L-MT-17-086, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46: Difference between revisions
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| issue date = 12/15/2017 | | issue date = 12/15/2017 | ||
| title = Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 | | title = Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 | ||
| author name = Church C | | author name = Church C | ||
| author affiliation = Northern States Power Company, Minnesota, Xcel Energy | | author affiliation = Northern States Power Company, Minnesota, Xcel Energy | ||
| addressee name = | | addressee name = | ||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Xcel Energy December 15, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant* Docket No. 50-263 Renewed Facility Operating License No. DPR-22 | {{#Wiki_filter:Xcel Energy Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 December 15, 2017 L-MT-17-086 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 No. 50-263 Renewed Facility Operating License No. DPR-22 2017 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 | |||
==References:== | ==References:== | ||
: 1) Letter from P. Gardner (NSPM) to NRC, "2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46," (L-MT-16-071), dated December 19, 2016 2) Letter from P. Gardner (NSPM) to NRC, "June 2017, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46," (L-MT-17-045), dat-ed June 22, 2017 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). Provided within Enclosure 1 is a report concerning any changes or errors identified in the AREVA ECCS evaluation models for MNGP. This report is for the period between July 2016 and July 2017 for the ATRIUM 10XM fuel. During this period there was a notification of changes or errors resulting in a change to the calculated Peak Clad Temperature (PCT) of 51 oF and therefore reported in a 30-day report (Reference 2). There have been no additional changes since that report. The previously report PCT of 2085oF for the ATRIUM | : 1) Letter from P. Gardner (NSPM) to NRC, "2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46," (L-MT-16-071), dated December 19, 2016 | ||
Provided within Enclosure 2 is a report concerning any changes or errors identified in the General Electric-Hitachi (GEH) ECCS evaluation models for MNGP. This report is for the period between July 2016 and July 2017 for the General Electric (GE) GE14 fuel. During this period no notification of any changes or errors resulting in a change to the calculated PCT were received from GEH. Therefore the PCT of less than 2170°F for the GE14 fuel and the PCT summary provided in the 2016 annual report (Reference | : 2) Letter from P. Gardner (NSPM) to NRC, "June 2017, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46," (L-MT-17-045), dat-ed June 22, 2017 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). | ||
Provided within Enclosure 1 is a report concerning any changes or errors identified in the AREVA ECCS evaluation models for MNGP. This report is for the period between July 2016 and July 2017 for the ATRIUM 10XM fuel. During this period there was a notification of changes or errors resulting in a change to the calculated Peak Clad Temperature (PCT) of 51 oF and therefore reported in a 30-day report (Reference 2). | |||
Document Control Desk L-MT-17-086 Page 2 of 2 Until all the GE14 fuel is permanently discharged from the MNGP core, the annual ECCS reports will continue to be provided for the associated GEH evaluation models (GE14 fuel) and AREVA evaluation models (ATRIUM 10XM fuel). Should you have questions regarding this letter, please contact Mr. Stephen Sollom at (763) 295-1611. | There have been no additional changes since that report. The previously report PCT of 2085oF for the ATRIUM 1OXM fuel since the 30-day report is unchanged. | ||
Summary of Commitments This letter proposes no new commitments and does not revise any existing commitments. C. CLtufM4., Christoph r urch Site Vice si ent, Monticello Nuclear Generating Plant Northern States Power Company-Minnesota Enclosures (2) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT | Provided within Enclosure 2 is a report concerning any changes or errors identified in the General Electric-Hitachi (GEH) ECCS evaluation models for MNGP. This report is for the period between July 2016 and July 2017 for the General Electric (GE) GE14 fuel. | ||
During this period no notification of any changes or errors resulting in a change to the calculated PCT were received from GEH. Therefore the PCT of less than 2170°F for the GE14 fuel and the PCT summary provided in the 2016 annual report (Reference 1) is unchanged. | |||
