ML020360098
| ML020360098 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/11/2002 |
| From: | Milano P NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Nuclear Operations |
| Milano, P , NRR/DLPM, 415-1457 | |
| References | |
| TAC MB2420 | |
| Download: ML020360098 (9) | |
Text
February 11, 2002 Mr. Michael Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT FOR A PROPOSED EXEMPTION FROM THE REQUIREMENTS OF 10 CFR 50.60(a)
Dear Mr. Kansler:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to an application by the Consolidated Edison Company of New York, Inc. (Con Edison),
the former licensee of Indian Point Nuclear Generating Unit No. 2, for an exemption dated July 16, 2001. On September 6, 2001, Con Edisons interests in the license was transferred to Entergy Nuclear Operations, Inc. (ENO). By letter dated September 20, 2001, ENO requested that the U.S. Nuclear Regulatory Commission (NRC) continue to review and act on all requests before the Commission which had been submitted before the transfer. Accordingly, the NRC staff has acted upon the request. The exemption request of July 16, 2001, was supplemented by ENO on January 11, 2002. The proposed exemption would provide an exemption from the requirements of 10 CFR 50.60(a). The exemption would permit the use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI Code Case N-640, Alternative Requirement Fracture Toughness for Development of P-T
[Pressure and Temperature] Limit Curves for ASME Section XI Division I, and ASME Code Section XI, Code Case N-588, Alternative to Reference Flaw Orientation of Appendix G for Circumferential Welds in Reactor Vessels,Section XI, Division I, in lieu of 10 CFR Part 50 Appendix G, paragraph I.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosure:
Environmental Assessment cc w/encl: See next page Mr. Michael Kansler
Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT FOR A PROPOSED EXEMPTION FROM THE REQUIREMENTS OF 10 CFR 50.60(a)
Dear Mr. Kansler:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to an application by the Consolidated Edison Company of New York, Inc. (Con Edison),
the former licensee of Indian Point Nuclear Generating Unit No. 2, for an exemption dated July 16, 2001. On September 6, 2001, Con Edisons interests in the license was transferred to Entergy Nuclear Operations, Inc. (ENO). By letter dated September 20, 2001, ENO requested that the U.S. Nuclear Regulatory Commission (NRC) continue to review and act on all requests before the Commission which had been submitted before the transfer. Accordingly, the NRC staff has acted upon the request. The exemption request of July 16, 2001, was supplemented by ENO on January 11, 2002. The proposed exemption would provide an exemption from the requirements of 10 CFR 50.60(a). The exemption would permit the use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI Code Case N-640, Alternative Requirement Fracture Toughness for Development of P-T
[Pressure and Temperature] Limit Curves for ASME Section XI Division I, and ASME Code Section XI, Code Case N-588, Alternative to Reference Flaw Orientation of Appendix G for Circumferential Welds in Reactor Vessels,Section XI, Division I, in lieu of 10 CFR Part 50 Appendix G, paragraph I.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosure:
Environmental Assessment cc w/encl: See next page DISTRIBUTION:
PUBLIC J. Munday B. Elliott, W. Beckner PDI R/F S. Little ASC\EMCB OGC G. Vissing M. Mitchell ACRS P. Milano C. Grimes B. Platchek, RI Accession Number: ML020360098 *See previous concurrence OFFICE PDI-1\PM PDI-1\LA PDI-1\PM DRIP/RLEP* OGC* PDI-1\ASC NAME GVissing SLittle PMilano CGrimes RHoefling JMunday DATE 02/11/02 02/11/02 02/11/02 02/06/02 02/11/02 02/11/02 OFFICIAL RECORD COPY
Indian Point Nuclear Generating Station Unit 2 Mr. Jerry Yelverton Ms. Charlene Fiason Chief Executive Officer Manager, Licensing Entergy Operations Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. Fred Dacimo Mr. John McCann Vice President - Operations Manager, Nuclear Safety and Licensing Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating Unit 2 Indian Point Nuclear Generating Units 1 & 2 295 Broadway, Suite 1 295 Broadway, Suite 1 P. O. Box 249 P.O. Box 249 Buchanan, NY 10511-0249 Buchanan, NY 10511-0249 Mr. Harry P. Salmon, Jr.
Mr. Robert J. Barrett Director of Oversight Vice President - Operations Entergy Nuclear Operations, Inc.
Entergy Nuclear Operations, Inc. 440 Hamilton Avenue Indian Point Nuclear Generating Units 3 White Plains, NY 10601 295 Broadway, Suite 3 P.O. Box 308 Mr. John M. Fulton Buchanan, NY 10511-0308 Assistant General Counsel Entergy Nuclear Operations, Inc.
Mr. Dan Pace 440 Hamilton Avenue Vice President Engineering White Plains, NY 10601 Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Mr. Thomas Walsh White Plains, NY 10601 Secretary - NFSC Entergy Nuclear Operations, Inc.
