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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
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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
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(l Xcel Energy.. Monticello Nuclear Generating Plant 2807 W County Rd 75 Monticello, MN 55362 May 24, 2016 L-MT-16-027 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 Annual Report of Changes in AREVA Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
References:
- 1) NRC (Terry A. Beltz) letter to NSPM (Peter A. Gardner), "Monticello Nuclear Generating Plant- Issuance of Amendment to Transition to AREVA ATRIUM 10XM Fuel and AREVA Safety Analysis Methods (TAG No. MF2479)," dated June 5, 2015 (ADAMS Accession No. ML15072A141)
- 2) NSPM (Karen D. Fili) letter to NRC Document Control Desk, "License Amendment Request for AREVA Extended Flow Window," dated October 3, 2014 (ADAMS Accession No. ML14283A119)
- 3) NSPM (Peter A. Gardner) letter to NRC Document Control Desk, "2015 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46", dated December 22, 2015 (ADAMS Accession No. ML15356A275)
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 report concerning changes or errors identified in the AREVA Emergency Core Cooling System (ECCS) evaluation models for the Monticello Nuclear Generating Plant (MNGP). This report is for the period between June 2015 and March 2016.
Please note that this report is associated only with the AREVA ECCS evaluation models of the AREVA ATRIUM 1OXM fuel type that will not be loaded into an MNGP core until the startup for Cycle 29 in 2017. This report does not relate in any way to the annual report provided by Reference 3. Until all GE14 fuel is permanently discharged from the MNGP core, such reports will continue to be provided for the associated General Electric - Hitachi (GEH) evaluation models, pursuant to 10 CFR 50.46. When both GE14 and ATRIUM 10XM fuel are in the core, NSPM intends to provide an annual report to include both the GEH and AREVA changes.
Document Control Desk Page 2 The MNGP Loss of Coolant Accident (LOCA) licensing analyses-of-record (AOR) for the pending AREVA fuel transition are contained in the AREVA reports submitted for the Fuel Transition license amendment (Amendment 188, issued with Reference 1) and the pending Extended Flow Window (EFW) license amendment (submitted as Reference 2). One AREVA fuel type has been used in these analyses- the ATRIUM 10XM. As noted above, ECCS modeling of the co-resident GE fuel will be analyzed by GEH and reported in a GEH report.
During this reporting period, AREVA made one notification of a change/error resulting in a 5 oF change to the calculated Peak Cladding Temperature (PCT). The total of all changes since the AOR is less than 50 °F, so no 30-day report was required.
The current adjusted licensing basis PCT for the fuel type in the MNGP licensing analyses during the period covered by this report is:
Licensing Basis Fuel Type PCT (°F)
AREVAATRIUM 10XM < 2083 The enclosure provides 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.
Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC
L-MT-16-027 Enclosure -Table 1, Summary of Monticello LOCA Changes and Errors Involving Changes in Peak Cladding Temperature (PCT)
Licensing Basis Ref. PCT (°F)
Applicable Analysis or Error/Change Description ATRIUM 10XM Initial calculated PCT 1 < 2088 Implementation of ACE in RELAX. The approved interpolation scheme required by Licensing Topical Report (LTR) EMF-2 0 2361 (Section 3.2.2) was not employed when the ACE Critical Heat Flux (CHF) correlations were implemented in RELAX.
Error in Modified Analysis Approach. Extraneous messages written in RELAX minor edits can impact the modified analysis 2 0 approach.
Error in Modified Analysis Approach. An error in a logic script associated with the modified analysis approach causes the 2 0 analysis to be overly conservative.
Error in Modified Analysis Approach. An error in a logic script that improperly implemented a limitation in the modified 2 0 analysis approach could cause incorrect reporting in the calculation documentation.
Low Pressure Coolant Injection (LPCI) Loop Selection Logic.
Relates to an input error when modeling breaks smaller than 0.4 fe. MNGP has instrumentation and logic to detect which recirculation line contains a break. When a break is detected, the logic injects all Low Pressure Coolant Injection (LPCI) flow into the recirculation line that does not contain the break and closes the discharge isolation valve in that same recirculation line. If a break is not detected, the LPCI flow is injected and 2 0 the discharge isolation valve is closed in a predefined recirculation line. LOCA analyses for breaks smaller than 0.4 ft 2 conservatively assumed the break was in the recirculation line that was predefined to receive the LPCI flow and should have closed the discharge isolation valve in the same recirculation line. Instead, the discharge isolation valve was modeled as closing in the intact recirculation line.
End of Slowdown Assumption. A modeling assumption was made that could result in an error in the time when rated Low Pressure Core Spray (LPCS) is reached. The time when rated LPCS flow is reached is used in two parts of the LOCA calculation and it relates to the use of the modified analysis 2 -5 approach. This error did cause a small change in the time when the heat transfer coefficients in the heatup calculation change from the calculated values to the values specified in 10 CFR 50 Appendix K.
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L-MT-16-027 Enclosure- Table 1, Summary of Monticello LOCA Changes and Errors Involving Changes in Peak Cladding Temperature (PCT)
Modeling Assumption for Time of Bypass Reflood. A modeling assumption could result in an error in the time of bypass reflood. The time of bypass reflood is the time the 2 0 heat transfer coefficient beneath the bypass mixture level is set to 25 Btu/hr-ft2 -°F.
Using End-of-Slowdown (EOB) Time for Selecting HUXY Boundary Conditions. At the EOB (which is the time of rated core spray), the hottest axial slab in the RELAX hot channel calculation is identified. This establishes the boundary conditions that are passed into the HUXY calculation. While 2 0 this is appropriate under some conditions when the slabs continue to heat up after EOB, it may not be appropriate for other conditions when the EOB time is much later and the nodes have cooled down.
Sum of absolute value of changes for the current reporting period, which N/A includes all changes since the previous 10 CFR 50.46 annual report.
Sum of absolute value of changes since the last Analysis of Record (AOR) 5 in Reference 1.
Arithmetic sum of changes for the current reporting period, which includes N/A all changes since the previous 10 CFR 50.46 annual report.
Arithmetic sum of changes since the last AOR in Reference 1. -5 Calculated Adjusted PCT < 2083
References:
- 1. ANP-3212(P) Revision 0, Monticello EPU LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM' 10XM Fuel, AREVA NP, May 2013 (Enclosure 20 to Xcel Energy Letter to NRC, L-MT-13-055, dated July 15, 2013, ADAMS Accession No. ML13200A185)
- 2. AREVA Report FS1-0026440 Revision 1, Monticello 10 CFR 50.46 PCT Reporting Estimates for ATRIUM 10XM Fuel, approved May 13, 2016 Page 2 of2