ML22332A454

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Attachment 6 - LaSalle County Generating Station Units 1 and 2 Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (EFPY) (Non-Proprietary)
ML22332A454
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Site: LaSalle  Constellation icon.png
Issue date: 11/10/2022
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ATTACHMENT 6

LaSalle County Generating Station Units 1 and 2 Pressure and Te mperature Limits Report (PTLR) for 54 Effective Full-Power Years (EFPY) (Non-Pro prietary)

Constellation Energy

LaSalle County Station Units 1 and 2

Pressure and Temperature Limits Report (PTLR) up to 54 Effective Full-Power Years (EFPY)

Revision 0 LaSalle County Station Units 1 and 2 PTLR Revision 0 Page 2 of 50

Table of Contents Section Page

1.0 Purpose 4 2.0 Applicability 4 3.0 Methodology 5 4.0 Operating Limits 6 5.0 Discussion 7 6.0 References 14

Appendix A LaSalle Reactor Vessel Materials Surveillance Program 50 LaSalle County Station Units 1 and 2 PTLR Revision 0 Page 3 of 50

List of Figures

Figure 1: LSCS Unit 1 P-T Curve A (Hydrostatic Pressure and Leak Tests) for 54 EFPY..........16 Figure 2: LSCS Unit 1 P-T Curve B (Normal Operation - Core Not Critical) for 54 EFPY........17 Figure 3: LSCS Unit 1 P-T Curve C (Normal Operation - Core Critical) for 54 EFPY...............18 Figure 4: LSCS Unit 2 P-T Curve A (Hydrostatic Pressure and Leak Tests) for 54 EFPY..........19 Figure 5: LSCS Unit 2 P-T Curve B (Normal Operation - Core Not Critical) for 54 EFPY........20 Figure 6: LSCS Unit 2 P-T Curve C (Normal Operation - Core Critical) for 54 EFPY...............21 Figure 7: LSCS Feedwater Nozzle 3-D Finite Element Model [17].............................................22 Figure 8: LSCS Feedwater Nozzle Stress Extraction Path [17]....................................................23 Figure 9: LSCS LPCI Nozzle Finite Element Model [18].............................................................24 Figure 10: LSCS LPCI Nozzle Stress Extraction Path [18]..........................................................25

List of Tables

Table 1: LSCS Unit 1 Pressure Test (Curve A) P-T Curves for 54 EFPY....................................26 Table 2: LSCS Unit 1 Core Not Critical (Curve B) P-T Curves for 54 EFPY..............................29 Table 3: LSCS Unit 1 Core Critical (Curve C) P-T Curves for 54 EFPY.....................................32 Table 4: LSCS Unit 2 Pressure Test (Curve A) P-T Curves for 54 EFPY....................................36 Table 5: LSCS Unit 2 Core Not Critical (Curve B) P-T Curves for 54 EFPY..............................39 Table 6: LSCS Unit 2 Core Critical (Curve C) P-T Curves for 54 EFPY.....................................42 Table 7: LSCS Unit 1 1/4T ART Table for 54 EFPY....................................................................45 Table 8: LSCS Unit 2 1/4T ART Table for 54 EFPY....................................................................47 Table 9: Nozzle Stress Intensity Factors........................................................................................49 LaSalle County Station Units 1 and 2 PTLR Revision 0 Page 4 of 50

1.0 Purpose

The purpose of the LaSalle County Station (LSCS) Pressure and Temperature Limits Report (PTLR) is to present operating limits relating to:

1. Reactor Coolant System (RCS) Pressure versus Temperature limits during Heat-up, Cool-down and Hydrostatic/Class 1 Leak Testing;
2. RCS Heat-up and Cool-down rates;
3. RPV head flange boltup temperature limits.

This report has been prepared in accordance with the requirements of Licensing Topical Reports SIR-05-044, Revision 1-A, contained within BWROG-TP-11-022-A, Revision 1 [1].

2.0 Applicability

This report is applicable to the LSCS Unit 1 and Unit 2 RPVs for up to 54 Effective Full-Power Years (EFPY).

The following LSCS Technical Specifications (TS) are affected by the information contained in this report:

TS 3.4.11 RCS Pressure/Temperature (P/T) Limits

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3.0 Methodology

The limits in this report were derived as follows:

1. The methodology used is in accordance with Reference [1], Pressure - Temperature Limits Report Methodology for Boiling Water Reactors, August 2013, incorporating the NRC Safety Evaluation in Reference [2].
2. The neutron fluence is calculated in accordance with NRC Regulatory Guide 1.190 (RG 1.190) [3] as documented in Reference [5].
3. The adjusted reference temperature (ART) values for the limiting beltline materials are calculated in accordance with NRC Regulator y Guide 1.99, Revision 2 (RG 1.99) [4], as documented in Reference [5].
4. The pressure and temperature limits, which were calculated in accordance with Reference

[1], are documented in Reference [6].

5. This revision of the pressure and temperature limits report is to incorporate the following changes:

Revision 0: Initial issue of PTLR.

Changes to the curves, limits, or parameters within this PTLR, based upon new irradiation fluence data of the RPV, or other plant design assumptions in the Updated Final Safety Analysis Report (UFSAR), can be made pursuant to 10 CFR 50.59 [8], provided the above methodologies are utilized. The revised PTLR shall be submitted to the NRC upon issuance.

Changes to the curves, limits, or parameters within this PTLR, based upon new surveillance capsule data of the RPV or other plant design assumption modifications in the UFSAR, cannot be made without prior NRC approval. Such analysis and revisions shall be submitted to the NRC for review prior to incorporation into the PTLR.

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4.0 Operating Limits

The pressure-temperature (P-T) curves included in this report represent steam dome pressure versus minimum vessel metal temperature and incorporate the appropriate non-beltline limits and irradiation embrittlement effects in the beltline region.

The operating limits for pressure and temperature are required for three categories of operation:

(a) hydrostatic pressure tests and leak tests, referred to as Curve A; (b) core not critical operation, referred to as Curve B; and (c) core critical operation, referred to as Curve C.

Complete P-T curves were developed for 54 EFPY for LSCS, as documented in Reference

[6], and are provided in Figure 1 through Figure 3 for LSCS Unit 1 and in Figure 4 through Figure 6 for LSCS Unit 2. A tabulation of the curves is included in Table 1 through Table 3 for LSCS Unit 1 and in Table 4 through Table 6 for LSCS Unit 2. The adjusted reference temperature (ART) tables for 54 EFPY for the LSCS Unit 1 and Unit 2 vessel beltline materials are shown in Table 7 and Table 8, respectively [5].

