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Issue date | Title | Topic | |
---|---|---|---|
ML20093K328 | 11 October 1984 | Requests Discontinuance of Document Distribution to Offshore Power Sys,Which Closed on 840901 | |
ML20083K730 | 27 March 1984 | Responds to IE Bulletin 83-08.Circuit Breakers Not Purchased or Specified for safety-related Applications.No Further Design Activities Planned Prior to Obtaining Customer | |
ML20073B517 | 8 April 1983 | Responds to Generic Ltr 83-10D Re Resolution of TMI Action Item II.K.3.5, Study Need for Auto Trip of Reactor Coolant Pumps. Resolution Will Be Initiated When Customer for First FNP Is Attained & Final Design Efforts Begun | |
ML20071E832 | 1 March 1983 | Ack Receipt of Generic Ltr 83-07 Re Requirements of Nuclear Waste Policy Act of 1982.Lists Reasons for Not Entering Into Waste Disposal Contract W/Doe | |
ML20069G529 | 17 September 1982 | Forwards Revisions to Environ Protection Plan Per 820915 Telcon | |
ML20041D686 | 24 February 1982 | Advises of Westinghouse Nuclear Energy Sys Organizational Changes.Organizational Charts Encl | |
ML20039E742 | 21 December 1981 | Delegates Authority for Review of Info Sought to Be Withheld from Public to Pb Haga,Director of Power Sys Technology | |
ML20062M299 | 11 December 1981 | Forwards Applicant 811211 Proposed Findings of Fact & Conclusions of Law in Form of Proposed Initial Decision. Document Supersedes Applicant 790601 Proposed Partial Findings of Fact in Form of Proposed Initial Decision | |
ML20038B591 | 12 November 1981 | Submits Info Requested in 811106 Telcon W/Nrc Re Turbine Missile Shield | Safe Shutdown Turbine Missile |
ML20049A737 | 17 September 1981 | Confirms 810917 Telcon Re Containment Design Pressure.Util Reluctantly Commits to Design Containment Vessel to Meet ASME Svc Level a Stress Limits for Design Interval Pressure of 25 Psig at Ambient Temp | Operating Basis Earthquake |
ML20010J374 | 10 September 1981 | Submits Addl Info Re Equipment Qualification Modifying 810902 Response Re Generic Issue A-24.Safety-related Equipment Will Be Qualified in Accordance w/NUREG-0588, Category I Requirements | |
ML20010E610 | 28 August 1981 | Corrects Date of Ref Cited in 810818 Ltr Responding to NRC Request for Info Re Generic Technical Issues A-2 & A-36 | |
ML19346A415 | 11 June 1981 | Forwards Draft App C to Plant Design Rept, in Response to post-TMI Requirements.App C Will Be Filed Formally at Conclusion of Technical Review & Upon Resolution of NRC Concerns | Safe Shutdown Non-Destructive Examination Grab sample Fire Barrier Hydrostatic Probabilistic Risk Assessment Earthquake |
ML20008F567 | 24 February 1981 | Urges Inclusion of OPS Mfg License Application in Proposed Rulemaking Defining TMI accident-related Requirements for Pending CP & Mfg Licenses | |
ML19332A083 | 5 September 1980 | Requests That Schedule Be Established for Completing Review of Application for Mfg License & That NRC Resources Be Committed for That Purpose.Nrc Should Initiate Review of Util 800715 Responses to NUREG-0660 | |
ML19320D462 | 15 July 1980 | Forwards 36A93, OPS Responses to Post-TMI NRC Requirements, Revision 1.Rept Represents Vast Majority of New Info Required to Support Issuance of Mgt License. Requests Meeting W/Nrc at Earliest Possible Convenience | |
ML19323C632 | 6 May 1980 | Forwards Review Re Applicability of post-TMI Action Plan Requirements Contained in Draft 3 of NUREG-0660 & Applicability of Item III.A.2-2 of NUREG-0654.Response to All Action Plan Items,Except Item II.B.8 Planned for | |
ML19305C424 | 18 March 1980 | Forwards Response to NRC 791017 Ltr Requesting Addl Info Re Core Thermohydraulic Effects | |
ML19257A301 | 21 December 1979 | Forwards 36A93, Responses to Post-TMI NRC Requirements, Per IE Bulletin 79-06,NRC 791010 & 1109 Ltrs Re TMI Lessons Learned Task Force short-term Requirements & TMI Lessons Learned Task Force Final Rept. | |
ML19253B419 | 5 October 1979 | Requests Plan & Schedule for Completion of Review of Application for Mfg License | Turbine Missile |
