ML090560527
| ML090560527 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/29/2009 |
| From: | Mazzaferro P Nine Mile Point |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML090560527 (8) | |
Text
Constellation Energy Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 January 29, 2009 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention:
Subject:
Document Control Desk 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 2008 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 (NMPI) 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 NMP1 and NMP2 for the period January 1, 2008 through December 31, 2008.
Should you have any questions regarding this submittal, please contact T. F. Syrell, Licensing Director, at (315) 349-5219.
Very truly yours, P. A. Mazzaferro Acting Manager Engineering Services PAM/MHS Ac~o;
Document Control Desk January 29, 2009 Page 2 Attachments:
- 1. Nine Mile Point Unit 1 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2008
- 2. Nine Mile Point Unit 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2008 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 2008 Nine Mile Point Nuclear Station, LLC January 29, 2009
ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2008 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, 2008 through December 31, 2008 for Nine Mile Point Unit 1 (NMP1).
DISCUSSION No changes or errors to the ECCS evaluation model were identified in 2008 for NMP1.
IMPACT Not applicable CONCLUSION As documented in Table 1, the NMP 1 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.
I of 2
ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2008 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 -
Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections -
This Year Absolute Sum of 10 CFR 50.46 Changes APCT =
0 °F APCT =
0 OF APCT =
0 OF 0 OF 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.
2 of 2
ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2008 Nine Mile Point Nuclear Station, LLC January 29, 2009
ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2008 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, 2008 through December 31, 2008 for Nine Mile Point Unit 2 (NMP2).
DISCUSSION A reanalysis was performed as reported in the License Amendment Request for implementation of Average Power Range Monitor/Rod Block Monitor/Technical Specifications/Maximum Extended Load Line Limit Analysis, submitted March 30, 2007. No changes or errors to the ECCS evaluation model were identified in 2008 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.
1 of 2
ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2008 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 Corrections -
APCT
=
Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections -
APCT This Year 0 OF 0 OF 0 OF 0 OF 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.
2 of 2