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| {{#Wiki_filter:RS-14-085 March 7, 2014 U. S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 10 CFR 50.46 | | {{#Wiki_filter:RS-14-085 10 CFR 50.46 March 7, 2014 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 |
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| ==Subject:== | | ==Subject:== |
| Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station | | Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station |
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| ==Reference:== | | ==Reference:== |
| | Letter from D. M. Gullatt (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station," dated March 7, 2013 In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a}(3}(ii}, Exelon Generation Company, LLC (EGC) is submitting the attached information to fulfill the annual reporting requirements for LaSalle County Station (LSCS), Units 1 and 2. The attachments describe the changes in accumulated peak cladding temperature (PCT) since the previous annual report submitted in the referenced letter. |
| | There are no regulatory commitments contained in this submittal. Should you have any questions concerning this letter, please contact Ms. Lisa A. Simpson at (630} 657-2815. |
| | Respectfully, David M. Gullatt Manager - Licensing Exelon Generation Company, LLC Attachments: |
| | : 1) LaSalle County Station, Units 1 and 2- 10 CFR 50.46 Report (GNF Fuel) 2} LaSalle County Station, Units 1 and 2-10 CFR 50.46 Report (AREVA NP Fuel) |
| | : 3) LaSalle County Station, Units 1 and 2- 10 CFR 50.46 Report Assessment Notes |
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| Letter from D. M. Gullatt (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station," dated March 7, 2013 In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a}(3}(ii}, Exelon Generation Company, LLC (EGC) is submitting the attached information to fulfill the annual reporting requirements for LaSalle County Station (LSCS), Units 1 and 2. The attachments describe the changes in accumulated peak cladding temperature (PCT) since the previous annual report submitted in the referenced letter. There are no regulatory commitments contained in this submittal.
| | ATTACHMENT1 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (GNF Fuel) |
| Should you have any questions concerning this letter, please contact Ms. Lisa A. Simpson at (630} 657-2815.
| | PLANT NAME: LaSalle County Station (LSCS), Units 1 & 2 ECCS EVALUATION MODEL: SAFER/PRIME LOCA REPORT REVISION DATE: March 7, 2014 CURRENT OPERATING CYCLE: L 1C16 and L2C15 ANALYSIS OF RECORD Evaluation Model Methodology: NEDE-23785-1-PA, Rev. 1, "GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident (Volume Ill), SAFER/GESTR Application Methodology," October 1984. |
| Respectfully, David M. Gullatt Manager -Licensing Exelon Generation Company, LLC Attachments:
| | "The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Pertormance," Technical Bases-NEDC-33256P-A, Qualification- NEDC-33257P-A, and Application Methodology- NEDC-33258P-A, September 2010. |
| : 1) LaSalle County Station, Units 1 and 2-10 CFR 50.46 Report (GNF Fuel) 2} LaSalle County Station, Units 1 and 2-10 CFR 50.46 Report (AREVA NP Fuel) 3) LaSalle County Station, Units 1 and 2-10 CFR 50.46 Report Assessment Notes ATTACHMENT1 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (GNF Fuel) PLANT NAME: ECCS EVALUATION MODEL: REPORT REVISION DATE: CURRENT OPERATING CYCLE: ANALYSIS OF RECORD LaSalle County Station (LSCS), Units 1 & 2 SAFER/PRIME LOCA March 7, 2014 L 1C16 and L2C15 Evaluation Model Methodology:
| | NED0-33173 Supplement 4-A, "Implementation of PRIME Models and Data in Downstream Methods," |
| NEDE-23785-1-PA, Rev. 1, "GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident (Volume Ill), SAFER/GESTR Application Methodology," October 1984. Calculation: | | September 2011. |
| Fuel: Limiting Single Failure: Limiting Break Size and Location:
| | Calculation: NEDC-32258P, "LaSalle County Station Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," GE Nuclear Energy, October 1993. |
