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Category:ARCHIVE RECORDS
MONTHYEARML20217K7641999-09-27027 September 1999 Rev 0 to DCR 990247, Containment Overpressure Duration Requirement (Addendum to Calculation QDC-1000-M-0781) ML20217K7441999-04-23023 April 1999 Rev 1 to QDC-0010-M-0396, Quad Cities Station Unit 2:ECCS Strainer Head Loss Estimates ML20155A6741998-09-29029 September 1998 Rev 1 to Calculation QDC-1000-M-0454, Short Term Rhr/Core Spray Pump NPSH Analysis - Design Basic Loca ML20155B5221998-09-29029 September 1998 Rev 1 to QDC-1000-M-0535, Long-Term Rhr/Core Spray Pump NPSH Analysis - Design Basis Loca IA-97-451, Plant Issues Matrix1997-12-0909 December 1997 Plant Issues Matrix ML20203J7501997-12-0909 December 1997 Plant Issues Matrix ML20135B8021996-12-0606 December 1996 Press Release III-96-073, Quad Cities Nuclear Plant Rated 'Good' in Two Areas, 'Acceptable' in Two Areas in NRC Performance Assessment ML20199K6041996-12-0303 December 1996 Rev 1 to 93C2806.3-C002, Cable Tray & Conduit Raceway Limited Analytical Review (LAR) for USI A-46 at Quad Cities Nuclear Station. Page 71 of 98 of Incoming Submittal Not Included ML20101Q7541996-04-0808 April 1996 Rev 3 to Calculation 9200-E0-S,demonstrating That Reduction of Torsional Loads from Auxiliary Steel Will Significantly Reduce IC Values for Beam & Connections ML20106J7921996-04-0404 April 1996 Calculation for Checking Functional Status of Beam B4 & Cheek Plate Connection at Right End of Beam B10 in Quad Cities,Unit 1 Southeast,Rhr Corner Room ML20101Q0581996-03-30030 March 1996 Flaw Evaluation for 02BS-F14 Weld in Quad Cities Unit 1 Loop B Recirculation Sys ML20101Q0481996-03-19019 March 1996 Flaw Evaluation for 02AS-S4 Weld in Quad Cities Unit 1 Loop a Recirculation Sys ML20101Q0271996-03-18018 March 1996 Flaw Evaluation for 02AS-F2 Weld in Quad Cities Unit 1 Loop a Recirulation Sys ML20101Q0361996-03-11011 March 1996 Flaw Evaluation for 02AD-F12 Weld in Quad Cities Unit 1 Loop a Recirculation Sys ML20086E0891995-07-0303 July 1995 Shroud Head Contact on Upper Support ML20091G3461995-06-15015 June 1995 Rev 0 to Shroud Repair Program for Quad Cities Unit 2, Shroud Head Contact on Upper Support ML20091G3561995-06-15015 June 1995 Rev 0 to Shroud Repair Program for Quad Cities Unit 2, Shroud Head Contact on Upper Support ML20101E8161993-11-22022 November 1993 Power Recovery Probabilities for Quad Cities Ipe ML20126G1021992-12-17017 December 1992 Rev 0 to RSA-D-92-07, LPCI Room Temperature Response Due to Loss of Room Cooler at Dresden Station ML20058M1641992-11-18018 November 1992 Quad-Cities 2/I Safety-Related Continuous Load Running/ Starting Voltages ML20058M1451992-07-31031 July 1992 Quad-Cities 1/I Safety-Related Continuous Load Running/ Starting Voltages ML20101Q7661992-06-16016 June 1992 RHR Pump 1C/1D Discharge Line 1-1008B-18 ML20058M1711992-05-20020 May 1992 Second-Level Undervoltage Relay Setpoint ML20058M1581992-05-0404 May 1992 Quad-Cities 1/II Safety-Related Continuous Load Running/ Starting Voltages ML20058M1541992-04-20020 April 1992 Evaluation of Toshiba Dgcwp Starting Voltage ML20058M1671992-04-15015 April 1992 Quad-Cities 2/II Safety-Related Continuous Load Running/ Starting Voltages ML20058M1491992-04-15015 April 1992 Evaluation of 460-Volt Diesel Generator Cooling Pump Min Starting Voltage ML20058M1741992-04-0303 April 1992 Evaluation of DG 2 Cooling Water Pump Cooler Fan a & B Min Starting Voltage ML20065S8691990-11-16016 November 1990 Draft Setpoint Calculation for RPS Turbine Control Valve Fast