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Category:Letter type:L
MONTHYEARL-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024
Subsequent License Renewal Application Supplement 8
L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023
License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data
L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023
Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2
L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023
2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023
Subsequent License Renewal Application Supplement 7
L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023
Update to the Technical Specification Bases
L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023
Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1
L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023
10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09
L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023
License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6
L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023
Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1
L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023
Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2
L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 3
L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6
L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023
Subsequent License Renewal Application Supplement 5
L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 1
L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023
2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report
L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023
10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11
L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023
Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1
L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023
Subsequent License Renewal Application Supplement 3
L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023
Subsequent License Renewal Application Supplement 2
L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023
Submittal of 2022 Annual Radiological Environmental Operating Report
L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023
Submittal of 2022 Annual Radioactive Effluent Release Report
L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023
Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32
L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023
2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023
Subsequent License Renewal Application Supplement 1
L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023
Core Operating Limits Report (COLR) for Cycle 31, Revision 3
L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023
Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2
L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023
10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)
L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023
CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program
L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023
Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)
L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022
Industry Groundwater Protection Initiative Special Report
L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022
L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative
L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022
2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022
Update to the Monticello Technical Specification Bases
L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022
Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022
Letter Submitting Post-Exam Package
L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022
Sixth Interval Inservice Testing (1ST) Plan
L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022
Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022
Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)
L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022
Changes to the Emergency Plan
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-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022
Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022
2021 Annual Radiological Environmental Operating Report
L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022
2021 Annual Radioactive Effluent Release Report
L-MT-22-016, 2021 Annual Report of Individual Monitoring2022-04-28028 April 2022
2021 Annual Report of Individual Monitoring
L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-04-18018 April 2022
Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022
License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency
L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System2022-03-15015 March 2022
Special Report for the Bypass of the Offgas Treatment Storage System
L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)2022-03-0707 March 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)
L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)
2024-01-11
[Table view]
Category:Report
MONTHYEARML23172A1112023-06-21021 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+).
ML15274A4742015-09-29029 September 2015
Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints
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
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)
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
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
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
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
ML13200A1922013-07-31031 July 2013
ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies.
ML13200A1962013-07-31031 July 2013
ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel.
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
ML13200A1902013-06-30030 June 2013
ANP-3224NP, Rev. 2, Applicability of Areva Np BWR Methods to Monticello.
2023-06-21
[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
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2011 Report of Changes and Errors in ECCS Evaluation Models
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Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants
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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
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ITS Conversion Beyond Scope Issue 7
ML0520104982005-07-0505 July 2005
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the Raptor Center (University of Minnesota) - Raptor Facts Bald Eagle
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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
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2023-06-21
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2807 West County Road 75 Monticello, MN 55362 (l Xcel Energy RES P 0 N SIBLE BY NAT U R E 800.895.4999 xcelenergy.com August 10, 2017 L-MT-17-060 License Conditions 2.C.(15)(f) and (g)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Steam Dryer Visual Inspection Report The Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, is providing the results of the steam dryer visual inspections conducted during the 2017 Refueling Outage (RFO) to meet Monticello Nuclear Generating Plant (MNGP) Renewed Facility Operating License DPR-22, License Conditions 2.C.(15)(f) and (g), stated below:
Condition f: During the first two scheduled refueling outages after reaching EPU [Extended Power Uprate] conditions, a visual inspection shall be conducted of all accessible, susceptible locations of the steam dryer in accordance with the inspection guidelines provided to the NRC.
Condition g: The results of the visual inspections of the steam dryer shall be reported to the NRC staff within 90 days following startup from the respective refueling outage.
The MNGP steam dryer visual inspection results are provided for the first complete operating cycle at full EPU conditions within the enclosure entitled "RFO 28 Steam Dryer Inspection Summary Report." Future inspections are to be performed following the second full operating cycle at EPU conditions during the 2019 RFO.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
L-MT-17-060 Document Control Desk Page 2 of 2 Should you have questions regarding this letter, please contact Mr. Richard Loeffler at (763) 295-1247.