| Reference Peak Cladding Temperature (PCT): "The PRIME Model for Analysis of Fuel Rod Mechanical Pertormance," Technical NEDC-33256P-A, Qualification-NEDC-33257P-A, and Application Methodology-NEDC-33258P-A, September 2010. NED0-33173 Supplement 4-A, "Implementation of PRIME Models and Data in Downstream Methods," September 2011. NEDC-32258P, "LaSalle County Station Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," GE Nuclear Energy, October 1993. GE Hitachi Calculation 0000-0121-8990-RO, "LaSalle County Station GNF2 ECCS-LOCA Evaluation," GE Hitachi Nuclear Energy, January 2012. GNF2 High Pressure Core Spray Diesel Generator 0.08 ft 2 Recirculation Pump Suction Line Break Page 1 of 2 MARGIN ALLOCATION ATTACHMENT 1 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (GNF Fuel) A. PRIOR LOSS-OF-COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS 10 CFR 50.46 report dated March 7, 2012 (Note 1) APCT = 0°F 10 CFR 50.46 report dated March 7, 2013 (Note 2) APCT = 0°F Net PCT 1540°F B. CURRENT LOCA MODEL ASSESSMENTS None (Note 4) APCT = 0°F Total PCT change from current assessments L:APCT = 0°F Cumulative PCT change from current assessments L: IAPCT I= ooF Net PCT 1540°F Page 2 of 2 ATTACHMENT 2 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (AREVA NP Fuel) PLANT NAME: ECCS EVALUATION MODEL: REPORT REVISION DATE: CURRENT OPERATING CYCLES: ANALYSIS OF RECORD LaSalle County Station (LSCS), Units 1 & 2 SAFER/PRIME LOCA March 7, 2014 L 1 C 16 and L2C 15 Evaluation Model Methodology:
| | GE Hitachi Calculation 0000-0121-8990-RO, "LaSalle County Station GNF2 ECCS-LOCA Evaluation," GE Hitachi Nuclear Energy, January 2012. |
| NEDE-23785-1-PA, Rev. 1, "GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident (Volume Ill}, SAFER/GESTR Application Methodology," October 1984. Calculation:
| | Fuel: GNF2 Limiting Single Failure: High Pressure Core Spray Diesel Generator Limiting Break Size and 0.08 ft 2 Recirculation Pump Suction Line Break Location: |
| Fuel: Limiting Single Failure: Limiting Break Size and Location:
| | Reference Peak Cladding Temperature (PCT): |
| Reference Peak Cladding Temperature (PCT): "The PRIME Model for Analysis of Fuel Rod Mechanical Performance," Technical NEDC-33256P-A, Qualification-NEDC-33257P-A, and Application Methodology -N EDC-33258P-A, September 2010. NED0-33173 Supplement 4-A, "Implementation of PRIME Models and Data in Downstream Methods," September 2011. NEDC-32258P, "LaSalle County Station Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," GE Nuclear Energy, October 1993. GE Hitachi Calculation 0000-0142-8555-RO, "LaSalle County Station ECCS-LOCA Evaluation for ATRIUM-10 Fuel," GE Hitachi Nuclear Energy, April2012. | | Page 1 of 2 |
| ATRIUM-10 High Pressure Core Spray Diesel Generator 0.08 ft 2 Recirculation Pump Suction Line Break Page 1 of 2 MARGIN ALLOCATION ATTACHMENT 2 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (AREVA NP Fuel) A. PRIOR LOSS-OF-COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS 10 CFR 50.46 report dated March 7, 2013 (Note 2}
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| 0°F Net PCT 1460°F B. CURRENT LOCA MODEL ASSESSMENTS None (Note 3)
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| = ooF Total PCT change from current assessments
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| = 0°F Cumulative PCT change from current assessments L:
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| I= ooF Net PCT 1460°F Page 2 of 2 ATTACHMENT 3 LaSalle County Station, Units 1 and 2 1 0 CFR 50.46 Report Assessment Notes 1. Prior Loss-of-Coolant Accident (LOCA) Model Assessment for AREVA NP Fuel and GNF Fuel The referenced letter provided the annual 10 CFR 50.46 report for LSCS, Units 1 and 2, for the 2012 reporting period. The referenced letter reported the introduction of GNF2 fuel into the LSCS, Unit 1, core. A new LOCA analysis of record for GNF2 fuel was performed by GE Hitachi Nuclear Energy (GEH). No Emergency Core Cooling System (ECCS) related changes or modifications have occurred at LSCS that affect the assumptions in the GEH GNF2 LOCA analysis.
