ML23024A154
| ML23024A154 | |
| Person / Time | |
|---|---|
| Site: | Summer  (NPF-012) |
| Issue date: | 01/23/2023 |
| From: | James Holloway Dominion Energy South Carolina |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 22-227 | |
| Download: ML23024A154 (1) | |
Text
Dominion Energy South Carolina, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 DominionEnergy.com Attn: Document Control Desk January 23, 2023 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 DOMINION ENERGY SOUTH CAROLINA VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 Dominion Energy
Serial No.:
NRANG:
Docket No.:
License No.:
22-227 RO 50-395 NPF-12 PROPOSED REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE TO SUPPORT POTENTIAL SUBSEQUENT LICENSE RENEWAL ACTIVITY Pursuant to the provisions of Title 10 of the Code of Federal Regulations Part 50 (10 CFR 50), Appendix H, Dominion Energy South Carolina, Inc. (DESC), hereby submits the attached request for approval to add a new surveillance capsule withdrawal schedule in the Virgil C. Summer Nuclear Station (VCSNS) Updated Final Safety Analysis Report (UFSAR) Section 5.4.3.6.2.3, Removal Schedule.
10 CFR 50, Appendix H, Section 111.B.3 requires that changes to the withdrawal schedule be submitted in accordance with 10 CFR 50.4 and that the proposed schedule must be approved by the NRC prior to implementation. Per NRC Administrative Letter 97-04, a proposed change to the withdrawal schedule may be approved without a license amendment if the changes conform to the American Society for Testing and Materials (ASTM) Standard Practice E 185-82. The proposed request complies with ASTM E 185-82 as discussed in the Attachment.
There is no in-vessel capsule at VCSNS currently and the capsules previously withdrawn did not receive fluence greater than the projected peak vessel fluence for an 80-year or 100-year operation. To support the demonstration of reactor vessel integrity through the potential subsequent license renewal(s) at VCSNS, a capsule is planned to be inserted in the reactor vessel with a proposed withdrawal schedule to meet the requirements for a potential 80-year or 100-year operating period.
A detailed description of, and justification for, the proposed activity are provided in the Attachment and Enclosures to this letter, respectively. DESC requests NRC review and approval of this request by January 23, 2024, with a 60-day implementation period for incorporating the VCSNS UFSAR changes.
In accordance with 10 CFR 50.91, a copy of this request, with the Attachment and Enclosures, is being provided to the designated South Carolina State Official.
Serial No.22-227 Docket No. 50-395 Page 2 of 3 Should you have any questions related to this submittal, please contact Yan Gao at (804) 273-2768.
Respectfully, James E. Holloway Vice President - Nuclear Engineering and Fleet Support c!m:n~etter: None.
Attachment:
Enclosures:
- 1. Westinghouse Report WCAP-18728-NP, Rev. 3, "V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Evaluation of Reactor Vessel Integrity Time-Limiting Aging Analysis," August 2022
- 2. Westinghouse Letter CGE-RV000-TM-ME-000004, Rev. 3, "V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal:
Recommended Changes to the Surveillance Capsule Withdrawal Schedule," September 9, 2022
cc:
U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 Mr. G. Edward Miller NRG Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 E-3 11555 Rockville Pike Rockville, Maryland 20852-2738 NRG Senior Resident Inspector V.C. Summer Nuclear Station Ms. Anuradha Nair-Gimmi Bureau of Environmental Health Services South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Mr. G. J. Lindamood Santee Cooper - Nuclear Coordinator 1 Riverwood Drive Moncks Corner, SC 29461 Serial No.22-227 Docket No. 50-395 Page 3 of 3 Serial No.22-227 Docket No. 50-395 Proposed Revision to VCSNS UFSAR Section 5.4.3.6.2.3, Removal Schedule Virgil C. Summer Nuclear Station (VCSNS) Unit 1 Dominion Energy South Carolina, Inc. (DESC)
TABLE OF CONTENTS Serial No.22-227 Docket No. 50-395 - Page 1 of 6
1.0 INTRODUCTION
............................................................................................................. 2
2.0 PROPOSED CHANGE
S AND TECHNICAL ANALYSIS.................................................. 3
3.0 CONCLUSION
S.............................................................................................................. 5
4.0 REFERENCES
................................................................................................................ 6
Serial No.22-227 Docket No. 50-395 - Page 2 of 6 Proposed Revision to VCSNS UFSAR Section 5.4.3.6.2.3, Removal Schedule
1.0 INTRODUCTION
NUREG-2191, "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report" [4.1 ], provides guidance for Subsequent License Renewal (SLR) applicants. The SLR is the renewal of the initial renewed operating license, thereby permitting plants to operate to 80 years. The period of operation between 60 and 80 years is referred to as the subsequent period of extended operation. This guidance states that the Reactor Vessel Material Surveillance Program must meet the requirements of Title 10 of the Code of Federal Regulations Part 50 (10 CFR 50), Appendix H [4.2], and further states that this program includes withdrawal and testing of at least one reactor vessel surveillance capsule addressing the subsequent period of extended operation.
10 CFR 50, Appendix H [4.2] provides the Nuclear Regulatory Commission (NRC) criteria for the design and implementation of reactor vessel material surveillance programs. 10 CFR 50, Appendix H requires the surveillance capsule withdrawal schedule meet the requirements of the edition of the American Society for Testing and Materials (ASTM) E 185 that is current on the issue date of the American Society of Mechanical Engineers (ASME) code to which the reactor vessel was purchased. For reactor vessels purchased after 1982, the design of the reactor vessel material surveillance program and the capsule withdrawal schedule must meet the requirements of ASTM E 185-82 [4.3]. For reactor vessels purchased during or before 1982, later editions of ASTM E 185 may be used, but including only those editions through 1982.
The Virgil C. Summer Nuclear Station (VCSNS), Unit 1 reactor vessel was designed and constructed to ASME Section Ill, 1971 Edition per UFSAR Table 5.2-1 [4.4]. Thus, per 10 CFR 50, Appendix H [4.2], the surveillance capsule program withdrawal schedule may meet the requirements of any version of the ASTM E 185 standard from the 1970 version (the version which was current on the issue date of the ASME Codes to which the reactor vessel was purchased) through the 1982 version.
Per WCAP-9234-NP [4.5], the surveillance capsule program was designed to ASTM E 185-73 [4.6], which was the version active at that time the program was developed. Therefore, the requirements of 10 CFR 50, Appendix H [4.2] were met at the time of the design of the VCSNS reactor vessel surveillance program.
NRC Administrative Letter (AL) 97-04 [4.7] summarizes the Commission's decision promulgated in Commission Memorandum and Order CLl-96-13 [4.8].
In this Memorandum and Order [4.8], the Commission found that, while 10 CFR 50, Appendix H
[4.2] section 111.B.3, requires prior NRC approval for all withdrawal schedule changes, only certain changes require the NRC staff to review and approve the changes through the NRC's license amendment process. Specifically, only those changes that are not in conformance with the ASTM standard referenced in 10 CFR 50, Appendix H [4.2], are required to be approved through the license amendment process, whereas changes that
Serial No.22-227 Docket No. 50-395 - Page 3 of 6 are determined to conform to the ASTM standard require only staff verification of such conformance.
The existing surveillance capsule withdrawal schedule fully satisfies the regulatory requirements for operation through the 60-year license renewal period. However, to preserve the possibility to operate the plant for 80 years and beyond, a capsule must be re-inserted into the reactor vessel to satisfy NUREC-2191 [8.04.1).
2.0 PROPOSED CHANGE
S AND TECHNICAL ANALYSIS DESC is planning to revise the VCSNS Unit 1 surveillance capsule withdrawal schedule as listed in VCSNS UFSAR [4.4], Section 5.4.3.6.2.3. Specifically, the following changes are being proposed:
2.1 Revise the withdrawal schedule to re-insert Capsule Y during Refueling Outage 30 (Fall 2027) as a standby capsule and withdraw Capsule Y during Refueling Outage 38 (Fall 2039)
To date, VCSNS Unit 1 has tested 5 of 6 capsules initially inserted. Capsule Y is the only remaining untested capsule. The capsules already tested satisfy the requirements under the 60-year license. However, the schedule change is being pursued to meet the 80-year recommendations of NUREG-2191 [4.1] which states one capsule should be withdrawn at an outage with a neutron fluence of between one and two-times the peak reactor vessel wall neutron fluence at the end of the subsequent period of extended operation (SPEO) and tested in accordance with the requirements of ASTM E 185-82 [4.3). The proposed schedule change satisfies the regulatory requirements of the Reactor Surveillance Program for 80 years, provides a mechanism to obtain a neutron fluence to bound 100 years of plant operation, and meets ASTM E 185-82 [4.3] as required by 10 CFR 50, Appendix H [4.2).
GALL-SLR [4.1] Recommendations for Fluence: The 80-year, assumed SPEO of 72 Effective Full Power Year (EFPY), one-times peak reactor vessel wall neutron fluence =
9.06 x 1019 n/cm2 (which includes a 10% bias on the peripheral and re-entrant corner assembly relative powers) and the two-times the end of SPEO fluence = 1.73 x 1020 n/cm2 (2 x 8.64 x 1019 n/cm2, which conservatively excludes the 10% unbiased). Therefore, the capsule must reach a fluence above 9.06 x 1019 n/cm2 and below 1.73 x 1020 n/cm2 to meet the GALL-SLR [4.1] recommendations.
Capsule Y: Capsule Ywas withdrawn at 17.71 EFPYwith a fluence of 7.01 x 1019 n/cm2.
Therefore, this capsule does not meet the GALL-SLR [4.1] requirements for fluence cited above. Therefore, Capsule Y is recommended to be reinserted and irradiated further. To meet the GALL-SLR [4.1] recommended fluence, Capsule Y must be exposed to a minimum of 4.9 additional EFPY of irradiation to experience one-times the end of SPEO fluence. In order to remain below the two-times the end of SPEO fluence, Capsule Y must be withdrawn before 22.4 EFPY of additional irradiation. Since the minimum 100-year fluence is within the allowable range of one to two-times the 80-year fluence, it is
Serial No.22-227 Docket No. 50-395 - Page 4 of 6 recommended that Capsule Y be withdrawn after being exposed to a minimum of 10.5 additional EFPY of irradiation in order to experience the minimum 100-year fluence of 1.14 x 1020 n/cm2.
Assuming that Capsule Y is reinserted during Refueling Outage 30 in the Fall of 2027, prior to cycle 31 (the final opportunity to reinsert the capsule), and an average fuel cycle length of 1.33 EFPY/cycle, (i.e., ~90% capacity factor), Capsule Y will need 8 fuel cycles to achieve an additional 10.5 EFPY of irradiation (10.5 EFPY) / (1.33 EFPY/cycle), and require removal following Cycle 38 (Fall of 2039). Since the plant has experienced 32.38 EFPY at the end of cycle 26, Capsule Y is projected to be reinserted at 37.7 EFPY and projected to be removed at 48.4 EFPY. These dates are only intended to be an estimate.
All actual dates will be based on withdrawing Capsule Y during the refueling outage nearest to, but following, the capsule fluence achieving the 100-year fluence, which is estimated to be after 10.5 EFPY with Capsule Y re-inserted into the 107° location (or symmetric locations 287° or 343°). Capsule fluence will be used to determine when the capsule is withdrawn, and 10.5 EFPY is an approximation based on the unbiased capsule projections.
2.2 Update the calculated fluence, removal time EFPY (effective full power years), and capsule lead factor values for capsules removed to date.
The values documented in WCAP-18728-NP [4.9] provide the most up to date information for the capsules.
Additionally, the updated values verify that the existing pressure temperature limit curves for VCSNS Unit 1 are still bounding.
The following table is a proposed FSAR Section 5.4.3.6.2.3 Surveillance capsule withdrawal schedule for VCSNS Unit 1:
5-4.3.6.2.3 Removal Schedule Serial No.22-227 Docket No. 50-395 - Page 5 of 6 The schedule for rermval of specimen capsules from the reactor vessel is as follows:
Capsule Calculated Ci12gile LQcatiQO (deg}
Lead Factor Rermval time <a>
Eluen~e (n/cm2} !b>
u 343 3.04 1.13(EOC1}
6.75 X 1018 V
107 3.34 2.93(EOC3}
1.54 x 1019 X
287 3.54 5.04 (EOC5}
2.51 X 1019 w
110 3.21 11.21 (EOC 10) 4.63x1019 z
340 3.10 16.36 (EOC 14) 6.53x1019 290 3.09 17.71 (EOC 15) 7.01 X 1019 Y{c) 10](c)
-3.5 48.2(cJ 1.14x1Q20
( a}
Effective full power yeas from plant startup. End of Cycle (EOC) value given in p.=renthesis. Note that core thermal power was uprated from2775 to 2900 MWth stating with operating cyde 10.
(b}
Values a-e taken from WCAP-18728-NP Table 2-1
{c}
Capsule Y will be reinserted during Refuefing Outage 30 in the Fall of 2027 (prior to Cyde 31) in location 107° (or symnetric locations 287° or 343°), which is projected to occur a 37.7 EFPY. Capsule Y will ochieve the peak 100-yea-fluence, 1.14 x 1()211 n/cml (E > 1.0 MeV}, before removal, which is calculated to require another 10.5 EFPY of opera-ion (37.7 + 10.5 = 48.2). The nea-est outage to the suggested removal of 482 EFPY will occur at EOC 38 after 48.4 EFPY, which is the projected removal time of Capsule Y.
3.0 CONCLUSION
S A strategy has been developed to reinsert and withdraw Capsule Y to support subsequent license renewal. The strategy is based on the revised fluence projections outlined in WCAP-18728-NP [4.9) and Westinghouse Letter CGE-RV000-TM-ME-000004 [4.10].
The proposed change to reinsert Capsule Y during Refueling Outage 30 (Fall 2027) and withdraw Capsule Y during Refueling Outage 38 (Fall 2039) meets the surveillance capsule recommendations of NUREG-2191 [4.1 ], the requirements of ASTM E185-82
[4.3) and 10 CFR 50, Appendix H [4.2).
The proposed change to update the calculated fluence, removal time EFPY (effective full power years), and capsule lead factor values has no impact on the requirements and guidance of ASTM E185-82 [4.3] or 10 CFR 50, Appendix H [4.2].
4.0 REFERENCES
Serial No.22-227 Docket No. 50-395 - Page 6 of 6 4.1 NUREG-2191, "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report," Volume 2, July 2017, ADAMS Accession No. ML17187A204 4.2 10 CFR 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements" 4.3 ASTM E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," September 1982 4.4 VCSNS UFSAR 4.5 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 4.6 ASTM E185-73, "Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels," American Society for Testing and Materials, 1973
- 4. 7 NRG Administrative Letter 97-04, "NRG Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules,"
September 30, 1997, ADAMS Accession No. ML031210296 4.8 NRG Memorandum and Order CLl-96-13, December 6, 1996, ADAMS Accession No. ML20135F473 4.9 WCAP-18728-NP, Rev. 3, "V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Evaluation of Reactor Vessel Integrity Time-Limited Aging Analysis," August 2022 4.10 CGE-RV000-TM-ME-000004, Rev. 3, "V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal Recommended Changes to the Surveillance Capsule Withdrawal Schedule," September 9, 2022 Serial No.22-227 Docket No. 50-395 Westinghouse Report WCAP-18728-NP, Rev. 3, "V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Evaluation of Reactor Vessel Integrity Time-Limiting Aging Analysis," August 2022 Virgil C. Summer Nuclear Station (VCSNS) Unit 1 Dominion Energy South Carolina, Inc. (DESC)
Page 1 of61 WCAP-18728-NP Reyision3 Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 1 of 61 August2022 V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal:
Evaluation of Reactor Vessel Integrity Time-Limited Aging Analyses
@Westinghouse
~2ot 61 Westinghouse Non-Proprietazy Class 3 WCAP-18728-:NP Rmsion *3 Serial No.22-227 Docket No. 50-395 : Page 2 of 61 V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: EYnluation of Reiartor Vessel Integrity Time-Limited Aging Analyses Tyler C. Ziegler'"'
RV/CV Design & Analysis D. Brett Lynch'"'
RV/CV Design &.AnaJ.rsis August 2022 Re\-iewen:: Donald M McNntt ill*
RV/CV Dfiign & Analysis Frank M. Nedwidek*
NucleM Operntioos Approved: Lynn A. Patterson*, M.aaager RV/CV Design & An:i.lysis Jesse J. Klingensmith*, Manager Radiation Engineering & Arutlysis
- Electronically approved records are authemicated in the electronic document management sysrun.
Westinghouse Electric Company llC 1000 Westinahouse Drire Cranbcny Tomnbip. PA 16066. *usA C 2022 Westwghouse Electric Company llC All Rights Resez.'ed.
Page 3of61 R,u sion 0
1 2
3 WCAP-l&nS-NP Westinghouse Non-Pr-oprietary Class 3 RECORD OF REVISION Incmporate Dominion's comments on Revision 0.
es are marked with revision bars.
Incorp0111te Dominion's comments on Revision 1.
es are marked with revision ba.-s.
Inccnporate Dominion's comments on CGE-RV000-1M-ME-000004 Revision 1 on the smveillance capsule schedule in Section 7.
es are marked with revision bar's.
Serial No.22-227 Docket No. 50-395 : Page 3 of 61 June 2022 July2022 August 2022 n
Angust 2022 Revision 3
Page4of61 W~.stinghouse N on-Proprietacy Class 3 TABLE OF CO~""TEJ.\"TS Serial No.22-227 Docket No. 50-395 : Page 4 of 61 Ill LIST OF TABLES***-*****************-********************************************-*******************************************************-******** iv LIST OF FIGURES..................................................................................................................................... "i EXECUTIVE SU}.11,;{ARY*******************************************************-*******************************************************- **-*** "ii 1
TildE-1..IldITED AGING ANALYSIS......................................................................................... 1-l 2
CALCUlATED FLUENCE......................................................................................................... 2-1 3
MATERIALPROPERTYINPUT................................................................................................. 3-l 4
PRESSURIZED THERMAL SHOCK ***************************************************************-************************4-1 5
UPPER-SllELF ENERGY........................................................................................................... 5-1 6
HEATUP AND COOl.DOWN PRESSURE-TEMPERATIJRE LIMIT CURVES....................... 6-1 6.1 ADJUSTED REFERENCE TEMPERATURES CALCULATION............................ -...... 6-1 62 P-TLIMITCUR.VESAPPLICABILI'IY............................................................. -*****-****6-14 7
SURVEII.LANCE CAPSULE wrnIDRAWAL SCHEDULES........ -**********-*********-**-*-**-**-** 7-1 8
REFERENCES ****************************************************************-*********************************************************** 8-1 APPENDIX A CREDIBII.lTYEVALUATION OF THE VCSNS UNIT 1 SURVEILLANCE PROGRAM.................................................................................................. *-*****************A-1 APPENDIX B EMERGENCY RESPONSE GUIDELINES.................. -*********-******-*********-**- *-**-**-* B-1 WCAP-18728-NP Angus12022 Revision 3
Page5 of61 Table 1-1 Table 2-1 Table2-2 TableJ-1 Table 3-2 Table 3-3 Table 4-1 Table 5-1 Table 6-1 Tab1e6-2 Table6-3 Tab1e6-4 Tab1e6-5 Table 6-6 Table 6-7 Tab1e6-8 Table6-9 Table7-1 Table A-I Westinghouse Non-Propriet.uy Class 3 LIST OF T.-\BLES Serial No.22-227 Docket No. 50-395 : Page 5 of 61 It' Evaluation ofTime-1.imitedAgingAnalyses Per the Criteria of 10 CFR 54.3............... 1-1 Calculated Fast Neutron (E > 1.0 MeV) Fluence at the Sun.-eillance Capsule Center for VCSNS Unit 1 *******************************************************************************-*********-*********************2-2 VCSNS Unit 1 - Maxinmro "):1ast Neutron (E > 1.0 1-feV) Fluence Experienced by the Pressure Vessel Materials in the Beltline and Extended Beltline hgions....................... 2-4 Best-Estimate Cu and Ni Weight Percent "1/2lues, Initial RTNi>r Values, and Initial USE Values for the VCSNS Unit 1 RPV Beltline and.Extended Beltline :Materials.. *-***********3-4 Calculation of Pootio:n 2.1 CF Values for VCSNS Unit 1 Sun-eillance Matcrials........ _3-5 Summary of the VCSNS Unit 1 RPV Beltline, Extended Beliline, and SurveillaDce Material CF Values based on Regulafofy Guide 1.99, Revision. 2, Position U and Position 2.1 ****************************-*******************************************************************-**- ***************3-6 RTPTS Calculations for VCSNS Unit 1 at 72 EFPY -*********************-********************************4-2 Predicted USE 1/4mes at n EFPY for the VCSNS Unit 1 Beltline and &tended Beltline 1.-Iateiials _............................ *................ _..................................*.. -*************-**-***************5-3 VCSNS Unit 1 Flnence and Fluence Factor Values for the Surntee, 1/4T, and 3/4T Locations at 56 EFPY........... *-***********************************************************************- ***************6-2 VCSNS Unit 1 Fluence and Fluence Factor Values for the Surl'ac:e, l /4T, and 3!4T Locations at 71 EFPY ****-********************************************************-*****************- *******************6-3 Calculation of the VCSNS Unit l ART Values at the 1/4T Location for the Reactor \1e§el Beltline and&tended Beltline Materials at the End of PEO (56 EFPY).. *-*******************6-4 Caknlation of the VCSNS Unit 1 ART Values at the 3/4T Location for-the Reactor Vessel Beltline and &tended Beltline Materials at the End of PEO (56 EFPY)........................ 6-6 Calcnlation of the VCSNS Uni11 ART Values for the Reactor Vessel Extended Beltline Nozzle Materials at the F.nd of PEO (56 EFPY)..................... *-**--********************************6-S Cakulation of the VCSNS Unit 1 ART Values at the l /4TLoc:ationfor the Reactor \e.s£cl Beltlwc andF..-nended Beltline Materials at the End ofSPEO (12 EFPY)*-**-*************-6-9 C-alcnlation of the VCSNS Unit 1 ART Values at the 3/4T Location.for the Reactor Vessel Behline and Extended Beltline Materials at the End ofSPEO [/2 EFPY).... *-*************6-11 Calculation of the VCSNS Unit 1 ART Values for the Reactoc Vessel Extended Beltline Nozzle Materials at the End ofSPEO f/2 EFP\') *******************************-************************6-13 Suinmar)' of the Limiting ART Valu.es................................................ *- *************-*********6-l4 VCSNS Unit 1 Recommended SUITeillance Capsule Withdrawal Sc:hedule................... 7-3 Regulatory Guide 1.99, Revision 2, Credibility Criteria................................................ A-1 WCAP-18728-NP Angust2022 RRision3
P.tge 6of61 TableA-2 TableA-3 TableB-1 Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 6 of 61 V
Calculation of Interim Cbemisuy Factors for the Credibility Evaluation Using VCSNS Unit l Smveillance Capsule Data Only.......................................................................... A-4 VCSNS Unit l Surveillanc-e Capsule Data Scatter about the Best-Fit Line................... A-5 Evaluation ofVCSNS Unit 1 ERG Limit Ca1egory....................................................... B-1 WCAP-18728-NP Angust 2022 Rtraion 3
Page7of6I Figuce2-1 Fignre3-l Fignre 5-l Figure 7-1 Westinghouse Non-Proprietruy Class 3 LIST OF FIGURES Serial No.22-227 Docket No. 50-395 : Page 7 of 61 Axial Boundary of the LOE +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 RPV Schematic for VCSNS Unit 1 ***-*************************************************************************-**3-3 Regulatory Guide 1.99, R.e,,ision 2, Position 1.2 & 2.2 Predicted Decrease in Upper-Shelf Eneigy as a Function of Copper and F1uence for VCSNS Unit 1 at fheEnd of SPEO (72 EFPY)*-******-**-****************************************-******************-*****************-************************5-5 Original Arrangement of Surveillance Capsules in the VCSNS Unit l Reactor Vessel.. 7-4 WCAP-1872&-NP Angmt2022 Revision 3
Page8 of61 Westinghouse Non-Proprietary Class 3 EXECUTIVE
SUMMARY
Serial No.22-227 Docket No. 50-395 : Page 8 of 61 vii This report presents the reactor vessel integrity Tune-Limited Aging Analyses (TI.AA) evaluations foe the Vugil. C. Summer Nuclear Station (VCSNS) Unit 1 reactor pressure vessel (RPV) in accordance with the requirements of the License Renewal Rule, 10 CFR Part 54. 1LAAs are calculations that address safety-related aspects of the RPV with.in the bounds of the cwrent 60-ye.ar license. These calrola.tions must also be evaluated to account for an extended period of operation (80 ye111S) al.so tenned Subsequent Period of Extended Operation (SPEO).