The resulting P-T curves are based on the geometry, design and materials information for the LSCS Unit 1 and Unit 2 vessels with the following conditions:

Heat-up/Cool-down rate limit during Hydrostatic Class 1 Leak Testing (Figures 1 and 4:

Curve A): 25F/hour1 [6].

Bounding Heat-up/Cool-down rate limit (Figures 2 and 5: Curve B - non-nuclear heating, and Figures 3 and 6: Curve C - nuclear heating): The Single Relief or Safety Valve (SRV) Blowdown thermal transient event, Event No. 14 from the RPV thermal cycle diagram (TCD), has a maximum cooldown rate of 155°F/hr and is the limiting Service Level A/B event used in the calculations of Limit Curve B and Curve C.

1 Interpreted as the temperature change in any 1-hour period is less than or equal to 25°F.

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RPV bottom head coolant temperature to RPV coolant temperature T limit during Recirculation Pump startup: 145F [1].

Recirculation loop coolant temperature to RPV coolant temperature T limit during Recirculation Pump startup: 50F [1].

RPV flange and adjacent shell temperature limit

o LSCS Unit 1: > 72°F [6].

o LSCS Unit 2: 86F [6].

Minimum temperature limits are set in accordance with 10 CFR 50, Appendix G [7, Table 1]. An additional 60°F margin above the requirements in Table 1 of 10 CFR 50, Appendix G, is required in the BWR industry. For the LSCS closure flange material, the minimum temperature would be 72°F for Unit 1 (i.e. RTNDT,max of 12°F + 60°F) and 86°F for Unit 2 (i.e. RTNDT,max of 26°F + 60°F) [6]. These values are consistent with the minimum temperature limits and minimum bolt-up temperature in the current docke ted P-T curves [9] [10]. These values also bound the lowest service temperatures (LST) for ferritic non-RPV components of the reactor coolant pressure boundary (RCPB) [9] [10], thereby addressing the NRC condition in Reference

[2, Section 4.0].

5.0 Discussion

The adjusted reference temperature (ART) of the limiting beltline material is used to adjust beltline P-T curves to account for irradiation effects. RG 1.99 [4] provides the methods for determining the ART. The RG 1.99 methods for determining the limiting material and adjusting the P-T curves using ART are discussed in this section.

The vessel beltline copper (Cu) and nickel (Ni) values were obtained from the evaluation of the LSCS vessel plate, weld, and forging materials [11]. The Cu and Ni values were used with Table 1 of RG 1.99 to determine a chemistry factor (CF) per Paragraph 1.1 of RG 1.99 for welds. The LaSalle County Station Units 1 and 2 PTLR Revision 0 Page 8 of 50

Cu and Ni values were used with Table 2 of RG 1.99 to determine a CF per Paragraph 1.1 of RG 1.99 for plates and forgings.

The peak RPV ID fluence values of 4.69 x 1017 n/cm2 for Unit 1 and 9.11 x 1017 n/cm2 for Unit 2 at 54 EFPY used in the P-T curve evaluations were obtained from Reference [12] and [13].

These fluence values apply to the limiting Integrated Surveillance Program weld heat no. 1P3571 for Unit 1 and Integrated Surveillance Program plate heat no. C3054-2 for Unit 2. The fluence values for the limiting beltline materials in each unit are based upon attenuation method [4] for a postulated 1/4T flaw. Consequently, the 1/4T fluence for 54 EFPY for the limiting lower intermediate shell plates are 3.25 x 1017 n/cm2 for LSCS Unit 1 and 6.28 x 1017 n/cm2 for LSCS Unit 2 [5]. The limiting values for ART for beltline plates and welds are 98.5°F for Unit 1 and 85.7°F for Unit 2 [5].

The P-T limits are developed to bound all ferritic materials in the RPV (where the fluence exceeds 1 x 1017 n/cm2), including the consideration of stress levels from structural discontinuities such as nozzles. LSCS Unit 1 and Unit 2 have a set of instrument (N12) nozzles, which are located in the middle shell beltline pl ates [11]. Additionally, low pressure coolant injection (LPCI) N6 nozzle is considered in th e evaluation of beltline region P-T limits. The feedwater (FW) nozzle is considered in the evaluation of the non-beltline (upper vessel) region P-T limits.

The instrument nozzles have an RPV ID fluence of 2.85 x 1017 n/cm2 for Unit 1 and 3.28 x 1017 n/cm2 for Unit 2 at 54 EFPY, obtained from Reference [12] and [13]. The fluence value for the instrument nozzle location is based upon attenuation method for a postulated 1/4T flaw in the instrument nozzle blend radius. Consequently, the 1/4T fluence for 54 EFPY for the limiting instrument nozzle location is 1.97 x 1017 n/cm2 for Unit 1 and 2.26 x 1017 n/cm2 for Unit 2 [5].

The limiting value for ART for the instrument nozzles is 25.7°F for Unit 1 and 68.3°F for Unit 2 at 54 EFPY [5]. There are no additional forged or partial penetration nozzles in the extended beltline (defined as regions where the fluence exceeds 1 x 1017 n/cm2) at LSCS Units 1 and 2.

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The P-T curves for the core not critical and core critical operating conditions at a given EFPY apply for both the 1/4T and 3/4T locations. When combining pressure and thermal stresses, it is usually necessary to evaluate stresses at the 1/4T location (inside surface flaw) and the 3/4T location (outside surface flaw). This is because the thermal gradient tensile stress of interest is in the inner wall during cool-down and is in the outer wall during heat-up. However, as a conservative simplification, the thermal gradient stresses at the 1/4T location are assumed to be tensile for both heat-up and cool-down. This results in the approach of applying the maximum tensile stresses at the 1/4T location. This approach is conservative because irradiation effects cause the allowable toughness at the 1/4T to be less than that at 3/4T for a given metal temperature. This approach causes no operational difficulties, since the BWR is at steam saturation conditions during normal operation, and for a given pressure, the coolant saturation temperature is well above the P-T curve limiti ng temperature. Consequently, the material toughness at a given pressure would exceed the allowable toughness.