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| The LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Units 1 and 2, for the 2012 reporting period was performed by AR EVA. The AREVA analysis has been replaced by GEH analysis as discussed in assessment notes 2 and 3. The assessments for the AREVA analysis have been removed from LSCS 10 CFR 50.46 report starting in 2014. [
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| ==Reference:== | | ATTACHMENT 1 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (GNF Fuel) |
| | MARGIN ALLOCATION A. PRIOR LOSS-OF-COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS 10 CFR 50.46 report dated March 7, 2012 (Note 1) APCT =0°F 10 CFR 50.46 report dated March 7, 2013 (Note 2) APCT =0°F Net PCT 1540°F B. CURRENT LOCA MODEL ASSESSMENTS None (Note 4) APCT = 0°F Total PCT change from current assessments L:APCT = 0°F Cumulative PCT change from current assessments L: IAPCT I= ooF Net PCT 1540°F Page 2 of 2 |
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| Letter from David M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, 11 Piant Specific ECCS Evaluation Changes -10 CFR 50.46 Report, 11 dated March 7, 2012.] 2. Prior LOCA Model Assessment for AREVA NP Fuel and GNF Fuel The referenced letter provided the annual 10 CFR 50.46 report for LSCS, Units 1 and 2, for the 2013 reporting period. The referenced letter reported the introduction of GNF2 fuel into the LSCS, Unit 2, core. The referenced letter also reported no vendor notifications of ECCS model errors/changes applicable to the GNF2 fuel in LSCS, Units 1 and 2, and reported that no ECCS related changes or modifications occurred at LSCS that affected the assumptions in the GEH GNF2 LOCA analysis of record for the GNF2 fuel in LSCS, Units 1 and 2. The referenced letter reported a new LOCA analysis of record for the ATRIUM-1 0 fuel in LSCS, Units 1 and 2, was performed by GEH and implemented only at LSCS, Unit 2. The referenced letter reported that no ECCS related changes or modifications occurred at LSCS that affected the assumptions in the GEH LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Unit 2. The LOCA analysis of record for the ATRIUM-1 0 fuel in LSCS, Unit 1, for the 2013 reporting period was performed by AREVA. The A REV A analysis has been replaced by GEH analysis as previously discussed and in assessment note 3. The assessments for the AREVA analysis have been removed from LSCS 10 CFR 50.46 report starting in 2014. [
| | ATTACHMENT 2 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (AREVA NP Fuel) |
| | PLANT NAME: LaSalle County Station (LSCS), Units 1& 2 ECCS EVALUATION MODEL: SAFER/PRIME LOCA REPORT REVISION DATE: March 7, 2014 CURRENT OPERATING CYCLES: L 1C 16 and L2C 15 ANALYSIS OF RECORD Evaluation Model Methodology: NEDE-23785-1-PA, Rev. 1, "GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident (Volume Ill}, SAFER/GESTR Application Methodology," October 1984. |
| | "The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Performance," Technical Bases-NEDC-33256P-A, Qualification- NEDC-33257P-A, and Application Methodology - N EDC-33258P-A, September 2010. |
| | NED0-33173 Supplement 4-A, "Implementation of PRIME Models and Data in Downstream Methods," |
| | September 2011. |
| | Calculation: NEDC-32258P, "LaSalle County Station Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," GE Nuclear Energy, October 1993. |
| | GE Hitachi Calculation 0000-0142-8555-RO, "LaSalle County Station ECCS-LOCA Evaluation for ATRIUM-10 Fuel," GE Hitachi Nuclear Energy, April2012. |
| | Fuel: ATRIUM-10 Limiting Single Failure: High Pressure Core Spray Diesel Generator Limiting Break Size and 0.08 ft 2 Recirculation Pump Suction Line Break Location: |
| | Reference Peak Cladding Temperature (PCT): |
| | Page 1 of 2 |
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| ==Reference:== | | ATTACHMENT 2 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (AREVA NP Fuel) |
| | MARGIN ALLOCATION A. PRIOR LOSS-OF-COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS 10 CFR 50.46 report dated March 7, 2013 (Note 2} ~PCT= 0°F Net PCT 1460°F B. CURRENT LOCA MODEL ASSESSMENTS None (Note 3) ~PCT = ooF Total PCT change from current assessments L:~PCT = 0°F Cumulative PCT change from current assessments L: l~PCT I= ooF Net PCT 1460°F Page 2 of 2 |
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| Letter from David M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, II Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station," dated March 7, 2013.] [
| | ATTACHMENT 3 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report Assessment Notes |
| | : 1. Prior Loss-of-Coolant Accident (LOCA) Model Assessment for AREVA NP Fuel and GNF Fuel The referenced letter provided the annual 10 CFR 50.46 report for LSCS, Units 1 and 2, for the 2012 reporting period. The referenced letter reported the introduction of GNF2 fuel into the LSCS, Unit 1, core. A new LOCA analysis of record for GNF2 fuel was performed by GE Hitachi Nuclear Energy (GEH). No Emergency Core Cooling System (ECCS) related changes or modifications have occurred at LSCS that affect the assumptions in the GEH GNF2 LOCA analysis. |
