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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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 3,2010 Mr. Paul Freeman Site Vice President c/o Mr. Michael O'Keefe NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 SUB~IECT: SEABROOK STATION, UNIT NO.1 - RELIEF REQUEST FOR CONTAINMENT BUILDING SPRAY PUMP BEARING VIBRATION ALERT RANGE LIMIT, THIRD 10-YEAR INTERVAL (TAC NO. ME2416)
Dear Mr. Freeman:
By letter dated October 13, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092890325), NextEra Energy Seabrook, LLC (the licensee),
submitted a proposed alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for Seabrook Station, Unit NO.1 (Seabrook). These requirements pertain to the inservice testing requirements. The proposed alternative would increase the Vibration Alert Range Absolute Limit from 0.325 inches per second (ips) to 0.350 ips.
The Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's analysis in support of the proposed alternative. The NRC staff concludes that the proposed alternative provides an acceptable level of quality and safety. The request is authorized for Seabrook pursuant to 10 CFR 50.55a(a)(3)(i) for the remainder of the third 1O-year interval.
The NRC staffs' evaluation and conclusions are contained in the enclosed safety evaluation.
P. Freeman -2 If you have any questions, please contact the Seabrook Project Manager, Mr. G. Edward Miller, at 301-415-2481.
Sincerely, /
I ,/
I/J//~
Harold K. Chernoff, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
As stated cc w/encls: Distribution via Listserv
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...-***i' RELIEF REQUEST ASSOCIATED WITH CONTAINMENT BUILDING SPRAY PUMP BEARING VIBRATION ALERT LIMIT NEXTERA ENERGY SEABROOK, LLC SEABROOK STATION, UNIT NO.1 DOCKET NO. 50-443
1.0 INTRODUCTION
By letter dated October 13, 2009 (ML092890325), NextEra Energy Seabrook, LLC, the licensee, submitted alternative request PR-1 for the third 1O-year inservice testing (1ST) program interval.
The licensee requested an alternative test plan in lieu of certain 1ST requirements of the 2004 Edition of the American Society of Mechanical Engineers (ASI\IIE) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). Specifically, the proposed alternative would increase the Vibration Alert Range Absolute Limit from 0.325 inches per second (ips) to 0.350 ips. The NextEra Energy Seabrook, LLC third 1O-year 1ST interval commences on August 18, 2010, and ends on August 17, 2020.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(f), "Inservice Testing Requirements," requires, in part, that ASME Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs (a)(3)(i) and (a)(3)(ii) of 10 CFR 50.55a.
In proposing alternatives, the licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety or compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Section 50.55a authorizes the NRC to approve alternatives to ASME OM Code requirements upon making necessary findings. NRC guidance contained in NUREG-1482, Revision 1, "Guidance for Inservice Testing at Nuclear Power Plants," provides alternatives to ASME Code requirements which are acceptable.
3.0 TECHNICAL EVALUATION
3.1 ASME Code Components Affected
CBS-P9A - Containment Building Spray Pump A CBS-P9B - Containment Building Spray Pump B
-2 3.2 ASME OM Code Requirements Table ISTB-5121-1, Centrifugal Pumps Test Acceptance Criteria ISTB-5121 (e) and ISTB-5123(e)
All deviations from the reference values shall be compared with the ranges of Table ISTB-5121-1 and corrective action taken as specified in ISTB-6200.
Vibration measurements shall be compated to both the relative and absolute criteria shown in the alert and required action ranges of Table ISTB-5212-1.
3.3 Proposed Alternative The licensee stated that, due to resonance amplification, CBS-P9B pump bearing vibrations have exceeded the ISTB Table 5121-1 absolute limit and CBS-P9A pump bearing vibrations have approached the limit. The licensee is proposing to increase the Vibration Alert Range Absolute Limit from 0.325 inches per second (ips) to 0.350 ips 3.4 Licensee Basis for the Alternative The licensee provided the following justification, in part, for the proposed alternative:
The ASME Code provides both a relative multiplier on the reference value, or an absolute limit. The lower of the relative multiplier or the absolute limit is used to define test acceptance criteria. The Code established that the absolute limit for the ALERT limit will be applied to all of the bearings. Based on the forcing function (e.g. pump casing resonance caused by the four vane impeller) being the same on both CBS-P-9-A and CBS-P-9-B, the absolute limit of 0.325 inches per second (ips) needs to be increased to 0.350 ips to provide test margin.
