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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
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 April 22, 2014 Ms. Sandra Gavutis, Executive Director C-10 Research and Education Foundation 44 Merrimac St.
Newburyport, MA 01950
SUBJECT:
SEABROOK STATION PUBLIC MEETING CONCERNING CONCRETE DEGRADATION DUE TO ALKALI-SILICA REACTION
Dear Ms. Gavutis:
I am responding to your letter dated March 10, 2014, regarding the public meeting held on December 18, 2013, to discuss concrete degradation at Seabrook Station due to Alkali-Silica Reaction (ASR). Your letter stated NextEra staff made misstatements that warranted correction by the U.S. Nuclear Regulatory Commission (NRC) managers in attendance and requested the NRCs position regarding related ASR topics. As communicated in the public meeting, the NRC has independently reviewed NextEras prompt operability determinations and concluded the Seabrook ASR-affected structures remain capable of performing their intended safety functions.
While NextEra has developed and implemented research and testing to gain a better understanding of the impact of ASR on reinforced concrete structures similar in design to the Seabrook structures, the NRC has not approved NextEras plans or methods for resolving the ASR issue at Seabrook. We acknowledge that the views of NextEra and C-10 differ, but would not characterize the differences as misstatements as described in your letter. The following provides our responses to the specific issues you raised in your March 10, 2014 letter:
- 1. NextEras testing plans do not include cancelled Seabrook Unit 2 structure tests.
During the meeting NextEra described their in-progress plans to fabricate and test large scale anchor, shear and rebar anchorage control and ASR affected specimens. NextEras plans do not currently include testing of Seabrook Unit 2. The NRC has neither recommended nor required NextEra to pursue their large scale test program or testing of Seabrook Unit 2. We expect that NextEra will need to clearly establish that the results of their large scale test program are representative of actual conditions at Seabrook. NextEras process for correlating the test program results to Seabrook concrete structures has not been provided to the NRC.
Should NextEra elect to use the results of their large scale test program, or implement another approach to resolve the ASR non-conforming condition, the methodology and results will be subject to NRC review to resolve this non-conforming condition.
- 2. Why are there not more core tests in Seabrook Unit 1?
Our conclusions regarding NextEras core sampling and testing activities are described in NRC Inspection Reports 05000443/2012009 and 05000443/2012010 (available on the NRCs Seabrook Concrete degradation public webpage). For affected structures, NextEra staff assessed structural design attributes using bounding values for assumed ASR degradation derived from concrete industry test data. These evaluations were informed using the material
S. Gavutis 2 property test results from core samples from various Seabrook ASR-affected and non-affected structures. NRC inspectors reviewed these prompt operability determinations and concluded that there is reasonable assurance, considering the core bore results and bounding structural evaluations, to conclude Seabrook ASR-affected structures remain capable of performing their intended safety functions. As described above, the NRC Staff will evaluate NextEras approach to resolve this non-conforming condition.
- 3. NextEras characterization of groundwater surrounding the Seabrook Station.
During inspections completed in 2013, NRC inspectors reviewed NextEras structures monitoring program (SMP) with respect to infiltrating groundwater. The inspectors determined that NextEra staff integrated elements of their groundwater monitoring program (in place for other regulatory requirements) into the SMP. The inspectors further determined that NextEra staff had initiated actions to investigate the expansion of their groundwater water monitoring activities to include periodic analysis and trending of infiltrated groundwater to test for aggressive chemistry conditions such as elevated chlorides, sulfates and pH. These inspector observations were documented in Section 7.0 of NRC Inspection Report 2012010 dated August 9, 2013. The NRC similarly described the status of our inspection activities in this regard in a letter to The Union of Concerned Scientists (UCS) dated December 6, 2013. The NRC inspection report and NRCs response letter to UCS are both available on the NRCs Seabrook Concrete degradation public webpage.
The NRC will continue to review and inspect NextEras activities to address the ASR affected structures at Seabrook.
Thank you for your continued interest in the NRCs inspections and oversight of Seabrook Station. Please feel free to contact Mr. Mel Gray at (610) 337-5209 or Mr. William Cook at (610) 337-5074 should you have any further questions or comments to share with us.
Sincerely,
/RA/
Raymond K. Lorson, Director Division of Reactor Safety Docket No. 50-443 License No. NPF-86
ML14112A323 Non-Sensitive Publicly Available SUNSI Review OFFICE RI/DRS/SRA RI/DRS/EB1 RI/DRS NAME WCook/WAC MGray/MG RLorson DATE 04/09/2014 04/09/2014 04/22/2014 S. Gavutis 3 Distribution: via email (EDATS: RegionI-2014-0088)
W. Dean, RA (R1ORAMAIL Resource) G. Dentel, DRP, BC B. Reyes, DRP D. Lew, DRA (R1ORAMAIL Resource) R. Barkley, DRP A. Cass, DRP, AA R. Lorson, DRS (R1DRSMail Resource) M. Draxton, DRP N. McNamara, RI, SLO J. Trapp, DRS (R1DRSMail Resource) P. Cataldo, DRP, SRI D. Tift, RI, SLO M. Scott, DRP (R1DRPMAIL Resource) C. Newport, DRP, RI D. Screnci, RI, PAO E. Benner, DRP (R1DRPMail Resource) M. Gray, DRS, BC N. Sheehan, RI, PAO RidsNrrPMSeabrook Resource A. McMurtray, NRR M. Marshall, NRR RidsNrrDorlLpl1-2 Resource J. Nick, OEDO M. Khanna, NRR RIDSNRRDLR Resource RIDSEDOMailCenter Resource