,e Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Document Control Desk, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello
ENCLOSURE RFO 28 STEAM DRYER INSPECTION
SUMMARY
REPORT CONDUCTED DURING THE 2017 REFUELING OUTAGE FOR RENEWED FACILITY OPERATING LICENSE DPR-22 LICENSE CONDITIONS 2.C.(15)(f) and (g)
MONTICELLO NUCLEAR GENERATING PLANT (MNGP) 6 pages follow
L-MT-17-060 RFO 28 Steam Dryer Inspection Summary Report The Monticello replacement steam dryer (RSD) was inspected in accordance with the inspection recommendations described in LTR-A&SA-12-8, Revision 1, "Westinghouse Recommendations for the Monticello Replacement Steam Dryer Inspections" which was submitted to the NRC in letter L-MT 090, dated October 16, 2012. The examinations performed and the results are detailed in Table 1.
Nine (9) weld locations were inaccessible for inspection or no weld was identified. The weld locations that were inaccessible for inspection are italicized in Table 1. No relevant indications were identified on the replacement steam dryer.
The examinations were performed using both VT-3 and VT-1-89 visual inspection techniques. VT-1-89 is a visual examination using VT-1 resolution, distance, and angle of view requirements as described in ASME Section XI, Subparagraph IWA-2211(b), 1989 Edition, No Addenda. VT-1-89 is the recommended technique for steam dryer inspections and should be used to the extent practical per BWRVIP-139-A, "Steam Dryer Inspection and Flaw Evaluation Guidelines." Attachment 1 of L-MT-12-090 notes that the general guidelines for the steam dryer inspections should be based on the general principles found within BWRVI P-139-A.
Page 1 of6
L-MT-17-060 Table 1: RFO 28 Monticello Replacement Steam Dryer Inspection Results Weld Name Weld Description Exam Exam Result Type RSD-INT-GEN Replacement Steam Dryer Interior VT-3 No relevant indications.
RSD-OUT-0°-90° Replacement Steam Dryer Outside 0°-90° VT-3 No relevant indications.
RSD-OUT-90°-180° Replacement Steam Dryer Outside 90°-180° VT-3 No relevant indications.
RSD-OUT-180°-270° Replacement Steam Dryer Outside 180°-270° VT-3 No relevant indications.
RSD-OUT -270°-360° Replacement Steam Dryer Outside 270°-360° VT-3 No relevant indications.
RSD-SR-VLSI-35° Support Ring Vessel Lug Interface at 35° VT-3 No relevant indications.
RSD-SR-VLSI-145° Support Ring Vessel Lug Interface at 145° VT-3 No relevant indications.
RSD-SR-VLSI-215° Support Ring Vessel Lug Interface at 215° VT-3 No relevant indications.
RSD-SR-VLSI-325° Support Ring Vessel Lug Interface at 325° VT-3 No relevant indications.
RSD-LS-35° Leveling Screw at 35° VT-3 No relevant indications.
RSD-LS-145° Leveling Screw at 145° VT-3 No relevant indications.
RSD-LS-215° Leveling Screw at 215° VT-3 No relevant indications.
RSD-LS-325° Leveling Screw at 325° VT-3 No relevant indications.
RSD-A1-V2a Vane Bank A 1 Right Vertical Weld VT-1-89 No relevant indications.
RSD-A1-V2b Vane Bank A1 Left Vertical Weld VT-1-89 No relevant indications.
RSD-B1-V2a Vane Bank B1 Right Vertical Weld VT-1-89 No relevant indications.
RSD-B1-V2b Vane Bank B1 Left Vertical Weld VT-1-89 No relevant indications.
RSD-C1-V2a Vane Bank C1 Right Vertical Weld VT-1-89 No relevant indications.
RSD-C1-V2b Vane Bank C1 Left Vertical Weld VT-1-89 No relevant indications.
RSD-A2-H1 Hood A2 Bottom Horizontal Weld VT-1-89 No relevant indications.
RSD-A2-H2 Hood A2 Top Horizontal Weld VT-1-89 No relevant indications.
RSD-A2-V1 Hood A2 Right Vertical Weld VT-1-89 No relevant indications.
RSD-A3-H1 Hood A3 Bottom Horizontal Weld VT-1-89 No relevant indications.
RSD-A3-H2 Hood A3 Top Horizontal Weld VT-1-89 No relevant indications.
RSD-A3-V1 Hood A3 Right Vertical Weld VT-1-89 No relevant indications.
