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MONTHYEARML16230A1822016-09-0101 September 2016 Proprietary Information Determination Project stage: Other SBK-L-16156, Response to Issuance of LR-ISG-2015-01 Changes to Buried and Underground Piping and Tank Recommendations2016-10-0707 October 2016 Response to Issuance of LR-ISG-2015-01 Changes to Buried and Underground Piping and Tank Recommendations Project stage: Request ML16277A5492016-10-13013 October 2016 Regulatory Audit Plan - Alkali Silica Reaction Aging Management Program, Regarding Seabrook Station, Unit 1, License Renewal Application Review Project stage: Other ML16301A4282016-11-14014 November 2016 Requests for Additional Information for the Review of the License Renewal Application Project stage: RAI SBK-L-16186, Supplement 50, Response to Request for Additional Information for the Review of License Renewal Application Providing Changes to Buried and Underground Piping and Tank Recommendations2016-11-23023 November 2016 Supplement 50, Response to Request for Additional Information for the Review of License Renewal Application Providing Changes to Buried and Underground Piping and Tank Recommendations Project stage: Response to RAI ML16326A0372016-11-30030 November 2016 Requests for Additional Information for the Review of the Seabrook Station License Renewal Application Project stage: RAI ML16333A2472016-12-21021 December 2016 Alkali Silica Reaction Monitoring Aging Management Program Audit Report Regarding the Seabrook Station, Unit 1, License Renewal Project stage: Other ML17017A3742017-02-27027 February 2017 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16342C4672017-03-0101 March 2017 12/01/2016 Summary of Teleconference Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Requests for Additional Information Pertaining to the Seabrook Station License Renewal Application Project stage: RAI ML16341B9022017-03-0707 March 2017 03/07/2016 Summary of Telecon Held on Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Request for Additional Information Pertaining to the Seabrook Station License Renewal Application Project stage: RAI ML17066A4882017-03-16016 March 2017 Steam Generator ISG RAI for the Review of the Seabrook Station License Renewal Application Project stage: RAI ML17088A6142017-03-29029 March 2017 Request for Additional Information for the Review of the Seabrook Station License Renewal Application Project stage: RAI ML17139B8352017-05-24024 May 2017 Final Request for Additional Information Regarding Seabrook License Renewal Application - Set 26 Project stage: RAI ML17357A0452017-05-24024 May 2017 2017/05/24 Seabrook La - Seabrook Station, Unit 1 Final Request for Additional Information Regarding Seabrook License Renewal Application Set 26 Project stage: RAI SBK-L-17087, Supplement 53 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components2017-05-25025 May 2017 Supplement 53 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components Project stage: Response to RAI ML17309A0692017-06-0505 June 2017 2017/06/05 Seabrook La - 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 Project stage: Meeting SBK-L-17102, Clarification to Supplement 53 - Response to Request for Additional Information for the Review of the License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components2017-06-20020 June 2017 Clarification to Supplement 53 - Response to Request for Additional Information for the Review of the License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components Project stage: Response to RAI SBK-L-17103, Supplement 55 - Response to Request for Additional Information for the Review of the License Renewal Application - Bolting Integrity Program2017-06-20020 June 2017 Supplement 55 - Response to Request for Additional Information for the Review of the License Renewal Application - Bolting Integrity Program Project stage: Response to RAI SBK-L-17169, Supplement 58 - Non-Proprietary Enclosure 1 to SBK-L-171552017-10-17017 October 2017 Supplement 58 - Non-Proprietary Enclosure 1 to SBK-L-17155 Project stage: Supplement ML17262A3742017-12-0808 December 2017 Project Manager Change for the License Renewal of Seabrook, Unit 1, License Renewal Application Project stage: Other ML18254A2942018-09-28028 September 2018 Safety Evaluation Report Re License Renewal of Seabrook Station Unit 1 Project stage: Approval ML18254A2812018-09-28028 September 2018 Final SER Project stage: Request ML18254A2932018-09-28028 September 2018 Safety Evaluation Report Re License Renewal of Seabrook Unit 1 Project stage: Approval ML18362A3702019-01-0202 January 2019 Safety Evaluation Report Re License Renewal of Seabrook Station Unit 1. Supersedes