Letter Sequence Other |
---|
|
|
MONTHYEARML0402105392004-01-14014 January 2004 ASME Section III Request for the Service Water and Service Water Cooling Tower Pumps Project stage: Request ML0422603122004-10-12012 October 2004 Relief, American Society of Mechanical Engineers Boiler and Pressure Vessel Code - Relief for Class 3 Service Water Piping System Project stage: Other 2004-01-14
[Table View] |
|
---|
Category:Code Relief or Alternative
MONTHYEARML22262A3142022-10-0404 October 2022 Relief Requests 3IR-18 and 3IR-19, Relief from the Requirements of the ASME Code ML22116A2442022-04-26026 April 2022 Acceptance of Requested Licensing Action Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage ML20237F3442020-09-21021 September 2020 Authorization of Alternative (Relief Request 3IIR-7) from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (EPIDs L-2020-LLR-0055, L-2020-LLR-0056, and L-2020-LLR-0057) ML20101L0402020-04-10010 April 2020 Acceptance of Requested Licensing Action Relief Request to Use Code Case OMN-13 with 2012 Edition of the OM Code ML20101H3912020-04-0808 April 2020 Verbal Authorization for Seabrook Relief Request 3IIR-7 SBK-L-20049, Relief Request 3IIR-7, Proposed Alternative to Deter Examinations Beyond the 1 Year Code Allowable2020-04-0505 April 2020 Relief Request 3IIR-7, Proposed Alternative to Deter Examinations Beyond the 1 Year Code Allowable SBK-L-20017, Relief Request SG-1 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Use of Code Case OMN-13 with 2012 Edition of the OM Code2020-03-20020 March 2020 Relief Request SG-1 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Use of Code Case OMN-13 with 2012 Edition of the OM Code ML20076D2812020-03-17017 March 2020 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML19340A1282019-12-13013 December 2019 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML19249B1012019-09-30030 September 2019 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code; Relief Request RA-19-001 ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-07-24024 July 2017 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML17065A1482017-03-27027 March 2017 Relief from the Requirements of the ASME Code ML17080A0382017-03-27027 March 2017 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code SBK-L-17027, Relief Request RA-17-002, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2017-02-0606 February 2017 Relief Request RA-17-002, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML14071A4102014-04-10010 April 2014 Request for Relief RA-14-001 from American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI Requirements Regarding the Reactor Vessel Head Flange Seal Leak Detection Piping (TAC No. Mfxxxx) ML12144A2402012-06-0404 June 2012 Second 10-Year Interval Inservice Inspection Program Plan Request for Relief No. 2lR-17 ML12145A1702012-06-0404 June 2012 Second 10-Year Interval Inservice Inspection Program Plan Request for Relief No. 2lR-20 SBK-L-11192, Request for Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds2011-10-27027 October 2011 Request for Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds ML1031901392010-11-22022 November 2010 Relief Request for Use of Alternate Depth Sizing Qualification, Third 10-Year Interval ML1023503412010-10-15015 October 2010 Relief Request for System Pressure Test Examinations on Class 1 Component Pressure Boundaries, Third 10-Year Interval ML1013801662010-06-0303 June 2010 Relief Request for Containment Building Spray Pump Bearing Vibration Alert Range Limit, Third 10-Year Interval 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-08204, CFR 50-55a Request for Alternative Requirements for ASME Class 1 Upper Level Instrumentation Lines on the Pressurizer2008-12-11011 December 2008 CFR 50-55a Request for Alternative Requirements for ASME Class 1 Upper Level Instrumentation Lines on the Pressurizer SBK-L-08174, Request for Relief to Use of an Alternate Depth Sizing Qualification Requirement for Coordinated Implementation of ASME Section XI, Supplements 2 and 10 for Piping Examinations Performed from Inside Surface2008-09-30030 September 2008 Request for Relief to Use of an Alternate Depth Sizing Qualification Requirement for Coordinated Implementation of ASME Section XI, Supplements 2 and 10 for Piping Examinations Performed from Inside Surface SBK-L-08175, Request for Relief from Inservice Inspection Requirements2008-09-30030 September 2008 Request for Relief from Inservice Inspection Requirements ML0422603122004-10-12012 October 2004 Relief, American Society of Mechanical Engineers Boiler and Pressure Vessel Code - Relief for Class 3 Service Water Piping System ML0334400092004-02-0404 February 2004 Relief Inservice Testing Program Relief Request PR-3 ML0310705102003-05-30030 May 2003 Relief, from ASME Code Operations and Maintenance Code Istb 4.3(e)(1) Ten-Year Interval Inservice Test for Containment Spray Pumps CBS-P9A and CBS-P9B (Tac No. MB6676) ML0314100182003-05-0909 May 2003 Inservice Test Program Relief Request PR-3 ML0134603962002-01-28028 January 2002 Inservice Inspection Program Relief Requests 2AR-03, 2AR-04, 2AR-05, and 2IR-14 2022-04-26
