In 2009, NextEra Energy Seabrook, LLC (NextEra) realized that the intrusion of moisture into sections of walls in certain below-grade structures at the Seabrook nuclear power plant, in Seabrook, N.H., could cause the degradation of some of the concrete. The NRC and NextEra confirmed in 2010 that the degradation at Seabrook is caused by alkali silica reaction, or ASR. The result of this reaction is a gel, which can expand and cause micro-cracks in the concrete. Graphics detailing the chemical reaction and the expansive gel can be viewed on slide 9 of the May 10, 2012 presentation "Seabrook Station Safety in Light of the Alkali-Silica Reaction Occurring in Plant Structures."
Subsequently, NextEra identified that the cumulative effect of ASR-induced micro-cracking has led to larger macro-cracking (bulk expansion) and the displacement of some concrete walls.
NextEra has determined that the structures affected by ASR can continue to perform their safety functions—the regulatory term for this is that they are "operable but degraded and nonconforming." The basis for continued operability includes confirmatory engineering design reviews using computer-based finite element analysis and detailed reviews of structural design calculations that demonstrate that sufficient safety margins remain based upon field measurements and/or bounding (worst-case) ASR degradation values. Reinforced concrete structural design margins for Seabrook were established in accordance with American Concrete Institute (ACI) Code 318-1971 and ensure that the as-built (design) structural capacity exceeds any assumed load or specified load combinations. NRC inspectors have reviewed these analyses, design reviews, and design calculations during on-site inspections and have concluded that NextEra has adequately demonstrated that the concrete structures at Seabrook affected by ASR are currently "operable but degraded and nonconforming." For more information on the issue and the status of NRC follow-up and planned activities, see the following topics on this page:
Summary of Event and Plant Conditions
As previously noted, NextEra confirmed the presence of ASR degradation of concrete in below-grade walls of several Category 1 structures in August 2010. Seabrook is the first plant in the U.S. nuclear fleet to exhibit ASR in concrete structures on site. In response, the NRC issued Information Notice (IN) 2011-20, "Concrete Degradation by Alkali Silica Reaction," on November 18, 2011, to provide the industry with information related to the ASR identified at Seabrook.
The NRC staff's review of this issue to date has determined that there are no immediate safety concerns due, in part, to existing safety margins, the localized nature of the ASR, the slow-moving nature of ASR, and ongoing monitoring.
Concrete issues other than ASR have also occurred at other nuclear power plants. Crystal River 3 was shut down due to cracking (e.g., delamination) of the concrete walls in the plant’s containment building. This cracking occurred during work on an opening in the containment in preparation for a steam generator replacement project. In response, Duke Energy, the plant’s owner, announced on February 5, 2013, that it planned to permanently cease operations at the Florida facility. In 2011, the Davis-Besse nuclear power plant discovered cracking in the Ohio plant’s Shield Building wall, a concrete enclosure around containment, while contractors were creating an opening for the replacement of the reactor vessel head. Information related to this issue can be found in NRC Inspection Report IR 05000346/2012007. The concrete degradation mechanisms in these plants are different from the ASR identified at Seabrook.
Confirmatory Action Letter
On May 16, 2012, the NRC staff issued a Confirmatory Action Letter (CAL) to NextEra confirming regulatory commitments made by the licensee to address ASR at Seabrook as a result of a management meeting with NRC staff on April 23, 2012.
On May 24, 2012, NextEra sent NRC a response to the CAL, which included the root cause for the organizational causes associated with the occurrence of ASR at Seabrook and an evaluation entitled, "Impact of ASR on Concrete Structures and Attachments."
On May 1, 2013, NextEra sent NRC a second submittal addressing the remaining CAL items, which included the details of their large-scale testing program and revised integrated corrective action plan.
The NRC conducted inspections to independently review NextEra’s actions to complete their commitments. The NRC documented these results in NRC Inspection Reports (IRs) 05000443/2012009 and 05000443/2012010. Based on its reviews, the NRC issued a closure letter on October 9, 2013, which closed the CAL.
