Letter Sequence Other |
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Results
Other: ML19309A304, ML19309B051, ML19309B057, ML19317G771, ML19317G888, ML19317G893, ML19317G896, ML19344E612, ML20027D177, ML20262H643, ML20262H646, ML20262H649, ML20262H650, ML20262H653, ML20262H656, ML20262H658
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MONTHYEARML19317G7711976-08-11011 August 1976 Requests Info Re Potential Reactor Vessel Overpressurization & Suggests Preventive Measures Project stage: Other ML19317G8931976-10-14014 October 1976 Forwards Evaluation of Potential Reactor Vessel Overpressurization Events in Response to NRC 760811 Request. Dual Setpoint Feature Will Be Added to Pressurization Pilot Actuated Relief Valve Project stage: Other ML19317H0171976-10-28028 October 1976 Supplements 761014 Analysis of Reactor Vessel Overpressurization Events.Dual Setpoint Feature Added to pilot-actuated Relief Valve.Any Maint on Valve Will Be Performed During Periods of Shutdown Project stage: Supplement ML19309A3041976-12-10010 December 1976 Requests Addl Info within 30 Days Re Proposed Measures to Prevent Reactor Vessel Overpressurization Project stage: Other ML19317G8961977-11-0202 November 1977 Notifies That Facility Overpressure Protection Sys Does Not Meet NRC Criteria.Requests Util Provide Detailed Electrical Circuit & Logic Diagrams, & Propose Tech Specs Re Sys Testing within 45 Days Project stage: Other ML19309B0511977-12-22022 December 1977 Advises That Info Requested in NRC Re Reassessment of Steam Generator & Reactor Coolant Pumps Support Matl to Be Submitted by 780131.Details Re Sys Mods, Providing Overpressure Protection to Be Submitted by 780228 Project stage: Other ML19317G8881978-03-13013 March 1978 Advises That Proposed Design of Dual Setpoint Power Operated Relief Valve Discussed in Util 761014 & 28 Ltrs Is Acceptable.Installation of Dual Setpoint Feature Before 770101 Is Important.Nrc Should Be Notified of Any Delay Project stage: Other ML19309B0571978-03-29029 March 1978 Submits Addl Info Re Proposed Mods to Provide Overpressure Protection in Response to RW Reid 771102 Request.Plant & Procedural Mods Can Be Made in Addition to Previous Dual Setpoint Relief Valve Proposal Project stage: Other ML19344E6121980-07-31031 July 1980 Electrical,Instrumentation & Control Aspects of Low Temp Overpressure Mitigating Sys, Informal Interim Rept Project stage: Other ML20262H6431980-10-14014 October 1980 Elementary Diagram:Reactor Auxiliaries. Sheet 65 Project stage: Other ML20262H6561981-07-27027 July 1981 Piping and Instrument Diagram:Make-up and Purification System. Sheet 3 of 3 Project stage: Other ML20262H6581981-12-0101 December 1981 P&I Diagram:Decay Heat Removal System Project stage: Other ML20052B8201982-04-0909 April 1982 Forwards Request for Addl Info Re Mechanical,Electrical & Instrumentation & Control Aspect of Overpressure Protection Sys During Low Temp Operation Project stage: RAI ML20262H6531982-06-15015 June 1982 Piping and Instrument Diagram Make-up and Purification System. Sheet 2 of 3 Project stage: Other ML20262H6501982-06-15015 June 1982 Piping and Instrument Diagram:Make-up and Purification System. Sheet 1 of 3 Project stage: Other ML20262H6461982-08-0303 August 1982 P&I Diagram:Reactor Coolant System. Sheet 1 of 2 Project stage: Other ML20262H6491982-08-0303 August 1982 P&I Diagram:Reactor Coolant System. Sheet 2 of 2 Project stage: Other ML20027D1771982-10-29029 October 1982 Forwards Addl Info Re Low Temp Overpressure Sys,Per 820409 Request.Addl Low Range Pressure Alarms Not Neccessary,Per Util 770317 & 780329 Submittals.W/Seven Oversize Drawings. Aperture Cards Are Available in PDR Project stage: Other 1978-03-29
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$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S street, Box 15830, Escramento, California 95813; (916) 452-3211 December 22,1977, ;c/T 1,-
Direc' Jr of Nuclear Reactor Regulation Attention:
Mr. Robert W. Reid, Chief n
Operating Reactors, Branch 4
' EO U. S. Nuclear Regulatory Commission
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'.'A Docket No. 50-312 Rancho Seco Nuclear Generating
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Station, Unit No.1
Dear Mr. Reid:
Your letter of September 14, 1977 requested information for a reassessmene of the Rancho Seco Unit No.1 steam generator and reactor coolant pumps support materials. The Sacramento Municipal Utility District replied on October 19, 1977 stating that we could provide this information by December 31, 1977.
The Babcock & Wilcox Company, which is developing this data for the District, has recently informed us that they will require an additional 30 days.
We now expect that this data can be provided by January 31, 1978.
In another letter dated November 2,1977, you requested additional details on our proposed system modifications which will provide reactor vessel overpressure protection. We.1ow estimate it will require an additional 60 days to provide the information in the detail you requested and therefore expect to submit the items requested by February 28, 1978. This time is required to complete the detailed design of these proposed modifications. This level of effort has not been expended to date because the District is waiting for NRC approval of this proposed design change,'since we consider it an unreviewed safety question pursuant to 10 CFR 50.59.
Sincerely yours,
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I J. J. Mattimoe Assistant General Manager and Chief Engineer f " ^
,- 7 AN ELECTRIC SYSTEM S ". R V I N G MoRE THAN 600,000 IN THE HEART OF C ALIF0 R N B A
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