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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
- ML20137T671 + (Rev 3 to Environ Qualification Summary Rept for Hope Creek Generating Station)
- ML17262A356 + (Rev 3 to Eop/Ap Attachment)
- ML20093K308 + (Rev 3 to Evaluation of Containment Coatings)
- ML18102B019 + (Rev 3 to Evaluation of Containment Structure for Latest Temp Loads)
- ML18064A578 + (Rev 3 to Evaluation of Palisades Current PTS Screenin Criteria Margin)
- ML20153F934 + (Rev 3 to FEP-2.0, Train a Plant Shutdown to Hot Standby Due to Fire)
- ML20153F969 + (Rev 3 to FEP-3.1, Train B Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire)
- ML20150C220 + (Rev 3 to FNP-0-M-011, Offsite Dose Calculation Manual)
- ML20248H881 + (Rev 3 to FNP-1-M-042 Re Second 10-yr Interval Inservice Testing Program for ASME Code Class 1,2 & 3 Pumps & Valves)
- ML20058Q154 + (Rev 3 to FNP-1-M-043, Jm Farley Nuclear Plant Unit 1 Second 10-Yr Inservice Insp Program,Asme Code Class 1,2 & 3 Components)
- ML17250B132 + (Rev 3 to FR-I.2, Response to Low Pressurizer Level)
- ML17250B134 + (Rev 3 to FR-I.3, Response to Voids in Reactor Vessel)
- ML20205R408 + (Rev 3 to Failure Analysis & Structural Integrity Evaluation of Leaking Small Bore Aluminum-Bronze Cast Valve Bodies & Fittings in Essential Cooling Water Sys)
- ML20082Q681 + (Rev 3 to Final Deficiency Rept DER 82-78 Re Improperly Crimped Termination Lugs in Control Panels for Water Chillers Supplied by Carrier.Condition Corrected Via Subj Design Change Packages.Also Reportable Under Part 21)
- ML20244B334 + (Rev 3 to Final Design Description of ATWS Mitigation Sys Actuation Circuitry)
- ML20205P777 + (Rev 3 to Final Part 21 & Deficiency Rept DER 82-46 Re Itt Barton Pressure Transmitters Supplied by C-E That Do Not Meet Overpressure Requirements.Rev Updates & Clarifies Info Re Description of Deficiency & Corrective Actions)
- ML20095D310 + (Rev 3 to Final Rept Overhead Handling Sys Review)
- ML20064F508 + (Rev 3 to Final Rept to NRC for IE Bulletin 79-14 Requirements at TMI-1)
- ML20133K488 + (Rev 3 to Findings,Corrective Actions & Generic Implications Rept, Toledo Edison - Main Steam Header Pressure)
- ML18038A485 + (Rev 3 to First 10-Yr ISI Program Plan. W/910930 Ltr)
- ML20237J990 + (Rev 3 to First 10-yr Interval Augmented Inservice Insp Program)
- ML20237J840 + (Rev 3 to First 10-yr Interval Inservice Insp Program)
- ML20205C946 + (Rev 3 to Fitzpatrick Emergency Procedure Guidelines)
- ML20091P401 + (Rev 3 to Fort Calhoun Station ISI Program Plan Third Ten-Yr Interval 1993-2003)
- ML20237C029 + (Rev 3 to Fort Calhoun Station,Unit 1,Inservice Insp Program Plan for 1983-1993 Interval)
- ML20235B910 + (Rev 3 to Framatome QA Program)
- ML20237H532 + (Rev 3 to Function Restoration Guidelines FR-0, Status Trees)
- ML20207H797 + (Rev 3 to Functional Test Procedures & Results for Isolation Boards Used in Vogtle 1 & 2)
- ML20084A034 + (Rev 3 to GGNS COLR Sr)
- ML20206T388 + (Rev 3 to General Instructions for Cable Tray Hanger Analysis for Comanche Peak Steam Electric Station 1 & 2)
- ML20212A219 + (Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2)
- ML20117H133 + (Rev 3 to Grand Gulf Nuclear Station ISI for 10-Yr Program)
- ML20212M735 + (Rev 3 to Grand Gulf Unit 1 Cycle 2 Plant Transient Analysis)
- ML20212M732 + (Rev 3 to Grand Gulf Unit 1 Cycle 2 Reload Analysis)
- ML20073D134 + (Rev 3 to H10.1, ASME Section XI Inservice Testing Implementing Program)
- ML18058B787 + (Rev 3 to HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment)
- ML20207K239 + (Rev 3 to HTRG-85-001, Licensing Plan for Std Htgr)
- ML20212N811 + (Rev 3 to Habitability of LaSalle County Station Control Room Following Postulated Accident Involving Shipments of Anhydrous Ammonia in Vicinity of LaSalle County Station)
- ML20211N356 + (Rev 3 to Hardware Validation Program. Supporting Documentation Encl)
- ML20195H010 + (Rev 3 to Hatch 9X9 Lead Fuel Assemblies Sar)
- ML20207P604 + (Rev 3 to Health Physics Facilities,Clothing & Protective Equipment)
- ML20214N922 + (Rev 3 to Health Physics Procedure RAC-002, Dosimetry Program)
- ML20214N991 + (Rev 3 to Health Physics Procedure RAC-015, Verification Procedures for Vicinity Properties & Tailings Sites (Soil Sampling & Analysis))
- ML20214N968 + (Rev 3 to Health Physics Procedure RAC-014, Excavation Control Procedure)
- ML20214N995 + (Rev 3 to Health Physics Procedure RAC-016, Indoor Working Level Verification Surveys)
- ML20129E649 + (Rev 3 to Hydrogen Control Program Plan)
- ML20082L545 + (Rev 3 to ISI Plan for Braidwood Nuclear Generating Station Units 1 & 2 1st Insp Interval)
- ML20215E163 + (Rev 3 to ISI-P-002, Preservice Insp Program)
- ML20043H309 + (Rev 3 to ISI-P-014, Inservice Insp Program)
- ML17156B067 + (Rev 3 to ISI-T-200.0, Pump & Valve Inservice Insp Testing Program)
- ML20073D367 + (Rev 3 to IST Program,Including Review Sheets to Add 17 Valves,Three Revised Pump Review Sheets,Reflecting Testing Requirements of Relief Request P3 & Review Sheets for Two Valves Which Had Testing Requirements Changed)