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| {{#Wiki_filter:NOC-AE- 14003161ATTACHMENT 1Cameron Measurement Systems/Caldon Ultrasonics Engineering Report:ER-1059 Rev 1, "Bounding Uncertainty Analysis for Thermal PowerDetermination at SouthTexas Project Units 1 and 2 Using theLEFM CheckPlus System" (Non-Proprietary) p.Caldon UltrasonicsEngineering Report:-Measurement SystemsER-1059 Rev. 1BOUNDING UNCERTAINTY ANALYSIS FORTHERMAL POWER DETERMINATION AT SOUTHTEXAS PROJECT UNITS 1 and 2 USING THELEFMV-+ SYSTEMPrepared by: Ed MaderaChecked by: David MarkowskiReviewed by: Don AugensteinReviewed for Proprietary Information by: Ernie HauserAugust 2014ER-1059 Rev. I Prepared by: EJM Reviewed by: ~ER-1059 Rev. IPrepared by: EJMReviewed by: And CCAMERONMeasurement SystemsEngineering Report No. ER-1059 Rev. 1August 2014ER-1059 Rev. I Prepared by: EJM Reviewed by: A~iL..ER-1059 Rev. IPrepared by: EJMReviewed by: A% tj rCAMERON Measurement SystemsEngineering Report: ER-1059 Rey. 1BOUNDING UNCERTAINTY ANALYSIS FOR THERMAL POWERDETERMINATION AT SOUTH TEXAS NUCLEAR PROJECT UNITS 1AND 2 USING THE LEFM,/+ SYSTEMTable of Contents | | {{#Wiki_filter:NOC-AE- 14003161 ATTACHMENT 1 Cameron Measurement Systems/Caldon Ultrasonics Engineering Report: ER-1059 Rev 1, "Bounding Uncertainty Analysis for Thermal Power Determination at South Texas Project Units 1 and 2 Using the LEFM CheckPlus System" (Non-Proprietary) |
| | : p. Caldon Ultrasonics Engineering Report:-Measurement Systems ER-1059 Rev. 1 BOUNDING UNCERTAINTY ANALYSIS FOR THERMAL POWER DETERMINATION AT SOUTH TEXAS PROJECT UNITS 1 and 2 USING THE LEFMV-+ SYSTEM Prepared by: Ed Madera Checked by: David Markowski Reviewed by: Don Augenstein Reviewed for Proprietary Information by: Ernie Hauser August 2014 ER-1059 Rev. I Prepared by: EJM Reviewed by: ~ER-1059 Rev. I Prepared by: EJM Reviewed by: And CCAMERON Measurement Systems Engineering Report No. ER-1059 Rev. 1 August 2014 ER-1059 Rev. I Prepared by: EJM Reviewed by: A~iL..ER-1059 Rev. I Prepared by: EJM Reviewed by: A% tj rCAMERON Measurement Systems Engineering Report: ER-1059 Rey. 1 BOUNDING UNCERTAINTY ANALYSIS FOR THERMAL POWER DETERMINATION AT SOUTH TEXAS NUCLEAR PROJECT UNITS 1 AND 2 USING THE LEFM,/+ SYSTEM Table of Contents |
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| ==1.0 INTRODUCTION== | | ==1.0 INTRODUCTION== |
| 2.0 SUMMARY3.0 APPROACH4.0 OVERVIEW | | |
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| | ==SUMMARY== |
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| | ===3.0 APPROACH=== |
| | 4.0 OVERVIEW |
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| ==5.0 REFERENCES== | | ==5.0 REFERENCES== |
| 6.0 APPENDICESA Information Supporting Uncertainty in LEFM/"+ Flow andTemperature MeasurementsA.1 LEFM,1+ InputsA.2 LEFMV+ Uncertainty Items/CalculationsA.3 LEFMv1+ Meter Factor Calculation and Accuracy AssessmentA.4 [ ] TradeSecret &A.5 [ ConfidentialCommercialInformationB Total Thermal Power and Mass Flow Uncertainties using the LEFM-/+SystemER-1059 Rev. I Prepared by: EJM Reviewed by: ~ER- 1059 Rev. IPrepared by: EJMReviewed by: ff!!LH CAM ERON Measurement SystemsPage I | | |
| | ==6.0 APPENDICES== |
| | A Information Supporting Uncertainty in LEFM/"+ Flow and Temperature Measurements A.1 LEFM,1+ Inputs A.2 LEFMV+ Uncertainty Items/Calculations A.3 LEFMv1+ Meter Factor Calculation and Accuracy Assessment A.4 [ ] Trade Secret &A.5 [ Confidential Commercial Information B Total Thermal Power and Mass Flow Uncertainties using the LEFM-/+System ER-1059 Rev. I Prepared by: EJM Reviewed by: ~ER- 1059 Rev. I Prepared by: EJM Reviewed by: ff!!LH CAM ERON Measurement Systems Page I |
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| ==1.0 INTRODUCTION== | | ==1.0 INTRODUCTION== |
| The LEFM" and LEFM,/+1 are advanced ultrasonic systems that accurately determine thevolume flow and temperature of feedwater in nuclear power plants. Using a feedwater pressuresignal input to the LEFM" and LEFMV+: mass flow can be determined and, along with thetemperature output are used along with plant data to compute reactor core thermal power. Thetechnology underlying the LEFMv' ultrasonic instruments and the factors affecting theirperformance are described in a topical report, Reference 1, and a supplement to this topicalreport, Reference 2. The LEFMv'+, which is made of two LEFMv" subsystems, is described inanother supplement to the topical report, Reference 3. The exact amount of the uprate allowableunder a revision to 1OCFR50 Appendix K depends not only on the accuracy of the LEFM-/+instrument, but also on the uncertainties in other inputs to the thermal power calculation.It is the purpose of this document to provide an analysis of the uncertainty contribution of the TradeLEFM,/+ System [ ]to Secret &Confidentialthe overall thermal power uncertainty of South Texas Nuclear Generating Station Units I and 2 Commercial(Appendix B). InformationThe uncertainties in mass flow and feedwater temperature are also used in the calculation of theoverall thermal power uncertainty (Appendix B). [ TradeSecret &ConfidentialCommercial] A detailed Informationdiscussion of the methodology for combining these terms is described in Reference 3.This analysis is a preliminary bounding analysis for the South Texas Nuclear Generating StationUnits 1 and 2. This revision utilizes nominal dimensions for the spool piece and nominal values Tradefor full power mass flow, final feed temperature, and steam conditions. [ Secret &ConfidentialCommercial] The commissioning tests for the LEFMV/+, to be performed following its Informationinstallation in the plant, will confirm that in fact, the time measurement uncertainties are withinthe bounding values used in the analysis.TradeSecret &ConfidentialCommercialInformationER-1059 Rev. IPrepared by: EJMReviewed by: Akjý eCAMERONMeasurement SystemsPage 22.0 SUMMARYFor South Texas Nuclear Project Units I and 2, Revision 1 results are as follows:1. The mass flow uncertainty approach is documented in Reference 3. The uncertainty in theLEFM,/+'s mass flow of feedwater is as follows:o Fully Functional LEFMV+ system mass flow uncertainty is [o Maintenance Mode LEFM,/+ system mass flow uncertainty is [ ][2. The uncertainty in the LEFM'+ feedwater temperature is as follows:o Fully Functional LEFM,/+ system temperature uncertainty is [ ]o Maintenance Mode LEFMV1+ system the uncertainty is [ I3. The total thermal power uncertainty approach is documented in Reference 3 and Appendix Bof this document. The total uncertainty in the determination of thermal power uses theLEFMv'+ system parameters and plant specific parameters, i.e., heat gain/losses, etc.;however, the uncertainty values below do not include the plant specific