[Table view] 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:Safety Evaluation
MONTHYEARML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements ML23073A1562023-03-23023 March 2023 Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code ML22287A1572022-12-0505 December 2022 Issuance of Amendment No. 171 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22262A3142022-10-0404 October 2022 Relief Requests 3IR-18 and 3IR-19, Relief from the Requirements of the ASME Code ML22230C9242022-09-30030 September 2022 Issuance of Amendment No. 170 Revision of 120-Volt AC Vital Instrument Panel Requirements ML21008A0142021-02-25025 February 2021 Issuance of Amendment No. 168 Revise Technical Specification Table 3.3.4 to Change Time Delay Setpoints for Degraded Voltage Relays ML20293A1572020-12-28028 December 2020 Issuance of Amendment No. 167 Reactor Trip System Instrumentation Technical Specification Changes to Implement WCAP-14333 and WCAP-15376 ML20298A2532020-11-24024 November 2020 Issuance of Amendment No. 166 Revise Technical Specification 3/4.8.1, A.C. Sources Operating ML20070Q0712020-03-27027 March 2020 Issuance of Amendment No. 165 Emergency Core Cooling System Accumulator Technical Specification Changes ML20076D2812020-03-17017 March 2020 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML20073E4342020-03-17017 March 2020 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19340A1282019-12-13013 December 2019 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML19326C4802019-12-0505 December 2019 Issuance of Amendment No. 163 One-Time Change to the Onsite Power Distribution Requirements ML19224A5632019-11-18018 November 2019 Issuance of Amendment No. 162 Revisions to Technical Specifications Associated with Movable Control Rods ML19249B1012019-09-30030 September 2019 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code; Relief Request RA-19-001 ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19065A2152019-03-29029 March 2019 Issuance of Amendment No. 160 Measurement and Assessment Frequency for Technical Specification 6.7.6.l, Control Room Envelope Habitability Program ML18204A2912019-03-11011 March 2019 Issuance of Amendment No. 159 Methodology for Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction ML18247A5382018-11-27027 November 2018 Issuance of Amendment No. 158 Removing Requirement to Perform Certain Surveillance Requirements During Shutdown and Changes to Administrative Technical Specifications ML18199A6092018-08-0707 August 2018 Issuance of Amendment No. 157 Changes to the Technical Specifications Requirements for DC Batteries (CAC No. MG0046; EPID L-2017-LLA-0289) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML17102A8892017-04-13013 April 2017 Issuance of Amendment Licensing Basis Change for Service Water Cooling Tower ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17080A0382017-03-27027 March 2017 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML17046A4432017-03-15015 March 2017 Issuance of Amendment Extension of Containment Leakage Rate Test Frequency ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16321A4182016-12-0101 December 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 (CAC Nos. MF0836 and MF0837) ML15096A2552015-11-0202 November 2015 Issuance of Amendment Regarding License Amendment Request 14-04, Revised Reactor Coolant System Pressure-Temperature Limits Applicable for 44 Effective Full Power Years ML15231A1442015-10-0606 October 2015 Issuance of Amendment No. 150 Regarding Note for Reactor Coolant System Surveillance Requirements ML15096A1432015-07-28028 July 2015 Exemption from Specific Requirements of 10 CFR Part 50, Appendix G, and 10 CFR 50.60 ML15205A3332015-07-28028 July 2015 Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Request for Exemption from Table 1 of 10 CFR Part 50, Appendix G NextEra Energy Seabrook, LLC Seabrook Station, Unit 1 Docket No. 50-443 ML15096A1312015-07-17017 July 2015 Issuance of Amendment Regarding Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations ML15118A6322015-05-18018 May 2015 Issuance of Amendment Regarding License Amendment Request Regarding New Fuel Valut ML15082A2332015-04-24024 