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| 5-345.2.3 Limit CurvesThe minimum alternating stress ratio, which was derived in Reference 10 and is 1.43. Figure 5-39 throughFigure 5-42 show the plots of the limit curves for MSL A through MSL D, respectively. In each plot,there are two lines; the limit curves Li and L2.Figure 5-39 [ ] | | 5-345.2.3 Limit CurvesThe minimum alternating stress ratio, which was derived in Reference 10 and is 1.43. Figure 5-39 throughFigure 5-42 show the plots of the limit curves for MSL A through MSL D, respectively. In each plot,there are two lines; the limit curves Li and L2.Figure 5-39 [ ] |
| 5-35bFigure 5-40 [b 5-36bFigure 5-41 [ | | 5-35bFigure 5-40 [b 5-36bFigure 5-41 [ |
| 5-375-3Figure 5-42 [IIb 6-16 CONCLUSIONS[]a~c[t~[]ac 7-17 REFERENCES1. []a~b2. United States Nuclear Regulatory Commission Regulatory Guide 1.20, Rev. 3, "ComprehensiveVibration Assessment Program for Reactor Internals During Preoperational and Initial StartupTesting," March 2007.3. []a,c4. []a~b5. r6.7. I8.9. I10. []a,cI a,c]a~b]a,c]a~c]a,c11. ASME, "ASME Steam Tables," Fifth Edition, 1983.12. []a~c13. I]a~c 7-214.]a,c15. r]ac16. I17. r18. [19.a,.c],.ca,.c | | 5-375-3Figure 5-42 [IIb 6-16 CONCLUSIONS[]a~c[t~[]ac 7-17 REFERENCES1. []a~b2. United States Nuclear Regulatory Commission Regulatory Guide 1.20, Rev. 3, "ComprehensiveVibration Assessment Program for Reactor Internals During Preoperational and Initial StartupTesting," March 2007.3. []a,c4. []a~b5. r6.7. I8.9. I10. []a,cI a,c]a~b]a,c]a~c]a,c11. ASME, "ASME Steam Tables," Fifth Edition, 1983.12. []a~c13. I]a~c 7-214.]a,c15. r]ac16. I17. r18. [19.a,.c],.ca,.c}} |
| }} | |
Letter Sequence Other |
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TAC:MD9990, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) TAC:MF6730, (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
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MONTHYEARML0907106832008-02-17017 February 2008 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Attachment 1-1g Through End of Encl. 1 Project stage: Other ML13064A4352008-03-20020 March 2008 CA-95-075, Main Steam Line High Flow Setpoint, Attachment 4 Project stage: Other ML0914101242008-08-11011 August 2008 Monticello - Calculation CA-08-050, Rev. 0, Instrument Setpoint Calculation - Average Power Range Monitor (APRM) Non-Flow Eiased Prnm Setpoints for Cl Tp and EPU Project stage: Other L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.2008-10-31031 October 2008 Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis. Project stage: Other ML0832301122008-10-31031 October 2008 NEDC-33322-NP, Revision 3, Monticello Nuclear Generating Plant, Safety Analysis Report, Constant Pressure Power Uprate. Project stage: Request ML0832301112008-11-0505 November 2008 Monticello Nuclear Generating Plant, License Amendment Request: Extended Power Uprate Project stage: Other ML0832301142008-11-0505 November 2008 Monticello Nuclear Generating Plant, Steam Dryer Dynamic Stress Evaluation. Project stage: Request ML0834003662008-12-0202 December 2008 Extended Power Uprate Acceptance Review Questions on Probabilistic Risk Assessment Issues Project stage: Acceptance Review ML0834004022008-12-0505 December 2008 Extended Power Uprate - Monticello - Request to Supplement the Application in the Probabilistic Risk Assessment Area Project stage: Other ML0835000992008-12-11011 December 2008 Monticello Extended Power Uprate (Usnrc TAC MD9990): Acceptance Review Supplement Regarding Steam Dryer Outer Hood Submodel Analysis Project stage: Supplement ML0835303022008-12-16016 December 2008 Draft Request for Additional Information, Environmental Issues of EPU Application Project stage: Draft RAI ML0936200242008-12-18018 December 2008 Report 0800760.401, Rev. 1, Flaw Evaluation and Vibration Assessment of Existing Monticello Steam Dryer Flaws for Extended Power Uprate. Project stage: Other ML0835005752008-12-18018 December 2008 Letter Finding 11/5/08 Application for Amendment Acceptable for Review Project stage: Other ML0835309982008-12-18018 December 2008 EPU Application - Additional RAI Question Regarding an Environmental Issue Project stage: RAI ML0835310022008-12-18018 December 2008 Proposed Eou Amendment - Revised RAI Re. Containment Analysis Project stage: RAI ML0914101222008-12-18018 December 2008 Monticello - Calculation CA-95-075, Revision 1, Main Steam Line High Flow Setpoint Project stage: Other ML0914101212008-12-19019 December 2008 Monticello - Calculation CA-95-073, Revision 4, Reactor Low Water Level SCRAM Setpoint Project stage: Other ML0835901272009-01-14014 January 2009 Letter Conveying Determination That Enclosure 5 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Withheld from Public Disclosure Project stage: Other ML0835706102009-01-26026 January 2009 Letter Conveying Determination That Enclosure 11 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Is Withheld from Public Disclosure Project stage: Other L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 20082009-01-29029 January 2009 Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008 Project stage: Other L-MT-09-005, Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate2009-02-0404 February 2009 Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate Project stage: Request L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 20082009-02-0404 February 2009 Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008 Project stage: Other ML0904204852009-02-11011 February 2009 Draft RAI from Materials Engineering Re. Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907106792009-02-17017 February 2009 Monticello, Response to NRC Containment & Ventilation Branch Request for Additional Information (Rals) Dated December 18, 2008 Project stage: Request ML0907106802009-02-17017 February 2009 Monticello, Enclosure 1 to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 1 Dated December 18, 2008, Cover Through Copy of MNGP Appr T0406 Data Transmittal Page 424 of 424 Project stage: Other L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 5382009-02-17017 February 2009 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538 Project stage: Other ML0907106842009-02-17017 February 2009 Enclosures 2 - 4: NSPM Response to Containment & Ventilation Branch RAI Numbers 2, 3 and 4 Dated December 18, 2008 Project stage: Other L-MT-09-018, Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 20092009-02-24024 February 2009 Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 2009 Project stage: Request ML0907100912009-03-11011 March 2009 Conveying Draft RAI Questions from the Instrumentation and Controls Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907200572009-03-12012 March 2009 Conveys Draft RAI Regarding Fire Protection for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800062009-03-18018 March 2009 Draft RAI from Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800042009-03-18018 March 2009 Conveys Draft RAI by the PRA Licensing Branch on the Proposed EPU Amendment Project stage: Draft RAI ML0907809032009-03-19019 March 2009 Conveys Draft RAI Provided by the Containment and Ventilation Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907809092009-03-19019 March 2009 RAI from the Containment and Ventilation Branch the Proposed Extended Power Uprate Amendment Project stage: RAI L-MT-09-017, Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 20092009-03-19019 March 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 2009 Project stage: Request ML0908200312009-03-20020 March 2009 Draft RAI Re. Health Physics Issues for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908200992009-03-23023 March 2009 Draft RAI from the Balance of Plant Branch Re the Proposed Amendment on Extended Power Uprate Project stage: Draft RAI ML0908800022009-03-28028 March 2009 Second Portion of Draft RAI from the Mechanical and Civil Engineering Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908800032009-03-28028 March 2009 Draft RAI from the Electrical Engineering Branch Re. the Proposed Extended Power Uprate Amendment for Monticello Project stage: Draft RAI ML0908800012009-03-29029 March 2009 Additional Draft RAI Questions from the Containment and Ventilation Branch Proposed EPU Amendment for Monticello Project stage: Draft RAI ML0910300212009-04-0606 April 2009 Draft RAI Question from Instrumentation and Controls Branch Re. Proposed EPU Amendment Project stage: Draft RAI ML0910300172009-04-0606 April 2009 Conveys an Additional EPU Draft RAI Question from Instrumentation and Controls Branch Project stage: Draft RAI L-MT-09-025, Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 20092009-04-22022 April 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 2009 Project stage: Request ML0911205782009-04-22022 April 2009 Request for Audit of Implementation of Long-Term Stability Solution Project stage: Other ML0911902092009-04-29029 April 2009 Transmit Revised Draft RAI from the Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0914101232009-05-0606 May 2009 Monticello - Calculation 96-054, Rev 5, Turbine Stop Valve Closure/Generator Load Reject Scram Bypass Project stage: Other ML0911404702009-05-0707 May 2009 Determination That Submitted Information Can Be Withheld from Public Disclosure Project stage: Other ML0914101202009-05-13013 May 2009 Monticello - Extended Power Uprate: Response to NRC Instrumentation & Controls Branch Request for Additional Information Dated March 11, 2009, and April 6, 2009, and Fire Protection Branch RAIs Dated March 12, 2009 Project stage: Request L-MT-09-045, Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 20092009-05-26026 May 2009 Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 2009 Project stage: Request L-MT-09-029, Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 20092009-05-29029 May 2009 Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 2009 Project stage: Request 2009-02-24
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Category:Topical Report
MONTHYEARL-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 ML19213A1602019-08-0101 August 2019 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 14 ML18213A1542018-08-0101 August 2018 Island Independent Spent Fuel Storage Installation, and Monticello, Submittal of Quality Assurance Topical Report (NSPM-1 Revision 13 ML17213A0362017-08-0101 August 2017 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 11 ML16272A1782016-09-28028 September 2016 Xcel Energy, Northern States Power Company - Minnesota - Quality Assurance Topical Report NSPM-1, Revision 10 ML15289A0752015-10-31031 October 2015 Enclosure 6, WCAP-17549-NP, Revision 3, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using Ace. ML15289A0742015-09-30030 September 2015 Enclosure 5, WCAP-17252-NP, Revision 5, Acoustic Loads Definition for the Monticello Steam Dryer Replacement Project. L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report.2015-09-30030 September 2015 Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report. ML15211A0252015-07-30030 July 2015 ISFSI and Monticello - Submittal of Quality Assurance Topical Report (NSPM-1), Revision 8 ML15020A7112015-01-20020 January 2015 Independent Spent Fuel Storage Installation and Monticello, Supplement to Request for Review and Approval of Northern States Power Company Quality Assurance Topical Report ML14283A1202014-07-31031 July 2014 ANP-3274NP, Revision 1, Analytical Methods for Monticello ATWS-1. ML14283A1212014-04-30030 April 2014 ANP-3284NP, Results of Analysis & Benchmarking of Methods for Monticello ATWS-1. L-MT-14-044, ANP-3135NP, Applicability of Areva BWR Methods to Extended Flow Window for Monticello.2014-04-30030 April 2014 ANP-3135NP, Applicability of Areva BWR Methods to Extended Flow Window for Monticello. ML14218A6732013-12-20020 December 2013 Enclosure 2 - Xcel Energy Northern States Power Company - Minnesota - Quality Assurance Topical Report NSPM-1, Revision 7 ML13220A0072013-08-0606 August 2013 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 6 ML12226A1782012-08-10010 August 2012 Independent Spent Fuel Storage Installation and Monticello - Submittal of Quality Assurance Topical Report (NSPM-1), Revision 5 ML1122014662011-08-0808 August 2011 Independent Spent Fuel and Monticello, Submittal of Quality Assurance Topical Report (NSPM-1), Revision 4 ML1020104662010-06-30030 June 2010 Enclosure 16 - Westinghouse WCAP-17252-NP, (Nonproprietary) Revision 0, Acoustic Loads Definition for the Monticello Steam Dryer Replacement Project ML1020104652010-06-30030 June 2010 Enclosure 15 - Westinghouse WCAP-17251-NP, (Nonproprietary) Revision 0, Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report ML1020104632010-06-30030 June 2010 Enclosure 12 - Westinghouse WCAP-17085-NP, (Nonproprietary) Revision 1, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads. L-HU-04-039, Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 20042004-09-22022 September 2004 Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 2004 ML0330701622003-10-31031 October 2003 Table Comparing ANSI N18.7-1976 to ASME Nqa -1-1994 & NMC QATR ML0330701642003-10-31031 October 2003 NQA-1 Vs Non-Programmatic ANSI Standards Comparison Tables 2023-07-04
