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EPID:L-2022-LLR-0011, Relief Request 69, Unit 2, Extension Request for Relief from Containment Tendon Inspections (Approved, Closed) |
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MONTHYEARML22031A0982022-01-28028 January 2022 Relief Request 69, Unit 2, Extension Request for Relief from Containment Tendon Inspections Project stage: Request ML22034A0132022-02-0202 February 2022 NRR E-mail Capture - Palo Verde, Unit 2 - Verbal Approval of RR-69 to Extend Containment Tendon Inspection from 2/8/22 to 6/8/22 Project stage: Other ML22049A0572022-02-23023 February 2022 Relief Request 69 to Extend Inservice Inspection of Containment Tendon by Four Months Due to the Covid 19 Pandemic (EPID L 2022 Llr 0011 (Covid 19)) Project stage: Approval 2022-02-02
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Category:Code Relief or Alternative
MONTHYEARML22124A2412022-05-12012 May 2022 Relief Request 67 for an Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection ML22049A0572022-02-23023 February 2022 Relief Request 69 to Extend Inservice Inspection of Containment Tendon by Four Months Due to the Covid 19 Pandemic (EPID L 2022 Llr 0011 (Covid 19)) ML21278B0912021-10-0606 October 2021 Presubmittal Meeting with Arizona Public Service Company Regarding Relief Request No. 68 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (EPID L-2021-LRM-0104) (Slides) ML21228A1042021-08-12012 August 2021 RR-67, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (EPID L-2021-LLR-0050) (Email) ML21089A0102021-04-0202 April 2021 Relief Request 66 to Defer Inservice Inspection of Containment Tendon by One Year Due to Covid-19 Pandemic ML20088A5332020-03-27027 March 2020 Relief Request 65 - Unit 2, COVID-19, Request for Relief from Bottom Mounted Instrumentation Nozzles and a Pressurizer Nozzle to Surge Line Weld Overlay Examination ML19263F8752019-09-20020 September 2019 Relief Request VRR-01: Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)C3)(xi) ML19107A3722019-04-19019 April 2019 Relief Request 62 Regarding Proposed Alternative Pressurizer Heater Sleeve Repairs ML19044A6412019-02-19019 February 2019 Relief Request No. 58 for the Third 10-Year Inservice Inspection Interval, Request for Relief from the American Society of Mechanical Engineers for Certain Class 1 and Class 2 Welds ML18285A0292018-10-19019 October 2018 Relief Request 59 for the Deferral of Reactor Vessel Beltline Region Interior Attachment Examinations ML18079A7252018-03-17017 March 2018 Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML18016A1722018-01-12012 January 2018 Relief Request 50 - Request for Alternative to American Society of Mechanical Engineers Section XI Requirements for Pressure Retaining Boundary During System Leakage Tests ML17074A2092017-03-16016 March 2017 Relief Request GRR-01 to ASME Code Case OMN-20 for Third 10-Year Interval Pump and Valve Inservice Testing Program ML16172A0382016-06-23023 June 2016 Relief Request 54 to Approve an Alternative to Flaw Removal for Reactor Coolant Pump 2A Suction Pressure Instrument Nozzle, for the Third 10-Year Inservice Inspection Interval ML15238B6612015-09-15015 September 2015 Relief Request 53, Alternative to ASME Code Section XI Requirements Related to Flaw Removal ML15079A0062015-03-30030 March 2015 Relief Request 52 - Request for Approval of Alternate to Flaw Removal, Flaw Characterization and Successive Examinations, for the Remainder of Its Useful Life ML14093A4072014-04-10010 April 2014 Relief Request 51, Alternative to ASME Code for Flaw Removal, Reactor Vessel Bottom-mounted Instrumentation Nozzle, Third 10-Year ISI Interval ML13091A1772013-04-12012 April 2013 Relief Request 48 - Alternative to ASME Section III, Phased Array Ultrasonic Exam Techniques in Lieu of Radiography for Remainder of Third 10-Year Inservice Inspection Interval ML13085A2542013-04-0404 April 2013 Relief Request 49, Alternative to ASME Code, Section XI, for Reactor Vessel Head Flange Seal Leak Detection Piping, Third 