Closure Trip Function ML20247R3711989-09-18018 September 1989 Package of Three FOIA Requests ML20247M2831988-01-11011 January 1988 Rev 1 to Quad Cities,Control Room Dose Analysis,Plot of Dose as Function of Standby Gas Treatment Sys Effluent ML20247M3191987-09-24024 September 1987 Control Room Dose Analysis, (Suppl to Dose Calculation 546Y-M-07) ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20247M2891987-04-0101 April 1987 Infiltration Analysis ML20212P1571987-02-28028 February 1987 News Release Informing That Util Selected Wastechem Corp as Prime Contractor for Processing & Disposal of 55 Control Rod Blades from Facilities Spent Fuel Pools.Responsibilities Include Radiation Monitoring & Waste Disposal ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML19316A8861980-03-25025 March 1980 Slide Presentation Entitled, Barrier Fuel Program. ML20084L6921967-05-0505 May 1967 Wire Svc Press Release Re Wall Collapsing on 670505. Undetermined Number of Men Injured & Trapped Under Debris 1999-09-27
[Table view] Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML20217K7641999-09-27027 September 1999 Rev 0 to DCR 990247, Containment Overpressure Duration Requirement (Addendum to Calculation QDC-1000-M-0781) ML20217K7441999-04-23023 April 1999 Rev 1 to QDC-0010-M-0396, Quad Cities Station Unit 2:ECCS Strainer Head Loss Estimates ML20155A6741998-09-29029 September 1998 Rev 1 to Calculation QDC-1000-M-0454, Short Term Rhr/Core Spray Pump NPSH Analysis - Design Basic Loca ML20155B5221998-09-29029 September 1998 Rev 1 to QDC-1000-M-0535, Long-Term Rhr/Core Spray Pump NPSH Analysis - Design Basis Loca ML20199K6041996-12-0303 December 1996 Rev 1 to 93C2806.3-C002, Cable Tray & Conduit Raceway Limited Analytical Review (LAR) for USI A-46 at Quad Cities Nuclear Station. Page 71 of 98 of Incoming Submittal Not Included ML20101Q7541996-04-0808 April 1996 Rev 3 to Calculation 9200-E0-S,demonstrating That Reduction of Torsional Loads from Auxiliary Steel Will Significantly Reduce IC Values for Beam & Connections ML20106J7921996-04-0404 April 1996 Calculation for Checking Functional Status of Beam B4 & Cheek Plate Connection at Right End of Beam B10 in Quad Cities,Unit 1 Southeast,Rhr Corner Room ML20101Q0581996-03-30030 March 1996 Flaw Evaluation for 02BS-F14 Weld in Quad Cities Unit 1 Loop B Recirculation Sys ML20101Q0481996-03-19019 March 1996 Flaw Evaluation for 02AS-S4 Weld in Quad Cities Unit 1 Loop a Recirculation Sys ML20101Q0271996-03-18018 March 1996 Flaw Evaluation for 02AS-F2 Weld in Quad Cities Unit 1 Loop a Recirulation Sys ML20101Q0361996-03-11011 March 1996 Flaw Evaluation for 02AD-F12 Weld in Quad Cities Unit 1 Loop a Recirculation Sys ML20086E0891995-07-0303 July 1995 Shroud Head Contact on Upper Support ML20091G3461995-06-15015 June 1995 Rev 0 to Shroud Repair Program for Quad Cities Unit 2, Shroud Head Contact on Upper Support ML20091G3561995-06-15015 June 1995 Rev 0 to Shroud Repair Program for Quad Cities Unit 2, Shroud Head Contact on Upper Support ML20101E8161993-11-22022 November 1993 Power Recovery Probabilities for Quad Cities Ipe ML20126G1021992-12-17017 December 1992 Rev 0 to RSA-D-92-07, LPCI Room Temperature Response Due to Loss of Room Cooler at Dresden Station ML20058M1641992-11-18018 November 1992 Quad-Cities 2/I Safety-Related Continuous Load Running/ Starting Voltages ML20058M1451992-07-31031 July 1992 Quad-Cities 1/I Safety-Related Continuous Load Running/ Starting Voltages ML20101Q7661992-06-16016 June 1992 RHR Pump 1C/1D Discharge Line 1-1008B-18 ML20058M1711992-05-20020 