ML080320151

CFR 50.46 ECCS Evaluation Model Annual Reports for 2007

ML080320151
Person / Time
Site:	Nine Mile Point
Issue date:	01/31/2008
From:	Laughlin G Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML080320151 (8)

Text

P.O. Box 63 Lycoming, NY 13093 January 31, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Document Control Desk

Subject:

Nine Mile Point Nuclear Station, LLC Unit No.1 ; Docket No. 50-220; License No. DPR-63 Unit No. 2; Docket No. 50-410; License No. NPF-69 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 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 1 (NMPl) 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 NMPI and NMP2 for the period January 1,2007 through December 31,2007.

This letter contains no NRC commitments. Should you have any questions regarding this submittal, please contact T. F. Syrell , Licensing Director, at (315) 349-5219.

G.I aughlin Manager Engineering Services GJL/MHS

Document Control Desk January 31, 2008 Page 2 Attachments: I. Nine Mile Point Unit I 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007

2. Nine Mile Point Unit 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 cc: S. 1. Collins, NRC Regional Administrator, Region I Senior NRC Resident Inspector M. J. David, NRC Project Manager

ATTACHMENT 1 Nine Mile Point Unit 1 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Nine Mile Point Nuclear Station, LLC January 31, 2008

Attachment 1 Nine Mile Point Unit 1 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 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 1,2007 through December 31, 2007 for Nine Mile Point Unit 1 (NMP1).

DISCUSSION No changes or errors to the ECCS evaluation model were identified in 2007 for NMP 1.

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

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Attachment 1 Nine Mile Point Unit 1 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 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 PCT Effect Absolute PCT Effect A. Prior 10 CFR 50.46 Changes or Error Corrections- APCT oOF Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections - MCT oOF This Year Absolute Sum of 10 CFR 50.46 Changes APCT The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT 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 2007 Nine Mile Point Nuclear Station, LLC January 31, 2008

Attachment 2 Nine Mile Point Unit 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 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 1,2007 through December 31,2007 for Nine Mile Point Unit 2 (NMP2).

DISCUSSION No changes or errors to the ECCS evaluation model were identified in 2007 for NMP2 .

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

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Attachment 2 Nine Mile Point Unit 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 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 PCT Effect Absolute PCT Effect A. Prior 10 CFR 50.46 Changes or Error Correct ions - APCT +90°F +90°F Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections - APCT oOF This Year Absolute Sum of 10 CFR 50.46 Changes APCT + 90°F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT impact for changes and errors identified since this analysis is less than 2200 degrees F.

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