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Category:Letter
MONTHYEARML24262A0972024-09-23023 September 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000529/2024011) ML24241A2782024-08-28028 August 2024 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information ML24240A2682024-08-27027 August 2024 Transmittal of Technical Specification Bases Revision 79 IR 05000528/20240052024-08-22022 August 2024 Updated Inspection Plan for Palo Verde Nuclear Generating Station - Units 1, 2, and 3 (Report 05000528/2024005, 05000529/2024005, 05000530/2024005) ML24208A0612024-08-20020 August 2024 Issuance of Amendment Nos. 224, 224, and 224 Regarding Revision to Technical Specifications 3.5.1, 3.5.2 and 3.6.5 IR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24177A3222024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a IR 05000528/20243012024-06-17017 June 2024 NRC Examination Report 05000528/2024301; 05000529/2024301; 05000530/2024301 ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A ML24157A3392024-06-0505 June 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium ML24144A2772024-05-23023 May 2024 Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24129A1482024-05-0707 May 2024 and Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 ML24109A0712024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 ML24032A1542024-04-0303 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24089A1892024-03-28028 March 2024 Present Levels of Financial Protection ML24068A2522024-03-0808 March 2024 License Amendment Request to Revise Technical Specifications 3.5.1 and 3.5.2 Using Risk-Informed Process for Evaluations ML24066A0472024-03-0606 March 2024 Response to Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown and TS IR 05000528/20240122024-03-0404 March 2024 Age-Related Degradation Inspection Report 05000528/2024012, 05000529/2024012 and 05000530/2024012 IR 05000528/20230062024-02-28028 February 2024 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Report 05000528/2023006 and 05000529/2023006 and 05000530/2023006 ML24053A3972024-02-22022 February 2024 License Renewal - Alloy 600 Management Program Plan ML24047A3632024-02-16016 February 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX177, AMZDFX178, AMZDFX179 Vertical Concrete Cask Identification No. AMZDNE179, AMZDNE178 IR 05000528/20230042024-02-12012 February 2024 Integrated Inspection Report Report 05000528/2023004 and 05000529/2023004 and 05000530/2023004 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owner’S 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 2024-09-23
[Table view] Category:Report
MONTHYEARML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owner’S 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 2024-04-12
[Table view] Category:Miscellaneous
MONTHYEARML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 1R24 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 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 ML17181A5152017-06-29029 June 2017 Flooding Focused Evaluation Summary 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 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 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 ML15012A4462015-01-0606 January 2015 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U1R18 ML14184B3822014-06-27027 June 2014 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R18 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 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 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 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 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 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 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 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 ML14034A1472014-01-24024 January 2014 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U3R17 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 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) ML12200A0312012-06-26026 June 2012 Third 10-Year Interval, First Period: Owner'S Activity Report Number U3R16 ML11195A0172011-07-0606 July 2011 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U2R16 ML11189A0952011-06-29029 June 2011 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of 10 CFR 50.59, 10 CFR 72.48, and Commitment Change Reports (January 2010 - December 2010) ML1103107342011-01-19019 January 2011 Third 10-Year Interval, First Period, Second Outage: Owner'S Activity Report Number U3R15 ML1024400382010-08-20020 August 2010 Third 10-Year Interval, First Period, Second Outage: Owner'S Activity Report Number 1R15 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1013103942010-04-30030 April 2010 Submittal of Steam Generator Tube Inspection Report ML1006805162010-03-0202 March 2010 Third 10-Year Interval, First Period, Second Outage: Owner'S Activity Report Number 2R15 ML1015302192009-12-16016 December 2009 APS 2004 Pump Installation Completion