parameters.o Thermal power uncertainty using a Fully Functional LEFMv+ system is [ Io Thermal power uncertainty using a Maintenance Mode LEFM,/+ system is[ ]TradeSecret &ConfidentialCommercialInformationTradeSecret &ConfidentialCommercialInformationTradeSecret &ConfidentialCommercialInformationI TradeSecret &ConfidentialCommercialInformationIER-1059 Rev. 1 Prepared by: EJM Reviewed by: ~IdLL!ER-1059 Rev. IPrepared by: EJMReviewed by: A95vi C CAMERON Measurement SystemsPage 33.0 APPROACHAll errors and biases are calculated and combined according to the procedures defined inReference 4 and Reference 5 in order to determine the 95% confidence and probability value.The approach to determine the uncertainty, consistent with determining set points, is to combinethe random and bias terms by the means of the RSS approach provided that all the terms areindependent, zero-centered and normally distributed.Reference 4 defines the contributions of individual error elements through the use of sensitivitycoefficients defined as follows:A calculated variable P is determined by algorithm f, from measured variables X, Y, and Z.P = f (X, Y, Z)The error, or uncertainty in P, dP, is given by:dP-f dX + if dY +-Y dZA =- Z A --As noted above, P is the determined variable--in this case, reactor power or mass flow-- which iscalculated via measured variables X, Y, and Z using an algorithm f (X, Y, Z). The uncertainty orerror in P, dP, is determined on a per unit basis as follows:&=Xqj___ýYy ýd+Zqy JdZwhere the terms in brackets are referred to as the sensitivity coefficients.If the errors or biases in individual elements (dX/X, dYfY, and dZ/Z in the above equation) are allcaused by a common (systematic) boundary condition (for example ambient temperature) thetotal error dP/P is found by summing the three terms in the above equation. If, as is more oftenthe case, the errors in X, Y, and Z are independent of each other, then Reference 4 and 5recommends and probability theory requires that the total uncertainty be determined by the rootsum square as follows (for 95% confidence and probability):dP ~X~f dXJ2 +(JY df xzdY)2(IZ_!f dz )2IObviously, if some errors in individual elements are caused by a combination of boundaryconditions, some independent and some related (i.e., systematic) then a combination of the twoprocedures is appropriate.ER-1059 Rev. IPrepared by: EJMReviewed by:. O&W SCAMERONMeasurement SystemsPage 44.0 OVERVIEWThe analyses that support the calculation of LEFM,'+ uncertainties are contained in theappendices to this document. The function of each appendix is outlined below.Appendix A.1, LEFMV+ InputsThis appendix tabulates dimensional and other inputs to the LEFMv/+. [TradeSecret &ConfidentialCommercialInformation] which is used by the LEFM-/+ for thecomputation of mass flow and temperature.Appendix A.2, LEFMV"+ Uncertainty Items CalculationsThis appendix calculates the uncertainties in mass flow and temperature as computed bythe LEFM,"+ using the methodology described in Appendix E of Reference 1 andAppendix A of Reference 33, with uncertainties in the elements of these measurementsbounded as described in both references4.The spreadsheet calculations draw on the dataof Appendix A. 1 for dimensional information. []These uncertainties are an important factor in establishing the overall uncertainty of theLEFM '/+.Revision 1 of this analysis utilizes the bounding values of Reference 3 for all uncertaintyelements5 in the computation of plant specific uncertainties. Revision 2 of this appendixwill utilize the results of the calibration test for the plant spool piece(s) for the uncertaintyin the meter factor (calibration coefficient). The engineering report for the spool piececalibration test will be included as Appendix A.3 to Revision 2 of this report.TradeSecret &ConfidentialCommercialInformationReference 3 (ER 157P-A) develops the uncertainties for the LEFM,/+ system. Because this system uses twomeasurement planes, the structure of its uncertainties differs somewhat that of an LEFMv.4 Reference 3 (ER 157P-A) revised some of the time measurement uncertainty bounds. The revised bounds are aconservative projection of actual performance of the LEFM hardware. ER 80P used bounds that were based on aconservative projection of theoretical performance.[IITradeSecret &ConfidentialCommercialInformationER-1059 Rev. 1 Prepared by: EJM Reviewed by: ~2L~ER-1059 Rev. IPrepared by: EJMReviewed by: AR" SCAMERONMeasurement SystemsPage 5Appendix A.3, Meter Factor (Calibration) UncertaintiesThis report documents the meter factor bounding uncertainty analysis for South TexasProject (STP) Units 1 and 2. Once the actual flow elements STP are made and calibrated,the actual calibration data and parametric tests will be used to compute a meter factoruncertainty for each unit.The calibration test report for the spool piece(s) establishes the overall uncertainty in themeter factor of the LEFM'/+. [TradeSecret &ConfidentiaCommerciaInformationIThis report's approach is to use the body of calibration and parametric testing thatCameron has performed on 195 nuclear power plant flow meters.Cameron will use the most conservative approach to compute a bounding uncertainty inthe meter factor as applied to STP. Further, additional conservatisms are used such thatthe uncertainty can be considered to be bounding.Appendix A.4, [[Appendix A.5, [IIITradeSecret &ConfidentialCommercialInformationTradeSecret &ConfidentialCommercialInformationIIAppendix B, Total Thermal Power Uncertainty due to the LEFM V"+The total thermal power uncertainty due to the LEFM,/+ is calculated in this appendix,using the results of Appendix A.2, A.4 and A.5. Plant supplied steam conditions (whichenter into the computation of errors due to feedwater temperature) are used for thiscomputation. This appendix also computes the fraction of the uncertainty in feedwatertemperature that is systematically related to the mass flow uncertainty.ER-1059 Rev. 1 Prepared by: EJM Reviewed by: ...~&~L4LER-1059 Rev. IPrepared by: EJMReviewed by: 45ý4d e CAMERON Measurement SystemsPage
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| ==65.0 REFERENCES== | | The LEFM" and LEFM,/+1 are advanced ultrasonic systems that accurately determine the volume flow and temperature of feedwater in nuclear power plants. Using a feedwater pressure signal input to the LEFM" and LEFMV+: mass flow can be determined and, along with the temperature output are used along with plant data to compute reactor core thermal power. The technology underlying the LEFMv' ultrasonic instruments and the factors affecting their performance are described in a topical report, Reference 1, and a supplement to this topical report, Reference |