April 2015 Issuance of Amendment Regarding Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement ML15058A7062015-04-22022 April 2015 Issuance of Amendment No. 146 Regarding the Cyber Security Plan Implementation Schedule ML15002A2512015-03-31031 March 2015 Unit No.1 - Issuance of Amendment Regarding License Amendment Request 14-06, Application Regarding the Removal of the Cold Leg Injection Permissive from Technical Specifications ML14345A2882015-02-0606 February 2015 Issuance of Amendment Regarding Technical Specifications Task Force Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation Using the Consolidated Line Item Improvement Process ML14363A2752015-02-0404 February 2015 Non-Proprietary SE for Issuance of Amendment Regarding License Amendment Request Regarding Fixed Incore Detector System Analysis ML14184A7952014-09-0303 September 2014 Issuance of Amendment Regarding License Amendment Request Regarding Fuel Storage Changes ML13212A0692014-07-24024 July 2014 Issuance of Amendment Regarding the Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML14071A4102014-04-10010 April 2014 Request for Relief RA-14-001 from American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI Requirements Regarding the Reactor Vessel Head Flange Seal Leak Detection Piping (TAC No. Mfxxxx) ML14029A4452014-03-0606 March 2014 Issuance of Amendment Regarding License Amendment Request 12-04, Application Regarding Cold Leg Injection Permissive ML13213A1432014-03-0505 March 2014 Issuance of Amendment Regarding the Use of Optimized Zirlo Fuel Rod Cladding Material ML13247A7772014-02-0909 February 2014 Request for Relief to Use an Alternative to the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML13107A0162013-10-25025 October 2013 Issuance of Amendment Regarding the License Amendment Request 13-02, Application to Revise Technical Specifications to Adopt TSTSF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.. ML13074A7602013-06-17017 June 2013 Issuance of Amendment Regarding the Administrative Changes and Corrections to the Technical Specifications ML13050A1382013-06-13013 June 2013 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML1130000632013-04-23023 April 2013 Issuance of Amendment Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System 2023-03-23
[Table view] |
Text
October 12, 2004 Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO. 1- AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE - RELIEF FOR CLASS 3 SERVICE WATER PIPING SYSTEM (TAC NO. MC1817)
Dear Mr. Warner:
By letter dated January 14, 2004, FPL Energy Seabrook, LLC (the licensee) submitted a proposed alternative to the requirements of IWA-4000 of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code),Section XI. The licensee requested that the Nuclear Regulatory Commission (NRC) approve ASME Code Case N-661, "Alternative Requirements for Wall Thickness Restoration of Class 2 and 3 Carbon Steel Piping for Raw Water Service" for use at the Seabrook Station, Unit No. 1 (Seabrook). The request was made pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(a)(3)(i) for the current 10-year inservice inspection (ISI) interval.
ASME Code,Section XI, IWA-4000 provides rules and requirements for the repair of pressure retaining components and their supports by welding, brazing, or metal removal. Code Case N-661 allows the application of a weld metal overlay on the exterior of the piping system to restore the wall thickness of the component.
Based on the information provided in the licensees submittal, the NRC staff concludes that the licensee has provided an acceptable alternative to the requirements of IWA-4000 of ASME Code,Section XI subject to the following three conditions that must be met when using Code Case N-661. These conditions are: (a) if the root cause of the degradation has not been determined, the repair is only acceptable for one cycle, (b) weld overlay repair of an area can only be performed once in the same location, and (c) when through-wall repairs are made by welding on surfaces that are wet or exposed to water, the weld overlay repair is only acceptable until the next refueling outage. The NRC staff concludes that the proposed alternative, as supplemented by the three conditions listed above provides reasonable assurance of structural integrity and safety. Therefore, the proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for Seabrook for the second 10-year ISI interval, or until Code Case N-661 is approved for general use by reference in Regulatory Guide 1.147 "Inservice Inspection Code Case Acceptability -- ASME Section XI, Division 1." The NRC staffs safety evaluation is enclosed.