10-Year Inservice Inspection Interval ML12257A1412012-09-18018 September 2012 Request for Relief to Use Subsequent Edition and Addenda of ASME Code, Section XI, for Examination Categories B-L-1, B-M-1, and C-G, for the Third 10-Year Inservice Inspection Interval ML1026700802010-10-14014 October 2010 Relief Request No. 47, from Certain ASME Code Requirements for Reactor Vessel Nozzle to Vessel Welds for Second 10-Year Inservice Inspection Interval ML1025001432010-09-21021 September 2010 Relief Request No. 45 from Certain ASME Code Class 1 Weld and Component Volumetric Exams of Reactor Vessel Outlet Nozzles for Second 10-Year Inservice Inspection Interval ML1021604872010-08-27027 August 2010 Relief Request No. RR-44, Reactor Vessel Weld Visual Examination Interval Extension for Third 10-Year Inservice Inspection Interval ML0921603982009-07-17017 July 2009 Submittal of Relief Request from the American Society of Mechanical Engineers (ASME) Code, Section XI - Relief Request No. 46 ML0917001972009-07-0202 July 2009 Relief Request No. 39, Alternative to Repair Weld Methods, ASME Code, Section XI for Remainder of Operating License ML0916304492009-06-0202 June 2009 Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing - Pump Relief Request PRR-08, Revision 1 ML0905801992009-02-17017 February 2009 Relief Request 41, to Use Appendix I of ASME Code Case N-729-1 ML0830105722008-11-10010 November 2008 Relief Request Nos. 18 and 36, Proposed Alternatives for the Third Interval 10-Year Inservice Inspection Program Interval ML0825905562008-10-0202 October 2008 Relief Request No. 34 for Second 10-Year Inservice Inspection Interval ML0822506752008-07-11011 July 2008 American Society of Mechanical Engineers (ASME) Code, Section XI, Request for Approval of an Alternative Repair Method - Relief Request No. 39 ML0817002812008-06-0606 June 2008 Request for Extension to Complete the Final Confirmatory Analysis and Validation of Containment Sump Strainers Associated with NRC GL-04-002 ML0715600082007-06-21021 June 2007 Relief Request Nos. 36 and 37 Alternatives to Weld Overlay Requirements for Inservice Inspection ML0711400332007-05-16016 May 2007 Supplement to Relief Request No. 34 Request to Extend the Second 10-Year Inservice Inspection Program Interval for Reactor Vessel Weld Examinations ML0629302082006-11-0303 November 2006 Relief Request No. 32, Risk-Informed Inservice Inspection Program ML0626401992006-10-0404 October 2006 Relief Request No. 35 Request to Extend the Second 10-Year Inservice Inspection Program Interval for Reactor Vessel Visual Examinations ML0624905132006-09-20020 September 2006 Relief, Request to Extend the Second 10-Year Inservice Inspection Program Interval ML0623003332006-09-12012 September 2006 Relief Request No. 31, Revision 1, Proposed Alternative Repair for Reactor Coolant System Hot Leg Alloy 600 Small-Bore Nozzles ML0615702092006-05-26026 May 2006 Additional Information to Support the Request to Extend the Second 10-Year, American Society of Mechanical Engineers Section IX, Inservice Inspection Program Interval for Reactor Vessel Weld Examinations - Relief Request No. 34 ML0610803942006-04-0707 April 2006 Relief, Request to Use a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities at PVNGS in Accordance with 10 CFR 50.55a(g)(4)(iv) ML0518901452005-06-28028 June 2005 Revision 1 to 10 CFR 50.55a(a)(3)(i) Request for Alternatives to 10 CFR 50.55a(c) Requirement to Comply with ASME Section III, Subsection NB-1120, Temperature Limits, for a Portion of the Plant Pressurizer That Was Subjected To. ML0512901232005-05-0505 May 2005 Relief, Relief Request No. 31 Proposed Alternative Repair for Reactor Coolant System Hot Leg Alloy 600 Small-Bore Nozzles ML0434201672004-11-24024 November 2004 Relief Request No. 25 for Palo Verde, Unit 2 - Relaxation from First Revised NRC Order EA-03-009 - Additional Analysis Information for Control Element Drive Mechanism (CEDM) Nozzles ML0432706262004-11-19019 November 2004 Palo Verde - Correction to Approval Letter