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MONTHYEARML13080A0792013-03-18018 March 2013 Relief Request Serial Number 13-CN-001, Relief Request to Use Alternative Depth Sizing Criteria Project stage: Request L-2013-112, ASME Section XI, Inservice Inspection, Relief Requests No. 11 Alternative Through-Wall Sizing Requirements for Implementation of Appendix Viii, Supplement 102013-04-0505 April 2013 ASME Section XI, Inservice Inspection, Relief Requests No. 11 Alternative Through-Wall Sizing Requirements for Implementation of Appendix Viii, Supplement 10 Project stage: Supplement ML13116A2702013-04-26026 April 2013 NRR E-mail Capture - Acceptance Review for Turkey Point, Units 3 and 4, Relief Request #11 (TACs MF1391/92) Project stage: Acceptance Review ML13281A6472013-09-0909 September 2013 NRR E-mail Capture - RAI for TurkeyPoint-3-4 (RR-11: Rmse); TAC Nos. MF1391 and MF1392 Project stage: RAI ML13329A1202014-01-14014 January 2014 SE for RR No. 11 for 4th 10-Year Inservice Inspection Interval - Alternative Through-Wall Sizing Requirements for Implementation of ASME Code, Section XI, Appendix V111, Supplement 10 (TAC Nos. MF1391-92) Project stage: Other 2013-04-05
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Category:Code Relief or Alternative
MONTHYEARML22123A1922022-05-10010 May 2022 Authorization of Relief Request Nos. 8 and 9 Regarding Extension of Inspection Interval for Reactor Pressure Vessel Welds ML22069A7112022-03-16016 March 2022 Authorization of Relief Request No. 10 Regarding Use of ASME Code Case N-513-4 for Extended Period for Intake Cooling Water Discharge Piping ML21302A0902021-10-29029 October 2021 Verbal Authorization by the Office Nuclear Regulation Relief Request No. 10 Use of ASME Code Case N-513-4 for Extended Period Not to Exceed Six Months L-2021-107, Fifth Ten-Year Inservice Inspection Interval Revised Relief Request Nos. 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Extension of Inspection Interval for Turkey Point Units 3 and 4 Reactor Pressure2021-05-13013 May 2021 Fifth Ten-Year Inservice Inspection Interval Revised Relief Request Nos. 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Extension of Inspection Interval for Turkey Point Units 3 and 4 Reactor Pressure ML20308A7472020-12-0707 December 2020 Withdrawal of Request for Relief Concerning Train a and B Component Cooling Water Supply and Return Piping ML20287A5512020-11-0606 November 2020 Approval of Alternative to Use ASME Code Section XI IWA-4340 - for Repairs of Component Cooling Water System Piping ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML17213A8632017-08-29029 August 2017 Safety Evaluation for Relief Request No. PR-03, for the Fifth 10 Year Inservice Testing Interval Regarding Boric Acid Transfer Pump Testing Instrumentation 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 ML17122A1402017-05-10010 May 2017 Safety Evaluation for Relief Request No. 5 for Fifth 10-Year Inservice Inspection Interval ML17082A5102017-04-0606 April 2017 Verbal Authorization of Relief Request No. 5 for Repair of High Head Safety Injection Recirculation Test Line - Fifth 10-Year Inservice Inspection Interval L-2017-050, Fifth Ten-Year Lnservice Inspection Interval Relief Request No. 52017-03-22022 March 2017 Fifth Ten-Year Lnservice Inspection Interval Relief Request No. 5 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) ML16293A7782016-10-26026 October 2016 Turkey Point Nuclear Generating, Unit Nos. 3 and 4 - Safety Evaluation for Relief Request No. 4 for Fifth 10 Year Inservice Inspection Interval - Risk-Informed Inservice Inspection Program (CAC Nos. MF7277 and MF7278) ML16047A1182016-03-0909 March 2016 Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval - Alternative for Examination of Snubbers (CAC Nos. MF6386 and MF6387) ML15352A1622015-12-23023 December 2015 Safety Evaluation for Relief Request No. 17, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A2402015-12-11011 December 2015 Safety Evaluation for Relief Request No. 15, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML13329A1202014-01-14014 January 2014 SE for RR No. 11 for 4th 10-Year Inservice Inspection Interval - Alternative Through-Wall Sizing Requirements for Implementation of ASME Code, Section XI, Appendix V111, Supplement 10 (TAC Nos. MF1391-92) L-2012-381, Fourth Ten-Year Interval, Relief Request No. 102012-11-13013 November 2012 Fourth Ten-Year Interval, Relief Request No. 10 L-2012-193, Concrete Containment Inservice Inspection Program, Exempt Tendon Inspection Relief Request No.72012-06-0505 June 2012 Concrete Containment Inservice Inspection Program, Exempt Tendon Inspection Relief Request No.7 ML1030502252010-11-0505 November 2010 Verbal Authorization of Relief Request No. 9, Visual Examination of Containment Liner Repair ML0533903272005-12-0606 December 2005 Relief Request, Safety Evaluation for Temporary Non-Code Repair of Spent Fuel Pool Cooling Line ML0520901822005-08-15015 August 2005 Relief, Regarding Mechanical Clamping Device on Pressure Boundary Piping ML0503503632005-03-0303 March 2005 Relief Request 1, Authorization of ISI Interval ML0428204702004-10-0606 October 2004 Safety Evaluation for Relief Requests PR-01 and PR-04 L-2004-164, ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds2004-07-22022 July 2004 ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds ML0416100682004-06-0404 June 2004 Correction Ltr, RAI Regarding Fourth Interval Inservice Test Relief Requests ML0330404922003-10-31031 October 2003 Relaxation of the Requirements of Order (EA-03-009) Regarding Reactor Pressure Vessel Head Inspections ML0306203852003-04-25025 April 2003 Relief, Associated with Reactor Vessel Closure Head Repair L-2003-063, ASME Section XI Relief Request No. 33, Alternative Requirements for Implementation of Appendix Viii, Supplement 102003-03-10010 March 2003 ASME Section XI Relief Request No. 33, Alternative Requirements for Implementation of Appendix Viii, Supplement 10 L-2002-085, Alternative Examination for Reactor Pressure Vessel Nozzle Inner Radius Re-submittal of Relief Request No. 252002-05-0606 May 2002 Alternative Examination for Reactor Pressure Vessel Nozzle Inner Radius Re-submittal of Relief Request No. 25 L-2002-044, Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-4242002-03-0101 March 2002 Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-424 2022-05-10
[Table view] Category:Letter
MONTHYEARIR 05000250/20240052024-08-23023 August 2024 Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005 ML24234A0062024-08-22022 August 2024 Project Manager Assignment L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 ML24135A0942024-05-0909 May 2024 Periodic Update to the Updated Final Safety Analysis Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000250/20240102024-05-0101 May 2024 Design Basis Assurance Inspection Programs Inspection Report 05000250/2024010 and 05000251/2024010 and Notice of Violation L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 ML24087A2002024-04-0505 April 2024 Letter to Miami-Dade County Office of Historic Preservation Re Section 106 on Turkey Point Units 3 & 4 EIS ML24087A2012024-04-0505 April 2024 Letter to Talbert Cypress, Miccosukee Tribe of Indians of Florida; Re., Section 106 Letters for Turkey Point ML24087A1982024-04-0505 April 2024 Notice of Availability of the Final Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML24096A2142024-04-0505 April 2024 Ltr. to David Hill, Principal Chief, the Muscogee (Creek) Nation, Re., Section 106 Letters for Turkey Point ML24087A1992024-04-0505 April 2024 Achp Section 106 Letter Re Notice of Availability of the Final Environmental Impact Statement for Turkey Point Units 3 & 4 Subsequent License Renewal Application ML24096A2162024-04-0505 April 2024 Ltr. to Marcellus Osceola, Chairman, Seminole Tribe of Florida, Re., Section 106 Letters for Turkey Point ML24096A2152024-04-0505 April 2024 Ltr. to Lewis Johnson, Principal Chief, Seminole Nation of Oklahoma, Re., Section 106 Letters for Turkey Point ML24096A2182024-04-0505 April 2024 Ltr. to Stephanie Bryan, Tribal Chair, Poarch Band of Creek Indians, Re., Section 106 Letters for Turkey Point ML24072A2832024-04-0101 April 2024 Ltr to Dianne Strand-Notice of Avail.