Letter Sequence Other |
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EPID:L-2018-LLR-0120, Relief Request 62 - Third and Fourth 10-Year Inservice Inspection (ISI) Intervals, Proposed Alternative - Pressurizer Heater Sleeve Repairs (Open) |
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MONTHYEARML18243A5442018-08-31031 August 2018 Relief Request 62 - Third and Fourth 10-Year Inservice Inspection (ISI) Intervals, Proposed Alternative - Pressurizer Heater Sleeve Repairs Project stage: Request ML19044A7342019-02-13013 February 2019 NRR E-mail Capture - Palo Verde1, 2, and 3 - Official Requests for Additional Information for RR 62, Third and Fourth 10-Year ISI Intervals, Proposed Alternative - Pressurizer Heat Sleeve Repairs Project stage: RAI ML19074A1382019-03-14014 March 2019 Response to Request for Additional Information - Relief Request 62 - Third and Fourth 10-Year Inservice Inspection Intervals, Proposed Alternative - Pressurizer Heater Sleeve Repairs Project stage: Response to RAI ML19107A3722019-04-19019 April 2019 Relief Request 62 Regarding Proposed Alternative Pressurizer Heater Sleeve Repairs Project stage: Other 2019-02-13
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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
MONTHYEARML24019A2012024-01-19019 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 IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information ML23251A2332023-09-13013 September 2023 Notification of Post Approval Site Inspection for License Renewal and Request for Information Inspection (05000528/2023011) ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program IR 05000528/20243012023-09-0606 September 2023 Notification of NRC Initial Operator Licensing Examination 05000528/2024301; 05000529/2024301; 05000530/2024301 IR 05000528/20230102023-08-22022 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000528/2023010, 05000529/2023010 and 05000530/2023010 IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) ML23222A2762023-08-10010 August 2023 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canister Identification Numbers AMZDFX175 and AMZDFX176 and Vertical Concrete Cask Identification Numbers AMZDNE175, and AMZDNE176 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 IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 ML23207A2482023-07-26026 July 2023 License Renewal Pressurizer Surge Line Inspection ML23188A1872023-07-0707 July 2023 Fourth 10-Year Interval, Second Period Owners Activity Report Number 2R24 ML23166B0832023-07-0505 July 2023 Independence Spent Fuel Storage Installation - Issuance of Exemption ML23181A1602023-06-30030 June 2023 2 to Updated Final Safety Analysis Report, and Revision 3 to Operations Quality Assurance Program Description ML23180A2222023-06-29029 June 2023 Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) - Operating, TS 3.5.2, Safety Injection Tanks (Sits) - Shutdown, and TS 3.6.5, Containment Air Temperature ML23181A0772023-06-29029 June 2023 Program Review - Simulator Testing Methodology ML23157A1292023-06-0101 June 2023 Annual Report of Guarantee of Payment of Deferred Premium ML23144A3722023-05-24024 May 2023 Response to Regulatory Issue Summary (RIS) 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23143A3912023-05-23023 May 2023 Independent Spent Fuel Storage Installation - Request for Exemption from NAC-MAGNASTOR Certificate of Compliance 72-1031 - Cask Lid Batch 3 Design Requirements ML23145A2772023-05-17017 May 2023 10-PV-2023-05 Post-Exam Comments ML23132A3392023-05-12012 May 2023 Application to Revise Technical Specifications 3.3.11 to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls IR 05000528/20230012023-05-0808 May 2023 and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000528/2023001 and 05000529/2023001 and 05000530/2023001 and 07200044/2023001 ML23128A0692023-05-0808 May 2023 Notification of Biennial Problem Dentification and Resolution Inspection and Request for Information ML23122A1822023-04-29029 April 2023 Transmittal of Technical Specification Bases Revision 76 ML23122A1912023-04-29029 April 2023 Unit 1 Core Operating Limits Report Revision 32, Unit 2 Core Operating Limits Report Revision 25, Unit 3 Core Operating Limits Report Revision 31 ML23116A2772023-04-26026 April 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2022 ML23115A4012023-04-26026 April 2023 Review of the 2022 