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MONTHYEARML19257D8081980-01-31031 January 1980
Forwards Proposed Mods to Improve post-accident Monitoring Capability.Mods Adequately Address Lessons Learned Task Force Category a Design Review Items & Description of Mods Contained in Section 2.1.8 of NRC
Project stage: Other
ML19340E1291980-12-30030 December 1980
Responds to NUREG-0737.Util Working W/Oh State Univ on Feasibility Evaluation of long-term Program to Phase Out Need for Shift Technical Advisor.Commitment Supersedes All Previous Commitments
Project stage: Other
ML20041C1731982-02-19019 February 1982
Notifies of Delays Re Implementation of NUREG-0737 Items II.F.1.2 & II.B.3.Station Vent Stack Monitor Mods to Be Performed After Outage.Reactor post-accident Sampling Sys Operational,Pending Delivery of Operator Panel
Project stage: Other
ML20065H9941982-09-29029 September 1982
Advises That Schedule for Responding to NUREG-0737,Item II.B.3, Post-Accident Sampling Sys, Will Be Provided by Mar 1983,in Response to 820721 Request
Project stage: Other
ML20069L5741983-04-25025 April 1983
Forwards Info for post-implementation Review of NUREG-0737, Item II.B.3, Post-Accident Sampling Sys, Per Util .Certain Requested Info Will Not Be Available Until After Completion Date of 831231
Project stage: Other
ML20115A2601984-07-19019 July 1984
Requests That Encl Request for Addl Info Be Transmitted to Util.Info Needed to Continue Review of plant-specific Emergency Operator Guidelines Associated W/Procedures Generation Package
Project stage: Request
ML20094Q2721984-08-14014 August 1984
Forwards Addl Info Concerning NUREG-0737,Item II.B.3 Re post-accident Sampling,Per 840719 Request.Rexnord Model 340 Portable Oxygen Monitor Used to Determine Dissolved Oxygen in Reactor Coolant Sample
Project stage: Other
1982-09-29
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% sus EDISON RCHAHo P. Cnaust vc. %w,a Peut 1,M I4191259 5221 Docket No. 50-346 License No. NPF-3 Serial No. 863 September 29, 1982 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
This is in response to your letter dated July 21, 1982 (Log No. 1036) concerning a schedule for responding to the attached information for NUREG-0737 Item II.B.3; (Post Accident Samplir System) Request for Information. Toledo Edison expects to provid. 2 response by the end of March 1983 for Davis-Besse Nuclear Power Station Unit F3. 1.
Very truly yours, ffkp ='
RPC: GAB: lab cc: DB-1 NRC Resident Inspector CY THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652
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8210050333 820929 PDR ADOCK 05000346 P
PDR
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