Letter Sequence Acceptance Review |
|---|
|
|
MONTHYEARML16139A1812016-05-19019 May 2016
Supplemental Information Needed for Acceptance of Requested Licensing Action Request to Extend Containment Leakage Test Frequency
Project stage: Acceptance Review
SBK-L-16082, Supplement to License Amendment Request 16-01 Request to Extend Containment Leakage Test Frequency2016-05-31031 May 2016
Supplement to License Amendment Request 16-01 Request to Extend Containment Leakage Test Frequency
Project stage: Supplement
ML16158A0182016-06-10010 June 2016
Acceptance of Requested Licensing Action Request to Extend Containment Leakage Test Frequency
Project stage: Acceptance Review
ML16216A2402016-08-0101 August 2016
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. Attachment 1 Markup of UFSAR Pages Enclosed
Project stage: Other
ML16230A1062016-10-0303 October 2016
Request for Additional Information Request to Extend Containment Leakage Test Frequency
Project stage: RAI
SBK-L-16165, Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency2016-10-27027 October 2016
Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency
Project stage: Response to RAI
SBK-L-16190, Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency2016-11-17017 November 2016
Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency
Project stage: Supplement
SBK-L-16205, Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency and EMCB-RAI-22016-12-30030 December 2016
Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency and EMCB-RAI-2
Project stage: Supplement
ML17046A4432017-03-15015 March 2017
Issuance of Amendment Extension of Containment Leakage Rate Test Frequency
Project stage: Approval
SBK-L-17163, Supplement 57 - Revision to License Renewal Application 10 CFR 50 Appendix J Program2017-10-0606 October 2017
Supplement 57 - Revision to License Renewal Application 10 CFR 50 Appendix J Program
Project stage: Supplement
SBK-L-18027, Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program2018-02-28028 February 2018
Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program
Project stage: Supplement
2016-05-31
[Table View] |
|
|---|
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
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 19, 2016 Mr. Eric McCartney Site Vice President Seabrook Station NextEra Energy 626 Lafayette Rd.
Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REQUEST TO EXTEND CONTAINMENT LEAKAGE TEST FREQUENCY (CAC NO. MF7565)
Dear Mr. McCartney:
By letter dated March 31, 2016, NextEra Energy Seabrook, LLC (NextEra) submitted a license amendment request for the Seabrook Station, Unit No. 1. The proposed amendment would revise Technical Specification 6.15, "Containment Leakage Rate Testing Program, to require a program that is in accordance with Nuclear Energy Institute (NEI) Topical Report NEI 94-01, Revision 3-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J." This proposed change will allow extension of the Type A test interval up to one test in 15 years and extension of the Type C test interval up to 75 months, based on acceptable performance history as defined in NEI 94-01, Revision 3-A. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following, as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that NextEra supplement the application to address the information requested in the enclosure by May 31, 2016. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with
E. McCartney the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated timeframe in this letter were discussed with Mr. Michael Ossing of your staff on May 16, 2016.
If you have any questions, please contact me at (301) 415-2048 or Justin.Poole@nrc.gov.
Sincerely, Justin C. Poole, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
cc w/enclosure: Distribution via Listserv
SUPPLEMENTAL INFORMATION NEEDED AMENDMENT REQUEST TO EXTEND CONTAINMENT LEAKAGE TEST FREQUENCY NEXTERA ENERGY SEABROOK, LLC SEABROOK STATION. UNIT NO. 1 DOCKET NO. 50-443
Background
By letter dated March 31, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16095A278), NextEra Energy Seabrook, LLC (NextEra) submitted a license amendment request (LAR) for the Seabrook Station, Unit No. 1 (Seabrook), to revise Technical Specification (TS) 6.15, "Containment Leakage Rate Testing Program." The proposed amendment would revise the TS to require a containment leakage rate testing program that is in accordance with Nuclear Energy Institute (NEI) Topical Report NEI 94-01, Revision 3-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J" (ADAMS Accession No. ML12221A202).
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the LAR and concluded that the following information is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment and exemption in terms of regulatory requirements and the protection of public health and safety and the environment.
EMCB-1 Section 3.2.1.2 of your submittal states that Seabrook has committed, as part of its license renewal, to maintain the exterior surface of the Containment Structure from elevation -30 feet to
+20 feet, in a dewatered state. NRR Office Instruction LIC-109, "Acceptance Review Procedures" (ADAMS Accession No. ML091810088), notes that a requested licensing action should not be accepted if it is contingent upon another review. The license renewal review is not complete, and the adequacy of associated commitments has not been determined by the NRC staff.
Please provide additional explanation of why the dewatering is relevant to this LAR, and if relevant, how this action is being tracked under the current licensing basis.
EMCB-2 NEI 94-01, Revision 3-A, Section 9.2, notes that a visual examination shall be conducted of accessible surfaces of the containment for structural problems that may affect either the containment leakage integrity or the performance of the Type A test. Section 3.2.1.2 of your submittal provides a very high-level summary of the Alkali-Silica Reaction (ASR) concrete degradation indications on the containment structure; however, no discussion is provided about the impacts of the degradation on the containment structure.
Enclosure
Please discuss the ASR degradation impact on the containment, including justification for extending the Type A test interval, considering that the previous test was conducted before ASR indications were identified on the containment building.
APLA-1 The LAR specifies that the technical basis for the proposed change utilizes a risk impact evaluation yielding results within the limits set forth by EPRI Technical Report (TR)
TR-1009325, Revision 2, "Risk Impact Assessment of Extended Integrated Leak Rate Testing Intervals" (ADAMS Accession No. ML072970208). The NRC safety evaluation report for the EPRI TR (ADAMS Accession No. ML081140105) directs the licensee to submit documentation indicating that the technical adequacy of its probabilistic risk assessment (PRA) is consistent with the requirements of RG 1.200, Revision 2, "An Approach for Determining the Technical Adequcay of Probabilistic Risk Assessment Results for Risk-Informed Activities" (ADAMS Accession No. ML090410014), relevant to the integrated leak rate test extension application.
RG 1.200, Revision 2, states that to demonstrate the technical adequacy of the PRA used in an application is of sufficient quality, a discussion of the resolution of pertinent PRA peer review findings and observations (F&Os) must be included.
While Attachment 4, Appendix A, of your submittal provides a high-level summary of industry peer reviews and self-assessments, specific applicable Seabrook F&Os were not included.
Thus, to demonstrate the technical adequacy of the Seabrook PRA against RG 1.200, Revision 2, submit a list of all F&Os cited as findings from the latest full- and focused-scope peer reviews that were conducted for any hazard for which a PRA model exists and was peer reviewed, including any self-assessments that were not closed by a subsequent peer review and for which the PRA failed to meet Capability Category I (CC I) of the applicable PRA standard supporting requirements, including any cited as not met. For each F&O, include details regarding its disposition and an explanation of why not meeting the corresponding CC I requirement has no impact on the application.
ML16139A181 *per e-mail dated 5/6/16 **per e-mail dated 4/25/16 OFFICE NRR/DORL/LPL 1-2/PM NRR/DORL/LPL 1-2/LA NRR/DE/EMCB/BC(A)*
NAME JPoole LRonewicz Yli DATE 5/19/2016 5/19/2016 5/6/2016 OFFICE NRR/DRA/APLA/BC** NRR/DORL/LPL 1-2/BC NRR/DORL/LPL 1-2/PM NAME SRosenberg DBroaddus (AHon for) JPoole DATE 4/25/16 5/19/2016 5/19/2016