Enhanced Oversight
On July 9, 2012, the NRC issued a "Working Group Charter" to ensure that all aspects of the ASR issue were coordinated among the NRC staff. This charter established the Seabrook ASR Issue Technical Team (SAITT) comprised of staff from the NRC Region I and Headquarters offices. The team coordinates the on-site inspections, in-office technical reviews, and other associated evaluations and assessment activities involving NextEra’s resolution of the ASR issue at Seabrook.
Further, on September 5, 2012, the NRC’s Executive Director for Operations approved a "Deviation Memorandum" that allows the agency to continue to devote additional review resources to the Seabrook ASR issue. Although, the NRC’s Reactor Oversight Process does not prescribe increased oversight for Seabrook based on its overall performance, the NRC staff determined that additional inspections and assessments were appropriate in these circumstances.
Following the completion of the second CAL follow-up inspection report (IR 05000443/2012010) and the mid-cycle performance assessment per IMC 0305, the NRC closed the Deviation Memorandum, as documented in NRC letter, "Mid-Cycle Performance Review," dated September 3, 2013. Since the closure of the deviation memorandum, the NRC has conducted focused inspections with specialist inspectors approximately every six months as part of the Reactor Oversight Process baseline inspection program, the results of which are documented in publicly available inspection reports. The NRC plans to continue these inspections in 2019. The NRC also continues to maintain oversight through the SAITT.
Developments Since Confirmatory Action Letter Closure
Following the closure of the Confirmatory Action Letter on Oct. 9, 2013, the NRC held a public meeting in Hampton, N.H. to discuss the ASR issue in detail, as well as the agency's monitoring efforts going forward. In 2014 and 2015, the NRC staff conducted periodic inspections and audits related to the ASR issue at Seabrook and at the Ferguson Structural Engineering Laboratory (FSEL) at the University of Texas, where a large-scale ASR testing program was being conducted for NextEra.
NextEra's large-scale testing program commenced in late 2013 and was completed in February 2016. Based on testing program developments, in 2015, NextEra revised its structures-monitoring/ASR-monitoring aging management programs to include through-wall expansion monitoring. This expansion is monitored by devices installed in over 40 representative locations in Seabrook structures.
In 2014, the NRC staff documented findings involving discrete, horizontal cracking in an internal wall of the Seabrook Residual Heat Removal (RHR) vault and displacements and cracking associated with the Seabrook Fuel Storage Building. Subsequently, NextEra identified that the cumulative effect of ASR-induced micro-cracking has led to larger macro-cracking (bulk expansion) and the displacement of some concrete walls. In 2015, the staff documented findings that identified global bulk expansion of the Seabrook Containment Enclosure Building. The staff concluded that these findings were of very low safety significance because the safety function of these structures was not affected. Additionally, as part of the license renewal process, the NRC staff requested additional information from NextEra to assess whether the effects of aging involving building deformation and discrete cracks will be adequately managed so that intended functions are maintained consistent with the current licensing basis during the period of extended operation. NextEra's response was received by the NRC on Aug. 9, 2016.
In 2016, the NRC staff documented an unresolved item after staff had identified that further inspection was warranted to review an ongoing issue of concern regarding NextEra’s implementation of the Seabrook Structures Monitoring Program, which monitors on-site structures for any signs of degradation, and NextEra’s structural evaluations of the Seabrook Containment Enclosure Building and the Residual Heat Removal vault. In the inspection for this unresolved item, the NRC staff identified a violation based on two instances in which NextEra did not perform initial and prompt operability determinations for ASR-affected structures until pressed by NRC inspectors. NextEra responded to this violation in early June 2016; NextEra averred that, while the violation occurred, the affected structures in question remained operable. An inspection in the fall of 2016 (IR 2016-004) found that NextEra had taken a number of corrective actions to prevent recurrence and closed this issue.
NextEra had three meetings with NRC staff, on March 29, April 28, and June 15, 2016, to discuss ASR-related issues at Seabrook. Moreover, the NRC staff performed a regulatory audit of NextEra’s license amendment application. This technical audit was performed March 19 – 23, 2018, consistent with NRC Office of Nuclear Reactor Regulation, Office Instruction LIC-111, "Regulatory Audits," dated December 29, 2008.
