RA-18-0022, Carolinas, LLC (Duke Energy) - Annual Report of Changes Pursuant to 10 CFR 50.46

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Carolinas, LLC (Duke Energy) - Annual Report of Changes Pursuant to 10 CFR 50.46
ML18150A705
Person / Time
Site: Oconee, Mcguire, Catawba, Harris, Brunswick, Robinson, McGuire  Duke energy icon.png
Issue date: 05/24/2018
From: Donahue J
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-18-0022
Download: ML18150A705 (29)
v • d • e


Text

( , DUKE JOSEPH DONAHUE Vice President

<(;; ENERG~

Nuclear Engineering 526 S. Church Street, EC-07H Charlotte, NC 28202 980-373-1758 Joseph.Donahue@duke-energy.com 10 CFR 50.46 Serial: RA-18-0022 May 24, 2018 U.S. Nuclear Regulatory Attn: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 RENEWED LICENSE NOS. DPR-71 AND DPR-62 CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 RENEWED LICENSE NOS. NPF-35 AND NPF-52 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT 2 DOCKET NO. 50-261 RENEWED LICENSE NO. DPR-23 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 RENEWED LICENSE NOS. NPF-9 AND NPF-17 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 RENEWED LICENSE NO. NPF-63 OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 DOCKET NOS. 50-269, 50-270, 50-287 LICENSE NOS. DPR-38, DPR-47 AND DPR-55

Subject:

CAROLINAS, LLC (DUKE ENERGY)

ANNUAL REPORT OF CHANGES PURSUANT TO 10 CFR 50.46 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 time period from January 1, 2017 to December 31, 2017, for the Brunswick Steam Electric Plant, Catawba Nuclear Station, H. B. Robinson Steam Electric Plant, McGuire Nuclear Station, Shearon Harris Nuclear Power Plant and the Oconee Nuclear Station .

U.S. NRC May 24, 2018 Page 2 This document contains no regulatory commitments. Please refer any questions regarding this submittal to Mr. Art Zaremba at 980-373-2062.

Sincerely, Joseph Donahue Vice President - Nuclear Engineering

Enclosures:

1. Brunswick Steam Electric Plant, Units 1 and 2
2. Catawba Nuclear Station, Units 1 and 2
3. H. B. Robinson Steam Electric Plant, Unit 2
4. McGuire Nuclear Station, Units 1 and 2
5. Shearon Harris Nuclear Power Plant, Unit 1
6. Oconee Nuclear Station, Units 1, 2 and 3

U.S. NRC May 24, 2018 Page 3 xc (with Enclosures):

C. Haney, Regional Administrator U. S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 M.C. Barillas, Project Manager (SHNPP)

U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 D.J. Galvin, Project Manager (HBRSEP, Unit 2 and BSEP)

U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 Michael Mahoney, Project Manager (Catawba and McGuire)

U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Audrey Klett, Senior Project Manager (ONS)

U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 Gale Smith, NRC Senior Resident Inspector Brunswick Steam Electric Plant, Unit Nos. 1 and 2 J. Rotton NRC Senior Resident Inspector H.B. Robinson Steam Electric Plant, Unit No. 2 J. Zeiler NRC Senior Resident Inspector Shearon Harris Nuclear Power Plant, Unit 1

U.S. NRC May 24, 2018 Page 4 xc (with Enclosures; continued):

J.D. Austin NRC Senior Resident Inspector Catawba Nuclear Station G.A. Hutto NRC Senior Resident Inspector McGuire Nuclear Station E.L. Crowe NRC Senior Resident Inspector Oconee Nuclear Station Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 S.E. Jenkins Manager, Radioactive & Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.