RSD-A4-V1 Hood A4 Right Vertical Weld VT-1-89 No relevant indications.
RSD-A6-H1 Hood A6 Bottom Horizontal Weld VT-1-89 No relevant indications.
RSD-A6-H2 Hood A6 Top Horizontal Weld VT-1-89 No relevant indications.
RSD-A6-V1 Hood A6 Right Vertical Weld VT-1-89 No relevant indications.
RSD-A7-H1 Hood A7 Bottom Horizontal Weld VT-1-89 No relevant indications.
RSD-A7-H2 Hood A7 Top Horizontal Weld VT-1-89 No relevant indications.
RSD-A7-V1 Hood A7 Right Vertical Weld VT-1-89 No relevant indications.
RSD-A8-V1 Hood AS Right Vertical Weld VT-1-89 No relevant indications.
RSD-B6-H1 Hood B6 Bottom Horizontal Weld VT-1-89 No relevant indications.
RSD-B6-H2 Hood B6 Top Horizontal Weld VT-1-89 No relevant indications.
Page 2 of 6
L-MT-17-060 Table 1: RFO 28 Monticello Replacement Steam Dryer Inspection Results Weld Name Weld Description Exam Exam Result Type RSD-B6-V1 Hood B6 Right Vertical Weld VT-1-89 No relevant indications.
RSD-B7-V1 Hood B7 Right Vertical Weld VT-1-89 No relevant indications.
RSD-C8-H1 Hood C8 Bottom Horizontal Weld VT-1-89 No relevant indications.
RSD-C8-H2 Hood C8 Top Horizontal Weld VT-1-89 No relevant indications.
RSD-C8-V1 Hood C8 Right Vertical Weld VT-1-89 No relevant indications.
RSD-C1-V1 Hood C1 Right Vertical Weld VT-1-89 No relevant indications.
RSD-A6-UG-H1 Upper Girder to Vane Bank Weld VT-1-89 No relevant indications.
RSD-A6-UG-H2 Upper Girder to Vane Bank Weld VT-1-89 No relevant indications.
RSD-B6-UG-H1 Upper Girder to Vane Bank Weld VT-1-89 No relevant indications.
RSD-B6-UG-H2 Upper Girder to Vane Bank Weld VT-1-89 No relevant indications.
RSD-C6-UG-H1 Upper Girder to Vane Bank Weld VT-1-89 No relevant indications.
RSD-C6-UG-H2 Upper Girder to Vane Bank Weld VT-1-89 No relevant indications.
RSD-EB-35° Earthquake Bracket at 35° VT-3 No relevant indications.
RSD-EB-145° Earthquake Bracket at 145° VT-3 No relevant indications.
RSD-EB-215° Earthquake Bracket at 215° VT-3 No relevant indications.
RSD-EB-325° Earthquake Bracket at 325° VT-3 No relevant indications.
RSD-GRS-SP-V1-0o Guide Rod Slot to Skirt Panel Weld at oo VT-1-89 No relevant indications.
RSD-GRS-SP-V1-180o Guide Rod Slot to Skirt Panel Weld at 180° VT-1-89 No relevant indications.
RSD-GRS-SP-V2-0o Guide Rod Slot to Skirt Panel Weld at oo VT-1-89 No relevant indications.
RSD-GRS-SP-V2-180° Guide Rod Slot to Skirt Panel Weld at 180° VT-1-89 No relevant indications.
RSD-Hub-PP Hub to Perforated Plate Weld VT-1-89 No relevant indications.
RSD-Hub-UG6 Hub to Upper Girder Weld VT-1-89 No relevant indications.
RSD-Hub-UG7 Hub to Upper Girder Weld VT-1-89 No relevant indications.
RSD-ID-LG4-ICP-3 Lower Girder to Inner Cover Plate Weld VT-1-89 No relevant indications RSD-ID-LG3-ICP-3 Lower Girder to Inner Cover Plate Weld VT-1-89 No relevant indications RSD-ID-A1-T-VB Trough to Vane Bank Weld VT-1-89 No relevant indications RSD-ID-B1-T-VB Trough to Vane Bank Weld VT-1-89 No relevant indications RSD-ID-C1-T-VB Trough to Vane Bank Weld VT-1-89 No relevant indications RSD-ID-A1-V1a Vertical Outer Plate Weld VT-1-89 Weld is inaccessible for inspection.