ML18254A294 Project stage: Approval ML18345A1202019-03-12012 March 2019 Issuance of Renewed Facility Operating License No. NPF-86 for Seabrook Station, Unit 1 Project stage: Request ML18345A1212019-03-12012 March 2019 Issuance of Renewed Facility Operating License No. NPF-86 for Seabrook Station, Unit 1 Project stage: Approval ML18345A2322019-03-12012 March 2019 Federal Register Notice - Issuance of Renewed Facility Operating License No. NPF-86 for Seabrook Station, Unit 1 Project stage: Approval ML19205A3902019-07-24024 July 2019 NRC042 - Letter from Tam Tran, NRC, to Eric Mccartney, NextEra, Alkali Silica Reaction Monitoring Aging Management Program Audit Report Regarding the Seabrook Station, Unit 1, License Renewal (CAC No. ME4028) (Dec. 21, 2016) Project stage: Other 2017-03-01
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Category:Letter
MONTHYEARIR 05000443/20240032024-10-30030 October 2024 Integrated Inspection Report 05000443/2024003 L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums 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 L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes 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 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 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 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 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-2024-037, 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-2024-033, 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-2024-032, 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 IR 05000443/20230062024-02-28028 February 2024 Annual Assessment Letter for Seabrook Station (Report 05000443/2023006) 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 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) 2024-09-25
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan 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 ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23011A3082023-01-11011 January 2023 Request for Additional Information Regarding Relief Request 4RA-22-001 (L-2022-LLR-0074) ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22228A0552022-08-15015 August 2022 Request for Additional Information Steam Generator Tube Inspection Report Review ML22153A4152022-05-31031 May 2022 Request for Additional Information Re 120V Inverter LAR from TS Branch - Final ML22062B6642022-02-0707 February 2022 Request for Additional Information 120V Inverter LAR from the Electrical Branch ML22063A0002022-01-25025 January 2022 Requests for Additional Information from Risk Branch Regarding 120V Inverter LAR ML21245A4382021-10-0505 October 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Revise 120-Volt AC Vital Instrument Panel Technical Specification Requirements ML21097A2512021-04-0707 April 2021 Request for Additional Information Regarding Steam Generator Tube Inspection Report Review for RFO 20 (EPID L-2020-LRO-0066) (Email) ML21054A0482021-02-23023 February 2021 Request for Additional Information Regarding Heat Flux Hot Channel Requirement Amendment Request ML20343A0942020-12-0303 December 2020 Request for Additional Information Regarding Seabrook (COVID-19) Part 73 Force-on-Force Exemption Request (L-2020-LLE-0219) ML20258A1502020-09-14014 September 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding One-Time Change to the AC Sources Operating TS ML20204A5422020-07-21021 July 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding Degraded Voltage Time Delay Setpoint ML20167A1842020-06-11011 June 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding TSTF-411 and TSTF-418 (L-2019-LLA-0237) ML20114E1592020-04-23023 April 2020 Email and Request for Additional Information Related to Seabrook License Amendment Request to Degraded Voltage Time Delay Setpoint (L-2020-LLA-0012) ML19296D9122019-10-23023 October 2019 NRR E-mail Capture - Request for Additional Information Related to Seabrook Inverter Amendment (L-2019-LLA-0216) ML18163A0352018-06-11011 June 2018 Requests for Additional Information for the Review of the Seabrook Station License Renewal Application ML18121A3992018-05-0101 May 2018 NRR E-mail Capture - Request for Additional Information Regarding ASR Amendment Request ML18113A5292018-04-18018 April 2018 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML18058A0522018-02-27027 February 2018 Enclosurequest for Additional Information (Letter: RAI Regarding Florida Power and Light/Nextera Decommissioning Funding Plan Updates for St. Lucie, Units 1 & 2; Seabrook Station; Duane Arnold Energy Center; and Point Beach, Units 1 and 2) ML18026A8792018-01-29029 January 2018 Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application Docket No. 05-443 ML17332A3412017-11-29029 November 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption ML17261B2172017-10-11011 October 2017 Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17276B7572017-10-0202 October 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17214A0852017-08-0404 August 2017 Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction ML17201Q1072017-07-18018 July 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17139B8352017-05-24024 May 2017 Final Request for Additional Information Regarding Seabrook License Renewal Application - Set 26 ML17150A2862017-05-0505 May 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17088A6142017-03-29029 March 2017 Request for Additional Information for the Review of the Seabrook Station License Renewal Application ML16341B9022017-03-0707 March 2017 03/07/2016 Summary of Telecon Held on Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Request for Additional Information Pertaining to the Seabrook Station License Renewal Application ML16342C4672017-03-0101 March 2017 12/01/2016 Summary of Teleconference Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Requests for Additional Information Pertaining to the Seabrook Station License Renewal Application ML16337A0082016-12-0101 December 2016 NRR E-mail Capture - Need for Supplement to ILRT License Amendment Seabrook Station, License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency ML16326A0372016-11-30030 November 2016 Requests for Additional Information for the Review of the Seabrook Station License Renewal Application ML16326A0092016-11-18018 November 2016 NRR E-mail Capture - Request for Additional Information Re. Nextera/Fpl LAR to Adopt TSTF-545 - CACs MF8203, MF8204, MF8208, and MF8209 ML16301A4282016-11-14014 November 2016 Requests for Additional Information for the Review of the License Renewal Application ML16319A4222016-11-10010 November 2016 NRR E-mail Capture - Need for Supplement to ILRT License Amendment ML16319A4212016-11-10010 November 2016 NRR E-mail Capture - Need for Supplement to EAL License Amendment ML16230A1062016-10-0303 October 2016 Request for Additional Information Request to Extend Containment Leakage Test Frequency ML16230A5332016-09-22022 September 2016 Request for Additional Information Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 ML16258A0222016-09-19019 September 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action Alkali-Silica Reaction ML16187A2032016-07-0808 July 2016 Requests For Additional Information For The Severe Accident Mitigation Alternatives (SAMA) Review Of The Seabrook Station License Renewal Application (TAC No. Me3959)- Enclosure ML15328A1392015-12-0404 December 2015 November 23, 2015, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Nextera Energy Seabrook, LLC, Concerning Requests for Additional Information Pertaining to the Seabrook Station ML15251A3332015-10-0202 October 2015 Request for Additional Information Related to the Review of the Seabrook Station, Unit 1, License Renewal Application-SET 25 ML15224A5662015-08-28028 August 2015 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application-Set 24 ML15131A3382015-06-0505 June 2015 Request for Additional Information Regarding License Amendment 14-03, Changes to Technical Specification 3.3.3.1,Radiation Monitoring for Plant Operations ML15043A2212015-02-24024 February 2015 Request for Additional Information for the Spring 2014 Steam Generator Tube Inspections ML14363A3672015-01-0909 January 2015 Request for Additional Information Regarding the License Amendment Request to Revise the Technical Specification Pressure-Temperature Limits and Request for Exemption from 10 CFR Part 50, Appendix G Minimum Tempt Requirements ML14358A0732014-12-24024 December 2014 Request for Additional Information for License Amendment Request 13-05. Fixed Incore Detector System Analysis Methodology 2024-07-12
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 12, 2016 Mr. Eric McCartney Site Vice President NextEra Energy Seabrook, LLC P.O. Box 300, Lafayette Road Seabrook, NH 03874
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEABROOK STATION LICENSE RENEWAL APPLICATION (CAC NO.
ME4028)
Dear Mr. McCartney:
By letter dated May 25, 2010, NextEra Energy Seabrook, LLC submitted an application pursuant to 10 CFR Part 54, to renew the operating license NPF-86 for Seabrook Station, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with Edward Carley, and a mutually agreeable date for the response is within 15 days from the date of this letter. If you have any questions, please contact me at (301) 415-3617 or e-mail Tam.Tran@nrc.gov.