May 1992 Second-Level Undervoltage Relay Setpoint ML20058M1581992-05-0404 May 1992 Quad-Cities 1/II Safety-Related Continuous Load Running/ Starting Voltages ML20058M1541992-04-20020 April 1992 Evaluation of Toshiba Dgcwp Starting Voltage ML20058M1491992-04-15015 April 1992 Evaluation of 460-Volt Diesel Generator Cooling Pump Min Starting Voltage ML20058M1671992-04-15015 April 1992 Quad-Cities 2/II Safety-Related Continuous Load Running/ Starting Voltages ML20058M1741992-04-0303 April 1992 Evaluation of DG 2 Cooling Water Pump Cooler Fan a & B Min Starting Voltage ML20065S8691990-11-16016 November 1990 Draft Setpoint Calculation for RPS Turbine Control Valve Fast Closure Trip Function ML20247M2831988-01-11011 January 1988 Rev 1 to Quad Cities,Control Room Dose Analysis,Plot of Dose as Function of Standby Gas Treatment Sys Effluent ML20247M3191987-09-24024 September 1987 Control Room Dose Analysis, (Suppl to Dose Calculation 546Y-M-07) ML20247M2891987-04-0101 April 1987 Infiltration Analysis 1999-09-27
[Table view] |
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EDE-40 1190
- DRF C71 00086 November 16. 1990 ENCLOSURE L '
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Setpoint Calculation for I Reactor Protection System 1 Turbine Control Valve Fast Closure Trip Function Prepared for Commonwealth Edison Company l
Quad Cities Nuclear Statior.
Prepared byt WYhne Date: 4$'4/90 W. K. Green - Principal Engineer ' ' ~
Verified by: [/ /,% 2
@ L. Leopg - Senior Engineer Date: //-/6 to Approved by: C # M N l
VB F. Fleischman - Manager Date: //-/4 - 9M ~
' Reactor Protection Systems Application Engineering 9012260127 901218
{DR ADOCK0500g4
- D .
1.0 Objectives The objective of this calculation is to determine the setpoint to be used for the Reactor Protection System (f.PS) Turbine control Valve Fast closure-(TCVFC These p)ressure switches are Part Ntaber 184C4815P001. This information- Trip function was obtained via telecon with Rob Xorneta of Commonwealth Edison on-November 6,1990.. The new pressure switches are being installed as part '
of turbine vendor Thesignalsfromth(GE)recoseendedmodificationstotheturbinesystem.
ese switches will replace the signals that originally came from contacts on the turbine system fast acting solenoids.
1,. 0 Nothodology :
p'NEDC 31336. " General Electric Instrument Setpoint Methodology,"
October 1986. This is a proprieta document that was developed under contract between BE and certain ers of the Licensing Reytow Group Instrumant Setpoint Methodology owners Group, i
3.0. Asstaptions This calculation makes the following assumptions:
The individual-error terms represent a two signa yalue (g8 percent 4 probability of the value being correct).
Primary Element Accuracy
. are considered negligible (PEA)ofand because theProcess Measurement, short instrument lines and Accuracy (P because the pressure switches are measuring the process directly.
is conservatively estimated to be The Calibration one percent 1%) ofAccuracy full range. tem (C)Since this-value is a function of the instrumen(tation and procedures used for calibration this value must be verified to be conservative by Quad Cities perso,nnel. If_it is found to be non-conservative the results of this report must be o recalculated to reflect the larger value. ,
Instrument Drift Accuracy (A) since(D) therefor is anosix month value given interval is equal for drift to Instrument on drawing L
' 184C4815'. This is consistent with'NEDC-31336. Driftisassumedto be random for the subsequent intervals.