In 2018, the NRC staff completed a second on-site team inspection in accordance with Inspection Procedure 71002, “License Renewal Inspection,” to review NextEra’s actions to address the effects of ASR in Seabrook reinforced concrete structures. The inspection results support the conclusion that there is reasonable assurance that the effects of aging due to ASR in the Seabrook systems, structures, and components will be managed through implementation of these programs as described in the application for a renewed license.
Licensing
The NRC has completed two licensing actions that are directly associated with ASR at Seabrook: a license renewal application (LRA) to allow operation for an additional 20 years and a license amendment request (LAR) to change the current licensing basis to account for the effects of ASR.
In May 2010, NextEra submitted an LRA to renew the Seabrook facility operating license for an additional 20 years. The Seabrook license renewal Safety Evaluation Report (SER) contained one Open Item related to NRC staff concerns that NextEra had not enhanced the Structures Monitoring Program to manage the effects of ASR. The SER explained that for the NRC staff to complete its LRA review and close this Open Item, NextEra would need to update the LRA to include a sufficient aging management program for concrete structures impacted by ASR to ensure safe operation through the period of extended operation (2030–2050). On August 9, 2016, the NRC received NextEra's updated LRA submittal. As a result of the staff’s review of the updated LRA submittal, the staff performed license renewal audits and issued requests for additional information (RAIs). NextEra provided application supplements to address issues identified during the audits and in the RAIs. In May 2018, the staff received NextEra’s revised Structures Monitoring Aging Management Program for Seabrook, which is based on the methodology for analyzing seismic category I structures with concrete affected by ASR that was provided in the LAR, discussed below. The NRC staff completed its review of the LRA and documented the results of the review in the Safety Evaluation Report, dated September 28, 2018. The license renewal Open Item regarding ASR was discussed during an Advisory Committee on Reactor Safeguards (ACRS) Subcommittee meeting on October 31, 2018. Additional information on the ACRS reviews is detailed below. For additional information on the license renewal process and schedule, see: License Renewal Review Schedule.
On June 15, 2016, the NRC staff held a public meeting with NextEra to discuss NextEra's plan to submit a license amendment request to revise the licensing basis to account for ASR at Seabrook. In August 2016, NextEra submitted the LAR, which would revise the Seabrook Updated Final Safety Analysis Report (UFSAR) to include methods for analyzing seismic Category I structures with concrete affected by ASR. In October 2016, the staff accepted the LAR for review. The NRC staff performed a regulatory audit of this application the week of June 5, 2017. In addition, the NRC staff held a public meeting with NextEra on November 17, 2017, to discuss the path to resolve the staff's requests for additional information (RAIs) related to the LAR. In 2018, the NRC staff performed a second regulatory audit of this application from March 19 – 23, 2018. The NRC staff documented its review of the LAR in a Draft Safety Evaluation and submitted this document to the ACRS on September 28, 2018. The LAR directly supports the staff's review of the LRA, which was evaluated in a separate process, as discussed above.
Both the LAR and the license renewal Open Item regarding ASR were discussed during an ACRS subcommittee meeting on October 31, 2018, as noted below. The NRC issued Amendment No. 159 approving the LAR on March 11, 2019, and subsequently issued the renewed facility operating license approving the LRA on March 12, 2019.
A request for a hearing on the LAR was filed by the C-10 Research and Education Foundation, Inc. (C-10). On October 6, 2017, the Atomic Safety and Licensing Board (ASLB) granted the hearing request, determining that C-10 had standing and admitting a single reformulated contention for hearing. The ASLB has scheduled the evidentiary hearing from September 24-27, 2019. More information on the NRC's adjudicatory process can be found on this webpage.
