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MONTHYEARML19259D1761979-05-16016 May 1979
Anticipatory Trip Functions for 177 Fuel Assembly Plants
Project stage: Other
ML15223A5311979-09-0707 September 1979
Notifies of Review of Responses to IE Bulletin 79-05B. Requests Addl Info Re Proposed Design Description & Implementation Schedule for safety-grade Anticipatory Reactor Trip
Project stage: Approval
ML19259D1741979-10-0909 October 1979
Forwards Anticipatory Trip Functions for 177 Fuel Assembly Plants
Project stage: Other
ML20214J2911979-12-20020 December 1979
Safety Evaluation Re Preliminary Design for safety-grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Turbine Trip
Project stage: Approval
ML20214J2801979-12-20020 December 1979
Safety Evaluation Re Preliminary Design for Upgrading Present control-grade Anticipatory Reactor Trip Sys for Loss of Main Feedwater & Turbine Trip to safety-grade
Project stage: Approval
ML20213D0761979-12-20020 December 1979
Forwards Safety Evaluation Re Preliminary Design for safety- Grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Main Turbine Generator
Project stage: Approval
ML20213D0721979-12-20020 December 1979
Forwards Safety Evaluation Approving Preliminary Design for safety-grade Anticipatory Reactor Trip on Loss of Feedwater & Turbine Trip.Requests Addl Info for Final Design Approval
Project stage: Approval
ML19257B4161979-12-20020 December 1979
Forwards Safety Evaluation Re Preliminary Design for safety- Grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Main Turbine Generator
Project stage: Approval
ML19257A9711979-12-20020 December 1979
Forwards Safety Evaluation Approving Preliminary Design for safety-grade Anticipatory Reactor Trip on Loss of Feedwater & Turbine Trip.Requests Addl Info for Final Design Approval
Project stage: Approval
ML19326D9901980-07-21021 July 1980
Notifies That Equipment Being Added to Reactor Protection Sys Cabinets Is of Sufficient Mass as to Require New Seismic Analysis of Cabinets.Analysis Requires Approx 20 Wks.Info Will Be Provided in Time to Allow for Final Design Approval
Project stage: Other
ML20009B0071981-07-0303 July 1981
Revises Submittal Date to 810814 for Final Design for Safety Grade Anticipatory Reactor Trip & Design Info for Safety Grade Initiation & Flow Indication of Auxiliary Feedwater Sys,Per NUREG-0737,TMI Items II.E.1.2 & II.K.2.10
Project stage: Other
ML20010G0141981-09-0808 September 1981
Forwards B&W Rept Auxiliary Feedwater Sys & 36 Oversize Drawings,Per 810703 Commitment to Submit Final Design Info Re NUREG-0737,Items II.K.2.10 & II.E.1.2.Aperture Cards Are Available in PDR
Project stage: Other
ML20031G5731981-10-19019 October 1981
Responds to Requesting Addl Info Safety Grade Anticipatory Reactor Trip.Forwards Procedure I-111,Revision 9, Reactor Protection Sys Channel Calibr & Procedure I-108A,Revision 17, Reactor Protection Sys Channel a Test
Project stage: Other
ML20032A6501981-10-21021 October 1981
Ack Receipt of 810908 Rept Re safety-grade Anticipatory Reactor Sys.Requests That Addl Info Per Encl List Be Forwarded within 14 Days
Project stage: Other
1980-07-21
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SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, Box 15830 Sacramento, California 95813; (916) 452-3211
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October 9,1979 Mr. Robert W. Reid, Chief Operating Reactor Branch No. 4 Division of Operating Reactor U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Occket No. 50-312 Rancho Seco Nuclear Generating Station, Unit No. 1
Dear Mr. Reid:
In its letter of October 8,1979, the Sacramento Municipal Utility District conmitted to provide a report titled " Anticipating Trip Function for 177 FA Plants". This letter forwards the report.
If you have questions concerning this report, please contact us.
Sincerely, b
Ys+.
./ John [. Mattimoe Assistant General Manager and Chief Engineer 1160 328
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79101604-76