JAFP-08-0067, Calculation No. FITZ-10Q-302, Revision 0, Revised Pressure-Temperature Curves.

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Calculation No. FITZ-10Q-302, Revision 0, Revised Pressure-Temperature Curves.
ML082100456
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 02/26/2008
From: Jaeger M J, Lohse C S
Structural Integrity Associates
To:
Office of Nuclear Reactor Regulation
References
10166220, JAFP-08-0067 FITZ-10Q-302, Rev 0
Download: ML082100456 (60)
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Proprietary Information Withhold from Public Disclosure Pursuant to 10 CFR 2.390(a)(4)

ATTACHMENT 4 to JAFP-08-0067 Entergy Nuclear Operations, Inc.James A. FitzPatrick Nuclear Power Plant Structural Integrity Associates CalcUlatiobnNo.

FITZ-10Q-302, Revision 0',"Revised Pressure-Temperature Curves," 2/26/2008 Attachments 2, 6, and 8 contain proprietary information as described in 10 CFR 2.390.When separated from these attachments this letter and its contents are non-proprietary.

Proprietary Information Withhold from Public Disclosure Pursuant to 10 CFR 2.390(a)(4)

ATTACHMENT 4 to JAFP-08-0067 CONTENTS 1) SIA Calculation FITZ-10Q-302 Calculation FITZ-10Q-302 51 Pages Calculation Attachment A 3 Pages Calculation Attachment B 4 Pages 58 Pages Attachments 2, 6, and 8 contain proprietary information as described in 10 CFR 2.390.When separated from these attachments this letter and its contents are non-proprietary.

Structural Integrity Associates, Inc. File No.: FITZ-10Q-302 CALCULATION PACKAGE Project No.: FITZ-1OQ PROJECT NAME: Analysis for Vessel Pressure-Temperature Curve Revision CONTRACT NO.: '10166220 CLIENT: PLANT: Entergy Nuclear Northeast James A. Fitzpatrick Nuclear Power Plant CALCULATION TITLE: Revised Pressure-Temperature Curves Note: This calculation supersedes all previous Pressure-Temperature curve calculations for the James A. Fitzpatrick Nuclear Power Plant.Project Manager Preparer(s)

&Document Affected Revision Description Approval Checker(s)

Revision Pages Signature

& Date Signatures&

Date 0 1-51, Initial Issue Appendices:

A1 -A3, BI -B4 G. L. Stevens M. J. Jaeger Computer Files 2/26/2008 2/26/2008 C. S. Lohse 2/26/2008 Page 1 of 51 F0306-OI RO V Structural Integrity Associates,.

Inc.Table of Contents 1.0 IN T R O D U C T IO N .......................................................................................................................

4 2.0 M E T H O D O L O G Y .......................................................................................................................

4 3.0 DESIGN INPUTS / ASSUMPTIONS

....................................................................................

10 4.0 C A L C U L A T IO N S ......................................................................................................................

11 4.1 Pressure Test (Curve A) .............................................

12 4.2 Normal Operation

-Core Not Critical (Curve B) ........................................................

12 4.3 Normal Operation

-Core Critical (Curve C) ..............................

13 5.0 C O N C L U SIO N S ........................................................................................................................

13 6.0 R E F E R E N C E S ...........................................................................................................................

14 APPENDIX A: P-T CURVE INPUT LISTING ...........................................................................

Al APPENDIX B: DEVELOPMENT OF SATURATED STEAM CURVE FITS ..........................

BI File No.: FITZ-1OQ-302 Revision:

0 Page 2 of 51 F0306-01 RO Structural Integrity Associates, Inc.List of Tables Table 1: JAFNPP Polynomial Coefficients for Nozzle Stress Intensity Distributions

..........................

15 Table 2: JAFNPP Beltline Region, Curve A, for 32 EFPY .....................

..............................................

16 Table 3: JAFNPP, Beltline Region, Curve A, for 40 EFPY .................................................................

18 Table 4: JAFNPP, Beltline Region, Curve A, for 48 EFPY .................................................................

20 Table 5: JAFNPP Beltline Region, Curve A, for 54 EFPY .................................................................

22 Table 6: JAFNPP Bottom Head Region, Curve A, for all EFPY ..........................................................

24 Table 7: JAFNPP, Upper Vessel Region, Curve A, for all EFPY ........................................................

25 Table 8: JAFNPP Beltline Region, Curve B, for 32 EFPY ...... .........................

26 Table 9: JAFNPP Beltline Region, Curve B, for 40 EFPY .................................................................

28 Table 10: JAFNPP Beltline Region, Curve B, for 48 EFPY .................................................................

30 Table 11: JAFNPP Beltline Region, Curve B, for 54 EFPY ....................................................................

32 Table 12: JAFNPP Bottom Head Region, Curve B, for all EFPY ........................................................

34 Table 13: JAFNPP Upper Vessel Region, Curve B, for all EFPY ...................................................

.........

35 Table 14: JAFNPP Curve C Values for 32 EFPY ......................................

36 Table 15: JAFNPP Curve C Values for 40 EFPY ...............

.......................

37 Tdble 16: JAFNPP Curve C Values for 48 EFPY ......................................

38 Table 17: JAFNPP Curve C Values for 54 EFPY ..... ....... :............

.................................

39 List of Figures Figure 1: JAFNPP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 32 EFPY .........................

40 Figure 2: JAFNPP P-T Curve A (Hydrostatic Pressure and Leak Tests) at 40 EFPY .........................

41 Figure 3: JAFNPP P-T Curve A (Hydrostatic Pressure and Leak Tests) at 48 EFPY .........................

42 Figure 4: JAFNPP P-T Curve A (Hydrostatic Pressure and Leak Tests) at 54 EFPY .........................

43 Figure 5: JAFNPP P-T Curve B (Normal Operation

-Core Not Critical) for 32 EFPY ......................

44 Figure 6: JAFNPP P-T Curve B (Normal Operation

-Core Not Critical) for 40 EFPY ......................

45 Figure 7: JAFNPP P-T Curve B (Normal Operation

-Core Not Critical) for 48 EFPY ......................

46 Figure 8: JAFNPP P-T Curve B (Normal Operation

-Core Not Critical) for 54 EFPY ......................

47 Figure 9: JAFNPP P-T Curve C (Normal Operation

-Core Critical) for 32 EFPY ...... .........

48 Figure 10: JAFNPP P-T Curve C (Normal Operation

-Core Critical) for 40 EFPY ..........................

49 Figure 11: JAFNPP P-T Curve C (Normal Operation

-Core Critical) for 48 EFPY ..........................

50 Figure 12: JAFNPP P-T Curve C (Normal Operation

-Core Critical) for 54 EFPY ..........................

51 File No.: FITZ-1OQ-302 Page 3 of 51 Revision:

0 F0306-0 1 RO V Structural Integrity Associates, Inc.

1.0 INTRODUCTION

This calculation updates the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) pressure-temperature (P-T) curves for the beltline, bottom head, limiting flange and non-beltline (feedwater nozzle / upper vessel) locations.

The P-T curves are created for 32, 40, 48 and 54 effective full power years (EFPY) of operation, and are developed using.the methodology of the 2001 Edition, 2003 Addenda of ASME Code,Section XI, Appendix G [I ],:and 10CFR50 Appendix G [311 This calculation has been developed in accordance with the methodology of the Boiling Water Reactor Owner's Group (BWROG) Licensing'Topical Report, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors" [5].2.0 METHODOLOGY A full set of P-T curves are computed, including the following plant conditions:

Pressure Test (Curve A), Normal Operation

-Core Not Critical (Curve B), and Normal Operation

-Core Critical (Curve C).The curves are consolidated into three evaluation regions of the reactor pressure vessel (RPV): (1) the beltline, (2) the bottom head, and (3) the feedwater nozzle / upper vessel.The primary methodology for calculating P-T curves is described in Reference

[5], thus, all equations and values in this section are obtained from Reference

[5], unless otherwise noted. The P-T curves are calculated by means of an iterative procedure, in which the following steps arem completed:

Step 1: A fluid temperature, T, is assumed. The P-T curves are calculated under the premise of a flaw that has extended 1/4 of the way through the vessel wall. According to Reference

[5], the temperature at the assumed flaw tip, T 1/4 , may be treated as equal to the assumed fluid temperature:

Step 2: The static fracture toughness factor, Ktc, is computed using the following equation: KlC = 20.734. e°°2(T-ART)

+33.2 (1)Where: K 1 c = the lower-bound static fracture toughness factor (ksi inch)T = the metal temperature at the tip of the postulated

'A-through-wall flaw (°F), as described above ART the Adjusted Reference Temperature (ART) for the limiting material in the RPV region under consideration (fF)File No.: FITZ-IOQ-302 Page 4 of 51 Revision:

0 F0306-O1 RO Structurai Integrity Associates, Inc.Step 3: The allowable stress intensity factor due to pressure, Kip, is calculated as: K Ki t (2)SF Where: Kip = the allowable stress intensity factor due to membrane (pressure) stress (ksiinch )the lower-bound static fracture toughness factor calculated in Equation 1 (ksi ifnch)Kit the thermal stress intensity factor (ksii-nch)

SF = the safety factor, based on the reactor condition Note: for hydrostatic and leak test conditions (i.e. P-T Curve A), the SF = 1.5. For normal operation, for both a non-critical and a critical reactor (i.e. P-T curves B and C), the SF = 2.0.When calculating values for Curve A, the thermal stress intensity factor is neglected (KI, =0), since the hydrostatic leak test is performed at or near isothermal conditions (typically, the rate of temperature change is 25°F/hr or less).For Curve B and Curve C calculations, Kit is computed in different ways based on the evaluation region. :For the beltline and bottom head regions, Kit is determined using the following equation:

..:Kit =0.953x10.

