ML17264B021
| ML17264B021 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/09/1997 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M95759, NUDOCS 9709160274 | |
| Download: ML17264B021 (6) | |
Text
Dr. Robert C. Mecred~
Vice President, Nucl Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION SPENT FUEL POOL (SFP)
MODIFICATIONS - SFP COOLING CONCERNS (TAC NO.'95759)
I eptember 9,
1997 modifications.
In order to continue our review, we have determined the need for additional information in the area of SFP cooling issues.
The enclosed request for additional information provides our concerns and since we are approaching the date when you requested the amendment, please provide your response as soon as possible.
Sincerely, ORIGINAL" SIGNED BY'ear Dr. Hecredy:
Me are in the process of reviewing your March 31, '1997, application for i
an amendment to the Technical Specifications relating to the proposed SFP 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
Enclosure:
Request for Additional Information cc w/encl:
See next page DISTRIBUTION:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 September 9,
1997 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION SPENT FUEL POOL (SFP)
MODIFICATIONS SFP COOLING CONCERNS (TAC NO. M95759)
Dear Dr. Mecredy:
We are in the process of reviewing your March 31, 1997, application for an amendment to the Technical Specifications relating to the proposed SFP modifications.
In order to continue our review, we have determined the need for additional information in the area of SFP cooling issues.
The enclosed request for additional information provides our concerns and since we are approaching the date when you requested the amendment, please provide your response as soon as possible.
Sincerely, Docket No. 50-244 Guy
. Vissing, Sen>or Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/encl:
See next page
Dr. Robert C. Hecredy 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 Hs. Hary Louise Heisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Fall
- Road, Room ll 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 RELATING TO THE PROPOSED SPENT FUEL POOL MODIFICATIONS R.E.
GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 With regard to the decay heat loads resulting from the proposed spent fuel pool (SFP) capacity expansion, Table 5.5-1 of the SFP Re-racking Licensing Report should be revised to include the decay heat generation rate for each batch of the spent fuel assemblies (SFAs) stored in the SFP.
In Section 5.7 of the SFP Re-racking Licensing Report, Ginna states that the Technical Specification (TS) limit for the SFP water is 150 F which is achieved with the present SFP cooling system.
The heat removal capability of the SFP cooling system heat exchangers varies as the temperature of Lake Ontario water varies.
Therefore, the duration of reactor shutdown required prior to any SFAs discha~ged to ensure that the SFP water temperature does not exceed its 150 F limit is a function of Lake Ontario water temperature.
For a full core offload scenario, the following summarizes the reactor shutdown times requi~ed prior to the discharge of any SFA for three lake temperatures (40 F,
60 'F and 80 F) to prevent the SFP water from exceeding the 150 F limit:
Lake Water Temperature,
'F 40 60 80 SFAs In Reactor Decay Time Required, Hrs.
100 132 280 Have these restrictions required for SFAs to decay in the reactor prior to the discharge of any SFA been incorporated in the Ginna TS? If not, provide detailed justifications for not having these restrictions imposed in the TS.
Also, provide the decay heat loads in the SFP and the corresponding calculated SFP water temperatures as a function of reactor shutdown time for each of the above cases.
For the normal (routine refueling with I/3 core discharged) discharge scenario as discussed in Section 5.5.2.1 of the SFP Re-racking Licensing Report, provide the decay heat loads in the SFP and the corresponding calculated SFP water temperatures as a function,.of reactor shutdown time.
Also, indicate the lake water temperature which was used in the analysis.
In an event of a complete loss of the SFP cooling system (i.e. resulting from a station blackout event, a seismic event, etc.), with the assumption that 1879 (a full core offload scenario with a full inventory of SFAs)
SFAs are stored in the pool and the pool temperature is 150 F,,
Enclosure
provide an analysis to show the time required for the SFP to boil.
Information to be provided should include: input parameters (i.e. the reactor shutdown time required prior to the SFA discharge, etc.)
used to calculate the decay heat load; SFP boiling off rate; methods to replenish the SFP water; and sources of make-up water.
In Section
- 5. 10 of the SFP Re-racking Licensing Report, Ginna states that in the event of a complete loss of the SFP cooling system, the original (loop I) SFP cooling system can be made operational in 45 minutes and that an additional 5.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> would be available for repair or to place the skid mounted ~nit (loop 3) into operation before the pool temperature reaches 180 F.
Provide the following information:
detailed discussion to show how the above cited 45 minutes were
- derived, detailed justifications (including equipment availability, readiness, etc.) to show that 5.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> will be adequate for repair or to place the skid mounted-unit into operation, and detailed discussion to show how long it will take to make the original SFP cooling system operational during an event of a complete loss of the SFP cooling system resulting from a station blackout event, a seismic event, etc.
Discuss the procedures to be utilized by the Ginna staff to monitor and control the SFP water temperature and decay heat load so as to remain within the design basis limiting values for routine refueling and planned or unplanned full core offload events.
Include discussion of the location of needed instrumentation, means of monitoring it and integration of operation staff activities with engineering staff activities in order to implement the procedure(s).