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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
MONTHYEARIR 05000443/20240032024-10-30030 October 2024 Integrated Inspection Report 05000443/2024003 ML24303A0352024-10-29029 October 2024 Operator Licensing Examination Approval IR 05000443/20244022024-10-17017 October 2024 Material Control and Accounting Program Inspection Report 05000443/2024402 (Cover Letter Only) L-2024-159, Core Operating Limits Report for Reload Cycle 242024-10-15015 October 2024 Core Operating Limits Report for Reload Cycle 24 ML24254A2552024-09-25025 September 2024 Alternative Request No. 4A-01 for the Fourth 10-Year Inservice Inspection Interval L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24239A5382024-09-20020 September 2024 Issuance of Amendment No. 175 One-Time Allowable Outage Time Extension to the Technical Specification 3.8.1.1, A.C. Sources – Operating, Limiting Condition for Operation L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000443/20240052024-08-29029 August 2024 Updated Inspection Plan for Seabrook Station (Report 05000443/2024005) ML24232A1142024-08-21021 August 2024 Correction to Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024 Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024 Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent . IR 05000443/20240022024-08-0606 August 2024 Integrated Inspection Report 05000443/2024002 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2024001 L-2024-127, Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent2024-08-0505 August 2024 Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024 Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite. ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-05-30030 May 2024 Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld IR 05000443/20240102024-05-29029 May 2024 Biennial Problem Identification and Resolution Inspection Report 05000443/2024010 IR 05000443/20240112024-05-24024 May 2024 Age-Related Degradation Inspection Report 05000443/2024011 IR 05000443/20240012024-05-13013 May 2024 Integrated Inspection Report 05000443/2024001 L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut2024-05-10010 May 2024 NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distributio ML24046A0512024-05-0707 May 2024 Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-078, 2023 Annual Radioactive Effluent Release Report2024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report L-2024-077, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report IR 05000443/20245012024-04-22022 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000443/2024501 L-2024-058, Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources2024-04-19019 April 2024 Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources SBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024 2023 Annual Environmental Operating Report L-2024-011, 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 Applications2024-03-13013 March 2024 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 ML24067A2622024-03-0808 March 2024 Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances) L-2024-038, to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0808 March 2024 to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-037, to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0606 March 2024 to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-035, Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0505 March 2024 Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source ML24065A2522024-03-0505 March 2024 Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033) L-2024-032, Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0404 March 2024 Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-033, Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B2024-03-0404 March 2024 Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B L-2024-019, Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-02-28028 February 2024 Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld IR 05000443/20230062024-02-28028 February 2024 Annual Assessment Letter for Seabrook Station (Report 05000443/2023006) L-2024-016, Radiological Emergency Plan (Ssrep), Revision 822024-02-13013 February 2024 Radiological Emergency Plan (Ssrep), Revision 82 IR 05000443/20230042024-02-12012 February 2024 Integrated Inspection Report 05000443/2023004 ML24009A1152024-01-29029 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 2024-09-25
[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