| | The LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Units 1 and 2, for the 2012 reporting period was performed by AR EVA. The AREVA analysis has been replaced by GEH analysis as discussed in assessment notes 2 and 3. The assessments for the AREVA analysis have been removed from LSCS 10 CFR 50.46 report starting in 2014. |
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| ==Reference:== | | ==Reference:== |
| | Letter from David M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, 11 Piant Specific ECCS Evaluation Changes -10 CFR 50.46 Report, 11 dated March 7, 2012.] |
| | : 2. Prior LOCA Model Assessment for AREVA NP Fuel and GNF Fuel The referenced letter provided the annual 10 CFR 50.46 report for LSCS, Units 1 and 2, for the 2013 reporting period. The referenced letter reported the introduction of GNF2 fuel into the LSCS, Unit 2, core. The referenced letter also reported no vendor notifications of ECCS model errors/changes applicable to the GNF2 fuel in LSCS, Units 1 and 2, and reported that no ECCS related changes or modifications occurred at LSCS that affected the assumptions in the GEH GNF2 LOCA analysis of record for the GNF2 fuel in LSCS, Units 1 and 2. |
| | The referenced letter reported a new LOCA analysis of record for the ATRIUM-1 0 fuel in LSCS, Units 1 and 2, was performed by GEH and implemented only at LSCS, Unit 2. The referenced letter reported that no ECCS related changes or modifications occurred at LSCS that affected the assumptions in the GEH LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Unit 2. |
| | The LOCA analysis of record for the ATRIUM-1 0 fuel in LSCS, Unit 1, for the 2013 reporting period was performed by AREVA. The A REVA analysis has been replaced by GEH analysis as previously discussed and in assessment note 3. The assessments for the AREVA analysis have been removed from LSCS 10 CFR 50.46 report starting in 2014. |
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| GE Hitachi Calculation 0000-0142-8555-RO, "LaSalle County Station ECCS-LOCA Evaluation for ATRIUM-10 Fuel," GE Hitachi Nuclear Energy, dated April 2012.] Page 1 of 2 ATTACHMENT 3 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report Assessment Notes 3. Current LOCA Model Assessment for AREV A NP Fuel (GEH Analysis of Record) The last annual report (referenced letter) reported the LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Units 1 and 2, was performed by GEH and implemented only at LSCS, Unit 2. Since the last annual report, the referenced report has been implemented at LSCS, Unit 1, as part of L 1 C16. No ECCS related changes or modifications have occurred at LSCS that affect the assumptions in the GEH ATRIUM-10 LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Units 1 and 2. [
| | ==Reference:== |
| | Letter from David M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, II Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station," dated March 7, 2013.] |
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| ==Reference:== | | ==Reference:== |
| | GE Hitachi Calculation 0000-0142-8555-RO, "LaSalle County Station ECCS-LOCA Evaluation for ATRIUM-10 Fuel," GE Hitachi Nuclear Energy, dated April 2012.] |
| | Page 1 of 2 |
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| Letter from David M. Gullatt (Exelon Generation Company, LLC) to U.S. NRC, "Annual10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station," dated March 7, 2013.) [
| | ATTACHMENT 3 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report Assessment Notes |
| | : 3. Current LOCA Model Assessment for AREV A NP Fuel (GEH Analysis of Record) |
| | The last annual report (referenced letter) reported the LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Units 1 and 2, was performed by GEH and implemented only at LSCS, Unit 2. Since the last annual report, the referenced report has been implemented at LSCS, Unit 1, as part of L 1C16. No ECCS related changes or modifications have occurred at LSCS that affect the assumptions in the GEH ATRIUM-10 LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Units 1 and 2. |
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| ==Reference:== | | ==Reference:== |
| | Letter from David M. Gullatt (Exelon Generation Company, LLC) to U.S. NRC, "Annual10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station," dated March 7, 2013.) |
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| GE Hitachi Calculation 0000-0142*8555-RO, "LaSalle County Station ECCS-LOCA Evaluation for ATRIUM-10 Fuel," GE Hitachi Nuclear Energy, dated April 2012.) 4. Current LOCA Model Assessment for GNF Fuel Since the last annual report, no vendor notifications of ECCS model errors/changes applicable to the GNF2 fuel in LSCS, Units 1 and 2, have been issued. No ECCS related changes or modifications have occurred at LSCS that affect the assumptions in the GEH GNF2 LOCA analysis of record for the GNF2 fuel in LSCS, Units 1 and 2. Page 2 of 2}} | | ==Reference:== |
