ML19066A085
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| ML19066A085 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde, Arkansas Nuclear, Waterford, San Onofre, 05200046  |
| Issue date: | 04/30/1986 |
| From: | Combustion Engineering |
| To: | Office of New Reactors |
| References | |
| CEN-310-NP-A, NUDOCS 8605270198 | |
| Download: ML19066A085 (39) | |
Category:Report
MONTHYEARML24295A1232024-10-21021 October 2024
[Table view]Enclosure 3: Relief Request ANO2-RR-24-001, Revision 0 (Non-Proprietary) 1CAN072401, Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply2024-07-0202 July 2024 Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply W3F1-2024-0024, Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days2024-06-17017 June 2024 Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0018, Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 252024-05-0101 May 2024 Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 25 ML24103A2482024-04-12012 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 W3F1-2023-0056, Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN062302, Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version2023-06-20020 June 2023 Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version ML23088A2172022-12-31031 December 2022 Relief Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Technical Report, ANP-4023NP, Revision 0, December 2022 ML22308A1662022-11-0404 November 2022 23rd Refueling Outage Steam Generator Tube Inspection Report W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days ML22119A0922022-05-0303 May 2022 Ril 2022-07, Assessment of San Onofre Concrete Susceptibility Against Irradiation Damage ML22091A3072022-04-0101 April 2022 Independent Spent Fuel Storage Installation (Isfsi), Evacuation Time Estimate Study 2CAN022202, Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-02-24024 February 2022 Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods ML21280A1032021-12-0606 December 2021 Updated Biological Assessment of Impacts to Federally Listed Species Under NMFS Jurisdiction for SONGS Decommissioning W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 0CAN102102, Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis2021-10-0606 October 2021 Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt ML21272A3032021-09-30030 September 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report ML21242A0592021-09-30030 September 2021 Biological Assessment of Impacts to Federally Listed Species Under NMFS Jurisdiction for SONGS Decommissioning ML21270A2172021-09-27027 September 2021 LTR-21-0264 David Lochbaum, Union of Concerned Scientists, Letter Study Regarding Spent Fuel in Dry Storage at San Onofre Nuclear Generating Station ML21237A0512021-08-25025 August 2021 Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment 2CAN062103, Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval2021-06-29029 June 2021 Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval ML21165A0822021-06-0303 June 2021 the Independent Spent Fuel Storage Installation, Facility Change Report, Summary Report of Commitment Changes 0CAN052102, Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes2021-05-10010 May 2021 Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes W3F1-2021-0004, License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual2021-04-0505 April 2021 License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual ML21272A3382021-04-0101 April 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report ML21090A0332021-03-31031 March 2021 Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1442021-03-22022 March 2021 Strategy 6 ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1422021-03-22022 March 2021 Strategy 4 ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1392021-03-22022 March 2021 Strategy 1 ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1372021-03-22022 March 2021 NEIMA Reporting 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 W3F1-2021-0015, Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-01-29029 January 2021 Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System ML21014A2672021-01-14014 January 2021 Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 W3F1-2020-0038, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2020-07-23023 July 2020 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System ML20178A3632020-06-22022 June 2020 Defueled Safety Analysis Report ML20118D0742020-04-27027 April 2020 SONGS Spotlight Section FAQ Updated 3-31-2020 2024-07-02 Category:Technical MONTHYEARML24295A1232024-10-21021 October 2024
