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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

• EPID:L-2021-NFN-0003  + (RIPE Exemption 11-17-21 Pre-submittal Public Meeting Presentation Slides)
• ML21245A421  + (RIPE Exemption to Eliminate Dafas Pre-submittal Meeting Summary)
• EPID:L-2021-LRM-0087  + (RIPE Exemption to Eliminate Dafas Pre-submittal Meeting Summary)
• NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information  + (RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information)
• NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions  + (RIPE License Amendment Request to Change Containment Air Temperature Actions)
• ML24113A096  + (RIPE Pre-Submittal Meeting Slides)
• ML20338A269  + (RIPE Presentation)
• ML20118C188  + (RIPE Presentation for Public Meeting May 2020)
• ML25216A237  + (RIPE Workshop - Session 1 RIPE Training (1))
• ML25216A236  + (RIPE Workshop - Sessions 3 Updated with Grip)
• ML25216A244  + (RIPE Workshop Slides - Diablo Canyon Updated)
• ML19056A528  + (RIS2002-22S1 NRC Public Mtg Presentation, Rev 0)
• ML21172A234  + (RISC - June 2021 - Rev.1)
• ML20338A270  + (RISC Presentations)
• ML18053A105  + (RISC Public Meeting February 20, 2018)
• ML18131A298  + (RISC Public Meeting May 3, 2018)
• ML20042D110  + (RISC- Crediting FLEX Feb 2020 Rev1)
• ML20056E213  + (RISK-BASED INSPECTION-DEVELOPMENT of Guidelines.Light Water Reactor (LWR) Nuclear Power Plant Components)
• ML20094L494  + (RISK-BASED Inspection - Development of Guidelines.General Document)
• ML20079D328  + (RISK-BASED Inspection Guide for Crystal River Unit 3 Nuclear Power Plant)
• ML20034G902  + (RISK-BASED Inspection Guide for Three Mile Island Nuclear Station Unit 1)
• ML20098B331  + (RISK-BASED Maintenance Modeling.Prioritization of Maintenance Importances and Quantification of Maintenance Effectiveness)
• ML20116J450  + (RISK-BASED Technical Specifications: Development and Application of an Approach to the Generation of a Plant Specific REAL-TIME Risk Model.Appendices)
• ML20116J134  + (RISK-BASED Technical Specifications: Development and Application of an Approach to the Generation of a Plant Specific REAL-TIME Risk Model.Main Report)
• TSTF-498  + (RISK-INFORMED Containment Isolation Valve Completion Times (BAW-2461))

• TSTF-424  + (RISK-INFORMED HPSI Aot/Ct Extension - WCAP-15773)

• ML17233A327  + (RITF Attendee List)
• ML18317A171  + (RITF Meeting Presentation 31 Oct 18)
• ML19056A582  + (RITF Public Meeting Attendee List)
• ML19291D437  + (RITF Public Meeting Talking Points on Regulatory Guide Reviews (October 17, 2019))
• ML062020402  + (RITSTF Meeting of June 29, 2006 - Risk Management Technical Specification Initiative Status Enclosure 4)
• ML12306A075  + (RIV-2006-A-0033 - Callaway)
• ML15161A207  + (RIV000142 - Supplemental Prefiled Written Testimony of Dr. Joram Hopenfeld Regarding Contention NYS-26B/RK-TC-1B)
• ML15161A208  + (RIV000143 - Supplemental Prefiled Written Testimony of Dr. Joram Hopenfeld Regarding Contention NYS-38/RK-TC-5)
• ML15161A209  + (RIV000144 - Supplemental Report of Dr. Joram Hopenfeld in Support of Contention NYS-26B/RK-TC-1B and Amended Contention NYS-38/RK-TC-5 (Public/Redacted))
• ML15161A214  + (RIV000149 - Material Aging Institute International Conference on Plants Materials Degradations, Chemical Conditioning of Light Water Reactor Systems (2008), IPEC00265853)
• ML15161A215  + (RIV000150 - Anl, Report on Assessment of Environmentally-Assisted Fatigue for LWR Extended Service Conditions, ANL-LWRS-47 (September 2011))
• ML15161A217  + (RIV000152 - G. E. Korth & M. D. Harper, Effects of Neutron Radiation on the Fatigue and Creep/Fatigue Behavior of Type 308 Stainless Steel Weld Metal at Elevated Temperatures (Seventh ASTM International Symposium on Effects of Radiation on)
• ML15161A219  + (RIV000153 - Argonne National Laboratory, Corrosion and Mechanics of Materials, Light Water Reactors, Irradiation-Induced Stress Corrosion Cracking of Austenitic Stainless Steels)
• ML15161A220  + (RIV000154 - S. Mohanty, S. Majumdar, & K. Natesan, Argonne National Laboratory, a Review of Stress Corrosion Cracking/Fatigue Modeling for Light Water Reactor Cooling System Components (June 2012))
• ML15161A221  + (RIV000155 - S. Mckelvey & A. Fatemi, Effect of Forging Surface on Fatigue Behavior of Steels: a Literature Review (University of Toledo))
• ML15161A223  + (RIV000158 - Herve Bodineau & Thierry Sollier, Tube Support Plate Clogging Up of French PWR Steam Generators, Eurosafe, Irsn - Reactor Safety Division, BP17 (2009))
• ML15161A224  + (RIV000159 - NUREG/BR-0058, Rev.4, Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission (2004), Available at http://www.nrc.gov/reading-rm/doc-collections/nuregs/brochures/br0058/br0058r4)
• ML15161A225  + (RIV000160 - U.S. NRC, Commissioner Apostolakis, Application of Risk Assessment and Management to Nuclear Safety (DOE Nuclear Safety Workshop, September 2012), Available at, http://energy.gov/sites/prod/files/2013/12/f5/Apostolakis)
• ML15252A509  + (RIV000164 - NUREG-1740, ACRS, Voltage-Based Alternative Repair Criteria: a Report to the Advisory Committee on Reactor Safeguards by the Ad Hoc Subcommittee on a Differing Professional Opinion (2001))
• IR 05000458/2015405  + (RIVER BEND STATION - NRC TEMPORARY INSTRUCTION 2201/004, "INSPECTION OF IMPLEMENTATION OF INTERIM CYBER SECURITY MILESTONES 1-7," INSPECTION REPORT 05000458/2015405)
• ML15161A226  + (RIVR12001 - Riverkeeper Updated Exhibit List)
• ML15252A511  + (RIVR13001 - Riverkeeper Updated Exhibit List)
• ML15309A171  + (RIVR14001 - Riverkeeper Tailored Track 2 Exhibit List)
• ML12219A403  + (RL-SO RG 1.73 Rev. 0 Vs. DG-1235)
• ML20041E540  + (RLPORINC-THE RELAP4/MOD5 Interface to Orinc)