for Relief Request No. 30 ML0328705392003-10-0909 October 2003 Relief, Inservice Inspection Program Surface Examination Requirements, (TACs MC0830, MC0831, and MC0832) ML0321105422003-07-30030 July 2003 Relief Request 23 Alternative to Temper Bead Welding Requirements for Inservice Inspection Program (Tac. MB8973, MB8974 and MB8975) ML0314000512003-05-15015 May 2003 CFR 50.55a Alternative Repair Request for the Second 10-Year Interval of the Inservice Inspection Program: Relief Request 23, Pressurizer Heater Sleeves ML0302902122003-01-27027 January 2003 Relief, Requirements of American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code (Code) Concerning Use of Electrical Discharge Machining (Edm), MB6439, MB6440 & MB6441 ML0302801692003-01-24024 January 2003 Mechanical Nozzle Seal Assembly Type 2 Code Replacement Request for Relief from 10 CFR 50.55a ML0235200682002-12-11011 December 2002 Resubmittal of 10 CFR 50.55a Alternative Repair Request for the Second 10-Year Interval of the Inservice Inspection Program (Relief Request 18) ML0227404992002-09-25025 September 2002 CFR 50.55a Alternative Repair Request for the Second 10-Year Interval of the Inservice Inspection Program (Relief Request 22) 2022-05-12
[Table view] Category:Letter
MONTHYEARML24241A2782024-08-28028 August 2024 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information ML24240A2682024-08-27027 August 2024 Transmittal of Technical Specification Bases Revision 79 IR 05000528/20240052024-08-22022 August 2024 Updated Inspection Plan for Palo Verde Nuclear Generating Station - Units 1, 2, and 3 (Report 05000528/2024005, 05000529/2024005, 05000530/2024005) IR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24129A1482024-05-0707 May 2024 and Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) IR 05000528/20243012024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 ML24032A1542024-04-0303 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24089A1892024-03-28028 March 2024 Present Levels of Financial Protection ML24068A2522024-03-0808 March 2024 License Amendment Request to Revise Technical Specifications 3.5.1 and 3.5.2 Using Risk-Informed Process for Evaluations ML24066A0472024-03-0606 March 2024 Response to Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown and TS IR 05000528/20240122024-03-0404 March 2024 Age-Related Degradation Inspection Report 05000528/2024012, 05000529/2024012 and 05000530/2024012 IR 05000528/20230062024-02-28028 February 2024 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Report 05000528/2023006 and 05000529/2023006 and 05000530/2023006 ML24053A3972024-02-22022 February 2024 License Renewal - Alloy 600 Management Program Plan ML24047A3632024-02-16016 February 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX177, AMZDFX178, AMZDFX179 Vertical Concrete Cask Identification No. AMZDNE179, AMZDNE178 IR 05000528/20230042024-02-12012 February 2024 Integrated Inspection Report Report 05000528/2023004 and 05000529/2023004 and 05000530/2023004 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle 2024-08-08
[Table view] Category:Safety Evaluation
MONTHYEARML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program ML23199A2942023-08-0909 August 2023 Issuance of Amendment Nos. 221, 221, and 221, to Revise Technical Specifications to Adopt TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable ML22334A0702022-12-15015 December 2022 Issuance of Amendment Nos. 220, 220, and 220, to Revise Technical Specifications to Adopt TSTF-487, Relocate DNB Parameters to the COLR ML22178A0042022-08-11011 August 2022 Issuance of Amendment Nos. 219, 219, and 219, to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump Ts to Address GSI-191 Issues ML22049A0572022-02-23023 February 2022 Relief Request 69 to Extend Inservice Inspection of Containment Tendon by Four Months Due to the Covid 19 Pandemic (EPID L 2022 Llr 0011 (Covid 19)) ML21347A0032021-12-22022 December 2021 Issuance of Amendment Nos. 217, 217, and 217 Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML21307A1312021-11-17017 