[Table view]Enclosure 3: Relief Request ANO2-RR-24-001, Revision 0 (Non-Proprietary) 1CAN072401, Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply2024-07-0202 July 2024 Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 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 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN062302, Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version2023-06-20020 June 2023 Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version ML23088A2172022-12-31031 December 2022 Relief Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Technical Report, ANP-4023NP, Revision 0, December 2022 ML22308A1662022-11-0404 November 2022 23rd Refueling Outage Steam Generator Tube Inspection Report ML22119A0922022-05-0303 May 2022 Ril 2022-07, Assessment of San Onofre Concrete Susceptibility Against Irradiation Damage ML22091A3072022-04-0101 April 2022 Independent Spent Fuel Storage Installation (Isfsi), Evacuation Time Estimate Study 2CAN022202, Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-02-24024 February 2022 Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods ML21280A1032021-12-0606 December 2021 Updated Biological Assessment of Impacts to Federally Listed Species Under NMFS Jurisdiction for SONGS Decommissioning W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 0CAN102102, Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis2021-10-0606 October 2021 Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt ML21272A3032021-09-30030 September 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report ML21270A2172021-09-27027 September 2021 LTR-21-0264 David Lochbaum, Union of Concerned Scientists, Letter Study Regarding Spent Fuel in Dry Storage at San Onofre Nuclear Generating Station ML21237A0512021-08-25025 August 2021 Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment 2CAN062103, Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval2021-06-29029 June 2021 Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval W3F1-2021-0004, License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual2021-04-0505 April 2021 License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual ML21272A3382021-04-0101 April 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report ML21090A0332021-03-31031 March 2021 Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) W3F1-2021-0015, Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-01-29029 January 2021 Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 W3F1-2020-0038, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2020-07-23023 July 2020 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System ML20178A3632020-06-22022 June 2020 Defueled Safety Analysis Report ML19158A0922019-06-0404 June 2019 Facility Change Report, Summary Report of Commitment Changes, and Cycle Specific Technical Specification Bases Page Updates San Onofre Nuclear Generating Station (SONGS) Units 1, 2, 3, and the Independent Spent Fuel Storage Installation W3F1-2019-0022, Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results2019-03-14014 March 2019 Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results ML19011A4572019-01-11011 January 2019 ISFSI Pad Surveys at San Onofre Nuclear Generating Station Final ML18330A0032018-11-16016 November 2018 Southern California Edison Company; San Onofre Nuclear Generating Station; Non-proprietary Summary of the Holtec Proprietary MPC-37 Drop Analysis in Holtec Report Number HI-2188261 Rev. 3, November 16, 2018 ML18235A1562018-08-31031 August 2018 APR1400-E-P-NR-14006-NP, Rev. 2, Severe Accident Mitigation Design Alternatives (Samdas) for the APR1400. ML18235A1072018-08-31031 August 2018 APR1400-K-O-NR-14001-NP, Rev. 3, Deviation Report Between NUREG-1432 Rev. 4.0 and APR1400 Technical Specifications. ML18225A3352018-08-13013 August 2018 APR1400-K-X-ER-14001-NP, Rev. 2, Applicant'S Environmental Report - Standard Design Certification. ML18225A3402018-07-31031 July 2018 APR1400-Z-A-NR-14019-NP, Rev. 3, CCF Coping Analysis. ML18214A5632018-07-31031 July 2018 Enclosure 9 to MKD/NW-18-0107L, APR1400-E-X-NR-14001-NP, Revision 4, Equipment Qualification Program ML18212A3452018-07-31031 July 2018 APR1400-E-I-NR-14001-NP, Rev. 4, Human Factors Engineering Program Plan. ML18187A4172018-07-0606 July 2018 License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel ML18215A1782018-06-30030 June 2018 WCAP-18169-NP, Rev 1, Arkansas Nuclear One Unit 2 Heatup and Cooldown Limit Curves for Normal Operation. ML18199A5652018-06-30030 June 2018 Loss of Large Area Analysis Report, Revision 2 ML18199A5632018-06-30030 June 2018 CPC Setpoint Analysis Methodology for APR1400, Revision 3 ML18176A0352018-06-21021 June 2018 Defueled Safety Analysis Report ML18233A4692018-06-18018 June 2018 Comment Disposition for High Energy Arcing Faults (Heafs) in Electrical Equipment Phase 2 ML18212A3432018-05-31031 May 2018 APR1400-Z-J-NR-14012-NP, Rev. 3, Control System CCF Analysis. ML18214A5612018-05-31031 May 2018 Enclosure 7 to MKD/NW-18-0107L, APR1400-Z-A-NR-14011-NP, Revision 3, Criticality Analysis of New and Spent Fuel Storage Racks ML18214A5592018-05-31031 May 2018 Enclosure 5 to MKD/NW-18-0107L, APR1400-Z-J-NR-14003-NP, Revision 3, Software Program Manual ML18214A5572018-05-31031 May 2018 Enclosure 3 to MKD/NW-18-0107L, APR1400-Z-J-NR-14002-NP, Revision 3, Diversity and Defense-in-Depth ML18212A3412018-05-31031 May 2018 APR1400-Z-J-NR-14001-NP, Rev. 3, Safety I&C System. ML18212A3382018-05-31031 May 2018 APR1400-Z-A-NR-14007-NP, Rev. 2, Mass and Energy Release Methodologies for LOCA and Mslb. 2024-07-02 Category:Topical Report MONTHYEARML21312A4782021-11-0505 November 2021
