LIC-06-0044, Annual Report for 2005 Loss of Coolant Accident Loca/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46

Annual Report for 2005 Loss of Coolant Accident Loca/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46

ML061150277
Person / Time
Site:	Fort Calhoun
Issue date:	04/12/2006
From:	Faulhaber H Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-06-0044
Download: ML061150277 (4)

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UYYU Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 April 12,2006 LIC-06-0044 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 I

References:

1. Docket 50-285 I

I 2. XN-NF-82-49(P)(A), Supplement 1, "Exxon Nuclear Company I Evaluation Model Revised EXEM PWR Small Break Model,"

Revision 1, December 1994

3. EMF-2087(P)(A), "SEWPWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Revision 0, June 1999

4. Letter from OPPD (R. L. Phelps) to NRC (Document Control Desk), "Annual Report for 2004 Loss of Coolant Accident (L0CA)lEmergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46," dated April 22,2005 (LIC-05-0045)

Subject:

Annual Report for 2005 Loss of Coolant Accident L0CA)IEmergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46 In accordance with 10 CFR 50(46)(a)(3)(ii), the Omaha Public Power District (OPPD) is submitting the annual 10 CFR 50.46 summary report for 2005. This summary report updates all identified changes or errors in the LOCMECCS codes, methods, and applications used by PLREVA (formerly Framatome ANP) to model Fort Calhoun Station, Unit No. 1 (FCS). References 2 and 3, respectively, describe the Small Break (SB) and Large Break (LB) LOCA analysis methodology used by AREVA for the FCS Analysis of Record.

OPPD has received the 2005 AREVA 10 CFR 50.46 Annual Notification Report for the SB and LB LOCA Analyses that are subject to the reporting requirements of 10 CFR 50.46. For 2005, there were no SB or LB LOCA Analysis Peak Clad Temperature (PCT) 10 CFR 50.46 Model Assessment errors.

Attachment 1 provides the 2005 SB LOCA PCT Margin Utilization Summary for FCS, which is unchanged from the 2004 Annual Report (Reference 4). The value of the PCT remains at 1864OF.

Employment with Equal Opportunity

U. S. Nuclear Regulatory Commission LIC-06-0044 Page 2 provides the 2005 LB LOCA PCT Margin Utilization Summary for FCS, which is unchanged from the 2004 Annual Report (Reference 4). The value of the PCT remains at 1954OF.

In summary, the FCS PCT values for SB and LB LOCA remain less than the 10 CFR 50.46(b) (1) acceptance criteria of 2200°F.

If you should have any questions, please contact Tom Matthews at (402) 533-6938. No commitments are made to the NRC in this letter.

Division Manager Nuclear Engineering Attachments:

1. FCS Small Break LOCA PCT Margin Utilization Summary

2. FCS Large Break LOCA PCT Margin Utilization Summary

LIC-06-0044 Fort Calhoun Station Small Break LOCA 2005 Peak Clad Temperature Margin Utilization Summary LICENSING BASIS Clad Temperature (OF)

Analysis of Record 1865 MARGIN ALLOCATIONS (APCT)

A. Prior Permanent ECCS Model Assessments -1 B. 2005 10 CFR 50.46 Model Assessments 0 (Permanent Assessments of PCT Margin)

LICENSING BASIS PCT + MARGIN ALLOCATIONS 1864

LIC-06-0044 Fort Calhoun Station Large Break LOCA 2005 Peak Clad Temperature Margin Utilization Summary LICENSING BASIS Clad Temperature ( O n Analysis of Record 1956 MARGIN ALLOCATIONS (APCT)

A. Prior Permanent ECCS Model Assessments -2 B. 2005 10 CFR 50.46 Model Assessments 0 (Permanent Assessments of PCT Margin)

LICENSING BASIS PCT + MARGIN ALLOCATIONS 1954