| : 1) Cameron Topical Report ER-80P, "Improving Thermal Power Accuracy and Plant SafetyWhile Increasing Operating Power Level Using the LEFM Check System", Rev. 02) Cameron Engineering Report ER-160P, "Supplement to Topical Report ER 80P: Basis fora Power Uprate with the LEFM System", May 20003) Cameron Engineering Report ER-157(P-A), "Supplement to Cameron Topical Report ER-80P: Basis for Power Uprates with an LEFM Check or an LEFM CheckPlus", dated May2008, Revision 8 and Revision 8 Errata4) ASME PTC 19.1-1985, Measurement Uncertainty5) ISA-RP67.04.02-2000, Methodologies for the Determination of Set Points for NuclearSafety-Related InstrumentationER15 e.1Peae b:EMRvee yER-1059 Rev. 1Prepared by: EJMReviewed by: x0W_1 CAMERON Measurement SystemsPage 7Appendix AAppendix A.1, LEFMvI+ InputsAppendix A.2, LEFMvl+ Uncertainty Items/CalculationsAppendix A.3, Meter Factor Calculation and Accuracy AssessmentAppendix A.4, [ ] TradeSecret &Appendix A.5, [ ]ConfidentialCommercialInformationER-1059 Rev. 1 Prepared by: EJM Reviewed by: .e~MLtL.ER- 105.9 Rev. IPrepared by: EJMReviewed by: Attg Appendix A.1LEFMI'+ InputsNo attachment to follow as Appendix is Proprietary in its Entirety Appendix A.2LEFM,'+ Uncertainty Items/CalculationsNo attachment to follow as Appendix is Proprietary in its Entirety Appendix A.3LEFM,'+ Meter Factor Calculation and Accuracy AssessmentThe meter factor report for Unit I and 2 is ER-1060 Rev 1. | | : 2. The LEFMv'+, which is made of two LEFMv" subsystems, is described in another supplement to the topical report, Reference |
| Appendix A.4TradeSecret &[ ] ConfidentialCommercialInformationNo attachment to follow as Appendix is Proprietary in its Entirety#~M f Appendix A.5[IITradeSecret &ConfidentialCommercialInformationNo attachment to follow as Appendix is Proprietary in its Entirety Appendix BTotal Thermal Power and Mass Flow Uncertainty using the LEFM,/+SystemNo attachment to follow as Appendix is Proprietary in its Entirety}} | | : 3. The exact amount of the uprate allowable under a revision to 1OCFR50 Appendix K depends not only on the accuracy of the LEFM-/+instrument, but also on the uncertainties in other inputs to the thermal power calculation. |
| | It is the purpose of this document to provide an analysis of the uncertainty contribution of the Trade LEFM,/+ System [ ]to Secret &Confidential the overall thermal power uncertainty of South Texas Nuclear Generating Station Units I and 2 Commercial (Appendix B). Information The uncertainties in mass flow and feedwater temperature are also used in the calculation of the overall thermal power uncertainty (Appendix B). [ Trade Secret &Confidential Commercial |
| | ] A detailed Information discussion of the methodology for combining these terms is described in Reference 3.This analysis is a preliminary bounding analysis for the South Texas Nuclear Generating Station Units 1 and 2. This revision utilizes nominal dimensions for the spool piece and nominal values Trade for full power mass flow, final feed temperature, and steam conditions. |
| | [ Secret &Confidential Commercial |
| | ] The commissioning tests for the LEFMV/+, to be performed following its Information installation in the plant, will confirm that in fact, the time measurement uncertainties are within the bounding values used in the analysis.Trade Secret &Confidential Commercial Information ER-1059 Rev. I Prepared by: EJM Reviewed by: Akjý eCAMERON Measurement Systems Page 2 2.0 |
| | |
| | ==SUMMARY== |
| | For South Texas Nuclear Project Units I and 2, Revision 1 results are as follows: 1. The mass flow uncertainty approach is documented in Reference |
| | : 3. The uncertainty in the LEFM,/+'s mass flow of feedwater is as follows: o Fully Functional LEFMV+ system mass flow uncertainty is [o Maintenance Mode LEFM,/+ system mass flow uncertainty is [ ][2. The uncertainty in the LEFM'+ feedwater temperature is as follows: o Fully Functional LEFM,/+ system temperature uncertainty is [ ]o Maintenance Mode LEFMV1+ system the uncertainty is [ I 3. The total thermal power uncertainty approach is documented in Reference 3 and Appendix B of this document. |
| | The total uncertainty in the determination of thermal power uses the LEFMv'+ system parameters and plant specific parameters, i.e., heat gain/losses, etc.;however, the uncertainty values below do not include the plant specific parameters. |
| | o Thermal power uncertainty using a Fully Functional LEFMv+ system is [ I o Thermal power uncertainty using a Maintenance Mode LEFM,/+ system is[ ]Trade Secret &Confidential Commercial Information Trade Secret &Confidential Commercial Information Trade Secret &Confidential Commercial Information I Trade Secret &Confidential Commercial Information I ER-1059 Rev. 1 Prepared by: EJM Reviewed by: ~IdLL!ER-1059 Rev. I Prepared by: EJM Reviewed by: A95vi C CAMERON Measurement Systems Page 3 3.0 APPROACH All errors and biases are calculated and combined according to the procedures defined in Reference 4 and Reference 5 in order to determine the 95% confidence and probability value.The approach to determine the uncertainty, consistent with determining set points, is to combine the random and bias terms by the means of the RSS approach provided that all the terms are independent, zero-centered and normally distributed. |
| | Reference 4 defines the contributions of individual error elements through the use of sensitivity coefficients defined as follows: A calculated variable P is determined by algorithm f, from measured variables X, Y, and Z.P = f (X, Y, Z)The error, or uncertainty in P, dP, is given by: dP-f dX + if dY +-Y dZ A =- Z A --As noted above, P is the determined variable--in this case, reactor power or mass flow-- which is calculated via measured variables X, Y, and Z using an algorithm f (X, Y, Z). The uncertainty or error in P, dP, is determined on a per unit basis as follows:&=Xqj___ýYy |
| | ýd+Zqy JdZ where the terms in brackets are referred to as the sensitivity coefficients. |
| | If the errors or biases in individual elements (dX/X, dYfY, and dZ/Z in the above equation) are all caused by a common (systematic) boundary condition (for example ambient temperature) the total error dP/P is found by summing the three terms in the above equation. |
| | If, as is more often the case, the errors in X, Y, and Z are independent of each other, then Reference 4 and 5 recommends and probability theory requires that the total uncertainty be determined by the root sum square as follows (for 95% confidence and probability): |
| | dP ~X~f dXJ 2 +(JY df xzdY)2(IZ_!f dz )2 I Obviously, if some errors in individual elements are caused by a combination of boundary conditions, some independent and some related (i.e., systematic) then a combination of the two procedures is appropriate. |
