L-2002-014, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - Annual Report

Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - Annual Report

ML020450527
Person / Time
Site:	Turkey Point
Issue date:	01/24/2002
From:	Mcelwain J Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2002-014
Download: ML020450527 (3)

Text

0 P JAN 2 4 2002

• FPL L-2002-014 10 CFR §50.46 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" - Annual Report 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, 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 2001.

Should there be any questions, please contact Olga Hanek at 305-246-6607.

Very truly yours, J.n P*Mclwain ice President Turkey Point Plant OIH Attachment cc: NRC Regulatory Issue Summary 2001-05 waived the requirements that multiple copies of documents be submitted to the NRC.

A o-0 an FPL Group company

Attachment L-2002-014 Page 1 of 2 Small Break Loss of Coolant Accident (SBLOCA)

By letter L-2001-010, dated January 29, 2001, Florida Power and Light Company (FPL) reported a Peak Clad Temperature (PCT) of 1691'F 0

applicable for Unit 3, and a PCT of 1689 F applicable for Unit 4, for the SBLOCA transient analysis. There are no reported changes for the Turkey Point Units 3 and 4 SBLOCA PCT during 2001.

Larqe Break LOCA (LBLOCA)

By letter L-2001-010, dated January 29, 2001, FPL reported a PCT of 2105'F for the LBLOCA transient analysis. Since the last report, an 8°F PCT credit has been calculated as a result of the correction of a previous inconsistency in the way the core axial power distributions were verified for each reload. An alternate method using plant specific limit lines was developed to address the inconsistency. A 12 0 F PCT penalty has been calculated due to an error in the decay heat uncertainty calculation in the Monte Carlo code used to calculate the 95th percentile PCT for BELOCA. These changes are summarized in Table 1. Based on the above, a PCT of 2109°F for the LBLOCA is applicable for both units.

Summary 0

The PCT of 1691'F for Unit 3 and 1689 F for Unit 4 for the SBLOCA and the PCT of 2109°F for the LBLOCA, are below the 10 CFR 50.46 ECCS acceptance criteria limit of 2200'F. Turkey Point Units 3 and 4 remain in compliance with the Emergency Core Cooling System performance criteria specified in 10 CFR 50.46 (b).

Attachment L-2002-014 Page 2 of 2 TABLE 1 TURKEY POINT UNITS 3 AND 4 PREDICTED LBLOCA PEAK CLAD TEMPERATURE Total LBLOCA PCT reported in 2000 Annual Report 2105°F (FPL letter L-2001-010)

Evaluations Performed in 2001 Axial Power Distribution Inconsistency -8 0 F MONTECF Decay Heat Uncertainty Error +120 F Total Estimated LBLOCA PCT 2109OF