|
---|
Category:E-Mail
MONTHYEARML24011A1002024-01-10010 January 2024 March 2024 Emergency Preparedness Program Inspection - Request for Information ML23334A1612023-11-30030 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - RAIs Associated with License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23334A0072023-11-29029 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR That Revises TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23298A1232023-10-25025 October 2023 NRR E-mail Capture - Palo Verde, Unit 1 - RAIs for Relief Request 70, Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle ML23243B0082023-08-31031 August 2023 NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX) ML23233A0132023-08-18018 August 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23220A0512023-08-0303 August 2023 NRR E-mail Capture - Re Palo Verde 1, 2, and 3 - SUNSI Review of UFSAR, Rev. 22 ML23202A0162023-07-20020 July 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR to Revise TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23143A1332023-05-23023 May 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR Revising TS 3.3.11 to Adopt TSTF-266-A, Rev. 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls ML23130A0132023-05-10010 May 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review for Authorized Use of Mururoa Supplied Air Suits (Models V4F1 and MTH2) Pursuant to 10 CFR 20.1703 and 10 CFR 20.1705 ML23017A0932023-01-17017 January 2023 NRR E-mail Capture - Palo Verde - Acceptance of License Amendment Request Regarding Adoption of TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable (L-2022-LLA-0181) ML23013A0632023-01-13013 January 2023 NRR E-mail Capture - Palo Verde Unit 1 -Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22348A1672022-12-14014 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22339A2372022-12-0505 December 2022 NRR E-mail Capture - Palo Verde Unit 1 Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22173A0682022-06-17017 June 2022 Email Concurrence on SE Input for Columbia Pltr LAR ML22167A1872022-06-16016 June 2022 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Revised Acceptance Review of LAR to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues ML22136A0922022-05-16016 May 2022 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR to Adopt TSTF-487-A, Revision 1, Relocate DNB Parameters to the COLR ML22075A1902022-03-16016 March 2022 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues ML22055A5842022-02-24024 February 2022 NRR E-mail Capture - Palo Verde, Unit 3 - Final RAIs for 22nd Refueling Outage (Spring 2021) Steam Generator Tube Inservice Inspection Report 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 ML22032A0312022-01-31031 January 2022 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review for an Exemption Regarding Elimination of Dafas Using RIPE Process ML22025A4012022-01-0303 January 2022 March 2022 Emergency Preparedness Program Inspection - Request for Information ML21333A1982021-11-19019 November 2021 NRC Review of PVNGS Training Needs Analysis and Training Required by Condition I of the Confirmatory Order EA-20-054 ML21306A1882021-10-18018 October 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Second Pre-submittal Meeting for the Proposed Exemption to Eliminate Dafas Using RIPE Process ML21272A0592021-09-28028 September 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - SUNSI Review of UFSAR, Rev. 21 ML21264A1352021-09-17017 September 2021 NRR E-mail Capture - Palo Verde 1, 2 and 3 - Acceptance Review of LAR Associated with Permanent Extension of Containment ILRT Frequency to 15 Years (Type a) and CIV Leak Rate Test Frequency to 75 Months (Type C) ML21237A0762021-08-25025 August 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of RR-67, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection ML21228A0082021-08-16016 August 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of an LAR for Administrative Changes to Technical Specifications 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) ML21237A5172021-08-10010 August 2021 Email to PV Licensee and Palo Verde Nuclear Generating Station, Units 1, 2 and 3 - Notification of Inspection of the Licensees Implementation Industry Initiative Associated with the Open Phase Condition (NRC Bulletin 2012-01) and Request Fo ML21160A1442021-06-0909 June 2021 NRR E-mail Capture - Palo Verde 1 and, 2 - Acceptance Review for Order Approving Transfers of Control of Licenses for Minority Interests Subject to Expiring Leases ML21154A0082021-05-26026 May 2021 NRR E-mail Capture - Palo Verde 1, 2 and 3 - Official RAIs for LAR Associated with Permanent Extension of Containment ILRT Frequency to 15 Years (Type a) and CIV Leak Rate Test Frequency to 75 Months (Type C) ML21146A3342021-05-14014 May 2021 ISFSI - Final Package for an Order Associated with Indirect Transfers of Control of Licenses from Pnm to Avangrid ML21132A2372021-05-12012 May 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3, and ISFSI - Final Package for an Order Associated with Indirect Transfers of Control of Licenses from Pnm to Avangrid ML21103A3632021-04-13013 April 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review for Indirect Transfer of Control of Licenses Pursuant to 10 CFR 50.80 and 10 CFR 72.50 ML21064A2372021-03-0303 March 2021 ISI Request for Information Rls ML21053A0262021-02-22022 February 2021 NRR E-mail Capture - Palo Verde 1, 2 and 3 - Acceptance Review of LAR Associated with Permanent Extension of Containment ILRT Frequency to 15 Years (Type a) and CIV Leak Rate Test Frequency to 75 Months (Type C) ML21043A1462021-02-11011 February 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAI for an Order Associated with Indirect License Transfer from Public Service Company of New Mexico to Avangrid, Inc ML21023A0212021-01-13013 January 2021 PVNGS PI&R Request for Information RA ML20366A1682020-12-31031 December 2020 NRR E-mail Capture - Palo Verde 1, 2, and 3, and ISFSI - Acceptance Review of an Order Associated with Indirect Transfers of Control of Licenses ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 ML20325A0392020-11-19019 November 2020 NRR E-mail Capture - Palo Verde 2 - Verbal Authorization of RR 66 to Extend Containment Tendon Inspection by One Year Based on 10 CFR 50.55a(Z)(2) ML20316A0162020-11-0909 November 2020 NRR E-mail Capture - Palo Verde 2 - Acceptance Review of RR 66, Request Containment Post-Tensioning System Inspection One-Time by One Year Due to COVID-19 Pandemic ML20295A4912020-10-21021 October 2020 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR Associated with Adopting TSTF-501, Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control ML20265A0982020-09-21021 September 2020 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of License Amendment Associated with Making Necessary Administrative Changes to Technical Specifications ML20108E9462020-04-16016 April 2020 NRR E-mail Capture - (External_Sender) Clarification to PVNGS Part 26 Exemption Request (ML20105A481) ML20091K0752020-03-31031 March 2020 NRR E-mail Capture - Palo Verde 2 - Acceptance Review of RR 65, Request for Relief from RPV Bottom Mounted Instrumentation Nozzles and a Pressurizer Surge Line Weld Overlay Examination ML20091M1992020-03-31031 March 2020 NRR E-mail Capture - Palo Verde 2 - Verbal Authorization of RR 65, Request for Relief from RPV Bottom Mounted Instrumentation Nozzles and a Pressurizer Surge Line Weld Overlay ISI Examinations ML20050C9742020-02-19019 February 2020 NRR E-mail Capture - Palo Verde 1,2, and 3 - Framatome Htp Fuel LAR and Exemption Third Audit Summary (EPIDs L-2018-LLA-0194 and L-2018-LLE-0010) 2024-01-10