M. Warner If you need clarification of this approval, please contact the project manager, Mr. Scott P. Wall, at (301) 415-2855.
Sincerely,
/RA/
Daniel S. Collins, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
As stated cc w/encl: See next page
M. Warner If you need clarification of this approval, please contact the project manager, Mr. Scott P. Wall, at (301) 415-2855.
Sincerely,
/RA/
Daniel S. Collins, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
PUBLIC DCollins SWall CRaynor OGC G. Matakas, RGN I PDI-2 R/F TChan GGeorgiev ACRS GHill(2) DLPM DPR Accession Numbers: ML042260312 OFFICE PDI-2/PM PDI-2/LA EMCB/SC OGC PDI-2/SC(A)
NAME SWall SLittle for CRaynor TChan HMcGurren DCollins DATE 8/26/04 8/25/04 SE dated 9/2/04 10/8/04 6/25/04 OFFICIAL RECORD COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO USE CODE CASE N-661 SEABROOK STATION, UNIT NO. 1 FPL ENERGY SEABROOK, LLC DOCKET NO. 50-443
1.0 INTRODUCTION
By letter dated January 14, 2004 (ADAMS Accession No. ML040210539), FPL Energy Seabrook, LLC (FPLE or the licensee) requested that the Nuclear Regulatory Commission (NRC or the Commission) approve an alternative to the requirements of IWA-4000 of American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (ASME Code),
Section XI. Specifically, the licensee requested that the NRC approve ASME Code Case N-661, "Alternative Requirements for Wall Thickness Restoration of Class 2 and 3 Carbon Steel Piping for Raw Water Service" for use at the Seabrook Station, Unit No. 1 (Seabrook).
The request was made pursuant to Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.55a(a)(3)(i). The relief is needed to address replacement or internal weld repair of wall thinning conditions resulting from various wall thinning degradation mechanisms such as erosion, corrosion, cavitation, and pitting in Class 3 carbon steel raw water piping systems.
Code Case N-661 provides an alternative to allow the licensee to restore wall thickness externally by means of a weld-deposited carbon or low-alloy steel reinforcement on the outside surface of the piping.
2.0 REGULATORY EVALUATION
Section 50.55a(g) specifies that inservice inspection (ISI) of nuclear power plant components shall be performed in accordance with the requirements of the ASME Code,Section XI, except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). 10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) will meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in ASME Code,Section XI, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system Enclosure
pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b), twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed therein and subject to Commission approval. The ISI Code of record for Seabrook, second 10-year ISI interval, is the 1995 Edition of ASME Code,Section XI with the 1996 Addenda
3.0 TECHNICAL EVALUATION
The licensees regulatory and technical analyses in support of its requests for relief is described in the licensees submittal dated January 14, 2004. The licensee submitted a relief request to use ASME Code Case N-661 at Seabrook as an alternative to ASME Section XI, IWA-4000. A description of the relief request and the NRC staff evaluation follows.
3.1 Systems/Components for Which Relief is Requested ASME Class 3 carbon steel service water piping system.
3.2 ASME Section XI Code Requirements (as stated by the licensee)
Article IWA-4000 in the 1995 edition with 1996 addenda of Section XI of the ASME Boiler and Pressure Vessel Code provides the rules and requirements for the repair of pressure retaining components and their supports, including appurtenances, subassemblies, parts of a component, core support structures, metal containments and their integral attachments, and metallic portions of Class CC containments and their integral attachments, by welding, brazing, or metal removal. Article IWA-4000 also provides the rules and requirements for the specification and construction of items to be used for replacement and installation of replacement items.
3.3 Basis for the Relief Request (as stated by the licensee)
Relief is being requested from the replacement and internal weld repair rules and requirements provided in ASME Section XI, Article IWA-4000 as applicable to ASME Class 3, carbon steel, Service Water system piping that has experienced internal wall thinning from localized errosion, corrosion, cavitation, or pitting.
Relief is being requested from the rules and requirements of ASME Section XI, Article IWA-4000 for replacements and internal weld repairs to ASME Class 3, carbon steel, Service Water piping pursuant to 10CFR50.55a(a)(3)(i) on the basis that the proposed alternative will provide an acceptable level of quality and safety.