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L-MT-1 5-074ENCLOSURE 7WESTINGHOUSE WCAP-1 8604-NP, (NON-PROPRIETARY) REVISION 0MONTICELLO EPU MAIN STEAM LINE STRAIN GAUGEDATA EVALUATION REPORT60 pages follow Westinghouse Non-Proprietary Class 3WCAP-1 8064-NPRevision 0September 2015Monticello EPUMain Steam Line Strain GaugeData Evaluation Report Westinghouse WESTINGHOUSE NON-PROPRIETARY CLASS 3WCAP-18064-NPRevision 0Monticello EPUMain Steam Line Strain Gauge Data Evaluation ReportInessa E. Berman*BWR EngineeringSeptember 2015Reviewers: AnnMarie Rowland*BWR EngineeringApproved: Sanjaybir S. Bakshi*, ManagerBWR Engineering*Electronically approved records are authenticated in the electronic document management system.Westinghouse Electric Company LLC1000 Westinghouse DriveCranberry Township, PA 16066, USA© 2015 Westinghouse Electric Company LLCAll Rights ReservedWCAP- 1 8064-NP.docx iiTABLE OF CONTENTSLIST OF TABLES ..................................................................................................iiLIST OF FIGURES ............................................................................................... ivEXECUTIVE SUMMARY ....................................................................................... viLIST OF ACRONYMS AND ABBREVIATIONS............................................................. vii1 INTRODUCTION...................................................................................... 1- 12 ASSUMPTIONS AND SUMMARY OF PREVIOUS WORK ..................................... 2-12.1 AS SUMPTIONS............................................................................... 2-12.2 ACOUSTIC SCREENING ................................................................... 2-12.3 SUB SCALE TESTING....................................................................... 2-13 DATA PROCESSING PLAN AND RESULTS ...................................................... 3-13.1 DATA COLLECTION ........................................................................ 3-13.2 STRAIN-TO-PRESSURE CONVERSION ................................................. 3-23.3 NARROW-BAND FILTERING.............................................................. 3-43.4 POWER SPECTRAL DENSITY............................................................. 3-73.5 RMS PRESSURE DERIVATION ............................................................ 3-73.6 PSD DERIVATION ........................................................................... 3-73.7 WAVELET DENOISING..................................................................... 3-73.8 LIMIT CURVES DERIVIATION ........................................................... 3-94 INPUTS TO PROCESSING ........................................................................... 4-15 DISCUSSION OF RESULTS.......................................................................... 5-15.1 DATA ANALYSIS AND SIGNAL PROCESSING OF MSL STRAIN GAUGEDATA AT [ ]a~c THERMAL POWER ........................................... 5-15.1.1 Evaluation of Raw MSL Strain Gauge Plant Data .............................. 5-15.1.2 Comparison of Raw MSL PSD -Data and EIC Signals ....................... 5-95.1.3 Strain to Pressure Conversion ................................................... 5-145.1.4 Wavelet DeNoising............................................................... 5-145.2 EVALUATION OF PLANT ACOUSTIC SIGNATURE.................................. 5-235.2.1 PSD Evaluation................................................................... 5-235.2.2 RMS Pressure Trends ............................................................ 5-325.2.3 Limit Curves ...................................................................... 5-346 CONCLUSIONS ....................................................................................... 6-17 REFERENCES ......................................................................................... 