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Category:Letter type:SBK
MONTHYEARSBK-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-21045, Submittal of 2020 Annual Radioactive Effluent Release Report2021-04-30030 April 2021 Submittal of 2020 Annual Radioactive Effluent Release Report SBK-L-21044, 2020 Annual Radiological Environmental Operating Report2021-04-30030 April 2021 2020 Annual Radiological Environmental Operating 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 SBK-L-20057, Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request2020-05-20020 May 2020 Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request 2023-06-22
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FPL Energy Seabrook Station FPL Energy P.O. Box 300 Seabrook, NH 03874 ri Seabrook Station (603) 773-7000 June 18, 2008 Docket No. 50-443 SBK-L-08103 U.S. Nuclear Regulatory Commission Attn.:. J. E. Dyer, Director Office of Nuclear Reactor Regulation One White Flint North 11555 Rockville Pike Rockville, MD 20852-2837 Seabrook Station Notification of Completed Actions and Commitments Addressed in Confirmatory Action Letter In Regard to Alloy 82/182 Butt Welds in the Pressurizer at Seabrook Unit No. 1
Reference:
NRC CAL No. NRR-07-001, Confirmatory Action Letter, Seabrook Station, Unit No. 1, dated March 12, 2007.
FPL Energy Seabrook, LLC (FPL Energy Seabrook) has completed the actions and commitments addressed in the above reference. FPL Energy Seabrook is providing in the enclosure to this letter the results of the pressurizer butt weld inspections and mitigation actions.
Should you have any questions regarding the examination results, please contact Michael Ossing, Engineering Support Manager, at (603) 773-7512.
Sincerely, FPL Energy Seabrook, LLC Gene St. Pierre Site Vice President cc: S.J. Collins, NRC Region I Administrator G.E. Miller, NRC Project Manager, Project Directorate 1-2 W.J. Raymond, NRC Senior Resident Inspector a0 I an FPL Group company ! *J$0
OATH AND AFFIRMATION I, Gene St. Pierre, Site Vice President of FPL Energy Seabrook, LLC, hereby affirm that the information and statements contained within this Notification of Completed Actions and Commitments Addressed in Confirmatory Action Letter NRR-07-001 are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
Sworn and Subscribed before me this day of 2008 ene Site Vice President
/
ENCLOSURE TO SBK-L-08103 Summary of NDE results for Pressurizer Weld Overlay PZR A Safety Nozzle No Recordable NRI, Barrier Layer NRI prior to Five indications were recorded. Four were laminar, lack of bond (LOB)
Indications excavation of indications and one was planar. Below are the dimensions and dispositions (NRI) - Indications adjacent to the volumetric of the indications.
barrier layer were indications Ind. # 1 - 9.80"L x .30"W, Reject identified during the Ind. # 2 - 1.00"L x .30"W, Accept barrier layer PT.
Ind. # 3 - 1.90"L x .30"W, Accept Excavation performed Ind. # 4 - 0.50"L x .30"W, Accept Excavation PT NRI after Ind. # 5 - 2.00"L x .30"W, Reject volumetric Indications # 1 & # 5 excavated and repaired. Indication # 3 was
- Indications identified after indication removal removed/repaired due to it's proximity to the repair cavity. Post repair UT grinding. Excavated to a depth of -. 220" was acceptable.
PT of Excavation area after Indications # 2 and # 4 remain after repairs weld restoration to base UT examination achieved full coverage of both the ISI and PSI examination material - NRI volumes.
PT of SWOL excavation to remove volumetric (UT) indication - NRI The UT exam was acceptable. Three indications were reported. Two were lack of bond (LOB); the other was planar and located within the ISI volume of the original dissimilar metal weld base material. Below are the dimensions and dispositions of the indications.
PZR B Relief Nozzle NRI NRI NRI Ind. # I - 1.10"L x .30"W, Accept Ind. # 2 - 0.80"L x .20"W, Accept Ind. # 3 - 1.2"L Accept per analysis of weld overlay design by vendor.
UT examination achieved full coverage of both the IS1 and PSI examination volumes
One circumferential lack of bond indication was reported in the nozzle radius to taper transition area. The indication dimensions and disposition is NRI prior to below.
excavation of volumetric NRI, Barrier Layer Ind. # 1 - 13.2"L x .40"W, Reject indications Indication # 1 excavated and repaired. The UT of the repair area was PZR C Safety Nozzle NRI PT of SWOL excavation to acceptable. Two lack of bond indications were reported, their dimensions remove volumetric (UT) are listed below indication - NRI NRI after Ind. # 1 - .50"L x .30"W volumetric Ind. # 2 - .40"L x .30"W indication removal UT examination achieved full coverage of both the ISI and PSI examination volumes 4 4 4 Two circumferential lack of bond indication were reported. One was at the nozzle radius to taper transition area and the other was over the safe end material at the interface of the weld overlay and the base material. Below NRI prior to excavation of are the dimensions and dispositions of the indications.
volumetric Ind. # 1 - 4.7"L x .30"W, Reject NRI, Barrier Layer indications Ind. # 2 - 29.0"L(360') x .40"W, Reject PZR D Safety Nozzle NRI PT of SWOL excavation to Indications # 1 & # 2 excavated and repaired. The UT of the repair areas remove volumetric (UT) was acceptable. Two lack of bond indications were reported, their indication - NRI dimensions are listed below NRI after Ind. # 1 - .70"L x .20"W volumetric Ind. # 2 - .70"L x .20"W indication removal UT examination achieved full coverage of both the ISI and PSI examination volumes The UT exam was acceptable. Three indications were recorded in the original dissimilar metal weld base material. These indications are below the PZR Spray Nozzle NRI NRI NRI ISI examination volume.
UT examination achieved full coverage of both the ISI and PSI examination volumes.
Four circumferential indications were reported/recorded. One was a lack of NRI prior to bond (LOB) and the other three were located within the original dissimilar excavation of metal weld base material outside the ISI examination volume. Below are the volumetric dimensions and dispositions of the indications.
NRI, Barrier Layer indications Ind. # I - 51.8'L (360°)x .30"W, Reject PZR Surge Nozzle NRI PT of SWOL excavation to Ind. # 2, # 3 and # 4 were recorded for future reference and were not remove volumetric (UT) evaluated.
indication - NRI Indication # 1 excavated and repaired. The UT of the repair was acceptable.
NRI after volumetric UT examination achieved full coverage of both the ISI and PSI examination indication removal volumes.
a Mitigation Summary The Seabrook Station pressurizer has six piping nozzle welds that were originally made with alloy 82/182 material as identified in the table below. During OR12 refueling outage all six piping nozzles were mitigated using alloy 52 by the method shown below.
Nozzle Mitigation Completed Susceptible Outage Mitigation Performed Function/Designation Material Oution Description Designation Surge "S" Nozzle to safe end OR12 Structural Weld Overlay Line # RC-49-01 weld only Spray "SP" Nozzle to safe end OR12 Structural Weld Overlay Line # RC-48-03 weld only Safety "A" Nozzle to safe end OR12 Structural Weld Overlay Line # RC-74-01 weld only Relief "B" Nozzle to safe end OR12 Structural Weld Overlay Line # RC-80-01 weld only Safety "C" Nozzle to safe end OR12 Structural Weld Overlay Line # RC-75-01 weld only Safety "D" Nozzle to safe end OR12 Structural Weld Overlay Line # RC-76-01 weld only