VCSNS Unit 1 is currently 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 TI.AAs evaluated in this report are applicable through 56 Effective Full Power Years (EFPY), which is deemed end of the Period of E.-ucnded Operation (PEO). Similarly, evaluations in this report perfomJed at 80 }-eatS of operation are applicable through 72 EFPY (90% capacity factor of80 ye.us), which is deemed the end ofSPEO. Updated neutron flucnce evaluations were performed and documented in WCAP-18709-NP (Reference 5), as well as in Section 2 of this report. Updated neutr011 fluence eir-aluatiom were used to identify the VCSNS Unit 1 extended be1tline materials and as input to the reactor vessel (RV) integrity evaluations in support of cmrent plant opeiations and subsequent lic61Se renewal In addition lo the RV integtitylLAAevaluations, the VCSNS Unit 1 surveillance data credibility evaluation is contained in Appendix A of this report. While not a TI.AA, Appendix B prcn.ides an Emergency Response Guidelines (ERG) assessment for VCSNS Unit 1 for completeness.
A summ.aiy of remits for the VCSNS Unit 1 Tl.AA evaluation is provided below. Based on the results of this TI.AA evaluation, it is concluded that the VCSNS Unit 1 RV will continue to meet regulatory requirements through the SPEO.
Flneoce The RV beltline and extended beltline neutron flucnce values applicable to a postulated 20-year license rene~-al period were calculated for the VCSNS Unit 1 materials. All transport calculations were carried out using the three-dimensional discrete ordinates code RAPTOR-MJG and the BUGLE-96 cross-section library. The an.al)'llis methodologie~ follow the guidance in Rega.J.atory Guide 1.190 (Reference 2). It is also consistent with the methodology descnoed 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 Secti011 2 for more details.
Prf'Ssurized Ther mal Shock All of the beliline and extended beltline materials in the VCSNS Unit 1 RV are projected to remain below the RTprs 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 de1ails_
WC-AP-18n8-NP Angust2022 Revision 3
P,11ll' 9of61 Westinghouse Non-Proprietaiy Class 3 Upper-Shelf Energy Serial No.22-227 Docket No. 50-395 : Page 9 of 61 VU1 All of the beltline and extended beltline materials in the VCSNS Unit 1 RV are projected to remain above the npper-shelf energy (USE} scaening criterion value of 50 ft-lb (per 10 CTR 50, Appendix G), through SPEO (J2 EFPY). See Section 5 for more details.
Adjusted Reference Templ'ratures and P-T Limit CUITes Applicability Chl'ck Adjusted Reference Temperatures {ARTs) are calculated for the end of PEO at 56 EFPY and for the end of SPEO ;rt 72 EFPY in ordei-to perf= an applicability check on the existing pressure-temperature (P-1) limit curves for VCSNS Unit 1. With the consideration of TI.AA fluence pcojections, revised Position 2.1 chemimy factor v-alnes, and recalculated initial RTNDT values, the applicability of the VCSNS Unit 1 cylindrical shell P-T limit curves curre:ntly in the Technical Specifications remain applicable through 72 EFPY. The conctu.sion considers the RV inleVoutlet nozzles.
Surnillante Capsull' Withdrawal Schedule With coosidemtion of a 20-year license renewal to 80 yeais of operation (12 EFPY), Capsule Y, which cnaently resides in the spent fuel pool, mnst be reinserted for additional imldiation. The sun,-eillance capsule withdrawal schedule in Table 7-1 identifies the additional exposure required by the capsule in order to mttf the guidance ofNUREG-2191 (Reference 18) (GAIL-SLR) for a capsule to be-withdrawn and tested between one and two times the pe.ak RV wall neutron flue1ice at the end of SPEO. See Section 7 for more details.
WCAP-1872&-NP Awrust 2022
~ vision 3
~
10 of 61 Westinghouse Non-Proprietary-Class 3 I
TIME-LL°'IITED AGING Al~ALYSIS Time--Limi.tedAging Analyses (fLAAs) are those licensee calculations that Serial No.22-227 Docket No. 50-395 : Page 10 of 61 1-1
- 1. Involve systems, stmctmes, and components (SSCs) within the scope of license renewal
- 2. Considtt the effects of aging.
- 3. Invoke 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 detcimination.
- 5. Involve conclnsions or provide the basis for conclusions related to the capability of the SSC to pen01D1 its intended functions.
- 6. Are contained or incorporated by reference in the cmrent licensing basis (CI.B).
The potential 1lAAs for the reactor pressure vesse-1 (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 TI..AAs.
Table 1-1 Ernuation of TDDe-Limited Aging Analyses Per the Criteria of 10 CFR 54.3 Presror~
Cak ulated Presmrized Upper-Shelf Temp-erature Tune-Limited Aging Analysis Thermal Limits for Fluence Shoc1.4>
Energy Heatup and Cooldomi Involves SSC Within the Scope of YES YES YES YES License Renewal ConsidefS the Effects of Aging YES YES YES YES Involves Time-Limited.Assumptions YES YES YES YES Defined by the Cuaeot Operating Tenn Determined to be Relevant by the Licensee in Making a Safety YES YES YES YES Deteonin.ation Involves Conclusions or Pnn,"ides the Basis for Conclusions Related to the YES YES YES YES Capability of SSC to Perf0m1 Its Intended Function Contained or Incoiporated by Reference YES YES YES YES in the CLB Note:
(a) The ~Pn,,surized Thmnal Shock(PIS) nlues arellSl!dto dmnninl!tbeapprq,rim~ Respome Guidelme (ERG)
Lillli:b catepy fer VCSNS Unit 1 ~
the end of ihe potential sub5eqaem license exlmaD period. How~nr, ERG limits ;u,,
aomde the ~
of 10 CFR Part 54.3. ERG limib are ~
in Appendix B.
WCAP-1872&-NP August 2022 Revision 3
Page 11 of 61 Westinghouse Non-Proprietary Class 3 2
CA.LCULATEDFLUENCE Serial No.22-227 Docket No. 50-395 : Page 11 of 61 2-1 Estimated RPV beltline and extended beltline fast neutron (E > 1.0 Me V) fluenres at the end of 80 yeacs of operation were calculated for VCSNS Unit 1 in WCAP-18709-NP. 1be ana1yses methodologies nsed to calculate the VCSNS Unit 1 RPV fluences followed 1he guidance ofRegulatory Guide 1.190, "Calculational and Dosimeliy Methods for Deteonining Pressuce Vessel Neutcon Flnence" (Reference 2). The.se methodologies have been appcoved by the USNRC for the beltline region, i.e., materials directly S1Jttoundiog the core and adjacent materials per 10 CFR 50, Appendix G (Reference 3), which are projected to experience fhe highest flnence. 1be methodologies, along with the NRC safety evaluation, are contained in detail in WCAP-18124-NP-A (Refecence 4). For VCSNS Unit 1, the beltline region has traditionally included the intennediate and lowec shell forgings, and the cireumfecential 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) flucnce of 1.0 x 1a17 o/cm2 at the end of the SPEO are evaluated for changes in fracture taugJmess. RPV materials that are not traditionally plant-limiting because oflow levels of neutron radiation must now be evaluated to detcnnine the a<<:llmlllatcd fl=e at the end ofSPEO. Therefore, fast neutron (E > 1.0 MeV) fluence calcuJations were perl'onned for the VCSNS Unit 1 RPV to detennine where it will exceed a fast neutron (E > 1.0 MeV) floence of 1.0 x ta17 n/cm2 at the end ofSPEO. The materials that exceed the 1.0 x 1017 o/cnl fast neutron (E > 1.0 MeV) fluence threshold and we.re not evaluated in pa.st analyses of record as part of the trnditioml be1t1ine, are n-fened to as extended beltline materials in this report and are evaluated to determine the effect of neutron in-adiation embrittlemeot during SPEO.
All the tramport calculations were canied out using the fluee.dimensional discre1e ordinates code RAPTOR-M3G and the BUGLE-96 cross-section library. The BUGLE-96 libr.uy provides a 67-groop coupled neutron-gamma ray cross-section data set produced specifically for light watec reactor applications_
In these analyses, anisotropic scattering was treated with a P3 Legendre expansion and the angular discretization was modeled with an S1& order of angular quadrature. Enagy-and space-dependent core powec distributions, as well as system opernting 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 cowpleted fuel cycles. The projection for Cyc1e 27 is based on the actual loading, but yet to be completed, fuel cycle. The projections for Cyl:le 28 and beyond, up to and including the end of PEO (56 EFPY) and the end of SPEO [/2 EFPY), are based on the average core power distnlmtions 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-entr.mt comer assembly relative powecs.
Table 2-1 gives the VCSNS Unit 1 calcula.ted fast neutron (E > 1.0 MeV) fluences at the capsule loc.atjons including all withdrawn surveillance capsules (Capsules U, V, X, W, Y, and Z).
Table 2-2 presents the fast neutron (E > 1.0 MeV) 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 ha'll-e fast neutron (E > 1.0 MeV) fluence greater than 1.0 x 1017 nlcm'- at the lowest extent of the nozzle forging to nozzle shell weld al 72 EFPY. All materials loe3ted above the nozzles will remain below 1.0 x 1a17 o/crn2 through 72 EFPY. Table 2-2 indicates that the lo\\\\"ec shell to lower vessel head WCAP-18728-NP Angust 2022 Revision3
Page 12 of 61 Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 12 of 61 2-2 circumferential weld, and all materials below it, will remain below 1.0 x 1017 n/c:m.2 through SPEO. Figme 2-1 shows the axial boundary of the 1.0 x 1017 n/cm.2 fluence threshold (at 54 EFPY and 72 EFPY) as a function of azimuthal position (Z versus 8).
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 Cyclr 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27'>)
Calculated Fast Neutron (E > 1.0 IeV) Flnence at the Surnillance Capsule Center for YCSNS Unit i<->
Cnle Cumulath-e Flurnce u itgth Operating (n/em2) lime (EFP\')
(EFPY) 17° 20° 1.13 1.13 6.75E+l8"UJ 5.90E+l8 0.67 1.80 1.01E+19 8.94E+18 1.13 2.93 U 4E+tg(<l l.36E+l9 1.16 4.09 2.03E+l9 1.80E+l9 0.95 5.04 2.51E+t9CtlJ 2.24E+l9 1.17 6.21 3.13E+19 2.79E+l9 1.22 7.43 3.63E+19 3.24E+l9 1.19 8.61 4.13E+l9 3.69E+19 1.27 9.89 4.66E+19 4.15E+19 132 11.21 5.18E+19 4.63E+t9<*>
136 12.56 5.78E+19 5-15E+19 137 13.94 6.35E+19 5.66E+19 1.09 15.03 6.76E+19 6.02E+19 133 16.36 734E+19 6.53E+l9\'I 135 17.71 7.88E+19 7.01E+19<1) 1.34 19.05 8.42E+19 7.49E+19 138 20.43 9.00E+19 8.01E+19 1.30 21.73 9.52E+19 8.49E+19 131 23.04 1.01E+20 8.97E+19 1.36 24.41 1.06E+20 9.46E+19 1.29 25.70 1.11E+20 9.93E+19 1.29 26.99 1.17E+20 1.04E+20 1.34 28.33 l.23E+20 l.09E+20 1.32 29.65 l.28E+20 1.14E+20 136 31.01 1.34E+20 1.19E+20 1.37 32.38 l.39E+20 1.24E+20 1.37 33.75 1.45E+20 1.30E+20 No bias 011 ths peripheral mid re,-entrant comu assembl)* relative powers Future\*J 36.00 1.55E+20 1.38E+20 Future{JJ 42.00 l.80E+20 1.61E+20 Future\11 48.00 2.05E+20 l.83E+20 WCAP-18728-NP Angim 2022 Revision 3
Page 13 of 61 Serial No.22-227 Docket No. 50-395 : Page 13 of 61 Westinghouse Non-Proprietary Class 3 Table-2-1 C:ikufated Fast Neutron (E > 1.0 Me\) Fluence at the Sun*eillance C:ip$ule Center for VCS1'-S Unit 1<->
~-ell' Cumulafu-e Flnence Cycle ungth Operating (n/cm2)
([FPY)
Time 17° 20° (EFPY)
Futnre'-'1 54.00 230E+20 2.06E+20 Future"
60.00 2.55E+20 2.28E+20 Futnre1'1 66.00 2.80E+20 2.51E+20 FutureW 72.00 3.05E+20 2.73E+20
+ 10% bias on the periplreral and re-entrant comer assembl;y relative Future© 36.00 1.56E+20 Future© 4200 1.83E+20 Future© 48.00 2.11E+20 Future© 54.00 238E+20 Future© 60.00 2.66E+20 Future© 66.00 2.93E+20 Future© 72.00 3.21E+20 Notes:
(a) In£n11n;rtioo tmn fu>m WCAP-I8709-NP (lWi,n,,:,ce 5).
(b) This '\'ilue is applicable to~
U.
(c) lhis ~
is ~b!e to~ V (d) This '\.uue is ~ble to Capsule X (e) This '\'Uue is ~ble to YpSule W.
(f) This 1,-m!i! is ~ble to ~
- z.
(g) This.,_-;due is appliab!e to Capsule Y.
l.39E+20 1.64E+20 1.88E+20 2.13E+20 2.38E+20 2.63E+20 2.87E+20 (b) Cycle 27 was tbe cqnnt oper,,fmgcycle at the tim,, lmSU!DII.IIY ~
mis :mlbmed.
(i) Values beymid Cycle 27 ara based on the.n.~ cora pcmw distribul:iotlS a:nd reactor apemingcomitiOl!S ofCycles25, 26, md27 md an, d,,tl'Dmll'dbofhmth.w,hrifbo1it a I.I bias oo. the peripbera md~
comeJ" :assemblyruaim!J)CJWt'l5.
2-3 WCAP-18728-NP Angust2022 Revision 3
Page 14cf61 l\htuW Loc::ition
&lmded.Belllme Mattriah Bellline Mmriili Omsidt ofbcltlme region WCAP-18728-NP Wmingbouse NOJ1-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 14 of 61 2-4 Tablt 2-2 YC~S Unit 1-i\lmmum Fad l'.tulron (E > 1.0 Mt-\).Flutnct E:q,tritnctd by tht PttMun Y<=el M:tttrials in tht Beltlint and E:s:ttndNI Btltliat ~on<
Projunons i.1ih no bias on the pmphnal tl1ld re.ffltrarrl comer assmnbly rd,,m,-. JIO>IWS Mattrial Fast l\tnlron (E > 1.0 Mt\) Flnmrt (n/cm1) 33.75.EFP\ 1,t 36Dl'Y 42 EFPY 48EFPY 5-I EFPY 60EFPY Ialtt Nozzle to Nozzle Shell Weld 1.41E+17 150E+17 l.75E+17 2.00E+17 2-24E+17 2.49E+17 Ocmwt -
fl Inltt Nozzle Postulaltd l.68E+16 l.79E+16 209E+16 239E+16 2.68Et16 2.98E+16 l/4T Flaw Outltt Nozzle to Nozzle SMIIWdd 5.99E+16 639E+l6 7.44E+16 8.49E+16 9.55E+16 1.06E+l7 acm-es1 awii)
Omlrt Nonie Postulatld 8.54£+15 9.11E+15 l.06E+16 121E+16 137E+16 1.52E+16 1/4TF!iw Nozzle Shd)('ol 1.83E+18 1.95E+18 226E+18 2.5SE+18 2.&9E+18 320E+18 Nozzlt..fo-ln!mnedir.e 1.94E+18 2.07E+18 240E+l8 2 74818 3.07E+18 3.40E+18 Shell Cimnnfl!fflllw Weld Int~te Shell 4.14E+19 4.40E+l9 5.10E+19 5.81E+19 6.51E+l9 721E+19 IntmntdiAlae Shell Lo~todinal Wtld-1.40E+19 1.49E+19 1.72E+19 1.96E+l9 2.19E+19 2.42E+19 45*ms*
In!Oilllldia~ fo-1.ower Shell 4.13E+19 4.40E+19 5.10E+19 5.S0E+l9 6.51E+19 721E+19 Cimmifamtial Weld I..cruw Shell 4.14E+19 4.40E+l9 5.11E+19 5.81E+l9 6.52E+l9 723E+19 urn-er Shell Lonmudinal 1.42E+19 1.51E+19 l.7SE+19 1.98E+19 222E+19 2.46E+19 Weld-135°/315° Lem-er Sbdl lo Bottom
!kad Cin:umfermlw 4.69E+15 5.00E+15 5.81E+15 6.62E+15 7.43E+15 824E+15 Wdd(<1 66 EFPY 2.74E+17 3-28E+16 l.17E+17 l.67E+l6 3.52E+l8 3.74E+18 7.92E+19 2.66E+19 7.91E+19 7.93E+19 2.70[+19 9.05E+15 72EFPY 2.99E+17 3.58E+16l4 127E+17 l.82E+16(4 3.83E+l8 4.07E+18 8.62E+19 2.89E+19 8.62E+19 8.64E+19 2.93E+19 9.86E+15 Angust2022 Revision 3
P-15 of61 Matuiol Loutio11 F.mnded Bellline Materials Behline :Mataials Ouwdi, of belllillf r,gion Na!=
Westingbou,,e Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 15 of 61 2-5 VCSXS Urut 1-M:mmrnn Fast Neutron (E > 1.0 Me\') Ilumu ~tritnced by the Pres~ure Vessel Materials in th.e Bdtline and Extended Beltline ~ons Proj<<ttoru Mith a+ 10-/4 bias on 1M peripheral llJltl J'!e-9ltrtmJ coma-imembly n/mn,;, JXl"W:.
Material Fast Neutron (£> 1.0 ll.Ie\') Fluenc,e (n/cm')
33.75 Ill'\ vl 36EFP¥.U EFPY 48EF1'¥ 5-tlll'Y 60 EFPY 66EF1'¥ 7lEFPY lnlet Nozzle to Nozzle Shell l.41E+17 151E+l7 l.77E+17 2.04E+17 230Et-17 2.57E+17 2.83E+l7 3.10E+17 Weld tlowest exfad) lnlet Nozzle Postulated 1.68£+16 1.80E+16 211E+16 2.43EH6 2.74E+16 3.06E+16 3.38E+16 3.69E+16'l l/4TFlaw Outltt Nozzle to Nozzle Shell Weld 5.99E+l6 6.42E+16 7.54EH6 8.66E+l6 9.79E+16 1.09E+17 1.20E+17 132E+17 tlowest _._...-.
Outltt Nozzle Postulated 8.54E+15 9.14E+15 l.07E+16 1.24E+l6 J.40E+16 1.56E+16 1.71E+16 1.88EH6'1 l/4TFlaw NozzieSJiell{1>)
1.83E+18 1.96E+18 2.30E+18 2.64E+18 2.9SE+18 3.32E+18 3.66E+18 4.00E+18 Nome-tG--~te 1.94E+18 2.08E+18 2.44E+18 2.80E+l8 3.16E+l8 3.52E+18 3.89E+18 4.25E+18 SbeU Cimmlfemltw Weld Intamediate Shrll 4.14EH9 4.42E+19 5.19E+19 5.96E+19 6.73E+19 7.50E+19 827E+l9 9.04E+19 Intmnediate Slid Longitudinal Weld-1.40E+l9 150E+19 l.75E+19 2.01E+19 226E+19 2.52E+l9 2.78E+l9 3.03E+19 45*ms*
Intmnediare-to-I..ower Shell 4.13E+19 4.42E+19 5.19E+19 5.96E+l9 6.73E+19 7.50E+l9 827E+19 9.04E+19 CircumfeRnlial Weld Lower Shell 4.14E+19 4.42E+19 5.20E+19 5.97E+19 6.74E+19 752E+19 8.29E+19 9.06E+19 1..owu ::ih~
Weld-135"/315° 1.42E+19 152E+19 1.78E+19 2.04EH9 230E+19 2.56E+19 2.!P..E+19 3.08E+19 I.mm-Shdl to Bottom Head Circumf,mdial 4.69Hl5 5.03E+15 5.91E+15 6.79£+15 7.67E+15 8.55E+15 9.44E+l5 1.03E+16 Weld{<l (a) V,J,,e limi is Ill< poj<<led EFPY at lhe om of Cycle 27.
(b) E,:poe,n,"Ulll!J b b n=le,hell~
u-.l.c!, ""'bour.l..tbytbe opc=n,nas Cm-lhe naz:zlo sh!!!l(ah -sbtll).
(c) Mnimmn opo,mo n.1,,r; occm al b RPV oatorDmll>.
(cl) \¥hi!., Ibo fhmice at tm l<<afionis Jess Ihm IB<-17 n'arr, itis idenlmed as o!io:>dod bdliJ:i,, siDct p<ldians o!d>tDCIZZ!e....,..,.i. 1ht ai!aian.
WCAP-18728-NP August2022 Revisi<m3
Page 16of6t Westinghouse Non-Proprietuy Class 3 Serial No.22-227 Docket No. 50-395 : Page 16 of 61 2-6
--3J.75 EFPY(EOC27)
---*5.f.EFPY
--72EFPY 40<}
o N~
Pootul td l 4T F!aw NllZ21eLoH &tWeld E.'!!tti 300 lOii 0
--=-'C':--:,.'&_~--=::~--;.___.~.
