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MONTHYEARML19289F7591979-05-0808 May 1979
Notification of 790508 Meeting W/Util in Bethesda,Md to Present Design for Control Grade hard-wired Reactor Trips Based on Loss of Feedwater & Turbine Trip Conditions
Project stage: Meeting
ML19263E9421979-05-15015 May 1979
Summary of 790508 Meeting W/Util & Bechtel in Bethesda,Md Re Licensee Design of Hard Wire control-grade Reactor Trip Caused by Loss of Feedwater &/Or Turbine Trip & Other Matters Related to NRC Shutdown Order
Project stage: Meeting
ML19208A9221979-05-18018 May 1979
FOIA Request for Documents Re Sept 1977,Apr 1978,Jan 1979 & Mar 1979 Incidences at Facility,Transcripts from NRC 790405 Executive Session,Mcmillan 790416 Testimony to ACRS, Toledo Edison 790423 Conference & 790425 Meeting
Project stage: Request
ML19246B0761979-05-18018 May 1979
Requests Addl Info in Order to Evaluate Adequacy & Acceptability of Response to Order Issued 790516
Project stage: Other
ML19289E9071979-05-19019 May 1979
Evaluation of Transient Behavior & Small Reactor Coolant Sys Breaks in 177 Fuel Assembly Plant,790516. Vol 3, Revision 1
Project stage: Other
ML19289E9051979-05-22022 May 1979
Forwards Evaluation of Transient Behavior & Small Reactor Coolant Sys Breaks in 177 Fuel Assembly Plant,790516, Vol 3,Revision 1
Project stage: Other
ML19289F3811979-05-23023 May 1979
Forwards Modified Operating Procedures Complying W/Nrc 790509 Order.W/Oversized Encl in Central Files Only
Project stage: Other
ML19259C7751979-06-27027 June 1979
Draft Fr Notice Re Authorization to Resume Operation
Project stage: Draft Other
ML19259C7831979-06-27027 June 1979
Draft Safety Evaluation Re Licensee Compliance W/Nrc 790516 Order.Licensee May Restart Facility
Project stage: Draft Approval
ML19259C7691979-06-27027 June 1979
Draft Ltr Forwarding Safety Evaluation & Fr Notice Re Authorization to Resume Operation
Project stage: Draft Approval
ML19259C7661979-06-27027 June 1979
Discusses Review of Util Actions Re NRC 790516 Order. Shutdown No Longer Required.Safety Evaluation & Draft Ltr to Licensee Encl
Project stage: Draft Approval
ML19224D3441979-06-29029 June 1979
Provides Info Re Util Handling of RO 79-062,in Response to NRC 790629 Request.Established Procedures Were Followed & Proper Evaluation & Dispositions Were Made in Reporting Failure of Auxiliary Feedwater Suction Switches
Project stage: Other
ML19225C7021979-06-29029 June 1979
Expresses Concern Over Util Failure to Inform NRC of 790521 RO 79-062 Involving Inoperable Auxiliary Feedwater Suction Pressure Switches & out-of-tolerance Pressure Setpoints. Submits Questions Re Mgt Awareness & Lack of Communication
Project stage: Other
ML19289G2651979-07-0202 July 1979
Safety Evaluation Re Licensees Compliance W/Nrc 790516 Order
Project stage: Approval
ML19289G2631979-07-0202 July 1979
Forwards Revised Safety Evaluation for Facility Re 790516 Shutdown Order
Project stage: Approval
ML19207B7291979-07-0505 July 1979
Transcript of NRC 790705 Meeting in Washington,Dc Re Review of Facility Operation.Pp 1-84
Project stage: Meeting
ML19207B7161979-07-0505 July 1979
Transcript of 790705 Public Meeting in Washington,Dc Re Order Per Request for Hearing on Facility Operation. Pp 1-15
Project stage: Meeting
ML19207A7381979-07-0606 July 1979
Evaluation of Licensee Compliance W/Nrc 790516 Order. Unit 1 May Resume Operation
Project stage: Other
ML19248D0161979-07-11011 July 1979
Summary of 790629 Meeting W/Util in Bethesda,Md to Discuss LER 79-062 Concerning Inoperability of Pressure Switches Associated w/DB-1 Auxiliary Feedwater Sys
Project stage: Meeting
ML15245A1051979-07-16016 July 1979
Requests Evaluation of Semiscale Small Break Experiment W/Small Break Computer Program by 790901
Project stage: Other
ML19242D0791979-08-0707 August 1979
Submits Update on Status of long-term Items Per NRC 790516 Order.Discusses Auxiliary Feedwater Sys,Control Sys,Failure Modes & Effects Analysis,Transient Analysis & Procedure for Mgt of Small Breaks
Project stage: Other
ML16138A4101979-08-15015 August 1979
Summary of 790718 Meeting W/Util in Bethesda,Md Re B&W Small Break LOCA Analyses
Project stage: Meeting
1979-06-29
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%ms EDISON Docket NO. 50-346 LOWELL E. ROE License No. NPF-3 I.*c' $I.*.'$1ce.m (419) 259 5242 May 22, 1979 Director of Fuclear Reactor Regulation Attention:
Mr. Robert N. Reid, Chief Operating Reactors Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Reid:
Under date of May 7, 1979, B&W transmitted to Dr. Roger Mattson the document
" Evaluation of Transient Behavior and Small Reactor Coolant System Breaks in the 177 Fuel Assembly Plants, Volumes I & II", which provided information related to the plant behavior during certain transients with special emphasit on various small break scenarios. This information was in response to previous commitments of B&W to supply such information and was intended to be in response to commitments in my April 27, 1979 letter (Serial No. 497). The information in the B&W document was for all B&W 177 Fuel Assembly plants in-cluding a lowered loop configuration, and the single raised loop configuration which is the Davis-Besse Nuclear Power Statien, Unit 1.
Our detailed review of these documents showed that although the Davis-Besse configurations and details were generally included, the documents were pre-pared more specifically for the lowered loop configuration plants. This could lead to possible misinterpretation in translating these results specifically for Davis-Besse operation.
In order to provide a more meaningful document for our use and hopefully for yours, while providing additional information supplementing Volumes I & II, we have worked with B&W to develop Volume III which includes information specific for Davis-Besse Unit 1.
This Volume III will be the source document from which changes to existing station procedures or new procedures are being developed as a result of these further analyses, ge Yours very truly, D
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2052 129 LER: cts cc: J. Zwetzig Operating Reactors Branch No. 4 Division of Operating Reactors - USNRC - Washington D. C. 20555 THE TOLECO ED! SON COMPANY EDISON PLAZA 300 MADISON ADENUE TOLECO, OHIO 43652 rgg052,90YN I )