Report for PVNGS Firing Range Well. Filed with Adwr on Aug. 3, 2004 (PV-406) PVNGS ML0933104422009-11-18018 November 2009 Steam Generator Tube Inspection Report ML0932401312009-11-12012 November 2009 Special Report 2-SR-2009-001-00 ML0923801522009-08-18018 August 2009 Third 10-Year Interval, First Outage of the First Period, Owner'S Activity Report - 3R14 ML0920202692009-07-16016 July 2009 Revised Steam Generator Tube Inspection Report ML1015907552009-06-12012 June 2009 Final Corrective Action Plan Report for 80-Acre Wsr, Submitted to Adeq June 12, 2009 ML0910304182009-03-31031 March 2009 2008 Decommissioning Funding Status Report ML0905801982009-02-17017 February 2009 Third 10-Year Interval, First Outage of the First Period, Owner'S Activity Report - U1R14 ML0825504022008-09-0303 September 2008 Third 10-Year Interval - Fourteenth Refueling Outage - Owner'S Activity Report ML1015503122008-05-15015 May 2008 APS 2008 PVNGS 2007 Annual Monitoring and Compliance Report App No. P-100388 ML0810102292008-04-10010 April 2008 Lesson Learned Inputs for the Reactor Oversight Program Safety Culture Evaluation for Use at 4/17/08 Public Meeting ML0807400502008-03-0505 March 2008 Response to Request for Additional Information Related to 2006 Steam Generator Tube Inspections ML0803702332008-01-24024 January 2008 Radioactive Waste Shipment Delay Special Report 1-SR-2008-001-00 ML0800901932008-01-0202 January 2008 Steam Generator Tube Inspection Report 2024-01-19
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David Mauldin Vice President Mail Station 7605 Palo Verde Nuclear Nuclear Engineering Tel: 623-393-5553 PO Box 52034 Generating Station and Support Fax: 623-393-6077 Phoenix, Arizona 85072-2034 102-05376-CDM/TNW/RJR November 16, 2005 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Reference:
APS letter 102-05119-CDM/SAB/TNW/GAM, "Information Regarding PVNGS Offsite Power Grid Reliability," dated June 17, 2004.
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3, Docket No.s STN 50-5281529/530 Results of the Investigation of the June 14, 2004 230 kV Transmission Line Fault In the referenced letter, Arizona Public Service (APS) agreed to forward the findings of the study being conducted by the Western Electricity Coordinating Council (WECC) of the June 14, 2004 230 kV transmission line fault when they became available. The investigation has been finalized and APS has completed its review.
The findings of the study conducted by the WECC are attached to this letter. This letter does not make any commitments to the NRC. Please contact Thomas N. Weber at (623) 393-5764 if you have any questions or require additional information.
Sincerely, CDM/TNW/RJR/ca
Attachment:
Results of 6-14-04 Westwing/Palo Verde Disturbance Validation Study cc: B. S. Mallett M. B. Fields G. G. Wamick A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway El Comanche Peak C Diablo Canyon U Palo Verde El South Texas Project El Wolf Creek
Attachment Western Electricity Coordinating Council Technical Studies Subcommittee Results of 6-14-04 Westwing/Palo Verde Disturbance Validation Study
WesternElectricityCoordinatingCouncil ABRAHAM ELLIS, P.E., PH.D.
CHAIR Modeling and Validation Work Group Public Service Company of New Mexico Alvarado Square, MS 0604 Albuquerque, NM 87158 TEL: (505) 241-4595 FAX: (505) 2414363 E-mail: aellis~pnmcom October 31, 2005 Dana Cabbell, Chair Technical Studies Subcommittee
Subject:
Results of 6-14-04 Westwing/Palo Verde Disturbance Validation Study The attached report summarizes work performed by the Modeling and Validation Work Group (MVWG) to simulate the June 14 2004 West Wing/Palo Verde disturbance. This is part of an on-going effort calibrate WECC's system planning models.
As in previous instances, simulation of this event revealed shortcomings of the existing models and gave us an opportunity to correct them. Specifically, the existing models for the Palo Verde units underestimate the effects of field saturation at the high excitation levels that the Palo Verde units experienced during the event. After the appropriate model adjustments were made, very close agreement between simulation and actual recordings was obtained.
Following the model validation, additional "what if" scenarios were conducted. The conclusions of these additional simulation scenarios are given below:
- 1. If the Palo Verde - Hassayampa 500 kV transmission lines had not tripped during the event, the simulations show that the Palo Verde generators still would have tripped. However, after the fault clears and assuming that all other Palo Verde 500 kV trip as they did, the simulations show that the Palo Verde 500 kV voltage would have recovered to an acceptable level, provided that the 500 kV lines from Jojoba and/or North Gila to Hassayampa had remained in service.
- 2. If the fault had cleared before the Palo Verde OEL took action, the simulations show that the Palo Verde units would not have tripped, and the system would have recovered to a stable condition.