7-1 iii°.LIST OF TABLESTable 3-1 Channel Combinations for Each Dataset .................................................... 3-3Table 3-2 Notch Filters, [.....................................................................3-4Table 3-3 Notch Filters, [.....................................................................3. 5Table 3-4 Notch Filters, [.....................................................................3-5Table 3-6 Notch Filters, [..................................................................... 3-6Table 3-7 Notch Filters, [..................................................................... 3-6Table 3-8 Notch Filters, [..................................................................... 3-6Table 4-1 Data Filenames and Recording Times ....................................................... 4-1Table 5-1 [ ]ac .............................5-14 ivLIST OF FIGURESFigure 5-1Figure 5-2Figure 5-3Figure 5-4Figure 5-5Figure 5-6Figure 5-7Figure 5-8Figure 5-9Figure 5-10Figure 5-11Figure 5-12Figure 5-13Figure 5-14Figure 5-15Figure 5-16Figure 5-17Figure 5-18Figure 5-19Figure 5-20Figure 5-21Figure 5-22................................ ................ 5-1........................ ................. 5-2............................... ............. 5-2................................ ..............5-3............................... ............ 5-3................................ .............. 5-4]......................5-4.................................... 5-6............................... ............... 5-7...................... ..................... 5-7].................5-9]a ........5-80] c .......5-11Sa¢........5-12] c.......5-11.................................................................. 5-12................................................................. 5-13......................................................5-15]a" .......................................................5-16]a ....................................................... 5-17IIFigure 5-23Figure 5-24Figure 5-25 VFigure 5-26[Figure 5-27 []a,c............................................................. 5-20]8'C. ......................................... 5-21Figure 5-28Figure 5-29Figure 5-30Figure 5-31Figure 5-32Figure 5-33Figure 5-34Figure 5-35Figure 5-36Figure 5-37Figure 5-38Figure 5-39Figure 5-40Figure 5-41Figure 5-42II]3° .......................................... 5-22........... ... ...............................................................................5-24......... ............................................................ i.......... 5-25........ ...................................................................... 5-26........ ........................................................................ 5-27........ ...................................................................... 5-28........ ..................................................................... 5-29........ ..................................................................... 5-30].... ...................................................... 5-31............ ....................................................... 5-32....... ..................................................................... 5-34........ .................................................................... 5-35........ .................................................................... 5-36........ .................................................................... 5-37 viEXECUTIVE SUMMARYMonticello Nuclear generating plant (MNGP, herein referred to as "Monticello") is implementing anextended power uprate (EPU) to increase plant power to[a]ac]aa~c]aa~c VIILIST OF ACRONYMS AND ABBREVIATIONSACM [ ]ASME American Society of Mechanical EngineersBWR boiling water reactorCLTP current licensed thermal power, 1775 MWtDAS data acquisition systemDS downstream (for Figures only)EIC electrical interference checkEPU extended power uprate, 2004 MWtFFT fast Fourier transformMSL main steam lineNRC Nuclear Regulatory CommissionOEM Original equipment manufacturerPCF [ ]PSD power spectral densityRMS root mean squareRSD Replacement steam dryerRRP reactor recirculation pumpSIA Structural Integrity Associates, Inc.SRV safety relief valveUS upstream (for Figures only)VPF vane passing frequenciesTrademark Note:MATLAB is a registered trademark of The Math Works, Inc.
