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Category:FACT Sheet
MONTHYEARML14076A0332014-03-13013 March 2014 NRC Response Letter to Don Tilbury Regarding Remarks at the December 18, 2013 Public Meeting for Seabrook Station (W/Enclosures) 2014-03-13
[Table view] Category:Letter
MONTHYEARL-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 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review 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 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 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-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024 Preparation and Scheduling of Operator Licensing Examinations 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 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 ML24065A2892024-02-28028 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 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 2024-08-06
[Table view] Category:Status Report
MONTHYEARIR 05000443/20230062024-02-28028 February 2024 Annual Assessment Letter for Seabrook Station (Report 05000443/2023006) L-2019-046, Stations - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2019-03-25025 March 2019 Stations - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2017-040, Decommissioning Funding Status Reports/Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2017-03-30030 March 2017 Decommissioning Funding Status Reports/Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2016-146, Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2016-07-26026 July 2016 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications SBK-L-16011, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-02-11011 February 2016 Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML15356A1022015-12-15015 December 2015 Final Compliance in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) SBK-L-15138, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-08-27027 August 2015 Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) SBK-L-15026, NextEra Energy Seabrook, Llc'S Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-02-27027 February 2015 NextEra Energy Seabrook, Llc'S Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) SBK-L-15025, NextEra Energy Seabrook, Llc'S Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12015-02-27027 February 2015 NextEra Energy Seabrook, Llc'S Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-0 SBK-L-14154, Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No EA- 12-05 1)2014-08-26026 August 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No EA- 12-05 1) ML14076A0332014-03-13013 March 2014 NRC Response Letter to Don Tilbury Regarding Remarks at the December 18, 2013 Public Meeting for Seabrook Station (W/Enclosures) SBK-L-14042, Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-02-27027 February 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) SBK-L-14041, Second Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-02-27027 February 2014 Second Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) SBK-L-13158, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation L-2013-103, Decommissioning Funding Status Reports2013-03-25025 March 2013 Decommissioning Funding Status Reports L-2009-055, Units 1 and 2, Decommissioning Funding Status Reports2009-03-27027 March 2009 Units 1 and 2, Decommissioning Funding Status Reports ML0613202062006-02-15015 February 2006 E-mail from D. Croulet of Entergy to Various, Regarding Monitoring Well Status - February 15, 2006-0600 SBK-L-05038, Decommissioning Funding Status Report2005-03-25025 March 2005 Decommissioning Funding Status Report ML0224007812002-01-18018 January 2002 E-mail from Jacob Zimmerman, Bulletin 2001-01 Status Report 2024-02-28
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 March 13, 2014 Mr. Don Tilbury 15 Bride Hill Drive Hampton, NH 03842
Dear Mr. Tilbury:
I am responding to questions you raised in your letter dated December 23, 2013, following the December 18 meeting in Hampton, New Hampshire held to discuss the concrete degradation experienced at Seabrook Station due to an Alkali-Silica Reaction (ASR) between the cement and the stone aggregate. Due to the number and range of concerns provided, I am addressing them in an enclosure to this letter. I have also provided documents from our Office of Public Affairs as well as other sources that directly related to your concerns.
I trust this is responsive to the concerns you raised. If you have additional questions or concerns about Seabrook Station, please do not hesitate to contact Richard Barkley of my staff at (610) 337-5328.
Sincerely,
/RA/
Glenn T. Dentel, Chief Reactor Projects Branch 3 Division of Reactor Projects
Enclosures:
- 1) Response to Questions Provided by Mr. Tilbury
- 2) Fact Sheets on Emergency Preparedness, License Renewal, and Dry Cask Storage and Waste Confidence
- 3) Decommissioning Funding Status Report for FP&L and NextEra
ML14076A033 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRP RI/DRS RI/ORA RI/DRP MGray/MG via DScrenci/DS via NAME mmt RBarkley/RSB GDentel/GTD phone/email phone/email DATE 03/07/14 03/12/14 03/12/14 03/13/14 Response to Concerns Raised by Don Tilbury
- 1) Seabrooks Plant Life Extension Request
Response
10 CFR 54.17 allows a power plant licensee to file for a renewed licensee up to 20 years in advance of the expiration of the current operating license. The NRC has determined that 20 years of operating experience is sufficient to assess aging and environmental issues at the site. Additionally, this affords the licensee the opportunity to perform long-term planning regarding the retirement and replacement of large power generation facilities. A major consideration for seeking license renewal so far in advance of the expiration date of the current license is that it takes about 10 years to design and construct major new generating facilities, and long lead times are also required by energy planning decision-makers. In addition, a request for license renewal for two or more units on the same site that entered service as much as a decade apart can be made as one consolidated application.