-Final Site-Specific Supp. 5a, 2nd Renewal to the GEIS for License Renewal L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports ML24073A1712024-03-26026 March 2024 Correction of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML24072A2382024-03-20020 March 2024 Review of the Fall 2023 Steam Generator Tube Inspections During Refueling Outage No. 33 L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-011, 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 Applications2024-03-13013 March 2024 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 IR 05000250/20244202024-03-11011 March 2024 – Security Baseline Inspection Report 05000250/2024420 and 05000251/2024420 - Final ML24064A1642024-03-11011 March 2024 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML24058A1182024-03-0101 March 2024 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 L-2024-014, Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report IR 05000250/20230062024-02-28028 February 2024 Annual Assessment Letter for Turkey Point Units 3 & 4 - Report 05000250/2023006 and 05000251/2023006 2024-08-05
[Table view] Category:Safety Evaluation
MONTHYEARML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML22307A1152022-11-28028 November 2022 Authorization of Relief Request No. 10 Part II Related to Repair of Intake Cooling Water Discharge Piping (EPID L-2022-LLR-0032) (Non-Proprietary) ML22028A0662022-05-24024 May 2022 Issuance of Amendment Nos. 296 and 289 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology (EPID L-2021-LLA-0070)- Non-Proprietary ML22123A1922022-05-10010 May 2022 Authorization of Relief Request Nos. 8 and 9 Regarding Extension of Inspection Interval for Reactor Pressure Vessel Welds ML22069A7112022-03-16016 March 2022 Authorization of Relief Request No. 10 Regarding Use of ASME Code Case N-513-4 for Extended Period for Intake Cooling Water Discharge Piping ML21032A0202021-02-26026 February 2021 Issuance of Amendment Nos. 295 and 268 Concerning Extension of Containment Leak Rate Testing Frequency ML20198M4982021-01-27027 January 2021 Issuance of Amendment Nos. 294 and 267 Regarding Emergency Action Level Scheme Upgrade (EPID L-2019-LLA-0271) (L-2019-203) ML20287A5512020-11-0606 November 2020 Approval of Alternative to Use ASME Code Section XI IWA-4340 - for Repairs of Component Cooling Water System Piping ML20237F3852020-10-20020 October 2020 Issuance of Amendment Nos. 293 and 286 Regarding Containment Atmospheric Radioactivity Ventilation Isolation and Leakage Detection System ML20104B5272020-04-16016 April 2020 Issuance of Exigent Amendment No. 291 Concerning the Deferral of Steam Generator Inspections 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 ML19266A5852019-12-17017 December 2019 Issuance of Amendment Nos. 289 and 283 Technical Specification Applicability to Equipment Shared Between Units and Exception to Technical Specification 4.0.4 ML19031C8912019-08-15015 August 2019 Issuance of Amendment Nos. 288 and 282 Regarding Revised Reactor Core Safety Limit to Reflect WCAP-17642-PA Revision 1 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 ML19064A9032019-03-27027 March 2019 Issuance of Amendments Regarding Transition License Conditions for Reactor Coolant Pump Seals ML18354A6732019-03-18018 March 2019 Issuance of Amendments Regarding Technical Specifications Changes to Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement ML18270A4292018-12-0303 December 2018 Issuance of Amendments Nos. 284 and 278 Regarding Adoption of Risk-Informed Completion Times in Technical Specifications (CAC Nos. MF5455 and MF5456; EPID L-2014-LLA-0002) ML18255A3602018-11-14014 November 2018 Issuance of Amendments Regarding Technical Specifications Changes to Address Non-Conservative Actions for Containment and Control Room Ventilation Functions ML18130A4662018-06-12012 June 2018 Amendments Regarding Technical Specifications Pertaining to IST Program and ISI Program Requirements and Surveillance Frequency Control Program Applicability ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18071A0802018-04-0606 April 2018 Correction to Safety Evaluation for Amendment Nos. 278 and 273 Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) ML18019A0782018-03-19019 March 2018 Issuance of Amendments Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID L-2017-LLA-0213) ML18018A5592018-02-20020 February 2018 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) ML17228A5632017-10-26026 October 2017 Issuance of Amendments Regarding Technical Specifications for High-Range Noble Gas Effluent Monitors ML17209A3192017-09-28028 September 