Columbia, SC 29201 A.Gantt Chief, Bureau of Radiological Health (SC) 2600 Bull Street Columbia, South Carolina 29201

RA-18-0022 Page 1 of 4 Enclosure 1 Brunswick Steam Electric Plant, Units 1 and 2 A10 Summary A10XM Summary Atrium 11 Summary

RA-18-0022 Page 2 of 4 AlO Summary 10 CFR 50.46 Report for Brunswick Steam Electric Plant Units 1, and 2 Plant: Brunswick Steam Electric Plant, Unit 1 Reportinq Period : January 1, 2017- December 31, 2017 LOCA Analysis Type (if applicable):

Evaluation Model: EMF-2361(P)(A), Revision0 EXEM BWR-2000 ECCS Evaluation Model, May 2001 Fuel: ATRIUM-10 (A10)

A. Analysis of Record PCT 1904 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported 1 °F 1 °F C. Baseline PCT for assessing new changes for significance (A+ B) 1905 °F 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 PCT 0 °F 0 °F F. Licensinq Basis PCT (C + E) 1905 °F

RA-18-0022 Page 3 of 4 AlOXM Summary 10 CFR 50.46 Report for Brunswick Steam Electric Plant Units 1, and 2 Plant: Brunswick Steam Electric Plant, Units 1 and 2 ReportinQ Period : January 1, 2017 - December 31, 2017 LOCA Analysis Type (if applicable):

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

A. Analysis of Record PCT 1885 °F B. Net Cumulative 10CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +2 °F 2 °F C. Baseline PCT for assessing new changes for significance (A + B) 1887 °F D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. Transition from the DEC ALPHA 0 °F computing platform to a new LINUX based computing platform for the LOCA analysis (AREVA Report FS1-0028074,Revision 1.0).
2. Elimination of local peaking 0 °F history grouping in the HUXY analysis as a result of transitioning from the DEC ALPHA computing platform to a new LINUX based computing platform (AREVA Report FS1-0028074, Revision 1.0).

E. Sum of 10CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 1887 °F

RA-18-0022 Page 4 of 4 ATRIUM 11 Summary 10 CFR 50.46 Report for Brunswick Steam Electric Plant Units 1, and 2 Plant: Brunswick Steam Electric Plant, Unit 2 ReportinQ Period: January 1, 2017 - December 31, 2017 LOCA Analysis Type (if applicable):

Evaluation Model: EMF-2361(P)(A), RevisionO EXEM BWR-2000 ECCS Evaluation Model, May 2001 Fuel: ATRIUM 11 (A11)

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 0 °F 0 °F C. Baseline PCT for assessing new changes for significance (A+ B) 1762 °F 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 PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 1762 °F

RA-18-0022 Page 1 of 7 Enclosure 2 Catawba Nuclear Station, Units 1 and 2 General Code Maintenance Catawba Unit 1, Large Break LOCA Catawba Unit 1, Small Break LOCA Catawba Unit 2, Large Break LOCA Catawba Unit 2, Smail Break LOCA

RA-18-0022 Page 2 of 7 GENERAL CODE MAINTENANCE Affected Evaluation Model(s):

1996 Westinghouse Best Estimate Large Break LOCA 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 modifying input variable definitions, units and defaults; 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 ofWCAP-13451.

The nature of these changes leads to an estimated Peak Cladding Temperature (PCT) impact of O 0 P.

ERROR IN THE UPPER PLENUM FLUID VOLUME CALCULATION Affected Evaluation Model: 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP An error was found in the fluid volume calculation in the upper plenum where the support column outer diameter was being used instead of the inner diameter. The correction of this error lead to a reduction in the upper plenum fluid volume used in the Appendix K Small Break LOCA analyses. The corrected values represent a less than 1% change in the total RCS fluid volume and will be incorporated on a forward-fit basis, based on the evaluated impact on the current licensing basis analysis results. These changes represent a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

The differences in the upper plenum fluid volume are relatively minor and have been evaluated to have a negligible effect on small break LOCA analysis results, leading to an estimated PCT impact of 0 op, INCONSISTENT APPLICATION OF NUMERICAL RAMP APPLIED TO THE ENTRAINED LIQUID/VAPOR INTERFACIAL DRAG COEFFICIENT Affected Evaluation Model: 1996 Westinghouse Best Estimate Large Break LOCA A numerical ramp which was used to account for the disappearance of the entrained liquid phase was applied to the entrained liquid/ vapor interfacial drag coefficient. The numerical ramp was applied such that the interfacial drag coefficient used in the solution of the entrained liquid and vapor momentum equations was not consistent. WCOBRA/TRAC was updated to apply the numerical ramp prior to usage of the interfacial drag coefficient in the momentum equations, such that a consistent interfacial drag coefficient was used in the entrained liquid and vapor momentum equations. This item represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

Based on the code validation results, the impact of correcting the error is estimated to have a O 0 P impact on PCT.

