RA-15-0047, Annual Report of Changes Pursuant to 10 CFR 50.46

Annual Report of Changes Pursuant to 10 CFR 50.46

ML15321A021
Person / Time
Site:	Robinson
Issue date:	11/17/2015
From:	Nolan M Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-15-0047
Download: ML15321A021 (3)

Text

M. Christopher Nolan

( -, DUKE 526 South Church Street ENERGY~

Charlotte, NC 28202 Mailing Address:

Mail Code EC2ZF /P.O. Bax 1006 Charlotte, NC 28201-1006 704-382-7426 November 17, 2015 RA-15-0047 10 CFR 50.46 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 H.B. Robinson Steam Electric Plant, Unit No. 2 Docket Nos. 50-261 I Renewed License Nos. DPR-23

Subject:

Annual Report of Changes Pursuant to 10 CFR 50.46 Pursuant to 10 CFR 50.46(a)(3)(ii), Duke Energy Progress, Inc. hereby submits the enclosed annual report of changes to and errors discovered in the loss of coolant accident analyses for the H. B. Robinson Steam Electric Plant, Unit No. 2, for the period October 22, 2014, through October 26, 2015.

This document contains no regulatory commitments. Please refer any questions regarding this submittal to Art Zaremba at (980) 373-2062.

Sincerely,

~~

M. Christopher Nolan Director Nuclear Regulatory Affairs

Enclosure:

1) Annual Report of Changes Pursuant to 10 CFR 50.46

U.S. Nuclear Regulatory Commission November 17, 2015 Page2 xc:

USNRC, Region II, 245 Peachtree Center Avenue, NE., Suite 1200, Atlanta, GA 30303-1257.

Martha Barillas, NRC Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Dennis Galvin, NRC Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Kevin Ellis NRC Senior Resident Inspector

RA-15-0047 Page 1 of 1 ENCLOSURE 1 Annual Report of Changes Pursuant to 10 CFR 50.46 10 CFR 50.46 REPORT FOR H. B. ROBINSON, UNIT 2 This report provides an estimate of the effect on peak cladding temperature (PCT) of changes and error corrections in the Loss-of-Coolant Accident (LOCA) evaluation models (EMs) for the Emergency Core Cooling System (ECCS) at the H. B. Robinson Steam Electric Plant, Unit No. 2, covering the period of October 22, 2014 through October 26, 2015.

Large Break Loss-of-Coolant Accident (LBLOCA) Evaluation Model CHANGED CONDITION PCT IMPACT c°Fl Change in Robinson pressurizer pressure range from 2205 - 0 2285 psio to 2195 - 2285 osio (FAB 15-00063)

Cumulative Impact 0 Small Break Loss-of-Coolant Accident (SBLOCA) Evaluation Model CHANGED CONDITION PCT IMPACT °F Change in Robinson pressurizer pressure range from 2205 - 0 2285 si to 2195 - 2285 si FAB 15-00063 .

0 PEAK CLADDING TEMPERATURE ESTIMATES The current PCT estimates associated with LOCA ECCS EMs are listed below. These estimates include the cumulative effects of significant and non-significant error corrections and evaluation model changes through October 26, 2015.

EVENT PCT (°F}

LBLOCA, ECCS Injection Mode 2088 SBLOCA, ECCS Injection Mode 1552

M. Christopher Nolan

( -, DUKE 526 South Church Street ENERGY~

Charlotte, NC 28202 Mailing Address:

Mail Code EC2ZF /P.O. Bax 1006 Charlotte, NC 28201-1006 704-382-7426 November 17, 2015 RA-15-0047 10 CFR 50.46 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 H.B. Robinson Steam Electric Plant, Unit No. 2 Docket Nos. 50-261 I Renewed License Nos. DPR-23

Subject:

Annual Report of Changes Pursuant to 10 CFR 50.46 Pursuant to 10 CFR 50.46(a)(3)(ii), Duke Energy Progress, Inc. hereby submits the enclosed annual report of changes to and errors discovered in the loss of coolant accident analyses for the H. B. Robinson Steam Electric Plant, Unit No. 2, for the period October 22, 2014, through October 26, 2015.

This document contains no regulatory commitments. Please refer any questions regarding this submittal to Art Zaremba at (980) 373-2062.

Sincerely,

~~

M. Christopher Nolan Director Nuclear Regulatory Affairs

Enclosure:

1) Annual Report of Changes Pursuant to 10 CFR 50.46

U.S. Nuclear Regulatory Commission November 17, 2015 Page2 xc:

USNRC, Region II, 245 Peachtree Center Avenue, NE., Suite 1200, Atlanta, GA 30303-1257.

Martha Barillas, NRC Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Dennis Galvin, NRC Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Kevin Ellis NRC Senior Resident Inspector

RA-15-0047 Page 1 of 1 ENCLOSURE 1 Annual Report of Changes Pursuant to 10 CFR 50.46 10 CFR 50.46 REPORT FOR H. B. ROBINSON, UNIT 2 This report provides an estimate of the effect on peak cladding temperature (PCT) of changes and error corrections in the Loss-of-Coolant Accident (LOCA) evaluation models (EMs) for the Emergency Core Cooling System (ECCS) at the H. B. Robinson Steam Electric Plant, Unit No. 2, covering the period of October 22, 2014 through October 26, 2015.

Large Break Loss-of-Coolant Accident (LBLOCA) Evaluation Model CHANGED CONDITION PCT IMPACT c°Fl Change in Robinson pressurizer pressure range from 2205 - 0 2285 psio to 2195 - 2285 osio (FAB 15-00063)

Cumulative Impact 0 Small Break Loss-of-Coolant Accident (SBLOCA) Evaluation Model CHANGED CONDITION PCT IMPACT °F Change in Robinson pressurizer pressure range from 2205 - 0 2285 si to 2195 - 2285 si FAB 15-00063 .

0 PEAK CLADDING TEMPERATURE ESTIMATES The current PCT estimates associated with LOCA ECCS EMs are listed below. These estimates include the cumulative effects of significant and non-significant error corrections and evaluation model changes through October 26, 2015.

EVENT PCT (°F}

LBLOCA, ECCS Injection Mode 2088 SBLOCA, ECCS Injection Mode 1552