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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

• ML030760715  + (Reactor Pressure Vessel Head Replacement Reconciliation Inspection)
• 05000348/LER-2003-002, Reactor Pressure Vessel Head Set in Place with Technical Specification 3.4.12 Not Met  + (Reactor Pressure Vessel Head Set in Place with Technical Specification 3.4.12 Not Met)
• ML12138A135  + (Reactor Pressure Vessel Head Weld Flaw Evaluation - Response to NRC Request for Additional Information)
• ML12342A323  + (Reactor Pressure Vessel Head Weld Flaw Evaluation - Clarification Regarding Subsequent Examination of the Weld Flaw Indication)
• ML020700711  + (Reactor Pressure Vessel Head at Davis Besse Nuclear Power Station)
• ML22096A006  + (Reactor Pressure Vessel Inservice Inspection Requirements in the U.S)
• ML16274A227  + (Reactor Pressure Vessel Integrity)
• ML17138B779  + (Reactor Pressure Vessel Internals Vibration Test)
• ML040920397  + (Reactor Pressure Vessel Lower Head Penetration Inspection Results)
• RS-17-014, Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11  + (Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11)
• ML20092N287  + (Reactor Pressure Vessel Preservice Insp Program Plan)
• ML20197B424  + (Reactor Pressure Vessel Preservice Ultrasonic Exam Limitations at Sequoyah Nuclear Plant,Unit 1, Supplemental Rept)
• ML20197B430  + (Reactor Pressure Vessel Preservice Ultrasonic Exam Limitations at Sequoyah Nuclear Plant,Unit 2, Supplemental Rept)
• ML20262E108  + (Reactor Pressure Vessel Rollout Id)
• ML20262E114  + (Reactor Pressure Vessel Rollout Id. No Rev Date)
• BSEP 11-0037, Reactor Pressure Vessel Shell-to-Flange Weld Analytical Evaluation  + (Reactor Pressure Vessel Shell-to-Flange Weld Analytical Evaluation)
• ML20149L826  + (Reactor Pressure Vessel Status Report)
• ML20079A134  + (Reactor Pressure Vessel Status Report)
• ML19330B488  + (Reactor Pressure Vessel Support Mod for Midland Nuclear Power Plant, Preliminary Rept 1)
• ML13032A251  + (Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment)
• ML20235H690  + (Reactor Pressure Vessel Surveillance Matls Testing & Fracture Toughness Analysis, Technical Rept)
• ML20062J404  + (Reactor Pressure Vessel Surveillance Program:Capsule Basket 2,Capsule Basket 3 & Neutron Dosimeter Monitor)
• ML20062J407  + (Reactor Pressure Vessel Surveillance Program:Capsule Basket 12 & Capsule Basket 13)
• L-89-098, Reactor Pressure Vessel Temp Limits Determination  + (Reactor Pressure Vessel Temp Limits Determination)
• ML050140187  + (Reactor Pressure Vessel Upper and Lower Head Inspection Results)

• TSTF-542  + (Reactor Pressure Vessel Water Inventory Control)

• ML20093G910  + (Reactor Pressure Vessel Water Level Measurement Sys Evaluation Rept,Interim Closure Rept)
• ML20101E688  + (Reactor Pressure Vessel Water Level Measurement Sys Evaluation Rept)
• 05000335/FIN-2011005-01  + (Reactor Pressure Vessel supports not included in the St. Lucie ISI Program)
• ML20059J209  + (Reactor Primary Containment Bldg Ilrt,Byron Nuclear Station Unit 2,930909-10)
• ML20080L436  + (Reactor Primary Containment Bldg Integrated Leak Rate Test, 830629-0703)
• ML20064N280  + (Reactor Primary Containment Integrated Leak Rate Test LaSalle County Nuclear Power Station)
• ML19261A281  + (Reactor Primary Coolant Sys Pipe Rupture Study Method for Detection of Sensitization in Stainless Steel, Rept 43 Jan-Mar 1978)
• ML19254A794  + (Reactor Primary Coolant Sys Pipe Rupture Study Method for Detection of Sensitization in Stainless Steel, Progress Rept 46,Oct-Dec 1978)
• ML19246C215  + (Reactor Primary Coolant Sys Pipe Rupture Study Method for Detection of Sensitization in Stainless Steel, Progress Rept 42,Oct-Dec 1977)
• ML19289E394  + (Reactor Primary Coolant Sys Pipe Rupture Study Method for Detection of Sensitization in Stainless Steel, Monthly Progress Ltr,Jan 1979)
• ML19261B401  + (Reactor Primary Coolant Sys Pipe Rupture Study,Method for Detection of Sensitization in Stainless Steel. Monthly Progress Ltr for Nov 1978.Discusses Stringer Weld Study)
• ML19274D239  + (Reactor Primary Coolant Sys Pipe Rupture Study Method for Detection of Sensitization in Stainless Steel, Progress Rept 44,Apr-June l978)
• ML20266D982  + (Reactor Primary Shielding & Penetrations Plan & Sections Containment)
• ML20266F422  + (Reactor Primary Shielding and Penetrations Plan & Sections Containment)
• ML19338B843  + (Reactor Primary Sys Behavior from Four to Twenty Hundred. Repts Re Core Damage Encl)
• ML23304A067  + (Reactor Program System (RPS) Privacy Impact Assessment (Pia))
• ML17329A717  + (Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 TS Compliance Assessment)
• ML17329A720  + (Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Reactor Protection Sys Functional Diversity Assessment)
• ML17329A706  + (Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Spec 200/SPEC 200 Micro Hardware & Firmware Sys Description)
• ML17329A718  + (Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plants Units 1 & 2 Qualification Compliance)
• ML17331B169  + (Reactor Protection & Control Process Instrumentation Replacement Project at Donald C Cook Nuclear Plant Units 1 & 2,Reactor Protection Sys Functional Diversity Assessment)
• ML17329A715  + (Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Functional Requirement Summary)
• ML17329A719  + (Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Test Program Summary)
• ENS 49296  + (Reactor Protection Actuation (Scram))
• ENS 48664  + (Reactor Protection Actuation (Scram) - Recirculation Pump Trip)