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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

• ML20117D821  + (ML20117D821)
• 05000321/LER-1996-005, :on 960414,supply Breaker for 4160V/600V Station Svc Transformer 1D Opened de-energizing 600V Bus 1R23-S004.Caused by Personnel Error.Personnel Involved Counseled  + (ML20117D825)
• 05000219/LER-1996-003, :on 960409,determined Certain 4160 Vac Emergency Electrical Bus Grid Undervoltage Relay Contacts Not Functionally Tested Required by TS Table 4.1-1,Items 28 a & B.Caused by Inadequate Testing  + (ML20117D840)
• 05000263/LER-1996-003, Forwards LER 96-003-00 Re re-analysis of High Energy Line Break,Error Found in Existing Analysis.Rept Contains Submitted New NRC Commitments  + (ML20117D841)
• 05000263/LER-1996-003-01, :on 960404,personnel Identified Error in Current Licensing Basis Analysis.Caused by Improper Analyzed Ambient Temps in Vicinity.Mods Will Be Installed During Current Outage  + (ML20117D846)
• 05000322/LER-1985-013, :on 850407,failure of HPCI Circuit Inverter Rendered HPCI Sys Inoperable.Caused by Failure of Cooling Fan Causing Inverter Cabinet & Circuitry to Overheat. Procedures for Fan Insp Will Be Revised  + (ML20117D848)
• ML20117D851  + (ML20117D851)
• ML20117D864  + (ML20117D864)
• ML20117D876  + (ML20117D876)
• ML20117D877  + (ML20117D877)
• 2CAN038505, Provides Justification That Senior Reactor Operators Adequately Trained to Cope W/Emergency Situations.Scope of Training for Future Senior Reactor Operator Candidates Will Place More Emphasis on Emergency Plan Training  + (ML20117D878)
• JAFP-96-0200, Responds to NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core or Over Safety-Related Equipment,  + (ML20117D880)
• ML20117D886  + (ML20117D886)
• ML20117D891  + (ML20117D891)
• ML20117D912  + (ML20117D912)
• ML20117D919  + (ML20117D919)
• NRC-96-0048, Requests NRC Review & Approval of Proposed QA Program Change for Audit Program,Deleting Frequencies from Audits Specified by Regulations & Deleting Requirement to Perform Annual Audit of Fitness for Duty Lab  + (ML20117D931)
• ML20117D953  + (ML20117D953)
• 05000373/LER-1985-036-01, :on 850403,RHR Inboard Shutdown Cooling Suction Isolation Valve 1E12-F009 Isolated.Caused by Spurious Pressure Spike.Pressure Snubbers Installed & Upgrades for Environ Qualification Reviewed  + (ML20117D959)
• ML20117D968  + (ML20117D968)
• DCL-96-102, Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld  + (ML20117D970)
• ML20117D971  + (ML20117D971)
• ML20117D974  + (ML20117D974)
• ML20117D993  + (ML20117D993)
• ML20117D996  + (ML20117D996)

• ML20117D997  + (ML20117D997)

• ML20117E004  + (ML20117E004)
• RBG-20753, Responds to NRC Re Violations Noted in Insp Rept 50-458/85-02.Corrective Actions:Ansi & ASME Codes Reviewed for Spare Parts Storage Requirements & MSP-0002 Revised to Clarify Methods Used to Meet Requirements  + (ML20117E009)
• ML20117E025  + (ML20117E025)
• ML20117E037  + (ML20117E037)
• ML20117E048  + (ML20117E048)
• ML20117E052  + (ML20117E052)
• ML20117E056  + (ML20117E056)
• RBG-20183, Responds to NRC Re Violations Noted in Insp Rept 50-458/84-28.Corrective Actions:Qa Sys Audited Until Maint to Address Preventive Maint of Equipment & QA Instruction 2.1, Audit Performance & Reporting, Revised  + (ML20117E060)
• ML20117E065  + (ML20117E065)
• ML20117E068  + (ML20117E068)
• ML20117E074  + (ML20117E074)
• ML20117E079  + (ML20117E079)
• AECM-85-0129, Forwards Revised Fire Protection Review Summary Rept,Per 10CFR50,App R & Bechtel Rept, Fire Hazards Analysis,Grand Gulf Nuclear Station,Unit 1. Review of Mods Increasing Fire Protection Requested.Fee Paid  + (ML20117E082)
• ML20117E085  + (ML20117E085)
• ML20117E086  + (ML20117E086)
• ML20117E096  + (ML20117E096)
• ML20117E102  + (ML20117E102)
• ML20117E106  + (ML20117E106)
• ML20117E130  + (ML20117E130)
• ML20117E146  + (ML20117E146)
• HL-5171, Discusses Gpc Determination to Follow BWR Vessel & Internals Project:Guidelines for Reinspection of BWR Core Shrouds (BWRVIP-07) for Hatch Units 1 & 2  + (ML20117E148)
• ML20117E152  + (ML20117E152)
• ML20117E166  + (ML20117E166)
• ML20117E168  + (ML20117E168)
• ML20117E170  + (ML20117E170)