RSD-ID-A1-V1b Vertical Outer Plate Weld VT-1-89 Weld is inaccessible for inspection.
RSD-ID-B1-V1a Vertical Outer Plate Weld VT-1-89 No relevant indications RSD-ID-B1-V1b Vertical Outer Plate Weld VT-1-89 No relevant indications RSD-ID-C1-V1a Vertical Outer Plate Weld VT-1-89 No relevant indications RSD-ID-C1-V1 b Vertical Outer Plate Weld VT-1-89 No relevant indications RSD-1 D-A3-LG3-T2 Trough to Lower Girder Weld VT-1-89 No relevant indications Page 3 of 6
L-MT-17-060 Table 1: RFO 28 Monticello Replacement Steam Dryer Inspection Results Weld Name Weld Description Exam Exam Result Type RSD-1 D-A3-LG4-T1 Trough to Lower Girder Weld VT-1-89 No relevant indications RSD-1 D-B3-LG3-T2 Trough to Lower Girder Weld VT-1-89 No relevant indications RSD-1 D-B3-LG4-T1 Trough to Lower Girder Weld VT-1-89 No relevant indications RSD-1 D-C3-LG3-T2 Trough to Lower Girder Weld VT-1-89 No relevant indications RSD-1 D-C3-LG4-T1 Trough to Lower Girder Weld VT-1-89 No relevant indications RSD-ID-B1-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B1-S2 Stiffener Welds VT-1-89 No relevant indications I RSD-ID-B2-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B2-S2 Stiffener Welds VT-1-89 No relevant indications RSD-1 D-B3-S 1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B3-S2 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B4-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B4-S2 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B5-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B5-S2 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B6-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B6-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B7-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B7-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B8-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-B8-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-C1-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-C2-S2 Stiffener Welds VT-1-89 No relevant indications RSD-ID-C3-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-C4-S2 Stiffener Welds VT-1-89 No relevant indications RSD-ID-C5-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-C6-S2 Stiffener Welds VT-1-89 No relevant indications RSD-ID-C7-S1 Stiffener Welds VT-1-89 No relevant indications RSD-ID-C8-S1 Stiffener Welds VT-1-89 No relevant indications RSD-LR-BRKT -35° Lifting Rod Bracket at 35° VT-1-89 No relevant indications RSD-LR-BRKT -145° Lifting Rod Bracket at 145° VT-1-89 No relevant indications RSD-LR-BRKT -215° Lifting Rod Bracket at 215° VT-1-89 No relevant indications RSD-LR-BRKT -325° Lifting Rod Bracket at 325° VT-1-89 No relevant indications RSD-LR-LE-35° Lifting Eye to Rod Weld at 35° VT-1-89 No weld identified in this location.
RSD-LR-LE-145° Lifting Eye to Rod Weld at 145° VT-1-89 No weld identified in this location.
Page 4 of 6
L-MT-17-060 Table 1: RFO 28 Monticello Replacement Steam Dryer Inspection Results Weld Name Weld Description Exam Exam Result Type RSD-LR-LE-215° Lifting Eye to Rod Weld at 215° VT-1-89 No weld identified in this location.
RSD-LR-LE-325° Lifting Eye to Rod Weld at 325° VT-1-89 No weld identified in this location.