Steam Generator Tube Inspections During Refueling Outage 23 ML23115A4982023-04-25025 April 2023 2022 Annual Environmental Operating Report IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI ML23108A0342023-04-18018 April 2023 NRC Initial Operator Licensing Examination Approval 05000528/2023301; 05000529/2023301; 05000530/2023301 ML23103A4642023-04-13013 April 2023 Annual Radiological Environmental Operating Report 2022 ML23103A4312023-04-13013 April 2023 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022 IR 05000528/20224012023-04-13013 April 2023 Cyber Security Inspection Report 05000528/2022401 and 05000529/2022401 and 05000530/2022401 ML23102A3292023-04-12012 April 2023 Application for Authorized Use of Mururoa Single-Use, Supplied Air Suits, Models V4F1 and MTH2 ML23102A3242023-04-12012 April 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-107-A, Separate Control Rods That Are Untrippable Versus Inoperable ML23089A4002023-03-30030 March 2023 Consolidated Decommissioning Funding Status Report - 2022 ML23088A4012023-03-30030 March 2023 Project Manager Assignment IR 05000528/20234022023-03-29029 March 2023 and 3 - NRC Security Inspection Report 05000528-2023402, 05000529-2023402, and 05000530-2023402, (Cover Letter Only) ML23080A3002023-03-21021 March 2023 Present Levels of Financial Protection 2024-01-19
[Table view] Category:Safety Evaluation
MONTHYEARML23241B0182023-09-13013 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 ML16358A4152016-12-23023 December 2016 Technical Specifications for One-Time Extension of Completion Time for Emergency Diesel Generator ML16358A6762016-12-23023 December 2016 Issuance of Amendment No. 199, Request for One-Time Extension of the Diesel Generator Completion Time (Emergency Circumstances) 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 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 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 ML15058A0292015-03-27027 March 2015 Staff Assessment Regarding Review of Pressurized-Water Reactor Vessel Internals Aging Management Program Plan ML14202A3782014-09-0909 September 2014 Issuance of Amendment Nos. 194, 194, and 194, Request to Revise TS 3.3.3, Control Element Assembly Calculators and TS 3.3.6, Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip (TAC Nos. MF2879-81) ML14115A0452014-06-25025 June 2014 Issuance of Amendment Nos. 193, 193, and 193, Adopt Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 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 2023-09-13
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 19, 2019 Mr. Robert S. Bement Executive Vice President Nuclear/
Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3-RELIEF REQUEST 62 REGARDING PROPOSED ALTERNATIVE PRESSURIZER HEATER SLEEVE REPAIRS (EPID L-2018-LLR-0120)
Dear Mr. Bement:
By letter dated August 31, 2018, as supplemented by letter dated March 14, 2019 (Agencywide Documents Access and Management System Accession Nos. ML18243A544 and ML19074A138, respectively), Arizona Public Service Company (the licensee) submitted Relief Request 62 for the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3. This relief request proposes an alternative to the American Society of Mechanical Engineers Boiler &
Pressure Vessel Code (ASME Code),Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," requirements related to potential flaws in the original heater sleeve partial penetration welds in all 36 penetrations of each pressurizer.
Specifically, pursuant to Title 10 of the Code of Federal Regulations ( 10 CFR) 50.55a(z)( 1), the licensee submitted Relief Request 62, which pertains to pressurizer heater sleeve remnant J-groove weld flaw evaluation and successive examination requirements, on the basis that the proposed alternative provides an acceptable level of quality and safety.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittals and determined that the alternative proposed by the licensee in Relief Request 62 will provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)( 1).
Therefore, the NRC staff authorizes the use of the proposed alternative in Relief Request 62 for the remainder of the third, and the entire fourth, 10-year inservice inspection intervals at PVNGS, Unit 1, and the remainder of the fourth 10-year inservice inspection intervals at PVNGS, Units 2 and 3, as identified in Section 3.2 of the enclosed safety evaluation.
