ML23233A176

Application for Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390

ML23233A176
Person / Time
Site:	Summer
Issue date:	08/17/2023
From:	Dominion Energy Nuclear Connecticut
To:	Office of Nuclear Reactor Regulation
References
23-193 PWROG-21037-NP, Rev 2
Download: ML23233A176 (1)

Text

Serial No.: 23-193 Docket No.: 50-395 Enclosure 4 NON-PROPRIETARY REFERENCE DOCUMENTS AND A REDACTED VERSION OF A PROPRIETARY REFERENCE DOCUMENT (PUBLIC VERSION)

Virgil C. Summer (VCSNS) Unit 1 Dominion Energy South Carolina, Inc. (DESC)

,)

Serial No.: 23-193 Docket No.: 50-395 Enclosure 4 Attachment 1 PWROG-21037-NP, REVISION 2 Virgil C. Summer (VCSNS) Unit 1 Dominion Energy South Carolina, Inc. (DESC)

I PWROG Revision 2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Determination of Unirradiated RT NDT and Upper-Shelf Energy Values of the V.C. Summer Unit 1 Reactor Vessel Materials March 2023

Westinghouse Non-Proprietary Class 3

@Westinghouse To: James P. Molkenthin Date: March 3, 2023 cc: Melinda J. Higby Lynn Patterson Benjamin E. Mays From: D. Brett Lynch and Raymond Simmen Your ref: N/A Tel: 412-342-1788 and 412-342-1728 Ourref: PWROG-21037-NP, Revision 2

Subject:

Determination ofUnirradiated RTN>>Tand Upper-Shelf Energy Values of the V.C. Summer Unit 1 Reactor Vessel Materials Attachments: A. Summary ofUnirradiated RTNDTand Upper-Shelf Energy Values of the V.C. Summer Unit 1 Reactor Vessel Materials B. PA-MSC-1367, Tasks 1 -3 Evaluations for V.C. Summer Unit 1 Plate and Forging Materials C. PA-MSC-1367, Tasks 1-3 Evaluations for V.C. Summer Unit 1 Reactor Vessel Welds References 1. PWR Owners Group Letter OG-21-94, Revision 0, "Electronic Endorsement for V.C. Summer Unit 1 to Participate in PA-MSC-1367R0 'Document/Reconcile/Define Basis for Reactor Vessel Material Initial RTNDT and USE Values' Cafeteria Tasks 1-3," dated August 29, 2021.

Attachment A contains a summary of the results and methodologies used in the determination of the unirradiated nil-ductility transition temperature (RTNDT) and Upper-Shelf Energy (USE) values for the V.C.

Summer Unit 1 reactor vessel materials included under PA-MSC-1367, Tasks 1- 3. This attachment also compares previously documented unirradiated RTNDT and USE values with those updated herein. In addition, summary tables containing the chemistry, initial RTNDT and unirradiated USE values for all of the V.C. Summer Unit 1 reactor vessel materials are provided.

Attachment B and Attachment C document the data and calculations for the determination of the unirradiated RTNDT and USE values for the V.C. Summer Unit 1 reactor vessel materials updated under PA-MSC-1367 Tasks 1 3. Data was obtained from Certified Material Test Reports (CMTRs), vessel fabrication files, and Reactor Vessel Surveillance Program baseline report. The evaluations use the methodologies of ASME Code Section III to determine unirradiated RTNDT and USE values, as appropriate.

Revision 1 of this report was issued to correct an error in the reported Lower Shell (Heat# C9923-2) initial RTNoT and USE values in Table A.4-2, "Summary of V.C. Summer Unit 1 Reactor Vessel Material Properties." The incorrect values are only in the summary table. Changes are marked with change bars.

Revision 2 of this report was issued to correct an error in the Table A.2-1 for the "Original RTNDT" for the Nozzle Shell (Heat# C0123-2)", the identification of the vessel fabricator in Section C.2, and the SMAWs' maximum & average Initial RTNDT values in Table C.2-2.

Please transmit this technical report to Beth Haluska at Dominion.

© 2023 Westinghouse Electric Company UC All Rights Reserved

• "" This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 2 of3 PWROG-21037-NP Revision 2 March 3, 2023 Do not hesitate to contact the undersigned if you have any questions regarding the contents of this technical report.

Authored by: ELECTRONICALLY APPROVED 1 D. Brett Lynch RV/CV Design & Analysis Verified by: ELECTRONICALLY APPROVED 1 Tyler Ziegler RV/CV Design & Analysis Approved by: ELECTRONICALLY APPROVED 1 Lynn Patterson, Manager RV/CV Design & Analysis Approved by: ELECTRONICALLY APPROVED 1 James P. Molkenthin, Program Director PWR Owners Group PMO 1

Electronically approved records are authenticated in the electronic document management system.

© 2023 Westinghouse Electric Company LLC All Rights Reserved

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 3 of3 PWROG-21037-NP Revision 2 March 3, 2023 LEGAL NOTICE This report was prepared as an account of work performed by Westinghouse Electric Company LLC. Neither Westinghouse Electric Company LLC, nor any person acting on its behalf:

A. Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefulness of the information contained in this report, or that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or B. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this report.

COPYRIGHT NOTICE This report has been prepared by Westinghouse Electric Company LLC and bears a Westinghouse Electric Company copyright notice. As a member of the PWR Owners-Group you are permitted to copy and redistribute all or portions of the report within your organization; however, all copies made by you must include the copyright notice in all instances.

DISTRIBUTION NOTICE This report was prepared for the PWR Owners Group. This Distribution Notice is intended to establish guidance for access to this information. This report (including proprietary and non-proprietary versions) is not to be provided to any individual or organization outside of the PWR Owners Group program participants without prior written approval of the PWR Owners Group Program Management Office. However, prior written approval is not required for program participants to provide copies of Class 3 Non-Proprietary reports to third parties that are supporting implementation at their plant, and for submittals totheNRC.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 1 of 16 Attachment A to PWROG-21037-NP Revision 2 Attachment A Summary ofUnirradiated RTNDT and Upper-Shelf Energy Values of the V.C. Summer Unit 1 Reactor Vessel Materials

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 2 of 16 Attachment A to PWROG-21037-NP Revision 2 A.1 Introduction This attachment summarizes the results and methodologies used in the determination of the unirradiated nil-ductility transition temperature (RTNDT) and Upper-Shelf Energy (USE) values for the V.C. Summer Unit 1 reactor vessel materials included under Dominion participation in Pressurized Water Reactor Owners Group (PWROG) Project Authorization (PA) PA-MSC-1367, Tasks l - 3 as documented in OG-21-94

[Ref. 1]. The material properties documented herein are based on all available data from the Westinghouse archives and the most up-to-date methodologies; therefore, these values may supersede any previously documented values. Based on the data available, the RTNDT is determined using the methods in Sub-article NB-2331 of Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) [Ref. 2] or NUREG-0800, Branch Technical Position (BTP) 5-3 [Ref. 3). The USE is detennined using the methods American Society for Testing and Materials (ASTM) E185-82 [Ref. 4].

These methodologies used for determination of the initial material properties are detailed in this attachment.

Over time, NRC regulations and industry best practices for material property determination have changed.

As a result of the age ofV.C. Summer Unit 1, which began commercial operation in 1982, it is appropriate to re-evaluate the material properties for these plants. The currently licensed base metal material property values were determined many years ago without the use of modem analytical techniques and without consideration of all weld material. Typically, only the weld data for the core region welds were documented in the Certified Material Test Report (CMTR) [Ref. 5]; however, additional data may be available for select materials in a given plant's reactor vessel. The testing and reporting requirements were significantly less strict than core region materials. As a result, new estimation methods (such as those discussed herein) were developed, which allow for the determination of initial properties using limited data. This report utilizes the most up-to-date methodologies and all available data to determine the most appropriate initial property values for the V.C. Summer Unit 1 reactor vessel materials. The methodologies used for the evaluations contained herein are described in subsequent sections of this attachment.

Following is a list of the V.C. Summer Unit I materials included in PA-MSC-1367, Tasks 1 3, and a reactor vessel schematic diagram is contained in Figure A.1-1. The associated welds were also investigated for this report. For some welds in the presumed extended beltline, the heat number used in specific weld seams could not be identified. To address these situations, bounding or generic V.C. Summer weld properties were developed to be used anywhere the specific weld heat cannot be identified:

• Replacement Reactor Vessel Closure Head

• Reactor Vessel Flange Forging

• Inlet Nozzle Forgings e Outlet Nozzle Forgings

• Upper Shell Plates

• Intermediate Shell Plates

• Lower Shell Plates

• Bottom Head Ring

• Bottom Head Dome

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 3 of 16 Attachment A to PWROG-21037-NP Revision 2 Figure A.1-1 V.C. Summer Unit 1 Reactor Vessel Schematic MELDS 18 THRU 23 Rt:F. 1,.1 tO li, 12-.-

(2511) 15, -

(225")

l<I*""""""'

(4s=*)

U' -

(.315°)

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 4 of 16 Attachment A to PWROG-21037-NP Revision 2 A.2 Initial RTNDT Determination Subarticle NB-2331 of Section III of the ASME Code [Ref. 2] requires both drop-weight test data as well as Charpy V-notch (CVN) test data from transverse specimens for determination of unirradiated RTNnT values. This methodology is copied below:

A.2.1 ASME Code Section III, NB-2331, "Material for Vessels" Pressure-retaining materials for vessels, other than bolting, shall be tested as follows.

(a) Establish a reference temperature RTNDr; this shall be done as follows:

(1) Determine a temperature TNDT that is at or above the nil-ductility transition temperature by drop weight tests.

(2) At a temperature not greater than TNDr + 60°F (TNDT + 33°C), each specimen of the Cv test (NB-2321.2) shall exhibit at least 35 mils (0.89 mm) lateral expansion and not less than 50 ft-lb (68 J) absorbed energy. Retesting in accordance with NB-2350 is permitted. When these requirements are met, TNDT is the reference temperature RTNDr-(3) In the event that the requirements of (2) above are not met, conduct additional Cv tests in groups of three specimens (NB-2321.2) to determine the temperature Tcv at which they are met. In this case the reference temperature RTNDT = Tcv - 60°F (Tcv - 33°C).

Thus, the reference temperature RTNDT is the higher of TNDT and [Tcv - 60°F (Tcv -

33°C)}.

(4) When a C. test has not been performed at TNDr + 60°F (TNDT + 33°C), or when the Cv test at TNnr + 60°F (TNDT + 33°C) does not exhibit a minimum of50ft-lb (68 J) and 35 mils (0.89 mm) lateral expansion, a temperature representing a minimum of 50 ft-lb (68 J) and 35 mils (0.89 mm) lateral expansion may be obtained from a full Cv impact curves developed from the minimum data points of all the Cv tests performed.

(b) Apply the procedures ofNB-2331 (a) to NB-2331 (b)(l), (2), and (3):

(1) the base material; (2) the base material, the heat affected zone, and weld metal from the weld procedure qualification tests in accordance with NB-4330; (3) the weld metal ofNB-2431.

The appropriate test data necessary to use these Code requirements for determination of unirradiated RTNDT values is not available for all V.C. Summer Unit 1 reactor vessel materials in the CMTR [Ref. 5]. As a result, the use of Branch Technical Position (BTP) 5-3 [Ref 3], formerly known as MTEB 5-2, was used in conjunction with Subarticle NB-2331 of Section III of the ASME Code for determination of initial RTNnT for some reactor vessel materials, as necessary. Figure A.2-1 shows the orientation of the "strong" direction (longitudinal or tangential) test specimens compared to the "weak" direction (transverse or axial) test specimens. The BTP 5-3 methodology is copied below.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 5 of 16 Attachment A to PWROG-21037-NP Revision2 A.2.2 BTP 5-3 Methodology for Initial RTNDT Determination as Documented in NUREG-0800 1.1 Determination of RT,vDT for Vessel Materials Temperature limitations are determined in relation to a characteristic temperature ofthe material, RT,vnT, that is established from the results of fracture toughness tests. Both dropweight nil-ductility transition temperature (NDTT) [TNor] tests and Charpy V-Notch tests should be run to determine the RTNDT. The NDTTtemperature, as determined by drop weight tests (ASTM E-208-1969) is the RI'NnT if, at 33°C (60°F) above the TNDT, at least 68 J (50 ft-lbs) of energy and 0.89 mm (35 mils) lateral expansion (LE) are obtained in Charpy V-Notch tests on specimens oriented in the weak direction (transverse to the direction ofmaximum working).

In most cases, the fracture toughness testing performed on vessel material for older plants did not include all tests necessary to determine the RTNnTin this manner. Acceptable estimation methods for the most common cases, based on correlations ofdata from a large number ofheats of vessel material, are provided below for guidance in determining RTNDTWhen measured values are not available.

(1) Ifdropweight tests were not performed, butfull Charpy V-notch curves were obtained, the NDTT/or SA-533 Grade B, Class 1 plate and weld material may be assumed to be the temperature at which 41 J (30 ft-lbs) was obtained in Charpy V-notch tests, or 18°C (0°F), whichever was higher.

(2) If dropweight tests were not performed on SA-508, Class II forgings, the NDTT may be estimated as the lowest ofthe following temperatures:

(a) 33°C (60°F).

(b) The temperatures ofthe Charpy V-notch upper shelf (c) The temperature at which 136 J (100 ft-lbs) was obtained on Charpy V-notch tests if the upper shelf energy values were above 136 J (100 ft-lbs).

(3) If transversely-oriented Charpy V-notch specimens were not tested, the temperature at which 68 J (50 ft-lbs) and 0.89 mm (35 mils) lateral expansion would have been obtained on transverse specimens may be estimated by one of the following criteria:

(a) Test results from longitudinally-oriented specimens reduced to 65% of their value to provide conservative estimates of values expected from transversely oriented specimens.

(b) Temperatures at which 68 J (50 ft-lbs) and 0.89 mm (35 mils) LE were obtained on longitudinally-oriented specimens increased l1°C (20°F) to provide a conservative estimate of the temperature that would have been necessary to obtain the same values on transversely-oriented specimens.

(4) Iflimited Charpy V-notch tests were performed at a single temperature to confirm that at least 41 J (30 ft-lbs) was obtained, that temperature may be used as an estimate of the RTNDTprovided that at least 61 J (45 ft-lbs) was obtained if the specimens were longitudinally oriented. If the minimum value obtained was less than 61 J (45 ft-lbs),

the RTNDrmay be estimated as 11°C (20°F) above the test temperature.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 6 of 16 Attachment A to PWROG-21037-NP Revision 2 Figure A.2-1 Comparison of "Weak" Direction and "Strong" Direction Test Specimens

• weA1<11 DIRECTION "STRONG* PIBECIJQN ASME TRANSVERSE ASME LONGITUDINAL ASTMT-L ASTML*T APV CIRC, FLAW RPV AXIAL R.AW A.2.3 Methodology Implementation Attachment B details the available drop-weight test data and Charpy V-notch test data for the V.C. Summer Unit I reactor vessel base metal materials included under PA-MSC-13 67, Tasks I - 3. The data is used to determine the material properties, i.e., Cu, Ni, unirradiated RTNDT, & unirradiated USE values. The unirradiated CVN test data were input into CVGRAPH, Version 6.02 for hyperbolic tangent curve fitting of the Charpy V-notch data sets, where appropriate. This software requires certain values to be fixed for the purposes of curve-fitting. Typically, this includes fixing the lower-shelf energy to 2.2 ft-lb for curve-fitting the CVN energy data. Similarly, the upper-shelf energy (USE) must also be fixed for curve-fitting the CVN energy data. USE calculation methodology is described in further detail in Section A.3. When graphing the minimum data points in accordance with ASME Code III Subarticle NB-2331 criteria, the upper-shelf value is fixed to the minimum absorbed energy or lateral expansion value with a shear 2: 95%,

regardless of the temperature at which it was achieved.

Attachment C details the available drop-weight test data and Charpy V-notch test data for the V.C. Summer Unit I reactor vessel weld materials included under PA-MSC-1367, Tasks 1 - 3. The data is used to evaluate material properties, i.e., Cu, Ni, unirradiated RTNDT, & unirradiated USE, for all welds used in the fabrication of the V.C. Summer Unit 1 reactor vessel. These welds were identified from a review ofCMTR

[Ref. 5], Reactor Vessel Manual [Ref. 6], surveillance capsule program [Ref. 7], and Chicago Bridge &

Iron (CB&I) fabrication records [Ref. 8] available to Westinghouse. Information from sister-plant Shearon Harris CMTR [Ref. 9] and surveillance capsule program [Ref. IO] were also used. The weld heats

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 7 of 16 Attachment A to PWROG-21037-NP Revision 2 identified in the fabrication records were cross-referenced against an investigation performed on CB&I fabricated vessels to address NRC IE Bulletin 78-12 regarding atypical weld metal in reactor pressure vessel welds [Ref. 11]. In some situations, in the presumed extended beltline, the heat number used in specific weld seams could not be identified. To address these situations, a bounding RTNoT value was identified based on the highest initial RTNoT for all V.C. Summer weld heats that can be used anywhere the specific weld heat cannot be identified.

Table A.2-1 compares the initial RTNnT values documented in the V.C. Summer FSAR with those updated herein. All material RTNnT (both original and updated) were determined consistent with the NB-2300 section of the ASME Code Section III. The differences between the unirradiated RTNDT values summarized in the V.C. Summer FSAR and those determined herein are a result of a change in curve-fitting method (hand-drawn versus hyperbolic tangent) used to fit the Charpy V-notch test data. Although some initial RTNnT values increased as a result of the PA-MSC-1367 Tasks 1 - 3 evaluations, these updates do not require changes to the current V.C. Summer Pressure-Temperature (P-T) limit curves, as the updated materials remain non-limiting with respect to these curves. See Table A.2-2 for a more detailed disposition of the impact to the P-T limit curves.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 8 of 16 Attachment A to PWROG-21037-NP Revision 2 Table A.2-1 V.C. Summer Unit 1 Initial RTNnT Comparison for Materials Included Under PA-MSC-1367, Tasks 1-3 Original Updated Limiting Initial Initial Material Identification Parameter(<)

RTNDT(a) RTNDT(b)

(OF)

(OF) (OF)

Base Metals Replacement Reactor Vessel Closure Head

-34 -34 TNDT (Heat# 2B145585 & 2Bl45586)

Vessel Flange 0 0 TNDT (Heat# 5P5343, 4P4845, & 3P4570)

Inlet Nozzle 436B-1 (Heat# 02041 W) -20 -20 TNDT Inlet Nozzle 436B-2 (Heat# O2O39W) 0 0 TNDT Inlet Nozzle 436B-3 (Heat# O2O39W) -20 -20 TNDT Outlet Nozzle 437B-1 (Heat# 02040) -10 -10 TNDT Outlet Nozzle 437B-2 (Heat# O2O40W) -10 -10 TNDT Outlet Nozzle 437B-3 (Heat# Q2Q44W) 0 0 TNDT Nozzle Shell (Heat# C9955-2) 18 9 Tso/35 Nozzle Shell (Heat# C0123-2) 26 IS Tso/35 Intermediate Shell (Heat# A9154-l) 30 21 Tso/35 Intermediate Shell (Heat# A9153-2) -20 -20 TNDT Lower Shell (Heat # C9923-1) 10 s Tso/35 Lower Shell ffieat # C9923-2) IO 4 Tso/35 Transition Ring ffieat # A9249-1) -37 -40 TNDT Bottom Head (Heat# A9231-2) -10 O(d) Tsoi35 Welds Nozzle to Intermediate Shell Circ. Weld (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Intermediate Shell Long. Weld (Heat# 4P4784, Flux Type Linde 124 Lot# 3930)

-44 -49 Tso/35 Intermediate to Lower Shell Circ. Weld (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Lower Shell Long. Weld (Heat# 4P4784 Flux Type Linde 124, Lot# 3930)

Lower Shell to Transition Ring Circ. Weld NIA -20 TNDT (Heat# 3P4966, Flux Type Linde 124, Lot# 1214)

Bounding Weld Value NIA 10<*) BTP S-3 Notes for Table A.2-1:

(a) The original initial RTNDT values were taken from the V.C. Summer FSAR, Table 5.2-11 [Ref. 12], as available. These values are consistent with those documented in WCAP-16305-NP [Ref. 13] and WCAP-16306-NP [Ref. 14].

(b) The evaluations of the updated initial RTl\'DT values are detailed in Attachment B for base metal and Attachment C for welds.

(c) As documented in Attachments B and C, the limiting parameter is defined as the testing parameter that governs the initial RTNDT determination. It can be one of the following values:

• Nil-Ductility Transition Temperature (TNDT) determined per drop-weight testing.

• 50 ft-lb transition temperature (Tso ft-lb) based on measured transversely oriented specimen data sufficient to meet the ASME Code III Subarticle NB-2331 criteria.

• BTP 5-3 based on measured specimen data per BTP 5-3 Position 1.1(4).

(d) Based on strong-direction data, which is limiting.

(e) The bounding value based on the highest initial RTNDT for all V.C. Summer weld heats.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 9 of 16 Attachment A to PWROG-21037-NP Revision 2 Only one of the V.C. Summer Unit 1 materials had initial RTNoT values that increased as a result of the technical evaluations performed under PA-MSC-1367 Tasks 1 - 3. However, this increase does not result in changes to the V.C. Summer P-T limit curves or in violations of the 10 CFR 50.61 [Ref. 15] Pressurized Thermal Shock (PTS) limits. Table A.2-2 summarizes the limiting one-quarter thickness (1/4T) and limiting three-quarter thickness (3/4T) adjusted reference temperature (ART) values applicable to the end of license renewal P-T limit curves taken from WCAP-16305-NP [Ref. 13]. The RTPTs screening criteria values of 10 CFR 50.61 are 270°F for plates, forgings and axial weld materials, and 300°F for circumferential weld materials. The material with an initial RTNoT value that increased are in regions of the reactor vessel not considered during the previous evaluations of the P-T limits and PTS; therefore, these increases have no adverse effect on the P-T limit curves or PTS analyses of record (AOR). The extended beltline consists of those materials which previously did not need to consider irradiation embrittlement but are projected to have fluence values greater than 1 x 10 17 n/cm 2 at 72 EFPY, the criterion ofRlS 2014-11

[Ref. 16] above which irradiation embrittlement needs to be considered. Table A.2-2 shows the effect on margin resulting from the updated initial RTNoT value of the limiting material against the ART values documented in the P-T limits AOR and the 10 CFR 50.61 criteria. In future analyses, all materials with a projected fluence greater than 1 x 10 17 n/cm 2 (E > 1.0 MeV) at the end of the licensed operating period should be considered in the P-T limit curves basis.

Table A.2-2 Available Margin Resulting from Initial RTNnT Value Changes Material Intermediate Shell Plate (Heat# A9154-1)

AOR Initial Updated Initial Added Margin<c> Updated ART(dl RTNDT Value<*> RTNDT Value(b)

(OF) (OF)

Reactor Vessel {°F) {°F)

Integrity Limiting Value<*

1/4T ART-153°F 144 3/4T ART- 138°F 129 30 21 9 RTPTs-159°F 150 (Regulatory Limit 270°F)

Notes for Table A.2-2:

(a) AOR ART values are taken from WCAP-16305-NP [Ref. 13] and WCAP-16306-NP [Ref. 14].

(b) Taken from Table A.2-1.

(c) Added margin= AOR initial RTNDT

• the updated RTNDr values.

(d) Updated ART= AOR limiting ART - added margin.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 10 of 16 Attachment A to PWROG-21037-NP Revision 2 A.3 Upper-Shelf Energy (USE) Determination The current 10 CFR 50, Appendix G [Ref. 17] requirements specify that upper-shelf energy (USE) be calculated based on ASTM E 185-82. Herein, USE is calculated based on an interpretation of ASTM El 85-82 that is best explained by the most recent version of the ASTM El85 manual (2016 version).

A.3.1 ASTM E185 ASTM E185-16, Section 3.1.5, defines the Charpy upper-shelfenergy level as the following:

"the average energy value for all Charpy specimen tests (preferably three or more) whose test temperature is at or above the Charpy upper-shelfonset; specimens tested at temperatures greater than 83°C (l 50°F} above the Charpy upper-shelf onset shall not be included, unless no data are available between the onset temperature and onset +83°C (+ J50°F)."

ASTM E 185-16 [Ref. 18], Section 3.1.6, defines Charpy upper-shelfonset as the following:

"the temperature at which the fracture appearance of all Charpy specimens tested is at or above 95%shear."

Using the guidelines in ASTM El 85-82 and ASTM E185-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment, per the standard Westinghouse methodology, to remove 'out of family' data was not necessary for V.C. Summer Unit 1.

A.3.2 Methodology Implementation Details of the evaluation and re-evaluation performed to determine the USE values for the V.C. Summer Unit 1 materials included under PA-MSC-1367, Tasks 1 3 are contained in Attachment B and Attachment C for the base metals and welds, respectively. Comparisons of the updated unirradiated USE values from this evaluation to the USE values documented in the V.C. Summer FSAR are documented in Table A.3-1. In some situation, no data are available with shear~ 95%. In these cases, a minimum USE is provided based on the maximum shear experienced. To address the situations where specific weld wire heat numbers could not be identified for a specific weld seam, a generic USE value was defined as the mean minus two standard deviations of the USE values from all V.C. Summer weld heats with shear data~ 95%.

The use of two standard deviations provides confidence that it will also bound those material with limited data, i.e., no shear data~ 95% .

.... This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 11 of 16 Attachment A to PWROG-21037-NP Revision 2 Table A.3-1 V.C. Summer Unit 1 Initial USE Comparison for Materials Included Under PA-MSC-1367, Tasks 1-3 Original Unirradiated Updated Unirradiated Material Identification USE<a> USE(b)

(ft-lb) (ft-lb)

Base Metals Replacement Reactor Vessel Closure Head 195.5 203 (Heat# 2B 145585 & 2B 145586)

Vessel Flange 172 159 (Heat# 5P5343, 4P4845, & 3P4570)

Inlet Nozzle 436B-1 (Heat# Q2Q41 W) 130 152 Inlet Nozzle 436B-2 (Heat# Q2Q39W) 114.S(c) ll5(c)

Inlet Nozzle 436B-3 (Heat# Q2Q39W) 135 138 Outlet Nozzle 437B-1 (Heat# Q2Q40) 146 159 Outlet Nozzle 437B-2 (Heat# Q2Q40W) 165 165 Outlet Nozzle 437B-3 (Heat# Q2Q44W) 150 155 Nozzle Shell (Heat# C9955-2) 100.5 101 Nozzle Shell (Heat# C0123-2) 91 91 Intermediate Shell (Heat# A9154-l) 80.5 76 Intermediate Shell (Heat# A9153-2) 106.5 107 Lower Shell (Heat # C9923- l) 106 106 Lower Shell (Heat# C9923-2) 91.5 92 Transition Ring (Heat# A9249-1) 107 107 Bottom Head (Heat # A9231-2) 134 125(c)

Welds Nozzle to Intermediate Shell Circ. Weld (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Intermediate Shell Long. Weld (Heat# 4P4784, Flux Tvoe Linde 124, Lot# 3930) 84 86 Intermediate to Lower Shell Circ. Weld (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Lower Shell Long. Weld (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Lower Shell to Transition Ring Circ. Weld (Heat# 3P4966, Flux Type Linde 124, Lot# 1214)

- > 88 ft-lb @ 85% Shear Generic Weld Value - 80(d)

Notes for Table A.3-1:

(a) The original initial RTNDT values were taken from the V.C. Summer FSAR, Table 5.2-11 [Ref. 12], as available.

(b) The evaluations of the updated initial RTNDT values are detailed in Attachment B for base metal and Attachment C for welds.

USE values preceded by a greater than or equal to symbol,">", identifies a material with no shear data 2: 95%; thus, the initial USE values for these materials were set to greater than the impact energy with highest shear. The percent value identifies the shear value corresponding to the lower bound USE. These data points are excluded from the statistical analysis.

(c) Based on strong-direction data, which is limiting.

(d) The bounding USE value was defined as the mean minus two standard deviations of the USE values from all V.C. Summer weld heats with shear data 2: 95%.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 12 of 16 Attachment A to PWROG-21037-NP Revision 2 Some materials in V.C. Summer Unit 1, including the limiting Intermediate Shell (Heat# A9154-l), have initial USE values that decreased as a result of the technical evaluations performed under PA-MSC-1367 Tasks 1 - 3. However, these decreases do not result in violations of the USE screening criterion of 10 CFR 50, Appendix G [Ref. 17]. Table A.3-2 disposition the materials with decreased initial USE values evaluated in the AOR and shows that it remains above the 10 CFR 50, Appendix G criterion of 50 ft-lb for irradiated material.

It should be noted that the RAI responses [Ref. 19] and SER [Ref. 20] for V.C. Summer initial license renewal indicates a bounding USE for the Intermediate Shell of 51.75 ft-lb. However, this prediction is based solely on the initial USE of75 ft-lb for the surveillance plate in WCAP-9234 [Ref. 7]. This is a more conservative number than the updated value in Table A.3-1 of 76 ft-lb. In addition, the projection in the AOR, WCAP-16306-NP, Appendix A, are based on the latest surveillance result from Capsule Z presented in WCAP-16298-NP [Ref. 21]. Regulatory Guide (RG) 1.99, Revision 2, [Ref. 22] states that the USE projections based on Position 2.2 should be used in preference to Position 1.2. RG 1. 99, Position 2.2 is still used even though the surveillance data for Intermediate Shell (Heat # A9154-1) was non-credible.

Credibility Criterion 3 of RG 1.99 indicates that even if the surveillance data are not considered credible for determination of LiRTNDT, "they may be credible for determining decrease in upper-shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E 185-82." Hence, the updated initial USE value for Intermediate Shell (Heat # A9154-l) will not cause it to drop below the 10 CFR 50, Appendix G limit.

Table A.3-2 10 CFR 50, Appendix G End of License Renewal USE Evaluation for Materials with Decreased Initial USE Values AOR Updated AOR Updated AORUSE Material Irradiated Irradiated > 50 ft-lb?

Initial USE<al Initial USE(b) Percent Identification<*) USE<al USE<c> (YIN)

(ft-lb) (ft-lb) Decrease<*>

(ft-lb) (ft-lb)

Intermediate Shell Plate 81 76 16% 68 64 Yes A9154-l Notes for Table A.3-2:

(a) AOR USE values are taken from WCAP-16306-NP, Appendix A [Re£ 14].

(b) Taken from Table A.3-1.

(c) Irradiated USE Initial USE x (1 Percent Decrease)

• "" This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 13 of 16 Attachment A to PWROG-21037-NP Revision 2 A.4 Material Properties Summary As a part of the V.C. Summer Unit 1 participation in PA-MSC-1367, Tasks 1 - 3 [Ref. 1], the copper (Cu) and nickel (Ni) weight percent (wt.%) chemical compositions of the V.C. Summer Unit 1 reactor vessel materials not currently addressed by the 10 CFR 50, Appendix G, licensing basis were defined by a review of the available original test documentation. These reviews are contained in Attachment B and Attachment C for the base metals and welds, respectively. These materials include the V.C. Summer Unit 1 reactor vessel closure head, vessel flange, inlet and outlet nozzles, nozzle shell, bottom head ring and bottom head dome, and associated welds. When component specific chemistry data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with RG 1.99, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table A.4-2.

Some of data used to create the generic weld chemistry is included in plant surveillance programs.

Specifically Heat# 4P4784, Flux Type Linde 124, Lot# 3930 is in the V.C. Summer surveillance program, documented in WCAP-9234 [Ref. 7], and Heat #5P6771, Flux Type Linde 124, Lot# 0342 is in the Shearon Harris surveillance program, documented in WCAP-10502 [Ref. 1O]. The latest V.C. Summer surveillance data in WCAP-16298-NP [Ref. 21], Table 5-10, demonstrates that the measured ARTNDT are less than RG 1.99, Position 1.1, predicted ARTNDT* The latest Shearon Harris surveillance data in ANP-3798NP

[Ref. 23], Table F-2, show measured ARTNDT greater than RG 1.99, Position 1.1, predicted ARTNnT at higher fluences. However, as shown in Table A.4-1, the RG 1.99, Position 1.1 chemistry factor (CF) based on the generic chemistry is greater than the RG 1.99, Position 2.1 (best fit), CF based on Shearon Harris surveillance data. Therefore, it is conservative to use the generic chemistry data to calculate RG 1.99, Position 1.1, CF.

Table A.4-1 Comparison of Chemistry Factors Shearon Harris V.C. Summer PWROG-21037-NP Surveillance Data Surveillance Data CF gz(a) 72.6 42.2 WCAP-16305-NP, Source RG 1.99, Table 2 ANP-3798NP, Table F-4 Table 3 Note for Table A.4-1:

(a) CF based on the generic weld chemistry data of Cu 0.06% and Ni= 1.01% from Table A.4-2.

Table A.4-2 also summarizes the updated initial RTNDT and unirradiated USE values for all of the V.C.

Summer Unit 1 reactor vessel materials. Since Table A.4-2 is based on the most up-to-date analyses of the V.C. Summer Unit 1 reactor vessel materials, in future analyses, Table A.4-2 can be referenced for all V.C.

Summer Unit I reactor vessel initial material properties.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 14 of 16 Attachment A to PWROG-21037-NP Revision 2 Table A.4-2 Summary ofV.C. Summer Unit 1 Reactor Vessel Material Properties Initial Unirradiated

<n<*>

Material Identification Wt. %Cu Wt. %Ni RTNDT USE (OF) {°F)

(ft-lb)

Base Metals Replacement Reactor Vessel Closure Head 0.03 0.73 -34 0 203 (Heat# 2B145585 & 2Bl45586)

Vessel Flange o.153(c) 0.70 0 0 159 (Heat# 5P5343, 4P4845, & 3P4570)

Inlet Nozzle 436B-1 (Heat# Q2Q41 W) 0.127(b) 0.76 -20 0 152 Inlet Nozzle 436B-2 (Heat# Q2O39W) 0.127(b) 0.82 0 0 115 Inlet Nozzle 436B-3 (Heat# Q2O39W) 0.127(b) 0.82 -20 0 138 Outlet Nozzle 437B-1 (Heat# 02040) 0.J27(b) 0.85 -10 0 159 Outlet Nozzle 437B-2 <Heat# O2O40W) 0.127(b) 0.80 -10 0 165 Outlet Nozzle 437B-3 (Heat# O2O44W) 0.127(b) 0.78 0 0 155 Nozzle Shell (Heat# C9955-2) 0.13 0.57 9 0 101 Nozzle Shell (Heat# C0123-2) 0.12 0.58 15 0 91 Intermediate Shell (Heat # A9154-1) 0.10 0.51 21 0 76 Intermediate Shell ffieat # A9153-2) 0.09 0.45 -20 0 107 Lower Shell (Heat # C9923-1) 0.08 0.41 5 0 106 Lower Shell (Heat# C9923-2) 0.08 0.41 4 0 92 Transition Ring (Heat # A9249-1) o.172(c) 0.53 -40 0 107 Bottom Head (Heat# A9231-2) 0.172cc) 0.45 0 0 125 Welds Nozzle to Intermediate Shell Circ. Weld (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Intermediate Shell Long. Weld (Heat# 4P4784, Flux Type Linde 124, Lot# 3930) 0.05 0.91 -49 0 86 Intermediate to Lower Shell Circ. Weld (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Lower Shell Long. Weld (Heat# 4P4784, Flux Type 124, Lot# 3930)

Lower Shell to Transition Ring Circ. Weld > 88 ft-lb@

0.03 0.90 -20 0 (Heat# 3P4966, Flux Type 124, Lot# 1214) 85% Shear Generic Weld Value 0.06(d) l.0l(d) 10 0 80 Notes for Table A.4-2:

(a) 01 set equal to 0°F per WCAP-14040-A [Ref. 24] if the initial RTNDT is based on ASME Code Section III/ BTP 5-3 using measured data, unless otherwise noted.

(b) Generic value for SA-508 Class 2 nozzle forgings from PWROG-15109-NP-A [Ref. 25]

(c) Generic value based on a mean plus one standard deviation analysis of the high copper A508, Class 2 forging or A533, Grade B, Class I, plate materials contained in Table G.2 ofORNL/TM-2006/530 [Ref. 26].

(d) Generic value was defined as the mean plus one standard deviation of available data from all V.C. Summer weld heats, consistent with Regulatory Guide 1.99, Revision 2 [Ref. 22].

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 15 of 16 Attachment A to PWROG-21037-NP Revision 2 A.5 References

1. PWR Owners Group Letter OG-21-94, Revision 0, "Electronic Endorsement for V.C. Summer Unit 1 to Participate in PA-MSC-1367R0 'Document/Reconcile/Define Basis for Reactor Vessel Material Initial RTNDT and USE Values' Cafeteria Tasks 1-3," dated April 29, 2021.

2. ASME Boiler and Pressure Vessel (B&PV) Code,Section III, Division 1, Subarticle NB-2300, "Fracture Toughness Requirements for Material."

3. NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Chapter 5 ofL WR Edition, Branch Technical Position 5-3, "Fracture Toughness Requirements,"

Revision 4, U.S. Nuclear Regulatory Commission, March 2019. [Agencywide Documents Access and Management System (ADAMS) Accession Number MLI 8338A5 l 6}

4. ASTM El 85-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," ASTM, July 1982.

5. CMTR-RV-CGE, Revision 0, "Reactor Vessel Certified Material Test Reports for CGE [V.C. Summer Unit 1]."

6. Reactor Vessel Manual RVM-CGE, Revision 1, "V.C. Summer Unit 1 Reactor Vessel Instruction Manual," March 2017.

7. Westinghouse Report WCAP-9234, Revision 0, "South Carolina Electric and Gas Company Virgil C.

Summer Nuclear Plant Unit No. 1 Reactor Vessel Radiation Surveillance Program," January 1978.

8. V.C. Summer Unit 1, Reactor Vessel Material Property data file. [Attached in PRIME}

9. CMTR-RV-CQL, "Reactor Vessel Certified Material Test Reports for CQL [Shearon Harris Unit 1]."

10. Westinghouse Report WCAP-10502, Revision 0, "Carolina Power and Light Company Shearon Harris Unit No. 1 Reactor Vessel Radiation Surveillance Program," May 1984.

11. CB&I Report DDP-1595, "Report in Compliance with the NRC Bulletins 78-12 & 78-12a," April 1979.

12. V.C. Summer Final Safety Analysis Report, May 2018.

13. Westinghouse Report WCAP-16305-NP, Revision 0, "V.C. Summer Heatup and Cooldown Limit Curves for Normal Operation," August 2004.

14. Westinghouse Report WCAP-16306-NP, Revision 0, "Evaluation of Pressurized Thermal Shock for V.C. Summer," August 2004.

15. Code of Federal Regulations 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," U.S. Nuclear Regulatory Commission, Federal Register, January 4, 2010.

16. NRC Regulatory Issue Summary (RIS) 2014-11, "Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components," U.S. Nuclear Regulatory Commission, October 2014. [ADAMS Accession Number MLI 4149Al 65J

17. Code of Federal Regulations 10 CFR 50, Appendix G, "Fracture Toughness Requirements," U.S.

Nuclear Regulatory Commission, Federal Register, December 12, 2013.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 16 of 16 Attachment A to PWROG-21037-NP Revision 2

18. ASTM E185-16, "Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels," ASTM International, December 2016.

19. SCE&G Letter RC03-0112, "Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Responses to Request for Additional Information (RAI) for the Review of the License Renewal Application for Virgil C Summer Nuclear Station," date June 12, 2003. [ADAMS Access Number ML031681125]

20. NRC Safety Evaluation Report (SER), "Safety Evaluation Report, Related to the License Renewal of the Virgil C. Summer Nuclear Station," January 2004. [ADAMS Access Number ML040300170, ML040300174, & ML040300177]

21. Westinghouse Report WCAP-16298-NP, Revision 0, "Analysis of Capsule Z from the South Carolina Electric & Gas Company V. C. Summer Reactor Vessel Radiation Surveillance Program," August 2004.

22. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," May 1988. [ADAMS Accession Number ML003740284]

23. Framatome Report ANP-3798NP, "Analysis of Capsule Z Duke Energy Shearon Harris Nuclear Power Plant," September 2019. [ADAMS Access Number ML19296C841]

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

[ADAMS Accession Number ML050120209]

25. PWROG Report PWROG-15109-NP-A, Revision 0, "PWR Pressure Vessel Nozzle Appendix G Evaluation," January 2020. [ADAMS Accession Number ML20024E573}

26. Oak Ridge National Laboratory Report, ORNL/TM-2006/530, "A Physically Based Correlation of Irradiation-Induced Transition Temperature Shifts for RPV Steels," November 2007.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 1 of86 Attachment B to PWROG-21037-NP Revision 2 Attachment B PA-MSC-1367, Tasks 1- 3 Evaluations for V.C. Summer Unit 1 Plate and Forging Materials

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 2 of86 Attachment B to PWROG-21037-NP Revision2 B.1 V.C. Summer Unit 1 Replacement Closure Head F14362-010, Heat# 2Bl45585 & 2Bl45586 Tables B.1-1 and B.1-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for the Replacement Closure Head.

Table B.1-1 Charpy V-Notch Test Data for the Replacement Closure Head F14362-010 Tangential Axial CVNimpact Lateral CVNimpact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F) (%) (OF) (%)

(ft-lb) (mils) (ft-lb) (mils) 26 175 90 81 26 190 90 100 26 171 79 77 26 205 95 100 26 130 80 57 26 172 82 81 26 204 86 100 26 171 78 77 26 220 85 100 26 188 85 81 26 219 90 100 26 215 90 100 Table B.1-2 Drop-Weight Test Data for Replacement Closure Head F14362-010 Test Temperature TNDT Drop-Weights<al

{°F) (OF)

-24 2-NF

-34

-34 2-F Note for Table B.1-2:

(a) NF "No Fail," F "Fail" B.1.1 Determination of the Initial RTNDT Using the data summarized in Tables B.1-1 and B.1-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 26°F, TNnr + 60°F (-34°F + 60°F 26°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNoT is the initial reference temperature RTNDT, Replacement Closure Head F14362-010 Initial RTl\m =-34°F

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 3 of86 Attachment B to PWROG-21037-NP Revision 2 B.1.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM El85 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data:::: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineeringjudgment to remove 'out offamily' data was not necessary for this material. The USE (weak direction) is displayed below; this value is the average of each of the impact energy values contained in Table B.1-1 with shear:::: 95%.

Replacement Closure Head F14362-010 Initial USE = Average (190, 205, 215) ft-lb

= 203 ft-lb B.1.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.1-3.

Table B.1-3 Chemistry Data for Replacement Closure Head F14362-010 Copper Nickel Source (wt.-%) {wt.-%)

0.03 0.73 CMTR, Doosan Analysis Therefore, the chemical content will be defined as shown below going forward:

Replacement Closure Head F14362-010 Cu Content = 0.03 wt-%

Replacement Closure Head Fl4362-010 Ni Content = 0.73 wt-%

""* This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page4 of86 Attachment B to PWROG-21037-NP Revision2 B.2 V.C. Summer Unit 1 Vessel Flange 5301-V-1, Heat# 5P5343, 4P4845, &

3P4570)

Tables B.2-1 and B.2-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit I CMTRs for the Vessel Flange.

Table B.2-1 Charpy V-Notch Test Data for the Vessel Flange 5301-V-1 Tangential Axial CVNimpact Lateral CVNimpact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion (OF) (%) (OF) (%)

(ft-lb) (mils) (ft-lb) (mils)

-100 6 4 0 -40 13 12 5

-100 17 11 3 -40 84 68 40

-50 87 67 29 -40 30 26 20

-50 84 65 25 -30 82 72 35

-50 143 101 46 -30 22 23 20

-20 76 57 23 -30 71 62 35

-20 127 85 50 0 99 83 70

-20 100 73 51 0 108 87 80

-10 121 87 47 0 87 68 65 40 220 84 99 60 118.5 83 80 40 190 90 97 60 155 90 100 40 186 89 98 60 90 70 65 212 180 79 100 60 130 75 80 212 176 92 100 60 151 93 100 212 174 86 100 60 137 82 85

- - - - 120 156 91 95

- - - - 120 131 86 80

- - - - 212 145 90 100

- - - - 212 161 100 100

- - - - 212 153 86 100

- - - - 212 150 84 100

- - - - 212 166 87 100

- - - - 212 158 85 100

- - - - 212 193 83 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 5 of86 Attachment B to PWROG-21037-NP Revision 2 Table B.2-2 Drop-Weight Test Data for Vessel Flange 5301-V-1 Test Temperature TNDT Drop-Weights(aJ

{°F) {°F) 50 I-NF 10 2-NF 0

0 1-F

-10 1-F Note for Table B.2-2:

(a) NF "No Fail," F "Fail".

B.2.1 Determination of the Initial RTNDT Using the data summarized in Tables B.2-1 and B.2-2, the initial RT.NnT value can be detennined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNor (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 60°F, TNDT + 60°F (0°F + 60°F 60°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNnT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNnr is the initial reference temperature RTNDT, Vessel Flange 5301-V-1 Initial RTNDr =0°F B.2.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM El85-82 and E 185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE (weak direction) is displayed below; this value is the average of each of the impact energy values contained in Table B.2-1 with shear;::: 95%.

Vessel Flange 5301-V-1 Initial USE = Average (155, 151,156,145,161,153,150,166,158,193) ft-lb

= 159 ft-lb

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 6 of86 Attachment B to PWROG-21037-NP Revision 2 B.2.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.2-3.

Table B.2-3 Chemistry Data for Vessel Flange 5301-V-1 Copper Nickel Source (wt.-%) (wt.-%)

- 0.70 CMTR, US Steel, Homestead Works, Analysis Generic value based on a mean plus one standard deviation analysis of the high copper 0.153 A508, Class 2 forging materials contained in Table G.2 ofORNL/TM-2006/530.

Therefore, the chemical content will be defined as shown below going forward:

Vessel Flange 5301-V-1 Cu Content = 0.153 wt-%

Vessel Flange 5301-V-1 Ni Content = 0.70 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 7 of86 Attachment B to PWROG-21037-NP Revision 2 B.3 V.C. Summer Unit 1 Inlet Nozzle Forging 436B-1, Heat# Q2Q41W Tables B.3-1 and B.3-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Inlet Nozzle Forging 436B~ 1.

Table B.3-1 Charpy V-Notch Test Data for the Inlet Nozzle Forging 436B-1 Tangential Axial CVN Impact Lateral CVNlmpact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion (OF) (%) {°F) (%)

(ft-lb) (mils) (ft-lb) (mils)

-100 2 1 1 -50 45 30 20

-100 3 2 1 -50 34 25 10

-100 3 3 1 -50 24 18 1

-50 64 50 50 -30 64 44 20

-50 40 30 30 -30 71 51 20

-50 45 30 30 -30 41 29 10

-20 94 66 90 -10 87 58 30

-20 82 57 80 -10 82 55 30

-20 84 61 80 -10 72 53 30 10 92 64 80 30 111 69 40 10 96 66 80 30 101 67 50 10 104 72 90 30 102 68 50 10 41 32 20 30 105 64 50 10 39 30 20 30 117 70 60 10 33 26 20 30 102 66 50 40 111 72 80 120 170 91 100 40 116 76 80 120 160 92 100 40 100 68 70 120 175 85 100 40 112 76 80 212 159 86 100 40 129 80 80 212 150 81 100 40 125 76 80 212 160 88 100 212 157 82 100 212 130 85 100 212 152 60 100 212 133 83 100 212 146 66 100 212 128 76 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 8 of86 Attachment B to PWROG-21037-NP Revision 2 Table B.3-2 Drop-Weight Test Data for Inlet Nozzle Forging 436B-1 Test Temperature TNDT Drop-Weights<*>

(OF) (°F)

-10 2-NF

-20 2-NF, 2-F -20

-30 1-F Note for Table B.3-2:

(a) NF= "No Fail," F = "Fail".

B.3.1 Determination of the Initial RTNDT Using the data summarized in Tables B.3-1 and B.3-2, the initial RTNDT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 30°F, which is less than TNDT + 60°F (-20°F + 60°F = 40°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNDT is the initial reference temperature RTNDT*

Inlet Nozzle Forging 436B-1 Initial RTNnT = -20°F B.3.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out offamily,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The Axial (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.3-1 with shear~ 95%.

Inlet Nozzle Forging 436B-1 Initial USE = Average (170, 160, 175, 159, 150, 160, 130, 133, 128) ft-lb

= 152 ft-lb

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 9 of86 Attachment B to PWROG-21037-NP Revision 2 B.3.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.3-3.

Table B.3-3 Chemistry Data for Inlet Nozzle Forging 436B-1 Copper Nickel Source (wt.-%) (wt.-%)

- 0.76 CMTR, Lenape Forge Analysis CMTR, Verifying Analysis

- 0.76 (performed by Bethlehem Steel)

Generic value for SA-508 Class 2 nozzle 0.127 -

forgings from PWROG-15109-NP-A Therefore, the chemical content will be defined as shown below going forward:

Inlet Nozzle Forging 436B-1 Cu Content = 0.127 wt-%

Inlet Nozzle Forging 436B-1 Ni Content = 0.76 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 10 of 86 Attachment B to PWROG-21037-NP Revision 2 B.4 V.C. Summer Unit 1 Inlet Nozzle Forging 436B-2, Heat# Q2Q39W Tables B.4-1 and B.4-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Inlet Nozzle Forging 436B-2.

Table B.4-1 Charpy V-Notch Test Data for the Inlet Nozzle Forging 436B-2 Tangential Axial CVNimpact Lateral CVNlmpact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F) (%) {°F) (%)

(ft-lb) (mils) fft-lb) (mils)

-100 13 29 1 -50 36 26 10

-100 9 9 1 -50 14 10 1

-100 10 9 1 -50 11 8 1

-60 44 31 30 -20 82 60 40

-60 40 29 30 -20 74 55 30

-60 54 39 30 -20 63 45 20

-30 48 35 40 0 81 59 30

-30 45 35 30 0 89 63 40

-30 29 21 30 0 70 51 20 10 74 65 70 60 118 79 60 10 67 51 70 60 121 81 80 10 70 49 70 60 119 84 60 10 41 33 20 60 110 78 50 10 33 27 20 60 109 74 50 10 32 22 20 60 124 82 60 40 93 67 50 120 145 85 100 40 99 68 50 120 148 70 100 40 89 64 50 120 154 66 100 40 71 58 40 212 146 88 100 40 70 56 40 212 139 90 100 40 72 58 40 212 148 98 100 212 112 79 100 212 156 113 100 212 118 78 100 212 150 91 100 212 114 81 100 212 150 92 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 11 of 86 Attachment B to PWROG-21037-NP Revision 2 Table B.4-2 Drop-Weight Test Data for Inlet Nozzle Forging 436B-2 Test Temperature TNDT Drop-Weights<*>

{°F) {°F) 10 2-NF 0 1-F

-10 1-F 0

-20 1-F

-30 1-F Note for Table B.4-2:

(a) NF= "No Fail," F = "Fail".

B.4.1 Determination of the Initial RTNDT Using the data summarized in Tables B.4-1 and B.4-2, the initial RTNDT value can be detennined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to detennine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 60°F, TNDT + 60°F (0°F + 60°F = 60°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNDT is the initial reference temperature RTNDT*

While the tangential direction is usually considered the "strong" direction, the tangential Charpy data exhibit lower impact energies than the axial data. However, the 50 ft-lb and 35 mils LE criteria as still satisfied using the tangential impact energy data at 40°F, which is less than TNDT + 60°F. Therefore, TNDT still defines the initial RTNDT*

Inlet Nozzle Forging 4368-2 Initial RTNor= 0°F B.4.2 Determination of the Initial USE The current IO CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE (weak direction) is displayed below; this value is the average of each of the impact energy values contained in Table B.4-1 with shear~ 95%.

Inlet Nozzle Forging 436B-2 Initial USE = Average (145, 148, 154, 146, 139, 148, 156, 150, 150) ft-lb

=148ft-lb

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 12 of 86 Attachment B to PWROG-21037-NP Revision 2 However, while the tangential direction is usually considered the "strong" direction, the tangential Charpy data in Table B.4-1 exhibit lower impact energies at 2: 95% shear than the axial data. Therefore, the USE will be recalculated using the tangential impact energy data with shear 2: 95% because it represents the lower bound USE. It is noted that the BTP 5-3 methodology is NOT being implemented here, which reduces the tangentially oriented impact energies to 65% of the reported values in order to conservatively estimate axially oriented specimens. This is because axial data is available and does not need to be estimated.

Inlet Nozzle Forging 436B-2 Initial USE = Average (112, 118, 114) ft-lb

= 115 ft-lb B.4.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.4-3.

Table B.4-3 Chemistry Data for Inlet Nozzle Forging 436B-2 Copper Nickel Source (wt.-%) (wt.-%)

- 0.81 CMTR, Lenape Forge Analysis CMTR, Verifying Analysis

- 0.82 (performed bv Bethlehem Steel)

Generic value for SA-508 Class 2 nozzle 0.127 -

forgings from PWROG-15109-NP-A Therefore, the chemical content will be defined as shown below going forward:

Inlet Nozzle Forging 436B-2 Cu Content = 0.127 wt-%

Inlet Nozzle Forging 436B-2 Ni Content = 0.82 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 13 of86 Attachment B to PWROG-21037-NP Revision 2 B.5 V.C. Summer Unit 1 Inlet Nozzle Forging 436B-3, Heat# Q2Q39W Tables B.5-1 and B.5-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Inlet Nozzle Forging 436B-3.

Table B.5-1 Charpy V-Notch Test Data for the Inlet Nozzle Forging 436B-3 Tangential Axial CVNimpact Lateral CVNimpact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F) (%) {°F) (%)

(ft-lb) (mils) (ft-lb) (mils)

-100 3 2 1 -50 35 25 10

-100 4 3 1 -50 40 30 10

-100 3 2 1 -50 17 12 10

-60 11 10 10 -30 59 44 20

-60 29 23 20 -30 65 48 30

-60 21 18 10 -30 45 34 20

-30 79 57 60 -20 61 46 20

-30 52 40 30 -20 50 36 20

-30 76 56 60 -20 70 51 30 10 87 60 70 40 97 61 60 10 78 55 60 40 114 70 80 10 87 62 70 40 97 65 50 10 26 20 10 40 112 74 50 10 40 31 30 40 101 64 40 10 45 35 20 40 96 60 40 40 113 69 80 120 128 75 99 40 111 74 80 120 125 81 90 40 120 76 80 120 131 77 99 40 116 75 80 212 140 82 100 40 106 69 80 212 135 80 100 40 88 64 60 212 131 88 100 212 150 63 100 212 140 89 100 212 151 66 100 212 142 66 100 212 153 51 100 212 153 73 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 14 of 86 Attachment B to PWROG-21037-NP Revision 2 Table 8.5-2 Drop-Weight Test Data for Inlet Nozzle Forging 436B-3 Test Temperature TNDT Drop-Weights<*>

(OF) (OF)

-10 2-NF

-20 1-F -20

-30 1-F Note for Table B.5-2:

(a) NF= "No Fail," F = "Fail".

B.5.1 Determination of the Initial RTNDT Using the data summarized in Tables B.5-1 and B.5-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNOT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 40°F, TNoT + 60°F (-20°F + 60°F = 40°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNoT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNOT is the initial reference temperature RTNoT-Inlet Nozzle Forging 4368-3 Initial RTNoT = -20°F B.5.2 Determination of the Initial USE The current 10 CPR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out offamily,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE (weak direction) is displayed below; this value is the average of each of the impact energy values contained in Table B.5-1 with shear 2: 95%.

Inlet Nozzle Forging 4368-3 Initial USE= Average (128,131,140,135, 131, 140, 142, 153) ft-lb

= 138 ft-lb

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 15 of 86 Attachment B to PWROG-21037-NP Revision 2 B.5.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.5-3.

Table B.5-3 Chemistry Data for Inlet Nozzle Forging 436B-3 Copper Nickel Source (wt.-%) (wt.-%)

- 0.81 CMTR Lenape Forge Analysis CMTR, Verifying Analysis

- 0.82 (performed by Bethlehem Steel)

Generic value for SA-508 Class 2 nozzle 0.127 - forgings from PWROG-15109-NP-A Therefore, the chemical content will be defined as shown below going forward:

Inlet Nozzle Forging 436B-3 Cu Content = 0.127 wt-%

Inlet Nozzle Forging 436B-3 Ni Content = 0.82 wt-%

"""* This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 16 of 86 Attachment B to PWROG-21037-NP Revision 2 B.6 V.C. Summer Unit 1 Outlet Nozzle Forging 437B-1, Heat# Q2Q40 Tables B.6-1 and B.6-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Outlet Nozzle Forging 437B- l.

Table B.6-1 Charpy V-Notch Test Data for the Outlet Nozzle Forging 437B-1 Tangential Axial CVN Impact Lateral CVN Impact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F)

(ft-lb) (mils) (%) {°F)

(ft-lb) (mils) (%)

-100 5 3 I -60 80 55 30

-100 17 11 1 -60 63 48 20

-100 19 14 1 -60 69 47 20

-60 91 52 50 -30 83 63 50

-60 35 27 30 -30 64 45 30

-60 51 40 40 -30 79 67 40

-30 95 69 80 -10 86 58 50

-30 83 61 70 -10 86 60 40

-30 95 69 80 -10 64 43 30 10 llO 74 50 50 155 91 100 10 94 68 40 50 138 71 85 10 112 72 50 50 128 71 75 10 33 23 10 50 127 71 75 10 74 51 60 50 134 56 85 10 87 60 70 50 135 72 75 40 95 64 50 120 155 81 100 40 64 45 40 120 138 83 100 40 86 61 50 120 128 85 100 40 113 78 70 212 147 69 100 40 99 73 60 212 158 63 100 40 125 79 70 212 144 84 100 212 174 66 100 212 176 76 100 212 175 69 100 212 190 79 100 212 177 71 100 212 201 67 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 17 of 86 Attachment B to PWROG-21037-NP Revision 2 Table B.6-2 Drop-Weight Test Data for Outlet Nozzle Forging 437B-1 Test Temperature TNDT Drop-Weights<11l

{°F) (OF) 10 2-NF

-1Q(b) 0 2-NF Notes for Table B.6-2:

(a) NF= "No Fail," F = "Fail".