RSD-LR-SR-35° Lifting Rod to Support Ring Weld at 35° VT-1-89 No relevant indications RSD-LR-SR-145° Lifting Rod to Support Ring Weld at 145° VT-1-89 No relevant indications RSD-LR-SR-215° Lifting Rod to Support Ring Weld at 215° VT-1-89 No relevant indications RSD-LR-SR-325° Lifting Rod to Support Ring Weld at 325° VT-1-89 No relevant indications RSD-SFW-0° -90° Skirt to Flange Weld from oo -90° VT-1-89 No relevant indications RSD-SFW-90°-180° Skirt to Flange Weld from 90°-180° VT-1-89 No relevant indications RSD-SFW-180° -270° Skirt to Flange Weld from 180°-270° VT-1-89 No relevant indications RSD-SFW-270° -360° Skirt to Flange Weld from 270°-360° VT-1-89 No relevant indications RSD-SR-SP-0° -90° Support Ring to Skirt Panel Weld from 0°-90° VT-1-89 No relevant indications RSD-SR-SP-90°-180° Support Ring to Skirt Panel Weld from 90°-180° VT-1-89 No relevant indications RSD-SR-SP-180° -270° Support Ring to Skirt Panel Weld from 180°-270° VT-1-89 No relevant indications RSD-SR-SP-270° -360° Support Ring to Skirt Panel Weld from 270°-360° VT-1-89 No relevant indications RSD-SRCP-35° -90° Support Ring Cover Plate Weld from 35°-90° VT-1-89 No relevant indications RSD-SRCP-90° -145° Support Ring Cover Plate Weld from 90°-145° VT-1-89 No relevant indications RSD-SRCP-215°-270° Support Ring Cover Plate Weld from 215°-270° VT-1-89 No relevant indications RSD-SRCP-270° -325° Support Ring Cover Plate Weld from 270°-325° VT-1-89 No relevant indications RSD-UG6-0B Upper Girder to Octagonal Beam Weld VT-1-89 No relevant indications RSD-UG7-0B Upper Girder to Octagonal Beam Weld VT-1-89 No relevant indications RSD-ID-DC3-V1 Skirt to Drain Channel Weld - Left Side of Weld VT-1-89 No relevant indications RSD-ID-DC4-V1 Skirt to Drain Channel Weld - Left Side of Weld VT-1-89 No relevant indications RSD-ID-DC7-V1 Skirt to Drain Channel Weld - Left Side of Weld VT-1-89 No relevant indications RSD-ID-DC8-V1 Skirt to Drain Channel Weld - Left Side of Weld VT-1-89 No relevant indications RSD-ID-DC2-V2 Skirt to Drain Channel Weld - Right Side of Weld VT-1-89 No relevant indications RSD-ID-DC3-V2 Skirt to Drain Channel Weld - Right Side of Weld VT-1-89 No relevant indications RSD-ID-DC6-V2 Skirt to Drain Channel Weld - Right Side of Weld VT-1-89 No relevant indications RSD-ID-DC7-V2 Skirt to Drain Channel Weld - Right Side of Weld VT-1-89 No relevant indications RSD-ID-LG3-LR Lower Girder to Lower Ring Weld VT-1-89 No relevant indications RSD-ID-LG4-LR Lower Girder to Lower Ring Weld VT-1-89 No relevant indications RSD-1 D-1 C P-C3 Inner Cover Plate to Trough Weld VT-1-89 No relevant indications RSD-1 D-LR-CCP Lower Ring to Center Cover Plate Weld VT-1-89 No relevant indications RSD-ID-LR-ICP-3 Lower Ring to Inner Cover Plate Weld VT-1-89 No relevant indications RSD-1 D-LG-DC 1 Lower Girder to Drain Channel Weld VT-1-89 No relevant indications RSD-1 D-LG-DC2 Lower Girder to Drain Channel Weld VT-1-89 No relevant indications Page 5 of 6
L-MT-17-060 Table 1: RFO 28 Monticello Replacement Steam Dryer Inspection Results Weld Name Weld Description Exam Exam Result Type RSD-1 D-LG-DC3 Lower Girder to Drain Channel Weld VT-1-89 No relevant indications RSD-1 D-LG-DC4 Lower Girder to Drain Channel Weld VT-1-89 No relevant indications RSD-1 D-LG-DC5 Lower Girder to Drain Channel Weld VT-1-89 No relevant indications RSD-1 D-LG-DC6 Lower Girder to Drain Channel Weld VT-1-89 No relevant indications RSD-1 D-LG-DC7 Lower Girder to Drain Channel Weld VT-1-89 No relevant indications RSD-ID-LG-DC8 Lower Girder to Drain Channel Weld VT-1-89 No relevant indications RSD-A1-H3 Hood Vane Bank Top Plate to Perforated Plate VT-1-89 Weld inaccessible for inspection RSD-B1-H3 Hood Vane Bank Top Plate to Perforated Plate VT-1-89 Weld inaccessible for inspection RSD-C1-H3 Hood Vane Bank Top Plate to Perforated Plate VT-1-89 Weld inaccessible for inspection Page 6 of 6
