Text

Duke Energy Annual Report of Changes Pursuant to 10 CFR 50.46
	ML16152A104
Person / Time
Site:	Oconee, Mcguire, Catawba, Harris, Brunswick, Robinson, McGuire
Issue date:	05/31/2016
From:	Elnitsky J; Duke Energy Carolinas, Duke Energy Progress
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RA-16-0025
	Download: ML16152A104 (29)
	v • d • e

(_~ DUKE John Elnitsky 526 South Church Street ENERGY Charlotte, NC 28202 Mailing Address:

Mail Code EC07H I P.O. Box 1006 Charlotte, NC 28201-1006 704-382-4371 10 CFR 50.46 Serial: RA-16-0025 May 31, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington , DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 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 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 I RENEWED LICENSE NOS. NPF-9 AND NPF-17 OCONEE NUCLEAR STATION, UNIT NOS. 1, 2 AND 3 DOCKET NOS. 50-269, 50-270 AND 50-287 I RENEWED LICENSE NOS. DPR-38, DPR-47 AND DPR-55 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400 I RENEWED LICENSE NO. NPF-63 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 I RENEWED LICENSE NO. DPR-23

SUBJECT:

DUKE ENERGY ANNUAL REPORT OF CHANGES PURSUANT TO 10 CFR 50.46 Pursuant to 10 CFR 50.46 (a)(3)(ii), Duke Energy Progress, Inc. and Duke Energy Carolinas, LLC, collectively referred to hence forth as 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 ending December 31, 2015, 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. Rebaselining of the Annual 10 CFR 50.46 Reports submission dates for the respective sites allows Duke Energy the flexibility of submitting one consolidated 10 CFR 50.46 report.

U.S. Nuclear Regulatory Commission May 31, 2016 Page 2 This document contains no regulatory commitments. Please refer any questions regarding this submittal to Mr. Art Zaremba at 980-373-2062.

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. Nuclear Regulatory Commission May 31, 2016 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 Andrew Hon, Project Manager (Brunswick)

U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Michael D. Orenak, Project Manager (Catawba)

U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 G. Edward Miller, Project Manager (McGuire)

V. Sreenivas (temporary Project Manager)

U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 Martha Barillas, Project Manager (Harris)

U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Dennis Galvin, Project Manager {Robinson)

U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 R. Hall, Project Manager (Oconee)

U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 Michelle P. Catts NRC Senior Resident Inspector Brunswick Nuclear Plant

U.S. Nuclear Regulatory Commission May 31, 2016 Page4 xc (with Enclosures; continued):

G.A. Hutto, Ill NRC Senior Resident Inspector Catawba Nuclear Station John Zeiler NRC Senior Resident Inspector McGuire Nuclear Station J.D. Austin NRC Senior Resident Inspector Harris Nuclear Plant Kevin Ellis NRC Senior Resident Inspector Robinson Nuclear Plant E.L. Crowe NRC Senior Resident Inspector Oconee Nuclear Station Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

U.S. Nuclear Regulatory Commission May 31, 2016 Page 5 bxc (with Enclosures):

M.C. Nolan A.H. Zaremba A. Young M.C. Handrick K. Nolan S.B. Thomas D.C. Culp D.A. Cummings ELL File: (Corporate)

W.R. Gideon L.J. Grzeck W.R. Murray (For BSEP Licensing/Nuclear Records)

K. Henderson C.A. Fletcher NCMPA PMPA NC EMC CNS Master File 801.01 - CN04DM T. S. Lowery (For CNS Licensing/Nuclear Records)

S.L. Batson C.J. Wasik P.C. Metler (For ONS Licensing/Nuclear Records)

ONS Master File 801.01 - ON03DM M.R. Glover M.S. Connelly C.A. Caudell (For RNP Licensing/Nuclear Records)

S.D. Capps J.N. Robertson MNS Master File 801.01 - MG02DM K. L. Crane (For MNS Licensing/Nuclear Records)

B.C. Waldrep J.R. Caves Christine Magner (For HNP Licensing/Nuclear Records Files)

