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| {{#Wiki_filter:NExTera April 19, 2011 SBK-L- 11081 Docket No. 50-443 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Seabrook Station Withdrawal of License Amendment Request 10-06 Request to Revise Technical Specification (TS) Sections 6.7.6.k, "Steam Generator (SG)Program," and TS 6.8.1.7, "Steam Generator Tube Inspection Report," For Temporary Alternate Repair Criteria Reference NextEra Energy Seabrook, LLC letter SBK-L-10234, "License Amendment Request to Revise Technical Specification (TS) Sections 6.7.6.k, "Steam Generator (SG) Program," and TS 6.8.1.7, "Steam Generator Tube Inspection Report," for Temporary Alternate Repair Criteria," January 27, 2011 (ML110330202) | | {{#Wiki_filter:NExTera April 19, 2011 SBK-L- 11081 Docket No. 50-443 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Seabrook Station Withdrawal of License Amendment Request 10-06 Request to Revise Technical Specification (TS) Sections 6.7.6.k, "Steam Generator (SG) |
| NextEra Energy Seabrook, LLC (NextEra) submitted License Amendment Request (LAR) 10-06 for an amendment to the Technical Specifications (TS) for Seabrook Station. The proposed change would revise TS 6.7.6.k, "Steam Generator (SG) Program," to exclude portions of the SG tubes below the top of the SG tubesheet from periodic inspections during refueling outage 14 (OR14) in the spring of 2011 and the subsequent inspection cycle. In addition, this amendment request proposed to revise TS 6.8.1.7 "Steam Generator Tube Inspection Report." The requested amendment would have been required if primary water stress corrosion cracking (PWSCC) had been detected during the steam generator tube inspections in the April 2011 refueling outage. The inspections completed with no indications of PWSCC; therefore, NextEra is withdrawing LAR 10-06.1400d NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 United States Nuclear Regulatory Commission SBK-L-11081 Page 2 Should you have any questions regarding this letter, please contact Mr. Michael O'Keefe, Licensing Manager, at (603) 773-7745.Sincerely, NextEra Energy Seabrook, LLC Paul Freeman Site Vice President cc: NRC Region I Administrator G. E. Miller, NRC Project Manager W. J. Raymond, NRC Senior Resident Inspector Mr. Christopher M. Pope, Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399}} | | Program," and TS 6.8.1.7, "Steam Generator Tube Inspection Report," |
| | For Temporary Alternate Repair Criteria Reference NextEra Energy Seabrook, LLC letter SBK-L-10234, "License Amendment Request to Revise Technical Specification (TS) Sections 6.7.6.k, "Steam Generator (SG) Program," |
| | and TS 6.8.1.7, "Steam Generator Tube Inspection Report," for Temporary Alternate Repair Criteria," January 27, 2011 (ML110330202) |
| | NextEra Energy Seabrook, LLC (NextEra) submitted License Amendment Request (LAR) 10-06 for an amendment to the Technical Specifications (TS) for Seabrook Station. The proposed change would revise TS 6.7.6.k, "Steam Generator (SG) Program," to exclude portions of the SG tubes below the top of the SG tubesheet from periodic inspections during refueling outage 14 (OR14) in the spring of 2011 and the subsequent inspection cycle. In addition, this amendment request proposed to revise TS 6.8.1.7 "Steam Generator Tube Inspection Report." |
| | The requested amendment would have been required if primary water stress corrosion cracking (PWSCC) had been detected during the steam generator tube inspections in the April 2011 refueling outage. The inspections completed with no indications of PWSCC; therefore, NextEra is withdrawing LAR 10-06. |
| | 1400d NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 |
| | |
| | United States Nuclear Regulatory Commission SBK-L-11081 Page 2 Should you have any questions regarding this letter, please contact Mr. Michael O'Keefe, Licensing Manager, at (603) 773-7745. |
| | Sincerely, NextEra Energy Seabrook, LLC Paul Freeman Site Vice President cc: NRC Region I Administrator G. E. Miller, NRC Project Manager W. J. Raymond, NRC Senior Resident Inspector Mr. Christopher M. Pope, Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399}} |
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MONTHYEARML1103302022011-01-27027 January 2011 Seabrock - License Amendment Request 10-06, to Revise Technical Specification (TS) Section 6.7.6.k, Steam Generator (SG) Program, & TS 6.8.1.7, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criteria Project stage: Request ML1103502522011-02-23023 February 2011 Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, Opportunity for a Hearing, and Order Imposing Procedures for Document Access.. Project stage: Other NRC-2011-0044, Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, Opportunity for a Hearing, and Order Imposing Procedures for Document Access..2011-02-23023 February 2011 Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, Opportunity for a Hearing, and Order Imposing Procedures for Document Access.. Project stage: Approval ML1103502482011-03-0101 March 2011 License Amendment, Issuance of Amendment, the Proposed Amendment Would Modify Technical Specification 6.7.6.k, Steam Generator, and Technical Specification 6.8.1.7, Steam Generator Tube Inspection Report. Project stage: Approval SBK-L-11081, Withdrawal of License Amendment Request 10-06, Request to Revise Technical Specification (TS) Sections 6.7.6.k, Steam Generator (SG) Program, and TS 6.8.1.7, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criteria2011-04-19019 April 2011 Withdrawal of License Amendment Request 10-06, Request to Revise Technical Specification (TS) Sections 6.7.6.k, Steam Generator (SG) Program, and TS 6.8.1.7, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criteria Project stage: Withdrawal ML1111802212011-05-0202 May 2011 Withdrawal of License Amendment Request 10-06 Project stage: Withdrawal 2011-03-01
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Category:Letter type:SBK
MONTHYEARSBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024 2023 Annual Environmental Operating Report SBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report SBK-L-22093, 75 Day and 150 Day Submittal Letters2022-12-0101 December 2022 75 Day and 150 Day Submittal Letters SBK-L-22113, Radiological Emergency Plan (Ssrep), Revision 792022-11-16016 November 2022 Radiological Emergency Plan (Ssrep), Revision 79 SBK-L-22114, Independent Spent Fuel Storage Installation (Isfsi), Cask Registration2022-11-0909 November 2022 Independent Spent Fuel Storage Installation (Isfsi), Cask Registration SBK-L-22112, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-11-0303 November 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22094, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2022-10-26026 October 2022 Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) SBK-L-22105, Supplement to 2021 Annual Radioactive Effluent Release Report2022-10-24024 October 2022 Supplement to 2021 Annual Radioactive Effluent Release Report SBK-L-22103, 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan2022-10-12012 October 2022 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan SBK-L-22102, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-10-0606 October 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22080, Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 20222022-08-12012 August 2022 Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 2022 SBK-L-22054, SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0909 June 2022 SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections SBK-L-22044, 2021 Annual Radioactive Effluent Release Report2022-04-29029 April 2022 2021 Annual Radioactive Effluent Release Report SBK-L-22036, Steam Generator Tube Inspection Report2022-04-25025 April 2022 Steam Generator Tube Inspection Report SBK-L-22040, Radiological Emergency Plan (Ssrep), Revision 7822022-04-20020 April 2022 Radiological Emergency Plan (Ssrep), Revision 782 SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-22003, Inservice Inspection Examination Report2022-01-24024 January 2022 Inservice Inspection Examination Report SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan2022-01-0404 January 2022 Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan SBK-L-21135, Submittal of Changes to the Seabrook Station Technical Specification Bases2021-12-29029 December 2021 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-21108, Core Operating Limits Report for Cycle 222021-11-0404 November 2021 Core Operating Limits Report for Cycle 22 SBK-L-21106, Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program2021-09-30030 September 2021 Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program SBK-L-21105, Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension2021-09-27027 September 2021 Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension SBK-L-21103, Request for Exercise of Enforcement Discretion2021-09-25025 September 2021 Request for Exercise of Enforcement Discretion SBK-L-21104, Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension2021-09-25025 September 2021 Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension SBK-L-21098, Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-09-22022 September 2021 Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21083, NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage2021-08-18018 August 2021 NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage SBK-L-21067, License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-07-21021 July 2021 License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-022021-06-24024 June 2021 Revision to Updated Final Response to NRC Generic Letter 2004-02 SBK-L-21056, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:2021-05-20020 May 2021 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References: SBK-L-21044, 2020 Annual Radiological Environmental Operating Report2021-04-30030 April 2021 2020 Annual Radiological Environmental Operating Report SBK-L-21045, Submittal of 2020 Annual Radioactive Effluent Release Report2021-04-30030 April 2021 Submittal of 2020 Annual Radioactive Effluent Release Report SBK-L-21042, Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations SBK-L-21033, Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements2021-03-24024 March 2021 Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements SBK-L-21023, Radiological Emergency Plan (Ssrep), Revision 772021-03-0404 March 2021 Radiological Emergency Plan (Ssrep), Revision 77 SBK-L-20154, Submittal of Changes to the Seabrook Station Technical Specification Bases2020-12-22022 December 2020 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-20149, Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-12-0808 December 2020 Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20146, One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c2020-12-0303 December 2020 One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c SBK-L-20144, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-23023 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20143, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-022020-11-19019 November 2020 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-02 SBK-L-20132, Fourth Interval Inservice Testing (IST) Program2020-10-21021 October 2020 Fourth Interval Inservice Testing (IST) Program SBK-L-20127, Generator Tube Inspection Report2020-10-20020 October 2020 Generator Tube Inspection Report SBK-L-20117, Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request2020-09-23023 September 2020 Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request SBK-L-20103, Inservice Inspection Examination Report2020-07-27027 July 2020 Inservice Inspection Examination Report SBK-L-20092, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-4182020-07-13013 July 2020 Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-418 SBK-L-20068, License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating2020-07-13013 July 2020 License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating SBK-L-20085, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-16016 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic SBK-L-20077, Core Operating Limits Report for Cycle 212020-06-0101 June 2020 Core Operating Limits Report for Cycle 21 2024-04-12
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NExTera April 19, 2011 SBK-L- 11081 Docket No. 50-443 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Seabrook Station Withdrawal of License Amendment Request 10-06 Request to Revise Technical Specification (TS) Sections 6.7.6.k, "Steam Generator (SG)
Program," and TS 6.8.1.7, "Steam Generator Tube Inspection Report,"
For Temporary Alternate Repair Criteria Reference NextEra Energy Seabrook, LLC letter SBK-L-10234, "License Amendment Request to Revise Technical Specification (TS) Sections 6.7.6.k, "Steam Generator (SG) Program,"
and TS 6.8.1.7, "Steam Generator Tube Inspection Report," for Temporary Alternate Repair Criteria," January 27, 2011 (ML110330202)
NextEra Energy Seabrook, LLC (NextEra) submitted License Amendment Request (LAR) 10-06 for an amendment to the Technical Specifications (TS) for Seabrook Station. The proposed change would revise TS 6.7.6.k, "Steam Generator (SG) Program," to exclude portions of the SG tubes below the top of the SG tubesheet from periodic inspections during refueling outage 14 (OR14) in the spring of 2011 and the subsequent inspection cycle. In addition, this amendment request proposed to revise TS 6.8.1.7 "Steam Generator Tube Inspection Report."
The requested amendment would have been required if primary water stress corrosion cracking (PWSCC) had been detected during the steam generator tube inspections in the April 2011 refueling outage. The inspections completed with no indications of PWSCC; therefore, NextEra is withdrawing LAR 10-06.
1400d NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
United States Nuclear Regulatory Commission SBK-L-11081 Page 2 Should you have any questions regarding this letter, please contact Mr. Michael O'Keefe, Licensing Manager, at (603) 773-7745.
Sincerely, NextEra Energy Seabrook, LLC Paul Freeman Site Vice President cc: NRC Region I Administrator G. E. Miller, NRC Project Manager W. J. Raymond, NRC Senior Resident Inspector Mr. Christopher M. Pope, Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399