RA-22-0028, Annual Report of Changes Pursuant to 10 CFR 50.46

Annual Report of Changes Pursuant to 10 CFR 50.46

ML22118A005
Person / Time
Site:	Oconee, Mcguire, Catawba, Harris, Brunswick, Robinson, McGuire
Issue date:	04/27/2022
From:	Gibby S Duke Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-22-0028
Download: ML22118A005 (32)

Text

Shawn Gibby Vice President Nuclear Engineering 526 South Church Street, EC-07H Charlotte, NC 28202 704-519-5138 Shawn.Gibby@duke-energy.com 10 CFR 50.46 Serial: RA-22-0028 April 27, 2022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Catawba Nuclear Station, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. NPF-35 and NPF-52 Docket Nos. 50-413 and 50-414 Shearon Harris Nuclear Power Plant, Unit 1 Renewed Facility Operating License No. NPF-63 Docket No. 50-400 McGuire Nuclear Station, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. NPF-9 and NPF-17 Docket Nos. 50-369 and 50-370 Oconee Nuclear Station, Unit Nos. 1, 2 and 3 Renewed Facility Operating License Nos. DPR-38, DPR-47 and DPR-55 Docket Nos. 50-269, 50-270 and 50-287 H. B. Robinson Steam Electric Plant, Unit 2 Renewed Facility Operating License No. DPR-23 Docket No. 50-261

SUBJECT:

Annual Report of Changes Pursuant to 10 CFR 50.46 Ladies and Gentlemen:

Pursuant to 10 CFR 50.46(a)(3)(ii), Duke Energy hereby submits the enclosed annual reports of changes to, or errors in, Emergency Core Cooling System (ECCS) evaluation models. These reports cover the period from January 1, 2021 to December 31, 2021 for the Brunswick Steam Electric Plant (BNP), Catawba Nuclear Station (CNS), Shearon Harris Nuclear Power Plant (HNP), McGuire Nuclear Station (MNS), Oconee Nuclear Station (ONS), and H.B. Robinson Steam Electric Plant (RNP) are provided in Enclosures 1 through 6 respectively.

U.S. Nuclear Regulatory Commission RA-22-0028 Page 2 No regulatory commitments are contained in this submittal.

Should you have any questions concerning this letter and its enclosures, please contact Lee Grzeck, Manager - Nuclear Fleet Licensing at (980) 373-1530.

Sincerely, Shawn Gibby Vice President, Nuclear Engineering

Enclosures:

1. BNP 10 CFR 50.46 Annual Report

2. CNS 10 CFR 50.46 Annual Report

3. HNP 10 CFR 50.46 Annual Report

4. MNS 10 CFR 50.46 Annual Report

5. ONS 10 CFR 50.46 Annual Report

6. RNP 10 CFR 50.46 Annual Report

U.S. Nuclear Regulatory Commission RA-22-0028 Page 3 cc:

L. Dudes, USNRC, Region II Regional Administrator L. Haeg, USNRC NRR Project Manager for BNP Z. Stone, USNRC NRR Project Manager for CNS A.. Hon, USNRC NRR Project Manager for HNP J. Klos, USNRC NRR Project Manager for MNS S. Williams, USNRC NRR Project Manager for ONS T. Hood, USNRC NRR Project Manager for RNP G. Smith, USNRC Senior Resident Inspector for BNP J. Austin, USNRC Senior Resident Inspector for CNS J. Zeiler, USNRC Senior Resident Inspector for HNP A. Hutto, USNRC Senior Resident Inspector for MNS J. Nadel, USNRC Senior Resident Inspector for ONS M. Fannon, USNRC Senior Resident Inspector for RNP General Counsel to Chair of NC Utilities Commission (swatson@ncuc.net)

D. Crowley (david.crowley@dhhs.nc.gov), NC DHHS, Radiation Protection Section P. D. Cox (patrick.cox@dhhs.nc.gov), NC DHHS, Environmental Program SC Attorney General (HKirkland@scag.gov)

