Category:Letter
MONTHYEARIR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24206A0062024-08-0808 August 2024 Notice of Availability of the Final Environmental Impact Statement for the North Anna Nuclear Power Station Unit Numbers 1 and 2 Subsequent License Renewal (Docket Numbers: 50-338 and 50-339) ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change ML24206A0902024-07-24024 July 2024 Owners Activity Report IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information 2024-08-08
[Table view] Category:Topical Report
MONTHYEARML21264A5352021-09-30030 September 2021 PWROG-19047-NP-A, Rev 0, North Anna Units 1 and 2 Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis ML20182A6922020-06-29029 June 2020 & ISFSI, Millstone Power Station, Units 1, 2 3, & ISFSI, North Anna Power Station, Units 1, 2 & ISFSI, Virgil C. Summer Station, Surry Power Station, Units 1 & 2 and ISFSI - Submission of Revision 28 of the Quality Assurance. ML19175A0712019-06-13013 June 2019 ISFSI, Millstone, Units 1, 2, 3, & ISFSI, North Anna, Units 1, 2 & ISFSI, Surry, Units 1 & 2 & ISFSI - Submittal of Revision 27 of the Quality Assurance Topical Report ML19095A6052019-03-31031 March 2019 Enclosure 5 - Topical Report WCAP-15550-NP, Rev 2, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for Surry Units 1 and 2 Nuclear Power Plants for the Subsequent License Renewal Progra ML19042A1382019-01-31031 January 2019 PWROG-17011-NP, Revision 2, Update for Subsequent License Renewal: WCAP-14535A, Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination and WCAP-15666-A, Extension of Reactor Coolant Pump Motor Flywheel Examination. ML18291A8372018-06-30030 June 2018 Enclosure 4, Attachment 2, ANP-3680NP, Revision 0, Topical Report ML18291A8362018-06-30030 June 2018 Enclosure 4, Attachment 1: ANP-3679NP, Revision 0, Topical Report ML18065A1942018-02-28028 February 2018 Submittal of Approval Version of the Quality Assurance Topical Report, Revision 24-A ML18012A0982018-01-0404 January 2018 Submittal of Topical Report VEP-NE-1-A Revision 0, Minor Revision 3, Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Technical Specifications & Topical Report. ML18085A1642017-10-31031 October 2017 WCAP-18243-NP, Rev. 0, Surry, Units 1 and 2, Heatup and Cooldown Limit Curves for Normal Operation. ML18085A1612017-10-31031 October 2017 WCAP-18242-NP, Rev. 0, Surry, Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity for Subsequent License Renewal. ML17187A1322017-06-28028 June 2017 Submittal of Topical Report VEP-NE-1, Revision 0.2-A, Relaxed Power Distribution Control Methodology and Associated Fq Surveillance Technical Specifications for Information Only ML16196A2922016-07-11011 July 2016 ISFSI, Millstone, Units 1, 2 & 3, and ISFSI, North Anna, Units 1 & 2, and ISFSI, Surry, Units 1 & 2, and ISFSI Submission of Rev. 21 of Quality Assurance Topical Report for NRC Approval and Submission of Revision 22 for Information Only ML18085A1602015-09-30030 September 2015 WCAP-18028-NP, Rev. 01, Extended Beltline Pressure Vessel Fluence Evaluations Applicable to Surry, Units 1 and 2. ML15313A1412015-03-31031 March 2015 Topical Report, VEP-FRD-41-NP-A, Rev. 0.2, VEPCO Reactor System Transient Analyses Using the Retran Computer Code, March 2015 ML14188B1342014-06-30030 June 2014 Nuclear Facility Quality Assurance Programs Description Topical Report DOM-QA-1, Rev. 16 ML13191A9132013-06-17017 June 2013 ISFSI, Millstone, Units 1, 2, & 3 & ISFSI, North Anna, Units 1 & 2 & ISFSI and Surry, Units 1 & 2 & ISFSI - Submission of Revision 14 of the Quality Assurance Topical Report ML11245A0772011-08-15015 August 2011 ISFSI, Millstone, Units 1, 2, & 3 and ISFSI, North Anna, Units 1, & 2 and ISFSI and Surry, Units 1 & 2 and ISFSI - Re-Submission of Quality Assurance Topical Report ML1118007302011-06-28028 June 2011 Connecticut, Inc., Virginia Electric and Power Company, Submission of Revision 11 of the Quality Assurance Topical Report ML0926606172009-06-30030 June 2009 Attachment 3 - Corrected Pages for WCAP-17092-NP (Non-Proprietary) ML0936200862009-04-30030 April 2009 WCAP-17071-NP, Rev 0, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F) ML0816805082008-06-19019 June 2008 Stations - Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions ML0631904672006-11-0606 November 2006 Transmittal of Approved Topical Report DOM-NAF-3 NP-A, Gothic Methodology for Analyzing the Response to Postulated Pipe Ruptures