Sincerely,
/RA/
Tam Tran, Project Manager License Renewal Branch, RPB1 Division of License Renewal Office of Nuclear Reactor Regulation 50-443
Enclosure:
Requests for Additional Information cc w/encl: See next page
ML16326a037
(*) concurred by e-mail Publicly Available Non-Publicly Sensitive Non-Sensitive A il bl To receive a copy of this document, indicate in the concurrence box C = Copy without attach/encl, E = Copy with attach/encl, N = No copy OFFICE PM:RPB1:DLR BC:RASB:DLR BC:RPB1:DLR OGC PM:RPB1:DLR NAME TTran* Brian Wittick* RChazell* *JWatchuka TTran DATE 12/06/2016 12/06/2016 12/12/2016 12/07/2016 12/12/2016
SEABROOK STATION LICENSE RENEWAL APPLICATION (LRA)
REQUESTS FOR ADDITIONAL INFORMATION (RAI)
RAI B.2.1.31A-A1 (PARAMETERS MONITORED OR INSPECTED)
Background
SRP-LR Section A.1.2.3.3 states that the Parameters Monitored or Inspected program element should identify the aging effects that the program manages and should provide a link between the parameter or parameters that will be monitored and how the monitoring of these parameters will ensure adequate aging management. The SRP also states that the parameter monitored or inspected should be capable of detecting the presence and extent of aging effects.
In its August 9, 2016, submittal, the applicant stated under the Section B.2.1.31A Parameters Monitored or Inspected program element that initial screening for ASR [expansion] will be performed using combined cracking index (CCI) only and CCI values exceeding 1 mm/m will trigger additional actions. The program also states that the large-scale test program conducted at the University of Texas indicated that direction of expansion is not significantly affected by the reinforcement when expansion is at or below 1 mm/m but that beyond this level, through-thickness expansion dominates. The staff noted in the Acceptance Criteria program element that 1 mm/m is the threshold for Tier 3 and subject to enhanced ASR monitoring, such as through-wall expansion monitoring using Extensometers. The Parameters Monitoring or Inspected program element states that the periodic extensometer measurements of through-thickness expansion is the parameter to be monitored when an ASR location reaches the Tier 3 monitoring criteria.
The August 9, 2016, letter states that CCI is also used to measure the effects of associated rebar strain.
Issue During its onsite audit the staff reviewed program basis information and reviewed implementation of the ASR Monitoring program to date, including the CCI monitoring at Tier 2 locations and the through-wall extensometer measurements at Tier 3 locations. The staff noted that the through-wall monitoring acceptance criteria values were based on the large-scale testing program results, and that the tests considered volumetric expansion (i.e. in the horizontal, vertical, and through-wall directions), and not just the through-wall expansion. From the staffs review of the program, it is not clear to the staff whether the program considers the volumetric expansion, and whether strain in the horizontal and vertical directions is monitored, once a location is placed into the Tier 3 category. Further, the staff noted that (a) the applicant has completed some of its core testing from Seabrook structure locations for installation of extensometers and (b) there have been variations in crack distribution depending on the location of the core such that in-plane strain may not be insignificant compared to out-of-plane expansion, contrary to the applicants claim. From its review of the Acceptance Criteria program element, the staff noted that acceptance criteria for volumetric expansion did not appear to be included.
Enclosure
In addition, it is not clear how the program explicitly uses CCI to measure the effects of rebar strain due to ASR expansion as is stated in the August 9, 2016 submittal.
Request
- 1. Considering (a) variations in boundary conditions of Seabrook structures compared to large-scale test beams and (b) results of plant-specific information regarding in-plane vs.
out-of-plane expansion-to-date of concrete cores taken at Seabrook, state whether additional parameters such as volumetric expansion will be monitored such that ASR expansion effects are captured in their totality; or provide additional information supporting the use of through-wall monitoring as the only monitoring parameter for Tier 3 ASR locations. If volumetric expansion will be monitored, explain how this will be accomplished.
- 2. State how the program will use CCI to manage ASR-induced rebar strains and stresses such that they remain within design code limits, by the ASR-induced strains alone and in combination with design basis loads and load combinations, during the period of extended operation.
RAI B.2.1.31A-A2 (DETECTION OF AGING EFFECTS)
Background
SRP-LR Section A.1.2.3.4 states that the Detection of Aging Effects program element should describe when, where, and how program data are collected (i.e., all aspects of activities to collect data as part of the program).