RA-16-0025 Page 1of4 Enclosure 1 Brunswick Steam Electric Plant, Units 1 and 2 A10 Summary A10XM Summary Atrium 11 Summary

RA-16-0025 Page 2 of 4 AtO Summary 10 CFR 50.46 Report for Brunswick Steam Electric Plant Units 1, and 2 Plant: Brunswick Steam Electric Plant, Unit 1 Reporting Peri od: August 6, 20 15 - December 31, 2015 LOCA Analysis Tvoe (if aoolicable):

Evaluation Model: EMF -236 1(P)(A), Revision O EXEM BWR-2000 ECCS Evalu ation Model, Mav 2001 Fuel: ATRIUM-10 (A 10)

A. An alysis 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. Basel ine PCT for assessing new changes or significance (A + B) 1900 °F D. Cumulative 10 CFR 50.46 Changes and Error Correctio s

- This Reporting Period

1. None -

E. Sum of 10 CFR 50-46 Changes and Net PCT Effect Absolute PCT Effect rror Corrections aga inst Baseline PCT 0 °F 0 °F F. licensina Basis PCT CC + E) 1905 °F

RA-16-0025 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 Reporting Period: August 6, 20 15 - December 31, 2015 LOCA Analysis T ype (if aoolicable):

Evaluation Model: EMF-236 1(P)(A), Revision 0 EXEM BWR-2000 ECCS Evaluation Model, May 2001 Fuel: ATRIUM 10XM (A 10XM)

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 N/A* N/A*

C. Baseline PCT for assessing ew changes or signi cance (A + B) 1885 °F0 D. Cumulative 10CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. Impl ementation of ACE correlation +2 °F in RELAX error (

Reference:

AREVA Report FS 1-0020025, Revision 2. 0)

2. Evaluation of the effect of 0 °F expo su r~depen dent thermal oonductivity degradation

(

Reference:

AREVARepor FS1-0020025. Revision 2.0)

E. Sum of 10 CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect Error Corrections against Baseline PCT 2 °F 2 "F F. Licensin q Basis PCT (C + E) 1887 °F

A LOCA re-analysis establishing a new Analysis of Record PCT of 1885 °F was performed during this reporting period (

Reference:

AREVA Report ANP-2943(P), Revision 3).

RA- 16-0025 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 Reporting Period: August 6, 20 15 - December 31 , 2015 LOCA Analysis Type (if aoolicable):

Evaluation Model: EMF-236 1(P)(A) , Revision 0 EXEM BWR-2000 ECCS Evaluation Model, May 2001 Fuel: ATRIUM 11 (A 11 )

A Analysis of Record PCT 1762 °F 8 . Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported 0 °F 0 °F C. Basel ine PCT for assessing 1 ew changes for significance (A + 8 ) 1762 °F D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None --

E. Sum of 10CFR 50.46 Changes and et PCT Effect Absolute PCT Effect Error Corrections against Baseli e PCT 0 °F 0 °F F. Licensina Basis PCT (C + El 1/62 °F

RA-16-0025 Page 1 of 6 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, Small Break LOCA

RA-16-0025 Page 2of6 GENERAL CODE MAINTENANCE Affected Evaluation Models: 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 of WCAP-13451.

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

INCORRECT LOWER SUPPORT PLATE UNHEATED CONDUCTOR INPUT Affected Evaluation Model: 1996 Westinghouse Best Estimate Large Break LOCA An error in the wetted perimeter input for the lower support plate unheated conductor was discovered in the Catawba and McGuire Units 1 and 2 Best-Estimate Large Break Loss-of-Coolant Accident (BE LBLOCA) analysis-of-record (AOR). A wetted perimeter 3.5% lower than the calculated value was inadvertently input in the analysis. This error was evaluated to estimate the impact on the Catawba/McGuire BE LBLOCA analysis. The primary impact of this error is an underestimation of the lower support plate metal heat transfer area. The resolution of this issue represents a Non-Discretionary Change in the application of the Evaluation Model as described in Section 4.1.2 ofWCAP-13451.