Noulc.to-I,,rnmfdi&t! Slllll Circ.. U'tld (HruXc.:4l't7S4)
LOl\"i!IS!ltll
-10.)
{Hst N.o C9923-l)
LINHS!llll (He¥ No.. C992J-2) 0 Nczil.1 Sh.J1
{Hm Na Cill2l-2) bilermedia.le Shell
@e:n Na.. A9 m.1,
-300 Lau~ Sl:.!1!-tc-Botlo!!l Had Cir:. We1:1 lH*!d No.3]~P66) 0 90 m
HO 170 31}
-4t4 0
3ff.l Figure2-l
.-uial Boundary of the l.OE+l7 u/crn.1 Fast:l'\entron (E > 1.0 lie\) Fluence Threshold in the +Z Direction at 33.75 (end of Cycle 27), 5-1, and 72 IIPY WCAP~l872&-NP A.ugust 2021 Re\ision 3
Page 17 of 61 Westinghouse Non-Proprietary Class 3 3
MATERIAL PROPERTY INPUT Serial No.22-227 Docket No. 50-395 : Page 17 of 61 3-1 The requirements for RV integrity are specified in 10 CFR 50, Appendix G (Reference 3) and 10 CFR 50.61 (Refemice 6). The beltline region of the RV is defined as the following in 10 CFR 50, Appendix G:
... the region of the reactor vessel (shell material incblding welds, heat affected zones, m,d plntes or forgings) that directly sum,unds the effective lteight of the active core and adjacent regions of the reactor vessel that am predicted to experience sufficient neutron mdiah"o11 damage to be considered in the selection of the most limiting materlal>>tth regani to radiation damage.
The VCSNS Unit 1 beliline materials coosist of two (2) Intennediate Shell Plates, two (2) Lower Shell Plates, and their associated welds. The VCSNS Unit 1 smveillanre plate material was made from RV Intennediate Shell Plate 11-l, Heat#A91 54-1. The VCSNS Unit 1 RVbeltline 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 n=tron flnence exposure greater than 1.0 x 1017 n/cm.2 (E > l.O MeV) at the end of the licensed operating period should be considered to experi.ence neutron embrittlement. Based on the results of Section 2 of this report, the materials that exceeded the 1 x 1 ot7 n/cm2 (E > 1.0 MeV) threshold at 72 EFPY that were not included within the original beltline are considered to be the VCSNS Unit l extended beltline materials and are evaluated to detennine their impact on the proposed SPEO of operatiOll. The VCSNS Unit 1 RV extended beltline contains one (1) Nozzle Shell-to-Intemiediate Shell circumferential weld, hvo (2) Nozzle Shell Plates (also termed upper shell), two (2)
Nozzle Shell longitudinal,relds, three (3) Inlet Nozzles, three (3) Ootlet Nozzles, and the six (6) Nozzle-to-Nozzle Shell welds. Only those materials with a fluence greatec than 1 x 1<>17 u/cnl (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 tams "girtbn and "circumfecential" are used interchangeably; herein, these welds shall be refelled to as cin:nmfefefltial welds. Similarly, for RV welds, the lem1s "axial" and "longitudimtl" are used interchangeably; herein, these welds shall be referred to as longitudinal welds.
The unimldiated material property inputs used for the RV integrity evaluations herein are contained in PWROG-21037-NP (Refecence 7). PWROG-21037-NP defined or redefined many of the matecial properties and chemistty values using the most up-to-date methodologies and all available data; therefore, the values utiliz.ed herein supersede previously documented vames. The sources and methods used in the detennination of the chemis1ry :fuctOIS and the fracture toughness properties are summarized below.
Chemical Compositions The best-estimate copper (Cu) and nickel (Ni) chemical compositions for the VCSNS Unit l beltl.ine and elrte.ruied beltline materials are presented in Table 3-1. The best-estimate weight percent copper and nickel WCAP-18728-NP Angmt2022 Re\>ision 3
P.tge 18 of 61 Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 18 of 61 3-2 values for the beltlinr and extended beliline materials were previously reported in PWROG-21037-NP and were included in RY integrity evaluations as part of this TLAA effort.
Fracture Toughn~ PropertiH The most up-to..date initial RTh'Dr and initial USE values ace documented in PWROG-21037-NP for VCSNS Unit 1. The beltline and exten~
beltline material properties of the VCSNS Unit I RV are presented in Table 3-1 hemn.. The differences between the unirnidiated RTNDr values summarized in the FSAR and those determined herein are a result of a change in curve-fitting method (hand-dra\11'11 versus hjperl,olic tangent) used to fit the Chatpy V-notch test data.
Chemil.try Factor \'alues 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 R.egn!atoty Guide along with the be-St-estimate copper and nickel weight percent values ( contained in Table 3-1 ). Position 2.1 uses the sun-eill.ance capsule data from all capsules tested to date and surveillance data from other plants, as applicable.
Credibility ev-alnations of the VCSNS Unit 1 sunreillance data ar-e prorided in Appendix A of this report.
The calculated capsule flue.nee values ar-e provided in Table 2-1 and are used to detennine the Position 2.1 CFs as shown in Table 3-2. Table 3-3 summarizes the Positions 1.1 and 21 CF values deteanined for the VCSNS Unit 1 RPV belttine and extended beltline materials.
WCAP-18728-NP An.,aust 2022 Re\>ision 3
P3ge t9 of6t Serial No.22-227 Docket No. 50-395 : Page 19 of 61 Westinghouse No11-Proprietary Class 3 3-3 1--Repr~ents \ eswl ~-eld~ I Figure3-l WCAP-18n&-NP FLAAaE l lGI.HENTS
- F. t~1100A lDS 18 TlflU 23 REF. l ~llOOA Intermediate Shell RPV Schematic for VCSNS Unit I Angust2022 Rf\'ision3
Paoe 20 of61 Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 20 of 61 3-4 Table 3-1 Best-Estimate Cu and l\1 Weight Percent Values, Initial RTl'\DT Values, and Initial lJSE
\'n.lue-s for the VCSNS Unit I RP\. Brltlin.e and Extended Bl'ltline Interials
lnilial UnilTlldiated laterW Identifkation Wt. % Cu Wt. %?\1 RTN>T OJ USE (OJ) ffi (ft-lb)
Bdtline Intermediate Shell 11-1 (Heat# A9154-1) 0.10 0.51 21 0
76 Jnlmnediate Shell 11-2 (Heat# A9153-2) 0.09 0.45
-20 0
107 Lower Shell 10-1 (Hl'llt # C'9923-1) 0.08 0.41 5
0 106 Lower Shell 10-2 (Heat# C'9923-2) 0.08 0-41 4
0 92 Intemifdiate Shd.l Long. Weld Seams BC & BD (Heat # 4P4784, Flux Type Lmde 124, Lot# 3930)
Jntezmediate to Lower Shell Cm:. 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 H 4P4784, Flm Type Linde 124, Lot# 3930)
Entnded Bfltline Nozzle Sbdl 12-1 (Heat # C9955-2) 0.13 0.57 9
0 101 Nozzle SMll 12-2 (Heat # C-0123-2) 0.12 0.58 15 0
91 Inlet Nozzle 436B-1 (Heat# Q2Q41W) 0.127<bl 0.76
-20 0
152 Inlet NozzJe 4368-2 (Heat# Q2Q39\ll) 0.127<b) 0.82 0
0 115 Inlet Nozzle 4368-3 (Heat fl Q2Q39W) 0.12'7tl>)
0.82
-20 0
138 Outlet Nozzle437B-1 (}mt# Q2Q40) 0.127<bl 0.85
-10 0
159 Outlet Nozzle 437B-2 (Heat# Q2Q40W) 0.12'7tl>)
0.80
-10 0
165 Outlet Nozzle 437B-3 (Heat # Q2Q44W) 0.12700 0.78 0
0 155 Nozzle to Intennediate Shell Cm:. Weld Seam AC 0.05 0.91
-49 0
86 (Heat# 4P4784, Flu:t Type Lioo.e 124, Lot# 3930)
Nozzle Shell Long. Weld Seams BE and BF(<>
o.cw=>
1.01<<)
10C<)
rf<)
go(<)
Inlet/Outlet Nozzle Foigings to Nozzle Sh.ell Weld Seams l5AIB!C & 16AIB/O<)
Surreillance Material<">
Jntemiediate Shell 11-1 (Heat# A9154-1)
Smveillance Weld 0.04 0.95 (Heat# 4P4784, Flt<< Type Linde 124, Lot# 3930)
Nol!!s:
(a) Th! infonnation is mradi>d from PWROG-21037-NP ~
7). All 1.Mll!S ;a:re based on inf~
extracted from the V.C.
SlUllllll!I" Unit I CMIRs aDdlor TI!S.Sel fabncaliQll IKOrds, ww= noted cihem-ise..
(b) Gensic nlue for SA-508 Cbss 2 IJDZZ!,, fuq;inp fuzn PWR.OG-15109-NP-A ~
9).
(c) Th! specific hilt mmiberus"'1 in weld 22IDS could not be ide.ntitied. To addnss lhese situations,..mies "-eel! determine~ on a re1,;m, of all V.C. 5tmllill!I" v.-eld heats used in lhe flbrication of the VCSNS Unit I RV. The.e generic n lue; m!11! defined in PWR.OG-21037-NP ~
e 7).
(d) Sun-e:ill.mce pLm and v.-nd data ~
in WCAP-16298-NP (Re.mmce 10).
WCAP-18728-NP Allgust 2022 Revision 3
Page 2 1 of 61 Westinghouse Non-Proprietary-Cl.ass 3 Serial No.22-227 Docket No. 50-395 : Page 21 of 61 3-5 Table 3-2 Calculation of Position 2.1 CF Values for VCS?\S Unit 1 Sun;eillance Iaterial,;
Capsult lliamred IFP&R.Tiwr Material Capsule Flnt c~II)
- fP)
ART~'>
FF1
(:s: IOU o/cm2,
("F)
E>l.OMe\)
("F) u 0.675 0.890 36.1 32.1 0.792 V
1.54 1.119 532 59.6 1.253 Inlennedi.ate Shell 11-1 X
251 1.247 383 47.8 1.555 (Longitudinal) w 4.63 1387 662 91.8 1.924 z
653 1.451 98.9 143.5 2.106 u
0.675 0.890 14.5 12.9 0.792 V
154 1.119 32.1 35.9 1253 X
251 1247 26.7 33.3 1.555 Intermediate Shell 11-1 w
4.63 1387 57.8 802 1.924 (I'ransvene) z 653 1.451 87.0 1263 2.106 SUM:
663.4 15261 CFn-1 =L(FF
- MlTNDI) + Z(FF2)=(663.4) +(15261)=435"F u
0.675 0.890 28.6 25.4 0.792 (21.1)
V 154 1.119 592 663 1253 (47.0)
X 251 1247 28.6 35.7 1.555 SUI\-eillance Weld (22.7)
(He.at #-IP4784) w 4.63 1387 54.8 76.0 1.924 (43.5) z 653 1.451 822 1192 2.106 (652)
SUM:
3'll..7 7.630 CFS=. w..i =L(FF
- MlT= ) + I:(FF2) =(3'll..7)+ (7.630) =423Gf Notes:
(a) F1neice taken from Table 2-1.
(b) FF= fluem:e bdir= f."1'1- 010-~crn_
(c) Musurai MtTi= bkmfnm WCAP-16298-NP ~
10). The VCSNS Unit l sun-ullmi:e weld musuredMlT,mr results m-n, been adj~ by a ratio of 126 ID accomd for chmiistry difFeruices beiv;em the Heat ii 4P4784 sun'2illance weld (CF= 54°F) arid R.V welds (CF= 6S"F). The unadjusted musured MIT>= nlu.es are listed in~
WCAP-18n8-NP August 2022 Revision 3
Page 22 of 61 Serial No.22-227 Docket No. 50-395 : Page 22 of 61 Westinghouse Non-Propriet.uy Class 3 3-6 Table 3-3 Summary of the VC:SXS Unit I RP\' Beltline, Extended Beldine, and Surnillrulce Material CF Values based on Regufatory Guide 1.99, Rmsion ?,
P osition I.I and Position ?.l Chr~* Factor Mattrial Drmiption Position Ll <->
Position ?.I (I>)
C°F)
(OF)
Btltli111 Intermediate Sht:ll 11-1 (Heat H A9154-1) 65.0 43.5 Intermediate Shell 11-2 (Heat # A9153-2) 58.0 Lower Shd.1 10..1 (Heat# C9923-D 51.0 Lower Sbell 10..2 /'Heat# C9923-2) 51.0 Intmnedi.ate Shell Lomr. Weld Seams BC & BD 68.0 42.3 Infeimediate to Lower Shell Cire. Weld Seam AB 68.0 42.3 Lower Shell Lon2. Weld Seams BA & BB 68.0 42.3 E.umdrd Beltlin, Nozzle Shell 12-1 ffieat # C9955-2) 90.1 Nozzle Shell 12-2 l'H""t # C0123-2l 82.6 Inlet Nozzle 4368-1 (Heat# 0 2041 Wl 92.1 Jnlet No.zz:le 436B-2 l'He.at # 02039W) 93.0 Inlet Nozzle 436B-3 (H..,.t # 02039W) 93.0 Outlet Nazzle 437B-l lHe.at # 02040) 93.0 Outlet Nozzle 437B-2 lHP.at # 02040\\\\')
93.0 Outl.etNo2Zle 437B-3 <Heat#02Q44W) 92.6 Nome to Intennediate Shell Cire. Weld Seam AC 68.0 42.3 Nozzle Shell Loim. Weld Se.ams BE and BF 82.0 Jnlet/Oatlet Nozzle Forl!llll!S to NazzJe Shell Weld 82.0 Sun*~1la11c-e M11tmals Inlamediate Shell 11-1 65.0 Swveillanre Weld 54.0 Notes:
(a) All '\.Ines = based on Tables 1 md 2 of~
Guide 1.99, Rerision 2 (Positia:i 1.1) using the ui md Ni ~
pacmtruues git:min Table 3-1 oflhisreport. DrlEi illdicm WWI a at~isnotappmble to the maJ:aial.
(b) Values are from Table 3-2 of this report.
.Angus12022 R.evision3
Page 23 of 61
'Westinghouse Non-Proprietary Class 3 4
PRESSURIZED THERMAL SHOCK Serial No.22-227 Docket No. 50-395 : Page 23 of 61 4-1 A limiting condition on RPV integrity known as Pressurized Themial Shock: (PIS) may occur during a severe system transient such as a loss-of-eoolaot accident (LOCA) or steam line break. Such transients may challeflge the integrity of the RPV under the following conditions: severe overcooling of the inside sncface 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 wait In 1985, the USNRC issued a foonal ruling on PTS (10 CFR 50.61 (Reference 6D that established screening criteria on pressurized water reactor (PWR) vessel embrittlement, as measured by the maxinmrn reference nil-ductility transition temperature in the limiting beltline component at the end of license, termed RTPTS.
RT FrS screening values were set by the USNRC for belttine axial welds, forgings or plates, and for beltline cin:umferential weld seams for plant operation to the end of plant license. All domestic PWR. vessels have been required to evaluate vessel embri.ttlemem 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 maJre the procedure for calculating the reference temperature for pressurized then:nal shock: (R.Tm) values consistent with the methods given in ~gulatOty Guide 1.99, Revision 2 (Refer-ence 8).
These accepted methods were used with the smface tluence values of Section 2 to calculate the following RTPTS \lalues for the VCSNS Unit 1 RPV materials. The end ofSPEO RTvm caknlations ace presmted in Table 4-1.
PTS Conclu..ion All of the beltline and extended beltline materials in the VCSNS Unit 1 RV are below the Rf= screening criteria values of270"F foe base metal and/or longitudinal welds, and 300°F for circumferentially oriented welds through SPEO (/2 EFPY). These RTprs values are based on the revised initial RTNDr '-'rulles in PWR.00-21037-NP (Reference 7), which are de"v-eloped using ASME Section III (Reference 11) and, if needed, NUREG..0800, BTP 5-3 (Reference 12) methodologies. Limiting tluence values corresponding to the lowest extent of the nozzle welds were med to ca.kn.late fhe RTPTS values foe both the nozzle welds and nozzle forgings.
The VCSNS Unit 1 limiting RTm value for base metal and longitudinal welds at 72 EFPY is 152.5°F (see Table 4-1 ), which c01TeSpon.ds to VCSNS Unit 1 Intermediate Shell 11-1 based on Regulatory Guide 1.99, Position 1.1. Note, that there is sut'\"eillance data available for this material that indicated the ~T:imr will be less than that predicted by RG 1.99, Position 1.1. Howevec, because the surveillance data was detennined to be non-conservative, it is not credited here. Tue VCSNS Unit 1 limiting Rf PTS value for circnmferentially oriented welds at 72 EFPY is 42.5"F (see Table 4-1), which corresponds to the VCSNS Unit 1 Intennediate to Lower Shell Circumferential Weld Heat # 4P4784 oosed on Regulatory Guide 1.99, Position 2.1 with credible surveillance data. The credible surveillance data for Heat# 4P4784 supersedes the higher RTPIS based onRG 1.99, Position 1.1. Note, both the Position 1.1 an.d2.1 remain below 300°F.
WCAP-18728-NP Angust2022 Revision3
f'a9e24 al GI Werungbonse Non-Propri*t.uy Class 3 Tabk4--1 RTns Cakula tio 1L1 (or \"CSXS Unli 1 at 7l EFPy<,/
R.G.
SmFhm,cr
- u.a1,ru1 1.99, CJ1')
(x 101' alr111',
Surf.
RT~(t)
Rel".?
E > L01f,\ ')I~
fill)
("F)
Position Boldinr Malt riah hitmiiedill* Shell l l-1 (Heal #.A9_154-l) 1.1 tit9
.i~
1.501 21 Usinv 1IOIHffdibl*.naw:i//Jmce dattfV 2.1 43.5 9.04 1..501 21 lnlmmdillr Shell 11-2 (Hell fJ A!l153-2)
I.I 58.0 9.04 1.501
-20 l.ow,r Shell 10-1 (Heat II C9923-1)
I.I 51.0 9.06 1.501 5
1.cm-e, Shell 10-2 (Hell I C9923-2)
I.I 51.0 9.06 1.501 4
Int~ Sbellloog. Weld SeaimBC&BD 1.1 68.0 3.03 1.293
-49 (Bnt# 4P4784)
UrinJ? cndibh nm..nJance d,m/11 2.1 423 3.03 1.293
-49 Im~
lo i...n-Shell Cirt. Weld Sem,AB (Hell 11 1.1 68.0 9.04 1.501
-49 4P4784)
Ustn~ adbh !illr'Milmre datifll 2.1 423 9.04 1.501
-49 Lov,-er Shell Loog. Weld ~ ams BA & BB (Hntl 4P4784) 1.1 68.0 3.08 1.297
-49
~
crtdib/.e JJDWi11anc11 tbfdll 2.1 423 3.08 1.297
-49 utmc M JSfll IJlf MaltlUIS Nozzle Sbell 12-1 (Heat II C9955--2)
I.I 90.1 0.400 0.746 9
Nozzle Sbell 12-2 (Hffl II C0123-2}
1.1 82.6 0.400 0.146 15 lnlrtNozzle 436B-1 (Hut iJ Q2Q41W) 1.1 92.1 0.0310 0.224
-20 Inld Nozzle436B-2 (Hat il 02039W) 1.1 93.0 0.0310 0.224 0
Inltt Nozzle 436B-3 (He.II fJ Q2Q39W) 1.1 93.0 0.0310 0.224
-20 Outlti Nozzle 437B-1 (Heat II Q2Q40) 1.1 93.0 0.0132 0.132
-10
~
Nozzlt 4378-2 {H5t# Q2Q40W) 1.1 93.0 0.0132 0.132
-10 ru!el Name 4378-3 ~
II Q2Q44W) 1.1 926 0.0132 0.132 0
NOlZle to Immnediate Shell Cirt:. W.M Semi AC 1.1 68.0 0.425 0.762
-49 (Bnt Ii 4P4784}
thing ardibh SJU\wlJmrl dalrlfl 2.1 42.3 0.415 0.762
-49 Nozzle Sbfll Long. Wdd Semi.s BE md BF I.I 820 0.400 0.762 10 WCAP-18728-KP Serial No.22-227 Docket No. 50-395 : Page 24 of 61 PndKtNI ART~
'11 CJ.1
("F)I')
C'F) ~
?1.5 9.9 J7.0 653 0.0 17.0 87.0 0.0 17.0 16.6 0.0 17.0 16.6 0.0 17.0 87.9 0.0 28.0 54.7 0.0 14.0 1020 0.0 28.0 635 0.0 14.0 88.2 0.0 28.0 54.9 0.0 14.0 67.2 0.0 17.0 61.6 0.0 17.0 20.6 0.0 103 20.8 0.0 10-4 20.8 0.0 10.4 123 0.0 6.1 123 0.0 6.1 122 0.0 6.1 51.8 0.0 25.9 322 0.0 14.0 61.2 0.0 28.0 4-2 M
("F)
("F) 34.0 151.~
34.0 1203 34.0 101.0 34.0 115.6 34.0 114.6 56.0 94.9 28.0 33.7 56.0 109.0 28.0 42.5 56.0 95.2 28.0 33.9 34.0 110.2 34.0 110.6 20.6 21.2 20.8 41.6 20.8 21.6 123 14.5 123 14.5 12.2 24.4 51.8 54.7 28.0 11.2 56.0 127.2
~
2022 Re\i'iiou3
P*25al81 Westingbous<<e Noo-Proprietuy Class 3 Serial No.22-227 Docket No. 50-395 : Page 25 of 61 4-3 Tablt 4-1 RTns Cakalatloo1 for YCSXS Unit I :it 72 £JP\,(,)
R.G.
Matuial 1.99, CTI')
Rn.?
PMt.t..
lnlet/Outld Nozzle Forpngs to Nozzle Shell Weld Seams 15A/BIC& 16A/B/C u
820 Nott.:
(a) 'Ju 10 CfR. 50.61 IDl!ffl0do!o11 wu 1llilimd m tbo ~
mtbo RTm nlms_
(l,) a..misaybcbs ara twn &an Tabl.3-3.
(<) ~
lilbD fram T.b!e 2-2 oftbi:, n;,crt (d) FF=fba:ebcmr* _,._.,..,.Oli_
(e) JU",_,lll nme, bnD fram Tm!ti 3-1.
S1uf. Fhlm<<
(x 101' n/cm1, Surf.
E> l.illt\')(<l Illll 0.0310 0224 PNdictNI RTlll1I(C)
MtT.sur Cl!