All other ASME Code,Section XI requirements for which relief was not specifically requested and authorized in the subject relief request remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
R. Bement 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, Robert J. Pascarelli, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosure:
Safety Evaluation cc: Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST 62 REGARDING PROPOSED ALTERNATIVE PRESSURIZER HEATER SLEEVE REPAIRS ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 DOCKET NOS. STN 50-528, 50-529, AND 50-530
1.0 INTRODUCTION
By letter dated August 31, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18243A544), as supplemented by letter dated March 14, 2019 (ADAMS Accession No. ML19074A138), Arizona Public Service Company (APS, the licensee) submitted Relief Request (RR) 62, requesting an alternative to certain requirements of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code (ASME Code) for previously repaired pressurizer heater sleeve nozzles at the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3.
Specifically, pursuant to Title 1O of the Code of Federal Regulations ( 10 CFR) 50.55a(z)( 1), the licensee submitted RR 62, which pertains to pressurizer heater sleeve remnant J-groove weld flaw evaluation and successive examination requirements, on the basis that the proposed alternative provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
The inservice inspection (ISi) of ASME Code Class 1, 2, and 3 components is to be performed in accordance with ASME Code,Section XI, and applicable editions and addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the U.S. Nuclear Regulatory Commission (NRC).
The regulations in 10 CFR 50.55a(z) state, in part, that alternatives to the requirements of 10 CFR 50.55a(g) may be used, when authorized by the NRC, if the licensee demonstrates that: (1) the proposed alternative would provide an acceptable level of quality and safety, or (2) compliance with the specified requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
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 proposed alternative requested by the licensee.
Enclosure
3.0 TECHNICAL EVALUATION
3.1 ASME Code Components Affected
The affected component is the pressurizer vessel, specifically, the original partial penetration welds at the associated remnant heater sleeves for PVNGS, Units 1, 2, and 3. The pressurizer is an ASME Code Class 1 component.
3.2 Applicable Code Editions and Addenda The licensee provided the applicable ASME Code,Section XI editions and addenda for each unit as shown in the table below. In addition, the table shows the applicable ISi 10-year intervals, including the scheduled start and end dates.
PLANT ISi INTERVAL ASME CODE EDITION START END PVNGS Unit 1 2001 Edition through third 07/18/08 05/31/19 2003 Addenda PVNGS Unit 1 fourth 2013 Edition 06/01/19 07/17/28 PVNGS Unit2 fourth 2013 Edition 11/01/18 10/31/28 PVNGS Unit 3 fourth 2013 Edition 06/01/18 01/10/28 The applicable edition of ASME Code, Section Ill, for PVNGS, Units 1, 2, and 3, is the 1974 Edition, through winter 1975 Addenda.
3.3 Applicable Code Requirements As stated by the licensee in its letter dated August 31, 2018, following are the applicable requirements of ASME Code,Section XI, for which the licensee seeks an alternative:
- Section XI, Article IWA-4000 provides requirements for repair/replacement activities.
IWA-4421 states, in part:
Defects shall be removed or mitigated in accordance with the following requirements ...
IWA-4422.1 (a) states, in part:
A defect is considered removed when it has been reduced to an acceptable size ...
IWA-4422.1 (b) states, in part:
Alternatively, the defect removal area and any remaining portion of the defect may be evaluated and the component accepted in accordance with the appropriate flaw evaluation provisions of Section XI ...
- Section XI, Article IWA-3000, provides standards for examination evaluation.
IWA-31 OO(a) states, in part:
Evaluation shall be made of flaws detected during an inservice examination as required by IWB-3000 for Class 1 pressure retaining components ...
IWA-3300(b) states, in part:
Flaws shall be characterized in accordance with IWA-3310 through IWA-3390, as applicable.
- Section XI, Article IWB-3000, provides acceptance standards for Class 1 components.
