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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
- ML20070N455 + (ML20070N455)
- ML20070N461 + (ML20070N461)
- ML20070N471 + (ML20070N471)
- AECM-83-010, Responds to NRC Re Violations Noted in IE Safeguards Insp Rept 50-416/82-74.Corrective Actions Withheld + (ML20070N476)
- L-82-548, Responds to NRC Re Violations Noted in IE Insp Repts 50-250/82-30 & 50-251/82-30.Corrective Actions:Special Training Classes on Heat Tracing Conducted,Checklist for Reviewing Plant Work Orders Prepared & Valve Locked + (ML20070N479)
- HL-4579, Responds to NRC Re Violations Noted in Insp Rept 50-366/94-05.Corrective Action:Operations Manager Met W/Staff Emphasizing Importance of Procedural Compliance + (ML20070N485)
- ML20070N487 + (ML20070N487)
- ML20070N498 + (ML20070N498)
- ML20070N526 + (ML20070N526)
- ML20070N528 + (ML20070N528)
- LD-94-027, Forwards Summary of Sys 80+ Design & Operational Features Involving Deviations from Current Regulations + (ML20070N529)
- LD-94-026, Provides Matl to Close Issues Raised by NRC Staff,Including Summary of Approach to Design Verification & List of Calculations + (ML20070N530)
- ML20070N542 + (ML20070N542)
- ML20070N548 + (ML20070N548)
- ML20070N560 + (ML20070N560)
- ML20070N562 + (ML20070N562)
- ST-HL-AE-4750, Application for Amends to Licenses NPF-76 & NPF-80,revising Max Allowable Power Range Neutron Flux High Setpoint When One or More Main Steam Safety Valves Inoperable + (ML20070N580)
- ML20070N585 + (ML20070N585)
- L-82-541, Submits Addl Response to NRC Re Violations Noted in IE Insp Rept 50-389/82-43.Corrective Actions Cited in 821108 Final Response.Site Quality Instruction (Qi) 10.13 Requires Installation Insp for ASME Class 1,2 & 3 Tanks + (ML20070N593)
- ML20070N596 + (ML20070N596)
- ML20070N608 + (ML20070N608)
- L-82-489, Responds to NRC Re Violations Noted in IE Insp Rept 50-389/82-43.Corrective Actions:Nrc 1627m Issued to Document & Correct Problems Encountered W/Anchoring Component Cooling Water Surge Tank + (ML20070N610)
- 3F0494-17, Bold Strokes for Progress 1993 Annual Rept Florida Progress Corp + (ML20070N616)
- ML20070N622 + (ML20070N622)
- NRC-94-0019, Annual Nonradiological Environ Operating Rept for 1993 + (ML20070N627)
- ML20070N636 + (ML20070N636)
- ML20070N647 + (ML20070N647)
- RBG-14-130, Interim Deficiency Rept DR-71 Re Inconsistencies Found in QA Program at Wj Woolley Co,Mfg of Personnel Air Locks. Initially Reported on 820827.Evaluation Incomplete.Next Rept Expected by 830419 + (ML20070N651)
- RC-94-0126, Forwards Scope Reduction for GL 88-20,Suppl 4 Seismic Evaluation,Per Draft NUREG-1488, Revised Livermore Seismic Hazard Estimates for 69 Nuclear Power Plant Sites East of Rocky Mountains + (ML20070N657)
- ML20070N660 + (ML20070N660)
- ML20070N667 + (ML20070N667)
- ML20070N675 + (ML20070N675)
- L-82-404, Provides Updated Response to IE Insp Repts 50-250/82-19 & 50-251/82-19 Re Moisture Problems W/Air Ejector Radiation Monitors.No Schedule Available to Resolve Problem Due to Complexity.Periodic Repts Will Be Provided + (ML20070N677)
- LIC-20-0004, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration + (ML20070N679)
- ML20070N681 + (ML20070N681)
- U-602283, Forwards Rev to 931026 Application for Amend to License NPF-62,involving Rev of TS to Apply NUREG-1434,per Changes Recommended in NRC + (ML20070N691)
- L-82-358, Provides Supplemental Response to IE Insp Repts 50-250/82-19 & 50-251/82-19 Re Status of Continuous Monitors Sampling Air Ejector Exhaust.Ae Expects to Provide Schedule to Resolve Problem in 2 Wks + (ML20070N694)
- ML20070N695 + (ML20070N695)
- ML20070N697 + (ML20070N697)
- ML20070N702 + (ML20070N702)
- ML20070N703 + (ML20070N703)
- ML20070N705 + (ML20070N705)
- ML20070N706 + (ML20070N706)
- ML20070N727 + (ML20070N727)
- ML20070N728 + (ML20070N728)
- ML20070N731 + (ML20070N731)
- LD-83-004, Informs That Schedule Will Be Provided by 830228 in Response to Questions Re Application of Statistical Combination of Uncertainties Methodology to Sys 80TM Reactor Design + (ML20070N732)
- ML20070N733 + (ML20070N733)
- LIC-94-0083, Radiological Environ Operating Rept TS 5.9.4.b Jan-Dec 1993 + (ML20070N741)
- ML20070N749 + (ML20070N749)
- ML20070N752 + (ML20070N752)