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A list of all pages that have property "Title" with value "Justification Rept for Fisher Valves in EPRI Test Program". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML22167A159  + (June 8, 2022, Meeting Summary on Staffs Plan to Expand the Common Cause-Failure Policy for Digital Instrumentation and Controls Systems to Allow Consideration of Risk-Informed Alternatives to Staff Requirements Memo to SECY-93-087)
  • ML23171A047  + (June 8, 2023 Meeting Summary Public Meeting with the Uiuc to Discuss NRC Staffs Preliminary Questions on Uiuc Applicability of NRC Regulations Topical Report)
  • ML15121A057  + (June 9 - 12, 2014 Summary of Audit at Point Beach Nuclear Plant, Unit Nos. 1 and 2, Associated with License Amendment Request to Transition to National Fire Protection Association Standard 805)
  • ML20170A907  + (June 9 2020 Summary of Annual Meeting with the NRC and INPO-6-17-20)
  • ML101650169  + (June 9, 2010 Summary of Conference Call with Entergy on Proposed Response to Request for Additional Information on Generic Letter 2004-02)
  • ML15173A289  + (June 9, 2015, Summary of Category 1 Public Meeting with Arizona Public Service Company to Discuss Palo Verde Nuclear Generating Station Seismic Hazard Reevaluation Associated with Implementation of Japan Lessons-Learned NTTF Recommendation)
  • ML15217A541  + (June 9, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 5 Pertaining to the LaSalle County Station License Renewal Application)
  • ML21155A051  + (June 9, 2021 Public Meeting Presentation on Modernizing the Fuel Cycle and Materials Decommissioning Inspection Program)
  • ML21132A016  + (June 9, 2021, Notice of Public Meeting for Seabrook Station Unit 1)
  • ML25162A177  + (June 9, 2025, Summary of Public Meeting on Submittal of Nuclear Energy Institute (NEI) 05-05, Force-On-Force Exercise Controller Responsibilities Guideline, Revision 7)
  • ML081620529  + (June Exam 05000338-08301, 05000339-08-301 Approval Letter)
  • ML091760286  + (June Exam 05000424/2009301 and 05000425/2009301 Approval Letter 6-25-2009)
  • ML032471531  + (June Exam 50-269/2003-301 Draft JPMs & Outlines)
  • ML032471483  + (June Exam 50-269/2003-301 Draft Ro/Sro Written Exam & Outline)
  • ML032471475  + (June Exam 50-269/2003-301 Draft Simulator Scenarios & Outlines)
  • ML11167A105  + (June Hearing File Update)
  • ML091950304  + (June NPDES Discharge Monitoring Report)
  • ML25199A031  + (June NRC Statistics on Allegations)
  • ML20211E621  + (Juniata College Docket 7100885, 10CFR71 QA Program for Shipment of 239 Plutonium-Beryllium Neutron Sources)
  • ML20024C619  + (Just After Interuption)
  • ML22031A153  + (Justice Security Inspections During Periods of Site Inaccessibility)
  • ML22140A342  + (Justicej-hv-w20)
  • ML22145A270  + (Justicej-w20-bio)
  • ML20214K907  + (Justification & Background for Tech Spec Improvements)
  • ML18047A443  + (Justification Rept - Power Operated Relief Valve)
  • ML18047A456  + (Justification Rept for Fisher Valves in EPRI Test Program)
  • ML18047A447  + (Justification Rept of EPRI Testing of Crosby Style HB-BP-86 Pressurizer Safety Valves, Revision 1)
  • ML18047A449  + (Justification Rept of EPRI Testing of Crosby Style HPV-SN Power Operated Relief Valves, Revision 1)
  • ML18047A446  + (Justification Rept,Power Operated Relief Valves Supplied to PWR Plants, Revision 1)
  • ML25246C232  + (Justification Statements for Advisory Committees Cy 1979)
  • ML19209A551  + (Justification for 3-Man Fire Brigade)
  • 0CAN030504, Justification for ANO Exemption Request for Loading of Damaged Fuel  + (Justification for ANO Exemption Request for Loading of Damaged Fuel)
  • ML20238C307  + (Justification for Continued Operation)
  • ML17305B338  + (Justification for Continued Operation - Potential for Small Break Loss of Coolant Accident Due to Tube Rupture in Reactor Coolant Pump Seal Cooler)
  • ML20125A649  + (Justification for Continued Operation 2-91-1 Main Steam Line Break Inside Containment)
  • ML20212F079  + (Justification for Continued Operation for Exceeding Steady State Pressure Limit)
  • ML17304A221  + (Justification for Continued Operation of Auxiliary Feedwater Pumps)
  • ML13052A787  + (Justification for Continued Operation of Oconee Nuclear Station)
  • ML18093A413  + (Justification for Continued Operation of Salem Units 1 & 2 W/Outstanding Fire Protection Concerns)
  • ML18093A453  + (Justification for Continued Operation of Salem Units 1 & 2 W/Outstanding Fire Protection Concerns)
  • ML17304B294  + (Justification for Continued Operation,Control Element Assembly Drop Events)
  • RS-02-122, Justification for Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure & Temperature (P/T) Limits  + (Justification for Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure & Temperature (P/T) Limits)
  • ML19340E212  + (Justification for Criteria for Re-evaluation of Concrete Masonry Walls)
  • ML20049A684  + (Justification for Exemption:Central Valley Water Reclamation Facility Vicinity Property Existing Structures)
  • ML11187A324  + (Justification for Extension of Temper Bead Limit to 1000 Square Inches for WOL of P1 and P3 Materials)
  • ML19210A531  + (Justification for Increase in Max Allowable Reactor Protection Sys High Pressure Trip Setpoint, Prepared for Met Ed)
  • ML19332D838  + (Justification for Increasing Reactor Trip Sys On-Line Test Intervals)
  • ML20147G337  + (Justification for Long-Term Operation for Vermont Yankee Core Spray Nozzle Weld Overlays)
  • SBK-L-07138, Justification for Mitigation of Alloy 600/82/182 Pressurizer Butt Welds in 2008  + (Justification for Mitigation of Alloy 600/82/182 Pressurizer Butt Welds in 2008)
  • ML20207Q346  + (Justification for Multi-Cycle Operation for Vermont Yankee Core Spray Nozzle Weld Overlays)
  • ML20114E291  + (Justification for Nuclear Materials Relief Request Online Form)