ML081970099
| ML081970099 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  (DPR-063) |
| Issue date: | 07/16/2008 |
| From: | Richard Guzman NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Polson K Nine Mile Point |
| Guzman R, NRR/DORL, 415-1030 | |
| References | |
| TAC MD8434 | |
| Download: ML081970099 (4) | |
Text
July 16, 2008 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO. 1 - REQUESTED LICENSING ACTION RE: REMOVAL OF BORAFLEX CREDIT (TAC NO.
MD8434)
Dear Mr. Polson:
By letter dated April 3, 2008, Nine Mile Point Nuclear Station, LLC (NMPNS) submitted a license amendment for Nine Mile Point, Unit No. 1 (NMP1). The proposed amendment would revise NMP1 Technical Specification (TS) Section 5.5, Storage of Unirradiated and Spent Fuel, to reflect the current spent fuel storage rack configuration and to eliminate reliance on Boraflex as a neutron absorber in the two remaining Boraflex storage racks. The purpose of this letter is to provide the results of the Nuclear Regulatory Commission (NRC) staff=s acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. 10 CFR 50.34 addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
By letter dated July 9, 2008, you requested to withdraw the application from NRC review. The NRC staff acknowledges your request to withdraw the application. NRC staff activities on the review have ceased and the associated Technical Assignment Control number has been closed.
The NRC staff notes that its review to date has identified that your application and supplemental letter dated, June 27, 2008, did not provide the following technical information in sufficient detail to enable the staff to complete its detailed technical review. Therefore, if you decide to re-submit the request, it must include the following information:
(1)
Justification for using the CASMO-4 methodology and/or other referenced applications of the methodology for modeling the NMP1 Boraflex spent fuel pool storage racks (related to Item 2 of NRC letter dated June 16, 2008).
(2)
Justification for using best estimate values related to the delta between the bias and uncertainty calculated in the cited Appendix and that used in Section 3.1 analysis (related to Item 5 of NRC letter dated June 16, 2008).
K. J. Polson (3)
Justification for using best estimate values in Section 3.2, Reactivity Calculation, of the criticality analysis (related to Item 6 of NRC letter dated June 16, 2008).
(4)
Explanation and justification to support the increase in maximum nominal gadolina loading in the revised analysis (related to Item 6 of NRC letter dated June 16, 2008).
(5)
Explanation and justification to support the differences in mean bias values between Section 3.1 and Section 4.0 (related to Item 10 of NRC letter dated June 16, 2008).
If you have any questions, please contact me at (301) 415-1030.
Sincerely,
/RA/
Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220 cc: See next page
ML081970099 NRR-106 OFFICE LPLI-1/PM LPLI-1/LA SRXB/BC LPLI-1/BC NAME RGuzman SLittle GCranston MKowal DATE 7/16/08 7/16/08 7/15/08 7/16/08
Nine Mile Point Nuclear Station, Unit No. 1 cc:
Mr. Michael J. Wallace, Vice-Chairman Constellation Energy 100 Constellation Way, Suite 1800P Baltimore, MD 21202 Mr. Henry B. Barron, President, CEO &
Chief Nuclear Officer Constellation Energy Nuclear Group, LLC 100 Constellation Way, Suite 200C Baltimore, MD 21202 Mr. Terry F. Syrell Director, Licensing Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 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 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Paul D. Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Mark J. Wetterhahn, Esquire Winston & Strawn 1700 K Street, NW Washington, DC 20006 Carey W. Fleming, Esquire Sr. Counsel - Nuclear Generation Constellation Energy Nuclear Group, LLC 750 East Pratt Street, 17th Floor Baltimore, MD 21202 Mr. John P. Spath New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Tonko President and CEO New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Gary L. Detter Manager - Nuclear Safety and Security 100 Constellation Way, Suite 200C Baltimore, MD 21202