ML19253B591 | 26 September 1979 | Agrees to Use McGuire Nodalization Scheme or More Detailed Model for Analyses of Pressure Transient in Steam Generator Encl Following Steam Line Rupture | |
ML19208D555 | 21 September 1979 | Forwards Revision 2 to Rept 36A59, Fnp Core Ladle Design & Safety Evaluation. Revision Reflects Sandia Lab Comments Transmitted in NRC 790605 Ltr & Results of 790724 Meeting W/Nrc & Sandia Lab | |
ML19208B028 | 14 September 1979 | Forwards Responses to ACRS Subcommittee 790725 Questions Re Core Ladle & TMI-2.Response Modifies Design Presented in Rept 36A59 Floating Nuclear Plant Core Laddle Design & Safety Evaluation. Requests ACRS Meeting in Oct | |
ML19247A049 | 19 July 1979 | Discusses Effect of Core Ladle on Reactor Cavity Pressure Analysis.Supersedes 790711 Ltr | |
ML19225A026 | 13 July 1979 | Forwards Assessment of Potential Impacts of Releases of Insoluble Core Debris Following Postulated Core Melt Accident.Transport of Radioactivity as Particulate Matter Is Considered Highly Unlikely | Veliger |
ML19241B923 | 11 July 1979 | Provides Addl Info for Plant Design Rept Re Effect of Core Ladle on Reactor Cavity Pressure Analysis | |
ML19241B893 | 9 July 1979 | Discusses Problems Experienced W/Pipe Support Baseline Design,As Outlined in IE Bulletin 79-02 & Transmitted to ASLB on 781207.Criteria for Design of Steel Embedments Prevents Problems Occurring | |
ML19289F547 | 6 June 1979 | Forwards Revision 1 to 790517 Core Ladle Rept (OPS Rept 36A59) | |
ML19282D163 | 11 May 1979 | Discusses Current Activities of Product Assurance Organization:Review & Approval of Drawings & Specs.Seeks to Obtain Mfg License & Customers as Soon as Possible. & Approve Drawings & Specifications | |
ML19283B582 | 12 February 1979 | Informs NRC of Recent Changes of Upper Mgt at Offshore Power Sys | |
ML19274D562 | 31 January 1979 | Submits Addl Info Re Containment Shell Buckling Criteria & Application.Requests Concurrence W/Approach Before Inclusion in Rept | |
ML19289C893 | 11 January 1979 | Responds to 780809 Ltr Which Forwarded NRC Guidelines Re Component Cooling Water Supply to Reactor Coolant Pumps.As Discussed in Util 781031 Ltr & NRC 781122 Ltr,Category 4 Matters Will Be Addressed During Final Design Review Stage | |
ML19256A715 | 5 January 1979 | Forwards Amend 26 to Application for License to Mfg Floating Nuclear Plants.Amend Deals Soley W/Subj Matter of the Plant Design Rept | |
ML19322A064 | 21 December 1978 | Notifies NRC That Document SS15A18/A, Portable Fire Extinquishers-Sys Specs Is Being Forwarded to Us Coast Guard for Review & Approval | |
ML19263B065 | 21 December 1978 | Responds to NRC Request of 781106 for Addl Info Re Containment Shell Buckling Criteria & Application of Criteria to Static Buckling Load | Hydrostatic Operating Basis Earthquake |
ML19263A725 | 15 December 1978 | Forwards Revised Language to Motion to Plead Matter in Controversy Filed 780905.Areas Remaining for ASLB Resolution Are Identified | |
ML20150E896 | 15 December 1978 | Disagrees w/780817 Licensing Sched Review Comm(Lsrc)Meeting Conclusions That Plant Design Rept Req Significant Updating to Assure Licensability.W/Enc Outlining Disagreements | |
ML20150D481 | 29 November 1978 | Forwards 781103 EPA Ltr to OPS Re Riverine & Estuary Siting of Floating Nuc Plants & Requests Its Inclusion in the Comments Section of RDES-11 to Complete the Record | |
ML20204D539 | 29 November 1978 | Requests That Bd Defer Ruling on Applicant'S Motion to Plead a Matter in Controversy,As Applicant Will Send Rev Language Documenting Areas of Agreement During Week of Dec 11,1978, Based on Comments Received from Staff | |
ML20147D803 | 28 November 1978 | Informs NRC That Attach Elec on-line Diagrams Are Being Forwarded to USCG for Review & Approval.W/Att List | |
ML20150E620 | 21 November 1978 | Forwards Newspaper Article Re Death of Kenneth Walton, Intervenor Pro Se in Proceeding, & Requests Deletion of His Name from Service Lists | |
ML20148F766 | 31 October 1978 | Responds to 781012 NRC Ltr W/Addl Info Re Sched for Update Review of Plant Design Rept |