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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
- 05000155/LER-1997-004, :on 970410,determined Potential Loss of DC Power for Primary Containment Spray & Liquid Poison Systems. Caused by Inadequate Design Control Program.Removed & Replaced Breaker 72-12 + (ML20141C210)
- ML20141C214 + (ML20141C214)
- ML20141C217 + (ML20141C217)
- ML20141C218 + (ML20141C218)
- ML20141C221 + (ML20141C221)
- ML20141C222 + (ML20141C222)
- ML20141C223 + (ML20141C223)
- ML20141C226 + (ML20141C226)
- ML20141C228 + (ML20141C228)
- ML20141C231 + (ML20141C231)
- ML20141C235 + (ML20141C235)
- ML20141C238 + (ML20141C238)
- ML20141C240 + (ML20141C240)
- ML20141C241 + (ML20141C241)
- 05000313/LER-1996-002, :on 970519,surveillance Tests Required by TS Were Incomplete Because All Combinations of Contacts Not Tested Due to Procedure Deficiencies.Verified Operability of RPS + (ML20141C245)
- ML20141C246 + (ML20141C246)
- ML20141C247 + (ML20141C247)
- NSD-NRC-97-5174, Forwards Responses to 970514 RAI Re Containment Systems & Severe Accident Branch Relating to AP600 Initial Test Program + (ML20141C250)
- ML20141C251 + (ML20141C251)
- ML20141C253 + (ML20141C253)
- ML20141C256 + (ML20141C256)
- ML20141C260 + (ML20141C260)
- NSD-NRC-97-5178, Forwards W Responses to RAI Re AP600 Subcompartment Pressurization Analysis & Containment External Pressure Analysis.Response Numbers,Listed + (ML20141C262)
- 05000266/LER-1997-026, :on 970521,discovered TS Violation of Operability Requirement of MSL Isolation.Caused by Inadequate Consideration for Operability of All Required Functions.Verified Low RCS Sys Average Temp + (ML20141C266)
- ML20141C267 + (ML20141C267)
- ML20141C268 + (ML20141C268)
- ML20141C270 + (ML20141C270)
- ML20141C271 + (ML20141C271)
- ML20141C274 + (ML20141C274)
- ML20141C275 + (ML20141C275)
- ML20141C278 + (ML20141C278)
- BVY-97-059, Monthly Operating Rept for Apr 1997 for Vermont Yankee Nuclear Station + (ML20141C279)
- NSD-NRC-97-5169, Discusses Comparison of Methodolody Included in Spr 6.2.5 App a Used in Calculation & Results Compared to Results Using AP600 Model + (ML20141C282)
- ML20141C283 + (ML20141C283)
- ML20141C284 + (ML20141C284)
- ML20141C286 + (ML20141C286)
- ML20141C287 + (ML20141C287)
- ML20141C293 + (ML20141C293)
- ML20141C295 + (ML20141C295)
- ML20141C298 + (ML20141C298)
- ML20141C301 + (ML20141C301)
- ML20141C302 + (ML20141C302)
- ML20141C303 + (ML20141C303)
- RBG-43920, Forwards Proprietary Response to RAI Re GE Methodology for Calculating Cycle Specific Safety Limit Min Critical Power Ratio.Response Needed to Support License Amend to TS 2.1.1.2, Reactor Core (Safety Limits). Encl Withheld + (ML20141C306)
- ML20141C308 + (ML20141C308)
- ML20141C311 + (ML20141C311)
- ML20141C313 + (ML20141C313)
- ML20141C315 + (ML20141C315)
- ML20141C319 + (ML20141C319)
- ML20141C322 + (ML20141C322)
- RBG-43-933, NPDES Noncompliance Notification:On 970506 & 07 Several Unanticipated Bypasses of Station Circulating Water Sys Occurred.Caused by Manual Shutdown of Station.Secured CWS to Compensate for Decrease Demand for Makeup Water + (ML20141C323)