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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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NEx~era ENEFRGY-7X August 1, 2012 Docket No. 50-443 SBK-L-12137 U.S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20582.
Seabrook Station Relief Request - Proposed Alternative in accordance with 10 CFR 50.55a (a)(3)(ii)
Pursuant to 10 CFR 50.55a(a)(3)(ii), NextEra Energy Seabrook, LLC (NextEra Energy Seabrook) respectfully requests approval for an alternative to the requirements of ASME Code,Section XI, subarticle IWA 4422.1. NextEra Energy Seabrook is planning to examine Class 3 service water (SW) system buried piping in accordance with the requirements of the Seabrook Station buried piping program during the upcoming fall 2012 refueling outage. Some portions of the buried SW piping to be inspected are located more than 24 feet below grade, with run lengths several hundred feet from the point of entry. Should areas requiring repair be detected during these inspections, NextEra Energy Seabrook requests relief from ASME Code,Section XI, subarticle IWA 4422.1 requirements that defective portions of components be removed prior to performing a repair activity by welding. NextEra Energy Seabrook is in the third 10-year inservice inspection interval which ends August 18, 2020.
Details of the request are contained in the attachment to this letter. NextEra Energy Seabrook.requests approval of this request by September 25, 2012, to support schedules for inspecting portions of the Seabrook Station service water system during the fall 2012 refueling outage.
NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
United States Nuclear Regulatory Commission SBK-L-12137/Page 2 If you have any questions regarding this submittal, please contact Mr. Michael O'Keefe, Licensing Manager, at (603) 773-7745.
Sincerely, NextEra Energy Seabrook, LLC Kevin T. Walsh Site Vice President
Attachment:
Request RA-12-001, Proposed Alternative in accordance with 10 CFR 50.55a (a)(3)(ii) cc:
W. M. Dean, NRC Region I Administrator J. G. Larnb, NRC Project Manager W. J. Raymond, NRC Senior Resident Inspector
Attachment to SBK-L- 12137 Request RA-12-001 Proposed Alternative in accordance with 10 CFR 50.55a (a)(3)(ii)
SEABROOK STATION UNIT 1 RELIEF REQUEST RA-12-001, REVISION 0 Proposed Alternative in accordance with 10 CFR 50.55a (a)(3)(ii)
Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
- 1. ASME Code Component Affected The affected piping is the A train 24-inch diameter service water supply pipes, line numbers 1801-3 and 1818-3, which supply cooling water to the Primary Component Cooling Water (PCCW) Heat Exchanger CC-E- 17-A. These lines supply seawater to the PCCW Heat Exchanger, which is used to remove heat from systems and components during normal plant operation and emergency plant evolutions.
- 2. Applicable Code Edition and Addenda The applicable Code of Record for the current 10-Year Inservice Inspection (ISI) program is the ASME Code,Section XI, 2004 Edition with no Addenda. The affected portion of the service water piping was designed and constructed in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section III, Subsection ND, 1977 Edition, with no Addenda.
- 3. Applicable Code Requirement IWA-4422.1 requires that defects be removed or reduced to an acceptable size prior to implementing a repair or replacement in accordance with the requirements of IWA-4000.
The proposed repair method would not be consistent with IWA-4422. 1.
- 4. Reason for Request During the scheduled September 2012 refueling outage, NextEra Energy Seabrook personnel and/or their representatives will be entering the A train service water buried piping for the purpose of inspecting the integrity of the cement lining. The potential exists for the identification of a localized area of liner loss and the need for repair.
Adherence to all of the provisions of ASME Section XI, Article IWA-4000 will be challenging due to the confined space of the piping inside diameter (ID) of 22.50 inches (24-inch nominal pipe, standard schedule, 0.375-inch liner), which presents a significant safety concern. Some portions of the buried SW piping are located 24.50 feet below grade, with pipe run lengths several hundred feet from the point of entry. Full defect removal of discovered thin wall sections may result in a through wall defect. This case, and in those situations where a through wall defect is discovered, would result in the potential for in-leakage of groundwater into the pipe along with possible exposure to asbestos used in the external pipe wrap. Full defect removal for these cases presents a significant safety concern.
