Letter Sequence Approval |
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TAC:MF4572, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
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MONTHYEARSBK-L-14024, License Amendment Request (LAR) - 14-01, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler - 523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated.2014-06-24024 June 2014 License Amendment Request (LAR) - 14-01, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler - 523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated. Project stage: Request SBK-L-14080, Changes to Technical Specification 3.3.3.1. Radiation Monitoring for Plant Operations2014-07-24024 July 2014 Changes to Technical Specification 3.3.3.1. Radiation Monitoring for Plant Operations Project stage: Request ML14245A2042014-09-0909 September 2014 Acceptance of Proposed Licensing Amendment Request Regarding Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations Project stage: Acceptance Review ML14276A4312014-10-30030 October 2014 Request for Additional Information Regarding License Amendment 14-03, Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations Project stage: Approval SBK-L-14184, Supplement to LAR 13-05, LAR 14-01, LAR 14-02 and LAR 14-03 in Response to Issuance of Amendment 141, Risk-Informed Justifications for Relocation of Specific Surveillance Frequency Requirements to Surveillance Frequency Control Program2014-12-11011 December 2014 Supplement to LAR 13-05, LAR 14-01, LAR 14-02 and LAR 14-03 in Response to Issuance of Amendment 141, Risk-Informed Justifications for Relocation of Specific Surveillance Frequency Requirements to Surveillance Frequency Control Program Project stage: Supplement SBK-L-14202, Response to Request for Additional Information Regarding License Amendment 14-03 Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations2014-12-11011 December 2014 Response to Request for Additional Information Regarding License Amendment 14-03 Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations Project stage: Response to RAI ML15147A6742015-05-11011 May 2015 NRR E-mail Capture - for Your Review - Draft Second Round RAI - Seabrook Radiation Monitor LAR (MF4572) Project stage: Draft Approval ML15152A3102015-06-0101 June 2015 NRR E-mail Capture - for Your Review - Draft Second Round RAI - Revised - Seabrook Radiation Monitor LAR (MF4572) Project stage: Draft Approval 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 Project stage: Approval SBK-L-15109, Response to Second Request for Additional Information Regarding License Amendment 14-03, Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations2015-06-30030 June 2015 Response to Second Request for Additional Information Regarding License Amendment 14-03, Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations Project stage: Request ML15096A1312015-07-17017 July 2015 Issuance of Amendment Regarding Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations Project stage: Approval 2014-09-09
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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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23318A0772023-11-14014 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 ML14324A6372014-11-24024 November 2014 Request for Additional Information Regarding License Amendment Request to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement 2023-06-22
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Text
October 30, 2014 Mr. Dean Curtland, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT 14-03, CHANGES TO TECHNICAL SPECIFICATION 3.3.3.1, RADIATION MONITORING FOR PLANT OPERATIONS (TAC NO. MF4572)
Dear Mr. Curtland:
By letter dated July 24, 2014 (Agencywide Documents Access and Management System Accession No. ML14209A919), NextEra Energy Seabrook, LLC (NextEra or the licensee) requested a license amendment request (LAR) to change the Technical Specifications (TSs) for Seabrook Station, Unit 1 (Seabrook). The proposed LAR would modify TS 3.3.3.1, Radiation Monitoring for Plant Operations.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is required to complete its review. The NRC staff's request for additional information (RAI) is contained in the enclosure.
A draft of these questions was previously sent to Mr. Mike Ossing of your staff on October 1, 2014, with an opportunity to have a teleconference to ensure that NextEra understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed.
A conference call was held on October 23, 2014, and Mr. Kilby of your staff agreed that NextEra would respond to the RAI by December 12, 2014. Please note that if you do not respond to the RAI by the agreed upon date, the NRC staff may reject your amendment under the provisions of 10 CFR, Section 2.108, Denial of application for failure to supply information.