The core not critical curve (Curve B) and the core critical curve (Curve C) are prepared considering a coolant heat-up and cool-down temperature rate corresponding to the limiting Service Level A/B transient on the RPV thermal cycle diagram, the SRV Blowdown event, which has a maximum cool-down rate during the transient of 155°F/hr, although for the majority of the transient, the cool-down rate is 100°F/hr. P-T curves are developed for normal operating conditions, and Technical Specifications limit operation to 100°F/hr. Additionally, for LaSalle, the SRV blowdown event is explicitly classified in the RPV thermal cycles as an Emergency condition. For conservatism, the SRV blowdown event was selected for evaluation as the limiting Service Level A/B transient. For the hydros tatic pressure and leak test curve (Curve A),

a coolant heat-up and cool-down temperature rate of 25°F/hr must be maintained. The P-T limits and corresponding limits of either Curve A or B may be applied, if necessary, while achieving or recovering from test conditions.

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The initial RTNDT, chemistry (weight-percent copper and nickel), and ART at the 1/4T location for all RPV beltline materials significantly affected by fluence (i.e., fluence > 1017 n/cm2 for E >

1 MeV) are shown in Table 7 and Table 8 for Unit 1 and Unit 2, respectively [5]. Use of initial RTNDT values in the determination of P-T cu rves for LSCS was approved by the NRC in Reference [11].

Per Reference [5] and in accordance with Appendix A of Reference [1], the LSCS representative weld and plate surveillance materials data were reviewed from the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) [14]. The representative plate material for LSCS Unit 1 (C6345-1) in the ISP is not the same as the target plate material (C5978-2). However, the C6345-1 is a plate heat in LSCS Unit 1 vessel beltline. The fitted CF is used for LSCS Unit 1 ISP plate material. The ISP representative weld material for LSCS Unit 1 (IP3571) is the same as the target weld material. The fitted CF value for LSCS Unit 1 ISP weld material is adjusted based on the difference between the surveillance weld and vessel weld. The ISP representative plate material for LSCS Unit 2 (C3054-2) is not the same heat number as the target plate material (C9404-2), nor does the representative plate heat exist in the LSCS Unit 2 beltline. The ISP representative weld materials for LSCS Unit 2 (402K9171, 411L3071) are not the same as the target weld material (3P4966). Therefore, for LSCS Unit 2 beltline materials, the CF values are calculated using table values from R.G. 1.99, Revision 2, Position 1.1 [4].

The only computer code used in the determination of the LSCS P-T curves was the ANSYS finite element computer program:

ANSYS, Release 14.5 Service Pack 1 [15] for:

o FW nozzle (non-beltline) through-wall thermal and pressure stress distributions in Reference [17].

ANSYS, Release 18.1 [16] for:

o LPCI nozzle thermal and pressure stress distributions in Reference [18].

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ANSYS finite element analyses were used to develop the stress distributions through the FW and LPCI nozzles as well as the vessel shell, and these stress distributions were used in the determination of the stress intensity factors for the FW and LPCI nozzles [17, 18] and vessel shell. At the time that each of the analyses above was performed, the ANSYS program was controlled under the vendors 10 CFR 50 Appendix B [19] Quality Assurance Program for nuclear quality-related work. Benchmarking consistent with NRC GL 83-11, Supplement 1 [20]

was performed as a part of the computer program verification by comparing the solutions produced by the computer code to hand calculations for several problems.

The plant-specific LSCS FW nozzle analyses were performed to determine through-wall pressure stress distributions and thermal stress distributions due to bounding thermal transients.

Detailed information regarding the analyses can be found in Reference [17]. The following summarizes the development of the thermal and pressure stress intensity factors for the FW nozzle:

A one-quarter symmetric, three-dimensional (3-D) finite element model (FEM) of the FW nozzle was constructed and is shown in Figure 7. Details of the model and material properties are provided in Reference [17]. The Youngs modulus and thermal expansion coefficient are taken from the 1968 Edition with 1969 Winter Addenda [21] for Unit 1 and 1970 Winter Addenda [22] for Unit 2. The thermal conductivity and thermal diffusivity are taken from the ASME Code Section II 2001 through addenda 2003 Edition

[23].

Heat transfer coefficients were calculated in Reference [17] and are a function of FW temperature and flow rate.

With respect to emergency conditions, the thermal transient which represents the maximum thermal ramp for the regions co rresponding to the FW nozzles during SRV Blowdown transient and the shutdown vessel flooding transient were analyzed [17]. The thermal stress distributions, corresponding to the limiting times presented in Reference

[17], along a linear path through the nozzle corner is used as shown in Figure 8. The boundary integral equation/influence function (BIE/IF) methodology presented in LaSalle County Station Units 1 and 2 PTLR Revision 0 Page 12 of 50

Reference [1] is used to calculate the thermal stress intensity factor, K It, due to the thermal stresses by fitting a th ird order polynomial equation to the path stress distribution for the thermal load case.

With respect to pressure stress, a unit pressure of 1000 psig was applied to the internal surfaces of the 3-D model in Reference [17]. The pressure stress distribution was taken along a linear path through the nozzle corner as shown in Figure 8. The BIE/IF methodology presented in Reference [1] was used to calculate the applied pressure stress intensity factor, KIp, by fitting a third order polynomial equation to the path stress distribution for the pressure load case. The resulting KIp may be linearly scaled to determine the KIp for various RPV internal pressures.

The plant-specific LSCS LPCI nozzle analysis was performed to determine through-wall pressure stress distributions and thermal stress distributions due to bounding thermal transients.

Detailed information regarding the analysis can be found in Reference [18]. The following summarizes the development of the thermal and pr essure stress intensity factors for the LPCI nozzle:

A one-quarter symmetric, 3-D FEM of the instrument nozzle was constructed and is shown in Figure 9. ASME 1968 Edition with 1970 Winter Addenda [22] is used for Youngs Modulus and thermal expansion coefficients. Thermal conductivity was taken from 2001 ASME Code through 2003 Addenda [23], were used in the evaluation and are described in Reference [18].

A single model was developed to bound both units.

With respect to operating conditions, the bounding thermal transient for the region corresponding to the instrument nozzles during normal and upset operating conditions was analyzed [18]. The thermal stress distribution, corresponding to the limiting time in Reference [18], along a linear path through the nozzle corner as shown in Figure 10 is used. The BIE/IF methodology presented in Reference [1] was used to calculate the thermal stress intensity factor, K It, due to the thermal stresses by fitting a third order polynomial equation to the path stress distribution for the thermal load case.

