ML110400194

10 CFR 50.46 ECCS Evaluation Model Annual Report for 2010

ML110400194
Person / Time
Site:	Nine Mile Point
Issue date:	01/31/2011
From:	Joseph Pacher Constellation Energy Group, EDF Group, Nine Mile Point
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML110400194 (7)

Text

CENG.S a joint venture of P.O. Box 63 Lycoming, New York 13093 Conselatie l on n

Energy O0%"Zý NINE MILE POINT NUCLEAR STATION January 31, 2011 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Nine Mile Point Nuclear Station, LLC Unit Nos. 1 and 2; Docket Nos. 50-220 and 50-410 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2010 Pursuant to the reporting requirements of 10 CFR 50.46(a)(3)(ii), Nine Mile Point Nuclear Station, LLC (NMPNS) is submitting the Emergency Core Cooling System (ECCS) evaluation model annual reports for Nine Mile Point Unit I (NMP1) and Nine Mile Point Unit 2 (NMP2).

These annual reports, provided in Attachments I and 2, summarize the nature of and estimated effect of any changes or errors in the ECCS models for NMPI and NMP2 for the period January 1, 2010 through December 31, 2010.

Should you have any questions regarding this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.

Vyg truly yours, oseph E. Pacher Manager Engineering Services JEP/RJC Attachments: 1. Nine Mile Point Unit 1-10 CFR 50.46 ECCS Evaluation Model Annual Report for 2010

2. Nine Mile Point Unit 2-10 CFR 50.46 ECCS Evaluation Model Annual Report for 2010 cc: NRC Regional Administrator, Region I NRC Resident Inspector NRC Project Manager

ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2010 Nine Mile Point Nuclear Station, LLC January 31, 2011

ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2010 BACKGROUND In accordance with 10 CFR 50.46(a)(3)(ii), this annual report summarizes the nature of and estimated effect of any changes or errors in the Emergency Core Cooling System (ECCS) evaluation model for the period January 1, 2010 through December 31, 2010 for Nine Mile Point Unit I (NMPI).

DISCUSSION No changes or errors in the ECCS evaluation model were identified in 2010 for NMP 1.

IMPACT Not applicable CONCLUSION As documented in Table 1, the NMP1 Loss of Coolant Accident analysis Peak Cladding Temperature (PCT) remains in compliance with 10 CFR 50.46(b)(1), which requires that the PCT shall not exceed 2200 degrees F.

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ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2010 Table 1 LOCA Margin Summary Sheet Nine Mile Point Nuclear Station Nine Mile Point Unit 1 Evaluation Model: General Electric SAFER / GESTR - LOCA methodology Net Absolute PCT Effect PCT Effect A. Prior 10 CFR 50.46 Changes or Error Corrections - APCT = 0 OF 0 OF Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections - APCT = 0 OF 0 OF This Year Absolute Sum of 10 CFR 50.46 Changes APCT = 0 OF The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis is less than 2200 degrees F.

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ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2010 Nine Mile Point Nuclear Station, LLC January 31, 2011

ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2010 BACKGROUND In accordance with 10 CFR 50.46(a)(3)(ii), this annual report summarizes the nature of and estimated effect of any changes or errors in the Emergency Core Cooling System (ECCS) evaluation model for the period January 1, 2010 through December 31, 2010 for Nine Mile Point Unit 2 (NMP2).

DISCUSSION No changes or errors in the ECCS evaluation model were identified in 2010 for NMP2.

IMPACT Not applicable CONCLUSION As documented in Table 1, the NMP2 Loss of Coolant Accident analysis Peak Cladding Temperature (PCT) remains in compliance with 10 CFR 50.46(b)(1), which requires that the PCT shall not exceed 2200 degrees F.

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ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2010 Table 1 LOCA Margin Summary Sheet Nine Mile Point Nuclear Station Nine Mile Point Unit 2 Evaluation Model: General Electric SAFER / GESTR - LOCA methodology Net Absolute PCT Effect PCT Effect A. Prior 10 CFR 50.46 Changes or Error Corrections - APCT = 0 OF 0 OF Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections - APCT = 0 OF 0 OF This Year Absolute Sum of 10 CFR 50.46 Changes APCT = 0 OF The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis is less than 2200 degrees F.

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