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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
- ML20198P528 + (Rev 8 to MP 716.3, Feedwater Regulating Control Valve Maintenance)
- ML20203E177 + (Rev 8 to MP 745.2, Repair of Struthers Wells Feedwater Heat Exchanger)
- ML20059C647 + (Rev 8 to Maine Yankee Atomic Power Co Operational QA Program)
- ML20212P070 + (Rev 8 to Maint Procedure MP-121, Pump Repacking)
- ML20212P082 + (Rev 8 to Maint Procedure MP-509, Maint of Philadelphia Gear Drives on SWP-1A,1B & EFP-1)
- ML20212C948 + (Rev 8 to Maint Procedure Mpo 1410.32, Testing of Motor- Operated Valves Using Movats)
- ML20096F165 + (Rev 8 to McGuire Nuclear Station Selected Licensee Commitment Manual, Adding Clarity to Halon Sys Testing Requirements)
- ML20113C481 + (Rev 8 to McGuire Unit 2 Cycle 11 Colr)
- ML20215N370 + (Rev 8 to Mod & Additions Instruction M&AI-7, Cable Terminations,Splicing & Repairing of Damaged Cables)
- ML18005A348 + (Rev 8 to Mod Procedure MOD-103, Engineering Evaluations)
- ML20155C942 + (Rev 8 to N-UT-9, Ultrasonic Examination of Reactor Vessel Welds)
- ML20126D516 + (Rev 8 to N49720-SP666, Const Procedure for Drilled-In Expansion Type Anchors Seismic-I)
- ML20217R082 + (Rev 8 to NEDO-11209-04A, GE Nuclear Energy QA Program Description, Replacing Index)
- ML17056B983 + (Rev 8 to Nine Mile Point Nuclear Station Unit 1 Odcm)
- ML20137H325 + (Rev 8 to ODCM for Bfn)
- ML20056G007 + (Rev 8 to ODCM for Comanche Peak Steam Electric Station Ubits 1 & 2)
- ML20096H457 + (Rev 8 to ODCM for Comanche Peak Steam Electric Station, Units 1 & 2)
- ML20216B307 + (Rev 8 to ODCM for Haddam Neck Plant)
- ML20101E377 + (Rev 8 to OP-1903.066, Emergency Response Facility Osc)
- ML20151R092 + (Rev 8 to OP-C.13A, Remote Shutdown)
- ML20078Q567 + (Rev 8 to OPGP03-ZA-0090, Work Process Program)
- ML20078Q485 + (Rev 8 to OPMP02-ZG-0003, Insp & Maint for Cranes,Hoists, Monorail Sys & Lifting Devices)
- ML20107C302 + (Rev 8 to Odcm)
- ML20090B041 + (Rev 8 to Odcm)
- ML20059E650 + (Rev 8 to Odcm)
- ML20056G669 + (Rev 8 to Odcm)
- ML17056A967 + (Rev 8 to Odcm)
- ML20080G152 + (Rev 8 to Offsite Dose Calculation Manual)
- ML20090A906 + (Rev 8 to Offsite Dose Calculation Manual)
- ML20127M504 + (Rev 8 to Offsite Dose Calculation Manual)
- ML20237K067 + (Rev 8 to Offsite Dose Calculation Manual)
- ML20215C192 + (Rev 8 to Offsite Dose Calculation Manual)
- ML20212D800 + (Rev 8 to Offsite Dose Calculation Manual. Marked-up Rev 8 to Manual Encl)
- ML20082M299 + (Rev 8 to Operating Procedure 1104-28I, Waste Solidification Process Control Program)
- ML20083B236 + (Rev 8 to Operating Procedure AR-601, Tgf M Annunciator Response)
- ML20066H216 + (Rev 8 to Operations QA Plan)
- ML20065D382 + (Rev 8 to Operations QA Plan)
- ML20138K491 + (Rev 8 to Ort 72, Electrical Penetration Leak Test for Unit 1)
- ML20138K496 + (Rev 8 to Ort 73, Electrical Penetration Leak Test for Unit 1)
- ML20154Q337 + (Rev 8 to Oyster Creek Cycle 17,COLR)
- ML20070J797 + (Rev 8 to Oyster Creek Nuclear Generating Station Pump & Valve Inservice Testing Program)
- ML20211G238 + (Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm)
- ML20212A026 + (Rev 8 to Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual)
- ML20198K518 + (Rev 8 to Prerequisite Test Instruction XCP-ME-4, Sys Cleanliness Verification. Related Info Encl)
- ML17139D234 + (Rev 8 to Preservice Insp Rept 80A2804 for 1979-1983.Insp of Class 1,2 & 3 Components & Areas Described)
- ML20198A495 + (Rev 8 to Preventive Maint Procedure PMP 9.5-23, Preventive Maint of Reactor Trip & Isolation Breakers)
- ML20092H055 + (Rev 8 to Procedure 00653-C, Protected Area Entry/Exit Control)
- ML20237D691 + (Rev 8 to Procedure 1302.025, Spent Fuel Removal & Dry Storage Operations)
- ML20100J353 + (Rev 8 to Procedure 21.004.01, Main Control Room - Conduct of Personnel)
- ML20198J883 + (Rev 8 to Procedure 5000-ADM-7311.02 (EP-009), Design Verification)
- ML20090L769 + (Rev 8 to Procedure 7220-C-211(Q), Tech Specs for Backfill for Midland Plant,Units 1 & 2)
- ML20236N817 + (Rev 8 to Procedure 8.M.1-29, ATWS Functional & Trip Unit Calibr Test)
- ML20092H042 + (Rev 8 to Procedure 90015-C, Vehicle Access)
- ML20092G811 + (Rev 8 to Procedure 91704-C, Actions for Security During Radiological Emergency. Supporting Documentation Encl)
- ML17254A536 + (Rev 8 to Procedure A-25.4, Reactor Post-Trip Review)