- 5. Proposed Alternative and Basis for Use In lieu of the requirements of IWA-4422.1 discussed above, NextEra will not remove the degraded area prior to implementing an IWA-4000 repair. The corroded areas will be cleaned and assessed visually for signs of other damage mechanism, specifically the presence of cracking. If the degraded area appears consistent with no cracking present, 1
the area will be repaired by the application of an encapsulation device (Figure A) in accordance with the provisions of IWA-4000.
The structural repair consists of a 6" diameter circular encapsulation device designed to accommodate the design pressure as well as mechanical loading. Since welding of the cap will impact the capability of the exterior wrap to preclude outer diameter (OD) corrosion due to contact with ground water, no credit will be taken for the localized external wrap in determining the service life of the repair. The encapsulation cap ID will be such that the inside diameter is greater than the maximum diameter of the defective area plus a minimum of twice the nominal thickness of the pipe.
- a. Materials and Installation The material of the component to be repaired is concrete lined Standard Wall, Carbon Steel, SA 106, Grade B. The proposed encapsulation device material is SA 105 or SA 350 Grade LF2, while the welding process to be used in this repair is metal inert gas (MIG) with an ER 70S-6 weld wire.
The welding will be performed per the requirements of ASME Code,Section XI using qualified welders and the weld procedure will be qualified in accordance with ASME Code,Section XI.
- b. Design Parameters The applied encapsulation device is a pipe restoration approach equivalent to an unstayed flat head. ASME Section III, Subsection ND Figure ND-3325-1 depicts acceptable configurations for flat heads. The relevant configuration for the encapsulation device is shown in Figure b-2 of Figure ND-3325-1. The dimension of the cap top, skirt, and full penetration weld to the pipe are based upon the metal area replacement Code methodology and considers design pressure, external soil pressure, as well as mechanical loading. The size (outer diameter) of the cap considered the conservative assumption of future metal loss due to both seawater (internal content) and groundwater (external environment) during the period of service.
- c. Non-Destructive Examination Initial surface cleanup will be performed and a contour gauge will be used to determine the extent of wall loss. Upon discovery of a degraded area with pipe wall thickness less than Code required, further cleaning will be performed. UT examination will be used to establish that the existing surrounding area, consisting of good wall (sufficient wall thickness to support welding of the repair) is available. This UT examination will address the possible existence of external OD corrosion. Liquid penetrant or magnetic particle examination of the final attachment weld pass shall be performed. Its application results in a full Code approved structural repair with the exception being removal of the degraded material and resultant inaccessibility for future inspection.
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- d. Post Repair Monitoring Plan Upon return to operation, and in consideration that the pipe is buried, post repair Monitoring is not possible. The repaired location will be placed into the NextEra Energy Seabrook Buried Pipe Inspection Program. A future excavation of the piping will be performed prior to the end of the 36 month service period for the purpose of defect removal from the exterior and repair of the external wrap.
- e. Degradation Mechanism Seabrook Station typically uses 30 mills per year (mpy) for a corrosion rate of carbon steel piping exposed to seawater. Based upon industry review, a conservative corrosion rate of 10 mpy is being used for the exterior of the carbon steel pipe subjected to groundwater. A total corrosion rate of 40 mpy will be used to ensure that the potential continued corrosion of the encapsulated pipe wall as well as the inner surface of the cap and its attachment welds remain intact during the intended service life of the repair. The 40 mpy is a conservative value as the pipe and encapsulation device that will be exposed to seawater inside the pipe will have a protective liner that will inhibit seawater degradation.
- f. Applicable Loads The encapsulation device will be designed to accommodate all appropriate deadweight, pressure, and seismic loads. Since the system is a moderate energy system which operates at a low temperature, differential thermal expansion between the encapsulation device and the repaired component is not a concern.
- 6. Duration of Proposed Alternative Use of the relief request resulting in the installation of the internal encapsulation device will have a limited service life of two operating cycles (approximately 36 months).
Encapsulation of the degraded area shall be used only once at each identified location.
- 7. Precedent I. Indian Point Nuclear Generating Unit No. 3 - Relief Request (RR) No. RR-3-43 for Temporary Non-Code Repair of Service Water Pipe (ML080280073).
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SEABROOK STATION UNIT 1 RELIEF REQUEST RA-12-001, REVISION 0 FIGURE A 4