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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
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure +
- IR 05000397/1992041 +
- ML18010B066 +
- ML18058B736 +
- ML19342A547 +
- ML112380574 +
- PNO-II-93-014, on 930324,NRC Duty Officer Notified That Previous Random Screening for Drugs of Licensed Reactor Operator at Plant Had Been Confirmed Positive for Cocaine. State of Sc & Local Officials Have Been Notified +
- PNO-III-93-018, on 930326,licensee Reported That Licensed Senior Reactor Operator Tested Positive for Alcohol During Routine Medical Exam.Individual Not Performing NRC-licensed Duties at Time of Incident,At Site Only for Medical Exam +
- ML20262B561 +
- ML20262B557 +
- ML20262B551 +
- ML20262B547 +
- ML20262B544 +
- ML20262B539 +
- ML20262B535 +
- ML20262B530 +
- ML20262B526 +
- ML20262B521 +
- ML20262B120 +
- ML20056C171 +
- ML20199J770 +
- ML20056C262 +
- ML20046A826 +
- ML20044C590 +
- IR 05000029/1993003 +
- 05000277/LER-1993-004, :on 930302,automatic Scram on Reactor Water Level When Condensate Pump Trip Caused Two Reactor Feed Pumps to Trip on Low Suction Pressure.Control Panel Will Be Evaluated +
- 05000278/LER-1993-002-03, :on 930307,automatic Scram on Reactor Water Level When Reactor Feed Pump Feed Tripped on High Vibrations.Evaluation Will Be Performed on Defective Controller to Identify C/As Necessary +
- LD-93-056, Forwards Rev 1 to NPX80-IC-RR790-02, Human Factors Evaluation & Allocation of Sys 80+ Functions +
- HL-3215, Special Rept 1-93-001:on 930224,discovered That Surveillance on Diesel engine-driven Fire Pumps Missed Since 930113 & Pumps Exceeded TS Operability Requirements of 14 Days.Caused by Personnel Error.Test Procedure Revised +
- JPN-93-023, Confirms Recent Telcon Re 921120 Application for Amend to License DPR-59,revising TS 3.0.D,w/respect to Temporary Exemptions from 10CFR50,App R Re Adequacy of Fire Suppression Sys in East & West Cable Tunnels +
- BSEP-93-0041, Part 21 Rept Re Mfg Defects Associated W/Westinghouse Type Hmcp & Type Hfd Breakers,Resulting in Possibility That Breaker Contacts May Not Open During Trip.Initially Reported on 930225.Functional Testing Procedures Revised +
- 3F0393-11, Discusses Issue Re Relocating TS Administrative Controls. Requests That 870810 Exemption Request Be Expeditiously Reviewed & Approved for Expedited Resolution of Issue. Summary of 930303 Meeting W/Nrc Re Issue Encl +
- B14417, Informs NRC of Mgt Changes within Nuclear Organization Which Will Become Effective 930328.Listed Changes Are Reflected in Attached Rev to Distribution List for NRC Correspondence +
- 05000333/LER-1993-005, :on 930225,RHR/LPCI Started in Shutdown Cooling Mode & Isolation Valves Closed Upon Initial Startup of Pump. Caused by Procedure Deficiencies.Operating Procedure for RHR Shutdown Cooling Has Been Revised +
- JPN-93-021, Forwards Inservice Insp Summary Rept,1992 Refuel Outage (Reload 10/Cycle 11), Consisting of Results of Jet Pump Beam Insps Performed Per NRC Bulletin 80-07 & Access Hole Cover Insps Performed Per GE SIL 462 +
- 3F0393-10, Submits Itemization of Various Insurance Policies Currently in Place for Unit 3 Nuclear Power Plant +
- 05000333/LER-1993-004-01, :on 930225,scram Initiated by Taking Reactor Mode Switch Out of Run Mode When Water Level Observed to Be Below Normal.Caused by Slush Ice Present in Front of Bar Racks.Water Level Indicator Installed +
- ML20035B818 +
- 05000498/LER-1993-010, :on 930224,halon Actuation Occurred in Plant Computer Room,Associated Distribution Room & Battery Room. Caused by Electrical Load Test on Fps.Licensee Will Revise Fire Harzards Evaluations Procedure +
- LD-93-055, Forwards Revised Safety Analysis,Being Submitted in Response to Draft Issues,Nrc Staff Questions & Comments Provided at Dec 1992 & Jan 1993 Meetings +
- 05000373/LER-1993-007, :on 930226,circuit Breaker Tripped on Thermal Overloads While Attempting to Open RCIC Sys Inboard Isolation Valve.Caused by Hydraulic Lock.Broken Disc Retainer Pin Replaced +
- B14425, Requests Enforcement Discretion Associated W/Compliance W/Millstone Unit 2 TS 3.4.10, RCS-Structural Integrity, to Afford Util Sufficient Time to Effect Temporary Repair to Provide Addl Structural Integrity to Supply Piping +
- LIC-93-0100, Forwards Fort Calhoun Station Performance Indicators,Feb 1993 +
- IR 05000498/1993010 +
- LD-93-054, Forwards Amend M to Vols 19 Through 26 of Sys 80+ Std Design CESSAR Design Certification (Dc). Amend M Provides Revised PRA (Level 1) as Chapter 19 of CESSAR-DC +
- LIC-93-0102, Forwards Public & Central Files Versions of Rev 9 to RERP- App a, Ltrs of Agreement. Central Files Version Withheld +
- JAFP-93-0164, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-333/92-21.Corrective Actions:Administrative Procedure Has Been Developed & Issued to Provide Guidance on Chemical Replenishment,Hypo Testing & Methylene Blue Testing +
- HL-3162, Forwards Revised Proposed Changes to TS Re Gaseous Effluent Release Rate Limits,Per Telcons W/Nrc in Connection W/Nrc Review of 921014 & 930115 Applications for Amends to TS Associated W/Implementation of New 10CFR20 Requirements +
- 1CAN039306, Forwards Response to NRC 921116 Request for Addl Info Re in- Structure Response Spectra in Order to Complete Review of 920918 Response to Suppl 1 to GL 87-02 on Rev 2 to SQUG Generic Implementation Procedure +
- IR 05000352/1993008 +