Advisory Committee on Reactor Safeguards (ACRS)
The ACRS is independent of the NRC staff and reports directly to the Commission. It is composed of outside experts in various technical fields. One of the ACRS's purposes is to review and report on safety studies and reactor facility license and license renewal applications. Due to the first-of-a-kind nature of ASR in the U.S. nuclear industry, the ACRS held a subcommittee meeting on October 31, 2018, to specifically review the technical aspects of ASR at Seabrook. In support of this meeting, the staff provided the subcommittee with both the safety evaluation report for license renewal and the draft safety evaluation for the ASR-related license amendment request. On November 15, 2018, the ACRS subcommittee held a meeting on the remaining issues related to the Seabrook license renewal application. On December 6, 2018, the full Committee held a meeting on the Seabrook license renewal application. On December 14, 2018, the ACRS issued a letter to the Commission stating that the staff's evaluations of ASR at Seabrook provide thorough assessments and findings and that the ACRS agrees with the staff’s conclusions that NextEra's programs related to ASR are acceptable. On December 19, 2018, the ACRS issued a letter to the Commission stating that the Seabrook license renewal application should be approved. The ACRS webpage includes meeting schedules, meeting transcripts, and letter reports.
Next Steps
The NRC will continue its evaluation of ASR at Seabrook through:
- Inspecting NextEra's monitoring of ASR-affected structures and implementation of the enhanced structures monitoring program. These activities will be documented in inspection reports approximately every six months in 2019. Using the normal reactor oversight process, the NRC staff will determine the need for such inspections to continue following the ASLB hearing, into 2020, and beyond.
Publicly Available Documents
The following table lists the publicly available documents that the NRC has issued in connection with the special oversight of Seabrook.
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| Date |
Title/Description |
| 11/24/2020 |
Seabrook Station, Unit No. 1 – Issuance of Revised Page for Renewed Facility Operating License Re: Atomic Safety and Licensing Board Decision LBP-20-09 and LBP-20-12 |
| 11/06/2020 |
Atomic Safety and Licensing Board Memorandum and Order Denying Motion to Reopen, Motion for Leave, and Motion for Partial Reconsideration; Granting in Part and Denying in Part Motion for Leave to Reply |
| 09/21/2020 |
Atomic Safety and Licensing Board Initial Decision on Reformulated Contention involving ASR at the Seabrook nuclear power plant. |
| 03/12/2019 |
Issuance of a Renewed Facility Operating License No. NPF-86 for Seabrook Station, Unit No. 1 (CAC No. ME4028) |
| 03/11/2019 |
Issuance of Amendment No. 159 Re: Methodology for Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction |
| 01/03/2019 |
Safety Evaluation Report for the License Renewal of Seabrook Station Unit 1 (supersedes ML18254A294 from 9/28/2018) |
| 11/13/2018 |
ASR Problem Identification and Resolution Sample – NRC Inspection Report 05000443/2018003, Section 71152 |
| 09/28/2018 |
Safety Evaluation Report for the License Renewal of Seabrook Station Unit 1 |
| 09/28/2018 |
Submission of ASR License Amendment Request Draft Safety Evaluation to Support Advisory Committee on Reactor Safeguards Review of Seabrook License Renewal |
| 08/31/2018 |
Seabrook Station, Unit No. 1 – License Renewal Application (Region I Memo to NRR) |
| 08/10/2018 |
Seabrook Station – Follow-up of ASR Open Item License Renewal Inspection Report 05000443/2018011 |
| 06/07/2018 |
Seabrook Station Response to Request for Additional Information Regarding License Amendment Request 16-03 |
| 05/21/2018 |
Seabrook, 1 Site Visit Report Regarding Regulatory Audit for License Amendment Request Re: Alkali Silica Reaction License Amendment Request and License Renewal Alkali-Silica Reaction Aging Management Program Review (CAC NO. MF8260; EPID L-2016-LLA-0007) |