November 2021 the Independent Spent Fuel Storage Installation - Order Approving Transfers of Control of Licenses for Minority Interests Subject to Expiring Leases (EPID L-2021-LLM-0003) (Letter) ML21225A0932021-08-17017 August 2021 Ng Station, Units 1, 2,& 3 - Issuance of Amendment Nos. 216, 216, and 216 Regarding Revision to Technical Specifications to Adopt TSTF-501, Rev.1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21118B0282021-05-25025 May 2021 Letter/Se Approving Indirect Transfer of Licenses for Units 1, 2, and 3, and the Independent Spent Fuel Storage Installation ML21105A3402021-04-21021 April 2021 Issuance of Amendment Nos. 215, 215, and 215 Revision to Technical Specifications to Adopt TSTF-563, Revision 0 ML21089A0102021-04-0202 April 2021 Relief Request 66 to Defer Inservice Inspection of Containment Tendon by One Year Due to Covid-19 Pandemic ML20350B8032021-02-0808 February 2021 Issuance of Amendment Nos. 214, 214, and 214 to Make Administrative Changes to the Technical Specifications ML20216A5392020-08-0606 August 2020 Relief Request 65 for Inspection of Reactor Pressure Vessel Bottom Mounted Instrument Nozzles and Pressurizer Surge Line Weld Overlay ML20163A0372020-07-31031 July 2020 the Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 213, 213, and 213 to Revise Emergency Plan Staff Augmentation Times ML20114E3252020-04-30030 April 2020 Relief Request 64 for Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML20031C9472020-03-0404 March 2020 Nonproprietary, Issuance of Amendment Nos. 212, 212, and 212 to Revise Technical Specifications to Support the Implementation of Framatome High Thermal Performance Fuel ML20016A4582020-02-10010 February 2020 Issuance of Amendment Nos. 211, 211, 211, to Extend Implementation Date for Amendment Nos. 209, 209, and 209 Associated W/Initiative 4b That Permit the Use of Risk-Informed Completion Times on the TS ML19309F3042019-12-18018 December 2019 Issuance of Amendment Nos. 210, 210, and 210, to Revise Technical Specifications to Adopt Traveler TSTF-529, Revision 4,Clarify Use and Application ML19304C5622019-11-0505 November 2019 Safety Evaluation - Arizona Public Service Company - Palo Verde Nuclear Generating Station - License Amendment Request to Adopt TSTF-529 ML19085A5252019-05-29029 May 2019 Issuance of Amendments Nos. 209, 209, and 209 - Regarding Adoption of Risk Informed Completion Times in Technical Specifications (CAC Nos. MF6576, MF6577, and MF6578; EPID L-2015-LLA-0001) ML19107A3722019-04-19019 April 2019 Relief Request 62 Regarding Proposed Alternative Pressurizer Heater Sleeve Repairs ML19070A2182019-04-0303 April 2019 Issuance of Amendment Nos. 208, 208, and 208 - Regarding Response Time Testing of Pressure Transmitters ML19044A6412019-02-19019 February 2019 Relief Request No. 58 for the Third 10-Year Inservice Inspection Interval, Request for Relief from the American Society of Mechanical Engineers for Certain Class 1 and Class 2 Welds ML19037A0552019-02-19019 February 2019 Relief Requests 60 & 61 for the Fourth 10-Year Inservice Inspection Interval, Request for Relief from the American Society of Mechanical Engineers Half-Nozzle Repairs (EPID L-2018-LLR-0111 & EPID L-2018-LLR-0112) ML18285A0292018-10-19019 October 2018 Relief Request 59 for the Deferral of Reactor Vessel Beltline Region Interior Attachment Examinations ML18243A2802018-10-10010 October 2018 Issuance of Amendment Nos. 207, 207, and 207 to Adopt 10 CFR 50.69 (CAC Nos. MF9971, MF9972, and MF9973; EPID L-2017-LLA-0276) ML17254A4992017-09-27027 September 2017 Issuance of Amendment Nos. 204, 204, and 204 to Modify the Completion Date for Implementation of Milestone 8 of the Cyber Security Plan ML17188A4122017-07-28028 July 2017 Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendment Nos. 203, 203, and 203 to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis (CAC Nos. MF7138, MF7139, and MF7140) ML17123A4352017-05-16016 May 2017 Issuance of Amendment Nos. 202, 202, and 202 