[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:Report
MONTHYEARML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML23325A1612023-10-26026 October 2023 Relief Request 70 - Proposed Alternatives in Accordance with 10 CFR 50.55a(z)(1) for Pressurizer Lower Shell Temperature Nozzle ML22308A1662022-11-0404 November 2022 23rd Refueling Outage Steam Generator Tube Inspection Report ML22091A3072022-04-0101 April 2022 Independent Spent Fuel Storage Installation (Isfsi), Evacuation Time Estimate Study ML21077A2562021-03-18018 March 2021 El Paso Electric Co., Application for Approval of Indirect Transfer of Control of Licenses Pursuant to 10 C.F.R. 50.80 and 72.50 ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 ML19136A4092019-05-16016 May 2019 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for Calendar Year 2018 ML19046A3512019-02-15015 February 2019 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R21 ML18187A4172018-07-0606 July 2018 License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel ML17181A5152017-06-29029 June 2017 Flooding Focused Evaluation Summary ML17248A5262017-05-30030 May 2017 3INT-ISI-3, Revision 4, Third Inspection Interval Inservice Inspection Program Summary Manual, Unit 3, Enclosure 3 to 102-07551-MDD/MSC ML17006A2172017-01-0505 January 2017 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U3R19 ML16306A4442016-11-14014 November 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML16321A0032016-10-31031 October 2016 WCAP-18030-NP, Revision 1, Criticality Safety Analysis for Palo Verde Nuclear Generating Station Units 1, 2, and 3. ML16221A6042016-09-13013 September 2016 Staff Assessment of Information Provided Under Title 10 of Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of Near-Term Task Force Review of Insights from . ML16120A3892016-04-28028 April 2016 1-SR-2016-001-00, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional ML15336A0842015-11-30030 November 2015 NET-300047-07 Revision 1, Material Qualification Report of Maxus for Spent Fuel Storage. ML15188A0492015-06-30030 June 2015 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U3R18 ML15111A4302015-04-17017 April 2015 Attachments 2 & 3: Flaw Fracture Mechanics, Corrosion & Loose Parts Evaluations for One Cycle Relief (DAR-MRCDA-15-6-NP) and APS Response to NRC Request for Additional Information Dated April 14, 2015 ML15076A0732015-03-10010 March 2015 Seismic Hazard and Screening Report ML15012A4462015-01-0606 January 2015 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U1R18 ML15027A1222014-12-19019 December 2014 Technical Specification (TS) Bases Revision 61 ML14184B3822014-06-27027 June 2014 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R18 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14126A6362014-04-30030 April 2014 APS Supplement to the Seismic Walkdown Report Requested by the NRC Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1, 2.3, and 9.3 of the Near-Term Task Force. ML14087A1882014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident ML14034A1472014-01-24024 January 2014 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U3R17 ML13329A0382013-08-31031 August 2013 WCAP-17787-NP, Rev 0, Palo Verde Nuclear Generating Station STAR Program Implementation Report. ML13252A1112013-08-31031 August 2013 WCAP-17680-NP, Supplement 1, Rev. 0, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2 - Supplemental Information. CY-12-009, Closure Options for Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance2013-05-16016 May 2013 Closure Options for Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance ML13120A5032013-04-10010 April 2013 Technical Requirements Manual, Revision 57 ML1307003422013-02-28028 February 2013 APS Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML13022A4072013-01-14014 January 2013 Third 10-Year Interval, Second Period: Owner'S Activity Report for Unit 2 Refueling Outage 17 (U2R17) ML12355A7482012-12-31031 December 2012 Evacuation Time Estimate Study; Cover Through Section 4 ML12355A7512012-12-14014 December 2012 Evacuation Time Estimate Study; Section 5 Through 12 ML12355A7522012-12-14014 December 2012 Evacuation Time Estimate Study; Appendix a Through H ML12278A1002012-09-0707 September 2012 Pressurized Water Reactor (PWR) Internals Aging Management Program Plan ML12229A1192012-08-0303 August 2012 Attachment 4, PVNGS Engineering Study 13-ES-A037, Revision 0, Fault Tree Analysis and Reliability Evaluation for Low Pressure Safety Injection (LPSI) Pump Trip at the Recirculation Actuation Signal (RAS) ML12229A1202012-08-0303 August 2012 Attachment 5, PVNGS Engineering Study 13-NS-C089, Revision 0, PRA Evaluation of LPSI Pump Failing to Trip on RAS ML12200A0312012-06-26026 June 2012 Third 10-Year Interval, First Period: Owner'S Activity Report Number U3R16 2024-01-19
[Table view] Category:Technical