(b) Drop-weight testing had no breaks at the lowest test temperature, i.e., 0°F; therefore, the NDT :::: the next test temperature, i.e., -10°F.

B.6.1 Determination of the Initial RTNDT Using the data summarized in Tables B.6-1 and B.6-2, the initial RTNDT value can be detennined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to detennine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction. Charpy V-notch tests were conducted at 50°F, TNDT + 60°F (-10°F + 60°F = 50°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of SO ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F satisfy the criteria. PerASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TrmT is the initial reference temperature RTNDT-While the tangential direction is usually considered the "strong" direction, the tangential Charpy data exhibit lower impact energies than the axial data. However, the 50 ft-lb and 35 mils LE criteria as still satisfied using the tangential impact energy data at 40°F, which is less than T NDT + 60°F. Therefore, TNDT still defines the initial RTNDT.

Outlet Nozzle Forging 437B-1 Initial RTNDT =-10°F B.6.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM El85 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data 2'.: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineeringjudgment to remove 'out offamily' data was not necessary for this material. The Axial (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.6-1 with shear~ 95%.

Outlet Nozzle Forging 437B-1 Initial USE= Average (155,155,138,128,147,158,144,176,190,201) ft-lb

= 159 ft-lb

-This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 18 of 86 Attachment B to PWROG-21037-NP Revision 2 B.6.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.6-3.

Table B.6-3 Chemistry Data for Outlet Nozzle Forging 437B-1 Copper Nickel Source (wt.-%) (wt.-%)

- 0.81 CMTR, Lenape Forge Analysis CMTR, Verifying Analysis

- 0.89 (performed by Bethlehem Steel)

Generic value for SA-508 Class 2 nozzle 0.127 -

forgings from PWROG-15109-NP-A Therefore, the chemical content will be defined as shown below going forward:

Outlet Nozzle Forging 437B-1 Cu Content = 0.127 wt-%

Outlet Nozzle Forging 437B-1 Ni Content = 0.85 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 19 of 86 Attachment B to PWROG-21037-NP Revision 2 B.7 V.C. Summer Unit 1 Outlet Nozzle Forging 437B-2, Heat# Q2Q40W Tables B.7-1 and B.7-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Outlet Nozzle Forging 437B-2.

Table B.7-1 Charpy V-Notch Test Data for the Outlet Nozzle Forging 437B-2 Tangential Axial CVN Impact Lateral CVN Impact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion (OF) (%) (OF) (%)

(ft-lb) (mils) (ft-lb) (mils)

-100 5 3 1 -60 63 45 20

-100 29 18 1 -60 44 30 10

-100 28 19 1 -60 65 47 20

-60 64 50 60 -40 46 35 20

-60 74 58 70 -40 77 54 30

-60 15 10 10 -40 79 54 30

-30 66 40 40 -10 76 54 30

-30 101 72 80 -10 74 55 40

-30 40 30 20 -10 97 67 50 10 176 87 99 50 155 83 100 10 106 76 80 50 159 84 100 10 112 74 80 50 168 80 100 10 71 50 70 50 138 71 75 10 72 51 70 50 168 90 100 10 56 40 90 50 129 71 70 40 128 79 70 120 152 88 100 40 111 75 70 120 159 85 100 40 158 84 80 120 169 84 100 40 128 79 70 212 165 87 100 40 111 75 70 212 170 74 100 40 158 84 90 212 161 89 100 212 168 64 100 212 170 89 100 212 161 66 100 212 190 81 100 212 172 84 100 212 157 94 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 20 of86 Attachment B to PWROG-21037-NP Revision 2 Table B.7-2 Drop-Weight Test Data for Outlet Nozzle Forging 437B-2 Test Temperature TNDT Drop-Weights(*)

(DF) {°F) 0 2-NF

-10 1-F

-10

-20 1-F

-30 1-F Note for Table B.7-2:

(a) NF= No Fail," F = "Fail".

B.7.1 Determination of the Initial RTNDT Using the data summarized in Tables B.7-1 and B.7-2, the initial RTNDT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 50°F, TNDT + 60°F (-10°F + 60°F = 50°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNm is the initial reference temperature RTNDT-While the tangential direction is usually considered the "strong" direction, the tangential Charpy data exhibit lower impact energies than the axial data. However, the 50 ft-lb and 35 mils LE criteria as still satisfied using the tangential impact energy data at 40°F, which is less than TNDT + 60°F. Therefore, TNDT still defines the initial RTNDT-Outlet Nozzle Forging 437B-2 Initial RTNoT = -10°F B. 7.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and El85-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out offamily,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The Axial (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B. 7-1 with shear~ 95%.

Outlet Nozzle Forging 437B-2 Initial USE = Average (155, 159, 168, 168, 152, 159, 169, 165, 170, 161, 170, 190, 157) ft-lb

= 165 ft-lb

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 21 of 86 Attachment B to PWROG-21037-NP Revision 2 B.7.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B. 7-3.

Table B.7-3 Chemistry Data for Outlet Nozzle Forging 437B-2 Copper Nickel Source (wt.-%) (wt.-%)

- 0.80 CMTR, Lenape Forge Analysis Generic value for SA-508 Class 2 nozzle 0.127 - forgings from PWROG-15109-NP-A Therefore, the chemical content will be defined as shown below going forward:

Outlet Nozzle Forging 437B-2 Cu Content = 0.127 wt-%

Outlet Nozzle Forging 437B-2 Ni Content = 0.80 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 22 of 86 Attachment B to PWROG-21037-NP Revision 2 B.8 V.C. Summer Unit 1 Outlet Nozzle Forging 437B-3, Heat# Q2Q44W Tables B.8-1 and B.8-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Outlet Nozzle Forging 437B-3.

Table B.8-1 Charpy V-Notch Test Data for the Outlet Nozzle Forging 437B-3 Tangential Axial CVN Impact Lateral CVN Impact Lateral Temp. Shear Temp. Shear (OF) Energy Expansion Energy Expansion

(%) (OF) (%)

(ft-lb) (mils) (ft-lb) (mils)

-100 5 2 1 -50 21 14 1

-100 8 6 1 -50 33 23 10

-100 4 1 1 -50 87 61 40

-60 33 24 10 -40 54 38 20

-60 27 21 20 -40 8 5 1

-60 80 57 50 -40 15 11 1

-30 85 64 90 -20 88 60 50

-30 43 31 30 -20 67 50 40

-30 71 54 90 -20 96 67 50 10 104 73 80 40 121 77 65 10 117 78 80 40 119 71 70 10 103 71 80 40 123 79 65 10 76 55 40 40 130 80 75 10 37 26 20 40 130 75 75 10 75 54 50 40 119 68 70 40 116 76 70 120 126 70 90 40 111 73 70 120 129 69 80 40 115 74 70 120 149 85 100 40 127 79 80 212 150 62 100 40 121 78 80 212 144 81 100 40 120 73 70 212 156 82 100 212 162 66 100 212 160 85 100 212 164 70 100 212 160 81 100 212 163 86 100 212 168 79 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 23 of 86 Attachment B to PWROG-21037-NP Revision 2 Table B.8-2 Drop-Weight Test Data for Outlet Nozzle Forging 437B-3 Test Temperature TNDT Drop-Weights<*)

{°F) {°F) 20 2-NF 0 1-NF, 1-F

-10 2-NF O(b)

-20 1-F

-30 1-F Notes for Table B.8-2:

(a) NF= "No Fail," F = "Fail".

(b) Two test presented inconsistent results for drop-weight. The more conservative result will be used to define the material properties, i.e., 0°F.

B.8.1 Determination of the Initial RTNDT Using the data summarized in Tables B.8-1 and B.8-2, the initial RTNDT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight T NDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 40°F, which is less than TNDT + 60°F (0°F + 60°F = 60°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNDT is the initial reference temperature RTNDT-While the tangential direction is usually considered the "strong" direction, the tangential Charpy data exhibit lower impact energies than the axial data. However, the 50 ft-lb and 35 mils LE criteria as still satisfied using the tangential impact energy data at 40°F, which is less than TNDT + 60°F. Therefore, TNDT still defines the initial RTNDT-Outlet Nozzle Forging 437B-3 Initial RTNoT = 0°F B.8.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM El85 manual (2016 version). Using the guidelines in ASTM El85-82 and E 185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 24 of 86 Attachment B to PWROG-21037-NP Revision 2 this material. The Axial (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.8-1 with shear 2: 95%.

Outlet Nozzle Forging 437B-3 Initial USE = Average (149, 150, 144, 156, 160, 160, 168) ft-lb

= 155 ft-lb B.8.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.8-3.

Table B.8-3 Chemistry Data for Outlet Nozzle Forging 437B-3 Copper Nickel Source (wt.-%) (wt.-%)

- 0.78 CMTR, Lenape Forge Analysis CMTR, Verifying Analysis 0.77 (performed by Bethlehem Steel)

Generic value for SA-508 Class 2 nozzle 0.127 -

forgings from PWROG-15109-NP-A Therefore, the chemical content will be defined as shown below going forward:

Outlet Nozzle Forging 437B-3 Cu Content = 0.127 wt-%

Outlet Nozzle Forging 437B-3 Ni Content = 0.78 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 25 of 86 Attachment B to PWROG-21037-NP Revision 2 B.9 V.C. Summer Unit 1 Nozzle Shell Plate, Heat# C9955-2 Tables B.9-1 and B.9-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Nozzle Shell Plate, Heat# C9955-2.

Table B.9-1 Charpy V-Notch Test Data for the Nozzle Shell Plate, Heat# C9955-2 Longitudinal Transverse CVNimpact Lateral CVN Impact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion (OF) (%) (°F) (%)

(ft-lb) (mils) (ft-lb) (mils)

-100 4(a) 2(a) 1 -20 11 (a) 13(a) 15

-100 4 3 1 -20 15.5 18 15

-100 4 2 1 -20 15 17 20

-50 15 11 (a) 10 40 49 43 50

-50 15 15 10 40 55.5 49 45

-50 12(a) 14 10 40 34(a) 34(a) 35 10 55 48 50 50 59 51 55 10 66 47(a) 50 50 46.5 43 45 10 52(a) 49 50 50 38(a) 4o(a) 60 40 50(a) 50 40 70 43(a) 45(a) 50 40 65 43 40 70 55 53 55 40 61 37(a) 40 70 48 45 50 100 113 7o(a) 70 120 88 72 75 100 99(a) 79 70 120 85(a) 71 (a) 75 100 105 82 70 120 92 72 80 212 147 95(a)(b) 99 212 103 78 100 212 148 96 99 212 106.5 76(a)(b) 100 212 140(a)(b) 96 99 212 93(a) 78 100 Notes for Table B.9-1:

(a) Minimum value used in the CVGRAPH plots in accordance with ASME Code III Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CVGRAPH plots.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 26 of 86 Attachment B to PWROG-21037-NP Revision 2 Table B.9-2 Drop-Weight Test Data for Nozzle Shell Plate, Heat# C9955-2 Test Temperature TNDT Drop-Weights<*>

{°F) {°F) 0 1-NF

-10 2-NF

-20

-20 I-NF, 1-F

-30 1-F Note for Table B.9-2:

(a) NF= "No Fail," F = "Fail".

B.9.1 Determination of the Initial RTNDT Using the data summarized in Tables B.9-1 and B.9-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNoT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 40°F, TNoT + 60°F (-20°F + 60°F = 40°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNoT + 60°F would NOT satisfy the criteria.

To precisely determine the temperature at which 50 ft-lb and 35 mils LE were obtained on the specimens, the unirradiated Charpy V-notch data may be plotted and fit using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-2331, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience 2: 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNoT-Tso ft-lb= 68.9°F Ls mils= 42°F Tcv = Max [Tso ft-lb, Lsmi1] = Max [68.9°F, 42°F]

Tcv = 68.9°F Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNoT is the higher of TNoT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

RTNDT = Max [TNoT, Tcv - 60°F]

RTNDT = Max [-20°F, 68.9°F - 60°F] = Max [-20°F, 8.9°F]

Nozzle Shell Plate, Heat# C9955-2 Initial RTNnT = 9°F

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 27 of86 Attachment B to PWROG-21037-NP Revision 2 B.9.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The Transverse (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.9-1 with shear 2: 95%.

Nozzle Shell Plate, Heat# C9955-2 Initial USE == Average (103, 106.5, 93) ft-lb

== 101 ft-lb B.9.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.9-3.

Table B.9-3 Chemistry Data for Nozzle Shell Plate, Heat# C9955-2 Copper Nickel Source (wt.-%) (wt.-%)

Q_13(a) 0.57 CMTR, Lukens Steel Analysis Note for Table B.9-3:

(a) The chemistry value is based on a ladle analysis since no material check value is available.

Therefore, the chemical content will be defined as shown below going forward:

Nozzle Shell Plate, Heat# C9955-2 Cu Content == 0.13 wt-%

Nozzle Shell Plate, Heat# C9955-2 Ni Content == 0.57 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 28 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.9-1 Nozzle Shell Plate, Heat # C9955-2 Plot of Measured Transverse Direction CVN Data CVGrapb 6.02: Hyperbolic Tangent Curve Printed on 9/14/2021 I: 16 PM A= 47.60 B = 45.40 C =64.65 TO= 65.38 D =0.00 Correlation Coefficient = 0.989 Equation is A+ B * [Tanlt((T*TO)/(C+D1))]

Upper Shelf Energy= 93.00 (Fb,cd) Lower Shelf Energy= 2.20 (FLxed)

Temp@30 ft-lbs= 39.00° F Tcmp:@35 ft-lbs= 47.00° F Temp@50 ft-lbs= 68.90° F Plant: V.C. Summer l\faterial: SA533B1 Heat: C9955-2 Orientation: Trans. Capsule: Unirrad Fluence: 0.00E-t-000 n/cm' 100 ,----,----,----,----,----,----,----,--~-,--~-----

-~

• • • -**~-----* .. ****-***** ..... ----*-*1~*--~-*****- *****-:-**--- --*-**;***-- -* *--*-****.

90 80

--r,,

.,Q I

70 60 4:

bJl 50

~

=

r:-l

~*-****'.-*

40 u

~ 1---*-~*--*** ......... ., ......... ---*****--

30 1----

20

... ,--*--* I 10 I I I 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature (0 F)

CVGmph6.02 09/14/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 29 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.9-1 Nozzle Shell Plate, Heat# C9955-2 Plot of Measured Transverse Direction CVN Data (cont.)

Plant: V.C.Summer Material: SA533B1 Heat: C9955-2 Orientation:' Trans. Capsule:.Unirrad Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature(" F) InputCVN Compui:£dCVN Differential

-20 11.0 8-2 2.'16 40 34.0 30.6 3.36 50 38:0 37.0 1.00 70 43.0 50.8 -7.84 120 85.0 78.9 6.15 212 93.0 92.0 0.96 CVGraph 6.02 09/14/2021 Page2i2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 30 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.9-2 Nozzle Shell Plate, Heat# C9955-2 Plot of Measured Transverse Direction Lateral Expansion Data CVGraph 6.02: Hyperoolic Ta11ge11t Cmve Printed on 9/14/2021 1:35 PM A =38.50 B =37.50 C=73.25 TO =48,78 D =0,00 Correlation Coefficient= 0.993 Equation is A+ B

• rranh((T-TO)/(C+Dl))]

Upper ShclfL.E. = 76.00 (Fixed) Lower ShclfL.E. = 1.00 (fi.<ed)

Tcmp'.g:35 mils= 42.00° F Plant: V.C. Summer Material: SA533B1 Heat: C9955-2 Orientation: Trans. Capsule: Unirrad Flucncc: 0.00E+o00 n/cm' 80 70

--....e (l:l 60

-....=

50 Q

(l:l

=

= 40

~

-=

r:-1

~

J,.c 30

~= 20 10 o l:::::+/-=:+/-:::i::::J..--1_L...1...-...L...i...---1.----1.-L..i..,_...L...i...---1.--i___J

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGmph6.02 09/14/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 31 of 86 Attachment B to PWROG-21037-NP Revision 2 Figure B.9-2 Nozzle Shell Plate, Heat# C9955-2 Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C. Summer Material: SAS33B1 Heat: C9955-2 Orientation: Trans. Capsule: Unlrrad Fluence: 0.00E+000 n/cm' Charpy V-Notch Data Temperature (0 F) Input L. E. Computed L. E. Differential

-20 13.0 10.9 2.05 40 34.0 34.0 -0.03 50 40.0 39.1 0.87 70 45.0 49.1 -4.07 120 71.0 66.6 4.39 212 76.0 75.l 0.86 CVGraph 6.02 09/14/2021 Page 212

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 32 of86 Attachment B to PWROG-21037-NP Revision 2 B.10 V.C. Summer Unit 1 Nozzle Shell Plate, Heat# C0123-2 Tables B.10-1 and B.10-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Nozzle Shell Plate, Heat# C0123-2.

Table B.10-1 Charpy V-Notch Test Data for the Nozzle Shell Plate, Heat# C0123-2 Longitudinal Transverse CVN Impact Lateral CVN Impact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F)

(ft-lb) (mils)

(%) {°F)

(ft-lb) (mils) (%)

-100 5 4 1 -30 21 19 20

-100 5 4 1 -30 16.5 16 25

-100 4(a) 3 1 -30 14(a) 14(a) 15

-50 13 12 10 30 34 33 40

-50 15 15 10 30 41 37 30

-50 15 15 10 30 34(*) 31<*) 35 10 33(a) 36 30 50 41 40 45 10 44 34 30 50 37 35 35 10 61 58 30 50 37 38 50 40 85 61 60 70 41.5(a) 41<*) 50 40 76(*) 68 60 70 55 52 55 40 94 60 60 70 44 43 50 100 120 87 90 120 72(a) 60(*) 60 100 119(*) 85 90 120 75 60 60 100 122 80 90 120 80 66 60 212 }45(a)(b) 95 99 212 97 80 100 212 148 90(a)(b) 99 212 37(a)(b) 78 95 212 158 92 99 212 89 7}(a)(b) 100 Notes for Table B.10-1:

(a) Minimum value used in the CVGRAPH plots in accordance with ASME Code III Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CV GRAPH plots.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 33 of 86 Attachment B to PWROG-21037-NP Revision 2 Table B.10-2 Drop-Weight Test Data for Nozzle Shell Plate, Heat# C0123-2 Test Temperature TNDT Drop-Weights<*>

{°F) {°F)

-10 I-NF

-20 2-NF

-30 1-F -30

-40 1-F

-50 1-F Note for Table B. l 0-2:

(a) NF= "No Fail," F = "Fail".

B.10.1 Determination of the Initial RTNoT Using the data summarized in Tables B.10-1 and B.10-2, the initial RTNnT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction. Charpy V-notch tests were conducted at 30°F, TNDT + 60°F (-30°F + 60°F = 30°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNnT + 60°F would NOT satisfy the criteria.

To precisely determine the temperature at which 50 ft-lb and 35 mils LE were obtained on the specimens, the unirradiated Charpy V-notch data may be plotted and fit using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-2331, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience~ 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNDT.

Tso ft-lb= 74.9°F T35 mils= 45.9°F Tcv =Max [Tso ft-lb, T35mil] =Max [74.9°F, 45.9°F]

Tcv = 74.9°F Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNnT is the higher of TNnT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 34 of86 Attachment B to PWROG-21037-NP Revision 2 RTNoT = Max [TNoT, Tcv - 60°F]

RTNDT = Max [-30°F, 74.9°F - 60°FJ = Max [-30°F, 14.9°F]

Nozzle Shell Plate, Heat# C0123-2 Initial RTNoT = 15°F B.10.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The Transverse (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.10-1 with shear 2: 95%.

Nozzle Shell Plate, Heat# C0123-2 Initial USE = Average (97, 87, 89) ft-lb

= 91 ft-lb B.10.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.10-3.

Table B.10-3 Chemistry Data for Nozzle Shell Plate, Heat# C0123-2 Copper Nickel Source (wt.-%) (wt.-%)

0.12<*) 0.58 CMTR, Lukens Steel Analysis Note for Table B.10-3:

(a) The chemistry value is based on a ladle analysis since no material check value is available.

Therefore, the chemical content will be defined as shown below going forward:

Nozzle Shell Plate, Heat# C0123-2 Cu Content = 0.12 wt-%

Nozzle Shell Plate, Heat# C0123-2 Ni Content = 0.58 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 35 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.10-1 Nozzle Shell Plate, Heat# C0123-2 Plot of Measured Transverse Direction CVN Data CVGraplt 6.02: Hyperbolic Tangent Curve Printed on 9/14/2021 2: IO PM A = 44.60 B = 42.40 C = 91,27 TO= 63.19 D = 0.00 Conelation Coefficient= 0.989 Equation is A+ B * (Tanh((T-TO)/(C+DT))I Upper Shelf Enc1gy = 87.00 (Fixed) Lower Shelf Energy = 2.20 (Fixed)

Tcmp@30 fi-Ibs= 30.50° F Temp(i(J5 fi-lbs= 42.20° F Temp,:?!)50 ft-lbs= 74.90° F Plant: V.C. Summer Material: SA533B1 Heat: C0123-2 Orientation: Trans. Capsule: unirmd Fluence: 0.00E+-000 n/cm' 90 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

50

.. ,* . - ~.

40

"\""

30 20 10 0 .....

I _ - . .......

. - . . . - - ~_

/

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

CVGraplt 6.02 09/14/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 36 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.10-1 Nozzle Shell Plate, Heat# C0123-2 Plot of Measured Transverse Direction CVN Data (cont.)

Plant: V.C. Summer Material: SA533B1 .Heat: C0123-2 Orientation:'Trans. Capsule: unirrad Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature {° F) InputCVN Computed CVN Differential

-30 14.0 11.9 2,06 30 34.0 29.8 4,17 50 31.0 38.5 -1.51 70 41.5 47.8 II -6.26 120 no 68.0 3.96 212 87.0 83.9 3,13 CVGraph 6.02 09/14/2021 Page2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 37 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.10-2 Nozzle Shell Plate, Heat# C0123-2 Plot of Measured Transverse Direction Lateral Expansion Data CVGrapl16.02: Hyperbolic Tangent Curve Printed on 9/14/2021 2: 12 PM A= 36,00 B = 35..00 C =97.41 TO= 48,63 D = 0.00 Correlation Coefficient-' 0.995 Equation is A+ B

• ffanh((T*TIJ)/(C+DT))J Upper ShclfL.E. =71.00 (Fb:cd) LowcrShclfL.E. 1.00 (Fixed)

Tcmp:@35 mils= .is.90° F Plant: V,C, Summer Material: SA533B1 Heat; C012J..2 Orientation: Tranli. Capsule: unirrad Flucnec: O.OOE+oOO n/cm*

80 70

-.-...a

['-I 60

-....=

0

~

so

=

= 40

~

-.!='""

~

30

~

=

20 10 o l=::i=:::t=:::i:..-1.--1._L..1.-..L...L-1.-.i.-L.J.-..L...L-1.--1._.J

-300 -200 -100 0 100 200 300 400 500 600 Temperature{° F)

CVGn,ph 6.02 09/14/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 38 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.10-2 Nozzle Shell Plate, Heat# C0123-2 Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C.Summer Material: SA533B1 Heat' C0U3-2 Orientation: Trans. Capsule: unirrad Fluence: 0.00E+000 nlcm*

Charpy V-Notch Data Temperature {° F) InputL. E. Computed L. E. Differential

-30 14.0 '12,6 1.38 30 31.0 29.4 1.61 50 35.0 36.5 -l.4g 70 41.0 43.6* -2.56 120 60.0 57.9 2.14 212 71.0 68.6 I 2.36 CVGraph 6.02 09/14/2021 Page2/2

""* This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 39 of 86 Attachment B to PWROG-21037-NP Revision 2 B.11 V.C. Summer Unit 1 Intermediate Shell Plate, Heat# A9154-1 Tables B.11-1 and B .11-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Intermediate Shell Plate, Heat# A9154 1. This data is combined with the additional data available from V.C. Summer Unit 1 surveillance program documented in WCAP-9134.

Table B.11-1 Charpy V-Notch Test Data for the Intermediate Shell Plate, Heat# A9154-1 Longitudinal Transverse CVNlmpact Lateral CVNimpact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F)

(ft-lb) (mils) (%) (OF)

(ft-lb) (mils)

(%)

-100 5 5 1 -40 7.5(a) 2C*) 9

-100 3(a) 6 1 -40 9 4 10

-100 4 2Ca) 1 -20 12.5(*) 15(a) 10

-40 7_5(a) 3(a) 8 -20 20 19 20

-40 27 16 14 -20 19 18 20

-20 17 18 20 0 29(a) 22(a) 13

-20 10<*) 16 20 0 31 26 16

-20 15 13(a) 20 40 36 34 35

-20 20 14 20 40 41 40 45 0 49_5(a) 35(a) 20 40 38 37 30 0 55 40 25 40 25 24 42 10 54 46 40 40 23(a) 22<*) 25 10 50 44 40 40 35 28 23 10 4g(a) 42<*) 40 70 56 52 60 15 60 44 25 70 36<*> 40 40 15 56.5(*) 42<*) 25 70 40 39(a) 40 40 70 72 60 70 48 46 56 40 88 58 60 70 47 42 51 40 70 57 60 80 60 51 71 40 86 61 55 80 55(a) 49(a) 66 40 10<*) 51 (a) 43 90 51_5<*) 52 50 70 so<*) 78 80 90 60.5 51 (a) 60 70 107 81 80 90 58 51 60 70 112 66<*) 80 100 68 61 75 75 93_5(a) 68(*) 61 100 5s<*l 50(*) 66 75 114 79 75 120 56(*) 57(a) 65 100 118.5 77 77 120 64 57 60 100 100<*) 69(*) 68 120 74 65 60

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 40 of86 Attachment B to PWROG-21037-NP Revision 2 Table B.11-1 Charpy V-Notch Test Data for the Intermediate Shell Plate, Heat# A9154-1 (cont.)

Longitudinal Transverse CVN Impact Lateral CVN Impact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F) (%) (OF) (%)

(ft-lb) (mils) fft-lb) (mils) 125 127(a) 84(a) 100 125 69(a)(b) 61 (a) 98 150 126.S(a) 86 100 150 82(a) 69(a) 100 150 131 85 100 210 76 60 100 210 140.5 84 100 210 70_5(a) 58(a)(b) 100 210 132.5<*l 83(a) 100 210 72 58 100 212 121 (a)(b) 96 99 212 82.5 70 100 212 144 97 99 212 76.5(a) 69 100 212 144 92(a)(b) 99 212 83 68(a) 100 Notes for Table B.11-1:

(a) Minimum value used in the CVGRAPH plots in accordance with ASME Code III Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CV GRAPH plots.

Table B.11-2 Drop-Weight Test Data for Intermediate Shell Plate, Heat# A9154-1 Test Temperature TNDT Drop-Weights<*l (OF) {°F)

-10 2-NF

-20 1-F

-20

-30 1-F

-40 1-F Note for Table B.11-2:

(a) NF= "No Fail," F = "Fail".

B.11.1 Determination of the Initial RTNDT Using the data summarized in Tables B.11-1 and B.11-2, the initial RTNnT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 40°F, TNnT + 60°F (-20°F + 60°F = 40°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNnT + 60°F would NOT satisfy the criteria.

To precisely determine the temperature at which 50 ft-lb and 35 mils LE were obtained on the specimens, the unirradiated Charpy V-notch data may be plotted and fit using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 41 ofS6 AttachmentB to PWROG-21037-NP Revision 2 as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-2331, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience?: 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNDT*

T50ft-lb = SO.S P0 T35 mils 48. 7°F Tcv Max [Tso ft-lb, T3smil] = Max [80.S 0 P, 48.7°P]

Tcv S0.8°P Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNDr is the higher of TNnT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

RTNoT = Max [TNnT, Tcv - 60°F]

RTNDT = Max [-20°F, 80.S°F - 60°F] = Max [-20°F, 20.8°F]

Intermediate Shell Plate, Heat# A9154-1 Initial RTNDT = 21°F B.11.2 Determination of the Initial USE The current 10 CPR 50, Appendix G requirements specify that USE be calculated based onASTM ElS5-S2.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data?: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The Transverse (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.11-1 with shear ?: 95%.

Intermediate Shell Plate, Heat# A9154-1 Initial USE = Average (69 ,82, 76, 70.5, 72, 82.5, 76.5, 83) ft-lb 76 ft-lb B.11.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.11-3.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 42 of 86 AttachmentB to PWROG-21037-NP Revision2 Table B.11-3 Chemistry Data for Intermediate Shell Plate, Heat# A9154-1 Copper Nickel Source (wt.-%) (wt.-%)

0.10 0.51 CMTR, Lukens Steel Analysis Therefore, the chemical content will be defined as shown below going forward:

Intermediate Shell Plate, Heat# A9154-1 Cu Content = 0.10 wt-%

Intermediate Shell Plate, Heat# A9154-1 Ni Content = 0.51 wt-%

• • • This record was final approved on 3/6/2023, 12:36:1'6 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 43 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.11-1 Intermediate Shell Plate, Heat# A9154-1 Plot of Measured Transverse Direction CVN Data CVGraph 6.02: Hypeibolic Tangent Curve Printed on 9/15/2021 8:49 Ai'v!

A= 35.60 B = 33,-'0 C = 71.14 TO= 47,98 D = 0.00 Conelation CoeITTcient =0. 949 Equation is A+ B

• fTanh((r-TO)/(C+DT))]

Upper ShclfEncrgy =69.00 (Fb:cd) Lower ShclfEocrgy = 2.20 (Fixed)

Temp@J0 n-lbs= 36.00° l' Temp@.35 fl-lbs= 46.80° F Temp,:@50 fl-lbs= 80,80° l' Plant: V.C. Summer Material: SAS33B1 Heat: A91S4-1 Orientation: Trnns. Capsolc: unirrad Flueru:c: 0.00.E+oOO ni'~'lll*

o-....__.........._.....__...__,__.,_......______....__..._....._.,_....._.....___.........

-300 -200 0 100 200 300 400 500 600 Temperature {° F)

CVGmph6.02 09/15/2021 Page l/2

""'* This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 44 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.11-1 Intermediate Shell Plate, Heat# A9154-1 Plot of Measured Transverse Direction CVN Data (cont.)

Plant: V.C. Swnmer Material: SA533B1 Heat: A9154-1 Orientation: Trans. Capsule: unirrad Fluence: O.OOE+OOO nlcm*

Charpy V-Notch Data Temperature {° F) InputCVN Computed CVN I Differential AO 7:5 7.4 0.11

-26 12.5 10.8 1.69 0 29.0 16.0 13.04 I

40 23.0 31.9 i

-8.87 70 36.0 45.6 09.62 80 55.0 49.7 5.31 90 51.5 53.3 -1.81 100 58.0 56.4 1.56 120 56.0 61.2 -521 125 69.0 62.1 6.87 150 82.0 65.4 16.59 210 70.5 68:3 2.20 212 76.5 68:3 8.16 CVGraph 6.02 09/15/2021 Page2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 45 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.11-2 Intermediate Shell Plate, Heat# A9154-1 Plot of Measured Transve1*se Direction Lateral Expansion Data CV Graph 6.02: Hyperbolic Taagern Curve Printed on W15/2021 8:51 AM A= 29.50 B = 28.50 C =62.77 TO= 36.43 D = 0.00 Correlruion Coefficient= 0.961 Equation is A+ B

• ffanh((T*'IO)/(C+DT))j Upper ShelfL.E. = 58.00 (Fixed) Lower Shelf L.E. = LOO (Fixed)

Temp@i35 mils= 4&.70° F Plant: V.C. Summer Material: SA533Bl Heat: A9t54-1 Orientation: Trnru. Capsule: unirrad Flncncc: O.OOE-1-000 ntcm*

60

-....e

~ 50

-....=

C')

11'.l 40

=

=

~

-....=-

ri1ii1

~

30

= 20

.:I 10 o t:=::c:=+/-::::::::t:::::I::.........i~L_.__..L...i........l.--1_L..i......L...i........l.___i__J

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGmph6.02 09/15/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 46 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.11-2 Intermediate Shell Plate, Heat# A9154-1 Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C.,Summer Material: SA533B1 .Heat: A9154-1 Orientation: Trans. Capsule: unirrad Fluence: O.OOE+OOO n/cm' Charpy V-Notch Data Temperature (" F) InputL. E. Computed L. E. Differential

-40 2.0 5.6 -3.59

~20 15.0 9.1 5.90 0 22.0 14.6 7.40 40 22.0 31.l -9.12 70 39.0 43.4 4.44 80 49.0 46.6 2.38 90 51.0 49.2 1.75 100 50,0 :51.4 -1.36 120 57.0 54.3 2,72 125 61.0 54.8 6.20 150 69.0 56.5 12.49 210 58,0 57:8 i 0.23 212 68.0 57.8 10.21 CVGTaph 6.02 09/1512021 Page212

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 47 of86 Attachment B to PWROG-21037-NP Revision 2 B.12 V.C. Summer Unit 1 Intermediate Shell Plate, Heat# A9153-2 Tables B.12-1 and B.12-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Intermediate Shell Plate, Heat# A9153-2.

Table B.12-1 Charpy V-Notch Test Data for the Intermediate Shell Plate, Heat# A9153-2 Longitudinal Transverse CVN Impact Lateral CVNimpact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F) (%) (OF) (%)

(ft-lb) (mils) (ft-lb) (mils)

-100 9 2<a) 1 -20 14(a) 21 20

-100 3(a) 6 1 -20 26 23 25

-100 8 5 1 -20 18 16(a) 25

-20 54(a) 4z(a) 20 20 43 38 35

-20 58 45 20 20 42_5(a) 36 35

-20 54 44 20 20 47 35(a) 40 10 68 52 30 40 59 49 40 10 56(a) 58 30 40 51 42(a) 45 10 74 45(a) 30 40 so<*) 43 50 40 82 63 50 70 65(*) 56 70 40 83 64 50 70 71 59 80 40 82(a) 63(a) 50 70 68 55(a) 65 70 108 72(a) 60 120 93 74 80 70 107 74 60 120 9o(a) 7l(a) 80 70 IOS(a) 74 60 120 94 76 80 212 142 92(a)(b) 99 212 101 (a)(b) 69(a)(b) 100 212 146 97 99 212 108 78 100 212 136(a)(b) 96 99 212 111.5 72 100 Notes for Table B.12-1:

(a) Minimum value used in the CV GRAPH plots in accordance with ASME Code Ill Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CVGRAPH plots.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 48 of86 Attachment B to PWROG-21037-NP Revision 2 Table B.12-2 Drop-Weight Test Data for Intermediate Shell Plate, Heat# A9153-2 Test Temperature TNDT Drop-Weights<*>

(OF) (OF) 1-NF

-10 2-NF -20

-20 1-F Note for Table B.12-2:

(a) NF= "No Fail," F = "Fail".

B.12.1 Determination of the Initial RTNDT Using the data summarized in Tables B.12-1 and B.12-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 40°F, TNoT + 60°F (-20°F + 60°F = 40°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNDT is the initial reference temperature RTNDT, However, since the Charpy V-notch tests at TNoT + 60°F met the ASME Section III criterion with no margin, it was decided to verify the RTNoT by plotting and fitting the unirradiated Charpy V-notch data using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-2331, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience 2: 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNoT, Tso ft-lb= 40.4°F T35 mils= 22.5°F TCv = Max [Tso ft-lb, T35 mil] = Max [40.4 °F, 22.5°F]

Tcv = 40.4°F Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNoT is the higher of TNDT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

RTNDT = Max [TNDT, Tcv - 60°F]

RTNoT = Max [-20°F, 40.4°F - 60°F] = Max [-20°F, -19.6°F]

Intermediate Shell Plate, Heat# A9153-2 Initial RTNoT = -20°F

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 49 of86 Attachment B to PWROG-21037-NP Revision 2 B.12.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E 185 manual (2016 version). Using the guidelines in ASTM E 185-82 and E185-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The Transverse (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.12-1 with shear~ 95%.

Intermediate Shell Plate, Heat# A9153-2 Initial USE = Average (101, 108, 111.5) ft-lb

= 107 ft-lb B.12.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.12-3.

Table B.12-3 Chemistry Data for Intermediate Shell Plate, Heat# A9153-2 Copper Nickel Source (wt.-%) (wt.-%)

0.09 0.45 CMTR, Lukens Steel Analysis Therefore, the chemical content will be defined as shown below going forward:

Intermediate Shell Plate, Heat# A9153-2 Cu Content = 0.09 wt-%

Intermediate Shell Plate, Heat# A9153-2 Ni Content = 0.45 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 50 of 86 Attachment B to PWROG-21037-NP Revision 2 Figure B.12-1 Intermediate Shell Plate, Heat # A9153-2 Plot of Measured Transverse Direction CVN Data CVGmph 6.02: Hyperbolic Tangent Cutvc Printed on 9/15/20218:56 AM A =Sl.60 B =49,40 C= 77,17 T0=-12.87 D =0.00 Correlation Coefficient = 0. 995 Equation is A+ B * [Tanh((T-T0)/(C+D11)]

Upper Shelf Energy = 101.00 (Fixed) Lower Shelf Energy = 2.20 (Fixed)

Ternp@30 ft-lbs= 6. 70° F Temp@35 ft-lbs= 15.90° F Tcmp@50 ft-lbs= 40.-10° F Plant: V.C. Summer Material: SAS33B1 Heat: A91SJ-2 Orientation: Trans. Capsule: unirrad Flucnce: 0.00E+o00 ntcm*

110 n

100 '.

90 80 r ll

,.Q

- 4 ..... - - - -

• 70 I

ct:

60

-=

~

~

J:;i;l 50

• * * * **** * *J: **>****

z ------t----t----+---1---+----i---------------

u 40

.,. /:.. . ..

30 - ~ - - + - - . ; _ _ - + - ~ - - - - - - ' - - - - + - - ' - - - i f - - ~ - - - - - - + - - ' - - - - 1

.... *r"i**

20 1-----+---+-----'**:/o--o-++--'--+------'--+--'--.f-..-...-'.-. -.- - - - + - - - - ' - - - I 10 1-----+--.;__-+-~-1/4----'---+--'----+--'---if----+-----+--'---I

..............:...~V; 0 .._....,..___,i,_..i,._...__._......1---,1,*_..i,._.,1;_ _._....._ _ _, _,*-..i..._....;_..i,._.,1;_ _.

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGraph 6.02 09/15/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 51 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.12-1 Intermediate Shell Plate, Heat# A9153-2 Plot of Measured Transverse Direction CVN Data (cont.)

'Plant: V.C.,Summer Material: SA533Bl Heat: A9153-2 Orientation: Trans. Capsule: unirrad Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature {° F) InputCVN Computed CVN Differential

-20 14.0 18.4 A.40 20 42.5 37.4 5.12 40 50.0 49.8 0.23 70 65,0 68.3 -3.29 120 90.0 89.2 0.79 212 101.0 99.8 1.22 CVGraph 6.02 09/15/2021 Page 2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 52 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.12-2 Intermediate Shell Plate, Heat # A9153-2 Plot of Measured Transverse Direction Lateral Expansion Data CVGmph 6.02: Hypcroolic Tangent Curve Printed on 9/15/2021 11:28 AM A= 51.10 B =-18.90 C = 90.58 TO =67.18 D = 0.00 Correlation Coefficient= o. 996 Equation is A + B " [Tanli((T-TO}/(C+DT))J Upper ShclfEucrgy = 100.00 (Fixed) Lower Shelf Energy= 2.20 (Fixed)

Tcmp'.{?,30 ft-lbs= 2.,.40°F Tcmp'@35 ft-lbs= 36.30° F Tcmp@S0 ft-lbs= 65.200 F Plant: V.C. Summer Material: SA533B1 Heat: C9923-l Orientation: Tr:m... Cupsulc: unirr.id Flucucc: 0.00E+o00 ntcm*

0 L - - J . . -..........L.--'---.a.-.i..._,a.-..i....--i.-..i.........1.-....... ---i-_,_......~...... -...

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGrapli 6.(>2 09/15/2021 Page 112

-* This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 53 of 86 Attachment B to PWROG-21037-NP Revision 2 Figure B.12-2 Intermediate Shell Plate, Heat# A9153-2 Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C. Summer Material: :!'lA533Bl Heat: A9\53-2 Orientation: Trans. Capsule: unirrad Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature {° F) InputL. E. Computed L. E. Differential

-20 16.0 15.4 0.61 20 35.0 33.7 1.31 40 42.0 44.0 -1.99 70 55.0 56.3 -1.29 120 71.0 65.8 5.17 212 69.0 68.8 0.19 CVGraph 6.02 09/15/2021 Page 2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 54 of86 Attachment B to PWROG-21037-NP Revision 2 B.13 V.C. Summer Unit 1 Lower Shell Plate, Heat# C9923-1 Tables B.13-1 and B.13-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Lower Shell Plate, Heat # C9923-1.

Table B.13-1 Charpy V-Notch Test Data for the Lower Shell Plate, Heat# C9923-1 Longitudinal Transverse CVNimpact Lateral CVNimpact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F) (%) {°F) (%)

(ft-lb) (mils) (ft-lb) (mils)

-100 7(a) 5(a) 10 -30 11 9 10

-100 10 5 10 -30 9(a) g{a) 5

-100 9 6 10 -30 12 11 10

-75 35 25 20 30 37 34 30

-75 17 9(a) 20 30 42.5 37 35

-75 12(a) 15 20 30 35(a) 34(a) 30

-50 52 40 50 50 47 43 40

-50 60 45 50 50 44 40 30

-50 44(a) 38(*) 50 50 43.5(a) 39(a) 35 10 92 70 80 70 68 57 55 10 7o(a) 64 80 70 51 47 50 10 82 61<*> 80 70 5l(a) 47(a) 50 40 92 77 80 120 74.5(*) 63(a) 60 40 100 76(a) 80 120 81 64 70 40 89(a) 78 80 120 80 63 70 212 148 96 99 212 104 83 100 212 147(a)(b) 96(a)(b) 99 212 114 81 95 212 150 96 99 212 l00(a)(b) 77(a)(b) 95 Notes for Table B.13-1:

(a) Minimum value used in the CVGRAPH plots in accordance with ASME Code III Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CVGRAPH plots.

... This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 55 of 86 Attachment B to PWROG-21037-NP Revision 2 Table B.13-2 Drop-Weight Test Data for Lower Shell Plate, Heat# C9923-1 Test Temperature TNDT Drop-Weights(a)

{°F) {°F) 10 1-NF 0 1-NF

-20 2-NF -30

-30 1-F

-40 1-F Note for Table B.13-2:

(a) NF = "No Fail," F ="Fail".

B.13.1 Determination of the Initial RTNDT Using the data summarized in Tables B.13-1 and B.13-2, the initial RTNDT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight T NDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 30°F, TNnr + 60°F (-30°F + 60°F 30°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F would NOT satisfy the criteria.

To precisely determine the temperature at which 50 ft-lb and 35 mils LE were obtained on the specimens, the unirradiated Charpy V-notch data may be plotted and fit using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-2331, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience;:::: 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNDT*

Tso ft-lb 65.2°F T35 mils 40.5°F TCv = Max [Tso ft-lb, T35 mil] = Max [65.2°F, 40.5°F]

Tcv = 65.2°F Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNDT is the higher of TNDT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 56 of86 Attachment B to PWROG-21037-NP Revision2 RTNoT = Max [TNoT, Tcv - 60°F]

RTNDT = Max [-30°F, 65.2°F - 60°F) = Max [-30°F, 5.2°F]

Lower Shell Plate, Heat# C9923-1 Initial RTNDT = 5°F B.13.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data?: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The Transverse (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.13-1 with shear?: 95%.

Lower Shell Plate, Heat# C9923-1 Initial USE =Average (104, 114, 100) ft-lb

= 106 ft-lb B.13.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.13-3.

Table B.13-3 Chemistry Data for Lower Shell Plate, Heat# C9923-1 Copper Nickel Source (wt.-%) (wt.-%)

0.08 0.41 CMTR, Lukens Steel Analysis Therefore, the chemical content will be defined as shown below going forward:

Lower Shell Plate, Heat# C9923-1 Cu Content = 0.08 wt-%

Lower Shell Plate, Heat# ~9923-1 Ni Content = 0.41 wt-%

.,.. This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 57 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.13-1 Lower Shell Plate, Heat # C9923-1 Plot of Measured Transverse Direction CVN Data CVGraph 6.02: Hyperbolic Tangent Cwve Printed on 9/15/2021 11:28 AM A =51.10 B =48.90 C =90,58 TO =67.18 D =0,00 Correlation Coefficient= 0. 996 Equation is A+ B * [Tanh((T-TO)/(C+DT))]

Upper Shelf Energy= 100.00 (Fb.cd) Lower Shelf Energy= 2.20 (Fb:cd)

Temp@)30 fl-lbs= 25.40° F Temp@J5 ft-lbs= 36.30° F Tcmp@.50 fl*lbs= 65.20° F Plant: V.C. Summer Material: SA533B1 Heat: C9923-t Orientation: Trans. Capsule: unirrnd Fluencc: 0,00E+000 n/cm*

110 ...---...----.----.----.----.---.......-----...---.----

• • • • • • t---**

50 40 30 20 I

10 -----t---i*[,_/_'-----+- ....._....-,--

~vv __ _....,____,* ____,* ____,* ____. , ____;__

- + .- - - - - - , - - - - l r - - - , - - - t - - - - - t 0  !:=========..-,_:-_ _______

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

CVGmph6.02 09/15/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 58 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.13-1 Lower Shell Plate, Heat# C9923-1 Plot of Measured Transverse Direction CVN Data (cont.)

Plant: V.C. Summer Material: SA533B1 Heat: C9923-1 Orientation: Trnns. Capsule: unirrad Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature {° F) InputCVN Computed CVN Differential

-30 9.0 12.4 -3.44 30 35.0 32.l 2.91 50 43.5 41.9 1.56 70 51.0 52.6 -1.62 120 74.5 76.8 -2.27 212 JOO.O 96.2 3.84 CVGraph 6.02 09/l5/202l Page2/2

• "" This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 59 of 86 Attachment B to PWROG-21037-NP Revision 2 Figure B.13-2 Lower Shell Plate, Heat # C9923-1 Plot of Measured Transverse Direction Lateral Expansion Data CVGrapb 6.02: Hyperbolic Tangent Cmve Printed on 9/15/2021 11:30 AM A =39.00 B =38.00 C =85.82 TO =49.56 D =0.00 Correlation Coefficient = 0. 995 Equation is A+ B * (Tanb((T-TO)/(C+D1))]

Upper SbclfL.E. = 77.00 (Fb;cd) Lower ShclfL.E. = 1.00 (FLxcd)

Temp'.f/J35 mils= -10.50° F Plant: V.C. Summer Material: SA533B1 Heat: C9923-t Orientation: Trans. Capsule: unirrad Flucncc: O.OOE+oOO nlcm' 80 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

O__;_:--+-~-,---r-------t 70 1----,.--+------'l----+-----I--L---+----+---,--+-----+--.---f

• • 7~~-

,_ 60 ***/

1----,.--+---,---1-~--+---,---ir---;----,-----,--+---,---+--.---f

! 50

• /*****

• I

~

40 t{

= 30 j *******************/

20

. - - . ~- ---- - .... : ........... :*/

IO

.. . . /~-  :

o l:::::::i::::::+/-:::::i:::...L......i-L-'--...L_.i...-1.......i-L-'--...L_.i...-1.---1.__J

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGrapb6.02 09/15/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

7 Westinghouse Non-Proprietary Class 3 Page 60 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.13-2 Lower Shell Plate, Heat # C9923-1 Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C. Summer Material: SA533B1 Heat: C9923-1 Orientation: Trans. Capsule: unfrrad Fluence: 0.00E+000 n/cm*

Charpy V-Notch Data Temperature{° F) InputL. E. Computed L. E. Differential

-30 8.0 11.3 -3.29 30 34.0 30.5 3.51 50 39.0 39.2 -0.20 70 47.0 47.9 -0.89 120 63.0 64.7 -1.67 212 77.0 75.3 1.69 CVGraph 6.02 09/15/2021 Page 2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 61 of 86 Attachment B to PWROG-21037-NP Revision 2 B.14 V.C. Summer Unit 1 Lower Shell Plate, Heat# C9923-2 Tables B.14-1 and B.14-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for Lower Shell Plate, Heat# C9923-2.

Table B.14-1 Charpy V-Notch Test Data for the Lower Shell Plate, Heat# C9923-2 Longitudinal Transverse CVNimpact Lateral CVN Impact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F)

(ft-lb) (mils)

(%) (OF)

(ft-lb) (mils)

(%)

-100 4(a) 3 1 -10 23(a) 27 25

-100 5 2<*) 1 -10 31 28 20

-100 5 2 1 -10 33.5 29 25

-50 8 10 1 40 56 48 50

-50 6(a) 7(a) 1 40 42.5 37 35

-50 12 9 1 40 37_5(a) 34(a) 30

-20 42 3o(a) 40 50 4o(a) 38(a) 30

-20 50 37 40 50 46 42 45

-20 35(a) 39 40 50 53 45 45 10 56 44(a) 50 70 55 50 55 10 56 46 50 70 5o(a) 45(a) 50 10 55(a) 46 50 70 51 46 55 40 86 64 70 120 82 68 80 40 76<*) 61 (a) 70 120 79(a) 65(a) 75 40 85 66 70 120 84 74 85 212 164 95 99 212 93 76(a)(b) 100 212 164 95(a)(b) 99 212 94 78 100 212 155(a)(b) 96 99 212 88(a)(b) 77 100 Notes for Table B.14-1:

(a) Minimum value used in the CVGRAPH plots in accordance with ASME Code III Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CVGRAPH plots.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 62 of86 Attachment B to PWROG-21037-NP Revision 2 Table B.14-2 Drop-Weight Test Data for Lower Shell Plate, Heat# C9923-2 Test Temperature TNDT Drop-Weights<*>

(OF) {°F) 10 I-NF 0 2-NF

-10 1-F -10

-20 1-F

-20 1-F Note for Table B.14-2:

(a) NF= "No Fail," F = "Fail".

B.14.1 Determination of the Initial RTNDT Using the data summarized in Tables B.14-1 and B.14-2, the initial RTNDT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight T NDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 50°F, TNDT + 60°F (- l 0°F + 60°F = 50°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNoT + 60°F would NOT satisfy the criteria.

To precisely determine the temperature at which 50 ft-lb and 35 mils LE were obtained on the specimens, the unirradiated Charpy V-notch data may be plotted and fit using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-2331, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience~ 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNoT, Tso ft-lb= 63.6°F Ls mils= 33.9°F Tcv = Max [Tsoft-Ib, T3smir] = Max [63.6°F, 33.9°F]

Tcv = 63.6°F Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNoT is the higher of TNoT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

- 7 Westinghouse Non-Proprietary Class 3 Page 63 of 86 Attachment B to PWROG-21037-NP Revision2 RTNnT = Max [TNnT, Tcv - 60°F]

RTNDT=Max [-10°F, 63.6°F- 60°FJ =Max [-10°F, 3.6°F]

Lower Shell Plate, Heat# C9923-2 Initial RTNoT = 4°F B.14.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The Transverse (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.14-1 with shear 2: 95%.

Lower Shell Plate, Heat# C9923-2 Initial USE = Average (93, 94, 88) ft-lb

= 92 ft-lb B.14.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.14-3.

Table B.14-3 Chemistry Data for Lower Shell Plate, Heat# C9923-2 Copper Nickel Source (wt.-%) (wt.-%)

0.08 0.41 CMTR, Lukens Steel Analysis Therefore, the chemical content will be defined as shown below going forward:

Lower Shell Plate, Heat# C9923-2 Cu Content = 0.08 wt-%

Lower Shell Plate, Heat# C9923-2 Ni Content = 0.41 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 64 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.14-1 Lower Shell Plate, Heat# C9923-2 Plot of Measured Transverse Direction CVN Data CVGrapll 6.02: Hyperbolic Tangent Cutve Printed on 9/15/2021 11:33 AM A = 45,10 B = -12.90 C = 83.59 TO = 53.99 D = 0.00 Correlation Coefficient= 0.988 Equation is A+ B * [Tanh((T-TO)/(C+DT))l Upper Shelf Energy= 88.00 (Fixed) Lower Shelf Energy =2.20 (Fb,cd)

Temp@.30 ft-lbs= 23.30° F Tcmp@.'.15 ft-lbs= 34.00° F Tcmp!@50 fl-lbs= 63.60° F Plant: V.C. Summer Material: SA533B1 Heat: C9923-2 Orientation: Trans. Capsule: unirrad Flucncc: 0.00E.f-000 n/cm1 90 80 70 I

.c 60

~

I

¢::

>. 50

-z=

r-1 bJ)

(jj 40

• --*c*----

'C' ......

-f-

__ { , . * ..... , . . . . . . . . ---*

u 30 20 10 0 _____________..____.__.....,______.____._......______.___________.

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGraph6.02 09/15/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 65 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.14-1 Lower Shell Plate, Heat# C9923-2 Plot of Measured Transverse Direction CVN Data (cont.)

Plant: V.C. Summer Material: SA533B1 .Heat: C9923-2 Orientation: Trans. Capsule: unirrad Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature {° F) InputCVN Computed CVN Differential

-10 23.0 17.5 5.54 50 40.0 43.1 -3.05 40 37.5 38.0 -0.49 70 50.0 53.2 -3.22 120 79.0 73.3 5.66 212 88.0 86.1 1.91 CVGraph 6.02 09115/2021 Page 2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 66 of86 Attachment B to PWROG-21037-NP Revision2 Figure B.14-2 Lower Shell Plate, Heat# C9923-2 Plot of Measured Transverse Direction Lateral Expansion Data CVGmpb 6.02: Hyperoolic Tangent Curve Printed on 9/15/Z021 11:35 AM A= 38.50 B =37.50 C = 109.89 TO = 44.13 D =0,00 Correlation Coefficient= 0.979 Equation is A+ B * (Tanh((T-TO)/(C+D1))]

Upper ShclfL.E. = 76.00 (Fixed) Lower SbclfL.E. = LOO (Fbred)

Temp@35 mils= 33.900 F Plant: V.C. Summer Material: SA533B1 Heat: C!l923-2 Orientation: Trans. Capsule: unirrad Flucncc: o.OOE+o00 ntcm*

~

i,:i 30 1-----'---+-------+-...;....-r+----+----'--+----+---+-------+---'---t

=

~ 20 ----1---'----1-----1-+---'--+--'--+-_..;.--+-----+----+----f 0 1=::t:::::t:::....._..L...........L--i..--1___,l_L_.,__J__;__L....i...._j___L_J

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGraph 6.02 09/15/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 67 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.14-2 Lower Shell Plate, Heat# C9923-2 Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C. Summer Material' SA533B1 Heat: C99,23-2 Orientation: 'Trans. Capsule: unlrrad- Fluence: 0.00E+000 n/cm*

Charpy V-Notch Data Temperature {° F) InputL. E. Computed L. E. Differential

-10 27.0 21.4  ! 5.61 i

50 3f0 40.5 '2.50 40 34.0 37.l -309 70 45.0 47:2 -2.17 120 65.0 60.9 4.07 212 76.0 72.6 3.37 CVGraph6.02 09/15/2021 Page212

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 68 of 86 Attachment B to PWROG-21037-NP Revision 2 B.15 V.C. Summer Unit 1 Transition Ring Plates, Heat# A9249-1 Tables B.15-1 and B.15-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for the Transition Ring Plates.

Table B.15-1 Charpy V-Notch Test Data for the Transition Ring Plates, Heat# A9249-1 Longitudinal Transverse CVN Impact Lateral CVN Impact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F) (%) {°F) (%)

(ft-lb) (mils) (ft-lb) (mils)

-100 6 6 10 -100 11 6 10

-100 6 6 10 -100 6(a) 3(a) 10

-100 6(a) 6(a) 10 -100 7 4 10

-50 38 29 20 -50 2s<a) 27(a) 30

-50 21 23(a) 20 -50 30 29 30

-50 14(a) 32 20 -50 32 31 30

-20 63 46 40 -20 54 43 40

-20 46(a) 39(a) 40 -20 36(a) 36(a) 40

-20 60 51 40 -20 39 46 40 10 96 65Cal 70 10 60 51 50 10 82 80 70 10 50 45 50 10 so<*l 67 70 10 45(a) 45(a) 50 40 115 73 80 40 61 46<*) 50 40 gg(a) 72(a) 80 40 5s<*l 50 50 40 108 84 80 40 61 52 50 212 163 93 99 212 108 88 99 212 160 91(a)(b) 99 212 103(a)(b) S0(a)(b) 99 212 126(a)(b) 92 99 212 111 81 99 Notes for Table B.15-1:

(a) Minimum value used in the CVGRAPH plots in accordance with ASME Code III Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CVGRAPH plots.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 69 of86 AttachmentB to PWROG-21037-NP Revision 2 Table B.15-2 Drop-Weight Test Data for Transition Ring Plates, Heat# A9249-1 Test Temperature TNDT Drop-Weights(a)

{°F) {°F)

-20 I-NF

-30 2-NF -40

-40 1-F Note for Table B.15-2:

(a) NF "No Fail," F = "Fail".

