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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
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (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) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement 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 L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to 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, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 L-2023-146, 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 L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis 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 IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 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 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary 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) 2024-02-05
[Table view] Category:Safety Evaluation
MONTHYEARML23320A3062024-01-22022 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) 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 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 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 ML15294A4432015-11-0909 November 2015 Issuance of Amendments Regarding Emergency Core Cooling System Technical Specifications ML15271A3252015-10-14014 October 2015 Safety Evaluation for Relief Request No. 1, Revision 1 for Fifth 10-Year Inservice Inspection Interval - Repair of Pressurizer Stainless Steel Heater Sleeve Without Flaw Removal ML15233A3792015-09-28028 September 2015 Issuance of Amendments Regarding Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses 2024-01-22
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 29, 2017 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.
Juno Beach, FL 33408
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 - SAFETY EVALUATION FOR RELIEF REQUEST NO. PR-03, FOR THE FIFTH 10-YEAR INSERVICE TESTING INTERVAL REGARDING BORIC ACID TRANSFER PUMP TESTING INSTRUMENTATION (CAC NOS. MF9526 AND MF9527)
Dear Mr. Nazar:
By letter L-2017-047 dated March 23, 2017, Florida Power & Light Company (the licensee) submitted Relief Request No. PR-03 for the fifth 10-year inservice testing intervals of Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point 3 and 4). Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Paragraph 55a(z)(1), the licensee requested that the U.S. Nuclear Regulatory Commission (NRC) authorize a proposed alternative to the requirements of paragraph ISTB-351 O(b)(1) of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the boric acid transfer pump flow testing instrumentation.
The NRC staff reviewed the submittal and, as set forth in the enclosed safety evaluation, concludes that the licensee's proposed alternative to the ASME OM Code provides an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(z)(1 ), the NRC staff authorizes the licensee's proposed alternative in Relief Request No. PR-03 for the remainder of the fifth 10-year inservice testing intervals at Turkey Point 3 and 4, which expire on February 21, 2025, and April 14, 2025, respectively.
All other 10 CFR 50.55a and ASME OM Code requirements for which the proposed alternative was not specifically requested and authorized remain applicable.
M. Nazar If you have any questions regarding this issue, please contact the project manager, Mr. Michael Wentzel, at (301) 415-6459 or by e-mail at Michael.Wentzel@nrc.gov.
Sincerely, JitlJ~
,fo /
Undine Shoop, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251
Enclosure:
Safety Evaluation cc w/encl.: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NO. PR-03 FIFTH 10-YEAR INSERVICE TESTING 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 L-2017-047 dated March 23, 2017, 1 Florida Power & Light Company (FPL, or the licensee) submitted Relief Request No. PR-03 for the fifth 10-year inservice testing intervals of Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point 3 and 4). Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Paragraph 55a(z)(1 ), the licensee requested that the U.S. Nuclear Regulatory Commission (NRC) authorize a proposed alternative to the requirements in paragraph ISTB-351 O(b)(1) of the American Society of Mechanical Engineers (ASME) Code for the Operation and Maintenance of Nuclear Power Plants (OM Code) for boric acid transfer pump (BATP) flow testing instrumentation.
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(f), "lnservice Testing Requirements," state, in part, that inservice testing (IST) of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the applicable ASME OM Code and addenda, except where alternatives have been authorized, pursuant to 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2).
In proposing alternatives, a licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety as outlined in 10 CFR 50.55a(z)(1 ), or compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety as outlined in 10 CFR 50.55a(z)(2).
Based on the above, the NRC staff finds regulatory authority exists for the licensee to request, and the NRC to authorize, the proposed alternatives to the ASME OM Code, subject to the evaluation given below.
1 Agencywide Documents Access and Management System Accession No. ML17089A646.
Enclosure
3.0 TECHNICAL EVALUATION
The fifth 10-year IST program intervals began on February 22, 2015, and on April 15, 2015, for Turkey Point 3 and 4, respectively. The applicable ASME OM Code edition and addenda for Turkey Point 3 and 4 fifth 10-year IST program intervals is the 2004 Edition through the 2006 Addenda.
3.1 Licensee's Proposed Alternative Applicable Code Requirements Per OM Code paragraph ISTB-351 O(b)(1 ), Range, the full scale range of each analog instrument shall not be greater than three times the reference value.
ASME Code Components Affected Relief is requested for the flow rate instruments for the following Boric Acid Transfer Pumps (BATP):
3P203A Boric Acid Transfer Pump 3P203B Boric Acid Transfer Pump 4P203A Boric Acid Transfer Pump 4P203B Boric Acid Transfer Pump Licensee's Reason for Request The licensee states, in part:
The reason for requesting relief pursuant to 10 CFR 50.55a(z)(1) is that the existing flow rate instrument used for BATP comprehensive testing does not meet the analog instrument range requirement of ASME OM Code-2004, ISTB-3510(b)(1). However, compliance with ISTB- 3510(b)(1) would not yield more accurate readings than obtained by the instrument presently installed.
Specifically, the BATP comprehensive test, performed in accordance with ASME OM Code-2004, ISTB-5123, consists of varying the flowrate to an established reference point and comparing the measured pump differential pressure against the requirements of ASME OM Code-2004, Table ISTB-5121-1, Centrifugal Pump Test Acceptance Criteria. In establishing the reference value for flowrate, FPL utilizes analog flow instruments Fl-3/4-110, Emergency Boration Flow Indicator, (where "3/4" designates Fl-3-110 for Unit 3 and Fl-4-110 for Unit 4).