3.CR;.t 2.5 (3), Where: CR = the cooldown rate of the vessel (0 F/hr)t = the RPV wall thickness (in.)For the feedwater nozzle / upper vessel region, Kit is obtained from the stress distribution.

output of a finite element model (FEM). A thermal transient finite element analysis (FEA) is performed, and a polynomial curve-fit is applied to the through-wall stress distribution at each time point. The subsequent method to evaluate Kit is: 2 -1 2a a2 4a 3 Kh, Poly = 0.706Co/+

-0.537CIt + -" .0.448C 2 t +-" 0.393C3t (4)Z 2 3,z Where: a = 'A through-wall postulated flaw depth, a = 1/4 t (in.)t = thickness of the cross-section through the limiting nozzle inner blend radius corner (in.)COt,Cjt = thermal stress polynomial coefficients, obtained from a curve-fit of C 2 t,C 3 t the extracted stresses from an FEM transient analysis.File No.: FITZ-IOQ-302 Page 5 of 51 Revision:

0 F0306-0 I RO Structural Integrity Associates, Inc.The thermal stress polynomial coefficients are based on the assumed polynomial form of*.( 3 .a t ar(x) = Co + C(+ ( a al. In this equation, "a" represents the radial distance in inches from the inside surface to any point on the crack front, and"ama=" is the maximum crack depth, in inches.The transient FEA is performed assuming a fixed thermal shock between a high and a low temperature.

In reality, the available thermal shock varies for each evaluation step, as the maximum temperature is bounded by the pressure-temperature saturation curve. Thus, the value of Kit calculated in Equation 4 can be scaled to account for the maximum available thermal shock, as shown in the following expression:

sTi, -T ow.K , , = K h -, 01, , (Ioi n = K i, , ,,o ,, .(5)Where: Kit = the scaled thermal stress intensity factor, which is subsequently used in Equation 2 (ksiinch)Kitpoly = the thermal stress intensity factor computed from the polynomial expression defined in Equation 4 (ksiinch ).Fscaling = the scaling factor to apply to the polynomial, stress.intensity factor Tsat = the saturation temperature of the reactor ('F)Tiow = the lower limit of the thermal shock applied to the FEA ('F)Thigh = the upper limit of the thermal shock applied to the FEA ('F)Tsat is determined from the pressure-temperature saturation curve. A power fit of this curve is developed in Appendix B, resulting in the following equation: Tjat 119.3.0.7987Ps-'

Psat02198 In the above equation, Psat is the saturation pressure corresponding to Tsat. For the purposes of this evaluation, Psat is conservatively applied at the final P-T curve pressure, which is calculated below in Equation 12. This results in an iterative calculation process for each evaluation step, where a saturation pressure is assumed, a scaling factor is determined, the final pressure (Pp-T) is computed, and the assumed saturation pressure is adjusted until the results achieve a suitable level of convergence.

(6)File No.: FITZ-IOQ-302 Revision:

0 Page 6 of 51 F0306-OI RO Structural Integrity Associates, Inc.Step 4: The allowable internal pressure of the RPV is calculated differently for each evaluation region. For the beltline region, the allowable pressure is determined as follows: Ip Kip -t alwM,,,

  • Ri(7 Where: Pallow = the allowable RPV internal pressure (psig)Kip = the allowable stress intensity factor due to membrane (pressure) stress, as defined in Equation 2 (ksiifnch) t = the RPV wall thickness (in.)Mm .the membrane correction factor for an inside surface axial flaw: Mm = 1.85 for It < 2 Mm = 0.926,ft for 2 < It < 3.464 Mm = 3.21 for T> 3.464 Ri = the inner radius of the RPV (in.)For the bottom head region, the allowable pressure is calculated with the following equation: T 2 .= t (8),SCF.- M,,, R-Where: SCF = conservative stress concentration factor to account for bottom head penetration discontinuities; SCF = 3.0 per Reference

[5]Pallow, Kip, t, Mm and Ri are defined in the footnotes of Equation 7 For the feedwater nozzle / upper vessel region, the allowable pressure is determined from a ratio of the allowable and applied stress intensity factors. The applied factor can be determined from an FEM that outputs the stresses due to the internal pressure on the nozzle /RPV. The methodology for this approach is as follows: K ip*.Prej 9 PTall... -(9)Kp l- app Where: Pref = RPV internal pressure at which the finite element analysis was performed (psig)SKip-app = the applied pressure stress intensity factor (ksifi)nch Pailow and Kip are defined in the footnotes of Equation 7 The applied pressure stress intensity factor is determined using a polynomial curve-fit approximation for the through-wall pressure stress distribution from an FEA, similar to the methodology of Equation 4: 2a a 2 4 3 K -p-pp = 2a[0.706COp

+--'0.537C p+- .0.448C2p + -.0.393C 3p] (10)File No.: FITZ-1OQ-302 Page 7 of 51 Revision:

0 F0306-01 RO Structurai Integrity Associates, Inc.Where: a = 1/4 through-wall postulated flaw depth, a = 1/4 t (in.)t = thickness of the cross-section through the limiting nozzle inner blend radius comer (in.)Cop,Clp =thermal stress polynomial coefficients, obtained from a curve-fit of C 2 p,C 3 p the extracted stresses from an FEM unit pressure analysis Step 5: Steps 1 through 4 are repeated in order to generate a series of P-T points; the fluid temperature is incremented with each repetition.

The iteration continues until the allowable pressure has reached a value greater than the maximum operational pressure.Step 6: The following additional minimum temperature requirements apply to the feedwater nozzle /upper vessel region, according to Table 1 of 1OCFR50, Appendix G [3]:* If the pressure is greater than 20% of the pre-service hydro-test pressure, the temperature must be greater than the RTNDT of the limiting flange material plus a temperature adjustment.

For Curve A calculations, the temperature adjustment is 90'F; for Curve. B, the temperature adjustment is 120'F." If the pressure is less than or equal to 20% of the pre-service hydro-test pressure, the minimum temperature must be greater than or equal to the RTNDT of the limiting flange material.,,Step 7: The final P-T limits are calculated using the following equations:

T1_ -T+U (11)P-T = P.allow -PH -UP (12)Where: TPT = the. allowable coolant (metal) temperature (OF)UT = the coolant temperature instrument uncertainty

(°F)PP-T = the allowable reactor pressure (psig)PH = the pressure head to account for the water in the RPV (psig).Can be calculated from the following expression:

PH = p" Ah p = Water weight density at ambient temperature (lbm/ft 3)Ah = elevation of normal water level in RPV (in.)Up = the pressure instrument uncertainty (psig)Step 8: The fluid temperature (T) is incremented, and the calculations resume from Step 1.Calculations proceed in this iterative manner until the allowable reactor pressure (PP-T)exceeds the maximum possible pressure.

The maximum pressure limit is usually set to 1600 psig, since this value bounds the typical hydrostatic test pressure of 1,563 psig (see Section 3.0).File No.: FITZ-1OQ-302 Page 8 of 51 Revision:

0 F0306-01 RO Structural Integrity Associates, Inc.The P-T Curves for the hydrostatic leak test (Curve A) and normal operation

-core not critical (Curve B) can be computed by following Steps 1 through 7. Values ,for Curve C, the core-critical operating curve, are generated from the requirements of 10 CFR50 Appendix G [3] and the Curve A and Curve B limits. Table 1 of Reference

[3] requires that core critical P-T limits be 40'F above any Curve A or Curve B limits at all pressures.

10CFR50 Appendix G [3] also stipulates that, above the 20% pressure transition point, the Curve C temperatures must be either the reference temperature (RTNDT) of the closure region plus 1 60°F, or the temperature required for the hydrostatic pressure test, whichever is greater.For P-T Curves A and B, the initial fluid temperature assumed in Step 1 is typically taken at the bolt-up-temperature of the closure flange. According to Reference

[3], the minimum bolt-up temperature is equal to the limiting material RTNDT of the regions affected by bolt-up stresses.

Consistent with Reference

[5], the minimum bolt-up temperature shall not be lower than 60'F. Thus, the minimum bolt-up temperature shall be 60'F or the material RTNDT, whichever is higher.For P-T Curve C, when the reactor is critical, the initial fluid temperature is equal to the calculated minimum criticality temperature in this region. Table 1 of Reference

[3] indicates that, for a BWR with normal operating water levels, the allowable temperature for initial criticality at the closure flange region is equal to the reference temperature (RTNDT) at the flange region plus 60'F.File No.: FITZ-IOQ-302 Revision:

0 Page 9 of 51 F0306-01 RO Structural Integrity Associates, Inc.3.0 DESIGN INPUTS /ASSUMPTIONS All design inputs and assumptions used to perform the JAFNPP P-T curve calculations are summarized in the input listings in Appendix A.ART values in the JAFNPP beltlineregion are obtained from a previous SI calculation

[6]. The calculations were performed in accordance with Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99, Revision 2 (RG1.99) [4]. Based on Tables 1-4 of Reference

[6], the limiting beltline material is the 2-233-A lower-shell longitudinal weld, which has ART values of 109.6'F, 118.0°F, 125.5 0 F, and 130.6°F for 32, 40, 48 and'54 EFPY, respectively.

Since JAFNPP does not have any nozzles in the RPV beltline where the fluence exceeds 1.0x10 1 7 n/cm 2 , it'is not necessary to perform additional beltline component calculations.

Non-beltline regions are not subjected-to fluence; therefore, reference temperature (RTNDT) values are valid substitutions for corresponding ART values. RTNDT values for non-beltline regions are obtained from Tables 3-2 and 3-3 of Reference, [7]. The values for the bottom head, upper vessel, and closure flange are 10°F, 20'F, and 30'F, respectively.

These values remain constant for all EFPY levels in the evaluation.

The inner radius of the RPV, as defined in the drawing on page 7 of Reference

[10],Jis 110.375 inches. -The vessel shell thicknes is taken-as 5.375 inches from the same source Dimensions for the bottom head radius and thickness are also obtained from the drawing on page 7 of [10] as 110.5 inches and 6.8125 inches, respectively.