MONTHYEARML23325A1612023-10-26026 October 2023 Relief Request 70 - Proposed Alternatives in Accordance with 10 CFR 50.55a(z)(1) for Pressurizer Lower Shell Temperature Nozzle ML22308A1662022-11-0404 November 2022 23rd Refueling Outage Steam Generator Tube Inspection Report ML22091A3072022-04-0101 April 2022 Independent Spent Fuel Storage Installation (Isfsi), Evacuation Time Estimate Study ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 ML18187A4172018-07-0606 July 2018 License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel ML17248A5262017-05-30030 May 2017 3INT-ISI-3, Revision 4, Third Inspection Interval Inservice Inspection Program Summary Manual, Unit 3, Enclosure 3 to 102-07551-MDD/MSC ML16321A0032016-10-31031 October 2016 WCAP-18030-NP, Revision 1, Criticality Safety Analysis for Palo Verde Nuclear Generating Station Units 1, 2, and 3. ML15336A0842015-11-30030 November 2015 NET-300047-07 Revision 1, Material Qualification Report of Maxus for Spent Fuel Storage. ML15076A0732015-03-10010 March 2015 Seismic Hazard and Screening Report ML15027A1222014-12-19019 December 2014 Technical Specification (TS) Bases Revision 61 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request ML14126A6362014-04-30030 April 2014 APS Supplement to the Seismic Walkdown Report Requested by the NRC Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1, 2.3, and 9.3 of the Near-Term Task Force. ML14087A1882014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident ML13329A0382013-08-31031 August 2013 WCAP-17787-NP, Rev 0, Palo Verde Nuclear Generating Station STAR Program Implementation Report. ML13120A5032013-04-10010 April 2013 Technical Requirements Manual, Revision 57 ML12355A7482012-12-31031 December 2012 Evacuation Time Estimate Study; Cover Through Section 4 ML12355A7512012-12-14014 December 2012 Evacuation Time Estimate Study; Section 5 Through 12 ML12355A7522012-12-14014 December 2012 Evacuation Time Estimate Study; Appendix a Through H ML12278A1002012-09-0707 September 2012 Pressurized Water Reactor (PWR) Internals Aging Management Program Plan ML12229A1202012-08-0303 August 2012 Attachment 5, PVNGS Engineering Study 13-NS-C089, Revision 0, PRA Evaluation of LPSI Pump Failing to Trip on RAS ML12229A1192012-08-0303 August 2012 Attachment 4, PVNGS Engineering Study 13-ES-A037, Revision 0, Fault Tree Analysis and Reliability Evaluation for Low Pressure Safety Injection (LPSI) Pump Trip at the Recirculation Actuation Signal (RAS) ML1106107582011-01-26026 January 2011 Technical Requirements Manual, Revision 54 ML1106107572011-01-26026 January 2011 PVNGS Technical Requirements Manual, Revision 54. List of Effective Pages ML1021500372010-07-22022 July 2010 Engineering Study 13-MS-B094, Revision 0 ML1016607492009-05-0101 May 2009 Adeq 2009a Palo Verde Aquifer Protection Permit (Area Wide) No. P-100388. Issued by Arizona Dept of Environmental Quality. May 2009 ML0828200292008-10-0101 October 2008 Request for Amendment to Technical Specification 5.5.16, Containment Leakage Rate Testing Program ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0906410162008-06-30030 June 2008 WCAP-16835-NP, Rev. 0, Palo Verde Nuclear Generating Station Units 1, 2, and 3; Basis for RCS Pressure and Temperature Limits Report. ML0810801162008-04-10010 April 2008 Request for Amendment to Technical Specification 3.5.5, Refueling Water Tank (RWT) to Increase the RWT Minimum Water Level Under Exigent Circumstances ML0719303162007-03-12012 March 2007 Chemical Effect Head Loss Test Specification ML0719303652007-03-0707 March 2007 CCI Chemical Laboratory Bench Top Test Rev 0 ML0626301802006-08-16016 August 2006 Request for Amendment to Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.9, 3.8.1.10, & 3.8.1.14 ML0617804692006-04-30030 April 2006 Enclosure 2D, Non-Proprietary, Redacted Westinghouse Response to NRC Request for Additional Information Regarding Technical Specification Improvement and Tubesheet Inspection Depth for Steam Generator Tubes ML0602005772006-01-13013 January 2006 Revised Redacted Version of Response to Information Request Dated February 24, 2005 ML0602005752006-01-13013 January 2006 Revised Redacted Version of Recirculation Sump Void Testing and Probabilistic Risk Assessment Preliminary Results Dated December 27, 2004 ML0534802032005-12-0505 December 2005 Report of Boron Deposit at Control Element Drive Mechanism Vent ML0531203902005-10-28028 October 2005 Revised Station Blackout Evaluation ML0525601382005-07-0505 July 2005 Redacted Version of Proprietary Submittal Dated February 15, 2005 Regarding Safety Significance Evaluation of ECCS Containment Sump Voided Piping ML0517903492005-06-21021 June 2005 List of References Associated with ASME Code Case N-499 to Support NRC Review of Inservice Inspection (ISI) Program Relief Request No. 33 for Pressurizer Base Material Heating ML0519404732005-02-28028 February 2005 Attachment 2-E, DAR-OA-05-3, Revision 0, Report of SBLOCA Analyses with Degraded ECCS Flow After RAS Performed for Arizona Public Service in Support of Palo Verde Nuclear-Generating Station Units 1, 2, and 3 ML0505402582005-02-15015 February 2005 Attachment 2-F, 13-NS-C074, Rev 0, Significance Determination of Containment Sump Air Entrainment. ML0504503532005-02-0404 February 2005 Submittal of Redacted Version of Recirculation Sump Void Testing and Probabilistic Risk Assessment Preliminary Results ML0429603662004-07-0202 July 2004 Discussion and Proposed Resolution of NRC AIT URI (Unresolved Issue) Relating to MSIS Impact on AF-A Operability (6/14/04 Three Unit LOOP Trip). ML0424500452004-06-30030 June 2004 Reformatted Technical Report SIR-04-045, Revision 0, Supporting the Palo Verde Pressurizer Heater Sleeve Mid-Wall Repair ML0429603432004-06-28028 June 2004 Evaluation of CVCS Soft Parts Due to High Temperature Letdown Event. ML0412102272004-04-15015 April 2004 Emergency Core Cooling System (ECCS) Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report ML0316201772003-06-0404 June 2003 ISFSI, Registration of Dry Spent Fuel Transportable Storage Canister Identification No. AMZDFX003 & Report of Cask Performance ML0309806332003-04-0202 April 2003 Response to Request for Additional Information Regarding Relaxation Request to NRC Order EA-03-009 ML0233004122002-11-21021 November 2002 Supplement to Request for a License Amendment to Support Replacement of Steam Generators & Uprated Power Operations ML0230903252002-10-29029 October 2002 Special Report 1-SR-2002-002 2023-10-26
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle ML23048A3202023-02-17017 February 2023 Response to NRC Requests for Additional Information Regarding 2022 Unit 1 Steam Generator Tube Inspections ML22090A0802022-03-31031 March 2022 Response to NRC Requests for Additional Information Regarding 2021 Unit 3 Steam Generator Tube Inspections ML22053A2122022-02-22022 February 2022 Response to Requests for Confirmation of Information for Exemption from Certain Requirements of 10 CFR 50.62(c)(1) Using Risk-Informed Process for Evaluations ML21173A3602021-06-22022 June 2021 Response to Request for Additional Information for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML21061A1562021-02-26026 February 2021 Spent Fuel Storage Installation, Response to Request for Additional Information Regarding Application for Order Approving Indirect Transfers of Control of Licenses ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 ML20090L9442020-03-30030 March 2020 APS Response to Request for Additional Information- Relief Request 65 Unit 2, COVID-19, Request for Relief from Bottom Mounted Instrumentation Nozzles and a Pressurizer Nozzle to Surge ML20073R7532020-03-13013 