L. Garner (garnerld@dhec.sc.gov), SC DHEC A. Nair (naira@dhec.sc.gov), SC DHEC Page 1 of 6 RA-22-0028 ENCLOSURE 1: BNP 10 CFR 50.46 Annual Report Brunswick Steam Electric Plant, Units 1 and 2 Docket Nos. 50-325 and 50-324 / Renewed License Nos. DPR-71 and DPR-62 Page 2 of 6 RA-22-0028 Summary of Errors Reported 10 CFR 50.46 Report for Brunswick Steam Electric Plant Units 1 and 2 During this reporting period there was one error report on the EXEM BWR-2000 evaluation model for ATRIUM 10XM, four error reports on the AURORA-B evaluation model for ATRIUM 11, and no error reports on the ATRIUM 11 LUAs.

Two of the four error reports on the AURORA-B evaluation model for ATRIUM 11 were previously reported as described below:

1) Error report Reference 1 was received in January 2021 and was reported to the NRC per Reference 2.

2) Error report Reference 3 was received in April 2021 and was reported to the NRC per Reference 4.

The third AURORA-B error report, FS1-0052486 Revision 4.0 (Reference 5), was received in September 2021 documenting an error in the AURORA-B evaluation model automation code AUTOSR5BDK that specified incorrect S-RELAP5 trip input values for the hot wall effect resulting in a +3°F PCT change in the AURORA-B methodology results for ATRIUM 11 fuel.

Reference 4 established the ATRIUM 11 Licensing Basis PCT at 1875°F so with the third report (Reference 5), the ATRIUM 11 Licensing Basis PCT changed to 1878°F.

Finally, the fourth AURORA-B error report, FS1-0060612 Revision 2.0 (Reference 6), was received in February 2022 documenting three errors in the AURORA-B evaluation model applicable this reporting period: (1) an S-RELAP5 code error in the calculation of the cladding thermal conductivity resulting in a 0°F PCT change; (2) a non-zero value for the initial cladding manufactured hydrogen content should have been used in RODEX4 or a justification for the use of a 0 value, which resulted in a 0°F PCT change; (3) a non-zero value for the initial manufactured oxide thickness should have been used in RODEX4 or a justification for the use of a 0 value, which resulted in a 0°F PCT change. The net effect of these three errors results in the new Licensing PCT value of 1878°F (established above from Reference 5).

The one ATRIUM 10XM EXEM BWR-2000 evaluation model error report, FS1-0040060 Revision 3.0 (Reference 7), was received in December 2021 which documents corrections to the EXEM BWR-2000 evaluation model automation code RDX2_2_RDX4 that calculates thermal-conductivity degradation (TCD) factors resulting in a +0°F PCT change in the EXEM BWR-2000 methodology results for ATRIUM 10XM fuel.

Reference 8 established the ATRIUM 10XM Licensing Basis PCT at 1925°F so with the single ATRIUM 10XM EXEM BWR-2000 evaluation model error report (Reference 8), the ATRIUM 10XM Licensing Basis PCT remains at 1925°F.

Page 3 of 6 RA-22-0028

References:

1) FS1-0052486 Revision 2.0, 10 CFR 50.46 PCT Error Report for Brunswick Units 1 and 2 ATRIUM 11 Fuel, Framatome Inc., January 2021.

2) Duke Letter RA-21-0021, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model, Steve Snider to U.S. Nuclear Regulatory Commission, February 9, 2021, NRC Accession Number ML21040A383.

3) FS1-0052486 Revision 3.0, 10 CFR 50.46 PCT Error Report for Brunswick Units 1 and 2 ATRIUM 11 Fuel, Framatome Inc., April 2021.

4) Duke Letter RA-21-0154, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model, John Krakuszeski to U.S. Nuclear Regulatory Commission, May 26, 2021, NRC Accession Number ML21146A259.

5) FS1-0052486 Revision 4.0, 10 CFR 50.46 PCT Error Report for Brunswick Units 1 and 2 ATRIUM 11 Fuel, Framatome Inc., September 2021.