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Actuation ML17213A8632017-08-29029 August 2017 Safety Evaluation for Relief Request No. PR-03, for the Fifth 10 Year Inservice Testing Interval Regarding Boric Acid Transfer Pump Testing Instrumentation ML17172A1152017-08-0303 August 2017 Turkey Point Nuclear Plant Generating Unit Nos. 3 and 4 - Issuance of Amendments Regarding Technical Specifications for Control Room Emergency Ventilation System (CAC Nos. MF8221 and MF8222) ML17122A1402017-05-10010 May 2017 Safety Evaluation for Relief Request No. 5 for Fifth 10-Year Inservice Inspection Interval ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML16335A1952017-02-14014 February 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Pumps ML17004A2922017-02-0909 February 2017 Issuance of Amendments Regarding Technical Specifications for Snubbers 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) ML16279A4552016-10-28028 October 2016 Turkey Point Nuclear Generating Station Units 3 & 4 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16293A7782016-10-26026 October 2016 Turkey Point Nuclear Generating, Unit Nos. 3 and 4 - Safety Evaluation for Relief Request No. 4 for Fifth 10 Year Inservice Inspection Interval - Risk-Informed Inservice Inspection Program (CAC Nos. MF7277 and MF7278) ML16120A4732016-06-20020 June 2016 Issuance of Amendments Regarding Technical Specifications for Moderator Temperature Coefficient Measurements ML16004A0192016-04-26026 April 2016 Issuance of Amendments Regarding Technical Specification Figure for the Boric Acid Tank Minimum Volume ML16040A3732016-03-29029 March 2016 Issuance of Amendments Regarding Technical Specifications for Communications and the Manipulator Crane ML16047A1182016-03-0909 March 2016 Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval - Alternative for Examination of Snubbers (CAC Nos. MF6386 and MF6387) ML16008B0722016-02-25025 February 2016 Issuance of Amendments Regarding Technical Specifications for Facility Staff Qualifications for Licensed Operators ML16011A4402016-02-0101 February 2016 Safety Evaluation for Relief Request No. 2 for the Fifth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations of the Regenerative Heat Exchanger Welds (MF6384-MF6385) ML16011A2052016-01-22022 January 2016 Safety Evaluation for Relief Request No. PR-02, for the Fifth 10-Year Inservice Testing Interval Regarding Requirements for the Quarterly Testing of the Residual Heat Removal Pumps (CAC Nos. MF6388 & MF6389) ML15352A1622015-12-23023 December 2015 Safety Evaluation for Relief Request No. 17, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15350A2032015-12-23023 December 2015 Safety Evaluation for Relief Request No. 16, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A2402015-12-11011 December 2015 Safety Evaluation for Relief Request No. 15, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A1082015-12-0909 December 2015 Safety Evaluation for Relief Request No. PR-01, for the Fifth 10-Yeaer Inservice Testing Interval Regarding Requirements for the Quarterly Testing of the Boric Acid Transfer Pumps 2024-07-16
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UNITED STATES .
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 14, 2014 Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power & Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4- SAFETY EVALUATION FOR RELIEF REQUEST NO. 11 FOR FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL- ALTERNATIVE THROUGH-WALL SIZING REQUIREMENTS FOR IMPLEMENTATION OF ASME CODE, SECTION XI, APPENDIX VIII, SUPPLEMENT 10 (TAC NOS. MF1391 AND MF1392)
Dear Mr. Nazar:
By letter to the U.S. Nuclear Regulatory Commission (NRC or the Commission) dated April 5, 2013, as supplemented by letter dated October 9, 2013, Florida Power & Light Company (the licensee) submitted Relief Request No. 11. Pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Paragraph 50.55a(g)(5)(iii), the licensee requested relief from the depth-sizing requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds." The licensee requested to use an alternate root mean square error criteria for sizing any flaws in the reactor vessel elbow-to-nozzle and nozzle-to- pipe dissimilar metal butt end welds at the Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point 3 and 4).
