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Category:Report
MONTHYEARL-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024
Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)
ML23172A1112023-06-21021 June 2023
SLRA - Requests for Confirmation of Information - Set 1
L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022
Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies
L-MT-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report2022-01-20020 January 2022
Technical Specification 5.6.4 Post Accident Monitoring Report
ML21211A5962021-06-30030 June 2021
Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, Affidavit
L-MT-21-016, Nuclear Material Transaction Report2021-03-25025 March 2021
Nuclear Material Transaction Report
L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange2020-01-31031 January 2020
10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange
ML19308A0562019-10-0808 October 2019
Enclosure 1 - Notification of Changes to the Emergency Response Data System (ERDS)
L-MT-19-020, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..2019-04-25025 April 2019
Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..
L-MT-17-060, Steam Dryer Visual Inspection Report2017-08-10010 August 2017
Steam Dryer Visual Inspection Report
L-MT-17-055, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 42017-07-26026 July 2017
Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4
ML17088A5272017-03-31031 March 2017
NSIR Dpcp Confirmatory Review Report, 10 CFR 50.54(p)(2) Changes to the Security Plan, Revision 16, Northern States Power Company, Monticello Nuclear Generating Plant
L-MT-17-015, Mitigating Strategies Flood Hazard Assessment (MSA) Submittal2017-03-28028 March 2017
Mitigating Strategies Flood Hazard Assessment (MSA) Submittal
ML16302A2462016-10-28028 October 2016
Spent Fuel Pool Evaluation Supplemental Report, Response to 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 Fukushima..
ML16221A2752016-07-31031 July 2016
ANP-3274NP, Revision 2, Analytical Methods for Monticello ATWS-I.
L-MT-16-037, ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.2016-07-31031 July 2016
ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.
L-MT-16-010, Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+).2016-02-29029 February 2016
Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+).
ML15274A4752015-09-29029 September 2015
Enclosure 6, Areva Report ANP-3435NP, Revision 0 to Are VA Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW LAR (Non-Proprietary)
L-MT-15-065, Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits2015-09-29029 September 2015
Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits
ML15274A4742015-09-29029 September 2015
Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints
ML15175A3362015-07-0808 July 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force
ML15169A3582015-06-11011 June 2015
PSP Rev 14 Technical Review 06-11-15
ML16035A1842015-01-30030 January 2015
Document 51-9234641-001, Technical Report of the Demonstration of UT NDE Procedure 54-UT-114-000, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds.
ML16035A1862015-01-30030 January 2015
54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3
ML16035A1852015-01-30030 January 2015
54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 1 of 3
L-MT-14-103, Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-1032014-12-31031 December 2014
Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-103
ML16005A1102014-09-25025 September 2014
Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant
L-MT-14-075, LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set 8.2014-09-19019 September 2014
LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #8.
ML14269A3252014-09-0505 September 2014
LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process.
ML14269A3232014-09-0505 September 2014
LTR-BWR-ENG-14-034-NP, Investigation Into the Cause of Exceeding the Level 1 (L1) and Level 2 (L2) Limit Curves Generated Based on 2011 Monticello Main Steam Line Strain Gauge Data.
ML14204A6232014-07-18018 July 2014
Enclosure 3, Attachment - Response to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Accoustic/Structural Ananlyses Set #7
ML14176A9612014-06-24024 June 2014
Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014
ML18100A1902014-05-22022 May 2014
Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records
ML14136A2892014-05-12012 May 2014
14C4229-RPT-001, Revision 3, Monticello Nuclear Generating Plant Seismic Hazard and Screening Report.
L-MT-14-041, ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.2014-05-0909 May 2014
ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.
ML14069A0052014-04-11011 April 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of NTTF Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident
ML14014A2682014-02-28028 February 2014
Staff Review and Evaluation of the Fifth 10-Year Interval Inservice Inspection Program Plan
ML14064A1862014-02-25025 February 2014
Structural Integrity Associates, Inc., Evaluation File No. 1301525.301, Monticello Shroud Support Structure Flaw Evaluation Review and Support Plate Weld Inspection Recommendations
L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information2014-01-31031 January 2014
Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information
ML13358A3732013-12-31031 December 2013
Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit Plus
L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit2013-12-20020 December 2013
Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit
ML13282A1422013-10-0404 October 2013
GE-MNGP-AEP-3304R1, Enclosure 2, GEH Response to Mella + RAI 2
L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages2013-10-0404 October 2013
GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages
ML13248A3442013-08-29029 August 2013
WCAP-17548-NP, Revision 2 - Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data, Enclosure 10
ML13248A3452013-08-29029 August 2013
WCAP-17251-NP, Revision 2 - Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report, Enclosure 11
ML13248A3462013-08-29029 August 2013
WCAP-17252-NP, Revision 4 - Acoustic Loads Definition for the Monticello Steam Dyer Replacement Project, Enclosure 12
ML13248A3482013-08-29029 August 2013
WCAP-17549-NP, Revision 2 - Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, Enclosure 13
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 142013-08-29029 August 2013
WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14
ML13200A1962013-07-31031 July 2013
ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel.
