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Category:Graphics incl Charts and Tables
MONTHYEARL-MT-21-068, 2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462021-12-15015 December 2021
2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-18-071, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462018-12-12012 December 2018
Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML16245A7202016-09-16016 September 2016
MSFHI Tables Final 8-31-2016
ML16056A1392016-03-11011 March 2016
Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
ML14307B7072014-12-10010 December 2014
Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T
L-MT-14-054, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462014-06-17017 June 2014
Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML14141A3992014-05-27027 May 2014
Correction Letter for License Amendment No. 180 Maximum Extended Load Line Limit Plus (Mellla+)
L-MT-13-034, Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End2013-04-10010 April 2013
Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End
ML13105A1882013-04-10010 April 2013
Monticello Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 1 of 96 Through Page 57 of 96
L-MT-08-058, Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel2008-10-16016 October 2008
Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel
ML0728203072007-10-11011 October 2007
Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
ML0612402692006-06-0505 June 2006
Attachment 6 - Table R - Relocated Specifications for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402662006-06-0505 June 2006
Attachment 5 - Table La - Removed Details for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402642006-06-0505 June 2006
Attachment 4 - Table L - Less Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402592006-06-0505 June 2006
Attachment 3 - Table M - More Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402552006-06-0505 June 2006
Attachment 2 - Table a - Administrative Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0613901442005-08-0404 August 2005
Web References for Monticello Dseis: Socioeconomics
ML0520105032005-08-0101 August 2005
Xcel Energy - Migratory Bird Reporting Form and Flow Chart, Revised 2003
ML0520104582005-04-11011 April 2005
NCDC Listing of Nonattainment Status for Each County by Year, as of April 11, 2005
ML0434501802003-12-11011 December 2003
NMC Program Health Status Fleet Program at a Glance
2021-12-15
[Table view]
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] |
Text
fl Xcel Energy 2807 West County Road 75 Monticello, MN 55362 December 15, 2021 L-MT-21-068 10 CFR 50.46(a)(3)(ii)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 References :
- 1. Correspondence, L-MT-20-045, Thomas A. Conboy to U.S. Nuclear Regulatory Commission, "2020 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46,"
December 16, 2020.
- 2. GNF Correspondence JMT-NMC-EK1-21 -007, Jeanne Thome (GNF) to David Mienke (Xcel Energy), "Monticello 10 CFR 50.46 Reporting Period of July 2020 to July 2021," dated October 26, 2021 .
- 3. GNF Notification Letter 2021-01 "Error in Fuel Pellet to Plenum Spring Conductance", GNF, February 18, 2021.
- 4. GNF Notification Letter 2021-02 "Discrepancy in Inner Cladding Surface Roughness" GNF, February 18, 2021 .
- 5. Framatome Report FS1 -0057936, Revision 1.0, "Monticello 10 CFR 50.46 PCT Reporting Estimates for ATRIUM 10XM Fuel Between September 2020. and September 2021, " dated September 2021 .
- 6. Framatome Condition Report 2021-1456, "Incorrect Parameters Input to Monticello ATRIUM 11 LOCA Database, " Framatome, June 16, 2021.
- 7. Framatome Condition Report 2021-2025, "Corrections Implemented by the RDX2 2 RDX4 code for the TCD Factor calculation for the EXEM BWR-2000 LOCA Method," Framatome, September 2, 2021.
- 8. ANP-3720P Revision 0, "Monticello LOCA MAPLHGR Limits for EPU/EFWwith ATRIUM 10XM Fuel and Revised Modeling Parameters,"
January 2019.
L-MT-21-068 Page 2 Pursuant to 10 CFR 50.46(a)(3)(ii), the Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, is providing this annual report concerning changes or errors identified in the Emergency Core Cooling System (ECCS) evaluation models for the Monticello Nuclear Generating Plant (MNGP).
GNF GE14 fuel and Framatome ATRIUM 10XM fuel are currently in the Monticello core.
This report is for the period between July 2020 and July 2021.
The last annual report was transmitted on December 16, 2020 (Reference 1).
Global Nuclear Fuel GE14 Fuel The Nuclear Analysis Department requested from the fuel vendor, Global Nuclear Fuel, any applicable 10 CFR 50.46 notification of errors or changes that have occurred during the reporting period from July 2020 to July 2021. Correspondence from Global Nuclear Fuel (Reference 2) noted that two new notifications (References 3 and 4) were made during this period.