The cause of the vibration is well understood and is a result of our original pump design and the sizing of our re-circulation line. It is not the result of any material degradation from the original installation. An impeller design change would be required to obtain vibration test margin; however, this design change would not fix any material degradation or restore lost margin.
CBS pump design uses a wide, four-vane impeller that is susceptible to elevated vane pass vibration. This induced vibration amplitude, along with casing resonance near vane pass frequency, results in elevated overall vibration levels.
There are no corrective actions to minimize this condition without replacing the pump impeller, or to modify the stiffness of the pump bearing housings.
Implementing either of these design changes to prevent entering the Alert Range, would require extensive work and testing, with no improvement to equipment reliability.
Pump bearing housing resonance amplification results in testing challenges due to lack of any margin between our reference value and the ISTB Table 5121-1, Centrifugal Pump Tests Acceptance Criteria Alert Range absolute limit.
-3 Exceeding the 0.325 ips Alert limit would result in additional testing. Reduced interval testing does not provide any compensating increase in the level of quality and safety. The pumps are infrequently run, on the order of 200 hours8.333 days <br />1.19 weeks <br />0.274 months <br /> for an 18 month cycle.
Pump bearing resonance test results and vibration spectrum analysis are consistent with tests performed during initial plant startup (1986). These results identify that the casing resonance contributes to the overall vibration amplitude.
Continued pump operation at these levels is acceptable. Additionally, high resolution vibration data analysis has not found any indications of bearing wear or degradation.
Seabrook Station has also recognized the impact of the Silica Removal Program that will periodically be using the CBS pumps to recirculate the RWST for removal of silica. The CBS pumps were considered Category B pumps during the Second
[1ST] Interval. The CBS pumps have already been classified as Category A pumps and now have vibration data taken on a quarterly basis. The increased frequency of testing will provide a larger more frequent sample of trend data to be used in analysis of the pumps performance.
Increasing the ISTB Table 5121-1 Alert Range Absolute Limit from 0.325 ips to 0.350 ips for all of the pump bearing limits on both 1-CBS-P-9-A and 1-CBS-P-9 B, will provide adequate margin for test repeatability.
The CBS pumps will be subject to additional testing, trending, and diagnostic analysis as required by the Seabrook Station Predictive Maintenance Program.
This program employs predictive monitoring techniques that go beyond the vibration monitoring and analysis required by ISTB. These techniques also now include thermography and lube oil sampling and analysis.
3.5 NRC Staff Evaluation Pursuant to 10 CFR 50.55a(f)(4)(ii), the Seabrook Station 1ST program will comply with the ASME OM Code, 2004 Edition. ASME OM Code, 2004 Edition, ISTB-5121 (e), for Group A pump tests, and ISTB-5123(e), for Comprehensive Pump Tests, both require that all deviations from the reference values shall be compared with the ranges of Table ISTB-5121-1. ISTB 5121(e) and ISBE-5123(e) also require that vibration measurements shall be compared to both the relative and absolute criteria shown in the alert and required action ranges of Table ISTB 5121-1. For centrifugal pumps that operate above 600 revolutions per minute (rpm), the absolute value Alert Range is from 0.325 ips to 0.7 ips. CBS-P-9-A and CBS-P-9-B are both operated above 600 rpm.
The licensee has proposed a change to the ASIVIE OM Code Table ISTB-5121-1, Centrifugal Pump Test Acceptance Criteria Alert Range Limits for its CBS Pumps CBS-P-9-A and CBS-P-9-B. Specifically, the licensee is requesting to increase the Alert Range Absolute limit from 0.325 ips to 0.350 ips for all bearings of the subject CBS pumps.