B.15.1 Determination of the Initial RTr,;1>T Using the data summarized in Tables B.15-1 and B.15-2, the initial RTNDT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT ( or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 10°F, which is less than TNoT + 60°F (-40°F + 60°F 20°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F would NOT satisfy the criteria.

To precisely determine the temperature at which 50 ft-lb and 35 mils LE were obtained on the specimens, the unirradiated Charpy V-notch data may be plotted and fit using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-2331, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience 2': 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNDT, Tsoft-lb 17.9°F Ls mils = -1 l.2°F Tcv = Max [Tsoft-Ib, TJsmi!] Max [17.9°F, -l 1.2°F]

Tcv = 17.9°F Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNoT is the higher of TNnT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

RTNnT Max [TNDT, Tcv - 60°F]

RTNoT=Max [-40°F, 17.9°F - 60°F] Max [-40°F, -42.l°F]

Transition Ring Plates Initial RTNDT -40°F

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 70 of86 Attachment B to PWROG-21037-NP Revision 2 B.15.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E185-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM El85-82 and E 185-16, the average of all Charpy data?: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out offamily' data was not necessary for this material. The Transverse (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.15-1 with shear::: 95%.

Transition Ring Plates Initial USE = Average (108,103,111) ft-lb

= 107 ft-lb B.15.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.15-3.

Table B.15-3 Chemistry Data for Transition Ring Plates, Heat# A9249-1 Copper Nickel Source (wt.-%) (wt.-%)

- 0.53 CMTR, Lukens Steel Analysis Generic value based on a mean plus one standard deviation analysis of the high 0.172 - copper A533, Grade B, Class l, plate materials contained in Table G.2 of ORNL/lM-2006/530.

Therefore, the chemical content will be defined as shown below going forward:

Transition Ring Plates Cu Content = 0.172 wt-%

Transition Ring Plates Ni Content = 0.53 wt-%

• "" This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 71 of 86 Attachment B to PWROG-21037-NP Revision 2 Figure B.15-1 Transition Ring Plates Plot of Measured Transverse Direction CVN Data CVGraph6.02: Hyperbolic Tangent Cmve Printed on 9/l6/202l ll:14 AM A= 52.60 B = 50.40 C = 110.46 TO = 23,54 D = 0,00 Correlation Coefficient= 0. 993 Equation is A+ B * [Tanh((T*TO)/(C+D1))J Upper Shelf Energy= 103.00 (Fixed) Lower Shelf Energy = 2.20 (Fixed)

Temp@.30 ft-lbs=-29.70° F Tcmp@."!35 fl-lbs=-16.70° F TcmJ>@,50 ft-lbs= 17.90° F Plant: V.C, Summer Material: SA533B1 Heat: A9249-l Orientation: Trans. Capsule: Unirrad Flucnce: 0,00E+o00 n/cm' 120 . - - - - , - - - - , - - - - , - - - - . . - - - . . - - - - - - - - - - - - - - .

60 l----'---+---'----+--'---+--,£'--+--...;...-1----'---+---'----+----+-------t 0 ..........._...____,.._....__..........._ _.__............_...__,..__,__..___,__....__...____._ _,

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGraph6.02 09/16/2021 Page 1/2

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Westinghouse Non-Proprietary Class 3 Page 72 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.15-1 Transition Ring Plates Plot of Measured Transverse Direction CVN Data (cont.)

Plant: V.C. Summer Material: SA533Bl Heat: A9249-1 Orientation: Trans. Capsule: Unir.-ad Fluence: 0.00E+000 n/cm*

Charpy V-Notch Data Tern perature {° F) InputCVN Computed CVN Differential

-100 6.0 11.9 -5.93 050 28.0 23.3 4.74

-20 36:0 33.7 2.30 10 45.0 46.5 -1.45 40 58.0 60.1 -2.05 212 103.0 99.8 3.22 CVGraph 6.02 09/16/2021 Page 2/2

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Westinghouse Non-Proprietary Class 3 Page 73 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.15-2 Transition Ring Plates Plot of Measured Transverse Direction Lateral Expansion Data CVGraph 6.02: Hypeibolic Tangent Curve Printed on 9/16/2021 11: 16 AM A = 40.50 B =39.50 C =113.'.21 TO =4.65 D =0,00 Correlation Coefficie11l = 0. 976 Equation is A+ B * (Tanh({T-TO)/(C+DT))J Upper ShclfL.E. = 80.00 (Fixed) Lower ShclfL.E. 1.00 (FL\'.cd)

Temp@35 miis~-11.20° F Plant: V.C. Summer Material: SA533B1 Heat. A92-'9-1 Orientation: Trans. Capsule: Unirrad Flucncc: 0.OOE-<<100 Diem'

-e 30-------t----#--+-----------1---------+---

~

-=

.,.;;i 20 ---+-----t--1---+---+----t----1----1----t----1 0 ..._....._ ......__._...__,___ _............_ ......___._......_____...____._.....__.._....

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

CVOraph6.02 09/16/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 74 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.15-2 Transition Ring Plates Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C. Summer Material: SA533B1 Heat: C!l.923-2 Orientation:* Trans. Capsule: unirrad Fluence: O.iiOE+OOO n/cm*

Charpy V-Notch Data temperature(* F) Input L..E. Comppted L. E. Differential

-10 27.0 2L4 5.61 50 3&:o 40.5 -2.50 40 34.0 37.l -3.09 70 45.0 47.2 -2.17 120 65.0 60.9 4.07 212 16.0 72.6 3.37 CVGraph 6.02 09/15/2021

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Westinghouse Non-Proprietary Class 3 Page 75 of 86 Attachment B to PWROG-21037-NP Revision 2 B.16 V.C. Summer Unit 1 Bottom Head, Heat# A9231-2 Tables B.16-1 and B.16-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTRs for the Bottom Head.

Table B.16-1 Charpy V-Notch Test Data for the Bottom Head, Heat# A9231-2 Longitudinal Transverse CVN Impact Lateral CVN Impact Lateral Temp. Shear Temp. Shear Energy Expansion Energy Expansion

{°F) (%) {°F) (%)

(ft-lb) (mils) (ft-lb) (mils)

-100 10 7 10 -100 5(a) 3 10

-100 6 4 10 -100 7 3 10

-100 6(a) 4(a) 10 -100 6 2(a) 10

-20 26 22 20 -20 42 23(a) 30

-20 17(a) 16<*> 20 -20 28(a) 35 30

-20 22 26 20 -20 47 34 30 10 26<*> 32 40 10 23(a) 33 40 10 38 24<*) 40 10 53 22<*) 40 10 44 32 40 10 38 41 40 40 34(a) 28<*> 50 40 50 40 50 40 72 57 50 40 58 36(a) 50 40 62 49 50 40 48(a) 44 50 100 86 so<*> 70 100 92(a) 66(a) 80 100 77 62 70 100 102 70 80 100 76(*) 64 70 100 96 75 80 212 130 83 99 212 133(a)(b) 86(a)(b) 99 212 12Q(a)(b) 81 (a)(b) 99 212 136 89 99 212 126 84 99 212 133 90 99 Notes for Table B.16-1:

(a) Minimum value used in the CV GRAPH plots in accordance with ASME Code III Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CVGRAPH plots.

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Westinghouse Non-Proprietary Class 3 Page 76 of86 Attachment B to PWROG-21037-NP Revision 2 Table B.16-2 Drop-Weight Test Data for Bottom Head, Heat# A9231-2 Test Temperature TNDT Drop-Weights<*)

{°F) (OF) 10 I-NF 0 2-NF

-10

-10 1-NF, 1-F

-20 1-F Note for Table B.16-2:

(a) NF "No Fail," F "Fail".

B.16.1 Determination of the Initial RTNnT Using the data summarized in Tables B.16-1 and B.16-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 40°F, which is less than TNoT + 60°F (-10°F + 60°F 50°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNoT + 60°F would NOT satisfy the criteria.

To precisely determine the temperature at which 50 ft-lb and 35 mils LE were obtained on the specimens, the unirradiated Charpy V-notch data may be plotted and fit using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-2331, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience 2: 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNoT- It is noted that while the longitudinal direction is usually considered the "strong" direction, some of the longitudinal data is more limiting than the transverse data. Therefore, both the longitudinal and transverse data will be fitted and the more limiting results will be used to determine the initial RTNDT*

Tso ft-lb= Max [Tso ft-lb, Jong,, Tso ft-lb, trans.J = Max [59.9°F, 42.5°F] = 59.9°F T35 mils Max [T3s mils, long,, T3s mils, trans.] = Max [52.5°F' 32.5°F] == 52.5°F Tcv = Max [Tso ft-lb, T3s mils]= Max [59.9°F, 52.5°F]

Tcv 59.9°F Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNoT is the higher of TNoT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

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Westinghouse Non-Proprietary Class 3 Page 77 of86 Attachment B to PWROG-21037-NP Revision 2 RTNDT = Max [TNDT, Tcv - 60°F]

RTNDT = Max [-10°F, 59.9°F - 60°F] = Max [-10°F, -0.1 °FJ Bottom Head Initial RTNnT = 0°F B.16.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The transverse (weak direction) USE is displayed below; this value is the average of each of the impact energy values contained in Table B.16-1 with shear~ 95%.

Bottom Head Initial USE = Average (133, 136, 133) ft-lb

= 134 ft-lb However, the longitudinal Charpy data in Table B.16-1 exhibit lower impact energies at~ 95% shear than the axial data. Therefore, the USE will be recalculated using the longitudinal impact energy data with shear 2'.: 95% because it represents the lower bound USE. It is noted the BTP 5-3 methodology is NOT being implemented here, which reduces the longitudinally oriented impact energies to 65% of the reported values in order to conservatively estimate transversely oriented specimens. This is because transverse data is available and does not need to be estimated.

Bottom Head Initial USE = Average (130, 120, 126) ft-lb

= 125 ft-lb B.16.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table B.16-3.

Table B.16-3 Chemistry Data for Bottom Head, Heat# A9231-2 Copper Nickel Source (wt.-%) (wt.-%)

- 0.45 CMTR, Lukens Steel Analysis Generic value based on a mean plus one standard deviation analysis of the high copper A533, Grade 0.172 - B, Class 1, plate materials contained in Table G.2 ofORNL/TM-2006/530.

Therefore, the chemical content will be defined as shown below going forward:

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Westinghouse Non-Proprietary Class 3 Page 78 of86 AttachmentB to PWROG-21037-NP Revision 2 Bottom Head Cu Content = 0.172 wt-%

Bottom Head Ni Content = 0.45 wt-%

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Westinghouse Non-Proprietary Class 3 Page 79 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.16-1 Bottom Head Plot of Measured Transverse Direction CVN Data CVGraph 6.02: Hyperoolic Tangent Curve Printed on 9/16/2021 11:22 AM A =67.60 B =65..10 C = 86.70 T0=66.42 D =0.00 Correlalion Coefficient= 0.993 Equation is A+ B

• JTanb((T-'IO)/(C+DT))]

Upper Shelf Energy 133.00 (Fh;cd) Lower ShclfEoorgy =2.20 (Fi.'icd)

Tcmp@30 fi-lbs= 9.70° F Temp@35 ft-lbs= 19.00°F Temp@50 fl-lbs= 42.50° F Plant: V,C. Summer Material: S53381 Heat: A9231*2 Orientation: Trans. Capsule: Unirrad Flucncc: 0.00E+o00 n!cm*

140 -----,.-----,----,.-------,---~---,----r----,

- rl.l

,.Q 100

'i'

¢:

80

-=

bll ..... ~ - .... --~ .

Q,j

~ 60 z ... - ...

u

"' ~

40 o l:::::t:::::!=::CL..i..,_L..i-.L.,.j,,_J_...i......L...i......L_i.,__L--1-..J

-300 -200 -100 0 100 200 300 400 500 600 Temperature (0 F)

CVGruph 6.02 09/16/2021 Page l/2

• • • This record was final approved on 3/6/2023, 12:36: 16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 80 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.16-1 Bottom Head Plot of Measured Transverse Direction CVN Data (cont.)

Plant: V.C. Summer Material: S533Bl Heat: A9231-2 Orientation: Trans. Capsule: Unirrad Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature {° F) InputCVN Co.mputed CVN Differential

-100 5.0 5.0 0.05

-20 28.0 17.9 10.12 10 23.0 30.2 -7.18 40 48,0 48.3 .Q.27 100 92.0 9L7 0.26 212 133,0 128.6 4.40 CVGraph 6.02 09/16/2021 Page 212

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Westinghouse Non-Proprietary Class 3 Page 81 of 86 Attachment B to PWROG-21037-NP Revision 2 Figure B.16-2 Bottom Head Plot of Measured Transverse Direction Lateral Expansion Data CVGraph 6.02: Hyperbolic Tangent Curve Printed on 9/16/2021 11:24 AM A =43.50 B =42.50 C =91.28 TO =50.95 D =0.00 Correlation Coefficient= O. 992 Equation is A+ B * [Tanh((T-TO)/(C+D1))]

Upper ShclfL.E. =86.00 (FL,;cd) Lower Shelf L.E. =1.00 (Fixed)

Temp'!!,35 mil.- 32.50° F Plant: V.C. Summer Material: S533Bl Heat: A9231-2 Orientation: Trans. Capsule: Unirrad Flucncc: 0.00E+000 n/cm>

90 ..-~--,----.----,---"""T----,-------,---...,...---,

~

r:I}

}60  : .......*...........*;

[

-~ 50

~ 40

............. y t----,--+---,--+-----t--,--#---+----+----+---+-----t----1 t----+----+---+--l---+----+----+----+----+----1 e~ 30

• -***"*:***A***

t----+---'--+---'----t-l---'---+---'---1------+--'--+---'-----11----'---1

~ ***---* ./..'.; ......

20 10

.... \; 0 0 J----4----'--l--;--~~-'--4--'-----l--'---l---'---l------'--l--+----I t-------'--+--'----+--l--+----+--'---l---+--~--+---+---+----1

~)

/ .

0 l:::::::i:=:+/-::::C::~---L-L-...i,__..L_.i,_.....l..----1,_L_...i,__..L_.i,_.....l..----1,_J

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGmph6.02 09/16/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 82 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.16-2 Bottom Head Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C. Summer Material: S533Bl Heat: A9231-2 Orientation: Trans. Capsule: Unirrad Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature {° F) InputL. E. Computed r.*E. Differential

-100 2.0 4.0 -2.00

-20 23.0 15.8 7.17 10 22.0 25.6 -3.62 40 36.0 38.4 -2.43 100 66.0 64.4 1.63 212 86.0 83.6 2.42 CVGraph 6.02 09/16/2021 Page 2/2

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Westinghouse Non-Proprietary Class 3 Page 83 of 86 Attachment B to PWROG-21037-NP Revision 2 Figure B.16-3 Bottom Head Plot of Measured Longitudinal Direction CVN Data CVGraph 6.02: Hyperbolic Tangent Curve Printed on 9/16/2021 11 :27 AM A= 61.10 B = 58,90 C = 87.90 TO= 76.66 D = 0.00 Correlation Coefficient= 0. 997 Equation is A+ B

• rranh((T-TO)/(C+Dn)J Upper Shelf Energy= 120.00 (Fb,cd) Lower Shelf Energy = 2.20 (Fb:cd)

Temp@;.10 ft-lbs= 25.10° F Tcmp@.15 fl-lbs= 34. 90° F Tcmp(2f;50 fl-lbs= 59.90° F Plant: V.C. Summer Material: SA533Bt Heat: A9231-2 Orientation: Long. Capsule: Unirrad Rucncc: 0.00E+o00 n/cm1 140 - - - - - - - - - - - - - - - - - - - - - - - - . . . - - - -

120 t--1---t----'---il---:----t---'----t-:--:--J<<~;)-==.=1-,.._;-+--...;,_-+-~-t 100

• • /*;

1---+--+----l-----'--l--'---!-~---1-----+---,1---+-+----'--I 80 l

---

+----t------1-----------------'-----t---+-------t 60

)'

--,---+------------+---------t--+--+----+--'---+------1---+-------t

• • • • -'***--*** **,****** ......y, !... "

40 20

,1

--,---+----+-+----t-+---+--------+--,---+--;----1--;--+--+--t 1-----~-+--~--~---~--~---+---~.-~---~-

'J

"( **jv7'*** ., ...... .

o l=::t=+/-:::C=:J.._i,__JL_,i__L-1.--L-1..--1._i.._L..i.......L.....L..----'

-300 -200 -100 0 100 200 300 400 500 600 Temperature (0 F)

CVGraph 6.02 09/16/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 84 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.16-3 Bottom Head Plot of Measured Longitudinal Direction CVN Data (cont.)

Plant: V.C. Summer Material: SA533B1 Heat: A.9231-2 Orientation: Long. Capsule: Unirra.d Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature (0 F) InputCVN Computed CVN Differential

-100 6.0 4.3 1.72

-20 17.0 14.0 3.04 10 26.0 23.4 2.60 40 34.0 37.9 -3.87 100 76.0 76.4 -0.38 212 120.0 114.8 5,18 CVGraph 6.02 09/16/2021 Page 2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (fhis statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 85 of86 Attachment B to PWROG-21037-NP Revision 2 Figure B.16-4 Bottom Head Plot of Measured Longitudinal Direction Lateral Expansion Data CVGrapb 6.02: Hyperbolic Tangent CUIVe Printed on 9/16/2021 11:26 AM A= ,U.00 B = -10.00 C = 108.90 TO = 68.90 D = 0.00 Correlation CoeITTcienl = O. 994 Equation is A+ B * [Tanh((T-TO)/(C+D'D)l Upper SbclfL.E. = 81.00 (Fixed) Lower Shelf LE.= 1.00 (FL'<cd)

Tcmp:@35 mils= 52.50° F Plant: V.C. Summer Material: SA533Bt Heat: A9231-2 Orientation: Long. Capsule: Unirrad Flucncc: 0.OOE+o00 n/cm' 90 ----..-----.----.---.......-----.------..----...-----,

... l ----- -****-**

n 80  :

70

---

.... 60 t'll e  :. /:.

....e= 50

- -.. - , .' ... - ~ . -. - :

t'll

=

=

=- 40

~

-=

~

i-.

q,j 30

~

=

20 10

-,~v. .

o l::::::::i=:::t:=::i,~...l--i.....*..J_....i._.L_..i.,_.l._..1.,_...l._...i.._L_i.......J_--1._.J

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

CVGraph6.02 09/16/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 86 of 86 Attachment B to PWROG-21037-NP Revision 2 Figure B.16-4 Bottom Head Plot of Measured Longitudinal Direction Lateral Expansion Data (cont.)

Plant: V.C. Swnmer Material: SA533B1 Heat: A9231-2 Orientation: Long. Capsule: Unirrad Fluence: O.OOE+OOO n/cm' Charpy V-Notch Data Temperature {° F) InputL. E. Computed L. E. Differential

-100 4.0 4.4 -0.44

-20 16.0 14.1 1.92 10 24.0 21.3 2.75 40 28:0 30.6 -2.63 100 50.0 52.] -2.12 212 81.0 75.6 5.39 CVGraph 6.02 09/16/2021 Page 2/2

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Westinghouse Non-Proprietary Class 3 Page 1 of75 Attachment C to PWROG-21037-NP Revision 2 Attachment C PA-MSC-1367, Tasks 1-3 Evaluations for V.C. Summer Unit 1 Reactor Vessel Welds

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Westinghouse Non-Proprietary Class 3 Page 2 of75 Attachment C to PWROG-21037-NP Revision 2 C.1 Introduction This section evaluates material properties, i.e., Cu, Ni, unirradiated RTNDT, & unirradiated USE, for all welds used in the fabrication of the V.C. Summer Unit 1 reactor vessel. These welds were identified from a review of Certified Material Test Reports (CMTRs), surveillance capsule program, and Chicago Bridge

& Iron (CB&I) fabrication records available to Westinghouse. The weld heats identified in the fabrication records were cross-referenced against an investigation performed on CB&I fabricated vessels to address NRC IE Bulletin 78-12 regarding atypical weld metal in reactor pressure vessel welds. In some situations, in the presumed extended beltline, the heat number used in specific weld seams could not be identified. To address these situations, bounding or generic V.C. Summer weld properties will be developed to be used anywhere the specific weld heat cannot be identified.

C.2 Summary of Welds at V.C. Summer Unit 1 Two types of welds that were used in the fabrication ofCB&I vessels, shielded metal arc welds (SMA Ws) and submerged arc welds (SA Ws). Where the geometry permitted automatic SAW was used and SMAW was applied where it was required to complete the welds due to geometry and for repairs. Each weld type is addressed separately in the following sections. Table C.2-1 summarizes all material properties of the SAW taken from the V.C. Summer Unit 1 reactor vessel fabrication files. Table C.2-2 summarizes all material properties of the SMAW taken from the V.C. Summer Unit 1 reactor vessel fabrication files. The more limiting will be used to generate the bounding/generic material properties.

The sections below discuss the development of each bounding/generic material properties.

C.2.1 Determination of the Initial RTl'l1>T An initial RTNDT has been established for all weld heats used in the V.C. Summer reactor vessel. Because this is a critical property for demonstrating the safe operation of the plant, it was determined that the maximum initial RTNoT should be used in instances when the heat could not be determined.

The bounding RTNnr for SAW is l0°F. Since this is a bounding value based on measured data, the standard deviation associated with its initial measurement is zero (cr1 = 0°F). This value is considered conservative as it is based on BTP 5-3, Position 1.1(4) which uses data at only a single temperature. It is also more conservative than the generic initial RTNDT -56°F for Linde 124 flux with a cr1 = l 7°F permitted by 10 CFR 50.61, i.e., initial RTNDT + 2cr1 -22°F.

The bounding RTNDT for SMAW is 0°F. Since this is a bounding value based on measured data, the standard deviation associated with its initial measurement is zero ( cr1 = 0°F). This value is considered conservative as it is based on BTP 5-3, Position 1.1 (4) which uses data at only a single temperature. Instead, the TNDT is assumed to be equal to the next test temperature, i.e., 0°F.

The bounding RTNDT value between SAW and SMAW is 10°F.

Bounding Weld Initial RTNoT = 10°F

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Westinghouse Non-Proprietary Class 3 Page 3 of75 Attachment C to PWROG-21037-NP Revision 2 C.2.2 Determination of the Initial USE Roughly half the weld heats at V.C. Summer Unit 1 for both SAW and SMAW have shear data 2:: 95%

required by ASTM E185 to establish USE. Herein, generic USE values are determined based on the mean USE of common weld types minus 2 standard deviations (cr). The mean USE is based on a review of all Charpy impact energy with shear data 2:: 95%. If insufficient data is available to determine the USE, such as all data indicates a shear less than 95%, an approximate USE based on the data available is reported as greater than the CVN impact energy with the maximum shear. If the highest shear includes multiple CVN impact energies, then the USE is set to greater than the largest impact energy. This USE value does not provide an accurate representation of USE; therefore, this data point is excluded from the statistical analysis.

The results indicate that the average SAW USE minus two standard deviations is 81 ft-lb. This value is considered conservative because most of the weld heats with shear data < 95% experienced CVN impact energies greater than 81 ft-lb prior to the onset of the USE. The exception, Heat# 3P4955, Flux Type Linde 124, Lot #s 1214 & 3478, experienced nearly 81 ft-lb (77 ft-lb & 67 ft-lb, respectively) with a shear value much less than 95% (75% & 65% shear, respectively).

The results indicate that the average SMAW USE minus two standard deviations is 80 ft-lb. This value is considered conservative since the majority of the weld heats with shear data< 95% experience CVN impact energies greater than 80 ft-lb prior to the onset of the USE. Those that do not experience > 80 ft-lb also have shears much less than 95%. For example, Heat# 04P046, Lot# D217A27A experience only 40 ft-lb, but also experience only 30% shear.

The bounding generic USE value between SAW and SMAW is subsequently 80 ft-lb. This is greater than the 10 CFR 50, Appendix G minimum unirradiated USE value (75 ft-lb) and the irradiated USE screening criterion for operating plants (50 ft-lb).

Generic Weld Initial USE= 80 ft-lb C.2.3 Chemistry This value is based on the Regulatory Guide 1.99, Revision 2 mean plus one standard deviation approach.

The generic weight percent values of 0.06% for Cu and 1.01 % for Ni can be utilized for V.C. Summer reactor vessel SA Ws and/or SMAW when insufficient data is available to determine weld-specific chemistry values.

Generic Weld Cu Content 0.06 wt.-%

Generic Weld Ni Content= 1.01 wt.-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 4 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.2-1 Summary of Material Properties for SAWs<a)

Cu Ni Initial RTNDT USE(cl Heat# Flux Type Lot#

(wt-%) (wt-%) (OF) Method(bJ (ft-lb) 4P4784 Linde 124 3930 0.05 0.91 -49 AS:ME 86

> 77 ft-lb@

3P4955 Linde 124 1214 0.03 0.98 -20 AS:ME 75% Shear

> 67 ft-lb@

3P4955 Linde 124 3478 0.03 0.97 -20 AS:ME 70% Shear

> 88 ft-lb@

3P4966 Linde 124 1214 0.03 0.90 -20 AS:ME 85% Shear

> 95 ft-lb@

3P4966 Linde 124 0331 0.03 1.07 10 BTP 5-3 70% Shear 5P5657 Linde 124 0931 0.07 0.89 -60 AS:ME 88 5P6214B Linde 124 0331 0.02 0.82 -40 AS:ME 90 5P6771 Linde 124 0342 0.03 0.94 -20 AS:ME 83

> 95 ft-lb@

Maximum 0.07 1.07 10 70% Shear

> 67 ft-lb@

Minimum 0.02 0.82 -60 70% Shear Average 0.04 0.94 - 87 Standard Deviation (cr) 0.02 0.07 - 3 Average+/- cr 0.06 1.01 - 84 Average +/- 2cr - - - 81 Notes for Table C.2-1:

(a) The material properties are generated in subsequent sections of this attachment.

(b) "ASME" indicates the initial RTNDT value was developed be on ASME NB-2300 methods. "BTP 5-3" indicates that BTP 5-3, Position 1.1(4) was utilized because of lack of sufficient testing data to satisfy the ASME NB-2300 methods requirements.

( c) USE values preceded by a greater than or equal to symbol, ">", identifies a material with no shear data 2: 95%; thus, the initial USE values for these materials were set to greater than the impact energy with highest shear. The percent value identifies the shear value corresponding to the lower bound USE. These data points are excluded from the statistical analysis.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 5 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.2-2 Summary of Material Properties for SMAWs<a)

Cu Ni Initial RTNoT USE<c)

Heat# Lot# Method(b)

(wt-%) (wt-%) (OF) (ft-lb) 492L4871 A421B27AF 0.03 0.98 -60 ASME 130 492L4871 A421B27AE 0.04 0.95 -60 ASME 157 627069 C312A27AG 0.02 0.99 -60 ASlVIE 115 624039 D205A27A 0.06 0.92 -77 ASME 119 422K8511 G313A27AD 0.01 1.00 -78 ASME 142 627184 C314A27AH 0.03 1.01 -50 AS:ME 102 626677 C301A27AF 0.02 0.95 -20 AS:ME 93 051'776 L314A27AH 0.06 0.92 -50 ASME 119 624263 E204A27A 0.06 0.89 -20 ASlVIE > 73.5@75%

421A6811 F022A27A 0.07 0.88 -20 AS:ME >91@75%

07L669 K004A27A 0.03 1.02 -20 BTP 5-3 > 50@60%

C3L46C J020A27A 0.02 0.87 -20 ASME >57@65%

422B7201 L030A27A 0.04 0.90 -20 AS:ME >66@70%

09L853 A111A27A 0.03 0.86 -20 BTP 5-3 >78@80%

08M365 Gl28A27A 0.02 1.10 -20 BTP 5-3 > 51 @60%

421E0601 Lll7A27A 0.03 0.87 -20 ASME > 102.5@90%

09M814 Ll15A27A 0.03 0.92 -20 ASME >88@80%

09M814 Ll14A27A 0.01 0.82 -20 ASME >92@80%

623275 Ll21A27A 0.05 0.84 -20 ASME > 80@75%

627260 B322A27AE 0.06 1.08 -20 ASME > 80@25%

624039 D224A27A 0.07 1.01 -20 ASME >86@63%

05P018 D211A27A 0.09 0.90 -20 ASME >85@70%

42120611 L908A27A 0.03 1.01 -20 ASlVIE > 113.5 @85%

04P046 D217A27A 0.06 0.90 0 BTP 5-3 >40@30%

624063 C228A27A O.Q3 1.00 -20 ASME >70@60%

Maximum 0.09 1.10 0 157 Minimum 0.01 0.82 -78 >40@30%

Average 0.04 0.94 -31 122 Standard Deviation (cr) 0.02 0.07 - 21 Average+/- cr 0.06 1.01 - 101 Average +/- 2cr - - - 80 Notes for Table C.2-1:

(a) The material properties are generated in subsequent sections of this attachment.

(b) "ASME" indicates the initial RTNDT value was developed be on ASME NB-2300 methods. "BTP 5-3" indicates that BTP 5-3, Position 1.1 (4) was utilized because oflack of sufficient testing data to satisfy the ASME NB-2300 methods requirements.

(c) USE values preceded by a greater than or equal to symbol,">", identifies a material with no shear data 2': 95%; thus, the initial USE values for these materials were set to greater than the impact energy with highest shear. The percent value identifies the shear value corresponding to the lower bound USE. These data points are excluded from the statistical analysis.

• • • This record was final approved on 3/6/2023, 12:36: 16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 6 of75 Attachment C to PWROG-21037-NP Revision 2 C.3 V.C. Summer Unit 1, Heat# 3P4955, Linde 124 Flux, Lot# 1214 Tables C.3-1 and C.3-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files. The material properties were evaluated in two ways. 1*t, the material properties were evaluated with the weld being deposited as a single wire. 2nd, the material properties were evaluated with the weld being deposited by tandem wires. For the purpose of this analysis, both will be evaluated, and the limiting property will be used.

Table C.3-1 Charpy V-Notch Test Data for the Weld Heat# 3P4955, Linde 124 Flux, Lot# 1214 CVNimpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(fUb) (mils)

Single Wire 10 45 38 25 10 36 34 25 10 52 50 30 10 55 48 30 10 52 46 30 40 62 51 60 40 77 64 75 40 59 53 50 Tandem Wire 10 69 64 50 10 67 53 50 10 67 58 50 10 61 54 50 10 64 67 50 40 52 45 35 40 63 53 45 40 53 44 30

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 7 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.3-2 Drop-Weight Test Data for Weld Heat# 3P4955, Linde 124 Flux, Lot# 1214 Test Temperature TNDT Drop-Weights<*>

(OF) {°F)

-10 1-NF Single -20(b)

-10 1-NF

-10 1-NF Tandem -20(b)

-10 1-NF Note for Table C.3-2:

(a) NF= "No Fail," F = "Fail".

(b) Drop-weight testing had no breaks at the lowest test temperature, i.e., -10°F; therefore, the NDT less than or equal to the next test temperature, i.e., -20°F.

C.3.1 Determination of the Initial RTNoT Using the data summarized in Tables C.3-1 and C.3-2, the initial RTNDT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

For both the single and tandem wire analysis, the Charpy V-notch tests were conducted at 40°F, TNoT +

60°F (-20°F + 60°F = 40°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNoT +

60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNDT is the initial reference temperature RTNDT*

RTNDT = -20°F Weld Heat# 3P4955, Linde 124 Flux, Lot# 1214 Initial RTNnT = -20°F C.3.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E185-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E 185 manual (2016 version). Using the guidelines in ASTM E 185-82 and E 185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. Per Table C.3-1, no data with known shear 2: 95% exists. Thus, the USE is set to greater than the impact energy with highest shear. If the highest shear includes multiple CVN impact energies, then the USE is set to greater than the largest impact energy. The USE for the material will be defined as the USE value with highest shear between the single and tandem wire.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 8 of75 Attachment C to PWROG-21037-NP Revision2 Single Wire, Weld Heat# 3P4955, Linde 124 Flux, Lot# 1214 Initial USE > 77 ft-lb@ 75% Shear Tandem Wire, Weld Heat# 3P4955, Linde 124 Flux, Lot# 1214 Initial USE > 69 ft-lb @50% Shear Weld Heat# 3P4955, Linde 124 Flux, Lot# 1214 Initial USE > 77 ft-lb@ 75% Shear C.3.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. If data for single or tandem wire includes multiple measurements, then the average of all available data will be used. The limiting value between the single and tandem weld will be used. The chemical compositions are summarized in Table C.3-3.

Table C.3-3 Chemistry Data for Weld Heat# 3P4955, Linde 124 Flux, Lot# 1214 Copper Nickel Source (wt.-%) (wt.-%)

0.025 0.94 Single Wire Check Analysis 0.022 0.98 Tandem Wire Check Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 3P4955, Linde 124 Flux, Lot# 1214 Cu Content = 0.03 wt-%

Weld Heat# 3P4955, Linde 124 Flux, Lot# 1214 Ni Content = 0.98 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 9 of75 Attachment C to PWROG-21037-NP Revision 2 C.4 V.C. Summer Unit 1, Heat# 3P4955, Linde 124 Flux, Lot# 3478 Tables C.4-1 and C.4-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 vessel fabrication files. The material properties were evaluated in two ways.

1st, the material properties were evaluated with the weld being deposited as a single wire. 2nd , the material properties were evaluated with the weld being deposited by tandem wires. For the purpose of this analysis, both will be evaluated, and the limiting property will be used.

Table C.4-1 Charpy V-Notch Test Data for the Weld Heat# 3P4955, Linde 124 Flux, Lot# 3478 CVNimpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

Single Wire 10 44.5 45 45 10 55.5 50 55 10 52.5 55 55 10 53.5 55 55 10 32.5 40 39 40 65 61 60

• 40 58 56 50 40 54.5 54 50 Tandem Wire 10 67 66 70 10 65.5 69 70 10 59 59 70 10 48.5 46 50 10 51.5 53 55 40 56 49 55 40 56 56 50 40 60 46 50

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation) j

Westinghouse Non-Proprietary Class 3 Page 10 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.4-2 Drop-Weight Test Data for Weld Heat# 3P4955, Linde 124 Flux, Lot# 3478 Test Temperature TNDT Drop-Weights<*>

(°F) (°F)

-10 1-NF Single -20(b)

-10 1-NF

-10 1-NF Tandem

-10 1-NF Note for Table C.4-2:

(a) NF= "No Fail," F = "Fail".

(b) Drop-weight testing had no breaks at the lowest test temperature, i.e., -10°F; therefore, the NDT less than or equal to the next test temperature, i.e., -20°F.

C.4.1 Determination of the Initial RTNDT Using the data summarized in Tables C.4-1 and C.4-2, the initial RTNDT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NOT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

For both the single and tandem wires, the Charpy V-notch tests were conducted at 40°F, TNDT + 60°F (-

200F + 60°F = 40°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNDT is the initial reference temperature RTNDT-RTNDT = -20°F Weld Heat# 3P4955, Linde 124 Flux, Lot# 3478 Initial RTNDT = -20°F C.4.2 Determination of the Initial USE The current 10 CPR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out offamily,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. Per Table C.4-1, no data with known shear 2: 95% exists. Thus, the USE is set to greater than the impact energy with highest shear. If the highest shear includes multiple CVN impact energies, then the USE is set to greater than the largest impact energy. The USE for the material will be defined as the USE value with highest shear between the single and tandem wire.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 11 of75 Attachment C to PWROG-21037-NP Revision 2 Single Wire, Weld Heat# 3P4955, Linde 124 Flux, Lot# 3478 Initial USE > 65 ft-lb@ 60% Shear Tandem Wire, Weld Heat# 3P4955, Linde 124 Flux, Lot# 3478 Initial USE > 67 ft-lb@ 70% Shear Weld Heat# 3P4955, Linde 124 Flux, Lot# 3478 Initial USE > 67 ft-lb @ 70% Shear C.4.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. If data for single or tandem wire includes multiple measurements, then the average of all available data will be used. The limiting value between the single and tandem weld will be used. The chemical compositions are summarized in Table C.4-3.

Table C.4-3 Chemistry Data for Weld Heat# 3P4955, Linde 124 Flux, Lot# 3478 Copper Nickel Source (wt.-%) (wt.-%)

0.025 0.97 Single Wire Check Analysis 0.025 0.95 Tandem Wire Check Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 3P4955, Linde 124 Flux, Lot# 3478 Cu Content = 0.03 wt-%

Weld Heat# 3P4955, Linde 124 Flux, Lot# 3478 Ni Content = 0.97 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 12 of75 Attachment C to PWROG-21037-NP Revision 2 C.5 V.C. Summer Unit 1, Heat# 3P4966, Linde 124 Flux, Lot# 0331 Tables C.5-1 summarizes all available Charpy V-notch test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files. The material properties were evaluated in two ways. 1si, the material properties were evaluated with the weld being deposited as a single wire. 2nd, the material properties were evaluated with the weld being deposited by tandem wires. For the purpose of this analysis, both will be evaluated, and the limiting property will be used. No drop-weight test data is available.

Table C.5-1 Charpy V-Notch Test Data for the Weld Heat# 3P4966, Linde 124 Flux, Lot# 0331 CVNimpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

Single Wire 10 54 49 25 10 48 40 25 10 70 54 35 10 74 66 50 10 64 58 40 Tandem Wire 10 77 65 50 10 90 66 70 10 80 59 35 10 95 71 70 10 78 62 35 C.5.1 Determination of the Initial RTNDT Since there in no drop-weight data and tests were performed at a single temperature, NUREG-0800 BTP 5-3 Position 1.1(4) may be used as an estimate ofRTNoT- Per Table C.5-1, all impact energies are greater than 45 ft-lb at 10°F; therefore, the initial RTNoT is:

Weld Heat# 3P4966, Linde 124 Flux, Lot# 0331 Initial RTNDT = 10°F C.5.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E185-16, the average of all Charpy data::: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. Per Table C.5-1, no data with known shear:::: 95% exists. Thus, the USE is set to greater than the impact energy with highest shear. If the highest shear includes multiple CVN impact energies, then the

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 13 of75 Attachment C to PWROG-21037-NP Revision 2 USE is set to greater than the largest impact energy. The USE for the material will be defined as the USE value with highest shear between the single and tandem wire.

Single Wire, Weld Heat# 3P4966, Linde 124 Flux, Lot# 0331 Initial USE > 74 ft-lb @ 50% Shear Tandem Wire, Weld Heat# 3P4966, Linde 124 Flux, Lot# 0331 Initial USE > 95 ft-lb@ 70% Shear Weld Heat# 3P4966, Linde 124 Flux, Lot# 0331 Initial USE > 95 ft-lb @ 70% Shear C.5.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. If data for single or tandem wire includes multiple measurements, then the average of all available data will be used. The limiting value between the single and tandem weld will be used. The chemical compositions are summarized in Table C.5-2.

Table C.5-2 Chemistry Data for Weld Heat# 3P4966, Linde 124 Flux, Lot# 0331 Copper Nickel Source (wt.-%) (wt.-%)

0.023 1.07 Single Wire Check Analysis 0.025 0.94 Tandem Wire Check Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 3P4966, Linde 124 Flux, Lot# 0331 Cu Content = 0.03 wt-%

Weld Heat# 3P4966, Linde 124 Flux, Lot# 0331 Ni Content = 1.07 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 14 of 75 Attachment C to PWROG-21037-NP Revision 2 C.6 V.C. Summer Unit 1, Heat# 3P4966, Linde 124 Flux, Lot# 1214 Tables C.6-1 and C.6-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files. The material properties were evaluated in two ways. 1*t, the material properties were evaluated with the weld being deposited as a single wire. 2nd, the material properties were evaluated with the weld being deposited by tandem wires. For the purpose of this analysis, both will be evaluated, and the limiting property will be used.

Table C.6-1 Charpy V-Notch Test Data for the Weld Heat# 3P4966, Linde 124 Flux, Lot# 1214 CVNimpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

Single Wire 10 39 68 70 10 38 64 60 10 38 63 70 10 82 81 80 10 84 72 70 40 88 72 75 40 88 68 85 40 82 67 65 Tandem Wire 10 28 18 30 10 84 62 40 10 63 57 40 10 75 51 40 10 78 57 40 40 65 52 55 40 69 55 65 40 70 59 45

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 15 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.6-2 Drop-Weight Test Data for Weld Heat# 3P4966, Linde 124 Flux, Lot# 1214 Test Temperature TNDT Drop-Weights(a)

{°F) {°F)

-10 1-NF Single -20(b)

-10 1-NF

-10 1-NF Tandem -20(b)

-10 1-NF Note for Table C.6-2:

(a) NF= "No Fail," F "Fail".

(b) Drop-weight testing had no breaks at the lowest test temperature, i.e., 0°F; therefore, the NDT :5 the next test temperature, -10°F.

C.6.1 Determination of the Initial RTNDT Using the data summarized in Tables C.6-1 and C.6-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight T NDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

For both the single and tandem wire analysis, the Charpy V-notch tests were conducted at 40°F, TNDT +

60°F (-20°F + 60°F = 40°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT +

60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNoT is the initial reference temperature RTNDT, RTNDT -20°F Weld Heat# 3P4966, Linde 124 Flux, Lot# 1214 Initial RTNDT =-20°F C.6.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM El85-82 and E 185-16, the average of all Charpy data 2'.: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. Per Table C.6-1, no data with known shear 2'.: 95% exists. Thus, the USE is set to greater than the impact energy with highest shear. If the highest shear includes multiple CVN impact energies, then the USE is set to greater than the largest impact energy. The USE for the material will be defined as the USE value with highest shear between the single and tandem wire.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 16 of75 Attachment C to PWROG-21037-NP Revision 2 Single Wire, Weld Heat# 3P4966, Linde 124 Flux, Lot# 1214 Initial USE > 88 ft-lb@ 85% Shear Tandem Wire, Weld Heat# 3P4966, Linde 124 Flux, Lot# 1214 Initial USE > 69 ft-lb @65% Shear Weld Heat# 3P4966, Linde 124 Flux, Lot# 1214 Initial USE > 88 ft-lb @ 85% Shear C.6.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. If data for single or tandem wire includes multiple measurements, then the average of all available data will be used. The limiting value between the single and tandem weld will be used. The chemical compositions are summarized in Table C.6-3.

Table C.6-3 Chemistry Data for Weld Heat# 3P4966, Linde 124 Flux, Lot# 1214 Copper Nickel Source (wt.-%) (wt.-%)

0.03 0.90 Single Wire Check Analysis 0.03 0.88 Tandem Wire Check Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 3P4966, Linde 124 Flux, Lot# 1214 Cu Content = 0.03 wt-%

Weld Heat# 3P4966, Linde 124 Flux, Lot# 1214 Ni Content = 0.90 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 17 of75 Attachment C to PWROG-21037-NP Revision 2 C.7 V.C. Summer Unit 1, Heat# 4P4784, Linde 124 Flux, Lot# 3930 Tables C.7-1 and C.7-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 CMTR and reactor vessel fabrication files. This data is combined with the additional data available from V.C. Summer Unit I surveillance program documented in WCAP-9134.

Table C.7-1 Charpy V-Notch Test Data for the Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 CVN Impact Lateral Temp. Shear Energy Expansion (OF) (%)

(ft-lb) (mils)

-120 12 12 7

-120 7(a) 7<*) 7

-120 9 10 8

-100 8 11 10

-100 7(*) 10 10

-100 8 10 10

-100 14.5 9(a) 18

-100 15 11 20

-50 32(*) 21<*) 34

-50 34 25 25

-25 30<*) 34(a) 21

-25 51 42 47

-20 33 36 35

-20 22<*) 25(a) 25

-20 38 39 40 10 53 51 50 10 46(a) 46(*) 60 10 50 49 50 10 73.5 74 90 10 78 68 80 10 74 63 75 10 71 61 75 10 73 65 75 10 79 70 85 10 75 65 75 IO 81 71 90 10 70 68 75

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 18 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.7-1 Charpy V-Notch Test Data for the Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 (cont)

CVNimpact Lateral Temp. Shear Energy Expansion (OF) (o/o)

(ft-lb) (mils)

IO 81 68 90 IO 58 53 75 10 64.5 52 73 IO 62 50 95 40 94 78 90 40 93 61 80 40 95 55(a) 75 40 97 79 90 40 97 77 90 40 93 79 90 40 64(a) 64 75 40 70 69 75 40 66 64 80 50 84 72 96 50 71(a) 54(a) 73 80 8o(a)(b) 67 98 80 84 65(a)(b) 98 125 85.5 75 100 125 89 74(a) 100 210 91.5(a) 73(a) 100 210 94 79 100 210 93.5 78 100 212 79(a) so<a) 100 212 87 82 100 212 97 82 100 Notes for Table C.7-1:

(a) Minimum value used in the CVGRAPH plots in accordance with ASME Code III Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CVGRAPH plots.

• • • This record was final approved on 3/6/2023, 12:3?:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 19 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.7-2 Drop-Weight Test Data for Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 Test Temperature TNDT Drop-Weights<*>

(OF) (OF)

-10 2-NF

-30 1-NF

-50

-40 2-NF

-50 1-F Note for Table C.7-2:

(a) NF= "No Fail," F = "Fail".

C.7.1 Determination of the Initial RTNnT Using the data summarized in Tables C.7-1 and C.7-2, the initial RTNnT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE in the "weak" direction.

Charpy V-notch tests were conducted at 10°F, TNnT + 60°F (-50°F + 60°F = 10°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNnT + 60°F would NOT satisfy the criteria.

To precisely determine the temperature at which 50 ft-lb and 35 mils LE were obtained on the specimens, the unirradiated Charpy V-notch data may be plotted and fit using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-2331, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience~ 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNDT, Tso ft-lb= 10.6°F T35 mils= -14.1 °F Tcv = Max [Tso ft-lb, T3s mil]= Max [10.6°F, -14.1 °F]

Tcv = 10.6°F Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNnT is the higher of TNnT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 20 of75 Attachment C to PWROG-21037-NP Revision 2 RTNoT = Max [TNDT, Tcv - 60°F)

RTNDT = Max [-50°F, 10.6°F - 60°F] = Max [-50°F, -49.4°F]

Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 Initial RTNnT =-49°F C.7.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El85-82.

Herein, USE is calculated based on an interpretation of ASTM El85-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM El85-82 and El85-16, the average ofall Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out offamily' data was not necessary for this material. The USE is displayed below; this value is the average of each of the impact energy values contained in Table C.7-1 with shear 2:: 95%.

Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 Initial USE

= Average (62, 84, 80, 84, 85.5, 89, 91.5, 94, 93.5, 79, 87, 97) ft-lb

= 86 ft-lb C.7.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. When component specific data was not available, a generic value was defined as the mean plus one standard deviation of available data from similar materials. This method is consistent with Regulatory Guide 1.99, Revision 2, which allows the mean plus one standard deviation method to be used for conservative chemistry estimates based on generic data if component specific data is not available. The chemical compositions are summarized in Table C.7-3.

Table C.7-3 Chemistry Data for Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 Copper Nickel Source (wt.-%) (wt.-%)

0.06 0.87 CMTR, Single Wire Analysis CMTR, Tandem Wire Analysis &

0.05 0.91 Surveillance Program Baseline Measurement Analysis performed on irradiated 0.04 0.95 specimen CW14 from Capsule U Therefore, the chemical content will be defined as shown below going forward:

Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 Cu Content == 0.05 v.1-%

Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 Ni Content == 0.91 wt-%

""* This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 21 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.7-1 Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 Plot of Measured Transverse Direction CVN Data CVGraph 6.02: Hype!bolic Tangelll Qu:ve Printed on 9fl.3l202 l 1:03 PM

=

A= 41.10 B 38.90 C =67,54 TO= -5.17 D =0,00 Correlation Coefficien! = 0. 978 Equation is A+ B

• Ffanl1((T-TO)/(C+DT))]

Upper ShelfEnergy =80.00 (Fixed) Lower ShclfEnergy = 2.20 (Fixed)

Temp@',30 fl-lbs=-24.90° F Tetilp@.15 ft-lbs=-15.80° F Tcmp(q).50 fl-lbs= 10.60° F Plant: V.C. Summer Material: SAW Heat: 4P4784 (3930)

Orientation: NA Capsule: Unin-.ul Fluencc: O.OOE+oOO nlcm' o---------------.. . .---------------------

-300 -200 -100 0 100 200 300 400 600 Temperature{° F)

CVGr.tph6.02 09/23/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36: 16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 22 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.7-1 Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 Plot of Measured Transverse Direction CVN Data (cont.)

Plant: V.C. Summer Material: SAW Heat: 4P4784 (3930)

Orientation: NA Capsule: Unirrad Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature {° F) InputCVN Computed CVN Differential

-120 7.0 4.7 2.29

-100 7:0 6.6 0.38

-50 32.0 18,5 13.50

-25 30.0 30.0 O.oJ

-20 22.0 32.7 -10.69 10 46.0 49.7 c3.69 40 64.0 63.8 0.18 50 71.0 67.3 3.71 80 80.0 74.2 5.78 125 85.5 78.4 7.11 210 91.5 79:9 11.63 212 79.0 79.9 -0.87 CVGraph 6.02 09/23/2021 Page 2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 23 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.7-2 Weld Heat# 4P4784, Linde 124 Flux, Lot# 3930 Plot of Measured Transverse Direction Lateral Expansion Data CVGrapll 6.02: Hypemolic Tangent Cu1Ve Printed on 9/23/2021 1:42 PM A =33.00 B=3:Z.OO C = 71.15 TO= -18.60 D =0.00 Correlation Coefficient= 0.978 Equation is A+ B

• ITanh((T-TO)/(C+DT))]

Upper She!fL.E. = 65 .00 {Fixed) Lower Sllclf L.E. = LOO (Fb:cd)

Temp@JJS mils=-14.10° F Plant: V.C. S11mmer Material: SAW Heat: 4P4784 (3930}

Orientation: NA Capsule: Unirrad Flnence: 0.OOE+oOO nA-m' 80 70

• --a-60

~

so

=

0

~

=

= 40

=-

~

Ji-1 e: 30

~

~

.I 20 10 o l=:::i:::=t:::1--1._,1,_L.L._.L...J-_L.......i.__JL.i_.L...i...-L.......i.__J

-300 -200 -HO 0 100 200 300 400 500 ,oo Temperature{° F)

CVGlllJlh 6.02 09/23/2021 Page 112

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 24 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.7-2 Weld Heat# 4P4784, Linde 124 Fiux, Lot# 3930 Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C. Summer Material: SAW Heat: 4P4784 (3930)

Orientation: NA Capsule: Unirrad Fluence: O.OOE+OOO n/cm*

Charpy V-Notch Data Temperature{° F) Input L. E. Computed L. E. Differential

-120 7.0 4.5 2.50

-100 9.0 6.9 *2.10

-50 21.0 19.7 1.27

-25 34.0 30.1 3.87

-20 25.0 32.4 0 7.37 10 46.0 45.2 0.79 40 55.0 54.7 0.34, 50 54.0 56.9 -2.88 80 65.0 61.2 3.77 125 74.0 63.9 10.11 210 73.0 64.9 8.10 212 80.0 64.9 15.10 CVGraph 6.02 09/23/2021" Page 2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 25 of75 Attachment C to PWROG-21037-NP Revision 2 C.8 V.C. Summer Unit 1, Heat# 5P5657, Linde 124 Flux, Lot# 0931 Tables C.8-1 and C.8-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files. The material properties were evaluated in two ways. 1st, the material properties were evaluated with the weld being deposited as a single wire. 2nd, the material properties were evaluated with the weld being deposited by tandem wires. For the purpose of this analysis, both will be evaluated, and the limiting property will be used.

Table C.8-1 Charpy V-Notch Test Data for the Weld Heat# 5PS657, Linde 124 Flux, Lot# 0931 CVNimpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

Single Wire

-80 39 27 5

-80 39 37 5

-80 29 32 5

-60 19 18 10

-60 20 22 10

-60 32 28 10 0 51 50 30 0 55 50 30 0 68 63 55 10 69 61 50 10 69 65 50 10 66 59 40 10 62 60 60 10 57 63 40 40 77 73 70 40 76 72 80 212 88 86 100 212 91 75 100 212 85 83 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 26 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.8-1 Charpy V-Notch Test Data for the Weld Heat# 5P5657, Linde 124 Flux, Lot# 0931 (cont)

CVNlmpact Lateral Temp. Shear Energy Expansion

{°F)

(ft-lb) (mils) (%)

Tandem Wire

-80 14 15 5

-80 23 22 5

-80 20 19 5

-20 42 41 20

-20 45 43 15

-20 47 44 20

-10 48 44 15

-10 46 42 20

-10 39 40 20 0 51 50 20 0 57 54 30 0 55 40 20 10 58 58 55 10 61 54 40 10 65 59 55 10 55 50 45 10 63 60 75 40 69 64 75 40 76 74 80 212 88 75 100 212 88 84 100 212 91 74 100

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Westinghouse Non-Proprietary Class 3 Page 27 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.8-2 Drop-Weight Test Data for Weld Heat# 5P5657, Linde 124 Flux, Lot# 0931 Test Temperature TNDT Drop-Weights<*>

(OF) (OF)

-40 1-NF

-50 2-NF Single -60 1-F -60

-70 1-F

-80 1-F

-40 1-NF Tandem -70 2-NF -80

-80 1-F Note for Table C.8-2:

(a) NF= "No Fail," F = "Fail".

C.8.1 Determination of the Initial RTNoT Using the data summarized in Tables C.8-1 and C.8-2, the initial RTNOT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNOT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

For the single wire, the Charpy V-notch tests were conducted at 0°F, TNoT + 60°F (-60°F + 60°F = 0°F).

The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNoT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNoT is the initial reference temperature RTNm-RTNoT_single = -60°F For the tandem wire, the Charpy V-notch tests were conducted at -20°F, TNoT + 60°F (-80°F + 60°F =

-20°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNOT+ 60°F would NOT satisfy the criteria. Since the analysis is to identify a bounding material property values for use in the extended beltline, it is not necessary precisely determine the temperature at which 50 ft-lb and 35 mils LE based on a hyperbolic tangent curve-fit. Instead, the temperature where all specimens experience greater than or equal to 50 ft-lb and 35 mils LE is used as the TSO/ T35mils. From Table C.8-1, this occurred at 0°F for the tandem data. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNoT is this temperature minus 60°F.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 28 of75 Attachment C to PWROG-21037-NP Revision 2 RTNDT_tandem = Tcv - 60°F = 0°F - 60°F RTNDT_tandem = -60°F Weld Heat# 5P5657, Linde 124 Flux, Lot# 0931 Initial RTNnT = -60°F C.8.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E 185 manual (2016 version). Using the guidelines in ASTM E 185-82 and E 185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. As with the RTNoT, both the single and tandem wire data will be evaluated separately, and the limiting value will be used.

The USE from the single and tandem wire are displayed below. These values are the average of each of the impact energy values contained in Table C.8-1 with shear 2: 95%. The USE for the material will be defined as the minimum between the single and tandem wire USE values.

Single Wire, Weld Heat# 5P5657, Linde 124 Flux, Lot# 0931 Initial USE = Average (88, 91, 85) ft-lb

= 88 ft-lb Tandem Wire, Weld Heat# 5P5657, Linde 124 Flux, Lot# 0931 Initial USE = Average (88, 88, 91) ft-lb

= 89 ft-lb Weld Heat# 5P5657, Linde 124 Flux, Lot# 0931 Initial USE = Min (88, 89) ft-lb

= 88 ft-lb C.8.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. If data for single or tandem wire includes multiple measurements, then the average of all available data will be used. The limiting value between the single and tandem weld will be used. The chemical compositions are summarized in Table C.8-3.

Table C.8-3 Chemistry Data for Weld Heat# 5P5657, Linde 124 Flux, Lot# 0931 Copper Nickel Source (wt.-%) (wt.-%)

0.07 0.71 Single Wire Check Analysis 0.04 0.89 Tandem Wire Check Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 5P5657, Linde 124 Flux, Lot# 0931 Cu Content = 0.07 wt-%

Weld Heat# 5P5657, Linde 124 Flux, Lot# 0931 Ni Content = 0.89 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 29 of 75 Attachment C to PWROG-21037-NP Revision 2 C.9 V.C. Summer Unit 1, Heat# 5P6214B, Linde 124 Flux, Lot# 0331 Tables C.9-1 and C.9-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files. The material properties were evaluated in two ways. 1si, the material properties were evaluated with the weld being deposited as a single wire. 2nd ,

the material properties were evaluated with the weld being deposited by tandem wires. For the purpose of this analysis, both will be evaluated, and the limiting property will be used.

Table C.9-1 Charpy V-Notch Test Data for the Weld Heat# 5P6214B, Linde 124 Flux, Lot# 0331 CVNimpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

Single Wire

-70 22 17 2

-70 13 10 2

-70 11 9 2

-50 42 34 15

-50 13 11 5

-50 34 26 10 10 56 45 25 10 50 41 20 10 54 46 30 10 55 52 20 10 50 45 15 10 54 50 20 10 55 55 50 10 54 52 20 40 76 66 75 40 66 52 45 100 87 70 95 100 89 64 90 120 96 68 100 120 90 61 100 120 88 71 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 30 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.9-1 Charpy V-Notch Test Data for the Weld Heat# 5P6214B, Linde 124 Flux, Lot# 0331 (cont.)