0~
M
- .\RT
(°I)
("J)l*l
(°I) fF)CQ
("F)
("F) 10 18.4 0.0 9.2 18.4 46.7 (f) P.- 10 CfR. S0.61, the boselDl!lala* = 17'1',dim~
cbt,..-. DOC-<ndiole moot DZl todolmnim tho CF, ;md b i,,,,,IDl!laJ a, =8.5"1'-..fm cmliblesmmlhm:e dm an used. Also, p,< 10 CfR. 50.61, 1he,n.ld -.I <JA ~ 2S"F,.t.,, _,.~ dab ""' ""'1<!1!dible craot med lo cl.:mm. tlie CF, am! 1he weld motaI en & l4"F when credible scrnilJmee dab""' used.~. a*nood-o:D!ed 0.5'MIT>= f<<oilm base metils <<..uh, will,<< ffllhoo:I ""'1!ill:mce dab.
W TIM cnd,1,i]ijyenlmtm fu iho ~
Unit l ~
elm m Appe,dix A oflhisn,port clonmiad t1m b VCSNS Umt l smmllma! dab b-tbo ~
Sbell ll-1 (Hul#A915t-l) is deemed~ ml dio Sar\
Weld (Hmf 41'4784) is wmodawd,.b!a.
WCAP-18723-NP August2022 Reruian 3
Page 26 of ll1 Westinghouse Non-Proprietary Class 3 5
"UPPER-SHELF ENERGY Serial No.22-227 Docket No. 50-395 : Page 26 of 61 5-1 The decrease in Cbaqiy upper-shelf energy (USE) is associated with the detttmination of acceptable RPV toughness during the license renewal period when the vessel is exposed to additional inadiation..
The requirements on USE are included in 10 CFR 50, Appcndi,"'t G (Refet"cnre 3). 10 CFR 50, Apperulix G rtqUires utilit~s to submit an analysis at least 3 ye.ars prior to the time that the USE of any RPV material is predicted to drop below 50 ft-lb, as measured by Cluupy V-notch specimen testing.
There are two metho~ that can be used to predict the decrease in USE with irnldiation, depending on the availability of credible smveillance capsnle data as defi.oed in Regulatory Guide 1.. 99, Revision 2 (Reference 8). Foc vessel beltline materials that are not in the smveillance program or have non-credible data, the Chmpy USE (Position 1.2) is assumed to decrease as a function of flucnce 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 detemiine the Chmpy USE of the smveillance 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 Positioo 1.2 projected USE value. Note, if data from the S[l[Veillance materials is detennined to be non-crechole for determination of AR.Twr by Credibility Criterion 3 of Regulatory Guide 1.99, Revision 2, then "they may be credi"'ble foe determining decrease in uppec-s.helf eneigy if the uppei-shelf can be clearly determined, following the ddinition given inASTM E 185-82.n The 72 EFPY Positioo 1.2 USE values of the vessel materials can be predicted using the cotresponding l/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 22 USE values are detemiined for the RV materials that ai-e contained in the surveillance program by ming the reduced plant sunreillance data along with the correspondmg 1/4T tlue:nce projection. The surveillance data was plotted in Regulato:ry Guide 1.99, Revision 2, Figure 2 (i.ee Figure 5-1) using the sun'eillance capsule fluence values documerued in Table 2-1 of this report for VCSNS Unit 1. This data was fitted by drawing a line parnllel to the existing Jines 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 calcula.ted to detennine 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 Allgust 2022 Re-.ision 3
Page 27 af61 Westinghouse Non-Proprietary Class 3 USE Conclusion Serial No.22-227 Docket No. 50-395 : Page 27 of 61 5-2 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 22. The SU1Veillance data for lnteunediate Shell 11-1 is used despite it being detennined to be non-credible, as the upper shelf can be clearly determined for the swveilwlre specimens (see WCAP-16298-NP). Note, both the Position 1.1 and 2.1 results for Intemiediate Shell 11-1 remain above 50 ft-lb.
WCAP-18728-NP Angust2022 Rfvision 3
Page 28 of61 Westinghouse N on-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 28 of 61 5-3 Table 5-1 Predicted USE \ ':tlues at 7l EFPY for the \'CSXS Unit 1 Beltline and Extended Beltline Materials M.iterial Wt ~i Cu<*>
Jntmnediate Shell 11-1 (Heat# A9154-l) 0.10 Jnteonediate Shell 11-2 (Heat#A9153-2) 0.09 Lower Shell 10-1 (Heat# C9923-l) 0.08 Lower Shell 10-2 (Rm# C9923-2) 0.08 Jntamediate, Shell l.Dng. Weld SeaJns BC 0.05
&BD (Heat#4P4784)
Jntennediate to Lower Shell Cm:. Weld 0.05 Seam AB (Heat H 4P4784)
Lower Shell Long. WeldBA&BB 0.05 c&at # 4P4784)
Nozzle Shell 12-1 <Heat # C9955-2) 0.13 Nozzle ~
12-2 lHeat #J C0123-2) 0.12 Inlet Nozzle 4368-1 (He.at# Q2Q41 W) 0.127 Inlet Nozzle 4368-2 (Heat# Q2Q39W) 0.127 Inlet Nozzle 4368-3 (Heat# Q2Q39W) 0.127 Outlet Nozzle 437B-1 (Heat# Q2Q40) 0.127 Outlet Nozzle 437B-2 (Heat# Q2Q40W) 0.127 Outlet Nozzle 437B-3 (Heat # Q2Q44W) 0.127 Nozzle to Jntennediaie Shell Ciic. Weld 0.05 SeamAC(Heat#4P4784)
Nozzle Shell Long. Weld Seams BE & BF 0.06 ToletfOutlet Nozzle Foigings to Nozzle 0.06 Shell Weld Seams 15AJB/C & 16A/B Intermediate Shell 11-1 (Heat #A9154-l) 0.10 Intmnediate Shell Long. Weld Seams BC 0.05
& BD (Heat# 4P4784)
Intermediate to Lower Shell Circ. Weld 0.05 Seam AB (Heat# 4P4784)
Lower Shell Long. Weld Seams BA & BB 0.05 (He.at# 4P4784)
Nozzle to Jntennediate Shell Cm:. Weld 0.05 Seam AC (Heat# 4P4784)
Notes coubmed on ml.lo~ p;1ge.
WCAP-18728-NP 1/.ff Flu,nce Unimidiated
(:s: 1019 o/cui1-,
USE E > 1.0 feY)l'l (ft-lb)C*l Position 1.2{<)
5.68 76 5.68 107 5.69 106 5.69 92 1.90 86 5.68 86 1.93 86 0.251 101 0.251 91 0.031()(11) 152 0.0310Cd) 115 0.0310Cd) 138 0.0132(d) 159 0.0132(d) 165 0.0132(11) 155 02o7 86 0.251 80 0.031()(d) 80 Position 2.2<<>
5.68 76 1.90 86 5.68 86 1.93 86 0.2o7 86 Projeded USE Decnase
(%)
29 29 29 29 22 29 23 17 16 10 10 10 9
9 9
14 15 9
17 9
12 9
6 Proj<<ted USE (ft-lb) 54 76 15 65 67 61 66 84 76 137 104 124 145 150 141 74 68 73 63 78 76 78 81 Angust 2022 Revisio11 3
Page 20of61 Westinghouse Non-Proprietruy Class 3 Nms:
Serial No.22-227 Docket No. 50-395 : Page 29 of 61 5-4 (a) UlJllm" weight pereat,-a!nes.and ummdiated USE,'3lnes 'ITT!ff taken from Tab* 3-1 of this RpOrt. If the base mebl or -nitld Cu
~-eightpercentaps m, below the mmmmn1.-alw! pre;mtedinF~
2 of~Guide 1.99 (0.1 fcr base metal.md0.05 forU"l!lds),
fbl!D the Cu m!i.&ln~ = c:aasanti,.-el:yrouaded up to the mi:uim:n:nnlue forpmjeded USE deamse determination (b) V;,.Jues tahu mm Table 6-2 oflhi.s report Flumce.aas abol.'1! 1()17 n/mr- (E > 1.0 MeV) but below 2 x 1017 n!cm.1 (E > 1.0 MeV) were l'OllDlkd to 2x 1011 n.fcml {E> 1.0 MeV) mien demmining the% deause beause 2 x 1011 nlmr-is the l~t fl~
dispby1!d in Fi~
2 ofRG 1.99.
(c) Position 12 perceDQge USE ~
,"llhlti l'l'ln cakwmd by pJottmg the lf4T ni...- 1.,wes on RG 1.99, FtgDn! 2 and using the m.m.rw-specific Cu \rt. % n1ues. The puce,t-loss l.ines were atmded into the low £h.wict i1Q of RG 1.99, Figln 2, ie.,
below 1011 nlcm.1, in order to delEmine tbe USE % ~
as ~
Position 22 percm2'1! USE deCJuse nlms,.,._
deleimilll!d by dmving m upper-bound line~ to the existing RG 1.99, Figure 2 lines through the applicable smnilhnce chti poim. Thtse n=11s sbao1d be used in prafi!renc-e to the existing gr;qii liDes fa,- Me111i11i11g /lie decrease in USE, becmse the 5111\-eill.anm data is credible.
(d) V~
an, the muimmn fl=e 1.-al!Jei instead of the l/4T fiuence nlues.
WCAP-18728-NP Angust2022 Re\-ision 3
Page 30<>fl!I
~~ finghome Non-Proprietary Class 3
.,c_
l!u.l!!!9I
~
ltOJ
-- --Mafml<*
1
=ti
~.,!i::z,:eS,,.,, --
-- tniit c lrt!man Wei:IS YD~fl"!riJml
... --=-
- '\.
~---
L.,-
J_ 1_L
~~ -I,.------
w
~ =--...----- --
~ -
\}, -
.!i
- ~...- ---
... V
..... ~
i.--
e
~
~
I,,.----
0
~-_. t.--"'...- ---
... - ~ -
i.--
i-
--\-
i
,u e
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~ ~-
i--,--
tror1Ulalt9111'-""').... '<!G I T fl:J!n:e ii U(El 9r./t,.t e--"
~*ILO*ttSret I.01g Y/tf/6 o.atH!JDSei f 3:e *t7 MJnl 114!Autru *.. ~.,,_
I I
I I
l O U.11"51111101< l\'>1<1 1...,. I I~..
111-*---***
n.ero,,, ~ Ul!:*19-2"'
~~I tlll IIO.FmT"'
ll...-c:J S! d 1 *r fJuo-Ju:'"'
s -
t :Ul.d.
I.II I
I I
I Serial No.22-227 Docket No. 50-395 : Page 30 of 61
~ -----
~
lmnl<d.r.oSMI I/ Flal ll-l Lm
_..i -
L-- :.--- _.. r,,
Vt"a! He~
- dlrll11M *-
l.ooe+l7 U OE<!8 UU+1' I -
WCAP-18728-NP 11,utton Fluonct. n/tm1 IE > 1 lhVI Rr;ubtory Guidr 1.99, Rriision 2, Pogtion 1.2 & l.l Pndktrd D<<nase m l ),pfl"-ShrlfEMrcr a, a Tunnion of Copper and Flan~r for ycs.,_..._s Unit l :ir thr End of SPEO (72 EII'Y)
.Au2llSt 20ll
~ moo 3
Page 31 of61 Westinghouse Non-Proprictaiy Class 3 Serial No.22-227 Docket No. 50-395 : Page 31 of 61 6-1 6
HEATUP AND COOLDOWN PRESSURE-TEMPERATURE LDflT CURVES Heatop and cooldown limit cwves are calculated using the most limiting value of RTNDr (reference llil-ductility transition temperature) corresponding to the limiting material in the beltline region of the RPV The most limiting RT=
offhe materi.alin the core (beltline) regi..on of the RPV is detennmed byusing the miirradiated RPV material fracture toughness properties and estimating the imtdiation-induced shift (ARTNDT).
Ci.I ADJUSTED REFERENCE 1El'\IPERATURES CALCULATION RTNDr increases as the material is exposed to fast-neutron irradiation; therefore, to find the most limiting RTNDT at any time period in the reactors life, ARl'NDT due to the radiation exposure associated with that time period must be added to the original unirradiated RTNDr-Using the adjusted reference temperature (ARI) values, pressure-tempera.tore (P-1) limit curves ai-e detemiined in accordance with the requicements 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 cmv-es far nonnal 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 cUfVes, the floence values and initial material properties used to cakolateART values have been updated and an applicability check of the current P-T limit co.rres is appropriate.
To confian 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 vames, updated Chemimy F actor vames, and updated initial RT NDT values. The Regulatmy Guide 1.99, Revision 2 (Reference 8) methodology was used along with the sum.refluence of Section 2 to calculate ART values, which are summarized in Table 6-3 through Table 6-8. Note, the inlet/outlet nozzle fotgings and associated welds neglect attenuation through the material; thus, ART calcnlations are only needed at one location, i.e., the location ofma.-.wnum fluence. Table 6-1 and Table 6-2 show the sw:face, l /4T, and 3/4T floencc values for 56 EFPY and 72 EFPY, respectively.
ART projections contained herein are based on those projected fluence valoe-S with a 1.1 bias on the pecip.b.eral and re-entrant comef' assembly relative powers.
WCAP-18728-NP August 2022 R.evision 3
Page 32of61 Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 32 of 61 6-2 Table 6-1
\'CS:NS Uoit I Fluence and Fluence-Factor Yalues for the-Surface-, l /4T, and 3/4T Locations at 56 EFPY Surface l/41' Flunce<->
3/-IT Fluence<->
Flutnct<->
Surface 1/.ff 3/4T Material Description
(:i; 101'n/cm1, Ff(li)
(:x 1ou n/cm2, Ff{b)
(:x 101' n/cm2, f"?)
&l.O. le\)
I'.> 1.0:lli\')
&l.O le\)
<h"ue Intennedia1e Shell 11-1 6.99 1.463 439 1376 1.732 1.151 (Heat# A9154-1)
Intennediate Shell 11-2 6.99 1.463 439 1376 1.732 1.151 ffif'llf# A9153-2)
Lower Shell 10-1 7.00 1.463 4.40 1376 1.735 1.152
(&it# C9923-1)
Lower Shell 10-2 7.00 1.463 4.40 1376 1.735 1.152 fHeat # C9923-2)
Intermediate SMl Long. Weld 235 1231 1.48 1.108 0.582 0.849 l'Heat # 4P4784)
Inlennediate to Lower Shell 6.99 1.463 439 1376 1.732 1.151 Cm:. Weld(Heat# 4P47S4)
Lower Shell Long. Weld 239 1235 u o 1.112 0.592 0.853 l'Heat # 4P4784) fate11tled Bntline Nozzle Shell 12-1 0309 0.678 0.194 0562 0.0766 0.366 (Heat# C9955-2)
Nozzle Shell 12-2 0309 0.678 0.194 0562 0.0766 0.366 (H~t # C0123-2)
Inlet Nozzle 436B-1 0.0239 0.192 SeeNote(d)
(Heat#Q2Q41W)
Inlet Nozzle 436B-2 0.0239 0.192 SeeNote(d) m eat# 02039W>
Inlet Nozzle 436B-3 0.0239 0.192 SeeNote(d) m eat# 02039\V\
Outlet Nozzle 4378-1 0.0102 0.111 See Note (d)
(Heat# Q2Q40)
Outlet Nozzle 4378-2 0.0102 0.111 SeeNote(d) ffiea.H# Q2040WI Outlet Nozzle 4378-3 0.0102 0.111 SeeNote (d)
(Heat# 02044W)
Nozzle to Intermediate Shell 0328 0.693 0.206 0511 0.0813 0.377 Cin:. Weld (Heat # 4P4 7&4)
Nozzle Shell Long. Welds(<)
0309 0.678 0.194 0562 0.0766 0.366 InleVOutlet Nozzle F<<gings to 0.0239 0.192 Seenote (d)
Nozzle Shell Welds Notes:
(a) The smface fluence nlues for tbe RV materials= dimmined by iutapohtion from d3ta in Table 2-2 The l/4T and 314T fhEnce nl-. were calcnlm.d from tbe SUlface fhwJce, tbe R.V beltline thi~ (1-75 inclies).md eqmtiou f= f....r
- e4 24(*i from
~toiy Guide 1.99, Rrnsiao 2, "-here x = the depih into the TI!Ssel wall (mcliies).
(b) FF= fhmlce fador = II 0.IO'"" Cll)_
(c) Exposure'\~
for the DDzzle shell loogitadmal m!lds all! bounded by tbe exposure nlues fix the DOZZle shell (d).Analysis of the DOZZle f<<pngs and associah!d ~-elds <ft conser.am:ely permm,,d ~
the maximmn fhwlce through the '\'eSsel wall WCAP-18728-NP Angust 2022 R.e,,ision 3
Page 33ofCII Serial No.22-227 Docket No. 50-395 : Page 33 of 61 Westinghouse Non-Proprietary Class 3 6-3 Tablc-6-2 VCSNS Unit I Flurnce i:tnd Ilutnce Factor Values for th, Surface, l/4T, and 3/4T Locations at 72 EFPY Surfare 1/.ff Flue-nee(->
3/.ff Flumce<->
Flutnce(->
Surface-1/.tT 3/.ff Material Des<:ription (x IOU n/em7, Fftb}
(x IOU n/cm2, FF(\)
(x 101' n/cm2, f?)
&l.OAM')
E > l.O.Me,')
&l.OMe,')
Beltfi11e Intennedia.te Shell 11-1 9.04 l.501 5.68 1.427 2240 1218 (Heat# A9154-l)
Intennediate Shell 11-2 9.04 l.501 5-68 1.427 2.240 1218
<Hea.t # A9153-2)
Lower Sheil 10...1 9.06 l.501 5.69 1.427 2.245 1219 (Hmt# C9923-1)
Lower Shell 10...2 9.06 1501 5.69 1.427 2245 1219 (Heat# C9923-2)
Jnt=cdia1e Shell Lang.
3.03 1.293 1.90 1.176 0.751 0920 Weld (Rea.I #4P4784)
Intennediafe to Lower Shell Cm:. Weld 9.04 1.501 5.68 1.427 2240 1218 (Heat# 4P4784)
Lower Sbell Long. Weld 3.08 1.297 1.93 1.180 0.763 0.924 (Heat# 4P4784) fat.e111Jed Btftli11e Nozzle Shell 12-1 0.400 0.746 0251 0.625 0.0991 0.415
<Heat# C9955-2)
Nozzle Shell 12-2 0.400 0.746 0251 0.625 0.0991 0.415 (Heat# C0123-2)
Inlet Nozzle 436B-l 0.0310 0.224 See Note (d) fR..,.t# O2DtlW\
Inlet Nozzle 436B-2 0.0310 0.224 SeeNote(d)
(Hea.t # Q2Q39W)
Inlet Nozzle 436B-3 0.0310 0.224 SeeNote (d)
(Hea.t # 02039\\\\-'}
Outlet Nozzle 437B-l 0.0132 0.132 See Note(d)
<Heat#Q2rnO)
Outlet Nozzle 437B-2 0.0132 0.132 SeeNote(d)
(Heat# Q2Q40W)
Outlet Nozzle 437B-3 0.0132 0.132 SeeNote (d) ffiea.t # 02044W\
Nozzle to Intetmediate Shell 0.425 0.762 0261 0.640 0.105 0.427 Cm:. Weld (Heat# 4P4784)
Nozzle Shell Long. Welds(<)
0.400 0.746 0251 0.625 0.099 0.415 Inlet/Outlet Nozzle Foigings 0.0310 0.224 See note (d) to Nozzle Shell Welds Nolr.:
(:a) The smflice ilw!nce.:alues for the RV materiili "we daemined fnm Table 2-2 lhe l/4T aDd 3/41' :llumc.e.:alues m:re calculated from 1he sud'a~ f1uecce, lhe RV beltlme thiclmess (1.15 inch,,;) mid eqmtion f=f....r *rl24 <il from Regal:afmy Guide 1.99, Reruion 2, mlS1! x = th,, depch into Iba.e,;sel "-all (mches).
(b) fF = finence &dor-=
-0.la-lottl'II_
(c) &po;ure,.-ahu,s far the.nozm sbell loogitudin.l "'1ds.ire bounded by the expo~urn.lues fodho! nm:z1,, sh.ll.
(d) Anal}~ of~
IICIIZZl.e fmgin;s and assoc:utl!d '1\-..ld.s ue consentn,oly pmormed usmg the maxim.mi 6.IW!Ce ~
~
i.~sel
'I\.Jl.
WCAP-18728-NP Augmt2022 Revision3
Pago 34 ol 61 Wertingbcuse Non-Propriotary Cl.ass 3 Serial No.22-227 Docket No. 50-395 : Page 34 of 61 6-4 Tabtt6-3 Calculation of the \"CS:'.'i"S Ua.it lART\":ilurs al th* l/4TLoration for th* Iua~lor\"~*d &lllint andExtrn.d,d Bel.dint M.:ilfriab at Ibo End of PEO (56EFPY)<>l R.G.
ll-lT B n,ure hl.altrial U 9, Cft'I
(:,: 10" D/rm1, l/-lT Rn-*.?
E > 1.0 Mt\)l'l Ff('l Positioa Btltlint Maltriah lulmnediate Sb,1111-1 (Heat ii A91 >t--1) 1.1
_65.0 439 1376 Using nor,.m:dibl, sunYilllmu daf,µ)
2.1 435 439 1376 In!nmtcliate Shell 11-2 (Beat# A9153-2) 1.1 58.0 439 1376 Lawer Shell l0-1 (Bul#C9923-l) 1.1 51.0 4.40 1376 l.ow,r :.at.11 10-21):i,!al# l,YY.U-2) 1.1 51.0 4.40 1376
~ "Laig. w~Sums BC& 1W 1.1 68.0 1.48 1.108
(&atUP4784)
Using cndibl. sun*eiTlmtce dakftl n
4li 1.48 1.108 lulcmtdiote to Lower Shdl Cuc. Weld Seam AB 1.1 68.0 439 1376
(&ati14P4784)
- ltitng mdibl. nuwilhmu dat!fl!
2.1 423 439 1376 lower :illel.l I..oag. Wdd Semn HA & HH 1.1 68.0 150 1.112
(&at114P4784)
Vimg tntlibl.n,,wfllmia w,J 2.1 423 1.50 1.112 utrndrd Bellmlt Matuuh Now
~
12-1 (Heat,. a>>55-2) 1.1 90.1 0.194 0.563 No2Zle Sbt.11 12-2 (Heal I! C:0123-2) 1.1 82.6 0.194 0.563 N~tnln/rnnrdi,.., Shell Clrc. Wdd Se.miAC 1.1 68.0 0206 0577 (Heatit 4P4'>
z.1mt a mible nu,*d1ltmc;,, dm,t,J 2.1 423 0206 0.5T7 Nom Sbell Lmg. Wdd Seams BE mdBF 1.1 82.0 0.194 0.563
'Nolesmmioodcm~--
WCAP-18728-NP Prtdict,d RT1'DIIC) ilT1WT GI
(°l)!'l l"'F)
("I)
..11
~ -4 l>:O 21 59.9 0.0
-20 79.8 0.0 5
702 0.0 4
102 0.0
-49 153 0.0
-49 46.9 0.0
-49 93.6 0.0
-49 582 0.0
-49 15.6 0.0
-49 47.1 0.0 9
50.7 0.0 15 465 0.0
-49 392 0.0
-49 24.4 0.0 10 46.1 0.0 cu fFf1l l],!)
