NL-14-1899, Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 3: | Line 3: | ||
| issue date = 12/08/2014 | | issue date = 12/08/2014 | ||
| title = Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 | | title = Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 | ||
| author name = Pierce C | | author name = Pierce C | ||
| author affiliation = Southern Co, Southern Nuclear Operating Co, Inc | | author affiliation = Southern Co, Southern Nuclear Operating Co, Inc | ||
| addressee name = | | addressee name = | ||
Revision as of 05:41, 21 June 2019
| ML14344A056 | |
| Person / Time | |
|---|---|
| Site: | Vogtle, Farley |
| Issue date: | 12/08/2014 |
| From: | Pierce C Southern Co, Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-14-1899 | |
| Download: ML14344A056 (14) | |
Text
Charles R. Pierce Regulatory Affairs Director DFC o 8 2014 Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham , AL 35242 Tel 205.992.7872 Fax 205.992.7601 Docket Nos.: 50-348 50-424 50-364 50-425 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 SOUT ERN A. COMPANY NL-14-1899 1 0 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 Ladies and Gentlemen:
Southern Nuclear Operating Company (SNC) is the licensed operator for the Joseph M. Farley Nuclear Plant (Farley) Units 1 and 2, and the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2. The requirements of 10 CFR 50.46(a)(3)(ii) include an annual report by licensees of changes to or errors in acceptable emergency core cooling system (ECCS) models that affect the temperature calculation and the estimated effect of changes or errors on the limiting ECCS analysis. Accordingly , the reports required by 10 CFR 50.46(a)(3)(ii) for Farley and Vogtle are provided in Enclosures 1 and 2, respectively. The resulting peak cladding temperature (PCT) for Farley and Vogtle continue to meet the criterion of 10 CFR 50.46(b)(1) (i.e., ::; 2200°F). Please note that the 2013 annual report for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, was previously sent by letter dated June 20, 2014. This letter contains no NRC commitments.
If you have any questions, please contact Ken McElroy at (205) 992-7369.
Respectfully submitted, C. R. Pierce Regulatory Affairs Director CRP/RMJ/Iac U. S. Nuclear Regulatory Commission NL-14-1899 Page2
Enclosures:
- 1. Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 2. Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President
& CEO Mr. D. G. Bast, Executive Vice President
& Chief Nuclear Officer Ms. C. A. Gayheart, Vice President
-Farley Mr. D. R. Madison, Vice President-Fleet Operations Mr. B. K. Taber, Vice President-Vogtle 1 & 2 Mr. M. D. Meier, Vice President-Regulatory Affairs Mr. B. J. Adams, Vice President-Engineering Mr. R. R. Martin, Regulatory Affairs Manager-Farley Mr. G. W. Gunn, Regulatory Affairs Manager-Vogtle 1 & 2 (Acting) RType: Farley=CFA04.054; Vogtle=CVC7000 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. S. A. Williams, NRR Project Manager-Farley Mr. L. M. Cain, Senior Resident Inspector-Vogtle 1 & 2 Mr. P. K. Niebaum, Resident Inspector-Farley Mr. R.E. Martin, NRR Project Manager-Vogtle 1 & 2 Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 Enclosure 1 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 Joseph M. Farley Nuclear Plant -Unit 1 ASTRUM Best Estimate Large Break LOCA Evaluation Table 1-1a-Summary of Changes/Errors (2013) Description None affecting PCT* Table 1-1b-Cumulative Impact of Changes/Errors Description
- Changes/Errors Previously Reported (Reference
- 1)
- Summary of Changes/Errors (2013) (Reference
- 2) Cumulative Total *On October 30, 2013, a Significant Change/Error Report for Farley was submitted (Reference 1 ). This "resef' the baseline PCT for reporting purposes.
There were no additional changes/errors in 2013 from those reported in Reference
- 1. E1-1 Estimated Effect (d PCT °F) 0 diPCTI (DF) 0* 0* 0 None affecting PCT Joseph M. Farley Nuclear Plant -Unit 1 NOTRUMP Appendix K Small Break LOCA Evaluation Table 1-1c-Summary of Changes/Errors (2013) Description Table 1-1d-Cumulative Impact of Changes/Errors Description
- Changes/Errors Previously Reported (Reference
- 1)
- Summary of Changes/Errors (2013) (Reference
- 2) Cumulative Total E1-2 Estimated Effect PCT °F) N/A (OF) 0 0 0 Joseph M. Farley Nuclear Plant -Unit 2 ASTRUM Best Estimate Large Break LOCA Evaluation Table 1-2a-Summary of Changes/Errors (2013) Description None affecting PCT* Table 1-2b -Cumulative Impact of Changes/Errors Description
- Changes/Errors Previously Reported (Reference 1 )
- Summary of Changes/Errors (2013) (Reference
- 2) Cumulative Total *On October 30, 2013, a Significant Change/Error Report for Farley was submitted (Reference 1 ). This "resef' the baseline PCT for reporting purposes.