CVNlmpact Lateral Temp. Shear (OF) Energy Expansion

(%)

(ft-lb) (mils)

Tandem Wire

-80 17 14 2

-80 21 17 2

-40 25 20 5

-40 37 29 5

-40 29 28 5 10 50 46 50 10 61 50 40 10 64 52 35 10 61 55 30 10 37 42 20 10 54 50 25 10 47 47 15 10 68 63 45 20 75 53 55 20 69 47 60 20 78 55 55 40 82 65 75 40 80 62 75 120 100 60 100 120 96 81 100 120 97 57 100

.... This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 31 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.9-2 Drop-Weight Test Data for Weld Heat# SP6214B, Linde 124 Flux, Lot# 0331 Test Temperature TNDT Drop-Weights<*>

{°F) (OF)

-10 1-NF Single -40 2-NF -50

-50 1-F

-30 2-NF

-40 1-F Tandem -40

-50 1-F

-60 1-F Note for Table C.9-2:

(a) NF= "No Fail," F = "Fail" C.9.1 Determination of the Initial RTNnT Using the data summarized in Tables C.9-1 and C.9-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight T NDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

For the single wire, the Charpy V-notch tests were conducted at 1oap, T NDT + 60aF (-soap + 60aF = 1oaF).

The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNoT + 60aF satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNoT is the initial reference temperature RTNoT-RTNoT_singie = -soap For the tandem wire, the Charpy V-notch tests were conducted at 20°F, TNoT + 60aF (-40aF + 60aF =

2oaF). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 3 5 mils lateral expansion; therefore, the Charpy V-notch tests at T NDT + 60°F satisfy the criteria.

Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNDT is the initial reference temperature RTNoT-RTNoT_tandem = -40°F Weld Heat# SP6214B, Linde 124 Flux, Lot# 0331 Initial RTNnT = -40°F

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 32 of75 Attachment C to PWROG-21037-NP Revision 2 C.9.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E 185 manual (2016 version). Using the guidelines in ASTM E 185-82 and E 185-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out offamily,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. As with the RTNDT, both the single and tandem wire data will be evaluated separately, and the limiting value will be used.

The USE from the single and tandem wire are displayed below. These values are the average of each of the impact energy values contained in Table C.9-1 with shear~ 95%. The USE for the material will be defined as the minimum between the single and tandem wire USE values.

Single Wire, Weld Heat# 5P6214B, Linde 124 Flux, Lot# 0331 Initial USE = Average (87, 96, 90, 88) ft-lb

= 90 ft-lb Tandem Wire, Weld Heat# 5P6214B, Linde 124 Flux, Lot# 0331 Initial USE= Average (100, 96, 97) ft-lb

= 98 ft-lb Weld Heat# 5P6214B, Linde 124 Flux, Lot# 0331 Initial USE = Min (90, 98) ft-lb

= 90 ft-lb C.9.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. If data for single or tandem wire includes multiple measurements, then the average of all available data will be used. The limiting value between the single and tandem weld will be used. The chemical compositions are summarized in Table C.9-3.

Table C.9-3 Chemistry Data for Weld Heat# 5P6214B, Linde 124 Flux, Lot# 0331 Copper Nickel Source (wt.-%) (wt.-%)

0.02 0.82 0.02 0.82 Single Wire Check Analysis Average= 0.02 Average= 0.82 0.014 0.70 0.02 0.85 Tandem Wire Check Analysis Average= 0.017 Average= 0.775 Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 5P6214B, Linde 124 Flux, Lot# 0331 Cu Content = 0.02 wt-%

Weld Heat# 5P6214B, Linde 124 Flux, Lot# 0331 Ni Content = 0.82 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 33 of 75 Attachment C to PWROG-21037-NP Revision 2 C.10 V.C. Summer Unit 1, Heat# 5P6711, Linde 124 Flux, Lot# 0342 Heat# 5P6711, Linde 124 Flux, Lot# 0342 was used in the fabrication of Shearon Harris Unit 1. Therefore, the data shown in Tables C.10-1 and C.10-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the Shearon Harris Unit 1 CMTR and reactor vessel fabrication files. This data is combined with the additional data available from Shearon Harris Unit 1 surveillance program documented in WCAP-10502.

Table C.10-1 Charpy V-Notch Test Data for the Weld Heat# 5P6711, Linde 124 Flux, Lot# 0342 CVNlmpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

-110 7 1 15

-110 8 2 15

-100 6 7 5

-100 7 8 6

-100 7 7 4

-60 28.5 16 35

-60 34 18 40

-40 19 24 25

-40 22 29 30

-40 17 21 30

-30 28 20 55

-30 31 26 45

-30 33 26 45 0 42 36 50 0 46 41 55 0 52 45 55 10 40 41 50 10 39 46 50 10 37 38 60 10 61 52 45 10 49 41 30 10 54 47 35 10 56 48 30 10 61 53 55 lQ(a) 57(a) 46(a) 35(a) 10<*) 51 (a) 51<*) 40(a) 10<*) 55 47(a) 40(a)

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 34 of75 Attachment C to PWROG-21037-NP Revision2 Table C.10-1 Charpy V-Notch Test Data for the Weld Heat# 5P6711, Linde 124 Flux, Lot# 0342 (cont.)

CVN Impact Lateral Temp. Shear Energy Expansion

{°F)

(ft-lb) (mils)

(%)

IO(al 61 (a) 41(a) 3o(a) 1o(a) 42<*) 35(a) 25(a) 40 64 61 75 40 52 52 65 40 61 57 70 40 65 58 80 40 75 60 85 75 78 64 90 75 89 73 97 75 90 72 95 130 75 73 99 130 78 82 99 130 74 74 99 160 91 78 100 160 92 84 100 212 79 73 100 212 80 77 100 212 80 72 100 250 92 79 100 250 96 75 100 350 97 81 100 Note for Table C.10-1:

(a) Data from tandem wire specimens.

• • • This record was final approved on 3/6/2023, 12:36: 16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 35 of 75 Attachment C to PWROG-21037-NP Revision 2 Table C.10-2 Drop-Weight Test Data for Weld Heat# 5P6711, Linde 124 Flux, Lot# 0342 Test Temperature TNDT Source Drop-Weights<*l (OF) {°F)

-50 1-NF

-60 1-NF CMTR -80

-70 2-NF

-80 1-F Surv. Prog (Single) - - -30 Surv. Prog (Tandem) - - -20 Note for Table C.10-2:

(a) NF= "No Fail," F = "Fail" C.10.1 Determination of the Initial RTNoT Using the data summarized in Tables C.10-1 and C.10-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight T NDT ( or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE. The maximum T NOT is used. The Charpy V-notch tests were conducted at 40°F, TNDT + 60°F (-20°F + 60°F = 40°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 3 5 mils lateral expansion; therefore, the Charpy V-notch tests at T NOT+ 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNoT is the initial reference temperature RTNoT, Weld Heat# 5P6711, Linde 124 Flux, Lot# 0342 Initial RTNDT = -20°F C.10.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E185-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE is displayed below; this value is the average of each of the impact energy values contained in Table C.10-1 with shear~ 95% with the exception that all data at> 225°F are excluded from the calculation of USE. Per ASTM E 185-16, all data specimens tested at temperatures greater than 150°F above the Charpy upper-shelf onset, i.e.,~ 95% shear, which occurred at 75°F, shall not be included.

Weld Heat# 5P6711, Linde 124 Flux, Lot# 0342 Initial USE

= Average (89, 90, 75, 78, 74, 91, 92, 79, 80, 80) ft-lb

= 83 ft-lb

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 36 of75 Attachment C to PWROG-21037-NP Revision2 C.10.3 Chemistry The Cu and Ni wt. % chemical compositions of the reactor vessel materials were defined by a review of the available original test documentation. The average of all available data will be used. The chemical compositions are summarized in Table C.10-3.

Table C.10-3 Chemistry Data for Weld Heat# 5P6711, Linde 124 Flux, Lot# 0342<a)

Copper Nickel Source (wt.-%) (wt.-%)

0.03 0.88 Single Wire Analysis 0.04 0.95 Tandem Wire Analysis WCAP-10502 0.023 0.87 rHNP-1 Surveillance Report Unirradiatedl BAW-2083 0.026 0.94 fHNP-1 Sµrveillance Report - Irradiatedl BAW-2083 0.019 1.07 rHNP-1 Surveillance Report Irradiatedl BAW-2083 0.029 0.95 fHNP-1 Surveillance Report Irradiatedl Note for Table C.10-3:

(a) Information extracted from ANP-3798NP, "Analysis of Capsule Z Duke Energy Shearon Harris Nuclear Power Plant," dated September 2019 (ADAMS Access No. ML19296C841).

Therefore, the chemical content will be defined as shown below going forward:

Weld Heat# 5P6711, Linde 124 Flux, Lot# 0342 Cu Content = 0.03 wt-%

Weld Heat# 5P6711, Linde 124 Flux, Lot# 0342 Ni Content = 0.94 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 37 of75 Attachment C to PWROG-21037-NP Revision 2 C.11 V.C. Summer Unit 1 Shielded Metal Arc Welds Most of the SMAW Charpy tests were performed only at 2 or 3 temperature points. Table C.11-1 summarizes all available copper and nickel chemistry, Charpy V-notch test data, and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files for the heats with Charpy tests at only a few temperature points. Those heats with Charpy data over a full temperature range are evaluated in subsequent sections.

C.11.1 Determination of the Initial RTND*r The RTNDT values are determined one of two ways. First, the initial RTNDT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight T NDT ( or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE. If the requirements have been met, then TNoT is the initial reference temperature RTNDT*

Second, if the Charpy V-notch tests at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion, or the drop-weight data does not exist; NUREG-0800 BTP 5-3 Position 1.1(4) may be used as an estimate ofRTNoT when tests were performed at a single temperature. If all impact energies at that temperature are greater than 45 ft-lb; then the initial RTNDT is equal to that temperature. If the impact energies are less than 45 ft-lb, then the initial RTNDT is equal to that temperature

+ 20°F.

C.11.2 Determination of the Initial USE If no data with known shear 2".: 95% exists, the USE is set to greater than the impact energy with highest shear. If the highest shear includes multiple CVN impact energies, then the USE is set to greater than the largest impact energy. The USE for the material will be defined as the USE value with highest shear between the single and tandem wire.

C.11.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. If data includes multiple measurements, then the average of all available data will be used. The limiting value between the single and tandem weld will be used.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 38 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.11-1 SMAWs Material Properties Impact Shear Initial Best Est. Best Est.

Heat Temp LE Measured Measured TNDT USE Lot Number Energy Fracture RTNDT Cu Ni Number {°F) (mils) Cu Ni {°F) (ft-lb)

(ft-lb) (%) {°F) (wt. - o/o) (wt. - o/o)

-20 26 27 30

-20 38 34 40

-20 42 37 40

-20 50 45 50 >73.5@

624263 E204A27A 0.06 0.89 -20 -20 0.06 0.89

-20 75 62 60 75%

40 62 55 60 40 58.5 51 60 40 73.5 64 75

-20 38.5 34 40

-20 49.5 42 45

-20 41.5 38 40 0.04 0.95

-20 38 32 40

-20 56.5 48 60

>91@

421A6811 F022A27A 10 80 64 70 -20 -20 0.07 0.88 75%

10 85 73 75 0.09 0.81 10 91 72 75 40 50 47 50 - -

40 56.5 51 55 - -

40 50 46 50 - -

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 39 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.11-1 SMAWs Material Properties (cont.)

Impact Shear Initial Best Est. Best Est.

Lot Temp LE Measured Measured TNDT USE Cu Ni Heat Number Energy Fracture RTNDT Number {°F) (mils) Cu Ni {°F) (ft-lb)

(ft-lb) (%) (OF) (wt.-%) (wt. - %)

-20 49 41 40

-20 60 54 40

-20 55 46 35 O.Q3 1.02

-20 61 50 35 >50@

07L669 K004A27A NIA -20 0.03 1.02

-20 54 49 35 60%

10 50 44 50 10 50 44 60 0.03 1.02 10 54 46 40

-20 33 30 30

-20 34 31 35

-20 38 32 30 0.02 0.87

-20 31 28 30

-20 30 27 25

>57@

C3L46C J020A27A 10 35 34 60 -20 -20 65%

0.02 0.87 10 39 39 60 0.02 0.87 10 40 39 60 40 56 41 55 - -

40 50 43 55 - -

40 57 38 65 - -

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 40 of75 Attachment C to PWROG-21037-NP Revision2 Table C.11-1 SMAWs Material Properties (cont.)

Impact Shear Initial Best Est. Best Est.

Lot Temp LE Measured Measured Ti\UT USE Heat Number Energy Fracture RTNDT Cu Ni Number {°F) (mils) Cu Ni {°F) (OF)

(ft-lb)

(ft-lb) (%) (wt. - %) (wt. - %)

-20 52 46 35

-20 46 40 35

-20 43 39 30 0.04 0.9

-20 47 40 30

-20 48 40 30 10 65 52 60 >66@ 0.04 0.90 422B7201 L030A27A -20 -20 70%

10 66 55 70 0.04 0.9 10 72 56 60 40 80 55 40 - -

40 81 54 50 - -

40 78 57 55 - -

-20 54 46 46

-20 64 54 54

-20 54 45 45 0.03 0.86

-20 48 42 42 >78@

09L853 A111A27A NIA -20 0.03 0.86

-20 65 53 53 80%

10 78 60 70 10 78 62 80 0.03 0.86 10 79 62 60

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 41 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.11-1 SMAWs Material Properties (cont.)

Impact Shear Initial Best Est. Best Est.

Lot Temp LE Measured Measured TNDT USE Heat Number Energy Fracture RTNDT Cu Ni Number (OF) (mils) Cu Ni (OF) (ft-lb)

(ft-lb) (%) (OF) (wt. - %) (wt. - %)

-20 46 39 30

-20 50 43 35

-20 45 40 30 0.02 1.1

-20 50 43 35 >51@

08M365 Gl28A27A NIA -20 0.02 1.10

-20 47 40 35 60%

10 49 38 60 10 50 40 50 0.02 1.1 10 51 43 60

-20 33 29 40

-20 37 30 35 0.03 0.87

-20 38 26 40 > 102.5@

421E0601 Lll7A27A -20 -20 0.03 0.87 40 102.5 81 90 - - 90%

40 101.5 78 85 - -

40 106 75 85 - -

-20 33 35 25

-20 35 34 35 0.03 0.92

-20 36 31 25 >88@

09M814 Ll15A27A -20 -20 0.03 0.92 40 78.5 68 75 - - 80%

40 81 64 75 - -

40 88 74 80 - -

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 42 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.11-1 SMAWs Material Properties (cont.)

Impact Shear Initial Best Est. Best Est.

Lot Temp LE Measured Measured TNDT USE Ni Heat Number Energy Fracture RTNDT Cu Number {°F) (mils) Cu Ni {°F) (OF) (ft-lb)

(ft-lb) (%) (wt. - %) (wt. - %)

-20 38 34 50

-20 38 32 50 0.01 0.82

-20 40 35 60 >92@

09M814 L114A27A -20 -20 0.01 0.82 40 92 75 80 - - 80%

40 70 60 70 - -

40 77 64 75 - -

-20 28 27 40

-20 32 28 50 0.05 0.84

-20 42 35 45 >80@

623275 Ll21A27A -20 -20 0.05 0.84 40 68.5 52 55 75%

40 80 66 75 - -

40 77.5 61 70

-20 22 20 30

-20 30 24 20

-20 31 26 20 0.06 1.08

-20 43 36 30 >80@

627260 B322A27AE -20 -20 0.06 1.08

-20 55 44 40 25%

40 77 57 25 40 75 77 25 - -

40 80 60 25

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page43 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.11-1 SMAWs Material Properties (cont.)

Impact Shear Initial Best Est. Best Est.

Lot Temp LE Measured Measured TNDT USE Heat Number Energy Frncture RTNDT Cu Ni Number {°F) (mils) Cu Ni {°F) (ft-lb)

(ft-lb) (%) (OF) (wt. - %) (wt.-%)

-20 28 29 30

-20 33 32 40

-20 34 33 40 0.07 1.01

-20 36 34 40 >86@

624039 D224A27A -20 -20 0.07 1.01

-20 42 42 40 63%

40 80 56 45 40 86 63 63 - -

40 79 55 55

-20 29 26 30

-20 30 26 30

-20 31 31 30 0.09 0.90

-20 36 33 40 >85@

0SP018 D211A27A -20 -20 0.09 0.90

-20 38 35 40 70%

40 85 66 70 40 86 61 65 - -

40 88 65 60

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 44 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.11-1 SMAWs Material Properties (cont.)

Impact Shear Initial Best Est. Best Est.

Lot Temp LE Measured Measured TNDT USE Cu Ni Heat Number (OF)

Energy Fracture RTNDT Number (mils) Cu Ni {°F) (OF)

(ft-lb)

(ft-lb) (%) (wt. - %) (wt. - %)

-20 68 55 60

-20 68.5 54 60

-20 66.5 55 60 0.02 1.05

-20 48.5 41 50

-20 80 64 65

> 113.5@

42120611 L908A27A IO 66 53 70 -20 -20 0.03 1.01 85%

IO 79 58 70 O.o3 0.96 10 80 62 80 40 85 61 75 40 98.5 76 80 - -

40 113.5 79 85

-20 34 23 20

-20 36 28 20

>40@

04P046 D217A27A -20 37 24 30 0.06 0.90 NIA 0 0.06 0.90 30%

-20 39 20 30

-20 40 24 30

-20 37 33 30

-20 40 34 40

-20 51 41 40 0.03 1.00

-20 57 47 50 >70@

624063 C228A27A -20 -20 0.03 LOO

-20 70 55 60 60%

40 99 66 35 40 104 47 40 - -

40 107 80 50

""* This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 45 of75 Attachment C to PWROG-21037-NP Revision 2 C.12 V.C. Summer Unit 1, Heat# 05T776, Lot# L314A27AH Tables C.12-1 and C.12-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files.

Table C.12-1 Charpy V-Notch Test Data for the Weld Heat# 05T776, Lot# L314A27AH CVNimpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

-108 4 3 4

-108 5 4 4

-70 13 13 10

-70 14 15 10

-70 25 23 25

-30 59 33 30

-30 65 42 30

-20 38 37 15

-20 67 57 20

-20 63 53 15

-20 50 43 10

-20 72 60 20 10 65 56 40 10 84 71 50 40 101 79 80 40 108 72 75 130 103 90 100 130 126 96 100 130 127 94 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 46 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.12-2 Drop-Weight Test Data for Weld Heat# 05T776, Lot# L314A27AH Test Temperature TNDT Drop-Weights<al

{°F) (OF)

-60 2-NF

-70 1-F -70

-80 1-F Note for Table C.12-2:

(a) NF= "No Fail," F = "Fail".

C.12.1 Determination of the Initial RTNDT Using the data summarized in Tables C.12-1 and C.12-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to detennine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

The Charpy V-notch tests were conducted at-20°F, which is less than TNoT + 60°F (-70°F + 60°F -10°F).

The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNoT + 60°F would NOT satisfy the criteria. Since the analysis is to identify a bounding material property values for use in the extended beltline, it is not necessary precisely determine the temperature at which 50 ft-lb and 35 mils LE based on a hyperbolic tangent curve-fit. Instead, the temperature where all specimens experience greater than or equal to 50 ft-lb and 35 mils LE is used as the TSO/ T35mils. From Table C.12-1, this occurred at 10°F. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNoT is this temperature minus 60°F.

RTNoT = Tcv - 60°F l0°F - 60°F RTNDT =-50°F Weld Heat# 05T776, Lot# L314A27AH Initial RTNDT = -50°F C.12.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E185-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineeringjudgment to remove 'out of family' data was not necessary for this material. The USE is displayed below; this value is the average of each of the impact energy values contained in Table C.12-1 with shear~ 95%.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 47 of75 Attachment C to PWROG-21037-NP Revision 2 Weld Heat# 05T776, Lot# L314A27AH Initial USE = Average (103, 126, 127) ft-lb

= 119 ft-lb C.12.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit I reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. The chemical compositions are summarized in Table C.12-3.

Table C.12-3 Chemistry Data for Weld Heat# 05T776, Lot# L314A27AH Copper Nickel Source (wt.-%) (wt.-%)

0.06 0.92 CBI Wire Analysis 0.06 0.92 Chemetron verification Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 05T776, Lot# L314A27AH Cu Content = 0.06 wt-%

Weld Heat# 05T776, Lot# L314A27AH Ni Content = 0.92 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 48 of75 Attachment C to PWROG-21037-NP Revision 2 C.13 V.C. Summer Unit 1, Heat# 422K8511, Lot# G313A27AD Tables C.13-1 and C.13-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files.

Table C.13-1 Charpy V-Notch Test Data for the Weld Heat# 422K8511, Lot# G313A27 AD CVNimpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

-90 14(a) 15(a) 5

-90 17 16 5

-80 14(a) 15(a) 10

-80 16 16 10

-80 20 20 10

-40 26 26 30

-40 26(a) 24<*) 30

-40 40 33 30

-20 65 44 40

-20 74 48 50

-20 127 76 60

-20 62 52 30

-20 63 50 30

-20 83 60 35

-20 40<*) 32<*) 25

-20 49 35 25 25 107<*) 74(a) 80 25 108 80 70 40 125(a)(b) 84 100 40 125 89 100 40 140 82<*) 90 50 153 95 90 50 143(a) 81 (a) 80 50 156 91 90 68 153 35(a)(b) 100 68 143(a) 96 100 68 165 91 100 Notes for Table C.13-1:

(a) Minimum value used in the CVGRAPH plots in accordance with ASME Code III Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CVGRAPH plots.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 49 of75 Attachment C to PWROG-2I037-NP Revision 2 Table C.13-2 Drop-Weight Test Data for Weld Heat# 422K8511, Lot# G313A27AD Test Temperature TNDT Drop-Weights<*>

(OF) (OF)

-39 I-NF

-58 I-NF

-80

-70 2-NF

-80 I-F Note for Table C.13-2:

(a) NF= "No Fail," F = "Fail".

C.13.1 Determination of the Initial RTNnT Using the data summarized in Tables C.13-I and C.13-2, the initial RTNOT value can be determined in accordance with the ASME Code Section III, Subarticle NB-233 I requirements. Following the requirements of ASME Code Section III, Subarticle NB-233 I, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNoT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

The Charpy V-notch tests were conducted at -20°F, TNoT + 60°F (-80°F + 60°F = -20°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F would NOT satisfy the criteria. However, since the majority of the Charpy V-notch tests at TNoT + 60°F met the ASME Section III criterion, it was decided to plot and fit the unirradiated Charpy V-notch data using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-233I, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience 2: 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNOT, Tso ft-lb= -17.5°F T3s mils= -25.9°F Tcv = Max [Tso ft-lb, T3s mir] = Max [-I 7.5°F, -25.9°F]

Tcv = -17.5°F Following the requirements of ASME Code Section III, Subarticle NB-233 I, Paragraph (a)(3), the initial RTNoT is the higher of TNoT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 50 of75 Attachment C to PWROG-21037-NP Revision 2 RTNDT = Max [TNDT, Tcv - 60°F]

RTNDT = Max [-80°F, -17.5°F - 60°F] = Max [-80°F, -77.5°F]

Weld Heat# 422K8511, Lot# G313A27AD Initial RTNDT = -78°F C.13.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E 185 manual (2016 version). Using the guidelines in ASTM E 185-82 and E 185-16, the average of all Charpy data:::: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE is displayed below; this value is the average of each of the impact energy values contained in Table C.13-1 with shear:::: 95%.

Weld Heat# 422K8511, Lot# G313A27AD Initial USE = Average (125, 125, 153, 143, 165) ft-lb

= 142 ft-lb C.13.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. The chemical compositions are summarized in Table C.13-3.

Table C.13-3 Chemistry Data for Weld Heat# 422K8511, Lot# G313A27AD Copper Nickel Source (wt.-%) (wt.-%)

0.01 1.00 CBI Wire Analysis 0.01 1.00 Chemetron verification Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 422K8511, Lot# G313A27 AD Cu Content = 0.01 wt-%

Weld Heat# 422K8511, Lot# G313A27 AD Ni Content = 1.00 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 51 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.13-1 Heat# 422K8511, Lot# G313A27AD Plot of Measured Transverse Direction CVN Data CVGrnph 6.02: Hyperbolic Tangent Cmve Printed on 9/28/2021 11 :50 AM A=63.60 B =61.40 C = 31.71 T0=-10.41 D =0.00 Correlation Coefficient = 0. 986 Equation is A+ B * [Taah((T-TO)/(C+DT))I Upper Shelf Energy= 125.00 (Fhcd) Lower Shelf Energy = 2.20 (Fh,cd)

Tcmp@30 ft-lbs=-29.80° F Tcmp@.35 fl-lbs=-26.40° F Tcmp@',50 fl-lbs=-17.50° F Plant: V.C. Summer Material: Sl\lAW Heat: 422K85U (G313A27AD)

Orientation: NA Capsule: Unirrad Fluencc: O.OOE+-000 n/cm>

160 . . . - - - , - - - - , - - - - , - - - - , - - - - , - - - - , - - - - , - - - - , - - - -

140 00 I-****-:***

g..--+-.---+--...--+-...---t---,--1---,-----1 120

..0

~

100 I

ct:

. ~ .... - . I

-=

bJJ  :

80

~

r-1

z 60 u>

40 ,

20

q

~--

0

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

CVGraph 6.02 09/28/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 52 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.13-1 Heat# 422K8511, Lot# G313A27AD Plot of Measured Transverse Direction CVN Data (cont.)

Plant: V.C. Summer Material: SMAW Heat: 422K8511 (G313A27AD)

Orientation: NA Capsule: Unirrad Fluence: 0.00E+000 n/cm2 Charpy V-Notch Data Temperature{° F) InputCVN Computed CVN Differential

-90 14.0 3.0 10.99

-80 14.0 3.7 10.29

-40 26:0 18.6 7.35

-20 40.0 45.6 -5.57 25 107.0 113.l 0 6.11 40 125.0 120.1 4.91 50 143.0 122.3 20.66 68 143.0 124.1 18.87 CVGraph 6.02 09/28/2021 Page 2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 53 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.13-2 Heat# 422K8511, Lot# G313A27AD Plot of Measured Transverse Direction Lateral Expansion Data CVGraph 6.02: Hyperbolic Tangent Ctnve Printed on 9/28/2021 11 :53 AM A= 43.00 B = 42.00 C = 50.81 TO= -16.20 D = 0.00 Correlation Coefficient = 0. 987 Equation is A+ B

• rranh((T-TO)/(C+DT))]

Upper ShclfL.E. = 85.00 (Fb.cd) Lower Shelf L.E. = LOO (Fixed)

Plant: V.C. Summer Material: SMAW Heat: 422K851l (G313A27AD)

Orientation: NA Capsule: Unirrad Flucncc: 0.00E+o00 n/cm2 90 - - - - - - - . . . - - - . . . - - - - - - - - - - - - , - - - -.....- -......- - - -

80

--....e 70 r,:i l*******

....=

0 r,i 60 50 j

=

=

~

I

~

40

-=

~

r...

~

...... 30  : D

~

=

20 10 o I:::*=* ... =I

...i:::::: 1

... I:::.**::r:::::::~:..J- --i.---1---i.----L_..i,_-1..*_* .. -..i...~-*_*

• • • L**_*.*.i...***.*_*. .L-.1.....-L ........J

... ;L-

...._J

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGmph6.02 09/28/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 54 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.13-2 Heat# 422K8511, Lot# G313A27AD Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C. Summer Material: SMAW' Heat: 422K8511 (G313A27AD)

Orientation: NA Capsule: Unirrad Fluence: 0.00E+000 n/c1u*

Charpy V-Notch Data Temperature{° F) Input I.E. Computed L E. Differential

-90 15.0 5.4 9.64

-80 15.0 7.3 7.70

-40 24.0 24.6 -0.65

-20 32.0 39.9 -7.86 25 74.0 71.l 2.86 40 82.0 76.7 5.29 50 81.0 79.2 1.78 68 85.0 82.l 2.95 CVGraph 6.02 09/28/2021 Page2f2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 55 of75 Attachment C to PWROG-21037-NP Revision 2 C.14 V.C. Summer Unit 1, Heat# 492L4871, Lot# A421B27AE Tables C.14-1 and C.14-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files.

Table C.14-1 Charpy V-Notch Test Data for the Weld Heat# 492L4871, Lot# A421B27AE CVN Impact Lateral Temp. Shear (OF) Energy Expansion

(%)

(ft-lb) (mils)

-108 10 5 4

-108 11 4 4

-90 25 6 8

-90 30 6 10

-90 32 6 10

-30 19 19 20

-30 28 23 25

-30 31 25 25

-20 22 23 25

-20 26 21 25

-20 30 27 30

-20 92 63 25

-20 80 58 25

-20 66 48 20

-20 59 46 20

-20 59 42 20

-10 38 28 30

-10 41 32 30

-10 43 30 30 0 50 36 30 0 51 38 40 0 57 40 45 40 135 84 90 40 137 80 80 130 151 80 100 130 160 82 100 130 161 81 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 56 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.14-2 Drop-Weight Test Data for Weld Heat# 492L4871, Lot# A421B27AE Test Temperature TNDT Drop-Weights<a)

(OF) (OF)

-70 2-NF

-80 2-NF -90

-90 1-F Note for Table C.14-2:

(a) NF= "No Fail," F = "Fail".

C.14.1 Determination of the Initial RTNDT Using the data summarized in Tables C.14-1 and C.14-2, the initial RTNoT value can be determined in accordance with the ASME Code Section II1, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

The Charpy V-notch tests were conducted at -30°F, TNnT + 60°F (-90°F + 60°F = -30°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNDT + 60°F would NOT satisfy the criteria. Since the analysis is to identify a bounding material property values for use in the extended beltline, it is not necessary precisely determine the temperature at which 50 ft-lb and 35 mils LE based on a hyperbolic tangent curve-fit Instead, the temperature where all specimens experience greater than or equal to 50 ft-lb and 35 mils LE is used as the TSO/ T35mils. From Table C.14-1, this occurred at 0°F. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNnT is this temperature minus 60°F.

RTNDT Tcv - 60°F 0°F - 60°F RTNDT =-60°F Weld Heat# 492L4871, Lot# A421B27AE Initial RTNoT = -60°F C.14.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM El85 manual (2016 version). Using the guidelines in ASTM E185-82 and El 85-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE is displayed below; this value is the average of each of the impact energy values contained in Table C.14-1 with shear 2: 95%.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 57 of75 Attachment C to PWROG-21037-NP Revision 2 Weld Heat# 492L4871, Lot# A421B27AE Initial USE = Average (151, 160, 161) ft-lb

= 157 ft-lb C.14.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. The chemical compositions are summarized in Table C.14-3.

Table C.14-3 Chemistry Data for Weld Heat# 492L4871, Lot# A421B27 AE Copper Nickel Source (wt.-%) (wt.-%)

0.04 0.95 CBI Wire Analysis 0.04 0.95 CBI verification Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 492L4871, Lot# A421B27AE Cu Content = 0.04 wt-%

Weld Heat# 492L4871, Lot# A421B27AE Ni Content = 0.95 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 58 of75 Attachment C to PWROG-21037-NP Revision 2 C.15 V.C. Summer Unit 1, Heat# 492L4871, Lot# A421B27AF Tables C.15-1 and C.15-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files.

Table C.15-1 Charpy V-Notcb Test Data for the Weld Heat# 492L4871, Lot# A421B27AF CVN Impact Lateral Temp. Shear (OF) Energy Expansion

(%)

(ft-lb) (mils)

-108 7 6 4

-108 9 7 3

-80 40 9 10

-80 46 10 10

-80 49 13 10

-30 50 20 20

-30 51 17 20

-30 54 21 20

-20 49 18 20

-20 51 21 20

-20 52 20 20

-20 78 55 50

-20 82 60 45

-20 105 72 40

-20 93 64 25

-20 81 60 20

-10 43 27 30

-10 55 32 35

-10 56 33 35 0 33 31 30 0 50 36 40 0 52 34 28 10 56 38 35 10 58 37 35 10 61 42 35 40 62 49 35 40 63 50 40 40 68 56 30 130 126 93 100 130 129 94 100 130 136 91 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 59 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.15-2 Drop-Weight Test Data for Weld Heat# 492L4871, Lot# A421B27AF Test Temperature TNDT Drop-Weights<*>

{°F) {°F)

-70 2-NF

-80

-80 1-F Note for Table C.15-2:

(a) NF= "No Fail," F ="Fail".

C.15.1 Determination of the Initial RTNDT Using the data summarized in Tables C.15-1 and C.15-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

The Charpy V-notch tests were conducted at -20°F, TNoT + 60°F (-80°F + 60°F = -20°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNoT + 60°F would NOT satisfy the criteria. Since the analysis is to identify a bounding material property values for use in the extended beltline, it is not necessary precisely determine the temperature at which 50 ft-lb and 35 mils LE based on a hyperbolic tangent curve-fit. Instead, the temperature where all specimens experience greater than or equal to 50 ft-lb and 35 mils LE is used as the TSO/ T35mils. From Table C.15-1, this occurred at 0°F. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNoT is this temperature minus 60°F.

RTNDT = Tcv - 60°F = 0°F - 60°F RTNOT= -60°F Weld Heat# 492L4871, Lot# A421B27AF Initial RTNnT = -60°F C.15.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E185-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE is displayed below; this value is the average of each of the impact energy values contained in Table C.15-1 with shear 2: 95%.

Weld Heat# 492L4871, Lot# A421B27AF Initial USE = Average (126, 129, 136) ft-lb

= 130 ft-lb

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 60 of75 Attachment C to PWROG-21037-NP Revision 2 C.15.3 Chemistry The Cu and Ni wt % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. The chemical compositions are summarized in Table C.15-3.

Table C.15-3 Chemistry Data for Weld Heat# 492L4871, Lot# A421B27 AF Copper Nickel Source (wt.-%) (wt.-%)

0.03 0.98 CBI Wire Analysis 0.03 0.98 CBI verification Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 492L4871, Lot# A421B27 AF Cu Content 0.03 wt-%

Weld Heat# 492L4871, Lot# A421B27AF Ni Content 0.98 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 61 of75 Attachment C to PWROG-21037-NP Revision 2 C.16 V.C. Summer Unit 1, Heat# 624039, Lot# D205A27A Tables C.16-1 and C.16-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files.

Table C.16-1 Charpy V-Notch Test Data for the Weld Heat# 624039, Lot# D205A27A CVNimpact Lateral Temp. Shear (OF) Energy Expansion

(%)

(ft-lb) (mils)

-120 8 8 0

-120 6<*) 5(a) 0

-90 29 23 5

-90 11 9 2

-90 5(a) 5(a) 2

-60 16(*) 13<*) 5

-60 45 37 10

-60 21 19 5

-30 64 51<*l 20

-30 61 (a) 52 15

-30 69 57 20

-20 41C*) 32(*) 20

-20 44 39 30

-20 49 40 30

-20 54 41 35

-20 58 45 40 40 86(*) 70C*l 50 40 96 70 80 100 116 66(a)(b) 95 100 106<*) 84 90 150 118(a)(b) 68(*) 100 150 119 98 100 150 121 91 100 Notes for Table C.16-1:

(a) Minimum value used in the CVGRAPH plots in accordance with ASME Code III Subarticle NB-2331 criteria.

(b) The value fixed as the upper shelf in CVGRAPH plots.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 62 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.16-2 Drop-Weight Test Data for Weld Heat# 624039, Lot# D205A27A Test Temperature TNDT Drop-Weights<*>

{°F) (OF)

-60 1-NF

-80 2-NF

-90

-90 1-F

-100 1-F Note for Table C.16-2:

(a) NF= "No Fail," F = "Fail".

C.16.1 Determination of the Initial RTNDT Using the data summarized in Tables C.16-1 and C.16-2, the initial RTNoT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNOT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

The Charpy V-notch tests were conducted at -30°F, TNoT + 60°F (-90°F + 60°F = -30°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNoT + 60°F satisfy the criteria. However, minimum Charpy V-notch test data at a higher temperature failed to meet the ASME Section III criterion; therefore, it was decided to plot and fit the unirradiated Charpy V-notch data using a hyperbolic tangent curve-fitting software, CVGRAPH. Only the minimum data points at each Charpy V-notch test temperature were used as input to the curve-fitting software, in accordance with ASME Code Section III, Subarticle NB-2331, Paragraph (a)(4). When plotting, the USE is fixed to the minimum Charpy impact energy or lateral expansion used in the plot which experience 2'.: 95% shear. The resulting CVGRAPH figures are contained in the following pages for Charpy V-notch absorbed energy and lateral expansion.

Using these figures, the temperature at which 50 ft-lb absorbed energy and 35 mils lateral expansion were achieved may be obtained. The absorbed energy test data is more conservative than the lateral expansion test data; therefore, it becomes the dominant data set in defining initial RTNoT-T5oft-lb = -l6.8°F L5mils = -33.4°F Tcv = Max [T5o ft-lb, T3s mil]= Max [-16.8°F, -33.4°F]

Tcv = -16.8°F Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNoT is the higher of TNoT (determined from the drop-weight tests) and Tcv (determined above) minus 60°F.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 63 of75 Attachment C to PWROG-21037-NP Revision 2 RTNDT = Max [TNDT, Tcv - 60°F]

RTNDT = Max [-90°F, -16.8°F - 60°F] = Max [-90°F, -76.8°F]

Weld Heat# 624039, Lot# D205A27A Initial RTNnT = -77°F C.16.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE is displayed below; this value is the average of each of the impact energy values contained in Table C.16-1 with shear~ 95%.

Weld Heat# 624039, Lot# D205A27A Initial USE = Average (116, 118,119,121) ft-lb

= 119 ft-lb C.16.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. The chemical compositions are summarized in Table C.16-3.

Table C.16-3 Chemistry Data for Weld Heat# 624039, Lot# D205A27A Copper Nickel Source (wt.-%) (wt.-%)

0.028 0.91 CBI Wire Analysis Action Welding Supply Co. verification 0.10 0.92 Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 624039, Lot# D205A27A Cu Content = 0.06 wt-%

Weld Heat# 624039, Lot# D205A27A Ni Content = 0.92 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 64 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.16-1 Heat# 624039, Lot# D205A27A Plot of Measured Transverse Direction CVN Data CVGraph 6.02: Hyperbolic Tangent CuIVe Printed on 9/20/2021 3:57 PM A=60.l0 B=57.90 C =77.69 TO =-3,16 D= 0.00 Correlation Coefficient = 0. 978 Equation is A+ B * [Tanh((T-TO)/(C+D1))1 Upper Shelf Energy = 118.00 (Fh;cd) Lower Shelf Energy = 2.20 (Fb:cd)

Temp@30 ft-lbs=-47.90° F Tcmp@J5 fl-lbs=-39.20° F Tcmp@50 fl-lbs=-16.80° F Plant: V.C. Summer Material: SMAW Heat 624039 (D20SA27A)

Orientation: NA Capsule: Unirr.id Fluencc: O.OOE-+-000 n/cm' 80 -~--+--'---l-----+-1----i-----+--'----+---'----+--------1----'---I 0 _________...______________________..._____________

-300 -200 0 100 200 300 400 600 Temperature {° F)

CVGmph6.02 09/20/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 65 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.16-1 Heat# 624039, Lot# D205A27A Plot of Measured Transverse Direction CVN Data (cont.)

Plant: V.C. Summer Material: SMAW Heat: 624039 (D205A27A)

Orientation: NA Capsule: Unirrad Fluence: O.OOE+OOO n/cm 2 Charpy Y-Notch Data Temperature {° F) InputCVl'il Computed CVN Differential

-120 6.0 7.7 -1.65

-90 5.0 13.4 s8.39

-60 16:0 24.0 -7.97

-30 61.0 40.9 20.14

-20 41.0 47.7 -6.75 40 86.0 89.3 -3.32 100 106.0 110.4 -4.40 150 118.0 115.8 2.20 CVGraph 6.02 09/20/2021 Page 2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 66 of 75 Attachment C to PWROG-21037-NP Revision 2 Figure C.16-2 Heat# 624039, Lot# D205A27A Plot of Measured Transverse Direction Lateral Expansion Data CVGraph 6.112: Hype1bolic Tangent Curve Primed on 9/20/2021 3:59 PM A= 33.50 B = 32.50 C = 42.42 TO= -35.42 D =0.00 Conelation Coefficient = 0. 965 Equation is A+ B * (Tanh((T-TO)/(C+Dn)J Upper ShclfL.E. = 66.00 (Fixed) Lower Shelf L.E. = 1.00 (Fixed)

Tcmp:g)35 mils=-33.40° F Plant: V.C. Summer Material: SMAW Heat: 624039 (D205A27A)

Orientation: NA Capsule: Unirrad Flucncc: 0.00E-+-000 n/cm*

70 ,---,---,----,---....,...-t,t-.....,.---,---,-----,----.----.

6 60 -----------,---------+-----+----- T 1

';;' 50 0 1-+--'-------+-----+---+-----+-----t

=E t - - - - ' - - + - - - - --""'-

I

.s= 40 t------'---+---'---l---'--+--+------1----'---+--'----+---+---'---+---'----t rl'J

=

=

Q.,

~ 0

-.....=

r-1 30

""'aJ

---

+----il--+----+-----+----'---+----'--+---i--+-----1

= 20 --~--+------1--+----+-----+-~---------------

.. 10 t---,--+-~--------1-**t_-!,_-------+----,---+----I-*---~'.--_--_-- --;---f----;-----t---------;--'--------

-o , __ -- -

~ '

o t:::::::::i::::::+/-:::::i::._.L_,i_---1._1..-.L.....i....--1_.i..__L-1,.__JL..1........L---1.__J

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

CVGmph6.02 09/20/2021 Page 1/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 67 of75 Attachment C to PWROG-21037-NP Revision 2 Figure C.16-2 Heat# 624039, Lot# D205A27A Plot of Measured Transverse Direction Lateral Expansion Data (cont.)

Plant: V.C. Summer Material: s:MAW- Heat: 624039 (D205A27A)

Orientation: NA Capsule: Unirrad Fluence: O.OOE+OOO n/cm 2 Charpy V-Notch Data Temperature {° F) lnputL. E. Computed L. E. Differential

-120 5.0 2.2 2.82

-90 s.b 5.6 -0.61

-60 13.0 16.5 -3.53

-30 51.0 37.6 13.37 c20 32.0 44.8 -12.82 40 70.0 64.2 5.81 100 66.0 65.9 0.11 150 68.0 66.0 2.01 CVGraph 6.02 09/20/2021 Page 2/2

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 68 of75 Attachment C to PWROG-21037-NP Revision 2 C.17 V.C. Summer Unit 1, Heat# 626677, Lot# C301A27AF Tables C.17-1 and C.17-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files.

Table C.17-1 Charpy V-Notch Test Data for the Weld Heat# 626677, Lot# C301A27AF CVNimpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

-70 10 8 0

-70 13 12 0

-40 17 15 5

-40 20 17 5

-40 27 20 5

-20 27 24 10

-20 29 26 10

-20 24 25 30

-20 32 31 40

-20 34 32 30

-20 38 35 30

-20 44 38 30 0 43 33 20 0 22 21 15 40 53 36 25 40 51 37 25 40 54 35 25 70 66 54 75 70 70 46 75 100 83 61 90 100 89 69 95 150 90 74 100 150 92 61 100 150 102 78 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 69 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.17-2 Drop-Weight Test Data for Weld Heat# 626677, Lot# C301A27AF Test Temperature TNDT Drop-Weights(a)

(OF) (OF)

-30 2-NF

-40 1-F -40

-60 1-F Note for Table C.17-2:

(a) NF= "No Fail," F = "Fail".

C.17.1 Determination of the Initial RTNDT Using the data summarized in Tables C.17-1 and C.17-2, the initial RTNnT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

The Charpy V-notch tests were conducted at 0°F, which is less than TNnT + 60°F (-40°F + 60°F = 20°F).

The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNnT + 60°F would NOT satisfy the criteria. Since the analysis is to identify a bounding material property values for use in the extended beltline, it is not necessary precisely determine the temperature at which 50 ft-lb and 35 mils LE based on a hyperbolic tangent curve-fit. Instead, the temperature where all specimens experience greater than or equal to 50 ft-lb and 35 mils LE is used as the T50 / T35mils. From Table C.17-1, this occurred at 40°F. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNDT is this temperature minus 60°F.

RTNDT = Tcv - 60°F = 40°F - 60°F RTNDT =-20°F Weld Heat# 626677, Lot# C301A27AF Initial RTNoT =-20°F C.17.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E185-16, the average of all Charpy data:::: 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE is displayed below; this value is the average of each of the impact energy values contained in Table C.17-1 with shear:::: 95%.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 70 of75 Attachment C to PWROG-21037-NP Revision 2 Weld Heat# 626677, Lot# C301A27AF Initial USE =Average (89, 90, 92, 102) ft-lb

=93 ft-lb C.17.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. The chemical compositions are summarized in Table C.17-3.

Table C.17-3 Chemistry Data for Weld Heat# 626677, Lot# C301A27AF Copper Nickel Source (wt.-%) (wt.-%)

0.01 0.85 CB I Wire Analysis 0.03 1.04 Chemetron verification Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 626677, Lot# C301A27AF Cu Content = 0.02 wt-%

Weld Heat# 626677, Lot# C301A27AF Ni Content = 0.95 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 71 of75 Attachment C to PWROG-21037-NP Revision 2 C.18 V.C. Summer Unit 1, Heat# 627069, Lot# C312A27AG Tables C.18-1 and C.18-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files.

Table C.18-1 Charpy V-Notch Test Data for the Weld Heat# 627069, Lot# C312A27AG CVN Impact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

-80 9 6 2

-80 8 5 2

-60 28 26 5

-60 27 24 5

-60 30 25 5

-20 31 23 30

-20 36 21 30

-20 36 26 30

-20 37 25 30

-20 38 28 40 0 72 52 35 0 64 48 35 0 78 56 45 40 68 56 40 40 86 69 75 100 117 74 95 100 107 89 90 150 114 73 100 150 117 64 100 150 112 73 100 Table C.18-2 Drop-Weight Test Data for Weld Heat# 627069, Lot# C312A27AG Test Temperature TNDT Drop-Weights<a)

(OF) {°F)

-40 1-NF

-50 2-NF

-60 1-F -60

-70 1-F

-80 1-F Note for Table C.18-2:

(a) NF= "No Fail," F = "Fail".

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 72 of75 Attachment C to PWROG-21037-NP Revision 2 C.18.1 Determination of the Initial RTNDT Using the data summarized in Tables C.18-1 and C.18-2, the initial RTNDT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNnT (or NOT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

The Charpy V-notch tests were conducted at 0°F, T NDT + 60°F (-60°F + 60°F = 0°F). The minimum Charpy V-notch test data at this temperature exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNnT + 60°F satisfy the criteria. Per ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the requirements have been met such that TNnT is the initial reference temperature RTNDT-Weld Heat# 627069, Lot# C312A27AG Initial RTNDT = -60°F C.18.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM E 185-82.

Herein, USE is calculated based on an interpretation of ASTM E 185-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E 185-16, the average of all Charpy data 2: 95% shear is reported as the USE. In some instances, there may be data deemed 'out offamily,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE is displayed below; this value is the average of each of the impact energy values contained in Table C.18-1 with shear 2: 95%.

Weld Heat# 627069, Lot# C312A27AG Initial USE = Average (117, 114, 117, 112) ft-lb

= 115 ft-lb C.18.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. The chemical compositions are summarized in Table C.18-3.

Table C.18-3 Chemistry Data for Weld Heat# 627069, Lot# C312A27AG Copper Nickel Source (wt.-%) (wt.-%)

0.01 0.94 CBI Wire Analysis 0.03 1.04 Chemetron verification Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 627069, Lot# C312A27AG Cu Content = 0.02 wt-%

Weld Heat# 627069, Lot# C312A27AG Ni Content = 0.99 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 73 of75 Attachment C to PWROG-21037-NP Revision 2 C.19 V.C. Summer Unit 1, Heat# 627184, Lot# C314A27AH Tables C.19-1 and C.19-2 summarize all available Charpy V-notch test data and drop-weight test data taken from the V.C. Summer Unit 1 reactor vessel fabrication files.

Table C.19-1 Charpy V-Notch Test Data for the Weld Heat# 627184, Lot# C314A27AH CVNimpact Lateral Temp. Shear Energy Expansion

{°F) (%)

(ft-lb) (mils)

-70 7 5 5

-70 10 8 5

-70 6 5 5

-40 26 18 5

-40 31 21 5

-20 33 28 20

-20 34 29 30

-20 38 30 20

-20 38 27 30

-20 41 33 30

-10 46 38 25

-10 36 31 15

-10 32 30 15 0 55 46 35 0 50 37 25 0 35 26 20 10 53 40 30 10 66 45 35 10 63 46 35 40 57 45 50 40 60 39 45 40 69 59 50 80 86 70 75 80 89 73 75 120 89 62 80 120 82 60 80 180 107 94 100 180 101 60 100 180 97 77 100

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 74 of75 Attachment C to PWROG-21037-NP Revision 2 Table C.19-2 Drop-Weight Test Data for Weld Heat# 627184, Lot# C314A27AH Test Temperature TNDT Drop-Weights<*l

{°F) {°F)

-60 2-NF

-70 1-NF, 1-F -70

-80 1-F Note for Table C.19-2:

(a) NF= "No Fail," F = "Fail".

C.19.1 Determination of the Initial RTNoT Using the data summarized in Tables C.19-1 and C.19-2, the initial RTNnT value can be determined in accordance with the ASME Code Section III, Subarticle NB-2331 requirements. Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(2), the minimum Charpy V-notch test data is first checked at a temperature not greater than the drop-weight TNDT (or NDT) plus 60°F to determine if the material exhibits at least 50 ft-lb absorbed energy and 35 mils LE.

The Charpy V-notch tests were conducted at -10°F, TNnT + 60°F (-70°F + 60°F = -10°F). The minimum Charpy V-notch test data at this temperature did NOT exhibit a minimum of 50 ft-lb absorbed energy and 35 mils lateral expansion; therefore, the Charpy V-notch tests at TNnT + 60°F would NOT satisfy the criteria. Since the analysis is to identify a bounding material property values for use in the extended beltline, it is not necessary precisely determine the temperature at which 50 ft-lb and 35 mils LE based on a hyperbolic tangent curve-fit. Instead, the temperature where all specimens experience greater than or equal to 50 ft-lb and 35 mils LE is used as the TSO / T35mils. From Table C.19-1, this occurred at 10°F.

Following the requirements of ASME Code Section III, Subarticle NB-2331, Paragraph (a)(3), the initial RTNnT is this temperature minus 60°F.

RTNnT = Tcv - 60°F = 10°F - 60°F RTNDT = -50°F Weld Heat# 627184, Lot# C314A27AH Initial RTNnT = -50°F C.19.2 Determination of the Initial USE The current 10 CFR 50, Appendix G requirements specify that USE be calculated based on ASTM El 85-82.

Herein, USE is calculated based on an interpretation of ASTM El 85-82 that is best explained by the most recent version of the ASTM E185 manual (2016 version). Using the guidelines in ASTM E185-82 and E185-16, the average of all Charpy data~ 95% shear is reported as the USE. In some instances, there may be data deemed 'out of family,' which are removed from the determination of the USE based on engineering judgment. However, the use of engineering judgment to remove 'out of family' data was not necessary for this material. The USE is displayed below; this value is the average of each of the impact energy values contained in Table C.19-1 with shear~ 95%.

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Page 75 of75 Attachment C to PWROG-21037-NP Revision 2 Weld Heat# 627184, Lot# C314A27AH Initial USE =Average (107, 101, 97) ft-lb

= 102 ft-lb C.19.3 Chemistry The Cu and Ni wt. % chemical compositions of the V.C. Summer Unit 1 reactor vessel materials were defined by a review of the available original test documentation. The material's chemical properties are defined as the average of all available data. The chemical compositions are summarized in Table C.19-3.

Table C.19-3 Chemistry Data for Weld Heat# 627184, Lot# C314A27AH Copper Nickel Source (wt.-%) (wt.-%)

0.03 1.01 CBI Wire Analysis 0.03 1.01 Chemetron verification Analysis Therefore, to determine the generic chemical content of the welds in the V.C. Summer reactor vessel, the below values will be used:

Weld Heat# 627184, Lot# C314A27AH Cu Content = 0.03 wt-%

Weld Heat# 627184, Lot# C314A27AH Ni Content = 1.01 wt-%

• • • This record was final approved on 3/6/2023, 12:36:16 PM. (This statement was added by the PRIME system upon its validation)

Serial No.: 23-193 Docket No.: 50-395 Enclosure 4 Attachment 2 WCAP-13207-NP, REVISION 4 (Redacted version of WCAP-13206-P)

Virgil C. Summer (VCSNS) Unit 1 Dominion Energy South Carolina, Inc. (DESC)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-13207 April 2022 Revision 4 Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Virgil C. Summer Nuclear Power Plant

@Westinghouse

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-13207 Revision 4 Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Virgil C. Summer Nuclear Power Plant April2022 Author: Nadia B. Petkova*

Operating Plants Piping & Supports Piping Engineering Reviewer: Dulal Bhowmick*

Reactor Vessel and Containment Vessel Design and Analysis Approved: Lynn A. Patterson*. Manager Reactor Vessel and Containment Vessel Design and Analysis

• Electronically approved records are authenticated in the electronic document management system.

Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066, USA

© 2022 Westinghouse Electric Company LLC All Rights Reserved

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 iv TABLE OF CONTENTS 1.0 Introduction ................................................................................................................................... 1-1 1.1 Purpose ............................................................................................................................ 1-1 1.2 Scope and Objective ........................................................................................................ 1-1 1.3 Background Information .................................................................................................. 1-2 1.4 References ........................................................................................................................ 1-3 2.0 Operation and Stability of the Reactor Coolant System ............................................................... 2-1 2.1 Stress Corrosion Cracking ............................................................................................... 2-1 2.2 Water Hammer ................................................................................................................. 2-2 2.3 Low Cycle and High Cycle Fatigue ................................................................................. 2-3 2.4 References ........................................................................................................................ 2-3 3.0 Pipe Geometry and Loading ......................................................................................................... 3-1 3 .1 Introduction to Methodology ........................................................................................... 3-1 3.2 Calculation of Loads and Stresses ................................................................................... 3-1 3.3 Loads for Leak Rate Evaluation ...................................................................................... 3-2 3.4 Load Combination for Crack Stability Analyses ............................................................. 3-3 3.5 References ........................................................................................................................ 3-3 4.0 Material Characterization .............................................................................................................. 4-1 4.1 Primary Loop Pipe and Fittings Materials ....................................................................... 4-1 4.2 Tensile Properties ............................................................................................................. 4-1 4.3 Fracture Toughness Properties ......................................................................................... 4-2 4.4 Reference ......................................................................................................................... 4-6 5.0 Critical Location and Evaluation Criteria ..................................................................................... 5-1 5 .1 Critical Locations ............................................................................................................. 5-1 5.2 Fracture Criteria ............................................................................................................... 5-1 6.0 Leak Rate Predictions ................................................................................................................... 6-1 6.1 Introduction ...................................................................................................................... 6-1 6.2 General Considerations .................................................................................................... 6-1 6.3 Calculation Method .......................................................................................................... 6-1 6.4 Leak Rate Calculations .................................................................................................... 6-2 6.5 References ........................................................................................................................ 6-2 7.0 Fracture Mechanics Evaluation ..................................................................................................... 7-1 7.1 Local Failure Mechanism ................................................................................................ 7-1 7.2 Global Failure Mechanism ............................................................................................... 7-1 7.3 Results of Crack Stability Evaluation .............................................................................. 7-2 7.4 SG and RPV Nozzle Alloy 82/182 Welds ........................................................................ 7-4 7.5 References ........................................................................................................................ 7-5 8.0 Fatigue Crack Growth Analysis .................................................................................................... 8-1 8.1 References ........................................................................................................................ 8-3 9.0 Assessment of Margins ................................................................................................................. 9-1 10.0 Conclusions ................................................................................................................................. 10-1 APPENDIX A: Limit Moment ................................................................................................................. A- I WCAP-13207 April 2022 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 V LIST OF TABLES Table 3-1 Dimensions, Normal Loads and Nonnal Stresses for VCSNS Unit 1 .................................... 3-4 Table 3-2 Dimensions, Faulted Loads and Faulted Stresses for VCSNS Unit 1 .................................... 3-5 Table 4-1 Measured Room Temperature Tensile Properties for VCSNS Unit 1 Primary Loop Piping ....................................................................................................................................... 4-7 Table 4-2 Measured Room Temperature Tensile Properties for VCSNS Unit 1 Primary Loop Fittings (Elbows) ................................................................................................................................... 4-8 Table 4-3 Measured Room Temperature Tensile Properties for Hot Leg Loop A Inconel 152 Weld at Location 1 ................................................................................................................................ 4-9 Table 4-4 Mechanical Properties for VCSNS Unit 1 Materials at Operating Temperatures ................ .4-10 Table 4-5 Chemistry and Fracture Toughness Properties of the SA351 CF8A Material Heats of VCSNS Unit 1 .................................................................................................................. 4-11 Table 4-6 Enveloped J1c, Jmax, Tmat for the SA351 CF8A Material Heats from Revision 1 and Revision 2 ofNUREG/CR-4513 ..................................................................................... 4-12 Table 4-7 Fracture Toughness Properties of SA351 CF8A for VCSNS Unit 1 Primary Loops for Leak-Before-Break Evaluation at Critical Locations ........................................... .4-13 Table 6-1 Flaw Sizes Yielding a Leak Rate of 10 gpm at the Critical Locations with SA376-TP304N Material ......................................................................................................... 6-3 Table 6-2 Flaw Sizes Yielding a Leak Rate of 10 gpm at the Elbow Critical Locations with SA 351-CF8A Material ......................................................................................................................... 6-3 Table 6-3 Flaw Sizes Yielding a Leak Rate of 10 gpm at the Critical Locations with Alloy 82/182 and Inconel 152 Materials ...................................................................................................... 6-4 Table 7-1 VCSNS Unit 1 Stability Results Based on Elastic-Plastic J-Integral Evaluations for SA 351-CF8A ..................................................................................................................... 7-6 Table 7-2 VCSNS Unit 1 Stability Results Based on Limit Load for SA376-TP304N Material .......... 7-6 Table 7-3 VCSNS Unit 1 Stability Results Based on Limit Load for SA351-CF8AMaterials ............. 7-7 Table 7-4 VCSNS Unit 1 Stability Results Based on Limit Load for Alloy 82/182 and Inconel 152 Materials .............................................................................................................. 7-7 Table 8-1 Summary of Reactor Vessel Transients for VCSNS Unit l .................................................... 8-4 Table 8-2 Typical Fatigue Crack Growth at [ .......................... ]",c,e(40, 60 and 80-Years) .............. 8-5 Table 9-1 VCSNS Unit 1 Leakage Flaw Sizes, Critical Flaw Sizes, and Margins based on Limit Load Evaluation for SA376-TP304N Material .............................................................. 9-2 Table 9-2 VCSNS Unit 1 Leakage Flaw Sizes, Critical Flaw Sizes, and Margins based on Limit Load and J-Integral Evaluation for SA351-CF8A Material... ....................................... 9-2 Table 9-3 VCSNS Unit 1 Leakage Flaw Sizes, Critical Flaw Sizes, and Margins based on Limit Load Evaluation for Alloy 82/182 and Inconel 152 Materials ....................................... 9-3 WCAP-13207 April 2022 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 vi LIST OF FIGURES Figure 3-1 Hot Leg Coolant Pipe ............................................................................................................. 3-6 Figure 3-2 Schematic Diagram of VCSNS Unit l Primary Loop Showing Weld Locations ................... 3-7 Figure 4-1 Pre-Service J vs. Aa for SA351-CF8M Cast Stainless Steel at 600°F ................................. .4-14 Figure 6-1 Analytical Predictions of Critical Flow Rates of Steam-Water Mixtures ............................... 6-5 Figure 6-2 [ ]a,c,e Pressure Ratio as a Function of L/D ................................................ 6-6 Figure 6-2 ]a,c,e Pressure Ratio as a Function ofL/D ....................................................... 6-6 Figure 6-3 Idealized Pressure Drop Profile Through a Postulated Crack ................................................ 6-7 Figure 7-1 [ ]a,c,e Stress Distribution .................................................................................... 7-8 Figure 8-1 Typical Cross-Section of [ ]a,c,e ..................................................... 8-6 Figure 8-2 Reference Fatigue Crack Growth Curves for [ ]a,c,e **** 8-7 Figure 8-3 Reference Fatigue Crack Growth Law for [ ]a,c,e in a Water Environment at 600°F .............................................................................................................. 8-8 Figure A-1 Pipe with a Through-Wall Crack in Bending ......................................................................... A-2 WCAP-13207 April 2022 Revision 4

""* This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 Vil EXECUTIVE

SUMMARY

Westinghouse performed analysis for the Leak-Before-Break (LBB) of Virgil C. Summer Nuclear Station (VCSNS), Unit 1, primary loop piping in 1992. The results of the analysis were documented in WCAP-13206 (Reference 1-1) and approved by the United States Nuclear Regulatory Commission (U.S. NRC) in a letter dated January 11, 1993 (Reference 1-2). Westinghouse also perfonned an evaluation of the LBB of VCSNS primary loop piping in 1993 to account the effects of Steam Generator Replacement/Uprating program and the results were documented in WCAP-13605 (Reference 1-3).