RA-18-0022 Page 3 of 7 INAPPROPRIATE RESETTING OF TRANSVERSE LIQUID MASS FLOW Affected Evaluation Model: 1996 Westinghouse Best Estimate Large Break LOCA In the WCOBRA/TRAC routine which evaluates the mass and energy residual error of the time step solution, the transverse liquid mass flow is reset as the liquid phase disappears. The routine is updated to remove the resetting of the transverse liquid mass flow since the routine is to only evaluate the residual error based on the time step solution values. This item represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

Based on the code validation results and limited applicability of the logic removed, correcting the error is estimated to have a O°F impact on PCT.

RA-18-0022 Page 4 of 7

~ 01 CFIR 5'0 ..46 Report: fo*li Catawbai Unit 1 - Large, B'reak LOCA Plant: Caiavroa Nu:cleali Sta~ion, Un.it 1 Reootrtin.Q Period : Jlarill!J!arv 1,, 2017- Decemb:eli 3 1, 2017 lOCA Analysis Type (if applicable): large Breaik Evaluation Model :

WCAP-12945-P-A, Revision 0 Code Qualification Document for Best Estimate l OCA Analysis Fuel : 17x17 RFA A. Analysis of Recor,d PCT 2028 °F B. Net Cumulative 10CFR 50.46 Net PCT Effect Absolute PCT Effeel Changes and Error Corrections

- Previously Reported +58 °F 378 °F C. Baseline PCT for assessing new changes for significance (A + B) 2086 °F D. Cumulative 10CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None 0 °F E. Sum of 10CFR 50 .46 Changes and Net PCT Effect
  • Absolute PCT Effect Error Corrections against Baseline PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 2086 °F

RA-18-0022 Page 5 of 7 10 CFR 50.416, Repoliti for Catiawba, Un1iti 1 - Small Break LOCA Plant Calawbai N11.tcle:ar Stiation, Unit 1 Repoli1i111g Period : Jlanuary 1, 2017 - Decemberi 311, 2017 lOCA Analysis Type (if applicable): Small Break Evaluafon Model : WCAP-10054-P-A, Revision 0 NOTRUMP Fuel : 17xH RFA A. Analysis of Record PCT 132.3 °F B . Net Cumulative 10CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

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

RA-18-0022 Page 6 of 7 10 Cf'R: 5'0 ..46 Repe>rtfor Catawba l!Jlniti 2 - Lalige, Break LOCA Plant Ca1awba1N1.ccle,a ri Station, Unit 2 Reoorting Period : Jlanuiarv 1, 2017 - December 3:1, 2017 lOCA Analysis Type (if applicable): l arge Break Evaluation Model :

WCAP-12945-P-A , Revision 0 Code Qual ification Document for Best Estimate LOCA Analysis 17x17 RFA Fuel:

A A 111alysis. of Record PCT 2028 °F B. Net Cumulative 10CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +42 °F 362 °F C. Baseline PCT for assessing new changes for significance (A+ B) 2070 °F D. Cumulative 10CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None 0 °F E. Sum of 10CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline PCT 0 °F 0 °F F. Licensinq Basis PCT (C + E) 2070 °F

RA-18-0022 Page 7 of 7 10' CFR 5.0.416, R*epoli1! for Catawba Unit 2' -

  • Smaill B,reak LOCA Plant: Caiawba Nuclear Station , Unit 2 Reporting Period : JlalilJl!..llaJy 1, 2011 - Decembeli 3.1. 2017 l OCA Anialys.is Type (if applicable): Smail! Break Evaluation Model :

