Letter Sequence Request |
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MONTHYEARL-MT-14-022, the Comprehensive Methodology for Challenging BWR Fuel Assembly and Core Design Used at Framatome Anp2002-10-10010 October 2002
the Comprehensive Methodology for Challenging BWR Fuel Assembly and Core Design Used at Framatome Anp
Project stage: Other
ML13247A4522013-09-0404 September 2013
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance Review License Amendment Request to Transition to Areva Atrium 10XM Fuel & Areva Safety Analysis Methodology
Project stage: Acceptance Review
ML13353A3662013-12-18018 December 2013
NRR E-mail Capture - Monticello Nuclear Generating Plant - Request for Additional Information NRC Staff Review of Areva Fuel Transition License Amendment Request
Project stage: Approval
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
Project stage: Response to RAI
ML14035A2982014-01-31031 January 2014
Areva Atrium 10XM Fuel Transition - Response to Request for Additional Information
Project stage: Response to RAI
ML14077A3022014-03-12012 March 2014
Areva Atrium 10XM Fuel Transition - Response to Request for Additional Information
Project stage: Request
ML14090A0052014-03-27027 March 2014
NRR E-mail Capture - Monticello Nuclear Generating Plant - NRC Staff Request for Additional Information (Follow-up Question) Areva Fuel Transition License Amendment Request
Project stage: RAI
L-MT-14-033, Areva Atrium 10XM Fuel Transition - Supplement to Describe the Effect of Local Power Range Monitor Surveillance Grace Period2014-04-29029 April 2014
Areva Atrium 10XM Fuel Transition - Supplement to Describe the Effect of Local Power Range Monitor Surveillance Grace Period
Project stage: Supplement
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.
Project stage: Other
ML14132A1942014-05-0909 May 2014
Areva Atrium 10XM Fuel Transition - Response to Request for Additional Information
Project stage: Response to RAI
L-MT-14-042, Areva Atrium 10XM Fuel Transition - Errata Re License Amendment Request2014-05-0909 May 2014
Areva Atrium 10XM Fuel Transition - Errata Re License Amendment Request
Project stage: Request
ML14155A1672014-07-0808 July 2014
Request for Withholding Information from Public Disclosure Associated with Affidavit Executed on January 23, 2014, by Mr. Alan B. Meginnis of Areva Np, Inc.
Project stage: Withholding Request Acceptance
ML14155A1692014-07-0808 July 2014
Request for Withholding Information from Public Disclosure Associated with Affidavit Executed on April 22, 2014, by Mr. Alan B. Meginnis of Areva Inc.
Project stage: Withholding Request Acceptance
ML14155A1772014-07-0808 July 2014
Request for Withholding Information from Public Disclosure Associated with Affidavit Executed on April 28, 2014, by Mr. Philip A. Opsal of Areva Inc.
Project stage: Withholding Request Acceptance
ML15154A4772015-06-0505 June 2015
Safety Evaluation Regarding License Amendment No. 188 Associated with Areva Atrium 10XM Fuel Transition (TAC No. MF2479) - (Redacted)
Project stage: Approval
ML15072A1412015-06-0505 June 2015
Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods
Project stage: Approval
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
Project stage: Request
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
Project stage: Other
2014-03-27
[Table View] |
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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
Xcel Energy@ Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 December 22, 2015 L-MT-15-091 10 CFR 50.46(a)(3)(ii)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket: 50-263 Renewed License No.: DPR-22 2015 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
Reference:
- 1) NRC to NSPM, "Monticello Nuclear Generating Plant-Issuance of Amendment No. 176 to Renewed Facility Operating License Regarding Extended Power Uprate (TAC No. MD9990)," dated December 9, 2013.
- 2) NRC to NSPM, "Monticello Nuclear Generating Plant-Issuance of Amendment No. 180 to Renewed Facility Operating License Regarding Maximum Extended Load Line Limit Analysis Plus (TAC No. ME3145),"
dated March 28, 2014.
- 3) NSPM to NRC, "2014 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46", (L-MT-14-101) dated December 30,2014.
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). This report is for the period between July 2014 and July 2015.
The MNGP Loss of Coolant Accident (LOCA) analyses of record (AOR) are contained in the General Electric Hitachi (GEH) reports submitted for the MNGP Extended Power Uprate and the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) license amendments (Reference 1 and 2). One GE fuel type has been used over this time period, the GE14 fuel type. The current operation cycle (Monticello Cycle 28) core loading consists solely of the GE14 fuel design type.