Revision 1:

Westinghouse performed an LBB evaluation of the primary loop piping of VCSNS Unit 1 primary loop piping in 1997 due to the Steam Generator (SG) snubber elimination program. An evaluation was performed to account the combined effects of SG snubber elimination and revised Replacement Steam Generators (RSGs) weight and center of gravity (CG). Revision 1 was to document the results of the latest LBB evaluation and was a general revision of the original WCAP-13206. WCAP-13206 Revision 1 superseded the WCAP-13605 (Reference 1-3).

In WCAP-13206 Revision 1 it was shown that the primary loops are highly resistant to stress corrosion cracking and high and low cycle fatigue. Water hammer is mitigated by system design and operating procedures.

The primary loops were extensively examined. The as-built geometries for the pipe and elbows and loadings were obtained. The materials were evaluated using the Certified Materials Test Reports (CMTRs).

Mechanical properties were determined at operating temperatures. Since the piping systems are fabricated from cast stainless steel, fracture toughness values considering thermal aging were determined for each heat of material.

Based on loading, pipe geometry and fracture toughness considerations, enveloping critical locations were detennined at which Leak-Before-Break crack stability evaluations were made. Through-wall flaw sizes were postulated which would leak at a rate of ten times the leakage detection system capability of the plant.

Large margins for such flaw sizes were shown against flaw instability. Finally, fatigue crack growth was shown not to be an issue for the primary loops.

The effects of RSG and SG snubber elimination on the continued applicability of LBB for the reactor coolant loop piping of VCSNS Unit 1 were evaluated.

Revision 2:

For the hot leg of loop A at the reactor vessel outlet nozzle location, a replacement spool piece and welds (stainless steel and Inconel) were installed. The purpose of Revision 2 of WCAP-13206 was to reconcile the LBB analysis for this new configuration.

It was demonstrated that the previous LBB conclusions (References 1-1 and 1-3) analyses remained valid, and the dynamic effects of reactor coolant system primary loop pipe breaks need not be considered in the structural design basis of the VCSNS Unit 1 after the RSG, SG snubber elimination and the new configuration of hot leg loop A.

Revision 3:

A mechanical stress improvement process (MSIP) was applied at the reactor vessel outlet nozzle location on loops B and C to mitigate the effects of primary water stress corrosion cracking (PWSCC) of the nozzle to WCAP-13207 April 2022 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 Vlll safe end welds at these locations. Application of MSIP introduced axial displacements in the primary loop piping. The LBB evaluation was updated to account for the effects of MSIP and new results are presented to demonstrate that dynamic effects of reactor coolant system primary loop pipe breaks need not be considered in the structural design basis of the VCSNS Unit 1.

Additionally, the evaluation was updated again in 2004 to demonstrate that LBB remains valid for the 60-year license renewal period.

Revision 3 of WCAP-13206 is issued to document the updated results for consideration of MSIP and the license renewal period.

Revision 4:

The purpose of Revision 4 of WCAP-13206 is to document the LBB evaluations for the VCSNS Unit 1 primary reactor loop piping due to the subsequent license renewal (SLR) program for the plant operation extension into 80 years.

For the SLR program, this report demonstrates that the conclusions reached in WCAP-13206 Revision 3 remain applicable in the structural design basis for the 80-year plant life.

In addition, this report reviews the dissimilar metal (DM) weld locations at the reactor pressure vessel nozzles and the steam generator (SG) nozzles, which are susceptible to primary water stress corrosion cracking (PWSCC) effect to confirm that those locations have been appropriately mitigated and evaluated for LBB. Except for the reactor pressure vessel inlet nozzle (RPVIN) welds, all DM weld locations (reactor pressure vessel outlet nozzles (RPVONs), steam generator inlet nozzles (SGINs) and steam generator outlet nozzles (SGONs)) have been mitigated from PWSCC effect. It should be noted that the mitigative measures were taken for the DM welds at the SGIN and SGON to safe-end locations of VCSNS Unit 1 by installing Alloy 152 inlays on the inside surface of the dissimilar metal as a protective barrier for the Alloy 82 weld against PWSCC effect.

All critical locations are evaluated, including the mitigated RPVON and SG nozzle to safe-end locations, and unmitigated RPVIN safe-end locations, to reconfirm that the LBB evaluation conclusions remain valid for 80-year plant life SLR program. As shown in the performed LBB evaluation, the presence of Alloy 82/182 at the RPVIN (location 12) is also acceptable, since all the recommended LBB margins are satisfied.

The analysis accounts for the effects of the MSIP on the loops B and C reactor vessel outlet nozzles and the updated configuration replacement spool piece and Inconel 152 weld at the loop A reactor vessel outlet nozzle as previously evaluated in Revision 2 and Revision 3 of WCAP-13206. Therefore, the LBB analysis and results for Loop A are presented separately from the LBB analysis and results for Loops B and C. Note that bounding loads from Loops B and C are considered in the LBB evaluation.

The analysis also reconciles the impact on the RCL leak-before-break (LBB) loads due to the replacement reactor vessel closure head (RRVCH) and integrated head assembly (IHA) package. Since only the LOCA loads were mainly impacted with the RRVCH and IHA package, it is concluded that the impact on the LBB analysis is insignificant.

The results of the DM weld evaluation show that the presence of Alloy 82 or Alloy 82/182 is no longer a concern for primary water stress corrosion cracking at these locations.

WCAP-13207 April 2022 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 IX Non-Proprietary Version:

WCAP-13207, Revision 0, was generated as the non-proprietary version of WCAP-13206, Revision 0 (Reference 1-1). Non-proprietary version ofWCAP-13206, Revision 1 and Revision 2 were never requested and never generated. Non-proprietary version of WCAP-13206, Revision 3, was issued as WCAP-13207, Revision 3. This report is being generated as the non-proprietary version of WCAP-13206, Revision 4 and is being issued as WCAP-13207, Revision 4 to maintain consistent revision numbering between the proprietary and non-proprietary versions.

WCAP-13207 April 2022 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-1

1.0 INTRODUCTION

1.1 PURPOSE This report applies to the VCSNS Unit 1 Reactor Coolant System (RCS) primary loop piping only and does not apply to any branch lines connected to the primary loop piping (e.g., surge, accumulator, RHR and safety injection branch lines). It is intended to demonstrate that for the VCSNS Unit 1, RCS primary loop pipe breaks need not be considered in the structural design basis after the RSG, SG snubber elimination, replacement of the loop A hot leg spool piece, application of MSIP on the loops B and C reactor vessel outlet nozzle, inlay application of Alloy 152 at the SGINs and SGONs, and the SLR for the plant operation extension from 60-years to 80-years. The approach taken has been accepted by the U.S.

NRC per Generic Letter 84-04 (Reference 1-4).

1.2 SCOPE AND OBJECTIVE The purpose of this investigation is to demonstrate Leak-Before-Break for the VCSNS Unit 1 primary loops piping for 80-years of plant service. The recommendations and criteria proposed in SRP 3.6.3 (Reference 1-5 and 1-11) are used in this evaluation. The criteria and resulting steps of the evaluation procedure can be briefly summarized as follows:

1. Calculate the applied loads. Identify the locations at which the highest stress occurs.

2. Identify the materials and the associated material properties.

3. Postulate a through-wall flaw at the governing locations. The size of the flaw should be large enough so that the leakage is assured of detection with margin using the installed. leak detection equipment when the pipe is subjected to normal operating loads. A margin of 10 is demonstrated between the calculated leak rate and the leak detection capability.

4. Using maximum faulted loads, demonstrate that there is a margin of at least 2 between the leakage flaw size and the critical flaw size.

5. Review the operating history to ascertain that operating experience has indicated no particular susceptibility to failure from the effects of corrosion, water hammer, or low and high cycle fatigue.

6. For the materials actually used in the plant, provide representative material properties including toughness and tensile test data. Evaluate long term effects such as thermal aging.

7. Demonstrate margin on the calculated applied load value; margin of 1.4 using algebraic summation of faulted loads or margin of 1.0 using absolute summation of faulted loads.

8. Perform an assessment of fatigue crack growth. Show that a through-wall crack will not result.

This report provides a fracture mechanics demonstration of primary loop integrity for the VCSNS Unit 1 consistent with the NRC position for exemption from consideration of dynamic effects.

It should be noted that the terms "flaw" and "crack" have the same meaning and are used interchangeably.

"Governing location" and "critical location" are also used interchangeably throughout the report.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-2

1.3 BACKGROUND

INFORMATION Westinghouse has performed considerable testing and analysis to demonstrate that RCS primary loop pipe breaks can be eliminated from the structural design basis of all Westinghouse plants. The concept of eliminating pipe breaks in the RCS primary loop was first presented to the NRC in 1978 in WCAP-9283 (Reference 1-6). That topical report employed a deterministic fracture mechanics evaluation and a probabilistic analysis to support the elimination of RCS primary loop pipe breaks. That approach was then used as a means of addressing Generic Issue A-2 and Asymmetric Loss of Coolant Accident (LOCA)

Loads.

Westinghouse performed additional testing and analysis to justify the elimination of RCS primary loop pipe breaks. . This material was provided to the NRC along with Letter Report NS-EPR-2519 (Reference 1-7).

The NRC funded research through Lawrence Livermore National Laboratory (LLNL) to address this same issue using a probabilistic approach. As part of the LLNL research effort, Westinghouse performed extensive evaluations of specific plant loads, material properties, transients, and system geometries to demonstrate that the analysis and testing previously performed by Westinghouse and the research performed by LLNL applied to all Westinghouse plants (References 1-8 and 1-9). The results from the LLNL study were released at a March 28, 1983, Advisory Committee on Reactor Safeguards (ACRS)

Subcommittee meeting. These studies which are applicable to all Westinghouse plants east of the Rocky Mountains determined the mean probability of a direct LOCA (RCS primary loop pipe break) to be 4.4 x 10- 12 per reactor year and the mean probability of an indirect LOCA to be 10-7 per reactor year. Thus, the results previously obtained by Westinghouse (Reference 1-6) were confirmed by an independent NRC research study.

Based on the studies by Westinghouse, LLNL, the ACRS, and the Atomic Industrial Forum (AIF), the NRC completed a safety review of the Westinghouse reports submitted to address asymmetric blowdown loads that result from a number of discrete break locations on the pressurized water reactor (PWR) primary systems. The NRC Staff evaluation (Reference 1-4) concludes that an acceptable technical basis has been provided so that asymmetric blowdown loads need not be considered for those plants that can demonstrate the applicability of the modeling and conclusions contained in the Westinghouse response or can provide an equivalent fracture mechanics demonstration of the primary coolant loop integrity. In a more formal recognition of LBB methodology applicability for PWRs, the NRC appropriately modified 10 CFR 50, General Design Criterion 4, "Requirements for Protection Against Dynamic Effects of Postulated Pipe Rupture" (Reference 1-10).

This report provides a fracture mechanics demonstration of primary loop integrity for the VCSNS Unit 1 consistent with the NRC position for exemption from consideration of dynamic effects. The re-evaluations were performed to ensure that the LBB evaluation conclusions remain valid for 80-year plant life in the SLR program.

Several computer codes are used in the evaluations. The LBB computer programs are under Configuration Control which has requirements conforming to Standard Review Plan 3.9.1. The computer codes used in this evaluation for leak rate and fracture mechanics calculations have been validated and used for all the LBB applications by Westinghouse.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-3

1.4 REFERENCES

1-1 WCAP-13206, Revision 0, "Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Virgil C. Summer Nuclear Power Plant," April 1992.

1-2 NRC Docket No. 50-395 dated January 11, 1993, "Safety Evaluation of Request to use Leak-Before-Break for Reactor Coolant System Piping-Virgil C. Summer Nuclear Station Unit No. 1 (TAC No. M83971)."

1-3 WCAP-13605, Revision 0, "Primary Loop Leak-Before-Break Reconciliation to Account for the Effects of Steam Generator Replacement/Uprating," March 1993.

1-4 U.S. NRC Generic Letter 84-04, Subject "Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops," February 1, 1984.

1-5 Standard Review Plan; public comments solicited; 3.6.3 Leak-Before-Break Evaluation Procedures; Federal RegisterNol. 52, No. 167/Friday, February 28, 1987/Notices, pp. 32626-32633.

1-6 WCAP-9283, "The Integrity of Primary Piping Systems of Westinghouse Nuclear Power Plants During Postulated Seismic Events," March 1978.

1-7 Letter Report NS-EPR-2519, Westinghouse (E. P. Rahe) to NRC (D. G. Eisenhut), Westinghouse Proprietary Class 2, November 10, 1981.

1-8 Letter from Westinghouse (E. P. Rahe) to NRC (W. V. Johnston), April 25, 1983.

1-9 Letter from Westinghouse (E. P. Rahe) to NRC (W. V. Johnston), July 25, 1983.

1-10 Nuclear Regulatory Commission, 10 CFR 50, Modification of General Design Criteria 4 Requirements for Protection Against Dynamic Effects of Postulated Pipe Ruptures, Final Rule, Federal RegisterNol. 52, No. 207/Tuesday, October 27, 1987/Rules and Regulations, pp. 41288-41295.

1-11 NUREG-0800 Revision 1, March 2007, Standard Review Plan: 3.6.3 Leak-Before-Break Evaluation Procedures.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 2-1 2.0 OPERATION AND STABILITY OF THE REACTOR COOLANT SYSTEM 2.1 STRESS CORROSION CRACKING The Westinghouse reactor coolant system primary loops have an operating history that demonstrates the

• inherent operating stability characteristics of the design. This includes a low susceptibility to cracking failure from the effects of corrosion (e.g., intergranular stress corrosion cracking (IGSCC)). This operating history totals over 1400 reactor-years, including 16 plants each having over 30 years of operation, l O other plants each with over 25 years of operation, 11 plants each with over 20 years of operation, and 12 plants each with over 15 years of operation.

In 1978, the United States Nuclear Regulatory Commission (U.S. NRC) formed the second Pipe Crack Study Group. (The first Pipe Crack Study Group (PCSG), established in 1975, addressed cracking only in boiling water reactors). One of the objectives of the second PCSG was to include a review of the potential for stress corrosion cracking in Pressurized Water Reactors (PWRs). The results of the study performed by the PCSG were presented in NUREG-0531 (Reference 2-1) entitled "Investigation and Evaluation of Stress-Corrosion Cracking in Piping of Light Water Reactor Plants." In that report the PCSG stated:

"The PCSG has determined that the potential for stress corrosion cracking in PWR primary system piping is extremely low because the ingredients that produce IGSCC are not all present.

The use of hydrazine additives and a hydrogen overpressure limit the oxygen in the coolant to very low levels. Other impurities that might cause stress-corrosion cracking, such as halides or caustic, are also rigidly controlled. Only for brief periods during reactor shutdown when the coolant is exposed to the air and during the subsequent startup are conditions even marginally capable of producing stress-corrosion cracking in the primary systems of PWRs. Operating experience in PWRs supports this determination. To date, no stress corrosion cracking has been reported in the primary piping or safe ends of any PWR."

During 1979, several instances of cracking in PWR feedwater piping led to the establishment of the third PCSG. The investigations of the PCSG reported inNUREG-0691 (Reference 2-2) further confirmed that no occurrences of IGSCC have been reported for PWR primary coolant systems.

The discussion below further qualifies the PCSG's findings.

For stress corrosion cracking (SCC) to occur in piping, the following three conditions must exist simultaneously: high tensile stresses, susceptible material, and a corrosive environment. The potential for stress corrosion is minimized by properly selecting a material immune to SCC as well as preventing of a corrosive environment. The material specifications consider compatibility with the system's operating environment (both internal and external) as well as other material in the system, applicable American Society of Mechanical Engineers (ASl\tlE) Code rules, fracture toughness, welding, fabrication, and processing.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 2-2 The elements of a water environment known to increase the susceptibility of austenitic stainless steel to stress corrosion are oxygen, fluorides, chlorides, hydroxides, hydrogen peroxide, and reduced forms of sulfur (e.g., sulfides, sulfites, and thionates). Strict pipe cleaning standards prior to operation and careful control of water chemistry during plant operation are used to prevent the occurrence of a corrosive environment. Prior to being put into service, the piping is cleaned internally and externally. During flushes and preoperational testing, water chemistry is controlled in accordance with written specifications. Requirements on chlorides, fluorides, conductivity, and pH are included in the acceptance criteria for the piping.

During plant operation, the reactor coolant water chemistry is monitored and maintained within very specific limits. Contaminant concentrations are kept below the thresholds known to be conducive to stress corrosion cracking with the major water chemistry control standards being included in the plant operating procedures as a condition for plant operation. For example, during normal power operation, oxygen concentration in the RCS is expected to be in the ppb range by controlling charging flow chemistry and maintaining hydrogen in the reactor coolant at specified concentrations. Halogen concentrations are also stringently controlled by maintaining concentrations of chlorides and fluorides within the specified limits. Thus, during plant operation, the likelihood of stress corrosion cracking is minimized.

It should be noted that the VCSNS Unit 1 reactor coolant system (RCS) primary loop piping contains Alloy 82/182 DM welds which are susceptible to PWSCC. For the loop A piping, the hot leg spool piece was removed and replaced. In this process, the PWSCC susceptible was replaced with non-susceptible welding material. For loops B and C, the MSIP process was applied at the susceptible hot leg weld locations at the RPVON to modify the through-wall stress profile. This permanent application of MSIP serves to mitigate the effects of PWSCC. VCSNS Unit 1 RCS piping includes Alloy 82 DM welds at the SG nozzle safe-ends. As a protective barrier against PWSCC, Alloy 152 inlay were installed on the inside surface of the Alloy 82 DM nozzle safe-end welds. However, the conservative LBB evaluation of the Alloy 82 DM weld is performed without considering the Alloy 152 weld inlay application at these locations. The LBB evaluation for unmitigated weld locations at the RPVINs includes methodology to address the Alloy 82/182 PWSCC concerns for 80- year plant life in the SLR program. A detailed evaluation of Alloy 82/182 welds is documented in Sections 6.0, 7.4 and 9.0.

2.2 WATER HAMMER Overall, there is a low potential for water hammer in the RCS since it is designed and operated to preclude the voiding condition in normally filled lines. The reactor coolant system, including piping and primary components, is designed for normal, upset, emergency, and faulted condition transients. The design requirements are conservative relative to both the number of transients and their severity. Relief valve actuation and the associated hydraulic transients following valve opening are considered in the system design. Other valve and pump actuations are relatively slow transients with no significant effect on the system dynamic loads. To ensure dynamic system stability, reactor coolant parameters are stringently controlled. Temperature during normal operation is maintained within a narrow range by control rod position; pressure is controlled by pressurizer heaters and pressurizer spray also within a narrow range for steady-state conditions.

The flow characteristics of the system remain constant during a fuel cycle because the only Operation and Stability of the Reactor Coolant System April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 2-3 governing parameters, namely system resistance and the reactor coolant pump characteristics, are controlled in the design process. Additionally, Westinghouse has instrumented typical reactor coolant systems to verify the flow and vibration characteristics of the system. Preoperational testing and operating experience have verified the Westinghouse approach. The operating transients of the RCS primary piping are such that no significant water hammer can occur.

2.3 LOW CYCLE AND IDGH CYCLE FATIGUE Low cycle fatigue considerations are accounted for in the design of the piping system through the fatigue usage factor evaluation to show compliance with the rules of Section III of the ASME Code.

A further evaluation of the low cycle fatigue loadings was carried out as part of this study in the form of a fatigue crack growth analysis, as discussed in Section 8.0.

High cycle fatigue loads in the system would result primarily from pump vibrations. These are minimized by restrictions placed on shaft vibrations during hot functional testing and operation.

During operation, an alarm signals the exceedance of the vibration limits. Field measurements have been made on a number of plants during hot functional testing, including plants similar to VCSNS Unit 1. Stresses in the elbow below the reactor coolant pump resulting from system vibration have been found to be very small, between 2 and 3 ksi at the highest. These stresses are well below the fatigue endurance limit for the material and would also result in an applied stress intensity factor below the threshold for fatigue crack growth.

2.4 REFERENCES

2-1 Investigation and Evaluation of Stress-Corrosion Cracking in Piping of Light Water Reactor Plants, NUREG-0531, U.S. Nuclear Regulatory Commission, February 1979.

2-2 Investigation and Evaluation of Cracking Incidents in Piping in Pressurized Water Reactors, NUREG-0691, U.S. Nuclear Regulatory Commission, September 1980.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-1 3.0 PIPE GEOMETRY AND LOADING

3.1 INTRODUCTION

TO METHODOLOGY The general approach is discussed first. As an example, a segment of the primary coolant hot leg pipe is shown in Figure 3-1. The as-built outside diameter and minimum wall thickness of the pipe are 33.90 in.

and 2.345 in., respectively, as shown in the figure. The normal stresses at the weld locations are from the load combination procedure discussed in Section 3.3 whereas the faulted loads are developed as described in Section 3.4. The components for normal loads are pressure, dead weight, and thermal expansion. For loops B and C, the MSIP loads are considered as a part of the thermal expansion loads. An additional component, safe shutdown earthquake (SSE), is considered for faulted loads. As seen from Table 3-2, the highest faulted stress in all three loops is at the reactor vessel outlet nozzle to pipe weld, location 1. This highest stressed location is a load critical location and is one of the locations at which, as an enveloping location, Leak-Before-Break is to be established. Essentially a circumferential flaw is postulated to exist at this location which is subjected to both the normal loads and faulted loads to assess leakage and stability, respectively. The loads (developed below) at this location are also given in Figure 3-1.

Since the elbows are made of different materials than the pipe, locations other than the highest stressed pipe location are examined taking into consideration both fracture toughness and stress. The elbows are cast stainless steel, and therefore thermal aging must be considered (see Section 4.0). Thermal aging of cast stainless steel (CASS) material results in lower fracture toughness; thus, locations other than the load critical locations must be examined taking into consideration both fracture toughness and stress. The enveloping locations as determined are called toughness critical locations. The most critical locations are apparent only after the full analysis is completed. Once loads (this section) and fracture toughness values (see Section 4.0) are available, the load critical and toughness critical locations are determined (see Section 5.0). At these locations, leak rate evaluations (see Section 6.0) and fracture mechanics evaluations (see Section 7.0) are performed per the guidance of References 3-1 and 3-2. Fatigue crack growth (see Section 8.0) and stability margins are also evaluated (see Section 9.0). All the weld locations considered for the LBB evaluation are those shown in Figure 3-2.

3.2 CALCULATION OF LOADS AND STRESSES The stresses due to axial loads and total moments are calculated by the following equation:

F M (3-1)

CT=-+ -

A Z Where:

a stress, ksi F axial load, kips M total moment, in-kips A pipe cross-sectional area, in2 Z section modulus, in3 The total moments for the desired loading combinations are calculated by the following equation:

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-2 (3-2)

Where, M total moment for required loading Mx X component of bending moment Y component of bending moment Mz Z component of bending moment The axial load and total moment for leak rate predictions and crack stability analyses are computed by the methods to be explained in Sections 3.3 and 3.4.

3.3 LOADS FOR LEAK RATE EVALUATION The normal operating loads for leak rate predictions are calculated by the following equations:

F Fnw + Frn + fp (3-3)

Mx = (Mx)nw + (Mx)rn (3-4)

My = (My)nw + (My)rn (3-5)

Mz = (Mz)nw + (Mz)rn (3-6)

The subscripts of the above equations represent the following loading cases:

DW dead weight TH normal thermal expansion. Note that for loops B and C, the MSIP loads are included as a part of the normal thermal expansion loads.

p load due to internal pressure This method of combining loads is often referred to as the algebraic sum method (References 3-1 and 3-2).

The loads based on this method of combination are provided in Table 3-1 at all the weld locations identified in Figure 3-2. The as-built dimensions are also given in Table 3-1.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-3 3.4 LOAD COMBINATION FOR CRACK STABILITY ANALYSES In accordance with Standard Review Plan 3.6.3 (References 3-1 and 3-2), the margin in terms of applied loads needs to be demonstrated by crack stability analysis. Margin on loads of 1.4 can be demonstrated if normal plus Safe Shutdown Earthquake (SSE) are applied algebraically and increased by 1.4. The 1.4 margin can be reduced to 1.0 if the deadweight, thermal expansion, internal pressure, Safe Shutdown Earthquake (SSE) inertia and seismic anchor motion (SAM) loads are combined based on individual absolute values as shown in the following equations:

F IFow I+ IFm I+ I Fp I+ IFssEINERTIA I+ IFssEAM I (3-7)

Mx = I(Mx)ow I + I (Mx)rn I + I (Mx)ssEINERTIA I+ I (Mx)ssEAM I (3-8)

My= I(My)ow I+ I(My)rn I+ I(My)ssEINERTrAI + I(My)ssEA1v1I (3-9)

Mz I (Mz)ow I+ I (Mz)THI + I(Mz)ssEINERTrAI + I (Mz)ssEAMI (3-10)

Where subscript SSEINERTIA refers to safe shutdown earthquake inertia and SSEAM is safe shutdown earthquake anchor motion.

The loads so determined are used in the fracture mechanics evaluations (Section 7 .0) to demonstrate the LBB margins at the locations established to be the governing locations. These loads at all the weld locations (see Figure 3-2) are given in Table 3-2.

3.S REFERENCES 3-1 Standard Review Plan: Public Comments Solicited; 3.6.3 Leak-Before-Break Evaluation Procedures; Federal Register/Vol. 52, No. 167/Friday, August 28, 1987/Notices, pp. 32626-32633.

3-2 NUREG-0800 Revision 1, March 2007, Standard Review Plan: 3.6.3 Leak-Before-Break Evaluation Procedures.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-4 Table 3-1 Dimensions, Normal Loads and Normal Stresses for VCSNS Unit 1 RCSLoopA RCS Loops B and C Outside Minimum Locationa Diameter Thickness Axial Total Total Axial Total Total (in.) (in.) Loadb Moment Stress Loadb Moment Stress (kips) (in-kips) (ksi) (kips) (in-kips) (ksi) 1 33.90° 2.345° 1485 13548 14.28 1339 14213 14.05 2 33.90 2.345 1485 7166 10.56 1339 8520 10.73 3 36.23 2.510 1615 11943 11.77 1513 11068 10.97 4 36.23 2.510 1708 4096 8.38 1657 5757 8.98 5 36.20 2.495 1704 3920 8.33 1651 4418 8.37 6 36.20 2.495 1698 3433 8.08 1646 4192 8.24 7 36.20 2.495 1715 2875 7.87 1710 2131 7.50 8 36.20 2.495 1715 2379 7.63 1710 3173 8.00 9 37.56 3.178 1747 1568 5.66 1799 6511 7.63 10 32.14 2.215 1348 7355 11.52 1380 4371 9.62 11 32.14 2.215 1348 4752 9.73 1380 3634 9.12 12 32.18 2.238 1347 5946 10.55 1373 4530 9.59 Notes:

• See Figure 3-2 for piping layout and weld locations.

h Axial force includes pressure.

0 Outside diameter and thickness at location 1 for the hot leg loop A for Inconel 152 are 33.89 inches and 2.40 inches, respectively.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-5 Table 3-2 Dimensions, Faulted Loads and Faulted Stresses for VCSNS Unit 1 RCSLoopA RCS Loops B and C Outside Minimum Location a Diameter Thickness Axial Total Total Axial Total Total (in.) (in.) Loadh Moment Stress Loadh Moment Stress (kips) (in-kips) (ksi) (kips) (in-kips) (ksi) 1 33.90° 2.345° 1963 23194 21.96 2108 23845 22.96 2 33.90 2.345 1977 21927 21.28 2123 23288 22.70 3 36.23 2.510 1948 31524 22.35 2049 30731 22.35 4 36.23 2.510 1789 16741 14.71 1840 18784 15.88 5 36.20 2.495 1756 12234 12.52 1808 14040 13.58 6 36.20 2.495 1773 7440 10.28 1825 9502 11.47 7 36.20 2.495 1814 8446 10.92 1809 7027 10.22 8 36.20 2.495 1809 8212 10.79 1805 9202 11.25 9 37.56 3.178 1799 10813 9.21 1851 15682 11.15 10 32.14 2.215 1491 11753 15.22 1523 9332 13.71 11 32.14 2.215 1512 9300 13.64 1544 8405 13.18 12 32.18 2.238 1481 8530 12.96 1505 7953 12.54 Notes:

• See Figure 3-2 for piping layout and weld locations.

b Axial force includes pressure.

0 Outside diameter and thickness at location 1 for the hot leg loop A for Inconel 152 are 33.89 inches and 2.40 inches, respectively.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-6 Crack t~

~) M OD -I 0Da,d = 33.90 in Location 1 ta,d = 2.345 in Normal Loadsa Faulted Loadsh Axial Forcec: Axial Forcec:

Loop A - 1485 kips Loop A- 1963 kips Loop B/C- 1339 kips Loop B/C - 2108 kips Total Moment: Total Moment:

Loop A- 13548 in-kips Loop A- 23194 in-kips Loop B/C- 14213 in-kips Loop B/C - 23845 in-kips Notes:

a See Table 3-1.

b See Table 3-2.

0 Includes the force due to a pressure of2250 psia.

d See Note c on Table 3-1.

Figure 3-1 Hot Leg Coolant Pipe Pipe Geometry and Loading April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-7 Reacte>r Pressure Vessel

\__Reactor Coolani Pump

\,__ _ Steam Generator CROSSOVER LEG Critkal Location HOTLe§ Temperature 622°F, Pressure: 2250 psia HBQSSOVER LEG Temperature 553°F, Pressure: 2250 psia COLD LEG 7 Temperature 553°F, Pressure: 2250 psia Figure 3-2 Schematic Diagram ofVCSNS Unit 1 Primary Loop Showing Weld Locations Pipe Geometry and Loading April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-1 4.0 MATERIAL CHARACTERIZATION 4.1 PRIMARY LOOP PIPE AND FITTINGS MATERIALS The primary loop pipe materials are SA376 TP304N and the elbow fittings are SA351 CF8A.

4.2 TENSILE PROPERTIES The Certified Materials Test Reports (CMTRs) for VCSNS Unit 1 were used to establish the tensile properties for the Leak-Before-Break analyses. The CMTRs include tensile properties at room temperature for each of the heats of material. These properties for VCSNS Unit 1 primary loop piping and fittings are given in Tables 4-1 and 4-2, and for Inconel 152 weld in Table 4-3. The average yield strength and the minimum yield and ultimate strengths are also identified.

Piping: For the SA376 TP304N material, the properties at operating temperatures were established from the tensile properties at room temperature given in Table 4-1 by utilizing Section II of the ASME Boiler and Pressure Vessel (B&PVC) Code 2007 Edition up to and including 2008 Addenda (Reference 4-1).

Code tensile properties at the normal operating temperatures (622°F for Hot Leg and 553°F for Crossover leg and Cold leg) were obtained by a linear interpolation of the tensile properties provided in the Code.

The ratios of the tensile properties at the applicable operating temperatures to the corresponding tensile properties at room temperature were then applied to the room temperature values given in Table 4-1 to obtain the plant specific properties for SA376 TP304N at normal operating temperatures. Table 4-1 includes the replacement spool piece tensile properties. As shown in Table 4-1 minimum tensile properties remain unchanged, and the average yield strength is reduced by 0.4% (from 46.7 ksi to 46.5 ksi). The average yield strength of 46.7 ksi at room temperature from Table 4-1 is used to calculate the average yield strength at operating temperature as shown in Table 4-4. The calculated value in Table 4-4 is used in the leakage analysis for the SA376 TP304N pipe material since it results in a larger leakage flaw size.

Fittings (Elbows): For the SA35 l CF8A material, the properties at operating temperature were established from the tensile properties at room temperature given in Table 4-2. The representative tensile properties for SA351 CF8A at operating temperatures (622°F for Hot Leg and 553°F for Crossover leg and Cold leg) were obtained by utilizing Section II of the ASME B&PVC Code 2007 Edition up to and including 2008 Addenda (Reference 4-1 ). Code tensile properties at the applicable operating temperatures considered in this LBB analysis were obtained by a linear interpolation of the tensile properties provided in the Code. To obtain the plant specific properties for SA351 CF8A at operating temperatures of 622°F and 553°F as shown in Table 4-4, the Code minimum properties at the applicable operating temperatures were adjusted to account for the actual yield strength and ultimate tensile strength from the CMTR values at room temperature given in Table 4-2.

Weld Material: Table 4-3 shows the room temperature tensile properties for the Inconel 152 material.

The properties at operating temperature were established from the tensile properties at room temperature given in Table 4-3 by utilizing Section II of the ASME B&PVC Code 2007 Edition up to and including 2008 Addenda (Reference 4-1 ). A similar method, as indicated above, is used to obtain the plant specific properties for Inconel 152 at operating temperature of 622°F for Hot Leg piping presented in Table 4-4.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-2 For Alloy 82/182 DM welds CMTR data was not available, and the typical tensile properties from Westinghouse source for the 82/182 weld material at the applicable operating temperatures as listed in Table 4-4 are used in the LBB evaluation.

The LBB evaluation considers the normal operating temperature of 622°F for Hot leg and 553°F for Crossover and Cold legs for material property interpolation.

The average and lower bound yield strengths and ultimate strengths at operating temperatures of 622°F and 553°F which are used in the LBB evaluation are summarized in Table 4-4. The ASME Code values for modulus of elasticity at the applicable operating temperatures are also provided. Poisson's ratio was taken as 0.3.

It should be noted that there is no significant impact by using the ASME Code Section II edition up to and including 2008 Addenda for material properties for the LBB analysis, as compared to the VCSNS ASME Code of record, i.e.: ASME B&PVC Code Section III, Appendix I, 1971 edition including Addenda through Winter 1971.

4.3 FRACTURE TOUGHNESS PROPERTIES The pre-service fracture toughness (J) of cast austenitic stainless steel (CASS) that are of interest are in terms of Jrc (J at Crack Initiation) and have been found to be very high at 600°F. [

]a,c,e However, cast stainless steel is susceptible to thermal aging at the reactor operating temperature, that is, about 550°F. Thermal aging of cast stainless steel results in embrittlement, which means a decrease in the ductility, impact strength, and fracture toughness of the material. Depending on the material composition, the Charpy impact energy of a cast stainless steel component could decrease to a small fraction of its original value after exposure to reactor temperatures during service.

The susceptibility of the material to thermal aging increases with increasing ferrite and molybdenum contents.

In 1994, the Argonne National Laboratory (ANL) completed an extensive research program in assessing the extent of thermal aging of cast stainless steel materials (Reference 4-2). The ANL research program measured mechanical properties of cast stainless steel materials after they had been heated in controlled ovens for long periods of time. ANL compiled a data base, both from data within ANL and from international sources, of about 85 compositions of cast stainless steel exposed to a temperature range of 290°-400°C (550°-750°F) for up to 58,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (6.5 years). In 2015, the work done by ANL was augmented, and the fracture toughness database for CASS materials was aged to 100,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> at 290°-

3500C (554°-633°F). The methodology for estimating fracture properties has been extended to cover CASS materials with a ferrite content of up to 40%. From this database (NUREG/CR-4513, Revision 2),

ANL developed correlations for estimating the extent of thermal aging of cast stainless steel (Reference 4-4). From this data base (NUREG/CR-4513, Revision 2), ANL developed correlations for estimating the extent of thermal aging of cast stainless steel (Reference 4-4).

ANL developed the fracture toughness estimation procedures by correlating data in the database conservatively. After developing the correlations, ANL validated the estimation procedures by comparing Material Characterization April2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-3 the estimated fracture toughness with the measured value for several cast stainless steel plant components removed from actual plant service. The procedure developed by ANL in Revision 1 and Revision 2 of NUREG/CR-4513 (References 4-3 and 4-4) was used to calculate the end of life limiting fracture toughness values of the CASS elbows for the cold leg, crossover leg and hot leg locations. Note that LBB analyses have acceptable margins when performing the elastic-plastic J-integral evaluations with the use of lower bound fracture toughness properties from NUREG/CR-4513, Revision 1 and Revision 2.

Furthermore, this report used saturated toughness approved by NRC in NUREG/CR-4513 Revision 1 and Revision 2. Therefore, the LBB analysis is acceptable from a saturated toughness perspective.

The method described below was used to calculate the toughness properties for the cast material, SA351 CF8A, of the VCSNS Unit 1 primary coolant loop elbows.

The J1c, Jmax and T mat values for each material heat for CASS elbows was calculated using both Revision l and Revision 2 of NUREG/CR-4513 (References 4-3 and 4-4), and the enveloped values from both revisions are summarized in Table 4-6. While Revision 1 (Reference 4-3) provides more limiting Jrc values for material heats, it was found that Revision 2 (Reference 4-4) resulted in the most limiting fracture toughness (Jmax and Tmat) values for the material heats identified in Table 4-6. Therefore, the Jrc values in Table 4-6 are based on Revision 1 of NUREG/CR-4513, and the reported values for Imax and Tmat in Table 4-6 are based on Revision 2 ofNUREG/CR-4513.

Based on Reference 4-4, the lower bound fully aged fracture toughness correlations are used for the SA351 CF8A material.

The chemical compositions of the VCSNS Unit 1 primary loop elbow fitting material (SA351 CF8A) are available from CMTRs and are provided in Table 4-5. The following equations are taken from References 4-3 and 4-4. Note that equations provided below for both revisions are the same, except for Equations 4-8 and 4-10. Equations 4-8.a and 4.10.a are from Reference 4-3, and Equations 4-8.b and 4.10.b are from Reference 4-4:

Cr.4 =Cr+ l.21(Mo) + 0.48(Si)- 4.99 = (Chromium equivalent) (4-1)

Nieq =(Ni)+ 0.1 l(Mn) - 0.0086(Mn)2+ 18.4(N) + 24.5(C) + 2.77 = (Nickel equivalent) (4-2)

Oc =100.J(Creq /Nieq )2-170.72(Creq /Nieq )+74.22 = (Ferrite Content) (4-3) where the elements are in percent weight and Oc is ferrite in percent volume.

The saturation room temperature (RT) impact energies of the cast stainless steel materials were determined from the chemical compositions available from CMTRs and provided in Table 4-5.

For CF8A steel, the saturation value of RT impact energy Cv**1 (J/cm2) is the lower value determined from:

log10CV,at = 1.15 + 1.36 exp (-0.035~) (4-4)

Where the material parameter ~ is expressed as:

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-4

~ 6c (Cr+ Si)(C + 0.4N) (4-5) and from:

log10CVsat = 5.64 - 0.0066c - 0.185Cr + 0.273Mo - 0.204Si + 0.044Ni- 2.12(C + 0.4N) (4-6)

The saturation J-R curve at RT, for static-cast CF8A steel is given by:

(4-7) n = 0.20 + 0.12 loglO (CVsat) (4-8.a) n = 0.18 + 0.10 loglO (CVsat) (4-8.b)

Where Jd is the "deformation J" in kJ/m2 and Aa is the crack extension in mm.

The saturation J-R curve at 290°C (554°F), for static-cast CF8A steel is given by:

(4-9) n = 0.21 + 0.09 loglO (CVsat) n 0.17 + 0.09 log10 (CVsat) (4-10.b)

Where Jd is the "deformation J" in kJ/m2 and Aa is the crack extension in mm.

The critical heats with the most limiting allowable fracture values (lowest fracture toughness properties values and lowest tearing modulus) for VCSNS Unit 1 primary loop elbows from Table 4-7 is selected as shown below:

]a,c,e Toughness properties from these material heats are conservatively used for all the critical location evaluations.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-5 J1c and Jmax Calculations:

]a,c,e T mat Calculations:

The material tearing modulus, Tmat, is calculated as follows:

Tmat = dJ/da X E/(crra) 2 The results from the ANL Research Program indicate that the lower-bound fracture toughness of thermally aged cast stainless steel is similar to that of submerged arc welds (SA Ws). In addition, historic testing done on representative plants documented in References 4-5 and 4-6, has shown that the wrought and cast stainless steel piping exhibits more limiting (unaged) fracture toughness properties than the weld metal. Since the CASS material's aged lower bound fracture toughness values are similar to that of Submerged Arc Welds (SAWs), and since SAWs are considered to be the most limiting of welding processes (with respect to GTA Wand SMAW), it is concluded that the aged fracture toughness of the wrought and cast base metal is more limiting than the aged fracture toughness of the stainless-steel weld metal. Therefore, the stainless-steel weld regions are less limiting than the cast material, and the applied value of the I-integral for a flaw in the weld regions will be lower than that in the base metal because the yield stress for the stainless steel weld materials is much higher at operating temperature<*)_

Forged stainless steel piping such as SA376 TP304N does not degrade due to thermal aging. Thus, fracture toughness values well in excess of that established for the cast material exist for this material throughout service life and are not limiting.

Inconel 152 and Alloy 82/182 weld materials have high toughness values and do not degrade due to thermal aging. As discussed in Reference 4-7, the fracture resistance of Ni Alloys (Alloys 82 and 52) and their welds have been investigated by conducting fracture toughness J-R curve tests at 24-338°C in deionized water. The results indicated that Alloy 690 welds exhibit excellent fracture toughness in air and high-temperature water (> 93 °C).

Since nickel alloys are known to have high toughness properties and because CF8A CASS base metal is susceptible to thermal aging degradation of the fracture toughness, it is determined that the CF8A CASS base metal presents the most limiting condition. Therefore, in the fracture mechanics analyses that follow, the thermally aged fracture toughness allowables of the CASS material given in Table 4-7 will be used as the criteria against which the calculated applied fracture toughness values will be compared.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-6 4.4 REFERENCE 4-1 ASME Boiler and Pressure Vessel Code Section II, Part D, "Properties (Customary) Materials,"

2007 Edition up to and including 2008 Addenda.

4-2 0. K. Chopra and W. J. Shack, "Assessment of Thermal Embrittlement of Cast Stainless Steels,"

NUREG/CR-6177, U.S. Nuclear Regulatory Commission, Washington, DC, May 1994.

4-3 0. K. Chopra, "Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems," NUREG/CR-4513, Revision 1, U.S. Nuclear Regulatory Commission, Washington, DC, August 1994.

4-4 0. K. Chopra, "Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems," NUREG/CR-4513, Revision 2, U.S. Nuclear Regulatory Commission, Washington, DC, May 2016" including Errata, March 15, 2021.

4-5 Westinghouse Report, WCAP-9787, "Tensile and Toughness Properties of Primary Piping Weld Metal for Use in Mechanistic Fracture Evaluation," May 1981.

4-6 Westinghouse Report, WCAP-9558, Revision 2, "Mechanistic Fracture Evaluation of Reactor Coolant Pipe Containing a Postulated Circumferential Through-Wall Crack," May 1981.

4-7 NUREG/CR-6721, "Effects of Alloy Chemistry, Cold Work, and Water Chemistry on Corrosion Fatigue and Stress Corrosion Cracking of Nickel Alloys and Welds," April 2001.

(a) In the report, all the applied J values were conservatively determined by using base metal strength properties.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-7 Table 4-1 Measured Room Temperature Tensile Properties for VCSNS Unit 1 Primary Loop Piping Room Temperature Material Properties (ksi)

Component Loop Heat Number

'Iype Yield Ultimate Strength Strength 48.0 87.7 Hot Leg A I.J359/14462 SA376 TP304N 49.7 93.7 47.2 88.4 Hot Leg B Ll359/14463 SA376 TP304N 49.7 92.4 45.9 88.7 Hot Leg C Ll359/14464 SA376 TP304N 49.7 91.7 46.5 89.7 Crossover Leg A K3723/15903X SA376 TP304N 48.2 91.4 45.0 87.4 Crossover Leg A K3723/15692W SA376-TP304N 48.0 91.4 46.5 89.7 Crossover Leg B K3723/15903Y SA376 TP304N 48.2 91.4 45.0 87.4 Crossover Leg B K3723/15692X SA376 TP304N 48.0 91.4 46.5 89.7 Crossover Leg C K3723/15903Z SA376 TP304N 48.2 91.4 45.0 87.4 Crossover Leg C K3723/15692Y SA376 TP304N 48.0 91.4 40.9 82.1 Cold Leg A Ll336/14461 SA376 TP304N 45.9 88.6 43.7 86.4 Cold Leg B K3723/16098 SA376 TP304N 45.9 89.9 48.5 92.2 Cold Leg C Ll551/17989 SA376 TP304N 43.7 86.1 Hot Leg Spool A J6347 SA376 TP304N 41.2 83.6 Piece 46.7 Average (46.5*)

Room Temp. Minimum Yield Strength: 40.9 ksi Room Temp. Minimum Ultimate Strength: 82.1 ksi Room Temp. Average Yield Strength: 46.7 (*46.5, with spool piece) ksi Material Characterization April2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-8 Table 4-2 Measured Room Temperature Tensile Properties for VCSNS Unit 1 Primary Loop Fittings (Elbows)

Room Temperature Material Properties (ksi)

Component Loop Heat Number Type Yield Intimate Strength Strength Hot Leg A 79420-1 SA351 CF8A 38.1 81.5 Hot Leg B 79420-2 SA351 CF8A 38.l 81.5 Hot Leg C 80019-2 SA351 CF8A 35.2 77.7 Crossover Leg A 90946-1 SA351 CF8A 38.7 86.7 Crossover Leg A 89916-1 SA351 CF8A 44.3 86.9 Crossover Leg B 92293-1 SA351 CF8A 38.2 82.2 Crossover Leg B 89253-1 SA351 CF8A 42.5 85.7 Crossover Leg C 91068-1 SA351 CF8A 37.3 82.5 Crossover Leg C 93212-1 SA351 CF8A 37.9 83.7 Crossover Leg B 84013-1 SA351 CF8A 39.3 83.5 Crossover Leg C 84227-1 SA351 CF8A 40.5 82.5 Crossover Leg A 82695-2 SA351 CF8A 37.2 82.4 Cold Leg A 67487-1 SA351 CF8A 43.6 86.5 Cold Leg B 65692-2 SA351 CF8A 39.3 83.6 Cold Leg C 73359-4 SA351 CFSA 37.0 85.9 Average 39.2 Room Temp. Minimum Yield Strength: 35.2 ksi Room Temp. Minimum Ultimate Strength: 77.7 ksi Room Temp. Average Yield Strength: 39.2 ksi Material Characterization April 2022 WCAP-13207 Revision4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-9 Table 4-3 Measured Room Temperature Tensile Properties for Hot Leg Loop A lnconel 152 Weld at Location 1 Room Temperature Material Properties (ksi)

Component Loop Heat Number Type Yield Ultimate Strength Strength Hot Leg A 45D2 Inconel 152 61.60 101.20 Hot Leg A WC59D8 Inconel 152 59.60 99.50 Hot Leg A 49D4 Inconel 152 62.70 101.20 Average 61.30 Room Temp. Minimum Yield Strength: 59.60 ksi Room Temp. Minimum Ultimate Strength: 99.50 ksi Room Temp. Average Yield Strength: 61.30 ksi Material Characterization April 2022 WCAP-13207 Revision4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-10 Table 4-4 Mechanical Properties for VCSNS Unit 1 Materials at Operating Temperatures a,c,e Modulus of Elasticity at operating temperatures For SA376 TP304N and SA351 CF8A: E = 25.19 x 106 psi at T=622°F; E = 25.54 x 106 psi at T=553°F For Inconel 152: E = 27.99 x 106 psi at T=622°F For Alloy 82/182: E = 28.61 x 106 psi at T=622°F; E = 28.84 x 106 psi at T=553°F Poisson's ratio: 0.3 Material Characterization April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-11 Table4-5 a,c,e Chemistry and Fracture Toughness Properties of the SA351 CF8AMaterial Heats ofVCSNS Unit 1 Material Characterization April 2022 WCAP-13207 Revision4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-12 Table 4-6 Enveloped J1c, Jmax, T mat for the SA351 CF8A Material Heats from Revision 1 and Revision 2 of NUREG/CR-4513 Material Characterization WCAP-13207

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-13 Table 4-7 Fracture Toughness Properties of SA351 CF8A for VCSNS Unit 1 Primary Loops for Leak-Before-Break Evaluation at Critical Locations a,c,e Material Characterization April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-14 Figure 4-1 Pre-Service J vs. Aa for SA351-CF8M Cast Stainless Steel at 600°F Note: This plot is shown for demonstration purposes. While the material relevant to this evaluation is SA351 CF8A, the toughness characteristic ofSA351 CF8M, shown here, are also for reference only.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-1 5.0 CRITICAL LOCATION AND EVALUATION CRITERIA 5.1 CRITICAL LOCATIONS The Leak-Before-Break (LBB) evaluation margins are to be demonstrated for the limiting locations (governing locations). Candidate locations are designated load critical locations or toughness critical locations as discussed in Section 3.0. Such locations are established considering the loads (Section 3.0) and the material properties established in Section 4.0. Separate critical locations are created for VCSNS RCS primary loop A and loops B&C piping as described below. The critical locations are shown in Figure 3-2.

Load Critical Locations The highest stressed location for the SA376 TP304N straight pipes is location 1 for each of the three loops. For the weaker SA351 CF8A elbows: the highest faulted stressed welds at Hot leg are locations 2 and 3 for loops A, Band C; the highest faulted stress location at Crossover leg (XL) and Cold leg (CL) for each of the three loops is at location 4.

For the Alloy 82/182 DM welds at the SGIN, SGON and RPVIN to safe-end, the highest faulted stress locations are at the SGIN to safe-end, location 3, for loops A, B and C. Location 4 is selected as a representative location for evaluation of the Alloy 82/182 DM welds at the XL and the CL (location 4 and location 12). Evaluation of Alloy 82/182 DM welds at the RPVON location 1, loops B and C, is performed as well.

Toughness Critical Location Low toughness locations are at the end of each elbow since the elbows are made of cast materials and can be susceptible to thermal aging. Per Section 4.3, the critical material location for the elbows is [

Ja,c,e, due to low toughness. As identified above the highest faulted stresses at the elbow locations are 2, 3, 4 and 12 (location 4 is the governing location for both locations 4 and 12) for each of the three loops. The limiting toughness value determined in Section 4.3 is conservatively used in evaluating of these locations.

For the critical locations, the tensile properties are shown in Table 4-4, and the allowable toughness properties are shown in Table 4-7.

5.2 FRACTURE CRITERIA As will be discussed later, fracture mechanics analyses are made based on loads and postulated flaw sizes related to leakage. The stability criteria against which the calculated J (i.e., Japp) and tearing modulus (Tapp) are compared are:

(1) If Japp< Jic, then an existing crack is stable (or a crack will not initiate);

(2) If Japp> Jic; and Tapp< Tmat and Japp< Jmax, then the crack is stable.

Where: Japp = AppliedJ Jrc = J at Crack Initiation Tapp Applied Tearing Modulus Critical Location and Evaluation Criteria April 2022 WCAP-13207 Revision4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-2 Tmat Material Tearing Modulus Jmax Maximum J value of the material For critical locations, the limit load method discussed in Section 7.0 was also used.

For global failure mechanism, the stability analysis is performed using limit load method based on loads and postulated flaw sizes related to leakage, with the criteria as follows:

• Margin of 10 on the Leak Rate

• Margin of2.0 on Flaw Size

• Margin of 1.0 on Loads (using the absolute summation method for faulted load combination).

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-1 6.0 LEAK RATE PREDICTIONS

6.1 INTRODUCTION

The purpose of this section is to discuss the method which is used to predict the flow through postulated through-wall cracks and present the leak rate calculation results for through-wall circumferential cracks.

6.2 GENERAL CONSIDERATIONS The flow of hot pressurized water through an opening to a lower back pressure causes flashing which can result in choking. For long channels where the ratio of the channel length, L, to hydraulic diameter, Ori, (L/DH) is greater than [

6.3 CALCULATION METHOD The basic method used in the leak rate calculations is the method developed by [

The flow rate through a crack was calculated in the following manner. Figure 6-1 (from Reference 6-2) was used to estimate the critical pressure, Pc, for the primary loop enthalpy condition and an assumed flow. Once Pc was found for a given mass flow, the [

]a,e,e was found from Figure 6-2 (taken from Reference 6-2). For all cases considered, since [

].a.c,e Therefore, this method will yield the two-phase pressure drop due to momentum effects as illustrated in Figure 6-3, where Po is the operating pressure. Now using the assumed flow rate, G, the frictional pressure drop can be calculated using:

(6-1) where the friction factor f is determined using the [ ]a,c,e The crack relative roughness, e, was obtained from fatigue crack data on stainless steel samples. The relative roughness value used in these calculations was [ ]a,c,e The frictional pressure drop using Equation 6-1 is then calculated for the assumed flow rate and added to the [ ]a,c,e to obtain the total pressure drop from the primary system to the atmosphere.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-2 That is, for the primary loop:

Absolute Pressure - 14.7 [ (6-2) for a given assumed flow rate G. If the right-hand side of Equation 6-2 does not agree with the pressure difference between the primary loop and the atmosphere, then the procedure is repeated until Equation 6-2 is satisfied to within an acceptable tolerance which in turn leads to flow rate value for a given crack size.

6.4 LEAK RATE CALCULATIONS Leak rate calculations were made as a function of crack length at the governing locations previously identified in Section 5.1. The normal operating loads of Table 3-1 were applied in these calculations. The crack opening areas were estimated using the method of Reference 6-3, and the leak rates were calculated using the two-phase flow formulation described above. The average material properties of Section 4.0 (see Table 4-4) were used for these calculations.

The flaw sizes to yield a leak rate of IO gpm for VCSNS Unit I were calculated at the governing locations with pipe material SA376-TP304N, elbow material SA351-CF8A, and weld material Alloy 82/182 are given in Table 6-1, Table 6-2 and Table 6-3, respectively. Table 6-3 also shows the Inconel 152 weld flaw size for a 10 gpm leak rate for location I of the loop A hot leg. The flaw sizes, so determined, are called leakage flaw sizes. Based on the PWSCC crack morphology, an increase factor of 1.69 between the PWSCC and fatigue crack morphologies (Reference 6-4) is applied to the leakage flaw sizes for the Alloy 82/182 DM welds as shown in Table 6-3.