March 2020 Independent Spent Fuel Storage Installation (ISFSI) - APS Response to Request for Additional Information for Changes to PVNGS Emergency Plan Staffing Requirements ML20054A2692020-02-19019 February 2020 Response to Request for Additional Information - Relief Request 64 - Unit 1 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML19340B2142019-12-0606 December 2019 Response to NRC Request for Additional Information Regarding 2019 Steam Generator Tube Inspections ML19331A3612019-11-26026 November 2019 Supplemental Response to NRC Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome CE16HTP Fuel ML19277J4572019-10-0404 October 2019 Response to NRC Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome CE16HTP Fuel ML19165A1402019-06-14014 June 2019 Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML19137A1182019-05-17017 May 2019 Response to NRC Staff Request for Additional Information from Reactor Assessment and Human Performance Branch Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome High Thermal 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 ML19031C9052019-01-31031 January 2019 Supplemental License Amendment Request to Revise Technical Specifications Regarding Response Time Testing of Pressure Transmitters and Request for Additional Information Response ML18296A4662018-10-18018 October 2018 Supplemental Information Regarding License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel ML18278A2952018-10-0505 October 2018 Response to Request for Additional Information for Risk-Informed Completion Times Supplemental Responses for Items 17.f and 21 ML18264A3182018-09-21021 September 2018 Response to Request for Additional Information for Risk-Informed Completion Times ML18194A9142018-07-13013 July 2018 Supplemental Response to Request for Additional Information 3.a for License Amendment Request to Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML18152B8742018-06-0101 June 2018 Response to Electrical Engineering Operating Reactor Branch (Eeob) Request for Additional Information for Risk-Informed Completion Times ML18138A4802018-05-18018 May 2018 Response to Request for Additional Information for Risk-Informed Completion Times ML18129A4482018-05-0909 May 2018 APS Response to Request for Additional Information for License Amendment Request to Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML17272B0332017-09-29029 September 2017 Response to Request for Additional Information Regarding Fourth 10-Year Interval Pump and Valve Inservice Testing Program Relief Requests ML17153A3732017-06-0202 June 2017 Response to NRC Staff Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Next Generation Fuel ML17144A3762017-05-24024 May 2017 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis ML17002A0012017-01-0202 January 2017 Response to NRC Requests for Additional Information (Rais) Regarding Emergency License Amendment Request (LAR) to Extend Diesel Generator 3B Completion Time ML17066A1842017-01-0202 January 2017 Response to NRC Requests for Additional Information (Rais) Regarding Emergency License Amendment Request (LAR) to Extend Diesel Generator 3B Completion Time ML16358A7152016-12-23023 December 2016 Response to Request for Additional Information Regarding Emergency License Amendment Request for a One-Time Extension of the Diesel Generator Completion Time ML16340A9882016-12-0101 December 2016 Addendum to Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML17167A2152016-11-23023 November 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis - Revised ... ML16321A0022016-11-0909 November 2016 Response to RAI, Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis - Revised Technical Specifications and Bases and WCAP-18030, Revision 1 ML16300A1562016-10-26026 October 2016 Response to NRC Electrical Engineering Branch Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay ... ML16286A2422016-10-0606 October 2016 Westinghouse Electric Company, WCAP-18030-NP Review, Suggested Response to Request for Additional Information ML16286A2402016-10-0606 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis ML16257A5442016-09-0909 September 2016 Response to NRC Instrumentation and Controls Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications ML16203A3812016-07-21021 July 2016 Response to NRC Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications ML16182A5192016-06-30030 June 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Critical Safety Analysis ML16147A0922016-05-20020 May 2016 Response to Request for Additional Information Regarding Relief Request 54, Alternative to Flaw Removal ML16133A6212016-05-12012 May 2016 ISFSI - Response to Request for Additional Information Regarding Proposed Changes to Emergency Action Levels ML16102A4632016-04-11011 April 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505 ML16029A5062016-01-29029 January 2016 Response to Request for Additional Information Regarding the Request to Change the Quality Assurance Program Description ML15273A4702015-09-30030 September 2015 IR 05000528/2015004, 05000529/2015004, and 05000530/2015004; 11/16/2015 - 11/20/2015; Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Notification of NRC Triennial Heat Sink Performance Inspection ML15258A8482015-09-15015 September 2015 Response to Request for Additional Information Regarding Exigent License Amendment Request to Amend Technical Specification Surveillance Requirement 3.1.5.3 ML15223A2062015-08-0606 August 2015 Response to Request for Additional Information Associated with Seismic Hazard and Screening Report ML16133A3262015-05-0101 May 2015 Response to NRC Request for Flood Hazard Reevaluation Model Files ML18192A3891975-12-31031 December 1975 Public Service Company of New Mexico 1974 Annual Report, as Response to Request for Additional Financial Information ML18192B2781975-10-21021 October 1975 Response to NRC Liquefaction Questions. Review of Liquefaction Analysis in Parallel with the Site Dewatering Program 2024-01-12
[Table view] |
Text
Subject:
FW: 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 From: Howell, Linda <Linda.Howell@nrc.gov>
Sent: Tuesday, December 29, 2020 11:49 AM To: Maribel.Garcia@aps.com Cc: R4Enforcement <R4Enforcement.Resource@nrc.gov>; Kramer, John <John.Kramer@nrc.gov>; Peabody, Charley
<Charles.Peabody@nrc.gov>; Bruce.Rash@aps.com; Brian.Hansen@aps.com; Michael.Dilorenzo@aps.com; Thomas.N.Weber@aps.com; Muessle, Mary <Mary.Muessle@nrc.gov>
Subject:
RE: 10208208 PVNGS Communication Required by Confirmatory Order EA20054 NRC Region IV staff reviewed the subject communication and concluded that it meets the intent of Confirmatory Order EA-20-054,Section III, Communications, Item A. The NRC has no comments on the communication.
