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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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Text
O suun SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street. Box 15830. Sacramento. Cahfornia 95813; (916) 452 3211 July 3, 1981
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DIRECTOR OF NUCLEAR REACTOR REGULATION JUL 1319aN ATTENTION THOMAS M NOVAK ASSISTANT DIRECTOR
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OPERATING REACTORS 3,
NW U S NUCLEAR REGULATORY COMMISSION Q
9 WASHINGTON D C 20555
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DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION UNIT NO 1 TMI ACTION PLAN ITEMS II.E.1.2 AND II.K.2.10 On February 26, 1981 the Sacramento Municipal Utility District committed to submit a final design for the safety grade anticipatory reactor trip, item II.K.2.10 of NUREG 0/37, by October 1,1981.
By this letter, we are revising that commitment date to August 14, 1981.
In addition, we can commit at this time to have the design inforaation required by item II.E.1.2 for the safety grade initiation and flow indication of the auxiliary feedwater system by this same date.
It should be noted that the safety grade initiation of auxiliary feedwater is a portion of the major auxiliary feed-water system upgrade for Rancho Seco Unit 1, as described in our letter of November 17, 1980. The safety grade initiation design information we submit on August 14, 1981, will be a portion of the total design information package for the upgraded auxiliary feedwater system.
We are willing to cooperate to the fullest extent possible in providing this type of information for your review.
If we can provide any other information, please advise.
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/John J. Mattimoe Assistant General Manager and Chief Engineer 8107140647 810703 PDR ADOCK 05000312 P
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