There were no additional changes/errors in 2013 from those reported in Reference
- 1. E1-3 Estimated Effect (8 PCT °F) 0 8IPCTI COF) 0* 0* 0 None affecting PCT Joseph M. Farley Nuclear Plant -Unit 2 NOTRUMP Appendix K Small Break LOCA Evaluation Table 1-2c -Summary of Changes/Errors (2013) Description Table 1-2d -Cumulative Impact of Changes/Errors Description
- Changes/Errors Previously Reported (Reference
- 1)
- Summary of Changes/Errors (2013) (Reference
References:
- 1. Letter from C. R. Pierce to USNRC (NL-13-2277), "Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2012 and Significant Change/Error Report," dated October 30, 2013 2. Westinghouse Letter L TR-LIS-14-91, "J. M. Farley Units 1 and 2, 10 CFR 50.46 Annual Notification and Reporting for 2013," dated March 18,2014 E1-5 Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 Enclosure 2 Vogtle Electric Generating Plant Units 1 and 2 1 0 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 Vogtle Electric Generating Plant -Unit 1 BASH Large LOCA Evaluation Table 1-1a-Summary of Changes/Errors (2013) Description A change in the methodology used to calculate grid blockage ratio and porosity for 17x17 OFA fuel resulted in a change to the grid inputs used in the 1981 Appendix K Large Break LOCA Evaluation Model with BASH (BASH-EM), which affects the grid heat transfer in the LOCBART fuel rod heatup calculation.
Table 1-1b-Cumulative Impact of Changes/Errors Description
- Changes/Errors Previously Reported (Reference 1 )
- Summary of Changes/Errors (2013) (Reference
- 2) Cumulative Total E2-1 Estimated Effect (d PCT) (DF) 29 diPCTI (DF) 0 29 29 Vogtle Electric Generating Plant -Unit 1 BASH Large Break LOCA Evaluation Table 1-1c-Summary of Changes/Errors (2013) Description None affecting PCT Table 1-1d-Cumulative Impact of Changes/Errors Description
- Changes/Errors Previously Reported (Reference
- 1)
- Changes/Errors 2013 Calendar Year (Reference
- 2) Cumulative Total E2-2 Estimated Effect (8 PCT) N/A 8IPCTI eF> 0 0 0 Vogtle Electric Generating Plant -Unit 2 BASH Large Break LOCA Evaluation Table 1-2a-Summary of Changes/Errors (2013) Description A change in the methodology used to calculate grid blockage ratio and porosity for 17x17 OFA fuel resulted in a change to the grid inputs used in the 1981 Appendix K Large Break LOCA Evaluation Model with BASH (BASH-EM), which affects the grid heat transfer in the LOCBART fuel rod heatup calculation.
Table 1-2b-Cumulative Impact of Changes/Errors Description
- Changes/Errors Previously Reported (Reference
- 1)
- Summary of Changes/Errors (2013) (Reference
- 2)
- Cumulative Total E2-3 Estimated Effect (8PCn 29 lliPCTI COF) 0 29 29 Vogtle Electric Generating Plant -Unit 2 Appendix K Small Break LOCA Evaluation Table 1-2c-Summary of Changes/Errors (2013) Description None affecting PCT Table 1-2d -Cumulative Impact of Changes/Errors Description
- Changes/Errors Previously Reported (Reference
- 1)
- Changes/Errors 2013 Calendar Year (Reference
References:
- 1. Letter from C. A. Pierce to USNRC (NL-13-2576), .. Edwin I. Hatch Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 1 0 CFR 50.46 ECCS Evaluation Model Annual Report for 2012, .. dated December 23, 2013. 2. Westinghouse letter LTR-LIS-14-101, "A. W. Vogtle Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2013," dated March 17, 2014. E2-5