LIC-07-0034, Annual Report for 2006 Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46

Annual Report for 2006 Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46

ML071170467
Person / Time
Site:	Fort Calhoun
Issue date:	04/25/2007
From:	Faulhaber H Omaha Public Power District
To:	Document Control Desk, NRC/NRR/ADRO
References
LIC-07-0034
Download: ML071170467 (5)

Text

April 25,2007 LIC-07-Om4 U. S. Nuclear Regulatory Commission Am:Document Control Desk Wwhhgton, D. C . 20555

Reference:

Docket 50-285

Subject:

hnusrl Report for 2006 Loss af Coolamt Accident (LQCA)/Emergency Core G w h g System (ECCS) Models Pursuant to 10 CFR 50.46 In accordance with 10 CFR 50(46)(a)(3)(ii), the Omaha Public Bower District (OPPD) is submitting the annual 10 CFR 50.46 s m a r y report for 2006, This summary report updabs all identified changes or errors in the LOCAIECCS codes, methods, and applications used by W A (formerly Framatome ANT) to model Fort Calhoun Station, Unit No. 1 (FCS). References 1 and 2 (see list of references on page 3) 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 2006 AREVA 10 CFR 50.46 Annual Notification Rqort for the SB and LB LOCA Analyses fiat we subject to the reporting reiquirments of 10 CFR 59.46. For 2006, there were no SB or LB LQCA Analysis Peak Clad Temperature (PCT) 10 CFR 50.46 Model Assessment errors. There was one 10 CFR 50.59 Model Assesmmt change for the LB LOCA Analysis PCT. provides the 2006 SB LOCA PCT Margin Utilization Slunmary for FCS.

The SB LOCA analysis was redone in 2006 to support the fuel design change w h h utilized M5 cladding, grids, and guide tubes. The use of M5 at FCS was approved by the NRC in References 4 and 5. The SB LOCA methodology used in this analysis was approved by the NRC in Reference 6. The value of the PCT for the new d y s i s of record is 1537 T . provides the 2006 LB LOCA PCT Margin Utilization S m a r y for FCS.

The LB LOCA analysis was also redone in 2006 in support of the M5 fuel design changes. This reanalysis utilized the AREVA Realistic LB LOCA methodology which was approved for use in References 7 and 8. There has been one change to the previously

U.S. Nuclear Regulatory Commission LIC-07-0034 Page 2 reported PCT as a result of Cycle 24 neutronic parameter changes. The value of the PCT is now 1636°F.

In summary, the FCS PCT values for SB and LB LOCA remain less than the 10 CFR 50.46@) (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.

Sincerely, Division Manager Nuclear Engineerin$

Attachmmh:

1. FCS SmdI Break LOCA PCT Margin Utilization Summary

2. FCS Large Break LOCA PCT Margin Utili&n Summary

U. S. Nuclear RRgdatory Commission LIC-07-0034 Page 3 References

1. EMF-2328(P) (A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAPS Based," F m t o m e M ,Inc. March 2001

2. EMF-2103(P)(A), Revision 0, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Framatome ANP, Inc. April 2003

3. Letter from OPPD (H. J. Faulhaber) to NRC (Document Control Desk), "Annual Report for 2005 Loss o f Coolant Accident (LOCA)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46," dated April 12,2006 (LIC-06-0044)

4. Letter from NRC (A. B. Wang) to OPPD (R.T. Ridenoure), "Issuance of Amendment: Use of M5 Fuel Cladding," dated August 30,2006

5. Letter from NRC (A. B. Wang) to OPPD (R. T. Ridenoure), "Correction to the Safety Evaluation for the Issuance of Amendment Re: Use of M5 Fuel Cladding,"

dated September 18,2006

6. Letter from WRC (A. B. Wmg) to OPPD (R. T. Ridenoure), "Issuance of Amendment RE: Addition of Topical Report References to TS 5.9.5, Core Operating Limits Report," dated March 4,2002

7. Letter from NRC (A. B. W a g ) to OPPD (R. T. Ridenoure), "Issuance of Amendment Re: Use of Areva NP,hc, Realistic Large Break hss-of-Coolant-Accident Methodology," dated November 3,2006

8. Letter h m NRC (A. B. W a g ) to OPPD (R. T. Ridenome), "Correction to the Safkty Evaluation Regarding Issuance of Amendment Re: Use of Areva NP,k c ,

Realistic Large Break Loss-of-Coolant-Accident Methodology,'" dated December 4,2006

UC-07-01034 A*ha 1 Page 1 Fort Calhoun Station S d Break LOCA 2006 Peak Clad Temperature Margin Utilization Summary LICENSING BASIS Clad Temperature 0 F2 Analysis of Record 1537 MARGIN ALLOCATIONS (APCT)

A. Prior Permanent ECCS Model Asgesisments B. 2006 10 CFR 50.46 Model Asawsmeab (Ferment Assessmeents of PCT Margin)

LICENSING BASIS PCT + MARGIN ALLOCATIONS

Fort Cdhoun Shdon Large Break LOCA 2006 Peak Clad Temperature Margin Utilization Summary LICENSING BASIS Clad Temperature cq Analysis of Record 1675 MARGXN AL,LOCATIONS (bPCT)

A. Prior Permanent ECCS Model Assessments B. 2906 10 CFR 50.46 Model Assessments (Permanent Assessments of PCT Margin)

6. 2006 10 CFR 50.59 Model Assessments LICENSING BASIS PCT + MARGIN ALLOCATIONS