Pursuant to 10 CFR 50.55a(g)(6)(i), the NRC staff reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the licensee adequately addressed all regulatory requirements in 10 CFR 50.55a(g)(6)(i). Therefore, the NRC staff grants Relief Request No. 11 at Turkey Point 3 and 4 for the remainder of the fourth 10-year inservice inspection (lSI) intervals of Turkey Point 3 and 4, which are currently scheduled to end on February 21 and April14, 2014, respectively. The licensee may invoke the provision of the ASME Code,Section XI, paragraph IWA-2430, which allows the licensee to extend the fourth 10-year lSI intervals by 1 year. The licensee may perform the proposed alternative in the 1-year extension periods.
All other ASME Code,Section XI requirements for which the request was not specifically requested and approved remains applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
M. Nazar If you have any questions regarding this issue, please feel free to contact Ms. Audrey Klett at (301) 415-0489.
Sincerely, e F. Quichocho, Chief lant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-250 and 50-251
Enclosure:
Safety Evaluation cc w/enclosure: Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NO. 11 FOR THE FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 DOCKET NOS. 50-250 AND 50-251
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC or the Commission) dated April 5, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13114A294), as supplemented by letter dated October 9, 2013 (ADAMS Accession No. ML13294A026}, Florida Power & Light Company (the licensee) submitted Relief Request No. 11 (RR 11) for NRC review and approval. The licensee submitted RR 11 for the fourth 10-year inservice inspection (lSI) interval of the Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point 3 and 4). Pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Paragraph 50.55a{g){5)(iii), the licensee requested relief and to use alternative requirements for lSI items identified in RR 11 on the basis that the ASME Code requirement is impractical. The licensee requested relief from the depth-sizing requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds." The licensee requested relief from the 0.125-inch root mean square error (RMSE) criteria for the dissimilar metal (OM) butt weld examinations performed from the inner diameter (10) surface.
By electronic mail dated September 9, 2013 (ADAMS Accession No. ML13281A647), the NRC requested additional information regarding the relief request. By letter dated October 9, 2013, the licensee responded to this request.
The licensee requested relief and to use the alternative for Turkey Point 3 and 4 until the end of the fourth 10-year lSI intervals. The Turkey Point 3 fourth 10-year lSI interval is scheduled to end on February 21, 2014, and the Turkey Point 4 fourth 10-year lSI interval is scheduled to end on April 14, 2014. However, the licensee may invoke the provision of the ASME Code,Section XI, Paragraph IWA-2430, which allows the licensee to extend the fourth 10-year lSI intervals by 1 year. Extending the fourth 10-year lSI intervals would be necessary because the licensee extended previous refueling outages to install power uprate modifications.
Enclosure
2.0 REGULATORY EVALUATION
Paragraph 10 CFR 50.55a(g)(4) states that ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," 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 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), 12 months prior to the start of the 120-month interval, subject to the conditions listed therein.
Paragraph 10 CFR 50.55a(b)(2)(xv) states in part that licensees using Appendix VIII in the 1995 Edition through the 2001 Edition of the ASME Boiler and Pressure Vessel Code may elect to comply with all of the provisions in paragraphs (b)(2)(xv)(A) through (b)(2)(xv)(M), except for paragraph (b)(2)(xv)(F), which may be used at the licensee's option.
Paragraph 10 CFR 50.55a(g)(5)(iii) states that if the licensee has determined that conformance with certain ASME Code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in §50.4, information to support the determinations.
Determinations of impracticality in accordance with this section must be based on the demonstrated limitations experienced when attempting to comply with the code requirements during the inservice inspection interval for which the request is being submitted.
