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MONTHYEARML20204A2801982-08-18018 August 1982 Instructions for Calculation of Offsite Dose from Limiting Primary Sys Break Which Does Not Isolate Primary Containment Vent & Purge Valves Project stage: Other ML20076J5441983-08-31031 August 1983 Comments on 810629 Generic Evaluation of NUREG-0737,Item II.E.4.2 Containment Purge & Vent Valve High Radiation Isolation. Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation Unnecessary Project stage: Other ML20084P5971984-04-10010 April 1984 Forwards Final Design Criteria for Resolution of NUREG-0737, Item II.E.4.2(7), Purge & Vent Valve Isolation, Requiring Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation Project stage: Other ML20084L3701984-05-0707 May 1984 Forwards Figures 1 & 2,inadvertently Omitted from 840410 Submittal,Providing Description of Mods Planned to Satisfy Purge & Vent Valve Isolation Requirements of TMI Item II.E.4.2 Project stage: Other ML20097A7211984-09-0505 September 1984 Proposed Amend to Tech Specs,Reflecting Implementation of NUREG-0737,Item II.E.4.2(7) Re Automatic Closure of Containment Purge & Vent Valves on High Containment Radiation Signal Project stage: Other ML20097A7121984-09-0505 September 1984 Application to Amend License NPF-5,changing Tech Specs to Reflect Implementation of NUREG-0737,Item II.E.4.2(7) Re Containment Purge & Vent Valves.Change Adds Limiting Conditions for Operation & Surveillance Requirements Project stage: Request ML20128A0331985-06-25025 June 1985 Forwards Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981, Effective 860101. Interim Relief Requested in Event That Final Review/Approval Not Provided by Program Effective Date.Fee Paid Project stage: Request PNO-II-85-071, on 850724,unit Tripped as Result of High Steam Flow Signal.Caused by Malfunctioning Msiv.Unit out-of-svc for 3 to 5 Days While Valve Repaired & Maint Work Performed1985-07-25025 July 1985 PNO-II-85-071:on 850724,unit Tripped as Result of High Steam Flow Signal.Caused by Malfunctioning Msiv.Unit out-of-svc for 3 to 5 Days While Valve Repaired & Maint Work Performed Project stage: Request ML20137F9931985-08-20020 August 1985 Proposed Revs to Tech Spec Tables 3.2-1 & 4.2-1 Re Purge/Vent Valve Isolation Project stage: Other ML20137F9761985-08-20020 August 1985 Application for Amend to License DPR-57,reflecting Addition of High Radiation Isolation Signal for Containment Purge & Vent Valves.Fee Paid Project stage: Request ML20138B2331985-10-0404 October 1985 Informs That Util on Purge & Vent Mods Contained Proposed Tech Spec Requirements More Restrictive than Those Reviewed by Plant Review Board.Board Will Review Requirements by 851010 Project stage: Other ML20136A7651985-12-23023 December 1985 Forwards Request for Addl Info Re Inservice Insp Program for Second 10-yr Interval.Response Requested within 30 Days of Ltr Receipt Project stage: RAI ML20137E9761986-01-0707 January 1986 Application for Amend to License DPR-57,changing Tech Specs to Add High Radiation Isolation Signal to Containment Purge & Vent Valves.Thirty Days Requested Between Dates of Issue & Effectiveness to Allow Time for Procedure Rev Project stage: Request ML20244D7371986-03-11011 March 1986 Forwards Safety Evaluation Accepting BWR Owners Group 850620 Request for Review of Offsite Radiological Consequences for Accidental Releases Not Meeting NUREG-0737, Item II.E.4.2(7).Regulatory Analysis Also Encl Project stage: Approval ML20204A2781986-04-28028 April 1986 Forwards Request for Addl Info Re Request for Rev to Tech Specs to Reflect Addition of Closure of Containment Purge & Vent Valves on High Containment Radiation Signal.Response Requested within 60 Days Project stage: RAI ML20199K5171986-06-26026 June 1986 Forwards Response to 860428 Request for Info Re Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation Signal.Procedures for Venting Containment Have Separate Sections for Drywell & Torus Project stage: Request ML20235L7161987-07-14014 July 1987 Amends 143 & 78 to Licenses DPR-57 & NPF-5,respectively, Modifying Tech Specs by Adding Limiting Conditions for Operation,Trip Setpoints & Surveillance Requirements for Monitors Project stage: Other ML20235L7221987-07-14014 July 1987 Safety Evaluation Supporting Amends 143 & 78 to Licenses DPR-57 & NPF-5,respectively Project stage: Approval 1985-06-25
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Post Off:ce Box 4545 Atlanta. Georgra 30302 Georgia Power L T. Gucwa the southern electnc system Manager Nuclear Engineenng and Chlef Nuclear Eng neer NED-84-237 May 7, 1984 Director of Nuclear Reactor Regulation Attention: Mr. Johi; F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Cmmission Washington, D. C.
20555 NRC DOGas 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EIMIN I. HA'ICH NUCLEAR PIAVf UNITS 1, 2 NUREG-0737 ITEM II.E.4.2(7), PURGE AND VENT VALVE ISOLATION Gentlenen:
Our subnittal-dated April 10, 1984 provided a description of the modifications planned to satisfy the subject requirenent.
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