RS-14-085, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors

Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors

ML14066A143
Person / Time
Site:	LaSalle
Issue date:	03/07/2014
From:	Gullott D Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-14-085
Download: ML14066A143 (7)

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