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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
- Press Release-94-119, NRC Advisory Committee on Reactor Safeguards to Meet in Rockville, MD, August 4-5 +
- Press Release-94-118, the Nuclear Regulatory Commission Has Received the Attached Report from Its Advisory Committee on Nuclear Waste +
- ML18011A510 +
- ML18011A508 +
- ML18011A507 +
- ML061150505 +
- ML18100B234 +
- ML18100B232 +
- ML18059B127 +
- ML20070K806 +
- NRC-94-0046, Special Rept:On 940622,re Emergency Diesel Generator Test Failure.Troubleshooting Performed Into Cause.Vertical Drive Spring Pack Was Cleaned & Rebuilt Using New Springs & Wear Plates +
- ML20070J851 +
- ML20070J831 +
- ML20070J705 +
- ML20070J689 +
- ML20070J238 +
- ML20080P082 +
- ML20073B333 +
- ML20072A633 +
- ML20072A091 +
- ML20071Q886 +
- ML20071M299 +
- ML20071M252 +
- ML20071M187 +
- ML20071L168 +
- ML20071L111 +
- ML20071L107 +
- ML20071L067 +
- ML20071K579 +
- ML20071K466 +
- ML20071K459 +
- ML20071K458 +
- ML20071K376 +
- ML20071J540 +
- ML20071J535 +
- ML20071J489 +
- ML20071J263 +
- ML20071J189 +
- ML20149E808 +
- U-166243, Functional Diagrams Feedwater Control & Isolation.Sheet 13 +
- U-166237, Functional Diagrams Steam Generator Trip Signals.Sheet 7 +
- U-166232, Functional Diagrams Reactor Trip Signals.Sheet 2 +
- U-166231, Functional Diagram Index & Symbols.Sheet 1 of 1 +
- NRC-94-4233, Forwards non-proprietary & Proprietary Rev 1 to Simplified Passive Alwr Plant Program AP600 PRA, Replacing Chapters & Appendices to Be Inserted Into Existing Binders to Replace Superseded Pages.Pra Rept Withheld (Ref 10CFR9.17(a)(4)) +
- B14905, Application for Amend to License NPF-49,revising TS Tables 3.7-1,3.7-2 & Bases Section 3/4.7.1.1 Re Max Allowable Power Range Neutron Flux High Setpoint W/Inoperable Main Steam Line Safety Valves +
- B14803, Application for Amend to License NPF-49,proposing Changes to Ts,Addressing Shutdown Margins,Reactor Trip Sys & Heat Flux Hot Channel Factor +
- LIC-94-0155, Requests That Mailing Distribution Be Updated to Reflect Listed Attorney Name & Address +
- JPN-94-035, Provides Response to NRC 940520 RAI on NRC Bulletin 90-001, Suppl 1, Loss of Fill-Oil in Rosemount Transmitters, Relative to Enhanced Surveillance Program for Rosemount Transmitters +
- JPN-94-034, Forwards Response to NRC 940518 RAI on Plant App R Safe Shutdown Capability Assessment.Use of ADS & LPCI or ADS & CS from Inside CR to Achieve Safe Shutdown in Case of Fire Not Considered Alternative +
- 0CAN079404, Quality Assurance Manual Operations,Rev 17 +