1-11 INTRODUCTION1a~cTo satisfy the requirements of the United States Nuclear Regulatory Commiss ion (NRC) RegulatoryGuide 1.20, Revision 3 (Reference 2), an analysis must be performed to demonstrate the structuralintegrity of reactor internal components,[]a~cCurrent industry experience has shown that increasing power in a boiling water reactor (BWR) byincreasing the steam speed in the MSLs may lead to pressure increases above the expected increase fromthe increase in dynamic pressure. [I]C These requirements are contained inRegulatory Guide 1.20, Revision 3 (Reference 2).From November 2014 till June 2015, Monticello went through power ascension from 1775 MWt to 2004MWt thermal power. During the power ascension, time-history recordings were taken from 64 straingages (SGs) installed on MSLs at each of the following approximate power levels:[I]I]aCo The processing of the MSL strain gauge data at each powerlevel was described in Reference 4 through Reference 10.The main purposes for processing the Monticello data are as follows.1. []a~c2. [3. []a,c]a,c 2-12 ASSUMPTIONS AND SUMMARY OF PREVIOUS WORK2.1 ASSUMPTIONS[]a,cThe acoustic speed in steam is assumed to be 1600 ft/s (Reference 11).[I]a~cThe plant is assumed to be operating at steady state for the entire 4 minutes of data collection at each ofthe power levels at which data were collected.[]a~c2.2 ACOUSTIC SCREENING] a,bc2.3 SUBSCALE TESTING[]a,c 3-13 DATA PROCESSING PLAN AND RESULTSEPU power ascension MSL strain gauge data were collected by MNGP and provided to Westinghouse.The processing that was performed on the data is described in the following sections. All filteringoperations, as well as the processing for the data comparisons, were performed using custom MATLABprograms. These are documented in Reference 13. The processing methodology applied to theMonticello MSL strain gauge data was consistent with the benchmarking of the prediction of acousticpressures using MSL strain gauge data described in Reference 14.3.1 DATA COLLECTION][]a~c[]a~bData were recorded at each of the following approximate power levels:[a~bc 3-23.2 STRAIN-TO-PRESSURE CONVERSIONwhere, L I a'bab (3-1)K III ]a~cSa~b 3-3IIa.b 3-43.3 NARROW-BAND FILTERINGII]a,c[~a]ac]aa~eSTable 3-2 Notch Filters, [ ]__Filter Order Low Freq High Freq Filter Type Reason_fl b 3-5Table 3-3 Notch Filters, [ ]b ]Filter Order Low Freq High Freq Filter Type ReasonTable 3-4 Notch Filters, []Filter Order Low Freq High Freq Filter Type Reasonb-Table 3-5 Notch Filters, [Filter Order Low Freq High Freq [Filter TypeReasonb 3-6Table 3-6 Notch Filters, [ ]bFilter Order Low Freq High Freq Filter Type ReasonSTable 3-7 Notch Filters, [ ]bFilter OrderI Low Freq High Freq Filter Type ReasonbTable 3-8 Notch Filters, [Filter Order Low Freq High Freq Filter TypeReasonbII 3-73.4 POWER SPECTRAL DENSITYThe PSDs were calculated using Welch's Modified Periodogram method. The data were separated intosegments of 1 second, and a Hanning window was applied to reduce side-lobe leakage. This resulted in afrequency resolution of 1 Hertz.3.5 RMS PRESSURE DERIVATION]a,cL]ac(3 -2)where,KIa,c3.6 PSD DERIVATIONThe PSDs used in the methods presented in this report were derived using Welch's modified periodogrammethod. The signal was divided up into time ensembles with the same number of lines as the samplingfrequency, resulting in a 