The design function of the Service Water system is to transfer heat loads from various sources in both the primary and secondary portions of the plant to the ultimate heat sink. The ultimate heat sink for all operating and accident loads is normally the Atlantic Ocean. Four (4) Service Water pumps located in the
Service Water pump house normally supply the Service Water system heat loads. The design conditions for the Service Water system piping, valves, and pumps are 150 psig and 2000F. The piping in the safety-related portion of the Service Water system was designed, installed, and ASME Code stamped as a Class 3 component in accordance with ASME Section III, Subsection ND of the ASME Boiler & Pressure Vessel Code. The piping in the non safety-related portion of the Service Water piping system was designed and installed in accordance with the ANSI B31.1 Power Piping Code. There is no ASME Code Class 2 Service Water system piping in the plant.
In the unlikely event that the Atlantic Ocean seawater flow to the Service Water pumps in the Service Water pump house is restricted, a mechanical draft evaporative cooling tower is available to dissipate shutdown and accident heat loads. The two (2) Service Water Cooling Tower pumps are used to circulate water through the required Service Water system loads and the Service Water Cooling Tower.
3.4 Alternative Requirements (as stated by the licensee)
As an alternative to ASME Section XI, Article IWA-4000 replacement and internal weld repair rules and requirements, FPL - Energy Seabrook, LLC proposes to implement ASME Section XI Code Case N-661 titled "Alternative Requirements for Wall Thickness Restoration of Classes 2 and 3 Carbon Steel Piping for Raw Water Service". This ASME Code Case was recently approved by the ASME Board Nuclear Codes & Standards (BNC&S) and has subsequently been issued in Supplement 5 to the 2001 edition of the ASME Boiler & Pressure Vessel Code. This Code Case allows wall thickness restoration externally by means of a weld-deposited carbon steel or low-alloy steel reinforcement on the outside of the piping in accordance with the provisions of the Code Case.
In addition to the ASME Code Case N-661 requirements, all external weld repairs to Service Water system piping performed in accordance with Code Case N-661 will be performed by FPL Energy Seabrook, LLC or its Agent in accordance with the Operational Quality Assurance Program and work control program. Also, when FPL Energy Seabrook, LLC implements ASME Code Case N-661, the following three conditions will be met. These conditions are; (a) a root cause of the degradation will be determined, (b) the weld overlay repair of the area will only be performed once in the same location, (c) when through-wall repairs are made by welding on surfaces that are wet or exposed to water, the weld overlay repair will only be acceptable until the next refueling outage.
3.5 Duration of Proposed Alternative (as stated by the licensee)
FPL Energy Seabrook LLC proposes the use of Code Case N-661 pursuant to 10 CFR 50.55a(a)(3)(i) for Seabrook Station, Unit 1 until approved for general use by reference in Regulatory Guide 1. 147 "Inservice Inspection Code Case Acceptability - ASME Section XI Division 1."
3.6 Staff Evaluation By letter dated January 14, 2004, the licensee requested that the NRC approve an alternative to the requirements of IWA-4000 of ASME Code,Section XI. Specifically, the licensee requested to use the requirements of ASME Code Case N-661 to perform temporary weld repair of degraded ASME Class 3, carbon steel, service water piping using weld overlay. The request was made pursuant to 10 CFR 50.55a(a)(3)(i). Seabrook is currently in the second 10-year ISI interval and is committed to the 1995 Edition of ASME Code,Section XI with the 1996 Addenda.
ASME Code,Section XI, IWA-4000 requires that repairs be performed in accordance with the Owners Design Specification and the repairs meet the requirements of the original Construction Code of the component or system. The licensee is proposing to use the provisions of Code Case N-661 to perform an alternative repair of degraded components which involves the application of weld metal overlay on the exterior of the piping system to restore the wall thickness of the component.
The NRC staff finds the licensees reasoning in support of its request for relief acceptable. This finding is based on the fact that the staff has reviewed Code Case N-661 for inclusion in its Regulatory Guide (RG) 1.147. In addition, the licensee has committed to follow three conditions established by the staff when using the provisions of Code Case N-661 to repair raw water system components. These conditions are: (a) if the root cause of the degradation has not been determined, the repair is only acceptable for one cycle, (b) weld overlay repair of an area can only be performed once in the same location and (c) when through-wall repairs are made by welding on surfaces that are wet or exposed to water, the weld overlay repair is only acceptable until the next refueling outage.
