Letter Sequence Other |
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Results
Other: 05000312/LER-1985-019, :on 851002,reactor Trip Occurred & RCS Temp Decreased to Approx 70 F.Caused by Excessive Steam Loads Due to Two Open Relief Valves on Feedwater Heater 4A.HPI Flow Manually Initiated to Maintain Pressure, 05000312/LER-1985-023, :on 851205,reactor Trip Occurred on High RCS Pressure.Caused by Underfeeding of Main Feedwater Sys During Flow Scaling Procedure.Integrated Control Sys Modules Examined & Refurbished, ML20134A837, ML20137H936, ML20138B213, ML20138R097, ML20138R929
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MONTHYEARML20138B2131985-10-0404 October 1985
Confirmatory Action Ltr Re 851004 Telcon Concerning Return of Facility to Power Operations After 851002 Reactor Trip. Util Must First Conduct Root Cause Analysis of Trip & Provide Briefing to NRC Before Return to Power
Project stage: Other
ML20133K5131985-10-11011 October 1985
Notification of Significant Meeting on 851016 W/Util Onsite to Discuss Root Cause Assessment & Readiness for Resumption of Power Operations Following 851002 Reactor Trip
Project stage: Meeting
ML20133K5891985-10-14014 October 1985
Forwards Action List Providing Util Plan to Resolve Concerns Stemming from 851002 Transient,Per 851010-11 Meetings.Listed Commitments Scheduled for Completion Prior to Restart. Schedule for long-term Items Will Be Submitted by 851118
Project stage: Meeting
ML20133K7191985-10-18018 October 1985
Forwards Supplemental Info Re 851002 Transient,Per NRC Request During 851016 Meeting.Info Includes Main Feed Pump Trip Determination,Hpi a Flow Anomaly,Cooldown of RCS, Cooldown Rate,Tech Specs & Revised Action List
Project stage: Supplement
ML20133P8511985-10-25025 October 1985
Forwards Summary & Supplemental Info Re 851002 Transient, Per 851025 Telcon.Items in Plan Include pre- & post-startup Actions to Determine Root Cause of Event & Initiation of Corrective Programs
Project stage: Supplement
05000312/LER-1985-019, :on 851002,reactor Trip Occurred & RCS Temp Decreased to Approx 70 F.Caused by Excessive Steam Loads Due to Two Open Relief Valves on Feedwater Heater 4A.HPI Flow Manually Initiated to Maintain Pressure1985-10-29029 October 1985
- on 851002,reactor Trip Occurred & RCS Temp Decreased to Approx 70 F.Caused by Excessive Steam Loads Due to Two Open Relief Valves on Feedwater Heater 4A.HPI Flow Manually Initiated to Maintain Pressure
Project stage: Other
ML20134A8371985-11-0101 November 1985
Forwards Addendum to Attachment 5,Part Ii,Rev 1 to Auxiliary Feedwater/Main Feedwater Failure Analysis Contained in
Project stage: Other
ML20138R0971985-11-13013 November 1985
Forwards Rev 2 to Attachment 2 & Addendum NRC-5150 Re HPI a Flow Anomoly,Rev 1 to Attachment 5,Parts I & II Re Auxiliary Feedwater/Main Feedwater Failure Analysis & Attachment 8 Re Oil Levels on safety-related Pumps
Project stage: Other
ML20138R9291985-11-15015 November 1985
Forwards Latest Rev to Action List,Describing Program Plan to Resolve Concerns Stemming from 851002 Transient.All Startup Required Items Completed.All Power Escalation Items Will Be Completed by Full Power Operation
Project stage: Other
ML20137H9361985-12-23023 December 1985
Responds to Violations Noted in Insp Rept 50-312/85-30. Corrective Actions:Instrumentation & Control Procedure I.103 Revised to Include Multiplier Link Change Instructions & Pegging Steam Pressure Controller Setpoints Reduced
Project stage: Other
05000312/LER-1985-023, :on 851205,reactor Trip Occurred on High RCS Pressure.Caused by Underfeeding of Main Feedwater Sys During Flow Scaling Procedure.Integrated Control Sys Modules Examined & Refurbished1986-01-0202 January 1986
- on 851205,reactor Trip Occurred on High RCS Pressure.Caused by Underfeeding of Main Feedwater Sys During Flow Scaling Procedure.Integrated Control Sys Modules Examined & Refurbished
Project stage: Other
1985-10-04
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,o WALNUT CREEK, CALIFORNIA 94596 OCT 4 1985 Docket No. 50-312 License No. DPR-54 CONFIRMATORY ACTION LETTER Sacramento Municipal Utility District P.O. Box 15830 Sacramento, California 95813 Attention:
Mr. R. J. Rodriguez Subj ect: Return of Rancho Seco to Power Operations Geutlemen:
It is my understanding, as a result of our conversation on October 4, 1985, that prior to return of Rancho Seco to power operations you will conduct a root cause analysis of the reactor trip which occurred on October 2, 1985.
In addition, prior to return to power, you will provide the NRC, at its Walnut Creek Office, a briefing of your assessment of the root cause and your justification as to why the Rancho Seco facility is ready to resume power operations.
If my understanding concerning your proposed actions, as summarized above, is not correct, you should promptly notify this office in writing.
Sincerely, fes}..artiiaA ll -
~~
Regional Administhtor cc:
L. G. Schwieger, SMUD G. Coward, SMUD State of CA 8510150243 051004 PDR ADOCK 05000312 S
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