Neither notification letter resulted in more than a 0F change in PCT. Attached in is the peak cladding temperature (PCT) rack-up for GE 14 fuel for Monticello.
The current adjusted PCT of <2156F remains the same as the one provided in Enclosure 1 of the 2020 Annual Report (Reference 1).
Framatome ATRIUM 10XM Fuel Attached in Enclosure 2 is the peak cladding temperature (PCT) for Framatome ATRIUM 10XM fuel for Monticello.
The Nuclear Analysis Department requested from the fuel vendor, Framatome Inc., any applicable 10 CFR 50.46 notifications of errors or changes that have occurred during the reporting period from September 2020 to September 2021. Correspondence from Framatome Inc. (References 5, 6, and 7) identify the PCT changes during the September 2020 to September 2021 annual reporting period.
ANP-3720P (Reference 8) is the current analysis of record and provides a baseline for Framatome ATRIUM 10XM fuel at Monticello. During the September 2020 - September 2021 period, two errors were found with the Reference 8 Analysis of Record. Incorrect parameters were entered into the ATRIUM 11 LOCA database resulting in a 19F PCT penalty (This error which was uncovered during ATRIUM 11 analysis also pertains to ATRIUM 10XM fuel). Details of this error can be found in reference 6. The second error was uncovered in September 2021. The error dealt with corrections implemented by the RDX-2_RDX4 code for the TCD factor calculation for the EXEM BWR-2000 LOCA Method.
This error resulted in a 0F PCT change, details which can be found in Reference 7.
L-MT-21-068 Page 3 The current total assessed changes and errors to the analysis of record (ANP-3720P) is 19°F, so the total PCT is 2144°F.
Should you have questions regarding this letter, please contact Mr. David Gerads at (763) 295-1046 (w) or (612) 669-4741 (c).
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
~GC Thomas A. C o n b o y ~ ~ - - -
Site Vice President, Montice11Wu~1ear Generating Plant Northern States Power Company - Minnesota Enclosure (2) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC
ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR GE14 FUEL 3 Pages Follow
TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR GE14 FUEL Licensing Applicable Analysis or Error/Change Description Ref. Basis PCT(°F)
GE14 NEDC-33322P, Revision 3, Safety Analysis Report for Monticello G1 & <2140 Constant Pressure Power Uprate G2 PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties (10 CFR 50.46 Notification Letter 2012-01, Revision 1)
G3 +10 This change is due to the application of an NRC-approved procedure to estimate the change in Peak Clad Temperature (PCT) due to the change in fuel properties from GESTR to PRIME primarily to address inaccuracies in fuel pellet thermal conductivity as a function of exposure.
SAFER04A E4-Mass Non-Conservatism (10 CFR 50.46 Notification Letter 2014-02)
This change is due to a logic error that occurs when upper plenum G4 +15 liquid mass and core spray flow rate are low. System mass is gradually lost due to core spray being discarded, resulting in marginally less ECCS flow credited as reaching the core.
SAFER04A E4-Minimum Core DP Model (10 CFR 50.46 Notification Letter 2014-03)
This change is due to the use of a minimum p that could be non- G5 +20 conservative offering inappropriate steam cooling benefit above the core two- phase level.
SAFER04A E4-Bundle/Lower Plenum CCFL Head (10 CFR 50.46 Notification Letter 2014-04)
This change is due to the counter current flow limitation (CCFL) G6 -15 calculation representing the pressure head slightly different from that of the calculated water level in the bundle.
Modified performance characteristics of the RHR (LPCI) and core G8 -14 spray (LPCS) systems.
SAFER Lower Limit on Differential Pressure for Bypass Leakage G9 0 PRIME Coding Errors for Zircaloy Irradiation Growth and Zr Barrier G10 0 Thermal Conductivity as input to ECCS LOCA Analyses Error in Fuel Pellet to Plenum Spring Conductance G11 0 Page 1 of 3
CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR GE14 FUEL TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING Licensin Applicable Analysis or Error/Change Description Ref. g Basis PCT(°F)
GE14 Discrepancy in Inner Cladding Surface Roughness G12 0 Sum of absolute value of changes since the last 10 CFR 50.46 report (Reference 0 2)
Sum of absolute value of changes since last AOR (Reference G1). 74 Algebraic sum of changes since the last 10 CFR 50.46 report (Reference 2) 0 Algebraic sum of changes since last AOR (Reference G1). +16 Current Adjusted Peak Cladding Temperature <2156 References G1. GE Report: NEDC-33322P1 Revision 3, "Safety Analysis Report for Monticello Constant Pressure Power Uprate," dated October 2008 (Enclosure 5 of L-MT 052, dated November 5, 2008, ADAMS Accession No. ML083230111)
G2. NSPM letter to NRC, "Monticello Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests:
Supplement for Analytical Methods Used to Address Thermal Conductivity Degradation and Analytical Methods Limitations (TAC Nos. MD9990 and ME3145)," L-MT-13-053 dated July 8, 2013 (ADAMS Accession No. ML13191A568).
