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 Issue dateTitle
ML22192A07511 July 2022License Amendment Request - Application of Risk-Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure Supplemental Information
ML21175A18520 August 2021Issuance 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
ML20293A1608 December 2020Issuance 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
ML20296A62322 October 2020Request for NRC Approval to Apply Leak-Before-Break Methodology to Reactor Coolant System Branch Piping
ML21210A12630 September 20202 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency Systems (Epids L-2020-LRO-0076) - Redacted
ML21208A36730 September 20202 to Updated Final Safety Analysis Report, Chapter 14, Safety Analysis (EPID L-2020-LRO-0076) - Redacted
ML21210A12530 September 20202 to Updated Final Safety Analysis Report, Chapter 18, Programs and Activities That Manage the Effects of Aging (EPID L-2020-LRO-0076) - Redacted
ML20181A42229 June 2020Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Response to Request for Additional Information
ML20136A01014 May 2020NRR E-mail Capture - Final RAIs Regarding Surry Units 1 & 2 LAR to Adopt 10 CFR 50.69
ML19360A02027 December 2019SER 2019-12-23 for ADAMS
ML19343A0196 December 2019Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML19274C67631 October 2019NUREG-1437 - Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 6, Second Renewal Regarding Subsequent License Renewal for Surry Power Station Units 1 and 2, Draft Report for Comment
ML19249B77429 August 2019Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated)
ML19249B76829 August 2019Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated)
ML19204A35717 July 2019Subsequent License Renewal Application Response to Request for Additional Information - Set 2
ML19204A35830 June 2019WCAP-18258-NP, Revision 1, Flaw Tolerance Evaluation for Susceptible Reactor Coolant Loop Cast Austenitic Stainless Steel Elbow Components for Surry Units 1 and 2.
ML19095A60531 March 2019Enclosure 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
ML19058A58327 September 2018UFSAR Chapter 14-18
ML19058A44227 September 2018Updated Final Safety Analysis Report, Chapter 9
ML16323A18521 December 2016Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation
ML16327A06217 November 2016Reevaluated Seismic Hazard Mitigating Strategies Assessment Report
ML16158A4324 August 2016Safety Evaluation Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML15335A09315 December 2015Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation2.1 of the Near-Term Task Force Review
ML15078A28912 March 2015Engineering Evaluation 14-E15, Dominion Flooding Hazard Reevaluation Report, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Revision 1, Pp. 2-219 Through the End
ML15078A28812 March 2015Engineering Evaluation 14-E15, Dominion Flooding Hazard Reevaluation Report, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Revision 1, Pp. 2-115 Through 2-218
ML15078A28712 March 2015Engineering Evaluation 14-E15, Dominion Flooding Hazard Reevaluation Report, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Revision 1, Pp. 1 Through 2-114
ML15069A2342 March 2015Six-Month Status Report 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)
ML14251A03528 August 2014Six-Month Status Report 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)
ML14210A0218 August 2014June 25, 2014, Summary of Category 1 Public Meeting with Dominion Nuclear to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1
ML14233A51430 June 2014Redacted - Surry Power Station Units 1 & 2, Independent Spent Fuel Storage Installation (ISFSI) - Safety Analysis Report - Revision 20
ML14111A1479 May 2014Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights
ML14086A1739 April 2014Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML14086A1949 April 2014Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML14092A41431 March 2014Response to March 12, 2012 Information Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1
ML14069A01527 February 2014Six-Month Status Report 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)
ML14002A14519 February 2014Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14043A44412 February 2014Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Surry Power Station, Units 1 and 2, TAC Nos.: MF1002 and MF1003 (Revision 2)
ML13259A04112 September 2013Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.1 - 1.5 Year Response for CEUS Sites
ML13242A01323 August 2013Six Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)
ML13063A18128 February 2013Overall 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)
ML12354A07710 December 2012CFR50 Appendix R Exemption Request Reactor Coolant Pump Oil Collection System
ML13017A00227 November 2012Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3
ML12053A34012 March 2012Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
ML12056A04712 March 2012Enclosure 1 - Recommendation 2.1: Seismic
ML0912603867 May 2009Issuance of Amendment Regarding Modified Interim Alternate Repair Criteria for B Steam Generator Tube Repair
ML0912704445 May 2009Proposed Emergency License Amendment Request, Modified Interim Alternate Repair Criteria for Unit 1 B Steam Generator Tube Repair
ML08134006816 May 2008Letter - Issuance of Exigent Amendment Regarding Interim Alternate Repair Criteria for Steam Generator Tube Repair
ML08108004414 April 2008Proposed License Amendment Request, Interim Alternate Repair Criteria (Iarc) for Steam Generator (SG) Tube Repair
ML08065056229 February 2008Supplemental Response to NRC GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
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