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Issue date | Title | Topic | |
---|---|---|---|
ML19242A774 | 1 August 1979 | Forwards,Per s Ramos Request,Analyses of Design Basis Accident & Loca,In Support of Renewal of License R-47 | |
ML19254E459 | 18 October 1979 | Requests 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. | |
ML19256E225 | 26 October 1979 | Forwards Executed Amend 20 to Indemnity Agreement B-8 & Amend 2 to Indemnity Agreement G-2 | |
ML19257B926 | 16 January 1980 | Forwards Page 18a for Insertion in 791023 Rept Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. | |
ML19260B244 | 3 December 1979 | Submits Addl Info in Support of Request for Amend to License CX-10.Discusses Probability of Max Credible Accident & Need for Amend to Tech Specs | |
ML19269C521 | 29 January 1979 | Responds to NRC 780821 Ltr.Forwards Info Re Financial Data, Business Conducted,Organizational Structure,Radiological Monitoring,Safety Hazards & Tech Specs | Safe Shutdown Incorporated by reference |
ML19276H023 | 15 August 1979 | Responds 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 | |
ML19289D183 | 16 February 1979 | Responds 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 | |
ML19289E911 | 21 May 1979 | Forwards Executed Amend 1 to Indemnity Agreement G-2 & Amend 19 to Indemnity Agreement B-8 | |
ML19305A371 | 7 March 1979 | Responds 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 | |
ML19309E073 | 11 April 1980 | Submits 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 | |
ML19312D863 | 30 April 1980 | Submits Addl Info Re Equation for Effect of Uncertainty in Dp/Dt at Min Critical Moderator Height for Accident Condition | |
ML19323F590 | 19 May 1980 | Forwards Revised Page & App to Amended Reactor Security Plan.Encl Withheld (Ref 10CFR2.790) | |
ML19331D674 | 29 August 1980 | Forwards Tech Specs Incorporating Changes Proposed by 790501-02 Ltrs & Submitted in Connection w/780303 Request for Renewal of License R-47 | |
ML19338E900 | 1 October 1980 | Forwards Executed Amend 20 to Indemnity Agreement B-8, Modifying Prefatory Language of Paragraph 5,Article I Re Transportation | |
ML19345B648 | 25 November 1980 | Discusses NRC 801106 Ltr Requesting Submittal of Names of Personnel Responsible for Emergency Planning.Nrc Should Direct Such Requests to AF Olsen | |
ML20003E440 | 31 March 1981 | Forwards Info Re Security Plan,In Response to NRC 810302 Request.Info Withheld (Ref 10CFR2.790) | |
ML20004D370 | 3 June 1981 | Forwards Updated Security Plan.Plan Withheld (Ref 10CFR2.790) | |
ML20004D371 | 4 June 1981 | Requests Meeting W/Nrc to Discuss Requirements Re Planned Dismantling of Lynchburg Pool Reactor for Termination of License R-47 | |
ML20009B243 | 9 July 1981 | Forwards Rept Re Critical Experiment Program Authorized by Amend 11 to License CX-10.Experimental Measurements Verified That Core Parameters Are within Prescribed License Limits | |
ML20010G244 | 10 September 1981 | Requests 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 | |
ML20041C669 | 26 January 1982 | Forwards Revisions to Facility Security Plan.Revisions Withheld (Ref 10CFR2.790) | |
ML20052A880 | 23 April 1982 | Advises That Dismantling & Decontamination of Facility Have Been Completed.Nrc Verification Survey & Facility Release for Unrestricted Use Requested.Survey Results Encl | |
ML20062D774 | 3 August 1982 | Forwards Amend 21 to Indemnity Agreement B-8,in Response to NRC | |
ML20065G739 | 27 September 1982 | Details 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 | |
ML20069G400 | 23 September 1982 | Forwards Emergency Plan,Revision 0 | |
ML20082F103 | 22 November 1983 | Requests Waiver of Operator Requalification Program & 10CFR55.31(e) Requirement to Permit Operators & Senior Operators to Perform Fuel Handling Functions | |
ML20082H654 | 15 November 1983 | Forwards Rev 3 to Security Plan.Rev Withheld (Ref 10CFR2.790) | |
ML20082H665 | 19 September 1983 | Forwards Rev 3 to Page 6-2 of Reactor Security Plan.Page Withheld | |
ML20091P530 | 8 June 1984 | Requests Exemption from Requirements of 10CFR50.54(r) Re Emergency Plan Due to Dismantling of CX-10 Facility | |
ML20099D130 | 15 November 1984 | Forwards Responses to 841012 Questions Re 840807 Application for Dismantlement & Termination of CX-10 Facility | High Radiation Area |
ML20101S550 | 29 January 1985 | Requests 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 | |
ML20137M498 | 28 August 1985 | Responds 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 | |
ML20147D779 | 8 December 1978 | Concurs That Inspec Rept Contains No Proprietary Info & Agrees to Placing It in NRC PDR | |
ML20151A504 | 30 March 1988 | Forwards Executed Amend 22 to Indemnity Agreement B-8, Terminating Agreement | |
ML20199J942 | 2 July 1986 | Forwards Revised Section 8 of Dismantling Plan for CX-10 Reactor.Changes Due to Reorganization | |
ML20206L590 | 24 June 1986 | Forwards Replacement Table 2-1 Providing Specific Info for Final Survey Rept for License CX-10 |