ML070800557

Report Pursuant to 10 CFR 50.46, Changes to or Errors in ECCS Evaluation Model for January 1, 2005 - December 31, 2005

ML070800557
Person / Time
Site:	Oconee
Issue date:	03/13/2007
From:	Geer T Duke Energy Carolinas, Duke Power Co
To:	Document Control Desk, NRC/NRR/ADRO
References
TAC MA8465, TAC MA8468
Download: ML070800557 (4)

Text

Duke THOMAS Vice C.GEER President ore Energy. Nuclear Engineering Duke Energy Corporation 526 South Church St.

Charlotte, NC 28202 Mailing Address:

ECO8H / PO Box 1006 Charlotte, NC 28201-1006 March13, 2007 704 382 4712 704 382 7852 fax tcgeer@duke-energy.corn U. S. Nuclear Regulatory Commission Washington, D. C. 20555-001 Attention: Document Control Desk

Subject:

Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)

Oconee Nuclear Station, Units 1, 2, and 3 Docket Numbers 50-269, 50-270, and 50-287 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model

References:

1) Letter, L. W. Barnett (USNRC) to J. Mallay (Framatome ANP),

"Safety Evaluation of Framatome Technologies Topical Report BAW-10164P Revision 4, "RELAP5/MOD2-B&W, An Advanced Computer Program for Light Water LOCA and Non-LOCA Transient Analyses" (TAC Nos. MA8465 and 8468), April 9, 2002.

10 CFR 50.46 (a)(3)(ii) requires the reporting of changes to or errors in ECCS evaluation models (EM). This report covers the time period from January 1, 2005 to December 31, 2005.

Just prior to this time period, the steam generators were replaced in Unit 3 along with modifications to the low pressure injection system (LPI). To address these plant modifications for Unit 3's startup in early 2005, the LOCA analyses were revised and the analysis of record for Unit 3 was updated to be identical to the Unit 1 and Unit 2 analyses. The revised analyses were performed using a modification of the Framatome evaluation model incorporating Revision 4 of BAW-10164P-A which was approved by the NRC in 2002 (Reference 1). There were no other changes/errors to the EM.

Included in this report is a summary table of the peak cladding temperatures (PCT) for Units 1, 2, and 3.

There are no regulatory commitments associated with this letter.

www. duke-energy. com

U.S. Nuclear Regulatory Commission March 13, 2007 Page 2 This report is being submitted beyond the annual reporting requirement of 10 CFR 50.46. A licensee corrective action problem report (PIP G-07-0150) was issued to address the administrative failure to satisfy this requirement. This occurrence is currently being evaluated to identify appropriate corrective actions.

Please address any comments or questions regarding this matter to L. B. Jones at (704) 382-4753.

Sincerely, Thomas C. Geer Vice President, Nuclear Engineering Attachment Table 1 - Peak Cladding Temperature Summary - Oconee Units 1, 2, and 3 xc: (with attachment)

W. D. Travers, Region II Administrator U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center, 23 T85 61 Forsyth St., SW Atlanta, GA 30303-8931 L. N. Olshan, Senior Project Manager (ONS)

U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 D. W. Rich, NRC Senior Resident Inspector Oconee Nuclear Station

ATTACHMENT Table 1 - Peak Cladding Temperature Summary - Oconee Units 1, 2, and 3

Table 1 Peak Cladding Temperature Summary - Oconee Units 1, 2, and 3 LBLOCA PCT(°F) Comments Evaluation model: RELAP5/MOD2-B&W 2035 Mark-B11 (M5), 17.7 kW/ft Analysis of record PCT At 6.021 ft elevation 2028 Mark-B10T, Estimated based on the OTSG analysis Prior errors (APCT)

1. None 0 Prior evaluation model changes (APCT)

1. None 0 Errors (APCT)

1. None 0 Evaluation model changes (APCT)

1. None 0 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 2035 Mark-B11 2028 Mark-B10T SBLOCA PCT(oF) Comments Evaluation model: RELAP5/MOD2-B&W Analysis of record PCT 1461 Full Power -100% FP (2 HPI Case) 0.15 ft2 break Prior errors (APCT)

1. None 0 Prior evaluation model changes (APCT)

1. None 0 Errors (APCT)

1. None 0 Evaluation model changes (APCT)

1. None 0 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 1461 SBLOCA PCT(oF) Comments Analysis of record PCT 1774 Reduced Power - 75% FP (1 HPI case) 0.075 'ft2 break Prior errors (APCT)

1. None 0 Prior evaluation model changes (APCT)

1. None 0 Errors (APCT)

1. None 0 Evaluation model changes (APCT)

1. None 0 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 1774