The GE design hydro-test pressure Js defined in Reference

[9] as 1,250 psig. Typically, the pre-service system hydrostatic test pressure is taken as 1.25 times the typical GE design pressure, resulting in a value of 1,563 psig. The instrument uncertainty for bothtemperature and pressure is assumed to be equal to zero.The total height of the RPV is 825.2 inches, as shown in Section 8.2.7 of Reference

[7]. The density of the water is assumed to be 62.4 lbm/ft 3.Thus, the static pressure adjustment due to the pressure head of the water in the RPV is conservatively calculated as 29.8 psig for all evaluation regions. The maximum cool-down rate of the vessel is l00F/hr per Reference

[9].According to Section 2.8 of Reference

[5], the minimum bolt-up temperature for the RPV shall be no lower than 60'F. Since the upper-vessel RTNDT values are all less than 60'F, the initial assumed fluid temperature in the iterative P-T curve calculation process is set equal to 60°F. A temperature increment of 2'F between subsequent iterations is assumed.The 60'F initial temperature does not include the additional 60'F add-on margin for Curves A and B that was applied to the previous JAFNPP P-T curves [7]. This additional conservatism was required in pre-1971 ASME Section III Code, but is no longer required in ASME Section XI, Appendix G [1 ] or 1OCFR50, Appendix G [3]. When the PTLR [5] was developed, SI consciously recognized-the additional 60'F margin and chose to exclude it, as it is not technically required.File No.: FITZ-1OQ-302 Page 10 of 51 Revision:

0 F0306-O1RO V Structural Integrity Associates, Inc.The polynomial coefficients used to calculate the stress intensity factors for the feedwater nozzle / upper vessel region are obtained from a detailed FEA previously performed for JAFNPP [ 11]. A transient thermal stress analysis was performed for the transient described in Reference

[11 ]. A pressure stress analysis was also performed for a 1000 psig RPV pressure.

A linearized stress path was created through the nozzle's blend radius comer, and the limiting thermal and pressure stress distributions were extracted from the FEM results. In Reference

[8], each stress distribution in Reference

[11] was fit with a third-order polynomial as a function of distance into the nozzle; the polynomial coefficients are presented in Table 1. The wall thickness through the blend radius of the nozzle is 6.811 inches per Table 1 of Reference

[8].In Reference

[5], it is recognized that P-T limits generated for the RPV are also bounding for all portions of the reactor coolant system (RCS) piping, including the Lowest Service Temperature (LST) limits specified in NB-2332 [2]. There are at least four general reasons supporting this assumption:

1. The RPV is irradiated (thereby experiencing material degradation due to neutron embrittlement), whereas the RCS piping is not.2. The philosophy behind the design codes used to evaluate the RPV and RCS piping generally recognize that the RPV is more limiting than the RCS piping from a structural.standpoint.
3. Much of the RCS piping is austenitic stainless steel, which has ductile behavior and does not experience the same fracture concerns as the ferritic RPV.4. Stresses are typically higher in the thicker-walled RPV than in the thin:walled RCS piping.' Accdrdirig to Step 6 of Section 2.0 above, the minimum temperature for normal operating conditions
(Curve B) above 20% of the pre-service hydro test pressure must be greater than or equal to RTNDT +'120'F. The minimum temperature requirement for LST is RTNDT + 100°F, as defined in NB-2332 [2].Therefore, the P-T limits in this calculation will bound the LST requirements of NB-2332. This is supported by sub-section 16.5.10 of the JAFNPP Final Safety Analysis Report [ 11].4.0 CALCULATIONS The P-T curves in this calculation were developed using an Excel spreadsheet, which is independently verified for use on a project-specific basis in accordance with SI's QA program. Since the verified spreadsheet only supports calculations at two EFPY values, two copies of the spreadsheet were used to develop the P-T curves at 32, 40, 48 and 54 EFPY ("P-T Curves 32 40.xls" and "P-T Curves 48 54.xls").The polynomial stress coefficients in Table 1 were applied to Equations 4 and 8. The resulting pressure stress intensity (Kip-applied) and thermal stress intensity (Kit) factors are 56.17 ksi inch and 65.33 ksi , respectively.

File No.: FITZ-1OQ-302 Page 11 of.51 Revision:

0 F0306-O1RO m-Structural Integrity Associates, Inc.4.1 Pressure Test (Curve A)The minimum bolt-up temperature of 60'F is applied to all regions as the initial temperature in the iterative calculation process. The static fracture toughness (K,,) is calculated for all regions using Equation 1. The resulting value of Kl,, along with a safety factor of 1.5, is used in Equýation 2 to calculate the pressure stress intensity (Kip). The allowable RPV pressure was calculated for the beltline, bottom head, and upper vessel regions using Equations 7, 8, and 9, respectively.

For the feedwater nozzle / upper vessel region, the additional constraints specified in Step 6 of Section 2.0 are applied.Final P-T limits for temperature and pressure are obtained from Equations 11 and 12, respectively.

The data resulting from each P-T curve calculation was tabulated.

Values for the beltline region at 32, 40, 48 and 54 EFPY are given in Table 2 through Table 5, respectively.

Data for the bottom head region is listed in Table 6, and data for the feedwater nozzle / upper vessel region is presented in Table 7. The data for each region was graphed, and the resulting P-T curves for 32, 40, 48 and 54 EFPY are provided in Figure 1 through Figure 4, respectively.

4.2 Normal Operation

-Core Not Critical (Curve B)The minimum bolt-up temperature of 60'F is applied to all, regions as the initial temperature in the iterative calculation process. The static fracture toughness (K 1 t) is calculated for all regions using Equation 1, The thermal stress intensity factor (Kit) is calculated for the beltline and bottom head regions using Equation 3, and for the feedwater nozzle using Equation 4. For the feedwater nozzle, Kit is scaled using the iterative procedure described in thetext accompanying Equations 5 and 6. When the estimated pressure is within 0.5% of the calculated pressure (PP-r, Equation 12), the results are assumed to have satisfactorily converged.

The resulting values of K 1 , and Kit, along with a safety factor of 2.0, are used in Equation 2 to calculate the pressure stress intensity (Kip). The-allowable RPV pressure was calculated for the beltline, bottom head, and upper vessel regions using Equations 7, 8, and 9, respectively.

For the feedwater nozzle /upper vessel region, the additional constraints specified in Step 6 of Section 2.0 ate applied..

Final P-T limits for temperature and pressure are obtained from Equations 11 and 12, respectively.

The data resulting from each P-T curve calculation was tabulated.

Values for the beltline region at 32, 40, 48 and 54 EFPY are given in Table 8 through Table 11, respectively.

Data for the bottom head region is listed in Table 12, and data for the feedwater nozzle / upper vessel region is presented in Table 13. The data for each region was graphed, and the resulting P-T curves for 32, 40, 48 and 54 EFPY are provided in Figure 5 through Figure 8, respectively.

File No.: FITZ-IOQ-302 Page 12 of 51 Revision:

0 F0306-01 RO Structural Integrity Associates, Inc.4.3 Normal Operation

-Core Critical (Curve C)The pressure and temperature values for Curve C are calculated in a similar manner as Curve B, with several exceptions.

The initial evaluation temperature is calculated as the limiting upper-vessel RTNDT (in this case, that of the closure flange region: 30'F per Section 3.0) plus 60'F, resulting in a minimum critical temperature of 90'F. When the pressure exceeds 20% of the pre-service system hydro-test pressure (20% of 1563 psig = 312 psig), the P-T limits are specified as 40'F higher than the Curve B values. The minimum temperaturelabove the 20% pressure transition point is alwaysgreater than the reference temperature (RTNDT) of the closure region plus 160'F, or the temperature required for the hydrostatic pressure test. The final Curve C values are taken as the absolute maximum between the three regions of Curve B P-T curves.Tabulated overall values for Curve C are provided at 32, 40, 48 and 54 EFPY in Table 14 through Table 17, respectively.

The corresponding P-T curve plots are given in Figure 9 through Figure 12, respectively.

5.0 CONCLUSION

S P-T curves were calculated for JAFNPP using the methodology in Section 2.0 and the design inputs and assumptions defined in Section 3.0. A full set' of P-T curves were computed, including the following plant conditions:

Pressure Test (Curve A), Normal Operation

-Core Not Critical (Curve B), and Normal Operation

-Core Critical (Curve C). Calculations were performed for the beltline, bottom head, and feedwater nozzle / upper vessel regions. Values for the beltline regions were computed at 32, 40, 48 and 54 EFPY.Tabulated pressure and temperature values are provided for all regions and EFPY levels in Table 2 through Table 17. The accompanying P-T curve plots are provided in Figure 1 through Figure 12.File No.: FITZ-10Q-302 Revision:

0 Page 13 of 51 F0306-O1RO Structural Integrity Associates, Inc.

6.0 REFERENCES

1. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components, 2001 Edition including the 2003 Addenda.2. American Society of Mechanical Engineers (ASME) Boiler and Pressure vessel Code,Section III, Rules for Construction of Nuclear Power Plant Components, Division 1, Subsection NB,"Class 1 Components," 2004 Edition.3. Part 50 of Title 10 of the Code of Federal Regulations, Appendix G, "Fracture Toughness Requirements," January 2005.4. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," May 1988.5. Structural Integrity Associates Report No. SIR-05-044A, Revision 0, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," April 2007, SI File No. GE-10Q-401.
6. Structural Integrity Associates Calculation No. FITZ-1OQ-301, Revision A, "Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts." 7. GE Document No. GE-NE-B 1100732-01, "Plant Fitzpatrick RPV Surveillance Materials Testing and Analysis of 1200 Capsule at 13.4 EFPY," Revision 1, February 1998, SI File No.;FITZ-1OQ-202.8. Structural Integrity Associates Calculation No. NYPA-78Q-301, Revision .0, "Benchmark Analysis." 9. GE Drawing No. 729E762, Revision 1, "Reactor Thermal Cycles," SI File No. NYPA-62Q-205.
10. Combustion Engineering, Inc. Report No. CENC- 1159, "Analytical Report for PASNY Reactor Vessel for Fitzpatrick Station," August 1971, SI File No. FITZ-07Q-208.
11. GE Report No. NEDC-30799-P, "James A. FitzPatrick Nuclear Power Station Feedwater Nozzle Fracture Mechanics Analysis to Show Compliance With NUREG-0619," GE PROPRIETARY, December 1984, SI File No. NYPA-53Q-201.
12. James A. Fitzpatrick Nuclear Power Plant Final Safety Analysis Report, Section 16.5, "Pressure Integrity of Piping and Equipment Pressure Parts," Subsection 16.5.10.File No.: FITZ-10Q-302 Page 14 of 51 Revision:

0 F0306-01 RO V Structural Integrity Associates, Inc.Table 1: JAFNPP Polynomial Coefficients for Nozzle Stress Intensity Distributions I I File No.: FITZ-1OQ-302 Revision:

0 Page 15 of 51 F0306-OI RO Structural Integrity AsSociates, Inc.Table 2: JAFNPP Beltline Region, Curve A, for 32 EFPY Plant =Component

=Vessel thickness, t =Vessel Radius, R =ART =KIT =Safety Factor =Mm=Temperature Adjustment

