NL-16-0463, Submittal of 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2015 and Significant Change/Error Report

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Submittal of 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2015 and Significant Change/Error Report
ML16095A153
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 04/01/2016
From: Pierce C
Southern Co, Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-16-0463
Download: ML16095A153 (7)


Text

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 SOUTHERN * \

Fax 205.992.7601 NUCLEAR A SOUTHERN COMPANY April 1, 2016 Docket Nos.: 50-321 NL-16-0463 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 2015 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 2015. In addition, as a result of the use of GNF2 fuel for the HNP Unit 1 Cycle 28 core load, SNC is submitting for HNP Unit 1 a significant change/error report.

HNP Unit 1 Cycle 28 is the first HNP Unit 1 cycle with a reload of GNF2 fuel.

Cycle 28 went critical on March 3, 2016. HNP Unit 2 transitioned to GNF2 fuel last spring. The new fuel introduction required re-analysis of ECCS-LOCA performance evaluation of the limiting large break LOCA and small break LOCA.

The GNF2 ECCS-LOCA evaluation incorporates all previous code error notices and provides a new baseline for HNP Unit 1 with GNF2 fuel. The re-analysis resulted in an increase in the calculated peak cladding temperature (PCT) of 180°F for the GNF2 fuel as compared to the previous fuel design (GE14). The analysis also incorporated a methodology change to SAFERIPRIME-LOCA from the previous SAFER/GESTR-LOCA. The analysis meets the NRC Safety Evaluation Report (SEA) 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 Unit 1 GE14 ECCS-LOCA evaluation model for 2015. In addition, there were no changes or errors to the Unit 2 ECCS-LOCA evaluation model for 2015 other than those described in the April 8, 2015 Significant Change I Error report (SNC letter NL-15-0680).

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

U.S. Nuclear Regulatory Commission NL-16-0463 Page 2 ct(.lk:u.

Respectfully submitted, C. A. Pierce Regulatory Affairs Director CRP/RMJ

Enclosure:

Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & 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. B. J. Adams, Vice President- Engineering Mr. G. L. Johnson, Regulatory Affairs Manager- Hatch RTYPE: CHA02.004 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. M.D. Orenak, NRR Project Manager- Hatch Mr. D. H. Hardage, Senior Resident Inspector- Hatch

Edwin I. Hatch Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 and Significant Change/Error Report Enclosure Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & Significant Change/Error Report

Enclosure to NL-16-0463 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & Significant Change/Error Report Edwin I. Hatch Nuclear Plant Unit 1 Table 1-1a- SAFERIGESTR-LOCA Summary of Changes I Errors (2015) (GE14)

Estimated Description Effect (ll PCT)

None affecting PCT N/A Table 1-1b- SAFERIPRIME-LOCA Summary of Changes I Errors (2015) (GNF2)

Estimated Description Effect (ll PCT)

N/ A (Not used in 2015) N/A Table 1-1c- Current Changes I Errors GE14 GNF2 Estimated Estimated Description Effect Effect (ll PCT) (ll PCT)

None affecting PCT 1 0 02 Table 1-1d- Cumulative Impact of Changes /Errors GE14 GNF2 Description lliPCTI lliPCTI (oF) (oF)

  • Changes/Errors Previously Reported (Reference 1) 0 N/A
  • Current Changes I Errors 0 02
  • Summary of Changes/Errors {2015) 0 N/A Cumulative Total 0 0 1

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 GE14 error-corrected PCT. All E-1

Enclosure to NL-16-0463 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & Significant Change/Error Report previous code error notices have been included in the new GNF2 licensing basis PCT, while code error notices from 2011 - 2015 are not included in the GE14 licensing basis PCT. This explains why the difference in licensing basis PCT between GE14 and GNF2 is 70°F greater than the error-corrected PCT difference.

2 There have been no changes to the GNF2 "baseline" PCT for the common Unit 1 and Unit 2 analysis.

E-2

Enclosure to NL-16-0463 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & Significant Change/Error Report Edwin I. Hatch Nuclear Plant Unit 2 Table 1-2a- SAFERIGESTR-LOCA Summary of Changes I Errors (2015) (GE14)

Estimated Description Effect

{Ll PCT)

None affecting PCT 0 Table 1-2b- SAFERIPRIME-LOCA Summary of Changes I Errors (2015) (GNF2)

Estimated Description Effect

{Ll PCT)

None affecting PCT 1 0 Table 1-2c - Current Changes I Errors GE14 GNF2 Estimated Estimated Description Effect Effect

{Ll PCT) {Ll PCT)

None affecting PCT 0 0 Table 1-2d- Cumulative Impact of Changes /Errors GE14 GNF2 Description LliPCTI LliPCTI (oF) eF>

  • Changes/ Errors Previously Reported (Reference 1) 0 0
  • Current Changes I Errors 0 0
  • Summary of Changes/Errors (2015) 0 0 Cumulative Total 0 0 E-3

Enclosure to NL-16-0463 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & Significant Change/Error Report 1

On April 8, 2015, 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 2015 other than those reported in Reference 1.