6) FS1-0060612 Revision 2.0, 10 CFR 50.46 PCT Error Report for Brunswick Units 1 and 2 ATRIUM 11 Fuel, Framatome Inc., February 2022

7) FS1-0040060 Revision 3.0, 10 CFR 50.46 PCT Error Report for Brunswick Units 1 and 2 for MELLLA+ Operation, Framatome Inc., December 2021.

8) Duke Letter RA-21-0051, Annual Report of Changes Pursuant to 10 CFR 50.46, Steve Snider to U.S. Nuclear Regulatory Commission, April 5, 2021, NRC Accession Number ML21096A005.

Page 4 of 6 RA-22-0028 A10XM Summary 10 CFR 50.46 Report for Brunswick Steam Electric Plant Units 1 and 2 Plant: Brunswick Steam Electric Plant, Units 1 and 2 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable):

Evaluation Model: EMF-2361(P)(A), Revision 0 EXEM BWR-2000 ECCS Evaluation Model, May 2001 Fuel: ATRIUM 10XM (A10XM)

A. Analysis of Record PCT 1923 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +2 °F 2 °F C. Baseline PCT for assessing new 1925 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. CR 2021-2025 corrections to

+0 °F RDX2_2_RDX4 E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + net E) 1925 °F Page 5 of 6 RA-22-0028 ATRIUM 11 LUA Summary 10 CFR 50.46 Report for Brunswick Steam Electric Plant Units 1 and 2 Plant: Brunswick Steam Electric Plant, Unit 2 Reporting Period: January 1, 2021 - March 31, 2021 (NOTE)

LOCA Analysis Type (if applicable):

Evaluation Model: EMF-2361(P)(A), Revision 0 EXEM BWR-2000 ECCS Evaluation Model, May 2001 Fuel: ATRIUM 11 (A11) Lead Use Assemblies (LUA)

A. Analysis of Record PCT 1762 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +2 °F 2 °F C. Baseline PCT for assessing new 1764 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None -

E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline 0 °F 0 °F PCT F. Licensing Basis PCT (C + net E) 1764 °F NOTE: ATRIUM 11 LUAs were no longer in use after March 31, 2021.

Page 6 of 6 RA-22-0028 ATRIUM 11 Summary 10 CFR 50.46 Report for Brunswick Steam Electric Plant Units 1 and 2 Plant: Brunswick Steam Electric Plant, Units 1 and 2 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable):

Evaluation Model: ANP-10332P-A, Revision 0 AURORA-B LOCA Evaluation Model, March 2019 Fuel: ATRIUM 11 (A11)

A. Analysis of Record PCT 1957 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported -82 °F 92 °F C. Baseline PCT for assessing new 1875 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. AUTOSR5BDK incorrect hot wall +3 °F effect temperature

2. S-RELAP5 cladding thermal +0 °F conductivity

3. Cladding Hydrogen content +0 °F

4. Cladding oxide thickness +0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+3 °F 3 °F PCT F. Licensing Basis PCT (C + net E) 1878 °F Page 1 of 6 RA-22-0028 ENCLOSURE 2: CNS 10 CFR 50.46 Annual Report Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 / Renewed License Nos. NPF-35 and NPF-52 Page 2 of 6 RA-22-0028 Summary of Errors Reported 10 CFR 50.46 Report for Catawba Units 1 and 2 General Code Maintenance Affected Evaluation Model: 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Various changes have been made to enhance the usability of codes and to streamline future analyses.

Examples of these changes include improving the input diagnostic checks; enhancing the code output; optimizing active coding; and eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451.

The nature of these changes leads to an estimated peak cladding temperature impact of 0°F.