ML13200A1922013-07-31031 July 2013
ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies.
2024-06-10
[Table view]
Category:Miscellaneous
MONTHYEARML23172A1112023-06-21021 June 2023
SLRA - Requests for Confirmation of Information - Set 1
L-MT-17-060, Steam Dryer Visual Inspection Report2017-08-10010 August 2017
Steam Dryer Visual Inspection Report
ML17088A5272017-03-31031 March 2017
NSIR Dpcp Confirmatory Review Report, 10 CFR 50.54(p)(2) Changes to the Security Plan, Revision 16, Northern States Power Company, Monticello Nuclear Generating Plant
L-MT-17-015, Mitigating Strategies Flood Hazard Assessment (MSA) Submittal2017-03-28028 March 2017
Mitigating Strategies Flood Hazard Assessment (MSA) Submittal
ML16302A2462016-10-28028 October 2016
Spent Fuel Pool Evaluation Supplemental Report, Response to 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 Fukushima..
ML16221A2752016-07-31031 July 2016
ANP-3274NP, Revision 2, Analytical Methods for Monticello ATWS-I.
L-MT-16-037, ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.2016-07-31031 July 2016
ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.
ML15175A3362015-07-0808 July 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force
ML15169A3582015-06-11011 June 2015
PSP Rev 14 Technical Review 06-11-15
ML14204A6232014-07-18018 July 2014
Enclosure 3, Attachment - Response to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Accoustic/Structural Ananlyses Set #7
ML14136A2892014-05-12012 May 2014
14C4229-RPT-001, Revision 3, Monticello Nuclear Generating Plant Seismic Hazard and Screening Report.
ML14014A2682014-02-28028 February 2014
Staff Review and Evaluation of the Fifth 10-Year Interval Inservice Inspection Program Plan
L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit2013-12-20020 December 2013
Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit
ML13282A1422013-10-0404 October 2013
GE-MNGP-AEP-3304R1, Enclosure 2, GEH Response to Mella + RAI 2
L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages2013-10-0404 October 2013
GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages
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 142013-08-29029 August 2013
WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14
ML13248A3482013-08-29029 August 2013
WCAP-17549-NP, Revision 2 - Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, Enclosure 13
ML13248A3462013-08-29029 August 2013
WCAP-17252-NP, Revision 4 - Acoustic Loads Definition for the Monticello Steam Dyer Replacement Project, Enclosure 12
ML13248A3452013-08-29029 August 2013
WCAP-17251-NP, Revision 2 - Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report, Enclosure 11
ML13248A3442013-08-29029 August 2013
WCAP-17548-NP, Revision 2 - Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data, Enclosure 10
ML13205A0852013-07-12012 July 2013
Enclosure 2 - Westinghouse Electric Co. Letter LTR-A&SA-13-14, NP-Attachment, Revision 0, Responses to the U.S. NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #5
L-MT-13-053, 0000-0146-5423-SRLR, Rev. 1, Supplemental Reload Licensing Report for Monticello, Reload 26 Cycle 27 Extended Power Uprate (EPU)2013-01-31031 January 2013
0000-0146-5423-SRLR, Rev. 1, Supplemental Reload Licensing Report for Monticello, Reload 26 Cycle 27 Extended Power Uprate (EPU)
ML13039A2002013-01-21021 January 2013
Enclosures 1 & 2 to L-MT-12-114 - Responses to the Gap Analysis and Marked Up Page Changes to EPU Documentation Based on the Gap Analysis Results, Part 1 of 3
ML13039A2022013-01-21021 January 2013
Enclosures 1 & 2 to L-MT-12-114 - Responses to the Gap Analysis and Marked Up Page Changes to EPU Documentation Based on the Gap Analysis Results, Part 2 of 3
ML12356A1722012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 3 of 8
ML12356A1692012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 8 of 8
ML12356A1702012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 1 of 8
ML12356A1712012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 2 of 8
ML12356A1742012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 4 of 8
ML12340A4302012-11-30030 November 2012
Enclosure 2, Presentation Materials Used During the Course of the NRC Audit of General Electric - Hitachi Held on October 24-25, 2012 - Non-Proprietary
L-MT-12-112, Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 7 of 82012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 7 of 8
ML12356A1752012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 5 of 8
L-MT-12-103, Final Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012
Final Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML12146A1132012-06-0808 June 2012
Letter Approving Deviation from Response Schedule Imposed by 10 CFR 50.54(f) Letter Re. NTTF Issue R9.3
L-MT-11-076, 2011 Report of Changes and Errors in ECCS Evaluation Models2011-12-22022 December 2011
2011 Report of Changes and Errors in ECCS Evaluation Models
ML1127000692011-09-26026 September 2011
Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants
ML1027903732010-09-28028 September 2010
Enclosure 2, GE-MNGP-AEP-1913 R1, GEH Responses to Reactor Systems RAIs
ML1016705842010-06-10010 June 2010
Inservice Inspection Examination Plan, Rev. 4, Fourth Interval, May 1, 2003 Through May 31, 2012
ML1012704392010-05-0505 May 2010
Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML1007104442010-03-0404 March 2010
Monticello, Enclosure 2, GE-MNGP-AEP-1687, Rev. 1, GEH Responses to NRC Supplemental Requests 1, 3, and 4
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.