| | ER-1059 Rev. I Prepared by: EJM Reviewed by:. O&W SCAMERON Measurement Systems Page 4 4.0 OVERVIEW The analyses that support the calculation of LEFM,'+ uncertainties are contained in the appendices to this document. |
| | The function of each appendix is outlined below.Appendix A.1, LEFMV+ Inputs This appendix tabulates dimensional and other inputs to the LEFMv/+. [Trade Secret &Confidential Commercial Information |
| | ] which is used by the LEFM-/+ for the computation of mass flow and temperature. |
| | Appendix A.2, LEFMV"+ Uncertainty Items Calculations This appendix calculates the uncertainties in mass flow and temperature as computed by the LEFM,"+ using the methodology described in Appendix E of Reference 1 and Appendix A of Reference 33, with uncertainties in the elements of these measurements bounded as described in both references 4.The spreadsheet calculations draw on the data of Appendix A. 1 for dimensional information. |
| | []These uncertainties are an important factor in establishing the overall uncertainty of the LEFM '/+.Revision 1 of this analysis utilizes the bounding values of Reference 3 for all uncertainty elements 5 in the computation of plant specific uncertainties. |
| | Revision 2 of this appendix will utilize the results of the calibration test for the plant spool piece(s) for the uncertainty in the meter factor (calibration coefficient). |
| | The engineering report for the spool piece calibration test will be included as Appendix A.3 to Revision 2 of this report.Trade Secret &Confidential Commercial Information Reference 3 (ER 157P-A) develops the uncertainties for the LEFM,/+ system. Because this system uses two measurement planes, the structure of its uncertainties differs somewhat that of an LEFMv.4 Reference 3 (ER 157P-A) revised some of the time measurement uncertainty bounds. The revised bounds are a conservative projection of actual performance of the LEFM hardware. |
| | ER 80P used bounds that were based on a conservative projection of theoretical performance. |
| | [I I Trade Secret &Confidential Commercial Information ER-1059 Rev. 1 Prepared by: EJM Reviewed by: ~2L~ER-1059 Rev. I Prepared by: EJM Reviewed by: AR" SCAMERON Measurement Systems Page 5 Appendix A.3, Meter Factor (Calibration) |
| | Uncertainties This report documents the meter factor bounding uncertainty analysis for South Texas Project (STP) Units 1 and 2. Once the actual flow elements STP are made and calibrated, the actual calibration data and parametric tests will be used to compute a meter factor uncertainty for each unit.The calibration test report for the spool piece(s) establishes the overall uncertainty in the meter factor of the LEFM'/+. [Trade Secret &Confidentia Commercia Information I This report's approach is to use the body of calibration and parametric testing that Cameron has performed on 195 nuclear power plant flow meters.Cameron will use the most conservative approach to compute a bounding uncertainty in the meter factor as applied to STP. Further, additional conservatisms are used such that the uncertainty can be considered to be bounding.Appendix A.4, [[Appendix A.5, [I I I Trade Secret &Confidential Commercial Information Trade Secret &Confidential Commercial Information I I Appendix B, Total Thermal Power Uncertainty due to the LEFM V"+The total thermal power uncertainty due to the LEFM,/+ is calculated in this appendix, using the results of Appendix A.2, A.4 and A.5. Plant supplied steam conditions (which enter into the computation of errors due to feedwater temperature) are used for this computation. |
| | This appendix also computes the fraction of the uncertainty in feedwater temperature that is systematically related to the mass flow uncertainty. |
| | ER-1059 Rev. 1 Prepared by: EJM Reviewed by: ...~&~L4L ER-1059 Rev. I Prepared by: EJM Reviewed by: 45ý4d e CAMERON Measurement Systems Page 6 |
| | |
| | ==5.0 REFERENCES== |
| | : 1) Cameron Topical Report ER-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM Check System", Rev. 0 2) Cameron Engineering Report ER-160P, "Supplement to Topical Report ER 80P: Basis for a Power Uprate with the LEFM System", May 2000 3) Cameron Engineering Report ER-157(P-A), "Supplement to Cameron Topical Report ER-80P: Basis for Power Uprates with an LEFM Check or an LEFM CheckPlus", dated May 2008, Revision 8 and Revision 8 Errata 4) ASME PTC 19.1-1985, Measurement Uncertainty |
| | : 5) ISA-RP67.04.02-2000, Methodologies for the Determination of Set Points for Nuclear Safety-Related Instrumentation ER15 e.1Peae b:EMRvee y ER-1059 Rev. 1 Prepared by: EJM Reviewed by: x0W_1 CAMERON Measurement Systems Page 7 Appendix A Appendix A.1, LEFMvI+ Inputs Appendix A.2, LEFMvl+ Uncertainty Items/Calculations Appendix A.3, Meter Factor Calculation and Accuracy Assessment Appendix A.4, [ ] Trade Secret &Appendix A.5, [ ]Confidential Commercial Information ER-1059 Rev. 1 Prepared by: EJM Reviewed by: .e~MLtL.ER- 105.9 Rev. I Prepared by: EJM Reviewed by: Attg Appendix A.1 LEFMI'+ Inputs No attachment to follow as Appendix is Proprietary in its Entirety Appendix A.2 LEFM,'+ Uncertainty Items/Calculations No attachment to follow as Appendix is Proprietary in its Entirety Appendix A.3 LEFM,'+ Meter Factor Calculation and Accuracy Assessment The meter factor report for Unit I and 2 is ER-1060 Rev 1. |
| | Appendix A.4 Trade Secret &[ ] Confidential Commercial Information No attachment to follow as Appendix is Proprietary in its Entirety#~M f Appendix A.5[II Trade Secret &Confidential Commercial Information No attachment to follow as Appendix is Proprietary in its Entirety Appendix B Total Thermal Power and Mass Flow Uncertainty using the LEFM,/+System No attachment to follow as Appendix is Proprietary in its Entirety}} |