G3. GEH 10 CFR 50.46 Notification Letter 2012-01, Revision 1, "PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties," dated July 30, 2013.
G4.GEH 10 CFR 50.46 Notification Letter 2014-02, SAFER04A E4-Mass Non- Conservatism, dated May 21, 2014.
G5.GEH 10 CFR 50.46 Notification Letter 2014-03, SAFER04A E4-Minimum Core DP Model, dated May 21, 2014.
G6. GEH 10 CFR 50.46 Notification Letter 2014-04, SAFER04A E4-Bundle/Lower Plenum CCFL Head, dated May 21, 2014.
G7. L-MT-14-101, letter from K. Fili (NSPM) to NRC 2014 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, December 30, 2014.
G8. GE Report 0000-0163-2998 R0 "Monticello ECCS LOCA Evaluation for Modified Low Pressure ECCS Injection Performance Curves (LPCS and LPCI)" dated July 25, 2013 G9. GEH 10 CFR 50.46 Notification Letter 2019-05, SAFER Lower Limit on Differential Pressure for Bypass Leakage, dated October 23, 2019.
Page 2 of 3
G10. GEH 10 CFR 50.46 Notification Letter 2020-01, PRIME Coding Errors for Zircaloy Irradiation Growth and Zr Barrier Thermal Conductivity as input to ECCS LOCA Analyses, dated April 14, 2020.
G11. GNF Notification Letter 2021-01 Error in Fuel Pellet to Plenum Spring Conductance, dated February 18, 2021 G12. GNF Notification Letter 2021-02 Discrepancy in Inner Cladding Surface Roughness, February 18, 2021 Page 3 of 3
ENCLOSURE 2 MONTICELLO NUCLEAR GENERATING PLANT TABLE 2 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 10XM FUEL 1 Page Follows
TABLE 2 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 10XM FUEL Licensing Basis Applicable Analysis or Error/Change Description Ref.
PCT(°F) 10XM ANP-3720P Revision 0, Monticello LOCA MAPLHGR Limits for EPU/EFW with ATRIUM 10XM Fuel and Revised Modeling Parameters(1) A1 2125 FS1-0048088 Revision 0, Monticello 10 CFR 50.46 PCT Error Reporting -
Heat-up Analysis Input and RODEX4 Routine Issues A2 0 Framatome Condition Report 2021-1456 Incorrect Parameters Input to Monticello ATRIUM 11 LOCA Database. A3 +19 RDX2_2_RDX4 Corrections A4 0 Sum of absolute value of changes since the last 10CFR 50.46 report (Reference 2). 19 Sum of absolute value of changes since the last AOR (Reference A1) 19 Algebraic sum of changes since the last 10 CFR 50.46 report
+19 (Reference 1).
Algebraic sum of changes since last AOR (Reference A1). +19 Current Adjusted Peak Cladding Temperature 2144 (1) Framatome report ANP-3720P reflects a new LOCA analysis performed to provide a new baseline for Framatome ATRIUM 10XM fuel at MNGP as provided in Reference A1.
References A1. ANP-3720P Revision 0, Monticello LOCA MAPLHGR Limits for EPU/EFW with ATRIUM 10XM Fuel and Revised Modeling Parameters, Framatome, January 2019 A2. FS1-0048088 Revision 0, Monticello 10 CFR 50.46 PCT Error Reporting - Heatup Analysis Input and RODEX4 Routine Issues, Framatome, February 2020 A3. Framatome Condition Report 2021-1456, Incorrect Parameters Input to Monticello ATRIUM 11 LOCA Database, Framatome, June 16, 2021 A4. Framatome Condition Report 2021-2025, Corrections Implemented by the RDX2_2_RDX4 code for the TCD Factor calculation for the EXEM BWR-2000 LOCA Method, Framatome, September 2, 2021