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Boundary conditions and heat transfer coefficients used for the thermal analysis are described in Reference [18].

With respect to pressure stress, a unit pressure of 1000 psig was applied to the internal surfaces of the FEM [18]. The pressure stress distribution was taken along the same path as shown in Figure 10 as the thermal stress distribution. The BIE/IF methodology presented in Reference [1] is used to calculate the pressure stress intensity factor, KIp, by fitting a third order polynomial equation to the path stress distribution for the pressure load case. The resulting KIp can be linearly scaled to determine the KIp for various RPV internal pressures

Table 9 summarizes the pressure stress intensity factor and maximum thermal stress intensity factor for both feedwater and LPCI nozzle.

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6.0 References

1. BWROG-TP-11-022-A, Revision 1, Pressure Temperature Limits Report Methodology for Boiling Water Reactors, August 2013. (ADAMS Accession No. ML13277A557)
2. U.S. NRC Letter to BWROG dated May 16, 2013, Final Safety Evaluation for Boiling Water Reactor Owners Group Topical Report BWROG-TP-11-022, Revision 1, November 2011, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors (TAC NO. ME7649, ADAMS Accession No. ML13277A557).
3. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, March 2001.
4. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May 1988.
5. SI Calculation No. 2001063.304P, Revision 1, Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts, October 20, 2022.
6. SI Calculation No. 20001063.305, Revision 0, LaSalle Units 1 and 2 P-T Curve Calculation for 54 EFPY, October 20, 2022.
7. U.S. Code of Federal Regulations, Title 10, Part 50, Appendix G, Fracture Toughness Requirements, December 12, 2013.
8. U.S. Code of Federal Regulations, Title 10, Part 50, Section 59, Changes, tests and experiments, August 28, 2007.
9. Non-Proprietary General Electric Company Reports GE-NE-0000-0003-5526 R1a, Pressure-Temperature Curves for Exelon LaSalle Unit 1, May 2004, ADAMS Accession No. ML041950197.
10. Non-Proprietary General Electric Company Report GE-NE-0000-0003-5526-01R1a, Pressure-Temperature Curves for Exelon LaSalle Unit 2, May 2004, ADAMS Accession No. ML101130372.
11. License Renewal Application, LaSalle County Station, Units 1 and 2, December 9, 2014.
12. Exelon TODI No. SEAG 21-000040, Rev 0, SI File NO. 2001063.204.
13. Exelon TODI No. SEAG 21-000039, Rev 0, SI File NO. 2001063.204.
14. BWRVIP-135, Revision 4: BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations. EPRI, Palo Alto, CA: 2014.

3002003144. EPRI PROPRIETARY INFORMATION.

15. ANSYS Mechanical APDL, Release 14.5 (w/ Service Pack 1 UP20120918), ANSYS, Inc., September 2012.
16. ANSYS Mechanical APDL (UP20170403), March 31, 2017, Release 18.1, SAS IP, Inc.

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17. SI Calculation No. 2001063.301, Revision 0, Feedwater Nozzle Fracture Mechanics Evaluation for Pressure-Temperature Limit Curve Development, October 10, 2022.
18. SI Calculation No. 2001063.302, Revision 0, Low Pressure Coolant Injection Nozzle Fracture Mechanics Evaluation for Pressure -Temperature Limit Curve Development, October 10, 2022.
19. U.S. Code of Federal Regulations, Title 10, Energy, Part 50, Appendix B, Quality Assurance for Nuclear Power Plants and Fuel Reprocessing Plants.
20. U.S. Nuclear Regulatory Commission, Generic Letter 83-11, Supplement 1, License Qualification for Performing Safety Analyses, June 24, 1999.
21. ASME Boiler and Pressure Vessel Code Section III, Rules for Construction of Nuclear Vessels, 1968 Edition with 1969 Winter Addenda and Article 4 of the 1969 Winter Addenda.
22. ASME Boiler and Pressure Vessel Code Section III, Rules for Construction of Nuclear Vessels, 1968 Edition with 1970 Winter Addenda.
23. ASME Boiler and Pressure Vessel Code,Section II, Part D, Material Properties, 2001 Edition with Addenda through 2003.
24. U.S. Code of Federal Regulations, Title 10, Part 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements, January 31, 2008.
25. BWRVIP-86, Revision 1-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan. EPRI, Palo Alto, CA: 2012. 1025144.

EPRI PROPRIETARY INFORMATION.

26. BWRVIP-250NP, BWR Vessel and Internals Project, Testing and Evaluation of the LaSalle Unit 1 120° Surveillance Capsule. EPRI, Palo Alto, CA: 2011. 1022850.
27. BWRVIP-239, BWR Vessel and Internals Project, Updated Evaluation of the Integrated Surveillance Program (ISP) Capsule Withdrawal Schedule. EPRI, Palo Alto, CA: July 2010. 1021009.
28. SI File No. 2000115.401, Revision 0, Updated Evaluation of the EPRI BWRVIP ISP Capsule Withdrawal Schedule, May 3, 2021.

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Figure 1: LSCS Unit 1 P-T Curve A (Hydrostat ic Pressure and Leak Tests) for 54 EFPY

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Figure 2: LSCS Unit 1 P-T Curve B (Normal Operation - Core Not Critical) for 54 EFPY

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Figure 3: LSCS Unit 1 P-T Curve C (Norma l Operation - Core Critical) for 54 EFPY

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Figure 4: LSCS Unit 2 P-T Curve A (Hydrostat ic Pressure and Leak Tests) for 54 EFPY

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Figure 5: LSCS Unit 2 P-T Curve B (Normal Operation - Core Not Critical) for 54 EFPY

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Figure 6: LSCS Unit 2 P-T Curve C (Norma l Operation - Core Critical) for 54 EFPY

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Figure 7: LSCS Feedwater Nozzle 3-D Finite Element Model [17]

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Figure 8: LSCS Feedwater Nozzle Stress Extraction Path [17]

Unit 1

Unit 2

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Figure 9: LSCS LPCI Nozzle Finite Element Model [18]

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Figure 10: LSCS LPCI Nozzle Stress Extraction Path [18]