Issue The Detection of Aging Effects program element in the revised LRA Section B.2.1.31A of the August 9, 2016, submittal (including Out-of-Plane Expansion and Snap-Ring Borehole Extensometers sections) does not specify the inspection interval planned for monitoring through-wall expansion using snap-ring borehole extensometers.
Request Regarding the use of snap-ring borehole extensometers, clarify the methods and frequencies of inspection(s) for Tier 3 monitoring locations and update the aging management program (AMP) as necessary.
RAI B.2.1.31A-A3 (ACCEPTANCE CRITERIA)
Background
Section B.2.1.31A of the applicants updated LRA submittal dated August 9, 2016, states in the Element 6 - Acceptance Criteria section, [a] structural evaluation is needed when the CCI reaches what is classified as Tier 3 (CCI > 1mm/m).
Issue It is not clear to the staff to what the term structural evaluation is referring. Specifically, it is not clear whether this statement refers to an analysis in accordance with the deformation program Enclosure
(B.2.1.31B). Also, it is not clear what evaluation would be performed if the structure is not within the scope of B.2.1.31B and whether all structures within B.2.1.31B receive an analysis regardless of CCI.
Request State whether the term structural evaluation in Section B.2.1.31A refers to an analysis in accordance with the deformation program (B.2.1.31B). State what evaluation would be performed if the structure is not within the scope of B.2.1.31B and whether all structures within B.2.1.31B receive an analysis regardless of CCI. If not, provide technical justification.
RAI B.2.1.31A-A4 (OPERATING EXPERIENCE)
Background:
SRP-LR Section A.1.2.3.10 states that an applicant should commit to a future review of plant-specific and industry operating experience to confirm the effectiveness of its aging management programs or indicate a need to develop new aging management programs.
The applicants August 9, 2016, letter states that, with regard to large-scale testing:
- The results of the test program demonstrated that none of the assessed limit states are reduced by ASR when ASR expansion levels in plant structures are below those evaluated in the large-scale test programs."
- Results from the large-scale testing program are also used to support evaluations of structures subjected to deformation.
- Data from the structural testing programs have shown that expansion in the in-plane direction plateaus at low expansion levels, while expansion in the through-thickness direction continues to increase.
- A correlation relating expansion to reduction in elastic modulus was developed from the large scale testing program data. The correlation relating expansion to reduction in elastic modulus is applicable to reinforced concrete structures at Seabrook.
The staff noted that the methodology for computing through-wall expansion to-date is described in Report MPR-4153, which was submitted to the staff.
The Operating Experience program element states Seabrook will update the Aging Management Program for any new plant-specific or industry OE Issue:
The applicants above statements indicate that there is an assumption or hypothesis that the actual structures subject to ASR at Seabrook will behave as observed in the test specimens.
Although the test specimens have been created to be as representative as practical of Seabrook two-way reinforced concrete walls, the assumption that Seabrook ASR-affected concrete will behave as seen in the test specimens has not been corroborated or validated. The staff has the following concerns:
- The methodology described in MPR 4153 should be corroborated or validated. It is not clear whether the applicant plans to corroborate or validate, over sufficient time and prior Enclosure
to PEO, such that the behaviors observed due to ASR in the testing specimens and assumed to correlate to Seabrook concrete are consistent.
- The effects of ASR degradation are being addressed as a first-of-a-kind issue in the US nuclear power industry without a widely-accepted or standardized approach to addressing it, and the applicants AMP is based primarily on the scope and data of one plant-specific large-scale test program. It is not clear if and how the program will corroborate or validate assumptions made, once there is data available from implementation of the program to confirm the effectiveness of the ASR Monitoring AMP, to manage aging effects for which it is credited.
Request:
Explain whether and how the ASR Monitoring program will corroborate or validate assumptions (e.g., petrographic characteristics, reduction of elastic modulus at a given expansion, plateau behavior of in-plane expansion, dominant out-of-plane expansion, lack of evidence of in-plane cracking) about how structures at Seabrook would behave under ASR expansion based on observations from the testing program. If the ASR Monitoring program is not expected to corroborate or validate these assumptions, provide the technical basis for these assumptions.