ML0915405192008-05-14014 May 2008
Enclosures 1 and 2 - Radioactive Effluent Release Report and Off-Site Radiation Dose Assessment for January 1 - December 31, 2008
ML0805901332008-02-28028 February 2008
U.S. Dept. of Homeland Security/Final Report for the November 6, 2007, Radiological Emergency Preparedness (REP) Full Participation Plume Exposure Pathway Exercise for the Monticello Nuclear Generating Plant/Report
ML0613903922006-06-0808 June 2006
Web References for Monticello Dseis: Aquatic Ecology Part 1
ML0602304312006-01-23023 January 2006
ITS Conversion Beyond Scope Issue 7
ML0520104982005-07-0505 July 2005
Minnesota Department of Natural Resources Web Page 2000 Minnesota Bald Eagle Survey
ML0520104942005-07-0505 July 2005
the Raptor Center (University of Minnesota) - Raptor Facts Bald Eagle
ML0613901282005-06-0808 June 2005
Web References for Monticello Dseis: Terrestrial Ecology
ML0613902252005-06-0808 June 2005
Web References for Monticello Dseis: Water Use/Water Quality
L-HU-05-012, Report of Unsatisfactory Blind Performance Testing Results, Monticello Nuclear Generating Plant & Prarie Island Nuclear Generating Plant, Units 1 and 22005-06-0303 June 2005
Report of Unsatisfactory Blind Performance Testing Results, Monticello Nuclear Generating Plant & Prarie Island Nuclear Generating Plant, Units 1 and 2
2023-06-21
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Text
L-MT-14-060 ENCLOSURE 3 WESTINGHOUSE LETTER ATTACHMENT, LTR-BWR-ENG-14-01 0-NP RESPONSES TO THE US NRC REQUEST FOR ADDITIONAL INFORMATION RELATIVE TO THE MONTICELLO REPLACEMENT STEAM DRYER ACOUSTIC/STRUCTURAL ANALYSES SET #7 27 pages follow
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-14-010-NP Responses to the US NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #7 July 18, 2014 Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066 USA
© 2014 Westinghouse Electric Company LLC All Rights Reserved
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP REQUEST FOR ADDITIONAL INFORMATION MECHANICAL AND CIVIL ENGINEERING BRANCH (EMCB) OF THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING MONTICELLO NUCLEAR GENERATING PLANT EXTENDED POWER UPRATE POWER ASCENSION DATA TREND EVALUATION NORTHERN STATES POWER COMPANY - MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 (TAC NO. MF3330)
MNGP EPU-EMCB-RSD-RAI-120 During a review of power ascension data in March and April 2014, Xcel Energy discovered mislabeling of the main steam line (MSL)-C leads at the Monticello Nuclear Generating Plant (MNGP). In a conference call on April 9, 2014, the NRC staff were informed that the leads from the upper and lower strain gauges on MSL-C were confirmed to be erroneously reversed in 2011. Xcel Energy indicated during the conference call that the impact would be small. However, this issue could potentially impact the bias errors and uncertainties provided in the end-to-end benchmarking report for Acoustic Circuit Model Enhanced (ACE) 2.0 (Reference 1).
The NRC staff requests the following additional information:
- 1. Please provide a detailed technical explanation for why the changes in bias errors and uncertainties were small; when the upper and lower strain gauge signals for MNGP MSL-C were interchanged due to mislabeling, compared to the correct case. The explanation should address the entire frequency range, since the dominant dryer excitation is frequency dependent.