The probability t e avoiding a License Event Report (LER) event should be greater than 90 percent. This is consistent with NEDC-t 31336.
The probability for Spurious Trip Avoidance-(STA) should be granter than 96_ percent. This is consistent with NEDC 31336.
y 1-1
4.0 -Inputs to Calculation The pressuti switches to which this calculation ap>1ies are measuring-directly,the trip oil pressure that causes the turnine control valves to close in a rapid manner. According to-information in Desi n Record File (DRF)C7100017 this oil pressure a normally about 1500 t 1600 psig, and the control valve can't start-to close until the pressure drop; to 400
-psig. During normal operation of the control valves it is considered t possible to inve transients that would cause the trip system pressure to drop momentarily to about 740 psig. On the basis of this informatica the following values are derived:
Analytical Limit (AL) - 400 psig by the time the oil ressure Thecrossure-switchmusttri!oensurethatatrip reaches this level in order ignal will be generated within 30 milliseconds after start of control valve fast closure.
OperationalLimit(0L)=740psig The Nominal Trip setpoint must be far enough from this value so as to minimize the probability of tripping during normal operational transients.
Drawing 184C4815 indicates that the accuracy of this pressure switch is two percent ( 'of full ran e. Since the full: range of part one (P001)
, is 3000 psig, e accuracy is then 260 psig. Tliis value is assumed to apply over the full range o o)perating temperatures since no information regarding temperature effect on accuracy is given.
'A sumstry of the inputs to be used-in the calculations is as follows:
InstrumentAccuracy(A)=160psig CalibrationAccuracy(C)at30psig .
-Instrument Drift. (0) t60 psig (assume 6 me.)- = *104 psig (18 me.)
Analytical Limit (AL) 400 psig %~'
OperationalLimit-(0L)=-740ps'ig e
s l
0
-t-
.. . - _ - . . .- - . . - - . - . - . - -... ~_ . . . --
-. 5.0 Results The following are the results based on the methodology, assumptions, and inputs as given in sections 2.0 3.0, and 4.0 respectively: ;
paramatar Calculated Reconnended '
Valua value AllowableValue(AV) 456 psig 460 psig or Tech. Spec.Value(TSV)
NominalTripSetpoint(NTSP) 540 psig 550 psig Probability for License 92% N/A
-EventReport(LER) Avoidance .
(Using recommended values)
Probability of S urious ~ 99% N/A l
TripAvoidance(TA)
(Using recossend d va lues)
The NTSP now needs to be adjusted for the practicalities of plant calibration procedures.- The Required Limit the NTSP must ot be found in order that to assure (RL)-is the~ AV is the value be not exceeded.
The RL safunction-ofaccuracy(A)andcalibrationaccuracy(C)as follows 2' I RL = AV + (A + C )l/I Information received on 11 Edison indicates that the /4/90 from Erryl Mendenhall of Commonwealth calibration for this setpoint is accomplished using a Heise pressure gauge measuring 0 to 1000 psig with an accuracy of-1 psi. If one assumes an equal error when calibrating the Heise gauge and another 1 psi error when reading it, the total error is then:
CT " (1 +1 +1)/ = (3) / = 1.732 psi Use CT
= 2 psi I 2 Then RL = 460+(60.+2)1/2 - 520 psig However, this value is less than t'he value requ' ired for 90 percent probability of LER avoidance. -Therefore, use 540 psig as the RL.- ,
In order to obtain an STA probability of 95 percent or greater the NTSP
-should never exceed 638 psig. Therefore, select the NTSP to be midway betweenRL(540psig)Jand638psig.
HTSP=540+(638-540)/2=589psig Use NTSP = 590 nmic with As-Left and Leave Alone tolerances of *20 psi.
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1600 PSI F.A.S T.C. FLUtD TRIP CONTROLLED O-50 PS$ F.C.D FlutD DRAIN TO COOLER F.J S. F. A.S.T C 1600 PS3 F.J S FLUID JET SUPPLY Figure 1. Steam Control Valves Nos.1 through 4, and Intercept Valves Nos.1,3. and 5 (Fluid Flow Diagram)