ML14043A168

Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2013

ML14043A168
Person / Time
Site:	Nine Mile Point
Issue date:	01/30/2014
From:	Swift P Constellation Energy Nuclear Group, EDF Group, Nine Mile Point
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14043A168 (8)

Text

CENG a joint venture of Consteflation (

efEnergy* D NINE MILE POINT NUCLEAR STATION January 30, 2014 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 Docket Nos. 50-220 and 50-410 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2013 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 (NMP I) and Nine Mile Point Unit 2 (NMP2).

These annual reports, provided in Attachments 1 and 2, summarize the nature of and estimated effect of any changes or errors in the ECCS models for NMP 1 and NMP2 for the period January 1, 2013 through December 31, 2013.

Should you have any questions regarding this submittal, please contact Everett (Chip) Perkins, Director -

Licensing, at (315) 349-5219.

Sincerely, Paul M. Swift Manager - Engineering Services BTV/PMS Attachments: (1) Nine Mile Point Unit 1 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 (2) Nine Mile Point Unit 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 .- ,-7 Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093

Desk Document Control January 30, 2014 Page 2 Region I Administrator, cc: NRC Regional Inspector NRC Resident Manager NRC Project

ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2013 Nine Mile Point Nuclear Station, LLC January 30, 2014

ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2013 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) model for the period January 1, 2013 through December 31, 2013 for Nine Mile Point Unit 1 (NMP1).

DISCUSSION No changes or errors to the ECCS evaluation model were identified in 2013 for NMP 1.

IMPACT Not applicable.

CONCLUSION As documented in Table 1, the NMPI Loss of Coolant Accident analysis Peak Clad Temperature (PCT) remains in compliance with 10 CFR 50.46 (b)(1), which requires that the PCT shall not exceed 2200 'F.

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ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2013 Table 1 LOCA Margin Summary Sheet Nine Mile Point Nuclear Station, LLC Nine Mile Point Unit 1 Evaluation Model: General Electric SAFER / CORCL / GESTR methodology Net Absolute PCT Effect PCT Effect A. Prior 10 CFR 50.46 Changes or Error APCT = 0 OF 0 OF Corrections - Previous Years B. Prior 10 CFR 50.46 Changes or Error APCT = 0 OF 0 OF Corrections - 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 2013 Nine Mile Point Nuclear Station, LLC January 30, 2014

ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2013 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) model for the period January 1, 2013 through December 31, 2013 for Nine Mile Point Unit 2 (NMP2).

DISCUSSION No changes or errors to the ECCS evaluation model were identified in 2013 for NMP2.

IMPACT Not applicable.

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

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ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2013 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 - Previous Years

1. Notification 2011-02 (GEl4) APCT = 30 OF 30 OF

2. Notification 2011-03 (GE 14) APCT = -5 OF 5 OF

3. Notification 2012-01 (GE14) APCT = 0 OF 0 OF B. Prior 10 CFR 50.46 Changes or Error APCT = 0 OF 0 OF Corrections - This Year Absolute Sum of 10 CFR 50.46 Changes APCT = 35 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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