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 Issue dateSiteTitle
ML1212503873 May 2012VogtleLicensees, Response Opposing Petitioners' Motion to Stay
ML10075042016 October 2009Crystal RiverEmail from J. Fuller to A. Masters, Subj: FW: Crystal River U3 Containment Cracks
ML10075041916 October 2009Crystal RiverEmail from J. Fuller to A. Masters, Subj: Cause of Crack at CR Plant Not Yet Known
ML06059029028 February 2006HatchCracking Indications in Core Shroud Tie Rods
ML05084003014 March 2005VogtleEnclosure 2, Municipal Electric Authority of Georgia Letter March 14, 2005 Regarding Vogtle Electric Generating Plant Financial Assurance Requirements for Decommissioning Nuclear Power Reactors
ML05084006814 March 2005HatchEnclosure 2, Municipal Electric Authority of Georgia Letter Dated March 14, 2005. Edwin 1. Hatch Nuclear Plant Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1
ML0330305643 October 2003HatchEnclosure 2, Municipal Electric Authority of Georgia - Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10CFR50.75(f)(1)
ML20205H14925 March 1999HatchForwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Municipal Electric Authority of Georgia Is One of Licensed Owners of Ei Hatch,Owning 17.7% of Facility
ML20205H38925 March 1999VogtleForwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1).Page 2 in Third Amend Power Sales Contract of Incoming Submittal Not Included
ML20205H40525 March 1999VogtleForwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1)
ML20217M57222 April 1998Mod 23 to Contract NRC-31-83-671
ML20133F1832 January 1997Mod 22 to Contract NRC-31-83-671
ML20039C67322 December 1981PilgrimReaffirms 810825 Ltr Requesting Extension of Confirmatory Order Date.Torus Saddle Installation,Classified as Major Mod,Will Be Completed by 820501.Minor Mods Will Be Completed Coincident W/Cycle 7 Operation
ML19346A1861 June 1981Fort Saint VrainAdvises That Description of Emergency Response Facilities Will Be Sent Upon Determination of Applicable Requirements of HTGR to Facility by 810701.Requirements for Emergency Response Facilities Contained in NUREG-0696 Under Review
ML20004D48822 May 1981Fort Saint VrainResponds to IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Asiatic Clams Not in Evidence in Plant Vicinity
ML20003B0325 February 1981Fort Saint VrainForwards Structural Safety Evaluation of Cracked Fort St Vrain Core Support Block During Loss of Forced Circulation W/Firewater Cooldown. Core Support Block Cracking Will Not Interfere W/Safe Core Cooldown
ML19345F5324 February 1981Fort Saint VrainForwards Clarification of 800131 Ltr Re Elevator Security. Clarification Withheld (Ref 10CFR2.790)
ML20002C19631 December 1980Fort Saint VrainForwards Proposed Mods to Security Plan Re Elevator Security.Mods Withheld (Ref 10CFR2.790)
ML19338F83220 October 1980Fort Saint VrainWithdraws 800829 Request for Hearing Re NRC 800829 Order Amending License DPR-34 to Require That Certain Info Concerning Environ Qualification of Class IE Electrical Equipment Be Provided by 801101
ML20062J5503 October 1980Fort Saint VrainResponds to 800829 Order Re Environ Qualification of Electrical Equipment for Station Per IE Bulletin 79-01B. Equipment Is Qualified W/Criteria Consistent W/Ie Bulletin 79-01B Criteria.Component Tables Encl
ML19338D91617 September 1980Fort Saint VrainResponds to NRC 800829 Order Modifying License DPR-34 to Require Info by 801101 Re Environ Qualifications of IE Electrical Equipment in Operation Sys Exposed to High Energy Line Break Ambience.Hearing Requested Re Order
ML19331D75629 August 1980Fort Saint VrainResponds to NRC 800802 Ltr Requesting Addl Info Re Thermal Stresses in Core Support Blocks.Net Effect of Analytical Models & Assumptions on Stresses Not Clear at present.Short- Term Efforts in Progress.Results to Be Reviewed
ML19321A0903 July 1980Fort Saint VrainComments on Proposed Rule 10CFR50:to Require Same Spacing of Clear Air Space Horizontally & Vertically Is Inconsistent. Horizontal Spacing of 50 Ft Is Considered Very Extreme
ML19309F38825 April 1980Fort Saint VrainResponds to IE Bulletin 79-27, Loss of Non-Class IE Instrumentation & Control Power Sys Bus During Operation. Loss of Instrument Bus Voltage Is Alarmed in Control Room. Voltmeters Are Provided for Addl Verification
ML19309B10631 March 1980Fort Saint VrainForwards Category I Inservice Insp & Testing Program Submittals Re Helium Circulator & Secondary Coolant Sys
ML19309B8664 March 1980Fort Saint VrainRepresents That Util Notification to NRC Re Fuel Particles Opyc Microporosity Was Timely.Bases Opinion on Info Originally Presented to Util by Ga Co & in-reactor Performance of Fuel to Date
ML19305C3313 March 1980Fort Saint VrainForwards Inservice Insp & Testing:Proposed Tech Specs Surveillance Requirements:Prestressed Concrete Reactor Vessel, & Inservice Insp Testing Program:Surveillance Requirements Review for Prestressed Concrete Reactor ...
ML19260E2958 February 1980Fort Saint VrainForwards Category I Inservice Insp Submittals,Presented as Draft Proposed Mods to Tech Spec Surveillance Requirements. Application to Amend OL Will Be Submitted
ML19260C03830 November 1979Fort Saint VrainDiscusses Inservice Insp & Testing Program Re Review & Development of Modified Surveillance Requirements.Util Will Provide Development Schedule by 791201 & Proposed Requirements for Each Sys or Subsys as Developed
ML19210E27229 November 1979Fort Saint VrainForwards GA-D15474, Nuclear Detector Decalibration, Cycle 2, in Support of Mods Requested in 790011 Ltr
ML19211A80628 September 1979Fort Saint VrainResponds to IE Bulletin 79-01A.ASCO Solenoid Valves W/ safety-related Applications Have Been Qualified for Operability Through Exposure to Worst Postulated Environmental Accident Conditions
ML19254D97614 September 1979Fort Saint VrainResponds to IE Bulletin 79-15 W/Listing of Manufacturer, Model,Rated Capacity & Plant Application of 14 safety-related Deep Draft Pumps.Discusses Startup History, Type & Frequency of Testing & Maint of Pumps
ML19253B4784 September 1979Fort Saint VrainDiscusses Completed Field Audit & Preliminary Engineering Analysis of Random Sample of as-built safety-related Piping in Response to 790801 Ltr.Submits Proposal for Concurrence Re Returning of Reactor to Power Operation
ML19276H02428 August 1979Fort Saint VrainForwards for Review Progress Repts on Inservice Insp & Testing Program Review Conducted Per Tech Specs Surveillance Requirements.Nrc Concurrence on Proposed Methodology Requested by 790915
ML20049A2111 August 1979Fort Saint VrainSubmits Response to IE Bulletin 79-14,Item 1 Re Insp Elements to Be Used in Verifying That Seismic Analysis Input Info Conforms to Actual Configuration of Plant. Class I Pipe Support & Piping Indices Encl
ML19247A62325 July 1979Fort Saint VrainRequests Specific Licensing Approval to Use Grade H-451 Graphite in Fuel & Reflector Elements in Selected Regions of Reload Segment 9 & to Use Grade H-451 Graphite in All Regions of Subsequent Reload Segments by 791001
ML19242B40712 June 1979Fort Saint VrainResponds to IE Bulletin 79-01.Forwards List of Documents Previously Submitted to NRC Re Environmental Qualification Program & Environ Qualfications of Connectors,Penetrations, Terminal Blocks & Limit Switches
ML19263E3665 June 1979Fort Saint VrainForwards Addl Info to Jk Fuller 790315 Ltr.Discusses DOE-funded Program Re Tube Corrosion Monitoring Data
ML19273B7331 June 1979Fort Saint VrainResponds to NRC 790406 Ltr Requesting Addl Info to Verify That Only Modest Number of Fluctuations Would Be Initiated
ML19241C19123 May 1979Fort Saint VrainResponds to NRC 730703 Ltr Re Violations Noted in IE Insp Rept 50-267/73-04.Corrective Actions:Encl Corrosion Monitoring Program Was Established
ML19225B2829 May 1979Fort Saint VrainNotifies That Reinsp Completed of All Specified Class I Valves in Response to AEC Operations Bulletin 79-10. One Valve Had Defective Tack Weld.No Further Action Required.List of Valves Not Encl
ML19225B8424 May 1979Fort Saint VrainResponds to IE Bulletin 79-04.One 6-inch Velan Check Valve Found in Emergency Condensate Line to Loop 1 Steam Generators.Conservative Seismic Analysis Rate Provides Adequate Safety Margin
ML19274E51419 March 1979Fort Saint VrainForwards Amend A-1 to SAR for Instrumented Control Rod Drives.Includes Analysis to Support Locating Drives in Regions 5 & 35 of Reactor Core
ML19274E52115 March 1979Fort Saint VrainForwards Addl Info Re Inservice Insp Program,Per NRC 790115 Request
ML19269C8727 February 1979Fort Saint VrainResponds to NRC 790115 & 0122 Ltrs Requesting Info on Inservice Insp & Tech Spec Surveillance Planned for Upcoming Refueling Outage.Forwards List of Surveillances Planned. Confirms Three Surveillance Which Will Not Be Performed
ML19261A79330 January 1979Fort Saint VrainResponds to Item 7 of 790110 Request for Addl Info Re Continued Reactor Operation in Nonfluctuating Mode.Control Effected by Ordering Limiting Conditions for Operation in Terms of Delta P,Core Resistance & Fluctuations
ML19261A82130 January 1979Fort Saint VrainForwards General Insp Plan for Inspecting Region 35 During Upcoming Refueling Outage.Despite 781104 Fluctuation,There Are No Plans for Addl Detailed Insp of Regions Other than 35.Regions 5,10,17,21 & 28 Will Be Refueled During Outage
ML19261A70029 January 1979Fort Saint VrainInforms NRC Requested Info Was Forwarded on 790117
ML20008D66229 January 1979Fort Saint VrainForwards Rept Fluctuation Events of 781104 & 781212, Evaluation & Resultant Revisions to Normal & Test Operating Procedures
ML19296A11926 January 1979Fort Saint VrainForwards Amend 3 to Fuel Test Element SAR