ML021680068
| ML021680068 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/10/2002 |
| From: | Nerses V NRC/NRR/DLPM/LPD1 |
| To: | Price J, Danni Smith Dominion Nuclear Connecticut |
| Nerses V, NRR//DLPM, 415-1484 | |
| References | |
| TAC MB3700 | |
| Download: ML021680068 (8) | |
Text
July 10, 2002 Mr. J. A. Price Site Vice President - Millstone Dominion Nuclear Connecticut, Inc.
c/o Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 - ENVIRONMENTAL ASSESSMENT RE: REVISED FINAL SAFETY EVALUATION REPORT LICENSING BASIS FOR THE POST-ACCIDENT OPERATION OF THE SUPPLEMENTARY LEAKAGE COLLECTION AND RELEASE SYSTEM (TAC NO. MB3700)
Dear Mr. Price:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for amendment dated June 6,1998, as supplemented by letters dated April 5, 1999; April 7, April 19, July 31, and September 28, 2000; March 19, June 11, September 21, and December 20, 2001. The proposed amendment would revise the licensing basis for the post-accident operation of the Supplementary Leakage Collection and Release System as described in the Millstone Nuclear Power Station, Unit No. 3, Final Safety Analysis Report.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Victor Nerses, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Environmental Assessment cc w/encl: See next page
July 10, 2002 Mr. J. A. Price Site Vice President - Millstone Dominion Nuclear Connecticut, Inc.
c/o Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 - ENVIRONMENTAL ASSESSMENT RE: REVISED FINAL SAFETY EVALUATION REPORT LICENSING BASIS FOR THE POST-ACCIDENT OPERATION OF THE SUPPLEMENTARY LEAKAGE COLLECTION AND RELEASE SYSTEM (TAC NO. MB3700)
Dear Mr. Price:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for amendment dated June 6,1998, as supplemented by letters dated April 5, 1999; April 7, April 19, July 31, and September 28, 2000; March 19, June 11, September 21, and December 20, 2001. The proposed amendment would revise the licensing basis for the post-accident operation of the Supplementary Leakage Collection and Release System as described in the Millstone Nuclear Power Station, Unit No. 3, Final Safety Analysis Report.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Victor Nerses, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Environmental Assessment cc w/encl: See next page DISTRIBUTION:
PUBLIC PDI-2 R/F SRichards JClifford TClark VNerses JTappert OGC ACRS CCowgill, RI Accession Number: ML021680068 OFFICE PDI-2/PM PDI-2/LA RLEP/SC OGC PDI-2/SC NAME VNerses TClark AKugler for JTappert SUttal JZimmerman for JClifford DATE 6/18/02 6/18/02 6/20/02 6/27/02 7/10/02 OFFICIAL RECORD COPY
Millstone Nuclear Power Station Unit 3 cc:
Ms. L. M. Cuoco Mr. Evan W. Woollacott Senior Nuclear Counsel Co-Chair Dominion Nuclear Connecticut, Inc. Nuclear Energy Advisory Council Rope Ferry Road 128 Terrys Plain Road Waterford, CT 06385 Simsbury, CT 06070 Edward L. Wilds, Jr., Ph.D. Mr. D. A. Christian Director, Division of Radiation Senior Vice President - Nuclear Operations Department of Environmental Protection and Chief Nuclear Officer 79 Elm Street Innsbrook Technical Center - 2SW Hartford, CT 06106-5127 5000 Dominion Boulevard Waterford, CT 06385 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. C. J. Schwarz 475 Allendale Road Director -Nuclear Station Operations King of Prussia, PA 19406 and Maintenance Dominion Nuclear Connecticut, Inc.
First Selectmen Rope Ferry Road Town of Waterford Waterford, CT 06385 15 Rope Ferry Road Waterford, CT 06385 Senior Resident Inspector Millstone Nuclear Power Station Mr. P. J. Parulis c/o U.S. Nuclear Regulatory Commission Manager - Nuclear Oversight P. O. Box 513 Dominion Nuclear Connecticut, Inc. Niantic, CT 06357 Rope Ferry Road Waterford, CT 06385 Mr. G. D. Hicks Director - Nuclear Station Safety Mr. W. R. Matthews and Licensing Vice President and Senior Dominion Nuclear Connecticut, Inc.