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MONTHYEARML13302C2072013-11-0606 November 2013 Schedule Revision for the Review of the Davis-Besse Nuclear Power Station License Renewal Application (TAC ME4613 and ME4640) Project stage: Approval ML14260A4382014-08-31031 August 2014 Engineering Report ER-1059, Rev. 1, Bounding Uncertainty Analysis for Thermal Power Determination at South Texas Project Units 1 & 2 Using LEFM System. Project stage: Request NOC-AE-14003161, Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2.2014-08-31031 August 2014 Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2. Project stage: Request ML14269A1662014-09-25025 September 2014 NRR E-mail Capture - Acceptance of Application - LAR for Rev to (TS) 6.9.1.6, Core Operating Limit Report (Colr), at South Texas Project, Units 1 and 2 (TAC Nos. MF4639 and 4640) Project stage: Acceptance Review ML14290A2212014-11-13013 November 2014 Request for Withholding Information from Public Disclosure, 8/4/14 Affidavit Executed by E. Hauser, Cameron International, Caldon Ultrasonic Technology Center Engineering Report ER-1059, Revision 1 Project stage: Withholding Request Acceptance ML14290A2002014-11-13013 November 2014 Request for Withholding Information from Public Disclosure, 8/4/14 Affidavit Executed by E. Hauser, Cameron International, Caldon Ultrasonic Technology Center Engineering Report ER-1060, Revision 1 Project stage: Withholding Request Acceptance ML14336A0032014-12-0101 December 2014 NRR E-mail Capture - Request for Additional Information (RAI) - License Amendment Request for Revision to Technical Specification 6.9.1.6 (TACs MF4639 and MF4640) Project stage: RAI NOC-AE-14003204, Response to Request for Additional Information Regarding License Amendment Request - Proposed Revision to Administrative Controls Technical Specification 6.9.1.6, Core Operating Limits Report (COLR)2014-12-18018 December 2014 Response to Request for Additional Information Regarding License Amendment Request - Proposed Revision to Administrative Controls Technical Specification 6.9.1.6, Core Operating Limits Report (COLR) Project stage: Response to RAI ML15049A1292015-02-27027 February 2015 Issuance of Amendment Nos. 204 and 192, Revise Technical Specification 6.9.1.6, Core Operating Limits Report, with Respect to Analytical Methods Used to Determine Core Operating Limits Project stage: Approval 2014-12-18
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Category:Report
MONTHYEARNOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML23229A4992023-08-17017 August 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) ML21266A4262021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report ML21182A2412021-06-30030 June 2021 Commitment Change Summary Report ML17019A0032017-07-11011 July 2017 Attachment 2 to Safety Evaluation - In-Vessel Thermal-Hydraulic Analysis, Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 NOC-AE-17003468, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2017-05-10010 May 2017 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML16302A0152016-10-20020 October 2016 South Texas Project, Units 1 & 2 - Supplement 3 to Revised Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Address Generic Safety Issue (GSl)-191 and Respond to Generic Letter (GL) 2004-02 NOC-AE-16003345, LTR-PAFM-16-11-NP, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2016-03-31031 March 2016 LTR-PAFM-16-11-NP, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. NOC-AE-15003249, Submittal of 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report2015-06-0909 June 2015 Submittal of 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report ML14357A1362015-01-22022 January 2015 Review of Analysis of Capsule Withdrawal Schedule from Reactor Vessel Radiation Surveillance Program NOC-AE-14003190, Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application2014-10-30030 October 2014 Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application ML14344A5462014-10-30030 October 2014 Attachment 1 to NOC-AE-14003190 - Alion REP-STP-8998-13, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application Executive Summary NOC-AE-14003178, Update Foreign Ownership, Control, or Influence (FOCI)2014-09-17017 September 2014 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-14003161, Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2.2014-08-31031 August 2014 Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2. ML14260A4382014-08-31031 August 2014 Engineering Report ER-1059, Rev. 1, Bounding Uncertainty Analysis for Thermal Power Determination at South Texas Project Units 1 & 2 Using LEFM System. NOC-AE-14003101, Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application2014-06-25025 June 2014 Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application ML14168A2682014-05-0101 May 2014 Texas Pollutant Discharge Elimination System Major Amendment with Renewal Application for a Major Facility Tpdes Permit No. WQ000190800 NOC-AE-14003103, University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 12014-04-18018 April 2014 University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 1 ML14087A0782014-04-15015 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident (TAC MF0178 & MF0179) NOC-AE-14003114, Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai..2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai.. NOC-AE-14003082, Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 32014-03-11011 March 2014 Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 3 NOC-AE-13003067, Supplement to Seismic Walkdown Summary Report of Items Classified as Inaccessible2014-02-27027 February 2014 Supplement to Seismic Walkdown Summary Report of Items Classified as Inaccessible ML14072A0832014-02-24024 February 2014 CHLE-010, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition, Revision 3 ML14072A0872014-02-24024 February 2014 CHLE-016, Calculated Material Release to Estimate Chemical Effects, Revision 3 ML14072A0862014-02-24024 February 2014 CHLE-015, Summary of Chemical Effects Testing in 2012 for STP GSI-191 License Submittal, Revision 4 ML14072A0802014-02-24024 February 2014 CHLE-006, STP Material Calculations, Revision 2 ML14072A0822014-02-23023 February 2014 CHLE-008, Debris Bed Preparation & Formation Test Results, Revision 4 ML14072A0792014-02-22022 February 2014 CHLE-020, Test Results for 10-Day Chemical Effects Test Simulating LBLOCA Condition (T5), Revision 3 ML14072A0882014-02-22022 February 2014 CHLE-018, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions, Revision 3 ML14072A0852014-02-22022 February 2014 CHLE-014, T2 LBLOCA Test Report, Revision 3 ML14072A0842014-02-18018 February 2014 CHLE-012, T1 Mbloca Test Report, Revision 4 ML14072A0772014-02-18018 February 2014 CHLE-005, Determination of the Initial Pool Chemistry for the Chle Test, Revision 2 ML14149A4352014-02-14014 February 2014 Project, Units 1 and 2 - ALION-REP-STP-8998-02, Rev. 0, STP Casa Grande Analysis and LAR Enclosure 4-3 RAI Response, Enclosure 1 to Attachment 1 ML14072A0812014-02-13013 February 2014 CHLE-007, Debris Bed Requirements & Preparation Procedures, Revision 4 ML13339A7362014-01-29029 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13354B8332014-01-23023 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for South Texas Project, Units 1 and 2, TAC Nos.: MF0825 and MF0826 NOC-AE-13003070, Response to NRC Request for Reference Document for STP Risk-Informed GSI-191 Application2013-12-23023 December 2013 Response to NRC Request for Reference Document for STP Risk-Informed GSI-191 Application ML13323A1862013-11-12012 November 2013 Enclosure 4-1 - Risk-Informed Closure