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Table 1: LSCS Unit 1 Pressure Test (Curve A) P-T Curves for 54 EFPY Beltline Region CurveAPressureTest PTCurve PTCurve Temperature Pressure

°F psi 72.0 0.0 72.0 607.6 84.3 655.4 94.1 703.1 102.3 750.9 109.4 798.7 115.6 846.4 121.1 894.2 126.0 942.0 130.6 989.8 134.7 1037.5 138.5 1085.3 142.1 1133.1 145.4 1180.8 148.5 1228.6 151.4 1276.4 154.2 1324.1 156.8 1371.9 159.3 1419.7 161.7 1467.5 163.9 1515.2 166.1 1563.0

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Table 1: LSCS Unit 1 Pressure Test (Curve A) P-T Curves for 54 EFPY (continued)

Bottom Head Region CurveAPressureTest PTCurve PTCurve Temperature Pressure

°F psi 72.0 0.0 72.0 658.5 78.4 706.1 84.0 753.7 89.1 801.3 93.7 848.9 98.0 896.5 101.8 944.1 105.5 991.7 108.8 1039.3 112.0 1086.9 114.9 1134.5 117.8 1182.1 120.4 1229.8 122.9 1277.4 125.3 1325.0 127.6 1372.6 129.8 1420.2 131.9 1467.8 133.9 1515.4 135.8 1563.0

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Table 1: LSCS Unit 1 Pressure Test (Curve A) P-T Curves for 54 EFPY (continued)

Non-Beltline Region CurveAPressureTest PTCurve PTCurve Temperature Pressure

°F psi 72.0 0.0 72.0 312.6 102.0 312.6 102.0 939.0 105.5 987.0 108.8 1035.0 111.8 1083.0 114.7 1131.0 117.4 1179.0 120.0 1227.0 122.5 1275.0 124.8 1323.0 127.1 1371.0 129.2 1419.0 131.3 1467.0 133.3 1515.0 135.2 1563.0

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Table 2: LSCS Unit 1 Core Not Critical (Curve B) P-T Curves for 54 EFPY Beltline Region CurveBCoreNotCritical PTCurve PTCurve Temperature Pressure

°F psi 72.0 0.0 72.0 147.7 78.9 192.5 84.9 237.3 90.3 282.1 95.2 326.9 99.6 371.8 103.7 416.6 107.5 461.4 111.0 506.2 118.9 554.3 125.7 602.3 131.7 650.3 137.0 698.4 141.9 746.4 146.3 794.4 150.3 842.5 154.1 890.5 157.6 938.5 160.8 986.6 163.9 1034.6 166.8 1082.7 169.5 1130.7 172.1 1178.7 174.5 1226.8 176.9 1274.8 179.1 1322.8 181.3 1370.9 183.3 1418.9 185.3 1466.9 187.2 1515.0 189.0 1563.0

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Table 2: LSCS Unit 1 Core Not Critical (Curve B) P-T Curves for 54 EFPY (continued)

Bottom Head Region CurveBCoreNotCritical PTCurve PTCurve Temperature Pressure

°F psi 72.0 0.0 72.0 377.8 80.6 427.2 88.0 476.6 94.4 526.0 100.1 575.4 105.2 624.7 109.8 674.1 114.0 723.5 117.9 772.9 121.5 822.3 124.9 871.6 128.1 921.0 131.1 970.4 133.9 1019.8 136.5 1069.2 139.1 1118.6 141.5 1167.9 143.7 1217.3 145.9 1266.7 148.0 1316.1 150.1 1365.5 152.0 1414.9 153.9 1464.2 155.7 1513.6 157.4 1563.0

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Table 2: LSCS Unit 1 Core Not Critical (Curve B) P-T Curves for 54 EFPY (continued)

Non-Beltline Region CurveBCoreNotCritical PTCurve PTCurve Temperature Pressure

°F psi 72.0 0.0 72.0 211.0 79.5 244.9 85.9 278.7 91.4 312.6 132.0 312.6 132.0 742.3 134.9 790.6 137.6 838.9 140.2 887.1 142.7 935.4 145.0 983.7 147.2 1032.0 149.3 1080.2 151.3 1128.5 153.3 1176.8 155.1 1225.1 156.9 1273.3 158.7 1321.6 160.3 1369.9 161.9 1418.2 163.5 1466.4 165.0 1514.7 166.4 1563.0

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Table 3: LSCS Unit 1 Core Critical (Curve C) P-T Curves for 54 EFPY Beltline Region CurveCCoreCritical PTCurve PTCurve Temperature Pressure

°F psi 72.0 0.0 72.019.8 87.0 28.1 98.5 75.9 107.9 123.7 115.8 171.5 122.6 219.3 128.6 267.1 133.9 315.0 138.8 362.8 143.2 410.6 147.2 458.4 151.0 506.2 158.9 554.3 165.7 602.3 171.7 650.3 177.0 698.4 181.9 746.4 186.3 794.4 190.3 842.5 194.1 890.5 197.6 938.5 200.8 986.6 203.9 1034.6 206.8 1082.7 209.5 1130.7 212.1 1178.7 214.5 1226.8 216.9 1274.8 219.1 1322.8 221.3 1370.9

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Table 3: LSCS Unit 1 Core Critical (Curve C) P-T Curves for 54 EFPY (continued)

Beltline Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure

°F psi 223.3 1418.9 225.3 1466.9 227.2 1515.0 229.0 1563.0

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Table 3: LSCS Unit 1 Core Critical (Curve C) P-T Curves for 54 EFPY (continued)

Bottom Head Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure

°F psi 72.0 0.0 72.0 233.3 89.5 282.6 102.4 331.8 112.6 381.1 121.1 430.3 128.4 479.6 134.7 528.8 140.4 578.1 145.4 627.3 150.0 676.6 154.2 725.8 158.1 775.0 161.7 824.3 165.0 873.5 168.2 922.8 171.2 972.0 174.0 1021.3 176.6 1070.5 179.1 1119.8 181.5 1169.0 183.8 1218.3 186.0 1267.5 188.1 1316.8 190.1 1366.0 192.0 1415.3 193.9 1464.5 195.7 1513.8 197.4 1563.0

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Table 3: LSCS Unit 1 Core Critical (Curve C) P-T Curves for 54 EFPY (continued)

