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MONTHYEARML22236A6472022-08-31031 August 2022 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15106A3612015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Example Vogtle 1 and 2, Change Justification Matrix NL-15-0680, Annual Report for 2014 and Significant Change/Error Report2015-04-0808 April 2015 Annual Report for 2014 and Significant Change/Error Report ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T NL-14-0900, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 and Significant Change/Error Report2014-06-20020 June 2014 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 and Significant Change/Error Report NL-10-1021, Unit 1 & 2, Request to Implement Subsequent Edition of ASME OM Code for Class 1 Safety Relief Valves with Auxiliary Actuating Devices2010-10-29029 October 2010 Unit 1 & 2, Request to Implement Subsequent Edition of ASME OM Code for Class 1 Safety Relief Valves with Auxiliary Actuating Devices ML1008100052010-02-0202 February 2010 2009 Hatch FEMA Exercise Report Oct 14th ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0503804782004-02-19019 February 2004 E-mail from Naeem Iqbal to Various Addressees; Hatch Fire Model 2022-08-31
[Table view] Category:Letter type:NL
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Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35201 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN A COMPANY April 8, 2015 Docket Nos.: 50-321 NL-15-0680 50-366 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 and Significant Change I Error Report Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.46(a)(3)(ii), Southern Nuclear Operating Company (SNC) is submitting the enclosed Edwin I. Hatch Nuclear Plant (HNP) Units 1 & 2 emergency core cooling system (ECCS) evaluation model annual report for 2014. In addition, as a result of the use of GNF2 fuel for the HNP Unit 2 Cycle 24 core load, SNC is submitting a HNP Unit 2 significant change/error report.
HN P Unit 2 Cycle 24 is the first HNP cycle with a reload of GNF2 fuel. Cycle 24 went critical on March 10, 2015. The new fuel introduction required re-analysis of ECCS-LOCA performance evaluation of the limiting large break LOCA and small break LOCA. The re-analysis resulted in an increase in the calculated peak cladding temperature (PCT) increase of 180°F for the GNF2 fuel as compared to the previous fuel design (GE14). The analysis also incorporated a methodology change to SAFER/PRIME-LOCA from the previous SAFER/GESTR-LOCA. The analysis meets the NRC Safety Evaluation Report (SER) requirements on the SAFER/ PRIME-LOCA application, and demonstrates that the 10 CFR 50.46 PCT and maximum cladding oxidation acceptance criteria are satisfied.
There were no changes or errors to the GE14 ECCS-LOCA evaluation model for 2014 other than those reported in SNC letter dated June 20, 2014 (ML14171A627).
The GNF2 ECCS-LOCA evaluation incorporates all previous code error notices and provides a new baseline for HNP Unit 2 with GNF2 fuel. This re-analysis was performed for both units and will serve as a baseline for Unit 1 next spring after its first reload of GNF2 fuel is installed. However, until then, Unit 1 continues to be licensed using the existing GE14 ECCS-LOCA evaluation.
U. S. Nuclear Regulatory Commission NL-15-0680 Page 2 This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
Respectfully submitted, C.71-C. R. Pierce Regulatory Affairs Director CRP/RMJ
Enclosure:
Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 & Significant Change/Error Report cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. D. R. Vineyard, Vice President- Hatch Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. 8. J. Adams, Vice President- Engineering Mr. G. L. Johnson, Regulatory Affairs Manager - Hatch RTYPE: C HA02.004 U.S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager - Hatch Mr. D. H. Hardage, Senior Resident Inspector- Hatch
Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 and Significant Change/Error Report Enclosure Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 & Significant Change/Error Report
Enclosure to NL-15-0680 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20 14 & Significant Change/Error Report Edwin I. Hatch Nuclear Plant Unit 1 SAFERIGESTR-LOCA Analysis Model Table 1-1a- SAFERIGESTR-LOCA Summary of Changes I Errors (2014)
Estimated Description Effect
( P CT)
None affecting PCT1 N/A Table 1-1b- Cumulative Impact of Changes I Errors GE14 Description IPCTI (oF)
- Changes/Errors Previously Reported (Reference 1) 01
- Summary of Changes/Errors (2014) 01 Cumulative Total 0 1 On June 20, 2014, a Significant Change I Error report was submitted (Reference 1). This "reset the baseline PCT for reporting purposes. There were no additional changes I errors in 20 14 other than those reported in Reference 1.
E 1- 1
Enclosure to NL-15-0680 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 & Significant Change/Error Report Edwin I. Hatch Nuclear Plant Unit 2 Table 1-2a- SAFER/GESTR-LOCA Summary of Changes I Errors (2014) (GE14)
Estimated Description Effect
( PCT)
None affecting PCT1 N/A Table 1-2b- SAFER/PRIME-LOCA Summary of Changes I Errors (2014) (GNF2)
Estimated Description Effect
( PCT)
N/A (Not used in 2014) N/A Table 1-2c- Current Changes I Errors GE14 GNF2 Estimated Estimated Description Effect Effect
( PCT) ( PCT)
None affecting PCT2 0 03 Table 1-2d- Cumulative Impact of Changes /Errors GE14 GNF2 Description IPCTI IPCTI (oF) (oF)
- Changes/Errors Previously Reported (Reference 1) 01 N/A
- Current Changes I Errors 0 03
- Summary of Changes/Errors (2014) 01 N/A Cumulative Total 0 0 E1-2
Enclosure to NL- 15-0680 Hatch Nuclear Plant 1 0 CFR 50.46 ECCS Evaluation Model Annual Report for 20 14 & Significant Change/Error Report 1 On June 20, 20 14, a Significant Change I Error report was submitted (Reference 1) This "reset" the baseline PCT for reporting purposes. There were no additional changes I errors in 2014 other than those reported in Reference 1.
2 The GNF2 fuel has a licensing basis PCT that is 250°F greater than the GE14 licensing basis PCT, or 180°F greater than the GE 14 error-corrected PCT. All previous code error notices have been included in the new GNF2 licensing basis PCT, while code error notices from 20 1 1 -20 14 are not included in the GE14 licensing basis PCT. This explains why the difference in licensing basis PCT between GE 14 and GNF2 is 70°F greater than the error-corrected PCT difference.
3 There have been no changes to the GNF2 "baseline" PCT.
Reference:
- 1. Letter from C. R. Pierce to USNRC (NL- 14-0900), "Edwin I. Hatch Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 and Significant Change/Error Report," dated June 20, 2014 E 1-3