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Category:Annual Operating Report
MONTHYEARL-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-21-033, 2020 Annual Radioactive Effluent Release Report2021-05-13013 May 2021
2020 Annual Radioactive Effluent Release Report
L-MT-20-045, 2020 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462020-12-16016 December 2020
2020 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
L-MT-17-086, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462017-12-15015 December 2017
Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-17-037, 2016 Annual Radiological Environmental Operating Report2017-05-10010 May 2017
2016 Annual Radiological Environmental Operating Report
L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462016-12-19019 December 2016
Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-16-027, Annual Report of Changes in Areva Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462016-05-24024 May 2016
Annual Report of Changes in Areva Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-15-091, Submittal of 2015 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462015-12-22022 December 2015
Submittal of 2015 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-14-101, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462014-12-30030 December 2014
Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-13-116, 2013 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models2013-12-27027 December 2013
2013 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models
L-MT-13-042, Submittal of 2012 Annual Radiological Environmental Operating Report2013-05-10010 May 2013
Submittal of 2012 Annual Radiological Environmental Operating Report
L-MT-13-037, 2012 Annual Report of Individual Monitoring2013-04-18018 April 2013
2012 Annual Report of Individual Monitoring
L-MT-12-106, Submission of 10CFR72.48 Report Re Changes to Spent Fuel Storage Cask Design and Any Tests, Experiments or Procedures Changes for 10/04/2011 to 10/30/20122012-11-29029 November 2012
Submission of 10CFR72.48 Report Re Changes to Spent Fuel Storage Cask Design and Any Tests, Experiments or Procedures Changes for 10/04/2011 to 10/30/2012
L-MT-12-042, Submittal of 2011 Annual Radiological Environmental Operating Report2012-05-10010 May 2012
Submittal of 2011 Annual Radiological Environmental Operating Report
ML12114A0132012-04-18018 April 2012
Submittal of 2011 Annual Report of Individual Monitoring
L-MT-11-020, 2010 Annual Radiological Environmental Operating Report2011-05-12012 May 2011
2010 Annual Radiological Environmental Operating Report
L-MT-11-021, Submittal of 2010 Radioactive Effluent Release Report2011-05-12012 May 2011
Submittal of 2010 Radioactive Effluent Release Report
L-MT-10-075, 2010 Report of Changes and Errors in ECCS Evaluation Models for July 2009 Through July 20102010-12-20020 December 2010
2010 Report of Changes and Errors in ECCS Evaluation Models for July 2009 Through July 2010
L-MT-08-081, Report of Changes and Errors in ECCS Evaluation Models2008-12-30030 December 2008
Report of Changes and Errors in ECCS Evaluation Models
L-MT-04-012, Annual Report of Safety Relief Valve Failures and Challenges, January 1 Through December 31, 20032004-02-18018 February 2004
Annual Report of Safety Relief Valve Failures and Challenges, January 1 Through December 31, 2003
L-MT-03-077, 2003 Report of Changes and Errors in ECCS Evaluation Models2003-10-16016 October 2003
2003 Report of Changes and Errors in ECCS Evaluation Models
M200204, Annual Radiological Environmental Operating Report2002-05-15015 May 2002
Annual Radiological Environmental Operating Report
ML0214300222002-05-15015 May 2002
Part a - Monticello Nuclear Generating Plant 2001 Radioactive Effluent Release Report
2023-12-11
[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 11, 2023 L-MT-23-042 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 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
References:
- 1. Correspondence, L-MT-22-046, Shawn C. Hafen to U.S. Nuclear Regulatory Commission, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, December 13, 2022.
- 2. Global Nuclear Fuel (GNF) Correspondence KGO-NMC-EK1-23-080, Kimberly OConnor (GNF) to Sonja Jenko (Xcel Energy), Monticello 10 CFR 50.46 Reporting Period of July 2022 to July 2023, dated September 29, 2023.
