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MONTHYEARML20064N2771983-02-0808 February 1983
Forwards Addl Info Re Training for Mitigating Core Damage. Station Superintendent Receives Adequate Experience in Regular Duties Which Abrogates Need for Formal Training for Mitigating Core Damage
Project stage: Request
ML20072G0341983-03-21021 March 1983
Responds to Generic Ltr 83-10 Re Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Extension to 830701 Requested for Submittal of Schedule for Resolution of Issue
Project stage: Other
ML20090F6971983-06-30030 June 1983
Notifies of Postponement of Submittal of Plans & Schedules for Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pump (Generic Ltr 83-10) Until 830815, Due to Delay in Receipt of Generic Rept from B&W
Project stage: Other
ML20080C1031983-08-12012 August 1983
Responds to Generic Ltr 83-10 Re Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pump. Schedule to Be Submitted by 830930,since B&W Generic Proposal Re Std Lower Loop Configuration to Be Evaluated
Project stage: Other
ML20080N9771983-10-0303 October 1983
Forwards Plan & Schedule for Resolution of NUREG-0737,Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps, (Generic Ltr 83-10),per NRC 830208 Request.Operating Procedures for Pumps to Be Revised
Project stage: Other
ML20085N5701983-10-27027 October 1983
Advises of Delay in Submittal of Operating Procedures for Trip of Reactor Coolant Pumps (TMI Item II.K.3.5 & Generic Ltr 83-10).Program Reviewed in Light of Generic Ltr 83-31 Re Abnormal Transient Operating Guidelines
Project stage: Other
ML20091H9241984-05-29029 May 1984
Advises That Rept Re Resolution of TMI Action Item II.K.3.5 Automatic Trip of Reactor Coolant Pumps, in Response to Generic Ltr 83-10,will Be Submitted by 840731
Project stage: Other
ML20097C7021984-07-31031 July 1984
Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis
Project stage: Other
ML20097C6901984-09-0707 September 1984
Forwards Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis, (B&W Document 77-1152840-00) for Raised Loop Plant in Response to Generic Ltr 83-10 & TMI Item II.K.3.5
Project stage: Other
ML20207F6051986-12-29029 December 1986
Forwards Response to Generic Ltr 86-05 Re Implementation of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps, Addressing plant-specific Concerns,Including Instrumentation Uncertainties & Operator Training
Project stage: Other
ML20155G0611988-06-0909 June 1988
Advises That Implementation of NUREG-0737,Item II.K.3.5 Complete.Util 861229 Response Stated That Facility Procedures Require Reactor Coolant Pump Trip When RCS Subcooling Margin Falls Below 20 F
Project stage: Other
1983-08-12
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Text
TOLEDO
% EDISON
$__Uce Docket No. 50-346 License No. NPF-3 Serial No. 1051 May 29, 1984 Director of Nuclear Reactor Regulation Attention:
Mr. John F..Stolz Operating Reactor. Branch No. 4 Division of Operating Reactors United Staten Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
On October 3, 1983-(Serial No. 987) Toledo Edison responded to Mr. D. G.
Eisenhut's letter of February 8, 1983 (Log No. 1222) concerning Resolution of TMI Action Item II.K.3.5 " Automatic Trip Reactor Coolant Pumps" (Generic Letter 83-10).
In that letter we planned to submit our report for the raised loop unit two months after receipt of the report for the lower loop units. The revisions by B&W on the applicable sections on the raised configuration will take longer than originally planned. The report for Davis-Besse Nuclear Power Station Unit No. I will be submitted by July 31, 1984.
Very truly yours, ff
="
RPC: GAB:lah cc: DB-1 NRC Resident Inspector do
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THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 KO PDR
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