ML17265A172
| ML17265A172 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/02/1998 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M95759, NUDOCS 9802240116 | |
| Download: ML17265A172 (7) | |
Text
February 2, 1998 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONON THE COOLING ASPECTS OF THE SPENT FUEL POOL STORAGE RACK MODIFICATIONAT R.
E. GINNA NUCLEAR POWER PLANT (TAC NO. M95759)
Dear Dr. Mecredy The NRC staff 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 (RG&E) for R. E. Ginna Nuclear Power Plant and,issued a request for additional information (RAI). RG8E submitted responses to our RAI on November 11, 1997, and the staff reviewed the responses.
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, Or iginal Signed by:
Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Docket No. 50-244
Enclosure:
Request for Additional Information ccw/encl:
See next page DISTRIBUTION:
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Februa,y 2, 1998 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONON THE COOLING ASPECTS OF THE SPENT FUEL POOL STORAGE RACK MODIFICATIONAT R.
E. GINNA NUCLEAR POWER PLANT (TAC NO. M95759)
Dear Dr. Mecredy:
The NRC staff 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 (RG&E) for R. E. Ginna Nuclear Power Plant and issued a request for additional information (RAI). RG&E submitted responses to our RAI on November 11, 1997, and the staff reviewed the responses.
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, Origina1 Signed by:
Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Docket No. 50-244
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Docket File PUBLIC PDI-1 R/F JZwolinski SBajwa SLittle GVissing CHehl, Region I
OGC ACRS DOCUMENT NAME: G:>GINNA>M95759-3.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N"= No co E
LA:PDI-OFFICE P13:PDI-1 NAME GVissing/Ic SLIttie':PDI-1 SBa wa NRR:DSSA:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 February 3, 1998 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONON THE COOLING ASPECTS OF THE SPENT FUEL POOL STORAGE RACK MODIFICATIONAT R. E. GINNA NUCLEAR POWER PLANT (TAC NO. M95759)
Dear Dr. Mecredy:
The NRC staff 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 (RG8E) for R. E. Ginna Nuclear Power Plant and issued a request for additional information (RAI). RG&E submitted responses to our RAI and the staff reviewed the responses.
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, Guy S. Vissing, Senior Project Manager Project Directorate l-1 Division of Reactor Projects - I/II Docket No. 50-244
Enclosure:
Request for Additional Information ccw/encl: See next page
Dr. Robert C. Mecredy Rochester Gas and Electric Company R.E. Ginna'Nuclear Power Plant CC:
Peter D. Drysdale, Sr. Resident Inspector R.E. Ginna Plant U.S. Nuclear Regulatoiy 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 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 FaIls 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
REQUEST FOR ADDITIONALINFORMATIONREGARDING SPENT FUEL POOL CAPACITYEXPANSION R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 1.0 What are the design Seismic Categories for the spent fuel pool (SFP) cooling system Loops 1 and 2'?
2.0 The SFP cooling system Loop 2 is designed to operate at Lake Ontario water temperature of 80 'F to maintain the SFP water temperature at or below 150 'F with a SFP heat load of 16.0x10'tu/hr during a planned or unplanned full core off-load. Loops 1 and 3 are each designed to remove 7.93x10'tu/hr with a pool temperature of 150 'F and Lake Ontario water temperature of 80 'F. Discuss how Loops 1 and 3 can provide 100% backup cooling to Loop 2 during a planned or unplanned full core off-load.
3.0 In the event of a full core off-load, Loop 2 willbe operated alone with Loop 1 and 3 available for backup cooling. GINNAstated that to ensure 100% cooling system backup prior to a full core off-load, the skid-mounted loop is placed in position, hoses connected, and leak checked, to operate in parallel with Loop 1. Have these requirements been included in the plant operating procedures or TRM'?
4.0 In the November 11, 1997 submittal, GINNAstated that the TRM will be modified to ensure 100% backup for all SFP cooling scenarios along with Lake Ontario water temperature, in-reactor decay time, and associated SFP heat loads.
However, GINNAonly performed analyses to demonstrate the SFP heat loads with various core shutdown times and their corresponding SFP cooling system Loop 2 (primary loop) heat removal capability for three lake temperatures, 40 'F, 60 'F and 80 'F. Ifthe lake temperature is in between the above temperatures (i.e 55 'F), discuss the provision established in the TRM to require which core decay time, the one corresponding to the higher lake temperature (i.e. 60 'F) or a core decay time based on a new calculation for the lake temperature of 55 'F.
Enclosure
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