RA-15-0030, Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2014 for Oconee Nuclear Station, Units 1, 2, and 3

Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2014 for Oconee Nuclear Station, Units 1, 2, and 3

ML15188A430
Person / Time
Site:	Oconee
Issue date:	07/07/2015
From:	Martin L Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-15-0030
Download: ML15188A430 (5)

Text

(~ DUKE Leo A. Martin ENERGY. Vice President (acting)

Nuclear Engineering 526 S. Church Street Charlotte, NC 28202 Mailing Address:

EC07C I P.O. Box 1006 Charlotte, NC 28201-1006 980-373-9364 704-382-4541 fax Serial: RA-15-0030 10 CFR 50.46 July 7, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oconee Nuclear Station, Units 1, 2, and 3 Docket Numbers 50-269, 50-270, and 50-287 Renewed Operating License Nos. DPR-38, DPR-47, and DPR-55

Subject:

Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2014 for Oconee Nuclear Station, Units 1, 2, and 3 10 CFR 50.46 (a)(3)(ii) requires the reporting of changes to or errors in Emergency Core Cooling System (ECCS) evaluation models (EMs). This report covers the time period from January 1, 2014 to December 31, 2014 for the Oconee Nuclear Station (ONS). Attached are the Loss of Coolant Accident (LOCA) Peak Cladding Temperature (PCT) margin summary tables for Oconee Units 1, 2, and 3. There are no new regulatory commitments contained in this letter.

Please address any comments or questions regarding this matter to Michael K. Leisure at (980} 373-3619 (Mike.Leisure@duke-energy.com}.

Sincerely, Leo A. Martin Vice President (acting)

Nuclear Engineering

Attachment:

2014 Annual Report of Peak Cladding Temperature

U.S. Nuclear Regulatory Commission RA-15-0030 Page2 xc (with attachment):

V. M. McCree Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. R. Hall NRC Project Manager (ONS)

U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8G9A 11555 Rockville Pike Rockville, MD 20852-2738 Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station

U.S. Nuclear Regulatory Commission RA-15-0030 Attachment Page 1 of 3 Attachment Duke Energy Carolinas, LLC Oconee Nuclear Station, Units 1, 2, and 3 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors 2014 Annual Report of Peak Cladding Temperature Table 1: LOCA Peak Cladding Temperature Margin Summary- Oconee Units 1, 2, and 3

U.S. Nuclear Regulatory Commission RA-15-0030 Attachment Page 2 of 3 Table 1 LOCA Peak Cladding Temperature Margin Summary- Oconee Units 1, 2, and 3 LBLOCA PCT(°F) Comments Evaluation model: RELAP5/MOD2-B&W Analysis of record PCT 1852 References A, 8 2.506-ft MOL case Prior 10 CFR 50.46 Changes or Error Corrections (LlPCT) References A, 8

1. Transient fuel pellet thermal conductivity degradation +2 (considered a change in the application of the evaluation model)

2. PCT increase due to higher initial fuel average +428 ReferenceD temperatures when fuel pellet thermal conductivity degradation is considered. ReferenceD

3. PCT decrease due to MOL linear heat rate penalty -428 of 2 kW/ft at all core elevations.

Current 10 CFR 50.46 Changes or Error Corrections (LlPCT)

1. None Final licensing basis PCT 1854 SBLOCA Full Power -100% FP PCT(°F) Comments Evaluation model: RELAP5/MOD2-B&W Analysis of record PCT 1598 References A, 8 (2 HPI Case) 0.15 ft2 break Prior 10 CFR 50.46 Changes or Error Corrections (tlPCT) ReferenceD

1. Updated uncertainty to account for TCD in 0 TAC03/GDTACO Current 10 CFR 50.46 Changes or Error Corrections (LlPCT)

1. None Final licensing basis PCT 1598 SBLOCA Reduced Power [1] PCTCOF) Comments Analysis of record PCT N/A Reported under a separate LAR (Reference C)

Prior 10 CFR 50.46 Changes or Error Corrections (LlPCT) N/A Current 10 CFR 50.46 Changes or Error Corrections N/A (LlPCT)

Final licensing basis PCT N/A Operation Not Justified [2]

Notes

1. Partial power SBLOCA analysis with one HPI pump out of service, supports 30 day LCO forTS 3.5.2 Condition B. Also supports TS 3.5.2 Condition C1 and C2.

2. Pending review and approval of separate LAR. Refer to Reference C for additional details.

U.S. Nuclear Regulatory Commission RA-15-0030 Attachment Page 3 of 3 References for Table 1:

A) Letter, G. D. Miller (Duke Energy) to USNRC, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model, December 16, 2013 (ML13353A137)

B) Letter, B. C. Waldrep (Duke Energy) to USNRC, 10 CFR 50.46- Annual Report for 2013 for Oconee Nuclear Station, Units 1, 2, and 3, July 7, 2014 (ML14205A280)

C) Letter, S. L. Batson (Duke Energy) to USNRC, License Amendment Request (LAR) to Reduce Allowed Maximum Rated Thermal Power When High Pressure Injection (HPJ)

Equipment is Inoperable- License Amendment Request No. 2013-03, June 30,2014 (ML14184B384)

D) Letter RA-14-0032, E. J. Kapopoulos Jr. (Duke Energy) to USNRC, 10 CFR 50.46 30-Day Report for Oconee Nuclear Station, Units 1, 2, and 3; Estimated Impacts to Peak Cladding Temperature due to Fuel Pellet Thermal Conductivity Degradation, December 17, 2014 (ML14353A214).