of GSI-191, Volume 1 ML13323A1912013-11-0606 November 2013 Enclosure 4-3 Risk-Informed Closure of GSI-191, Volume 3, Engineering (Casa Grande) Analysis, Page 212 of 1-122 ML13323A1902013-11-0606 November 2013 Enclosure 4-3 Risk-Informed Closure of GSI-191, Volume 3, Engineering (Casa Grande) Analysis, Cover - Page 211 of 248 ML13323A1892013-10-22022 October 2013 Enclosure 4-2 - Risk-Informed Closure of GSI-191, Volume 2 Probabilistic Risk Analysis ML13323B2092013-10-0404 October 2013 Attachment 12: CHLE-020, Rev. 2, Test Results for a 10-day Chemical Effects Test Simulating LBLOCA Conditions (T5). ML13323B2082013-09-23023 September 2013 Attachment 11: CHLE-019, Rev. 2, Test Results for Chemical Effect Tests Stimulating Corrosion and Precipitation (T3 & T4) ML13323B2072013-09-16016 September 2013 Attachment 10: CHLE-018, Rev. 2, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions. NOC-AE-13003019, Submittal of Commitment Change Summary Report for the Period June 21, 2011 Through June 21, 20132013-07-18018 July 2013 Submittal of Commitment Change Summary Report for the Period June 21, 2011 Through June 21, 2013 ML13175A2122013-06-18018 June 2013 Project, Units 1 and 2, Enclosure 4-1 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 1 Project Summary NOC-AE-13002986, Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 161 of 260 Through End2013-06-0606 June 2013 Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 161 of 260 Through End 2023-08-31
[Table view] Category:Technical
MONTHYEARNOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML23229A4992023-08-17017 August 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) ML21266A4262021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) ML16302A0152016-10-20020 October 2016 South Texas Project, Units 1 & 2 - Supplement 3 to Revised Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Address Generic Safety Issue (GSl)-191 and Respond to Generic Letter (GL) 2004-02 NOC-AE-16003345, LTR-PAFM-16-11-NP, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2016-03-31031 March 2016 LTR-PAFM-16-11-NP, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. NOC-AE-14003161, Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2.2014-08-31031 August 2014 Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2. ML14260A4382014-08-31031 August 2014 Engineering Report ER-1059, Rev. 1, Bounding Uncertainty Analysis for Thermal Power Determination at South Texas Project Units 1 & 2 Using LEFM System. NOC-AE-14003082, Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 32014-03-11011 March 2014 Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 3 ML14072A0872014-02-24024 February 2014 CHLE-016, Calculated Material Release to Estimate Chemical Effects, Revision 3 ML14072A0862014-02-24024 February 2014 CHLE-015, Summary of Chemical Effects Testing in 2012 for STP GSI-191 License Submittal, Revision 4 ML14072A0802014-02-24024 February 2014 CHLE-006, STP Material Calculations, Revision 2 ML14072A0832014-02-24024 February 2014 CHLE-010, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition, Revision 3 ML14072A0822014-02-23023 February 2014 CHLE-008, Debris Bed Preparation & Formation Test Results, Revision 4 ML14072A0792014-02-22022 February 2014 CHLE-020, Test Results for 10-Day Chemical Effects Test Simulating LBLOCA Condition (T5), Revision 3 ML14072A0852014-02-22022 February 2014 CHLE-014, T2 LBLOCA Test Report, Revision 3 ML14072A0882014-02-22022 February 2014 CHLE-018, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions, Revision 3 ML14072A0772014-02-18018 February 2014 CHLE-005, Determination of the Initial Pool Chemistry for the Chle Test, Revision 2 ML14072A0842014-02-18018 February 2014 CHLE-012, T1 Mbloca Test Report, Revision 4 ML14149A4352014-02-14014 February 2014 Project, Units 1 and 2 - ALION-REP-STP-8998-02, Rev. 0, STP Casa Grande Analysis and LAR Enclosure 4-3 RAI Response, Enclosure 1 to Attachment 1 ML14072A0812014-02-13013 February 2014 CHLE-007, Debris Bed Requirements & Preparation Procedures, Revision 4 ML13339A7362014-01-29029 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13354B8332014-01-23023 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for South Texas Project, Units 1 and 2, TAC Nos.: MF0825 and MF0826 NOC-AE-13003070, Response to NRC Request for Reference Document for STP Risk-Informed GSI-191 Application2013-12-23023 December 2013 Response to NRC Request for Reference Document for STP Risk-Informed GSI-191 Application ML13323B2092013-10-0404 October 2013 Attachment 12: CHLE-020, Rev. 2, Test Results for a 10-day Chemical Effects Test Simulating LBLOCA Conditions (T5). ML13323B2082013-09-23023 September 2013 Attachment 11: CHLE-019, Rev. 2, Test Results for Chemical Effect Tests Stimulating Corrosion and Precipitation (T3 & T4) ML13323B2072013-09-16016 September 2013 Attachment 10: CHLE-018, Rev. 2, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions. ML13175A2122013-06-18018 June 2013 Project, Units 1 and 2, Enclosure 4-1 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 1 Project Summary ML13175A2402013-06-0606 June 2013 Project, Units 1 and 2, Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 1 of 260 Through Page 160 of 260 NOC-AE-13002986, Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 161 of 260 Through End2013-06-0606 June 2013 Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 161 of 260 Through End NOC-AE-13002975, Enclosuflooding Hazard Reevaluation Report, Cover Through Page 2.2-462013-03-31031 March 2013 Enclosuflooding Hazard Reevaluation Report, Cover Through Page 2.2-46 ML13079A8082013-03-11011 March 2013 Enclosuflooding Hazard Reevaluation Report, Cover Through Page 2.3-1 Through End ML13323B2012013-01-22022 January 2013 Attachment 7: CHLE-014, Rev. 2, T2 LBLOCA Test Report. ML13323B2042013-01-22022 January 2013 Attachment 9: CHLE-016, Rev. 2, Calculated Material Release to Estimate Chemical Effects. ML13323B2022013-01-15015 January 2013 Attachment 8: CHLE-015, Rev. 3, Summary of Chemical Effects Testing in 2012 for STP GSI-191 License Submittal. ML13323B2002013-01-0909 January 2013 Attachment 6: CHLE-012, Rev. 3, T1 Mbloca Test Report, Figure 53 Through End ML13323B1992013-01-0909 January 2013 Attachment 6: CHLE-012, Rev. 3, T1 Mbloca Test Report, Cover Through Figure 52 ML12335A1842012-11-26026 November 2012 Licensee Documents for December 12, 2012 Public Meeting ML12335A1902012-11-26026 November 2012 Licensee Documents for December 12, 2012 Public Meeting ML13025A1382012-10-31031 October 2012 STP GSI-191 Bypass Sensitivity Report - Water Conductivity Added ML12243A4742012-08-30030 August 2012 Email - Risk-Informed Approach to GSI-191, STP Cfd Data Analysis Report - Bypass Test Protocol