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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML21281A214  + (VEGP Units 3 and 4 Supplement to Exemption from Operator Written Examination and Operating Test for Unit 4)
• ML23243B049  + (VEGP Units 3 and 4, Safety Evaluation, LAR-22-002, TS 3.8.3 Inverters Operating, Completion Time Extension - Enclosure 3)
• ML23055A040  + (VEGP, Unit 4, Potential License Amendment Request for Prior to Initial Criticality Overview Presentation)
• ML23335A137  + (VEGP, Units 3 and 4 Safety Evaluation Regarding Implementation of Mitigating Strategies for Order EA-12-049)
• NL-09-0585, VEGP-ISI-ALT-01, Version 1.0, Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)  + (VEGP-ISI-ALT-01, Version 1.0, Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i))
• NL-10-0706, VEGP-ISI-ALT-03, Version 2, Proposed Alternative for the Third ISI Interval  + (VEGP-ISI-ALT-03, Version 2, Proposed Alternative for the Third ISI Interval)
• NL-10-1663, VEGP-ISI-ALT-03, Version 3, Proposed Alternative for the Third ISI Interval  + (VEGP-ISI-ALT-03, Version 3, Proposed Alternative for the Third ISI Interval)
• NL-09-1410, VEGP-ISI-RR-01, Version 1.0, Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii)  + (VEGP-ISI-RR-01, Version 1.0, Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii))
• EPID:L-2025-LLR-0053  + (VEGP3-4-ISI-ALT-2025-01, Request for Use of a Later Edition of the ASME Section XI Boiler and Pressure Vessel Code for Inservice Inspection (NL-25-0111))
• NL-25-0111, VEGP3-4-ISI-ALT-2025-01, Request for Use of a Later Edition of the ASME Section XI Boiler and Pressure Vessel Code for Inservice Inspection (NL-25-0111)  + (VEGP3-4-ISI-ALT-2025-01, Request for Use of a Later Edition of the ASME Section XI Boiler and Pressure Vessel Code for Inservice Inspection (NL-25-0111))
• ML042590169  + (VEP-FRD-41, Rev 0.1-A, Vepco Reactor System Transient Analyses Using the Retran Computer Code (Volume 1))
• ML20028H085  + (VEP-NAF-1, Pdq Two Zone Model)
• ML033250573  + (VEPCO - North Anna Power Station, Units 1 and 2 Notification of Revision in Commitment Tracking Movement of Fuel Assembles)
• ML20010B624  + (VEPCO Flame Model)
• ML20087B058  + (VEPCO Investigative Board Preliminary Rept. W/O Cover Sheet)
• ML19094A814  + (VEPCO Letter, Serial No.874 Dated 01/26/1976 Forwarded Inservice Inspection Report ISI 76-1. Inservice Inspection Schedule Enclosed Therein Should Read Refueling Outage No. 2)
• ML20078K336  + (VEPCO Nomad Code & Model)
• ML18130A395  + (VEPCO North Anna Power Station & Surry Power Station Compliance W/10CFR50.49(b)(2))
• ML20248E874  + (VEPCO North Anna Power Station Unit 1 Jul 1989 Reactor Containment Integrated Leakage Rate Test)
• ML20247B933  + (VEPCO North Anna Power Station Unit 2 Apr 1989 Reactor Containment Integrated Leakage Rate Test, Per 10CFR50,App J)
• ML20032C700  + (VEPCO Nuclear Design Reliability Factors)
• ML19093A790  + (VEPCO Nuclear Power Station Quality Assurance Manual, Corrective Action)
• ML19225C837  + (VEPCO Objections to 790601 Interrogatories from Potomac Alliance & Citizens Energy Forum.Potomac Alliance Format & Questions 21 & 44-47 Are Too Broad.Citizens Energy Forum Question 5-1 Requests Proprietary Drawings)
• ML20108B580  + (VEPCO Proposed Program,Mechanical Cleaning & Valve Repair Svc Water Sys,North Anna Power Station,Feb 1985. W/One Oversize Drawing.Aperture Card Available in PDR)
• ML18136A022  + (VEPCO Reactor Core Thermal-Hydraulic Analysis Using Cobra Iiic/Mit Computer Code)

• ML20129E988  + (VEPCO Reactor Sys Transient Analysis Using Retran Computer Code)

• ML20140D889  + (VEPCO Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs)
• ML19339A354  + (VEPCO Response to NRC Review of North Anna Emergency Plan Emergency Action Levels)
• ML18144A043  + (VEPCO Surry Units 1 & 2 RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices)
• ML18144A042  + (VEPCO Surry Units 1 & 2 RCS Loads & Component Support Margins Evaluation of Elimination of RCS Main Loop Pipe Break Protective Devices)
• ML18144A044  + (VEPCO Surry Units 1 & 2 Safety Balance Assessment for Elimination of RCS Main Loop Pipe Break Protective Activities)
• ML18139B922  + (VEPCO Sys Operator Procedures Manual,Power Sys Emergency Operation)
• ML050460316  + (VEPCO, Surry Power Station, Units 1 and 2 - Withdrawal of Exemption Request for Alternate Material Properties Basis Per 10 CFR 50.60(b))
• ML19093A719  + (VEPCOs Answer to Virginias Motion for Extension of Time)
• ML19095A199  + (VEPCOs Answer to Virginias Motion for Extension of Time)
• ML19093A715  + (VEPCOs Answer to Virginias Motion for Further Extension of Time)
• ML19095A197  + (VEPCOs Answer to Virginias Motion for Further Extension of Time)
• ML19093A791  + (VEPCOs Answer to the Commonwealths Motion for Further Extension of Time)
• ML19105B110  + (VEPCOs Response to Safety Evaluation Report by Office of Nuclear Reactor Regulation)
• ML20148A188  + (VEPCOs Response to Ucs Request to File Reply Brief.Vepco Opposes the Union of Concerned Scientistsrequest Re Issue of Turbine Missiles)
• ML19095A387  + (VEPCOs Views on the Relevancy of the Documents Designated by the Intervenor Arnold)
• ML20206C158  + (VICTORIA:Fission-Product Behavior Module Developed for Melprog Severe Accident Code)
• ML18078A180  + (VII Enclosure - Safety Culture Rev 2)
• 05000387/FIN-2009003-02  + (VIOLATION OF 10 CFR 50.73(A)(2)(VII), Report Common Cause of Failures of Independent Channels)
• 05000387/FIN-2012003-03  + (VIOLATION OF 10 CFR 50.73(a)(2)(i)(B), FAILURE TO REPORT CONDITION PROHIBITED BY TSs)
• ML24221A201  + (VIP-012 Environmental Qualification Final)
• ML20246B116  + (VIPRE-01 Core Thermal-Hydraulic Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications)
• ML20236N970  + (VIPRE-01:Thermal-Hydraulic Code for Reactor Cores Vol 4: Applications)
• ML042180089  + (VIPRE-D Topical Report DOM-NAF-2 Meeting with NRC)
• ML20211Q690  + (VISA-II Sensitivity Study of Code Calculations Input and Analytical Model Parameters)
• ML25083A218  + (VLSSIR Revision Slides for March 2025 ROP Public Meeting)