Paragraph 10 CFR 50.55a(g)(6)(i) states that the Commission will evaluate determinations under paragraph (g)(5) of 10 CFR 50.55a that ASME Code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the NRC to grant the relief requested by the licensee.
The code of record for the Turkey Point 3 and 4 fourth 10-year lSI interval is the 1998 Edition with Addenda through 2000 of the ASME Code,Section XI, as modified by 10 CFR 50.55a(b)(2)(xv)(A) through (b)(2)(xv)(M) of this section, except for paragraph (b)(2)(xv)(F).
3.0 TECHNICAL EVALUATION
3.1 Licensee's Proposed Alternative The ASME Code components affected by this request are the Class 1 reactor pressure vessel cold legs elbow-to-nozzle and hot legs nozzle-to-pipe OM butt welds in the reactor coolant system. Section 1 of RR 11 lists the 12 components (i.e., six OM welds per unit) for which the licensee requested relief. The subject cold leg elbow to nozzle joints are made of carbon steel
nozzle buttered with stainless steel, field welded to cast stainless steel elbow with stainless steel weld material. The subject hot leg nozzle to pipe joints are made of carbon steel nozzle buttered with stainless steel, field welded to forged stainless steel pipe with stainless steel weld material.
The subject DM welds are part of the Turkey Point risk informed (RI)-ISI program. The NRC approved the RI-ISI program by letter dated October 27, 2008 (ADAMS Accession No. ML082960550). The RI-ISI program listed these DM welds in the lSI schedule as Category R-A, Item No. R1.11. The Turkey Point RI-ISI program requires the subject DM welds to be examined by ultrasonic testing (UT). Paragraph IWA-2232 of Section XI of the ASME Code requires UT to be conducted in accordance with Appendix I. Paragraph 1-2220 of Appendix I requires ultrasonic examination procedures, equipment, and personnel used to detect and size flaws in piping welds to be qualified by performance demonstration in accordance with Appendix VIII of the ASME Code,Section XI. In its letter dated October 9, 2013, the licensee clarified that the requirements of the 1998 Edition through 2000 Addenda of the ASME Code,Section XI, Appendix VIII, are used for the UT performance demonstration in accordance with 10 CFR 50.55a(b)(2)(xv). In addition, the licensee implements the requirements of the ASME Code, Appendix Ill, Supplement 1 when examining the weld from the cast stainless steel elbow side.
For the examination of the subject DM welds, the UT qualification requirements of Supplement 10 of Appendix VIII apply. The licensee adopted ASME Code Case N-695 as an alternative to Supplement 10. The NRC accepted ASME Code Case N-695 in Revision 16 of NRC Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1" (ADAMS Accession No. ML093340041). According to ASME Code Case N-695, the UT procedures, equipment, and personnel are qualified for depth-sizing when the flaw depths estimated by the UT as compared with the true depths do not exceed an RMSE of 0.125 inches.
The licensee provided its basis for impracticality and burden caused by compliance with the ASME Code Case N-695 requirements. To date, the examination vendors have not met the ASME Code required RMSE (i.e., 0.125 inches) for depth-sizing when examining the weld from the ID. The licensee's latest qualification attempt in early 2008 and its prior attempts for achieving the 0.125-inch RMSE were unsuccessful. The attempts involved multiple vendors, ultrasonic instruments, personnel, and flaw depth sizing methodologies, all of which have been incapable of achieving the 0.125-inch RMSE value. The inability of examination procedures to achieve the required RMSE value is primarily caused by a combination of factors, such as surface condition (e.g., roughness), scan access, base materials, and the dendritic structure in the welds.