Catawba Units 1 and 2 Reduction in Flow Area to the Bottom of the Barrel/Baffle Region Affected Evaluation Model: 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP For plants without holes in the edge of the lower core plate, the flow area from the bottom of the core to the barrel/baffle region has historically been modeled as the gap between the baffle plate and the lower core plate, and this flow area did not consider the reduced flow area due to the presence of the bottom nozzle flow skirt. The impact of reducing the flow area between the core and barrel baffle region due to including the bottom nozzle flow skirt has been qualitatively evaluated. This item represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

The evaluation determined that considering a reduced flow area from the bottom of the core to the barrel/baffle region when considering the bottom nozzle flow skirt has a negligible effect on the SBLOCA analysis results, leading to an estimated peak cladding temperature impact of 0°F for Catawba Units 1 and 2.

Page 3 of 6 RA-22-0028 10 CFR 50.46 Report for Catawba Unit 1 - Large Break LOCA Plant: Catawba Nuclear Station, Unit 1 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Large Break Evaluation Model: WCAP-12945-P-A, Revision 0 Code Qualification Document for Best Estimate LOCA Analysis Fuel: 17x17 RFA A. Analysis of Record PCT 2028 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +58 °F 378 °F C. Baseline PCT for assessing new 2086 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None 0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline 0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 2086 °F Page 4 of 6 RA-22-0028 10 CFR 50.46 Report for Catawba Unit 1 - Small Break LOCA Plant: Catawba Nuclear Station, Unit 1 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Small Break Evaluation Model: WCAP-10054-P-A, Revision 0 NOTRUMP Fuel: 17x17 RFA A. Analysis of Record PCT 1323 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +0 °F 0 °F C. Baseline PCT for assessing new 1323 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. Reduction in Flow Area to the +0 °F Bottom of the Barrel/Baffle Region E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 1323 °F Page 5 of 6 RA-22-0028 10 CFR 50.46 Report for Catawba Unit 2 - Large Break LOCA Plant: Catawba Nuclear Station, Unit 2 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Large Break Evaluation Model: WCAP-12945-P-A, Revision 0 Code Qualification Document for Best Estimate LOCA Analysis Fuel: 17x17 RFA A. Analysis of Record PCT 2028 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +42 °F 362 °F C. Baseline PCT for assessing new 2070 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 2070 °F Page 6 of 6 RA-22-0028 10 CFR 50.46 Report for Catawba Unit 2 - Small Break LOCA Plant: Catawba Nuclear Station, Unit 2 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Small Break Evaluation Model: WCAP-10054-P-A, Revision 0 NOTRUMP Fuel: 17x17 RFA A. Analysis of Record PCT 1243 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +0 °F 0 °F C. Baseline PCT for assessing new 1243 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. Reduction in Flow Area to the +0 °F Bottom of the Barrel/Baffle Region E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 1243 °F Page 1 of 5 RA-22-0028 ENCLOSURE 3: HNP 10 CFR 50.46 Annual Report Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 / Renewed License No. NPF-63 Page 2 of 5 RA-22-0028 Summary of Errors Reported 10 CFR 50.46 Report for Shearon Harris Unit 1 The results of the HNP LOCA reanalysis for GAIA fuel were reported to NRC in June 2021 via 30-Day 10 CFR 50.46 report per Reference 1. The HNP PCT changes due to implementation of the Cycle 24 LOCA analysis for GAIA fuel are carried over for the full 2021 calendar year. There are no new SBLOCA or LBLOCA analysis errors or changes applicable to HNP for the 2021 calendar year.

As of December 31, 2021, HNP was operating Cycle 24, which contains fresh GAIA fuel and once-burned 17x17 HTP fuel. Therefore the +50 °F PCT evaluation for once-burned HTP fuel in mixed cores of GAIA and HTP fuel using EMF-2103, Rev. 3 methodology will be retained on the PCT reporting sheet for the 2021 calendar year.

Reference

1. Duke Energy Letter RA-21-0164, Kim E. Maza to USNRC, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model, June 7, 2021

[NRC ADAMS Accession No. ML21158A091].