| | GE Hitachi Calculation 0000-0142*8555-RO, "LaSalle County Station ECCS-LOCA Evaluation for ATRIUM-10 Fuel," GE Hitachi Nuclear Energy, dated April 2012.) |
| | : 4. Current LOCA Model Assessment for GNF Fuel Since the last annual report, no vendor notifications of ECCS model errors/changes applicable to the GNF2 fuel in LSCS, Units 1 and 2, have been issued. No ECCS related changes or modifications have occurred at LSCS that affect the assumptions in the GEH GNF2 LOCA analysis of record for the GNF2 fuel in LSCS, Units 1 and 2. |
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Category:Annual Operating Report
MONTHYEARRA23-028, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023
Submittal of 2022 Annual Radioactive Effluent Release Report
RS-19-020, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2019-03-0707 March 2019
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
ML18066A0522018-03-0707 March 2018
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-17-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-03-0707 March 2017
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-16-054, Transmittal of 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-03-0707 March 2016
Transmittal of 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015
Annual Property Insurance Status Report
RS-15-074, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2015-03-0606 March 2015
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RA14-015, Submittal of 2013 Annual Radioactive Effluent Release Report2014-05-0101 May 2014
Submittal of 2013 Annual Radioactive Effluent Release Report
RS-14-085, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2014-03-0707 March 2014
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RA13-021, County Station, Units I and 2, 2012 Annual Radiological Environmental Operating Report2013-05-15015 May 2013
County Station, Units I and 2, 2012 Annual Radiological Environmental Operating Report
RA13-020, Submittal of 2012 Annual Radioactive Effluent Release Report2013-04-26026 April 2013
Submittal of 2012 Annual Radioactive Effluent Release Report
ML11124A1012011-04-26026 April 2011
2010 Annual Radioactive Effluent Release Report
RA10-021, 2009 Annual Radiological Environmental Operating Report2010-05-12012 May 2010
2009 Annual Radiological Environmental Operating Report
RA10-020, 2009 Annual Radioactive Effluent Release Report2010-04-28028 April 2010
2009 Annual Radioactive Effluent Release Report
RA09-042, 2008 Annual Radiological Environmental Operating Report2009-05-15015 May 2009
2008 Annual Radiological Environmental Operating Report
RA07-041, Annual Radiological Environmental Operating Report, 1 January Through 31 December 20062007-05-15015 May 2007
Annual Radiological Environmental Operating Report, 1 January Through 31 December 2006
ML0629803142006-05-15015 May 2006
Annual Radiological Environmental Operating Report
ML0215004872002-05-15015 May 2002
Annual Radiological Environmental Operating Report
2023-04-28
[Table view]
Category:Letter type:RS
MONTHYEARRS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023
Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor
RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023
Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023
Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
RS-22-085, Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-01-12012 January 2023
Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis
RS-23-006, Supplemental Information Regarding License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report2023-01-10010 January 2023
Supplemental Information Regarding License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022
Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022
Response to Request for Additional Information License Amendments Related to Fuel Storage
RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022
Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022
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2023-08-04
[Table view] |
Text
RS-14-085 10 CFR 50.46 March 7, 2014 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
Reference:
Letter from D. M. Gullatt (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station," dated March 7, 2013 In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a}(3}(ii}, Exelon Generation Company, LLC (EGC) is submitting the attached information to fulfill the annual reporting requirements for LaSalle County Station (LSCS), Units 1 and 2. The attachments describe the changes in accumulated peak cladding temperature (PCT) since the previous annual report submitted in the referenced letter.