-4 The CBS system is designed to remove the energy discharged to the containment following a loss-of-coolant accident or main steam line break to prevent the containment pressure from exceeding design pressure and to reduce and maintain containment temperature and pressure within acceptable limits. The CBS pumps are motor-driven, horizontal, Bingham-Willamette Type CD centrifugal pumps. The pump style is a double-suction, single-discharge, single stage pump and the impeller is configured with a wide, flat discharge vane exiting to the discharge diffuser. According to the pump vendor, the pump impeller design is no longer manufactured and its current replacement impeller has a modified vane exit passage to reduce vane pass excitation. Each train of the CBS system includes one, 100% capacity pump. These pumps can only be tested on a recirculation flow path which is sized for 1900 gpm, which is approximately 63% of the best efficiency point (BEP) Flow of 3000 gpm and approximately 68% of the required design flow of 2808 gpm.
The staff finds the licensee's proposal to increase the Alert Range Absolute lower limit from 0.325 ips to 0.350 ips for all bearings of the subject CBS pumps acceptable for the following reasons:
- 1. The pumps are susceptible to higher vibrations due to the necessary test conditions.
The pumps are tested at approximately 63% of their BEP flow which increases pump internal recirculation flow. Pump internal recirculation flow increases the pump impeller vane pass vibration response.
- 2. The pumps are susceptible to higher vibration due to their design. The licensee's data analysis identified high pump vane pass spectral responses, and pump casing resonance testing identified that the pump has a resonance frequency similar to that of the pump vane pass. This condition results in increasing vibration amplitude that is responsible for most of the vibration magnitude. The pump vendor has evaluated this issue and agrees with the cause determination and with increasing the pump vibration limits.
- 3. The pumps have operated satisfactorily at these higher vibration levels since initial operation, including during the pre-operational test (1986). No unusual wear or degradation has been detected during testing or inspections due to this consistently elevated vibration. The licensee has been performing Vibration Spectral Analysis which detects pump bearing or motor bearing degrading trends and improper rotor balance or shaft rubs since at least 2003 with no indication of bearing wear or degradation.
- 4. The licensee has committed to continue the use of Condition Based Monitoring Techniques that have been used since at least 2003, including the use of Thermography, Lube Oil Sampling and Analysis, and Vibration Spectral Analysis which go beyond monitoring and analysis required by Subsection ISTB of the OM Code.
-5 Furthermore, the licensees proposed change meets the criteria as specified in NUREG/CP 0152, "Proceedings of the Fourth NRC/ASME Symposium on Value and Pump Testing." This NUREG gives four key components the staff must consider in evaluating such requests which are:
- 1. The licensee should have sufficient vibration history to verify the pump has operated at this level for a significant amount of time;
- 2. The licensee should have consulted with the pump manufacturer to determine if operation of the pump is acceptable;
- 3. The licensee should describe attempts to lower the vibration through modifications to the pump; and
- 4. The licensee should perform a spectral analysis of the pump-driver system to identify all contributors to the vibration levels. The licensee has consulted with the pump manufacturer to consider pump modifications to reduce or eliminate the vibration issue.
However, they have determined that there are no corrective actions to minimize this condition without replacing the pump impeller, or to modify the stiffness of the pump bearing housings.
Implementing either of these design changes to prevent entering the Alert Range, would require extensive work and testing, with no improvement to equipment reliability.
Therefore, the staff finds that the slight increase of the vibration Alert Range will have an insignificant effect on the timely detection of pump degradation prior to component failure, especially since the "Required Action" level of 0.7 ips remains unchanged.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the proposed alternative, PR-2, for CBS Pumps CBS-P9A and CBS-P9B, provides an acceptable level of quality and safety. Accordingly, the staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(i), and is in compliance with the ASME Code's requirements. All other ASME OM Code requirements for which relief was not specifically requested and approved, remain applicable. These proposed alternatives are authorized for the third 10-year 1ST interval, which commences on August 18, 2010, and ends on August 17, 2020.
Principal Contributor: R. Lake Date: June 3,2010
ML101380166 **not required per ML092220406
- via memorandum dated 4/22/10 OFFICE LPL1-2/PM LPL 1-2/LA CPTB/BC OGC LPL1-2/BC NAME GEMilier ABaxter AMcMurtray* HChernoff DATE 6/1/10 6/1/10 4/22/10 6/3/10