to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML17090A1642017-04-27027 April 2017 Issuance of Amendment No. 201, 201, and 201 to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications ML17074A2092017-03-16016 March 2017 Relief Request GRR-01 to ASME Code Case OMN-20 for Third 10-Year Interval Pump and Valve Inservice Testing Program ML17004A0202017-01-0404 January 2017 Issuance of Amendment No. 200, Revise Technical Specification 3.8.1, AC Sources - Operating, for One-Time Extension of the Diesel Generator Completion Time, Risk-Informed (Emergency Circumstances) ML17003A0832017-01-0303 January 2017 Safety Evaluation Input Regarding Changes to Technical Specifications for One-Time Extension of Completion Time for Emergency Diesel Generator ML17004A2092017-01-0303 January 2017 Safety Evaluation Input for Palo Verde Nuclear Generating Station, Unit 3, Llcense Amendment Request for a One-Time Extension of the 3B Emergency Diesel Generator Completion Time ML17003A3892017-01-0303 January 2017 Safety Evaluation Input Regarding the Palo Verde Nuclear Generating Station Unit 3 Emergency Request to Extend Diesel Generator 3B Completion Time ML16358A6762016-12-23023 December 2016 Issuance of Amendment No. 199, Request for One-Time Extension of the Diesel Generator Completion Time (Emergency Circumstances) ML16358A4152016-12-23023 December 2016 Technical Specifications for One-Time Extension of Completion Time for Emergency Diesel Generator ML16180A1092016-09-0808 September 2016 Issuance of Amendment Nos. 198, 198, and 198, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. ML16194A3232016-07-22022 July 2016 Review and Approval of Request for Quality Assurance Plan Change Per Nuclear Energy Institute (NEI) 11-04A, Nuclear Generation Quality Assurance Program Description ML16088A2612016-07-20020 July 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16172A0382016-06-23023 June 2016 Relief Request 54 to Approve an Alternative to Flaw Removal for Reactor Coolant Pump 2A Suction Pressure Instrument Nozzle, for the Third 10-Year Inservice Inspection Interval ML16004A0132016-02-19019 February 2016 Issuance of Amendment No. 197, 197, and 197, Adopt Technical Specification Task Force Traveler TSTF-439-A, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML15266A0052015-09-25025 September 2015 Issuance of Amendment No. 196, Revise Technical Specification Surveillance Requirement 3.1.5.3 for Control Element Assembly 88 for the Remainder of Cycle 19 (Exigent Circumstances) ML15238B6612015-09-15015 September 2015 Relief Request 53, Alternative to ASME Code Section XI Requirements Related to Flaw Removal ML15079A0062015-03-30030 March 2015 Relief Request 52 - Request for Approval of Alternate to Flaw Removal, Flaw Characterization and Successive Examinations, for the Remainder of Its Useful Life ML15070A1242015-03-30030 March 2015 Issuance of Amendment Nos. 195, 195, and 195, Adopt TSTF-486, Revision 2, Revise Mtc Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011) and TSTF-406, Revision 2 ML15058A0292015-03-27027 March 2015 Staff Assessment Regarding Review of Pressurized-Water Reactor Vessel Internals Aging Management Program Plan 2024-07-24
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON , D.C. 20555-0001 February 23, 2022 Mrs. Maria L. Lacal Executive Vice President/
Chief Nuclear Officer Arizona Public Service Company P.O. Box 52034, Mail Station 7605 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNIT 2 - RELIEF REQUEST 69 TO EXTEND INSERVICE INSPECTION OF CONTAINMENT TENDON BY 4 MONTHS DUE TO THE COVID-19 PANDEMIC (EPID L-2022-LLR-0011 [COVID-19])
Dear Mrs. Lacal:
By electronic submittal dated January 28, 2022, Arizona Public Service Company (APS, the licensee) submitted a COVID-19 relief request to extend containment tendon inspection at Palo Verde Nuclear Generating Station, Unit 2 (Palo Verde, Unit 2) by 4 months, in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(z)(2),
Hardship without a compensating increase in quality and safety.
