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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 05000443/LER-2024-001, 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 ML24065A2522024-03-0505 March 2024 Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033) 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 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
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 January 19, 2016 Ms. Debbie Grinnell Research Advocate C-10 Research and Education Foundation, Inc.
44 Merrimac Street Newburyport, MA 01950
Dear Ms. Grinnell:
In response to the questions you raised in your December 3, 2015 email (ML15341A106),
please see the publically available documents referenced in the following. The information we have retained regarding NextEras conduct of core sampling locations and material testing as part of their initial characterization of Alkali Silica Reaction (ASR) in affected Seabrook Nuclear Plant structures is described in these documents.
Detailed information provided by NextEra to the NRC on core sampling locations and material tests can be found in a submittal dated May 2012 (See Section 3.1, Examination and Testing of Cores (ML12151A397)). Additional information was provided by NextEra during a public meeting in April 2012. That slide presentation is available at ML121160422.
The NRCs review of NextEras actions to address structures affected by ASR, including their core sampling and material testing, are documented in two NRC inspection reports dated December 3, 2012, (ML12338A283) and August 8, 2013 (ML13221A172). Our 2012 report documents that the NRC determined NextEra's methods for assessing operability of ASR-affected reinforced concrete structures were reasonable and generally comprehensive.
Specially, the NRC determined NextEra staff conducted a margins analysis, using bounding ASR-affected concrete properties derived from research data, to demonstrate that Seabrook structures remained operable. Core material test sample results provided insights, but the values were not used in these analyses because NextEra staff concluded the results may not be representative or conservative. Our 2013 inspection report, Section 9.2, described our review of the cores and testing completed and acknowledged our understanding that NextEra planned to perform further core removal and testing to relate their large scale test program results to the condition in Seabrook structures affected by ASR.
D. Grinnell As part of our ongoing license renewal review process, regarding adequate material aging management measures for safe operation during the period of extended operation, NextEra submitted for NRC review details as to how they intend to relate their large scale test results to the actual conditions of Seabrook structures using core sampling and material testing.
NextEras submittal dated June 30, 2015 (ML15183A023) summarized their criteria and number of proposed core locations and tests. In response to NRC staff questions dated October 2, 2015 (ML15251A333), NextEra submitted an update to their plans, including changes to the criteria for identifying core locations in the Seabrook Nuclear Power Plant (See NextEra submittal dated December 3, 2015 (ML15343A470)). The adequacy of NextEras plans for core locations, sampling and material testing remain under NRC staff review. In addition, the staff conducted an audit of the large scale testing at the University of Texas - Austin in October 2015 (ML15287A017) and the resulting audit report was issued in December 2015 (ML15337A047).
Sincerely,
/RA/
Fred L. Bower, III, Chief Projects Branch 3 Division of Reactor Projects
ML16019A081 SUNSI Review Non-Sensitive Publicly Available Sensitive Non-Publicly Available OFFICE RI/DRP RI/DRS RI/HQ RI/DRS RI/DRP TTran/ RSB CONCU NAME RBarkley/ RSB WCook/ FLB for MGray/ MG FBower/ FLB RRED VIA EMAIL DATE 01/ 13 /16 01/ 13 /16 01/ 13 /16 01/ 13 /16 01/14 /16 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 January 19, 2016 Ms. Debbie Grinnell Research Advocate C-10 Research and Education Foundation, Inc.
44 Merrimac Street Newburyport, MA 01950
Dear Ms. Grinnell:
In response to the questions you raised in your December 3, 2015 email (ML15341A106),
please see the publically available documents referenced in the following. The information we have retained regarding NextEras conduct of core sampling locations and material testing as part of their initial characterization of Alkali Silica Reaction (ASR) in affected Seabrook Nuclear Plant structures is described in these documents.
Detailed information provided by NextEra to the NRC on core sampling locations and material tests can be found in a submittal dated May 2012 (See Section 3.1, Examination and Testing of Cores (ML12151A397)). Additional information was provided by NextEra during a public meeting in April 2012. That slide presentation is available at ML121160422.
The NRCs review of NextEras actions to address structures affected by ASR, including their core sampling and material testing, are documented in two NRC inspection reports dated December 3, 2012, (ML12338A283) and August 8, 2013 (ML13221A172). Our 2012 report documents that the NRC determined NextEra's methods for assessing operability of ASR-affected reinforced concrete structures were reasonable and generally comprehensive.
Specially, the NRC determined NextEra staff conducted a margins analysis, using bounding ASR-affected concrete properties derived from research data, to demonstrate that Seabrook structures remained operable. Core material test sample results provided insights, but the values were not used in these analyses because NextEra staff concluded the results may not be representative or conservative. Our 2013 inspection report, Section 9.2, described our review of the cores and testing completed and acknowledged our understanding that NextEra planned to perform further core removal and testing to relate their large scale test program results to the condition in Seabrook structures affected by ASR.
D. Grinnell As part of our ongoing license renewal review process, regarding adequate material aging management measures for safe operation during the period of extended operation, NextEra submitted for NRC review details as to how they intend to relate their large scale test results to the actual conditions of Seabrook structures using core sampling and material testing.
NextEras submittal dated June 30, 2015 (ML15183A023) summarized their criteria and number of proposed core locations and tests. In response to NRC staff questions dated October 2, 2015 (ML15251A333), NextEra submitted an update to their plans, including changes to the criteria for identifying core locations in the Seabrook Nuclear Power Plant (See NextEra submittal dated December 3, 2015 (ML15343A470)). The adequacy of NextEras plans for core locations, sampling and material testing remain under NRC staff review. In addition, the staff conducted an audit of the large scale testing at the University of Texas - Austin in October 2015 (ML15287A017) and the resulting audit report was issued in December 2015 (ML15337A047).
Sincerely,
/RA/
Fred L. Bower, III, Chief Projects Branch 3 Division of Reactor Projects
ML16019A081 SUNSI Review Non-Sensitive Publicly Available Sensitive Non-Publicly Available OFFICE RI/DRP RI/DRS RI/HQ RI/DRS RI/DRP TTran/ RSB CONCU NAME RBarkley/ RSB WCook/ FLB for MGray/ MG FBower/ FLB RRED VIA EMAIL DATE 01/ 13 /16 01/ 13 /16 01/ 13 /16 01/ 13 /16 01/14 /16