D. Curtland If you have any questions, please contact me at (301) 415-3100.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
ML14276A431
- via e-mail **via memo OFFICE LPL1-2/PM LPL1-2/LA* ARCB/BC** SCVB/BC** LPL1-2/BC LPL1-2/PM NKaripineni NAME JLamb ABaxter UShoop MKhanna JLamb for RDennig DATE 10/15/14 10/14/14 10/01/14 10/14/14 10/30/14 10/30/14 REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST 14-03 CHANGES TO TECHNICAL SPECIFICATION 3.3.3.1, RADIATION MONITORING FOR PLANT OPERATIONS NEXTERA ENERGY SEABROOK, LLC SEABROOK STATION, UNIT 1 DOCKET NUMBER 50-443 1.0 SCOPE By letter dated July 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14209A919), NextEra Energy Seabrook, LLC (NextEra or the licensee) requested a license amendment request (LAR) to change the Technical Specifications (TSs) for Seabrook Station, Unit 1 (Seabrook). The proposed LAR would modify TS 3.3.3.1, Radiation Monitoring for Plant Operations.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is required to complete its review.
2.0 REQUEST FOR ADDITIONAL INFORMATION ARCB-RAI-1 In a letter dated November 7, 2013 (ADAMS Accession No. ML13246A358), the NRC staff informed the Technical Specifications Task Force (TSTF) of concerns that the NRC staff had recently identified during a review of plant-specific license amendments requesting adoption of three travelers including traveler TSTF-51, Revision 2, Revise Containment Requirements during Handling Irradiated Fuel and Core Alterations (ADAMS Accession No. ML040400343).
In a letter dated July 24, 2014, page 9 of the LAR states that the proposed change is consistent with TSTF-51-A.
TSTF-51 states, in part, that:
The addition of the term recently associated with handling irradiated fuel in all of the containment function Technical Specification requirements is only applicable to those licensees who have demonstrated by analysis [emphasis added] that after sufficient radioactive decay has occurred, off-site doses resulting from a fuel handling accident remain below the Standard Review Plan limits (well within 10 CFR 100) [or 10 CFR 50.67].
Enclosure
NUREG-0800, Standard Review Plan (SRP) 15.0.1, Radiological Consequence Analyses Using Alternative Source Terms, dated July 2000 (ADAMS Accession Number ML003734190),
states, in part, that:
The models, assumptions, and parameter inputs used by the licensee should be reviewed to ensure that the conservative design basis assumptions outlined in RG-1.183 have been incorporated.
Appendix B of Regulatory Guide (RG) 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (ADAMS Accession Number ML003716792), Regulatory Position 1.1 states, in part, that:
The number of fuel rods damaged during the accident should be based on a conservative analysis that considers the most limiting case.
After reviewing the information submitted by NextEra that is consistent with TSTF-51, the NRC staff would like to review an analysis that shows that the fuel handling accident (FHA) doses remain within regulatory limits (when references to Core Alterations and irradiated fuel are removed from the TSs). The analysis cited on page 9 of the LAR (Amendment No. 94, dated October 3, 2003, ADAMS Accession Number ML032740512) does not appear to consider an inoperable Manipulator Crane Area Monitor with movement of loads other than irradiated fuel assemblies (such as sources, new fuel, tools or reactivity components).
- a. For the proposed change, please provide an FHA analysis that evaluates the dropping of loads allowed over irradiated fuel assemblies (i.e., sources, new fuel or reactivity control components) onto irradiated fuel assemblies with an inoperable Manipulator Crane Area Monitor. The analysis should only credit those safety systems required to be operable as required by TS. Provide the inputs, assumptions and methodology used, and the results. Provide a justification for any assumptions made. Although it is not required, the NRC staff has found it more efficient if the licensees calculation is provided.
- b. The LAR cites Amendment No. 94 as a justification for the proposed LAR, but Amendment No. 94 does not appear to support the current licensing basis. In Amendment No. 100, dated February 24, 2005 (ADAMS Accession Number ML050320373), a revised FHA was approved. At the time the revised FHA was approved, it appears that TS 3.3.3.1 required instrumentation that initiates containment ventilation isolation. Without the isolation of the containment purge system operable, radioactivity from the FHA could be released from the containment purge and exhaust system. Amendment No. 100 assumes the containment personnel hatch is the release pathway. Justify why releases from the containment and purge exhaust system (with an inoperable containment purge system) result in FHA doses that are lower than those from the containment personnel hatch.
