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MONTHYEARML19225B2461979-07-13013 July 1979 Forwards Application for Amend to License NPF-3 Revising Tech Specs to Reflect Changes Re Interim Anticipatory Reactor Trip Sys & Auxiliary Feedwater Flow Indications. Class IV Amend Fee Encl Project stage: Request ML15223A5321979-09-0707 September 1979 Requests Addl Info Re Upgrade of Anticipatory Reactor Trip Project stage: Other ML19256C7381979-10-0303 October 1979 Forwards Addl Info Re Upgrading of safety-grade Anticipatory Reactor Trip Sys (Arts),In Response to 790907 Request.One Oversize Drawing Available in Central Files Project stage: Other ML20213D0761979-12-20020 December 1979 Forwards Safety Evaluation Re Preliminary Design for safety- Grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Main Turbine Generator Project stage: Approval ML19257B4161979-12-20020 December 1979 Forwards Safety Evaluation Re Preliminary Design for safety- Grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Main Turbine Generator Project stage: Approval ML20009G0981981-07-24024 July 1981 Informs That During Next Refueling Outage in Feb 1982, Anticipatory Reactor Trip Sys Will Be Replaced W/Upgraded Sys.Revised Application Will Be Submitted Project stage: Other ML20032A6501981-10-21021 October 1981 Ack Receipt of 810908 Rept Re safety-grade Anticipatory Reactor Sys.Requests That Addl Info Per Encl List Be Forwarded within 14 Days Project stage: Other ML20033C8541981-11-25025 November 1981 Forwards Application to Amend License NPF-3 Project stage: Request ML20033C8621981-11-25025 November 1981 Application to Amend License NPF-3,revising Tech Specs to Reflect Proposed Changes to Sys Integrity Measurements & Improved Iodine Monitoring Programs & Anticipatory Reactor Trip Sys Project stage: Request ML20033C8651981-11-25025 November 1981 Proposed Tech Specs 6.8.4,3.3.2.3,4.3.2.3 & Tables 3.3-15 & 4.3-15 Re Administrative Controls & Anticipatory Reactor Trip Sys Instrumentation.Safety Evaluation & Bases Encl Project stage: Other ML20039F5871982-01-0505 January 1982 Responds to Questions Raised at 811208 Meeting W/Nrc & Consultants Re Anticipatory Reactor Trip Sys.Proposed Channel Functional Test Will Include Pressure Switch.Light Indicating Level Bypass Will Clear When Level Bypass Clears Project stage: Meeting ML20041G3811982-03-0505 March 1982 Application to Amend License NPF-3,allowing Rector Startup W/O Trip & Changing Tech Specs for safety-grade Anticipatory Reactor Trip Sys Project stage: Request ML20041G3791982-03-0505 March 1982 Transmits Application for Amend to License NPF-3,extending Length of Fuel Cycle 3 Project stage: Request ML20052H4931982-05-14014 May 1982 Safety Evaluation Re Final Design & Implementation of safety-grade Anticipatory Reactor Trip on Turbine Trip or Loss of Main Feedwater.Design Satisfies Reactor Protection Sys Safety Requirements & Criteria Project stage: Approval ML20054H2231982-06-15015 June 1982 Notifies That Seismic & Environ Qualification Summary Rept for Anticipatory Reactor Trip Sys Complete & Will Be Submitted by 820709 Project stage: Other ML20054M2011982-07-0707 July 1982 Revises 791003 Response to Request for Addl Info Re Operating Bypasses & Bypass Indications,In Support of 811125 Request for Amend to License NPF-3 Project stage: Request ML20063E2211982-07-0808 July 1982 Forwards Seismic Qualification Rept 3394-1..., Anticipatory Reactor Trip Sys Seismic Qualification Test Plan, Seismic Simulation Test Program... & Environ Qualification Rept..., in Response to NRC 820514 Request Project stage: Other ML20062F2651982-07-27027 July 1982 Concludes That Anticipatory Reactor Trip Sys Bypasses Classification as Operating Bypass Is Unacceptable Unless Addl Features to Alert Operator to Remove Bypasses Are Added Project stage: Other IR 05000346/19820191982-07-27027 July 1982 IE Insp Rept 50-346/82-19 on 820713.No Noncompliance Noted. Major Areas Inspected:Followup of Prompt Public Notification/Warning Sys Project stage: Request ML20065H9181982-09-29029 September 1982 Responds to Re NUREG-0737,Item II.K.2.10, Anticipatory Reactor Trip Sys (Arts). Adequate Features Available to Alert Operator to Remove Bypass When Automatic Bypass Removal Not Required Project stage: Other 1982-01-05
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%sm EDISON ACHAAD P. CROUSE U.Y "
(4191 Pa9 $221 License No. NPF-3 Docket No. 50-346 Serial No. 824 June 15, 1982 Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
Your letter (log no. 992) of May 14,1982 requested the Toledo Edison schedule for submittal of the Seismic and Environmental Qualification Summary Report for Anticipatory Reactor Trip System (ARTS; NUREG-0737 item II.K.2.10) for the Davis-Besse Nuclear Power Station Unit 1.
These reports are now completed. Our present schedule calls for submittal of these reports to you by July 9, 1982.
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DB-1 NRC Resident Inspector OY S206230123 h 03 M ADOCK o l
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PDR THE TOLED0 EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652
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