ND-19-0356, Pressurized Thermal Shock (PTS) Evaluation

Pressurized Thermal Shock (PTS) Evaluation

ML19100A427
Person / Time
Site:	Vogtle
Issue date:	04/10/2019
From:	Whitley B Southern Nuclear Operating Co
To:	Frederick Brown Document Control Desk, Office of New Reactors
References
ND-19-0356
Download: ML19100A427 (11)

Text

B. H. Whitley Southern Nuclear

.A Southern Nuclear Director Regulatory Affairs Operating Company, Inc.

3535 Colonnade Parkway Birmingham. AL 35243 Tel 205.992.7079 April10, 2019 Docket Nos.: 52-025 ND-19-0356 52-026 10 CFR 52.97(c)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Mr. Frederick D. Brown Director, Office of New Reactors Document Control Desk Washington, DC 20555-001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Units 3 and 4 Pressurized Thermal Shock (PTS) Evaluation Ladies and Gentlemen:

In accordance with combined operating license (COL) condition 2.D(12)(g)5 of the Vogtle Electric Generating Plant (VEGP) Units 3 and 4 Combined Licenses, Numbers NPF-91 and NPF-92, respectively, Southern Nuclear Operating Company (SNC) is submitting a copy of the VEGP Units 3 and 4 Pressurized Thermal Shock (PTS) Evaluation.

This letter contains no regulatory commitments. This letter has been reviewed and confirmed to contain no security-related information. Should you have any questions, please contact Mr. Corey Thomas at (205) 992-5221.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 1Oth day of April 2019.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY Brian H. Whitley Director, Regulatory Affairs Southern Nuclear Operating Company : Vogtle Electric Generating Pfant Units 3 and 4 Pressurized Thermal Shock (PTS)

Evaluation

U.S. Nuclear Regulatory Commission ND-19-0356 Page 2 of 3 cc:

Southern Nuclear Operating Company / Georgia Power Company Mr. S. E. Kuczynski (w/o enclosure)

Mr. D. G. Bost (w/o enclosure)

Mr. M. D. Meier (w/o enclosure)

Mr. D. H. Jones (w/o enclosure)

Mr. J. B. Klecha Mr. G. Chick Mr. D. L. McKinney (w/o enclosure)

Mr. T. W. Yelverton (w/o enclosure)

Mr. B. H. Whitley Ms. C. A. Gayheart Mr. C. R. Pierce Ms. A. G. Aughtman Mr. D. L. Fulton Mr. M. J. Yox Mr. C. T. Defnall Mr. J. Tupik Mr. W. A. Sparkman Ms. A. C. Chamberlain Mr. S. Leighty Mr. E. Riffle Ms. K. Roberts Mr. J. Haswell Mr. J. Andrews Document Services RTYPE: VND.LI.L00 File AR.01.02.06 Nuclear Regulatory Commission Mr. W. Jones (w/o enclosure)

Ms. J. Dixon-Herrity Mr. C. Patel Ms. J. M. Heisserer Mr. B. Kemker Mr. G. Khouri Ms. S. Temple Mr. F. Brown Mr. C. J. Even Mr. A. Lerch Mr. S. Walker State of Georgia Mr. R. Dunn Oglethorpe Power Corporation Mr. M. W. Price Ms. A. Whaley

U.S. Nuclear Regulatory Commission ND-19-0356 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Mr. L. Oriani (w/o enclosure)

Mr. T. Rubenstein (w/o enclosure)

Mr. M. Corletti Mr. M. L. Clyde Mr. D. Hawkins Mr. J. Coward Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. A. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.

Mr. S. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham NDDocumentinBox@duke-energy.com, Duke Energy Mr. S. Franzone, Florida Power & Light

Southern Nuclear Operating Company ND-19-0356 Enclosure 1 Vogtle Electric Generating Plant Units 3 and 4 Pressurized Thermal Shock (PTS) Evaluation (This enclosure consists of 7 pages, including this cover page.)

ND-19-0356 Pressurized Thermal Shock (PTS) Evaluation The purpose of this enclosure is to document the required Vogtle Units 3 and 4 reactor vessel (RV) integrity pressurized thermal shock (PTS) compliance with 10 CFR 50.61 [1] and the Vogtle Units 3 and 4 UFSAR (plant-specific DCD) [2] using the measured as-built material properties from the Certified Material Test Reports (CMTRs). This evaluation fulfills Southern Nuclear Operating Company (SNC) combined operating license (COL) Commitment 2.D(12)(g)5. There have been no changes between the approved DCD Rev. 19 document and the current UFSAR Subsections 5.3.3.1 and Tables 5.3-1 and 5.3-3 that would impact the original COL commitment.