ARCB-RAI-2 TS 3.3.3.1 requires two operable channels of the containment post-Loss-of-Coolant Accident (LOCA) area radiation monitor in Modes 1 through 6. On the other hand, TS 3.3.3.6, Accident Monitoring Instrumentation (AMI), only requires operability of the monitor in Modes 1, 2, and 3.
NextEra stated that deleting the monitor from TS 3.3.3.1 is justified, because TS 3.3.3.6 specifies the appropriate requirements for the monitor [AMI]. NextEra also stated that plant conditions in Modes 4, 5, and 6 are such that the likelihood of an event that would require AMI instrumentation is low; therefore, the AMI instrumentation is not required.
Reasonable assurance of adequate protection cannot be based solely on the probability of the accident occurring or risk. Current TSs like TS 3.4.8, Specific Activity, are APPLICABLE in Modes 1-5, because design basis accidents (i.e., Main Steamline Break, Steam Generator Tube Rupture) can occur in MODES other than 1-3. Therefore, the NRC staff requests that the licensee provide an additional justification why the current APPLICABILITY of ALL MODES should be removed from the TS for the AMI.
SCVB-RAI-1 This RAI is regarding the Proposed Change to Functional Units 5.a.1 and 5.a.2, Control Room East/West Isolation Air Intake Radiation Level.
The following excerpt comes from Page 5 of the Enclosure to the LAR dated July 24,2014 (ADAMS Accession No. ML14209A919).
The control room ventilation system, which includes redundant emergency cleanup subsystems, prevents the buildup of airborne particulates and radioactive iodines in the control room complex during an accident. Two remote air intakes (east and west), with two radiation monitors in each intake, are provided to furnish makeup air to the control room complex.
The following excerpt comes from Page 28, Section 12.3, Revision 15 of the Seabrook Station UFSAR (ADAMS Accession No. ML13134A088 - Document Date April 26, 2013):
Control Room Air Intake Monitors - Channels 6506A and B, 6507A and B Four detectors (Channels 6506A and B, 6507A and B) are located in the east air intake piping and four detectors are located in the west air intake piping. These detectors are located in the Control and Diesel Building. These GM detectors, which are Class 1E, monitor the control room air intake and automatically shut down, on a high radiation signal, the control room ventilation fans and isolation dampers.
Each monitor utilizes a two-out-of-two detector logic such that two detectors must be in alarm before the monitor initiates an isolation signal. These detectors are directly mounted in the air intake stream and do not require shielding.
The LAR details two radiation monitors in each intake. The Updated Final Safety Analysis Report (UFSAR) details four radiation detectors each in both the east and west air intake piping.
Please identify which document is correct.
SCVB-RAI-2 This RAI is regarding the Proposed Change to Functional Unit 2.a - Containment Ventilation Isolation On Line Purge Monitor.
The first paragraph on Page 8 of the Enclosure to SBK-L-14080 to the LAR (ADAMs Accession No. ML14209A919) reads:
The proposed change deletes the on line purge monitor from TS 3.3.3.1 because TS 3.3.2 provides essentially the same requirements for the instrument with the exception of the trip setpoints. However, the setpoint specified in TS 3.3.2, which will be retained in the TS, is more conservative than the setpoint in TS 3.3.3.1 .
The NRC staff notes that the TS 3.3.3.1, Table 3.3-6 Table Notation associated with the Alarm/Trip Setpoint of *reads in its entirety *Two times background; purge rate will be verified to ensure compliance with Offsite Dose Calculation Manual (ODCM) Control C.7.1.1 requirements. With the proposed change to Functional Unit 2.a, the requirement to verify that the purge rate is in compliance with the ODCM Control C.7.1.1 requirements will be deleted.
Please provide the regulatory justification for the deletion of this TS requirement.