- 3. Framatome Report FS1-0068817, Revision 1.0, Monticello 10 CFR 50.46 PCT Reporting Estimates for ATRIUM 10XM and ATRIUM 11 Fuel -
September 2022 to September 2023, dated September 2023.
- 4. ANP-3720P Revision 0, Monticello LOCA MAPLHGR Limits for EPU/EFW with ATRIUM 10XM Fuel and Revised Modeling Parameters, January 2019.
- 5. ANP-3934P Revision 0 Monticello LOCA Analysis for ATRIUM 11 Fuel dated July 2021.
- 6. Framatome Report FS1-0064057, Revision 1.0 Monticello 10 CFR 50.46 PCT Reporting Estimates for ATRIUM 10XM and ATRIUM 11 Fuel -
September 2021 to September 2022 dated September 2022.
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 and Framatome ATRIUM 11 fuel
L-MT-23-042 Page 2 were in the Monticello core. Atrium 11 fuel was first inserted in the Monticello core in April 2023; therefore, this will be the first 50.46 submittal to reference ATRIUM 11 fuel.
This report is for the period from July 2022 to July 2023.
The last annual report was transmitted on December 13, 2022 (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 2022 to July 2023. Correspondence from Global Nuclear Fuel (Reference 2) noted that no notifications were made in this period.
Attached in Enclosure 1 is the PCT rack-up for GE14 fuel for Monticello. This current adjusted PCT of < 2156F remains the same as the one provided in Enclosure 1 of the 2022 Annual Report (Reference 1).
Framatome ATRIUM 10XM Fuel 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 July 2022 to July 2023. Correspondence from Framatome, Inc.
(Reference 3 and 6) noted that no non-zero notifications were made during this period.
ANP-3720P (Reference 4) is the current analysis of record and provides a baseline for Framatome ATRIUM 10XM fuel at Monticello. Attached in Enclosure 2 is the PCT rack-up for ATRIUM 10XM fuel for Monticello. This current adjusted PCT of 2144F remains the same as the one provided in Enclosure 2 of the 2022 Annual Report. (Reference 1)
Framatome ATRIUM 11 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 July 2022 to July 2023. Correspondence from Framatome Inc.
(Reference 3 and 6) noted that no non-zero notifications were made during this period.
ANP-3934P (Reference 5) is the current analysis of record and provides a baseline for Framatome ATRIUM 11 fuel for Monticello. Attached in Enclosure 3 is the PCT rack-up for ATRIUM 11 fuel for Monticello. This current adjusted PCT of 2120F remains unchanged from the Analysis of Record (Reference 5).
Should you have questions regarding this letter, please contact Mr. David Gerads at (763) 295-1046 (w).
L-MT-23-042 Page 3 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
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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
Enclosure 1 Page 1 of 3 TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR GE14 FUEL Licensing Basis Applicable Analysis or Error/Change Description Ref.
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)
This change is due to the application of an NRC-approved G3 +10 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 liquid mass and core spray flow rate are low. System G4 +15 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 G5 +20 non-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 G8 -14 core spray (LPCS) systems.
SAFR Lower Limit on Differential Pressure for Bypass Leakage G9 0
Enclosure 1 Page 2 of 3 TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR GE14 FUEL Licensing Basis Applicable Analysis or Error/Change Description Ref.
PCT(F)
GE14 PRIME Coding Errors for Zircaloy Irradiation Growth and Zr Barrier Thermal Conductivity as input to ECCS LOCA Analysis G10 0 Error in Fuel Pellet to Plenum Spring Conductance G11 0 Discrepancy in Inner Cladding Surface Roughness G12 0 Sum of absolute value of changes for the current reporting period. 0 Sum of absolute value of changes since last AOR (Reference G1). 74 Algebraic sum of changes for the current reporting period 0 Algebraic sum of changes since last AOR (Reference G1). +16 Current Adjusted Peak Cladding Temperature <2156 References G1. GE Report: NEDC-33322P Revision 3, "Safety Analysis Report for Monticello Constant Pressure Power Uprate," dated October 2008 (Enclosure 5 of L-MT-08-052, 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.