=Height of Water for a Full Vessel =Pressure Adjustment

=Pressure Adjustment

=Gauge Fluid Temperature (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 nches nches'F ======>32 EFPY ,no thermal effects))F (applied after bolt-up, instrument uncertainty) nches)sig (hydrostatic pressure head for a full vessel at 70'F)psig (instrument uncertainty)

Kic (ksi*inchll 2)40.89 40.89 41.20 41.53 41.87 42.22 42.59 42.97 43.37 43.79 44.22 44.67 45.14 45.63 46.13 46.66 47.21 47.78 48.38'49.00 49.64 50.31 51.01 51.74 52.49 53.28 54.10 54.95 55.84 56.77 57.73 58.73 59.77 60.85 61.98 63.16 64.38 65.65 66.98 68.36 69.79 71.28 KIm (ksi*inch11 2)27.26 27.26 27.47 27.69 27.91 28.15 28.39 28.65 28.92 29.19 29.48 29.78 30.09 30.42 30.76 31.11 31.47 31.85 32.25 32.66 33.09 33.54 34.01 34.49 35.00 35.52 36.07 36.64 37.23 37.84 38.48 39.15 39.85 40.57 41.32 42.10 42.92 43.77 44.65 45.57 46.53 47.52 Temperature for P-T Curve (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 Adjusted Pressure for P-T Curve (psig)0 589 593 598 603 609 614 620 626 632 639 646 653 660 668 676 684 693 702 711 721 731 742 753 764 776 788 801 815 829 843 858 874 890 908 925 944 963 983 1,004 1,026 1,048 File No.: FITZ-1OQ-302 Revision:

0 Page 16 of 51 F0306-01 RO V Structurai Integrity Associates, Inc.Table 2: JAFNPP Beltline Region, Curve A, for 32 EFPY (continued)

Gauge Fluid Temperature

(*F)142.0 144.0 146.0 148.0 150.0.152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 Ki.(ksi*inch 1 2)72.84 74.46 76.14 77.89 79.72 81.61 83.59 85.65 87.79 90.01 92.33 94.75 97.26 99.87 102.59 105.42 108.37 Kim (ksi*inch"'

2)48.56 49.64 50.76 51.93 53.14 54.41 55.73 57.10 58.52 60.01 61.55 63.16 64.84 66.58 68.39 70.28 72.25 Temperature for P-T Curve (1F)142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 Adjusted Pressure for P-T Curve (psig)1,072 1,096 1,122 1,148 1,176 1,204 1,234 1,265 1,298 1,331 1,366 1,403 1,441 1,480 1,522 1,564 1,609 File No.: FITZ-1OQ-302 Revision:

0 Page 17 of 5l F0306-0 IRO Structural Integrity Associates, Inc.Table 3: JAFNPP, Beltline Region, Curve A, for 40 EFPY Plant =Component

=Vessel thickness,.t

=Vessel Radius, R =ART =KIT =Safety Factor =Mm Temperature Adjustment Height of Water for a Full Vessel =Pressure Adjustment Pressure Adjustment Gauge Fluid Temperature (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 inches inches'F ======> 4 (no thermal effects)0 EFPY'F (applied after bolt-up, instrument uncertainty)

Inches psig (hydrostatic pressure head for a full vessel at 70'F)psig (instrument uncertainty)

KIc (ksi*inch" 2)39.70 39.70 39.97 40.24 40.53 40.83 41.14 41.46 41.80 42.15 42.52 42.90 43.29 43.70 44.13 44.58 45.04 45.53 46.03 46.55 47.10 47.67 48.26 48.87 49.51 50.18 50.87 51.59 52.34 53.12 53.93 54.78 55.66 56.58 57.53 58.52 59.56 60.63 61.75 62.92 64.13 65.39 Kim (ksi*inch 112)26.47 26.47 26.64 26.83 27.02 27.22 27.43 27.64 27.87 28.10 28.34 28.60 28.86 29.14 29.42 29.72 30.03 30.35 30.69 31.04 31.40 31.78 32.17 32.58 33.01 33.45 33.91 34.39 34.89 35.41 35.96 36.52 37.11 37.72 38.35 39.02 39.71 40.42 41.17 41.95 42.75 43.60 Tern peratu re for P-T Curve (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 Adjusted Pressure for P-T Curve (psig)0 571 575 579 583 588 592 597 602 608 613 619 625 631 638 644 651 659 666 674 682 691 700 709 719 729 739 750 762 774 786 799 812 826 840 855 871 887 904 922 940 959 n:1 .~T. .V'~r"~7 1 fl~rle iNO.: F112L-,1 -It-j Revision:

0 Page 18 of 51 F0306-01 RO V Structural integrity Associates, Inc.Table 3: JAFNPP, Beltline Region, Curve A, for 40 EFPY (continued)

Gauge Fluid Temperature (1F)142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0-158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 Kic (ksi*inchl')

66.71 68.08 69.50 70.98 72.52 74.13 75.80 77.54 79.34 81.23 83.19 85.23 87.35 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 KIm (ksi*inchl1 2)44.47 45.38 46.33 47.32 48.35 49.42 50.53 51.69 52.90 54.15 55.46 56.82 58.23 59.71 61.24 62.84 64.50 66.23 68.03 69.90 71.85 73.88 Temperature for P-T Curve (1F)142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 Adjusted Pressure for P-T Curve (psig)979 1,000 1,021 1,044 1,067 1,091 1,116.1,143 1,170 1,199 1,228 1,259 1,291 1,325 1,359 1,396 1,433 1,472 1,513 1,556 1,600 1,646 File No.: FITZ-1OQ-302 Revision:

0 Page 19 of 5l F0306-01 RO Structural Integrity Associates, Inc..Table 4: JAFNPP, Beltline Region, Curve A, for 48 EFPY Plant =Component

=Vessel thickness, t =Vessel Radius, R =ART =KIT =Safety Factor =Mm=Temperature Adjustment

=Height of Water for a Full Vessel Pressure Adjustment

=Pressure Adjustment

=Gauge Fluid Temperature

(°F)60.0 60.0 62.0 64.0'66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 inches inches 0 F-====48 EFPY (no thermal effects)0 F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70'F)psig (instrument uncertainty)

Kic (ksi*inch11 2)38.79 38.79 39.02 39.26 39.51 39.77 40.03 40.31 40.60 40.90 41.22 41.55 41.89 42.24 42.61 42.99 43.39 43.81 44.24 44.69 45.16 45.65 46.16 46.69 47.24 47.81 48.41 49.03 49.67 50.35 51.05 51.77 52.53 53.32 54.14 55.00 55.89 56.81 57.78 58.78 59.82 60.91 KIm (ksi*inch112) 25.86 25.86 26.02 26.17 26.34 26.51 26.69 26.87 27.07 27.27 27.48 27.70 27.92 28.16 28.41 28.66 28.93 29.21 29.50 29.80 30.11 30.43 30.77 31.13 31.49 31.87 32.27 32.69 33.12 33.56 34.03 34.52 35.02 35.55 36.09 36.66 37.26 37.87 38:52 39.19 39.88 40.61 Temperature for P-T Curve (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0" 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 Adjusted Pressure for P-T Curve*(psig)0 557 560 564 568 572 576 580 584 589 594 598 604 609 615 620 626 633 639 646 653 661 668 676 685 693 702 712 721 732 742 753 765 777 789 802 815 829 844.859 875 891 File No.: FITZ-1OQ-302 Revision:

0 Page 20 of 5 1 F0306-0 IRO V Structural Integrity Associates, Inc.Table 4: JAFNPP, Beltline Region, Curve A, for 48 EFPY (continued)

Gauge Fluid Temperature 12F)142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 Kic (ksi-inch" 2)62.04 63.22 64.44 65.72 67.04 68.43 69.86 71.36 72.92 74.54 76.22 77.98 79.81 81.71 83.69 85.75 87.90 90.13 92.45 94.87 97.39 100.00 102.73 105.57 108.52 Kim (ksi*inch u)41.36 42.14 42.96 43.81 44.70 45.62 46.58 47.57 48.61 49.69 50.82 51.99 53.21 54.47 55.79 57.17 58.60 60.08 61.63 63.25 64.92 66.67 68.49 70.38 72.35 Temperature for P-T Curve 12F)142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0, 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 Adjusted Pressure for P-T Curve (psig)908 926 945 964 984 1,005 1,027 1,049 1,073 1,097 1,123 1,149 1,177 1,206 1,236 1,267 1,299 1;333 1,368 1,405 1,443 1,482 1,524 1,567 1,611 File No.: FITZ-1OQ-302 Revision:

0 Page 21 of 51 F0306-OIRO Structural Integrity Associates, Inc.Table 5: JAFNPP Beltline Region, Curve A, for 54 EFPY Plant =Component

=Vessel thickness, t =Vessel Radius, R =ART =KIT =Safety Factor,=Mm =Temperature Adjustment Height of Water for a Full Vessel=Pressure Adjustmert

=Pressure Adjustment

=Gauge Fluid Temperature

(*F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0.116.0 118.0 120.0 122.0 124.0 126.0 128:0 130.0 132.0 134.0 136.0 138.0 140.0 inches inches'F ======> 5 (no thermal effects)4 EFPY'F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70°F)psig (instrument uncertainty)

KIc (ksi*inchl1 2)38.25 38.25 38.46 38.67 38.90 39.13 39.37 39.62 39.88 40.16 40.44 40.74 41.04 41.36 41.70 42.04 42.41 42.78 43.17 43.58 44.00 44.44 44.90 45.38 45.88 46.39 46.93.47.49 48.08 48.68 49.32 49.97 50.66 51.37 52.11 52.88 53.69 54.52 55.39 56.30 57.24 58.22 Kim (ksi*inch 1 2)25.50 25.50 25.64 25.78 25.93 26.09 26.25 26.41 26.59 26.77 26.96 27.16 27.36 27.58 27.80 28.03 28.27 28.52 28.78 29.05 29.33 29.63 29.93 30.25 30.58 30.93 31.29 31.66 32.05 32.46 32.88 33.32 33.77 34.25 34.74 35.26 35.79 36.35 36.93 37.53 38.16 38.81 Temperature for P-T Curve (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 Adjusted Pressure for P-T Curve (psigt)0 549 552 555 558 562 566 569 573 577 582 586 591 596 601 606 611 617 623 629 636 642 649 656 664 672 680 688 697 706 716 726 736 747 758 770 782 795 808 822 836 851 File No.: FITZ-IOQ-302 Revision:

0 Page 22 of 51 F0306-O1 RO Structural Integrity Associates, Inc.Table 5: JAFNPP Beltline Region, Curve A, for 54 EFPY (continued)

Gauge Fluid Temperature 12F)142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0'182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 Kic (ksi-inch 1 2)59.24 60.31 61.41 62.56 63.76 65.01 66.31 67.66 69.07 70.53 72.05 73.64 75.29 77.01 78.79 80.65 82.59 84.61 86.70 88.89 91.16.93.53 95.99 98.55 101.22 103.99 106.88 109.89 Kim (ksi*inchl1 2)39.50 40.20 40.94 41.71 42.51 43.34 44.21 45.11 46.04 47.02 48.04 49.09 50.19 51.34 52.53 53.77 55.06 56.40 57.80 59.26 60.77 62.35 63.99 65.70 67.48 69.33 71.26 73.26 Temperature for P-T Curve 14F)142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 Adjusted Pressure for P-T Curve (psig)866 882 899 916 934 953 973 993 1,015 1,037 1,060 1,084 1,109 1,135 1,162 1,190 1,219 1,250 1,281 1,314 1,349 1,385 1,422 1,461 1,501 1,543 1,587 1,632 File No.: FITZ-IOQ-302 Revision:

0 Page 23 of 51 F0306-01 RO Structural Integrity Associates, Inc.Table 6: JAFNPP Bottom Head Region, Curve A, for all EFPY Plant =Component

=Bottom Head thickness, t =Bottom Head Radius, R =ART =KIt =Safety Factor =Stress Concentration Factor =Mm =Temperature Adjustment

=Height of Water for a Full Vessel =Pressure Adjustment

=Pressure Adjustment

=Gauge Fluid Temperature 60F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 (penetrations portion)rnches rnches'F ======> All EFPY (no thermal effects)(bottom head penetrations)

'F (applied after bolt-up, instrument uncertainty) rnches psig (hydrostatic pressure head for a full vessel at 70'F)psig (instrument uncertainty)

Kic (ksi*inchll 2)89.56 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 11i7.28 120.71 124.28 128.00 131.87 135.90 140.09 144.45 Kim (ksi*inch 1 1 2)59.71 59.71 61.24 62.84 64.50 66.23 68.03.69.90 71.85 73.88 75.99 78.19 80.47 82.86 85.33 87.91 90.60 93.39 96.30 Temperature for P-T Curve 1F)60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 Adjusted Pressure for P-T Curve (psig)0 987 1,013 1,040 1,068 1,098 1,128 1,160 1,193 1,228 1,264 1,301 1,340 1,381 1,423 1,467 1,513 1,560 1,610 File No.: FITZ-1OQ-302 Revision:

0 Page 24 of 51 F0306-0I RO V Structural Integrity Associates, Inc.Table 7: JAFNPP, Upper Vessel Region, Curve A, for all EFPY Plant =Component

=ART =Vessel Radius, R =Nozzle corner thickness, t' =Kit =Ktp-applied Crack Depth, a =Safety Factor =Temperature Adjustment

=Height of Water for a Full Vessel =Pressure Adjustment

=Pressure Adjustment

=Reference Pressure =Unit Pressure =Flange RTNDT =(based on FW nozzle)'F ======> AII.EFPY inches inches, approximate.(no thermal effects)ksi*inch"ý inches'F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70°F)psig (instrument uncertainty) psig (pressure at which the FEA stress coeffiecients are valid) [GREEN]psig (hydrostatic pressure)'F ======> All EFPY Gauge Fluid Temperature

(.F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 K1i (ksi*inch12) 79.34 79.34 81.23 83.19 85.23 87.35.89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 117.28 120.71 124.28 128.00 131.87 135.90 140.09 Ki, (ksi*inchll 2)52.90 52.90 54.15 55.46 56.82 58.23 59.71 61.24 62.84 64.50 66.23 68.03 69.90 71.85 73.88 75.99 78.19 80.47 82.86 85.33 87.91 90.60 93.39 P.T Curve Temperature

(°F)60 60.120 120 120 120 120 120 120 120 120 120 120 120 120 120 120 120 120 120 120 120 120 P.r.Curve Pressure (psig)0 313 313 957 982 1007 1033 1060 1089 1118 1149 1181 1215 1249 1285 1323 1362 1403 1445 1489 1535 1583 1633 C" File No.: FITZ-1OQ-302 Revision:

0 Page 25 of 51 F0306-OIRO Structural Integrity Associates, Inc.Table 8: JAFNPPBeltline Region, Curve B, for 32 EFPY Plant =Component

=Vessel thickness, t =Vessel Radius, R =ART =Kit =Safety Factor =Mm=Temperature Adjustment

=Height of Water for a Full Vessel =Pressure Adjustment

=Pressure Adjustment

=Heat Up and Cool Down Rate =Gauge Fluid Temperature (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 inches inches*F ======>ksi*inch"ý 32 EFPY'F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70'F)psig (instrument uncertainty)

°F/Hr K1.(ksi*inchll 2)40.89 40.89 41.20 41.53 41.87 42.22 42.59 42.97 43.37 43.79 44.22 44.67 45.14 45.63 46.13 46.66 47.21 47.78 48.38 49.00 49.64 50.31 51.01 51.74 52.49 53.28 54.10 54.95 55.84 56.77 57.73 58.73 59.77 60.85 61.98 63.16 64.38 65.65 66.98 68.36 69.79 71.28 Kim (ksi*inchll 2)17.25 17.25 17.41 17.57 17.74 17.92 18.10 18.30 18.50 18.70 18.92 19.14 19.38 19.62 19.87 20.14 20.41 20.70 21.00 21.31 21.63 21.96 22.31 22.68 23.06 23.45 23.86 24.29 24.73 25.19 25.67 26.17-26.69 27.24 27.80 28.39 29.00 29.63 30.30 30.99 31.70 32.45 Temperature for P-T Curve (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 Adjusted Pressure for P-T Curve (psigl)0 362 365 369 373 377 381 385 390 394 399 404 410 415 421 427 433 440 446 454 461 468 476 485 493 502 511 521 531 542 553 564 576 588 601 614 628 642 657 673 689 706 File No.: FITZ-1OQ-302 Revision:

0 Page 26 of 5l F0306-O1 RO VStructural Integrity Associates, Inc.Table 8: JAFNPP Beitline Region, Curve B, for 32 EFPY (continued)

Gauge Fluid Temperature (1F)142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0.158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 198.0 Ki.(ksi*inchll 2)72.84 74.46 76.14 77.89 79.72 81.61 83.59 85.65 87.79 90.01 92.33 94.75 97.26 99.87 102.59 105.42 108.37 111.44 114.63 117.96 121.41 125.01 128.76 132.66 136.72 140.95 145.34 149.92 154.68 KIm (ksi*inchl1 2)33.23 34.04 34.88 35.75 36.67 37.62 38.60 39.63 40.70 41.82 42.97 44.18 45.44'46.74 48.10 49.52 50.99 52.53 54.12 55.79 57.52 59.32 61.19 63.14 65.17 67.28 69.48 71.77 74.15 Temperature for P-T Curve (1F)142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0*174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 198.0 Adjusted Pressure for P-T Curve (psig)724 742 761 781 802 823 846 869 893 919 945 972 1,001 1,031 1,061 1,093 1,127 1,162 1,198 1,236 1,275 1,316 1,358 1,402 1,448 1,496 1,546 1,598 1,652 File No.: FITZ-1OQ-302 Revision:

0 Page 27 of 51 F0306-O IRO Structural Integrity Associates, Inc.Table 9: JAFNPP Beltline Region, Curve B, for 40 EFPY Plant =Component

=Vessel thickness, t =Vessel Radius, R =ART =Kit =Safety Factor =Mm =Temperature Adjustment

=Height of Water for a Full Vessel =Pressure Adjustment

=Pressure Adjustment

=Heat Up and Cool Down Rate =Gauge Fluid Temperature (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 inches inches oF ======>ksi*inchl/

40 EFPY'F (applied after bolt-up, instrument uncertainty) inches \psig (hydrostatic pressure head for a full vessel at 70'F)psig (instrument uncertainty)

°F/Hr KIc (ksi*inch11 2)39.70 39.70 39.97 40.24 40.53 40.83 41.14 41.46 41.80 42.15 42.52 42.90 43.29 43.70 44.13 44.58 45.04 45.53 46.03 46.55 47.10 47.67 48.26 48.87 49.51 50.18 50.87 51.59 52.34 53.12 53.93 54.78 55.66 56.58 57.53 58.52 59.56 60.63 61.75 62.92 64.13 65.39 Kim (ksi*inchlI 2)16.66 16.66 16.79 16.93 17.07 17.22 17.38 17.54 17.71 17.88 18.07 18.26 18.45 18.66 18.87 19.10 19.33 19.57 19.82 20.09 20.36 20.64 20.94 21.24 21.56 21.90 22.24 22.60 22.98 23.37 23.78 24.20 24.64 25.10 25.57 26.07 26.59 27.13 27.69 28.27 28.87 29.51 Temperature for P-T Curve (.F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 Adjusted Pressure for P-T Curve (psig])0 348 351 354 357 361 364 368 372 376 380 384 389 393 398 403 409 414 420 426 432 438 445 452 459 467 475 483 491 500 510 519 529 539 550 562 573 585 598 611 625 639 File No.: FITZ-1OQ-302 Revision:

0 Page 28 of 51 F0306-OIRO Structural Integrity Associates, Inc.Table 9: JAFNPP Beltline Region, Curve B, for 40 EFPY (continued)

Gauge Adjusted Fluid Temperature Pressure for Temperature KI. Kim for P-T Curve P-T Curve (°F) (ksi*inch11