This error was evaluated to have a negligible impact on the existing analysis, leading to an estimated Peak Cladding Temperature (PCT) impact of 0°F for Catawba and McGuire Units 1 and 2.

DISCREPANCY IN WETTED PERIMETER INPUTS Affected Evaluation Model: 1996 Westinghouse Best Estimate Large Break LOCA An inconsistency was discovered in the wetted perimeter inputs in the upper head region of the Catawba Units 1 and 2 and McGuire Units 1 and 2 Best-Estimate Large Break Loss-of-Coolant Accident (BE LBLOCA) analysis-of-record (AOR). An evaluation of the impact was performed on the current licensing-basis analysis results. The resolution of this issue represents a Non-Discretionary Change in the application of the Evaluation Model as described in Section 4.1.2 of WCAP-13451.

This error was evaluated to have a negligible impact on the Large Break LOCA analysis results, leading to an estimated Peak Cladding Temperature (PCT) impact of 0°F for Catawba Units 1 and 2 and McGuire Units 1 and 2.

RA-16-0025 Page 3 of 6 10 CFR 50.46 Report for Catawba Unit 1 - Large Break LOCA Plant: Catawba Nuclear Station, Unit 1 Reporting Period: January 1, 2015- December 31, 2015 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 changes for significance (A + B) 2070 °F D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. MUR Uprate to 101.7% of 3411 +16 °F MWt E. Sum of 10 CFR 50.46 Changes Net PCT Effect Absolute PCT Effect and Error Corrections against Baseline PCT +16 °F 16 °F F. LicensinQ Basis PCT (C + E) 2086 °F

RA-16-0025 Page 4 of 6 10 CFR 50.46 Report for Catawba Unit 1 - Small Break LOCA Plant: Catawba Nuclear Station, Unit 1 Reporting Period: January 1, 2015 - December 31, 2015 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 +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 Net PCT Effect Absolute PCT Effect and Error Corrections against Baseline PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 1323 °F

RA-16-0025 Page 5 of 6 10 CFR 50.46 Report for Catawba Unit 2 - Large Break LOCA Plant: Catawba Nuclear Station, Unit 2 Reporting Period: January 1, 2015 - December 31, 2015 LOCA Analysis Type (if applicable): Large Break Evaluation Model: WCAP-12945-P-A, RevisionO 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 changes for significance (A + B) 2070 °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 Net PCT Effect Absolute PCT Effect and Error Corrections against Baseline PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 2070 °F

RA-16-0025 Page 6of6 10 CFR 50.46 Report for Catawba Unit 2 - Small Break LOCA Plant: Catawba Nuclear Station, Unit 2 Reporting Period: January 1, 2015 - December 31, 2015 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 +O °F 0 °F C. Baseline PCT for assessing new changes for significance (A + B) 1243 °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 Net PCT Effect Absolute PCT Effect and Error Corrections against Baseline PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 1243 °F

RA-16-0025 Page 1of3 Enclosure 3 H. B. Robinson Unit 2 H. B. Robinson Unit 2 - Large Break LOCA H. B. Robinson Unit 2 - Small Break LOCA

RA-16-0025 Page 2 of 3 10 CFR 50.46 Report for H. 8. Robinson Unit 2 - Large Break LOCA Plant H. B. Robinson . Unit 2 Reoortina P*eriod: October 26. 2015 - December 3 1. 2015 LOCA Anatvsis T voe (if aoolicable): Lar<e.Je Break Evaluation Model: EMF-2103(P)(A). RevisionO Realistic Large B~eak LOCA for P\/\IRs Fuel: 15x15 HTP A Analysis of Rec*ord PCT 2084 °F B. Net Cumulative 10 CFR 50.46 Nlet PCT Eff*ect Absolute PCT Effect Changes and 111or Corrections

- Previously Reported +4 . 24 "F C. Baseline PCT for assessing new changes for significance (A + B) 2088 .

D. Cumulative 10 CFR 50.46 Changes an d Error Corrections

- This Reporting P*eriod

1. Err.or in pt1Ner *cutback rati os for 0 °F once-burned ga doli nia bearing fue l r*ods E. Sum *of 10CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect E111or Correcti ons against Baseline PCT 0. o*

F. licensing Basis PCT (C + E) 2088 *r

RA-16-0025 Page 3 of 3 10 CFR 50.46 Repprt for H.B. Robinson Unit 2- Small Break LOCA Plant: H.B . Ro~n son , Unlt 2 Reporting Period: October 26 . 2015 - December 31

2015 LOCA Analysis Tvpe (if applicable): Small Break Evaluation Model: EMF-2328(P)(A). Revision 0 PWR Small Break LOCA Evaluation Model Fuel: 15x15 HTP A. Analysis of Record PCT 1492 °F B. Net C m lative 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 significance (A + B) 1552 °F D. Cumulative 10 CFR 50 .46 Cha ges 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 o ~r F. Licensing Basis PCT (C + E) 1552 °F

RA-16-0025 Page 1of4 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-16-0025 Page 2of4 GENERAL CODE MAINTENANCE Affected Evaluation Models: 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 of WCAP-13451.

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

INCORRECT LOWER SUPPORT PLATE UNHEATED CONDUCTOR INPUT Affected Evaluation Model: 1996 Westinghouse Best Estimate Large Break LOCA An error in the wetted perimeter input for the lower support plate unheated conductor was discovered in the Catawba and McGuire Units 1 and 2 Best-Estimate Large Break Loss-of-Coolant Accident (BE LBLOCA) analysis-of-record (AOR). A wetted perimeter 3.5% lower than the calculated value was inadvertently input in the analysis. This error was evaluated to estimate the impact on the Catawba/McGuire BE LBLOCA analysis. The primary impact of this error is an underestimation of the lower support plate metal heat transfer area. The resolution of this issue represents a Non-Discretionary Change in the application of the Evaluation Model as described in Section 4.1.2 ofWCAP-13451.

This error was evaluated to have a negligible impact on the existing analysis, leading to an estimated Peak Cladding Temperature (PCT) impact of 0°F for Catawba and McGuire Units 1 and 2.

DISCREPANCY IN WETTED PERIMETER INPUTS Affected Evaluation Model: 1996 Westinghouse Best Estimate Large Break LOCA An inconsistency was discovered in the wetted perimeter inputs in the upper head region of the Catawba Units 1 and 2 and McGuire Units 1 and 2 Best-Estimate Large Break Loss-of-Coolant Accident (BE LBLOCA) analysis-of-record (AOR). An evaluation of the impact was performed on the current licensing-basis analysis results. The resolution of this issue represents a Non-Discretionary Change in the application of the Evaluation Model as described in Section 4.1.2 of WCAP-13451.

This error was evaluated to have a negligible impact on the Large Break LOCA analysis results, leading to an estimated Peak Cladding Temperature (PCT) impact of 0°F for Catawba Units 1 and 2 and McGuire Units 1 and 2.

RA-16-0025 Page 3 of 4 10 CFR 50.46 Report for McGuire Units 1 & 2 - Large Break LOCA Plant: McGuire Nuclear Station, Units 1 & 2 Reporting Period: January 1, 2015 - December 31, 2015 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 changes for significance (A + B) 2086 °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 Net PCT Effect Absolute PCT Effect and Error Corrections against Baseline PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 2086 °F

RA-16-0025 Page 4of4 10 CFR 50.46 Report for McGuire Units 1 & 2 - Small Break LOCA Plant: McGuire Nuclear Station, Units 1 & 2 Reporting Period: January 1, 2015 - December 31, 2015 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 +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 Net PCT Effect Absolute PCT Effect and Error Corrections against Baseline PCT 0 °F 0°F F. Licensing Basis PCT (C + E) 1323 °F

RA-16-0025 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-16-0025 Page 2 of 3 10 CFR 50A6 Report for Shearon Harris Unit 1 - Lar*g e Break LOCA Plant Shearon Harris

Unit 1 Reporting Period: Aoril 9. 2015 - December 3 1, 2015 LOCA Analvsis T voe {if annlicable\: Larae B~e.ak Evaluation Model: EMF-2103(P)(A ), RevisionO Realistic Lar*ge Br*eak LOCA for PWRs Fuet. 17x 17 HTP A. Analysis *of Record PCT 1935 °F B. Net Cumulative 10CFR 50.46 Net PCT Effect Absolute PCT Effed:

Changes and !Tor Corrections

- Previously Reported +138 . 138 ° C. Baseline P CT f or assessing new changes for significance (A+ B) 2073 ° D. Cumulative 10 CFR 50.46 Changes and rror Corrections

- This Reporting Period

1. Err.or in power *cutback ratios for () OF once-burned gadolinia bearing fuel r.ods E. Sum of 10CFR 50.46 Changes and Net PCT Effect Absolute PCT Effed:

Error Corrections against Basetine PCT '° * '°

F . Licensing Basis PCT (C + E) 2073 °F

RA-16-0025 Page 3 of 3 110 CFR 50.46 Report for Shearon Harris Unit 1 - Small Break LOCA Plant Shearon Harris

Unit 1 Reportino Period: Aoril 9.20115 - December 31 . 2015 LOCA Anatvsis Tvoe (if annlicable\: SmaU Break Evaluation Model: EMF-2328(P)(A), Revision 0 PWR Small Break LOCA va luation Model Fuel: 17x17 HTP A. Analysis of ~ecorn PCT 1664 °F B. Net Cumulative 10 CFR 50-46 Net PCT Effect Absolute PCT Effect Changes and rror Corrections

~ Previously Reported +17 0 17 ° C. Baseline PCT for assessi!YJ new changes for significance (A+ B) 168 1 ° D. Cumulative 10CFR 50.46 Changes and rror Correcti ons

- This Reporting Period

1. None E. Sum of 10CFR 50.46 Changes and Net PCT Effect Absolute PCT Effect rror Corrections against Bas,eUne PC '°

0 0 F - Licensino Basis PCT (C + F\ 1881 °F

RA-16-0025 Page 1of4 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-16-0025 Page 2of4 10 CFR 50.46 Report for Oconee Units 1, 2, & 3 - Large Break LOCA (1of2)

Plant: Oconee Nuclear Station, Units 1, 2, & 3 Reporting Period: January 1, 2015 - December 31, 2015 LOCA Analysis Type (if applicable): LarQe Break Evaluation Model: BAW-10192P-A, RevisionO, BWNT LOCA Evaluation Model for Once-Through Steam Generator Plants Fuel: 15x15 Mark-B-HTP A Analysis of Record PCT 1852 °F B. Net Cumulative 10 CFR 50.46 Net PCT Effect Absolute PCT Effect Changes and Error Corrections

- Previously Reported +2 °F 858 °F C. Baseline PCT for assessing new changes for significance (A + B) 1854 °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 Net PCT Effect Absolute PCT Effect and Error Corrections against Baseline PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 1854 °F

RA-16-0025 Page 3 of 4 10 CFR 50.46 Report for Oconee Units 1, 2, & 3 -Small Break LOCA (2 of 2)

Plant: Oconee Nuclear Station, Units 1, 2, & 3 Reportina Period: January 1, 2015 - December 31, 2015 LOCA Analysis Type (if applicable): Small Break Evaluation Model: BAW-10192P-A, RevisionO, 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 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) 1598 °F D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None E. Sum of 10 CFR 50.46 Changes Net PCT Effect Absolute PCT Effect and Error Corrections against Baseline PCT 0 °F 0 °F F. Licensing Basis PCT (C + E) 1598 °F

RA-16-0025 Page 4 of 4 10 CFR 50.46 Report for Oconee Units 1, 2, & 3-Small Break LOCA (2 of 2 continued)

A. Analysis of Record PCT 1480 °F Reduced Power - 50% FP B. Net Cumulative 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) 1480 °F D. Cumulative 10 CFR 50.46 Changes and Error Corrections

- This Reporting Period

1. None E. Sum of 10 CFR 50.46 Changes Net PCT Effect Absolute PCT Effect and Error Corrections against Baseline PCT 0°F 0 °F F. Licensing Basis PCT (C + E) 1480 °F