The licensee proposed alternatives for detecting flaws in its letters dated April 5, 2013, and October 9, 2013. The licensee proposed an alternative depth-sizing RMSE value greater than the 0.125-inch RMSE stated in ASME Code Case N-695 for the examination of the welds identified in RR 11. The licensee proposed to evaluate the vendor's depth-sizing performance of 0.224-inch RMSE against the flaw depth-sizing tolerance for the DM welds of 0.125-inch RMSE stated in ASME Code Case N-695. The licensee proposed that flaw(s) detected and measured as less than 50 percent through-wall in depth will be adjusted by adding a correction factor of the RMSE achieved by the vendor (0.224 inch)- 0.125 inch to the depth of the flaw. If the licensee's vendor demonstrates an improved depth-sizing RMSE prior to the examination, the licensee stated that the excess of that improved RMSE over the 0.125-inch RMSE
requirement, if any, will be added to the measured value for comparison with applicable acceptance criteria. In addition, the licensee proposed to use eddy current testing to determine if the flaw is 10 surface-breaking. If a flaw is detected and depth-sizing is required, the inner profile of the weld, pipe, and nozzle in the region of and surrounding the flaw will be provided along with an estimate of the percentage of potential surface areas with the UT probe lift-off.
For flaw(s) detected and measured as 50 percent or greater through-wall depth, and to remain in service without mitigation or repair, the licensee stated in its letters dated April 5, 2013, and October 9, 2013, that it will submit flaw evaluations to the NRC for review and approval prior to reactor startup. Such flaw evaluations submitted to the NRC will include information regarding the flaw degradation mechanism, the surface roughness/profile in the area of the pipe/weld, and an estimate of the percentage of potential surface areas with UT probe lift-off.
The licensee submitted RR 11 for the fourth 10-year lSI interval of Turkey Point 3, which began on February 22, 2004, and will end on February 21, 2014, and Turkey Point 4, which began on April 15, 2004, and will end on April 14, 2014. Because of the extended refueling outage for the extended power uprate (EPU) Turkey Point plant modifications, if necessary, the licensee may invoke the provision of Paragraph IWA-2430, allowing extension of the fourth 10-year lSI interval by one year. Should there be a need, the licensee stated that it may perform these proposed reactor vessel nozzle butt weld examinations during the extension period.
3.2 NRC Staff's Evaluation The NRC staff evaluated RR 11 pursuant to 10 CFR 50.55a(g)(6)(i). The NRC staff focused on whether the licensee's technical justification supported a determination that the ASME Code requirement is impractical, imposing the requirements could result a burden upon the facility, and the structural integrity and leak tightness of component is reasonably assured.
The NRC staff determined that the licensee provided an adequate description and technical information to support the basis for impracticality. The NRC staff confirmed that the industry made attempts to qualify the 10 ultrasonic inspection procedures since 2002. Enhancements in examinations, such as use of commercially available advanced UT systems, transducers, and software, have not resulted in the desired improvements in performance to meet the ASME Code acceptable RMSE criteria for the 10 ultrasonic inspection. To date, inspection vendors have not been able to meet the qualification requirement of not having greater than 0.125-inch RMSE, as established by the ASME Code for the UT inspection procedure for examining from the 10 surface.
The NRC staff determined that the licensee considered an alternative approach, such as examining the subject welds from the outer diameter (00) surface, as described in the licensee's letter dated October 9, 2013. The qualification requirement of not having greater than 0.125inch RMSE, as established by the ASME Code for the 00 ultrasonic inspection procedures, have been successful. However, the licensee determined that the reactor vessel shield wall and the reactor cavity sand plugs restrict access to the subject welds from the 00.
There is a 2-inch air gap between the bottom of the sand plug wall and the reactor coolant pipe insulation that limits examination from the 00. The licensee estimated that approximately 10 inches of the top 00 surface can only be accessed from the sand plug and examined.
Therefore, the NRC staff finds that a technical justification exists to support the determination that the ASME Code required RMSE of 0.125 inch for the 10 ultrasonic inspection qualification is
impractical, and if the ASME Code requirement was imposed on the facility, these welds would require major design modifications and replacement, which would be a burden on the licensee.