WCAP-10054-P-A, Revision 0 NOTRUMP Fuel : 17x17 RFA A. Analysis of Record PCT 1243 °F B. Net Cumulative 10CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Repor1ed +O °F 0 °F C. Baseline PCT for assessing new changes for significance (A+ B) 1243 °F D. Cumulative 10 CFR 50.46 Chang:e s 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 PCT 0 °F 0 Of F. Licensing Basis PCT (C + E) 1243 °F

RA-18-0022 Page 1 of 3 Enclosure 3 H. B. Robinson Unit 2 H. B. Robinson Unit 2 - Large Break LOCA H. B. Robinson Unit 2 - Small Break LOCA

RA-18-0022 Page 2 of 3 10 CF*R 50.46 Report foll' H. B,. Robinson Uni:t 2 - lalige B,lieak LOCA

+

Plant: H. B. Robinson , Unit 2 Reporting Period : January 1, 2017 - December 31, 2017 LOCA Ana lysis Type (if applicable}: Large Break Evaluation Model: EMF-2103(P)(A }, Revision 0 Rea listic Large Break LOCA for PWR.s Fuel: 15x15HTP A. Ana lysis of Record PCT 2084 °F B. Net Cumu lative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +4 °F 24 °F C. Baseline PCT for assessing new changes for significance (A + B) 2088 °F D. Cumu lative 10 CFR 50 .46 Changes and Error Corrections

- This Reporting Pe riod

1. None E. Sum of 10 CFR 50 .46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections aga inst Base line PCT 0 °F 0 °F F. Licens ing Bas is PCT (C + E) 2088 °F

RA-18-0022 Page 3 of 3 10 Cf'*R 50 . 46 Re*pO*lit fO*li 1H . B,. Rolt> ElilSO n IUniit: 2 - Sm aimBlieal:c ILOCA

+

Plant: H. B. Robinson , Unit 2 Reporting Period : January 1, 2017 - December 31, 2017 LOCA Analysis Type (if applicable}: Small Break Evaluation Model: EMF-2328(P}(A}, Revision O PWR Small Break LOCA Evaluation Model Fuel: 15x15 HTP A Analysis of Record PCT 1492 °F B. Net Cumulative 10 CFR 50 .46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +60 °F 98 °F C. Baseline PCT for assessing new changes for sign ificance (A + B) 1552 °F D. Cu mu lative 10 CFR 50 .46 Changes and Error Corrections

- This Reporting Pe riod

1. Estimate of impact due to MS 0 °F LOCA swelling and rupture mode l update
2. Estimate of error in oxidation 0 °F calcu lations due to use of cold cladd ing dimens ions E. Sum of 10 CFR 50 .46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections aga inst Base line PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 1552 °F

RA-18-0022 Page 1 of 5 Enclosure 4 McGuire Nuclear Station, Units 1 and 2 General Code Maintenance McGuire Units 1 and 2, Large Break LOCA McGuire Units 1 and 2, Small Break LOCA

RA-18-0022 Enclosure 4 Page 2 of 5 GENERAL CODE MAINTENANCE Affected Evaluation Model(s):

1996 Westinghouse Best Estimate Large Break LOCA 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 modifying input variable definitions, units and defaults; 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 ofWCAP-13451.

The nature of these changes leads to an estimated Peak Cladding Temperature (PCT) impact of O 0 P.

ERROR IN THE UPPER PLENUM FLUID VOLUME CALCULATION Affected Evaluation Model: 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP An error was found in the fluid volume calculation in the upper plenum where the support column outer diameter was being used instead of the inner diameter. The correction ofthis error lead to a reduction in the upper plenum fluid volume used in the Appendix K Small Break LOCA analyses. The corrected values represent a less than 1% change in the total RCS fluid volume and will be incorporated on a forward-fit basis, based on the evaluated impact on the current licensing basis analysis results. These changes represent a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

The differences in the upper plenum fluid volume are relatively minor and have been evaluated to have a negligible effect on small break LOCA analysis results, leading to an estimated PCT impact of 0 op_

INCONSISTENT APPLICATION OF NUMERICAL RAMP APPLIED TO THE ENTRAINED LIQUID/VAPOR INTERFACIAL DRAG COEFFICIENT Affected Evaluation Model: 1996 Westinghouse Best Estimate Large Break LOCA A numerical ramp which was used to account for the disappearance of the entrained liquid phase was applied to the entrained liquid / vapor interfacial drag coefficient. The numerical ramp was applied such that the interfacial drag coefficient used in the solution of the entrained liquid and vapor momentum equations was not consistent. WCOBRA/TRAC was updated to apply the numerical ramp prior to usage of the interfacial drag coefficient in the momentum equations, such that a consistent interfacial drag coefficient was used in the entrained liquid and vapor momentum equations. This item represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

Based on the code validation results, the impact of correcting the error is estimated to have a O 0 P impact on PCT.

RA-18-0022 Page 3 of 5 INAPPROPRIATE RESETTING OF TRANSVERSE LIQUID MASS FLOW Affected Evaluation Model: 1996 Westinghouse Best Estimate Large Break LOCA In the WCOBRA/TRAC routine which evaluates the mass and energy residual error of the time step solution, the transverse liquid mass flow is reset as the liquid phase disappears. The routine is updated to remove the resetting of the transverse liquid mass flow since the routine is to only evaluate the residual error based on the time step solution values. This item represents a Non-Discretionary Change in accordance with Section 4.1.2 ofWCAP-13451.

Based on the code validation results and limited applicability of the logic removed, correcting the error is estimated to have a O °F impact on PCT.

RA-18-0022 Page 4 of 5 10 CfR 50 .46 Repo,r tfoli McGuire Units 1 & 2 - large B,lieak l OCA Plant: McGuire Nuclear Station, Units 1 & 2 Reporting Period : January 1, 2017 - December 31, 2017 LOCA Analysis Type (if applicable): Large Brea k Evaluation Model:

WCAP-12945-P-A, Re vision 0 Code Qualification Docu ment for Best Estimate LOCA Ana lysis Fuel: 17x17 RFA A. Analysis of Record PCT 2028 °F B. Net Cumu lative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +58 °F 378 °F C. Base line PCT for assess ing new changes for sign ificance (A + B) 2086 °F D. Cumu lative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Pe riod

1. None 0 °F E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Base line PCT 0 °F 0 °F F. Licens ing Basis PCT {C + E) 2086 °F u

RA-18-0022 Page 5 of 5 10 CFR 50.46 Repollt foli McG uire Units 1 & 2 - Sma ll B,lieak l OCA Plant: McGuire Nuclear Station, Units 1 & 2 Reporting Period : January 1, 2017 - December 31, 2017 LOCA Analysis Type (if applicable }: Small Break Evaluation Model:

WCAP-10054-P-A, Revision 0 NOTRU MP Fuel: 17x17 RFA A Analysis of Record PCT 1323 °F B. Net Cu mu lative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +O °F 0 °F C. Baseline PCT for assessing new changes for significance (A + B) 1323 °F D. Cu mulative 10 CFR 50 .46 Changes and Error Corrections

- This Reporting Pe riod

1. None 0 °F E. Su m of 10 CFR 50 .46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline PCT 0 °F 0 °F F. Licens ing Basis PCT {C + E) 1323 °F

RA-18-0022 Page 1 of 3 Enclosure 5 Shearon Harris Unit 1 Shearon Harris Unit 1 - Large Break LOCA Shearon Harris Unit 1 - Small Break LOCA

RA-18-0022 Page 2 of 3 10 CFR 50 .46 Re,port fOli SlhealiOlil Haliliiis Uni:t 1 - lalige Blieal!c lOCA Plant: Shearon Harris , Unit. 1 R.eporting Period : January 1, 2017 - December 31, 2017 LOCA Analysis Type (if applicable}: Large Break Eva luation Model: EMF-2 103(P)(A}, Revision 0 Realistic Large Break LOCA for PWRs Fuel: 17x17 HTP A. Analysis of Record PCT 1935 °F B. Net Cumu lative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +138 °F 138 °F C. Baseline PCT for assessing new changes for significance (A+ B) 2073 °F D. Cumu lative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. Estimate of impact due to MS 0 °F LOCA swe lling and rupture mode l update
2. Estimate of error in oxidation +22 °F calcu lations due to use of cold cladd ing dimensions E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections aga inst Base line PCT +22 °F 22 °F F. Licens ing Basis PCT (C + E) 2095 °F

RA-18-0022 Page 3 of 3 10 CfR 50.46 Report fOli SlhealiOlil Halili[iS Unit 1 - Small Break lOCA Plant Shearon Harris , Unit 1 Reporting Period: January 1, 2017 - December 31, 2017 LOCA Analysis Type (if applicable): Sma ll Break.

Evaluation Model: EMF-232&(P)(A ), Revision 0 PWR Small Break LOCA Evaluation Model Fue l: 17x17HTP A. Analysis of Record PCT 1664 °F 8 . Net Cumu lative 10 CFR 50 .46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Report.ad +49 '"F 49 °F C. Baseline PCT for assessing new changes for significance (A + B) 1713 °F D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. Estimate of impact due to MS 0 °F LOCA swe lling and rupture mode l update
2. Estimate of error in oxidation +14 °F ca lcu lations due to use of cold cladd ing dimens ions E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Base line PCT +14 °F 14 °F F. Licensing Bas is PCT (C + E) 1727 °F

RA-18-0022 Page 1 of 3 Enclosure 6 Oconee Nuclear Station, Units 1, 2 and 3 Oconee Units 1, 2 and 3, Large Break LOCA Oconee Units 1, 2 and 3, Small Break LOCA

RA-18-0022 Page 2 of 3 1OCIFR 50 ..416 R*eport:for Oconee Uniit s 1,, 2 1, & 3 - large Break ILOCA (1 of 2)

Plant: Oconee Nuclear Station, Units 1, 2, & 3 Reporting Period: January 1, 2017 - December 31, 2017 LOCA Analysis Type {if applicable): Larqe Break Evaluation Model: BAW-10192P-A, Revision 0, BW NT LOCA Evaluation Model for Once-Through Steam Generator Plants Fuel: 15x1 5 Mark-B-HTP A A nalysis of Record PCT 1852 Of B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +2 Of 858 °F C. Baseline PCT for assessing new changes for significance (A+ B) 1854 Of D. Cumulative 10CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. MS LOCA Swelling and Rupture 0 °F Model Update, Estimated
  • E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 1854 °F

RA-18-0022 Page 3 of 3 10 CFR' 5'.0 ..416 Report for Ocon;ee IIJni~s 1 v 2v& 3 - Smallll Br~k ILOCA (2 of 2)

Plant Oconee Nuclear S1ation, Uni1s 1, 2. & 3 Reporting Period: January 1, 2017 - December 31, 2017 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: 15x1 5 Mark-B-HTP A. Analysis of Record PCT 1598 "F fu n Power- 100% FP 8 . 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 changes for significance (A + B) 1598 °F D. Cumulative 10CFR 50.46 Changes and Error Corrections

-This Reporting Period 0 °F

1. MS LOCASwelling and Rupture Model Update, Estimated E. Sum of 10CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 1598 °F A A n a lys is of Record PCT 1480 °F I Reduced Power - 50% FP B . N et C u m ulative 1 O CFR 50.46 N et PCT Effect Absolute PCT Effect C h a nges a nd E rro r Correctio ns

- P revio us ly Reporte d +0 °F 0 °F C . Baseline PCT for assessing ne w c h a nges for s ig nificance (A+ B ) 1480 °F D . Cumulative 10 CFR 50.46 Cha nges a nd E rro r Correctio n s

- This Repo rting Period 0 °F 1 . M S LOCA Sw e lling a nd R upt ure M odel Update, Estimated E. S um of 1 O CFR 50.46 C ha nges a nd N e t PCT Effect Absolute PCT Effect E rror Correctio ns against Baseline PCT 0 °F 0 °F F . Lice ns inQ Basis PCT (C + E) 1480 °F

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