17.0 17.0 17.0 17.0 28.0 1.fo 28.0 --
14.0 28.0 14.0 17.0 17.0 19.6 122 23.1 M
("I)
("I)
.34.0 144.4 34.0 114.9 34.0 93.8 34.0 1092 34.0 108' 56.0 823 28.0 25.9 56.0 100.6 28.0 372 56.0 82.6 28.0 26.1 34.0 93.7 34.0 955 392 29.4 24.4
-02 46.1 1023 August 2022 Rrvision3
P9 35of81 Westinghouse Non-Propridary Class 3 Nolo:s:
<*> n..~
Gmdo I.99, Kr.moo 2 me&oclo!o1Ywas dilmd"' 11,e c.dcub6an or11,e ARTnmes.
(b) Climiisl,yfdor.s m,bbn lnmTable 3-3.
(c) flDllx:a tum 6mt Table 6-l aldii> npcrt (cl) FF*floe,,a,ladll,-* ll-*-,.
<*> Rl'N>T0.1 {U,,imdiDdRI'= ),-..'nest.km fnm Tab!, 3-L Serial No.22-227 Docket No. 50-395 : Page 35 of 61 6-5 (0 !'..tho ~
al'~
Gaide l.99, h isi<,o 2, tllo base meblo-.= l'T"F for Pa.ilioll LI md Po,iticn 2.l 'lriih~ ~
<bta, md tllo l,a,emebla,. =8.5"F fir Po,mm,.21 -.rida mdihl<! SlaTI!illancemta. Also,~ Rap,latory G,,;de 1..99, Rfiisiau 2, lhe \ftld mota!o-, s2S"F Ir Pmili<n l.l.md Posilioa 2.l uh DOD-CAdio!o ~
dab, a,d 1be 1'ul.,,.1a1 m
- 14"1' far Posmoa 2.l m!h m,!ib!, smnilbm:, dm. ~.
a.,. need coDt uceed 0.5*,urr..,, Car eilbor m,e ml!t&b or nlds, 11-ilh or mlhaul
.......:n.,,,, elm.
W D,e~a"21mlia:, b lhe VCSNS Uni! J..,,,'l!illm<edminApps,dixA dtmmined !bat 1h! Va.NS Unit I ~d>b Cm Ibo ~
Sbell 11-1 (HutiA91.54-l) is d,omodll<llH:nd,1,!e mi lbe Sam,ill,m,o Weld (&,Iii 4P47S4) is doomod Cll!d,l,k_
WCAP-lBn~NP August 2012 Revision 3
Page JG of Cl Westinghouse Non-Ptopri.miy Class 3 Serial No.22-227 Docket No. 50-395 : Page 36 of 61 6-6 Tablt6-4 Cakulatinn nf tht \'CSXS Unit I ART \ '"aluts at tbt JU T Lo<-ation for the Ructor \'essd Btltliu* and Enended Beltlin*
Materiah al th* End of PEO (56EFPY)<-I R.G.
JI.ff Fluencr Material 1.99, Cf{b)
(i: 10" a/err, Rl"l".?
E >LOMe\ )I')
Position Btltlin* llittrials lnt~te Sbtll 11-1 (Heu II A9154-1) 1.1 65.0 1.73 Umw non--aodible SIDVdllance d1l1tP 21 43.5 1.73 lntmnrdim Sbtll 11-2 (Heu# A9153-2) 1.1 58.0 1.73 I..m.-.~ Sbtll 10.1 (Hen II C9923-1) 1.1 51.0 1.73 I.m>-.r Sbtll 10.2 (Heat # C9923-2) 1.1 51.0 1.73 Inlmnrdim Shell I..cmg. Weld ~
BC &BO 1.1 68.0 0.582 (Htatll4P-l784) lhing amibls ;ru,wilkmce dalll'"11 21 423 0.582 Inlrnmdwt tol..ow,r SMII Circ. WddSeamAB 1.1 68.0 1.73 (Heat# 4P4784)
U;;,,g,;;;;;j,le SIDWillance dafa'II 2.1 423 1.73 I..awu Shell I.a,g. Weld Stams BA & BB 1.1 68.0 0.592 (Heat I! 4P4784)
Using cndibb, nnwi&nce datn'fl 21 ill 0.592 Enmdtd Btldint llitn i.ili Nozzle Shell 12-1 (Heat # C9955-2) 1.1 90.1 0.0767 Nozzle Sbell 12-2 (He.a II C0123-2) 1.1 826 0.0767 Nome to lntmnl'dute Shell Circ. Weld Seam 1.1 68.0 0.0814 AC (Heu ii 4P4789 lhmg cndible Sll1'Wi11tmce daJD'll 2.1 42.3 0.0814 N~
Shell U11!2. Weld Seams BE 211d BF 1.1 820 0.0767 Nolos CClllbimd"" ~
pi WCAP-18728-NP Prtdkttd 3/ff RT!M(C)
("F)t-l ffi
("F)
_1.1~1 21 74.~
0.0 1.151 21 50.1 0.0 1.151
-20 66.8 0.0 1.152 5
58.7 0.0 1.152 4
58.7 0.0 0.849
-49 57.7 0.0 0.849
-49 35.9 0.0 1.151
-49 783 0.0 1.151
-49 48.7 0.0 0.853
-49 58.0 0.0 0.853
-49 36.1 0.0 0366 9
33.0 0.0 0366 15 302 0.0 03TI
-49 25.6 0.0 03TI
-49 15..9 0.0 0366 10 30.0 0.0 Ol
("F)I'>
17.0 17.0 17.0 17.0 17.0 28.0 14.0 28.0 14.0 28.0 14.0 16.5 15.1 12.8 8.0 15.0 I
("F)
("F) 34.0 129.8 34.0 105.1 34.0 80.8 34.0 97.7 34.0 96.7 56.0 64.7 28.0 14.9 56.0 853 28.0 27.7 56.0 65.0 28.0 15.1 33.0 74.9 30.2 75.4 25.6 23 15..9
-17.1 30.0 70.0 August2022 Rel.isi.on 3
P"ll'!37of81 We.rtingbouse Non-Pcoprietuy Class 3 Ncn;:
<*> u.. Rqubhilywdo 1.99, R.\-isim 2 ~
,ns ulilizadm tmcakubli... oftbeARTnlm..
(b) Chmislzy fad.,., an takm mm T,blt 3-3.
(c) Thlmce bbs, £mm Table 6-1 oftl,is npcrt.
(cl) fF* flam,ofadar=fl"'"-*-<lll.
(o) R.T,.,,.,lll (UmndialodJlT,.,,.),-.Jues tum 6-T>b!o 3-1.
Serial No.22-227 Docket No. 50-395 : Page 37 of 61 6-7 (f)
For Ibo piidazn of~1Dry Gmd,,, 1.99, Rr.ision 2, the base,ml>! <JA
- lrf £<< Po.ilian 1.1 and Posilioa 2.1 wilhll<IIHndibl,o Sill"\~ ma, and ibe base mm! GA=
8.S"F Ear Position 2.1 will, cndio!e ~
dm. Also, per Ra:,,lmy Gmd. 1.99, Rr. ision 2, tbe mid metal a,* 2S"F fer Positim 1.1 and Posilioa 2.1 witlu*n-<ndible surnilh:a<,, ma, :mil tbe lOOdlllllal a*
- 14"1' £or Pasilim 2.1 nhcndto!e S'\l1\""1lmcedab. B'oln!s,,,-, a DeedDDt --1 0.5*AR.T,.,T &nitbl!r basemetils or -id,.,,rim ar1"ithmt ""'1!illazice dab.
(v ll,e cndibilityr.-.lulia:, htbt VCSNS Unit 1 sun...U-.. elm in Appendix A deJamined thattbe VCSNS Ucif 1 s=~
elm fur tbe la!mmdim Shell 11-1 (Rut ii A91S4-l) is dNmod DOIKffl!l>!a and the S..,.'Oillai,ce Weld (Hut# 4Jl.l7S4) is dtemd<ffdi' WCAP-1872S-NP August2022 Re.ision3
Page38of6I
\\\\'estinghonse Non-Propridaty Cl= 3 Serial No.22-227 Docket No. 50-395 : Page 38 of 61 Tabk6-5 Cakulation of 1hr \"CS!'IS Unit l ART,*aln** for thr Rrador YHwl Extrndrd B,lclinr ~oul* Mnt,riab at tbr End of PEO (56 EFPY)(Il R.G.
Muima.m Marrrial 1.99, CJ1')
n uttmi Mn Red (x 10" n/cnr, Ill" Position E>LOMe\')(<l l.aletNo:z:zle436B--l (Hnt/#Q2Q41W) 1.1 92.1 0.0239 0.192 Inlet Nomr 4368--2 (}lttt# Q2Q39W) 1.1 93.0 0.0239 0.192 IDlrl r.om e 4368--3 ltlt.1111 Q2Q39W) 1.1 93.0 0.0239 0.192 OU!letr,;om,, 437B-l ltie.11#1,l~
J 1.1 93.0 0.0102 0.111 Outlet Nozzle 437B-2 (Heat ii Q~
W) 1.1 93.0 0.0102 0.111 Outltt No:z:zle437B-3 (Hnl ll Q1Q44W) 1.1 92.6 0.0102 0.111 w!dlClutld Nozzle Fmgiugs to N02Zle ~
Weld 1.1 82.0 0.0239 0.192 Semis l5A/B/C& l6A/BIC Nol.s:
(>) Tho L su]m,,y Guido 1.99, Rnision 2 mo!hodology,.... utilized m ibo ~011 alll>t AR.Tn!no,..
(b) Om,;st,y fadm,.,. bbD mm T>h!e :n (c) Fhma l>kmlhm T*bl* 6-1 ald:is npart (d) fl'= lhe,ce fado<=.*-d-tfll.
{e) IU',...,..,,, (Ucrradi;md RI...,.) n!nes bkmmm Table '.i-1.
PrNfirttd RI1'M'(t)
~TllDY GI cu M
("F) I*)
("I)
('F)
("I)('
("I)
("F)
-20 17.7 0.0 8.8 17.7 lS.4 0
17.8 0.0 8.9 17.8 35.7
-20 17.8 0.0 89 17.8 lS.7
-10 103 0.0 52 103 10.6
-10 103 0.0 52 103 10.6 0
103 0.0 5.1 103 20.5 10 lS.7 0.0 19 15.7 41.5 (f) Per tbo pida,,ca oCRquhlay Guida 1.99, Rms;m2, tl:a bz.emml<>4= 17"F rc.-Pmm"" l.l a Posilim 2.l m!h DOI><ndiba ~
dzb, mi ibo base -1 ru=
B.5"1' mr Posi!ico 2.1 l:rilh cncib!e smnill-. dm..Also, per~ Guide 1.99, IIR<-is:ioa 2, i1>o -id am.I a,.=2S"F fir Pomiau. 1.1 ml Posilim 2.1 ~-ilh DOCH:ft<hl,Je
~
mta, a,d Ibo -i.lmml "* = 14'F lot PO<ition 2.1..-:oh uodihlt ~
clala. llawe\w,a*needootsceed 0.5*AR:r,.,,. b--1>.- mot.ls.,,..,-uis, wuh
.,..Ti!lx,,t ~
.i.i..
WCAP-1872&-NP August 2022 Ra'ision 3
1'3go 39of81 Weslingbo~ Noo.-Propririaty Class 3 Serial No.22-227 Docket No. 50-395 : Page 39 of 61 6-9 Table 6-6 Cal(ubtioo of tbt VCSXS Un.it I ART Val ts at tbt l/4T Location for th* Rra(tor Y~sfl Btltlin* and h t,odtd B,Jtlin*
Materials at tht End of Sl'EO (72 EFP\1)<->
R.G.
1/.ff flltfll(f l.99, Mattrlal Rt,*.2 CFO>
(x 101' nlcml, Position E>LOAir\')(.,
Bf!dmt llittrlals Intmnodiate :.!lffl 11-1 (Httt#A9154-l) 1.1 65.0
- .68 Um,g non-cmiibl, sun"tillanc. dati#
2.1 43.5 5.68 Snai 11-2 tHUl # A9153-2) 1.1 58.0 5.68 Lower Shtll 10-1 (Httt II C99l3-1) 1.1 51.0 5.69 um-..-Shell 10-2 (Rm I C9923-2) 1.1 51.0 5.69 Inl~ Shell L1RJ!- Wtld Swns BC &: BD 1.1 68.0 1.90 (Hm li 4P4784) t&tng aimbt. ~
datiftl 2.1 423 1.90 tn:moNWe to Lcm;er =-~ Circ. w ad seam AH 1.1 68.0 5.68 (Heat 41'47&4) lGing a-edible sunYilltmos daJdtl 2.1 423 5.68 Lower Shell Lang. Weld Stnm BA & BB 1.1 68.0 1.93 (Htat f 4P4184) lGing mJi/,/,: sun-.lilmla datifl/
2.1 423 1.93 Extmded Beltbt Matu:uls Nome~ 12-1 (Heat i C99S5-2) 1.1 90.1 0.251 Nozzle Shell 12-2 (Hui Ii C0123-2) 1.1 82.6 0.251 NOZ21e to ~
ShellCirc. Wl'ld SeamAC 1.1 68.0 0267 (Httt II 4P47_!9 "tbi,,g a-t:tfibl6 ninYillana dttf(lt}
2.1 423 0267 Nozz.lr Sbdll.mg. W~ Sftlm BE md BF I.I 82.0 0.251 Ncm~cm mllol.-Egpa."1!.
WCAP-1872&-NP Prrdicted 1/.fT R~if FFl'l AR.Tiarr
('F) 1.427 21 92.7 1.427 21 62.l 1.427
-20 82.7 1.427 5
72.8 1.427 4
72.8 1.176
-49 so.o 1.176
-49 49.7 1.427
-49 97.0 -
1.427
-49 603 1.180
-49 803 1.180
-49 49.9 0.625 9
563 0.625 15 51.6 0.640
-49 43.6 0.640
-49 27.1 0.625 10 513 GI a~
{°I)
C°I) IO 0.0 17.0 0.0 17.0 0.0 17.0 0.0 17.0 0.0 17.0 0.0 28.0 0.0 14.0 0.0 28.0 0.0 14.0 0.0 28.0 0.0 14.0 0.0 17.0 0.0 17.0 0.0 21.8 0.0 13.5 0.0 25.6 M
("F)
{°I) 34.0 147.7 34.0 117.1 34.0 96.7 34.0 111.8 34_0 110.8 56.0 87.0 28.0 28.7 56.0 lOtO 28.0 393 56.0 873 28.0 28.9 34.0 993 34.0 100.6 43.6 38.I 27.1 52 513 1125 August 2022 Rew.ion 3
Page40ol61 Westinghouse Non-P.-oprietary Class 3 NDIH:
(a) The ~
Guido 1.99, Ra\IDl:m 2 mtlbodolo,r""' olllmd. m the akolatioa.oftheART nlua (b) Cbmiisby 6.c:im,..-. tlbn mm Ttbl. 3-3.
(c) n-:. md FlneDoo FildlD bbn lioon T>blot 6-2 of this npcrt (d) fFz Ouo,,a,ad,ara H-O'°"'lil'll.
(e) RT,_...., (Ummclimd R.T....,.) n.'ms tabn th>m Tab?. 3-l.
Serial No.22-227 Docket No. 50-395 : Page 40 of 61 6-10 (I) l'lr lbt gmdmce cfRep,lm,ryQiide 1.99,R.oruioo 2, the base..,.b} Ill* 17°F fir Po,itian l.l mdl'osilm2.l "'ithDOD-<ndib!ur<1ilmce dab, mdfho base mo!a! G.\=8.51'
£co-Position 2.1,.;;i,anb!a ~
elm. Also,por R,p,b!myGuid.t 1.99, R.-~ 2, the..-.!dlDl!bl GA a 2.&"F f<< Pomon l.l mdPosilion 2.1 m lhl!Oll-<ndible ~
elm, am the,...?,I..-1 G.\ = 147 far Posmaa 2.1 will> ~11I* ~ebb. ~..._ need DOt eia:aed. O.S*ARTmT r~ oitba-base mmls or ~
,rid, er "-itbout
""""1lm:,e ebb-(!;) The m!di.lutyorumion iortbe VCSNS Umt l ""'-eillm,e elm in Appa,d:iJ;A dotmninod tlmthe VCSNS Umt l ~
d3!a f<<the Imm,,,di,n Sholl l l-1 (&at 1!,A9l54--
l) is <lem,odnm-cndibl,, ar.d tbe Surm1m,co Weld {Hui I 4P47&4) is doomed~
WCAP-18728-NP Angust2022 R£\-ision 3
l'3ge41 ol81 Westi!lgbouse Non-Propriebsy Ct.us 3 Serial No.22-227 Docket No. 50-395 : Page 41 of 61 6-11 Tab!, 6-7 C:tlnilation of th* YCS:XS Unit l ART \ *aluts at th* 3/4T Location for th* Rn<tor Ytsstl BelrliM and Enmdtd Beltline Matuials at tb End of SPEO (72 En'Y)<->
RG.
3/.ff lhlmr*
llitnial 1.99, Cfl>I (x loJJn/cm1, Ru.?
E > 1.0 M,\)('l Position Bdtli.a* !bttrbls IDla:mtdia:e ~
11-1 (Hm # A9l54-1) 1.1 65.0 224 Umw non-a"'1ibh SUJ'\Qlkmc. daiJi 2.1 43.5 2.24 Jn!mnediate SbdJ 11-2 (Hm # A9153-2) 1.1 58.0 2.24 Lowa Shell 10-1 (Rm# C9923-1) 1.1 51.0 2..25 Loin*.- Slid) 10-2 (Rm# C9923-2) 1.1 51.0 2.2S JntrrrnrdimSbelll.mg. WeldSumsBC&BD (Heat ii 41'4 784) 1.1 68.0 0.751 Usmg crftb1'16 svrmllanee daJdll 2.1 42.3 0.751
~
lo l.cmw Shell Circ. Weld~ AB 1.1 68.0 224 Qhat # 4P4 784)
Usmg cmt,1'16 SJm¥illm,<< daJ.,p) 2.1 42.3 2.24 Lower Sbdl l.mg. Weld Seams BA & BB 1.1 68.0 0.763 (Hm# 4P_4784) rrm.., cri,dibl* no-mllana, daftllJ 2.1 42.3 0.763 utrDllfd Bd!luu ~ tuim Nozzle Shell 12-1 (Heat# C99SS-2) 1.1 90.1 0.0991 NozzkShdl 12-2(Heat# C0123-2) 1.1 82.6 0.0991 Nc,zm to Jnlmnedia SbeJI Circ. Wdd ~AC 1.1 68.0 0.105 (lkat # 4P4784)
UsiM,mlibl* mrmllm,ce daJJf/J 2.1 42.3 0.105 N~Sholllm2.. Wdd SmmBE mlBF 1.1 82.0 0.0991 Noh:, ca::t>imd cm lilllo,rmg pap,.
WCAP-18728-NP Pttdicttd 3/-IT RT~ (t) 4R.Tsr FFt4
(°F)l-l
("F) 1.218 21 792 1.218 21 53.0 1.218
-20 70.7 1.219 5
622 1.219 4
622 0.920
-49 62.5 0.920
-49 38.9 1.218
-49 82.9 1.218
-49 51.5 0.924
-49 62.8 0.924
-49 39.1 0.415 9
37.4 0.415 JS 343 0.427
-49 29.1 0.427
-49 IS.I 0.415 10 34.0 01
("F)
~
~ 11_0 0.0 17.0 0.0 17.0 0.0 17.0 0.0 17.0 0.0 28.0 0.0 14.0 0.0 28.0 0.0 14.0 0.0 28.0 0.0 14.0 0.0 17.0 0.0 17.0 0.0 14.5 0.0 9.0 0.0 17.0
- u ART
("F)
("F) 34.0 1342 34.0 108.0 34.0 84.7 34.0 101.2 34.0 1002 56.0 69.5 28.0 17.9 56.0 89.9 28.0 30.5
.56.0 69.8 28.0 18.1 34.0 80.4 34.0 833 29.1 9.1 18.1
-fiii 34.0 78.1 Angust 2022 Rmsioo 3
Pq 42 ol 61
\\\\'fflinghouse Non-Proprietruy Class 3 Not.:5:
(*) The R.p,l;,!myGuim l..99, R.-'im> 2 molbodolou,nslllilmdm lhe ~
oftbaART nlms.
(b) Cbomislry fadms an tum frtm Tit,!. 3-3.
(<) flimrt blom ha T*lu 6-2 of dm,_t.
(d) fFs llm,,co fimr= P"-*.,.,.dll_
(e) RI""'" (Urii,ndir,,d Rimr) ~
lam ha Tob!, 3-1.
Serial No.22-227 Docket No. 50-395 : Page 42 of 61 6-12 (f) P..-tbopidm<eof:R.p,bbyGwdt l..99,Rmsioo2,1habosemeblm=l7"F lc< PO<iticm I.I mll'osi6an2.I -.rilhDOD-<nd,l>!esg\-.illmotc!m,atha b....a.blaa=SSF
£..-Fmitian 2.1 wiihcnclil,J, =-.illmeeclm. Also,pu R...,.blay Guide 1.99,~-isian 2, lho,nldmoalaAs28"F r<< Posilian 1.l amP~2.1..-ith~l>le.....-.iJbnc,,
c!m, md the,nJd mob! a. s 14"F for Pcsiiim. 2.1 wrilh cmil,le sun-oilJ.mct dm. ~
,,. no.d DOt aa,ed O.S*MIT,...,y fa: oibo-base mmls or "Rids, with<< 'ilboal mn-.lbaco elm.
(v The cn<hl,i]jtyn-.!mliao hthe VCSNS Uflit I surmn_,., dabio..A_,di,tA dmmimedlhat the VCSNS Unit l ~
elm forthe bnnmdim Sbtll 11-1 (Ent ll A9154-
- 1) is deemed~
ml the ~
Weld(Hut 4P47S4) is doomed cndil>!e.
\\\\ CAP-18728-NP Augus12022 Re\-ision 3
F'3Qe 43 of 61
'\\\\'estulgbouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 43 of 61 6-13 Tablr 6--8 CakuL,tion of th* YCS~S Unit I ARI"\.alu~ for th* Rrtttor Y~wl En,ndrd Bdtlin* ~ozzle Maltriah at the End of SPEO (72 En-'}">
R.G.
