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 Issue dateTitleTopic
ML19242A7741 August 1979Forwards,Per s Ramos Request,Analyses of Design Basis Accident & Loca,In Support of Renewal of License R-47
ML19254E45918 October 1979Requests Amend to License CX-10 to Authorize Critical Experiments Utilizing nonmoderator-to-moderator Ratios Described in Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program.
ML19256E22526 October 1979Forwards Executed Amend 20 to Indemnity Agreement B-8 & Amend 2 to Indemnity Agreement G-2
ML19257B92616 January 1980Forwards Page 18a for Insertion in 791023 Rept Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program.
ML19260B2443 December 1979Submits Addl Info in Support of Request for Amend to License CX-10.Discusses Probability of Max Credible Accident & Need for Amend to Tech Specs
ML19269C52129 January 1979Responds to NRC 780821 Ltr.Forwards Info Re Financial Data, Business Conducted,Organizational Structure,Radiological Monitoring,Safety Hazards & Tech SpecsSafe Shutdown
Incorporated by reference
ML19276H02315 August 1979Responds to 790730 Ltr Requesting Info from Nonpower Reactor Licensees Re Effect of Safeguards Rule.Upgrade Rule Necessitates Protection of Reactor as Category I Facility for Physical Protection Purposes
ML19289D18316 February 1979Responds to 790202 Ltr.Provides Details of Amounts & Enrichments of Snm.Agrees to Add License Condition Requiring Mod of Reactor Security Plan.Claims No Exemptions for Any SNM
ML19289E91121 May 1979Forwards Executed Amend 1 to Indemnity Agreement G-2 & Amend 19 to Indemnity Agreement B-8
ML19305A3717 March 1979Responds to 790301 Telcon Request.Forwards 1977 Form 10K, Annual Rept to Sec Supporting Renewal of License R-47. Form Is Last One Transmitted to Sec Re B&W Merger Into Jr Mcdermott Co
ML19309E07311 April 1980Submits Addl Info Re 791018 Amend Request.Describes Range of Allowable Nonmoderator to Moderator Ratio & Computer Codes Used for front-end Calculations for Analysis of Max Credible Accident
ML19312D86330 April 1980Submits Addl Info Re Equation for Effect of Uncertainty in Dp/Dt at Min Critical Moderator Height for Accident Condition
ML19323F59019 May 1980Forwards Revised Page & App to Amended Reactor Security Plan.Encl Withheld (Ref 10CFR2.790)
ML19331D67429 August 1980Forwards Tech Specs Incorporating Changes Proposed by 790501-02 Ltrs & Submitted in Connection w/780303 Request for Renewal of License R-47
ML19338E9001 October 1980Forwards Executed Amend 20 to Indemnity Agreement B-8, Modifying Prefatory Language of Paragraph 5,Article I Re Transportation
ML19345B64825 November 1980Discusses NRC 801106 Ltr Requesting Submittal of Names of Personnel Responsible for Emergency Planning.Nrc Should Direct Such Requests to AF Olsen
ML19347F28113 May 1981Forwards Endorsement 98 to Nelia Policies NF-111 & NF-83
ML20003E44031 March 1981Forwards Info Re Security Plan,In Response to NRC 810302 Request.Info Withheld (Ref 10CFR2.790)
ML20004D3703 June 1981Forwards Updated Security Plan.Plan Withheld (Ref 10CFR2.790)
ML20004D3714 June 1981Requests Meeting W/Nrc to Discuss Requirements Re Planned Dismantling of Lynchburg Pool Reactor for Termination of License R-47
ML20009B2439 July 1981Forwards Rept Re Critical Experiment Program Authorized by Amend 11 to License CX-10.Experimental Measurements Verified That Core Parameters Are within Prescribed License Limits
ML20010G24410 September 1981Requests That Lynchburg Research Ctr Be Granted Exemption from Requirements for Submittal of Revised Emergency Plan Per 10CFR50.47.Proposed Plan Would Not Be Implemented Until After Facility Fuel Has Been Removed
ML20041C66926 January 1982Forwards Revisions to Facility Security Plan.Revisions Withheld (Ref 10CFR2.790)
ML20052A88023 April 1982Advises That Dismantling & Decontamination of Facility Have Been Completed.Nrc Verification Survey & Facility Release for Unrestricted Use Requested.Survey Results Encl
ML20062D7743 August 1982Forwards Amend 21 to Indemnity Agreement B-8,in Response to NRC
ML20065G73927 September 1982Details Evaluation of Discrepancy Between Electronically Simulated Reactor & Channel Periods Revealed in Calibr Test Performed on Log-N-2 Channel.No Unsafe Condition Existed & No Tech Spec Violation Occurred
ML20069G40023 September 1982Forwards Emergency Plan,Revision 0
ML20073B99018 June 1991Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors
ML20082F10322 November 1983Requests Waiver of Operator Requalification Program & 10CFR55.31(e) Requirement to Permit Operators & Senior Operators to Perform Fuel Handling Functions
ML20082H65415 November 1983Forwards Rev 3 to Security Plan.Rev Withheld (Ref 10CFR2.790)
ML20082H66519 September 1983Forwards Rev 3 to Page 6-2 of Reactor Security Plan.Page Withheld
ML20087N37226 March 1984Forwards Endorsements 108 & 109 to Nelia Policy NF-83, Endorsement 110 to Nelia Policy NF-111 & Endorsement 42 to Maelu Policy MF-84
ML20091P5308 June 1984Requests Exemption from Requirements of 10CFR50.54(r) Re Emergency Plan Due to Dismantling of CX-10 Facility
ML20099D13015 November 1984Forwards Responses to 841012 Questions Re 840807 Application for Dismantlement & Termination of CX-10 FacilityHigh Radiation Area
ML20101S55029 January 1985Requests That Lynchburg Research Ctr Be Granted Authorization to Proceed W/Dismantling & Decontamination of Facility.All Fuel Possessed Under License CX-10 Shipped to DOE Oak Ridge,Tn Facility
ML20116D88917 April 1985Requests Info Re Authorization for B&W to Dismantle & Decontaminate Reactor Facility Near Lynchburg,Va
ML20137M49828 August 1985Responds to NRC Re Violations Noted in Insp Repts 50-013/85-01 & 70-0824/85-05.Corrective Actions:Shipment of Fissle Class 2 Packages Suspended Until Checklist Containing Requirements for Shipments Developed
ML20147D7798 December 1978Concurs That Inspec Rept Contains No Proprietary Info & Agrees to Placing It in NRC PDR
ML20151A50430 March 1988Forwards Executed Amend 22 to Indemnity Agreement B-8, Terminating Agreement
ML20199J9422 July 1986Forwards Revised Section 8 of Dismantling Plan for CX-10 Reactor.Changes Due to Reorganization
ML20206L59024 June 1986Forwards Replacement Table 2-1 Providing Specific Info for Final Survey Rept for License CX-10
ML20239A4274 June 1992Forwards Proposed Survey Plan for Pathfinder Generating Station,Sioux Fall,Sd, for Approval