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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

• ML20217M600  + (Reliability Study: HIGH-PRESSURE Coolant Injection System, 1987-1993)
• ML20217M564  + (Reliability Study: High-Pressure Core Spray System, 1987- 1993)
• ML20217M873  + (Reliability Study: Isolation Condenser System, 1987-1993)
• ML20217M550  + (Reliability Study: Reactor Core Isolation Cooling System, 1987-1993)
• ML20205N754  + (Reliability Study: Westinghouse Reactor Protection System, 1984-1995)
• ML20151A581  + (Reliability Summary Rept for Bailey 862 Solid State Logic Module)
• ML20024C856  + (Reliability Sys Engineering Program Plan Safety Assurance & Failure Elimination, Draft Rept of Differing Prof Opinion)
• ML16284A011  + (Reliability and Diversity)
• ML20204G902  + (Reliability and Risk Analysis Methods Research Plan)
• ML20084N941  + (Reliability of AC Power at Grand Gulf Nuclear Station, Interim Assessment Rept)
• Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications  + (Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications)
• Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications  + (Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications)
• ML20085E207  + (Reliability of Emergency AC Power System at Nuclear Power Plants)
• ML16245A086  + (Reliability of Emergency AC Power at Nuclear Power Plants)
• ML20082R270  + (Reliability of Geotechnical,Environmental and Radiological Instrumentation in Nuclear Waste Repository Studies)
• Information Notice 1986-56, Reliability of Main Steam Safety Valves  + (Reliability of Main Steam Safety Valves)
• ML031220716  + (Reliability of Main Steam Safety Valves)
• ML20086C352  + (Reliability of Nondestructive Examination.Chapters 1-6)
• ML20086C344  + (Reliability of Nondestructive Examination.Chapters 12-15)
• ML20086C359  + (Reliability of Nondestructive Examination.Chapters 7-11)
• 05000298/FIN-2007008-03  + (Reliance On Unapproved Manual Actions)
• 05000298/FIN-2007008-04  + (Reliance On Unapproved Manual Actions)
• 05000327/FIN-2005011-01  + (Reliance on 20-foot Separation Zones for Fire Protection in Unit 1 480V Board Room 1B)
• 05000327/FIN-2005011-05  + (Reliance on Local Manual Operator Actions for Appendix R Fires)
• ML022800336  + (Reliant Energy, Leak Test Certificates Missing as Enclosures to Ltr Dtd 09/30/2002)

• ML063550348  + (Relicensing)

• ML11290A231  + (Relicensing - Indian Point Nuclear Generating Station F/NER/200900619)
• ML023380455  + (Relicensing Report for the Reactor Critical Facility at Rensselaer Polytechnic Institute)
• ML19196A064  + (Relied Request ISIR-4-10 Regarding Fourth Inservice Inspection Program Interval)
• ML12109A249  + (Relief (Alternative) Request 12 Concerning the Fourth 10-Year Inservice Testing Program)
• ML030700021  + (Relief ,Third 10-Year Interval Inservice Inspection Program Plan Relief RR-29 and RR-30 for Brunswick Units 1 & 2)
• ML020250222  + (Relief - Inservice Inspection Program Relief Request 2IR-13 (Tac No. MB1800))
• ML091240156  + (Relief 06-CN-003 for Use of Polyethylene Material in Buried Service Water Piping)
• ML082240386  + (Relief 06-CN-003, Use of Polyethylene Material in Nuclear Safety-Related Piping Applications)
• ML092570541  + (Relief 08-CN-001 Regarding Third 10-Year Interval Inservice Inspection)
• ML092530620  + (Relief 08-MN-005, for Control Rod Drive Mechanism (CRDM) Canopy Seal Welds)
• ML092300045  + (Relief 09-CN-002 Regarding Weld Buildup on Reactor Vessel Hot Leg Nozzles)
• ML110800426  + (Relief 09-MN-002, Revision 1, for a Proposed Alternative to Delay the Update to the Code of Record for the Fourth 10-Year Inservice Inspection (ISI) Interval)
• ML101580422  + (Relief 09-MN-005 for Alternative Leakage Testing for Various American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Class 1 Piping and Components During the Third 10-Year Inservice)
• ML100620018  + (Relief 09-MN-007 for Reactor Vessel Core Flood Nozzle Weld Examinations During the Third 10-Year Inservice Inspection)
• ML11187A001  + (Relief 10-CN-001, Alternative Requirements for Temporary Acceptance of a Through-Wall Flaw in Boric Acid Tank Nozzle Weld)
• ML110550770  + (Relief 10-MN-001 for a Proposed Alternative to to Delay the Update to the Code of Record During the Fourth 10-Year Inservice Inspection (ISI) Interval)
• ML11160A144  + (Relief 10-MN-002, Extension of Volumetric Inspection of Steam Generator Primary Manway Studs for One Operating Cycle Beyond the Third 10-Year Inservice Inspection Interval End Date)
• ML21293A096  + (Relief ANO2-R&R-012 Concerning Proposed Alternative for Repair of Reactor Vessel Closure Head Penetration 46)
• ML030150218  + (Relief ASME Boiler & Pressure Vessel Code Concerning Inservice Inspection Program Reactor Pressure Vessel Examination)
• ML020720229  + (Relief Code, Relief Request for Alternate ASME Code, Section XI, Risk-Informed Inservice Inspection Program)
• ML060970124  + (Relief E-2, 4-th 10-year Pump and Valve Inservice Testing Program)
• ML033440009  + (Relief Inservice Testing Program Relief Request PR-3)
• ML070160009  + (Relief Letter 2007-01-08)
• ML18346A314  + (Relief Nos. ANO1-ISI-027, -028, -029, -030, and -031 from ASME Code, Section XI, Examination Requirements for Fourth 10-Year Inservice Inspection Interval (EPID L-2018-LLR-0063, -0064, -0065, -0066, -0067))
• ML18122A152  + (Relief RR-RBS-ISI-015 from the Requirements of the ASME Code Regarding Reactor Vessel Weld Inspections)