The NRC staffs safety review of the Seabrook license renewal application is ongoing and no regulatory decision has been made on the application. The original safety review schedule was revised, in part, to address the staffs concerns associated with the applicants proposed plant-specific ASR monitoring program and to add a second meeting with the Advisory Committee on Reactor Safeguards, plant license renewal subcommittee. The NRC will ensure that the ASR monitoring program includes methods and/or techniques to adequately monitor the performance or condition of the affected structures in a manner that provides reasonable assurance that the ASR aging effects will be adequately managed before making a license renewal decision.
The NRC continues its efforts to better understand the impact of ASR on reinforced safety-related concrete structures at Seabrook Station. Our inspections and assessments to date have determined the ASR-affected structures at Seabrook remain capable of performing their intended safety function with margin from additional design and construction. Long-term resolution of this issue will require a thorough understanding of the effects of ASR and additional testing, monitoring and potential compensatory actions by NextEra. The NRC will continue to carefully assess NextEras actions to resolve this issue under their current operating license and conduct inspections at Seabrook Station to ensure corrective actions are effective.
- 2) ASR in the Concrete of Reactor Foundations and Other Buildings at Seabrook
Response
As noted during the meeting on December 18, 2013, NextEra staff and the NRC continue to review the impacts of ASR identified in various concrete buildings at Seabrook Station. Concrete is a composite of cement, aggregate (e.g., crushed rock and sand), water and, in some cases, small amounts of admixtures. For the reaction to take place in concrete, there must be a high alkali in the cement, reactive silica in the aggregate, and for ASR to proceed in cured concrete, it must also have sufficient water present. In an effort to reduce the amount of water impacting on the structures in question, Seabrook has undertaken several actions to dewater key areas of concern.
NextEra has also taken actions to help ensure the water in contact with the concrete contains less salt and other chemicals that can accelerate ASR by terminating the use Enclosure 1
2 of chemical deicers near the facility. The source of the water intrusion on the structures of concern at Seabrook is not salt water from the tidal estuary nearby, but rather fresh water from the prevailing water table inland. The facility itself rests on bedrock.
As discussed at the December 18 meeting, our staff will continue to review NextEras monitoring and analysis of the ASR at Seabrook Station. The NRC staff is also following NextERAs large-specimen testing program underway at the University of Texas Ferguson Structural Engineering Laboratory. Should NextEra elect to use the results of this test program to resolve the ASR non-conforming condition, the testing methodology and results will be subject to NRC review pursuant to the applicable regulatory processes described in 10 CFR 50.59 and/or 50.90. If NextEra decides to use another approach, the NRC will likewise implement these regulatory review processes.
As stated at the December 18 meeting, the safety-related concrete structures at Seabrook continue to remain operable and capable of performing their design function even with the ASR degradation noted to date.
As documented in NRC Inspection Reports 05000443/2012009 (in the agencys document management system ADAMS at Accession No. ML12338A283) and 05000443/2012010 (ML13221A172), the NRC summarized extensive reviews and hundreds of hours of detailed inspections, meetings and internal deliberations to understand and ensure a clear engineering and safety basis had been established by NextEra for the current structures operability determination. These operability determinations are based upon detailed structural evaluations that are independent of the large scale specimen testing being conducted by NextEra. The NRC plans to periodically inspect NextEras ASR monitoring program and testing activities at FSEL.
NextEra is obligated, consistent with their existing license, to maintain reasonable assurance of operability of Seabrook Station ASR-affected structures.
- 3) Nuclear Power Plant Waste
Response
As you noted, at this time there is no permanent disposal site for spent nuclear fuel.
In the interim, the Waste Confidence rule codifies the Commission's generic deter-mination of the environmental impacts associated with the storage of spent fuel during and after the end of a reactor's licensed life for operation. This generic analysis is found in 10 CFR 51.23. The Waste Confidence Rule is currently undergoing revision in light of a court ruling in 2012, but the draft Environmental Impact Statement (EIS) describes the environmental impacts of continuing to store spent nuclear fuel during and beyond the licensed life for operation of a reactor, and is the regulatory basis for the proposed rule.
