Letter Sequence Draft Approval |
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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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UNITED sTATss
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NUCLEAR REGULATORY COMMISSION
.E WASHINGTO N, O. C. 20555 2.
s, JL*/ g 7 ;g79 Docket No..
50-346 E WnANDUM FOR: Chairnan Hendrie Comissioner Gilinsky Ccmissioner Kennedy Com:nissicner 3radford Comnissioner Ahearne FRCM:
Harold R. Centon, Director Office of Nuclear Reac:ce Regulation THRU:
Lee V. Gossick N )TA
- Executive Director of Ocerations SU3 JECT-REMOVAL OF SUSPENSICN OF CPERATICN OF DAVIS 3 ESSE The Staff nas completed its review of tne imediate actions perfor ed by tne Toleco Edison Company and The Cleveland Electric Illuminating Comcany (tne licensees) in response to tne Ccmission's Orcer af May 15, 1979.
I am satisfied that tne licensees have satisfactorily ccmoletec tne crescribed actions, provided acceptable analyses, and specified accrecriate imolementing procecures. Accordingly, in accordance wi th the terms of the Ccmission's Order, I prepose to inforn the licensee that the suspension of operation of Davis Besse previously imcased is nc longer required.
I will, newever, not take this action pending the Ccmissicn's deternination of the request under the Orcer for a hearing of Ohio State Senator Tim McCor ack which has been feraarded to the Secretary by CELD. Assuming the Ccanission dces not require a hearing prior to the lif ting of the suspension and does not raise any cbjection to my preposed action, it will then be premotly imolemented.
In addition to Senator McCormack's e=auest for a hearing uncer the Orcer,
'ne Comissicn nas received correscendence from Mr. Terry Locge, Counsel for the Toleco Coaliticn fce Safe Energy ex::ressing concerns accut tne Cavis 3 esse Facility, requesting both ruiemaking and acticn ;nder 10 CFR 12.2C6, and asking nat hearings be held in connection wi-n *nese recuests prior to restart of tne facility.
I have inforred Mr. Ledge that I ex::ect to resolve his 2.2C6 request promotly, but not before resarction af ocera-tiens, and that nis ralemaking request nas been foruarded to tne Secretary of the Ccanission.
Enciased for Cemission consideration are ccpies of the Staff Safety Evalua-tien and tne preposed letter to :ne licensees. Cocies of.nis remorancum and enclosures are also being provided to :eti-icner Senator McCcenack, to
- re licensees and to Mr. Locge.
T R.i.
[y Harold R. Denton, Direc:cr Office of Nuclear Reactor Regulaticn
.,.2 Enclosures as stated C, d o _. i-7 908150 / M
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