2) (ksi*inchl1
2) (°F) (psig)142.0 66.71 30.16 142.0 654 144.0 68.08 30.85 144.0 670 146.0 69.50 31.56 146.0 686 148.0- 70.98 32.30 148.0 703 150.0 72.52 33.07 150.0 720 152.0 74.13.. 33.87 152.0 739 154.0 75.80 34.71 154.0 757 156.0 77.54 35.58 156.0 777 158.0 .79.34 36.48 158.0 798.160.0 81.23 37.42 160.0 819 162.0 83.19 38.40 162.0 841 164.0 85.23 39.42 164.0 864 166.0 87.35 40.48 166.0 889 168.0 89.56 41.59 168.0 914 170.0 91.86 42.74 170.0 940 172.0 94.25 43.94 172.0 967 174.0 96.75 45.18 174.0 995.176.0 99.34 176.0 1,024 178.0 102.04 47.83 178.0 1,055 180.0 104.85 49.23 180.0 1,087 182.0 107.77 50.69 182.0 1,120 184.0 110.82 52.22 184.0 1,155 186.0 113.98. 53.80 186.0 1,191 188.0 117.28 55.45 188.0 1,228 190.0 120.71 57.16 190.0 1,267 192.0 124.28 58.95 192.0 1,307 194.0 128.00 60.81 194.0 1,350 196.0 131.87 62.74 196.0 1,393 198.0 135.90 64.76 198.0 1,439 200.0 140.09 66.85 200.0 1,487 202.0 144.45 69.03 202.0 1,536 204.0 148.99 71.30 204.0 1,588 206.0 153.72 73.67 206.0 1,641 File No.: FITZ-1OQ-302 Page 29 of 51 Revision:

0 F0306-01 RO VStructural Integrity Associates, Inc.Table 10: JAFNPP Beltline Region, Curve B, for 48 EFPY Plant =Component

Vessel thickness, t =Vessel Radius, R =ART =Kit =Safety Factor =Mm Temperature Adjustment

Height of Water for a Full Vessel =Pressure Adjustment

=Pressure Adjustment

=Heat Up and Cool Down Rate =Gauge Fluid Temperature (6F)60.0 60.0 62.0 64.0 66.0 68.0.70.0* 72.0.74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 i20.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 inches inches'F ======>ksi*inch" (48 EFPY'F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70°F)psig (instrument uncertainty)

°F/Hr KI.(ksi*inchli) 38.79 38.79 39.02 39.26 39.51 39.77 40.03 40.31 40.60 40.90 41.22 41.55 41.89 42.24 42.61 42.99 43.39 43.81 44.24 44.69 45.16 45.65 46.16 46.69 47.24 47.81 48.41 49.03 49.67 50.35 51.05 51.77 52.53 53.32 54.14 55.00 55.89 56.81 57.78 58.78 59.82 60.91 K1.(ksi*inch'/

2)16.21 16.21 16.32 16.44 16.56 16.69 16.82 16.96 17.11 17.26 17.42 17.58 17.75 17.93 18.11 18.31 18.51 18.71 18.93 19.16 19.39 19.63 19.89 20.15 20.43 20.71 21.01 21.32 21.65 21.98 22.33 22.70 23.07 23.47 23.88 24.31 24.75 25.21 25.70 26.20 26.72 27.26 Temperature for P-T Curve (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 Adjusted Pressure for P-T Curve (psigl)0 338 340 343 346 349 352 355 358 362 365 369 373 377 381 385 390 395 400 405 410 416 421 427 434 440 447 454 461 469 477 485 494 503 512 522 532 542 553 564 576 589 File No.: FITZ-1OQ-302 Revision:

0 Page 30 of 51 F0306-OIRO Structural Integrity Associates, Inc.Table 10: JAFNPP Beltline Region, Curve B, for 48 EFPY (continued)

Gauge Fluid Temperature (1F)142.0 144.0 146.0 148.0 150.0 .152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 198.0 200.0 202.0 204.0 206.0 208.0 210.0 212.0 Kic (ksi*inchll 2).62.04 63.22 64.44 65.72 67.04 68.43 69.86 71.36 72.92 74.54 76.22 77.98 79.81 81.71 83.69 85.75 87.90 90.13 92.45 94.87 97.39 100.00 102.73 105.57 108.52 111.60 114.80 118.13 121.59 125.20 128.95 132.86 136.93 141.16 145.57 150.15 KIm (ksi*inchl 2)27.83 28.42 29.03 29.67 30.33 31.02 31.74 32.49 33.27 34.08 34.92 35.80 36.71 37.66 38.65 39.68 40.76 41.87 43.03 44.24 45.50 46.81 48.17 49.59 51.07 52.61 54.21 55.87 57.60 59.41 61.29 63.24 65.27 67.39 69.59 71.89 Temperature for P-T Curve (1F)142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 198.0 200.0 202.0 204.0 206.0 208.0 210.0 212.0 Adjusted Pressure for P-T Curve (psig)601 615 629 643 658 674 690 707 725 743 762 782 803 825 847 870 895 920 946 974 1,002 1,032 1,063 1,095 1,129 1,163 1,200 1,238 1,277 1,318 1,360 1,405 1,451 1,499 1,549 1,601 File No.: FITZ-1OQ-302 Revision:

0 Page 31 of 51 F0306-01 RO VStructural Integrity Associates, Inc.Table 11: JAFNPP Beltline Region, Curve B, for 54 EFPY Plant =Component

=Vessel thickness, t =Vessel Radius, R =ART =Kit =Safety Factor =Mm =Temperature Adjustment

=Height of Water for a Full Vessel =Pressure Adjustment

=Pressure Adjustment

=Heat Up and Cool Down Rate =Gauge Fluid Temperature (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 inches inches'F ======>ksi*inch "ý54 EFPY F (applied after bolt-up, instrument uncertainty) iches sig (hydrostatic pressure head for a full vessel at 70'F)sig (instrument uncertainty)

F/Hr KIc (ksi*inchl1 2)38.25 38.25 38.46 38.67 38.90 39.13 39.37 39.62 39.88 40.16 40.44 40.74 41.04 41.36 41.70 42.04 42.41 42.78 43.17 43.58 44.00 44.44 44.90 45.38 45.88 46.39 46.93 47.49 48.08 48.68 49.32 49.97 50.66 51.37 52.11 52.88 53.69 54.52 55.39 56.30 57.24 58.22 Kim (ksi*inch 2)15.93 15.93 16.04 16.14 16.26 16.37 16.49.16.62 16.75 16.89 17.03 17.18 17.33 17.49 17.66 17.83 18.01 18.20 18.39 18.60 18.81 19.03 19.26 19.50 19.75 20.01 20.27 20.55 20.85 21.15 21.47 21.79 22.14 22.49 22.86 23.25 23.65 24.07 24.50 24.96 25.43 25.92 Temperature for P-T Curve 60F)60.0 60.0 62.0 64.0 66.0 68.0 70.0, 72.0 74.0'76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 Adjusted Pressure for P-T Curve (psig)0 332 334 336 339 342 344 347 350 353 356 360 363 367 371 375 379 383 387 392 397 402 407 412 418 424 430 436 443 450 457 465 472 480 489 498 507 516 526 536 547-558 File No.: FITZ-1OQ-302 Revision:

0 Page 32 of 5l F0306-O1 RO Structural Integrity Associates, Inc.Table 11: JAFNPP Beltline Region, Curve B, for 54 EFPY (continued)

Gauge Adjusted Fluid Temperature Pressure for Temperature KI. Kim for P-T Curve P-T Curve (0 F) (ksi*inchl1

2) (ksi*inchli
2) (*F) (psig)142.0 59.24 26.43 142.0 570 144.0 60.31 26.96 144.0 582 146.0 61.41 27.51 146.0 594 148.0 62.56 28.09 148.0 607 150.0... 63.76 28.69 150.0 621 152.0 65.01 29.31 152.0 635 154.0 66.31 29.96 154.0 650 156.0 , 67.66 30.64 156.0 665 158.0 69.07 31.34 158.0 681 160.0 70.53 32.07 160.0 698 162.0 72.05 32.83 162.0 715 164.0 73.64 33.63 164.0 733 166.0 75.29 34.45 166.0 752 168.0 77.01 35.31 168.0 771 170.0 78.79 36.21 170.0 791 172.0 80.65 37.14 172.0 813 174.0 82.59 38.10 174.0 835 176.0 84.61 39.11 176.0 857 178.0 86.70 40.16 178.0 881 180.0 88.89 41.25 180.0 906 182.0 91.16 42.39 182.0 932 184.0 93.53 43.57 184.0 959 186.0 95.99 44.80 186.0 986 188.0 98.55 46.08 188.0 1,016 190.0 101.22 47.42 190.0 1,046 192.0 103.99 48.81 192.0 1,077 194.0 106.88 50.25 194.0 1,110 196.0 109.89 51.75 196.0 1,144 198.0 113.02 53.32 198.0 1,180 200.0 116.28 54.95 200.0 1,217 202.0 119.67 56.64 202.0 1,255 204.0 123.20 58.41 204.0 1,295 206.0 .126.87 60.24 206.0 1,337 208.0 130.69 62.15 208.0 1,380 210.0 134.67 64.14 210.0 1,425 212.0 138.81 66.21 212.0 1,472 214.0 143.12 68.37 214.0 1,521 216.0 147.61 70.61 216.0 1,572 218.0 152.28 72.95 218.0 1,625.File No.: FITZ-10Q-302 Page 33 of 51 Revision:

0 F0306-01 RO VStructural Integrity Associates, Inc.Table 12: JAFNPP Bottom Head Region, Curve B, for all EFPY Plant =Component

=Bottom Head thickness, t =Bottom Head Radius, R =ART =Kit =Safety Factor =Stress Concentration Factor =MM =Temperature Adjustment

=Height of Water for a Full Vessel Pressure Adjustment

=Pressure Adjustment

=Heat Up and Cool Down Rate =Gauge Fluid Temperature (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 (penetrations portion)inches inches 0 F ======> All EFPY (bottom head penetrations)

'F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70°F)psig (instrument uncertainty)

°F/Hr KIc (ksi*inchll) 89.56 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 117.28 120.71 124.28 128.00 131.87 135:90 140.09 144.45 148.99 153.72 158.63 163.75 169.08 174.63 180.40 186.40 192.66 199.16 205.94 KIm (ksi*inchll 2)39.01 39.01 40.16 41.36 42.60 43.90 45.25 46.65 48.11 49.64 51.22 52.87 54.58 56.37'58.23 60.16 62.18 64.27 66.45 68.72 71.09 73.54 76.10 78.77 81.54 84.43 87.43 90.56 93.81 97.20 Temperature for P-T Curve (OF)60 60 62 64 66 68 70"72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 Adjusted Pressure for P-T Curve (psig)0 634 654 674 695 718 741 764 789 815 842 870 899 930 962 994 1,029 1,064 1,102 1,140 1,180 1,222 1,266 1,311 1,358 1,408 1,459 1,512 1,567 1,625 File No.: FITZ-1OQ-302 Revision:

0 Page 34 of 51 F0306-OIRO SStructural Integrity Associates, Inc.Table 13: JAFNPP Upper Vessel Region, Curve B, for all EFPY Plant = Fitzpatrick Component

=Upper Vessel (based on FW nozzle)ART = 20.0 'F .....> All EFPY Vessel Radius, R = 110,375 inches Nozzle corner thickness, t = 681 inches, approximate t = 6532 ksi-inch

Kp-applied 56.17 ksi*inch"'

Crack Depth, a 1.703 inches Safety Factor 2.00 Temperature Adjustment 0.0 F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel 825.20 inches Pressure Adjustment

= 29. psig (hydrostatic pressure head for a full vessel at 70'F)Pressure Adjustment

= psig (instrument uncertainty)

Reference Pressure 1,000 psig (pressure at which the FEA stress coeffiecients are valid) [GREEN]Unit Pressure 1.563 psig (hydrostatic pressure)Flange RTNDT = 30.0 F ======> All EFPY Gauge Fluid Temperature (6F)60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 Kic (ksi-inch"')

79.34 79.34 81.23 83.19 85.23'.87.35 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 117.28 120.71 124.28 128.00 131.87 135.90 140.09 144.45 148.99 153.72 158.63 163.75 169.08 174.63 180.40 186.40 192.66 199.16 205.94 212.99 220.32 227.96 235.91 244.18 252.79 261.75 Kip , (ksi*inchl 2)7.01 17.19 17.86 18.55 19.31 20.37 20.87 21.72 22.62 23.55 24.53 25.57 26.65 27.79 28.98 30.24 31.55 32.91 34.35 35.86 37.45 39.10 40.84 42.65 44.56 46.55 48.62 50.80 53.08 55.46 57.96 60.57 63.30 66.15 69.13 72.25 75.50 78.89 82.45 86.16 90.04 94.08 P-T Curve Temperature (6F)60 60 62 64 64 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 150 P-T Curve Pressure (psig)0 276 288 301 313 313 342 357 373 389 407 425 445 465 486 508 532 556 582 609 637 666 697 730 763 799 836 875 915 958 1002 1048 1097 1148 1201 1256 1314 1375 1438 1504 1573 1645 File No.: FITZ-1OQ-302 Revision:

0 Page 35 of 51 F0306-0 1 RO Structural Integrity Associates, Inc.Table 14: JAFNPP Curve C Values for 32 EFPY Plant =Curve A Leak Test Temperature

=Curve A Pressure =Unit Pressure =Flange RTNDT Adjusted P-T Curve Temperature 90.00 90.00 90.00 90.00 90.00 95.17 103.92 104.00 190.00 190.00 190.00 190.00 190.00 190.00 190.00 190.00 190.00 190.00 190.00 194.36 198.52 202.36 205.94 209.26 212.39 215.33 218.11 220.73 223.23 225.61 227.89 230.06 232.15 234.14 236.07 psig psig (hydrostatic pressure)°OF Adjusted P-T Curve Pressure 0 50 100 150 200 250 300 312 313 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1250 1300 1350 1400 1450 1500 1550 1600 File No.: FITZ-1OQ-302 Revision:

0 Page 36 of 51 F0306-OIRO Structural Integrity Associates, Inc.Table 15: JAFNPP Curve C Values for 40 EFPY Plant F Curve A Leak Test Temperature

= 148.0 D Curve A Pressure , 1,025.0 psig Unit Pressure = 1,563 psig (hydrostatic pressure)Flange RTNDT = i" 30.0 ..Adjusted Adjusted P-T Curve P-T Curve Temperature Pressure 90.00 0 90.00 50 90.00 100 90.00 150 90.00 200 95.17 250 103.92 300 104.00 312 190.00 313 190.00 350 190.00 400 190.00 450 190.00 500 190.00 550 190.00 600 190.00 650 ,190.00 700 193.21 750 198.22 800 202.75 850 206.92 900 210.76 950 214.33 1000 217.67 1050 220.79 1100 223.73 1150 226.50 1200 229.13 1250 231.64 1300 234.02 1350 236.29 1400 238.46 1450 240.54 1500 242.54 1550 244.48 1600 File No.: FITZ-1OQ-302 Page 37 of 5l Revision:

0 F0306-OIRO Structural Integrity Associates, Inc.Table 16: JAFNPP Curve C Values for 48 EFPY Plant=Curve A Leak Test Temperature

=Curve A Pressure=Unit Pressure =Flange RTNDT =Adjusted P-T Curve Temperature 90.00 90.00.90.00 90.00 90.00 95.17 103.92 104.00 190.00 190.00 190.00 190.00 190.00 190.00 190.00 190.00 ,195.16 200.71*205.71'210.26 214.42 218.27 221.84 225.16 228.29 231.23 234.01 236.63 239.13 241.51 243.79 245.97 248.05 250.05 251.97 OF psig psig (hydrostatic pressure)OF Adjusted P-T Curve Pressure 0 50 100 150 200 250 300 312 313 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1250 1300 1350 1400 1450 1500 1550 1600 File No.: FITZ-1OQ-302 Revision:

0 Page 38 of 51F0306-01 RO VStructural Integrity Associates, Inc.Table 17: JAFNPP Curve C Values for 54 EFPY Plant Fitzpatrick Curve A Leak Test Temperature

= 160.0 F Curve A Pressure = 1,025.0 psig Unit Pressure = 1,563 psig (hydrostatic pressure)Flange RTNDT = O0.0 F °F Adjusted Adjusted P-T Curve P-T Curve Temperature, Pressure 90.00 0 90.00 50 90.00 100 90.00 150 90.00 200 95.17 250 103.92 300 104.00 312 190.00 313 190.00 350 190.00 400 190.00 450 190.00 500 190.00 550 190.00 600 194.02 650 200.26 700 ,205.82 750 210.81 800 215.35 850 219.52 900 223.36 950 226.93 1000 230.27 1050 233.39 1100 236.33 1150 239.10 1200 241.74 1250 244.24 1300 246.61 1350 248.88 1400 251.06 1450 253.14 1500 255.14 1550 257.10 1600 File No.: FITZ-10Q-302 Page 39 of 51 Revision:

0 F0306-0 I RO Structural Integrity Associates, Inc.Fitzpatrick Pressure Test (Curve A), 32 EFPY 1,600 1,500 1,400 1,300-1 ,200..r 0.01,100 w C 1,000 I---LJ Cn 900 U)w M 800 0 I-,, 700 z-600 u 500 U)LW 400 0.1'Bolt-up Ternp 60'F 300 200 100 0 IL-Beltline L Region IL IL--Bottom HeadL e L IL IL I --Upper VesselL IL IL 100 120 140 160 180 200 220 240 260 280 300 320 340 0 20 40 60 80 MINIMUM REACTOR VESSEL METAL TEMPERATURE

(°F)Figure 1: JAFNPP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 32 EFPY Note.: The instrument uncertainty due to temperature and pressure is assumed to be equal to zero, per Section 3. 0.File No.: FITZ-IOQ-302 Revision:

0 Page 40 of 51 F0306-01 RO Structural Integrity Associates, Inc.Fitzpatrick Pressure Test (Curve A), 40 EFPY 1,600 1,500 1,400 1,300-@1,200.r o 1,100 w 00 1,00 0 I--J w Cj 900 800 0 I-w700 z 6, 600 o ,, 500: 400 3n 00 20 U)uJ 400 300 200 100 0 I Bolt-up Temp 60'F Region I-Bottom Head L IVessel L I L 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)320 340 Figure 2: JAFNPP P-T Curve A (Hydrostatic Pressure and Leak Tests) at 40 EFPY Note: The instrument uncertainty due to temperature and pressure is assumed to be equal to zero, per Section 3. 0.File No.: FITZ-1OQ-302 Revision:

0 Page 41 of 51 F0306-OIRO Structural Integrity Associates, Inc.Fitzpatrick Pressure Test (Curve A), 48 EFPY 1,600 1,500 1,400 1,300-S1,200 0.01,100 LU a 1,000 I-LU 0n 900 w 800 0 w 700 Z-600 u 500 C,)C,)LU 400 0.300 200 100 0'Bolt-up]Ternp[60°F-Beltline Region IL--Bottom Head L IL---Upper Vessel L ffnm m 20 40 0 60 80 100 120 140 160 180 200 220 240 260 280 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)320 340 Figure 3: JAFNPP P-T Curve A (Hydrostatic Pressure and Leak Tests) at 48 EFPY Note.: The instrument uncertainty due to temperature and pressure iý assumed to be equal to zero, per Section 3. 0.File No.: FITZ-1OQ-302 Revision:

0 Page 42 of 51 F0306-01 RO Structural Integrity Associates, Inc.Fitzpatrick Pressure Test (Curve A), 54 EFPY 1,600 1,500 1,400 1,300-a1,200 (/), 01,100 w I[L 1,000 I-..J cn 900 Co w w 800 0 I-, 700 z t- 600 n 500 Co Co W 400 0Q.' e Bolt-up Temp 1600F1 300 200 100 0_________ -LýBeltline Region i-Bottom Head L i--. Upper Vessel L 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)320 340 Figure 4: JAFNPP P-T Curve A (Hydrostatic Pressure and Leak Tests) at 54 EFPY Note: The instrument uncertainty due to temperature and pressure is assumed to be equal to zero, per Section 3. 0.File No.: FITZ-1OQ-302 Revision:

0 Page 43 of 51 F0306-OIRO Structural Integrity Associates, Inc.Fitzpatrick Normal Operation

-Core Not Critical (Curve B), 32 EFPY 1,600 1,500 , 1,400.@<1,100 LU"r 1,000v-, 0 -,- -I--JI 900 LUl o 800 ,. I-- -z mI 600 Z U, wu 400 CL 300_ q-- -- ottom Head,_--100- =4-,_ Region _JL 0--_ HTem- ,- --Up e V s el -0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE

(°F)Figure 5: JAFNPP P-T Curve B (Normal Operation

-Core Not Critical) for 32 EFPY Note: The instrument uncertainty due to temperature and pressure is assumed to be equal to zero, per Section 3. 0.File No.: FITZ-1OQ-302 Page 44of51 Revision:

0 F0306-01 RO V Structurai Integrity Associates, Inc.Fitzpatrick Normal Operation

-Core Not Critical (Curve B), 40 EFPY 1,400 1,300 I V -1,200 01,100 w-Ii M:-IL 1,1000w< , w W 800 0 L.n 700 1 F- 600 W 500 4 400 300 -- Bottom Hea 100 Region 0.0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (ff)Figure 6: JAFNPP P-T Curve B (Normal Operation

-Core Not Critical) for 40 EFPY Note: The instrument uncertainty due to temperature and pressure is assumed to be equal to zero, per Section 3. 0.Fie No.: FITZ-IOQ-302 Page 45 of 51 Revision:

0 F0306-OIRO Structural Integrity Associates, Inc.Fitzpatrick Normal Operation

-Core Not Critical (Curve B), 48 EFPY 1,600i 1,500 1,400 1,300_ 1,200 Ul0 1,100 = '!n1,000:A 0 4,,/F-U) 900 8- 00 , 500 LuJ 7000100--1J 500 0w20 0 6 300.. ..-- --oto -H ad --4 -Bolt-uple N T s t-un d t t a p i ---Upper Vessel c 3 200 -- Temp L-- ROF, ,--Beltline 100-- --0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (Ff)Figure 7: JAFNPP P-T Curve B (Normal Operation

-Core Not Critical) for 48 EFPY Note." The instrument uncertainty due to temperature and pressure is assumed to be equal to zero, per Section.3.