Mr. James Knubel Indian Point Nuclear Generating Unit 2 Vice President Operations Support 295 Broadway, Suite 1 Entergy Nuclear Operations, Inc. P. O. Box 249 440 Hamilton Avenue Buchanan, NY 10511-0249 White Plains, NY 10601 Regional Administrator, Region I Mr. Lawrence G. Temple U.S. Nuclear Regulatory Commission General Manager Operations 475 Allendale Road Entergy Nuclear Operations, Inc. King of Prussia, PA 19406 Indian Point Nuclear Generating Unit 2 295 Broadway, Suite 1 Senior Resident Inspector, Indian Point 2 P.O. Box 249 U. S. Nuclear Regulatory Commission Buchanan, NY 10511-0249 295 Broadway, Suite 1 P.O. Box 38 Mr. John Kelly Buchanan, NY 10511-0038 Director of Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
Indian Point Nuclear Generating Station Unit 2 Mr. William M. Flynn, President David Lochbaum New York State Energy, Research, and Nuclear Safety Engineer Development Authority Union of Concerned Scientists Corporate Plaza West 1707 H Street, NW., Suite 600 286 Washington Avenue Extension Washington, DC 20006 Albany, NY 12203-6399 Fred Zalcman Mr. J. Spath, Program Director Pace University School of Law New York State Energy, Research, and The Energy Project Development Authority 78 North Broadway Corporate Plaza West White Plains, NY 10603 286 Washington Avenue Extension Albany, NY 12203-6399 Michael Mariotte Nuclear Information & Resources Service Mr. Paul Eddy 1424 16th Street, NW, Suite 404 Electric Division Washington, DC 20036 New York State Department of Public Service Deborah Katz 3 Empire State Plaza, 10th Floor Executive Director Albany, NY 12223 Citizens Awareness Network P.O. Box 83 Mr. Charles Donaldson, Esquire Shelburne Falls, MA 01370 Assistant Attorney General New York Department of Law Marilyn Elie 120 Broadway Organizer New York, NY 10271 Citizens Awareness Network 2A Adrain Court Mayor, Village of Buchanan Cortlandt Manor, NY 10567 236 Tate Avenue Buchanan, NY 10511 Tim Judson Organizer Mr. Ray Albanese Citizens Awareness Network Executive Chair 140 Bassett Street Four County Nuclear Safety Committee Syracuse, NY 13213 Westchester County Fire Training Center 4 Dana Road Anne Reynolds Valhalla, NY 10592 Environmental Advocates 353 Hamilton Street Ms. Stacey Lousteau Albany, NY 12210 Treasury Department Entergy Services, Inc. Mark Jacobs 639 Loyola Avenue Executive Director Mail Stop: L-ENT-15E Westchester Peoples Action Coalition New Orleans, LA 70113 255 Dr. M.L. King Jr. Boulevard White Plains, NY 10601
Indian Point Nuclear Generating Station Unit 2 Paul Gunter Nuclear Information & Resource Service 1424 16th Street, NW, #404 Washington, DC 20036 Alex Matthiessen Executive Director Riverkeeper, Inc.
25 Wing & Wing Garrison, NY 10524 Paul Leventhal The Nuclear Control Institute 1000 Connecticut Avenue NW Suite 410 Washington, DC, 20036 Karl Copeland Pace Environmental Litigation Clinic 78 No. Broadway White Plains, NY 10603 Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 50.60(a) for Facility Operating License No. DPR-26, issued to Entergy Nuclear Operations, Inc., (ENO or the licensee), for operation of the Indian Point Nuclear Generating Unit No. 2 (IP2), located in Westchester County, New York. 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 provide an exemption from the requirements of 10 CFR 50.60(a). The exemption would permit the use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Code Case N-640, Alternative Requirement Fracture Toughness for Development of P-T [Pressure and Temperature] Limit Curves for ASME Section XI Division I, and ASME Code Section XI Code Case N-588, Alternative to Reference Flaw Orientation of Appendix G for Circumferential Welds in Reactor Vessels,Section XI, Division I, in lieu of 10 CFR Part 50, Appendix G, paragraph I.
The proposed action is in accordance with the Consolidated Edison Company of New York, Inc. (Con Edison), the former licensee of IP2, request for an exemption dated
July 16, 2001. On September 6, 2001, Con Edisons interests in the license was transferred to Entergy Nuclear Operations, Inc. (ENO). By letter dated September 20, 2001, ENO requested that the NRC continue to review and act on all requests before the Commission which had been submitted before the transfer. Accordingly, the NRC staff has acted upon Con Edisons application dated July 16, 2001, as supplemented by an ENO letter dated January 11, 2002.
The Need for the Proposed Action:
The proposed action provides relief from unnecessary restriction of the P-T operating window defined by the P-T operating and test curves developed in accordance with ASME Code,Section XI, Appendix G procedure. ASME Code,Section XI, Appendix G procedure was conservatively developed based on the level of knowledge existing in 1974 concerning reactor pressure vessel materials and the estimated effects of operation. Since 1974, the level of knowledge about these topics has been greatly expanded. This increased knowledge permits relaxation of the ASME Code,Section XI, Appendix G, requirements via application of ASME Code Case N-640 while maintaining the underlying purpose of the ASME Code,Section XI, Appendix G procedure. The restriction of the P-T operating and test curves developed in accordance with ASME Code,Section XI, Appendix G procedure would challenge the operations staff when operating at lower temperatures.
Continued operation with P-T curves developed in accordance with the ASME Code,Section XI without relief would unnecessarily restrict the P-T operating window for IP2. This would constitute an unnecessary burden that can be alleviated by the application of ASME Code Case N-588 in the development of the proposed P-T curves. Implementation of the proposed P-T curves as allowed by ASME Code Case N-588 would not reduce the margin of safety originally contemplated by either the NRC or ASME.
Environmental Impacts of the Proposed Action:
The NRC has completed its evaluation of the proposed action and concludes as set forth below, there are no significant environmental impacts associated with the use of the alternative analysis methods to support the revision of the P-T curves.
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 the Indian Point Nuclear Generating Unit No. 3, dated September 1972.
Agencies and Persons Consulted:
On January 31, 2002, the staff consulted with the New York State official, Ms. Alyse Peterson of the New York State Research and Development Authority, 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 July 16, 2001, as supplemented by letter dated January 11, 2002. 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.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 11th day of February 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Joel T. Munday, Acting Chief, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation