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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023 Revised Steam Generator Tube Inspection Report SBK-L-22036, Steam Generator Tube Inspection Report2022-04-25025 April 2022 Steam Generator Tube Inspection Report 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-20132, Fourth Interval Inservice Testing (IST) Program2020-10-21021 October 2020 Fourth Interval Inservice Testing (IST) Program SBK-L-20103, Inservice Inspection Examination Report2020-07-27027 July 2020 Inservice Inspection Examination Report SBK-L-19052, Steam Generator Tube Inspection Report2019-04-19019 April 2019 Steam Generator Tube Inspection Report SBK-L-19001, Inservice Inspection Examination Report2019-01-24024 January 2019 Inservice Inspection Examination Report SBK-L-17166, Generator Tube Inspection Report2017-10-17017 October 2017 Generator Tube Inspection Report SBK-L-17117, Inservice Inspection Examination Report2017-07-18018 July 2017 Inservice Inspection Examination Report SBK-L-16100, Inservice Testing Program for the Third 10-Year Interval2016-07-21021 July 2016 Inservice Testing Program for the Third 10-Year Interval SBK-L-16015, Inservice Inspection Examination Report2016-02-10010 February 2016 Inservice Inspection Examination Report SBK-L-14119, Inservice Inspection Examination Report2014-06-14014 June 2014 Inservice Inspection Examination Report SBK-L-13019, Inservice Inspection Examination Report2013-01-28028 January 2013 Inservice Inspection Examination Report SBK-L-11197, Request for Alternative to Use ASME Code Case N-716 to Implement Risk-Informed Inservice Inspection Program2011-11-0707 November 2011 Request for Alternative to Use ASME Code Case N-716 to Implement Risk-Informed Inservice Inspection Program SBK-L-11191, Third Ten-Year Interval Inservice Inspection Relief Requests2011-09-26026 September 2011 Third Ten-Year Interval Inservice Inspection Relief Requests SBK-L-11170, Inservice Inspection Examination Report2011-08-11011 August 2011 Inservice Inspection Examination Report SBK-L-11132, Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program2011-06-22022 June 2011 Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program SBK-L-10027, Inservice Inspection Examination Report for Inspections Conducted Prior to and During the Thirteenth Refueling Outage That Concluded on November 12, 20092010-02-0909 February 2010 Inservice Inspection Examination Report for Inspections Conducted Prior to and During the Thirteenth Refueling Outage That Concluded on November 12, 2009 ML0929201562009-10-0707 October 2009 Seabrook Station - 10 CFR 50.55a Request 2AR-07, Second Interval ISI Program Category B-P Exams - 10-Year Class 1 System Leakage Test SBK-L-09122, Response to Request for Additional Information Regarding a Request for Relief from Inservice Inspection Requirements2009-05-27027 May 2009 Response to Request for Additional Information Regarding a Request for Relief from Inservice Inspection Requirements SBK-L-09038, Supplement to Request for Relief from Inservice Inspection Requirements2009-02-24024 February 2009 Supplement to Request for Relief from Inservice Inspection Requirements SBK-L-08135, Inservice Inspection Examination Report for Inspections Conducted Prior to and During the Twelfth Refueling Outage2008-07-21021 July 2008 Inservice Inspection Examination Report for Inspections Conducted Prior to and During the Twelfth Refueling Outage SBK-L-07088, Steam Generator Inservice Inspection2007-05-23023 May 2007 Steam Generator Inservice Inspection SBK-L-07024, Inservice Inspection Examination Report, for Inspections Conducted Prior to and During the Eleventh Refueling Outage That Concluded on November 10, 20062007-02-0202 February 2007 Inservice Inspection Examination Report, for Inspections Conducted Prior to and During the Eleventh Refueling Outage That Concluded on November 10, 2006 SBK-L-05145, Inservice Inspection Examination Report2005-07-29029 July 2005 Inservice Inspection Examination Report SBK-L-04040, Steam Generator Inservice Inspection2004-10-12012 October 2004 Steam Generator Inservice Inspection ML0403601082004-02-18018 February 2004 Review of Steam Generator Tube Inservice Inspection Report for the 2002 Refueling Outage ML0403706262004-01-29029 January 2004 Transmittal of Inservice Inspection Examination Report ML0331804642003-11-0303 November 2003 Steam Generator Tubes Plugged During Ninth Inservice Inspection ML0327314152003-09-23023 September 2003 Revision to Inservice Test Program Relief Request PR-3 ML0312200282003-04-24024 April 2003 Generator Inservice Inspection ML0225500502002-08-29029 August 2002 Inservice Inspection Examination Report 2023-08-03
[Table view] 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-22042, 1 to Updated Final Safety Analysis Report, Cover Letter and Information on Enclosures 1 to 72022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Cover Letter and Information on Enclosures 1 to 7 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 2024-04-12
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NEXTera ENERGY e SEABROOK July 18, 2017 Docket No. 50-443 SBK-L-17117 United States Nuclear Regulatory Commission Attn.: Document Control Desk Washington, D.C. 20555-0001 Seabrook Station Inservice Inspection Examination Report Enclosed is the NextEra Energy Seabrook, LLC Inservice Inspection Examination Report for inspections conducted prior to and during the eighteenth refueling outage that concluded on May 1, 2017. The enclosed report is submitted pursuant to the requirements of paragraph IWA-6240 of the 2004 Edition of Section XI of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code and approved ASME Code Case N-532-4. Additionally, a copy of this letter and the enclosed report are being submitted to the State of New Hampshire.
Should you have any questions regarding this information, please contact Mr. James Crowley, Engineering Support Manager, at (603) 773-7470.
Sincerely, Licensing Manager NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
United States Nuclear Regulatory Commission SBK-L-17117/Page 2 cc: NRC Region I Administrator NRC Project Manager, Project Directorate I-2 NRC Senior Resident Inspector Wayne Brigham, Boiler Inspector New Hampshire Department of Labor Inspection Division PO Box 2076 Concord, NH 03302-2076
Enclosure to SBK-L-17117 Page 1 of4 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: ISl-SBK-2017 Plant: NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 Commercial Service Date: August 19, 1990 Refueling Outage No.: OR18 Current Inspection Interval: ISi-Third Interval and IWE Second Interval Current Inspection Period: ISi Third Interval Second Period and IWE/IWL Second Interval Second Period Edition and Addenda of Section XI applicable to the inspection plans:*
ISi Third lnterval-2004 Edition No Addenda and IWE/IWL Second lnterval-2004 Edition No Addenda Date and Revision of inspection plans: ISi Third Interval and IWE/IWL Second Interval Effective -
December 28, 2016 Rev. 17 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan: ASME Section XI 2004 Edition no Addenda Code Cases Used: Approved Code Cases listed in Inspection Plan CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of OR18 conform to the requirements of Section XI.
Signed _ _ _ _ __ _._- -~-=-
- Owner or Owners Designee, Title
- ~ ______ Date -~?.....,...0_...~_,_0___Y___7_
7 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Hampshire and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford, CT have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. F.urt ore, neither the inspector nor his employer shall be liable in any manner for any per: o I inj y or property damage or loss of any kind arising from or connected with this insp i n.
- / Commissions f.LB l()7 tS- B,X
- :, N., R. i N.li 7(;,{)
National Board, State, Province and Endorsements Date 7- l!J-'9c {2
Page 2 of 4 FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Category and Evaluation Description Description Item Number E-A Degradation of For OR18, of the 21 Leak Chase Test Connections (LCTC)
E1.30 Moisture Barrier examined, evidence of degradation was identified in 11 LCTCs.
Two LCTCs were found with pressurized water, five with water present when viewed by a boroscope, and four were moist when viewed by a boroscope.
Chemistry was able to sample two of the seven LCTCs with water that had been noted by the boroscope examination. The boroscope cable is very small and able to navigate and extend through the tubing bends where the chemistry tubing used to draw a sample could not travel as far to obtain a sample.
Chemistry ran a comparable analysis on these two OR18 samples as was done in OR17. Both OR18 samples have a pH of 13.
There is no indication with these results that groundwater is leaking into the liner area. The gamma results are also consistent with OR 17 results and that these LCTC water samples are not indicative of active leaks. Overall the locations examined by boroscope appear to be in good condition with no significant level of corrosion/metal loss identified.
Based on the information and data obtained, it is evident that the inaccessible portions of the liner plate have maintained their specified design function as a leak-tight membrane.
Although a qualified NOE method could not be performed on the liner plate in locations associated with degraded moisture barriers, the body of information included in this evaluation supports the conclusion that the inaccessible portions of the liner plate have not experienced any appreciable loss of material that would compromise the liner plate's ability to perform its specified design function.
The following summarizes the information collected that support the conclusion that the liner plate has maintained its ability to perform its specified design function.
The qualitative visual inspections performed did not show any significant degradation of the liner plate.
Rate of corrosion for one outage is minimal, 0.0025 in/yr.
In 2008, an ILRT was performed on the containment structure
Page 3 of 4 FORM OAR-1 OWNER'S ACTIVITY REPORT and the results of that test showed that the containment structure was performing its specified design function.
Examination results indicate that no appreciable corrosion has occurred since the last ILRT in 2008, so there is no reason to expect the liner plate has degraded to a point of loss of containment integrity.
Based on the chemical comparison performed the leakage source is from internal to the containment. Additionally, the observed high pH is indicative of a low corrosive environment.
Using the general corrosion rate of 0.0025 inches per year and a general wall loss of 0.1875 inches for the base mat liner and cylinder wall liner, a 75 year life is supported .
In summary, based on the examinations, chemistry analysis, design , and the corrosion assessment, reasonable assurance exists to conclude that the liner has maintained the ability to perform its specified design function and that the liner plate is capable of performing its specified design function.
Page 4 of 4 FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Repair/Replacement Code Class Description Of Work Completed Plan Number Modification of Add Weld-o-let Service Water 40494687-07 3 to contain thru 02/02/2017 line SW-1818- EC 288230 wall leak 001 Modification of Add Weld-o-let Service Water 40516918-03 3 to contain thru 02/11/2017 line SW-1827- EC 288303 wall leak 001