IWB-3420 states:
Each detected flaw or group of flaws shall be characterized by the rules of IWA-3300 to establish the dimensions of the flaws. These dimensions shall be used in conjunction with the acceptance standards of IWB-3500.
- Section XI, Article IWB-2000 provides examination and inspection requirements for Class 1 components.
IWB-2420(b) states, in part:
If a component is accepted for continued service in accordance with IWB-3132.3 or IWB-3142.4, the areas containing flaws or relevant conditions shall be reexamined during the next three inspection periods listed in the schedule of the inspection program of IWB-2400 ...
3.4 Reason for Request The licensee stated that during the preparation and review of the ISi program documents for the fourth 10-year ISi interval for PVNGS, Units 1, 2 and 3, the licensee determined that previously approved RR 29 related to flaws in the remnant pressurizer heater sleeves and remnant J-groove welds had only been authorized for the second interval. The current relief request seeks the same alternative for the remainder of the third ISi interval at Unit 1, the remainder of the fourth ISi intervals at Units 2 and 3, and the fourth ISi interval at Unit 1.
3.5 Proposed Alternative and Basis for Use (As stated by the licensee)
As stated by the licensee in its letter dated August 31, 2018:
Pursuant to 10 CFR 50.55a(z)( 1), APS requests NRC authorization of RR 62, which proposes an alternative to the ASME Code requirements of Section XI related to potential flaws in the original heater sleeve partial penetration welds in all 36 penetrations of each pressurizer. Authorization was previously granted by the NRC for the flaw evaluation as an alternative to the ASME Section XI
requirements for flaw removal IWA-4421, flaw characterization of IWA-3300, and successive examinations of IWB-2420 (Reference 3 [of the licensee's submittal]).
The original remnant sleeve and penetration welds remain as evaluated in RR29.
The flaw evaluation submitted with RR 29 and associated corrosion analysis (Reference 7 [of the licensee's submittal]) have been analyzed for the 60-year licensed operating life of the plant and have previously been determined to provide an acceptable level of quality and safety (Reference 3 [of the licensee's submittal]).
The applicable Code edition and addenda for ASME Section XI activities at the time that RR 29 was submitted was the 1992 edition, 1992 addenda. Pressurizer heater penetration welds were listed as 84.20 inspection items in Table IWB-2500-1. The 84.20 examination item is no longer listed in Table IWB-2500-1 for the applicable Code editions/addenda for the successive third and fourth 10-year ISi intervals. The pressurizer heater penetrations are leak tested every refueling outage as part of a system leakage test as 815.10 items. Since the time of the half-sleeve repairs there have been no indications of leaks identified in the new welds at the heater sleeve penetrations. Examinations will continue as required per IWB-2500 of the ASME Code.
3.6 NRC Staff Evaluation The licensee requested authorization of proposed alternative RR 62 pursuant to 10 CFR 50.55a(z)(1). The licensee requested to use RR 62 on the basis that its proposed alternative to the ASME Code,Section XI requirements for flaws in pressurizer heater sleeve remnant J-groove welds provides an acceptable level of quality and safety.
By letter dated May 15, 2003 (ADAMS Accession No. ML031400051 ), the licensee submitted RR 23, "Pressurizer Heater Sleeves," for the second 10-year ISi interval at PVNGS, Units 1, 2, and 3. RR 23 was to perform ambient temperature temper bead welding to install weld buildups (pads) on the outside of the pressurizer to repair heater sleeves. The repair involved removing the lower portion of the heater sleeve, performing a weld buildup with Alloy 52 weld metal on the outside surface of the pressurizer, machining, inserting a new replacement Alloy 690 sleeve, and attaching the new replacement sleeve to the Alloy 52 weld pad using Alloy 52 weld metal with a J-groove weld design. In this design, the upper portion of the heater sleeve and the original J-groove weld on the inside surface of the pressurizer remain. This repair method is sometimes referred to as a half-sleeve pad repair. This type of repair is designed to be used on leaking heater sleeves due to degraded sleeve material or a degraded J-groove weld. In addition, this type of repair can be used proactively as a mitigation method. The NRC staff authorized this alternative for PVNGS, Units 1, 2, and 3, for the second 10-year ISi intervals on July 30, 2003 (ADAMS Accession No. ML032110542). RR 23 was only associated with the use of ambient temperature temper bead welding. RR 23 did not address potential flaws in the remnant sleeve material or the remnant J-groove weld. RR 23 was implemented to repair all of the PVNGS, Unit 2, heater sleeves during the November 2003 outage.