Specifically, pursuant to 10 CFR 50.55a(z)(2), the licensee requested U.S. Nuclear Regulatory Commission (NRC) approval of Relief Request 69 regarding the interval between containment tendon inspections as specified per Subsubarticle IWL-2420 of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Subsection IWL, Requirements for Class CC [Concrete Containment] Concrete Components of Light-Water Cooled Plants, required by 10 CFR 50.55a. Relief is requested on the basis that compliance with the Code-specified inspection interval during the COVID-19 pandemic would result in hardship without a compensating increase in the level of quality and safety for Palo Verde, Unit 2.
The U.S. Federal Government made a declaration of emergency due to COVID-19, under the Stafford Act on March 13, 2020, while the U.S. Centers for Disease Control and Prevention determined that COVID-19 poses a serious public health risk. Due to the COVID-19 pandemic, the licensee has enacted guidelines to limit outside contractors, including those that perform examinations for the inservice inspection program, in order to minimize the potential of inadvertently spreading the COVID-19 virus to Palo Verde personnel.
In its submittal dated January 28, 2022, the licensee stated, in part, that:
APS has made good faith efforts to complete the Unit 2 containment tendon examinations by the February 8, 2022, due date. Examinations were originally scheduled to start in November 2021. Unfortunately, due to tooling parts and material manufacturing at the other facilities, there were delays in vendor
M. Lacal completion of work at other sites, which delayed mobilization at [Palo Verde, Unit 2] until January 2022. The majority of the inspection work is expected to be completed by the deadline of [February 8, 2022]; however, further COVID-19 impacts have been experienced, with examiners being ill or isolated due to close contact. Initial inspections are targeted by February 8, 2022, with the final vendor report targeted for March 2022, and final APS acceptance in April 2022.
The proposed timeline provides contingency or margin in the schedule to ensure completion of the final report and closure of the surveillance package, to support containment operability.
The duration of the proposed alternative would extend from the current February 8, 2022, deadline for completing the Unit 2, 35th year, IWL Containment Post-Tensioning System Inspection until June 8, 2022. The licensee received verbal authorization from the NRC on February 2, 2022.
As set forth in the enclosed safety evaluation, the NRC staff determines that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The NRC staff concludes that the licensees proposed alternative in Relief Request 69 has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Accordingly, the NRC staff determines that granting relief pursuant to 10 CFR 50.55a(z)(2) 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. Therefore, the NRC staff authorizes the proposed alternative at Palo Verde, Unit 2 for the period beginning February 8, 2022, and ending June 8, 2022, during the Palo Verde, Unit 2, third 10-year Containment Tendon Inspection Program interval.
All other ASME Code Section XI requirements for which the alternative was not specifically requested and authorized in this proposed alternative remain applicable, including a third-party review by the Authorized Nuclear Inservice Inspector.
If you have any questions, please contact the Project Manager, Siva P. Lingam, at 301-415-1564 or by e-mail to Siva.Lingam@nrc.gov.
Sincerely, Digitally signed by Jennifer L. Jennifer L. Dixon-Herrity Dixon-Herrity Date: 2022.02.23 08:54:38 -05'00' Jennifer L. Dixon-Herrity, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-529
Enclosure:
Safety Evaluation cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST 69 REQUEST TO DEFER ASME CODE INSERVICE INSPECTION OF CONTAINMENT TENDON BY 4 MONTHS DUE TO COVID-19 PANDEMIC ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO. STN 50-529
1.0 INTRODUCTION
By electronic submittal dated January 28, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22031A098), Arizona Public Service Company (APS, the licensee) submitted COVID 19 Relief Request 69 (RR-69), to extend containment tendon inspection at Palo Verde Nuclear Generating Station, Unit 2 (Palo Verde, Unit 2) for one time from February 8, 2022, to June 8, 2022 (i.e., 4 months), in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(z)(2), Hardship without a compensating increase in quality and safety. Specifically, pursuant to 10 CFR 50.55a(z)(2), the licensee requested U.S. Nuclear Regulatory Commission (NRC) approval of RR-69 regarding the interval between containment tendon inspections as specified per Subsubarticle IWL-2420 of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Subsection IWL, Requirements for Class CC [Concrete Containment] Concrete Components of Light-Water Cooled Plants, required by 10 CFR 50.55a, Codes and standards.
