ML17187A132
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| ML17187A132 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/28/2017 |
| From: | Sly C D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 17-214 VEP-NE-1-A, Rev. 0, Minor Rev. 2 | |
| Download: ML17187A132 (44) | |
Similar Documents at North Anna | |
|---|---|
Category:Letter
MONTHYEARIR 05000338/20240032024-10-28028 October 2024
[Table view]– Integrated Inspection Report 05000338-2024003 and 05000339-2024003 ML24283A0392024-10-0909 October 2024 Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 5.5.13.D ML24281A1372024-10-0707 October 2024 ISFSI - Submittal of Cask Registration for Spent Fuel Storage 05000338/LER-2024-001-01, Automatic Reactor Trip Due to Prni High Negative Rate2024-09-24024 September 2024 Automatic Reactor Trip Due to Prni High Negative Rate IR 05000338/20244202024-09-23023 September 2024 Security Baseline Inspection Report 05000338/2024420 and 05000339/2024420, Cover Letter ML24243A0872024-09-20020 September 2024 Response to EPA Comments Regarding the Final Site Specific Supplement to the Generic Eist for License Renewal North Anna Power Station, Units 1 and 2 IR 05000338/20244022024-09-17017 September 2024 Security Baseline Inspection Report 05000338/2024402 and 05000339/2024402 ML24215A2622024-08-28028 August 2024 Transmittal Letter for Subsequent Renewed License IR 05000338/20240052024-08-27027 August 2024 Updated Inspection Plan for North Anna Power Station, Units 1 and 2 (Report 05000338/2024005 and 05000339/2024005) 05000339/LER-2024-001-01, Loss of Generator Field for 2J Eog During 2-PT-82.282024-08-20020 August 2024 Loss of Generator Field for 2J Eog During 2-PT-82.28 ML24234A0742024-08-15015 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-23-63, NEI 03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division 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) ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24241A0692024-08-0606 August 2024 ISFSI, Submittal of Cask Registration for Spent Fuel Storage IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant 05000338/LER-2024-001, Automatic Reactor Trip Due to Prni High Negative Rate2024-07-25025 July 2024 Automatic Reactor Trip Due to Prni High Negative Rate ML24206A0902024-07-24024 July 2024 Owners Activity Report 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 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 05000339/LER-2024-001, Loss of Generator Field for 2J EDG During 2-PT-82.282024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240102024-05-24024 May 2024 NRC Fire Protection Team Inspection (FPTI) Report 05000338/2024010 and 05000339/2024010 IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating Report ML24087A0572024-04-16016 April 2024 Correction to Issuance of Amendment Nos. 296 and 279 ML24088A2692024-03-27027 March 2024 Core Operating Limits Report Cycle 31 Pattern Sos Revision 0 ML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection 2024-09-24 Category:Technical Specifications MONTHYEARML23072A0892023-05-0101 May 2023
[Table view](Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML21232A2172021-10-19019 October 2021 Issuance of Amendment Nos. 288 and 271 to Revise Technical Specifications Battery Surveillance Testing ML21280A3282021-10-0707 October 2021 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML20325A0952021-03-19019 March 2021 Issuance of Amendment to Revise Technical Specifications to Allow Usage of a Small Break Loss of Coolant Accident Methodology (Non-Proprietary) ML20302A1792020-10-29029 October 2020 Non-Proprietary, Issuance of Amendment Nos. 286 and 269 to Revise Technical Specifications to Allow Usage of a Full Spectrum Loss of Coolant Accident Methodology ML19238A1272019-09-12012 September 2019 Issuance of Amendment Nos. 282 and 265 to Revise Technical Specifications Regarding Open Phase Protection ML19196A1102019-07-0909 July 2019 Attachments 2, 3 & 4 - Response to NRC Request for Additional Information and Correction of SBLOCA Analysis Error and Revised Marked-Up/Typed NAPS and SPS Technical Specifications Pages ML19156A2072019-05-24024 May 2019 Response