[Table view]NRC Staff Preliminary Questions Regarding X Energy LLC Xe-100 Topical Report: Risk-Informed Performance-Based Licensing Basis Development W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator ML18085B0442016-10-31031 October 2016 APR1400-K-Q-TR-11005-NP-A, Revision 2, KHNP Quality Assurance Program Description (QAPD) for the APR1400 Design Certification. ML15300A2142015-10-22022 October 2015 WCAP-18051-NP, Rev. 0, Palo Verde, Unit 3, Reactor Coolant Pump 2A Suction Safe End Instrumentation Nozzle Half-Nozzle Repair Evaluation. ML15336A0832015-09-30030 September 2015 WCAP-18030-NP, Revision 0, Criticality Safety Analysis for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. ML15170A3782015-06-18018 June 2015 PWROG-15039-NP, Revision 0, Waterford Unit 3 Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability. ML15170A3792015-06-18018 June 2015 PWROG-15054-NP, Revision 1, Waterford, Unit 3, RAI Response for Applicant Action Items 1, 2, and 7. ML14022A0552014-01-14014 January 2014 WCAP-17679-NP, Supplement 1, Revision 0, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 1 - Supplemental Information. ML11215A0912011-06-30030 June 2011 ANP-2975(NP), Revision 0, San Onofre Nuclear Generating Station, Unit 2 and Unit 3 - Realistic Large Break LOCA Report, Enclosure 6 ML0608603342006-03-31031 March 2006 Responses to NRC Requests for Additional Information on WCAP-16208-P, Rev. 1, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions for Waterford, Unit 3 ML0610405932006-02-28028 February 2006 WCAP-16524-NP, Rev. 0, Analysis of Capsule 230 from Arizona Public Service Company Palo Verde Unit 2 Reactor Vessel Radiation Surveillance Program. ML0619900742006-01-31031 January 2006 Rev. 1 to SG-SGDA-05-48-NP, WOG PA-MSC-0190, Revision 1: Test Results Related to Tig and Alloy 800 Sleeve Installation in 3/4 Inch and 7/8 Inch OD SG Tubing in Service Inspection Requirements. ML0601901072005-12-14014 December 2005 Non-Proprietary Rev. 0 to LTR-RCPL-05-153, Response to NRC Request for Additional Information on WCAP-16005-NP, Rev. 03, 'San Onofre Nuclear Generating Station Unit 2 RCS Pressure & Temperature Limits Report' & WCAP-16167-NP, Rev. 0. ML0527101642005-09-22022 September 2005 Westinghouse - Meeting Slides 9/22/05 ML0531102852005-07-31031 July 2005 WCAP-16208-NP, Rev. 1, Supplement 1, NDE Inspection Length for San Onofre 2 & 3 Steam Generator Tubesheet Region Cold Leg Explosive Expansions. ML0515204172005-05-31031 May 2005 WCAP-16208-NP, Revision 1, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions, Enclosure 5 ML0512604192005-03-31031 March 2005 CENPD-279, Supplement 16, Annual Report on Combustion Engineering ECCS Performance Evaluation Models for Pwrs. ML0436503542004-12-23023 December 2004 2003 Emergency Core Cooling System Annual 10 CFR 50.46 Report, San Onofre Nuclear Generating Station, Units 2 and 3 ML0503202992004-11-30030 November 2004 WCAP-16005-NP, Rev. 03, San Onofre Nuclear Generating Station Unit 2 RCS Pressure and Temperature Limits Report. ML0503203012004-11-30030 November 2004 WCAP-16167-NP, Rev 00, San Onofre Nuclear Generating Station Unit 3, RCS Pressure and Temperature Limits Report. ML0429305912004-10-15015 October 2004 Additional Information Supporting Third Ten-Year Inservice Inspection (ISI) Interval Relief Request ISI-3-1 Request to Use Risk-Informed Inservice Inspection (Ri ISI) ML0423902142004-08-20020 August 2004 Westinghouse Owners Group Request to Withdraw WCAP-16168-NP, Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval, (PA-MSC-0120) ML0417001242004-03-31031 March 2004 Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Palo Verde Units 1 and 2. ML0402600162004-01-19019 January 2004 Request for Review of BAW-2441, Revision 2, Risk Informed Justification for LCO End-State Changes. ML0332302252003-11-12012 November 2003 Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application. ML0318909262003-07-0202 July 2003 Notification of Updating Inservice Inspection Program & Submittal of Relief Requests for Third 10-Year Inspection Interval San Onofre Nuclear Generating Station Units 2 & 3 ML0312701052003-03-31031 March 2003 WCAP-16076-NP, Rev 0, Requirements Phase Human Factors Review for Common Q Phase 3 Core Protection Calculator System Project ML0324101772003-03-31031 March 2003 Rev 0 to WCAP-16005-NP, San Onofre Nuclear Generating Station, Unit 2 RCS Pressure & Temperature Limits Report. W3F1-2003-0020, Submittal of Second Reactor Vessel Surveillance Capsule Report2003-03-28028 March 2003 Submittal of Second Reactor Vessel Surveillance Capsule Report ML0303705902002-08-31031 August 2002 WCAP-15907-NP, Rev 01, CEOG, Auxiliary Feedwater System Safety System Functional Assessment, Palo Verde, Units 1, 2, & 3 ML0223901832002-08-15015 August 2002 Combustion Engineering Owners Group Request for Review of CE Owners Group Report WCAP-15691 Rev 03, Joint Applications Report for Containment Integrated Leak Rate Test Interval Extension. ML0230503872002-07-31031 July 2002 WCAP-15848-NP, Rev 0, Fuel Rod Cladding Development Program in Palo Verde Unit 3: Examination of Fuel Rods with Advanced Cladding Materials at End-of-Cycle 9. ML0214801312002-05-22022 May 2002 Proposed Change Number NPF-10/15-543, Exigent Steam Generator Technical Specification Change ML19066A0851986-04-30030 April 1986 CPC and Methodology Changes for the CPC Improvement Program (CEN-310-NP-A 8605270198) 2021-07-19 |
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