ML15313A149
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| ML15313A149 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 08/31/2003 |
| From: | Basehore K, Harrell J, Laroe C Dominion Resources |
| To: | Division of Operating Reactor Licensing |
| Guzman R | |
| References | |
| VEP-FRD-42, Rev 2 | |
| Download: ML15313A149 (152) | |
Similar Documents at Surry, North Anna | |
|---|---|
Category:Letter
MONTHYEARML24302A2402024-10-28028 October 2024
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[Table view]Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative 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) ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps 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 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23244A2352023-09-18018 September 2023 – Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 – Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations ML23181A1352023-08-22022 August 2023 Issuance of Amendment Nos. 295 and 278 License Amendment Request to Remove the Refueling Water Chemical Addition Tank and Change the Containment Sump Ph Buffer ML23136B1392023-06-29029 June 2023 Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML23061A0122023-05-0909 May 2023 Issuance of Amendment Nos. 312 and 312, Regarding Technical Specifications Task Force (TSTF) Traveler 547, Revision 1 ML23072A0892023-05-0101 May 2023 (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 ML23100A0652023-04-25025 April 2023 Issuance of Amendment Nos. 310 and 310, Regarding Turbine Building Tornado Classification ML23102A2832023-04-25025 April 2023 ASME OM Code Inservice Testing Program Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML23030B8472023-03-10010 March 2023 Issuance of Amendment Nos. 309 and 309, License Amendment Request Regarding a 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability ML21320A0072022-09-0707 September 2022 Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary) ML22193A2952022-08-26026 August 2022 Issuance of Amendment Nos. 308 and 308 License Amendment Request for Removal of the Refueling Water Chemical Addition Tank and Containment Sump, Ph Buffer Change and Safety Evaluation ML22196A1972022-07-28028 July 2022 Request for Relief Request N2-I4-LMT-004 Inservice Inspection Limitations ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22068A0712022-03-22022 March 2022 Issuance of Amendment Nos. 292 and 275 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22019A0022022-03-0808 March 2022 Regarding Request to Utilize Code Case OMN-28 ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML21323A1742021-12-22022 December 2021 Issuance of Amendment Nos. 289 and 272 to Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A ML21253A0632021-11-19019 November 2021 Issuance of Amendment Nos. 306 and 306 to Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis ML21188A1742021-10-26026 October 2021 Issuance of Amendment Nos. 305 and 305 Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 ML21232A2172021-10-19019 October 2021 Issuance of Amendment Nos. 288 and 271 to Revise Technical Specifications Battery Surveillance Testing ML21264A0112021-10-18018 October 2021 Safety Evaluation Report Related to the Subsequent License Renewal of North Anna Power Station, Units 1 and 2 ML21175A1852021-08-20020 August 2021 Issuance of Amendment Nos. 304 and 304 Leak-Before-Break for Pressurizer Surge, Residual Heat Removal, Safety Injection Accumulator, Reactor Coolant System Bypass and Safety Injection Lines ML21201A1172021-08-0606 August 2021 Proposed Alternative Requests S1-I5-ISI-05 and S2-I5-ISI-06 to Eliminate Examination of Threads in Reactor Pressure Vessel Flange ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 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) ML20364A0402021-01-15015 January 2021 Request for Relief Request N1-I4-LMT-003 Inservice Inspection Limitations ML20350B8062020-12-28028 December 2020 Request for Relief Request N1-I5-NDE-002 Inservice Inspection Alternative ML20293A1602020-12-0808 December 2020 Issuance of Amendment Nos. 301 and 301 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20148M3592020-12-0808 December 2020 Issuance of Amendment Nos. 302 and 302 to Revise Technical Specifications Figure 3.1 1, Surry Units 1 and 2 Reactor Coolant System Heatup Limitations, and Figure 3.1-2, Surry Units 1 and 2 Reactor Coolant System ML20321A2322020-11-20020 November 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 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 ML20301A4522020-10-28028 October 2020 Non-Proprietary, Issuance of Amendment Nos. 300 and 300 to Revise Technical Specifications 6.2.C, Core Operating Limits Report ML20253A3292020-09-30030 September 2020 Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency ML20252A0042020-09-23023 September 2020 Request for Relief Request Fifth 10-Year Interval ML20252A0072020-09-15015 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI ML20085G9642020-05-19019 May 2020 Issuance of Amendments Nos. 298 and 298 to Revise Technical Specifications Table 3.7-1, Reactor Trip Instrument Operating Conditions, for an Addition of 24-Hour Completion Time for an Inoperable Rector Trip Breaker ML20115E3522020-05-12012 May 2020 Alternative Request S2-I5-ISI-05 ASME Section XI Inservice Inspection Program Proposed Alternative Request to Use a Mechanical Clamping Device for a One-Inch Main Steam Line Repair ML20115E2372020-05-0707 May 2020 Issuance of Exigent Amendments Nos. 299 and 299, to Revise TS 6.4.Q, Steam Generator (SG) Program, to Allow a One-Time Deferral of the Inspection of Surry Unit 2 Sg B Spring 2020 Refueling Outage 2024-08-08 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. 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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) 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 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 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 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 . 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. 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 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 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 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) 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 ML0309902932003-03-27027 March 2003 WCAP-16001, Rev 0, Analysis of Capsule Y from Dominion Surry Unit 2 Reactor Vessel Radiation Surveillance Program, Attachment 1, Appendix C and Attachment 2, Appendix a ML0309100532003-03-21021 March 2003 Request for Additional Information on Topical Report VEP-FRD-42, Reload Nuclear Design Methodology ML0309902532003-02-28028 February 2003 WCAP-16001, Rev 0, Analysis of Capsule Y from Dominion Surry Unit 2 Reactor Vessel Radiation Surveillance Program, Attachment 1, Appendix a and B 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 ML0226706442002-08-22022 August 2002 E-mail Attaching BAW-2323, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of Surry Units 1 & 2 for Extended Life Through 48 Effective Full Power Years. 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 2021-09-30 |
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