| 05/18/2018 |
Seabrook Station – Revised Structures Monitoring Aging Management Program. |
| 05/14/2018 |
ASR Problem Identification and Resolution Sample – NRC Inspection Report 05000443/2018001, Section 4OA2 |
| 05/01/2018 |
Request for Additional Information Regarding ASR Amendment Request (MF8260 Follow-up RAIs) |
| 04/18/2018 |
DRAFT – Request for Additional Information Regarding ASR Amendment Request |
| 03/12/2018 |
Seabrook ASR LAR Site Visit Plan – Attachment 3.pdf |
| 02/28/2018 |
Supplement 60 – Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application – ASME Section XI, Subsection IWL Program |
| 02/27/2018 |
Seabrook ASR LAR Site Visit Plan - March 2018 - Final.pdf |
| 02/12/2018 |
Seabrook Station Integrated Inspection Report 05000443/2017004, documenting a semi-annual review of ASR monitoring |
|
01/29/2018
|
Seabrook Station – Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) |
| 12/11/2017 |
Seabrook Station – Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) |
| 11/03/2017 |
Supplement 58 – Revised Alkali-Silica Reaction Aging Management Program |
| 10/11/2017 |
Seabrook Station, Unit No. 1 - Request For Additional Information Regarding License Amendment Request Related To Alkali-Silica Reaction (CAC NO. MF8260; EPID L-2016-LLA-0007) |
| 10/03/2017 |
Seabrook Station – Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction (CAC No. MF8260) |
| 09/11/2017 |
Request For Additional Information (RAI) Regarding License Amendment Request (LAR) 16-03 To Revise Current Licensing Basis To Adopt A Methodology For The Analysis Of Seismic Category I Structures With Concrete Affected By Alkali-Silica Reaction, NextEra Energy Seabrook, LLC, Seabrook Station Docket No. 50-443 |
| 08/14/2017 |
ASR Problem Identification and Resolution Sample – NRC Inspection Report 05000443/2017002, Section 4OA2 |
| 08/04/2017 |
Seabrook Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request Related To Alkali-Silica Reaction (CAC No. MF8260) |
| 07/26/2017 |
Seabrook Station, Unit No. 1 - Site Visit Report Regarding Regulatory Audit for Alkali Silica Reaction License Amendment Request (CAC No. MF8260) |
| 07/20/2017 |
Revision to License Renewal ASME Section XL, Subsection IWL, Program Operating Experience |
| 06/27/2017 |
Response Date Change Related to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Building Deformation Analyses Related To Concrete Alkali-Silica Reaction |
| 06/16/2017 |
Seabrook Station - Update to Reply to a Notice of Violation; EA-16-101 Corrective Action Plan |
| 05/05/2017 |
DRAFT - Request for Additional Information Regarding ASR Amendment Request RAIs (MF8260) |
| 03/29/2017 |
Request For Additional Information For The Review Of The Seabrook Station License Renewal Application (CAC No. ME4028) |
| 03/01/2017 |
Summary Of Teleconference Held On December 1, 2016, Between The U.S. Nuclear Regulatory Commission And NextEra Energy Seabrook Concerning Requests For Additional Information Pertaining To The Seabrook Station, License Renewal Application (CAC No. ME4028) |
| 02/27/2017 |
Request For Withholding Information From Public Disclosure (CAC No. ME4028) |
| 02/08/2017 |
Alkali-Silica Reaction Monitoring and Closure of NOV for Failure to Complete Operability Determinations for ASR-affected Structures – NRC Inspection Report 05000443/2016004, Sections 4OA2 and 4OA5 |
| 01/13/2017 |
NRR Audit Plan for Seabrook Alkali-Silica Reaction (ASR) LAR Review |
| 12/23/2016 |
Seabrook Station, License Renewal Application Relating to the Alkali-Silica Reaction (ASR) Monitoring Program |
| 12/21/2016 |
Alkali Silica Reaction Monitoring Aging Management Program Audit Report Regarding The Seabrook Station, Unit 1, License Renewal (CAC No. ME4028) |
| 12/12/2016 |
Requests For Additional Information For The Review Of The Seabrook Station License Renewal Application (CAC No. ME4028) |
| 10/13/2016 |