By teleconference call on February 2, 2022, the NRC provided verbal authorization to APS for the subject RR-69 for Palo Verde, Unit 2 (ADAMS Accession No. ML22034A013).
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(g)(4), Inservice inspection standards requirement for operating plants, throughout the service life of a nuclear power facility, components that are classified as ASME Class CC pressure retaining components must meet the requirements set forth in Section XI of the ASME Code, Subsection IWL, as incorporated by reference in 10 CFR 50.55a(a)(1)(ii), ASME Boiler and Pressure Vessel Code,Section XI, subject to the conditions listed in 10 CFR 50.55a(b)(2)(ix),Section XI condition: Metal containment examinations.Section XI, Subsection IWL of the ASME Code, provides rules for inservice Enclosure
inspection (ISI) and repair/replacement activities of the reinforced concrete and post-tensioning system components of Class CC containment structures. The appropriate edition of the code to be used for successive 120-month inspection intervals is determined under paragraph (g)(4)(ii),
Applicable ISI Code: Successive 120-month intervals, of 10 CFR 50.55a. Alternatives to the requirements of 10 CFR 50.55a(g), Preservice and inservice inspection requirements, may be authorized by the NRC under 10 CFR 50.55a(z)(2) if the licensee demonstrates that the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant 10 CFR 50.55a(g)(4)(ii), the licensees Code of record for the third 10-year containment ISI interval is the 2007 Edition with the 2008 Addenda of ASME Code,Section XI, Subsection IWL. Subsubarticle IWL-2420 Unbonded Post-Tensioning Systems, subparagraph (a) states that Unbonded post-tensioning systems shall be examined in accordance with IWL-2520 at 1, 3, and 5 years following the completion of the containment Structural Integrity Test and every 5 years thereafter. Subsubarticle IWL-2420 further states in subparagraph (c) that The 10-year and subsequent examinations shall commence not more than 1 year prior to the specified dates and shall be completed not more than 1 year after such dates. If plant operating conditions are such that examination of portions of the post-tensioning system cannot be completed within this stated time interval, examination of those portions may be deferred until the next regularly scheduled plant outage. Table IWL-2500-1, Examination Category L-B, Unbonded Post-Tensioning System, provides the examination and test requirements for the post-tensioning system components.
Palo Verde, Unit 2s specified date for the 35th surveillance year subsequent examination under Subsubarticle IWL-2420(a) is February 8, 2020. Therefore, per Subsubarticle IWL-2420(c),
Palo Verde, Unit 2s deadline for the completion of the 35th year inspection is February 8, 2021.
By electronic submittal dated November 5, 2020 (ADAMS Accession No. ML20315A156), APS submitted COVID-19 RR-66 to extend the containment tendon inspection at Palo Verde, Unit 2 by 1 year, in accordance with the requirements of 10 CFR 50.55a(z)(2). On April 2, 2021, the NRC approved RR-66 extending the containment tendon inspection from February 8, 2021, to February 8, 2022 (ADAMS Accession No. ML21089A010). For this relief request, the licensee requests postponing the completion date for the 35th year surveillance to no later than June 8, 2022, under 10 CFR 50.55a(z)(2), because of hardship or unusual difficulty imposed by the national emergency declaration due to the COVID-19 pandemic.
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 authorize, the alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Licensees Proposed Alternative The licensees alternative request applies to the containment unbonded post-tensioning system inspections. Specifically, the request applies to the requirement in Subsubarticle IWL-2420(c) as stated above. The licensees proposed alternative corresponding to the above code requirement is a one-time, 4-month extension beyond the NRC approved date of February 8, 2022, for RR-66 until June 8, 2022.
The licensees November 5, 2020, letter stated that APS did not have the internal capability and equipment to perform the inspection, and this must be done by the vendor. The letter further
stated that 10 contractors were needed to perform the containment tendon inspections. In general, this work activity involves a team of people working in close proximity and does not allow for social distancing which could be a large contributor towards the spread of the virus. As stated in the licensees letter dated January 28, 2022, the vendor delay and sickness due to COVID-19 are the reasons for requesting a 4-month extension for completing the ASME Codes containment unbonded post-tensioning system inspections.