Mllimum 1\latnial 1.99, Cfl'l Flut11<<
R,,*.2 (x 101' n/cm 1, Porition E>LO ~lt\)l<l Inld Nozzl" 4368-1 (l:kat ii Q2Q4 I W) 1.1 921 0.0310
~
t Nozzle 4368-2 (&:ii I Q2QJ9W) 1.1 93.0 0.0310 lnl,t Nozzlr 4361>3 (Brat f Q2QJ9W) 1.1 93.0 0.0310 Ou11rt Nazzle 437B-1 (Heit Ii Q2Q40) 1.1 93.0 0.0132 Oallet Nozzle 437B-2 (Heal ii Q2Q40W) 1.1 93.0 0.0132 Oo!ltt Nozzle 4378-3 (Heal ii Q2Q44 W) 1.1 926 0.0132 Iolel/Oullet Nome F~ to Nozzle Sbtl.l Weld Stams 15 C & 16A/B/C 1.1 82.0 0.0310 No11s:
(>) lbe ~
Guide 1.99, Rm,im, 2 ~
"'2S ulilmd in tho cmla!ica ottbe ARI,~
(b) Cl>omislryf:adms.,,. tum £nm T.b!.t 3-3.
(c) Fhmi<etakm frcm T>ble 6-2 ord:is n,p<<t.
(d) FF*lh>mce f.octor *
(e) IIT= M ((JmDdimd.RT,.,,-) n hE bkc mm T 3--1.
Max fT("I 0224 0224 0224 0.132 0.132 0.132 0224 Pfflliclfll CJ1 RTllllr(q.un:<DT
("F) 1\1
.-\RT
("F) (oJ
("F)
("F)
(I)
("F)
("F)
-20 20.6 0.0 103 20.6 212 0
20.8 0.0 10.4 20.8 41.6
-20 20.8 0.0 10.4 20.8 21.6
-10 123 0.0 6.1 123 14.5
-10 123 0.0 6.1 123 14.5 0
122 0.0 6.1 12.2 24.4 10 18.4 0.0 92 18.4 46.7 (f) P..-the guid,,,ct of :Rqua1ory Gaide 1.99, Rr.'isian 2, tho i,.,.. mob!.,.
- l T'F fai-Positicm 1.1 md Positiai, 2.1,m1, mixndib!a.....-.illa,,a elm, md Ibo base mml.,_..
85"Fb-Posiliim 2.l wilhcn<lib!e ~
elm.Also, pa-Ro.p,hbyGuide 1.99, Rmsicm2, il>>inldmebl a..=2S"F fer Pcr.itim, l.l md Pooili.oal.l mth OOIHDdil,!e
~
dab, md Ila..-w!dmmla* = 14'Flar Pmilion 2.1 nh cndib!a sm,.--.,,ill...,,, elm. Ba...\v, "* medDCt o,-! 0.5*.1.RT,ny b-oil!m-l=emetals.,.. ~
wilh cr'lrilham ~
ml>.
WCAP-18TI8-NP Augmt 2022 Rei.-ision 3
Page 44 of 61 Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 44 of 61 6-14 6.2 P-T LIMIT CURVES APPLICABil,IJY This section detennin.es the applicability term. of the end of PEO P-T limit cmves by comparing the ART values contained in the analysis of record (AOR) with the ART values calculated nsing the updated flnenc-e projections and materials infomiation 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, fuen the applicability teon of the current curves will remain unchanged. If the ART values used in the previous analysis are lowt!r than the ART values cakufated using the updated flncnce and material properties, then the applicability term. of the current cwves 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 flnence projections. P-T limit curves for the end of SPEO (12 EFPY) do not need to be submitted as part of the VCSNS Unit 1 Subsequent License Renewal Application since P-T limit cmves are avail.able as a part of the current license. However, new P-T limit curve development or an extension of the applicability of the current curves mnst be completed prior to the expiration of the rouent cmves as specified in the VCSNS Unit I licensing basis.
Table 6-3 through Table 6-8 calculates the belt.line and extended beltlineARTvalues forVCSNS Unit 1 at the end of PEO (56 EFPY) and the end of SPEO [/2 EFPY). The limmng end of SPEO ART values correspond to the Jntennediate Shell 11-1.
Table 6-9 compares the lLAA 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 Limitin.g ARTalu.es limiting AR~ >
C"F}
YesRcl Wall Location P-TLimit Cu.rres 56EFPY 72EFPY AOR<->
1/4T 153 144.4 147.7 3/4T 138 129.8 1342 Notes:
(a) Inmom6an bkm &om WCAP-16305-NP.
(b) ~
limiting m1tmil (1~
Sluill 11-1) c~
ta m axial &w miich is lnOl1! limmDg than a cimmifm!ntw fbw.
Table 6-9 shows that the end of SPEO ART values at the 1/4T and 3/4T locations remain bounded by the ART value.s used in the current P-T limit cumis_ Thus, the P-T limit cmves implemented in the VCSNS Unit 1 Teclwical Specifications will remain v1llid through the end of SPEO (/2 EFPY) for the cylindrical shell materials. The extension offue P-T limit cmve is allowed because fhe redefinition of the Intennediate Shell 11-1 (Heat #A9154-1) initial RTNDr in PWROG-21037-NPresulted in a 9°F reduction.
WCAP-18728-NP Angost2022 Revision 3
P~ge 45 of 61 Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 45 of 61 6-15 Note that the lelDlS of applicability for the P-T limits also implicitly confum the bolt 1lJ> temperature and flange temperature limits. The bolt 1lP temperatm-e and flange-notch temperntnre limit a.re not affected by embrittlement, thus, they are unaffected by license renewal and may remain the same. Since de *elopment of the P-T limit cm,,-es in WCAP-16305-NP, the closure head bas been replaced. Howevtt", the RT1mT ofthe replacement closure head is lower than fhe original head flange; thus, the P-T limit cmves are not negatively affected.
Inlet and Outlet Nozzles P-T Limit Curves PWROG-15109-NP-A (Reference 9) addresses the cone-em of higher sfresses in nozzle comer regions generically for the U.S. pressurized water reactor (PWR) operating fleet. The results of PWR.OG-15109-NP-A demonstrate that P-T limit curves developed with c:urrmt NRC-appraved methods bound the generic nozzle P-T limit cun,-es. This document has been approved by the NRC as an acceplable means to address these conceins. The r~ults and conclusions of PWR.00-15109-NP-A are applicable as long as the plant-specific VCSNS Unit 1 fluence at the nozzle comeis remain less than the screening criterion of 4.28 x 1017 n/cr:ii, as described in PWROG-15109-NP-A WCAP-18709-NP (Raenince 5) ~tes VCSNS Unit 1 adherence to this screening criterion since the limiting nozzle flnence is 3.10 x 1017 n/cm.2, thus PWROG-15109-NP-A is applicable and no further consideration of the nozzles is required with respect to P-Tlimits.
Conclusion Based on the end of SPEO ART values calcntated herein and the P-T limits analysis c-0mpleted in WCAP-16305-NP(Reference 14), the P-Tlimitcmves cwrently in the Technical Specifications will remain valid through 72 EFPY.
WCAP-18728-NP Awrust 2022
~
ion 3
Serial No.22-227 Docket No. 50-395 : Page 46 of 61 Page 46of61 Westinghouse Non-Proprietary Class 3 7-1 7
SURVEILLA CE CAPSULE \VITHDRA\VAL 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 prescn"bed by 10 CFR 50, AppendixB (Reference 16) and consistent with the guidance ofNUREG-1801, Revision 2 (GALL [Reference 17D and NUREG-2191 (GALL-SLR [Reference 18D.
10 CFR 50, Appendix B states:
T11e design of the surveillance program and the withdrmnll schedule must meet the rcq11iremei1ts of the edition of A.SIME 185 that is current on the issue date of the ASME Code to which the l'cactor vessel was purchased;for reactor vessels purchased after 1982, the design of the surveillance program and the withdrawal schedule must meet the requirements of ASTM E 185-82. For reactor ws.rels purchased in or befo,-e 1982, IJJ.ter editions of ASTM E 185 may be used, but inchJ.ding ono, those editions through 1982. For each capsule withdrawal, t11e test procedures and reporling requirements must meet the requir: me11ts of ASTM E 185 to the exte11t practicable for the ronfigu.ration of the specimens in t11e capsule.
The VCSNS Unit 1 RV was designed and constructed to ASME Section Ill, 1971 Edition. Thus, per 10 CFR 50,.Appendix H, the VCSNS Unit 1 snrvei1lanre program withdrawal schedule may meet the requirements of any,*ersion of the ASTM El 85 standard from the 1970 version (which was CtJO'em 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 m.nreillance capsule pcogmm was designed to the ASTM El85-73 (Reference 20) standard, which was the 11-emon active at that time. Therefore, the requirements of 10 CFR 50, Appendix B 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 Fiml Safety Analysis R.q,ort (FSAR) (Rrftteoee 21) to support liceme R:newal (IR.) to 60 years and to meet the reqwremen1s of ASTM E185-82 (Reference 15). Recommended changes to this surveillance capsule withth'awa1 schedule to support SPEO is provided in Table 7-1. This schedule meets the Reommendations of ASTM E185-82 as required by 10 CFR 50, Appendix B and satisfies the guidance contained in the GAIL and GAIL-S1.R.
Specific details are described herein.
The first step in determining the surveillance capsule withdrawal schedule compli:mce is to determine the rnioinmm fJWilber of capsules to witbdrnw and/or test. ASlM E185-82 bases the onmber of capsules on the rnaxinmm ARTNI>r projected at the vessel surlace for all RV materials. Per Table 4-1 of this report, the maximum AR.Ti-'Dr "-aloes for the VCSNS Unit 1 is 102.0"F. Since the ruaxiomm ARTNDT are projected to be above 100°F, butbelow 200°F, fouc (4) capsules are required tobepulledperTable 1 of ASTME185-82.
To date, fu-e (5) capsules have bttn pulled and tested with the last tested capsule being Capsule Z.
Bowe-1.-""er, C-apsule Z does not satisfy the GALL-SLR guidance far the capsule to obtain a iluence at least equal to the 80-year RV projected iluence. VCSNS Unit 1 currmtly has only one untested capsule (Capsule Y), which was removed at 17.71 EFPY with.a fluenre of7.01 x 1019n/cm2 and placed in storage in the spent fuel pool WCAP-18728-NP August 2022 Rcvision 3
Page 47 of 61 Westinghouse Non-Proprietaty Class 3 Serial No.22-227 Docket No. 50-395 : Page 47 of 61 7-2 It is recommended that, in order to satisfy the GALL-SLR guidance for the 80-year operating lkense for a capsule to be withdrawn and tested betwttn one and two times the peak RV wall neutron fluence at the e.nd of SPEO, Capsule Y should be reinserted into a 17° octagonally symmetric location (107°, 287°, or 343°)
to be irradiated furlher. Capsule Y needs to be imidiated in a 17° location for ~ rnioiomm c,f 4.9 EFPY1 to experience the end of SPEO tluence of 9.06 x 1019 n/cm.2 ( 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 rec-eiving 2 x the 80-year fluence, i.e., 1. 73 x 1 ()20 n/cm2 ( conseivatively based on the fluence projection in Section 2 which exclnde.s 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 ovec 100 years) peak RV fluence of 1.14 x 1020 n/cm.2 (with 10% bias) should be achieved after " mjnjmnm of 10.5 EFPY of additional irradiation.
Cond usioo In order to mttt all ofllie conditions described,1bove, it is recommended that Capsule Y be exposed to a minimum of 10.5 EFPY of operation to experience thP rourinmm 100-year f.lnence of 1.14 x 1020 n/cai.
Assuming fhal Capsule Y is reinserted during Refue1itJg 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 additioual 10.5 EFPY of iaadiation (10.5 EFPY / l.33 EFPY /cycle), which means the projected removal of Capsule Y following Cycle 38 (Fa11of2039). This means that Capsule Ywillbereinserted at 37.7 EFPY atEOC 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 nnmbers are only estimates and may change as actual plant operation may differ from the assumptions used here.
1 The RV md capsule llumce projedions ;ire pro1.-ided in Section 2 with md v;-itbc,ut a 10'1/4 bias 011 1he periphery fuel assemblw. To emme that the appropriate flmnce is zclm-ed, wbm tbt minimum caprole cposun! is ~
the RV flumce is based 011 the 'bi.-.d projedion, while the capsule t3llElCI! is based cm tbt milii3sed. iluem:e. Wbm ibe m;mmmn C2pSllle fmence in cuailmd, the RV fl:uecce is based on 1he Ullbrued projection, Vii:iile 1he c.ipsule £1uea.,e is based 011 1he biased projection. 'Ihi:s uwdm:e of f1uence ebb. w.is COIISS\":il~ applied to l!IISIR the desi:red/mmimum flumr.:e was ac:hi.6-ed md to p-1!-.-mt the maximum lilWICe from beq ~
WCAP-18728-NP Angust 2022 Revision 3
Page 48of61 Westinghouse Non-Proprietary-Class 3 Serial No.22-227 Docket No. 50-395 : Page 48 of 61 7-3 Table 7-1 YCSKS Unit I Rfcommended Sun-eillance Capsule Withdrawal Schedule Capsule Location Capsule u ad Remonl TimeCI)
~sule Fllm1ce (deg)
Factor (IlPY)
(n/c
, E > 1.0 MeV) >
u 343 3.04 l.13(ECX: 1) 6.75 X 1011 V
107 334 293(ECX: 3) 1.54x 1019 X
287 354 5.04(EOC5) 251 X 1019 w
110 321 11.21 (EOC 10) 4.63x1019 z
340 3.10 1636 (EOC 14) 6.53 X 1019 y(c) 290 3.09 17.71 (ECX: 15) 7.01 X 1019 107(<)
~3.5 482(<)
1.14 X 1()20 Nate!;:
(a) Eff'edi.e full po...-..r yeas mm phnt stump. End of C:>-cle (EOC) "-alue gi\'eJl in p.uenlhesis. Note that con thmml powu-mu uprated from 2n5 to 2900 MW* stattmg"-ith apentiog Cycle 10.
(b) Fluencn~ \\\\'El! taken from Table 2-1.
(c) Capsule Y will be rmiserled dming Remelmg Oubge 30 in !be Fall 0£2027 (prior to Cycle 31) uito location I Or (OI" S}'llllDEttic location:. 2~ aa-343j, 'l\iuch is JrOjemd to occm- ;at 37.7 EFPY. Capsule Y will aclm-e !be pm: 100-,ear
~
1.14:s: I()lll nfan1 (E> 1.0 feV), bemmmxn.11, which is c.lcubted to nquin,.motba-10.5EFPY ofapu::atian (37.7 + 10.S =48.2).
WCAP-1872&-NP Augus.1:2022 Revision 3
P.ail" 49oHII Westme:house Non-Prnpriet;uy Class 3 Serial No.22-227 Docket No. 50-395 : Page 49 of 61 7-4 Figure 7-1 Original AITangement of S11ITeillance Capsules in the YCSNS Unit I Reactor Yes-sel WCAP-18718-NP Augmt 2022 Revision3
Page50 of6t V,.'estinghonse Non-Ptoprietaiy Class 3 8
REFERENCES Serial No.22-227 Docket No. 50-395 : Page 50 of 61 8-1 L Code of Fed.em RegulatiOllS, 10 CFR Part 54.3, "'Def'initi011S." ll_S. Nuclear Regulatory COllllllliSion,, Federal *Register, dated Augost 28. 2007.
- 2. U.S. Nnclear Regulatory Commiwon. Office of Nuclear Regulatory Research, Regulatory Gui.de 1.190. "Cakulafiona1 aru1 Dosimmy Methods for Detennining PresSlllC,csset New-on Fluence," March 2001.
[A.gcncy,dde Documents Access and Management S}'Stem (ADAMS) Accession Number MI.010890301]
- 3. Code ofFedenil Regulations, 10 CFR 50, Appendix G, ~Fracture Toughness Requirements," U.S.
Nuclear Regulatory Commifflon. Federal Register, No'\-anbet-29, 2019.
- 4. Westinghouse Repon WCAP-1812~ NP-A Revision 0, °Fluence Determination with RAPTOR-M3G and FERRET," July 2018.
- 5. Westinghouse Report WCAP-18709-NP, ~'ision 1, "V.C. Summer Nuclear Station Unit l SlJbsequeot license Renewal: Reactor Pressure Vessel Extended Beltline Neutton Exposure Emuation." F ebmaiy 2022.
- 6. Code ofFederal Regulations, 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Presmrized Theuna1 Shod: faents," U.S. Nuclear R.egulntory ~
'>ion, Federal Register, November 29, 2019.
- 7. Westinghouse PWROO Report PWROG-21037-NP, Re11ision 1, "Determination ofUnilradiated RT:sDT :ind Uppet-ShelfEnergy Values of the V.C. Summer Ullit 1 Reactor Vesrel Materials," May 2022.
- 8. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatoiy Re.s:ean:h, Regulatory Guide 1.99, Revision 2, '-'Radiation.Embrittlemem of Reactor Vessel :Materials," May 1988.
[ADAMS Accession Number l..ll.003740184]
- 9. WC$tinghouse PWROG Report PWROG-15109-NP-A, Revision 0, '-PWRPressure Vessel Nozzle Appendi:t G Evaluation," JannaIY 2020. [ADAMS Accession Number ML20024E573]
- 10. Westinghouse Report WCAP-1629&--NP, Revision 0, "Analysis of Capsule Z from the South Carolirui Electric & Gas Company V. C. Smnmer Reactor Vessel Radiation Snr."eillanre Progr.un,"
August 2004.
1 l. AS IE Boiler and Pressure Vessel (B&PV) Code, Section Ill, Diilision 1, Sub3rtide NB-2300,
'"Fracture Toughness Requirements foi: Material and Section NB-3210, "Requirements fOf' Acceptability," AS:ME Intemational"
- 12. NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Chapter 5 of LWR Editi= Branch Technical Position 5-3, '-"Fracture Toughness Requirements," Re1;isfon 4, U.S. 11."uclear Regulatory-Commis-sion, :March WU>. [ADk\lS 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, Di\1-ision 1, "Fracture Toughness Criteria foe Protection Against Failure.~
WCAP-18728-NP August2022 Re\i:.ion3
Page 51 ufi!1 Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 51 of 61 S-2
- 14. Wb-tinghouse Report WCAP-16305-NP, R.En.ision 0, "'v. C. Summer Heatup and CooldownLimit Curves for Nonna! Operation,,,,. August 2004.
- 15. AS1M E185-82, "Standard PractiC'e for Conducting Surveillance Tests fOT light-Water Cooled Nuclear Power Reactor Vessels,= American Sociely for Testing and Materia1s, 1982.
- 16. Code of Federal Regulations, 10 CFR 50,.Appendi:t H, "Reactor Vessel Material Sutveillance ProgramR.equirem.en:ts,"U.S. Nuclear RegulatoiyCommi.ssion, Federal Register, October 2, 2020.
- 17. NUREG-1801, Revision 2, "Generic Aging Lessons Leamed (GAIL) Report,." u_s_ Nncle.ar Regnlatoiy Commission, December 2010_ [ADAMS Accession Number MI.1034900.fl]
- 18. NUREG-2191, Volume 2, 'ueneric Aging Lessons Learned ror Subsequent license Renewal (GALL-SLR) Report." U.S. Nuclear Regulatory Commission, Inly 2017. [ADA..JJS Accession Number.MI.17187.t1204]
- 19. \Vb-tinghous-e Rfport WCAP-9214, =South Carolina Electric and Gas Company Virgil C. Summer Nuclear Plant Unit No. 1 Reactor Ves..ooel Radiation Smveillance Program," January 1978.
- 20. ASTM E185-73, "Standard Ref-nrorneoded Practice for Snn~lance Tests for Nuclear Reactor Vessels," American Society for Testing and Materials, 1973.
- 21. Virgil C. Summer 1'.'uclear Station Unit 1 Updated Final Safety Analysis Report(UFSAR), M.ay 31, 2018.
WCAP-18728-l\,P August2022 R.e\-ision3
Page 52 of61 Westinghouse Non-Proprietaiy Class 3 Serial No.22-227 Docket No. 50-395 : Page 52 of 61 A-1 APPENDIX A CREDIBILITY EVALUATION OF THE VCSNS UNIT I SURVEILLANCE PROGRAM Regulatoiy Guide 1.99, Revision 2 (Reference A-1) describes general procedures acceptable to the NRC staff for calculating the effects of neutron radwion embrittlement of the low-alloy steels currently ns.ed for light-water-<:ooled RVs. Positions 2.1 and 2.2 of Regulatory Guide 1.99, Revision 2, describe the method for calculating the adjusted reference temperature and Chaipy upper-shelf energy of RV beliline materials using sun,-eillance capsule data. The methods of PositiOJlS 2.1 and 2.2 can only be applied when two or more credtble smveillance data sets become available from the reactor in question.
To date there have been five (5) SUJVeillance capsules removed and te-Sted 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 cri1eria in Re.gulatory Guide 1.99, Revision 2. The following subsectiOJlS evaluate each of these five criteria for VCSNS Unit 1 in order to determine the credibility of the smnillance data for use in neutron radiation embrittlement calculations.
Tablr.-\.-1 Regulatory Guide l.99, Rrrinon 2, Credibility Critrd a Criterion
~ scriptio No.
1 Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.
Scatter in the plots of Charpy energy versus tempenture for the imldiated and uninacliated 2
conditiOtlS should be small enough to pennit the determination of the 30 ft-lbs temperature and UDDer-shili energy wwnbieuouslv.
When there are two or more sets of sun,,-eillimce data from one reactor., the scatter of ART NOT 111!lues about a best-fit line drawn as described in Regulatory Position 2.1 nonnally should be less than 28°F for welds and 17"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 nse in shift calculations, they may be credible for detemiining decrease in upper-shelf energy if the upper shelf can be clearly detemiined, following the defimtion given inASTM E18~.
4 The imldiation temperature of the Ch31py specimens in the capsule should match the vessel wall teDll)erature at the cladding/base metal interlace within+/- 25"F.
5 The swveillance data for the cOllClation monitor material in the capsule should fall within the scatter band of the database for !hat material WCAP-18728-NP Angmt2022 Revision 3
Serial No.22-227 Docket No. 50-395 : Page 53 of 61 Page53 or61 Westinghouse Non-Proprietary Class 3 A.I VCSNS UNIT 1 CREDIBILIIT E\~..\LUATION Critt"rion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement A-2 The VCSNS Uni:t 1 RV cowts of the following beltline region materials, which likely would have bttn comidered al the time 1he smveillance program was designed and licensed:
Intennediate Shell 11-1 (Heat#A9154-1)
Inteanediate Shell 11-2 (Heat #A9153-2)
Lower Shell 10-1 (Heat # C9923-2)
I.owerShell 10-2 (Heat# C9923-l)
Intennedia1e Shell Long_ Weld Seams BC & BD (Heat# 4P4784, Flux T:n >e Linde 124, Lot #3930) lntennediate to Lower Shell Cin'. Weld Seam AB (Heat # 4P4784, Flux Type Linde 124, I.ot#3930)
Lower Shell Long. Weld Seams BA & BB (Heat # 4P4784, Flux Type Linde 124, Lot#
3930)
The VCSNS Unit 1 swveillance program utiliz.es longitudinal and transverse test specimens from intermediate shell plate A9154-l. The sun-eillance weld metal was fabricated with weld wire Heat #
4P4 784, 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 Intennediate Shell PlateA9154-1 bad the highest Initial RT NOT and one of the lowest initial USE of all plate materials in the beltline region. In addition. the lntemiediate Shell Plate A9154-1 bad the highest content of copper and phosphorus of all the otherbellline plate materials. Therefore, based on the highest initial RTNI>r, the lowest initial USE and the highest copper and nickel content of all plate materials, Intermediate Shell Plate A9154-l was chosen for the swveillance program.