During this period covered, no notification of any changes or errors resulting in a change to the calculated Peak Clad Temperature (PCT) were received from GE.
Therefore, the licensing basis PCTs and the PCT Summary provided in Table 1 of are unchanged from the last annual report (Reference 3).
L-MT-15-091 Page 2 of 2 The current adjusted licensing basis PCT for the fuel type used at the MNGP during the period covered by this report is:
Licensing Basis Fuel Type PCT (°F)
GE14 <2170 provided an updated summary table of the applicable changes and errors in the LOCA analyses from when the last analyses of record were performed.
Summary of Commitments This letter makes no new commitments or changes any existing commitments.
If you have any questions please contact Mr. Stephen Sollom, at 763-295-1611.
~~
Peter A. Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure Regional Administrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector,~ Monticello Nuclear Generating Plant, US NRC
ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT TABLE 1-
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT)
Page 1 of 3 TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT)
Licensing Basis Applicable Analysis or Error/Change Description Ref.
PCT(°F)
GE14 NEDC-33322P, Revision 3, Safety Analysis Report for Monticello 1 &2 <2140 Constant Pressure Power Uprate PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties (1 0 CFR 50.46 Notification Letter 2012-01, Revision 1)
This change is due to the application of an NRC-approved 3 +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-Maintenance Update Changes (1 0 CFR 50.46 Notification Letter 2014-01)
This change is for a new version (E4) of SAFER04A that 4 +0 resolves several accumulated observations that are code maintenance items. Sensitivity calculations show these items have an insignificant effect on calculated PCT.
SAFER04A E4-Mass Non-Conservatism (1 0 CFR 50.46 Notification Letter 20 14-02)
This change is due to a logic error that occurs when upper plenum liquid mass and core spray flow rate are low. System 5 +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 (1 0 CFR 50.46 Notification Letter 2014-03)
This change is due to the use of a minimum ~p that could be 6 +20 non-conservative offering inappropriate steam cooling benefit above the core two-phase level.
Page 2 of 3 TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT)
Licensing Basis Applicable Analysis or Error/Change Description Ref.
PCT(°F)
GE14 SAFER04A E4-Bundle/Lower Plenum CCFL Head (1 0 CFR 50.46 Notification Letter 2014-04)
This change is due to the counter current flow limitation (CCFL) 7 -15 calculation representing the pressure head slightly different from that of the calculated water level in the bundle.
Sum of absolute value of changes for the current reporting period, which includes all changes since the 10 CFR 50.46 report in Reference 8. 0 Sum of absolute value of changes since last AOR (Reference 1). 60 Algebraic sum of changes for the current reporting period, which includes all changes since the 10 CFR 50.46 report in Reference 8 . +0 Algebraic sum of changes since last AOR (Reference 1). +30 Current Adjusted Peak Cladding Temperature <2170 References
- 1. GE Report: NEDC-33322Pt 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)
- 2. 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).
- 3. 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.
- 4. GEH 10 CFR 50.46 Notification Letter 2014-01, "SAFER04A E4-Maintenance Update Changes," dated May 21, 2014.
- 5. GEH 10 CFR 50.46 Notification Letter 2014-02, "SAFER04A E4-Mass Non-Conservatism," dated May 21, 2014.
- 6. GEH 10 CFR 50.46 Notification Letter 2014-03, "SAFER04A E4-Minimum Core DP Model," dated May 21, 2014.
Page 3 of 3 TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT)
- 7. GEH 10 CFR 50.46 Notification Letter 2014-04, "SAFER04A E4-Bundle/Lower Plenum CCFL Head,"/ dated May 21, 2014.
- 8. L-MT-14-101, letter from K. FiJi (NSPM) to NRC "2014 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46," December 30, 2014.
Xcel Energy@ Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 December 22, 2015 L-MT-15-091 10 CFR 50.46(a)(3)(ii)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket: 50-263 Renewed License No.: DPR-22 2015 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
Reference:
- 1) NRC to NSPM, "Monticello Nuclear Generating Plant-Issuance of Amendment No. 176 to Renewed Facility Operating License Regarding Extended Power Uprate (TAC No. MD9990)," dated December 9, 2013.
- 2) NRC to NSPM, "Monticello Nuclear Generating Plant-Issuance of Amendment No. 180 to Renewed Facility Operating License Regarding Maximum Extended Load Line Limit Analysis Plus (TAC No. ME3145),"
dated March 28, 2014.
