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A list of all pages that have property "Title" with value "Draft Site Redress Plan". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML22294A159  + (Draft Secy White Paper on Licensing and Regulating Fusion Energy Systems October 5-7, 2022 Full Committee)
  • ML19010A160  + (Draft Seep Monitoring Evaluation Report Mexican Hat, Utah, Umtrca Title I Disposal Site)
  • ML20210T959  + (Draft Seismic & Dymanic Qualification of Safety-Related Electrical & Mechanical Equipment in Operating Nuclear Power Plants. Supporting Documentation Encl)
  • ML20239A626  + (Draft Seismic Effects on Bodega Bay Reactor. Related Info Encl)
  • ML20003A096  + (Draft Seismic Evaluation of Bldg 102 of GE Vallecitos Nuclear Ctr)
  • ML20126D952  + (Draft Seismic Hazard Analysis for Savannah River Plant,Sc)
  • ML19249B997  + (Draft Seismic Hazard Analysis:Methodology for Eastern Us)
  • ML19249C008  + (Draft Seismic Hazard Analysis:Site Specific Response Spectra Results)
  • ML111720634  + (Draft Seismic Information Evaluation Flowchart)
  • ML19257C273  + (Draft Seismic Re-evaluation Program Criteria Document)
  • ML19268B868  + (Draft Seismic Review of Unit for Systematic Evaluation Program Phase 1 Rept)
  • ML20204E912  + (Draft Seismic Verification Program)
  • ML20234F515  + (Draft Seismicity & Tsunami Rept Bodega Head,Ca)
  • ML19338G041  + (Draft Senior Reactor Operator Level Instructor Certification Guide)
  • ML14261A276  + (Draft September 23, 2014, Category 1 Public Meeting with V. C. Summer - Draft License Amendment Related to Approval of the Technical Support Center)
  • ML20095C690  + (Draft Sequoyah Nuclear Plant Integrated Containment Analysis, Technical Rept)
  • ML20128G797  + (Draft Ser,Pump & Valve Inservice Testing Program,Millstone Nuclear Power Station,Unit 1)
  • ML20128G780  + (Draft Ser,Pump & Valve Inservice Testing Program,Millstone Nuclear Power Station,Unit 1,for Second 10-Yr Interval)
  • ML20065S869  + (Draft Setpoint Calculation for RPS Turbine Control Valve Fast Closure Trip Function)
  • ML19102A322  + (Draft Shine Medical Technologies, Inc. - Conforming Amendment to Construction Permit No. CPMIF-001)
  • ML13221A393  + (Draft Shine Response to Proposed Action Request 5)
  • ML20073K864  + (Draft Site Characterization Analysis of the Site Characterization Report for the Basalt Waste Isolation Project.Main Report and Appendices a Through D)
  • ML20069J686  + (Draft Site Characterization Analysis of the Site Characterization Report for the Basalt Waste Isolation Project)
  • ML20073L030  + (Draft Site Characterization Analysis of the Site Characterization Report for the Basalt Waste Isolation Project.Appendices E-W)
  • ML19331C233  + (Draft Site Dependent Response Spectra)
  • ML20128C120  + (Draft Site Rept for Plant on 730424 & 25.Related Info Encl)
  • ML062770324  + (Draft Slide Presentation for Nrc/Entergy/Westinghouse Pre-Submittal Meeting (Non-Proprietary))
  • ML24100A070  + (Draft Slides for 04/30/2024 Meeting on Sufficiency Gaps Identified in EPRI Report 3002025288 on Enhanced Risk-Informed Categorization Methodology for Pressure Boundary Components)
  • ML23137A116  + (Draft Slides for Advisory Committee on Reactor Safeguards Subcommittee Meeting Regarding Use of Accident Tolerant Fuel Lead Test Assemblies)
  • ML23137A114  + (Draft Slides for Advisory Committee on Reactor Safeguards Subcommittee Meeting Regarding Use of Accident Tolerant Fuel Lead Test Assemblies)
  • ML23130A386  + (Draft Slides for Advisory Committee on Reactor Safeguards Subcommittee Meeting Regarding Use of Accident Tolerant Fuel Lead Test Assemblies (EPID L-2022-LLA-0097) (Letter))
  • ML15156B352  + (Draft Slides for Public Meeting with Arizona Public Service Company Ongoing Resolution of Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3)
  • ML22130A727  + (Draft Slides to ACRS Subcommittee on CCF Secy Paper Presentation, May 20, 2022)
  • ML20126G656  + (Draft Soil Decontamination Criteria for Decommissioning of United Nuclear Corp Resources Co Facility)
  • ML20148K421  + (Draft Sorv Procedure LOA-NB-02, Failure of Relief Valve to Seat Properly or Inadvertent Actuation of Safety Relief Valve)
  • ML20137Q316  + (Draft Sp 24.324.01 CTG-11-1 Monthly Operability Check)
  • ML19338F564  + (Draft Special Low Power Testing Procedure TP/1/A/2150/26, Simulated Loss of All Onsite & Offsite AC Power)
  • ML19338F557  + (Draft Special Low Power Testing procedure,TP/1/A/2150/20, Natural Circulation Verification)
  • ML19338F561  + (Draft Special Low Power Testing procedures,TP/1/A/2150/23, Natural Circulation W/Simulated Loss of Offsite Power)
  • ML19338F558  + (Draft Special Low Power Testing procedures,TP/1/A/2150/21, Effect of Steam Generator Isolation on Natural Circulation)
  • ML19320B665  + (Draft Specs, Functional Requirement for Safety Parameter Display Technical Support Ctr Emergency Offsite Facility Nuclear Data Link)
  • ML20044A815  + (Draft Speech Entitled State-Dependent Enforcement:Empirical Investigation Using Data from NRC, Presented at 891228 Meeting of American Economic Assoc)
  • ML20028C003  + (Draft Speech Entitled, Alternative Piping Break Criteria & Evaluations for SEP Plants, to Be Presented at ANS 1983 Annual Meeting on 830612-17)
  • ML19331D027  + (Draft Speech Regulatory Needs Which Might Be Met by Probabilistic Safety Analysis or Reliability Techniques, Presented at NRC 800128 Executive Seminar)
  • ML20214Q466  + (Draft Spent Fuel Storage Capacity Mod, SAR)
  • ML18038A082  + (Draft Sser Re Use of NCIG-01,Rev 2, Visual Weld Acceptance Criteria for Structural Welding.... Criteria Will Provide Adequate Quality of non-ASME Class Welded Structural Steel Weldments)
  • ML14058B072  + (Draft Staff Assessment for Review 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)
  • ML14113A555  + (Draft Staff Assessment of Seismic Walkdown Report Near-term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident; PPL Susquehanna, LLC; Susquehanna Steam Electric Station, Unit 1. Docket No. 50-387)
  • ML23066A327  + (Draft Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at Vogtle Plant Site Following NRC Process for Ongoing Assessment of Natural Hazards Information)
  • ML022400350  + (Draft Staff Criteria for Evaluating Licensee Inspection Plans)
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