Regulatory Audit Plan – Alkali Silica Reaction Aging Management Program, Regarding Seabrook Station, Unit 1, License Renewal Application Review (CAC No. ME4028) |
| 10/12/2016 |
Seabrook Station, Unit No. 1 -Acceptance of Requested Licensing Amendment Action Re: Alkali-Silica Reaction |
| 09/30/2016 |
Supplement to License Amendment Request 16-03 Revise Current Licensing Basis to Adopt a Methodology for the Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction. |
| 09/19/2016 |
Seabrook Station, Unit No. 1 -Supplemental Information Needed For Acceptance Of Requested Licensing Action Re: Alkali-Silica Reaction |
| 08/09/2016 |
Seabrook Station, License Renewal Application (LRA) Relating to the Alkali-Silica Reaction Monitoring Program |
| 08/05/2016 |
ASR Operability Determinations and Functionality Assessments Sample – NRC Inspection Report 05000443/2016002, Section 1R15 |
| 08/01/2016 |
License Amendment Request (LAR) 16-03, "Revise Current Licensing Basis to Adopt a Methodology for the Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction" |
| 06/29/2016 |
Seabrook Station, Unit No. 1 – Acknowledgement of Reply to Notice of Violation – NRC Inspection Report 0500443/2016008 |
| 06/06/2016 |
Seabrook Station - Reply to a Notice of Violation EA-16-101 - Seabrook Station, Inspection Report 05000443/2016008 Related to Alkali-Silica Reaction Effects on Safety-Related Concrete Structures and Notice of Violation |
| 05/06/2016 |
NRC Inspection Report 05000443/2016008 - Alkali-Silica Reaction (ASR) Effects on Safety-Related Concrete Structures and Notice of Violation (NOV) |
| 03/29/2016 |
NextEra Drop-In with Division of License Renewal (DLR), Division of Operating Reactor Licensing (DORL), and Division of Engineering (DE) |
| 02/12/2016 |
ASR Problem Identification and Resolution Sample – NRC Inspection Report 05000443/2015004, Section 4OA2 |
| 12/23/2015 |
Summary of Telephone Conference Call Held on December 22, 2015, Between the NRC and NextEra Concerning a RAI Pertaining To Seabrook Station Operability Determinations for ASR-Affected Structures |
| 12/17/2015 |
ASR Monitoring Aging Management Program Audit Report Regarding the Seabrook Station |
| 12/03/2015 |
NextEra response to RAI for the Review of the Seabrook License Renewal Application– Set 25 |
| 11/19/2015 |
Schedule Revision and Change of Project Manager for the Review of the Seabrook Station License Renewal Application |
| 10/02/2015 |
RAI for the Review of the Seabrook License Renewal Application – Set 25 |
| 08/05/2015 |
ASR Problem Identification and Resolution Sample – NRC Inspection Report 05000443/2015002, Section 4OA2 |
| 06/30/2015 |
MPR-4153, Approach for Determining Through-Thickness Expansion from ASR (Enclosure 3 to the letter titled "NextEra second response to RAI – Set 23") |
| 06/30/2015 |
NextEra second response to RAI for the Review of the Seabrook License Renewal Application – Set 23 |
| 05/04/2015 |
Schedule Revision for the Safety and Environmental Reviews of the Seabrook Station License Renewal Application |
| 02/23/2015 |
NextEra response to RAI for the Review of the Seabrook License Renewal Application – Set 23 |
| 02/06/2015 |
ASR Problem Identification and Resolution Sample – NRC Inspection Report 05000443/2014005, Section 4OA2 |
| 11/25/2014 |
RAI for the review of the Seabrook License Renewal Application – Set 23 |
| 11/21/2014 |
NextEra Revised response to RAI for the review of the Seabrook License Renewal Application – Set 20 |
| 08/05/2014 |
ASR Maintenance Effectiveness Sample – NRC Inspection Report 05000443/2014003, Section 1R12 |
| 05/15/2014 |
NextEra response to RAI for the Review of the Seabrook License Renewal Application – Set 20 |
| 05/06/2014 |
ASR Problem Identification and Resolution Sample – NRC Inspection Report 05000443/2014002, Section 4OA2 |
| 02/19/2014 |
Revision to NRC Seabrook Alkali-Silica Reaction Issue Technical Team Charter |
| 01/30/2014 |
ASR Problem Identification and Resolution Sample – NRC Inspection Report 05000443/2013005, Section 4OA2 |
| 01/15/2014 |