If you have any further questions, please do not hesitate to contact me.
Sincerely, cc.
Robert Jenkins, Chair, Planning Coordination Committee
Disturbance Simulation Report for the June 14, 2004 Westwing Fault and Palo Verde Trip Event Modeling and Validation Work Group October 31, 2005 Introduction The June 14,2004 WECC disturbance [1] resulted in tripping of all 7 Palo Verde 500 kV lines and all 3 Palo Verde nuclear units. The event caused the system frequency to dip to 59.55 Hz, and produced significant power oscillations in Northwest as well as very low voltages in Palo Verde area. This disturbance was very complex in the sense that the fault type changed many times during the event. Single-line-to-ground, 2-line-to ground, and 3-phase faults occurred before the fault was finally cleared, 40 seconds after it started.
WECC's Modeling and Validation Work Group (MVWG) performed a detailed simulation of this event as part of an on-going effort to calibrate WECC's planning models. Several entities provided data required to conduct the simulation. WECC staff obtained generation, load, and line flow information from member utilities, and assembled the power flow and stability case data. WECC's Disturbance Monitoring Work Group (DMWG) provided high-speed recordings of the event at various key locations. Arizona Public Service Company assembled a detailed switching sequence, and provided the fault impedance data necessary to simulate the asymmetrical faults involved in the event.
Summary of the Model Validation Effort The initial simulation effort using the most up-to-date models was reasonably successful in reproducing the system frequency dip (Figure 1). However, the initial simulation failed to reproduce the voltage profile in the Palo Verde area (Figure 2). The actual voltage profile at the Palo Verde 500 kV bus was much worse than the simulation showed. The initial simulation also failed to reproduce the voltage collapse that occurred at the Palo Verde 500 kV bus. It was observed that the simulated Palo Verde generator reactive power response was too optimistic compared to actual measurements. The simulation showed that reactive power output of the Palo Verde units peaked at approximately 1500 MVAR (gross), whereas the actual recordings showed a maximum output of only 1200 MVAR (gross).
After a thorough review, it was determined that the existing generator model for the Palo Verde units underestimated the effects of saturation at the extreme conditions experienced during the disturbance.
During the June 146 2004 event, the Palo Verde field voltage reached its maximum limit, while field current was at a very high level (1.4 pu of AFFL). It is not possible to test saturation characteristics of the Palo Verde units at this operating point. During off-line model verification tests, the Palo Verde generator model had been verified with generator terminal voltage up to 1.08 pu. At this terminal voltage, the field voltage was well below its ceiling and the field current was well below 1.0 pu. To match the measured reactive power output of the Palo Verde units during the June 14t 2004 event, the saturation constant "sI .2" had to be increased significantly. MVWG is currently investigating whether a similar model adjustment applies to other WECC generator models.
It is worth noting that, during this event, the Palo Verde over-excitation limiter (OEL) operated. The OEL action, which took place 20 seconds after the disturbance started, had a decisive effect on the outcome of the event. Fortunately, OEL performance recordings were available, allowing the OEL model to be adjusted to match the actual behavior.
With accurate OEL modeling and after adjusting the saturation constant, close agreement was obtained between recorded and simulated reactive power output of Palo Verde generators. Palo Verde 500 kV bus
voltage also matched the recorded data reasonably well as shown in Figures 3a and 3b. Additional comparison plots are shown in Figure 4a to 4c.
Additional simulations Approximately 12 seconds into the fault, the three 500 kV lines connecting Palo Verde to Hassayampa tripped on a negative sequence condition. As part of an investigation of this event, the Nuclear Regulatory Commission (NRC) expressed interest in studying whether the Palo Verde units would have tripped under certain variations of the actual event. Two "what if' scenarios were simulated to address questions posed by the NRC. These scenarios and the simulation results are briefly described below.
Scenario 1 - Assume that the Palo Verde to Hassayampa transmission lines do not trip.
Assuming that the fault is cleared in 40 seconds, as it happened during this event, the Palo Verde units OEL would have operated and a voltage collapse at Palo Verde 500 kV bus would have occurred.
Therefore, the Palo Verde units still would have tripped under this scenario.