The VCSNS Unit 1 RCS pressure boundary leak detection system meets the intent of Regulatory Guide 1.45 (Reference 6-5), and the plant leak detection capability is 1 gpm. Thus, to satisfy the margin of 10 on the leak rate, the flaw sizes (leakage flaw sizes) are determined which yield a leak rate of 10 gprn.

6.5 REFERENCES

6-1 [

6-2 M. M, El-Wakil, "Nuclear Heat Transport, International Textbook Company," New York, N.Y.,

1971.

6-3 Tada, H., "The Effects of Shell Corrections on Stress Intensity Factors and the Crack Opening Area of Circumferential and a Longitudinal Through-Crack in a Pipe," Section Il-1, NUREG/CR-3464, September 1983.

6-4 D. Rudland, R. Wolterman, G. Wilkowski, R. Tregoning, "Impact of PWSCC and Current Leak Detection on Leak-Before-Break," proceedings of Conference on Vessel Head Penetration, Inspection, Cracking, and Repairs, Sponsored by USNRC, Marriot Washingtonian Center, Gaithersburg, MD, September 29 to October 2, 2003.

6-5 Regulator Guide 1.45, Revision 1, "Guidance on Monitoring and Responding to Reactor Coolant System Leakage," 2008.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-3 Table 6-1 Flaw Sizes Yielding a Leak Rate of 10 gpm at the Critical Locations with SA376-TP304N Material a,c,e Table 6-2 Flaw Sizes Yielding a Leak Rate of 10 gpm at the Elbow Critical Locations with SA 351-CFSA Material a,c,e Leak Rate Predictions April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-4 Table 6-3 Flaw Sizes Yielding a Leak Rate of 10 gpm at the Critical Locations with Alloy 82/182 and Inconel 152 Materials a.c.e Leak Rate Predictions April 2022 WCAP-13207 Revision4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-5 a.c.e STAGNATION ENTHALPY (1o2 Btu/lb)

Figure 6-1 Analytical Predictions of Critical Flow Rates of Steam-Water Mixtures Leak Rate Predictions April 2022 WCAP-13207 Revision4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-6 a,c,e LENGTH/DIAMETER RATIO (LIO)

Figure 6-2 r.c,e Pressure Ratio as a Function ofL/D Leak Rate Predictions April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-7

[

Figure 6-3 Idealized Pressure Drop Profile Through a Postulated Crack Leak Rate Predictions April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 7-1 7.0 FRACTURE MECHANICS EVALUATION 7.1 LOCAL FAILURE MECHANISM The local mechanism of failure is primarily dominated by the crack tip behavior in terms of crack-tip blunting, initiation, extension, and final crack instability. The local stability will be assumed if the crack does not initiate at all. It has been accepted that the initiation toughness measured in terms of J1c from a J-integral resistance curve is a material parameter defining the crack initiation. If, for a given load, the calculated J-integral value is shown to be less than the Jrc of the material, then the crack will not initiate.

If the initiation criterion is not met, one can calculate the tearing modulus as defined by the following relation:

dJ E Tapp -x- (7-1) da cr f2 Where:

Tapp applied tearing modulus E modulus of elasticity O"f 0.5 (cry+ O"u) flow stress a crack length O"y, O"u yield and ultimate strength of the material, respectively Stability is said to exist when ductile tearing does not occur if Tapp is less than Tmat, the experimentally determined tearing modulus. Since a constant Tmat is assumed, a further restriction is placed in Japp* Japp must be less than Jmax; where Jmax is the maximum value of J for which the experimental Tmat is greater than or equal to the Tapp used.

As discussed in Section 5.2 the local crack stability criteria is a two-step process:

(1) If Japp < Jrc, then an existing crack is stable (or a crack will not initiate);

(2) If Japp ~ J1c; and Tapp < T mat and Japp < Jmax, then the crack is stable.

7.2 GLOBALFAILUREMECHANISM Determination of the conditions which lead to failure in stainless steel should be done with plastic fracture methodology because of the large amount of deformation accompanying fracture. One method for predicting the failure of ductile material is the plastic instability method, based on traditional plastic limit load concepts, but accounting for strain hardening and taking into account the presence of a flaw. The flawed pipe is predicted to fail when the remaining net section reaches a stress level at which a plastic hinge is formed. The stress level at which this occurs is termed as the flow stress. The flow stress is generally taken as the average of the yield and ultimate tensile strength of the material at the temperature of interest. This methodology has been shown to be applicable to ductile piping through a large number of experiments and will be used here to predict the critical flaw size in the primary coolant piping. The failure criterion has been obtained by requiring equilibrium of the section containing the flaw (Figure 7-1)

Fracture Mechanics Evaluation April 2022 WCAP-13207 Revision 4

.... This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation}

WESTINGHOUSE NON-PROPRIETARY CLASS 3 7-2 when loads are applied. The detailed development is provided in Appendix A for a through-wall circumferential flaw in a pipe with internal pressure, axial force, and imposed bending moments. The limit moment for such a pipe is given by:

] a,c,e Where:

The analytical model described above accurately accounts for the piping internal pressure as well as imposed axial force as they affect the limit moment. Good agreement was found between the analytical predictions and the experimental results (Reference 7-1 ).

For application of the limit load methodology, the material, including consideration of the configuration, must have a sufficient ductility and ductile tearing resistance to sustain the limit load.

7.3 RESULTS OF CRACK STABILITY EVALUATION As discussed in Sections 7.1 and 7.2, the LBB evaluation for VCSNS Unit 1 consists of evaluating two failure mechanisms. Stability analyses were performed at the critical locations established in Section 5 .1.

The elastic-plastic fracture mechanics (EPFM) J-integral analyses for through-wall circumferential cracks in a cylinder were performed using the procedure in the EPRI fracture mechanics handbook (Reference 7-2).

The more limiting lower-bound tensile properties for base metal for SA351-CF8A elbow material from Section 4.0 were applied (see Table 4-4). The fracture toughness properties established in Section 4.3, and the normal plus SSE loads given in Table 3-2 were used for the EPFM calculations. Evaluations were performed at the toughness critical locations identified in Section 5.1. Note that one bounding J-integral evaluation was performed for both locations 2 and 3 of loop A and loops B&C using the most limiting geometry, the highest faulted loads from both locations as provided in Table 3-2. Also, the highest leakage flaw size from both locations 2 and 3 is used in the J-integral evaluation. The results of the elastic-plastic fracture mechanics J-integral evaluations are given in Table 7-1. The associated leakage Fracture Mechanics Evaluation April 2022 WCAP-13207 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 7-3 flaw sizes from Table 6-2 are also presented in Table 7-1, except for locations 2 and 3, where the highest from both leakage flaw sizes for locations 2 and 3 of loop A and loops B&C in Table 6-2 is used in the J-integral evaluation. In addition, one bounding J-integral evaluation was performed at governing location 4 for both locations 4 and 12 for all three loops, and results are presented in Table 7-1.

A stability analysis based on limit load as described in Section 7 .2 was performed for critical locations 1, 2, 3 and 4 (location 4 is the governing location for both locations 4 and 12). Table 7-2 and Table 7-3 summarize the results of the stability analyses based on the limit load for piping SA376 TP304N and SA351-CF8A elbow materials, respectively. The associated leakage flaw sizes (from Table 6-1 and Table 6-2) are also presented in Table 7-2 and Table 7-3.

The limit load analyses consider material properties (yield and ultimate strength) of the base metal, and not the material properties of the weld metal. The base metal (piping) is considered to have more limiting material properties than the weld metal. Therefore, in the limit load evaluation the faulted loads (include both the axial loads (including pressure) and the moment loads) from Table 3-2 were increased by the Z-correction factors to account for reduction of the material toughness due to the welding process used during construction consistently with the methodology of SRP 3.6.3. It is confirmed that the limit load analysis in this report bounds both the weld metal and base metal since the more limiting material properties of the base metals were used in combination with additional penalty Z-correction factor for the stainless-steel weld.

The welding process implemented at locations 1 and 3 is a combination of Gas Tungsten Arc Welding (GTAW) and Shielded Metal Arc Welding (SMAW). Location 1 of loop A envelopes the two types of welding process: GTAW between the RPVON and the spool piece, and SMAW at the other end of the spool piece. AZ-correction factor is not applicable for the GTAW welding process; therefore, the SMAW process governs these evaluations at locations 1 and 3. The welding process implemented at location 2 is Submerged Arc Welding (SAW). For LBB evaluations, SAW is more limiting for crack stability analysis compared to SMAW process. Therefore, a conservative approach is taken assuming a SAW process at location 4 for all loops. The Z-correction factor for the SMAW and SAW welding processes (References 7-3 and 7-5) are as follows:

Locations 1 and 3: Z = 1.15 [1.0 + 0.013 (OD-4)] for SMAW Locations 2 and 4: Z = 1.30 [1.0 + 0.010 (OD-4)] for SAW Where OD is the outer diameter of the pipe in inches.

The Z-correction factors were calculated for the critical locations using the dimensions given in Table 3-1.

The Z-correction factors are 1.60 for location 1, 1.69 for location 2, 1.63 for location 3 and 1.72 for location 4.

In the J-integral evaluation, Japp was calculated based on the faulted loads in Table 3-2 without any Z-correction factors to account for reduction in fracture toughness. This is because the calculation of J1c, as part of the J-integral evaluations, already considers reduction in fracture toughness due to thermal aging of the CASS materials at normal operating temperature over extended operating periods. This reduction in fracture toughness is based on correlations in NUREG/CR-4513 Revisions 1 and 2 (References 7-6 and 7-7), which have determined lower bound fracture toughness as discussed in Section 4.3. Therefore, no Fracture Mechanics Evaluation April 2022 WCAP-13207 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 7-4 additional Z-factors are necessary because the reduction in fracture toughness is already captured with the consideration of end-of-life (saturated) fracture toughness values from NUREG/CR-4513.

Therefore, the limit load analysis for CASS materials in this report considered the reduced fracture toughness of the weld (Z-correction factor), and the J-applied analysis considered the reduced fracture toughness of the thermally aged CASS material per References 7-6 and 7-7.

7.4 SG AND RPV NOZZLE ALLOY 82/182 WELDS Alloy 82/182 or Alloy 82 welds which are susceptible to PWSCC are present at the RPVINs, SGIN's and SGON's for all loops, and at the RPVONs for loops Band C. As discussed in Section 2.1, for RPVON's, SGIN's and SGON's the potential PWSCC have been mitigated. The limit load evaluation for the unmitigated and mitigated weld locations (locations 1 for loops B and C; locations 3, 4 and 12 for all loops) is performed.

The typical material properties of the Alloy 82/182 DM weld material from Table 4-4 were considered for the limit load analysis at locations 1 for loops B and C; at locations 3, 4 and 12 for all loops. The limit load analysis of the Alloy 82/182 welds considered a crack morphology factor (Z-multiplication factor).

]a,c,e The Z-multiplication factor of 1.21 for the Alloy 82/182 material was calculated at location 1, loops B and C; locations 3, 4 and 12 for all loops. Note that in the limit load calculation for these locations, the applicable Z-correction factors for SMAW and SAW were conservatively used instead of both, the Z-correction factor of 1.0 for GTAW welding process at Alloy 82 material locations and the additional Z-multiplication factor of 1.21 for Alloy 82 material. The Z- multiplication factor for Inconel 152 is 1.0.

As discussed in Section 6.4, an increased factor of 1.69 to account for the PWSCC as applicable is applied to the leakage flaw size calculation.

Table 7-4 provides summary results for Alloy 82/182 DM weld material including associated leakage flaw sizes from Table 6-3. Table 7-4 also shows the critical flaw size for the Inconel 152 weld for location 1 of the loop A hot leg.

Fracture Mechanics Evaluation April 2022 WCAP-13207 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 7-5

7.5 REFERENCES

7-1 Kanninen, M. F., et al., "Mechanical Fracture Predictions for Sensitized Stainless Steel Piping with Circumferential Cracks," EPRI NP-192, September 1976.

7-2 Kumar, V., German, M. D. and Shih, C. P., "An Engineering Approach for Elastic-Plastic Fracture Analysis," EPRI Report NP-1931, Project 1237-1, Electric Power Research Institute, July 1981.

7-3 Standard Review Plan; Public Comment Solicited; 3.6.3 Leak-Before-Break Evaluation Procedures; Federal Register/Vol. 52, No. 167/Friday, August 28, 1987/Notices, pp. 32626-32633.

7-4 ASME Pressure Vessel and Piping Division Conference Paper PVP2008-61840, "Technical Basis for Revision to Section XI Appendix C for Alloy 600/82/182/132 Flaw Evaluation in Both PWR and BWR Environments," July 28-31, Chicago IL, USA.

7-5 NUREG-0800, Revision 1, Standard Review Plan: 3.6.3 Leak-Before-Break Evaluation Procedures, March 2007.

7-6 0. K. Chopra, "Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems," NUREG/CR-4513, Revision 1, U.S. Nuclear Regulatory Commission, Washington, DC, August 1994.

7-7 0. K. Chopra, "Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems," NUREG/CR-4513, Revision 2, U.S. Nuclear Regulatory Commission, Washington, DC, May 2016" including Errata, March 15, 2021.

Fracture Mechanics Evaluation April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 7-6 Table 7-1 VCSNS Unit 1 Stability Results Based on Elastic-Plastic J-Integral Evaluations a,c,e for SA351-CF8A Table7-2 VCSNS Unit 1 Stability Results Based on Limit Load for SA376-TP304N Material a c,e Fracture Mechanics Evaluation April 2022 WCAP-13207 Revision 4

..,. This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 7-7 Table 7-3 VCSNS Unit 1 Stability Results Based on Limit Load for SA351-CF8A Materials a,c,e Table 7-4 VCSNS Unit 1 Stability Results Based on Limit Load for Alloy 82/182 and Inconel 152 Materials a,c,e Fracture Mechanics Evaluation April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 7-8 Neutral Axis Figure 7-1

}a,c,e Stress Distribution Fracture Mechanics Evaluation April 2022 WCAP-13207 Revision4

• "" This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-1 8.0 FATIGUE CRACK GROWTH ANALYSIS To determine the sensitivity of the primary coolant system to the presence of small cracks, a plant specific fatigue crack growth (FCG) analysis was carried out for the [ ]a,c,e region (see Location [ ]a,c,e of Figure 3-2). This region was selected because crack growth calculated here will be typical (i.e., the design transient thermal and pressure stresses will be representative) of that in the entire primary loop. The crack growth at the [ ]a,c,e will demonstrate that small surface flaws would not develop to through-wall flaws during the plant design life. Crack growths calculated at other locations can be expected to show less than 10% variation.

A[ ]a,c,e of a plant typical in geometry and operational characteristics to any Westinghouse PWR System.

]a,c,e All normal, upset, and test conditions were considered. A summary of the applied transients is provided in Table 8-1.

Circumferentially oriented surface flaws were postulated in the region, assuming the flaw was located in three different locations, as shown in Figure 8-1. Specifically, these were:

Cross Section A: [ ]a,c,e

]a,c,e Cross Section B: [

Cross Section C: [

Fatigue crack growth rate laws were used [

] a,c,e The law for stainless steel was derived from Reference 8-1, with a very conservative correction for the R ratio, which is the ratio of minimum to maximum stress during a transient. For stainless steel, the fatigue crack growth formula is:

-da = (5 .4xl O-i2)

• K.ff 4.48 .

mches/cycle (8-1) dn Where:

da/dn = crack growth rate Keff = K1maxx(l.O -R)°- 5 R = ratio of minimum K1 and maximum K1

= K1min/Klmax Fatigue Crack Growth Analysis April 2022 WCAP-13207 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-2

]a,c,e

[ (8-2)

Where:

Fatigue crack growth results for the Inconel 182 and Inconel 152 welds are expected to be about the same as Inconel 600 weld.

The calculated fatigue crack growth for semi-elliptic surface flaws of circumferential orientation and various depths is summarized in Table 8-2, and shows that the crack growth is very small, [

]. a,c,e To demonstrate that the small surface flaws will not result in a through-wall flaw over the design life of the plant. The aspect ratio for the postulated initial crack sizes are for a typical flaw shape of [ ]"*0 ** (flaw length/flaw depth). Various initial flaw depths were considered in the FCG analysis to demonstrate that small, NDE-detectable flaw sizes on the order of [

0

]"* ** would be acceptable for the life of the plant (i.e., will not grow to the become complete through-wall).

The intent of FCG in the LBB analysis was not to use initial flaw depths that are larger than the Acceptance Tables of ASME Section XI IWB-3410-1, but rather to show a defense in-depth fatigue crack growth based on small flaw sizes that are detectable based on NDE examination techniques, which would not become through-wall flaws over the design life of the plant.

It should be noted that an underlying main assumption of this FCG analysis is that the design transients and associated occurrences which had been established for a 40-year design life remain applicable for the 60-year license renewal period. As expected, increase of the cycles for certain transients used in the FCG evaluation from 60-year to 80-year subsequent license renewal period may occur. However, the potential of exceeding the allowable transients for 40-year design basis is minimal. Furthermore, if some exceedances of the cycles for the 80-year design transients occur, the fatigue crack growth results documented in Table 8-2 show that there is a sufficient margin to ensure that small surface flaws will not become through-wall flaws. Additionally, the fatigue crack growth evaluation is considered a defense in depth review. FCG is no longer a requirement for the Leak-Before-Break (LBB) analysis, since the LBB analysis is based on the postulation of through-wall flaw, whereas the FCG analysis is performed based on the surface flaw. Furthermore, Reference 8-4 has indicated that "the Commission deleted the fatigue crack growth analysis in the proposed rule. This requirement was found to be unnecessary because it was bounded by the crack stability analysis." Nevertheless, the fatigue crack growth analysis is retained herein for information purposes and to demonstrate that small surface flaws do not result in through-wall flaws over the life of the plant.

Fatigue Crack Growth Analysis April 2022 WCAP-13207 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-3

8.1 REFERENCES

8-1 Bamford, W. H., "Fatigue Crack Growth of Stainless Steel Piping in a Pressurized Water Reactor Environment," Trans. ASME Journal of Pressure Vessel Technology, Vol. 101, Feb. 1979.

8-2 [

]a,c,e 8-3 [

]a,c,e 8-4 Nuclear Regulatory Commission, 10 CPR 50, Modification of General Design Criteria 4 Requirements for Protection Against Dynamic Effects of Postulated Pipe Ruptures, Final Rule, Federal Register/Vol. 52, No. 207/Tuesday, October 27, 1987/Rules and Regulations, pp. 41288-41295.

Fatigue Crack Growth Analysis April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-4 Table 8-1 Summary of Reactor Vessel Transients for VCSNS Unit 1 Number of Number Typical Transient Identification Cycles Normal Conditions Heatup and Cooldown at 100°F/hr.

1 200 (pressurizer cooldown 200°F/hr.)

Load Follow Cycles 2 18300 (Unit loading and unloading at 5% of full power/min.)

3 Step Load Increase and Decrease 2000 4 Large Step Load Decrease, with Steam Dump 200 5 Steady State Fluctuations 1000000 Ui;iset Conditions 6 Loss of Load, without Immediate Turbine or Reactor Trip 80 Loss of Power 7 40 (blackout with natural circulation in the Reactor Coolant System)

Loss of Flow 8 80 (partial loss of flow, one pump only) 9 Reactor Trip from Full Power 400 Test Conditions 10 Turbine Roll Test 10 11 Hydrostatic Test Conditions Primary Side 5 Primary Side Leak Test 50 12 Cold Hydrostatic Test 10 Fatigue Crack Growth Analysis April 2022 WCAP-13207 Revision4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-5 Table 8-2 Typical Fatigue Crack Growth at [ ]a,c,e(40, 60 and 80-Years)

Final Flaw (in.)

Initial Flaw (in.) [ ]a,c,e [ ] a,c,e

[ ] a,c,e 0.292 0.31097 0.30107 0.30698 0.300 0.31949 0.30953 0.31626 0.375 0.39940 0.38948 0.40763 0.425 0.45271 0.44350 0.47421 Fatigue Crack Growth Analysis April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-6 Figure 8-1 Typical Cross-Section of [

Fatigue Crack Growth Analysis April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-7 a,c,e Figure 8-2

]a,c,e Reference Fatigue Crack Growth Curves for [

Fatigue Crack Growth Analysis April2022 WCAP-13207 Revision4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-8 a,c,e Figure 8-3 Reference Fatigue Crack Growth Law for [ ]a,c,e in a Water Environment at 600°F Fatigue Crack Growth Analysis April 2022 WCAP-13207 Revision4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (fhis statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 9-1 9.0 ASSESSMENT OF MARGINS The results of the leak rates of Section 6.4 and the corresponding stability and fracture toughness evaluations of Sections 7.1, 7.2, 7.3 and 7.4 are used in performing the assessment of margins. Margins are shown for piping SA376-TP304N material in Table 9-1, for elbow SA351-CF8Amaterial in Table 9-2 and for Alloy 82/182 and Inconel 152 weld material in Table 9-3. All of the LBB recommended margins are satisfied. Also, the existence of Alloy 82 DM welds at the SGIN and SGON to safe-end, and Alloy 82/182 DM welds at the RPVIN to safe-end for loops A, B and C, and RPVON to safe-end locations for loops B and C are acceptable for the SLR program for SO-years of plant operation.

In summary, at all the critical locations relative to:

1. Flaw Size - Using faulted loads obtained by the absolute sum method, a margin of 2 or more .

exists between the critical flaw and the flaw having a leak rate of 10 gpm (the leakage flaw).

2. Leak Rate - A margin of 10 exists between the calculated leak rate from the leakage flaw and the plant leak detection capability of 1 gpm.

3. Loads - At the critical locations the leakage flaw was shown to be stable using the faulted loads obtained by the absolute sum method (i.e., a flaw twice the leakage flaw size is shown to be stable; hence the leakage flaw size is stable). A margin of 1 on loads using the absolute summation of faulted load combinations is satisfied.

Assessment of Margins April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 9-2 Table 9-1 VCSNS Unit 1 Leakage Flaw Sizes, Critical Flaw Sizes, and Margins based on Limit Load Evaluation for SA376-TP304N Material a,c,e Table9-2 VCSNS Unit 1 Leakage Flaw Sizes, Critical Flaw Sizes, and Margins based on Limit Load and J-Integral Evaluation for SA351-CF8A Material a,c,e Assessment of Margins April 2022 WCAP-13207 Revision4

• '"' This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 9-3 Table9-3 VCSNS Unit 1 Leakage Flaw Sizes, Critical Flaw Sizes, and Margins based on Limit Load Evaluation for Alloy 82/182 and Inconel 152 Materials a,c,e Assessment of Margins April 2022 WCAP-13207 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 10-1

10.0 CONCLUSION

S This report justifies the elimination of RCS primary loop pipe breaks from the structural design basis for the VCSNS Unit 1 for the 80-year license renewal period (SLR) as follows:

a. Stress corrosion cracking is precluded by use of fracture resistant materials in the piping system and controls on reactor coolant chemistry, temperature, pressure, and flow during normal operation. Alloy 82/182 or Alloy 82 welds are present at the RPVINs, SGIN's and SGON's for all loops, and at the RPVONs for loops B and C. The Alloy 82/182 welds are susceptible to PWSCC (Primary Water Stress Corrosion Cracking). The Alloy 82/182 weld at the RPVON for loop A is replaced with Inconel 152 weld, therefore no further consideration of the PWSCC effects is required for the SLR program.

b. To mitigate PWSCC effect due to the existence of Alloy 82/182, MSIP is applied at the RPVON's locations for loop B and C; the Alloy 82/182 DM weld at the RPVON to safe-end locations for loop A is replaced with Inconel 152 weld; and Alloy 152 inlay are installed on the inside surface of the Alloy 82 DW at the SG nozzle to safe-end locations.

The LBB has been reevaluated for 80-year plant life SLR program at the mitigated DM weld locations, including the RPVON for loops B and C with applications of MSIP and the SGIN's and SGON's with Alloy 152 inlay. The LBB evaluation has been performed considering Alloy 82/182 material properties which includes appropriate PWSCC crack morphology parameter.

c. Evaluation of the RCS piping considering the thermal aging effects for the 80-year plant life period of the SLR program, and also the use of the most limiting fracture toughness properties ensures that each materials profile is appropriately bounded by the LBB results presented in this report. As stated in Section 7.0, for local and global failure mechanisms, all locations are evaluated using the cast stainless steel material properties (SA351-CF8A) which present a limiting condition due to the thermal aging effects.

d. Water hammer should not occur in the RCS piping because of system design, testing, and operational considerations.

e. The effects of low and high cycle fatigue on the integrity of the primary piping are negligible.

f. Adequate margin exists between the leak rate of small stable flaws and the capability of the VCSNS Unit 1 reactor coolant system pressure boundary Leakage Detection System.

g. Ample margin exists between the small stable flaw sizes ofitem (t) and larger stable flaws.

h. Ample margin exists in the material properties used to demonstrate end-of-service life (fully aged) stability of the critical flaws.

For the critical locations, postulated flaws will be stable because of the ample margins described in f, g, andh above.

Conclusions April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 10-2 Based on the discussion above, the Leak-Before-Break conditions and margins are satisfied for the VCSNS primary loop piping. All the recommended margins are satisfied. It is therefore concluded that dynamic effects of RCS primary loop pipe breaks need not be considered in the structural design basis for VCSNS Unit 1 for the 80-year plant life (subsequent license renewal program).

Conclusions April 2022 WCAP-13207 Revision 4

• • • This record was final approved on 4/29/2022, 2:22:07 PM. (This statement was added by the PRIME system upon its validation)

WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-1 APPENDIX A: LIMIT MOMENT

] a,c,e Limit Moment April 2022 WCAP-13207 Revision 4

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-2 FigureA-1 Pipe with a Through-Wall Crack in Bending Limit Moment April2022 WCAP-13207 Revision 4

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Serial No.: 23-193 Docket No.: 50-395 Enclosure 4 Attachment 3 WCAP-18728-NP, REVISION 5 Virgil C. Summer (VCSNS) Unit 1 Dominion Energy South Carolina, Inc. (DESC)

Westinghouse Non-Proprietary Class 3 WCAP-18728-NP June 2023 Revision 5 V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal:

Evaluation of Reactor Vessel Integrity Time-Limited Aging Analyses

@Westinghouse

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 WCAP-18728-NP Revision 5 V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Evaluation of Reactor Vessel Integrity Time-Limited Aging Analyses Tyler C. Ziegler*

RV/CV Design & Analysis June2023 Reviewers: Donald M. McNutt III*

RV/CV Design & Analysis Frank M. Nedwidek*

Fuel Engineering Services Product Solutions Approved: Lynn A. Patterson*, Manager RV/CV Design & Analysis Jesse J. Klingensmith*, Manager Radiation Engineering & Analysis

• Electronically approved records are authenticated in the electronic document management system.

Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066, USA

© 2023 Westinghouse Electric Company LLC All Rights Reserved

""* This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 ii RECORD OF REVISION Revision Description Completed 0 Original Issue Mav2022 Incorporate Dominion's comments on Revision 0.

1 June 2022 Changes are marked with revision bars.

Incorporate Dominion's comments on Revision 1.

2 July 2022 Changes are marked with revision bars.

Incorporate Dominion's comments on CGE-RV000-TM-ME-000004 Revision 1 on the 3 August 2022 surveillance capsule schedule in Section 7.

Changes are marked with revision bars.

Incorporate a comment from Dominion on CGE-GENW-TR-LG-000002 Revision 0-B 4 May2023 addressing the USE positions in Section 5.

Changes are marked with revision bars.

Incorporate a comment from Dominion to address low temperature overpressure protection (LTOP) 5 in Table 1-1 and address the disposition of nozzle June 2023 P-T Limit curves as requested by Dominion.

Changes are marked with revision bars.

WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 lll TABLE OF CONTENTS LIST OF TABLES ....................................................................................................................................... iv LIST OF FIGURES ..................................................................................................................................... vi EXECUTIVE

SUMMARY

......................................................................................................................... vii 1 TIME-LIMITED AGING ANALYSIS ......................................................................................... 1-1 2 CALCULATED FLUENCE ......................................................................................................... 2-1 3 MATERIAL PROPERTY INPUT ................................................................................................. 3-1 4 PRESSURIZED THERMAL SHOCK ......................................................................................... 4-1 5 UPPER-SHELF ENERGY ........................................................................................................... 5-1 6 HEATUP AND COOLDOWN PRESSURE-TEMPERATURE LIMIT CURVES ....................... 6-1 6.1 ADJUSTED REFERENCE TEMPERATURES CALCULATION .................................... 6-1 6.2 P-T LIMIT CURVES APPLICABILITY .......................................................................... 6-14 7 SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULES .................................................. 7-1 8 REFERENCES ............................................................................................................................. 8-1 APPENDIX A CREDIBILITY EVALUATION OF THE VCSNS UNIT 1 SURVEILLANCE PROGRAM ..................................................................................................................... A-1 APPENDIX B EMERGENCY RESPONSE GUIDELINES .................................................................. B-1 WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 iv LIST OF TABLES Table 1-1 Evaluation of Time-Limited Aging Analyses Per the Criteria of 10 CFR 54.3 ............... 1-1 Table 2-1 Calculated Fast Neutron (E > 1.0 Me V) Fluence at the Surveillance Capsule Center for VCSNS Unit 1 ................................................................................................................. 2-2 Table 2-2 VCSNS Unit 1 Maximum Fast Neutron (E > 1.0 MeV) Fluence Experienced by the Pressure Vessel Materials in the Beltline and Extended Beltline Regions ....................... 2-4 Table 3-1 Best-Estimate Cu and Ni Weight Percent Values, Initial RTNDT Values, and Initial USE Values for the VCSNS Unit 1 RPV Beltline and Extended Beltline Materials ................ 3-4 Table 3-2 Calculation of Position 2.1 CF Values for VCSNS Unit 1 Surveillance Materials .......... 3-5 Table 3-3 Summary of the VCSNS Unit 1- RPV Beltline, Extended Beltline, and Surveillance Material CF Values based on Regulatory Guide 1.99, Revision 2, Position 1.1 and Position 2.1 ...................................................................................................................... 3-6 Table 4-1 RTPTs Calculations for VCSNS Unit 1 at 72 EFPY ......................................................... 4-2 Table 5-1 Predicted USE Values at 72 EFPY for the VCSNS Unit 1 Beltline and Extended Beltline Materials .......................................................................................................................... 5-3 Table 6-1 VCSNS Unit 1 Fluence and Fluence Factor Values for the Surface, 1/4T, and 3/4T Locations at 56 EFPY ...................................................................................................... 6-2 Table 6-2 VCSNS Unit 1 Fluence and Fluence Factor Values for the Surface, l/4T, and 3/4T Locations at 72 EFPY ...................................................................................................... 6-3 Table 6-3 Calculation of the VCSNS Unit 1 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at the End of PEO (56 EFPY) ........................ 6-4 Table 6-4 Calculation of the VCSNS Unit 1 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at the End of PEO (56 EFPY) ........................ 6-6 Table 6-5 Calculation of the VCSNS Unit 1 ART Values for the Reactor Vessel Extended Beltline Nozzle Materials at the End of PEO (56 EFPY) .............................................................. 6-8 Table 6-6 Calculation of the VCSNS Unit 1 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at the End of SPEO (72 EFPY) ...................... 6-9 Table 6-7 Calculation of the VCSNS Unit 1 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at the End ofSPEO (72 EFPY) .................... 6-11 Table 6-8 Calculation of the VCSNS Unit 1 ART Values for the Reactor Vessel Extended Beltline Nozzle Materials at the End of SPEO (72 EFPY) ......................................................... 6-13 Table 6-9 Summary ofthe Limiting ART Values ........................................................................... 6-14 Table 7-1 VCSNS Unit 1 Recommended Surveillance Capsule Withdrawal Schedule................... 7-3 TableA-1 Regulatory Guide 1.99, Revision 2, Credibility Criteria ................................................ A-1 WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 V TableA-2 Calculation of Interim Chemistry Factors for the Credibility Evaluation Using VCSNS Unit 1 Surveillance Capsule Data Only .......................................................................... A-4 TableA-3 VCSNS Unit 1 Surveillance Capsule Data Scatter about the Best-Fit Line ................... A-5 Table B-1 Evaluation ofVCSNS Unit 1 ERG Limit Category ....................................................... B-1 WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51:49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 vi LIST OF FIGURES Figure 2-1 Axial Boundary of the I .OE+ 17 n/cm 2 Fast Neutron (E > 1.0 MeV) Fluence Threshold in the +Z Direction at 33.75 (end of Cycle 27), 54, and 72 EFPY ...................................... 2-6 Figure 3-1 RPV Schematic for VCSNS Unit 1.................................................................................. 3-3 Figure 5-1 Regulatory Guide 1.99, Revision 2, Position 1.2 & 2.2 Predicted Decrease in Upper-Shelf Energy as a Function of Copper and Fluence for VCSNS Unit 1 at theEnd of SPEO (72 EFPY) ........................................................................................................................ 5-5 Figure 7-1 Original Arrangement of Surveillance Capsules in the VCSNS Unit 1 Reactor Vessel .. 7-4 WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51:49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 vii EXECUTIVE

SUMMARY

This report presents the reactor vessel integrity Time-Limited Aging Analyses (TLAA) evaluations for the Virgil C. Summer Nuclear Station (VCSNS) Unit l reactor pressure vessel (RPV) in accordance with the requirements of the License Renewal Rule, 10 CFR Part 54. TLAAs are calculations that address safety-related aspects of the RPV within the bounds of the current 60-year license. These calculations must also be evaluated to account for an extended period of operation (80 years) also termed Subsequent Period of Extended Operation (SPEO).

VCSNS Unit 1 is cun-ently licensed through 60 years of operation; therefore, with a 20-year license extension, the SPEO is applicable through 80 years of operation. The 60-year TLAAs evaluated in this report are applicable through 56 Effective Full Power Years (EFPY), which is deemed end of the Period of Extended Operation (PEO). Similarly, evaluations in this report performed at 80 years of operation are applicable through 72 EFPY (90% capacity factor of 80 years), which is deemed the end of SPEO. Updated neutron fluence evaluations were performed and documented in WCAP-18709-NP (Reference 5), as well as in Section 2 of this report. Updated neutron fluence evaluations were used to identify the VCSNS Unit I extended beltline materials and as input to the reactor vessel (RV) integrity evaluations in support of current plant operations and subsequent license renewal.

In addition to the RV integrity TLAA evaluations, the VCSNS Unit 1 surveillance data credibility evaluation is contained in Appendix A of this report. While not a TLAA, Appendix B provides an Emergency Response Guidelines (ERG) assessment for VCSNS Unit 1 for completeness.

A summary of results for the VCSNS Unit 1 TLAA evaluation is provided below. Based on the results of this TLAA evaluation, it is concluded that the VCSNS Unit 1 RV will continue to meet regulatory requirements through the SPEO.

Fluence The RV beltline and extended beltline neutron :fluence values applicable to a postulated 20-year license renewal period were calculated for the VCSNS Unit 1 materials. All transport calculations were carried out using the three-dimensional discrete ordinates code RAPTOR-M3G and the BUGLE-96 cross-section library. The analysis methodologies follow the guidance in Regulatory Guide 1.190 (Reference 2). It is also consistent with the methodology described in WCAP-18124-NP-A (Reference 4) that was generically approved by the United States Nuclear Regulatory Commission (USNRC) for calculating exposures of the RPV beltline (i.e., in general, RPV materials opposite the active fuel). See Section 2 for more details.

Pressurized Thermal Shock All of the beltline and extended beltline materials in the VCSNS Unit 1 RV are projected to remain below the RTPTs screening criteria values of 270°F for base metal and/or longitudinal welds and 300°F for circumferentially oriented welds (per 10 CFR 50.61) through SPEO (72 EFPY). See Section 4 for more details.

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• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 viii Upper-Shelf Energy All of the beltline and extended beltline materials in the VCSNS Unit 1 RV are projected to remain above the upper-shelf energy (USE) screening criterion value of 50 ft-lb (per 10 CFR 50, Appendix G), through SPEO (72 EFPY). See Section 5 for more details.

Adjusted Reference Temperatures and P-T Limit Curves Applicability Check Adjusted Reference Temperatures (ARTs) are calculated for the end of PEO at 56 EFPY and for the end of SPEO at 72 EFPY in order to perfonn an applicability check on the existing pressure-temperature (P-T) limit curves for VCSNS Unit 1. With the consideration of TLAA fluence projections, revised Position 2.1 chemistry factor values, and recalculated initial RTNoT values, the applicability of the VCSNS Unit I cylindrical shell P-T limit curves currently in the Technical Specifications remain applicable through 72 EFPY. The conclusion considers the RV inlet/outlet nozzles.

Surveillance Capsule Withdrawal Schedule With consideration of a 20-year license renewal to 80 years of operation (72 EFPY), Capsule Y, which currently resides in the spent fuel pool, must be reinserted for additional irradiation. The surveillance capsule withdrawal schedule in Table 7-1 identifies the additional exposure required by the capsule in order to meet the guidance of NUREG-2191 (Reference 18) (GALL-SLR) for a capsule to be withdrawn and tested between one and two times the peak RV wall neutron fluence at the end of SPEO. See Section 7 for more details.

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• - This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 1-1 1 TIME-LIMITED AGING ANALYSIS Time-Limited Aging Analyses (TLAAs) are those licensee calculations that:

1. Involve systems, structures, and components (SSCs) within the scope oflicense renewal

2. Consider the effects of aging.

3. Involve time-limited assumptions defined by the current operating term (e.g., 60 years).

4. Were determined to be relevant by the licensee in making a safety determination.

5. Involve conclusions or provide the basis for conclusions related to the capability of the SSC to perform its intended functions.

6. Are contained or incorporated by reference in the current licensing basis (CLB).

The potential TLAAs for the reactor pressure vessel (RPV) are identified in Table 1-1 along with indication of whether or not they meet the six ( 6) criteria of 10 CFR 54 .3 (Reference 1) for TLAAs.

Table 1-1 Evaluation of Time-Limited Aging Analyses Per the Criteria of 10 CFR 54.3 Pressure- Low Pressurized Calculated Upper-Shelf Temperature Temperature Time-Limited Aging Analysis Thermal Fluence Energy Limits for Heatup Overpressure Shock<a) and Cooldown Protection Involves SSC Within the Scope of YES YES YES YES YES License Renewal Considers the Effects of Aging YES YES YES YES YES Involves Time-Limited I Assumptions Defined by the Current Operating Term YES YES YES YES YES Determined to be Relevant by the I Licensee in Making a Safety Determination YES YES YES YES YES Involves Conclusions or Provides the Basis for Conclusions Related I to the Capability of SSC to YES YES YES YES YES Perform Its Intended Function Contained or Incorporated by I Reference in the CLB YES YES YES YES YES Note:

(a) The limiting Pressurized Thermal Shock (PTS) values are used to determine the appropriate Emergency Response Guideline (ERG) Limits category for VCSNS Unit I through the end of the potential subsequent license extension period. However, ERG limits are outside the scope of 10 CFR Part 54.3. ERG limits are discussed in Appendix B.

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""* This record was final approved on 6/21/2023, 3:51:49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-1 2 CALCULATEDFLUENCE Estimated RPV beltline and extended beltline fast neutron (E > 1.0 Me V) fluences at the end of 80 years of operation were calculated for VCSNS Unit 1 in WCAP-18709-NP. The analyses methodologies used to calculate the VCSNS Unit 1 RPV fluences followed the guidance of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" (Reference 2). These methodologies have been approved by the USNRC for the beltline region, i.e., materials directly surrounding the core and adjacent materials per 10 CFR 50, Appendix G (Reference 3), which are projected to experience the highest fluence. The methodologies, along with the NRC safety evaluation, are contained in detail in WCAP-18124-NP-A (Reference 4). For VCSNS Unit 1, the beltline region has traditionally included the intermediate and lower shell forgings, and the circumferential welds between these components. The traditional beltline and extended beltline materials are identified in Table 2-2 and Figure 2-1.

Materials exceeding a fast neutron (E > 1.0 MeV) fluence of 1.0 x 10 17 n/cm 2 at the end of the SPEO are evaluated for changes in fracture toughness. RPV materials that are not traditionally plant-limiting because of low levels of neutron radiation must now be evaluated to determine the accumulated fluence at the end ofSPEO. Therefore, fast neutron (E > 1.0 Me V) fluence calculations were performed for the VCSNS Unit 1 RPV to determine where it will exceed a fast neutron (E > 1.0 MeV) fluence of 1.0 x 10 17 n/cm 2 at the end ofSPEO. The materials that exceed the 1.0 x 10 17 n/cm 2 fast neutron (E > 1.0 MeV) fluence threshold and were not evaluated in past analyses ofrecord as part of the traditional beltline, are referred to as extended beltline materials in this report and are evaluated to determine the effect of neutron irradiation embrittlement during SPEO.

All the transport calculations were carried out using the three-dimensional discrete ordinates code RAPTOR-M3G and the BUGLE-96 cross-section library. The BUGLE-96 library provides a 67-group coupled neutron-gamma ray cross-section data set produced specifically for light water reactor applications.

In these analyses, anisotropic scattering was treated with a P3 Legendre expansion and the angular discretization was modeled with an S16 order of angular quadrature. Energy- and space-dependent core power distributions, as well as system operating temperatures, were treated on a fuel-cycle-specific basis.

The calculations for fuel Cycles 1 through 26 determine the neutron exposure of the pressure vessel and surveillance capsules based on completed fuel cycles. The projection for Cycle 27 is based on the actual loading, but yet to be completed, fuel cycle. The projections for Cycle 28 and beyond, up to and including the end of PEO (56 EFPY) and the end of SPEO (72 EFPY), are based on the average core power distributions and reactor operating conditions of Cycles 25, 26, and 27 and are determined both with and without a 10% positive bias on the peripheral and re-entrant comer assembly relative powers.

Table 2-1 gives the VCSNS Unit 1 calculated fast neutron (E > 1.0 Me V) fluences at the capsule locations including all withdrawn surveillance capsules (Capsules U, V, X, W, Y, and Z).

Table 2-2 presents the fast neutron (E > 1.0 Me V) fluence results for the applicable portions of the pressure vessel from the neutron transport analyses. From Table 2-2 it is observed that outlet nozzles and inlet nozzles have fast neutron (E > 1.0 MeV) fluence greater than 1.0 x 10 17 n/cm2 at the lowest extent of the nozzle forging to nozzle shell weld at 72 EFPY. All materials located above the nozzles will remain below 1.0 x 10 17 n/cm 2 through 72 EFPY. Table 2-2 indicates that the lower shell to lower vessel head WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-2 circumferential weld, and all materials below it, will remain below 1.0 x 10 17 n/cm 2 through SPEO. Figure 2-1 shows the axial boundary of the 1.0 x 10 17 n/cm2 fluence threshold (at 54 EFPY and 72 EFPY) as a function of azimuthal position (Z versus 0).

All data presented in this section, along with additional details, are presented in WCAP-18709-NP (Reference 5). This includes description of uncertainties and validation of the analytical model based on the measured plant dosimetry.

Table 2-1 Calculated Fast Neutron (E > 1.0 MeV) Fluence at the Surveillance Capsule Center for VCSNS Unit 1<a)

Cumulative Fluence Cycle Operating (n/cm 2)

Cycle Length Time (EFPY) 17° 20° (EFPY) 1 1.13 1.13 6.75E+l8(b) 5.90E+18 2 0.67 1.80 l.01E+l9 8.94E+l8 3 1.13 2.93 l.54E+ 19<cl l.36E+19 4 1.16 4.09 2.03E+19 l.80E+19 5 0.95 5.04 2.51E+19(d) 2.24E+l9 6 1.17 6.21 3.13E+19 2.79E+l9 7 1.22 7.43 3.63E+19 3.24E+l9 8 1.19 8.61 4.13E+l9 3.69E+ 19 9 1.27 9.89 4.66E+19 4.15E+l9 10 1.32 11.21 5.18E+19 4.63E+ 19<*l 11 1.36 12.56 5.78E+l9 5.15E+l9 12 1.37 13.94 6.35E+19 5.66E+l9 13 1.09 15.03 6.76E+19 6.02E+l9 14 1.33 16.36 7.34E+l9 6.53E+ 19<t) 15 1.35 17.71 7.88E+ 19 7.01E+l9(g) 16 1.34 19.05 8.42E+l9 7.49E+l9 17 1.38 20.43 9.00E+19 8.0IE+l9 18 1.30 21.73 9.52E+19 8.49E+19 19 1.31 23.04 l.01E+20 8.97E+l9 20 1.36 24.41 1.06E+20 9.46E+l9 21 1.29 25.70 l.11E+20 9.93E+l9 22 1.29 26.99 l.17E+20 l.04E+20 23 1.34 28.33 1.23E+20 1.09E+20 24 1.32 29.65 l.28E+20 l.14E+20 25 1.36 31.01 1.34E+20 l.19E+20 26 1.37 32.38 l.39E+20 l.24E+20 27(h) 1.37 33.75 l.45E+20 l.30E+20 No bias on the peripheral and re-entrant corner assembly relative powers Future<i) -- 36.00 l.55E+20 l.38E+20 Future(il -- 42.00 l.80E+20 l.61E+20 Future<i) -- 48.00 2.05E+20 1.83E+20 WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (fhis statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-3 Table2-1 Calculated Fast Neutron (E > 1.0 MeV) Fluence at the Surveillance Capsule Center for VCSNS Unit 1(a)

Cumulative Fluence Cycle Cycle Operating (n/cm2)

Length Time (EFPY) 17° 200 (EFPY)

Future<i) -- 54.00 2.30E+20 2.06E+20 Future<il -- 60.00 2.55E+20 2.28E+20 Future<il -- 66.00 2.80E+20 2.51E+20 Future<i) -- 72.00 3.05E+20 2.73E+20

+ 10% bias on the peripheral and re-entrant corner assembly relative Future<il -- 36.00 l.56E+20 l.39E+20 Future<i) -- 42.00 l.83E+20 l.64E+20 Future<il -- 48.00 2.l 1E+20 l.88E+20 Future(i) -- 54.00 2.38E+20 2.13E+20 FutureCi) -- 60.00 2.66E+20 2.38E+20 Future<il -- 66.00 2.93E+20 2.63E+20 FutureCil -- 72.00 3.21E+20 2.87E+20 Notes:

(a) Information taken from WCAP-18709-NP (Reference 5).

(b) This value is applicable to Capsule U.

(c) This value is applicable to Capsule V

( d) This value is applicable to Capsule X.

(e) This value is applicable to Capsule W.

(t) This value is applicable to Capsule Z.

(g) This value is applicable to Capsule Y.

(h) Cycle 27 was the current operating cycle at the time this summary report was authored.

(i) Values beyond Cycle 27 are based on the average core power distributions and reactor operating conditions of Cycles 25, 26, and 27 and are determined both with and without a 1.1 bias on the peripheral and re-entrant comer assembly relative powers.

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• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-4 Table2-2 VCSNS Unit 1- Maximum Fast Neutron (E > 1.0 MeV) Fluence Experienced by the Pressure Vessel Materials in the Beltline and Extended Beltline Regions Projections with no bias on the peripheral and re-entrant corner assembly relative powers Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Material Location Material 33.75 EFPY<al 36EFPY 42EFPY 48EFPY 54EFPY 60EFPY 66EFPY 72EFPY Inlet Nozzle to Nozzle Shell Weld l.41E+l7 l.50E+17 1.75E+17 2.00E+l7 2.24E+l7 2.49E+l7 2.74E+l7 2.99E+l7 (lowest extent)

Inlet Nozzle Postulated 3.58E+ I6(d) l.68E+16 1.79E+16 2.09E+16 2.39E+16 2.68E+16 2.98E+l6 3.28E+l6 1/4TF!aw Outlet Nozzle to Nozzle Extended Beltline Shell Weld 5.99E+16 6.39E+16 7.44E+l6 8.49E+l6 9.55E+l6 l.06E+17 l.17E+l7 l.27E+17 Materials (lowest extent)

Outlet Nozzle Postulated l.82E+ J 6(d) 8.54E+15 9.11E+15 1.06E+16 1.21E+16 l.37E+16 1.52E+l6 l.67E+16 l/4TF1aw Nozzle SheU(b) l.83E+18 l.95E+18 2.26E+18 2.58E+18 2.89E+18 3.20E+18 3.52E+l8 3.83E+18 Nozzle-to-Intermediate l.94E+18 2.07E+18 2.40E+l8 2.74E+l8 3.07E+18 3.40E+18 3.74E+18 4.07E+18 Shell Circumferential Weld Intermediate Shell 4.14E+19 4.40E+19 5.10E+l9 5.81£+19 6.51£+19 7.21E+19 7.92E+19 8.62E+19 Intermediate Shell Longitudinal Weld l.40E+19 l.49E+l9 1.72E+l9 l.96E+l9 2.19E+19 2.42E+19 2.66E+l9 2.89E+l9 45°/225° Beltline Materials Intermediate-to-Lower Shell 4.13E+l9 4.40E+19 5.10E+19 5.80E+19 6.51E+l9 7.21E+l9 7.91E+l9 8.62E+l9 Circumferential Weld Lower Shell 4.14E+19 4.40E+l9 5.11E+l9 5.81E+19 6.52E+19 7.23E+19 7.93E+l9 8.64E+19 Lower Shell Longitudinal l.42E+19 l.51E+l9 l.75E+ 19 l.98E+19 2.22E+19 2.46E+l9 2.70E+l9 2.93E+l9 Weld 135°/315° 9.86E+l5 Lower Shell to Bottom Outside of beltline Head Circumferential 4.69E+15 5.00E+l5 5.81E+l5 6.62E+15 7.43E+15 8.24E+l5 9.05E+15 region Weld(c)

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• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-5 Table 2-2 VCSNS Unit 1 Maximum Fast Neutron (E > 1.0 MeV) Fluence Experienced by the Pressure Vessel Materials in the Beltline and Extended Beltline Regions Projections with a + 10% bias on the peripheral, and re-entrant corner assembly relative powers Fast Neutron (E > 1.0 MeV) Fluence (n/cm 2)

Material Location Material 33.75 EFPY(al 36EFPY 42EFPY 48EFPY 54EFPY 60 EFPY 66EFPY 72EFPY Inlet Nozzle to Nozzle Shell 1.41E+l7 1.51E+l7 l.77E+ 17 2.04E+17 2.30E+17 2.57E+l7 2.83E+l7 3.10E+l7 Weld (lowest extent)

Inlet Nozzle Postulated 3.69E+J6(d) 1.68E+l6 1.80E+l6 2.11E+l6 2.43E+ 16 2.74E+l6 3.06E+16 3.38E+l6 l/4TFlaw Outlet Nozzle to Nozzle Extended Beltline Shell Weld 5.99E+16 6.42E+l6 7.54E+l6 8.66E+l6 9.79E+16 1.09E+l7 l.20E+l7 1.32E+l7 Materials (lowest extent)

Outlet Nozzle Postulated 1.88E+ J6(d) 8.54E+l5 9.14E+l5 l.07E+16 l.24E+16 l.40E+16 1.56E+l6 1.72E+ 16 l/4TF1aw Nozzle ShelJ(h) l.83E+l8 l.96E+18 2.30E+l8 2.64E+l8 2.98E+18 3.32E+18 3.66E+18 4.00E+l8 Nozzle-to-Intermediate l.94E+18 2.08E+l8 2.44E+l8 2.80E+l8 3.16E+l8 3.52E+l8 3.89E+l8 4.25E+18 Shell Circumferential Weld Intennediate Shell 4.14E+19 4.42E+l9 5.19E+19 5.96E+19 6.73E+19 7.50E+19 8.27E+19 9.04E+l9 Intermediate Shell Longitudinal Weld l.40E+l9 1.50E+19 1.75E+ 19 2.01E+19 2.26E+l9 2.52E+19 2.78E+l9 3.03E+19 45°/225° Beltline Materials Intermediate-to-Lower Shell 4.13E+19 4.42E+19 5.19E+l9 5.96E+l9 6.73E+l9 7.50E+19 8.27E+l9 9.04E+I9 Circumferential Weld Lower Shell 4.14E+l9 4.42E+l9 5.20E+19 5.97E+19 6.74E+19 7.52E+19 8.29E+19 9.06E+19 Lower Shell Longitudinal l.42E+ 19 1.52E+19 l.78E+l9 2.04E+19 2.30E+l9 2.56E+l9 2.82E+l9 3.08E+l9 Weld 135°/315° Lower Shell to Bottom Outside of beltline Head Circumferential 4.69E+l5 5.03E+l5 5.91E+15 6.79E+l5 7.67E+l5 8.55E+15 9.44E+l5 l.03E+16 region Weld<cJ Notes:

(a) Value listed is the projected EFPY at the end of Cycle 27.

(b) Exposure values for the nozzle shell longitudinal welds are bounded by the exposure values for the nozzle shell (a.k.a. upper shell).

(c) Maximum exposure values occur at the RPV outer radius.

( d) While the fluence at this location is less than IE+ 17 n/cm2, it is identified as extended beltline since portions of the nozzle exceed the criterion.

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• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-6

--33]5 EFP,Y (EOC 27) ----* 54 EFPY --72EFPY*

o Nozzle-Postulated 1/4T Flaw x Nozzle Lowest \Veld Extent Nozzle- Shell Circ_ Weld (Heat'No_ 4 200

~---------

~

.r Intermediate 'Shell Intermediate S"neEl 100 (HeatNo. A9154-1) (Heat No. A9153~2)

a l'l 0

"j*

0 iii

--~*

i,il'

>I

• Lo\'.\'l!r *shell Lowei;Shcll

-100 (Heat No. C9923-1) (Heat No. CS-923-2)

-200 90 .135 180 315 360 Azimuthal_ Locatio!l [degree1 Figure 2-1 Axial Boundary of the 1.0E+l7 n/cm 2 Fast Neutron (E > 1.0 MeV) Fluence Threshold in the +Z Direction at 33. 75 ( end of Cycle 27), 54, and 72 EFPY WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6121/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 3-1 3 MATERIAL PROPERTY INPUT The requirements for RV integrity are specified in 10 CPR 50, Appendix G (Reference 3) and 10 CPR 50.61 (Reference 6). The beltline region of the RV is defined as the following in 10 CPR 50, Appendix G:

... the region of the reactor vessel (shell material including welds, heat affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection ofthe most limiting material with regard to radiation damage.

The VCSNS Unit 1 beltline materials consist of two (2) Intermediate Shell Plates, two (2) Lower Shell Plates, and their associated welds. The VCSNS Unit 1 surveillance plate material was made from RV Intermediate Shell Plate 11-1, Heat# A9154-1. The VCSNS Unit 1 RV beltline welds were fabricated using weld wire Heat# 4P4784, Flux Type Linde 124, Flux Lot# 3930. The weld material in the VCSNS Unit 1 surveillance program was fabricated with the same material heat, flux type, and flux lot number.

Any RV materials that are predicted to experience a neutron fluence exposure greater than 1.0 x 10 17 n/cm 2 (E > 1.0 Me V) at the end of the licensed operating period should be considered to experience neutron embrittlement. Based on the results of Section 2 of this report, the materials that exceeded the 1 x 10 17 n/cm 2 (E > 1.0 MeV) threshold at 72 EFPY that were not included within the original beltline are considered to be the VCSNS Unit 1 extended beltline materials and are evaluated to determine their impact on the proposed SPEO of operation. The VCSNS Unit 1 RV extended beltline contains one (1) Nozzle Shell-to-Intennediate Shell circumferential weld, two (2) Nozzle Shell Plates (also termed upper shell), two (2)

Nozzle Shell longitudinal welds, three (3) Inlet Nozzles, three (3) Outlet Nozzles, and the six (6) Nozzle-to-Nozzle Shell welds. Only those materials with a fluence greater than 1 x 10 17 n/cm 2 (E > 1.0 MeV) at the end of SPEO require the effects of embrittlement to be included when evaluating the RV integrity.

The RV forgings/plates and weld materials are shown in Figure 3-1 for VCSNS Unit 1. Used in conjunction with the fluence data in Table 2-2, and Figure 2-1, the beltline and extended beltline materials are identified as shown in Table 3-1. Note that for RV welds, the terms "girth" and "circumferential" are used interchangeably; herein, these welds shall be referred to as circumferential welds. Similarly, for RV welds, the tenns "axial" and "longitudinal" are used interchangeably; herein, these welds shall be referred to as longitudinal welds.

The unirradiated material property inputs used for the RV integrity evaluations herein are contained in PWROG-21037-NP (Reference 7). PWROG-21037-NP defined or redefined many of the material properties and chemistry values using the most up-to-date methodologies and all available data; therefore, the values utilized herein supersede previously documented values. The sources and methods used in the determination of the chemistry factors and the fracture toughness properties are summarized below.

Chemical Compositions The best-estimate copper (Cu) and nickel (Ni) chemical compositions for the VCSNS Unit 1 beltline and extended beltline materials are presented in Table 3-1. The best-estimate weight percent copper and nickel WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 3-2 values for the beltline and extended beltline materials were previously reported in PWROG-21037-NP and were included in RV integrity evaluations as part of this TLAA effort.

Fracture Toughness Properties The most up-to-date initial RTNnT and initial USE values are documented in PWROG-21037-NP for VCSNS Unit 1. The beltline and extended beltline material properties of the VCSNS Unit 1 RV are presented in Table 3-1 herein. The differences between the unirradiated RTNDT values summarized in the FSAR and those determined herein are a result of a change in curve-fitting method (hand-drawn versus hyperbolic tangent) used to fit the Charpy V-notch test data.

