICENSE AMENDMENT RELATED TO A PROPOSED SPENT FUEL STORAGE POOL MODIFICATION R.

E.

GINNA NUCLEAR POWER PLANT As a result of recent information, the NRC staff have found that the use of remote tools and spalling during spent fuel pool modifications may be an ALARA consideration during spent fuel modifications.

Therefore, we request the following information in order for us to complete the review.

1.

Discuss the remote tools which would be used during dry and wet operation during the spent fuel modification.

2.

NRC experiences have shown that when the storage racks are

added, the radioactivity concentrations in the spent fuel pool may be expected to increase due to crud deposits spalling from spent fuel assemblies which are shuffled.

This crud (spalling) has a loose fluffy layer that falls off the fuel assemblies to the floor of the fuel pools and canals.

This additional crud material has caused the activity of Mn-54 and Co-60 to exceed the values in the TS for spent fuel pool activities.

Provide a

detailed explanation of the ALARA considerations that will be used to combat spalling dur,ing spent fuel rerack.

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