RAI B.2.1.31B-B1 (SCOPE OF PROGRAM)
Background
SRP-LR section A.1.2.3.1 states that the Scope of Program program element should include the specific structures and components, the aging of which the program manages. The applicants August 9, 2016, submittal states [t]he Seabrook Building Deformation Monitoring Program provides for management of the effect of building deformation on Seismic Category 1 structures and associated components within the scope of license renewal. Also included is a list in Section B.2.1.31A of concrete structures within the scope of the license renewal structures monitoring program that will be monitored by the ASR Monitoring AMP and a list in Section B.2.1.31B of structures that will be managed by the Building Deformation program.
Issue During its onsite audit, the staff reviewed implementing documentation and a list of structures to be evaluated under the Building Deformation program and found discrepancies between the structures listed on the implementing documentation and the August 9, 2016, submittal.
Specifically, the seismic Category 1 Control Building, Diesel Generator Building, and Service Water Access (Inspection) Vault were not captured in the implementing documentation. It is not clear whether those structures are included in implementation of the Building Deformation program.
It is also unclear why the list of structures managed is not consistent between Section B.2.1.31A and Section B.2.1.31B; specifically, why the non-category I structures in the ASR Monitoring Program are not included in the Building Deformation Program.
Request Confirm whether the seismic Category 1 Control Building, Diesel Generator Building, and Service Water Access (Inspection) Vault are included in the Building Deformation Program. If Enclosure
they are not included, explain why not. In addition, explain why the non-category I structures in the ASR Monitoring Program are not included in the Building Deformation Program.
RAI B.2.1.31B-B2 (PARAMETERS MONITORED OR INSPECTED, DETECTION OF AGING EFFECTS)
Background
SRP-LR Section A.1.2.3.3 states that the Parameters Monitored or Inspected program element should identify the aging effects that the program manages and should provide a link between the parameter or parameters that will be monitored and how the monitoring of these parameters will ensure adequate aging management. The SRP also states that the parameters monitored or inspected should be capable of detecting the presence and extent of aging effects.
SRP-LR Section A.1.2.3.4 Detection of Aging Effects states that the program element describes when, where, and how program data are collected. For a condition monitoring program the discussion should provide justification that the [monitoring] method and frequency are adequate to detect aging effects before a loss of structure and component (SC)-intended function.
SRP-LR Section A.1.2.3.6 Acceptance Criteria states that the acceptance criteria, against which the need for corrective actions are evaluated, could be specific numerical values, or could consist of a discussion of the process for calculating specific numerical values of conditional acceptance criteria to ensure that the structure- and component-intended function(s) will be maintained under all current licensing basis (CLB) conditions.
The applicants Building Deformation AMP in Section B.2.1.31B of its August 9, 2016, submittal Parameters Monitored or Inspected program element describes a methodology for identifying parameters to monitor for each in-scope structure. The methodology includes three stages of analysis or evaluation, one or more of which will be applied to each structure, that will result in threshold parameters to monitor, each with threshold limits (i.e., monitoring acceptance criteria),
and a specified monitoring frequency depending on the stage of analysis that was applied to the structure. The applicant stated that [a] set of monitoring elements (consisting of strain measurements, deformation measurements, seismic gap measurements, and/or other quantifiable behaviors) is established along with threshold limits for each monitoring element.
The building deformation monitoring frequency for structures for each stage are provided in Table 1 of Enclosure 4 of the August 9, 2016, submittal. The acceptance criteria program element states that a systematic approach to evaluation [Stage 1, 2, or 3 process] of structures impacted by ASR expansion and building deformation is utilized to evaluate ASR and CLB load combinations to validate compliance with structural design code requirements.
Issue During its onsite audit, the staff reviewed implementing documentation for the Building Deformation monitoring program and interviewed cognizant staff. The staff noted that the program does not have one set of parameters monitored or acceptance criteria, but that the applicant establishes a set of parameters to monitor and acceptance criteria for each structure.