Document Control Desk L-MT-17-086 Page 2 of 2 Until all the GE14 fuel is permanently discharged from the MNGP core, the annual ECCS reports will continue to be provided for the associated GEH evaluation models (GE14 fuel) and AREVA evaluation models (ATRIUM 10XM fuel). | |||
Should you have questions regarding this letter, please contact Mr. Stephen Sollom at (763) 295-1611. | |||
Summary of Commitments This letter proposes no new commitments and does not revise any existing commitments. | |||
~{Zntf- | |||
-~r C. CLtufM4., | |||
Christoph r urch Site Vice si ent, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosures (2) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC | |||
ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT | |||
==SUMMARY== | ==SUMMARY== | ||
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 1 OXM FUEL (2 page follows) | OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 1 OXM FUEL (2 page follows) | ||
L-MT-17-086 Enclosure 1 Page 1 of 2 TABLE- | L-MT-17-086 Enclosure 1 Page 1 of 2 TABLE- | ||
==SUMMARY== | ==SUMMARY== | ||
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 10XM FUEL Licensing Basis Applicable Analysis or Error I Change Description Ref. PCT(°F) | |||
ATRIUM 10XM ANP-3558P Revision 0, "Monticello LOCA MAPLHGR Limits for EPU/EFWwith ATRIUM 10XM Fuel and Revised ECCS A1 2034 Parameters" (1) | |||
MSIV Closure The impact of this MSIV closure change was estimated for the A2 +51 Monticello LOCA break spectrum and exposure-dependent MAPLHGR analyses. | |||
Sum of absolute value of changes for the current reporting period, which 51 includes all changes since the 10 CFR 50.46 report Reference A 1.(2) | |||
Sum of absolute value of changes since last analysis of record (AOR) 51 (Reference A 1). | |||
Algebraic sum of changes for the current reporting period, which includes all | |||
+51 changes since the 10 CFR 50.46 report in Reference A1.( 2) | |||
Algebraic sum of changes since last AOR (Reference A 1). +51 Current Adjusted Peak Cladding Temperature 2085 1 | |||
( ) AREVA report ANP-3558P reflects a new LOCA analysis performed to provide a new baseline for the AREVA ATRIUM 10XM fuel at the MNGP as provided to the NRC in Reference A3. | |||
2 | |||
( ) Since a new baseline was established during the reporting period, only the changes since the new baseline are required. | |||
References A 1. AREVA Report ANP-3558P Revision 0, "Monticello LOCA MAPLHGR Limits for EPU/EFW with ATRIUM 1OXM Fuel and Revised ECCS Parameters," January 2017. | |||
L-MT -17 ~086 Page 2 of 2 A2. AREVA Report FS1-0032297 Revision 1, "Monticello 10 CFR 50.46 PCT Reporting for ATRIUM 10XM Fuel Through May 2017," May 25, 2017. | |||
A3. Letter from P. Gardner (NSPM) to NRC, "June 2017, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluations Models Pursuant to 10 CFR 50.46," (L-MT-17-045) dated June 22, 2017. | |||
L-MT -17 | ENCLOSURE 2 MONTICELLO NUCLEAR GENERATING PLANT | ||
ENCLOSURE 2 MONTICELLO NUCLEAR GENERATING PLANT | |||
==SUMMARY== | ==SUMMARY== | ||
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE FOR (PCT) FOR GE14 FUEL (3 pages follow) | OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE FOR (PCT) FOR GE14 FUEL (3 pages follow) | ||
L-MT-17-086 | |||
L-MT-17-086 Page 1 of 3 TABLE- | |||
==SUMMARY== | ==SUMMARY== | ||
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR GE14 FUEL Licensing Basis Applicable Analysis or Error I Change Description Ref. | |||
PCT(°F) | |||
GE14 NEDC-33322P, Revision 3, "Safety Analysis Report for G1& | |||
<2140 Monticello Constant Pressure Power Uprate" G2 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 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-Maintenance Update Changes (1 0 CFR 50.46 Notification Letter 2014-01) | |||
This change is for a new version (E4) of SAFER04A that G4 +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 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 G5 +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 20 14-03) | |||
This change is due to the use of a minimum ~p that could be G6 +20 non-conservative offering inappropriate steam cooling benefit above the core two-phase level. | |||
L-MT-17-086 Page 2 of 3 TABLE- | |||
L-MT-17-086 | |||
==SUMMARY== | ==SUMMARY== | ||