There are no regulatory commitments contained in this submittal. Should you have any questions concerning this letter, please contact Ms. Lisa A. Simpson at (630} 657-2815.
Respectfully, David M. Gullatt Manager - Licensing Exelon Generation Company, LLC Attachments:
- 1) LaSalle County Station, Units 1 and 2- 10 CFR 50.46 Report (GNF Fuel) 2} LaSalle County Station, Units 1 and 2-10 CFR 50.46 Report (AREVA NP Fuel)
- 3) LaSalle County Station, Units 1 and 2- 10 CFR 50.46 Report Assessment Notes
ATTACHMENT1 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (GNF Fuel)
PLANT NAME: LaSalle County Station (LSCS), Units 1 & 2 ECCS EVALUATION MODEL: SAFER/PRIME LOCA REPORT REVISION DATE: March 7, 2014 CURRENT OPERATING CYCLE: L 1C16 and L2C15 ANALYSIS OF RECORD Evaluation Model Methodology: NEDE-23785-1-PA, Rev. 1, "GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident (Volume Ill), SAFER/GESTR Application Methodology," October 1984.
"The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Pertormance," Technical Bases-NEDC-33256P-A, Qualification- NEDC-33257P-A, and Application Methodology- NEDC-33258P-A, September 2010.
NED0-33173 Supplement 4-A, "Implementation of PRIME Models and Data in Downstream Methods,"
September 2011.
Calculation: NEDC-32258P, "LaSalle County Station Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," GE Nuclear Energy, October 1993.
GE Hitachi Calculation 0000-0121-8990-RO, "LaSalle County Station GNF2 ECCS-LOCA Evaluation," GE Hitachi Nuclear Energy, January 2012.
Fuel: GNF2 Limiting Single Failure: High Pressure Core Spray Diesel Generator Limiting Break Size and 0.08 ft 2 Recirculation Pump Suction Line Break Location:
Reference Peak Cladding Temperature (PCT):
Page 1 of 2
ATTACHMENT 1 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (GNF Fuel)
MARGIN ALLOCATION A. PRIOR LOSS-OF-COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS 10 CFR 50.46 report dated March 7, 2012 (Note 1) APCT =0°F 10 CFR 50.46 report dated March 7, 2013 (Note 2) APCT =0°F Net PCT 1540°F B. CURRENT LOCA MODEL ASSESSMENTS None (Note 4) APCT = 0°F Total PCT change from current assessments L:APCT = 0°F Cumulative PCT change from current assessments L: IAPCT I= ooF Net PCT 1540°F Page 2 of 2
ATTACHMENT 2 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (AREVA NP Fuel)
PLANT NAME: LaSalle County Station (LSCS), Units 1& 2 ECCS EVALUATION MODEL: SAFER/PRIME LOCA REPORT REVISION DATE: March 7, 2014 CURRENT OPERATING CYCLES: L 1C 16 and L2C 15 ANALYSIS OF RECORD Evaluation Model Methodology: NEDE-23785-1-PA, Rev. 1, "GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident (Volume Ill}, SAFER/GESTR Application Methodology," October 1984.
"The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Performance," Technical Bases-NEDC-33256P-A, Qualification- NEDC-33257P-A, and Application Methodology - N EDC-33258P-A, September 2010.
NED0-33173 Supplement 4-A, "Implementation of PRIME Models and Data in Downstream Methods,"
September 2011.
Calculation: NEDC-32258P, "LaSalle County Station Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," GE Nuclear Energy, October 1993.
GE Hitachi Calculation 0000-0142-8555-RO, "LaSalle County Station ECCS-LOCA Evaluation for ATRIUM-10 Fuel," GE Hitachi Nuclear Energy, April2012.