ML13323B1982012-08-19019 August 2012 Attachment 5: CHLE-010, Rev. 2, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition. ML13323B1912012-08-14014 August 2012 Attachment 2: CHLE-006, Rev. 1, STP Material Calculations. NOC-AE-13003040, Attachment 1: CHLE-005, Rev. 1, Determination of the Initial Pool Chemistry for the Chle Test.2012-08-13013 August 2012 Attachment 1: CHLE-005, Rev. 1, Determination of the Initial Pool Chemistry for the Chle Test. ML13323B1942012-08-11011 August 2012 Attachment 3: CHLE-007, Rev. 3, Debris Bed Requirements and Preparation Procedures. ML13323B1962012-06-12012 June 2012 Attachment 4: CHLE-008, Rev. 3, Debris Bed Preparation and Formation Test Results. ML1206100682012-02-28028 February 2012 Southtexas Project, Units 1 and 2 - Test Plan for STP High Temperature Vertical Loops Testing ML1205408162012-02-23023 February 2012 Experimental Setup for Chle Test Equipment ML1205406672012-02-22022 February 2012 Casa Grande Summary ML1205407272012-02-0909 February 2012 Actions Taken to Resolved Pirt Items 2023-08-17
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{{#Wiki_filter:NOC-AE- 14003161 ATTACHMENT 1 Cameron Measurement Systems/Caldon Ultrasonics Engineering Report: ER-1059 Rev 1, "Bounding Uncertainty Analysis for Thermal Power Determination at South Texas Project Units 1 and 2 Using the LEFM CheckPlus System" (Non-Proprietary)
- p. Caldon Ultrasonics Engineering Report:-Measurement Systems ER-1059 Rev. 1 BOUNDING UNCERTAINTY ANALYSIS FOR THERMAL POWER DETERMINATION AT SOUTH TEXAS PROJECT UNITS 1 and 2 USING THE LEFMV-+ SYSTEM Prepared by: Ed Madera Checked by: David Markowski Reviewed by: Don Augenstein Reviewed for Proprietary Information by: Ernie Hauser August 2014 ER-1059 Rev. I Prepared by: EJM Reviewed by: ~ER-1059 Rev. I Prepared by: EJM Reviewed by: And CCAMERON Measurement Systems Engineering Report No. ER-1059 Rev. 1 August 2014 ER-1059 Rev. I Prepared by: EJM Reviewed by: A~iL..ER-1059 Rev. I Prepared by: EJM Reviewed by: A% tj rCAMERON Measurement Systems Engineering Report: ER-1059 Rey. 1 BOUNDING UNCERTAINTY ANALYSIS FOR THERMAL POWER DETERMINATION AT SOUTH TEXAS NUCLEAR PROJECT UNITS 1 AND 2 USING THE LEFM,/+ SYSTEM Table of Contents
1.0 INTRODUCTION
2.0
SUMMARY
3.0 APPROACH
4.0 OVERVIEW
5.0 REFERENCES
6.0 APPENDICES
A Information Supporting Uncertainty in LEFM/"+ Flow and Temperature Measurements A.1 LEFM,1+ Inputs A.2 LEFMV+ Uncertainty Items/Calculations A.3 LEFMv1+ Meter Factor Calculation and Accuracy Assessment A.4 [ ] Trade Secret &A.5 [ Confidential Commercial Information B Total Thermal Power and Mass Flow Uncertainties using the LEFM-/+System ER-1059 Rev. I Prepared by: EJM Reviewed by: ~ER- 1059 Rev. I Prepared by: EJM Reviewed by: ff!!LH CAM ERON Measurement Systems Page I
1.0 INTRODUCTION
The LEFM" and LEFM,/+1 are advanced ultrasonic systems that accurately determine the volume flow and temperature of feedwater in nuclear power plants. Using a feedwater pressure signal input to the LEFM" and LEFMV+: mass flow can be determined and, along with the temperature output are used along with plant data to compute reactor core thermal power. The technology underlying the LEFMv' ultrasonic instruments and the factors affecting their performance are described in a topical report, Reference 1, and a supplement to this topical report, Reference
- 2. The LEFMv'+, which is made of two LEFMv" subsystems, is described in another supplement to the topical report, Reference
- 3. The exact amount of the uprate allowable under a revision to 1OCFR50 Appendix K depends not only on the accuracy of the LEFM-/+instrument, but also on the uncertainties in other inputs to the thermal power calculation.
It is the purpose of this document to provide an analysis of the uncertainty contribution of the Trade LEFM,/+ System [ ]to Secret &Confidential the overall thermal power uncertainty of South Texas Nuclear Generating Station Units I and 2 Commercial (Appendix B). Information The uncertainties in mass flow and feedwater temperature are also used in the calculation of the overall thermal power uncertainty (Appendix B). [ Trade Secret &Confidential Commercial
] A detailed Information discussion of the methodology for combining these terms is described in Reference 3.This analysis is a preliminary bounding analysis for the South Texas Nuclear Generating Station Units 1 and 2. This revision utilizes nominal dimensions for the spool piece and nominal values Trade for full power mass flow, final feed temperature, and steam conditions.
[ Secret &Confidential Commercial
] The commissioning tests for the LEFMV/+, to be performed following its Information installation in the plant, will confirm that in fact, the time measurement uncertainties are within the bounding values used in the analysis.Trade Secret &Confidential Commercial Information ER-1059 Rev. I Prepared by: EJM Reviewed by: Akjý eCAMERON Measurement Systems Page 2 2.0
SUMMARY
For South Texas Nuclear Project Units I and 2, Revision 1 results are as follows: 1. The mass flow uncertainty approach is documented in Reference
- 3. The uncertainty in the LEFM,/+'s mass flow of feedwater is as follows: o Fully Functional LEFMV+ system mass flow uncertainty is [o Maintenance Mode LEFM,/+ system mass flow uncertainty is [ ][2. The uncertainty in the LEFM'+ feedwater temperature is as follows: o Fully Functional LEFM,/+ system temperature uncertainty is [ ]o Maintenance Mode LEFMV1+ system the uncertainty is [ I 3. The total thermal power uncertainty approach is documented in Reference 3 and Appendix B of this document.
The total uncertainty in the determination of thermal power uses the LEFMv'+ system parameters and plant specific parameters, i.e., heat gain/losses, etc.;however, the uncertainty values below do not include the plant specific parameters.
o Thermal power uncertainty using a Fully Functional LEFMv+ system is [ I o Thermal power uncertainty using a Maintenance Mode LEFM,/+ system is[ ]Trade Secret &Confidential Commercial Information Trade Secret &Confidential Commercial Information Trade Secret &Confidential Commercial Information I Trade Secret &Confidential Commercial Information I ER-1059 Rev. 1 Prepared by: EJM Reviewed by: ~IdLL!ER-1059 Rev. I Prepared by: EJM Reviewed by: A95vi C CAMERON Measurement Systems Page 3 3.0 APPROACH All errors and biases are calculated and combined according to the procedures defined in Reference 4 and Reference 5 in order to determine the 95% confidence and probability value.The approach to determine the uncertainty, consistent with determining set points, is to combine the random and bias terms by the means of the RSS approach provided that all the terms are independent, zero-centered and normally distributed.