The PTS reference temperatures (RTPTS) calculated with the Vogtle Units 3 and 4 actual RV chemical and mechanical properties from the CMTRs are below the RTPTS screening criteria values of 270F for plates, forgings, and longitudinal welds, and 300F for circumferential welds at 56 EFPY. This satisfies 10 CFR 50.61 [1] and the UFSAR [2]. A comparison of the plant specific RTPTS values to the screening limits is provided in Table 1. Tables 5 and 6 contain the RTPTS calculations for each of the beltline materials for the Vogtle Units 3 and 4 at 56 effective full power years (EFPY).

The scope of this assessment includes the beltline material for Vogtle Units 3 and 4. The beltline materials are those that will receive a fluence greater than 1017 n/cm2 (E > 1.0 MeV) during the 40-year licensed operating period. For the AP1000 units, the beltline materials include:

Upper Shell (US) Forging, Lower Shell (LS) Forging, Transition Ring (TR), and the welds connecting these components The initial RTNDT values and best-estimate Cu and Ni weight % values for the RV beltline materials are provided in Table 2 for Vogtle Unit 3 and in Table 3 for Vogtle Unit 4.

The neutron fluence values used to calculate the RTPTS are provided in Table 4. These fluence values represent the projected fluence at 56 EFPY for Vogtle Units 3 and 4 at clad/base metal interface for RV beltline materials, and are taken from APP-RXS-M3C-026 [3]. The use of 56 EFPY fluence values is conservative compared to a 40-year life, and the 54 EFPY term defined in Table 5.3-3 of the UFSAR [2] for the 60-year design life.

Table 1 Comparison of Plant Specific RTPTS with the Bounding RTPTS Values RTPTS

(°F)

Material 10 CFR 50.61 [1]

Vogtle Unit 3 Vogtle Unit 4

[Table 5] [Table 6]

UFSAR [2]

Upper Shell (US) 29 23 < 270 Lower Shell (LS) 39 19 < 270 Transition Ring (TR) 13 23 < 270 US-to LS-Circumferential

-18 -18 < 300 (Circ.) Weld LS-to-TR Circ. Weld -13 -13 < 300 2 of 7

ND-19-0356 Pressurized Thermal Shock (PTS) Evaluation Table 2 Material Properties for the Vogtle Unit 3 Reactor Vessel Beltline Materials(a)

Fracture Chemical Composition(b) Toughness Properties Material Description Initial Cu Ni RTNDT(c)

Wt. % Wt. %

(°F)

US Forging 08W172-1-1 0.03 0.76 -20 LS Forging 09W4-1-1 0.03 0.76 -20 Transition Ring 08D1090-1-1 0.03 0.75 -40 US-to-LS Circumferential Weld US-40N (Heat # GZ005499727) with PF-H55SN Flux 0.02 0.02 -70 (Lot # 0KGY610)

LS-to-TR Circ. Weld US-40N (Heat #

GZ005499727) with PF-H55SN Flux 0.02 0.02 -70 (Lot # 0KGY610)

Notes for Table 2:

(a) All values were obtained from CMTRs.

(b) The best-estimate chemical composition values listed here are the maximum of the materials product analyses as documented in the CMTRs.

(c) All initial RTNDT values are based on measured data.

Table 3 Material Properties for the Vogtle Unit 4 Reactor Vessel Beltline Materials(a)

Fracture Chemical Composition(b) Toughness Properties Material Description Initial Cu Ni RTNDT(c)

Wt. % Wt. %

(°F)

US Forging F09173 010 0.04 0.83 -40 LS Forging F09174 010 0.03 0.84 -40 Transition Ring F09175 010 0.03 0.78 -30 US-to-LS Circumferential Weld US-40N (Heat # GZ005499727) with PF-H55SN Flux 0.02 0.02 -70 (Lot # 0KGY610)

LS-to-TR Circ. Weld US-40N (Heat #

GZ005499727) with PF-H55SN Flux 0.02 0.02 -70 (Lot # 0KGY610)

Notes for Table 3:

(a) All values were obtained from CMTRs.

(b) The best-estimate chemical composition values listed here are the maximum of the materials product analyses as documented in the CMTRs.

(c) All initial RTNDT values are based on measured data.

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ND-19-0356 Pressurized Thermal Shock (PTS) Evaluation Table 4 Vogtle Units 3 and 4 Calculated Pressure Vessel Clad/Base Metal Interface Fast Neutron Fluence Fluence, n/cm2 (E > 1.0 MeV)

Reactor Vessel Material 56 EFPY(a)

US Forging(b) 2.24 x 1019 LS Forging 7.32 x 1019 Transition Ring(c) 3.54 x 1019 US-to-LS Circ. Weld 2.24 x 1019 LS-to-TR Circ. Weld 3.54 x 1019 Notes for Table 4:

(a) All fluence values are taken from APP-RXS-M3C-026, Revision 1 [3].

(b) US Forging fluence value is conservatively deemed equivalent to the US-to LS-Circ. Weld fluence value.