- 2. Also, provide plots of the MSL-C monopole and dipole sources for the two cases, and a plot of overlaid or super-imposed Power Spectral Densities (PSDs) of MSL-C strain gauge signals to compare the similarities and the differences.
Reference
- 1. Letter L-MT-13-091 from Mark Schimmel, Xcel Energy, to U.S. Regulatory Commission Document Control Desk, dated August 29, 2013 (ADAMS Accession No. ML13248A343): Enclosure 6 (proprietary) and Enclosure 14 (non-proprietary), Westinghouse WCAP-17716-P(NP), Revision 1, "Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project," dated August 2013 (ADAMS Accession Nos. ML13248A353 (proprietary) and ML13248A349 (non-proprietary), respectively).
I
Westinghouse Non-Proprietary Class 3 LTR-BVWR-ENG- 14-010-NP
RESPONSE
Background In April 2014, Xcel Energy identified that the main steam line (MSL)C strain gauge cable switching performed during the 2011 refuel outage, as a corrective action in response to a cable labeling issue, appeared to have resulted in erroneous reversal of the upstream and downstream strain gauge cables. Numerous methods were employed to validate that the MSLC cables were incorrectly switched. A revised replacement steam dryer (RSD) acoustic-structural analysis has consequently been performed and is documented in this response. The revised analysis addresses the impact to the MSLC strain gauge signals due to the switched cables.
Additionally, this response provides brief descriptions of the revisions that will be made to the previously submitted RSD reports as a result of the revised acoustic-structural analysis.
The MSL strain gauge signals are [
]a,c Figure RAI-120-1 summarizes the steps in the process which are affected by the correcting of the signals. In both cases (MSLC-2011 and MSLC-Corrected), the methods used in each step are identical; however, changing the input MSL signals [ ]a,c a,c Figure RAI-120-1 Summary of the Acoustic-Structural Analysis Process 2
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP Response to Request 1 ACE Revision 2.0 was benchmarked against
]a,c Table RAI-120-1 Bias and Uncertainty a,b,c Table RAI-120-2 MNGP Total Uncertainty a,b,c In the frequency ranges for which the MSLC upstream and downstream signals differ (see Figure RAI-120-1),
a,b,c 3
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-01 0-NP Response to Request 2 Plots of the MSLC monopole and dipole sources for the two cases are presented in Figure RAI-120-8 and Figure RAI-120-9. A plot of the MSLC upstream and downstream signal Power Spectral Densities (PSDs) is provided in Figure RAI-120-2.
Detailed Results This RAI response documents the portions of the acoustic-structural analysis that are affected by switching the MSLC signals. Revisions to the previously submitted reports will be updated to include the changes documented herein due to the MSLC signal correction. The proprietary and non-proprietary versions of the following reports will be updated and submitted along with the final EPU report after power ascension to EPU is complete:
WCAP-17716, Rev 1, "Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project."
WCAP-17252, Rev 4, "Acoustic Loads Definition for the Monticello Steam Dryer Replacement Project."
WCAP-1 7549, Rev 2, "Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE."
SES09-127, Rev 2, "Monticello Steam Dryer Replacement - Structural Verification of Steam Dryer."
The ASME qualification for the RSD will be updated to include the FIV stresses resulting from the correction of the MSLC signals. All ASME Section III, Subsection NG requirements are met with the updated FIV stress values.
Signal Processing Digital signal processing is performed to
]a.c The signal processing techniques used for the CLTP and EPU signal generation were identical to those documented and accepted in WCAP-17716-P Rev. 1.
Any plots of MSL signals for MSLA, MSLB, and MSLD are unchanged. For MSLC, any plot previously labeled as "upstream" will now be "downstream" and vice-versa.
]a,c 4
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP a,b,c Figure RAI-120-2 CLTP Signal (after signal processing) - MSLC 5
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP a,b,c Figure RAI-120-3 Predicted EPU Signal - MSLC 6
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-01 0-NP ACE Revision 2.0.1 Benchmarkinq The ACE Revision 2.0 model was benchmarked
]ac Table RAI-120-3 [ I a,c 7]a,b,c I
]ac 7
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-01 0-NP
-]a,b,c Figure RAI-120-4 [ Iax a,b,c Figure RAI-120-5 [ ]a,c 8
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-01 0-NP Table RAI-120-4 Predicted RMS Strains a,b,c I
]ac a,c I
Ia,c I I a,c Based on the above measurements, predictions, and calculations, the biases/uncertainties and total uncertainties for ACE Revision 2.0.1 are presented in Table RAI-120-1 and Table RAI-120-2.