Request for Additional Information (RAI) for the Review of the Seabrook License Renewal Application – Set 20 |
| 12/23/2013 |
Aging Management Program Audit Report Regarding Seabrook Station License Renewal Application |
| 12/06/2013 |
NRC response to UCS letter regarding ASR concrete degradation |
| 11/04/2013 |
Union of Concerned Scientists (UCS) letter regarding ASR concrete degradation at Seabrook Station, dated 11/4/2013 |
| 10/09/2013 |
Seabrook Station, Unit No. 1 – Closure of Confirmatory Action Letter 1-2012-002 |
| 09/13/2013 |
Supplemental license renewal application information submitted to the NRC on September 13, 2013 regarding the Seabrook ASR monitoring program |
| 08/09/2013 |
Seabrook Station, Unit No. 1 – Confirmatory Action Letter Follow-Up Inspection – NRC Inspection Report 05000443/2012010 |
| 05/01/2013 |
NextEra response to Confirmatory Action Letter Items 2, 4, 8, dated May 1, 2013 |
| 02/28/2013 |
NextEra response to Confirmatory Action Letter Item 11, dated February 28, 2013 |
| 01/14/2013 |
Revision to Confirmatory Action Letter, Seabrook Station, Unit 1 – Information Related to Concrete Degradation Issues |
| 12/13/2012 |
NextEra response to Confirmatory Action Letter, dated December 13, 2012 |
| 12/03/2012 |
Seabrook Station, Unit No. 1 – Confirmatory Action Letter Follow-Up Inspection – NRC Inspection Report 05000443/2012009 |
| 09/05/2012 |
NRC staff request for deviation from Reactor Oversight Process to provide increased oversight of ASR issues at Seabrook |
| 07/09/2012 |
Charter for NRC technical team assigned to look at ASR issues at Seabrook |
| 06/28/2012 |
NexrEra response to CAL: Large scale testing |
| 06/21/2012 |
NexrEra response to CAL: Large scale testing (enclosure) |
| 06/08/2012 |
NexrEra response to CAL: Corrective Action Plan |
| 05/24/2012 |
NextEra response to CAL: Impact of ASR on Concrete Structures and Attachments (Foreign Print 100716) |
| 05/24/2012 |
NextEra response to NRC CAL on Seabrook ASR |
| 05/16/2012 |
Supplemental license renewal application information submitted to the NRC on May 16, 2012 regarding ASR monitoring at Seabrook |
| 05/16/2012 |
NRC Confirmatory Action Letter (CAL) issued to NextEra on May 16, 2012 regarding information required on ASR issues at Seabrook |
| 05/10/2012 |
NextEra Letter Committing to Supplemental to Actions for Resolution of ASR issues |
| 05/03/2012 |
NextEra Letter Committing to Actions for Resolution of ASR Issues |
| 03/26/2012 |
NRC Inspection Report 05000443/2011010, issued March 26, 2012 on ASR at Seabrook |
| 08/12/2011 |
ASR – 1R15 Operability Samples – NRC Inspection Report 05000443/2011003 |
| 05/23/2011 |
NextEra Energy Seabrook - NRC License Renewal Inspection Report 05000443/2011007 |
| 05/12/2011 |
ASR – 1R12 Maintenance Effectiveness Sample – NRC Inspection Report 05000443/2011002 |
Public Meetings
The following table lists the public meetings in connection with the special oversight of Seabrook.
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| Date |
Title/Description |
| 02/13/2019 |
The purpose of this meeting is to discuss the NRC's plans related to the schedule for issuing the license amendment associated with ASR and the renewed Seabrook license.
|
| 05/02/2018 |
The NRC will host an open house with the public to discuss the NRC's assessment of safety performance at Seabrook for 2015. Following the open house, the NRC will then give an update and respond to questions regarding the NRC's evaluation of the effect of the ASR in concrete structures at Seabrook.
|
| 11/17/2017 |
The purpose of the meeting is to discuss with NextEra Energy Seabrook, LLC (NextEra) the path to resolution for stage 3 requests for additional information related to the review of the alkali-silica reaction license amendment request.
|
| 08/24/2017 |
The purpose of this meeting is to discuss with NextEra Energy Seabrook, LLC (NextEra), the NRC staff's review of the Seabrook Station, Unit No. 1, Alkali-Silica Reaction License Amendment Request.
