L-2011-120, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 2010 Annual Report
| ML11130A092 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/26/2011 |
| From: | Kiley M Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2011-120 | |
| Download: ML11130A092 (3) | |
Text
WAPR 2 6 2011 FPL.
L-2011-120 POWERING TODAY.
10 CFR 50.46 EMPOWERING TOMORROW.1 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re:
Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors" - 2010 Annual Report
References:
- 1. Letter from Michael Kiley to US NRC Document Control Desk, 'Turkey Point Units 3 & 4, Dockets Nos. 50-250 and 50-251 10 CFR 50.46, 'Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors' - 2009 Annual Report," L-2010-074, April 15, 2010.
- 2. Letter from Michael Kiley to US NRC Document Control Desk, 'Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.46, 'Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors' - 30 Day Special Report,"
L-2010-231, October 19, 2010.
10 CFR 50.46(a)(3)(ii) requires that licensees report to the Commission at least annually the nature of changes to, or errors discovered in, the Emergency Core Cooling System (ECCS) evaluation models (EM), or in the application of such models that affect the peak clad temperature calculation and their effect on the limiting ECCS analysis. The attachment to this letter provides the Florida Power and Light Company (FPL) report for Turkey Point Units 3 and 4 for 2010.
FPL letter L-2010-074 (Reference 1), documented no changes in Peak Clad Temperature (PCT) for the Large Break Loss of Coolant Accident (LBLOCA) and no changes for the Small Break Loss of Coolant Accident (SBLOCA) during 2009 for Turkey Point Units 3 and 4. The LBLOCA PCT reported was 1986 OF, and the SBLOCA PCT reported was 1689 OF. The cumulative changes reported by L-2010-074 for the LBLOCA and SBLOCA were 271 OF and 105 OF, respectively.
10 CFR 50.46(a)(3)(ii) requires that changes to the LBLOCA Evaluation Model (EM) and SBLOCA EM PCT exceeding 50 OF have to be reported to the NRC within 30 days from its determination. FPL letter L-2010-231 (Reference 2), documented the impact on PCT due to Turkey Point mixed cores starting with Unit 3 Cycle 25 and Unit 4 Cycle 26 with the presence of 15X15 DRFA and 15X15 Upgrade fuel assemblies in these cores. There was no change in PCT for the SBLOCA. Therefore, the SBLOCA PCT of 1689 OF with a cumulative change of 105 OF remains unchanged. The mixed core penalty for LBLOCA was an increase of 12 OF in PCT with a resulting LBLOCA PCT of 1998 OF and a cumulative change of 283 OF.
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L-2011-120 Page 2 of 2 There were no changes in PCT for the SBLOCA and LBLOCA during 2010 other than the mixed core penalty discussed above. Attachment 1 provides the PCT cumulative changes for the LBLOCA and SBLOCA for Turkey Point Units 3 and 4.
10 CFR 50.46(a)(3)(ii) also requires that a schedule for reanalysis be provided or compliance with the requirements of the regulation be shown. Compliance with 10 CFR 50.46 requirements is demonstrated by the total estimated LBLOCA PCT of 1998 OF, and the SBLOCA PCT of 1689 OF, both remaining well below the limit of 2200 OF and by the total cumulative PCT changes having been calculated conservatively. Accordingly, a schedule for reanalysis is not required.
Should there be any questions, please contact Robert Tomonto, Licensing Manager, at 305-246-7327.
Very truly yours, Michael Kiley Vice President Turkey Point Nuclear Plant Attachment cc:
Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant
L-2011-120 Attachment 1 Page 1 of 1 Table 1 SBLOCA 2009 10 CFR 50.46 Annual Report (Ref. 1)
Peak Cladding Temperature 1689 OF Cumulative Chan1e 105 OF Errors in 2010
- Pellet Crack and Dish Volume Calculation
- Treatment of Vessel Average Temperature Uncertainty 0 OF 0 OF 0 OF 0 OF 2010 10 CFR 50.46 Annual Report 1689 OF 105 OF LBLOCA 2009 10 CFR 50.46 Annual Report (Ref. 1)
Mixed Core Assessment (Ref. 2)
- Transition Core (to Upgrade Fuel)*
Peak Cladding Temperature 1986 OF Cumulative Change 271 OF 12 OF 283 OF Errors in 2010 Treatment of Vessel Average Temperature Uncertainty 0 OF 0 OF 2010 10 CFR 50.46 Annual Report 1998 OF 283 OF Mixed core assessment applies to Unit 3 starting in Cycle 25 (November 2010) and to Unit 4 starting in Cycle 26 (projected to start May 2011).