Page 3 of 5 RA-22-0028 10 CFR 50.46 Report for Shearon Harris Unit 1 - Large Break LOCA - GAIA Fuel Plant: Shearon Harris, Unit 1 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Large Break Evaluation Model: EMF-2103(P)(A), Revision 3 Realistic Large Break LOCA for PWRs Fuel: 17x17 GAIA A. Analysis of Record PCT 1820 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +0 °F 0 °F None C. Baseline PCT for assessing new 1820 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 1820 °F Page 4 of 5 RA-22-0028 10 CFR 50.46 Report for Shearon Harris Unit 1 - Large Break LOCA - HTP Fuel Plant: Shearon Harris, Unit 1 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Large Break Evaluation Model: EMF-2103(P)(A), Revision 3 Realistic Large Break LOCA for PWRs Fuel: 17x17 HTP A. Analysis of Record PCT 1820 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +50 °F 50 °F C. Baseline PCT for assessing new 1870 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 1870 °F Page 5 of 5 RA-22-0028 10 CFR 50.46 Report for Shearon Harris Unit 1 - Small Break LOCA Plant: Shearon Harris, Unit 1 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Small Break Evaluation Model: EMF-2328(P)(A), Rev. 0, and EMF-2328(P)(A), Rev. 0, Supplement 1, Rev. 0 PWR Small Break LOCA Evaluation Model Fuel: 17x17 GAIA and HTP A. Analysis of Record PCT 1832 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +0 °F 0 °F C. Baseline PCT for assessing new 1832 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 1832 °F Page 1 of 4 RA-22-0028 ENCLOSURE 4: MNS 10 CFR 50.46 Annual Report McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 / Renewed License Nos. NPF-9 and NPF-17 Page 2 of 4 RA-22-0028 Summary of Errors Reported 10 CFR 50.46 Report for McGuire Units 1 and 2 There are no new errors or changes that affect the McGuire SBLOCA or LBLOCA analyses of record for the 2021 calendar year.

General Code Maintenance Affected Evaluation Model: 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Various changes have been made to enhance the usability of codes and to streamline future analyses.

Examples of these changes include improving the input diagnostic checks; enhancing the code output; optimizing active coding; and eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451.

The nature of these changes leads to an estimated peak cladding temperature impact of 0°F.

Page 3 of 4 RA-22-0028 10 CFR 50.46 Report for McGuire Units 1 & 2 - Large Break LOCA Plant: McGuire Nuclear Station, Units 1 & 2 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Large Break Evaluation Model: WCAP-12945-P-A, Revision 0 Code Qualification Document for Best Estimate LOCA Analysis Fuel: 17x17 RFA A. Analysis of Record PCT 2028 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +58 °F 378 °F C. Baseline PCT for assessing new 2086 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 2086 °F Page 4 of 4 RA-22-0028 10 CFR 50.46 Report for McGuire Units 1 & 2 - Small Break LOCA Plant: McGuire Nuclear Station, Units 1 & 2 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Small Break Evaluation Model: WCAP-10054-P-A, Revision 0 NOTRUMP Fuel: 17x17 RFA A. Analysis of Record PCT 1323 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +0 °F 0 °F C. Baseline PCT for assessing new 1323 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 1323 °F Page 1 of 4 RA-22-0028 ENCLOSURE 5: ONS 10 CFR 50.46 Annual Report Oconee Nuclear Station, Units 1, 2 and 3 Docket Nos. 50-269, 50-270 and 50-287 Renewed License Nos. DPR-38, DPR-47 and DPR-55 Page 2 of 4 RA-22-0028 Summary of Errors Reported 10 CFR 50.46 Report for Oconee Units 1, 2, & 3 The ONS Large Break LOCA PCT changes due to implementation of the LBLOCA reanalysis for the impacts of fuel pellet thermal conductivity degradation (TCD) reported to the NRC in April 2021 via Reference 1, are carried over for the full 2021 calendar year.

Reference

1. Duke Energy Letter RA-21-0094, (S. Snider) to USNRC 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model, April 5, 2021.