The licensees letter dated November 5, 2020, stated that the prior containment post-tensioning surveillances had been completed successfully with no abnormal degradation. The recent inspection results of the 25th and 30th years inspections concluded that the structural and functional integrity of the post tensioning system was acceptable. The licensees November 5, 2020, letter further stated that a visual examination of the Unit 2 Concrete Containments exterior surface was completed in August of 2017. The inspection results indicated that no conditions which would require structural repair or more frequent examinations were identified, and the condition of the exterior concrete surface was deemed acceptable, per paragraph IWL-3211, Acceptance by Examination.
In the licensees submittal dated January 28, 2022, the licensee stated that it had made good faith efforts to complete the Unit 2 containment tendon examinations by the February 8, 2022, due date. Examinations were originally scheduled to start in November 2021. However, due to the delay of vendor completion of work at other sites, which delayed the mobilization at Palo Verde, Unit 2 until January 2022. The inspection work was completed during the week of February 7, 2022. The vendor report will take approximately 45 days, and APS will complete the finalization of the report by June 8, 2022.
The proposed timeline provides contingency or margin in the schedule to ensure completion of the final report and closure of the surveillance package, to support containment operability. The duration of the proposed alternative would extend from the current February 8, 2022, deadline for completing the Unit 2, 35th year IWL Containment Post-Tensioning System Inspection until June 8, 2022.
3.2 NRC Staff Evaluation The NRC staff reviewed the information provided in the proposed alternative request, as well as general information available regarding the COVID-19 pandemic, and finds that completing the inspections as required would result in a hardship or unusual difficulty.
Summary results of the 25th and 30th years Tendon Surveillances, performed on Palo Verde, Unit 2, was attached to the licensees November 5, 2020, submittal. The tendon surveillances results confirmed that the functional integrity of the selected post-tensioning system met the applicable code requirements. The NRC staff reviewed the licensees tendon surveillances results and noted that the inspections have been completed successfully with no indications of degradation to the post-tensioning system that would compromise the structural integrity of the containment building. Specifically, the NRC staff finds that the licensee performed all the ASME Code,Section XI, Table IWL-2500-1 (L-B) inspection requirements of the containment post-tensioning system and met the requirements as specified in the Code.
Since the previous inspection results were all acceptable, the regression analysis shows that the tendon forces in the post-tensioning system are expected to exceed the minimum prescribed lower limit value for each tendon type for the duration of the current license, and the 2017 visual inspection showed no significant signs of degradation. The NRC staff finds that
conducting the required inspections of the unbonded post-tensioning system by the February 8, 2022, deadline would not have provided an increase in quality or safety commensurate with the increased hardship.
Based on its review, the NRC staff finds it is acceptable for the licensee to defer completion of the required ASME Section XI, Table IWL-2500-1 (L-B) inspections of the containment post-tensioning system for an additional 4 months, or until no later than June 8, 2022. The NRC staff also finds that there is reasonable assurance that the structural integrity of the containment building will be maintained until June 8, 2022, when the required ASME Code inspections will be completed.
4.0 CONCLUSION
As set forth above, the NRC staff determines that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The NRC staff concludes that the licensees proposed alternative in RR 69 has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(2).
Accordingly, the NRC staff determines that granting relief pursuant to 10 CFR 50.55a(z)(2) 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. Therefore, the NRC staff authorizes the proposed alternative at Palo Verde, Unit 2 for the period beginning February 8, 2022, and ending June 8, 2022, during the Palo Verde, Unit 2, third 10-year Containment Tendon Inspection Program interval.
All other ASME Code Section XI requirements for which the alternative was not specifically requested and authorized in this proposed alternative remain applicable, including a third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: J. Ma, NRR Date: February 23, 2022
ML22049A057 *by e-mail OFFICE NRR/DORL/LPL4/PM* NRR/DORL/LPL4/LA* NRR/DEX/ESEB/BC* NRR/DORL/LPL4/BC*
NAME SLingam PBlechman JColaccino JDixon-Herrity DATE 2/18/2022 2/22/2022 2/17/2022 2/23/2022