Thank you, Linda Howell Deputy Director, Division of Nuclear Materials Safety NRC Region IV From: Maribel.Garcia@aps.com <Maribel.Garcia@aps.com>
Sent: Wednesday, December 02, 2020 4:24 PM To: Muessle, Mary <Mary.Muessle@nrc.gov>
Cc: R4Enforcement <R4Enforcement.Resource@nrc.gov>; Warnick, Greg <Greg.Warnick@nrc.gov>; Kramer, John
<John.Kramer@nrc.gov>; Peabody, Charley <Charles.Peabody@nrc.gov>; Bruce.Rash@aps.com; Brian.Hansen@aps.com; Michael.Dilorenzo@aps.com; Thomas.N.Weber@aps.com
Subject:
[External_Sender] 10208208 PVNGS Communication Required by Confirmatory Order EA20054 Good Afternoon, Attached is company correspondence 10208208 PVNGS Communication Required by Confirmatory Order EA20054 for your records.
Thank you, Maribel Maribel Garcia Support Services Nuclear Regulatory Affairs: Licensing, Compliance, Environmental 5801 South Wintersburg Road, M.S. 7636/7626 Tonopah, AZ 85354-7529 Office: (623) 393-5174 1
ML21005A271
Palo Verde Nuclear Generating Station 5871 S. Wintersburg Road Tonopah, AZ 85354 623-393-5764 102-08208 TNW December 2, 2020 Mary Muessle Director, Division of Nuclear Materials Safety (email mary.muessle@nrc.gov )
U.S. Nuclear Regulatory Commission, Region IV 1600 E. Lamar Blvd.
Arlington, TX 76011-4511
SUBJECT:
Palo Verde Nuclear Generating Station Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Communication Required by Confirmatory Order EA-20-054 This correspondence is written to provide the NRC an advanced copy of the communication that was written to satisfy Condition A of Confirmatory Order EA-20-054. We anticipate comments from the NRC within one month from the date of this letter as identified in the Confirmatory Order. If you have any questions or comments on this letter, please do not hesitate to contact me at 602-615-2131.
Sincerely, Digitally signed by Weber, Thomas Weber, Thomas N(Z00499)
DN: cn=Weber, Thomas N(Z00499)
Reason: I am approving this N(Z00499) document Date: 2020.12.02 14:50:47 -07'00' Thomas N. Weber Director, Nuclear Regulatory Affairs
Enclosure:
Draft Communication Required by Condition A of the Palo Verde Confirmatory Order EA-20-054 cc: NRC Region IV email to R4Enforcement@nrc.gov G. Warnick email to greg.warnick@nrc.gov J. Kramer email to john.kramer@nrc.gov C. Peabody email to charles.peabody@nrc.gov B. Rash email to bruce.rash@aps.com B. Hansen email to brian.hansen@aps.com M. Dilorenzo email to michael.dilorenzo@aps.com
ENCLOSURE Draft Communication Required by Condition A of the Palo Verde Confirmatory Order EA-20-054
Maria L. Lacal Executive Vice President &
Chief Nuclear Officer Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7602 Tel 623.393.6491 102-XXXXX-MLL January XX, 2021 To Qualified 10 CFR 50.59 and 10 CFR 72.48 Personnel
Subject:
Palo Verde Nuclear Generating Station Communication Required by MAGNASTOR Confirmatory Order EA-20-054, Conditions A and B This communication is written to satisfy Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054 issued by the Nuclear Regulatory Commission (NRC) on November 17, 2020. The Confirmatory Order was the result of an agreement that was reached during an Alternative Dispute Resolution (ADR) mediation session between the NRC and Arizona Public Service Company (APS) conducted on September 16, 2020, to address two apparent violations regarding the initial implementation of the NAC MAGNASTOR Dry Cask Storage System at Palo Verde Nuclear Generating Station (PVNGS). The two apparent violations were documented in an NRC inspection report dated July 6, 2020.
In accordance with the requirements of Conditions A and B of the Confirmatory Order, APS agreed to develop a standalone communication that would be verified to be read by the PVNGS qualified 10 CFR 50.59 and 10 CFR 72.48 personnel. The contents of the communication are required to include the following:
- 1. A summary of the PVNGS Independent Spent Fuel Storage Installation (ISFSI) event that resulted in the Confirmatory Order;
- 2. The root and contributing causes;
- 3. The corrective actions from the root cause evaluation; and
- 4. The additional corrective actions from the Confirmatory Order.
APS also agreed to provide the communication to the NRC prior to sending it out to the qualified 10 CFR 50.59 and 10 CFR 72.48 personnel at Palo Verde and incorporate any comments received from the NRC, which has been accomplished.
The enclosure contains the communication that is required to be read by the qualified 10 CFR 50.59 and 10 CFR 72.48 personnel at PVNGS. After reading this communication, there is a computer based training that was developed by our APS Training Department as the method to document verifiable evidence of the completion of the reading assignment.
A member of the STARS Alliance LLC Callaway Diablo Canyon Palo Verde Wolf Creek
102-XXXX- MLL Page 2 The Confirmatory Order requires the communication to be read by all 10 CFR 50.59 and 10 CFR 72.48 qualified personnel within four months of the date of the issuance of the Confirmatory Order, or by March 17, 2021.
If there are any questions from the 10 CFR 50.59 or 10 CFR 72.48 qualified personnel, please do not hesitate to contact Michael D. DiLorenzo, Nuclear Regulatory Affairs Department Leader, at 623-393-3495.
