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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
- ML11241A137 + (NRR Operating Experience Community Forum Posting, EDG Ventilation Fan Nose Cone Corrosion Results in Fan Damage)
- ML24276A187 + (NRR Operating Reactor Licensing Project Manager Qualification for Jeffery D. Smith - Certificate)
- ML17242A287 + (NRR Organization Chart Effective 990328)
- ML081780732 + (NRR Oyster Creek Generating Station License Renewal 06-2008)
- ML031400649 + (NRR Peer Review of Preliminary ASP Analysis of November 2001 Operational Condition at Point Beach, Units 1 & 2)
- ML18141A393 + (NRR Perspectives on Probabilistic Fracture Mechanics Calculations)
- IR 05000315/2014005 + (NRR Position on NCV 05000315/2014005-03; 05000316/2014005-003 Radiological Impact of the Removal of the Auxiliary Shield Blocks on the Containment Accident Shield Post LBLOCA)
- ML25066A001 + (NRR Priorities March 10th Slides Final)
- ML18275A164 + (NRR RIDM Action Plan - September 14, 2018 - Public Meeting Presentation)
- ML19219A070 + (NRR Released Set Part 1_NRC-2017-000292 (Interim 2))
- ML19219A072 + (NRR Released Set Part 2_NRC-2017-000292 (Interim 2))
- ML19219A073 + (NRR Released Set Part 3_NRC-2017-000292 (Interim 2))
- ML19219A074 + (NRR Released Set Part 4_NRC-2017-000292 (Interim 2))
- ML20143A274 + (NRR Response - Safety Evaluation of the NuScale Power, Chapter 15, Transient and Accident Analysis - Open Item Closure and Area of Focus Reviews - Return to Criticality and Boron Distribution)
- ML20154K622 + (NRR Response to ACRS Report on the Safety Aspects of the Subsequent License Renewal Application for Surry Power Station, Units 1 and 2)
- ML102670535 + (NRR Response to NEI Proposed Alternative to ECCS Performance Generic Letter)
- ML18116A023 + (NRR Risk Informed Decision Making (RIDM) Action Plan - April Revision)
- PMNS20180853, NRR Risk-Informed Decision-Making Action Plan + (NRR Risk-Informed Decision-Making Action Plan)
- ML080370428 + (NRR Staff Comments on TMI-1 GL 2004-02 Supplemental Response)
- ML25240B529 + (NRR Staff Slides - Seabrook Alkali-Silica Reaction - ACRS Fc - September 3, 2025)
- ML20116M956 + (NRR Technical Newsletter.Volume 1,Number 4)
- ML20116M959 + (NRR Technical Newsletter.Volume 1,Number 5)
- ML20116M962 + (NRR Technical Newsletter.Volume 1,Number 6)
- ML20116M888 + (NRR Technical Newsletter.Volume 2,Number 1)
- ML20116M889 + (NRR Technical Newsletter.Volume 2,Number 2)
- ML20081K729 + (NRR Technical Newsletter.Volume 2,Number 3)
- ML20096D591 + (NRR Technical Newsletter.Volume 3,Number 1)
- ML20096D588 + (NRR Technical Newsletter.Volume 4,Number 1)
- ML20116H318 + (NRR Technical Newsletter.Volume 4,Number 2)
- ML20063M282 + (NRR Technical Newsletter.Volume 6,Number 1)
- ML20073D405 + (NRR Technical Newsletter.Volume 6,Number 2)
- ML20092J126 + (NRR Temporary Staff Guidance Exemptions from NRC Part 26 Regulations)
- ML043020494 + (NRR Work Request to IEPB-A)
- ML043020499 + (NRR Work Request to SPSB-C)
- ML15272A676 + (NRR e-mail Capture - Correction to Millstone Power Station Unit 3, Safety Evaluation, Amendment No. 262 RWST Temperature Change)
- ML15279A109 + (NRR e-mail Capture - Millstone Power Station, Unit 3, NRC Staff Request for Additional Information - Relief Request Nos. IR-3-19,3-20,3-21)
- ML060750143 + (NRR, Potential Vulnerabilities Discovered During Design Basis Fire Review at Wolf Creek, Unit 1)
- ML20338A262 + (NRR-106 University of California Davis License Renewal - Regulatory Audit Letter and Plan)
- ML20338A261 + (NRR-106 University of California Davis License Renewal - Audit Questions)
- ML050830452 + (NRR-2004-A-0026, Allegations Review Board Briefing and Meeting Summary Sheet)
- ML050830461 + (NRR-2004-A-0026, Open Case Chronology Sheet)
- ML19289D291 + (NRR-COM-106 Revitalization (October 17, 2019))
- ML12135A301 + (NSA-TR-09-14, Rev. 2, Nuclear Criticality Safety Assessment of the Us Ecology Idaho (Usei) Site for the Land Fill Disposal of Decommissioning Waste from the Hematite Site. NSA-TR-09-14. December 2011)
- ML22195A159 + (NSAL-06-6 LOCA Mass and Energy Release Analysis)
- ML22195A177 + (NSAL-14-2: Westinghouse Loss-of-Coolant Accident Mass and Energy Release Calculation Issue for Steam Generator Tube Material Properties)
- ML15105A346 + (NSAL-15-2 - Impact of a Break in the Reactor Coolant Pump No. 1 Seal Leak-off Line Piping on Seal Leakage During a Loss of Seal Cooling Event)
- ML24092A088 + (NSC Support to Standards Organizations and Preparations for Future Reactors - H. Mazhar Slides)
- ML20262F564 + (NSCW Chlorine Bldg HVAC System Air Flow Diagrams & P&ID System 1599)
- ML20349H436 + (NSCW Cooling Towers 1A & 1B General Arrangement Plan Elevation & Sections)
- ML20265E208 + (NSCW Cooling Towers 1A & 1B General Arrangement Plan Elevation & Sections)
- ML20265B982 + (NSCW Cooling Towers 1A & 1B General Arrangement Plan, Elevation & Sections)