ML050600041
| ML050600041 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/04/2005 |
| From: | Tam P NRC/NRR/DLPM/LPD1 |
| To: | Spina J Nine Mile Point |
| References | |
| TAC MA1945, TAC MC6218 | |
| Download: ML050600041 (4) | |
Text
March 4, 2005 Mr. James A. Spina Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION - CORRECTION OF AMENDMENT NO. 167 RE: STORAGE CAPACITY OF THE SPENT FUEL POOL (TAC NOS. MA1945 AND MC6218)
Dear Mr. Spina:
On June 17, 1999, the Nuclear Regulatory Commission (NRC) staff issued the subject amendment. The amendment revised Section 5.5 of the Technical Specifications to reflect a planned modification to increase the storage capacity of the spent fuel pool. On July 29, 1999, the NRC staff issued a letter to correct a number of pages in the safety evaluation (SE) associated with that amendment.
On February 24, 2005, you notified the NRC that an erroneous statement was made in the May 15, 1998, application and an April 1, 1999, supplement. Specifically, the statement said that a 72-hour minimum in-core hold time limit existing for transfer of reactor fuel assemblies to the spent fuel pool was governed by radiological requirements. You corrected that statement by stating that the 72-hour hold time was an administrative limit based on past practice. As a result of your correction, the NRC staff is also correcting a similar statement it made in the SE associated with Amendment No. 167. Enclosed please find a corrected page 5 to the SE.
We appreciate your staffs efforts to keep the records accurate.
Sincerely,
/RA/
Peter S. Tam, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
As stated cc w/encl: See next page
Mr. James A. Spina March 4, 2005 Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION - CORRECTION OF AMENDMENT NO. 167 RE: STORAGE CAPACITY OF THE SPENT FUEL POOL (TAC NOS. MA1945 AND MC6218)
Dear Mr. Spina:
On June 17, 1999, the Nuclear Regulatory Commission (NRC) staff issued the subject amendment. The amendment revised Section 5.5 of the Technical Specifications to reflect a planned modification to increase the storage capacity of the spent fuel pool. On July 29, 1999, the NRC staff issued a letter to correct a number of pages in the safety evaluation (SE) associated with that amendment.
On February 24, 2005, you notified the NRC that an erroneous statement was made in the May 15, 1998, application and an April 1, 1999, supplement. Specifically, the statement said that a 72-hour minimum in-core hold time limit existing for transfer of reactor fuel assemblies to the spent fuel pool was governed by radiological requirements. You corrected that statement by stating that the 72-hour hold time was an administrative limit based on past practice. As a result of your correction, the NRC staff is also correcting a similar statement it made in the SE associated with Amendment No. 167. Enclosed please find a corrected page 5 to the SE.
We appreciate your staffs efforts to keep the records accurate.
Sincerely,
/RA/
Peter S. Tam, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
PUBLIC OGC PD1-1 R/F G. Hill (2)
R. Laufer P. Tam G. Hunegs S. Little ACRS J. Trapp, RI Accession Number: ML050600041 OFFICE PD1-1/PM PD1-1/LA PDI-1/SC NAME PTam SLittle RLaufer DATE 3/4/05 3/3/05 3/4/05 OFFICIAL RECORD COPY 3.2 Spent Fuel Pool Cooling Evaluation The SFP cooling system (SFPCS) at NMP1 is a Seismic Category 1 system consisting of two cooling trains, each primarily equipped with one pump, one filter and one heat exchanger. The SFPCS is designed with both cooling trains operable and only one cooling train is required to be operating to maintain the SFP water temperature at or below 140 EF during normal (planned) refueling outages (i.e., during a normal (planned) refueling outage at NMP1, an entire core is offloaded). Heat is removed from the SFPCS heat exchangers by the reactor building closed loop cooling system (RBCLCS). The RBCLCS water temperature is maintained between 40 EF and 95 EF depending upon the water temperature of Lake Ontario (the ultimate heat sink).
As a result of the increase in SFAs to be stored in the SFP, the decay heat generated in the SFP will increase. To maintain the SFP water at or below the temperature limit of 140 EF, SFAs must be held in the reactor for a minimum period of time after shutdown before being transferred to the SFP. Based on past practice, the licensee has specified an administrative l
limit on hold time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Since the heat removal capability of the SFPCS is a function of l
RBCLCS water temperature, NMPC performed analyses to determine the reactor shutdown time required before discharging SFAs from the reactor in order to maintain the SFP water temperature at or below 140 EF with RBCLCS water temperatures at 40 EF, 60 EF, 80 EF, and 95 EF. In the analyses, one SFPCS train is assumed to be operating, with both SFPCS trains operable. The following summarizes the results of these analyses:
RBCLCS Water Temp (EF)
Reactor Shutdown Time Required (hours)
Coincident Time1 After Reactor Shutdown (hours)
Coincident Net Heat Load (Mbtu/hr)
Time-to-Boil (hours)
Max. Boil-off Rate (gpm) 40 722 177 20.72 8.97 43.72 60 141 250 18.39 8.87 39.05 80 458 573 13.80 11.79 29.41 95 1008 1129 10.35 15.70 22.09 As indicated in the above table, maintaining the SFP temperature limit of 140 EF is based on two primary parameters. The first is the RBCLCS water temperature which, in turn, is a function of the water temperature of Lake Ontario. The second is the SFAs in reactor decay time following reactor shutdown. Therefore, NMPC established the following constraints which are applicable to all full-core discharge operations:
1 The time after reactor shutdown at which the SFP water reaches its temperature limit of 140 EF.
2 The calculated peak SFP temperature for this case is 130.1 EF.
Corrected by letters dated 7/29/99 and 3/4/05
Nine Mile Point Nuclear Station, Unit No. 1 cc:
Mr. Michael J. Wallace President Nine Mile Point Nuclear Station, LLC c/o Constellation Energy Group 750 East Pratt Street Baltimore, MD 21202 Mr. Mike Heffley Senior Vice President and Chief Nuclear Officer Constellation Generation Group 1997 Annapolis Exchange Parkway Suite 500 Annapolis, MD 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 126 Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Paul D. Eddy Electric Division NYS Department of Public Service Agency Building 3 Empire State Plaza Albany, NY 12223 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mark J. Wetterhahn, Esquire Winston & Strawn 1400 L Street, NW Washington, DC 20005-3502 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mr. James M. Petro, Jr., Esquire Counsel Constellation Energy Group, Inc.
750 East Pratt Street, 5th Floor Baltimore, MD 21202 Ms. Deb Katz, Executive Director Nuclear Security Coalition c/o Citizens Awareness Network P.O. Box 83 Shelburne Falls, MA 01370