Enclosure 1 Page 3 of 3 TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR GE14 FUEL 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.
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 Analysis, 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 Corrections Implemented by the RDX2_2_RDX4 code for the TCD Factor calculation for the EXEM BWR-2000 LOCA Method, Framatome, September 2, 2021.
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 2 Pages Follow
Enclosure 2 Page 1 of 2 TABLE 2 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 10XM FUEL Licensing Applicable Analysis or Error/Change Description Ref. Basis PCT(F)
ANP-3720P Revision 0, Monticello LOCA MAPLHGR Limits for EPU/EFW with ATRIUM 10XM Fuel and Revised Modeling A1 2125 Parameters FS1-0048088 Revision 0, Monticello 10 CFR 50.46 PCT Error Reporting - Heat-up Analysis Input and RODEX4 Routine Issues A2 0 Framatome Condition Repot 2021-1456 Incorrect Parameters Input to Monticello ATRIUM 11 LOCA Database. A3 +19 RDX2_2_RDX4 Corrections A4 0 RODEX4 Pellet Rim Porosity Model* A5 0 Sum of absolute value of changes for the current reporting period. 0 Sum of absolute value of changes since last AOR (Reference A1) 19 Algebraic sum of changes for the current reporting period 0 Algebraic sum of changes since the last AOR (Reference A1) +19 Current Adjusted Peak Cladding Temperature 2144
- The 0o PCT RODEX4 Pellet Rim Porosity Model error occurred outside the reporting period for this letter but is included since the error has been identified and listed in Framatome Report FS1-0068817 Revision 1.0 (Reference 3).
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 -
Heat-up Analysis Input and RODEX4 Routine Issues, Framatome, February 2020.
A3. Framatome Condition Report 2021-1456 Incorrect Parameters Input to Monticello ATRIUM 11 LOCA Database, 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, September 2, 2021.
Enclosure 2 Page 2 of 2 TABLE 2 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 10XM FUEL A5. Framatome Condition Report 2023-1602 Rim Porosity Model in RODEX4 Inconsistent with Theory Manual, July 2023.
Enclosure 3 MONTICELLO NUCLEAR GENERATING PLANT TABLE 3 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 11 FUEL 1 Page Follows
Enclosure 3 Page 1 of 1 TABLE 3 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 11 FUEL Licensing Applicable Analysis or Error/Change Description Ref. Basis PCT(F)
ANP-3934P Revision 0, Monticello LOCA Analysis for ATRIUM 11 Fuel, Framatome Inc., July 2021 A1 2120 S-RELAP5 cladding thermal conductivity A2 0 Cladding hydrogen content A2 0 MB2 ACE input with explicit water rod model A3 0 Cladding Oxide thickness A2 0 RODEX4 Pellet Rim Porosity Model* A4 0 Sum of absolute value of changes for the current reporting period. 0 Sum of absolute value of changes since last AOR (Reference A1) 0 Algebraic sum of changes for the current reporting period 0 Algebraic sum of changes since the last AOR (Reference A1) 0 Current Adjusted Peak Cladding Temperature 2120
- The 0 PCT RODEX4 Pellet Rim Porosity Model error occurred outside the reporting period for o
this letter but is included since the error has been identified and listed in Framatome Report FS1-0068817 Revision 1.0 (Reference 3).
References A1. ANP-3934P Revision 0, Monticello LOCA Analysis for ATRIUM 11 Fuel, Framatome, July 2021 A2. Condition Report 2022-0152, AURORA-B Inputs to RODEX4 - Resinter Density, Initial Oxide Thickness, and Initial Hydrogen Content, Framatome Inc., January 2022 A3. Framatome Condition Report 2022-1650, MICROBURN-B2 Explicit Water Rod Model Flow Inappropriately Included in Inlet Node for ACE Calculations, Framatome Inc., June 2022 A4. Framatome Condition Report 2023-1602 Rim Porosity Model in RODEX4 Inconsistent with the Theory Manual, July 2023