Chemistry Factor Values The chemistry factor (CF) values were calculated using Positions 1.1 and 2.1 of Regulatory Guide 1.99, Revision 2 (Reference 8). Position 1.1 uses Tables 1 and 2 from the Regulatory Guide along with the best-estimate copper and nickel weight percent values (contained in Table 3-1 ). Position 2.1 uses the surveillance capsule data from all capsules tested to date and surveillance data from other plants, as applicable.

Credibility evaluations of the VCSNS Unit 1 surveillance data are provided in Appendix A of this report.

The calculated capsule fluence values are provided in Table 2-1 and are used to determine the Position 2.1 CFs as shown in Table 3-2. Table 3-3 summarizes the Positions 1.1 and 2.1 CF values determined for the VCSNS Unit 1 RPV beltline and extended beltline materials.

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Westinghouse Non-Proprietary Class 3 3-3 I--Represents Vessel Welds 16--

t13S"')

Lower Shell 17 -

(315")

Figure 3-1 RPV Schematic for VCSNS Unit 1 WCAP-18728-NP June 2023 Revision 5

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Westinghouse Non-Proprietary Class 3 3-4 Table 3-1 Best-Estimate Cu and Ni Weight Percent Values, Initial RTNoT Values, and Initial USE Values for the VCSNS Unit 1 RPV Beltline and Extended Beltline Materials(a)

Initial Unirradiated (JJ Material Identification Wt. %Cu Wt. %Ni RTNDT USE (OF)

(OF) (ft-lb)

Beltline Intermediate Shell 11-1 (Heat# A9154-l) 0.10 0.51 21 0 76 Intermediate Shell 11-2 (Heat# A9153-2) 0.09 0.45 -20 0 107 Lower Shell I 0-1 (Heat # C9923- l) 0.08 0.41 5 0 106 Lower Shell 10-2 (Heat# C9923-2) 0.08 0.41 4 0 92 Intermediate Shell Long. Weld Seams BC & BD (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Intermediate to Lower Shell Circ. Weld Seam AB 0.05 0.91 -49 0 86 (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Lower Shell Long. Weld Seams BA & BB (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Extended Beltline Nozzle Shell 12-1 (Heat# C9955-2) 0.13 0.57 9 0 101 Nozzle Shell 12-2 (Heat# C0123-2) 0.12 0.58 15 0 91 Inlet Nozzle 436B-1 (Heat# Q2Q4 l W) o.127(bJ 0.76 -20 0 152 Inlet Nozzle 4368-2 (Heat # Q2Q39W) 0.127(b) 0.82 0 0 115 Inlet Nozzle 4368-3 (Heat# Q2Q39W) 0.127(b) 0.82 -20 0 138 Outlet Nozzle 437B-1 (Heat# Q2Q40) 0.127(b) 0.85 -10 0 159 Outlet Nozzle 437B-2 (Heat# Q2Q40W) 0.127(b) 0.80 -10 0 165 Outlet Nozzle 437B-3 (Heat# Q2Q44W) 0.127(b) 0.78 0 0 155 Nozzle to Intermediate Shell Circ. Weld Seam AC 0.05 0.91 -49 0 86 (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

Nozzle Shell Long. Weld Seams BE and BF(c) 0.06(c) 1.01 (c) lQ(c) o(c) so<c)

Inlet/Outlet Nozzle Forgings to Nozzle Shell Weld Seams 15A/8/C & 16A/BfC(c)

Surveillance MateriaJCdJ Intermediate Shell 11-1 (Heat# A9154-l) - - - - -

Surveillance Weld (Heat# 4P4784, Flux Type Linde 124, Lot# 3930) 0.04 0.95 - - -

Notes:

(a) The information is extracted from PWROG-21037-NP (Reference 7). All values are based on information extracted from the V.C.

Summer Unit 1 CMTRs and/or vessel fabrication records, unless noted otherwise.

(b) Generic value for SA-508 Class 2 nozzle forgings from PWROG-15109-NP-A (Reference 9).

(c) The specific heat number used in weld seams could not be identified. To address these situations, values were determine based on a review of all V.C. Summer weld heats used in the fabrication of the VCSNS Unit 1 RV. These generic values were defmed in PWROG-21037-NP (Reference 7).

(d) Surveillance plate and weld data identified in WCAP-16298-NP (Reference 10).

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Westinghouse Non-Proprietary Class 3 3-5 Table 3-2 Calculation of Position 2.1 CF Values for VCSNS Unit 1 Surveillance Materials Capsule FluenceCa) Measured Material Capsule FF(b) ARTr,l}T(c) FF*ARTNDT FF2 (x 10 19 n/cm2, {°F)

{°F)

E> 1.0 MeV) u 0.675 0.890 36.1 32.1 0.792 V 1.54 1.119 53.2 59.6 1.253 Intermediate Shell 11-1 X 2.51 1.247 38.3 47.8 1.555 (Longitudinal) w 4.63 1.387 66.2 91.8 1.924 z 6.53 1.451 98.9 143.5 2.106 u 0.675 0.890 14.5 12.9 0.792 V 1.54 1.119 32.1 35.9 1.253 X 2.51 1.247 26.7 33.3 1.555 Intermediate Shell 11-1 (Transverse) w 4.63 1.387 57.8 80.2 1.924 z 6.53 1.451 87.0 126.3 2.106 SUM: 663.4 15.261 CF 11-1 = I:(FF

• LiRTNm) + l:(FF ) 2 (663.4) + (15.261) = 43.5°F 28.6 u 0.675 0.890 (22.7) 25.4 0.792 59.2 V 1.54 1.119 (47.0) 66.3 1.253 28.6 X 2.51 1.247 (22.7) 35.7 1.555 Surveillance Weld (Heat #4P4784) 54.8 w 4.63 1.387 (43.5) 76.0 1.924 82.2 z 6.53 1.451 (65.2) l 19.2 2.106 SUM: 322.7 7.630 CFsurv. Weld

• LiRT1'.m) :E(FF2) = (322.7) + (7.630) = 42.3°F Notes:

(a) Fluence taken from Table 2-1.

(b) FF fluence factor f(0-2s-o.w1og(l))_

(c) Measured LiRTNDT taken from WCAP-16298-NP (Reference 10). The VCSNS Unit 1 surveillance weld measured ~RTNDT results have been adjusted by a ratio of 1.26 to account for chemistry differences between the Heat# 4P4784 surveillance weld (CF 54°F) and RV welds (CF= 68°F). The unadjusted measured ~RTNDT values are listed in parentheses.

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Westinghouse Non-Proprietary Class 3 3-6 Table 3-3 Summary of the VCSNS Unit 1 RPV Beltline, Extended Beltline, and Surveillance Material CF Values based on Regulatory Guide 1.99, Revision 2, Position 1.1 and Position 2.1 Chemistry Factor Material Description Position 1.1 <*J Position 2.1 (b)

(OF) (OF)

Beltline Intermediate Shell 11-1 (Heat#A9154-1) 65.0 43.5 Intermediate Shell 11-2 (Heat# A9153-2) 58.0 -

Lower Shell 10-1 <Heat # C9923- l) 51.0 "

Lower Shell 10-2 (Heat # C9923-2) 51.0 -

Intermediate Shell Long. Weld Seams BC & BD 68.0 42.3 (Heat# 4P4784)

Intermediate to Lower Shell Circ. Weld Seam AB 68.0 42.3 (Heat# 4P4784)

Lower Shell Long. Weld Seams BA & BB 68.0 42.3 (Heat# 4P4784)

Extended Beltline Nozzle Shell 12-1 (Heat# C9955-2) 90.1 -

Nozzle Shell 12-2 (Heat# C0123-2) 82.6 -

Inlet Nozzle 436B-1 meat# 02041 W) 92.1 -

Inlet Nozzle 436B-2 <Heat# Q2O39W) 93.0 "

Inlet Nozzle 436B-3 <Heat # O2O39W) 93.0 -

Outlet Nozzle 437B-1 (Heat# 02040) 93.0 -

Outlet Nozzle 437B-2 (Heat# O2O40W) 93.0 -

Outlet Nozzle 437B-3 £Heat# O2O44W) 92.6 -

Nozzle to Intermediate Shell Circ. Weld Seam AC 68.0 42.3 (Heat# 4P4784)

Nozzle Shell Long. Weld Seams BE and BF 82.0 -

Inlet/Outlet Nozzle Forgings to Nozzle Shell Weld Seams 15A/B/C & 16A/B/C 82.0 -

Surveillance Materials Intermediate Shell 11-1 65.0 -

Surveillance Weld (Heat# 4P4784) 54.0 -

Notes:

(a) All values are based on Tables 1 and 2 of Regulatory Guide 1.99, Revision 2 (Position 1. 1) using the Cu and Ni weight percent values given in Table 3-1 of this report. Dashes indicate when a category is not applicable to the material.

(b) Values are from Table 3-2 of this report.

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Westinghouse Non-Proprietary Class 3 4-1 4 PRESSURIZED THERMAL SHOCK A limiting condition on RPV integrity known as Pressurized Thermal Shock (PTS) may occur during a severe system transient such as a loss-of-coolant accident (LOCA) or steam line break. Such transients may challenge the integrity of the RPV under the following conditions: severe overcooling of the inside surface of the vessel wall followed by high pressurization, significant degradation of vessel material toughness caused by radiation embrittlement, and the presence of a critical-size defect anywhere within the vessel wall.

In 1985, the USNRC issued a formal ruling on PTS (10 CFR 50.61 [Reference 6]) that established screening criteria on pressurized water reactor (PWR) vessel embrittlement, as measured by the maximum reference nil-ductility transition temperature in the limiting beltline component at the end of license, termed RT PTS, RTPTs screening values were set by the USNRC for beltline axial welds, forgings or plates, and for beltline circumferential weld seams for plant operation to the end of plant license. All domestic PWR vessels have been required to evaluate vessel embrittlement in accordance with the criteria through the end of license.

The USNRC revised 10 CFR 50.61 in 1991 and 1995 to change the procedure for calculating radiation embrittlement. These revisions make the procedure for calculating the reference temperature for pressurized thermal shock (RTPTs) values consistent with the methods given in Regulatory Guide 1.99, Revision 2 (Reference 8).

These accepted methods were used with the surface fluence values of Section 2 to calculate the following RTPTs values for the VCSNS Unit 1 RPV materials. The end of SPEO RTPTs calculations are presented in Table 4-1.

PTS Conclusion All of the beltline and extended beltline materials in the VCSNS Unit 1 RV are below the RTPTs screening criteria values of270°F for base metal and/or longitudinal welds, and 300°F for circumferentially oriented welds through SPEO (72 EFPY). These RTPTS values are based on the revised initial RT NDT values in PWROG-21037-NP (Reference 7), which are developed using ASME Section III (Reference 11) and, if needed, NUREG-0800, BTP 5-3 (Reference 12) methodologies. Limiting fluence values corresponding to the lowest extent of the nozzle welds were used to calculate the RTPTs values for both the nozzle welds and nozzle forgings.

The VCSNS Unit I limiting RTPTs value for base metal and longitudinal welds at 72 EFPY is 152.5°F (see Table 4-1 ), which corresponds to VCSNS Unit 1 Intermediate Shell 11 - 1 based on Regulatory Guide 1.99, Position 1.1. Note, that there is surveillance data available for this material that indicated the LiRTNDT will be less than that predicted by RG 1.99, Position 1. 1. However, because the surveillance data was determined to be non-conservative, it is not credited here. The VCSNS Unit 1 limiting RTPTS value for circumferentially oriented welds at 72 EFPY is 42.5°F (see Table 4-1 ), which corresponds to the VCSNS Unit 1 Intermediate to Lower Shell Circumferential Weld Heat# 4P4784 based on Regulatory Guide 1.99, Position 2.1 with credible surveillance data. The credible surveillance data for Heat # 4P4784 supersedes the higher RT PTs based on RG 1.99, Position 1.1. Note, both the Position 1.1 and 2.1 remain below 300°F.

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Westinghouse Non-Proprietary Class 3 Table 4-1 RTPTs Calculations for VCSNS Unit 1 at 72 EFPY(a)

R.G. Surf. Fluence Predicted 1.99, Surf. RT!'.'DT(U) Ol O'LI. M ART Material CF(bl (x 1019 n/cm2 , 11.RTNDT Rev.2 FF(d) {°F) {°F) {°F)<O {°F) {°F)

E > 1.0MeV)<c) (OF)<*l Position Beltline Materials Intennediate Shell 11-1 (Heat# A9 l 54- l) 1.1 65.0 9.04 1.501 21 97.5 0.0 17.0 34.0 152.5 Using non-credible surveillance data(g) 2.1 43.5 9.04 1.501 21 65.3 0.0 17.0 34.0 120.3 Intennediate Shell 11-2 (Heat# A9153-2) 1.1 58.0 9.04 1.501 -20 87.0 0.0 17.0 34.0 101.0 Lower Shell 10-1 (Heat # C9923-1) 1.1 51.0 9.06 1.501 5 76.6 0.0 17.0 34.0 115.6 Lower Shell 10-2 (Heat# C9923-2) 1.1 51.0 9.06 1.501 4 76.6 0.0 17.0 34.0 114.6 Intermediate Shell Long. Weld Seams BC & BD 1.1 68.0 3.03 1.293 -49 87.9 0.0 28.0 56.0 94.9 (Heat# 4P4784)

Using credible surveillance data(g) 2.1 42.3 3.03 1.293 -49 54.7 0.0 14.0 28.0 33.7 Intermediate to Lower Shell Circ. Weld Seam AB (Heat#

1.1 68.0 9.04 1.501 -49 102.0 0.0 28.0 56.0 109.0 4P4784)

Using credible surveillance datcfg) 2.1 42.3 9.04 1.501 -49 63.5 0.0 14.0 28.0 42.5 Lower Shell Long. Weld Seams BA & BB 1.1 68.0 3.08 1.297 -49 88.2 0.0 28.0 56.0 95.2 (Heat# 4P4784)

Using credible surveillance data(g) 2.1 42.3 3.08 1.297 -49 54.9 0.0 14.0 28.0 33.9 Extended Beltline Materials Nozzle Shell 12-1 (Heat# C9955-2) 1.1 90.1 0.400 0.746 9 67.2 0.0 17.0 34.0 110.2 Nozzle Shell 12-2 (Heat# C0123-2) 1.1 82.6 0.400 0.746 15 61.6 0.0 17.0 34.0 110.6 Inlet Nozzle 43 6B- l (Heat # Q2Q4 l W) I.I 92.1 0.0310 0.224 -20 20.6 0.0 10.3 20.6 21.2 Inlet Nozzle 436B-2 (Heat# Q2Q39W) 1.1 93.0 0.0310 0.224 0 20.8 0.0 10.4 20.8 41.6 Inlet Nozzle 436B-3 (Heat# Q2Q39W) 1.1 93.0 0.0310 0.224 -20 20.8 0.0 10.4 20.8 21.6 Outlet Nozzle 437B-l (Heat# Q2Q40) 1.1 93.0 0.0132 0.132 -10 12.3 0.0 6.1 12.3 14.5 Outlet Nozzle 43 7B-2 (Heat# Q2Q40W) 1.1 93.0 0.0132 0.132 -10 12.3 0.0 6.1 12.3 14.5 Outlet Nozzle 437B-3 (Heat# Q2Q44W) 1.1 92.6 0.0132 0.132 0 12.2 0.0 6.1 12.2 24.4 Nozzle to Intermediate Shell Circ. Weld Seam AC 1.1 68.0 0.425 0.762 -49 51.8 0.0 25.9 51.8 54.7 (Heat# 4P4784)

Using credible surveillance data(g) 2.1 42.3 0.425 0.762 -49 32.2 0.0 14.0 28;0 11.2 Nozzle Shell Long. Weld Seams BE and BF 1.1 82.0 0.400 0.762 10 61.2 0.0 28.0 56.0 127.2 WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (fhis statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 4-3 Table 4-1 RTPTs Calculations forVCSNS Unit 1 at 72 EFPY(a)

R.G. Predicted Surf. Fluence 1.99, CF(b) Surf. RTNDT(U) O'I O'il. M ART Material (x 10 19 n/cm 2 , FF(d) ~RTNDT (OF)<f)

Rev.2 (OF) (OF) (OF) (OF)

E > 1.0MeV)<c) (°F)<*>

Position Inlet/Outlet Nozzle Forgings to Nozzle Shell Weld 1.1 82.0 0.0310 0.224 IO 18.4 0.0 9.2 18.4 46.7 Seams ISNB/C & 16A/B/C Notes:

(a) The IO CFR 50.61 methodology was utilized in the calculation of the RTPTs values.

(b) Chemistry factors are taken from Table 3-3.

(c) Fluence taken from Table 2-2 of this report.

(d) FF= fluence factor= :f(O.ZS-O.IO*Iog (t))_

(e) RTNDT(U) values taken from Table 3-1.

(f) Per IO CFR 50.61, the base metal at.= 17°F when surveillance data are non-credible or not used to determine the CF, and the base metal crt. = 8.5°F when credible surveillance data are used. Also, per IO CFR 50.61, the weld metal at.= 28°F when surveillance data are non-credible or not used to determine the CF, and the weld metal crt. = 14°F when credible surveillance data are used. However, crt. need not exceed 0.5*MTNDT for either base metals or welds, with or without surveillance data.

(g) The credibility evaluation for the VCSNS Unit 1 surveillance data in Appendix A of this report determined that the VCSNS Unit 1 surveillance data for the Intermediate Shell 11-1 (Heat# A9154-l) is deemed non-credible and the Surveillance Weld (Heat# 4P4784) is deemed credible.

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Westinghouse Non-Proprietary Class 3 5-1 5 UPPER-SHELF ENERGY The decrease in Charpy upper-shelf energy (USE) is associated with the determination of acceptable RPV toughness during the license renewal period when the vessel is exposed to additional irradiation.

The requirements on USE are included in 10 CPR 50, Appendix G (Reference 3). 10 CFR 50, Appendix G requires utilities to submit an analysis at least 3 years prior to the time that the USE of any RPV material is predicted to drop below 50 ft-lb, as measured by Chatpy V-notch specimen testing.

There are two methods that can be used to predict the decrease in USE with irradiation, depending on the availability of credible surveillance capsule data as defined in Regulatory Guide 1.99, Revision 2 (Reference 8). For vessel beltline materials that are not in the surveillance program or have non-credible data, the Charpy USE (Position 1.2) is assumed to decrease as a function offluence and copper content, as indicated in Regulatory Guide 1.99, Revision 2. When two or more credible surveillance sets become available from the reactor, they may be used to determine the Chatpy USE of the surveillance material. The surveillance data are then used in conjunction with the Regulatory Guide to predict the change in USE (Position 2.2) of the RPV material due to irradiation. Per Regulatory Guide 1.99, Revision 2, when credible data exist, the Position 2.2 projected USE value should be used in preference to the Position 1.2 projected USE value. Note, if data from the surveillance materials is determined to be non-credible for determination of ARTNDT by Credibility Criterion 3 of Regulatory Guide 1.99, Revision 2, then "they may be credible for determining decrease in upper-shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E 185-82."

The 72 EFPY Position 1.2 USE values of the vessel materials can be predicted using the corresponding 1/4T fluence projections, the copper content of the materials, and Figure 2 in Regulatory Guide 1.99, Revision 2 (see Figure 5-1).

The predicted Position 2.2 USE values are determined for the RV materials that are contained in the surveillance program by using the reduced plant surveillance data along with the corresponding 1/4T fluence projection. The surveillance data was plotted in Regulatory Guide 1.99, Revision 2, Figure 2 (see Figure 5-1) using the surveillance capsule fluence values documented in Table 2-1 of this report for VCSNS Unit 1. This data was fitted by drawing a line parallel to the existing lines as the upper bound of all the surveillance data. These reduced lines were used instead of the existing lines to determine the Position 2.2 end of SPEO USE values.

The projected USE values were calculated to determine if the VCSNS Unit 1 beltline and extended beltline materials remain above the 50 ft-lb criterion at 72 EFPY (end ofSPEO). These calculations are summarized in Table 5-1.

WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-2 USE Conclusion As shown in Table 5-1, all VCSNS Unit 1 RV materials are projected to remain at or above the USE screening criterion value of 50 ft-lb at 72 EFPY. The limiting USE value at 72 EFPY is 63 ft-lb (see Table 5-1 ); this value corresponds to Intermediate Shell 11-1 using Position 2.2. The surveillance data for Intermediate Shell 11-1 is used despite it being determined to be non-credible, as the upper shelf can be clearly determined for the surveillance specimens (see WCAP-16298-NP). Note, both the Position 1.2 and 2.2 results for Intermediate Shell 11-1 remain above 50 ft-lb.

WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-3 Table 5-1 Predicted USE Values at 72 EFPY for the VCSNS Unit 1 Beltline and Extended Beltline Materials Projected 1/4T Fluence Unirradiated Projected Material Wt%

(x 10 19 n/cm2, USE USE Cu(a) Decrease USE E > 1.0 MeV)(hJ (ft-lb)<*> (ft-lb)

(%)

Position l.2<cJ Intermediate Shell 11-1 (Heat# A9154-1) 0.10 5.68 76 29 54 Intermediate Shell 11-2 (Heat# A9153-2) 0.09 5.68 107 29 76 Lower Shell 10-1 (Heat# C9923-1) 0.08 5.69 106 29 75 Lower Shell 10-2 (Heat# C9923-2) 0.08 5.69 92 29 65 Intermediate Shell Long. Weld Seams BC 0.05 1.90 86 22 67

& BD (Heat# 4P4784)

Intermediate to Lower Shell Circ. Weld 0.05 5.68 86 29 61 Seam AB (Heat # 4P4784)

Lower Shell Long. Weld BA & BB 0.05 1.93 86 23 66 (Heat# 4P4784)

Nozzle Shell 12-1 (Heat# C9955-2) 0.13 0.251 101 17 84 Nozzle Shell 12-2 (Heat# C0123-2) 0.12 0.251 91 16 76 Inlet Nozzle 436B-1 (Heat# Q2Q4 l W) 0.127 0.0310(d) 152 10 137 Inlet Nozzle 436B-2 (Heat# Q2Q39W) 0.127 0.0310(d) 115 IO 104 Inlet Nozzle 436B-3 (Heat# Q2Q39W) 0.127 0.031Q(d) 138 10 124 Outlet Nozzle 43 7B-1 (Heat# Q2Q40) 0.127 0.0132(d) 159 9 145 Outlet Nozzle 437B-2 (Heat# Q2Q40W) 0.127 0.0132(d) 165 9 150 Outlet Nozzle 437B-3 (Heat# Q2Q44W) 0.127 0.0132(d) 155 9 141 Nozzle to Intermediate Shell Circ. Weld 0.05 0.267 86 14 74 Seam AC (Heat# 4P4784)

Nozzle Shell Long. Weld Seams BE & BF 0.06 0.251 80 15 68 Inlet/Outlet Nozzle Forgings to Nozzle 0.031Q(d) 0.06 80 9 73 Shell Weld Seams 15A/B/C & 16A/B/C Position 2.2<c)

Intermediate Shell 11-1 (Heat#A9154-1) 0.10 5.68 76 17 63 Intermediate Shell Long. Weld Seams BC 0.05 1.90 86 9 78

& BD (Heat# 4P4784)

Intermediate to Lower Shell Circ. Weld 0.05 5.68 86 12 76 Seam AB (Heat# 4P4784)

Lower Shell Long. Weld Seams BA & BB 0.05 1.93 86 9 78 (Heat# 4P4784)

Nozzle to Intermediate Shell Circ. Weld 0.05 0.267 86 6 81 Seam AC (Heat# 4P4784)

Notes contained on following page.

WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51:49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-4 Notes:

(a) Copper weight percent values and unirradiated USE values were taken from Table 3-1 of this report. If the base metal or weld Cu weight percentages are below the minimum value presented in Figure 2 of Reg Guide 1.99 (0.1 for base metal and 0.05 for welds),

then the Cu weight percentages were conservatively rounded up to the minimum value for projected USE decrease determination.

(b) Values taken from Table 6-2 of this report. Fluence values above 10 17 n/cm2 (E > 1.0 MeV) but below 2 x 10 17 n/cm2 (E > 1.0 MeV) were rounded to 2 x 10 17 n/cm2 (E > 1.0 MeV) when determining the% decrease because 2 x 10 17 n/cm2 is the lowest fluence displayed in Figure 2 ofRG 1.99.

(c) Position 1.2 percentage USE decrease values were calculated by plotting the l/4T fluence values on RG 1.99, Figure 2 and using the material-specific Cu w1. % values. The percent-loss lines were extended into the low fluence area ofRG 1.99, Figure 2, i.e.,

below 1018 n/cm2, in order to determine the USE % decrease, as needed. Position 2.2 percentage USE decrease values were determined by drawing an upper-bound line parallel to the existing RG 1.99, Figure 2 lines through the applicable surveillance data points. These results should be used in preference to the existing graph lines for determining the decrease in USE, because the surveillance data is credible.

(d) Values are the maximum fluence values instead of the 1/4T fluence values.

WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-5

% Copper BaseMetal ~

0.35 Inlet Nazzle Max Fluence and lnlet'Outlet Nozzle Forgings to Nozzle Shell Welds Max Fluence=

3.1 0E+17 nlcm 2 w

Cl)

.5 0.

e Cl 41

....Cg> 10.0 Id Heat#

G) 4784 Line

~

G) 0..

Intermediate Shell Long. Weld 114T Fluence = 1.90E+19 n/cm2 and LiJ,\/er Shell Long. Weld 1/4 T Fluence 1.93E+19 n/cm2 to Lower Shell Circ. Weld 1/4T Fluence= 5.68E+19 n/cm 2 and LowerShell 1/4T Fluence=

2 1.0 1.00E+17 1.00E+18 1.00E+19 1.00E+20 Neutron Fluence, n/cm 2 (E > 1 MeV)

Figure 5-1 Regulatory Guide 1.99, Revision 2, Position 1.2 & 2.2 Predicted Decrease in Upper-Shelf Energy as a Function of Copper and Fluence for VCSNS Unit 1 at the End of SPEO (72 EFPY)

WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-1 6 HEATUP AND COOLDOWN PRESSURE-TEMPERATURE LIMIT CURVES Heatup and cooldown limit curves are calculated using the most limiting value of RT NDT (reference nil-ductility transition temperature) corresponding to the limiting material in the beltline region of the RPV.

The most limiting RTNDT of the material in the core (beltline) region of the RPV is determined by using the unirradiated RPV material fracture toughness properties and estimating the irradiation-induced shift (ARTNDT).

6.1 ADJUSTED REFERENCE TEMPERATURES CALCULATION RTNDT increases as the material is exposed to fast-neutron irradiation; therefore, to find the most limiting RTNDT at any time period in the reactor's life, ~RTNDT due to the radiation exposure associated with that time period must be added to the original unirradiated RTl\m. Using the adjusted reference temperature (ART) values, pressure-temperature (P-T) limit curves are determined in accordance with the requirements of 10 CFR Part 50, Appendix G (Reference 3), as augmented by Appendix G to Section XI of the ASME Boiler and Pressure Vessel Code (Reference 13).

The P-T limit curves for normal heatup and cooldown of the primary reactor coolant system for VCSNS Unit 1 were previously developed in WCAP-16035-NP (Reference 14). The existing P-T limit curves are based on the limiting beltline material ART values, which are influenced by both the fluence and the initial material properties of that material. Since the development of the curves, the fluence values and initial material properties used to calculate ART values have been updated and an applicability check of the current P-T limit curves is appropriate.

To confirm whether or not the current P-T limit curves will remain valid through the PEO and through the SPEO, updated ART values for the limiting materials were computed to account for updated 56 EFPY and 72 EFPY fluence values, updated Chemistry Factor values, and updated initial RTNDT values. The Regulatory Guide 1.99, Revision 2 (Reference 8) methodology was used along with the surface fluence of Section 2 to calculate ART values, which are summarized in Table 6-3 through Table 6-8. Note, the inlet/outlet nozzle forgings and associated welds neglect attenuation through the material; thus, ART calculations are only needed at one location, i.e., the location of maximum fluence. Table 6-1 and Table 6-2 show the surface, 1/4T, and 3/4T fluence values for 56 EFPY and 72 EFPY, respectively.

ART projections contained herein are based on those projected fluence values with a 1.1 bias on the peripheral and re-entrant comer assembly relative powers.

WCAP-18728-NP June 2023 Revision 5

• "" This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-2 Table 6-1 VCSNS Unit 1 Fluence and Fluence Factor Values for the Surface, 1/4T, and 3/4T Locations at 56 EFPY Surface 1/4T Fluence<*l 3/4T Fluence<*l Fluence<*l Surface l/4T 3/4T Material Description FF(b) (x 10 19 n/cm 2, FF(b) (x 10 19 n/cm 2, FF(b)

(x 10 19 n/cm2, E>l.OMeV) E> 1.0MeV)

E>l.OMeV)

BelJline Intennediate Shell 11 -1 6.99 1.463 4.39 1.376 1.732 1.151 (Heat# A9154-1)

Intennediate Shell 11-2 6.99 1.463 4.39 1.376 1.732 1.151 (Heat# A9153-2)

Lower Shell 10-1 7.00 1.463 4.40 1.376 1.735 1.152 (Heat # C9923- l)

Lower Shell 10-2 7.00 1.463 4.40 1.376 1.735 1.152 (Heat# C9923-2)

Intermediate Shell Long. Weld 2.35 1.231 1.48 1.108 0.582 0.849 (Heat# 4P4784)

Intermediate to Lower Shell 6.99 1.463 4.39 1.376 1.732 1.151 Circ. Weld (Heat# 4P4784)

Lower Shell Long. Weld 2.39 1.235 1.50 1.112 0.592 0.853 (Heat# 4P4784)

Extended Beltline Nozzle Shell 12-1 0.309 0.678 0.194 0.562 0.0766 0.366 (Heat# C9955-2)

Nozzle Shell 12-2 0.309 0.678 0.194 0.562 0.0766 0.366 (Heat# C0123-2)

Inlet Nozzle 436B-1 0.0239 0.192 See Note (d)

(Heat # 02041 W)

Inlet Nozzle 436B-2 0.0239 0.192 See Note (d)

(Heat#O2O39W)

Inlet Nozzle 436B-3 0.0239 0.192 See Note (d)

(Heat# O2O39W)

Outlet Nozzle 43 7B-1 0.0102 0.111 See Note (d)

(Heat# Q2Q40)

Outlet Nozzle 437B-2 0.0102 0.111 See Note (d)

(Heat # O2O40W)

Outlet Nozzle 437B-3 0.0102 0.111 See Note (d)

(Heat# Q2O44W)

Nozzle to Intermediate Shell 0.328 0.693 0.206 0.577 0.0813 0.377 Circ. Weld (Heat# 4P4784)

Nozzle Shell Long. Welds< 0) 0.309 0.678 0.194 0.562 0.0766 0.366 Inlet/Outlet Nozzle Forgings to 0.0239 0.192 See note (d)

Nozzle Shell Welds Notes:

(a) The surface fluence values for the RV materials were determined by interpolation from data in Table 2-2. The 1/4T and 3/4T fluence values were calculated from the surface fluence, the RV beltline thickness (7.75 inches) and equation f=fsurr* e*0-24 (x) from Regulatory Guide 1.99, Revision 2, where x the depth into the vessel wall (inches).

(b) FF fluence factor= i 028 - 0 IO*log (l))_

(c) Exposure values for the nozzle shell longitudinal welds are bounded by the exposure values for the nozzle shell.

(d) Analysis of the nozzle forgings and associated welds are conservatively performed using the maximum fluence through the vessel wall.

WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-3 Table 6-2 VCSNS Unit 1 Fluence and Fluence Factor Values for the Surface, 1/4T, and 3/4T Locations at 72 EFPY Surface 1/4T Fluence<*> 3/4T Fluence<al FluenceC*l Surface l/4T 3/4T Material Description FF(bJ (x 10 19 n/cm2, FF(b) (x 10 19 n/cm2, (x 10 19 n/cm 2 , FF(b)

E>l.OMeV) E>l.OMeV)

E> 1.0 MeV)

Beltline Intermediate Shell 11-1 9.04 1.501 5.68 1.427 2.240 1.218 (Heat# A9154-1)

Intermediate Shell 11-2 9.04 1.501 5.68 1.427 2.240 1.218 (Heat# A9153-2)

Lower Shell 10-1 9.06 1.501 5.69 1.427 2.245 1.219 (Heat # C9923- l)

Lower Shell 10-2 9.06 1.501 5.69 1.427 2.245 1.219 (Heat # C9923-2)

Intermediate Shell Long.

3.03 1.293 1.90 1.176 0.751 0.920 Weld (Heat# 4P4784)

Intermediate to Lower Shell Circ. Weld 9.04 1.501 5.68 1.427 2.240 1.218 (Heat# 4P4784)

Lower Shell Long. Weld 3.08 1.297 1.93 1.180 0.763 0.924 (Heat# 4P4784)

Extended Beltline Nozzle Shell 12-1 0.400 0.746 0.251 0.625 0.0991 0.415 (Heat# C9955-2)

Nozzle Shell 12-2 0.400 0.746 0.251 0.625 0.0991 0.415 (Heat# C0123-2)

Inlet Nozzle 436B-1 0.0310 0.224 See Note (d)

(Heat # Q2Q41 W)

Inlet Nozzle 436B-2 0.0310 0.224 See Note (d)

(Heat#O2O39W)

Inlet Nozzle 436B-3 0.0310 0.224 See Note (d) ffieat # O2O39W)

Outlet Nozzle 437B-1 0.0132 0.132 See Note (d)

(Heat# 02040)

Outlet Nozzle 4378-2 0.0132 0.132 See Note (d) ffieat # O2O40W)

Outlet Nozzle 437B-3 0.0132 0.132 See Note (d)

(Heat#O2O44W)

Nozzle to Intermediate Shell 0.425 0.762 0.267 0.640 0.105 0.427 Circ. Weld (Heat# 4P4784)

Nozzle Shell Long. Welds(c) 0.400 0.746 0.251 0.625 0.099 0.415 Inlet/Outlet Nozzle Forgings 0.0310 0.224 See note (d) to Nozzle Shell Welds Notes:

(a) The surface fluence values for the RV materials were determined from Table 2-2. The l/4T and 3/4T fluence values were calculated from the surface fluence, the RV beltline thickness (7.75 inches) and equation f=f,ur£*e.o. 24 (xl from Regulatory Guide 1.99, Revision 2, where x = the depth into the vessel wall (inches).

(b) FF= fluence factor= f(02 s-o.10*1og (f)J.

(c) Exposure values for the nozzle shell longitudinal welds are bounded by the exposure values for the nozzle shell.

(d) Analysis of the nozzle forgings and associated welds are conservatively performed using the maximum fluence through the vessel wall.

WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-4 Table 6-3 Calculation of the VCSNS Unit 1 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at the End of PEO (56 EFPY)<a>

R.G.

1/4T Fluence Predicted 1.99, 1/4T RTNDT(U) GI GA M ART Material CF(h) (x 1019 n/cm2, (OF)<*) ARTNDT (OF) {°F)ll) (OF)

Rev.2 FF(d) {°F)

E > 1.0 MeV)<c) {°F)

Position Beltline Materials Intermediate Shell l 1-1 (Heat# A9154-1) 1.1 65.0 4.39 1.376 21 89.4 0.0 17.0 34.0 144.4 Using non-credible surveillance data's) 2.1 43.5 4.39 1.376 21 59.9 0.0 17.0 34.0 114.9 Intermediate Shell 11-2 (Heat# A9153-2) 1.1 58.0 4.39 1.376 -20 79.8 0.0 17.0 34.0 93.8 LowerShell 10-1 (Heat#C9923-1) 1.1 51.0 4.40 1.376 5 70.2 0.0 17.0 34.0 109.2 Lower Shell I 0-2 (Heat# C9923-2) 1.1 51.0 4.40 1.376 4 70.2 0.0 17.0 34.0 108.2 Intermediate Shell Long. Weld Seams BC & BD (Heat# 4P4784) 1.1 68.0 1.48 1.108 -49 75.3 0.0 28.0 56.0 82.3 Using credible surveillance data(g) 2.1 42.3 1.48 1.108 -49 46.9 0.0 14.0 28.0 25.9 Intermediate to Lower Shell Circ. Weld Seam AB (Heat# 4P4784) 1.1 68.0 4.39 1.376 -49 93.6 0.0 28.0 56.0 100.6 Using credible surveillance data<g) 2.1 42.3 4.39 1.376 -49 58.2 0.0 14.0 28.0 37.2 Lower Shell Long. Weld Seams BA & BB (Heat# 4P4784) 1.1 68.0 1.50 1.112 -49 75.6 0.0 28.0 56.0 82.6 Using credible surveillance data(g) 2.1 42.3 1.50 1.112 -49 47.1 0.0 14.0 28.0 26.1 Extended Beltline Materials Nozzle Shell 12-1 (Heat# C9955-2) 1.1 90.1 0.194 0.563 9 50.7 0.0 17.0 34.0 93.7 Nozzle Shell 12-2 (Heat# C0123-2) 1.1 82.6 0.194 0.563 15 46.5 0.0 17.0 34.0 95.5 Nozzle to Intermediate Shell Circ. Weld Seam AC 1.1 68.0 0.206 0.577 -49 39.2 0.0 19.6 39.2 29.4 (Heat# 4P4784)

Using credible surveillance data(g} 2.1 42.3 0.206 0.577 -49 24.4 0.0 12.2 24.4 -0.2 Nozzle Shell Long. Weld Seams BE and BF 1.1 82.0 0.194 0.563 10 46.1 0.0 23.1 46.1 102.3 Notes contained on following page.

WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-5 Notes:

(a) The Regulatory Guide 1.99, Revision 2 methodology was utilized in the calculation of the ART values.

(b) Chemistry factors are taken from Table 3-3.

(c) Fluence taken from Table 6-1 of this report.

(d) FF = fluence factor = t<0*28 1O*log (f)).

(e) RTNDT(U) (Unirradiated RTNDr) values taken from Table 3-1.

(f) Per the guidance of Regulatory Guide 1.99, Revision 2, the base metal CJt, = 17°F for Position I.I and Position 2.1 with non-credible surveillance data, and the base metal CJt, = 8.5°F for Position 2.1 with credible surveillance data. Also, per Regulatory Guide 1.99, Revision 2, the weld metal CJt, = 28°F for Position 1.1 and Position 2.1 with non-credible surveillance data, and the weld metal CJt, = 14°F for Position 2.1 with credible surveillance data. However, CJt, need not exceed 0.5*~RTNDT for either base metals or welds, with or without surveillance data.

(g) The credibility evaluation for the VCSNS Unit I surveillance data in Appendix A determined that the VCSNS Unit 1 surveillance data for the Intermediate Shell 11-1 (Heat# A9154-

1) is deemed non-credible and the Surveillance Weld (Heat# 4P4784) is deemed credible.

WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-6 Table 6-4 Calculation of the VCSNS Unit 1 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at the End of PEO (56 EFPY)(a)

R.G.

3/4T Fluence Predicted 1.99, 3/4T RTNDT(U) <JI <JA M ART Material CF(b) (x 10 19 n/cm2, FF(d) (OF)(*) ARTNDT {°F)Cf) (OF) (OF)

Rev.2 {°F)

E > 1.0 MeV)(<l (OF)

Position Beltline Materials Intennediate Shell 11-1 (Heat# A9154-l) 1.1 65.0 1.73 1.151 21 74.8 0.0 17.0 34.0 129.8 Using non-credible surveillance data<s) 2.1 43.5 1.73 1.151 21 50.1 0.0 17.0 34.0 105.1 Intennediate Shell 11-2 (Heat# A9153-2) 1.1 58.0 1.73 1.151 -20 66.8 0.0 17.0 34.0 80.8 Lower Shell 10-1 (Heat# C9923-1) 1.1 51.0 1.73 1.152 5 58.7 0.0 17.0 34.0 97.7 Lower Shell 10-2 (Heat# C9923-2) 1.1 51.0 1.73 1.152 4 58.7 0.0 17.0 34.0 96.7 Intermediate Shell Long. Weld Seams BC & BD 1.1 68.0 0.582 0.849 -49 57.7 0.0 28.0 56.0 64.7 (Heat# 4P4784)

Using credible surveillance data(g) 2.1 42.3 0.582 0.849 -49 35.9 0.0 14.0 28.0 14.9 Intermediate to Lower Shell Circ. Weld Seam AB 1.1 68.0 1.73 1.151 -49 78.3 0.0 28.0 56.0 85.3 (Heat# 4P4784)

Using credible surveillance data(g) 2.1 42.3 1.73 1.151 -49 48.7 0.0 14.0 28.0 27.7 Lower Shell Long. Weld Seams BA & BB 1.1 68.0 0.592 0.853 -49 58.0 0.0 28.0 56.0 65.0 (Heat# 4P4784)

Using credible surveillance data(g) 2.1 42.3 0.592 0.853 -49 36.1 0.0 14.0 28.0 15.1 Extended Beltline Materials Nozzle Shell 12-1 (Heat# C9955-2) 1.1 90.1 0.0767 0.366 9 33.0 0.0 16.5 33.0 74.9 Nozzle Shell 12-2 (Heat# C0123-2) 1.1 82.6 0.0767 0.366 15 30.2 0.0 15.1 30.2 75.4 Nozzle to Intennediate Shell Circ. Weld Seam 1.1 68.0 0.0814 0.377 -49 25.6 0.0 12.8 25.6 2.3 AC (Heat# 4P4784)

Using credible surveillance data(g) 2.1 42.3 0.0814 0.377 -49 15.9 0.0 8.0 15.9 -17.1 Nozzle Shell Long. Weld Seams BE and BF 1.1 82.0 0.0767 0.366 10 30.0 0.0 15.0 30.0 70.0 Notes contained on following page.

WCAP-18728-NP June2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-7 Notes:

(a) The Regulatory Guide 1.99, Revision 2 methodology was utilized in the calculation of the ART values.

(b) Chemistry factors are taken from Table 3-3.

(c) Fluence taken from Table 6-1 of this report.

(d) FF= fluence factor= f{O.ZS-O.IO'Iog(f))_

(e) RTNDT(U) (Unirradiated RTNDT) values taken from Table 3-1.

(f) Per the guidance of Regulatory Guide 1.99, Revision 2, the base metal cr8 = l 7°F for Position 1. 1 and Position 2.1 with non-credible surveillance data, and the base metal <r8 =

8.5°F for Position 2.1 with credible surveillance data Also, per Regulatory Guide 1.99, Revision 2, the weld metal cr8 = 28°F for Position 1.1 and Position 2.1 with non-credible surveillance data, and the weld metal cr8 = 14°F for Position 2.1 with credible surveillance data. However, c:;8 need not exceed O.S*~RTNDT for either base metals or welds, with or without surveillance data.

(g) The credibility evaluation for the VCSNS Unit 1 surveillance data in Appendix A determined that the VCSNS Unit 1 surveillance data for the Intermediate Shell 11-1 (Heat#

A9154-1) is deemed non-credible and the Surveillance Weld (Heat# 4P4784) is deemed credible.

WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-8 Table 6-5 Calculation of the VCSNS Unit 1 ART Values for the Reactor Vessel Extended Beltline Nozzle Materials at the End of PEO (56 EFPY)<a)

R.G. Maximum Predicted 1.99, CF(b) Fluence Max RTNDT(U) <Ji <JA M ART Material FF(d) (oF)(e) ARTNDT (OF)Cf)

Rev.2 (x 10 19 n/cm2, {°F) (OF) {°F)

E > 1.0 MeV)Cc) {°F)

Position Inlet Nozzle 436B-1 (Heat# Q2Q4 l W) 1.1 92.1 0.0239 0.192 -20 17.7 0.0 8.8 17.7 15.4 Inlet Nozzle 436B-2 (Heat# Q2Q39W) 1.1 93.0 0.0239 0.192 0 17.8 0.0 8.9 17.8 35.7 Inlet Nozzle 436B-3 (Heat# Q2Q39W) 1.1 93.0 0.0239 0.192 -20 17.8 0.0 8.9 17.8 15.7 Outlet Nozzle 437B-1 (Heat# Q2Q40) 1.1 93.0 0.0102 0.111 -10 10.3 0.0 5.2 10.3 10.6 Outlet Nozzle 437B-2 (Heat# Q2Q40W) 1.1 93.0 0.0102 0.111 -10 10.3 0.0 5.2 10.3 10.6 Outlet Nozzle 437B-3 (Heat# Q2Q44W) 1.1 92.6 0.0102 0.111 0 10.3 0.0 5.1 10.3 20.5 Inlet/Outlet Nozzle Forgings to Nozzle Shell Weld 1.1 82.0 0.0239 0.192 IO 15.7 0.0 7.9 15.7 41.5 Seams 15A/B/C & 16A/B/C Notes:

(a) The Regulatory Guide 1.99, Revision 2 methodology was utilized in the calculation of the ART values.

(b) Chemistry factors are taken from Table 3-3.

(c) Fluence taken from Table 6-1 of this report.

(d) FF= fluence factor= f( 0*28 -O.IO*log (I))_

(e) RTNDT(U) (Unirradiated RTNDT) values taken from Table 3-1.

(f) Per the guidance of Regulatory Guide 1.99, Revision 2, the base metal 0,1 = 17°F for Position I.I and Position 2.1 with non-credible surveillance data, and the base metal 0,1 =

8.5°F for Position 2.1 with credible surveillance data. Also, per Regulatory Guide 1.99, Revision 2, the weld metal 0,1 = 28°F for Position 1.1 and Position 2.1 with non-credible surveillance data, and the weld metal 0,1 = 14°F for Position 2.1 with credible surveillance data. However, 0,1 need not exceed 0.5* ~TNDT for either base metals or welds, with or without surveillance data.

WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-9 Table 6-6 Calculation of the VCSNS Unit 1 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at the End of SPEO (72 EFPY)<a>

R.G.

l/4T Fluence Predicted 1.99, CF(b) 1/4T RTNDT(U) G'I G'A M ART Material (x 10 19 n/cm 2, (OF)<*) ARTNDT {°F)<O (OF)

Rev.2 FF(d)

(OF) {°F) {°F)

E> l.OMeV)M Position Beltline Materials Intermediate Shell 11-1 (Heat # A9154-1) 1.1 65.0 5.68 1.427 21 92.7 0.0 17.0 34.0 147.7 Using non-credible surveillance data(J/,J 2.1 43.5 5.68 1.427 21 62.1 0.0 17.0 34.0 117.1 Intermediate Shell l 1-2 (Heat# A9153-2) 1.1 58.0 5.68 1.427 -20 82.7 0.0 17.0 34.0 96.7 Lower Shell 10-1 (Heat # C9923- l) 1.1 51.0 5.69 1.427 5 72.8 0.0 17.0 34.0 111.8 Lower Shell 10-2 (Heat# C9923-2) 1.1 51.0 5.69 1.427 4 72.8 0.0 17.0 34.0 l 10.8 Intermediate Shell Long. Weld Seams BC & BD (Heat# 4P4784) 1.1 68.0 1.90 1.176 -49 80.0 0.0 28.0 56.0 87.0 Using credible surveillance data(gJ 2.1 42.3 1.90 1.176 -49 49.7 0.0 14.0 28.0 28.7 Intermediate to Lower Shell Circ. Weld Seam AB (Heat# 4P4784) 1.1 68.0 5.68 1.427 -49 97.0 0.0 28.0 56.0 104.0 Using credible surveillance data{g) 2.1 42.3 5.68 1.427 -49 60.3 0.0 14.0 28.0 39.3 Lower Shell Long. Weld Seams BA & BB (Heat# 4P4784) 1.1 68.0 1.93 1.180 -49 80.3 0.0 28.0 56.0 87.3 Using credible surveillance data(g) 2.1 42.3 1.93 1.180 -49 49.9 0.0 14.0 28.0 28.9 Extended Beltline Materials Nozzle Shell 12-1 (Heat# C9955-2) 1.1 90.1 0.251 0.625 9 56.3 0.0 17.0 34.0 99.3 Nozzle Shell 12-2 (Heat# C0123-2) 1.1 82.6 0.251 0.625 15 51.6 0.0 17.0 34.0 100.6 Nozzle to Intermediate Shell Circ. Weld Seam AC 1.1 68.0 0.267 0.640 -49 43.6 0.0 21.8 43.6 38.1

<Heat# 4P4784)

Using credible surveillance data{g) 2.1 42.3 0.267 0.640 -49 27.1 0.0 13.5 27.1 5.2 Nozzle Shell Long. Weld Seams BE and BF 1.1 82.0 0.251 0.625 IO 51.3 0.0 25.6 51.3 l 12.5 Notes contained on following page.

WCAP-18728-NP June 2023 Revision 5

• • • This record was final approved on 6/21/2023, 3:51 :49 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-10 Notes:

(a) The Regulatory Guide 1.99, Revision 2 methodology was utilized in the calculation of the ART values.

(b) Chemistry factors are talcen from Table 3-3.

(c) Fluence and Fluence Factors taken from Table 6-2 of this report.

(d) FF= fluence factor= f(0-2s-O.!O*Iog(f))_

(e) RTNDT(UJ (Unirradiated RTNDt) values taken from Table 3-1.

(f) Per the guidance of Regulatory Guide 1.99, Revision 2, the base metal 0"6 = l 7°F for Position 1.1 and Position 2.1 with non-credible surveillance data, and the base metal 0"6 = 8.5°F for Position 2.1 with credible surveillance data. Also, per Regulatory Guide 1.99, Revision 2, the weld metal 0"6 = 28°F for Position 1.1 and Position 2.1 with non-credible surveillance data, and the weld metal 0"6 = 14°F for Position 2.1 with credible surveillance data. However, 0"6 need not exceed 0.5*iiRTNDT for either base metals or welds, with or without surveillance data.

(g) The credibility evaluation for the VCSNS Unit 1 surveillance data in Appendix A determined thatthe VCSNS Unit 1 surveillance data for the Intermediate Shell 11-1 (Heat# A9154-l) is deemed non-credible and the Surveillance Weld (Heat# 4P4784) is deemed credible.

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Westinghouse Non-Proprietary Class 3 6-11 Table 6-7 Calculation of the VCSNS Unit 1 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at the End of SPEO (72 EFPY)<a>

R.G.

3/4T Fluence Predicted 1.99, 3/4T RTNDT(U) GI GA M ART Material CF(b) (x 10 19 n/cm2, FF(d) (OF)(e) ARTNDT (OF)<t)

Rev.2 {°F) {°F) {°F)

E > 1.0 Mev)<*> {°F)

Position Beltline Materials Intermediate Shell 11-1 (Heat# A9154-1) 1.1 65.0 2.24 1.218 21 79.2 0.0 17.0 34.0 134.2 Using non-credible surveillance datrfal 2.1 43.5 2.24 1.218 21 53.0 0.0 17.0 34.0 108.0 Intermediate Shell 11-2 (Heat# A9153-2) 1.1 58.0 2.24 1.218 -20 70.7 0.0 17.0 34.0 84.7 Lower Shell 10-1 (Heat # C9923-1) 1.1 51.0 2.25 1.219 5 62.2 0.0 17.0 34.0 101.2 Lower Shell 10-2 (Heat# C9923-2) 1.1 51.0 2.25 1.219 4 62.2 0.0 17.0 34.0 100.2 Intermediate Shell Long. Weld Seams BC & BD 1.1 68.0 0.751 0.920 -49 62.5 0.0 28.0 56.0 69.5 ffieat # 4P4784)

Using credible surveillance data(g) 2.1 42.3 0.751 0.920 -49 38.9 0.0 14.0 28.0 17.9 Intermediate to Lower Shell Circ. Weld Seam AB 1.1 68.0 2.24 l.218 -49 82.9 0.0 28.0 56.0 89.9 (Heat# 4P4784)

Using credible surveillance datarg; 2.1 42.3 2.24 1.218 -49 51.5 0.0 14.0 28.0 30.5 Lower Shell Long. Weld Seams BA & BB 1.1 68.0 0.763 0.924 -49 62.8 0.0 28.0 56.0 69.8 (Heat# 4P4784)

Using credible surveillance data(g) 2.1 42.3 0.763 0.924 -49 39.1 0.0 14.0 28.0 18.1 Extended Beltline Materials Nozzle Shell 12-1 (Heat# C9955-2) 1.1 90.1 0.0991 0.415 9 37.4 0.0 17.0 34.0 80.4 Nozzle Shell 12-2 (Heat# C0123-2) 1.1 82.6 0.0991 0.415 15 34.3 0.0 17.0 34.0 83.3 Nozzle to Intermediate Shell Circ. Weld Seam AC 1.1 68.0 0.105 0.427 -49 29.1 0.0 14.5 29.1 9.1 (Heat# 4P4784)

Using credible surveillance datdg) 2.1 42.3 0.105 0.427 -49 18.1 0.0 9.0 18.1 -12.8 Nozzle Shell Long. Weld Seams BE and BF 1.1 82.0 0.0991 0.415 10 34.0 0.0 17.0 34.0 78.1 Notes contained on following page.

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Westinghouse Non-Proprietary Class 3 6-12 Notes:

(a) The Regulatory Guide 1.99, Revision 2 methodology was utilized in the calculation of the ART values.

(b) Chemistry factors are taken from Table 3-3.

(c) Fluence taken from Table 6-2 of this report.

(d) FF fluence factor f(O.zs-o.io*Jog(f))_

(c) RTNDT(U) (Unirradiated RTNDT) values taken from Table 3-1.

(l) Per the guidance of Regulatory Guide l .99, Revision 2, the base metal cr,1 = l 7°F for Position I. I and Position 2.1 with non-credible surveillance data, and the base metal cr,1 = 8.5°F for Position 2.1 with credible surveillance data. Also, per Regulatory Guide 1.99, Revision 2, the weld metal cr,1 = 28°F for Position 1.1 and Position 2.1 with non-credible surveillance data, and the weld metal cr,1 14°F for Position 2.1 with credible surveillance data. However, <JA need not exceed 0.5*MTNDr for either base metals or welds, with or without surveillance data.

(g) The credibility evaluation for the VCSNS Unit 1 surveillance data in Appendix A determined that the VCSNS Unit 1 surveillance data for the Intermediate Shell I I-I (Heat# A9154-

1) is deemed non-credible and the Surveillance Weld (Heat# 4P4784) is deemed credible.

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Westinghouse Non-Proprietary Class 3 6-13 Table 6-8 Calculation of the VCSNS Unit 1 ART Values for the Reactor Vessel Extended Beltline Nozzle Materials at the End of SPEO (72 EFPY)<a)

R.G. Maximum Predicted G'A 1.99, CF(b)

Fluence Max RTNDT(U) G'I (OF) M ART Material FF(d) {°F) (e) ARTNDT (OF) (OF)

Rev.2 (x 10 19 n/cm2, {°F) (I)

E > 1.0 MeV) (cl

{°F)

Position Inlet Nozzle 436B-l (Heat# Q2Q41 W) 1.1 92.1 0.0310 0.224 -20 20.6 0.0 10.3 20.6 21.2 Inlet Nozzle 436B-2 (Heat# Q2Q39W) 1.1 93.0 0.0310 0.224 0 20.8 0.0 10.4 20.8 41.6 Inlet Nozzle 436B-3 (Heat# Q2Q39W) 1.1 93.0 0.0310 0.224 -20 20.8 0.0 10.4 20.8 21.6 Outlet Nozzle 437B-1 (Heat# Q2Q40) 1.1 93.0 0.0132 0.132 -10 12.3 0.0 6.1 12.3 14.5 Outlet Nozzle 437B-2 (Heat# Q2Q40W) 1.1 93.0 0.0132 0.132 -10 12.3 0.0 6.1 12.3 14.5 Outlet Nozzle 437B-3 (Heat# Q2Q44W) 1.1 92.6 0.0132 0.132 0 12.2 0.0 6.1 12.2 24.4 Inlet/Outlet Nozzle Forgings to Nozzle Shell Weld 1.1 82.0 0.0310 0.224 IO 18.4 0.0 9.2 18.4 46.7 Seams 15A/B/C & 16A/B/C Notes:

(a) The Regulatory Guide 1.99, Revision 2 methodology was utilized in the calculation of the ART values.

(b) Chemistry factors are taken from Table 3-3.

(c) Fluence taken from Table 6-2 of this report.

(d) FF fluence factor= f( 0-2s-o.io*1og Ct)l_

(e) RTl'.l)T(U) (Unirradiated RTNvr) values taken from Table 3-1.

(f) Per the guidance of Regulatory Guide 1.99, Revision 2, the base metal O"A l 7°F for Position 1.1 and Position 2.1 with non-credible surveillance data, and the base metal crA 8.5°F for Position 2.1 with credible surveillance data. Also, per Regulatory Guide 1.99, Revision 2, the weld metal !JA =28°F for Position 1.1 and Position 2.1 with non-credible surveillance data, and the weld metal crtt = 14°F for Position 2.1 with credible surveillance data. However, crtt need not exceed 0.5* AR.TNDT for either base metals or welds, with or without surveillance data.

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Westinghouse Non-Proprietary Class 3 6-14 6.2 P-T LIMIT CURVES APPLICABILITY This section determines the applicability term of the end of PEO P-T limit curves by comparing the ART values contained in the analysis of record (AOR) with the ART values calculated using the updated fluence projections and materials information contained herein. If the ART values used in the previous analysis are higher or equal to the ART values calculated using the updated fluence and material properties, then the applicability term of the current curves will remain unchanged. If the ART values used in the previous analysis are lower than the ART values calculated using the updated fluence and material properties, then the applicability term of the current curves may need to be shortened. This new period of applicability can be calculated based on a comparison of the ART values and linear interpolation using the fluence projections. P-T limit curves for the end of SPEO (72 EFPY) do not need to be submitted as part of the VCSNS Unit 1 Subsequent License Renewal Application since P-T limit curves are available as a part of the current license. However, new P-T limit curve development or an extension of the applicability of the current curves must be completed prior to the expiration of the current curves as specified in the VCSNS Unit 1 licensing basis.