Reference:

1. Letter from C. R. Pierce to USNRC (NL-15-0680), "Edwin I. Hatch Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 and Significant Change/Error Report," dated April 8, 2015 E-4

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 SOUTHERN * \

Fax 205.992.7601 NUCLEAR A SOUTHERN COMPANY April 1, 2016 Docket Nos.: 50-321 NL-16-0463 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 2015 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 2015. In addition, as a result of the use of GNF2 fuel for the HNP Unit 1 Cycle 28 core load, SNC is submitting for HNP Unit 1 a significant change/error report.

HNP Unit 1 Cycle 28 is the first HNP Unit 1 cycle with a reload of GNF2 fuel.

Cycle 28 went critical on March 3, 2016. HNP Unit 2 transitioned to GNF2 fuel last spring. The new fuel introduction required re-analysis of ECCS-LOCA performance evaluation of the limiting large break LOCA and small break LOCA.

The GNF2 ECCS-LOCA evaluation incorporates all previous code error notices and provides a new baseline for HNP Unit 1 with GNF2 fuel. The re-analysis resulted in an increase in the calculated peak cladding temperature (PCT) of 180°F for the GNF2 fuel as compared to the previous fuel design (GE14). The analysis also incorporated a methodology change to SAFERIPRIME-LOCA from the previous SAFER/GESTR-LOCA. The analysis meets the NRC Safety Evaluation Report (SEA) 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 Unit 1 GE14 ECCS-LOCA evaluation model for 2015. In addition, there were no changes or errors to the Unit 2 ECCS-LOCA evaluation model for 2015 other than those described in the April 8, 2015 Significant Change I Error report (SNC letter NL-15-0680).

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

U.S. Nuclear Regulatory Commission NL-16-0463 Page 2 ct(.lk:u.

Respectfully submitted, C. A. Pierce Regulatory Affairs Director CRP/RMJ

Enclosure:

Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & 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. B. J. Adams, Vice President- Engineering Mr. G. L. Johnson, Regulatory Affairs Manager- Hatch RTYPE: CHA02.004 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. M.D. Orenak, NRR Project Manager- Hatch Mr. D. H. Hardage, Senior Resident Inspector- Hatch

Edwin I. Hatch Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 and Significant Change/Error Report Enclosure Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & Significant Change/Error Report

Enclosure to NL-16-0463 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & Significant Change/Error Report Edwin I. Hatch Nuclear Plant Unit 1 Table 1-1a- SAFERIGESTR-LOCA Summary of Changes I Errors (2015) (GE14)

Estimated Description Effect (ll PCT)

None affecting PCT N/A Table 1-1b- SAFERIPRIME-LOCA Summary of Changes I Errors (2015) (GNF2)

Estimated Description Effect (ll PCT)

N/ A (Not used in 2015) N/A Table 1-1c- Current Changes I Errors GE14 GNF2 Estimated Estimated Description Effect Effect (ll PCT) (ll PCT)

None affecting PCT 1 0 02 Table 1-1d- Cumulative Impact of Changes /Errors GE14 GNF2 Description lliPCTI lliPCTI (oF) (oF)

  • Changes/Errors Previously Reported (Reference 1) 0 N/A
  • Current Changes I Errors 0 02
  • Summary of Changes/Errors {2015) 0 N/A Cumulative Total 0 0 1

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 GE14 error-corrected PCT. All E-1

Enclosure to NL-16-0463 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & Significant Change/Error Report previous code error notices have been included in the new GNF2 licensing basis PCT, while code error notices from 2011 - 2015 are not included in the GE14 licensing basis PCT. This explains why the difference in licensing basis PCT between GE14 and GNF2 is 70°F greater than the error-corrected PCT difference.

2 There have been no changes to the GNF2 "baseline" PCT for the common Unit 1 and Unit 2 analysis.

E-2

Enclosure to NL-16-0463 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & Significant Change/Error Report Edwin I. Hatch Nuclear Plant Unit 2 Table 1-2a- SAFERIGESTR-LOCA Summary of Changes I Errors (2015) (GE14)

Estimated Description Effect

{Ll PCT)

None affecting PCT 0 Table 1-2b- SAFERIPRIME-LOCA Summary of Changes I Errors (2015) (GNF2)

Estimated Description Effect

{Ll PCT)

None affecting PCT 1 0 Table 1-2c - Current Changes I Errors GE14 GNF2 Estimated Estimated Description Effect Effect

{Ll PCT) {Ll PCT)

None affecting PCT 0 0 Table 1-2d- Cumulative Impact of Changes /Errors GE14 GNF2 Description LliPCTI LliPCTI (oF) eF>

  • Changes/ Errors Previously Reported (Reference 1) 0 0
  • Current Changes I Errors 0 0
  • Summary of Changes/Errors (2015) 0 0 Cumulative Total 0 0 E-3

Enclosure to NL-16-0463 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 & Significant Change/Error Report 1

On April 8, 2015, 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 2015 other than those reported in Reference 1.

Reference:

1. Letter from C. R. Pierce to USNRC (NL-15-0680), "Edwin I. Hatch Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 and Significant Change/Error Report," dated April 8, 2015 E-4