Sincerely,
Enclosure:
Communication Required by Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054 cc:
B. J. Rash E. A. Pittman B. E. Cable D. R. Lott T. Horton D. L. Cotter M. E. McLaughlin N. Aaronscooke M. G. Green S. M. Kane E. Andrews C. J. Stephenson G. R. Cameron D. R. Bence D. C. Elkinton R. F. Carbonneau M. S. Cox A. J. Montgomery M. D. DiLorenzo J. E. Glass T. N. Weber H. A. Al-Nakib A. R. Meeden J. Kuzela M. E. Kura N. A. Thibodaux B. J. Hansen L. McIntyre J. Fearn E. A. Pittman J. Hernandez A member of the STARS Alliance LLC Callaway Diablo Canyon Palo Verde Wolf Creek
Enclosure Communication Required by Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054
Enclosure Communication Required by Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054
Background
In accordance with the requirements of Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054, Arizona Public Service Company (APS) agreed to develop a standalone communication that would be verified to be read by the Palo Verde Nuclear Generating Station (PVNGS) qualified 10 CFR 50.59 and 10 CFR 72.48 personnel. The contents of this enclosure are intended to meet that requirement and include the following:
- 1. A summary of the PVNGS Independent Spent Fuel Storage Installation (ISFSI) event that resulted in the Confirmatory Order;
- 2. The root and contributing causes;
- 3. The corrective actions from the root cause evaluation; and
- 4. The additional corrective actions from the Confirmatory Order After reading this enclosure, each qualified 10 CFR 50.59 and 10 CFR 72.48 member shall complete the computer based training developed to document the completion of reading this communication. The Confirmatory Order requires this to be done within four months of the issuance of the Confirmatory Order, or by March 17, 2021.
- 1. Summary of the ISFSI Event that Resulted in the Confirmatory Order:
APS elected to make a change to utilize the Nuclear Regulatory Commission (NRC) approved NAC MAGNASTOR spent fuel storage system at PVNGS. The NRC approval of the MAGNASTOR system is in the form of a Certificate of Compliance (CoC) which includes Technical Specifications for the loading and storage of used fuel. These are used with the respective NAC Final Safety Analysis Report (FSAR) which contain license requirements, design requirements and the design bases. In order for APS to utilize the MAGNASTOR spent fuel storage casks, APS is required to review and evaluate the provisions and conditions delineated in 10 CFR 72.212 for the MAGNASTOR System. One of the many conditions that APS had to evaluate that is described in the NAC FSAR is to analyze the occurrence of a cask tip-over event. A tip-over event occurs when a cask spontaneously moves from a position of balance, overturns and falls onto the surface of the ISFSI concrete pad. The design of the cask and the seismic values at PVNGS preclude a tip-over event from ever happening, but the analysis is required and ensures sufficient margin exists in the design. The tip-over analysis computes the maximum acceleration values at which the cask and its internals would strike the ISFSI pad during a tip-over event. These acceleration values are then used to assess the force of impact in order to confirm that the cask and the fuel basket, internal to the cask, are sufficiently robust to sustain the impact. The NAC FSAR specifically states that a finite element analysis using the nonlinear computer software program LS-DYNA will be used as the method of evaluation for the tip-over analysis.
APS worked with NAC to perform a tip-over analysis for the PVNGS plant configuration. One of the challenges was that the concrete pad characteristics that Page 1
Enclosure Communication Required by Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054 are included in the approved NAC generic MAGNASTOR design are NOT the same as the characteristics for the Palo Verde ISFSI concrete pad. The analysis that was done initially for Palo Verde used linear scaling (ratios) to account for changes in the concrete thickness, concrete density, concrete compressive strength, soil thickness, soil density and soil modulus of elasticity. Based upon the linear scaling results, APS and NAC concluded that the results for the generic NAC tip-over analysis were the same as the results would be for a PVNGS plant specific tip-over analysis. Therefore, no plant specific Palo Verde tip-over analysis was done.
However, during the NRC MAGNASTOR inspection, the NRC made the determination that the usage of a linear scaling method to satisfy the NAC FSAR requirements for a tip-over analysis resulted in errant conclusions that were non-conservative and that it was not the NAC FSAR-described method of evaluation.
As a result, as specified in 10 CFR 72.48 and as discussed in Nuclear Energy Institute (NEI) 96-07 Appendix B, Guidelines for 10 CFR 72.48 Implementation, the NRC determined that prior NRC approval was required prior to implementing the MAGNASTOR system. Specifically, APS changed from a method described in the NAC FSAR (LS-DYNA) to another method (linear scaling) that was not approved by the NRC for the intended use at Palo Verde. This resulted in a departure from the NAC FSARs described method of evaluation for establishing the design bases for a tip-over event.
The NRC issued two apparent violations for Palo Verde in the MAGNASTOR inspection report dated July 6, 2020. The first apparent violation referred to 10 CFR 72.48(c)(2)(viii) that requires that a general licensee request the certificate holder to obtain a CoC amendment pursuant to 10 CFR 72.244 prior to implementing a proposed change that would result in a departure from a method of evaluation described in the FSAR (as updated) used in establishing the design bases or in the safety analysis.
The second apparent violation referred to 10 CFR 72.146(a), Design Control, which requires, in part, that applicable regulatory requirements and the design bases are correctly translated into specifications, drawings, procedures and instructions.
In order to establish compliance, APS and NAC performed a plant specific LS-DYNA analysis for the tip-over analysis on the PVNGS concrete pad, prior to loading the first MAGNASTOR cask, which satisfied the NAC FSAR requirement for the tip-over analysis and eliminated the need for prior NRC approval.
Page 2
Enclosure Communication Required by Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054
- 2. Root and Contributing Causes:
The following causes were identified by the APS investigation team assigned to Level 1 Root Cause Evaluation Number 20-07210-007, Revision 2, MAGNASTOR Tip-Over Analysis Method Different from NAC FSAR.
Direct Cause:
The direct cause of the failure of the 10 CFR 72.48 screening to identify a change in the MAGNASTOR FSAR required methodology in the tip-over analysis was because APS personnel did not ensure that the applicable regulatory requirements and design basis criteria were correctly translated into the tip-over analysis.
Root Cause (RC-01)
The root cause of the failure of the 10 CFR 72.48 screening to identify a change in a MAGNASTOR FSAR required methodology in the tip-over analysis was less than adequate proficiency when answering the 10 CFR 72.48 method of evaluation questions.
Contributing Cause (CC-01)
A contributing cause of the failure of the 10 CFR 72.48 screening to identify a change in the MAGNASTOR FSAR required methodology in the tip-over analysis was due to inadequate understanding of what constituted a change to a prescribed method of evaluation.