Table 6-3 through Table 6-8 calculates the beltline and extended beltline ART values for VCSNS Unit 1 at the end of PEO (56 EFPY) and the end of SPEO (72 EFPY). The limiting end of SPEO ART values correspond to the Intermediate Shell 11-1.

Table 6-9 compares the TLAA limiting ART values at the end of PEO and the end of SPEO to the limiting ART values used in development of the existing PEO P-T limit curves implemented in the Technical Specifications which are based on WCAP-16305-NP (Reference 14);

Table 6-9 Summary of the Limiting ART Values Limiting ART!bl (OF)

Vessel Wall Location P-T Limit Curves 56EFPY 72EFPY AOR<*>

1/4T 153 144.4 147.7 3/4T 138 129.8 134.2 Notes:

(a) Information taken from WCAP-16305-NP.

(b) The limiting material (Intermediate Shell 11-1) corresponds to an axial flaw which is more limiting than a circumferential flaw.

Table 6-9 shows that the end of SPEO ART values at the 1/4T and 3/4T locations remain bounded by the ART values used in the current P-T limit curves. Thus, the P-T limit curves implemented in the VCSNS Unit 1 Technical Specifications will remain valid through the end of SPEO (72 EFPY) for the cylindrical shell materials. The extension of the P-T limit curve is allowed because the redefinition of the Intermediate Shell 11-1 (Heat# A9154-1) initial RTNoT in PWROG-21037-NP resulted in a 9°F reduction.

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Westinghouse Non-Proprietary Class 3 6-15 Note that the terms of applicability for the P-T limits also implicitly confirm the bolt up temperature and flange temperature limits. The bolt up temperature and flange-notch temperature limit are not affected by embrittlement; thus, they are unaffected by license renewal and may remain the same. Since development of the P-T limit curves in WCAP-16305-NP, the closure head has been replaced. However, the RTNDT of the replacement closure head is lower than the original head flange; thus, the P-T limit curves are not negatively affected.

Inlet and Outlet Nozzles P-T Limit Curves NRC Regulatory Issue Summary (RIS) 2014-11 (Reference 22) requires that the P-T limit curves account for the higher stresses in the nozzle corner region due to the potential for more restrictive P-T limits, even if the RTNDT for these components are not as high as those of the reactor vessel beltline shell materials that have simpler geometries. As shown in Table 2-2, the 80-year fluence at the inlet/outlet nozzle postulated 1/4T flaw is below the fluence threshold of RIS 2014-11, 1 x 10 17 n/cm 2 (E > 1.0 MeV). In addition, PWROG-15109-NP-A (Reference 9) addresses the concern of higher stresses in nozzle corner regions generically for the U.S. PWR operating fleet. Therefore, the inlet/outlet nozzles are confirmed not to be limiting.

Conclusion Based on the end of SPEO ART values calculated herein and the P-T limits analysis completed in WCAP-163 05-NP (Reference 14), the P-T limit curves currently in the Technical Specifications will remain valid through 72 EFPY.

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Westinghouse Non-Proprietary Class 3 7-1 7 SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULES This section provides recommended capsule withdrawal schedules for VCSNS Unit 1 as well as technical justifications and demonstration of the schedule's compliance with ASTM E185-82 (Reference 15), as prescribed by 10 CFR 50, Appendix H (Reference 16) and consistent with the guidance ofNUREG-1801, Revision 2 (GALL [Reference 17]) and NUREG-2191 (GALL-SLR [Reference 18]).

10 CFR 50, Appendix H states:

The design of the surveillance program and the withdrawal schedule must meet the requirements of the edition ofASTM E 185 that is current on the issue date of the ASME Code to which the reactor vessel was purchased; for reactor vessels purchased after 1982, the design of the surveillance program and the withdrawal schedule must meet the requirements ofASTM E 185-82. For reactor vessels purchased in or before 1982, later editions ofASTM E 185 may be used, but including only those editions through 1982. For each capsule withdrawal, the test procedures and reporting requirements must meet the requirements of ASTM E 185 to the extent practicable for the configuration of the specimens in the capsule.

The VCSNS Unit 1 RV was designed and constructed to ASME Section III, 1971 Edition. Thus, per 10 CFR 50, Appendix H, the VCSNS Unit 1 surveillance program withdrawal schedule may meet the requirements of any version of the ASTM E185 standard from the 1970 version (which was current on the issue date of the ASME Code to which the RV was purchased) through the 1982 version. Per WCAP-9234 (Reference 19), the VCSNS Unit 1 surveillance capsule program was designed to the ASTM E185-73 (Reference 20) standard, which was the version active at that time. Therefore, the requirements of 10 CFR 50, Appendix H were met at the time of the design of the RV surveillance program. Figure 7-1 shows the initial installation of the capsules in the VCSNS Unit 1 RV.

Since that time VCSNS Unit 1 has implemented the capsule withdrawal schedules in Final Safety Analysis Report (FSAR) (Reference 21) to support license renewal (LR) to 60 years and to meet the requirements of ASTM El 85-82 (Reference 15). Recommended changes to this surveillance capsule withdrawal schedule to support SPEO is provided in Table 7-1. This schedule meets the recommendations of ASTM E185-82 as required by 10 CFR 50, Appendix H and satisfies the guidance contained in the GALL and GALL-SLR.

Specific details are described herein.

The first step in determining the surveillance capsule withdrawal schedule compliance is to determine the minimum number of capsules to withdraw and/or test. ASTM E 185-82 bases the number of capsules on the maximum ~RTNoT projected at the vessel surface for all RV materials. Per Table 4-1 of this report, the maximum ~RTNoT values for the VCSNS Unit 1 is 102.0°F. Since the maximum ~RTNoT are projected to be above 100°F, but below 200°F, four (4) capsules are required to be pulled per Table 1 of ASTM E 185-82.

To date, five (5) capsules have been pulled and tested with the last tested capsule being Capsule Z.

However, Capsule Z does not satisfy the GALL-SLR guidance for the capsule to obtain a fluence at least equal to the 80-year RV projected fluence. VCSNS Unit 1 currently has only one untested capsule (Capsule Y), which was removed at 17.71 EFPY with a fluence of7.0l x 10 19 n/cm2 and placed in storage in the spent fuel pool.

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Westinghouse Non-Proprietary Class 3 7-2 It is recommended that, in order to satisfy the GALL-SLR guidance for the 80-year operating license for a capsule to be withdrawn and tested between one and two times the peak RV wall neutron fluence at the end of SPEO, Capsule Y should be reinserted into a 17° octagonally symmetric location (107°, 287°, or 343°)

to be irradiated further. Capsule Y needs to be irradiated in a 17° location for a minimum of 4.9 EFPY 1 to experience the end of SPEO fluence of 9.06 x 10 19 n/cm2 ( conservatively based on the fluence projection in Section 2 which includes a 10% bias on the periphery fuel assemblies), but it should be withdrawn before receiving 2 x the 80-year fluence, i.e., 1.73 x 1020 n/cm2 (conservatively based on the fluence projection in Section 2 which excludes a 10% bias on the periphery fuel assemblies), at 22.4 EFPY. To assist in asset management and because Capsule Y is the last available capsule in the VCSNS RV surveillance program, it is recommended that a potential 100-year operating period also be considered. A projected 90 EFPY (90% capacity factor over 100 years) peak RV fluence of 1.14 x 10 20 n/cm 2 (with 10% bias) should be achieved after a minimum of 10 .5 EFPY of additional irradiation.

Conclusion In order to meet all of the conditions described above, it is recommended that Capsule Y be exposed to a minimum of 10.5 EFPY of operation to experience the minimum 100-year fluence of 1.14 x 1020 n/cm 2

• Assuming that Capsule Y is reinserted during Refueling Outage 30 in the Fall of 2027, prior to Cycle 31, this fluence will be achieved at a plant EFPY of 48.2 EFPY. Based on an average fuel cycle length of 1.33 EFPY/cycle, i.e., -90% capacity factor, Capsule Y will need 8 cycles to achieve the additional 10.5 EFPY of irradiation (10.5 EFPY / 1.33 EFPY/cycle), which means the projected removal of Capsule Y following Cycle 38 (Fall of2039). This means that Capsule Y will be reinserted at 37 .7 EFPY at EOC 30 and removed at 48.4 EFPY at EOC 38 as this is the nearest outage to the suggested removal of 48.2 EFPY. These dates and cycle numbers are only estimates and may change as actual plant operation may differ from the assumptions used here.

The RV and capsule fluence projections are provided in Section 2 with and without a 10% bias on the periphery fuel assemblies. To ensure that the appropriate fluence is achieved, when the minimum capsule exposure is calculated, the RV fluence is based on the biased projection, while the capsule fluence is based on the unbiased fluence. When the maximum capsule fluence in calculated, the RV fluence is based on the unbiased projection, while the capsule fluence is based on the biased projection. This mixture of fluence data was conservatively applied to ensure the desired/minimum fluence was achieved and to prevent the maximum fluence from being exceeded.

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Westinghouse Non-Proprietary Class 3 7-3 Table 7-1 VCSNS Unit 1 Recommended Surveillance Capsule Withdrawal Schedule Location Capsule Lead Removal Time<*> Capsule Fluence Capsule (deg) Factor (EFPY) (n/cm2, E > 1.0 MeV)<h) u 343 3.04 1.13 (EOC 1) 6.75 X 10 18 V 107 3.34 2.93 (EOC 3) 1.54 X 10 19 X 287 3.54 5.04 (EOC5) 2.51 X 10 19 w 110 3.21 11.21 (EOC 10) 4.63 X 10 19 z 340 3.10 16.36 (EOC 14) 6.53 X 10 19 y(c) 290 3.09 17.71 (EOC 15) 7.01 X 10 19 lQ7(c) ~3.5 48.2(c) 1.14 X 1020 Notes:

(a) Effective full power years from plant startup. End of Cycle (EOC) value given in parenthesis. Note that core thermal power was uprated from 2775 to 2900 MWth starting with operating Cycle 10.

(b) Fluence values were taken from Table 2-1.

(c) Capsule Y will be reinserted during Refueling Outage 30 in the Fall of2027 (prior to Cycle 31) into location 107° (or symmetric locations 287° or 343°), which is projected to occur at 37.7 EFPY. Capsule Y will achieve the peak 100-year fluence, 1.14 x 1020 n/cm2 (E > 1.0 Me V), before removal, which is calculated to require another 10.5 EFPY ofoperation (37.7 + 10.5 = 48.2).

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Westinghouse Non-Proprietary Class 3 7-4 Figure 7-1 Original Arrangement of Surveillance Capsules in the VCSNS Unit 1 Reactor Vessel WCAP-18728-NP June 2023 Revision 5

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Westinghouse Non-Proprietary Class 3 8-1 8 REFERENCES

1. Code of Federal Regulations, 10 CFR Part 54.3, "Definitions," U.S. Nuclear Regulatory Commission, Federal Register, dated August 28, 2007.

2. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," March 2001. [Agencywide Documents Access and Management System (ADAMS) Accession Number ML010890301}

3. Code of Federal Regulations, 10 CFR 50, Appendix G, "Fracture Toughness Requirements," U.S.

Nuclear Regulatory Commission, Federal Register, November 29, 2019.

4. Westinghouse Report WCAP-18124-NP-A, Revision 0, "Fluence Determination with RAPTOR-M3G and FERRET," July 2018.

5. Westinghouse Report WCAP-18709-NP, Revision 1, "V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Reactor Pressure Vessel Extended Beltline Neutron Exposure Evaluation," February 2022.

6. Code of Federal Regulations, 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," U.S. Nuclear Regulatory Commission, Federal Register, November 29, 2019.

7. Westinghouse PWROG Report PWROG-21037-NP, Revision 1, "Determination ofUnirradiated RTNDT and Upper-Shelf Energy Values of the V.C. Summer Unit 1 Reactor Vessel Materials," May 2022.

8. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," May 1988.

[ADAMS Accession Number ML003740284]

9. Westinghouse PWROG Report PWROG-15109-NP-A, Revision 0, "PWR Pressure Vessel Nozzle Appendix G Evaluation," January 2020. [ADAMS Accession Number ML20024E573]

10. Westinghouse Report WCAP-16298-NP, Revision 0, "Analysis of Capsule Z from the South Carolina Electric & Gas Company V. C. Summer Reactor Vessel Radiation Surveillance Program,"

August 2004.

11. ASME Boiler and Pressure Vessel (B&PV) Code,Section III, Division 1, Subarticle NB-2300, "Fracture Toughness Requirements for Material and Section NB-3210, "Requirements for Acceptability," ASME International."

12. NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Chapter 5 of LWR Edition, Branch Technical Position 5-3, "Fracture Toughness Requirements," Revision 4, U.S. Nuclear Regulatory Commission, March 2019. [ADAMS Accession Number ML18338A516}

13. Appendix G to the 1998 through the 2000 Addenda Edition of the ASME Boiler and Pressure Vessel (B&PV) Code,Section XI, Division 1, "Fracture Toughness Criteria for Protection Against Failure."

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Westinghouse Non-Proprietary Class 3 8-2

14. Westinghouse Report WCAP-16305-NP, Revision 0, "V. C. Summer Heatup and Cooldown Limit Curves for Normal Operation," August 2004.

15. ASTM E185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," American Society for Testing and Materials, 1982.

16. Code of Federal Regulations, 10 CPR 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements," U.S. Nuclear Regulatory Commission, Federal Register, October 2, 2020.

17. NUREG-1801, Revision 2, "Generic Aging Lessons Learned (GALL) Report," U.S. Nuclear Regulatory Commission, December 2010. [ADAMS Accession Number MLJ03490041]

18. NUREG-2191, Volume 2, "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report," U.S. Nuclear Regulatory Commission, July 2017. [ADAMS Accession Number ML17187A204]

19. Westinghouse Report WCAP-9234, "South Carolina Electric and Gas Company Virgil C. Summer Nuclear Plant Unit No. 1 Reactor Vessel Radiation Surveillance Program," January 1978.

20. ASTM E185-73, "Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels," American Society for Testing and Materials, 1973.

21. Virgil C. Summer Nuclear Station Unit 1 Updated Final Safety Analysis Report (UFSAR), May 31, 2018.

22. NRC Regulatory Issue Summary 2014-11, "Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components," U.S.

Nuclear Regulatory Commission, October 2014. [ADAMS Accession No. MLl4149AJ65]

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Westinghouse Non-Proprietary Class 3 A-1 APPENDIX A CREDIBILITY EVALUATION OF THE VCSNS UNIT 1 SURVEILLANCE PROGRAM Regulatory Guide 1.99, Revision 2 (Reference A-1) describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled RVs. Positions 2.1 and 2.2 of Regulatory Guide 1.99, Revision 2, describe the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of RV beltline materials using surveillance capsule data. The methods of Positions 2.1 and 2.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.

To date there have been five (5) surveillance capsules removed and tested from the VCSNS Unit 1 RV. In accordance with Regulatory Guide 1.99, Revision 2, the credibility of the surveillance data will be judged based on five criteria.

Table A-1 reviews the five criteria in Regulatory Guide 1.99, Revision 2. The following subsections evaluate each of these five criteria for VCSNS Unit 1 in order to determine the credibility of the surveillance data for use in neutron radiation embrittlement calculations.

TableA-1 Regulatory Guide 1.99, Revision 2, Credibility Criteria Criterion Description No.

Materials in the capsules should be those judged most likely to be controlling with regard to 1

radiation embrittlement.

Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated 2 conditions should be small enough to permit the determination of the 30 ft-lbs temperature and upper-shelf enerl!V unambiguously.

When there are two or more sets of surveillance data from one reactor, the scatter of LlRTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28°F for welds and l 7°F for base metal. Even if the fluence range is large (two or 3 more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper-shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM El 85-82.

The irradiation temperature of the Charpy specimens in the capsule should match the vessel 4

wall temperature at the cladding/base metal interface within+/- 25°F.

The surveillance data for the correlation monitor material in the capsule should fall within the 5

scatter band of the database for that material.

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Westinghouse Non-Proprietary Class 3 A-2 A.1 VCSNS UNIT 1 CREDIBILITY EVALUATION Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.

The VCSNS Unit 1 RV consists of the following beltline region materials, which likely would have been considered at the time the surveillance program was designed and licensed:

• Intermediate Shell 11-1 (Heat # A9154-1)

• Intermediate Shell 11-2 (Heat# A9153-2)

• Lower Shell 10-1 (Heat# C9923-2)

• Lower Shell 10-2 (Heat# C9923-1)

• Intermediate Shell Long. Weld Seams BC & BD (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

• Intermediate to Lower Shell Circ. Weld Seam AB (Heat# 4P4784, Flux Type Linde 124, Lot# 3930)

• Lower Shell Long. Weld Seams BA & BB (Heat# 4P4784, Flux Type Linde 124, Lot#

3930)

The VCSNS Unit 1 surveillance program utilizes longitudinal and transverse test specimens from intermediate shell plate A9 l 54-1. The surveillance weld metal was fabricated with weld wire Heat #

4P4784, Linde 124 Flux, Lot# 3930.

At the time the VCSNS Unit 1 surveillance program material was selected it was believed that copper and phosphorus were the elements most important to embrittlement of the RV steels. The Intermediate Shell Plate A9154- l had the highest Initial RTNDT and one of the lowest initial USE of all plate materials in the beltline region. In addition, the Intermediate Shell Plate A9154-l had the highest content of copper and phosphorus of all the other beltline plate materials. Therefore, based on the highest initial RTNDT, the lowest initial USE and the highest copper and nickel content ofall plate materials, Intermediate Shell PlateA9154-l was chosen for the surveillance program.

The weld material in the VCSNS Unit 1 surveillance program was chosen as it is made of the same heat, flux type, and lot # as all of the RV beltline welds.

Based on the discussion, Criterion 1 is met for the VCSNS Unit I surveillance program.

Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lbs temperature and upper-shelf energy unambiguously.

Based on engineering judgment, the scatter in the data presented in these plots, as documented in WCAP-16298-NP (Refence A-2), is small enough to permit the determination of the 30 ft-lb temperature and the upper-shelf energy of the VCSNS Unit 1 surveillance materials unambiguously.

Hence, Criterion 2 is met for the VCSNS Unit 1 surveillance program.

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Westinghouse Non-Proprietary Class 3 A-3 Criterion 3: When there are two or moi:e sets of surveillance data from one reactor, the scatter of

~RTNoT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28°F for welds and l 7°F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper-shelf energy if the upper shelf can be clearly determined, following the definition given inASTM E185-82.

The functional form of the least squares method as described in Regulatory Position 2.1 will be utilized to determine a best-fit line for this data and to determine if the scatter of these ~RTNDT values about this line is less than 28°F for welds and less than l 7°F for the forgings.

Resulting is the calculation of the best-fit line as described in Regulatory Position 2.1 of Regulatory Guide 1.99, Revision 2. In addition, the recommended NRC methods for determining credibility will be followed.

The NRC methods were presented to the industry at a meeting held by the NRC on February 12 and 13, 1998 (Reference A-3). At this meeting the NRC presented five cases. Of the five cases, Case 1

("Surveillance data available from plant but no other source") most closely represents the situation for the VCSNS Unit 1 surveillance forging and weld material.

Case 1: Evaluation of VCSNS Unit 1 Data Only Following the NRC Case 1 guidelines, the VCSNS Unit 1 surveillance plates and weld metal (Heat#

4P4784) will be evaluated using the VCSNS Unit 1 data. Table A-2 provides the calculation of the interim CFs. Only VCSNS Unit 1 data is being considered; therefore, no temperature adjustment or chemistry adjustments are required.

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Westinghouse Non-Proprietary Class 3 A-4 TableA-2 Calculation of Interim Chemistry Factors for the Credibility Evaluation Using VCSNS Unit 1 Surveillance Capsule Data Only Capsule Measured Fluence<*J FF(b) FF*ARTNDT Material Capsule ARTNDic) FF2 (x 10 19 n/cm2, (OF)

(OF)

E>l.OMeV) u 0.675 0.890 36.1 32.1 0.792 Intermediate V 1.54 1.119 53.2 59.6 1.253 Shell 11-1 X 2.51 1.247 38.3 47.8 1.555 (Longitudinal) w 4.63 1.387 66.2 91.8 1.924 z 6.53 1.451 98.9 143.5 2.106 u 0.675 0.890 14.5 12.9 0.792 V 1.54 1.119 32.1 35.9 1.253 Intermediate X 2.51 1.247 26.7 33.3 1.555 Shell 11-1 w 4.63 1.387 57.8 80.2 1.924 (Transverse) z 6.53 1.451 87.0 126.3 2.106 SUM: 663.4 15.261 CF11-1 = L(FF

• ARTNDT) + L(FF 2) = (663.4) + (15.261) = 43.5°F u 0.675 0.890 22.7 20.2 0.792 V 1.54 1.119 47.0 52.6 1.253 X 2.51 1.247 22.7 28.3 1.555 Surveillance Weld w 4.63 1.387 43.5 60.3 1.924 z 6.53 1.451 65.2 94.6 2.106 SUM: 256.1 7.630 CFsurv. Weld= L(FF

• ARTNDT) + L(FF 2) = (256.1) + (7.630) = 33.6°F Notes:

(a) Fluence taken from Table 2-1.

(b) FF= fluence factor= f(0.28 -o.10*1og (l)J.

(c) Measured Lill.TNDT taken from WCAP-16298-NP (Reference A-2).

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Westinghouse Non-Proprietary Class 3 A-5 The scatter of ~RTNoT values about the functional fonn of a best-fit line drawn as described in Regulatory Position 2.1 is presented in Table A-3.

TableA-3 VCSNS Unit 1 Surveillance Capsule Data Scatter about the Best-Fit Line Capsule <17°F CF<*> Measured Predicted Scatter Fluence<h) (Plate)

Material Capsule (Slopebest-fit) FF<c> ARTNDid) ARTNDi*> ARTNDT(t)

(OF)

(x 10 19 n/cm2, <28°F

{°F) {°F) (OF)

E> 1.0MeV) (Weld) u 43.5 0.675 0.890 36.1 38.7 2.6 Yes V 43.5 1.54 1.119 53.2 48.7 4.5 Yes Intermediate Shell 11-1 X 43.5 2.51 1.247 38.3 54.2 15.9 Yes (Longitudinal) w 43.5 4.63 1.387 66.2 60.3 5.9 Yes z 43.5 6.53 1.451 98.9 63.1 35.8 No u 43.5 0.675 0.890 14.5 38.7 24.2 No V 43.5 1.54 1.119 32.1 48.7 16.6 Yes Intermediate Shell 11-1 X 43.5 2.51 1.247 26.7 54.2 27.5 No (Transverse) w 43.5 4.63 1.387 57.8 60.3 2.5 Yes z 43.5 6.53 1.451 87.0 63.1 23.9 No u 33.6 0.675 0.890 22.7 29.9 7.2 Yes V 33.6 1.54 1.119 47.0 37.6 9.4 Yes Surveillance Weld X 33.6 2.51 1.247 22.7 41.9 19.2 Yes (Heat# 4P4784) w 33.6 4.63 1.387 43.5 46.6 3.1 Yes z 33.6 6.53 1.451 65.2 48.8 16.4 Yes Notes:

(a) CF calculated in Table A-2 of this report.

(b) Fluence taken from Table 2-1 of this report.

(c) FF= fluence factor= f(0.2s-o.10*1og(I))_

(d) Measured L'.RTNDT taken from WCAP-16298-NP (Reference A-2).

(e) Predicted L'.RTNDT = CF x FF (f) Scatter L'.RTNDT = Absolute Value [Predicted LlRTNDT- Measured L'.RTNDT].

The scatter of ~RTNm values about the best-fit line, drawn as described in Regulatory Guide 1.99, Rev. 2, Position 2.1, should be less than l 7°F for base metal and 28°F for welds. From a statistical point of view,

+/- lo- would be expected to encompass 68% of the data. Table A-3 indicates that the Intermediate Shell Plate 11-1 (Heat # A9154-1) has 6 of the 10 surveillance data points falling inside the +/- 1cr of l 7°F scatter WCAP-18728-NP June2023 Revision 5

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__J

Westinghouse Non-Proprietary Class 3 A-6 band for surveillance plate materials. Therefore, 60% of the data are bounded (6/10 x 100) and the surveillance plate data are deemed "non-credible" per the third criterion.

Table A-3 indicates that the Surveillance Weld has 5 of the 5 surveillance data points falling inside the+/-

1cr of 28°F scatter band for surveillance weld materials. Therefore, 100% of the data are bounded and the surveillance weld data are deemed "credible" per the third criterion.

Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within+/- 25°F.

The capsule specimens are located in the reactor between the neutron shielding pads and the vessel wall and are positioned opposite the center of the core. The test capsules are in guide tubes attached to the neutron shielding pads. The location of the specimens with respect to the RV beltline provides assurance that the RV wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25°F. Hence, this criterion is met.

Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material.

The VCSNS Unit 1 surveillance program does not contain correlation monitor material. Hence, this criterion is not applicable to the VCSNS Unit 1 surveillance program.

CONCLUSION Based on the preceding responses to the 5 criteria of Regulatory Guide 1.99, Revision 2, Section B, the VCSNS Unit 1 surveillance data for the Intermediate Shell Plate 11-1 (Heat # A9 l 54-1) is deemed non-credible and the Surveillance Weld (Heat# 4P4784) is deemed credible.

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Westinghouse Non-Proprietary Class 3 A-7 A.2 REFERENCES A- 1. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," May 1988.

[ADAMS Accession Number ML003740284]

A-2. Westinghouse Report, WCAP-16298-NP, Revision 0, "Analysis of Capsule Z from the South Carolina Electric & Gas Company V. C. Summer Reactor Vessel Radiation Surveillance Program,"

August 2004.

A-3. K. Wichman, M. Mitchell, and A. Hiser, US NRC, "Generic Letter 92-01 and RPV Integrity Assessment, Status, Schedule, and Issues," NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998. [ADAMS Accession Number MLJJ0070570]

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F Westinghouse Non-Proprietary Class 3 B-1 APPENDIXB EMERGENCY RESPONSE GUIDELINES The Emergency Response Guideline (ERG) limits were developed to establish guidance for operator action in the event of an emergency situation, such as a PTS event (Reference B-1 ). Generic categories of limits were developed for the guidelines based on the limiting inside surface RTNoT- These generic categories were conservatively generated for the Westinghouse Owners Group (WOG) to be applicable to all Westinghouse plants.

The highest value of RTNDT for which the generic category ERG limits were developed is 250°P for a longitudinal flaw and 300°P for a circumferential flaw. Therefore, if the limiting vessel material has an RTNoT that exceeds 250°P for a longitudinal flaw or 300°P for a circumferential flaw, plant-specific ERG P-T limits must be developed.

The ERG category is determined by the magnitude of the limiting RTNoT value, which is calculated the same way as the RTPTS values are calculated in Section 4 of this report. The material with the highest RTNoT defines the limiting material, which for VCSNS Unit 1 is the Intermediate Shell 11-1. Table B-1 identifies ERG category limits and the limiting material RTNoT values at 72 EFPY for VCSNS Unit 1.

Table B-1 Evaluation ofVCSNS Unit 1 ERG Limit Category ERG Pressure-Temperature Limits (Reference B-1)

Applicable RTNnT Value<a) ERG P-T Limit Category RTNDT < 200°P Category I 200°P < RTNDT < 250°P Category II 250°P < RTNDT < 300°P Category Illb Limiting RT NDT Value<h)

Limiting Reactor Vessel Material RTNnT Value@72 EFPY Intermediate Shell 11-1 152.5 Note(s):

(a) Longitudinally oriented flaws are applicable only up to 250°F; circumferentially oriented flaws are applicable up to 300°F.

(b) Limiting value taken from Table 4-1.

Per the ERG limit guidance document (Reference B-1 ), some vessels do not change categories for operation through the end of license. However, when a vessel does change ERG categories between the beginning and end of operation, a plant-specific assessment must be performed to determine at what operating time the category changes. Thus, the ERG classification need not be changed until the operating cycle during which the maximum vessel value of actual or estimated real-time RTNoT exceeds the limit on its current ERG category.

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Westinghouse Non-Proprietary Class 3 B-2 Conclusion of ERG P-T Limit Categorization The limiting VCSNS Unit 1 RV material RTNDT values do not exceed 200°F. Therefore, VCSNS Unit I will remain in Category I through SPEO.

B.1 REFERENCES B-1. Westinghouse Owners Group Document, HF04BG, "Background Information for Westinghouse Owners Group Emergency Response Guidelines, Critical Safety Function Status Tree, F-0.4 Integrity, HP/LP-Rev. 3," March 31, 2014.

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WCAP-18728-NP Revision 5 Non-Proprietary Class 3

• • This page was added to the quality record by the PRIME system upon its validation and shall not be considered in the page numbering of this document.**

Approval Information Author Approval Ziegler Tyler Jun-20-2023 16:20:35 Reviewer Approval Nedwidek Frank M Jun-20-2023 16:30:37 Reviewer Approval McNutt Don Jun-20-2023 16:32:19 Manager Approval Patterson Lynn Jun-20-2023 19:43: 11 Manager Approval Klingensmith Jesse J Jun-21-2023 15:21 :14 Hold to Release Approval Ziegler Tyler Jun-21-2023 15:51 :49 Files approved on Jun-21-2023

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Serial No.: 23-193 Docket No.: 50-395 Enclosure 4 Attachment 4 WCAP-18754-NP, REVISION 2 Virgil C. Summer (VCSNS) Unit 1 Dominion Energy South Carolina, Inc. (DESC)

Westinghouse Non-Proprietary Class 3 WCAP-18754-NP August 2022 Revision 2 V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Reactor Pressure Vessel Internals Neutron Exposure Evaluation

.@ Westinghouse_ _ _ _ _ _ __

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Westinghouse Non-Proprietary Class 3 ii WCAP-18754-NP Revision 2 V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Reactor Pressure Vessel Internals Neutron Exposure Evaluation Sylena E. Smith*

Radiation Engineering & Analysis August 2022 Reviewer: Frank M. Nedwidek*

Nuclear Operations Approved: Jesse J Klingensmith*, Manager Radiation Engineering & Analysis

• Electronically approved records are authenticated in the electronic document management system.

Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066, USA

© 2022 Westinghouse Electric Company LLC All Rights Reserved

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Westinghouse Non-Proprietary Class 3 iii RECORD OF REVISIONS Revision Description of Changes 0 Initial issue.

1 Changes made to resolve customer comments attached to archive record. The global editorial change from "<I020 "to

"< 1020" was not tracked.

2 Resolved a corrective action to correct the calculated exposure region for several components.

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Westinghouse Non-Proprietary Class 3 iv TABLE OF CONTENTS LIST OF TABLES ........................................................................................................................................ V LIST OF FIGURES ..................................................................................................................................... vi 1 INTRODUCTION ........................................................................................................................... 1 2 NEUTRON TRANSPORT ANALYSIS .......................................................................................... 1 3 REACTOR INTERNALS ................................................................................................................ 4 4 EXPOSURE RESULTS ................................................................................................................... 5 5 REFERENCES .............................................................................................................................. 19 WCAP-18754-NP Revision 2 August2022

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Westinghouse Non-Proprietary Class 3 V LIST OF TABLES Table 4-1. Maximum Fast Neutron (E > 1.0 Me V) Fluence, Iron Atom Displacements and Exposure Region Assignments at 72 EFPY .................................................................................................... 7 WCAP-18754-NP Revision 2 August 2022

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Westinghouse Non-Proprietary Class 3 VI LIST OF FIGURES Figure 2-1. A View of the Reactor Geometry Clipped at the Core Midplane .............................................. 2 Figure 2-2. Oblique View of the Reactor Geometry ..................................................................................... 3 Figure 3-1. Excerpt from MRP-191 Revision 2 Showing Typical Westinghouse Reactor Internals ........... .4 Figure 4-1. Cross-Sectional Views of the Reactor Internals at Selected Azimuthal Locations ................. 15 Figure 4-2. Regional Map of the Core Baffle ............................................................................................ 16 Figure 4-3. Regional Map of the Formers .................................................................................................. 17 Figure 4-4. Regional Maps at Select Axial Cross-Sections of the Reactor Internals ................................. 18 WCAP-18754-NP Revision 2 August 2022

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Westinghouse Non-Proprietary Class 3 1 INTRODUCTION This report describes a comparison between the calculated fast neutron (E > 1.0 Me V) exposure received by reactor internals components in V.C. Summer Nuclear Station (VCSNS) Unit 1 (after 80 years of plant operation (72 effective full power years (EFPY)) against the estimated component fluence for a Westinghouse plant after 80 years of operation as documented in MRP-191 Revision 2, "Materials Reliability Program: Screening, Categorization, and Ranking of Reactor Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191, Reference l)." Revision 2 of MRP-191 documents the process for and updates the categorization results in support of developing the basis for aging management programs in subsequent license renewals.

The neutron transport methodology used to generate the data provided in this attachment was developed consistent with the guidance of Regulatory Guide 1.190 (Reference 2). It is also consistent with the methodology described in WCAP-18124-NP-A (Reference 3) that was approved by the United States Nuclear Regulatory Commission (USNRC). The methodology described in Reference 3 was approved for calculating exposures of the reactor pressure vessel beltline. Presently, there are no regulator-approved methods for calculating exposures of reactor internals components.

2 NEUTRON TRANSPORT ANALYSIS The neutron transport analyses utilized for evaluation of the reactor internals are described in WCAP-18709-NP (Reference 4). To summarize the analysis method, discrete ordinates transport calculations were performed on a fuel-cycle-specific basis to determine the neutron and gamma ray environment within the reactor geometry. In those analyses, anisotropic scattering was treated with a P3 Legendre expansion. The angular discretization was modeled with an S16 order of angular quadrature.

Material cross-section data were based on data derived from the ENDF/B-VI cross section database.

Energy-dependent and space-dependent core power distributions, as well as system operating temperatures, were treated on a fuel-cycle-specific basis. The uncertainties associated with the method of analysis apply equally to this analysis of the reactor internals.

The discrete ordinates transport calculations described in WCAP-18709-NP yielded a three-dimensional database comprised of fuel-cycle specific scalar fluence rate data, which was interrogated to generate the projected component-specific exposure data presented herein for VCSNS Unit 1 after 72 EFPY, or 80 years of operation. For those projections, a 10% positive bias was applied to the relative powers of the fuel assemblies on the periphery of the core and on the re-entrant corners of the core baffle.

The VCSNS Unit 1 reactor is a Westinghouse-designed, 3-loop pressurized water reactor with neutron panels (as opposed to thermal shields). The model geometry used in the transport analysis is described in WCAP-18709-NP. A view of the model geometry clipped at the core midplane is shown in Figure 2-1.

Regarding the reactor internals, this figure reflects a single quadrant arrangement of the core, core baffle, core barrel, neutron panels and surveillance capsule holder with the carbon steel capsule contents. The RPV and other components and structures not making up the reactor internals are also shown. An oblique view of the model geometry is shown in Figure 2-2. Figure 2-2 also depicts the upper and lower core plates and the core former plates, which were explicitly included in the model, as well as the upper and lower reactor internals, which were modeled as a combination of discrete components and homogenized regions.

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Westinghouse Non-Proprietary Class 3 2 Figure 2-1. A View of the Reactor Geometry Clipped at the Core Midplane WCAP-18754-NP Revision 2 August 2022

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Westinghouse Non-Proprietary Class 3 3 Figure 2-2. Oblique View of the Reactor Geometry WCAP-18754-NP Revision 2 August2022

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Westinghouse Non-Proprietary Class 3 4 3 REACTOR INTERNALS The excerpt from MRP-191 Revision 2 in Figure 3-1 shows the relative location of the component groups identified in the results in Section 4. The exposure analysis for the reactor internals components employs nominal design dimensions for the explicitly modeled components, such as the upper core plate, lower core plate, core baffle, formers and core barrel. The smaller internals subcomponents, such as fuel pins, inserts, locking caps, etc., were not explicitly modeled. Exposure of these smaller subcomponents was conservatively assigned based on the maximum fluence observed in the general area in which the components reside.

VesselHead Upper Support Plate Hotl-Oown Spring Upper Sup port COiumn COntrolRod Gulde Tube Outlet Nozzle petC.ore Plate core Barrel Baffle Plate ThfflMI Shield Lower core Plate Lower Support,, _ _ __

COiumn Body Secondary _ _ _ _ __

core Support Figure 3-1. Excerpt from MRP-191 Revision 2 Showing Typical Westinghouse Reactor Internals WCAP-18754-NP Revision 2 August2022

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Westinghouse Non-Proprietary Class 3 5 4 EXPOSURE RESULTS Revision 2 of MRP-191 identifies radiation exposure criteria to be used in screening evaluations for reactor internals components. The exposure bin ranges as defined in Section 4.2.3 ofMRP-191 Revision 2 were as follows:

• Region 1: cj>t < lxl020 n/cm2

• Region 2: lx1020 n/cm2 (0.15 dpa) ::; cj>t < 7xl020 n/cm2

• Region 3: 7xl020 n/cm2 (I dpa) ::; cj>t < lxl021 n/cm2

• Region 4: lx1021 n/cm2 (1.5 dpa) ::; cj>t < lxl022 n/cm 2

• Region 5: lx10 22 n/cm 2 (15 dpa) ::; cj>t < 5xl022 n/cm2

• Region 6: 5xl 022 n/cm 2 (75 dpa) ::; cj>t where cj>t (fluence) is for neutron energies with E > 1.0 MeV.

The calculated exposure region for each component in Table 4-1 was calculated by applying the three-dimensional fluence rates developed from the transport analyses described in WCAP-18709-NP (Reference 4) and then assigning each component to the appropriate exposure "bin" previously described.

The calculated maximum fast neutron (E > 1.0 MeV) fluence, iron atom displacements, and the calculated exposure region, as well as the estimated exposure region as defined in Section 4.2.3 ofMRP-191 Revision 2 for each applicable component of the VCSNS Unit 1 reactor internals are reflected in Table 4-1. For the calculated neutron fluence and iron atom displacements in Table 4-1, the values reflect the neutron fluence at the specific location of the component, except for components for which the calculated fluence is identified by the range "< 1020 ." An elevation was selected above the upper core plate and below the lower core plate beyond which the neutron fluence would be below the MRP-191 Region 1 level for all components. The components whose fluence is identified by this range are located either above or below the relevant cut off elevation. The calculated exposure region assigned in Table 4-1 could be based on the calculated fluence or the calculated iron atom displacements. That is, an item with fluence below the upper limit of Region 4 that has iron atom displacements greater than the lower limit of Region 5 would be assigned to Region 5. Conventional rounding methods are applied. The calculated fast neutron fluence, calculated iron atom displacements and calculated exposure region can be compared to the estimated exposure region and estimated fluence range in Table 4-7 ofMRP-191 Revision 2, which are also reflected in the results.

Several plots were generated showing the distribution of the MRP-191 exposure regions across reactor internals components. Figure 4-1 shows a distribution of the fast neutron fluence at the azimuth of maximum fluence (0°), at 17" (the location of the surveillance capsule with the highest fluence rate), and at 45° (the azimuth oflowest fluence). Figure 4-2 shows a distribution of the fast neutron fluence on the baffle plates, which were most highly exposed on the reentrant corners. Figure 4-3 shows a distribution of the fast neutron fluence on the former plates, which were also most highly exposed on the reentrant corners. Figure 4-4 depicts the distribution of the fast neutron fluence on the core-facing side of the upper core plate and the lower core plate. These figures provide a visualization tool should evaluation of a component not explicitly described in Table 4-1 become necessary or if greater refinement is desired.

With the exception of the components below, the neutron exposures received by the reactor internal components were bounded by the estimated exposures in MRP-191 Revision 2. The following components WCAP-18754-NP Revision 2 August 2022

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Westinghouse Non-Proprietary Class 3 6 were projected to receive neutron exposures higher than estimated by MRP-191 Revision 2 at 72 EFPY:

• Irradiation specimen guide bolts:

The irradiation specimen guide bolts were estimated to be in Exposure Region 2 at 72 EFPY. The calculated fast neutron fluence at the radius and axial range of the irradiation specimen guide bolts was 2x1021 n/cm2 with 2.6 displacements per iron atom (dpa), which put these bolts in Exposure Region 4.

• Irradiation specimen guides:

The irradiation specimen guides were estimated to be in Exposure Region 2 at 72 EFPY. The calculated fast neutron fluence at the irradiation specimen guides was 6xl020 n/cm2 (Exposure Region 2 fluence), but the iron atom displacements totaled more than 1 dpa, putting these components in Exposure Region 3.

• Irradiation specimen guide lock caps:

The irradiation specimen guide lock caps were estimated to be in Exposure Region 2 at 72 EFPY.

The calculated fast neutron fluence at the irradiation specimen guide lock caps was 6xl 020 n/cm 2 (Exposure Region 2 fluence ), but the iron atom displacements totaled more than 1 dpa, putting these components in Exposure Region 3.

• Neutron panel bolts:

The neutron panel bolts were estimated to be in Exposure Region 4 at 72 EFPY. The calculated fast neutron fluence at the neutron panel bolts was 9x1021 n/cm2 (Exposure Region 4 fluence), but the iron atom displacements totaled more than 15 dpa, putting these components in Exposure Region 5.

• Neutron panel locking devices:

The neutron panel locking devices were estimated to be in Exposure Region 2 at 72 EFPY. The calculated fast neutron exposure at the neutron panel locking devices was lxl021 n/cm2 with 2.1 dpa, putting these components in Exposure Region 4.

For the irradiation specimen guide bolts, the fluence reported is that which occurs at the embedded end of the bolt near the inner surface of the neutron pad. For the neutron panel bolts, the fluence reported is that which occurs at the embedded end of the bolt near the inner surface of the core barrel.

The screening described in MRP-191 Revision 2 provides criteria upon which to gauge the susceptibility of reactor internals components to postulated aging-related degradation mechanisms (ARDM). For the reactor internals components determined herein to receive calculated neutron exposure less than or equal to the estimated exposure regions documented in MRP-191 Revision 2, the credible irradiation-related ARDMs are identified in the screening results in Section 5.2 ofMRP-191 Revision 2. The calculated fast neutron (E > 1.0 Me V) fluence or iron atom displacements at 72 EFPY for the previously itemized components was higher than the exposure regions documented in MRP-191 Revision 2, potentially resulting in additional irradiation-related ARDMs screening in for these components. Further evaluation of these components is required to show continued applicability of the failure modes, effects, and criticality analysis results of MRP-191 , Revision 2 and to apply the downstream results in MRP-227, Revision 2. Such an evaluation is outside of the scope of this analysis.

WCAP-18754-NP Revision 2 August 2022

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Westinghouse Non-Proprietary Class 3 7 Table 4-1. Maximum Fast Neutron (E > 1.0 MeV) Fluence, Iron Atom Displacements and Exposure Region Assignments at 72 EFPY Calculated MRP-191 Estimated Component Component Iron Atom Group Description Fluence Fluence Range Displacements Region Region (n/cm 2) (n/cm 2)

(dpa)

Anti-rotation studs < 1020 < 1020

< 0.15 1 1 and nuts Bolts < 1020 <0.15 1 1 < 1020 C-tubes 6xlO 20 0.81 2 3 7xlO 20 to lxl0 21 Enclosure pins < 1020 < 0.15 1 1 < 1020 Guide tube 6x1O20 0.81 2 3 7x10 20 to lxlO 21 enclosures Flanges, < 1020 < 1020

< 0.15 1 1 intennediate Flanges, lower 6x1O 20 0.81 2 4 lx10 21 to lx10 22 Guide plates/cards < 1020 < 0.15 1 2 lxlO 20 to 7x1O 20 Control Rod Guide Tube Guide tube support Assemblies l xlO 21 1.6 4 4 lxlO 21 to 1x1O22 pins and Flow Downcomers Housing plates < 1020 < 0.15 1 ] < 1020 Lock bars < 1020 < 0.15 1 1 < 1020 Sheaths 6x1020 0.81 2 3 7x10 20 to lx1021 Cover plates < 1020 < 0.15 1 1 < 1020 Cover plate cap < 1020 < 1020

< 0.15 1 1 screws Cover plate locking < 1020 < 1020

< 0.15 l 1 caps and tie straps Support pin nuts 6x1O 20 0.81 2 4 l x1O 21 to lx10 22 Water flow slot l x1O20 0.21 2 3 7x1O 20 to lxl0 21 ligaments Mixing Mixing Devices lxl021 1.6 4 4 lx1O 21 to lxlO 22 Devices WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022 , 10:27:52 AM . (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8 Table 4-1. Maximum Fast Neutron (E > 1.0 MeV) Fluence, Iron Atom Displacements and Exposure Region Assignments at 72 EFPY Calculated MRP-191 Estimated Component Component Iron Atom Group Description Fluence Fluence Range Displacements Region Region (n/cm 2) (n/cm 2)

(dpa)

Fuel alignment pins 3x10Z 1 4.0 4 4 lx1021 to lx1022 UCP lx1O21 1.6 4 4 lxlO21 to lx1022 Upper Core Plate (UCP) UCP insert 3x1O20 0.48 2 3 7x1020 to lxlO 21 and Fuel Alignment UCP insert bolts 3x1020 0.48 2 3 7x10 20 to lx1O21 Pins UCP insert locking devices and dowel 3x1O20 0.48 2 3 7x1O20 to lxl021 pins Bolting < 1020 <0.15 1 1 < 1020 Brackets, clamps terminal blocks, and < 1020 <0.15 1 3 7x1020 to lxl0 21 conduit straps Conduit seal assembly: body, < 1020 < 1020 Upper <0.15 1 1 tube sheets, Instrumen- tubesheet welds tation Conduit and Conduit seal < 1020 < 1020

<0.15 1 1 Support assembly: tubes Conduits < 1020 <0.15 1 2 lx1O 20 to 7xlO20 Flange base < 1020 <0.15 1 1 < 1020 Locking Caps < 1020 <0.15 1 1 < 1020 Support tubes < 1020 <0.15 1 1 < 1020 WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022, 10:27:52 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 9 Table 4-1. Maximum Fast Neutron (E > 1.0 MeV) Fluence, Iron Atom Displacements and Exposure Region Assignments at 72 EFPY Calculated MRP-191 Estimated Component Component Iron Atom Group Description Fluence Fluence Range Displacements Region Region (n/cm 2) (n/cm 2)

(dpa)

Adapters < 1020 <0.15 1 1 < 1020 Bolts lxl0 21 1.6 4 4 lxl0 21 to lx10 22 Column bases lxl021 1.6 4 4 lx1O21 to lxl0 22 Upper Column bodies 6x1O20 0.81 2 2 lxl020 to 7x1Q2° Support < 1020 < 1020 Extension tubes <0.15 1 1 Column Assemblies Flanges < 1020 <0.15 1 1 < 1020 Lock keys < 1020 <0.15 1 3 7x1020 to lxl0 21 Lockcaps 1 6x1O 20 0.81 2 -- --

Nuts < 1020 <0.15 1 1 < 1020 Upper support plate < 1020 <0.15 1 1 < 1020 Upper support ring < 1020 Upper <0.15 1 1 < 1020 or skirt Support Plate Assembly- Deep beam ribs < 1020 <0.15 1 1 < 1020 Flat Plate Design Deep beam < 1020 < 1020

<0.15 1 1 stiffeners Locking device < 1020 <0.15 1 1 < 1020 1

Upper support column bases use locking caps instead oflocking keys. Though not explicitly listed in MRP-191, the locking caps are similar in function and location to locking keys and are thus included. The MRP-191 inspection program is considered applicable because the fast neutron fluence at the lock caps is within the exposure range estimated for the lock keys.

WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022, 10:27:52 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Table 4-1. Maximum Fast Neutron (E > 1.0 MeV) Fluence, Iron Atom Displacements and Exposure Region Assignments at 72 EFPY Calculated MRP-191 Estimated Component Component Iron Atom Group Description Fluence Fluence Range Displacements Region Region (n/cm 2) (n/cm 2)

(dpa)

Baffle bolting lock lxl023 176 6 6  ::: 5x1022 devices Baffle-edge bolts lxl023 176 6 6  ::: 5xl022 Baffle and Baffle plates lx10 23 176 6 6  ::: 5x1022 Former Assembly Baffle-former bolts lx1023 176 6 6  ::: 5x1022 Barrel-former bolts lx1022 15 5 5 lx1022 to 5x1022 Former plates 8x1022 114 6 6  ::: 5x1022 BMI column bodies < 1020 <0.15 1 1 < 1020 BMI column bolts < 1020 <0.15 1 5 lx1022 to 5xl022 BMI column collars lx1022 19 5 5 lx1022 to 5x1022 BMI column < 1020 <0.15 1 5 lx10 22 to 5x1022 Bottom- cruciforms Mounted Instrumen- BMI column 2x1022 32 5 5 lx1022 to 5xl022 tation (BMI) extension bars Column Assemblies BMI column < 1020 < 1020

<0. 15 I 1 extension tubes BMI column locking lxl022 19 5 5 lxl0 22 to 5x1022 devices BMI column nuts 2x10 22 32 5 5 lxl022 to 5xl022 WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022, 10:27:52 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 11 Table 4-1. Maximum Fast Neutron (E > 1.0 MeV) Fluence, Iron Atom Displacements and Exposure Region Assignments at 72 EFPY Calculated MRP-191 Estimated Component Component Iron Atom Group Description Fluence Fluence Range Displacements Region Region (n/cm 2) (n/cm 2)

(dpa)

Core barrel flange < 1020 <0.15 1 1 < 1020 Upflow conversion core barrel plug - lx1O 21 1.6 4 4 lx1O 21 to lx1022 body Upflow conversion core barrel plug - lxlO21 1.6 4 4 lxlO21 to lx1022 mandrel Core barrel outlet < 1020 < 1020

< 0.15 1 1 nozzles Core Barrel Lower core barrel axial welds (MAW lxl021 2.2 4 5 lxlO22 to 5x1022 and LAW)

Lower core barrel girth welds (LGW 9x1021 14 4 5 lxlO22 to 5xl022 andLFW)

Upper core barrel < 1020 < 0.15 1 2 lxlO20 to 7xl020 axial welds (UAW)

Upper core barrel girth welds (VFW < 1020 < 0.15 1 2 lxlO 20 to 7xlO20 and UGW)

Flux thimble tube

~ 5xlD22 > 75 6 6 ~ 5xlO22 Flux plugs Thimbles Flux thimbles

~ 5x1022 >75 6 6 ~ 5xlO22 (tubes)

Head Cooling Head cooling spray < 1020 < 1020 Spray < 0.15 1 1 nozzles Nozzles WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022, 10:27:52 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 12 Table 4-1. Maximum Fast Neutron (E > 1.0 MeV) Fluence, Iron Atom Displacements and Exposure Region Assignments at 72 EFPY Calculated MRP-191 Estimated Component Component Iron Atom Group Description Fluence Fluence Range Displacements Region Region (n/cm 2) (n/cm 2)

(dpa)

Irradiation specimen 6x1O 20 1.1 3 2 lx1O20 to 7xl020 guides Irradiation specimen 2xl021 2.6 4 2 lxlO 20 to 7x1020 guide bolts Irradiation Irradiation specimen 6x1O20 1.1 3 2 lx1O 20 to 7xlO20 Specimen guide lock caps Guides Spring < 1020 <0.15 1 1 < 1020 Irradiation Dowel < 1020 < 1020 specimen <0.15 1 1 pin plug Plug < 1020 <0.15 1 1 < 1020 Fuel alignment pins 3xlO22 42 5 6 2:: 5x1O22 Lower Core LCP and manway Plate (LCP) 2x1O22 32 5 5 lx10 22 to 5x1022 bolts and Fuel Alignment LCP and manway 2x1O22 32 5 5 lxl022 to 5x1022 Pins locking devices Lower core plate lxl022 19 5 5 lx1O22 to 5x1022 Lower support 6x1021 8.9 4 5 lxl0 22 to 5xl022 column bodies Lower support 2xl022 32 5 5 lx1O 22 to 5x1O22 column bolts Lower Lower support Support column bolt locking 2x1022 32 5 5 lxl0 22 to 5x1O22 Column devices Assemblies Lower support < 1020 <0.15 1 5 lxl022 to 5x1022 column nuts Lower support < 1020 <0.15 1 2 lx10 20 to 7x1020 column sleeves WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022, 10:27:52 AM. (This statement was added by the PRIME system upon its validation}

Westinghouse Non-Proprietary Class 3 13 Table 4-1. Maximum Fast Neutron (E > 1.0 MeV) Fluence, Iron Atom Displacements and Exposure Region Assignments at 72 EFPY Calculated MRP-191 Estimated Component Component Iron Atom Group Description Fluence Fluence Range Displacements Region Region (n/cm 2) (n/cm 2)

(dpa)

Lower Support Lower support < 1020 < 1020

<0.15 1 1 Casting or forging Forging Neutron panel bolts 9xl021 15 5 4 lx1 O21 to lx1O22 Neutron Neutron panel Panels 1x1021 2.1 4 2 lx1O 20 to 7xlO 20 locking devices Neutron panels 4x1D2 1 6.5 4 4 lxlO21 to lx1O22 Radial support key < 1020 < 1020

<0.15 1 1 bolts Radial support key < 1020 < 1020

<0.15 1 1 Radial lock keys Support Keys Radial support key < 1020 < 1020

<0.15 I 1 dowels Radial support keys < 1020 <0.15 I 1 < 1020 SCS base plates < 1020 <0. 15 1 1 < 1020 SCS bolts < 1020 <0. 15 1 1 < 1020 SCS energy < 1020 < 1020

< 0.1 5 1 I Secondary absorber Core Support < 1020 < 1020 SCS guide post <0.15 1 1 (SCS)

Assembly SCS housing < 1020 <0.15 1 I < 1020 SCS lock keys < 1020 <0.15 1 1 < 1020 Upper and lower tie < 1020 < 1020

<0. 15 1 1 plates WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022, 10:27:52 AM . (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 14 Table 4-1. Maximum Fast Neutron (E > 1.0 MeV) Fluence, Iron Atom Displacements and Exposure Region Assignments at 72 EFPY Calculated MRP-191 Estimated Component Component Iron Atom Group Description Fluence Fluence Range Displacements Region Region (n/cm 2) (n/cm 2)

(dpa)

Clevis insert bolts < 1020 <0.15 1 1 < 1020 Clevis insert dowels < 1020 <0.15 1 1 < 1020 Clevis insert locking < 1020 < 1020

<0.15 1 1 devices Clevis inserts < 1020 <0.15 1 1 < 1020 Head and vessel < 1020 < 1020

<0.15 1 1 alignment pin bolts Head and vessel Interfacing < 1020 < 1020 alignment pin lock <0.15 1 1 Components caps Head and vessel < 1020 < 1020

<0.15 1 1 alignment pins Internals hold-down < 1020 < 1020

<0. 15 1 1 spring UCP alignment pins 3x1020 0.48 2 3 7xl0 20 to lx1021 Replacement reactor vessel head (RRVH) < 1020 <0.15 1 1 < 1020 extension tubes Note: The components located in the active fuel region were conservatively assigned to Region 6 and were not explicitly modeled.

WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022, 10:27:52 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 15 45 ° eglon ~

-Reglon4 -Reglon4 lon 3 lon 3 eglon 3

'-Reglon2 r-Reglon 2 t-Reglon 2

~eglon 1 11--Reglon l 11--Reglon 1 z z z

~ ~ L.

Figure 4-1. Cross-Sectional Views of the Reactor Internals at Selected Azimuthal Locations WCAP-18754-NP Revision 2 August 2022

- This record was final approved on 8/19/2022, 10:27:52 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 16 Region 6 Region 5

- Region 4 Region 3

- Reg ion 2 Region l Figure 4-2. Regional Map of the Core Baffle WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022, 10:27:52 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 17 Region o Region 5 Reglon 3 1

-Region 2 Region 1 Figure 4-3. Regional Map of the Formers WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022, 10:27:52 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 18 Lower Core Plate 160 140 l.Z0 100 80 60 40

.zo Region 6 0

Region 5 0 20 40 60 80 100 l.ilO 140 160

-Reglon4 Upper Core Plate Region 3 160

-Region 2 140 Region l l.Z0 100 80 60 40

.zo 0

0 .zo 40 60 80 100 l.20 140 160 Figure 4-4. Regional Maps at Select Axial Cross-Sections of the Reactor Internals (Dimensions are distance from core center in centimeters. Core Barrel is also shown.)

WCAP-18754-NP Revision 2 August 2022

• • • This record was final approved on 8/19/2022, 10:27:52 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 19 5 REFERENCES

1. Electric Power Research Institute (EPRI) Document, MRP-191 , Revision 2, "Materials Reliability Program: Screening, Categorization, and Ranking of Reactor Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191 , Revision 2)," 2018.

2. USNRC Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," Office of Nuclear Regulatory Research, March 2001.

3. Westinghouse Report WCAP-18124-NP-A, Revision 0, "Fluence Determination with RAPTOR-M3G and FERRET," July 2018.

4. Westinghouse Report WCAP-18709-NP, Revision 1, "V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Reactor Pressure Vessel Extended Beltline Neutron Exposure Evaluation," February 2022.

WCAP-18754-NP Revision 2 August 2022

... This record was final approved on 8/19/2022. 10:27:52 AM. (This statement was added by the PRIME system upon its validation)