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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
- ML20092H854 + (Rev 2 to 22336-C, Differential Pressure Switch)
- ML20151Y613 + (Rev 2 to 22A2537, Field Cleaning & Cleanliness of Nuclear Plant Components. Related Documentation Encl)
- ML20209E789 + (Rev 2 to 22S-110M-0063, Max Cladding Temp for Uncovered Spent Fuel Rod)
- ML20210G149 + (Rev 2 to 237.1(B), Electrical Protection Design,Thermal Overload Bypass & Indication Problems, Employee Concerns Special Program Rept)
- ML17277B733 + (Rev 2 to 23A1900AA, RHR Sys)
- ML20236T197 + (Rev 2 to 24A5412, Supplemental Reload Licensing Rept for Brunswick Steam Electric Plant Unit 2 Reload 12 Cycle 13)
- ML20248C508 + (Rev 2 to 24A5416, Supplemental Reload Licensing Rept for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20)
- ML20116K305 + (Rev 2 to 250 Vdc Battery 1D550 - Battery & Battery Charger Sizing Calculation)
- ML18040A162 + (Rev 2 to 25A5583, Shroud Repair Hardware)
- ML20096F409 + (Rev 2 to 25A5764, Panda Test Plan - Tests M3,M3A,M3B,M4 & M7)
- ML18037A961 + (Rev 2 to 3-STM-001,plant Startup Test Manual)
- ML20106J260 + (Rev 2 to 3C10-1082-002, Implementation of BWR Emergency Procedure Guidelines Into Specific Emergency Procedures)
- ML20151Z901 + (Rev 2 to 5AWI 6.1.0, Design Change General)
- ML20198B974 + (Rev 2 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual)
- ML20140D377 + (Rev 2 to 80A4427, Preservice Insp Program Plan:Main Steam Sys)
- ML20140D391 + (Rev 2 to 80A4428, Preservice Insp Program Plan:Reactor Recirculation Sys)
- ML20140D411 + (Rev 2 to 80A4430, Preservice Insp Program Plan:Crd Sys)
- ML20207L991 + (Rev 2 to 80A7616, Ultrasonic Exam Procedure for Reactor Vessel Feedwater Nozzle Inner Radius for Vermont Yankee)
- ML20196A866 + (Rev 2 to 80A8610, Inservice Insp Program Plan,Main Steam Sys,Shoreham Nuclear Power Plant Unit 1. W/One Oversize Drawing)
- ML20196A877 + (Rev 2 to 80A8611, Inservice Insp Program Plan,Feedwater Sys,Shoreham Nuclear Power Plant Unit 1)
- ML20196A918 + (Rev 2 to 80A8615, Inservice Insp Program Plan,Hpci Sys, Shoreham Nuclear Power Plant Unit 1. W/Two Oversize Drawings)
- ML20196A936 + (Rev 2 to 80A8617, Inservice Insp Program Plan,Standby Liquid Control Sys,Shoreham Nuclear Power Plant Unit 1)
- ML20196A947 + (Rev 2 to 80A8618, Inservice Insp Program Plan,Rwcu Sys, Shoreham Nuclear Power Plant Unit 1)
- ML20196A960 + (Rev 2 to 80A8619, Inservice Insp Program Plan,Crd Sys, Shoreham Nuclear Power Plant Unit 1)
- ML20210P216 + (Rev 2 to 81A1050, QA Program Plan for Transport Casks)
- ML20076G067 + (Rev 2 to 8301-PIP-1-Q, Procedure for Project Interface Control)
- ML20076G094 + (Rev 2 to 8301-WTP-1-Q, Procedure for Documentation of Postulated Interactions)
- ML20076G106 + (Rev 2 to 8301-WTP-2-Q, Procedure for Training of Ssip/S Walkdown Team Members)
- ML20076G121 + (Rev 2 to 8301-WTP-3-Q, Procedure for Performing Walkdowns of Ssip/S Targets)
- ML20140A399 + (Rev 2 to 840928 Application for SNM License,Updating Section 3.3, Other Matl Requiring NRC License, to Include Addl Monitor Check & Bias Sources)
- ML20210K765 + (Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca)
- ML20235W672 + (Rev 2 to 861222 Application for Rev to Certificate of Compliance 9019,demonstrating Model BU-7 Compliance W/ 10CFR71 Requirements.Rev Consists of Replacement Pages 15-21 to Original Submittal)
- ML20149E035 + (Rev 2 to 870814 Application for Amends to Licenses DPR-42 & DPR-62,revising Tech Specs Re Plant Organization & Requirements for Senior Reactor Operator Requirements for Mgt & Support Staff)
- ML20246B622 + (Rev 2 to 9300-ADM-4010.03, Oyster Creek Emergency Dose Calculation Manual)
- ML20091K673 + (Rev 2 to 940608 LAR to License DPR-22,re Section 3.7/4.7, SGTS)
- ML20210P312 + (Rev 2 to 96-R-2015-02, ANO-2 COLR for Cycle 13)
- ML20205L839 + (Rev 2 to 960103, Neutronics Licensing Rept for LaSalle Unit 2,Cycle 8)
- ML20203D665 + (Rev 2 to 970044, Operating Limits Rept (Olr) for Braidwood Unit 1 Cycle 7)
- ML17251A352 + (Rev 2 to A-502.1, Emergency & Abnormal Operating Procedures Writers Guide)
- ML20066H260 + (Rev 2 to A120.0021/S236, Signature/Initials Log)
- ML20077R918 + (Rev 2 to ABWR Design Control Document)
- ML20211D252 + (Rev 2 to AES 97043057-1-1, Probabilistic Operational Assessment of SG Tube Degradation at Songs,Unit 2,for Cycle 9)
- ML20092C626 + (Rev 2 to ALARA Program Instruction 1, General Program Instruction for Maintaining Occupational Exposure to Radiation Alara)
- ML20092C633 + (Rev 2 to ALARA Program Instruction 2, Specific Program Instruction for Maintaining Occupational Exposure to Radiation Alara)
- ML20096F386 + (Rev 2 to ALPHA-410, Panda Steady-State Tests Pcc Performance Test Plan & Procedures)
- ML20096F421 + (Rev 2 to ALPHA-520, Panda Transient Tests M3A,M3B & M4 Integral Sys Test Procedure)
- ML20033F101 + (Rev 2 to AP-250, Radiation Monitor Actuation)
- ML20202B157 + (Rev 2 to AP-430, Loss of Control Room Alarms)
- ML20196F724 + (Rev 2 to AP-510, Rapid Power Reduction)
- ML20199C049 + (Rev 2 to AP-604, Waterbox Tube Failure)
- ML17261A988 + (Rev 2 to AP-RHR.2, Loss of RHR While Operating at RCS Reduced Inventory Conditions)