As for dry cask storage, the NRC developed cask licensing requirements through a public process to provide a sound basis for ensuring protection of public health and safety and the environment. NRC staff conducts thorough reviews and only approves designs that meet those requirements. The NRC periodically inspects the design, manufacturing and use of dry casks. These inspections ensure licensees and vendors are following safety and security requirements and meeting the terms of their licenses and quality assurance programs. NRC inspectors also observe practice runs before licensees begin moving their spent fuel into dry casks.
Enclosure 1
3 Since the first casks were loaded in 1986, dry storage has released no radiation that affected the public or contaminated the environment. Tests on spent fuel and cask components after years in dry storage confirm that the systems are providing safe and secure storage. NRC also analyzed the risks from loading and storing spent fuel in dry casks. That study found the potential health risks are very small. Spent fuel is currently in dry storage at more than 65 sites around the country. Further information regarding spent fuel storage and dry casks is provided in the attached fact sheets.
- 4) Emergency Planning/Evacuation
Response
In accordance to the NRC Code of Federal Regulations, 10 CFR 50.54(q), all licensees must maintain an Emergency Plan. Those plans must be approved by the NRC prior to the issuance of an operating license. The Federal Emergency Management Agency (FEMA) is the lead authority for reviewing and approving all offsite State emergency plans, including the states evacuation plans.
All nuclear power plants conduct a variety of exercises and drills on a recurring basis, including a required full-scale participation emergency exercise on a biennial basis. These biennial exercises test the capability of both the onsite and offsite emergency response organizations to ensure adequate emergency response actions will be taken to adequately protect the safety of the public. The NRC evaluates the onsite portion of these exercises and FEMA evaluates the offsite portion. If you would like to view the FEMA exercise reports from previous Seabrook exercises, they can be found on the following public website: http://www.nrc.gov/about-nrc/emerg-preparedness/related-information/fema-after-action-reports.html. These reports will provide you a good description of the numerous of activities that are conducted and evaluated during these exercises for testing the approved emergency plans.
- 5) Seabrook Decommissioning Funding Payments
Response
The NRCs focus is to ensure that licensees provide reasonable assurance that sufficient funds will be accumulated for decommissioning to NRC standards regardless of whether a license renewal is granted. Whether or not a renewal is granted, the licensee is required to demonstrate that there is adequate funding for decommissioning. The NRC regulates radiological decontamination as defined in 10 CFR 50.2. As explained in the regulations in 10 CFR 50.75, the table of minimum amounts focuses on the minimum amount of money a licensee is required to accumulate for radiological decommissioning.
As long as a licensee is providing reasonable assurance that sufficient funds will be accumulated for decommissioning to NRC standards, the licensee is complying with NRC regulations.
The table of minimum amounts (sometimes referred to as the Decommissioning Funding Amount, or DFA) assumes that there is an increase in decommissioning expenses and decommissioning funds over time. Therefore full payment of all costs into the decommissioning fund in advance of decommissioning is not required. So as long as the licensee meets the DFA formula amount, the NRC considers the licensee to be in compliance with our regulations.
Enclosure 1
4 As of the end of 2012, approximately $460 million has already been set aside in decommissioning funds for Seabrook Station. NRC received this information as part of the biennial decommissioning report review and found reasonable assurance that adequate decommissioning funds exist; a copy of that report is attached. The NRCs decommissioning funding requirements are separate and independent of any state Public Utility Commission (PUC) requirements or the oversight of state boards, such as the NH Nuclear Decommissioning Financing Committee.
- 6) The If Factor - Reactor Safety Post-Fukushima
Response
The NRC has taken significant action to enhance the safety of reactors in the United States based on the lessons learned from earthquake and tsunami that extensively damaged four nuclear power reactors at the Fukushima Dai-ichi facility. I urge you to visit the NRCs webpage at: http://www.nrc.gov/reactors/operating/ops-experience/japan-dashboard.html This page is intended to serve as a navigation hub to follow the NRC's progress in implementing the many different lessons-learned activities in response to this event.
Enclosure 1