The NRC staff determined that the licensee's proposed alternative to use an RSME correction factor for flow depths is acceptable. In July 2012, the NRC staff reviewed the proprietary Performance Demonstration Initiative (POl) program (administered by the Electric Power Research Institute (EPRI)) data used in blind tests. This review was conducted to verify the information and analysis presented by the industry in the public meeting held among the NRC, POl, EPRI, and industry on March 16, 2012 (ADAMS Accession No. ML12097A071), and June 19,2012 (ADAMS Accession Nos. ML12173A517 and ML12173A522). The NRC staff determined that adding the industry-proposed correction factor (procedure RMSE - 0.125 inches) to the depths of any flaw found by the UT prior to the flaw evaluation for flaws less than 50 percent through-wall satisfactorily reduces the effect of the increased sizing error associated with not meeting the ASME Code required 0.125-inch RMSE.
The NRC staff finds that the RMSE acceptance criteria of ASME Code Case N-695 need not be met to provide reasonable assurance of structural integrity or leak tightness of the subject components provided that the following alternative requirements, which are imposed by the NRC staff in accordance with 10 CFR 50.55a(g)(6)(i), are met. If any cracks are detected and measured by the UT as 50 percent through-wall depth or greater and to remain in service without mitigation or repair, the license shall perform and submit a flaw evaluation for the NRC review and approval prior to the reactor startup. The flaw evaluations shall include: a) the inner profile of the weld, pipe, and nozzle in the region at and surrounding the flaw, b) an estimate of the percentage of potential surface areas with the UT probe lift-off, and c) information on the degradation mechanism that caused the crack. Requiring the NRC approval for restart when a flaw greater than 50 percent through-wall is discovered and is to be left in service without mitigation or repair provides additional assurance of preventing potential large undersizing errors in deep flaws.
Therefore, the NRC staff finds that for flaws measured at 50 percent or less through-wall depth, adding the licensee's proposed correction factor (procedure RMSE - 0.125 inch) to the depths of any flaw found by the inspections and obtaining the NRC review and approval prior to startup for any flaws measured as greater than 50 percent through-wall depth provides reasonable assurance of structural integrity and leak tightness of the subject components. On the basis of the above evaluation, the NRC staff grants RR 11 for the remainder of the fourth 10-year lSI interval of Turkey Point 3, which will end on February 21,2014, and Turkey Point 4 which will end on April14, 2014. The licensee may invoke the provision of the ASME Code,Section XI, Paragraph IWA-2430, which allows the licensee to extend the fourth 10-year lSI intervals by 1 year. The licensee may perform the proposed alternative in the 1-year extension periods.
4.0 REGULATORY COMMITMENTS In its letter dated April 5, 2013, the licensee included a regulatory commitment that for flaws detected and measured as 50 percent through-wall depth or greater, and to remain in service without mitigation or repair, the licensee will submit flaw evaluations to the NRC for review and approval prior to reactor startup. The NRC staff considers the granting of the relief request to be subject to such flaw evaluation submittals and the associated NRC review and approval of the flaw evaluation submittals prior to startup. Therefore, the licensee's flaw evaluation
submittals, should they be required in accordance with this relief request, are obligations that are not changeable in accordance with the licensee's commitment management program.
5.0 CONCLUSION
As set forth in the aforementioned evaluation, the NRC staff determines that it is impractical for the licensee to comply with the ASME Code Case N-695 requirements. The NRC staff also determines that the proposed alternative provides reasonable assurance of structural integrity and leak tightness of the subject welds. Granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(6)(i) and is in compliance with the requirements of the ASME Code for which relief was not requested. Therefore, the NRC staff grants RR 11 for the remainder of the fourth 10-year lSI interval of Turkey Point, Unit 3, which will end on February 21, 2014, and Unit 4 which will end on April 14, 2014. The licensee may invoke the provision of the ASME Code,Section XI, Paragraph IWA-2430, which allows the licensee to extend the fourth 10-year lSI intervals by 1 year. The licensee may perform the proposed alternative in the 1-year extension periods.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable, including the third party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: Ali Rezai Date: January 14, 2014
M. Nazar If you have any questions regarding this issue, please feel free to contact Ms. Audrey Klett at (301) 415-0489.
Sincerely, IRA/
Jessie F. Quichocho, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-250 and 50-251
Enclosure:
Safety Evaluation cc w/enclosure: Listserv DISTRIBUTION:
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