Contributing Cause (CC-02)
A contributing cause of the failure of the 10 CFR 72.48 screening to identify a change in a MAGNASTOR FSAR required methodology in the tip-over analysis was the inadequate rigor during the owner acceptance of linearly scaled generic concrete cask CC5 tip-over analysis and site specific ISFSI pad tip-over analysis for the modification.
- 3. Corrective Actions from the Root Cause Evaluation The following level 3 corrective action items were required by the Level 1 Root Cause Evaluation No. 20-07210-007, Revision 2, MAGNASTOR Tip-Over Analysis Method Different from NAC FSAR.
- 1. Immediate Action IA-01: The Site specific tip-over analysis was completed using LS-DYNA.
- 2. Immediate Action IA-02: The 10 CFR 72.48 screening for the site specific tip-over analysis was revised.
- 3. Immediate Action IA-03: The PVGS 10 CFR 72.212 report for MAGNASTOR was revised to include the LS-DYNA site specific tip-over analysis.
- 4. Interim Action IA-01: Revise 93DP-0LC07, 10 CFR 50.59 and 72.48 Screenings and Evaluations, to add a step to section 4.2.13 that states:
Page 3
Enclosure Communication Required by Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054
- a. If a change involves a methodology, an input parameter, and/or an input to the methodology, and the answer to question 3 is NO, then contact the 50.59 program owner to assign a 50.59 Single Point of Contact to review the screening.
- b. Update the basis for this procedure to identify this step as a root cause corrective action
- c. Update any FSAR reference for dry cask to MAGNASTOR FSAR or UMS FSAR
- 5. Interim Action IA-02: Document that the Lead evaluator attended the 10 CFR 50.59 SPOC meeting and briefed 10 CFR 50.59 Single Point of Contacts (SPOCs) on the root cause event at program owner request. SPOCs were asked to provide mentoring on method of evaluation and how to tell the difference between a question 1 and question 3 response whenever possible on future screenings and evaluations.
- 6. Corrective Action CA-01: Revise NGS80, Initial 10 CFR 50.59 Screener Training, to add:
- a. This event as OE
- b. What a good Yes and No response looks like for a method of evaluation question
- c. Updating the method of evaluation and adverse change examples to contain more detail on how the questions were answered, while shifting the focus away from the consequence of the wrong answer. State the Why we got the consequence in more details.
- d. Give examples of what a change in methodology looks like and how to approach recognizing a change to methodology
- e. Emphasize recognizing your knowledge limitations and working with your leader to get the right expertise involved.
- 7. Corrective Action CA-02: Revise NGS03, 10 CFR 50.59/72.48 Screener Continuing Training, to add:
- a. This event as OE
- b. What a good Yes and No response looks like for a method of evaluation question
- c. Updating the method of evaluation and adverse change examples to contain more detail on how the questions were answered, while shifting the focus away from the consequence of the wrong answer.
State the Why we got the consequence in more details
- d. Give examples of what a change in methodology looks like and how to approach recognizing a change to methodology.
- e. Emphasize recognizing your knowledge limitations and working with your leader to get the right expertise involved.
- 8. Corrective Action CA-03: Revise NGS59, 10 CFR 72.48 Initial and Re-Qualification Training, to add:
- a. This event as OE
- b. What a good Yes and No response looks like for a method of evaluation question Page 4
Enclosure Communication Required by Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054
- c. Updating the method of evaluation and adverse change examples to contain more detail on how the questions were answered, while shifting the focus away from the consequence of the wrong answer.
State the Why we got the consequence in more details.
- d. Give examples of what a change in methodology looks like and how to approach recognizing a change to methodology.
- e. Emphasize recognizing your knowledge limitations and working with your leader to get the right expertise involved.
- 9. Corrective Action CA-04: Update Job Qualification Card (JQC) ESP27-XX-001 for the 50.59 Screener to add branching steps for questions 1-3, what to do if the answer is yes, what would a yes look like for each of the questions.
- 10. Corrective Action CA-05: Update JQC ESP40-XX-001 for the 72.48 Screener to add branching steps for questions 1-3, what to do if the answer is yes, what would a yes look like for each of the questions.
- 11. Corrective Action CA-06: Develop a briefing for all qualified 10 CFR 50.59/72.48 screeners and evaluators to discuss the root cause evaluation and training changes.
- 12. Corrective Action CA-07: Initiate and record attendance of the briefing for all qualified 10 CFR 50.59/72.48 screeners and evaluators to discuss the root cause evaluation and training changes
- 13. Corrective Action CA-08: Develop and present an Engineering Leader led workshop for all Engineers to review how to perform owner acceptance reviews, complete a dynamic learning activity on what an excellent owner acceptance review looks like, and restate all management expectations for owner acceptance reviews.
- 14. Corrective Action CA-09: Revise EDG-01 to include owner acceptance review requirements in Appendix E- Vendor Oversight and which procedures are used to process the documents. Include:
- a. How to perform Owner Acceptance Review inclusive of incorporating feedback from the workshop session. The proposed appendix is an expansion of what is already included in the industry Standard Design Process (SDP) procedure IP-ENG-001
- b. How/where to document the Owner Acceptance Review comments and resolutions
- 15. Corrective Action CA-10: Review and revise the Design Modification Package DMWO 4623203 to identify the tip-over analysis design requirements and the 72.48 that was completed
- 4. The Additional Corrective Actions from the Confirmatory Order Confirmatory Order EA-20-054 was issued by the NRC on Tuesday, November 17, 2020. The Confirmatory Order modified the Operating Licenses for Palo Verde (NPF-41, NPF-51 and NPF-74) and was effective upon issuance. The Confirmatory Order identified the actions agreed to during the Alternative Dispute Resolution (ADR) mediation session held on September 16, 2020, and included actions in the areas of Communications, Training, Reviews, Training Assessments, Effectiveness Page 5
Enclosure Communication Required by Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054 Reviews and Administrative Items. The final wording of the Conditions in the Confirmatory Order was revised slightly from the wording that was initially agreed upon at the ADR mediation session. These changes were agreed upon by the NRC and APS during the final review. The specific conditions from the Confirmatory Order are as follows:
Condition A: Within 2 months of the issuance date of the Confirmatory Order, APS will develop a communication that will include: a summary of the ISFSI event that resulted in the Confirmatory Order, the root and contributing causes, the corrective actions from the root cause evaluation, and the additional corrective actions from the Confirmatory Order, and APS will submit the proposed communication to the NRC for its review. The NRC will provide any comments to APS on the communication within 1 month from the date of the submittal. APS will consider the NRCs comments and incorporate those comments that APS agrees are appropriate.