(c) Transition Ring fluence value is conservatively deemed equivalent to the LS-to-TR Circ. Weld fluence value.

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ND-19-0356 Pressurized Thermal Shock (PTS) Evaluation Table 5 Calculation of the Vogtle Unit 3 RTPTS Values for 56 EFPY Fluence(b)

CF(a) RTNDT(U)(d) RTNDT(e) U(d) (f) Margin(g) RTPTS(h)

Reactor Vessel Material (x1019 n/cm2, FF(c)

(F) (F) (F) (°F) (°F) (F) (F)

E > 1.0 MeV)

US Forging 08W172-1-1 20 2.24 1.2184 -20 24.4 0 12.2 24.4 29 LS Forging 09W4-1-1 20 7.32 1.4700 -20 29.4 0 14.7 29.4 39 Transition Ring 08D1090-1-1 20 3.54 1.3292 -40 26.6 0 13.3 26.6 13 US-to-LS Circ. Weld US-40N (Heat # GZ005499727) with 21.5 2.24 1.2184 -70 26.2 0 13.1 26.2 -18 PF-H55SN Flux (Lot # 0KGY610)

LS-to-TR Circ. Weld US-40N (Heat # GZ005499727) with 21.5 3.54 1.3292 -70 28.6 0 14.3 28.6 -13 PF-H55SN Flux (Lot # 0KGY610)

Notes for Table 5:

(a) Values determined using the chemical compositions from Table 2 of this letter in conjunction with Tables 1 and 2 of 10 CFR 50.61 [1].

(b) Taken from Table 4 of this letter.

(c) FF = fluence factor = f(0.28 - 0.1 log (f)); per 10 CFR 50.61 [1].

(d) Initial RTNDT values are taken from Table 2 of this letter. All initial RTNDT values are based on material-specific measured data; therefore, U = 0°F consistent with WCAP-14040-A [4].

(e) RTNDT = CF

• FF; per 10 CFR 50.61 [1].

(f) Per 10 CFR 50.61 [1], = 17°F for the base metal and = 28°F for the weld metal; however, need not exceed 0.5*RTNDT.

(g) Margin 2  ; per 10 CFR 50.61 [1].

(h) RTPTS values calculated in accordance with 10 CFR 50.61 [1].

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ND-19-0356 Pressurized Thermal Shock (PTS) Evaluation Table 6 Calculation of the Vogtle Unit 4 RTPTS Values for 56 EFPY Fluence(b)

CF(a) RTNDT(U)(d) RTNDT(e) U(d) (f) Margin(g) RTPTS(h)

Reactor Vessel Material (x1019 n/cm2, FF(c)

(F) (F) (F) (°F) (°F) (F) (F)

E > 1.0 MeV)

US Forging F09173 010 26 2.24 1.2184 -40 31.7 0 15.8 31.7 23 LS Forging F09174 010 20 7.32 1.4700 -40 29.4 0 14.7 29.4 19 Transition Ring F09175 010 20 3.54 1.3292 -30 26.6 0 13.3 26.6 23 US-to-LS Circ. Weld US-40N (Heat # GZ005499727) with 21.5 2.24 1.2184 -70 26.2 0 13.1 26.2 -18 PF-H55SN Flux (Lot # 0KGY610)

LS-to-TR Circ. Weld US-40N (Heat # GZ005499727) with 21.5 3.54 1.3292 -70 28.6 0 14.3 28.6 -13 PF-H55SN Flux (Lot # 0KGY610)

Notes for Table 6:

(a) Values determined using the chemical compositions from Table 3 of this letter in conjunction with Tables 1 and 2 of 10 CFR 50.61 [1].

(b) Taken from Table 4 of this letter.

(c) FF = fluence factor = f(0.28 - 0.1 log (f)); per 10 CFR 50.61 [1].

(d) Initial RTNDT values are taken from Table 3 of this letter. All. Initial RTNDT values are based on material-specific measured data; therefore U = 0°F consistent with WCAP-14040-A [4].

(e) RTNDT = CF

• FF; per 10 CFR 50.61 [1].

(f) Per 10 CFR 50.61 [1], = 17°F for the base metal and =28°F for the weld metal; however, need not exceed 0.5*RTNDT.

(g) Margin 2  ; per 10 CFR 50.61 [1].

(h) RTPTS values calculated in accordance with 10 CFR 50.61 [1].

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ND-19-0356 Pressurized Thermal Shock (PTS) Evaluation References

1. 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events, Federal Register, Volume 60, No. 243, dated December 19, 1995, effective January 18, 1996.

2. Vogtle Units 3 and 4 Updated Final Safety Analysis Report.

3. APP-RXS-M3C-026, AP1000 Neutron Fast Fluence, DPA, and Heating Rate Evaluation -

Long-Term Power Distribution, Revision 1, April 2012.

4. WCAP-14040-A, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, Revision 4, May 2004.

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