The simulation also shows that if the Hassayampa lines had not tripped, then the Palo Verde 500 kV switchyard would have recovered to an acceptable voltage level following tripping of the lines from Palo Verde to Devers, Rudd and Westwing, provided that the 500 kV transmission lines from Hassayampa to Jojoba and/or North Gila had remained unaffected by the fault (Figure 5a and 5b).
Tripping of the Palo Verde lines separates the fault from Palo Verde 500 kV bus and the Palo Verde 500 k V bus voltage recovers. This is seen in Figures 5a. Tripping of the Palo Verde units causes the frequency to dip to 59.3 Hz but the frequency also recovers. This recovery of the Palo Verde 500 kV voltage is due to it being connected to Hassayampa 500 kV bus and the assumption that the Hassayampa 500 kV bus sources remained in service.
Scenario 2 - Assume that the fault clears before the OEL operates and no Palo Verde 500 kV lines trip.
Since the fault is assumed to clear before OEL action takes place, the Palo Verde 500 kV voltage would not have collapsed. The studies show that no lines or units at Palo Verde would have tripped, and the system would have remained in a stable condition (Figure 6).
Reference
[I] WECC Detailed System Disturbance Report by WECC Disturbance Report Task Force, Dec 3,2004 (http://www.wecc.biz/documents/library/disturbance/6-14/14JunO4_Westwingfinal reviewdraft.pdf).
la-i Fr I-Maiin n 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 Tim. [s]
Figure 1: Comparison of simulated and actual frequency at Malin 500 kV before model adjustments
=Palo.Verde V I-Act I
Time two.]
Figure 2: Comparison of simulated and actual Palo Verde 500 kV bus voltage before model adjustments
600.00 7.300.00 -Palo Verde V 200.00-100.00 0.00--
0 5 10 15 20 25 30 Time [pecl Figure 3a: Comparison of simulated and actual Palo Verde 500 kV bus voltage after model adjustments 1000 1000 800 800 600 600 400 / 400 200 M 200 0 L0
-200 r 5 10 15 20 25 -200 I0 15 20 25
-400 400 Fig 3b. Comparison of simulated (left) and actual (right) reactive power output for Palo Verde Unit #2, after model adjustments
I I 7 : \of
- ~ - lMalin IFle U.59.7 - __ __ __
59.6 _ _ __ _ _ _ _ _
59.5 0 5 10 Is 20 25 30 35 40 45 50 55 60 65 70 75 Tnm. [.ec3 Figure 4a: Comparison of simulated and actual frequency at Malin 500 kV after model adjustments 550 0 5 10 15 20 25 30 35 40 45 s0 55 60 65 75 Time [socl Figure 4b: Comparison of simulated and actual Malin 500 kV voltage after model adjustments
0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 Tnme [sec]
Figure 4c: Comparison of simulated and actual COI real power transfer after the model adjustments
- 1. 2BL<__ 1
- 0. 2 0.0 Time ( sec ) .0 0.25 vbus 14921 PALOVRDI 94000 1 1 1.25 550400 ibgs 16921 PALOVRDE 34000 1 1 100600 0.0 efd 14931 PALOVRD1 24.0 1 1 5.0 flnl t 14 p TdPAT"vwml n4 n 1 1 7 n Figure 5a. Palo Verde voltage (blue) and system frequency (red) for Scenario 1. Palo Verde units trip at 20 seconds following OEL action
Time ( sec )
0.2 Vt 14931 PALOVRD1 24.0 1 1 1.2
-100.0 ang 14931 PALOVRD1 24.0 1 1 100.0 0.0 efd 14931 PALOVRD1 24.0 1 1 5.0 0.0 it 14931 PALOVRD1 24.0 1 1 2.0
-0,0 Pg 14931 PALOVRD1 24.0 1 1 3118.0
-779.5 qg 14931 PALOVRD1 24.0 1 1 2338.5 Figure 5b. Palo Verde Unit #1 quantities for Scenario 1, showing unit instability and trip at 20 seconds following OEL action. Results from Units #2 and #3 are similar.
700 600 500 1e _
400 300 200 100 0
0 5 10 15 20 25 30 35 40 Figure 6. Palo Verde 500 kV bus voltage for Scenario 2, showing [that the system would have remained in a stable condition if the fault would have been cleared in 19 seconds.
The Palo Verde units did not trip during this simulation.