ML042240114
| ML042240114 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/11/2004 |
| From: | Nerses V NRC/NRR/DLPM/LPD1 |
| To: | Christian D Dominion Nuclear Connecticut |
| Nerses V, NRR//DLPM, 415-1484 | |
| References | |
| TAC MB6479 | |
| Download: ML042240114 (5) | |
Text
August 11, 2004 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - SELECTIVE IMPLEMENTATION OF THE ALTERNATIVE SOURCE TERM - FUEL HANDLING ACCIDENT ANALYSES, MILLSTONE POWER STATION, UNIT NO. 2 (TAC NO. MB6479)
Dear Mr. Christian:
By letter dated September 26, 2002, as supplemented by letter dated May 7, 2004, you submitted a proposed amendment to the Technical Specifications (TSs) for Millstone Power Station, Unit No. 2. The proposed amendment would revise the TSs based on a re-analysis of the limiting design basis Fuel Handling Accident using an Alternative Source Term in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.67 and Regulatory Guide 1.183.
The U.S. Nuclear Regulatory Commission staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is presented in the enclosure. This information was previously requested in a July 13, 2004, conference call with your staff. We request that the additional information be provided by August 20, 2004. The response time frame was discussed with Mr. David Dodson of your staff on August 4, 2004. The staff considers this due date essential to timely completion of this licensing action. Please contact me at (301) 415-1484. if you have any questions.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
Request for Additional Information cc w/encl: See next page
ML04220114 OFFICE PDI-2/PM SRXB/SC PDI-2/SC NAME VNerses FAkstulewicz JClifford DATE 8/11/04 8/11/04 8/11/04
Millstone Power Station, Unit No. 2 cc:
Lillian M. Cuoco, Esquire Senior Counsel Dominion Resources Services, Inc.
Rope Ferry Road Waterford, CT 06385 Edward L. Wilds, Jr., Ph.D.
Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 First Selectmen Town of Waterford 15 Rope Ferry Road Waterford, CT 06385 Charles Brinkman, Director Washington Operations Nuclear Services Westinghouse Electric Company 12300 Twinbrook Pkwy, Suite 330 Rockville, MD 20852 Senior Resident Inspector Millstone Power Station c/o U.S. Nuclear Regulatory Commission P.O. Box 513 Niantic, CT 06357 Mr. W. R. Matthews Senior Vice President - Nuclear Operations Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. P. J. Parulis Manager - Nuclear Oversight Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. J. Alan Price Site Vice President Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. John Markowicz Co-Chair Nuclear Energy Advisory Council 9 Susan Terrace Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terrys Plain Road Simsbury, CT 06070 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870 Mr. G. D. Hicks Director - Nuclear Station Safety and Licensing Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. S. E. Scace Assistant to the Site Vice President Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. Chris L. Funderburk Director, Nuclear Licensing and Operations Support Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
Millstone Power Station, Unit No. 2 cc:
Mr. A. J. Jordan, Jr.
Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. S. P. Sarver Director - Nuclear Station Operations and Maintenance Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. David W. Dodson Licensing Supervisor Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED AMENDMENT TO TECHNICAL SPECIFICATIONS SELECTIVE IMPLEMENTATION OF THE ALTERNATIVE SOURCE TERM FUEL HANDLING ACCIDENT ANALYSES MILLSTONE POWER STATION, UNIT NO. 2 DOCKET NO 50-336 By letter dated September 26, 2002, as supplemented by letter dated May 7, 2004, Dominion Nuclear Connecticut, Inc. (DNC or licensee) submitted a proposed amendment to the Technical Specifications (TSs) for Millstone Power Station, Unit No. 2. The proposed amendment would revise the TSs based on a re-analysis of the limiting design basis Fuel Handling Accident using an Alternative Source Term in accordance with Title 10 of the Code of Federal Regulations Section 50.67 and Regulatory Guide (RG) 1.183.
The Nuclear Regulatory Commission staff has reviewed the information the licensee provided that supports the proposed TS changes. In order for the staff to complete its evaluation, the following additional information is requested:
In your May 7, 2004 letter, you state the calculation method used to determine the ANSI/ANS 5.4 gap fractions is the same as submitted and approved on the Fort Calhoun Station (FCS) docket in 2001. In our review of your May 7, 2004, letter, we found this was not the case. The FCS docket used non-LOCA gap fractions that are a factor of 2 greater than the RG 1.183 values and was able to demonstrate the radiation doses analyzed will bound the radiation doses from an actual event. Your analysis was not performed in the same manner as the FCS method. Therefore, the staff has not been able to conclude that your alternative methodology provides adequate assurance that it conforms to RG 1.183 and thus meets the requirements of 10 CFR 50.67.
Please provide additional detailed information on the alternative methodology used for determining the bounding non-LOCA gap fractions outlined in the May 7, 2004 supplemental letter. Information should be included on a step-by-step basis so that the method can be clearly understood. Any references used in the development of the methodology should also be clearly stated. Also, provide the specific information, such as the vendor supplied inputs DNC used in performing the gap fraction calculations, so the staff can perform a confirmatory analysis.