By letter dated June 15, 2004 (ADAMS Accession No. ML041750296), the licensee submitted RR 28, "Ambient Temperature Temper Bead Welding for Pressurizer Half-Sleeve replacement,"
and RR 29, "Remnant Sleeve(s) Flaw Evaluation," for the second 10-year ISi intervals for PVNGS, Units 1, 2, and 3.
In RR 28, the licensee proposed an alternative to use ambient temperature temper bead welding to perform sleeve repairs that use a half-sleeve repair approach, but did not have a weld buildup on the outside of the pressurizer for attachment of the replacement sleeve, as proposed and authorized in RR 23. The RR 28 approach was similar to control rod drive mechanism/control element drive mechanism nozzle repairs, where the attachment weld is located in the bore (half-sleeve mid-wall repair). At the time, the licensee intended to use this repair method on PVNGS, Units 1 and 3. Although approved for use by the NRC, this repair method in RR 28 was never implemented, and PVNGS used the method approved in RR 23 for all pressurizer sleeves on Units 1, 2, and 3.
In RR 29, the licensee proposed an alternative to flaw evaluation requirements and successive examinations of the remnant half-sleeves, including the J-groove attachment weld left in place after performing pressurizer heater sleeve repairs. The licensee requested RR 29 for use at PVNGS, Units 1, 2, and 3, and it can be applied to either of the heater sleeve repair methods (RR 23 or RR 28). The flaw evaluation supporting this alternative utilized both linear elastic fracture mechanics and elastic plastic fracture mechanics. The flaw evaluation demonstrated compliance with the ASME Code,Section XI criteria for the 40-year plant life, as well as for a potential 20-year life extension. However, the licensee requested, and the NRC authorized, RR 29 for the second 10-year ISi intervals only for all three units. The NRC staffs evaluation of remnant heater sleeves and remnant sleeve J-groove welds under RR 29 is detailed in Section 5.2 of its safety evaluation dated November 5, 2004, for RR 29 (ADAMS Accession No. ML043130170).
As stated in its letter dated August 31, 2018, the alternative in RR 29 was inadvertently not submitted for the third 10-year ISi interval. In its RR 62 request, the licensee requested the proposed alternative for the third and fourth 10-year ISi intervals for PVNGS, Units 1, 2, and 3.
Units 2 and 3 are currently in the fourth 10-year ISi interval, and Unit 1 will begin the fourth 10-year ISi interval on June 1, 2019. In a request for additional information dated February 13, 2019 (ADAMS Accession No. ML19044A734), the NRC staff noted that in accordance with 10 CFR 50.55a(z), which states, in part, "A proposed alternative must be submitted and authorized prior to implementation," the staff would be unable to approve a proposed alternative in accordance with 10 CFR 50.55a(z) for the third intervals at PVNGS, Units 2 and 3, and all but the remainder of the third interval for Unit 1. In its letter dated March 14, 2019, the licensee modified its proposed alternative to apply to the remainder of the third ISi interval at Unit 1, the remainder of the fourth ISi intervals at Units 2 and 3, and the fourth ISi interval at Unit 1. The NRC staff finds this acceptable because the time periods that the licensee has requested in its alternative are consistent with 10 CFR 50.55a(z)(1 ).