9
Westinghouse Non-Proprietaty Class 3 LTR-BWR-ENG- 14-01 0-NP
]a,c a,b,c Figure RAI-120-6 [ I a,c 10
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP a,b,c Iaxc Figure RAI-120-7 [
11
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP Application of ACE Revision 2.0.1 - Acoustic Load Definition of Monticello Steam Dryer at EPU Using Corrected MSLC Signals I
a,c a,b,c Figure RAI-120-8 ACE Dipole Signal - EPU - MSL C 12
Westinghouse Non-Proprietary Class 3 LTR-B WR-ENG- 14-010-NP a,b,c Figure RAI-120-9 ACE Monopole Signal - EPU - MSL C Application of r la - Acoustic Load Definition of Monticello Steam Dryer at EPU Usina Corrected MSLC Sicnals I
13
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP
]a,c a,b,c Figure RAI-120-10 [ ]a Dipole Signal - EPU - MSLC 14
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP a,b,c Figure RAI-120-11 [ ]a Monopole Signal - EPU - MSLC 15
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP Structural Evaluation for High-cycle Acoustic Loads A high-cycle fatigue evaluation of the MNGP RSD was completed with acoustic loads generated using ACE Revision 2.0.1 [ ]a. The methods and techniques used in the evaluation are identical to those submitted in WCAP-17549-P Revision 2. The finite element model was identical to what was previously used.
]a,c Summary of Results I
]ac 16
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP
]a,c a,b,c Table RAI-120-5 Summary of Results at EPU: [
Table RAI-120-6 Summary of Results at EPU: [ a,c a,b,c 17
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP a,b,c axc Figure RAI-120-12 Limiting High-Stress Locations [
18
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP a,c Figure RAI-120-13 Limiting High-Stress Locations [ Iac 19
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-01 0-NP I a,b,c F
Figure RAI-120-14 MASR[ ]a,c. MSLC 2011 - Stress PSD a,b,c Figure RAI-120-15 MASR[
]a,c. MSLC Corrected - Stress PSD 20
Westinghouse Non-Proprietary Class 3 LTR-B WR-ENG- 14-01 0-NP I a,b,c Figure RAI-120-16 MASR [ ]a,c. MSLC 2011 - Stress PSD a,b,c Figure RAI-120-17 MASR [ ]a,c - MSLC Corrected - Stress PSD 21
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP I
a,c a,b,c Figure RAI-120-18 [ Ja,c Submodel Maximum Detailed View (Acoustic Stress) 22
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-1 4-010-NP I
]a,c a,c Figure RAI-120-19 [ ]a,c Weld Evaluation Location 23
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP MSL Limit Curves The method and technique used to develop the limit curves for the MNGP EPU power ascension are identical to those previously submitted in LTR-A&SA-09-32, Revision 8. For MSL A, B, and D, the shape of the upstream and downstream limit curves will be identical to those submitted in LTR-A&SA-09-32, Revision 8. [
]a,b,c. For MSLC, the same is true except the figures previously labeled upstream will now be labeled as downstream and vice versa. Figure RAI-120-20 through Figure RAI-120-23 present the updated MSL limit curves for the MNGP RSD. Level 1 limit curves ensure that the ASME allowable alternating stress value on the RSD is not exceeded. Level 2 limit curves ensure that 80% of the allowable alternating stress value on the RSD is not exceeded. During power ascension, the plant will be monitored and the PSDs will be compared to the limit curves at each power level test condition in the EPU Power Ascension Test. The situations presented in Table RAI-120-7 may occur depending on the magnitude of the pressure load. This process will be repeated until the EPU power level is achieved.
Table RAI-120-7 EPU Power Ascension Condition Action Pressure Load < Level 2 Increase power to the next level Perform a stress analysis at the current power Level 2 < Pressure Load < Level 1 level Reduce power to the previous step, engineering evaluation, and consideration of Pressure Load > Level 1 mitigation actions 24
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-01 0-NP a,b,c Figure RAI-120-20 Limit Curves - MSLA a,b,c Figure RAI-120-21 Limit Curves - MSLB 25
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG- 14-010-NP a,b,c Figure RAI-120-22 Limit Curves - MSLC a,b,c Figure RAI-120-23 Limit Curves - MSLD 26
QF0212, Revision 5 (FP-SC-RSI-04) Page 1 of 1 XcelEnergy° SHIPPING DOCUMENT NORTHERN STATES POWER -MN D/B/A Xcel Energy Monticello Nuclear Plant, 2807 W Hwy. 75, Monticello, MN 55362 Date: 7-22-14 Shipping Document Tracking Number: 15'4-Ship To:
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