The NRC staff established these three conditions based on the following considerations: (a) if the root cause of the degradation has not been determined, a suitable reinspection frequency cannot be established, (b) weld overlay repair of an area can only be performed once to ensure that ineffective repairs are not being repeatedly implemented in the same location, and (c) performing through-wall weld repairs on surfaces that are wet or exposed to water would produce welds that include weld defects such as porosity, lack of fusion, and cracks. It is highly unlikely that a weld can be made on an open root joint with water present on the backside of the weld without having several weld defects. These types of weld defects can, and many times do, lead to premature failure of a weld joint.
4.0 CONCLUSION
Based on the information provided in the licensees submittal, the NRC staff concludes that the licensee has provided an acceptable alternative to the requirements of IWA-4000 of ASME Code,Section XI subject to the following three conditions which must be met when using Code Case N-661. These conditions are: (a) if the root cause of the degradation has not been determined, the repair is only acceptable of one cycle of operation, (b) weld overlay repair of an area can only be performed once in the same location and (c) when through-wall repairs are made by welding on surfaces that are wet or exposed to water, the weld overlay repair is only acceptable until the next refueling outage. The staff concludes that the proposed alternative, as supplemented by the three conditions listed above provides an acceptable level of quality and safety, and provides reasonable assurance of structural integrity and safety. Therefore, the
proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for the Seabrook Station, Unit 1 for the current 10-year ISI interval, or until Code Case N-661 is approved for general use by reference in RG 1.147. After that time, if the licensee wishes to continue to use Code Case N-661, the licensee must follow the conditions, if any, specified in the RG. All other ASME Code,Section XI, requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: G. Georgiev Date: October 12, 2004
Seabrook Station, Unit No. 1 cc:
Mr. J. A. Stall Mr. Stephen McGrail, Director Senior Vice President, Nuclear and ATTN: James Muckerheide Chief Nuclear Officer Massachusetts Emergency Management Agency Florida Power & Light Company 400 Worcester Road P.O. Box 14000 Framingham, MA 01702-5399 Juno Beach, FL 33408-0420 Philip T. McLaughlin, Attorney General Mr. Peter Brann Steven M. Houran, Deputy Attorney Assistant Attorney General General State House, Station #6 33 Capitol Street Augusta, ME 04333 Concord, NH 03301 Resident Inspector Mr. Bruce Cheney, Director U.S. Nuclear Regulatory Commission New Hampshire Office of Emergency Seabrook Nuclear Power Station Management P.O. Box 1149 State Office Park South Seabrook, NH 03874 107 Pleasant Street Concord, NH 03301 Town of Exeter 10 Front Street Mr. Gene F. St. Pierre Exeter, NH 03823 Station Director Seabrook Station Regional Administrator, Region I FPL Energy Seabrook, LLC U.S. Nuclear Regulatory Commission P.O. Box 300 475 Allendale Road Seabrook, NH 03874 King of Prussia, PA 19406 Mr. M. S. Ross, Managing Attorney Office of the Attorney General Florida Power & Light Company One Ashburton Place, 20th Floor P.O. Box 14000 Boston, MA 02108 Juno Beach, FL 33408-0420 Board of Selectmen Mr. Rajiv S. Kundalkar Town of Amesbury Vice President - Nuclear Engineering Town Hall Florida Power & Light Company Amesbury, MA 01913 P.O. Box 14000 Juno Beach, FL 33408-0420 Ms. Deborah Bell Federal Emergency Management Agency James M. Peschel Region I Regulatory Programs Manager J.W. McCormack P.O. & Seabrook Station Courthouse Building, Room 401 FPL Energy Seabrook, LLC Boston, MA 02109 PO Box 300 Seabrook, NH 03874 Mr. Tom Crimmins Polestar Applied Technology One First Street, Suite 4 Los Altos, CA 94019
Seabrook Station, Unit No. 1 cc:
David Moore Vice President, Nuclear Operations Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi Senior Attorney Florida Power & Light Company 801 Pennsylvania Ave., NW Suite 220 Washington, DC 20004