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MONTHYEARML19282C7371979-04-27027 April 1979
Informs That Facility Will Shut Down 790428 to Complete safety-related Actions.Also Lists Commitments to Actions Per Ofc of Nuclear Reactor Regulation 790425 Status Rept.Info Re Auxiliary Feedwater Sys Upgrade & Guidelines Encl
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
ML20054C2111982-04-15015 April 1982
Responds to 820317 Request for Info Re TMI Action Plan Items I.A.3.1,II.B.2,II.B.3,II.B.4,II.E.1.2,II.E.4.2,II.F.1 & II.K.2.10,per NUREG-0737.Anticipatory Reactor Trips Will Be Upgraded to Safety Grade During Sept 1982 Outage
Project stage: Request
ML20052F3171982-05-0505 May 1982
Advises That Unit 1 Will Be Shut Down Until Approx 820801 to Perform Repairs on Auxiliary Feedwater Header in Steam Generator.Mods Required by NUREG-0737 Now Scheduled to Begin 830101 Rather than 820901
Project stage: Other
ML20058E3251982-07-21021 July 1982
Submits Data Re Loading of Auxiliary Feedwater Pumps Onto Diesel generated-powered Bus,In Response to NRC 820701 Request for Addl Info Concerning Util 800218 Submittal
Project stage: Request
ML20027D0701982-10-22022 October 1982
Comments on NRC Safety Evaluation of NUREG-0737,Items II.E.1.2.1 & II.E.1.2.2 Re Auxiliary Feedwater Automatic Initiation & Flow Indication,Transmitted by . Safety Grade Flow Instrumentation Info Due by Jan 1983
Project stage: Other
ML20028A7811982-11-15015 November 1982
Requests Addl Info Re Auxiliary Feedwater Sys,Tmi Action Plan Item II.E.1.2,in Order to re-examine Design of Sys to Be Installed.Detailed Electrical Schematic Diagrams Showing Actual Automatic Initiation Circuitry Requested
Project stage: Other
ML20137H9091986-01-17017 January 1986
Summarizes Expanded Scope of Living Schedule to Accommodate Accelerated Efforts to Install Majority of Emergency Feedwater Initiation & Control Sys During Upcoming Cycle 8 Outage,Per & 851023 Meeting
Project stage: Meeting
ML20154J7941986-02-27027 February 1986
Responds to IE Bulletin 85-001 Re Steam Binding of Auxiliary Feedwater Pumps.Procedures for Monitoring Fluid Conditions within Feedwater Sys to Identify Binding & for Restoring Sys to Operable Status If Binding Occurs Provided
Project stage: Other
ML20154G7051986-03-0303 March 1986
Provides Functional Description of Emergency Feedwater Initiation & Control Cycle 8 Refueling Outage Scope,Per Rj Rodriguez .Significant Changes in Design to Accommodate Resource/Equipment Lead Time Listed
Project stage: Other
ML20210K8421986-09-12012 September 1986
Rev 1 to Design Basis Rept
Project stage: Other
NL-86-672, Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy1986-09-26026 September 1986
Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy
Project stage: Other
ML20212D1541986-11-14014 November 1986
Rev 2 to Design Basis Rept
Project stage: Other
ML20212D1341986-12-0505 December 1986
Proposed Tech Spec Sections 3.1, RCS, 3.4, Steam & Power Conversion Sys, 3.5, Instrumentation Sys, 4.1, Operational Safety Review & 4.8, Auxiliary Feedwater Pump Periodic Testing
Project stage: Other
ML20212D1131986-12-0505 December 1986
Application to Amend License DPR-54,revising Listed Tech Specs,Including Sections 3.1, RCS, 3.4, Steam & Power Conversion Sys & 3.5, Instrumentation Sys. W/13 Oversize Figures.Fee Paid
Project stage: Request
ML20212D1661986-12-0505 December 1986
Rev 1 to Emergency Feedwater Initiation & Control Auxiliary Feedwater Sys Description
Project stage: Other
ML20205H7581987-03-26026 March 1987
Proposed Tech Specs,Clarifying Limiting Conditions of Operations & Surveillance Requirements for Emergency Feedwater Initiation & Control Sys Time Delay Modules
Project stage: Other
ML20205H6901987-03-26026 March 1987
Rev 1 to Proposed Amend 152 to License DPR-54,clarifying Limiting Conditions of Operation & Surveillance Requirements for Emergency Feedwater Initiation & Control Sys.Description of Proposed Changes & Safety Analysis Encl
Project stage: Request
ML20236M3661987-06-11011 June 1987
Rev 3 to Design Basis Rept
Project stage: Other
ML20236M3531987-07-31031 July 1987
Proposed Tech Specs,Clarifying Proposed Limiting Conditions of Operation & Addl Surveillance Requirements for Emergency Feedwater Initiation & Control Sys