Nuclear Executive - Millstone Rope Ferry Road Dominion Nuclear Connecticut, Inc. Waterford, CT 06385 Rope Ferry Road Waterford, CT 06385 Mr. J. Alan Price Site Vice President - Millstone Ernest C. Hadley, Esquire c/o Mr. David A. Smith P.O. Box 1104 Dominion Nuclear Connecticut, Inc.
West Falmouth, MA 02574-1104 Rope Ferry Road Waterford, CT 06385 Mr. John Markowicz Co-Chair Nuclear Energy Advisory Council 9 Susan Terrace Waterford, CT 06385
Millstone Nuclear Power Station Unit 3 cc:
Mr. D. A. Smith Manager - Licensing Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056 Mr. S. E. Scace Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. M. J. Wilson Manager - Nuclear Training Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Title 10 of the Code of Federal Regulations (10 CFR) Part 50 for Facility Operating License No. NPF-49 issued to Dominion Nuclear Connecticut, Inc. (the licensee), for operation of the Millstone Nuclear Power Station, Unit No. 3 (MP3), located in Waterford, Connecticut. Therefore, as required by 10 CFR 51.21, the NRC is issuing this environmental assessment and finding of no significant impact.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed action would revise the Final Safety Analysis Report (FSAR) description of the Supplementary Leakage Collection and Release System (SLCRS) operation after a postulated accident. As a result, this revision modifies the licensing basis for the post-accident operation of the SLCRS.
The proposed action is in accordance with the licensees application dated June 6, 1998, as supplemented by letters dated April 5, 1999; April 7, April 19, July 31, and September 28, 2000; March 19, June 11, September 21, and December 20, 2001.
The Need for the Proposed Action:
The proposed action is necessary because the SLCRS is used to maintain a negative pressure relative to atmospheric in the secondary containment by collecting air from the enclosure building and connecting areas, filtering it to remove iodine, and discharging the filtered air to the atmosphere. The licensee has identified potential release pathways from secondary containment to the environment that could bypass the SLCRS filter following a design-basis accident due to non-nuclear safety-grade (NNS) exhaust fan operation after the accident. These additional pathways are not included in the current design-basis accident dose analyses as documented in the MP3 FSAR, therefore making them non-conservative. The proposed action would include the additional pathway in the current design-basis accident dose analyses.
Environmental Impacts of the Proposed Action:
The NRC has completed its evaluation of the proposed action and concludes that issuance of the proposed amendment would not have a significant environmental impact. The proposed changes to the FSAR provide documentation of a combination of events not previously included in the FSAR. Based on the licensees use of acceptable methodologies and assumptions, and staff confirmation of the licensees dose results, the staff has determined that the licensees revised design-basis accident radiological consequences analyses for the Loss of Coolant Accident (LOCA) and rod ejection accident, which take into account additional SLCRS bypass release pathways, are acceptable. The analyses show that the radiological consequences of a postulated design-basis LOCA are within 10 CFR Part 100 dose limits for offsite doses and 10 CFR Part 50, Appendix A, General Design Criterion 19, dose limits with regard to control room habitability.
The proposed action will not significantly increase the probability or consequences of accidents, no changes are being made in the types of effluents that may be released off site,
and there is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action.
With regard to potential nonradiological impacts, the proposed action does not have a potential to affect any historic sites. It does not affect nonradiological plant effluents and has no other environmental impact. Therefore, there are no significant nonradiological environmental impacts associated with the proposed action.
Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action (i.e., the "no-action" alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar.
Alternative Use of Resources:
The action does not involve the use of any different resource than those previously considered in the Final Environmental Statement for MP3, dated December 1984.
Agencies and Persons Consulted:
On June 12, 2002, the staff consulted with the Connecticut State official, Mr. Michael Firsick of the Connecticut Department of Environmental Protection, regarding the environmental impact of the proposed action. The State official had no comments.
FINDING OF NO SIGNIFICANT IMPACT On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action, see the licensees letter dated June 6, 1998, as supplemented by letters dated April 5, 1999; April 7, April 19, July 31, and September 28, 2000; March 19, June 11, September 21, and December 20, 2001. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 10th day of July 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Victor Nerses, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation