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Issue date | Title | Topic | |
---|---|---|---|
ML20205T649 | 7 November 1988 | Ack Receipt of to Chairman Zech Re Alchemie Applications to Operate Facility for Separation of Stable Isotopes at Oak Ridge,Tn & Construct Similar Facility at Oliver Springs,Tn | |
ML20154P396 | 27 September 1988 | Forwards Info in Preparation for ACRS Subcommittee on Safeguards & Security 881006 Meeting.Encls Withheld (Ref 10CFR2.790) | |
ML20154N968 | 25 May 1988 | Recommends That ACRS Begin Review Schedules Upon Agreement That Viable Util Restart Plan Established & That ACRS Consider Subcommittee Site Visit & Meeting in Early Jul Followed by Full Committee Meeting in mid-Jul | |
ML20154P067 | 28 April 1988 | Requests Close Coordination W/Edo to Ensure That Review of Shutdown Nuclear Power Plants Complete | |
IR 05000528/1985012 | 25 September 1985 | Forwards 850806 & 0730 Ltrs & Insp Rept 50-528/85-12 Per ACRS 811215 Request for Info Re Startup Experience on Unit 1 Prior to Loading on Unit 2.Unit 2 Fuel Load Scheduled for Nov.Initial Criticality Expected by Jan 1986 | |
ML20197J694 | 2 May 1985 | Forwards Addl Info in Response to 850226 Request Re Emergency Evacuation Procedures During Seismic Events from Other Countries & Earthquake Emergency Planning Studies. W/O Encl | Earthquake |
ML20140E685 | 12 February 1985 | Discusses Followup Items of 841101-03 ACRS 295th Meetings, Per 841204 Memo.Seismic Design Margin Program Expected to Be Completed by FY86.Addl Sys Interaction Studies at Facility Would Not Result in Significant Improvement in Risk | Probabilistic Risk Assessment Scram Discharge Volume |
ML20054G582 | 15 June 1982 | Responds to 820512 Memo Re Control of Occupational Doses by Prevention of Transport & Buildup of Radioactive Crud,By Removal of Radionuclide Deposits & Minimization of Failure of Major Plant Components | |
ML20140G928 | 9 April 1982 | Forwards,For Review,Seismic site-specific Spectra Info,Per Telcon & Request by D Okrent.Comments Will Determine Discussion Topics at ACRS Subcommittee on Midland 820520-21 Meetings | Earthquake |
ML20235C401 | 17 July 1978 | Informs That on 740821,agreement Reached to Assist Arcs in Early Identification of Potential Problem Areas & Potentially Difficult Novel Features for Each Application. Comparison of Principal Design Characteristics of NSSS Encl | |
ML20137D881 | 14 June 1978 | Responds to ACRS 770117 & 0217 Recommendations for Review of Sys Design for Safe Shutdown & Shutdown Heat Removal to Assure Adequate Seismic Design Margins.Final Rept Will Be Developed Based on Current Available Info | Safe Shutdown |
ML20137D641 | 8 March 1978 | Forwards Case Responding to Allen Re Seismicity in Region of Facilities | |
ML20137D576 | 1 March 1978 | Forwards J Allen Ltr to L Reiter Re Seismicity in Site Region,Per Request | |
ML20235C944 | 23 September 1975 | Assesses Plant Application for Ol,Per 740821 Agreement to Render Technical Assistance.No Const or Licensing Delays Anticipated Pending Resolution of Concern Re Dynamic Loads on Containment Resulting from LOCA & Relief Valve Action | |
ML20235F637 | 30 January 1975 | Submits Comments on Technical Issues Addressed in Lj Koch to WR Stratton,Recommending That ACRS Reconsider Position on High Pressure Testing of Drywell Structure Described in ACRS on Allens Creek Station | Probabilistic Risk Assessment Fatigue Rule |
ML20155F001 | 12 January 1974 | Forwards Responses to Inquiries for Use by Subcommittee Prior to 740117-18 Meeting.Responses Will Form Basis for Further Discussions W/Staff | |
ML20235E925 | 21 December 1972 | Forwards to Applicants Re Consequences of Postulated Pipe Failures Outside Containment Structure | |
ML20235E914 | 8 December 1972 | Forwards Util Re Reporting Requirements of Tech Specs for Listed Plants & to Util Re QA Program for Listed Plants | |
ML20235E665 | 16 November 1972 | Forwards to Util Requesting That Analyses Be Performed Re Changes in Shape of Scram Reactivity Curve & Requesting Addl Info Concerning Valve Failures | |
ML20235E345 | 29 September 1972 | Forwards Util Providing Info Re Availability & Reliability of HPCI Sys for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 | |
ML20235D577 | 17 February 1972 | Forwards Div of Reactor Licensing & 720124 Discussion & Conclusions Re 20% Operation of Plant for ACRS Info | |
ML20235C148 | 29 December 1971 | Transmits Div of Reactor Licensing ,Which Requests Addl Info on Design Features of Energy Absorbing Sys,As Info for ACRS | |
ML20235E291 | 26 October 1971 | Forwards Div of Reactor Licensing 711018 Request for Rept on Large Number of Unusual Occurrences During Operation of Plant,For Info | |
ML20235E179 | 26 October 1971 | Forwards Util 711005 Rept of 710905 & 09 Occurrences & 711018 Transmittal of Summary of HPCI Problems Experienced During Startup Testing at Monticello Plant | |
ML20235D864 | 4 October 1971 | Forwards Util 710915,24 & 28 Ltrs Re Inoperable HPCI Sys on 710904,failure of ECCS Pump on 710915 & 710918 Occurrence Involving HPCI Sys,Respectively | |
ML20235E596 | 20 August 1971 | Forwards Rept to ACRS Re Wh Zimmer Nuclear Power Station Unit 1 CP Review, for Review | |
ML20235B702 | 21 June 1971 | Forwards Util 710526 & 0611 Ltrs Transmitting Amends 11 & 12,respectively to Application for License.Amends 11 & 12 Also Encl | |
ML20235D510 | 11 June 1971 | Transmits Util Reporting Unusual Occurrences on 710420,26 & 0502 | |
ML20235D159 | 11 May 1971 | Transmits Util Re Occurrence Relating to off-gas Monitors & Util Reporting AO Relating to Safety/ Relief Valve Setting Exceeding 1,080 Psig | |
ML20235C832 | 1 May 1971 | Forwards Util 710428 Twx Advising That HPCI Sys Became Inoperable on 710422 & Div of Reactor Licensing Advising That Plant Must Be Shut Down,For Info | |
ML20235D911 | 22 April 1971 | Forwards Div of Reactor Licensing 710407 Request for Addl Info for Review of Design Repts 7 & 8 | |
ML20235D892 | 11 March 1971 | Forwards Util Transmitting Design Rept 8, Small Steam Line Break, for Info | |
ML20235D757 | 17 February 1971 | Forwards Util Summarizing Status of Items on Structural Design | |
ML20235F165 | 1 December 1970 | Forwards Design Repts in Response to ACRS Concerns on Containment Analysis & Seismic & Structural Design | |
ML20235B656 | 5 November 1970 | Forwards Preliminary Rept to ACRS, for Review.Rept Presents Preliminary Comments on Proposed Plant | |
ML20235C649 | 2 September 1970 | Forwards AEC Re Util Request for Reduction of Design Pressure for Drywell & Torus of Containments | |
ML20235C565 | 11 August 1970 | Forwards Util Transmitting Rept Containing Addl Info on Pressure Suppression Concept in Response to 700427 & 0528 Ltrs | |
ML20235C509 | 1 June 1970 | Forwards AEC Requesting Addl Info Re Proposed Reduction in Design Pressure for Containment Drywell & Torus for Plant | |
ML20235C412 | 27 May 1970 | Forwards Util Transmitting GE Rept Entitled, Addl Info Pressure Suppression Concept Test Data Rept, for Review.Util Requested That Rept Be Withheld from Public Disclosure | |
ML20235C369 | 4 May 1970 | Forwards Listed Items,Including Util Transmitting Table for Insertion in Rept on Proposed Containment Design Pressure for Brunswick Steam Electric Plant & AEC 700427 Response to Util Request for Design Change in Containment | |
ML20244E141 | 2 May 1970 | Forwards H Denton to RW Staehle Re Recommendations for Course of Action to Be Taken for Repair of Safe Ends on Reactor Vessels of Utils for Committee Use | |
ML20235C269 | 30 April 1970 | Forwards Util Informing of Mgt Changes in Company | |
ML20140G901 | 28 April 1970 | Forwards 10CFR30-36 & 150,for Info in Connection W/Review of Midland.W/O Encls | |
ML20140G835 | 15 April 1970 | Submits Agenda for ACRS Subcommittee on Midland Plant 700424 Meeting in Chicago,Il to Discuss Radioactive Matl in Process Steam,Potential for Subsidence,Seismic Design Criteria, Emergency Plans & Flood Protection Level | |
ML20140G850 | 12 February 1970 | Submits Agenda for ACRS Subcommittee on Midland Plant 700424 Meeting in Washington,Dc to Discuss Emergency Plans,Adequacy of ESF & Protection Sys,Containment Design,Silting of ECCS Reservoir & Steam Purity & Monitoring | |
ML20235B890 | 9 December 1969 | Forwards Exhibit H of Util CP Application for Facility for Review | |
ML20235B754 | 24 November 1969 | Forwards Div of Reactor Licensing 691124 Rept Concerning AEC Review of Util Facility for ACRS Review at Dec Meeting | |
ML20235B730 | 20 November 1969 | Forwards 691119 Amend 9 to License Application for Review. W/O Encl | |
ML20235B649 | 4 November 1969 | Forwards S&W Forwarding Proprietary SWND-2, Loctvs,Computer Code to Determine Pressure & Temp Response of Pressure Suppression Containments to LOCA & Util Requesting Rept Be Withheld for Review | |
ML20235C145 | 8 October 1969 | Forwards Second Supplemental Rept to ACRS Re Util Application to Const Brunswick Steam Electric Plant Units 1 & 2 for Review |