to Request for Additional Information on Proposed License Amendment Request Open Phase Protection Per NRC Bulletin 2012-01 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 ML16252A4782016-10-17017 October 2016 Issuance of Amendments Revising Technical Specifications to Address the Issue Identified in Westinghouse NSAL-09-5, Revision 1, and NSAL-15-1, Revision 0 ML16013A4442016-02-22022 February 2016 (NAPS) - Issuance of Amendment for Changes to Technical Specification (TS) 3.8.1 - AC Sources, Operating Revised Surveillance Requirement ML15307A3002016-02-0202 February 2016 (NAPS) - Issuance of Amendments for Changes to the Emergency Action Level Revisions - Correction of Equipment Mark Number ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15133A3812015-06-16016 June 2015 Issuance of Amendments to Extended Type a Test Frequency to 15 Years ML15147A0292015-05-22022 May 2015 Proposed License Amendment Request (Lar), TS 3.8.1 - AC Sources - Operating, Revised Surveillance Requirement ML15083A4362015-05-14014 May 2015 Issuance of Amendments Regarding Alternate Control Rod Position Monitoring ML15041A6672015-02-0404 February 2015 Proposed License Amendment Request Re Alternate Control Rod Position Monitoring ML14188C4532014-08-27027 August 2014 Issuance of Amendments Regarding Modification of Control Bank Sequence and Overlap Technical Specifications ML14169A3592014-08-12012 August 2014 Stations, Units 1 and 2, Issuance of Amendments Regarding Addition of an Analytical Methodology to the Core Operating Limits Reports and an Increase to the Surry Minimum Temperature for Criticality ML14183B3182014-06-30030 June 2014 Proposed License Amendment Request Permanent Fifteen-Year Type a Test Interval ML13302B8922013-10-0202 October 2013 Technical Specification Bases ML12356A2982012-12-13013 December 2012 Supplemental Information for Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process. 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ML1029804472010-10-21021 October 2010 Proposed License Amendment Request (LAR) Addition of Analytical Methodology to COLR Best-Estimate Large Break Loss of Coolant Accident (BE-LBLOCA) ML0935004002010-03-0303 March 2010 Issuance of Amendments to Adopt TSTF-490, Revision 0, Regarding Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Using the Consolidated Line Item Improvement Process ML0920503812009-07-23023 July 2009 License Amendment Request, One Time Extension of the Completion Time for 1 J - 480 Volt AC Distribution Subsystem ML0909000552009-03-26026 March 2009 License Amendment Request, Measurement Uncertainty Recapture Power Uprate ML0904004652009-02-0606 February 2009 License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Work Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0815106502008-06-30030 June 2008 Technical Specifications, Issuance of Amendment Regarding One-Time 5-Year Extension to Type a Test Interval ML0735202472007-12-17017 December 2007 Proposed License Amendment Request, One-time Risk-Informed Extension to the Completion Time for EDG Fuel Oil Storage Tank Recoating ML0730604062007-10-31031 October 2007 Tech Spec Pages for Amendments 252 and 232 Control Room Habitability, Using the Technical Specification Task Force Traveler, TSTF-448, Revision 3 ML0730304002007-10-17017 October 2007 Tech Pages for Amendments 251 and 231 Technical Specification Change to Add Limiting Condition for Operation 3.0.8 on the Inoperability of Snubbers, Using the Consolidated Line Item Improvement Process, TSTF-372, Rev 4 ML0715001452007-05-29029 May 2007 Proposed License Amendment Request, Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0714104632007-05-21021 May 2007 Proposed License Amendment Request Addition of LCO 3.0.8 - Inoperability of Snubbers Using the Consolidated Line Item Improvement Process Technical Specification Improvement ML0702202192007-01-19019 January 2007 Technical Specifications Corrected Page for Amendment Nos. 249 and 229 ML0701003492007-01-0909 January 2007 Technical Specifications, Relocated the ASTM Standard Used to Test the Total Particulate Concentration of the Stored Fuel Oil from TS 5.5.12, Emergency Diesel