- 3) NSPM to NRC, "2014 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46", (L-MT-14-101) dated December 30,2014.
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). This report is for the period between July 2014 and July 2015.
The MNGP Loss of Coolant Accident (LOCA) analyses of record (AOR) are contained in the General Electric Hitachi (GEH) reports submitted for the MNGP Extended Power Uprate and the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) license amendments (Reference 1 and 2). One GE fuel type has been used over this time period, the GE14 fuel type. The current operation cycle (Monticello Cycle 28) core loading consists solely of the GE14 fuel design type.
During this period covered, no notification of any changes or errors resulting in a change to the calculated Peak Clad Temperature (PCT) were received from GE.
Therefore, the licensing basis PCTs and the PCT Summary provided in Table 1 of are unchanged from the last annual report (Reference 3).
L-MT-15-091 Page 2 of 2 The current adjusted licensing basis PCT for the fuel type used at the MNGP during the period covered by this report is:
Licensing Basis Fuel Type PCT (°F)
GE14 <2170 provided an updated summary table of the applicable changes and errors in the LOCA analyses from when the last analyses of record were performed.
Summary of Commitments This letter makes no new commitments or changes any existing commitments.
If you have any questions please contact Mr. Stephen Sollom, at 763-295-1611.
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Peter A. Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure Regional Administrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector,~ Monticello Nuclear Generating Plant, US NRC
ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT TABLE 1-
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT)
Page 1 of 3 TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT)
Licensing Basis Applicable Analysis or Error/Change Description Ref.
PCT(°F)
GE14 NEDC-33322P, Revision 3, Safety Analysis Report for Monticello 1 &2 <2140 Constant Pressure Power Uprate PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties (1 0 CFR 50.46 Notification Letter 2012-01, Revision 1)
This change is due to the application of an NRC-approved 3 +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-Maintenance Update Changes (1 0 CFR 50.46 Notification Letter 2014-01)
This change is for a new version (E4) of SAFER04A that 4 +0 resolves several accumulated observations that are code maintenance items. Sensitivity calculations show these items have an insignificant effect on calculated PCT.
SAFER04A E4-Mass Non-Conservatism (1 0 CFR 50.46 Notification Letter 20 14-02)
This change is due to a logic error that occurs when upper plenum liquid mass and core spray flow rate are low. System 5 +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 (1 0 CFR 50.46 Notification Letter 2014-03)
This change is due to the use of a minimum ~p that could be 6 +20 non-conservative offering inappropriate steam cooling benefit above the core two-phase level.
Page 2 of 3 TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT)
Licensing Basis Applicable Analysis or Error/Change Description Ref.
PCT(°F)
GE14 SAFER04A E4-Bundle/Lower Plenum CCFL Head (1 0 CFR 50.46 Notification Letter 2014-04)
This change is due to the counter current flow limitation (CCFL) 7 -15 calculation representing the pressure head slightly different from that of the calculated water level in the bundle.
Sum of absolute value of changes for the current reporting period, which includes all changes since the 10 CFR 50.46 report in Reference 8. 0 Sum of absolute value of changes since last AOR (Reference 1). 60 Algebraic sum of changes for the current reporting period, which includes all changes since the 10 CFR 50.46 report in Reference 8 . +0 Algebraic sum of changes since last AOR (Reference 1). +30 Current Adjusted Peak Cladding Temperature <2170 References
- 1. GE Report: NEDC-33322Pt 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)
- 2. 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).
- 3. 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.
- 4. GEH 10 CFR 50.46 Notification Letter 2014-01, "SAFER04A E4-Maintenance Update Changes," dated May 21, 2014.
- 5. GEH 10 CFR 50.46 Notification Letter 2014-02, "SAFER04A E4-Mass Non-Conservatism," dated May 21, 2014.
- 6. GEH 10 CFR 50.46 Notification Letter 2014-03, "SAFER04A E4-Minimum Core DP Model," dated May 21, 2014.
Page 3 of 3 TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT)
- 7. GEH 10 CFR 50.46 Notification Letter 2014-04, "SAFER04A E4-Bundle/Lower Plenum CCFL Head,"/ dated May 21, 2014.
- 8. L-MT-14-101, letter from K. FiJi (NSPM) to NRC "2014 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46," December 30, 2014.