Project stage: Other
ML20236M3391987-07-31031 July 1987
Application for Amend to License DPR-54,consisting of Rev 2 to Proposed Amend 152,clarifying Proposed Limiting Conditions of Operation & Addl Surveillance Requirements for Emergency Feedwater Initiation & Control Sys
Project stage: Request
ML20236P3511987-11-0606 November 1987
Proposed Tech Specs Re Limiting Condition for Operation of Instrumentation Sys
Project stage: Other
ML20236P3411987-11-0606 November 1987
Supplemental Application for Rev 2 to Proposed Amend 152 to License DPR-54,revising Tech Specs Re Limiting Conditions for Operation of Instrumentation Sys
Project stage: Supplement
ML20207A6401987-12-0404 December 1987
Forwards Request for Addl Info Based on Preliminary Review of Proposed Inservice Testing Program for Plant.Meeting to Initiate Resolution of Encl Issues Proposed for 880106 & 07
Project stage: RAI
ML20234F5711987-12-24024 December 1987
Forwards Formal Responses to NRC Questions from 871215 Exit Meeting at Conclusion of Insp of Util Response to IE Bulletin 79-27
Project stage: Meeting
ML20148C6301988-01-0505 January 1988
Forwards Amend 93 to License DPR-54 & Safety Evaluation. Amend Revises Criteria Re Auxiliary Feedwater Sys & Adds Specific Requirements Associated W/Emergency Feedwater Instrumentation & Control Sys
Project stage: Approval
1986-02-27
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$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramento, Califomia 95813; (916) 452-3211 October 22, 1982 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION JOHN F STOLZ CHIEF OPERATING REACTORS BRANCH 4 US NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION UNIT N0 1 NUREG 0737 ITEMS II.E.1.2.1 AND II.E.1.2.2 AUXILIARY FEEDWATER (AFW) AUTOMATIC INITIATION AND FLOW INDICATION Your September 7,1982 letter, transmitted the NRC staff's Safety Evaluation Report on the Rancho Seco AFW system. This review was conducted based on the proposed AFW upgrade described in attachments to the District's submittals of November 17, 1980, September 8, 1981 and July 27, 1982.
Your September 7,1982 letter, further stated that the upgraded AFW system modifications will be completed during the next refueling outage presently scheduled to begin in January, 1983.
Based on conversations with your Sydney Miner, we believe that the NRC staff has an understanding that the AFW upgrade which includes the safety grade EFIC (Emergency Feedwater Instrumentation &
Control) system will not be completed until the refueling outage after fuel cycle 6 which is currently scheduled for late 1984/early 1985. However, safety grade AFW flow instrumentation and an interim safety grade initiation of AFW will be provided during the next refueling outage now scheduled for January, 1983.
There are two additional items which we feel should be made relative to the Safety Evaluation Report transmitted with your September 7,1982 letter.
First, your review of the upgraded AFW system was based upon B&W Document No.
15-1120580-Revision 01. Minor changes continue to be identified as the manu-facture proceeds and consequently, the document is revised as needed. Since the NRC staff has accepted the design as described in Revision 01, the District proposes to review changes from that revision under the provisions of 10CFR50.59 and provided that no unreviewed safety question is identified, we will not seek further NRC review prior to implementation. The second item relates to a state-ment in our November 17, 1980 letter, which said that the upgraded AFW design This implies will automatically load both AFW pumps on the emergency) diesels.
that the motor driver on the dual drive AFW pump (P-318 will be automatically 8210280228 821022 W
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JOHN F STOLZ CHIEF Page 2 October
, 1982 started.
This is not the District's intent. Automation actuation of P-318 will be via the automatic startup of the turbine driver and the necessary associated valves will be powered by an emergency diesel generator. The motor drive on P-318 will be capable of manual start from diesel power in the event of failure of the turbine to start.
?>L John J. Mattimoe General Manager