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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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s Docket No. 50-346 License No. NPF-3 7gL,gg Serial No. 533 tustl3[]l6l()fd August 7, 1979 LOWELL E. ROE v,c. pr.
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Fac* tree Developmens (4191 2S9-5242 Director of Nuclear 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:
This letter is to provide you and your staff with an update on the status of the long term items related to the May 16, 1979 Order on the Davis-Besse Nuclear Power Station, Unit 1.
Where applicable, schedules for station modifications identified in the Order are provided below as required by Mr. H. R. Denton's letter of July 6, 1979.
In the >by 16, 1979 order five items were listed under the Part II, long term section.
The status of these items follows:
1.
Continued Auxiliary Feedwater System Performance Review: Toledo Edison is continuing to review the auxiliary feedwater system reliability and performance. An independent evaluation currently underway is expected to be complete and submitted in conjunction with other B&W plant studies in February, 1980.
2.
Integrated Control Systems Failure Modes and Effects Analysis This analysis is being conducted by Babcock & Wilcox.
Currently the final report is expected to be submitted to the Nuclear "egulatory Commission staff by August 9, 1979.
3.
Upgraded Anticipatory Reactor Trip Toledo Edison responded to Item 5 of NRC's Inspection and Enforcement Bulletin 79-05B on May 21, 1979 with the preliminary design of the upgraded anticipatory reactor trip system ( ARTS).
Installation of the ARTS is expected for the first refueling outage twelve months af ter indicated design acceptability.
4.
Continued Attention to Transient Analysis and Procedure for Management of Small Breaks.
Toledo Edison is continuing through the efforts of the B&W Owner's Group in the areas of transient analysis and small reactor coolant breaks.
The scope and schedule of this effort is currently under discussion with your staf f and the Owner's Group.
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l THE TCLECO EDISCN CCMPANY ECISCN PLAZA 3CO MACISCN AVENUE TCLEDO. CHiO 43552 o
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Docket No. 50-346 License No. NPF-3 Serial No. 533 Augus t 7, 1979 Page Two 5.
Continued Operator Training Toledo Edison has factored the recent changes and lessons of TMI-2 into its on-going operator training program.
Very truly yours, i
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