Letter Sequence Meeting |
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Results
Other: ML19282C737, ML20027D070, ML20154G705, ML20154J794, ML20205H758, ML20210K842, ML20212D134, ML20212D154, ML20212D166, ML20236M353, ML20236M366, ML20236P351, 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 Adequacy
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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
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
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
ML20212D1661986-12-0505 December 1986
Rev 1 to Emergency Feedwater Initiation & Control Auxiliary Feedwater Sys Description
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
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
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
1986-09-12
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1SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT [] 6201 s Street. P.O. Box 15830, Sacramento CA 95852-1830.(916) 452-3211 RJR 86-27 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA January 17, 1986 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION FRANK J MIRAGLIA JR DIRECTOR PWR-B DIVISION U S NUCLEAR REGULATORY COMMISSION WASHINGTION D C 20555 DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION UNIT NUMBER 1 STATUS OF EMERGENCY FEEDWATER INITIATION AND CONTROL (EFIC) IMPLEMENTATION
REFERENCES:
R. J. Rodriguez to H. L. Thompson letter dated 10/25/85 (RJR 85-531)
SMUD/NRC meeting in Bethesda on 10/23/85 As discussed in the above references the District has accelerated its efforts in order to install a majority of tne EFIC system during the upcoming Cycle 8 Refueling Outage.
The District has revised its Living Schedule to accommodate the expanded scope.
In summary the scope involves the following aspects:
Install four (4) instrument channels (each OTSG)
Low range level Wide range level Pressure Provide power to previously installed EFIC cabinets Connect EFIC to plant computer monitoring system Install four (4) channel MFW flow to each MFW line Connect flux to MFW flow circuits into Reactor Protection System (RPS)
Connect RPS and Safety Features Actuation System (SFAS) to EFIC Install N2 backup power to AFW/MFW control valves 00 0
8601220137 860117 PDR ADOCK 050 2
P
l FRANK J MIRAGLIA January
, 1986 Initiate automatic EFIC closure of the AFW full flow recirculation line Replace existing auto start circuits with EFIC initiation of AFW pumps Integrate EFIC controls in the Control Room Replace ICS and SFAS valve activation signals with EFIC actuation of AFW control valves Replace ICS control of ADV's with EFIC control of ADV's Provide EFIC controls for ADV's and AFW flow control valves at the remote shutdown panel.
If there any question concerning the increased EFIC Cycle 8 scope, please contact Mr. Jerry Delezenski at Rancho Seco.
1 i
R. J. R0 RIGUEZ k
ASSISTANT GENERAL AGER NUCLEAR i
RJ86 Page 2