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR GE14 FUEL Licensing Basis Applicable Analysis or Error I 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) G7 -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. 0 Sum of absolute value of changes since last AOR (Reference G1). 60 Algebraic sum of changes for the current reporting period, which includes all changes since the 10 CFR 50.46 report in Reference G8. +0 Algebraic sum of changes since last AOR (Reference G1 ). +30 Current Adjusted Peak Cladding Temperature <2170 References G1. GE Report: NEDC-33322P Revision 3, "Safety Analysis Report for Monticello Constant Pressure Power Uprate," dated October 2008 (Enclosure 5 of NSPM (T. O'Connor) to NRC, "License Amendment Request: Extended Power Uprate (TAC MD9990)," L-MT-08-052, dated November 5, 2008, ADAMS Accession No. ML083230111 ). | |||
G2. NSPM (M. Schimmel) 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 2014-01, "SAFER04A E4-Maintenance Update Changes," dated May 21, 2014. | |||
L-MT-17-086 Page 3 of 3 G5. GEH 10 CFR 50.46 Notification Letter 2014-02, "SAFER04A E4-Mass Non-Conservatism," dated May 21, 2014. | |||
G6. GEH 10 CFR 50.46 Notification Letter 2014-03, "SAFER04A E4-Minimum Core DP Model," dated May 21, 2014. | |||
G7. GEH 10 CFR 50.46 Notification Letter 2014-04, "SAFER04A E4-Bundle/Lower Plenum CCFL Head," dated May 21, 2014. | |||
G8. L-MT-16-071, letter from P. Gardner (NSPM) to U.S. Nuclear Regulatory Commission, "2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46," December 19, 2016.}} | |||
L-MT-17-086 |
Latest revision as of 22:40, 3 February 2020
ML17349A620 | |
Person / Time | |
---|---|
Site: | Monticello ![]() |
Issue date: | 12/15/2017 |
From: | Church C Northern States Power Company, Minnesota, Xcel Energy |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
L-MT-17-086 | |
Download: ML17349A620 (9) | |
Text
Xcel Energy Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 December 15, 2017 L-MT-17-086 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 No. 50-263 Renewed Facility Operating License No. DPR-22 2017 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
References:
- 1) Letter from P. Gardner (NSPM) to NRC, "2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46," (L-MT-16-071), dated December 19, 2016
- 2) Letter from P. Gardner (NSPM) to NRC, "June 2017, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46," (L-MT-17-045), dat-ed June 22, 2017 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).
Provided within Enclosure 1 is a report concerning any changes or errors identified in the AREVA ECCS evaluation models for MNGP. This report is for the period between July 2016 and July 2017 for the ATRIUM 10XM fuel. During this period there was a notification of changes or errors resulting in a change to the calculated Peak Clad Temperature (PCT) of 51 oF and therefore reported in a 30-day report (Reference 2).
There have been no additional changes since that report. The previously report PCT of 2085oF for the ATRIUM 1OXM fuel since the 30-day report is unchanged.
Provided within Enclosure 2 is a report concerning any changes or errors identified in the General Electric-Hitachi (GEH) ECCS evaluation models for MNGP. This report is for the period between July 2016 and July 2017 for the General Electric (GE) GE14 fuel.
During this period no notification of any changes or errors resulting in a change to the calculated PCT were received from GEH. Therefore the PCT of less than 2170°F for the GE14 fuel and the PCT summary provided in the 2016 annual report (Reference 1) is unchanged.
Document Control Desk L-MT-17-086 Page 2 of 2 Until all the GE14 fuel is permanently discharged from the MNGP core, the annual ECCS reports will continue to be provided for the associated GEH evaluation models (GE14 fuel) and AREVA evaluation models (ATRIUM 10XM fuel).
Should you have questions regarding this letter, please contact Mr. Stephen Sollom at (763) 295-1611.
Summary of Commitments This letter proposes no new commitments and does not revise any existing commitments.
~{Zntf-
-~r C. CLtufM4.,
Christoph r urch Site Vice si ent, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosures (2) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC
ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 1 OXM FUEL (2 page follows)
L-MT-17-086 Enclosure 1 Page 1 of 2 TABLE-
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR ATRIUM 10XM FUEL Licensing Basis Applicable Analysis or Error I Change Description Ref. PCT(°F)
ATRIUM 10XM ANP-3558P Revision 0, "Monticello LOCA MAPLHGR Limits for EPU/EFWwith ATRIUM 10XM Fuel and Revised ECCS A1 2034 Parameters" (1)
MSIV Closure The impact of this MSIV closure change was estimated for the A2 +51 Monticello LOCA break spectrum and exposure-dependent MAPLHGR analyses.
