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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
- ML17263A999 +
- ML17332A700 +
- Press Release-95-034, NRC Advisory Committee on Reactor Safeguards to Meet in Rockville, MD, April 6-8 +
- Press Release-95-032, the Nuclear Regulatory Commission Has Received Two Reports from Its Independent Advisory Committee on Reactor Safeguards +
- ML18038B229 +
- ML18064A659 +
- ML20087G493 +
- ML20087G401 +
- ML20087G338 +
- ML20087G326 +
- ML20087G266 +
- ML20087G253 +
- ML20087G245 +
- NRC-95-0047, Comment on GL, Pressure Locking & Thermal Binding of Safety Related Power-Operated Gate Valves. Draft GL Should Be Revised to Permit Some Use of Plant Operating Experience as Basis for Engineering Judgement +
- ML20082F592 +
- ML20082E190 +
- ML20082B587 +
- ML20082B469 +
- 05000301/LER-1995-001, Forwards LER 95-001 Re Inadvertent EDG Start.Rept Describes Situation That Caused Normal Power Supply Breaker for Unit 2 Train A,4160 Volt Safeguards Bus to Open +
- ML20082A980 +
- ML20082A511 +
- ML20082A385 +
- ML20082A376 +
- ML20081L975 +
- ML20081L937 +
- ML20081L900 +
- ML20081L429 +
- NRC-95-0010, Notifies NRC of Completion of Design Basis Reviews, Analyses,Verifications,Tests & Insps Described in GL 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance +
- NPL-95-0144, Submits Annual Rept of Changes to & Errors Discovered in ECCS Evaluation Models Fo Plant.Summary of ECCS Evaluation Model Changes & Errors Identified Since Last Annual Rept Encl +
- TAC:M91225 +
- B15135, Proposed Tech Specs Re Feedwater Isolation +
- ST-HL-AE-5037, Requests Exemption from Certain Requirements of 10CFR73.55, Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage +
- NRC-95-4422, Forwards Proprietary Tables Containing Mass & Energy Info from Test 220.1 Performed at AP600 PCS Large Scale Test Facility.Info Provided in Response to Action Item from 950317 Meeting Between Westinghouse & Nrc.Tables Withheld +
- BSEP-95-0152, Responds to Violations Noted in Insp Repts 50-324/95-01 & 50-325/95-01.Corrective Actions:Previously Prepared Field Revs for Minor Mods re-reviewed for Design Adequacy +
- LD-95-015, Transmits Corrected Page for Incorporation Into Sys 80+ DCD Revs +
- ML20266H624 +
- ML20266H628 +
- ML20266H635 +
- ML20266G816 +
- ML20087G328 +
- 05000301/LER-1995-001-01, :on 950227,normal Power Supply Breaker for 4160 Volt Safeguards Bus 2A05 Was Inadvertently Tripped Open During Mod Work for Installation of Addl EDG Due to Cognitive Error.Recovered Affected Equipment +
- 05000282/LER-1995-002, :on 950205,noticed That SFP CAM Not Operating. Caused by Broken Drive Belt.Cr Operator Notified & SFP Normal Ventilation Secured +
- 05000331/LER-1995-004, :on 950307,circuit Continuity Momentarily Lost During Installation of Jumper.Caused by Loosening of Nut Required to Insert Forklug Jumper.Cr Operators Verified That All Automatic Actions Occurred as Designed +
- 05000327/LER-1995-003-01, :on 950224,inadvertent MFW Isolation Occurred During Testing of Reactor Trip Bypass Breakers.Caused by Failure to Follow Procedures.Individual That Inadvertently Bumped Breaker Close Pushbutton Counseled +
- 05000298/LER-1995-007, :on 950224,iodine Channel of CR Air Sampling Monitor RMV-RM-1 Failed to Meet Calibr Tolerance Required by Sp 6.4.6.3.1 Due to Inadequate Procedure.Sps 6.4.6.3.1 & 6.2.3.3.1 Will Be Revised by 950430 +
- ML20081L889 +
- ML20081L894 +
- ML20082A990 +
- ML20082E628 +
- ML20082B699 +