1be weld material in the VCSNS Uni:t 1 sun-eillance 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 1 sunreillance program.
Criterion 2: Scatter in the plots of Ch.mpy en.eigy 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 eneigy unambiguously.
Based on engineering judgment, the scatter in the data presented in these plots, as documented in WCAP-16298-NP (Refene:e A-2), is small enough to pennit the determination of the 30 ft-lb temperature and the upper-shelf eneqzy of the VCSNS Unit 1 swveillance materials unambiguously.
Hence. Criterion 2 is met for the VCSNS Unit 1 surveillance progrnm, WCAP-18728-NP An~ t2022 Revision 3
Serial No.22-227 Docket No. 50-395 : Page 54 of 61 Page 54 of61 Westinghouse Non-Proprietary Class 3 Criterioo 3: When there are two or more sets of surveillance data from one reactor, the scatter of MIT1'Dr values about a best-fit line drawn as descn"bed in Regulatory-Position 2.1 noanally 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 mice 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 inASThl E185-82.
A-3 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 detmnine if the scatter of these ARTNDr values about this 1ioe is less than 28°F for welds and less than 17°F for the forgings.
Resoltiog is the calculation of the best-fit line as dcscnbed in Regulatory Position 2.1 of Regulatory Guide 1.99, Revision 2. In addition, the recommended NRC methods for detmnining aedloility will be follow-ed.
'Ibl! NR.C methods were presented to the indostiy at a mttting held by the NRC on February 12 and 13, 1998 (Refecence A-3). At this meeting the NRC presented five cases. Of the five cases, Case 1
('Smveillance data a1,-ailable from plant but no other source") most closely represents the situation for* the VCSNS Unit 1 surveillance forging and weld material.
Case 1: Evamatioo ofVCSNS Unit 1 Data Only Follo"llt-ing the NRC Case 1 guidelines, the VCSNS Unit 1 sm,..--eillance 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 adjusunent or chemisuy adjustments are requiced.
WCAP-18728-NP Allgust2022 Revision 3
P* 55 of 61 Table A-2 Ahttriru Intennediate Shell 11-1 (J.ongitudina I)
Intennediate Shell 11-1 (TillIISVme)
Smveillance Weld Note:.:
Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 55 of 61 A-4 Cakofation oflnterbn Chemistry Factors for tht Credibility Enluatio Using YCSNS Unit I Sornillance Capsole Data Only Capsule Measured Capsule FJum.ceC->
Ff(b)
ARTNDi<*>
FPART:rmr FF1 (x 101f n/cm1,
("F)
E>LOlhYl
(°F) u 0_675 0.890 36.1 32-1 0.792 V
154 1.119 53.2 59_6 1.253 X
2.51 1.247 383 47.8 1.555 w
4.63 1387 66.2 91.8 1.924 z
6.53 1.451 98.9 143.5 2.106 u
0.675 0.890 14.5 129 0.792 V
154 1.119 32.1 359 1.253 X
2.51 1247 26.7 333 1.555 w
4.63 1387 57.8 80.2 1.924 z
6.53 1.451 87.0 1263 2.106 SUM:
663.4 15.261 CFu-1 = I:(FF
- 6RTNDt) + 1:(IF) = (663.4) + (15.261) = 43.5"F u
0.675 0.890
'12.1 20.2 0.792 V
154 1.119 47.0 52.6 1.253 X
2.51 1247
'12.1 283 1.555 w
4.63 1387 43.5 603 1.924 z
6.53 1.451 65.2 94.6 2.106 SUM:
256.1 7.630 CFS=.l!.old =1:(FF
- t\RTwr) + UFF2) =(256.1) +O.630)= 33.6°F (a) flumce taken &om Table 2-L (b) FF= flumce bd:ar-=
~*-'-
(Ill_
(c) Musured.MIT !WT bken from WCAP-16298-NP (Ref'ermce A-2).
WCAP-18728-NP Angust 20'12 Re\iision 3
Page 56 of6I Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 56 of 61 A-5 The scatter of MITNDr values about the functional fonn of a best-fit line drawn as described in Regulatory Position 2.1 is presented in Table A-3.
Table A-3 YCSNS Unit I Sun *eillance Capntle Data Scatter about the Best-Fit Line
(:p)
M.1telial Capsule (Slopfk.i-61)
("F) u 43.5 V
43.5 Intermediate Shell 11-1 X
43.5 U-on@tudinal) w 43.5 z
43.5 u
43.5 V
43.5 Intermediate Shell 11-1 X
43.5 (fm 1svme) w 43.5 z
43.5 u
33.6 V
33.6 Sumiillmce Weld X
33.6 (Heat # 4P4784) w 33.6 z
33.6 N!iw; (a) CT cakula1ed in Tab~ A-2 of this report.
(b) Fhwice taken from T:a.b!e 2-1 of this n,part.
(c) FF = 8-fadm-=
- o..... (Ill_
Capsule FlntnceOi>
(x 101' n/crn2, E>L0 MeV) 0.675 1.54 2.51 4.63 6.53 0.675 1.54 2.51 4.63 6.53 0.675 1.54 2.51 4.63 6.53 (d) Mu.m-ed ART= bkm &om "tllCAP-16298-NP (Re.ma,a! A-2).
(e) Pttdide.d AR.Ti= =CFxFF ff{<}
0.890 1.119 1.247 1387 1.451 0.890 1.119 1.247 1387 1.451 0.890 1.119 1.247 1387 1.451 (f) Satts-ART= = Absolim Value [Pn,dictl'd &ITSDT-Muswed ARTmr].
~!P.uured Pndicted Scatter
<l7"F ARTNWd)
Mtrr-m<*> ART.wi© (Plate)
<28"F
("F)
("F)
("F)
(We,ld) 36.1 38.7 2.6 Yes 53.2 48.7 4.5 Yes 383 54.2 15.9 Yes 662 603 5.9 Yes 98.9 63.1 35.8 No 14.5 38.7 24.2 No 32.1 48.7 16.6 Yes 26.7 542 27.5 No 57.8 603 2.5 Yes 87.0 63.1 23.9 No 22.7 29.9 7.2 Yes 47.0 37.6 9.4 Yes 22.7 41.9 19.2 Yes 43.5 46.6 3.1 Yes 652 48-8 16.4 Yes The scatter of ARl'ND? values about the best-fit line, drawn as descnoed in Regulatory Guide 1.99, Rev. 2, Position 2.1, should be less than 17°F for base metal and 28°F for welds. From a statistical point of view,
+/- l cr would be expected to encompass 68% of the data. Table A-3 indicates that the Inteonediate Shell Plate 11-1 (Heat #A9154-l) has 6 of1he 10 surveillance data points falling inside the+l-1o-of 17"F scatter WCAP-18728-NP Angus.t2022 Revision 3
Page 57 of 61 Westinghouse N on-Proprietaiy Class 3 Serial No.22-227 Docket No. 50-395 : Page 57 of 61 A-6 band for smveillance plate materials. Therefore, 60% of the data are bounded (6/10 x 100) and the surveillance plate data are deemed "non-credible"' per the tblcd criterion.
Table A-3 indicates that the Surveillance Weld bas 5 of the 5 surveillance data points falling inside the +I-la of28"F scatter band for surveillance weld materials. Therefore, 100% of fhe data are bounded and fhe surveillance weld data are deemed "crediblen per the third aitcrion.
Criterion 4: The irradiation temperature of the Clwpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal inted'ace 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 centei-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 pnn,--ides assurance that the RV wall and the specimens experience equivalent operating conditions such that the tempecatuces will not differ by more than 25°F. Hence. this criterion is met.
Criterion 5: The survm lance 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 sun'eil!ance program does not contain correlation monitor material Hence, this criterion is not applicable to the VCSNS Unit 1 s:mveillance program.
CONCLUSION Ba,sed on the preceding responses to the 5 criteria of Regulatory Guide 1.99, R.e\---ision 2, Section B, the VCSNS Unit 1 mrveillance data for the Intemiediate Shell Plate 11-1 (Heat # A9154-1) is deemed non-credible and the Surveillance Weld (Heat# 4P4784) is deemed credible.
WCAP-18728-NP August 2022 Re~-ision 3
Page58 of61 Westinghouse Non-Proprietary Class 3 A.2 REFERENCES Serial No.22-227 Docket No. 50-395 : Page 58 of 61 A-7 A-1.
U.S. Nuclear Regulatoiy Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel :Materials," May 1988.
[ADAMS Acce.ssion Number MI.003740284]
A-2.
Westinghouse Report, WCAP-16298-NP, Revision 0, "Analysis of Capsule Z from the South Carolina Electric & Gas CompanyV. C. Summer Reactor Vessel Radiation Swveill.anceProgram,"
August 2004.
A-J.
K. Wichman, M Mitchell, and A. Hiser, US NR.C, "Generic Letter 92-01 and RPV Integrity Assessment, Status, Schedule, and Jssue-s," NRC/Industiy Wosbhop on RPV Integrity Issues, February 12, 1998. [ADAMS Accession Nwnber MLJ 10070570)
WCAP-18728-NP Allgust 2022 Revision 3
P* 59 of 61 V.'e$tinghouse Non-Propriemy Class 3 Serial No.22-227 Docket No. 50-395 : Page 59 of 61 B-1 APPENDIXB El\'IERGENCY RESPONSE GUIDELINES The Emergency R.esp-Onse Guideline (ERG) limits were developed to establish guidance fot operator action in the event ofan emergency situation, such as a PIS event (Reference B-1). Generic categories of limits were de\>-eloped for the guidelines based on the limiting inside surface RTNDr. These generic categories were conservatively generated for the Westinghouse Owners Group (WOO) to be applicable to all Westinghouse plants.
The highest value of RTNDT for which the generic category ERG limits were developed is 250"F for a longitudinal flaw and 300"F for a circumiHential flaw. Therefore, if the limiting vessel material has an RTNDT that exceeds 250"F for a longitudinal flaw or 300"F for a circ:umreremial flaw, plant-specific ERG P-T limits must be developed.
The ERG category is detennined by the magnitude of the limiting RT :NDT value, which is calculated the same way as the RT PIS values are calculated in Section 4 of this report. The material with the highest RT NDT defines the limiting material, which for VCSNS Unit 1 is the Inte:m.iediate Shell 11-1. Table B-1 identifies ERG category limits and the limiting material RTNDr values at 72 EFPY for VCSNS Unit 1.
TableB-1 Enluation ofVCS?-IS Unit I ERG Limit C ategory ERG Pressure-Temperature Umin (Refennce B-1)
Applicable RTNDT Valu~*>
ERG P-T Limit Category RTNDJ < 200"F Category I 200"F < RTNDT < 2~0°F Category II 250°F < RTNDT < 300"F Category IIlb Limiting RTNM Valnel'>
Limiting Reactor,*essel ~faterial RT?ll>r Value@ 72 EFPY Inteanediate Shell 11-1 152.5 Note(s):
(a) T ongitn,lina]Jy crimted flim-s are app!icabl,, only q, to 250"F; cin:umfmntwly oriented flaw.i 3It! applicabl,, up to 300"F.
(b) I.imilingi..lue taken Crm1 Table 4-1.
Per the ERG limit guidance documeo.t (Reference B-1 ), some \ressels do not change cate.gories 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. Thns, the ERG classification need not be changed until the operating cycle during which the maximum vessel vahle of actual or estimated real-tim.e RTi,,'DJ exceeds the limit on its current ERG category.
WCAP-18728-NP August 2022 R.tvision3
Page 60 of 61
~ghouse Non-Proprietary Class 3 Conclusion of ERG P-T Limit Categorization Serial No.22-227 Docket No. 50-395 : Page 60 of 61 B-2 The limiting VCSNS Unit 1 RV material RTNDTvalues do not exceed 200°F. Therefore, VCSNS Unit 1 will remain in Categoiy I through SPEO.
B.l REFERENCES B-1.
Westinghouse Owners fuoup Document, HF04BG, "Background Infoonation for Westinghouse Owners Group Emergency Response Guidelines, Critical Safety Function Status Tree, F-0.4 Integrity, HP/LP-Rev. 3,n March 31, 2014.
WCAP-18728-NP ADgust2022 Revision 3
P*
61of61 WCAP-11721-lfP ltM&IOn S Serial No.22-227 Docket No. 50-395 : Page 61 of 61 HCIM'l'aplllUfy Clan S
"'Tlllii J!i9! wn.tlld.edlo Ille qff1y rec<rO ~}' iM PRll.!f Sj'SIHll..,CX, Its vainx, a<111 5!Wl nd be c:or.DIVM III lht page~
at 11111; IIDCll'.MrL **
Approval Information Author Approval Ziegler Tyler Aug-25-2022 15:19:36 Author Approval Lynch Donald Aug-25-202216:45:28 Verifier Approval McNutt Don Aug-25-2022 16:59:34 Verifier Approval Nedwidek Frank M Aug-26-2022 08:35:44 Manager Approval Patterson Lynn Aug-26-2022 08:45:01 Manager Approval Klingensmith Jesse J Aug-26-202210:55:16 Files approved on Aug-26-2022 Serial No.22-227 Docket No. 50-395 Westinghouse Letter CGE-RV000-TM-ME-000004, Rev. 3, "V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Recommended Changes to the Surveillance Capsule Withdrawal Schedule," September 9, 2022 Virgil C. Summer Nuclear Station (VCSNS) Unit 1 Dominion Energy South Carolina, Inc. (DESC)
Page I af 14 WestinghOU3e Non-Proprietuy Class 3 Serial No.22-227 Docket No. 50-395 : Page 1 of 14
@Westinghouse Westinghouse Electric Company 301 Building 1331 Beulah Road To: John~am From: Tyler C_ Ziegler Tel: 412-374-4868 Pittsburgh, PamsyJ...,-an.ia 15235-:5081 USA Date: September 9, 2022 Your ref: NIA Oucref: CGE-RVOOO-TM-ME-000004, Rev. 3
Subject:
V.C_ Swrtmer Nuclear Station Unit 1 Sllhsequent lie~
~wal: Recommended Changes to the Surreillmce CaJ>f,ule Withdrawal Schedule Attachment A Recommended V.C_ Summer Nudea:r Station Unit 1 Sunreillaru:e Capsule Withdrawal Schedule This letter transmits the changes recommended to the V.C. Summer Nucleai-Station Umt 1 capsule withdrawal sclrMnle. Attachment A provides. technical justification and demonstrates scliedule compli:mce,vith the applicable vetsion(s) of American Society for Testing and Materials (ASTM) E185. Note that these recommended schednles support the Vugil C. Summer Nuclear Station Unit 1 proposed 80-year license.
Do not hesitate to contact the uodersigned with any questions regarding the contents of this letter.
The putp<>se of.Rfiision 1 was to incOll)O.rate Dominion* s comments on Re,'isioo 0.
The purpose ofRe-..ision 2 is to update the schedule consistent with the remsertion of Capsule Yin the Fall of 2027.
The rei.ision also corrects all error-in the stated EFPY for EOC 26. Thls correction does extend the last opportunity to reinsert Capsule Y by one cycle; howei.-er, the fPCOOlrnendation for the reinsertion in the Fall of20l7 is still maintained in ot"der to provide extra tim.e fur analysis and licensing.
The putp0se of Revision 3 is to coaect a typographical error. Cha:oges are marked with revision bars.
EI..ECTRONICAll. Y APPROVEIY.
Tyler c_ Ziegler & D_ Brett L}iich RV/CV Design &.Analy3is Verified:
ELECTRONICAILY APPROVED1 Donald M Mcl'."'utt ill RV/CV De~gn & Analysis Approved: ELECTRONICALl...Y APPROVED1 L}'Illl,A_ Patterson, Manager RV/CV Design & Analysis 1Eleetro11icaJl.f awrm-rrl ucords are autl1e11ticated in tlie electronic tlocw11e11t ma11ageme11t system.
©2022 W~
Elec:tric Company llC All Rights R.esaved.
Page 2 of 14 Westinghouse Non-Propri~taty Class 3 Serial No.22-227 Docket No. 50-395 : Page 2 of 14 CGE-RVOO0-TM-ME-000004, Rev. 3 Attachment A Page 1 of 12 Attachment A Recommended V.C. Summer Nuclear Station Unit 1 Surveillance Capsule Withdrawal Schedule
Page3of 14 Serial No.22-227 Docket No. 50-395 : Page 3 of 14 Westinghouse Non-Proprietary Class 3 CGE-RVOO0-TM-ME-000004, Rev. 3 Attachment A Page 2 of 12 This attachment provides the recomme11ded capsule withdrawal :.chedule for V.C. SummH Nuclear Station (VCSNS) Unit 1. This includes demonstration of the schedule's compliance with ASTM E185-82 [Ref 1 ],
as prescribed by 10 CFR 50, Appendix H (Ref. 2] with consideration ofNUREG-1801 (GALL) [Ref 11]
andNUREG-2191 (GAIL-SLR) (Ref. 3].
10 CFR 50, Appendix H [Ref 2] states:
The design of the surveillance program and the wit/1d1*a1*,al schedule must meet tl1e requirements of the edition of AS'IM E 185 that is current 011 the issue date of the ASME Code to which the reactor W!sscl was purchased; f or reactor vessels purchased ofter 1982, tire design of lite su.rveilltmce program and the withdrawal schedule must meet the requirements of ASTM E 185-82.
For reactor vessels purchased in or before 1982, later editions of ASTM E 185 may be used, but including onzy those editions through 1982. For each capsule withdrawat the test procedures and reporting requirements must meet the requirements of ASTM E 185 to the extent practicable for tire configuration of the specimens in the capsule.
The reactor vessel was designed and constmcted to ASME Section III, 1971 Edition pee FSAR. Table 5.2-1
[Ref 4). Tons, per 10 CFR 50, AppendiK H, the sun.-ei.Uance program withdrawal schedule may meet the requirements of any venion of the AS1M E185 s1andard from the 1970 vasion (the vasion which was etment on the issue date of the ASME Codes to which the reactor vessel was purchased) through the 1982 version.
Per WCAP-9234-NP [Ref 5], the surveillance capsule pcogram was designed to AS1M E185-73 [Ref 9],
which was the veision active at that time the program was developed. Therefore, the requirements of 10 CFR. 50, Appendix H were met at the time of the design of the reactor vessel surveillance program.
ASTM El85-82 Schedule Recommendations To d:r.te, VCSNS Uni1 l has tested 5 of6 capsules initially inserted. Capsule Y is the only m:uafoinguntested capsule. The capsule-S tested satisfy the requirements under the 60-year license, as discussed later in the letter, therefore, this letter addcesses the schedule changes necessary to support 80 years of operation.
Table 1 of this letter contams the recommended surveillance capsule withdrawal schedule for 11pdating the FSAR Section 5.4.3.6.2.3 in support of 80 years of operation. The schedule satisfies the regnlatory reqnirements of the Reactor Surveillance Program for 80 years, and meets ASTM El85-82 [Ref 1] as required by 10 CFR 50, Appendix H [Ref. 2].
PerNUREG-2191 [Ref 3],one capsule should be withdrawn at anoutage \\\\"itha neutron fluence ofbetween one Mld two times the peak reactor v-essel wall neutron flnence at the end of the SPEO and tes1ed in accordance with the requirements of ASTM E185-82 [Ref. 1]. Assuming an end ofSPEO of 72 EFPY; the endofSPEO fluence = 9.06 x 1019 o/cm.2 {which includes a 10% bias on the peripheral and re-entrant comer assembly relati\-e powen) and two times the end of SPEO tlnence of 1.73 x 1020 o/cm.2 (2 x 8.64 x 1019 o/cni2, which conse.rvatively e.-tcludes the 10% unbiased). In order to optimize the value of this S1JITeillance capsule, it is recommended that a potential 100-year operating period also be conndered.
Extrapolating from the 66 EFPY and 72 EFPY fluence results from WCAP-18709-NP yields a projected 90 EFPY peak reactor vessel fluence of 1.14 x 102° o/c:ni2. Capsule Y was pulled at 17.71 EFPY with a fluence of7.0l x 1019o/cm2* Therefore, this capsule cunently fails to meet the GALL-SLR. requirements.
Page 4 of 14 Serial No.22-227 Docket No. 50-395 : Page 4 of 14 Westinghouse Non-Proprietacy Class 3 CGE-RVOO0-TM-}.£000004, Rev. 3 Attachment A Page3ofl2 Capsule Y should be reinserted into a 17° octagonally symmetric location (the highest lead factor locations:
107'>, 287", or 343°) to be irradiated further. Using the unblased data in Table 4, Capmle Y should be exposed to a minimum of 4.9 EFPY of operation in order to experience the end of SPEO fluence, but it should be withdrawn before 22.4 EFPY to remain below 2 x the 80-y~ar flueace. Howenr, it is recommended that Capsule Y be exposed to~ roioinmm of 10.5 EFPY of operation to experience the peak 100-year iluence ofl.14 x l oN n!cm.2*
To prevent fhe RV.from experiencing a fluence greater than the a\.-ailable test da1a (6.53 x 1019 nlcnibase-d on the exposure of Capmle Z), Capsule Y should be reinserted 105 EFPY prior to the RV reaching 6.53 x 1 lr9 n/cm1, which is projected to occur at 52.4 EFPY per Table 2-2 of WCAP-18728-NP (Ref 6].
HoweYer, this does not acc-OWif fur ~ psule resting. Currently 10 CFR. 50, Appendix H requires that results of capsule testing be provided to the NR.C staff no later than 18 months (1.5 yem ) after the capsule is withoom-n.. 'lbe:refore, it is RCommended that Capsule Y be reinserted prior to 40 EFPY (:::: 52.4 EFPY -
10.5 EFPY - 1.5 EFPY). Based ~
C)"Cle 26 (the la,t fully completed cycle) being canplcted in the Fall of2021 at 3238 EFPY, there is 7.62 EFPY remaining. D epending on capacity factor, this is approximately 8 to 8.5 years. This u,jll pnt 40 EFPY at the Fall of2029 or Spring of 2030. Therefore. Refueling Outage 31 (Spring of 2029) will provide 1he final opportunity to reinsert the capsule. It is recommended to reinsert Capsul.c Yin.Refueling Outage 30 (Fall of2027) in order to proi.ide extra time for analysis and licensing.