Generator Fuel Oil Testing Program to a Licensee-controlled Program ML0634502592006-12-11011 December 2006 Tech Spec Pages for Amendments 249 and 229 Regarding Diesel Fuel Oil Testing Program ML0630000282006-10-16016 October 2006 Tech Spec Pages for Amendments 248 and 228 Regarding Consolidated Line Item Improvement Process for the Steam Generator Tube Integrity ML0627700182006-09-25025 September 2006 Technical Specification Bases Pages ML0620604672006-07-18018 July 2006 Technical Specifications, Issuance of Amendments on Changes to Analytical Methodology and Core Operating Limits Report, MC7526 and MC7527 ML0615101992006-05-30030 May 2006 Proposed Technical Specifications Change Diesel Fuel Oil Testing Program ML0533502792005-11-21021 November 2005 10 CFR 50.9 Correction of Information Provided to Support Technical Specification Change for Quench Spray and Recirculation Spray Nozzles Surveillance Frequency ML0529900852005-10-25025 October 2005 Enclosure, Technical Specifications, Amd MC7612, Equation for Over-Temperature Delta T Function Allowable Value ML0529900152005-10-24024 October 2005 Technical Specifications, Revised Test Frequency of P-4 Interlock Function ML0526301042005-09-15015 September 2005 Tech Spec Pages for Amendment Nos. 243 and 224, Revise the Administrative Controls Section ML0519604352005-07-14014 July 2005 Proposed Technical Specification Changes Correction to Equation for Overtemperature T Function Allowable Value ML0518900342005-07-0505 July 2005 Proposed Technical Specification Changes Addition of Analytical Methodology to COLR 2023-05-01 Category:Topical Report MONTHYEARML21264A5352021-09-30030 September 2021
[Table view]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 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. 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 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 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 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 . 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 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 ML0424700182004-08-24024 August 2004 Attachment 3 - Comparative Analysis of Current N45.2 Series QA Standards to NQA-1-1994 Standards 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 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 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) 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. ML15313A1492003-08-31031 August 2003 Topical Report, VEP-FRD-42, Rev. 2.1-A, Reload Nuclear Design Methodology, August 2003 ML15313A1542003-08-31031 August 2003 Topical Report, VEP-NE-1, Rev. 0.1-A, VEPCO Relaxed Power Distribution Control Methodology and Associated Fq Surveillance Technical Specifications, August 2003 ML0326807202003-08-29029 August 2003 Submittal of Approved Topical Report VEP-FRD-42, Revision 2.0-A, Reload Nuclear Design Methodology for Application ML0316901082003-06-11011 June 2003 Submittal of Approved Topical Report DOM-NAF-1-REV, 0.0-P-A Qualification of Studsvik Core Management System Reactor Physics Methods for Application to North Anna & Surry Power Stations ML0309100532003-03-21021 March 2003 Request for Additional Information on Topical Report VEP-FRD-42, Reload Nuclear Design Methodology ML0233801012002-11-25025 November 2002 Request for Additional Information, Topical Report DOM-NAF-1- Qualification of Studsvik Core Management System Reactor Physics Methods for Application to North Anna & Surry Power Stations ML0217107902002-06-13013 June 2002 Attachment 2, Topical Report DOM-NAF-1, Qualification of the Studsvlk Core Management System Reactor Physics Methods for Application to North Anna Surry Power Stations ML0209103142002-03-22022 March 2002 Supplemental Information - NRC Bulletin 200-01, Circumferential Cracking of Reactor Vessel Head Penetration Nozzles Results of Metallurgical Investigation of Alloy 82/182 Cracking ML19094A8011976-05-28028 May 1976 Submits Thirty-Five Copies of Amendment Two to Topical Report Entitled, Quality Assurance Program-Operations Phase (VEP-1-A) for Approval 2021-09-30 |
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