Non-Beltline Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure

°F psi 72.0 0.0 72.0 103.3 92.1 145.2 105.8 187.0 116.1 228.9 124.4 270.7 131.4 312.6 172.0 312.6 172.0 742.3 174.9 790.6 177.6 838.9 180.2 887.1 182.7 935.4 185.0 983.7 187.2 1032.0 189.3 1080.2 191.3 1128.5 193.3 1176.8 195.1 1225.1 196.9 1273.3 198.7 1321.6 200.3 1369.9 201.9 1418.2 203.5 1466.4 205.0 1514.7 206.4 1563.0

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Table 4: LSCS Unit 2 Pressure Test (Curve A) P-T Curves for 54 EFPY Beltline Region CurveAPressureTest PTCurve PTCurve Temperature Pressure

°F psi 86.0 0.0 86.0 454.1 95.6 502.3 103.6 550.6 110.5 598.8 116.6 647.0 122.0 695.2 126.9 743.4 131.3 791.6 135.4 839.8 139.2 888.0 142.7 936.2 146.0 984.5 149.1 1032.7 152.0 1080.9 154.7 1129.1 157.3 1177.3 159.8 1225.5 162.1 1273.7 164.4 1321.9 166.5 1370.2 168.6 1418.4 170.6 1466.6 172.5 1514.8 174.3 1563.0

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Table 4: LSCS Unit 2 Pressure Test (Curve A) P-T Curves for 54 EFPY (continued)

Bottom Head Region CurveAPressureTest PTCurve PTCurve Temperature Pressure

°F psi 86.0 0.0 86.0 790.2 90.7 838.5 95.1 886.8 99.1 935.1 102.7 983.4 106.2 1031.7 109.4 1080.0 112.4 1128.3 115.3 1176.6 118.0 1224.9 120.5 1273.2 122.9 1321.5 125.3 1369.8 127.5 1418.1 129.6 1466.4 131.6 1514.7 133.6 1563.0

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Table 4: LSCS Unit 2 Pressure Test (Curve A) P-T Curves for 54 EFPY (continued)

Non-Beltline Region CurveAPressureTest PTCurve PTCurve Temperature Pressure

°F psi 86.0 0.0 86.0 312.6 116.0 312.6 116.0 1563.0

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Table 5: LSCS Unit 2 Core Not Critical (Curve B) P-T Curves for 54 EFPY Beltline Region CurveBCoreNotCritical PTCurve PTCurve Temperature Pressure

°F psi 86.0 0.0 86.0 175.4 94.8 213.5 105.8 263.5 114.7 313.5 122.3 363.5 128.9 413.4 134.7 463.4 140.0 513.4 144.7 563.4 149.0 613.4 153.0 663.3 156.6 713.3 160.1 763.3 163.3 813.3 166.3 863.3 169.1 913.3 171.8 963.2 174.4 1013.2 176.8 1063.2 179.1 1113.2 181.3 1163.2 183.5 1213.1 185.5 1263.1 187.4 1313.1 189.3 1363.1 191.1 1413.1 192.9 1463.0 194.6 1513.0 196.2 1563.0

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Table 5: LSCS Unit 2 Core Not Critical (Curve B) P-T Curves for 54 EFPY (continued)

Bottom Head Region CurveBCoreNotCritical PTCurve PTCurve Temperature Pressure

°F psi 86.0 0.0 86.0 486.6 92.3 535.6 97.9 584.5 102.9 633.4 107.5 682.3 111.7 731.3 115.5 780.2 119.1 829.1 122.5 878.0 125.6 927.0 128.6 975.9 131.4 1024.8 134.0 1073.7 136.5 1122.7 138.9 1171.6 141.2 1220.5 143.3 1269.4 145.4 1318.4 147.4 1367.3 149.4 1416.2 151.2 1465.1 153.0 1514.1 154.7 1563.0

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Table 5: LSCS Unit 2 Core Not Critical (Curve B) P-T Curves for 54 EFPY (continued)

Non-Beltline Region CurveBCoreNotCritical PTCurve PTCurve Temperature Pressure

°F psi 86.0 0.0 86.0 312.6 146.0 312.6 146.0 1563.0

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Table 6: LSCS Unit 2 Core Critical (Curve C) P-T Curves for 54 EFPY Beltline Region CurveCCoreCritical PTCurve PTCurve Temperature Pressure

°F psi 86.0 0.0 110.3 86.0 118.4 128.5 125.3 171.0 134.8 213.5 145.8 263.5 154.7 313.5 162.3 363.5 168.9 413.4 174.7 463.4 180.0 513.4 184.7 563.4 189.0 613.4 193.0 663.3 196.6 713.3 200.1 763.3 203.3 813.3 206.3 863.3 209.1 913.3 211.8 963.2 214.4 1013.2 216.8 1063.2 219.1 1113.2 221.3 1163.2 223.5 1213.1 225.5 1263.1 227.4 1313.1 229.3 1363.1 231.1 1413.1 232.9 1463.0 234.6 1513.0 236.2 1563.0

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Table 6: LSCS Unit 2 Core Critical (Curve C) P-T Curves for 54 EFPY (continued)

Bottom Head Region CurveCCoreCritical PTCurve PTCurve Temperature Pressure

°F psi 86.0 0.0 86.0 286.0 99.1 335.1 109.5 384.2 118.1 433.4 125.4 482.5 131.8 531.6 137.5 580.7 142.6 629.8 147.2 678.9 151.4 728.0 155.3 777.2 158.9 826.3 162.3 875.4 165.5 924.5 168.4 973.6 171.2 1022.7 173.9 1071.8 176.4 1121.0 178.8 1170.1 181.1 1219.2 183.3 1268.3 185.4 1317.4 187.4 1366.5 189.3 1415.7 191.2 1464.8 193.0 1513.9 194.7 1563.0

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Table 6: LSCS Unit 2 Core Critical (Curve C) P-T Curves for 54 EFPY (continued)

Non-Beltline Region CurveCCoreCritical PTCurve PTCurve Temperature Pressure

°F psi 86.0 0.0 86.0 305.1 87.2 312.6 186.0 312.6 186.0 1563.0

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Table 7: LSCS Unit 1 1/4T ART Table for 54 EFPY

54EFPY 54 Component Heat Initial 1/4T Fluence RTNDT i EFPY No. No. Lot No. % Cu % Ni CF RTNDT Fluence Factor f (°F) (°F) (°F) 1/4T

(°F) (n/cm2) ART

(°F)