|
| 06/07/2017 |
The NRC will host an open house with the public to discuss the NRC's assessment of safety performance at Seabrook for 2015. Following the open house, the NRC will then give an update and respond to questions regarding the NRC's evaluation of the effect of the ASR in concrete structures at Seabrook
|
| 06/05/2017 |
Summary Of Meeting Held On May 9, 2017, Between The U.S. Nuclear Regulatory Commission Staff And NextEra Energy Seabrook, LLC, Representatives To Discuss The Seabrook Station, License Renewal Application (CAC NO. ME4028)
|
| 06/21/2016 |
The NRC will host an open house with the public to discuss the NRC's assessment of safety performance at Seabrook for 2015. Following the open house, the NRC will then give an update and respond to questions regarding the NRC's evaluation of the effect of the ASR in concrete structures at Seabrook
|
| 06/15/2016 |
The purpose of this meeting is for NextEra Energy to present to the NRC staff its plan for a license amendment request regarding revising the licensing basis for Alkali-Silica Reaction at the Seabrook Station, Unit No. 1.
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| 06/06/2016 |
The purpose of this public meeting is for C-10 to address the NRC PRB regarding the 2.206 Petition submitted by C-10 on December 22, 2015, regarding Seabrook.
Related Documents
- Meeting Notice
- 06/06/2016 Forthcoming Meeting with the NRC Petition Review Board (PRB) and C-10 Research & Education Foundation (C-10) Regarding the 2.206 Petition Submitted December 22, 2015, for Seabrook Station, Unit 1 (Seabrook)
- 2016/02/12 NRR E-mail Capture - [External_Sender] Comments for February 16, 2016, pre-PRB call with C-10 regarding Seabrook 2.206 petition
- 2016/02/14 NRR E-mail Capture - [External_Sender] Paul Brown's comments for the NRC PRB considering C-10's 2, 206 Petition on Feb 16th
- Management Directive 8.11, "Review Process for 10 CFR 2.206 Petitions."
- OEDO-16-00007 - 2.206 - Seabrook Immediate Implementation and Enforcement of ACI 349.3R & ASTM C 856-11 Code Standards Requiring Core Sampling and Petrographic Testing for the Mechanical Properties of Tensile
- 2016/02/15 NRR E-mail Capture - [External_Sender] C-10 Comments on the NRC PRB call
- Transcript - Original - Teleconference Held on February 16, 2016, Regarding 2.206 Petition from C-10 Research & Education Foundation for Seabrook Station, Pages 1-40
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| 04/28/2016 |
The purpose of this public meeting is for NextEra Energy Seabrook, LLC (NextEra) to discuss with U.S. Nuclear Regulatory Commission (NRC) staff about (a) the staff request for information (RAI) and (b) NextEra's plan for response to the RAI and the completion of the licensing action for Seabrook Station (Seabrook) license renewal.
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| 06/18/2015 |
The NRC will host a 1-hour Open House before the meeting, as well as a question and answer session, to discuss NextEra’s performance at Seabrook during 2014.
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| 06/24/2014 |
The NRC will host a one-hour open house, as well as a question and answer session, to discuss NextEra’s performance at Seabrook during calendar year 2013.
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| 12/18/2013 |
The NRC conducted an open house and a public meeting with NextEra to discuss NextEra's testing program regarding concrete degradation caused by the Alkali-Silica Reaction (ASR) at Seabrook Station.
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| 02/21/2013 |
The NRC conducted a public meeting with NextEra to discuss aging effects and management associated with alkali-silica reaction regarding the license renewal application for Seabrook Station.
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| 12/11/2012 |
The NRC conducted an open house and public meeting to discuss the safety implications and status of its review of NextEra's commitment actions related to the ASR conditions in safety-related structures at Seabrook Station.
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| 04/23/2012 |
The NRC conducted a public meeting with representatives from NextEra to discuss NextEra's plans and schedule regarding concrete degradation caused by ASR at Seabrook as referenced in the NRC inspection report.
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Page Last Reviewed/Updated Thursday, February 11, 2021