|
---|
Category:Environmental Assessment
MONTHYEARML21062A1472021-04-21021 April 2021 Final Environmental Assessment and Finding of No Significant Impact of 2012 and 2015 Decommissioning Funding Plans for Seabrook Station Unit 1 Independent Spent Fuel Storage Installation SBK-L-10039, Request for Exemption from Specific 10 CFR 73 Requirements, Physical Protection of Plants and Materials.2010-02-25025 February 2010 Request for Exemption from Specific 10 CFR 73 Requirements, Physical Protection of Plants and Materials. ML0529204492005-12-0606 December 2005 Environmental Assessment ML0429300082004-12-0808 December 2004 Environmental Assessment and Finding of No Significant Impact - Power Uprate Modification ML0316405792003-07-21021 July 2003 Environmental Assessment Exemption Request ML0205105942002-03-27027 March 2002 Environmental Assessment Related to Administrative Technical Specification Amendment (Tac No. MB2852) 2021-04-21
[Table view] Category:Finding of No Significant Impact
MONTHYEARML0429300082004-12-0808 December 2004 Environmental Assessment and Finding of No Significant Impact - Power Uprate Modification ML0316405792003-07-21021 July 2003 Environmental Assessment Exemption Request 2004-12-08
[Table view] Category:Letter
MONTHYEARML24009A1152024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24022A0652024-01-22022 January 2024 Senior Reactor and Reactor Operator Initial License Examinations L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024 NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023 Submittal of Changes to the Technical Specification Bases L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-160, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule ML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 IR 05000443/20234032023-11-0707 November 2023 Security Baseline Inspection Report 05000443/2023403 and Independent Spent Fuel Storage Installation 07200063/2023401 IR 05000443/20230032023-11-0606 November 2023 Integrated Inspection Report 05000443/2023003 IR 05000443/20230102023-10-19019 October 2023 Triennial Fire Protection Inspection Report 05000443/2023010 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A0522023-10-0202 October 2023 Requalification Program Inspection IR 05000443/20234012023-09-0808 September 2023 Cybersecurity Inspection Report 05000443/2023401 (Cover Letter Only) IR 05000443/20234202023-09-0505 September 2023 Security Baseline Inspection Report 05000443/2023420 IR 05000443/20230052023-08-31031 August 2023 Updated Inspection Plan for Seabrook Station (Report 05000443/2023005) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000443/20233022023-08-16016 August 2023 Operator Licensing Retake Examination Report 05000443/2023302 IR 05000443/20230022023-08-0808 August 2023 Integrated Inspection Report 05000443/2023002 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-104, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report ML23192A0782023-07-11011 July 2023 Operator Licensing Retake Examination Approval L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) SBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 ML23157A0722023-06-0606 June 2023 Notification of Conduct of a Fire Protection Team Inspection L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000443/20233012023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000443/2023301 L-2023-064, License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-05-11011 May 2023 License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves IR 05000443/20230012023-05-11011 May 2023 Integrated Inspection Report 05000443/2023001 ML23129A0312023-05-0909 May 2023 Reactor Operator Retake License Examination ML23117A3652023-05-0404 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from PTL and Low Temperature Over Pressure Protection Curves SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report L-2023-053, Core Operating Limits Report for Cycle 232023-04-0505 April 2023 Core Operating Limits Report for Cycle 23 ML23088A1522023-03-29029 March 2023 Summary of Meeting Between Nrc/Region I and C-10 - Questions Regarding Seabrook 4Q2022 Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML23073A1562023-03-23023 March 2023 Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code L-2023-012, License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-03-15015 March 2023 License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023 Revised Steam Generator Tube Inspection Report ML23020A1002023-03-0303 March 2023 OEDO-22-00419 - 2.206 Petition for Seabrook Station Structure Concrete Concerns (EPID L-2022-CRS-0000)- Closure Letter 2024-01-29
[Table view] |
Text
July 21, 2003 Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station PO Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - ENVIRONMENTAL ASSESSMENT RE: EXEMPTION REQUEST (TAC NO. MB6699)
Dear Mr. Warner:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application and exemption request dated October 11, 2002. The proposed exemption is from the requirements of Title 10 of the Code of Federal Regulations Part 50, Section 50.60(a) and Appendix G, and would allow the use of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Code Case N-641 as the basis for revised reactor vessel pressure and temperature limit curves.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Environmental Assessment cc w/encl: See next page
ML031640579
- See Previous Concurrence OFFICE PDI-2/PM PDI-2/PM PDI-2/LA EMCB/SC* RLEP/SC* OGC PDI-2/SC NAME GMiller VNerses CRaynor SCoffin REmch for JTappert SCole JClifford DATE 7/1/03 7/2/03 7/1/03 6/20/03 6/30/03 7/9/03 7/21/03 Seabrook Station, Unit No. 1 cc:
Mr. J. A. Stall Mr. Jack Devine Senior Vice President, Nuclear and Polestar Applied Technology Chief Nuclear Officer One First Street, Suite 4 Florida Power & Light Company Los Altos, CA 94019 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Stephen McGrail, Director ATTN: James Muckerheide Mr. Peter Brann Massachusetts Emergency Management Agency Assistant Attorney General 400 Worcester Road State House, Station #6 Framingham, MA 01702-5399 Augusta, ME 04333 Philip T. McLaughlin, Attorney General Resident Inspector Steven M. Houran, Deputy Attorney U.S. Nuclear Regulatory Commission General Seabrook Nuclear Power Station 33 Capitol Street P.O. Box 1149 Concord, NH 03301 Seabrook, NH 03874 Mr. Donald Bliss, Director Town of Exeter New Hampshire Office of Emergency 10 Front Street Management Exeter, NH 03823 State Office Park South 107 Pleasant Street Regional Administrator, Region I Concord, NH 03301 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. Daniel G. Roy King of Prussia, PA 19406 Nuclear Training Manager Seabrook Station Office of the Attorney General FPL Energy Seabrook, LLC One Ashburton Place, 20th Floor P.O. Box 300 Boston, MA 02108 Seabrook, NH 03874 Board of Selectmen Mr. Gene F. St. Pierre Town of Amesbury Station Director Town Hall Seabrook Station Amesbury, MA 01913 FPL Energy Seabrook, LLC P.O. Box 300 Mr. Dan McElhinney Seabrook, NH 03874 Federal Emergency Management Agency Region I Mr. M. S. Ross, Attorney J.W. McCormack P.O. & Florida Power & Light Company Courthouse Building, Room 401 P.O. Box 14000 Boston, MA 02109 Juno Beach, FL 33408-0420
Seabrook Station, Unit No. 1 cc:
Mr. Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION FPL ENERGY SEABROOK, LLC, ET AL.
DOCKET NO. 50-443 SEABROOK STATION ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC or the Commission) is considering issuance of an exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.60, Acceptance criteria for fracture prevention measures for light-water nuclear power reactors for normal operation, and 10 CFR Part 50, Appendix G, Fracture Toughness Requirements, for Facility Operating License No. NPF-86, issued to FPL Energy Seabrook, LLC, et al. (the licensee), for operation of the Seabrook Power Station, located in Seabrook, New Hampshire. 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 exempt the licensee from the requirements of 10 CFR Part 50, Section 50.60(a) and Appendix G, and allow the use of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Code Case N-641 in the development of the Seabrook Reactor Pressure Vessel (RPV) Pressure and Temperature (P-T) limits. These limits would be used through 20 effective full-power years of operation.
10 CFR 50.60(a) requires, in part, that except where an exemption is granted by the Commission, all light-water nuclear power reactors must meet the fracture toughness requirements for the reactor coolant pressure boundary set forth in Appendices G and H to 10 CFR Part 50. Appendix G to 10 CFR Part 50 requires that P-T limits be established for RPVs during normal operating and hydrostatic or leak-rate testing conditions. Specifically, 10 CFR Part 50, Appendix G states, The appropriate requirements on both the pressure-temperature limits and the minimum permissible temperature must be met for all conditions.
Additionally, the Appendix specifies that the requirements for these limits are given in the ASME Code,Section XI, Appendix G limits.
ASME Code Case N-641 permits the use of alternate reference fracture toughness curves (i.e., use of the KIC fracture toughness curve instead of the KIA fracture toughness curve, as defined in ASME Code,Section XI, Appendices A and G, respectively) for reactor vessel materials in determining the P-T limits for heatup, cooldown, and inservice testing.
The proposed action is in accordance with the licensees application dated October 11, 2002.
The Need for the Proposed Action:
The provisions of ASME Code Case N-641 were incorporated in Appendix G of Section XI of the ASME Code in the 1998 though the 2000 Addenda, which is the edition and addenda of record in the 2003 Edition of 10 CFR Part 50. However, the proposed action is needed to apply Code Case N-641, because the Seabrook licensing basis has only been updated to include the 1995 Edition through the 1996 Addenda of the ASME Code.
Environmental Impacts of the Proposed Action:
The NRC has completed its evaluation of the proposed action and concludes that, as set forth below, there are no significant environmental impacts associated with the use of
ASME Code Case N-641 in developing RPV P-T limits for heatup, cooldown, and inservice testing. The proposed action does not adversely affect the integrity of the reactor vessel or the function of the reactor vessel to act as a radiological barrier during an accident.
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 offsite, 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 non-radiological impacts, the proposed action does not have a potential to affect any historic sites. The proposed action does not affect non-radiological plant effluents and has no other environmental impact. Therefore, there are no significant non-radiological 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 resources than those previously considered in the Final Environmental Statement for the Seabrook Station, Unit No. 1, dated December 1982.
Agencies and Persons Consulted:
On June 4, 2003, the staff consulted with the New Hampshire State Official, Mike Nawoj of the New Hampshire Office of Emergency Management, and with the Massachusetts State
Official, Diane Brown-Couture, of the Massachusetts Emergency Management Agency, regarding the environmental impact of the proposed action. The State Officials 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 October 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/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 21st day of July, 2003.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation