ML051790209

Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model, Covering the Time Period from January 1, 2004 to December 31, 2004

ML051790209
Person / Time
Site:	Oconee
Issue date:	06/21/2005
From:	Morris J Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML051790209 (6)

Text

JAMES R MORRIS

_ Duke Vice President, Nuclear Support rPowere Nuclear Generation Duke Power 526 South Church St.

Charlotte, NC 28202 Mailing Address:

EC07H / PO Box 1006 Charlotte, NC 28201-1006 June 21, 2005 704 382 6401 704 382 6056 fax U. S. Nuclear Regulatory Commission james.rnorris@duke-energy.com Washington, D. C. 20555-001 Attention: Document Control Desk

Subject:

Duke Energy Corporation 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

Reference:

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

"Safety Evaluation of Framatome Technologies Topical Report BAW-101 64P Revision 4, uRELAP5/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, 2004 to December 31, 2004.

During this time period, the steam generators were replaced in Unit 1 and Unit 2 along with modifications to the low pressure injection system (LPI). To address these plant modifications, the LOCA analyses were revised and thus the analysis of record for these two units was updated. 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). No other changes or error corrections were made to the evaluation model during this time period.

Included in this report are two summary tables. Table 1 provides a summary of the peak cladding temperatures for Units 1 and 2 while Table 2 provides the peak cladding temperature summary for Unit 3.

There are no regulatory commitments associated with this letter.

41Dd www. dukepower. corn

U.S. Nuclear Regulatory Commission June 21, 2005 Page 2 Please address any comments or questions regarding this matter to L. B. Jones at (704) 382-4753.

Very truly yours, James R. Morris Attachments Table 1 - Peak Cladding Temperature Summary - Oconee Units 1 and 2 Table 2 - Peak Cladding Temperature Summary - Oconee Unit 3 xc: (with attachments)

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 M. C. Shannon, NRC Senior Resident Inspector Oconee Nuclear Station

ATTACHMENTS Table 1 - Peak Cladding Temperature Summary - Oconee Units 1 and 2 Table 2 - Peak Cladding Temperature Summary - Oconee Unit 3

Table 1 Peak Cladding Temperature Summary - Oconee Units 1 and 2 LBLOCA PCT(OF) 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-B1 OT, 16.8 kW/ft At 4.264 ft elevation, 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-B11 OT SBLOCA PCT(OF) Comments Evaluation model: RELAP5/MOD2-B&W _

Analysis of record PCT 1461 Full Power 0.15 ft? 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 Page 1

Table 2 Peak Cladding Temperature Summary - Oconee Unit 3 LBLOCA PCT(PF) Comments Evaluation model: RELAP5/MOD2-B&W 2037 Mark-B1 1 (M5),16.8 kW/ft Analysis of record PCT At 6.021 ft elevation 2050 Mark-B13OT, 16.8 kWM At 4.264 ft elevation Prior Errors (APCT)

1. Containment press. correction -25 Reference A

2. BEACH inlet area correction +3 Reference A (only Mark-B1 OT)

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 2012 Mark-B11 l 2028 Mark-B1OT SBLOCA PCT( 0 F) Comments Evaluation model: RELAP5/MOD2-B&W Analysis of record PCT 1369 Full Power 0.15 ft2 break Prior errors (APCT)

1. Change from min to max CFT level 43 Reference B Note (1)

2. SG primary tube region drag model input error -14 Reference B

3. Limiting RCP type & two-phase degradation model(PSC 1-99) -5 Reference B

4. RELAP5 water property and Unix operating system -25 Reference B

5. Implementation of void-dependent cross flow model -12 Reference C 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 1356 Page 2

Table 2 (continued)

Peak Cladding Temperature Summary - Oconee Unit 3 SBLOCA PCT( 0 F) Comments Analysis of record PCT 1261 Reduced Power - 50% FP (1 HPI case) 0.06 f2 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 1261

References:

A) letter, W. R. McCollum, Jr. (Duke) to USNRC, "Report Pursuant to 10 CFR 50.46, Error Related to Application of the LBLOCA Evaluation Moder, May 26, 2004.

B) letter, M. S. Tuckman (Duke) to USNRC, "Report Pursuant to 10 CFR 50.46, Error Related to Application of the LBLOCA Evaluation Model", May 31, 2002.

C) letter, W. R. McCollum, Jr. (Duke) to USNRC, "Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model", May 19, 2003.

Note:

(1) In Reference B this PCT change was listed as an estimate since it was based on calculations using a model that was under review (void-dependent cross-flow model). Given that this model is now approved, the APCT value is no longer considered an estimate.

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