Assuming that Capsule Y is reinserted during Refueling Outage 30 in the Fall of2027, prior to Cycle 31 0 and an average fuel cycle length of 1.33 EFPY/cycle, i.e. - 90"/4 capacity factor, Capsule Y \liill need 8 cycles to achiere an additional 10.5 EFPY of.imldiation (105 EFPY} / (1.33 EFPY/cycle), which means the remo\'al of Capsule Y following Cycle 38 (Fall of 2039). Sim::e the plant has experienced 3238 EFPY at EOC 26, Capsule Y will be rejmerted at 37.7 EFPY andiemo'l.*ed at 48.4 EFPY.
These dates a.re only intended to be an em.mate. All commifment3 should be based 0 11 t1t"ithdcawing Capsule Y at the outage n~arest to, but follo-wing, the capsule fluence achieving the 100-year flue-nee, which is estimated to be after 10.5 EFPY after Capsnle Y is re-inserted into the 107° location {or symmetric locations 287° or 343°).
It is noted that the cap5Dle fluence should be used to detennine when the capsule is withdrav.u, and the EFPY is an approximation based on the unbiased capsule projections. The capsule should be withdrawn at the outage nearest to, but following, when the capsule fluence is met.
E,aluation of Compliance with *.\STM I:185-82 The first step in determining the surveillance capmle withdrawal schedule compliance with ASTM El85-82 is to de1emiiae the minimum number of caprules to withdraw and/or rest. ASTM El85-82 bases the number of capsules on the ma.'rinmm ARTwT projected at the,.--essel surface for all reactor vessel materials. Per Table 2 of this letter, the maximum AR.TNDT value at the end ofSPEO is 102.0°F. Sinre the maximnm ARTwy values are projecled to be abm..-e 100°F, but below 200"F0 fonr capsules are required to be pulled per Table 1 of ASTM El85-82. To date, VCSNS Unit l bas *withdrawn and tested 5 of the capsules. Beamse AS1ME185-82 u based on plant operati011 during the original 40-year license term. the requi:remems are supplmien1cd 1l3ing NUREG-1801 {GAll.) and NUREG-2191 (GALL-SLR) [Ref. 3].
Page 5 of 14 Westinghouse Non-Proprietaiy Class 3 Serial No.22-227 Docket No. 50-395 : Page 5 of 14 CGE-RVOOO-TM-ME-000004, Rev. 3 Attachment A Page 4 of12 The next step is to demonstrate that fhe condition of the capsules rested, or scheduled to be tested, meet fhe requirements of ASTM E185-82. This comparison is performed in Table 3. This tible demonstrates that the recommended schedule mee.ts the recommendations of ASTM E185-82 as reqwred by 10 CFR. 50, Appendix H and the guidance in the GALL and GALL-SLR..
Page6of 14 Rl'fnence.s Westinghouse Non-Proprietary Class 3 Serial No.22-227 Docket No. 50-395 : Page 6 of 14 CGE-RVOO0-lM-ME-000004 Re\*. 3 Attachment A Page5of12
- 1. ASTME185-82, "Sta:ndardPracticeforCon.ductingSnn'eill:!:nceTestsforlight-WatecCoo1edNuclear Power Reactor Vessels," American Society for Testing and Materials, 1982.
- 2. Code ofF~
Regulations 10 CFR. 50. Appendix IL "Reactor Vess.el Material S1J11.--e:illa.nce Program Requirements" U.S. Nuclear Regulatoty Commission, Fede.rai Register, October 2, 2020.
- 3. U.S. Nuclear Regulabny Co~on, "Generic Aging Lessons I.earned for Subsequent License Renewal (GALL-SLR) Report," NUREG-2191, Vol 2, Inly 2017. [Age>>C}wide Documents Access and Management System (ADA... \lS) Accession Number MLl 7187A204]
- 4. Virgil C. Summer NucleM Station Unit 1 Updated Final Safety Analysis Report, R.e.,"ision 20.01,
- 1n1y2021,
- 5. Westinghouse Report, WCAP-9234, Revision 0, "South Carolin.a Electric and Gas Company Virgil C.
Summer Nuclear Plant Unit No. l Reactor Vessel Radiation Sun--e.illance Program," Januuy 1978.
- 6. Westinghouse Report, WCAP-18728-NP, Revision 3, "V.C. Summer Nuclear Station Unit 1 Subseqllellt License Renewal: Evaluation of"Rnctor Vessel Integrity Time-limited Aging Analyses,"
August 2022.
!--1I.20024EJ73]
- 9. ASTM E185-73, "'Standard Recommended Pmctice for Surveillance Tests for Nuclear Reactor Vessels." American Society for Tes1ing and Materials, 1973.
- 10. U.S. Noclear R.egulatoty Commissi~ Office of Nudear R.egulatoiy Research., Regulatory Guide 1.99, R.e\,"ision 2. '-"Radiation Embrittlement of Reactor Vessel Materials,.. fay 1988. [ADAMS Ace -ssion Numbe.r MI.00374028,fJ
- 11. NUREG-1801, R.el..-ision 2, ~eric Aging Lessons Leamed (GALL) Report" U.S. Nuclear R.egulaiory Commission, December 2010. [ADAMS Accession Number MI.103490041 J
Page 7 of 14 Capmle u
V X
w z
y(c)
NotesforTable l:
Serial No.22-227 Docket No. 50-395 : Page 7 of 14 Westinghouse Non-Proprietary Class 3 T able I CGE-RVOO0-TM-ME-000004, Rev. 3 Attachment A Page6of12 Recommended Sun*eillance Capsule \Vithdr:nral Schedule<*>
Location Capsule Lead Remonl TuneOO Cafsule Flue ce (deg)
Factor (EFPY)
(n/cm, E>l.O Me\) (1,)
343 3.04 l.13(EOC 1) 6.75 X 1011 107 3.34 2.93 (EOC 3) 1.54 X 1()111 287 3.54 5.04(EOC5) 2.51 X 1019 110 3.21 11.21 (EOC 10) 4.63 X 10111 340 3.10 1636 (EOC 14) 6.53 X 1<>1!1 290 3.09 17.71 (EOC 15) 7.0} X 10111 101<*>
- 3.5 48.2(<)
1.14 X 1()20 (a) E&'edm! fiill po11,w year. from plant startup. End of Cycle (E(X;),.me P'\"1!11 in~- Note tb.t C'On!
thmnal pov.wwas uprated m>m m s to 2900 MWa. stutmg with operating cycle 10.
(b) Valoes ill!! taken from WCAP-lS-TIS-NP {Rei 6] Table 2-l (c) Capsule Y will be reinserted clmmg lW'u.eling Oubge 30 in the Fill of2fl1.7 (prior to Cycle 31) in location 107" (orS)'Dlllll!'lric~ons 28T or343j, which is project~to occurat 37.7 EFPY. Capsule Y mllachir..-.! thepeak 100-year ~. 1.14 x l 010n!an2 (E > l.0 ~leV), befon remoi.-al, miicb is ~
to n,qain? :mother 10.5 EFPY of operation (37.7 + 10.5 = 48.2). The Ill!m!St ou12ge to the ~
remw.11 of 482 EFPY will occur at EOC 38 after 48.4 EfPY, which is the project~ mma..d time of Capsule Y.
Page 8of 14 Serial No.22-227 Docket No. 50-395 : Page 8 of 14 Westinghouse Non-Proprietary Class 3 TablPl CGE--RVOO0-TM-ME-000004, Rev. 3 Attachment A Page7of12 ARTNDT Calculations for thl' Y.C. Summl'r Unit I RPaetor Y essel at 72 EFPY Surlael' PndictPd RHrtor Vessel Matnial RG l.99 Wt. *,t, Wt. %
CFII>>
Flume~>
Ff{,I)
ARTm~>
Position Cu<*>
Ni<>
("F)
(x IOlt nlrm.1, E>LOMPV)
("F)
Beltti.ne l'tlaterials fulel:mcdiate Shell 11-1 1.1 0.10 0.51 65.0 9.04 1.501 975
@at l#_A9!?+1) ___
Using non-aedib/a SU1Willm1ce 2.1 435 9.04 1.501 65.3 datdfJ Intennediate Sbell 11-2 u
0.09 0.45 58.0 9.04 1.501 87.0
<Heat# A9153-2)
Lower Shell 10-1 1.1 0.08 0.41 51.0 9.06 1.501 76.6 tHeat # C9923-D Lower Shell 10-2 1.1 0.08 0.41 RO 9.06 1.501 76.6 fHPM# C9923-2)
Intermediate Shell Long.
Weld Seams BC & BD 1.1 0.05 0.91 68.0 3.03 1.293 87.9
@ at# 4P4784)
. Usini *cret1tbb;;;;;:Ji1nn"ce "Jtiia'.fJ.
2.1
- 423 ""
3.03 1.293 54.7 Intenned.iate to Lower Shell Circ.
Weld Seam AB 1.1 0.05 0.91 68.0 9.04 1.501 102.0
...... @~t~~f:1-J~L........
I
- * * * * * * * * --*423 ** ******1ro.r***-- ***uoc* **** 63_5**--
Usinll credible SILT'l'eillance dnlrf!J 2.1 l ower Shell Long.
Weld Seams BA & BB 1.1 0.05 0.91 68.0 3.08 1.297 882
.....*.... Qieat# 4P4784L......*..
Usin2 aediblB sun*eillmtce dnlrf.lJ 2.1 423 3.08 1.297 54.9 Extended & ltlin.t> Mattrials Nozzle Shell 12-1 1.1 0.13 0.57 90.1 0.400 0.746 612 tHeat# C9955-2)
Nozzle Shell 12-2 1.1 0.12 0.58 826 0.400 0.746 61.6 fHeat # C0123-2)
Nozzle to Intmnediate Shell Circ.
WeldSeam AC 1.1 0.05 0.91 68.0 0.425 0.762 51.8 (Ht~!Jt~f~}S§)
........... ***423 ** ******o.425 ***-- *--0_16i ** ***. 32.2****
Using credible Sllr'fflllance dalrfll 2.1 Nozzle Shell Long.
1.1 0.06 1.01 820 0.400 0.746 61.2 Weld Seams BE and BF Inlet Nozzle 436B-1 1.1 0.127 0.76 92.1 0.0310 0.224 20.6
<HP.at# 0 20.tlWI Inlet Nozzle 436B-2 1.1 0.127 0.82 93.0 0.0310 0.224 20.8
<Heat# Q2Q39Wl Inlet Nozzle 436B-3 1.1 0.127C!>
0.82 93.0 0.0310 0.224 20.8
<Heat# O2O39Wl Outlet Nozzle 437B-1 1.1 0.127C!>
0.85 93.0 0.0132 0.132 123 ffieat # 02040)
Outlet Nozzle 437B-2 1.1 0.127{!)
0.80 93.0 0.0132 0.132 123 rHPat #1-,,.-,...--,w, Outlet Nozzle 437B-3 1.1 0.12100 0.78 92.6 0.0132 0.132 12.2 (Heat# Q2Q44W)
Serial No.22-227 Docket No. 50-395 : Page 9 of 14 Page 9of 14 Westinghouse Non-Proprietary Class 3 C-GE-RVOOO-TM-ME-000004, Rev. 3 Attachment A Page8 of 12 InlctlOutlct Nozzle Forgings to Nozzle Shell 1.1 0.06 1.01 82.0 0.031 0.224 Weld Seams 15AIBJC & 16AIB/C Notes for Table 2:
(a) Chemimy1,alt11!s were tlbn from t\CAP-18728-NP [Re£ 6], UDless ocherniseDOted.
(b) Regulatmy Guidi! (R.G) 1.99 [Re£ IO], Position 1.1 Oenisby Fart= (CFs).Ill! based on Tublei l and 2 of Regulattxy Guidi! 1.99, Rerisian 2 using thl! Cu and Ni~ peta!llt, -ahies. Regubtmy Guide (RG) 1.99, Position 21 CFs an c:alomted based on anilab e sur.-eillaoce dab in WCAP-18728-NP [Re£ 6].
(c) FJn,,,,a, bbn man \JlCAP-187>-8-NP pw: 6] and include a 10"/4 bias on the periphery.
(d) FF= fl:umce f.ctor= f111.2&-cno-q (I))_
(e) ARI=
(f) Th! cndilnlity e..iluation fbr1he VCSNS Unit I sun~
data in.Appem!ix A ofWCAP-18728-NP ~
that tru-VCSNS Unit I son.-ei:llma data fix-tru-Inle:nMdiate Shell ll-1 (Heat # A9154-l) is deaned non-credible and the S~
W21.d (Heat Ii 4P4784) isdeemedCil!diole.
(g) ~
,.tlue £or SA-508 Class 2 name £,xgiDgs &om PWR.OG-15109-NP-A [Re£ S].
18.4
T ahlt 3 Compari>oa of dit Y.C. S R,q-.in111ttl for Capo \Titlulmnl S<htdlllt i!
pu ASill £18-"-S? Tahlt Il<I 3 EFPY or al thr time when the ~
omtrOll 1hmn of the capsule =<eds.S " 10" 1J!ari, ar at I
thr time ooim ibe ~pr,di<t,d&rr,,wof all
~
11111mm is ~
j()'f,
- hicli<\..,-.,.,.,.,_fint_
6 EFPY ar at the time i1t.m ibe acamiab.~ Dflllnm 2
flomce oftheap,ule c~
to 1hr
- pprulIIIII!< mkf.U-(EOL) llnonce at 1hr ruttor,*Cl$Cl l/4T loc:alica, wlli<hr= m-. fir 15 EFPY or al ibt timt wh,ri theattlm!lll!ltd 3
l:N1llll llxD::e of the ~
com,pon,:b to the
~
EOL ~
al 1llf md<<..,.,:d imfr
.. -.n locali,on, ~
<<:mOS lim.
EOL arnot las ihlll COC1' or n,all'f Ihm micf pw EOL'--' ~.
Thismaybe mocUtd ca 4
1hr bosis of[,R"ious lnts. This apmlf may~ bold wilhom liS!ing follcming wilh<hm-al.
s NIA Serial No.22-227 Docket No. 50-395 : Page 10 of 14 We.--Jingllome Non-Proprim,y Class 3 CGE-RVOOO-nl-ME-000004, Rev. 3 Altadmem A Pagr9ofl2 n t.'air l Cap,lllt Uitlulr:m~ Sd1tdlllt ffidi ASill EIS.~, dit G.U.L, nd da* GAlL-SLR.
S"'Zltmt*lal Gllid.uct from All ud G.ll.L-SI.R CoDU11tJ1uO'l
~
U was 1ri!bdl:n-n al EOC I, "'ilh c ""P""'R of 1.13 EFPY md 1
~
-6.7 5x 1011.,1cn,l.
N!A AS'IME185-112ismrt~ the czpsnk,ns'WillldJN,n wiJ:h a tm.nc.
pal,r fhm j X 1011 ll'a!r.
Capowo V wn 'lritlwlln-nal EOC3, wilh m "'P"S'ft of 2.93 EFl'Y and 1 f!amte = J.54x lO" n'r:ml. ThepH): lt4T &.noeatEOL (.....aed lobe 36 ElJ'Y, 4..42 X I0"1>'cnr)ll 2.Jt X 10" 1>'c:m2. (lj s mce c apml,. V flumc,n mnchltss 11w, 278 x 10'* n1cm1, Caps,,kx NIA will be <oD>id<rld. ClplU!eX W111 i1iihdn,m at EOC.S, wilh m l!llpC>Sln of.S.04 EFPY m:I I lluma, of251 x 10" D!c:m2.
ASlM EIS5-ll isme!.
thr lm!,no, iJ \~ -
thr lt-iT llnosic, md the 6EFPY amia. ha addition, at the time of wilhdmnl of llli capsw.
the EFPY un Jibly bo<ed m diffued flumu ~
and posm>ly a cliffi!nm EFPY tttm..
Cqm1f W in.swilhmnua1EOC 10, *ilh m apo=e oflUI EFPY w h Jlumce --4.63 x 10'11>'mr. The clad~
m,o}flumce at EOL WA (36Ffl'Y} WH"Jlll'~H2 x 10'1n/cm1.
AS1ME185--ll2 ismrt ~
thec..,ie fluma,.,.. pater Ihm the t!uair:t of the cbd/ba\e mtbL up,uleZ wu1'ilbfhwDIIEOC 14, 1'illl
~
of1636EFPY md * ~
= 6.53 x lO"nlmi. ~
cbd-1,ue mttal flnentt at 1hr fDd Pe1 lbt GALL, me capsule is of PEO (56 EFPY)\QS waJimr,dy 7.00 x 1011 nlcml. Ho-,.fl; lbt
-.rill>:ll:n11 md ~
at a fhlaxe of sch<dw* imp!,mmlfd.h liameRlle'i<II md app=ei by the NRC
-lfz lhmo,n or gutt<> lh1ll
!h,c,a.
m, also....n,.ilhm lbt 20'/4 unamintyrequirrd by Rr!"l1lo<YGuide LllJO.
ASlM El8~ md OAIJ.. mi<l>In are a:mida-td met GAIL-SLR. one capsule is mtblmm Addi6.oml data is n,:p,ir,d IO meet thu aitmaa; 1llmmre, Cap<Ul,, Y mi tes'.td at a Jln!!lce of not 1... lh,u should be ~
md iindwrd as :mv.-n in Tobit I.
<m<e or p na: 6w, twic.~the pw
<lld ofSPEOve=ltlutix:e.
Pago 11 of 14 Westinghouse Non-Proprietaiy Cl&U 3 No<.; bDJ,'s:l:
(I) lboap,u-nbo.<J-d.mm,b,,s, mdEfPY='-... bbn&.m T.ble 4 oflhis loaw.
Serial No.22-227 Docket No. 50-395 : Page 11 of 14 CGE-RVOOO. TM-ME-000004, Rev. 3 Attac:hmentA P1ge 10 of 12 (b) 11io 1!4T-.nlM was ~- tho,.,bc,e ll,m,oe, tbt n12<tor nssel behliae ~
(l.7S inc:!-,), md ~
£= t.r* __.,."' mm RG 1.99,:Rmsiool,-., x= ll:a doplh tho ns,ol,nll (m:u:).
(o) VCSNSmom tho ~
oC.4 cap,,L'-mthdmnl:d,ad,:!t za danoedi:iASI'Ml!l8~sincetl,e limilmg=
=-ispull!rlhao. lOO"F mdlossd= 200"F.
Page 12 of 14 Serial No.22-227 Docket No. 50-395 : Page 12 of 14 Westinghouse N on-Proprietary Class 3 T able 4 CGE-RVOOO-TM-ME-000004, Rev. 3 Attachment A Page 11 of12 SuIYrilllince Capsule Projrrted Floeate (n/cm1, E >1.0 Mel) for V.C. Summrr Unit 1<->
Cydl' Lfngth Cumubiin R o,n.cr (n/cm2)
Cydt Operating (EFPY)
Timr (EFPY) 17" 20° 1
1.13 1.13 6.75E+tg(bl 5.90E+18 2
0.67 1.80 l.01E+19 8.94E+l8 3
1.13 2-93 l.54E+t!){<l 136E+19 4
1.16 4.09 2.03E+19 1.80E+19 5
0.95 5.04 2.51E+19<,I) 224E+19 6
1.17 6.21 3.13E+l9 2.79E+l9 7
1.22 7.43 3.63E+l9 3.24E+l9 8
1.19 8.61 4.13E+19 3.69E+19 9
1.27 9.89 4.66E+19 4.15E+19 10 1-32 11.21 5.18E+19 4.63E+tg(*l 11 1.36 12.56 5.78E+19 5.15E+19 12 1.37 13.94 6.35E+19 5.66E+19 13 1.09 15.03 6.76E+19 6.02E+19 14 1.33 16.36 7.34E+19 6.53E+t9© 15 1.35 17.71 7.88E+l9 7.0lE+tg(!)
16 1.34 19.05 8.42E+19 7.49E+l9 17 1.38 20.43 9.00E+19 8.01E+19 18 1.30 21.73 9.52E+19 8.49E+l9 19 1.31 23.04 l.01E+20 8.97E+l9 20 1.36 24.41 l.06E+20 9.46E+19 21 1.29 25.70 l.11E+20 9.93E+19 22 1.29 26.99 1.17E+20 1.04E+20 23 1.34 28.33 l.23E+20 l.09E+20 24 1.32 29.65 1.28E+20 1.14E+20 25 1.36 31.01 l.34E+20 1.19E+20 26 1.37 32.38 1.39E+20 124E+20 27(/1) 1.37 33.75 l.45E+20 1.30E+20 No bias on t!ie peripheral a11d re-e:nlnmt comer assembly relo.tive powers Future@
36.00 l.55E+20 138E+20 Future 42.00 1.80E+20 1.61E+20 Future@
48.00 2.05E+20 l.83E+20 Future© 54.00 2.30E+20 2.06E+20 Future© 60.00 2.55E+20 228E+20 Future© 66.00 2.80E+20 2.51E+20 Future 72.00 3.05E+20 2.73E+20
Page 13 of 14 Serial No.22-227 Docket No. 50-395 : Page 13 of 14 Westinghome Non-Propriet31Y Class 3 Cydt u ngth Cumufatin Cyd t Operating (EFPY)
Time (EFPY)
CGE-RV000-1M-ME-000004, Rev. 3 Attachment A Page 12 of12 Flutnce (n/C"m2) 17° 20" 10% bias on the peripheral and re-entrant corner assembly relatil'e powers Future© 36.00 Future(i) 42.00 Future© 48.00 Future© 54.00 Future(i) 60.00 Future© 66.00 Future(i) 72.00 Notes foc T b e 4:
(a) Infonmtion bl.en from WCAP-18728-NP [Re£ 6].
(b) This v.uue is applic.ble to Capmle U.
{ c) This.alm, is applicable to Capmle V.
(d) This r.iiue is applic.ble to Capmle X (e) This r.!lue is applicable to Capsule W.
(f) This r.!lue is applic.ble to Capsule Z.
(g) This nlue is applicable to Capmle Y.
1.56E+20 139E+20 1.83E+20 1.64E+20 2.11E+20 1.88E+20 2.38E+20 2.13E+20 2.66E+20 23 8E+20 2.93E+20 2.63E+20 3.21E+20 2.87E+20 (h) Cycle 27 was &e currat openting cycle at the time the lhlence analysis was perl'mmed.
(i) Values beyuod Cycle 27 are based on the.nuage an power d:istnlrotims and rudoc ~
CODditions of cycles 25, 26, and 27 and are de_1Emi:Ded bo1h lrilh and mfbout a 1.1 bias on 1he periphel'.lll and re--entr.mt <<1rI1B.wembly i:ehtm powers.
Pag@ 14 of 14 CGE-ffVOOC)-TIHlf-GOOOO( Rt tlOn :S Serial No.22-227 Docket No. 50-395 : Page 14 of 14 N 011-f>ropltabry ~
3 ancl 511311 not bf~
l'I Ille P* numbeMg Df U-doclzmnl. **
Approval Information Author Approval Lynch Donald Sep-09-2022 13:41 :22 Author Approval Ziegler Tyler Sep-12-2022 08:49:48 Verifier Approval McNutt Don Sep-12-2022 09:15:01 Manager Approval Patterson Lynn Sep-12-2022 09:27:50