Sum of absolute value of changes for the current reporting period, which 51 includes all changes since the 10 CFR 50.46 report Reference A 1.(2)
Sum of absolute value of changes since last analysis of record (AOR) 51 (Reference A 1).
Algebraic sum of changes for the current reporting period, which includes all
+51 changes since the 10 CFR 50.46 report in Reference A1.( 2)
Algebraic sum of changes since last AOR (Reference A 1). +51 Current Adjusted Peak Cladding Temperature 2085 1
( ) AREVA report ANP-3558P reflects a new LOCA analysis performed to provide a new baseline for the AREVA ATRIUM 10XM fuel at the MNGP as provided to the NRC in Reference A3.
2
( ) Since a new baseline was established during the reporting period, only the changes since the new baseline are required.
References A 1. AREVA Report ANP-3558P Revision 0, "Monticello LOCA MAPLHGR Limits for EPU/EFW with ATRIUM 1OXM Fuel and Revised ECCS Parameters," January 2017.
L-MT -17 ~086 Page 2 of 2 A2. AREVA Report FS1-0032297 Revision 1, "Monticello 10 CFR 50.46 PCT Reporting for ATRIUM 10XM Fuel Through May 2017," May 25, 2017.
A3. Letter from P. Gardner (NSPM) to NRC, "June 2017, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluations Models Pursuant to 10 CFR 50.46," (L-MT-17-045) dated June 22, 2017.
ENCLOSURE 2 MONTICELLO NUCLEAR GENERATING PLANT
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE FOR (PCT) FOR GE14 FUEL (3 pages follow)
L-MT-17-086 Page 1 of 3 TABLE-
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR GE14 FUEL Licensing Basis Applicable Analysis or Error I Change Description Ref.
PCT(°F)
GE14 NEDC-33322P, Revision 3, "Safety Analysis Report for G1&
<2140 Monticello Constant Pressure Power Uprate" G2 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 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-Maintenance Update Changes (1 0 CFR 50.46 Notification Letter 2014-01)
This change is for a new version (E4) of SAFER04A that G4 +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 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 G5 +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 20 14-03)
This change is due to the use of a minimum ~p that could be G6 +20 non-conservative offering inappropriate steam cooling benefit above the core two-phase level.
L-MT-17-086 Page 2 of 3 TABLE-
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT) FOR GE14 FUEL Licensing Basis Applicable Analysis or Error I 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) G7 -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. 0 Sum of absolute value of changes since last AOR (Reference G1). 60 Algebraic sum of changes for the current reporting period, which includes all changes since the 10 CFR 50.46 report in Reference G8. +0 Algebraic sum of changes since last AOR (Reference G1 ). +30 Current Adjusted Peak Cladding Temperature <2170 References G1. GE Report: NEDC-33322P Revision 3, "Safety Analysis Report for Monticello Constant Pressure Power Uprate," dated October 2008 (Enclosure 5 of NSPM (T. O'Connor) to NRC, "License Amendment Request: Extended Power Uprate (TAC MD9990)," L-MT-08-052, dated November 5, 2008, ADAMS Accession No. ML083230111 ).
G2. NSPM (M. Schimmel) 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 2014-01, "SAFER04A E4-Maintenance Update Changes," dated May 21, 2014.
L-MT-17-086 Page 3 of 3 G5. GEH 10 CFR 50.46 Notification Letter 2014-02, "SAFER04A E4-Mass Non-Conservatism," dated May 21, 2014.
G6. GEH 10 CFR 50.46 Notification Letter 2014-03, "SAFER04A E4-Minimum Core DP Model," dated May 21, 2014.
G7. GEH 10 CFR 50.46 Notification Letter 2014-04, "SAFER04A E4-Bundle/Lower Plenum CCFL Head," dated May 21, 2014.
G8. L-MT-16-071, letter from P. Gardner (NSPM) to U.S. Nuclear Regulatory Commission, "2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46," December 19, 2016.