The currently proposed alternative proposes the same alternative as RR 29, which, as stated above, was approved by the NRC for the second ISi intervals at PVNGS, Units 1, 2, and 3. The licensee had previously submitted Report No. SIR-04-045, Revision 0, dated June 2004, to support RR 29. The licensee referenced this report in support of RR 62. The report includes fracture mechanics analyses of postulated flaws in the original Alloy 600 heater sleeve and weld metal. The fracture mechanics analyses demonstrate that an assumed flaw left in place is acceptable for the life of PVNGS, Units 1, 2, and 3, including 20-year life extensions. In addition, the report provides the results of a corrosion analysis for the crevice region between the sleeve and pressurizer base material. The licensee's analysis concludes that anticipated corrosion in the crevice region will be within code allowable values, and is acceptable for the life
of the plant, including the 20-year life extensions. The ASME Code of Record for the second 10-year ISi intervals at PVNGS, Units 1, 2, and 3, was the 1992 Edition through the 1992 Addenda. The fracture mechanics analysis associated with RR 29 was performed in accordance with the 2001 Edition through 2003 Addenda of ASME Code,Section XI. However, the 2013 Edition of ASME Code,Section XI, is applicable to the fourth 10-year ISi interval at PVNGS, Units 1, 2, and 3. In its request for additional information dated February 13, 2019, the NRC staff requested that the licensee clarify whether it had performed a reconciliation between the ASME Code,Section XI edition/addenda used for the second 10-year ISi interval and the one used for the fourth 10-year ISi interval, and whether any differences impact the analysis detailed in Report No. SIR-04-045. The licensee responded in its letter dated March 14, 2019, as follows:
APS has performed a reconciliation of the 1992 Edition/Addenda to the 2013 Edition of the ASME Code Section XI for the purpose of determining whether the supporting analysis (Report No. SIR-04-045) continues to meet the applicable requirements of the Code for the analytical evaluation of flaws. There are no differences identified between the 1992 Editions/Addenda and the 2013 Edition that impact the outcome and/or conclusions of the supporting analysis.
The NRC staff compared the ASME Code requirements applicable to RR 29 to the ASME Code requirements applicable to RR 62. The staff did not identify any differences that would result in a significant change in the results of the licensee's fracture mechanics analysis or corrosion analysis detailed in Report No. SIR-04-045. The staff previously reviewed this report as part of the review and authorization of RR 29. The results of the staff's review of Report No. SIR-04-045 are detailed in Section 5.2 of the RR 29 safety evaluation. Therefore, the NRC staff finds that RR 62 is acceptable.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the alternative proposed by the licensee in RR 62 will provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)( 1). Therefore, the NRC staff authorizes the use of the proposed alternative in RR 62 for the remainder of the third and the entire fourth 10-year ISi interval at PVNGS, Unit 1, and the remainder of the fourth 10-year ISi intervals at PVNGS, Units 2 and 3, as identified in Section 3.2 of this safety evaluation.
All other ASME Code,Section XI requirements for which relief was not specifically requested and authorized in the subject RR remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: R. Davis Date: April 19, 2019
R.Beme~
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3-RELIEF REQUEST 62 REGARDING PROPOSED ALTERNATIVE PRESSURIZER HEATER SLEEVE REPAIRS (EPID L-2018-LLR-0120) DATED APRIL 19, 2019 DISTRIBUTION:
PUBLIC PM File Copy RidsRgn4MailCenter Resource RDavis, NRR RidsNrrDorlLpl4 Resource RidsNrrPMPaloVerde Resource RidsNrrLAPBlechman Resource RidsNrrDmlrMphb Resource RidsACRS_MailCTR Resource ADAMS Access1on No.: ML19107A372 *b1y e-ma1*1 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DMLR/MPHB/BC(A)*
PBlechman NAME SLingam (TWengert for) SCumblidge (LRonewicz for)
DATE 04/19/2019 04/17/2019 04/15/2019 OFFICE NRR/DORL/LPL4/BC NRR/DORL/LPL 1/PM NAME RPascarelli SLingam (TWengert for)
.*
DATE 04/19/2019 04/19/2019 OFFICIAL RECORD COPY