[ADAMS Accession No. ML21096A007]

Page 3 of 4 RA-22-0028 10 CFR 50.46 Report for Oconee Units 1, 2, & 3 - Large Break LOCA Plant: Oconee Nuclear Station, Units 1, 2, & 3 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Large Break Evaluation Model: BAW-10192P-A, Revision 0, BWNT LOCA Evaluation Model for Once-Through Steam Generator Plants and BAW-10192PA, Revision 0, Supplement 1P-A, Revision 0 Fuel: 15x15 Mark-B-HTP A. Analysis of Record PCT; 1988 °F Reanalysis to fully incorporate fuel TCD, reported via ML21096A007 B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported N/A N/A C. Baseline PCT for assessing new 1988 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 1988 °F Page 4 of 4 RA-22-0028 10 CFR 50.46 Report for Oconee Units 1, 2, & 3 - Small Break LOCA Plant: Oconee Nuclear Station, Units 1, 2, & 3 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Small Break Evaluation Model: BAW-10192P-A, Revision 0, BWNT LOCA Evaluation Model for Once-Through Steam Generator Plants Fuel: 15x15 Mark-B-HTP A. Analysis of Record PCT 1598 °F Full Power - 100% FP B. Net Cumulative 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections

- Previously Reported +0 °F 0 °F C. Baseline PCT for assessing new changes for 1598 °F significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Error Net PCT Effect Absolute PCT Effect Corrections against Baseline PCT +0 °F 0 °F F. Licensing Basis PCT (C + E) 1598 °F A. Analysis of Record PCT 1480 °F Reduced Power - 50% FP B. Net Cumulative 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections

- Previously Reported +0 °F 0 °F C. Baseline PCT for assessing new changes for 1480 °F significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Error Net PCT Effect Absolute PCT Effect Corrections against Baseline PCT +0 °F 0 °F F. Licensing Basis PCT (C + E) 1480 °F Page 1 of 4 RA-22-0028 ENCLOSURE 6: RNP 10 CFR 50.46 Annual Report H. B. Robinson Steam Electric Plant, Unit 2 Docket No. 50-261 / Renewed License No. DPR-23 Page 2 of 4 RA-22-0028 Summary of Errors Reported 10 CFR 50.46 Report for H.B. Robinson Unit 2 There are no new errors or changes that affect the Robinson SBLOCA or LBLOCA analyses of record for the 2021 calendar year.

As of December 31, 2021, RNP was operating Cycle 33, which contains fresh W15-LC fuel and once-burned W15 HTP fuel. Therefore the +0 °F PCT evaluation for once burned HTP fuel in mixed cores of W15-LC and W15 HTP fuel using EMF-2103, Rev. 3 methodology will be retained for the 2021 reporting calendar year.

Page 3 of 4 RA-22-0028 10 CFR 50.46 Report for H.B. Robinson Unit 2 - Large Break LOCA Plant: H.B. Robinson, Unit 2 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Large Break Evaluation Model: EMF-2103(P)(A), Revision 3 Realistic Large Break LOCA for PWRs Fuel: W15-LC, W15 HTP A. Analysis of Record PCT 1771 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +0 °F 0 °F C. Baseline PCT for assessing new 1771 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 1771 °F Page 4 of 4 RA-22-0028 10 CFR 50.46 Report for H.B. Robinson Unit 2 - Small Break LOCA Plant: H.B. Robinson, Unit 2 Reporting Period: January 1, 2021 - December 31, 2021 LOCA Analysis Type (if applicable): Small Break Evaluation Model: EMF-2328(P)(A), Rev. 0 and EMF-2328(P)(A), Rev. 0, Supplement 1, Rev. 0 PWR Small Break LOCA Evaluation Model Fuel: W15-LC, W15 HTP A. Analysis of Record PCT 1538 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +0 °F 0 °F C. Baseline PCT for assessing new 1538 °F changes for significance (A + B)

D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None +0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline

+0 °F 0 °F PCT F. Licensing Basis PCT (C + E) 1538 °F