1 Hz frequency resolution in the final PSD. A Hanning window was used toreduce spectral leakage, and 50 percent overlap was used to increase the number of ensembles availablefor averaging.3.7 WAVELET DENOISINGIIII]a,c]ac[]a,o 3-8]aa~cFigure 3-1 [ ]a'c]a~c 3-9]a~c[]a,C (3-3)where,[ ]a~r ]a]a~c3.8 LIMIT CURVES DERIVIATION]aa~c[]a,c (3-4)[]a,c (3-5)where,]a,c[ a,c[ ]o~[]a,c 4-14 INPUTS TO PROCESSINGThe inputs to the data processing include the Monticello plant signals. These were gathered by MNGPduring and transmifted electronically to Westinghouse. The signals were formally documented inReference 13. The dates, times, and filenames are listed in Table 4-1.Table 4-1Data Filenames and Recording TimesFilenameSignalTypeDate TimePowerLevela,b 5-15 DISCUSSION OF RESULTS5.1 DATA ANALYSIS AND SIGNAL PROCESSING OF MSL STRAIN GAUGE DATAAT [ ]a~ THERMAL POWER5.1.1 Evaluation of Raw MSL Strain Gauge Plant DataThe raw time domain data and spectrograms from the MSL SG instruments were plotted and evaluatedfor channels that showed no data, or data that showed noticeable transients. If an MSL strain gaugechannel showed no data, it was removed from processing.[Figure 5-11[]b[
5-2Figure 5-21[]Similar results are observed for all other channels shown in Figure 5-3 and Figure 5-4. Except,time history and PSD curve of channel 5 show elevated noise, and therefore this channel was alsoexcluded from processing.Figure 5-3[
5-3Figure 5-4 [j]K 7bFigure 5-5 5-4mbFigure 5-6 [ ]bF 7bFigure 5-7[
5-5bFigure 5-8 ]bn 7bFigure 5-9[
5-6]bbF 7bFigure 5-11 [jb 5-7]bbF 7bFigure 5-13[
5-8bFigure 5-15[jb 5-9b-Figure 5-16 [5.1.2 Comparison of Raw MSL PSD -Data and ETC Signals[]a~c 5-10a,bFigure 5-17 [J a,c 5-11a,bFigure 5-18[I ,c 5-12a,bFigure 5-19[la,c 5-13a,bFigure 5-20[I ,c 5-145.1.3 Strain to Pressure Conversion[]a,cb5.1.4 Wavelet De-Noising]a~o 5-15Sa,bFigure 5-21 [Sa,c 5-16a,bFigure 5-22[I, 5-17a,bFigure 5-23[Ia,c 5-18a,bFigure 5-24[Ia,c 5-19a,bFigure 5-25[a,c 5 -20a,bFigure 5-26[Ia,c 5-21-- a,bFigure 5-27[j ac 5 -22a,bFigure 5-28[I~
5 -235.2 EVALUATION OF PLANT ACOUSTIC SIGNATUREThe evaluation of the plant acoustic signature is performed by examining the PSDs and the RMS pressuretrends. The PSDs are derived as described in Section 3.6, and the RMS pressures are derived per themethodology detailed in Section 3.5.5.2.1 PSD Evaluation]a,c 5-24bFigure 5-29[jb 5-25bFigure 5-30[jb 5 -26bFigure 5-31[
5-27Figure 5-32 []
5-28bFigure 5-33 [jb 5-29bFigure 5-34[
5-30bFigure 5-35 []Ii 5-31bFigure 5-36[jb 5-325.2.2 RMS Pressure TrendsabbFigure 5-37[],
5-33bFigure 5-38[],
5-345.2.3 Limit CurvesThe minimum alternating stress ratio, which was derived in Reference 10 and is 1.43. Figure 5-39 throughFigure 5-42 show the plots of the limit curves for MSL A through MSL D, respectively. In each plot,there are two lines; the limit curves Li and L2.Figure 5-39 [ ]
5-35bFigure 5-40 [b 5-36bFigure 5-41 [
5-375-3Figure 5-42 [IIb 6-16 CONCLUSIONS[]a~c[t~[]ac 7-17 REFERENCES1. []a~b2. United States Nuclear Regulatory Commission Regulatory Guide 1.20, Rev. 3, "ComprehensiveVibration Assessment Program for Reactor Internals During Preoperational and Initial StartupTesting," March 2007.3. []a,c4. []a~b5. r6.7. I8.9. I10. []a,cI a,c]a~b]a,c]a~c]a,c11. ASME, "ASME Steam Tables," Fifth Edition, 1983.12. []a~c13. I]a~c 7-214.]a,c15. r]ac16. I17. r18. [19.a,.c],.ca,.c