Reference 4 defines the contributions of individual error elements through the use of sensitivity coefficients defined as follows: A calculated variable P is determined by algorithm f, from measured variables X, Y, and Z.P = f (X, Y, Z)The error, or uncertainty in P, dP, is given by: dP-f dX + if dY +-Y dZ A =- Z A --As noted above, P is the determined variable--in this case, reactor power or mass flow-- which is calculated via measured variables X, Y, and Z using an algorithm f (X, Y, Z). The uncertainty or error in P, dP, is determined on a per unit basis as follows:&=Xqj___ýYy
ýd+Zqy JdZ where the terms in brackets are referred to as the sensitivity coefficients.
If the errors or biases in individual elements (dX/X, dYfY, and dZ/Z in the above equation) are all caused by a common (systematic) boundary condition (for example ambient temperature) the total error dP/P is found by summing the three terms in the above equation.
If, as is more often the case, the errors in X, Y, and Z are independent of each other, then Reference 4 and 5 recommends and probability theory requires that the total uncertainty be determined by the root sum square as follows (for 95% confidence and probability):
dP ~X~f dXJ 2 +(JY df xzdY)2(IZ_!f dz )2 I Obviously, if some errors in individual elements are caused by a combination of boundary conditions, some independent and some related (i.e., systematic) then a combination of the two procedures is appropriate.
ER-1059 Rev. I Prepared by: EJM Reviewed by:. O&W SCAMERON Measurement Systems Page 4 4.0 OVERVIEW The analyses that support the calculation of LEFM,'+ uncertainties are contained in the appendices to this document.
The function of each appendix is outlined below.Appendix A.1, LEFMV+ Inputs This appendix tabulates dimensional and other inputs to the LEFMv/+. [Trade Secret &Confidential Commercial Information
] which is used by the LEFM-/+ for the computation of mass flow and temperature.
Appendix A.2, LEFMV"+ Uncertainty Items Calculations This appendix calculates the uncertainties in mass flow and temperature as computed by the LEFM,"+ using the methodology described in Appendix E of Reference 1 and Appendix A of Reference 33, with uncertainties in the elements of these measurements bounded as described in both references 4.The spreadsheet calculations draw on the data of Appendix A. 1 for dimensional information.
[]These uncertainties are an important factor in establishing the overall uncertainty of the LEFM '/+.Revision 1 of this analysis utilizes the bounding values of Reference 3 for all uncertainty elements 5 in the computation of plant specific uncertainties.
Revision 2 of this appendix will utilize the results of the calibration test for the plant spool piece(s) for the uncertainty in the meter factor (calibration coefficient).
The engineering report for the spool piece calibration test will be included as Appendix A.3 to Revision 2 of this report.Trade Secret &Confidential Commercial Information Reference 3 (ER 157P-A) develops the uncertainties for the LEFM,/+ system. Because this system uses two measurement planes, the structure of its uncertainties differs somewhat that of an LEFMv.4 Reference 3 (ER 157P-A) revised some of the time measurement uncertainty bounds. The revised bounds are a conservative projection of actual performance of the LEFM hardware.
ER 80P used bounds that were based on a conservative projection of theoretical performance.
[I I Trade Secret &Confidential Commercial Information ER-1059 Rev. 1 Prepared by: EJM Reviewed by: ~2L~ER-1059 Rev. I Prepared by: EJM Reviewed by: AR" SCAMERON Measurement Systems Page 5 Appendix A.3, Meter Factor (Calibration)
Uncertainties This report documents the meter factor bounding uncertainty analysis for South Texas Project (STP) Units 1 and 2. Once the actual flow elements STP are made and calibrated, the actual calibration data and parametric tests will be used to compute a meter factor uncertainty for each unit.The calibration test report for the spool piece(s) establishes the overall uncertainty in the meter factor of the LEFM'/+. [Trade Secret &Confidentia Commercia Information I This report's approach is to use the body of calibration and parametric testing that Cameron has performed on 195 nuclear power plant flow meters.Cameron will use the most conservative approach to compute a bounding uncertainty in the meter factor as applied to STP. Further, additional conservatisms are used such that the uncertainty can be considered to be bounding.Appendix A.4, [[Appendix A.5, [I I I Trade Secret &Confidential Commercial Information Trade Secret &Confidential Commercial Information I I Appendix B, Total Thermal Power Uncertainty due to the LEFM V"+The total thermal power uncertainty due to the LEFM,/+ is calculated in this appendix, using the results of Appendix A.2, A.4 and A.5. Plant supplied steam conditions (which enter into the computation of errors due to feedwater temperature) are used for this computation.
This appendix also computes the fraction of the uncertainty in feedwater temperature that is systematically related to the mass flow uncertainty.
ER-1059 Rev. 1 Prepared by: EJM Reviewed by: ...~&~L4L ER-1059 Rev. I Prepared by: EJM Reviewed by: 45ý4d e CAMERON Measurement Systems Page 6
5.0 REFERENCES
- 1) Cameron Topical Report ER-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM Check System", Rev. 0 2) Cameron Engineering Report ER-160P, "Supplement to Topical Report ER 80P: Basis for a Power Uprate with the LEFM System", May 2000 3) Cameron Engineering Report ER-157(P-A), "Supplement to Cameron Topical Report ER-80P: Basis for Power Uprates with an LEFM Check or an LEFM CheckPlus", dated May 2008, Revision 8 and Revision 8 Errata 4) ASME PTC 19.1-1985, Measurement Uncertainty
- 5) ISA-RP67.04.02-2000, Methodologies for the Determination of Set Points for Nuclear Safety-Related Instrumentation ER15 e.1Peae b:EMRvee y ER-1059 Rev. 1 Prepared by: EJM Reviewed by: x0W_1 CAMERON Measurement Systems Page 7 Appendix A Appendix A.1, LEFMvI+ Inputs Appendix A.2, LEFMvl+ Uncertainty Items/Calculations Appendix A.3, Meter Factor Calculation and Accuracy Assessment Appendix A.4, [ ] Trade Secret &Appendix A.5, [ ]Confidential Commercial Information ER-1059 Rev. 1 Prepared by: EJM Reviewed by: .e~MLtL.ER- 105.9 Rev. I Prepared by: EJM Reviewed by: Attg Appendix A.1 LEFMI'+ Inputs No attachment to follow as Appendix is Proprietary in its Entirety Appendix A.2 LEFM,'+ Uncertainty Items/Calculations No attachment to follow as Appendix is Proprietary in its Entirety Appendix A.3 LEFM,'+ Meter Factor Calculation and Accuracy Assessment The meter factor report for Unit I and 2 is ER-1060 Rev 1.
Appendix A.4 Trade Secret &[ ] Confidential Commercial Information No attachment to follow as Appendix is Proprietary in its Entirety#~M f Appendix A.5[II Trade Secret &Confidential Commercial Information No attachment to follow as Appendix is Proprietary in its Entirety Appendix B Total Thermal Power and Mass Flow Uncertainty using the LEFM,/+System No attachment to follow as Appendix is Proprietary in its Entirety}}