Fuel: ATRIUM-10 Limiting Single Failure: High Pressure Core Spray Diesel Generator Limiting Break Size and 0.08 ft 2 Recirculation Pump Suction Line Break Location:
Reference Peak Cladding Temperature (PCT):
Page 1 of 2
ATTACHMENT 2 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report (AREVA NP Fuel)
MARGIN ALLOCATION A. PRIOR LOSS-OF-COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS 10 CFR 50.46 report dated March 7, 2013 (Note 2} ~PCT= 0°F Net PCT 1460°F B. CURRENT LOCA MODEL ASSESSMENTS None (Note 3) ~PCT = ooF Total PCT change from current assessments L:~PCT = 0°F Cumulative PCT change from current assessments L: l~PCT I= ooF Net PCT 1460°F Page 2 of 2
ATTACHMENT 3 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report Assessment Notes
- 1. Prior Loss-of-Coolant Accident (LOCA) Model Assessment for AREVA NP Fuel and GNF Fuel The referenced letter provided the annual 10 CFR 50.46 report for LSCS, Units 1 and 2, for the 2012 reporting period. The referenced letter reported the introduction of GNF2 fuel into the LSCS, Unit 1, core. A new LOCA analysis of record for GNF2 fuel was performed by GE Hitachi Nuclear Energy (GEH). No Emergency Core Cooling System (ECCS) related changes or modifications have occurred at LSCS that affect the assumptions in the GEH GNF2 LOCA analysis.
The LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Units 1 and 2, for the 2012 reporting period was performed by AR EVA. The AREVA analysis has been replaced by GEH analysis as discussed in assessment notes 2 and 3. The assessments for the AREVA analysis have been removed from LSCS 10 CFR 50.46 report starting in 2014.
[
Reference:
Letter from David M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, 11 Piant Specific ECCS Evaluation Changes -10 CFR 50.46 Report, 11 dated March 7, 2012.]
- 2. Prior LOCA Model Assessment for AREVA NP Fuel and GNF Fuel The referenced letter provided the annual 10 CFR 50.46 report for LSCS, Units 1 and 2, for the 2013 reporting period. The referenced letter reported the introduction of GNF2 fuel into the LSCS, Unit 2, core. The referenced letter also reported no vendor notifications of ECCS model errors/changes applicable to the GNF2 fuel in LSCS, Units 1 and 2, and reported that no ECCS related changes or modifications occurred at LSCS that affected the assumptions in the GEH GNF2 LOCA analysis of record for the GNF2 fuel in LSCS, Units 1 and 2.
The referenced letter reported a new LOCA analysis of record for the ATRIUM-1 0 fuel in LSCS, Units 1 and 2, was performed by GEH and implemented only at LSCS, Unit 2. The referenced letter reported that no ECCS related changes or modifications occurred at LSCS that affected the assumptions in the GEH LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Unit 2.
The LOCA analysis of record for the ATRIUM-1 0 fuel in LSCS, Unit 1, for the 2013 reporting period was performed by AREVA. The A REVA analysis has been replaced by GEH analysis as previously discussed and in assessment note 3. The assessments for the AREVA analysis have been removed from LSCS 10 CFR 50.46 report starting in 2014.
[
Reference:
Letter from David M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, II Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station," dated March 7, 2013.]
[
Reference:
GE Hitachi Calculation 0000-0142-8555-RO, "LaSalle County Station ECCS-LOCA Evaluation for ATRIUM-10 Fuel," GE Hitachi Nuclear Energy, dated April 2012.]
Page 1 of 2
ATTACHMENT 3 LaSalle County Station, Units 1 and 2 10 CFR 50.46 Report Assessment Notes
- 3. Current LOCA Model Assessment for AREV A NP Fuel (GEH Analysis of Record)
The last annual report (referenced letter) reported the LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Units 1 and 2, was performed by GEH and implemented only at LSCS, Unit 2. Since the last annual report, the referenced report has been implemented at LSCS, Unit 1, as part of L 1C16. No ECCS related changes or modifications have occurred at LSCS that affect the assumptions in the GEH ATRIUM-10 LOCA analysis of record for the ATRIUM-10 fuel in LSCS, Units 1 and 2.
[
Reference:
Letter from David M. Gullatt (Exelon Generation Company, LLC) to U.S. NRC, "Annual10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station," dated March 7, 2013.)
[
Reference:
GE Hitachi Calculation 0000-0142*8555-RO, "LaSalle County Station ECCS-LOCA Evaluation for ATRIUM-10 Fuel," GE Hitachi Nuclear Energy, dated April 2012.)
- 4. Current LOCA Model Assessment for GNF Fuel Since the last annual report, no vendor notifications of ECCS model errors/changes applicable to the GNF2 fuel in LSCS, Units 1 and 2, have been issued. No ECCS related changes or modifications have occurred at LSCS that affect the assumptions in the GEH GNF2 LOCA analysis of record for the GNF2 fuel in LSCS, Units 1 and 2.
Page 2 of 2