The staff also noted that the baseline structural evaluations to establish the criteria for each structures individual building deformation monitoring were not complete for all structures in the Enclosure
scope of the program, and therefore the applicant could not provide the parameters monitored and monitoring method(s) for all of the structures that are in scope of license renewal (i.e., that have license renewal intended functions). The staff was also not provided comprehensive documentation of the process for performing the evaluations, including, but not limited to: (a) a detailed list of the possible monitoring parameters and monitoring method(s) for those parameters; (b) the process for determining what stage of analysis will be used for a given structure; (c) the process for determining that another analysis (different stage) is necessary; and (d) the process for selecting what parameters will be monitored and their monitoring method(s).
The section titled Stage Two: Analytical Evaluation states that additional inspections are performed to measure structural strains and deformations at a broader range of critical locations of the structure. It is not clear to the staff whether (a) there is a procedure for performing the additional inspections, including location and number of additional inspections or (b) a repeatable process for determining when adequate information has been gathered.
Without either the list of parameters monitored for each structure or comprehensive understanding of the procedures and methodology for determining the parameters to be monitored and their monitoring method(s) such that it is clear that the process is repeatable, the staff is not able to verify that the parameters monitored or inspected and detection of aging effects program elements are adequate in accordance with the SRP-LR.
Request Provide, for each structure, a list of parameters monitored and their monitoring method(s), or provide a comprehensive discussion of the processes and procedures for determining the parameters to monitor and monitoring method(s) for structures within the scope of the Building Deformation Program in a manner that would demonstrate repeatability of the process. As a minimum, the discussion of the process should address the items listed in the Issue section above.
RAI 3.5-A1 (AGING MANAGEMENT REVIEW)
Background
10 CFR 54.21(a)(3) states that for each structure and component (SC) subject to an aging management review (AMR) as identified in an applicants integrated plant assessment, the applicant must demonstrate that the effects of aging will be adequately managed so that the intended function(s) will be maintained consistent with the CLB for the period of extended operation.
The applicants letter dated August 9, 2016, states in the Scope of Program program element that the Building Deformation aging management program provides for management of the effect of building deformation on Seismic Category 1 structures and associated components within the scope of license renewal. Program scope includes components within the scope of license renewal contained in concrete structures within the scope of the Structures Monitoring Program.
Issue Enclosure
The applicants August 9, 2016, submittal does not include Table 2 AMR line items for SCs that may be subject to aging effects of building deformation, including supported SCs. Since building deformation (i.e., global manifestations of ASR expansion) is being managed by the Building Deformation program, it is not clear whether the applicant evaluated the need to revise the AMR tables associated with the affected SCs and identify whether building deformation would result in aging effects not previously considered in the license renewal application (LRA).
In addition, it is not clear if the other program(s) that manage any affected components employ the methods and frequency of inspection to bound those of the Building Deformation program to ensure adequate aging management for affected components.
Request Provide the results of any evaluation in accordance with the requirements of 10 CFR 54.21(a) that demonstrates that for all SCs affected by building deformation caused by ASR expansion, that either (a) the Building Deformation program will specifically inspect and manage for the effects of building deformation; (b) building deformation will not result in behavior of supported SCs that was not previously considered; or (c) the other AMPs that manage aging of the SCs are adequate to ensure that the effects of building deformation do not affect the SCs from performing their intended functions.
Enclosure
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEABROOK STATION, LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC [or NON-PUBLIC, if applicable]
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Tam.Tran@nrc.gov Lois.James@nrc.gov Russell.Chazell@nrc.gov Brian.Wittick@nrc.gov Justin.Poole@nrc.gov David.McIntyre@nrc.gov, OPA Jenny.Weil@nrc.gov, OCA Eugene.Dacus@nrc.gov, OCA Brian.Harris@nrc.gov, OGC Jeremy.Watchuka@nrc.gov, OGC Anita.Ghosh@nrc.gov, OGC Mel.Gray@nrc.gov, RI Fred.Bower@nrc.gov, RI Paul.Cataldo@nrc.gov, RI Peter.Meier@nrc.gov, RI Richard.Barkley@nrc.gov, RI Robert.Vadella@nrc.gov, RI Mark.Draxton@nrc.gov, State Liason Dough.Tiff@nrc.gov, State Liason Neil.Sheehan@nrc.gov, RI PAO Diane.Screnci@nrc.gov, RI PAO Enclosure