However, the gauges for Fl- 3/4-110 range from zero to 200 gallons per minute (gpm), whereas the BATP flow reference value for the comprehensive test is 60 gpm. Hence, Fl-3/4-110 do not satisfy the analog instrumentation range requirements of ISTB-3510(b)(1) since the 200 gpm full-scale range of Fl-3/4-11 O exceeds three times the pumps' reference value (i.e. 180 gpm).
Proposed Alternative and Basis for Use The licensee states, in part:
FPL proposes as an alternative to ASME OM Code-2004, ISTB-3510(b)(1),
continued use of Fl-3/4-110 when conducting the BATP comprehensive test.
The basis for the proposed alternative is that compliance with the instrumentation range requirement of ASME OM Code-2004, ISTB-3510(b)(1), would not result in obtaining information more useful than that currently available using the existing flow instrumentation. FPL's determination is based upon the following:
NUREG-1482, Guidelines for lnseNice Testing at Nuclear Power Plants, states that when the range of a permanently installed analog instrument is greater than three times the reference value but the accuracy of the instrument is more conservative than required by the Code, the staff may grant relief when the combination of the range and accuracy yields a reading at least equivalent to the reading achieved using instruments meeting the Code requirements.
NUREG-1482 further states that the use of any available instrument that meets the intent of the Code for the actual reading yield an acceptable level of quality and safety for testing.
ASME OM Code-2004, ISTB-351 O(a) states that the instrument accuracy shall be within the limits of Table ISTB-3510-1, Required Instrument Accuracy. For the measured flowrate during comprehensive pump testing, Table ISTB-3510-1 requires an instrument accuracy of +/- 2% of full scale. The accuracy of installed flowrate instruments, Fl-3/4-110, is +/- 1.5% and thereby exceeds the requirements of Table ISTB-3510-1 for BATP comprehensive test flow measurements. Moreover, the overall measured reading using Fl-3/4-110, equates to +/- 3.0 gpm (i.e. +/- 1.5% of 200 gpm) whereas the measured reading using a Code compliant flow meter equates to +/- 3.6 gpm (i.e. +/- 2% of 180 gpm). Hence even though the instrument range of Fl-3/4-110 is above the limits of ISTB-351 O(b)(1 ), the combination of range and accuracy yield an overall measured reading more accurate than the measured reading for a flow meter compliant with the instrumentation requirements of ISTB-351 O(a) and ISTB-3510(b)(1 ). Accordingly, the installed flow instruments, Fl-3/4-110, meet the recommendations in NUREG-1482, Section 5.5.1, Range and Accuracy of Analog Instruments, for requesting relief from ISTB-351 O(b)(1 ).
Based upon the foregoing, FPL asserts that continued use of the installed instruments, Fl-3/4- 110, yields a measured reading of greater overall accuracy than the reading achieved from a Code compliant instrument, providing thus an acceptable level of quality and safety to the ASME Code ISTB-3510(b)(1) requirements. FPL will use installed flow instruments, Fl-3/4-110, when performing BATP comprehensive inservice testing for the remainder of the Fifth Ten-Year IST Interval as an alternative to ASME Code ISTB-3510(b)(1) requirement.
3.2 NRC Staff's Evaluation of Proposed Alternative The licensee requests relief from the instrument range requirements of ISTB-351 O(b)(1) for the BATP flow instruments during the comprehensive test. The Code requires that the full-scale range of each analog instrument shall not be greater than three times the reference value. The licensee proposes to use instruments that do not meet this Code requirement.
For comprehensive tests, the Code requires instrument accuracy to be within 2 percent of full-scale and the full-scale range of each instrument be no greater than three times the reference value. The combination of these two requirements results in an effective maximum inaccuracy limit of plus or minus 6 percent of the reference flowrate. The licensee has demonstrated that by using flow instruments with higher accuracy than required by code yet with ranges that would otherwise exceed what the code allows, the overall accuracy required by the code for the flowrate value can still be met and, in fact, exceeded.
In complying with the Code requirements, the licensee would not obtain information that would be more useful than the information that is currently available. For example, installing a flow instrument with a range of three times the reference value (or less) to comply with Code requirements would not yield more accurate readings than those provided by the flowrate instruments that are presently installed. This justification is consistent with the long held staff position described in NUREG-1482, Revision 2, concerning test instrument ranges and code compliance and therefore provides reasonable assurance that the BATPs are operationally ready. (Reference NUREG-1482 Revision 2, para. 2.5.1.1.)
4.0 CONCLUSION
As set forth in this safety evaluation, the NRC staff determines that Relief Request No. PR-03 provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). Therefore, the NRC staff authorizes the use of Relief Request No. PR-03 for the remainder of the fifth 10-year inservice testing intervals for Turkey Point 3 and 4, which expire on February 21, 2025, and April 14, 2025, respectively. All other 10 CFR 50.55a and ASME OM Code requirements for which the proposed alternative was not specifically requested and authorized remain applicable.
Principal Contributor: John G. Billerbeck Date: August 29, 2017
M.Nazar
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 - SAFETY EVALUATION FOR RELIEF REQUEST NO. PR-03, FOR THE FIFTH 10-YEAR INSERVICE TESTING INTERVAL REGARDING BORIC ACID TRANSFER PUMP TESTING INSTRUMENTATION (CAC NOS. MF9526 AND MF9527)
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