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Category:ARCHIVE RECORDS
MONTHYEARML20154J2731998-10-0202 October 1998
Audit Rept on Implementation of GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants, on 980915-17
ML20206S1181998-05-11011 May 1998
Rev 2 to NSP-21Q-302, Charpy V-Notch (Cvn) Test Data Files for Monticello RPV Plates,Curve Fits of Cvn Data & Calculation of Plant Specific Chemistry Factors
ML20216H4021998-04-0707 April 1998
Rev 5 to 98-106, Evaluation for LOCA Aging at 1880 Mwt
ML20206S1331998-04-0606 April 1998
Rev 1 to NSP-21Q-304, Pressure Test,Non-Critical Core Operation & Critical Core Operation P-T Curve Development
ML20249C5241998-04-0303 April 1998
Rev 2 to Calculation 96C2913-C016, HP & LP Turbine Condenser Anchorage Capacity Evaluations
ML20249C5211998-01-13013 January 1998
Rev 0 to Calculation 96C2913-C20, Monticello Unit 1 Limited Analysis for Baseplate Qualification,Computer Analysis & Hand Calculations
ML20199G9951997-12-19019 December 1997
Rev 0 to Calculation 97C2999-C-001, T-44 Seismic Displacement Evaluation
ML20141B9341997-06-18018 June 1997
Rev 0 to Calculation V75100.NSP97.00501, Determination of Containment Overpressure Required for Adequate NPSH of Low Pressure ECCS Pumps
ML20249C5221997-06-10010 June 1997
Rev 0 to Calculation 96C2913-C015, Gang Hangar Support
ML20148S6531997-04-0808 April 1997
RHR Room Temp Response to GE Ltrs GLN-97-017 & GLN-97-019, Rev 0
ML20136B5431997-01-0202 January 1997
Low Pressure ECCS Net Positive Suction Head
ML20134D2231996-10-17017 October 1996
Press Release III-96-63, Aerial Radiation Measurements Planned for NPPs in Wisconsin & Minnesota
ML20199H0471995-11-0808 November 1995
Rev 0 to Calculation C-017, LAR RB-AB-L1
ML20199H0201995-11-0808 November 1995
Rev 0 to Calculation C-017, LAR RB-AB-L1
ML20199H0531995-10-10010 October 1995
Rev 0 to Calculation C-016, Seismic Analysis of Standby DG Day Tank T-45A & B
ML20084C3501995-05-19019 May 1995
Estimation of Cable Spreading Room Equipment Floor Loading
ML20058N9841993-07-29029 July 1993
Package Consisting of Employee Concerns Programs for Plant
ML20073S8521993-04-30030 April 1993
Rev 2 to Calculation 1961-2.2-001, Verification of Toxpuff & Toxevap Lotus 1-2-3 Spreadsheet
ML20073S8491993-04-11011 April 1993
Rev 1 to Calculation 1961-2.2-004, MNGP Toxic Chemical Analysis Probability Analysis of Trucking Accidents
ML20136B5491993-01-29029 January 1993
Rev 1 to ECCS Analysis for Mnp W/Nukon Insulation Sys
ML20140G8021992-07-0101 July 1992
Rev 0 to Control Room & Offsite Dispersion Factors
ML20079N3621991-11-11011 November 1991
Responds to NUMARC Survey in Support of NRC License Renewal Rulemaking Covering Util Environ Monitoring & Ecological Studies program,1989 Annual Rept,Water Monitoring Summary, 1987 Annual Rept & Creel Survey 1982 Annual Rept
ML20064E4861982-10-14014 October 1982
Slide Presentation for Northern States Power Co - NRC 821014 Meeting
ML19305B7641980-02-21021 February 1980
Slide Presentation Entitled, Monticello Feedwater Nozzle Bypass Leakage Temp Monitoring.
ML20090M5361974-03-21021 March 1974
Package Consisting of Util Responses to AEC Questions on Facility High Energy Line Breaks Outside of Containment
ML20127N9251970-01-16016 January 1970
Press Release Discussing Util Intention to Seek License to Operate Plant.Acrs Rept Encl
ML20128A8311969-12-0404 December 1969
Record of Telcon W/Applicant Re Drawings Showing Addl Independence Between Redundant SGTS Schematic Drawings
1998-05-11
[Table view]
Category:TELEPHONE OR VERBAL CONVERSATION RECORD
MONTHYEARML20128A8311969-12-0404 December 1969
Record of Telcon W/Applicant Re Drawings Showing Addl Independence Between Redundant SGTS Schematic Drawings
1969-12-04
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UNITED STATES ATOMIC ENERGY COMMISSION k W ASWNGToN, D C. 20$45
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December 4, 1969 Files *"7/f//
TERU t V .# Mo6r , hief, Instrumentation & Power Technology Branch, DRL TEI40N REVIEW OF HONTICELLO PLANT SGTS SCHEMATIC DRAWINGS; DOCKET #50-263 As stated in my memo to files dated November 14, 1969 (RT-857A), the applicant had agreed at our November 4 meeting to provide some addi-tional independence between the redundant Standby Gas Treatment Systems CVI and to submit the details of the modification to us for review.
Dwgs #A511-3203, Sheets 1-3 (Chg. B) were subsequently sent to us.
To assist us in the review we arranged a conference call with the Participating in applicant and his representatives on December 2.
the call were NSP C. Ross C , E_.
G. L. Davis J. W. Lingafelter L. Wolf H. Clinton AEC D. Vassallo T. Ippolito D. Sullivan Functionally, the SGTS has not been changed; the " preferred" system (System A) is selected initially and, if it fails, System B is selected after a time delay of 50 seconds. 'rne modifications relate to the manner in which this is accomplished.
In the original design the control circuits of System A also controlled certain portions of System B. For exampic, the starting relays of System B were deenergized by the relays in System A which were actuated when System A was successful. In sunar.ary, the two control circuits were not independent.
In the modified design there is complete electrical independence between the two systems. There are two independent flowmeters in the common duct (we can call them 'A' and 'B') which control only their respective systems. For example, if System A fails to start, this condition would 9212030465 DR 691204 ADOCK 05000263 u PDR
Telcon 2 December 4, 1969 t
be sensed by flowmeter 'B' which would then start System B independently of the System A controllers. Thus, the only lack of independer.ce arises !
from the process itself. This does have at least one potential common failure modes a useless flow via a broken duct in System A which would l appear to System B as successful operation.
We were able to complete our review of the SGTS drawings during the course of the telcon.
....,..r.+-
D. F.-Sullivan Instrumentation & Power RT-902 A Technology Branch DRL:1&PTB:DFS Division of Reactor Licensing cc F. Schroedar S. Levine R. Boyd R. DeYoung ['
D. Huller D. Vassallo '
T. Ippolito 4
'Y * * * " vvt4'f TW$ q-- .p,W.3