Unit 1 Lower Shell Assembly 307-04 Plates:

G-5603-1 C5978-1 N/A 0.11 0.58 74 14 2.24E+17 0.185 13.6 0 6.8 41.3 G-5603-2 C5978-2 N/A 0.11 0.59 74 23 2.24E+17 0.185 13.6 0 6.8 50.3 G-5603-3 C5979-1 N/A 0.12 0.66 84 10 2.24E+17 0.185 15.5 0 7.7 41.0 Unit 1 Lower-Intermediate Shell Assembly 308-06 Plates:

G-5604-1 C6345-1 N/A 0.15 0.49 104 -20 6.77E+17 0.343 35.7 0 17.0 49.7 G-5604-2 C6318-1 N/A 0.12 0.51 81 -20 6.77E+17 0.343 27.9 0 13.9 35.8 G-5604-3 C6345-2 N/A 0.15 0.51 105 -20 6.77E+17 0.343 36.1 0 17.0 50.1 Unit 1 Middle Shell Assembly 308-05 Plates:

G-5605-1 A5333-1 N/A 0.12 0.54 82 -10 5.83E+17 0.318 26.0 0 13.0 42.0 G-5605-2 B0078-1 N/A 0.15 0.5 105 -10 5.83E+17 0.318 33.2 0 16.6 56.4 G-5605-3 C6123-2 N/A 0.13 0.68 93 -10 5.83E+17 0.318 29.5 0 14.8 49.1 Unit 1 Lower Shell Axial Welds 2-307A,B 172 -50 1.99E+17 0.171 29.5 0 14.8 9.1

&C (BA) 21935 3889 0.183 0.704 2-307A,B 233 -50 2.01E+17 0.173 40.3 0 20.1 30.5

&C (BB) 12008 3889 0.235 0.975 2-307A,B 21935 & 209 -50 1.69E+17 0.155 32.3 0 16.1 14.6

&C (BC) 12008 3889 0.213 0.867 Unit 1 Lower-Intermediate Shell Axial Welds:

4-308A, B 209 -50 4.06E+17 0.261 54.6 0 27.3 59.3

& C (BE) 305414 3947 0.337 0.609 4-308A, B 233 -50 6.42E+17 0.334 78.0 0 28.0 84.0

& C (BF) 12008 3947 0.235 0.975 4-308A, B 12008 & 3947 219 -50 4.98E+17 0.292 64.0 0 28.0 70.0

& C (BD) 305414 (tandem) 0.286 0.792 Unit 1 Middle Shell Axial Welds:

3-308A,B 189 -50 4.40E+17 0.273 51.8 0 25.9 53.5

&C (BH) 305424 3889 0.273 0.629 3-308A,B 212 -30 3.25E+17 0.230 48.8 0 24.4 67.6

&C (BJ) 1P3571 3958 0.283 0.755 Unit 1 Circumferential Weld Between Lower Shell and Lower-Intermediate Shell:

1-313 (AB) 4P6519 N/A 0.131 0.06 64 -52 2.38E+17 0.191 12.2 0 6.1 -27.6 Unit 1 Circumferential Weld Between Lower-Intermediate Shell and Middle Shell:

6-308 (AC) 6329637 N/A 0.205 0.105 98 -50 5.83E+17 0.318 31.3 0 15.6 12.5

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Table 7: LSCS Unit 1 1/4T ART Table for 54 EFPY (continued)

Initial 54EFPY 54 EFPY Component Heat No. Lot % % CF RTNDT 1/4T Fluence RTNDT i 1/4T ART No. No. Cu Ni (°F) Fluence Factor f (°F) (°F) (°F) (°F)

(n/cm2)

Unit 1 N6 LPCI Nozzle Forgings:

N6A,B,&C Q2Q22W N/A 0.1 0.82 67 10 9.69E+16 0.107 7.2 0 3.6 24.4 Unit 1 N6 LPCI Nozzle Welds:

N6A,B,&C ABEA N/A 0.04 0.98 54 -50 2.89E+17 0.215 11.6 0 5.8 -26.8 N6A,B,&C FAGA N/A 0.03 0.95 41 -50 2.89E+17 0.215 8.8 0 4.4 -32.4 N6A,B,&C CCJA N/A 0.02 0.86 27 -50 2.89E+17 0.215 5.8 0 2.9 -38.4 N6A,B,&C FOAA N/A 0.03 1 41 -50 2.89E+17 0.215 8.8 0 4.4 -32.4 N6A,B,&C EAIB N/A 0.12 0.86 155 -50 2.89E+17 0.215 33.4 0 16.7 16.7 Unit 1 N12 Water Level Instrument Nozzle Locations in Middle Shell Assembly 308-05 Plates:

G-5605-1 A5333-1 N/A 0.12 0.54 82 -10 1.97E+17 0.171 14.0 0 7.0 17.9 G-5605-2 B0078-1 N/A 0.15 0.5 105 -10 1.97E+17 0.171 17.8 0 8.9 25.7 G-5605-3 C6123-2 N/A 0.13 0.68 93 -10 1.97E+17 0.171 15.9 0 7.9 21.7 Unit 1 N12 Water Level Instrument Nozzle Welds:

Nickel Alloy N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Unit 1 Best-Estimate Chemistry Values from BWRVIP-135 Revision 4:

Plate N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Weld N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Unit 1 Integrated Surveillance Program Chemistry Values from BWRVIP-135 Revision 4:

Plate C6345-1 N/A 0.14 0.54 152 -20 6.77E+17 0.343 52.3 0 17.0 66.3 Weld 1P3571 N/A 0.21 0.75 437 -30 3.25E+17 0.230 100.5 0 14.0 98.5

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Table 8: LSCS Unit 2 1/4T ART Table for 54 EFPY

Initial 54EFPY 54 EFPY Component Heat Lot % Cu % CF RTNDT 1/4T Fluence RTNDT i 1/4T ART No. No. No. Ni (°F) Fluence Factor f (°F) (°F) (°F) (°F)

(n/cm2)

Unit 2 Lower Shell Assembly Plates:

21-1 C9425-2 N/A 0.12 0.51 81 30 6.28E+17 0.330 26.8 0 13.4 83.7

21-2 C9425-1 N/A 0.12 0.51 81 32 6.28E+17 0.330 26.8 0 13.4 85.7

21-2 C9434-2 N/A 0.09 0.51 58 10 6.28E+17 0.330 19.2 0 9.6 48.3 Unit 2 Lower-Intermediate Shell Assembly Plates:

22-1 C9481-1 N/A 0.11 0.5 73 10 7.38E+17 0.359 26.2 0 13.1 62.4

22-2 C9404-2 N/A 0.07 0.49 44 52 7.38E+17 0.359 15.8 0 7.9 83.6

22-3 C9601-2 N/A 0.12 0.5 81 10 7.38E+17 0.359 29.1 0 14.5 68.1 Unit 2 Lower Shell Assembly Axial Welds:

BA 3P4000 3933 0.02 0.93 27 -50 4.46E+17 0.275 7.4 0 3.7 -35.2 BB 3P4000 3933 0.02 0.93 27 -50 4.33E+17 0.270 7.3 0 3.7 -35.4 BC 3P4000 3933 0.02 0.93 27 -50 5.57E+17 0.310 8.4 0 4.2 -33.2 Unit 2 Lower-Intermediate Shell Assembly Axial Welds:

BD 3P4966 1214 0.026 0.92 35 -6 4.44E+17 0.274 9.7 0 4.9 13.4 BE 3P4966 1214 0.026 0.92 35 -6 6.97E+17 0.349 12.3 0 6.2 18.7 BF 3P4966 1214 0.026 0.92 35 -6 5.46E+17 0.307 10.9 0 5.4 15.7 Unit 2 Circumferential Weld Between Lower Shell and Lower-Intermediate Shell:

AB 5P6771 342 0.04 0.94 54 -34 6.28E+17 0.330 17.8 0 8.9 1.7

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Table 8: LSCS Unit 2 1/4T ART Table for 54 EFPY (continued)

54EFPY 54 Component Initial 1/4T Fluence RTNDT i EFPY No. Heat No. Lot No. % Cu % Ni CF RTNDT Fluence Factor f (°F) (°F) (°F) 1/4T

(°F) (n/cm2) ART

(°F)

Unit 2 N6 LPCI Nozzle Forgings:

N6A,B,&C Q2Q36W N/A 0.22 0.83 177 -6 1.05E+17 0.113 20.0 0 10.0 34.0 Unit 2 N6 LPCI Nozzle Welds:

N6A,B, &C C3L46C J0202A27A 0.02 0.87 27 -20 3.15E+17 0.226 6.1 0 3.0 -7.8 N6A,B, &C (single 3P4966 1214/3482 0.02 0.8 27 -30 3.15E+17 0.226 6.1 0 3.0 -17.8 wire)

N6A,B, &C (tandem 3P4966 1214/3482 0.02 0.92 27 -48 3.15E+17 0.226 6.1 0 3.0 -35.8 wire)

N6A,B, &C 05P018 D211A27A 0.09 0.9 122 -38 3.15E+17 0.226 27.5 0 13.8 17.1 N6A,B, &C 04P046 D217A27A 0.06 0.9 82 -48 3.15E+17 0.226 18.5 0 9.3 -11.0 Unit 2 N12 Water Level Instrument Nozzle Locations in Lower-Intermediate Shell Assembly Plates:

22-1 C9481-1 N/A 0.11 0.5 73 10 2.26E+17 0.186 13.5 0 6.8 37.1 22-2 C9404-2 N/A 0.07 0.49 44 52 2.26E+17 0.186 8.2 0 4.1 68.3 22-3 C9601-2 N/A 0.12 0.5 81 10 2.26E+17 0.186 15.0 0 7.5 40.1 Unit 2 N12 Water Level Instrument Nozzle Welds:

N12-1,2,&3 Nickel Alloy N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Unit 2 Best-Estimate Chemistry Values from BWRVIP-135 Revision 4:

Plate N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Weld 3P4000 N/A 0.02 0.935 27 -50 5.57E+17 0.310 8.4 0 4.2 -33.2 Weld 3P4966 N/A 0.025 0.913 34 -6 6.97E+17 0.349 11.8 1 5.9 17.9 Weld 5P6771 N/A 0.034 0.934 46 -34 6.28E+17 0.330 15.3 2 7.6 -3.0 Unit 2 Integrated Surveillance Program Chemistry Values from BWRVIP-135 Revision 4:

Plate C3054-2 N/A 0.08 0.67 51 52 7.38E+17 0.359 18.3 0 9.2 88.6 Weld 402K9171 411L3071 0.02 0.95 27 -6 6.97E+17 0.349 9.4 0 4.7 12.8

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Table 9: Nozzle Stress Intensity Factors

Nozzle Applied Pressure, KIp-app Thermal, KIt

Unit 1 Feedwater 72.05 41.74 Unit 2 Feedwater 75.05 41.69 LPCI (N6) 88.35 55.32 KI in units of ksi-in0.5

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APPENDIX A

LASALLE REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM

In accordance with 10 CFR 50, Appendix H, R eactor Vessel Material Surveillance Program Requirements [24], one surveillance capsule has been removed and tested from each of the LSCS Unit 1 and Unit 2 reactor vessels. The first LaSalle Unit 1 capsule was removed at 6.5 EFPY [25] and the first LaSalle Unit 2 capsule was removed at 6.98 EFPY [ 25]. The second LaSalle Unit 1 capsule was removed at 18.9 EFPY in 2010 [28]. The surveillance capsu les contained flux wires for neutron fluence measurement, Charpy V-Notch impact test specimens and uniaxial tensile test specimens fabricated using materials from the vessel materials within the core beltline region. The methods and results of testing are presented in References [25, 26]. There is one remaining capsules in LSCS Unit 1 and two remaining capsules in LSCS Unit 2 which will remain in place to serve as backup surveillance material for the BWRVIP program, or as otherwise needed.

LSCS has replaced the original RPV material surveillance program with the BWRVIP ISP [24]. LSCS is currently committed to use the BWRVIP ISP and h as made a licensing commitment to use the ISP for LSCS during the period of extended operation. The BW RVIP ISP meets the requirements of 10 CFR 50, Appendix H, for Integrated Surveillance Programs, and has been approved by NRC. LSCS committed to use the ISP in place of its existing surveillance programs in the license amendment issued by the NRC regarding the implementation of the BWRVIP ISP. Under the ISP, one further capsule is scheduled for removal from the LSCS Unit 1 vessel in 2030 [28].

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