Inside Containment. ML0626501842006-09-14014 September 2006 Approved Topical Report DOM-NAF-2, Rev 0.0-A, Reactor Core Thermal-Hydraulics Using the Vipre-D Computer Code Including Appendixes a & B ML0535702762005-12-12012 December 2005 Quality Assurance Program Topical Report ML0534701942005-12-0707 December 2005 ISFSI Associated Radioactive Material Packages - DOM-QA-A Cover Page - Index ML0530602662005-11-0101 November 2005 Request for Approval of Topical Report DOM-NAF-3, Gothic Methodology for Analyzing the Response to Postulated Pipe Ruptures Inside Containment. Cover Letter Through Topical Report Page 40 ML0530602732005-11-0101 November 2005 Request for Approval of Topical Report DOM-NAF-3, Gothic Methodology for Analyzing the Response to Postulated Pipe Ruptures Inside Containment. Topical Report Page 40 Through End ML0525104842005-09-0808 September 2005 Stations Units 1 & 2, Millstone Power Station Units 2 & 3, Information Regarding a Lynxt Error Supporting the Request for Approval of Topical Report DOM-NAF-2 Reactor Core Thermal-hydraulics Using the VIPRE-D Computer . ML0522704202005-08-0808 August 2005 Revision 27, MP-02-OST-BAP01, Quality Assurance Program Topical Report. ML0515205322005-05-19019 May 2005 MP-02-OST-BAP01, Revision 26, Change 5, Quality Assurance Program Topical Report, Millstone Power Station ML0511003282005-04-0808 April 2005 Quality Assurance Program (QAP) Topical Report - Millstone Power Station Revision 26, Change 4 ML0503303292004-12-30030 December 2004 Quality Assurance Program (QAP) Topical Report - Millstone Power Station Revision 26, Change 3 (Document No. MP-02-OST-BAP01) ML0428001182004-09-30030 September 2004 Request for Approval of Topical Report DOM-NAF-2 Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code Including Appendix a - Qualification of the F-ANP Bwu CHF Correlations in the Dominion VIPRE-D Computer Code ML0428001222004-09-30030 September 2004 Attachment 2 - Appendix a to Topical Report DOM-NAF-2, Qualification of the F-ANP Bwu CHF Correlations in the Dominion VIPRE-D Computer Code. ML0424700172004-08-24024 August 2004 Attachment 2 - Discussion of Changes to Current QA Program Descriptions for the Above Dominion Facilities ML0424700182004-08-24024 August 2004 Attachment 3 - Comparative Analysis of Current N45.2 Series QA Standards to NQA-1-1994 Standards ML0424700192004-08-24024 August 2004 Attachment 4 - Table of Where ANSI N18.7 Requirements Are Addressed by NQA-1-1994 Standards And/Or the New QA Topical Report ML0424700212004-08-24024 August 2004 Attachment 6 - Current 10 CFR 50, Appendix B Quality Assurance Program Topical Report for Millstone Power Stations and Associated Radioactive Material Packages ML0424700202004-08-24024 August 2004 Attachment 5 - Current 10 CFR 50, Appendix B Quality Assurance Program Topical Report for North Anna and Surry Power Stations Associated Radioactive Material Packages and ISFSI 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) ML0424003682004-08-13013 August 2004 MP-02-OST-BAP01, Rev 26, Change 1, Quality Assurance Program Topical Report. ML0424700162004-07-0606 July 2004 Attachment 1 - Proposed Nuclear Facility Quality Assurance Program Description - Topical Report DOM-QA-1, Revision 0, Final Draft July 06, 2004 ML0425901692004-06-30030 June 2004 VEP-FRD-41, Rev 0.1-A, Vepco Reactor System Transient Analyses Using the Retran Computer Code (Volume 1) ML0418904362004-06-29029 June 2004 Quality Assurance Program (QAP) Topical Report - Millstone Power Station Revision 26 (Document No. MP-02-OST-BAP01) ML0416301542004-05-26026 May 2004 Quality Assurance Program (QAP) Topical Report - Millstone Power Station Revision 25, Change 4 (Change 3 Correction - Document No. MP-02- OST-BAP01) ML0410704722004-04-15015 April 2004 Request for Approval of Topical Report DOM-NAF-2, Reactor Core Thermal-Hydraulics Using VIPRE-D Computer Code Including Appendix a, Qualification of F-ANP Bwu CHF Correlations in Dominion VIPRE-D Computer Code. ML0332302252003-11-12012 November 2003 Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application. ML0329506292003-10-14014 October 2003 Quality Assurance Program Topical Report - Millstone Power Station, Revision 25 Document No. MP-02-OST-BAP01 ML0329301032003-08-31031 August 2003 to WCAP-15813-NP, Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Millstone, Unit 2. 2021-09-30
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