Condition B: Within 4 months of the issuance date of the Confirmatory Order, APS will issue the Condition A communication as a stand-alone communication from the Chief Nuclear Officer to all qualified personnel in the development, review, and approval of 10 CFR 50.59/72.48 Changes, test, and experiments documents. APS will retain a copy of the communication presented and verifiable evidence of the personnel receiving the communication. APS will document the reason for any person not obtaining the communication and the additional efforts used to provide the communication.
Condition C: Within 6 months of the issuance date of the Confirmatory Order, APS will develop a presentation and will submit the proposed presentation to the NRC for its review. The NRC will provide any comments to APS on the presentation within 1 month from the date of the submittal. APS will consider the NRCs comments and incorporate those comments that APS agrees are appropriate. The presentation will:
- 1. Include a summary of the ISFSI event that resulted in the Confirmatory Order, the root and contributing causes, the corrective actions from the root cause evaluation, additional corrective actions from the Confirmatory Order, and a discussion on what a Methodology is and what are input parameters.
- 2. Emphasize a General Licensees requirement to adequately review a vendors 10 CFR 72.48 analysis through its 10 CFR 50.59/72.48 program for acceptance prior to being implemented at the General Licensees site.
Condition D: Within 15 months of the issuance date of the Confirmatory Order, APS will deliver the presentation developed in Condition C to: (1) the INPO Engineering VP Forum, (2) the NEI Used Fuel Conference, and (3) the NEI High Level Waste Working Group (subject to acceptance Page 6
Enclosure Communication Required by Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054 of the forum or conference organizing committee) as allowed by current COVID-19 considerations.
Condition E: Within 6 months of the issuance date of the Confirmatory Order, APS will develop a refresher training on 10 CFR 50.59/72.48 requirements and processes and will submit the proposed training to the NRC for its review. The NRC will provide any comments to APS on the proposed training within 1 month from the date of the submittal. APS will consider the NRCs comments and incorporate those comments that APS agrees are appropriate.
Condition F: Within 9 months of the issuance date of the Confirmatory Order, APS will provide the training developed in Condition E above to all qualified personnel in the development, review, and approval of 10 CFR 50.59/72.48 changes. APS will continue to provide the refresher training at intervals not to exceed 15 months until December 31, 2024. APS will retain a copy of the training and verifiable evidence of the personnel receiving the training. APS will document the reason for any person not obtaining the training and the additional efforts used to provide the training.
Condition G: Within 4 months of the issuance date of the Confirmatory Order and until December 31, 2024, APS will create a challenge review board consisting of three 10 CFR 50.59 program single point of contact (SPOC) members who will review 10 CFR 72.48 screenings and evaluations prior to the implementation of a design change. By March 31 of the calendar year following the Condition G reviews, APS will send a copy of the previous calendar year reviews and a copy of any additional corrective actions developed from the reviews to the NRC.
Condition H: Within 4 months of the issuance date of the Confirmatory Order and until December 31, 2024, APS will utilize a design review board to review NACs design changes with experienced, qualified 10 CFR 50.59/72.48 individuals on both NAC MAGNASTOR and NAC UMS systems applicable to APS prior to all loading campaigns. By March 31 of the calendar year following the Condition H reviews, APS will send a copy of the previous calendar year reviews and a copy of any additional corrective actions developed from the reviews to the NRC.
Condition I: Within 12 months of the issuance date of the Confirmatory Order, APS will perform a training needs analysis to determine what training should be provided to engineering personnel relative to software quality assurance. The training needs analysis will consider procedures and processes related to the APS software quality assurance program and aspects of NUREG-2215, Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities, Appendix 4A, Computational Modeling Software Technical Review Guidance, NRCs Agencywide Documents Access and Management System (ADAMS) Accession No. ML20121A190. APS will send the results of the training needs analysis and proposed training to the Page 7
Enclosure Communication Required by Conditions A and B of the MAGNASTOR Confirmatory Order EA-20-054 NRC for its review. The NRC will provide any comments to APS on the training within 1 month from the date of the submittal. APS will consider the NRCs comments and incorporate those comments that APS agrees are appropriate.
Condition J: Within 24 months of the issuance date of the Confirmatory Order, APS will provide the training resulting from the training needs analysis discussed in Condition I to qualified personnel in the development, review, and approval of 10 CFR 50.59/72.48 changes.
Condition K: By December 31 of calendar years 2021 and 2023, APS will perform an effectiveness review of the implemented root cause evaluation corrective actions, and actions associated with the Confirmatory Order. The effectiveness review will include lessons learned from each action implementation or completion, new operating experience since issuance of the Confirmatory Order, and training feedback associated with 10 CFR 50.59/72.48 which occurred during the effectiveness review period. APS will modify its corrective actions, as needed and consistent with the Confirmatory Order, based on the results of the effectiveness review. By March 31 of each year following the effectiveness review, APS will send a copy of the effectiveness review and a copy of any additional corrective actions developed from the effectiveness review to the NRC.
Condition L: Until December 31, 2026, APS will retain a copy of all documentation created during the implementation of the Confirmatory Order Conditions.
Condition M: Documents that are required to be sent to the NRC as a result of the Confirmatory Order Conditions will be sent to the Director, Division of Nuclear Materials Safety, U.S. Nuclear Regulatory Commission, Region IV, 1600 E. Lamar Blvd., Arlington, TX 76011-4511 and emailed to R4Enforcement@nrc.gov.
Condition N: In consideration of the Conditions delineated above, the NRC agrees that the issuance of this Confirmatory Order will not be considered as escalated enforcement. However, for any future escalated enforcement actions involving 10 CFR 72.48 or 10 CFR 72.146, the NRC will consider this Confirmatory Order for the civil penalty assessment purposes as discussed in the NRC Enforcement Policy.
Condition O: In consideration of the Conditions delineated above, the NRC agrees not to issue a notice of violation and not impose a civil penalty for the apparent violations discussed in the NRC inspection report to APS dated July 6, 2020.
Page 8