0.File No.: FITZ-IOQ-302 Page 46 of 51 Revision:

0 F0306-01 RO Structural Integrity Associates, Inc.Fitzpatrick Normal Operation

-Core Not Critical (Curve B), 54 EFPY 1,6008 1,500 1,400 I 1,300 1,200 S1,100 IL 0 1,000 ,.-/LU V) 900 S.800 L" 700 i- 600 LU 500 '0n 3Li 400 10 Rg 300 280 180.200 220.240 B2 0 3tto00 320- 34 MI N R M Tolt-up __ T~Temn am t b Upper Vessel S-FilNo: TZ Q Page47,oiBeltline

-Revision:

0 -100 -_ _ L l--- -~ ~ --0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (Ff)Figure 8: JAFNPP P-T Curve B (Normal Operation

-Core Not Critical) for 54 EFPY Note." The instrument uncertainty due to temperature and pressure is assumed to be equal to zero, per Section 3. 0.Fie No.: FITZ-IOQ-302 Page 47 of 51 Revision:

0 F0306-O I RO Structural Integrity Associates, Inc.Fitzpatrick Normal Operation

-Core Critical (Curve. C), 32 EFPY 1,600 1,500 1,400 1,300-a1,200 (/}, 01,100 w LU 1 1,000 0 I--J 900 Co)uLJ n 800.0 I--.< 700 i- 600"W 500 Cn L 400 a.300 200 100 0 I Minimum Criticality Temp 90°F 0 20 40 6(0 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (F)Figure 9: JAFNPP P-T Curve C (Normal Operation

-Core Critical) for 32 EFPY Note: The instrument uncertainty due to temperature and pressure is assumed to be equal to zero, per Section 3. 0.File No.: FITZ-1OQ-302 Revision:

0 Page 48 of 51 F0306-01 RO Structural Integrity Associates, Inc.Fitzpatrick Normal Operation

-Core Critical (Curve C), 40 EFPY 1,600 1,500 1,400 1 ,300-a1,200 0.01,100 w a 1,000 ,-I-O0 cj, 900 U), 800 0 I-< 700 ILl I- 600 Lu 500 u)LU 400 a.300 200 100 0 Minimum-- -Criticality Temp 90°0 20 40 6(F 0 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)Figure 10: JAFNPP P-T Curve C (Normal Operation

-Core Critical) for 40 EFPY Note: The instrument uncertainty due to temperature and pressure is assumed to be equal to zero, per Section 3. 0, File No.: FITZ-1OQ-302 Revision:

0 Page 49 of 51 F0306-O1RO Structural Integrity Associates, Inc.Fitzpatrick Normal Operation

-Core Critical (Curve C), 48 EFPY 1,600 1,500 1,400 1,300-1,200 0.01,100 w x a 1,000 0 I-.-J uJ in 900 V)w.W 800 0o I--< 700 I- 600 Lu 500 Cr u 400 300 200 100 0 j Minimum Criticality Temp 90'F 0 20 40 6(0 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)Figure 11: JAFNPP P-T Curve C (Normal Operation

-Core Critical) for 48 EFPY Note: The instrument uncertainty due to temperature and pressure is assumed to be equal to zero, per Section 3. 0.File No.: FITZ-1OQ-302 Revision:

0 Page 50 of 51 F0306-01 RO V Structural Integrity Associates, Inc.Fitzpatrick Normal Operation

-Core EFPY Critical (Curve C), 54 1,600 1,500 1,400 1,300-a1,200 0.01,100 w a 1,000 0 I--uj con 900 cn uL W 800 0 I-.< 700 I.600 LW 500 C', U, wj 400 w CL 300 200 100 0 Minimum Criticality Temp 90'F 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)Figure 12: JAFNPP P-T Curve C (Normal Operation

-Core Critical) for 54 EFPY Note: The instrument uncertainty due to temperature andpressure is assumed to be equal to zero, per Section 3. 0.File No.: FITZ-1OQ-302 Revision:

0 Page 51 of 51 F0306-O1 RO U Structural Integrity Associates, Inc.APPENDIX A: P-T CURVE INPUT LISTING File No.: FITZ-1OQ-302 Revision:

0 Page Al of A3 F0306-OIRO Structural Integrity Associates, Inc.List of Design Inputs and Source References for JAFNPP P-T Curves at 32 and 40 EFPY Instrument Uncertainty

Reference:

Reactor Vessel Metal Temp Reactor Vessel Pressure 0 *F 0%Assumed Assumed Geometry ART/RTNDT 32 EFPY Vessel Radius Vessel Shell thickness Bottom Head Thickness Bottom Head Radius Limiting Beltine Limiting Bottom Head Limiting Upper Vessel (Feedwater)

RTNDT Flange Material (Boltup)110.375 in.5.375 in.6.8125 in.110.5 in.109.6 'F 10 *F 20 'F 30 0 F CE Report [10]CE Report [10]CE Report [10]CE Report [10]SI ART Calc [6]GE Report [7]GE Report [7]GE Report [7]SI ART Calc [6]GE Report [7]GE Report [7]GE Report [7]40 EFPY Limiting Beltine Limiting Bottom Head Limiting Upper Vessel (Feedwater)

RTNDT Flange Material (Boltup)Safety Factor/Stress Concentration Factor Core Not Critical (Curve B) Core Critical (Curve C)Pressure (Curve A)Lower Penetrations (SCF)K, During Pressure Test (near isothermal conditions) 118 10 20 30 2 1.5 3 0-F oF-F oF PTLR [5]PTLR [5]PTLR [5]Assumed Water Density Pressure Water Elevation (pressure head)Hydrostatic Test Pressure Static Head Pressure Adjustment Bolt Up Temperature Increment Heat Up and Cool Down Rate 62.4 1250 825.2 1563 29.8 lb/ft3 psig in psig psig Assumed GE Dwg [9]GE Report [7]Calculated Calculated PTLR [5]Assumed GE Dwg [9]Assumed Temperature Rate of Temp Change 60 2 100 'F File No.: FITZ-1OQ-302 Page A2 of A3 Revision:

0 F0306-01 RO Structural Integrity Associates, Inc.List of Design Inputs and Source References for JAFNPP P-T Curves -at 48 and 54 EFPY Instrument Uncertainty..

Reference:

Geometry Reactor Vessel Metal Temp Reactor Vessel Pressure Vessel Radius.Vessel Shell thickness Bottom Head Thickness Bottom Head Radius 0 *F 0%Assumed Assumed 110.375 in.5.375 in.6.8125 in.110.5 in.ART/RTNDT 48 EFPY Limiting Beltine Limiting Bottom Head Limiting Upper Vessel (Feedwater)

RTNDT Flange Material (Boltup)125.5 'F 10 'F 20 °F 30 'F 54 IFPY .Limiting Beltine Limiting Bottom Head Limiting Upper Vessel (Feedwater)

RTNDT Flange Material (Boltup)Safety Factor/Stress Concentration Factor Core Not Critical (Curve B) Core Critical (Curve C)Pressure (Curve A)Lower. Penetrations (SCF)Kt During Pressure Test (near isothermal conditions)

Water Density Pressure Water Elevation (pressure head)Hydrostatic Test Pressure Static Head Pressure Adjustment 130.6 'F 10 'F 20 0 F 30 'F 2 1.5 3 0 62.4 lb/ft3 1250 psig.825:2 in 1563 psig 29.8 psig CE Report [10]CE Report [10]CE Report [10]CE Report [10]SI ART Calc [6]GE Report [7]GE Report [7]GE Report [7]SI ART Calc [6]GE Report [7]GE Report [7]GE Report [7]PTLR [5]PTLR [5]PTLR [5]Assumed Assumed GE Dwg [9]GE Report [7]Calculated Calculated Assumed Temperature Rate of Temp Change Bolt Up Temperature Increment Heat Up and Cool Down Rate 60 2 PTLR [5]Assumed GE Dwg [9]100 'F File No.: FITZ-10Q-302 Revision:

0 Page A3 of A3 F0306-01RO 0 Structural Integrity Associates, Inc.APPENDIX B: DEVELOPMENT OF SATURATED STEAM CURVE FITS File No.: FITZ-1OQ-302 Revision:

0 Page B I of B4 F0306-01 RO Structural Integrity Associates, Inc.Curve Fit for Saturated Steam

Reference:

Steam Table data obtained from "Steam Tables, Properties of Saturated and Superheated Steam," CE Power Systems, 7th Printing.Curve Fit: Tsat = 119.3"(0.7 9 8 7)(lPsat)

  • Psat0.2198 Pressure Psat (psia)Temperature

`Tsat ,(°F)Curve Fit Tsat (VF)Difference Error (*F) (%)14.696 15 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 250 260 270 280 290 300 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 212.00 21,3.03 227.96 250.34 267.25 281.02 292.71 302.93 312.04 320.28 327.82 334.79 341.27 347.33 353.04 358.43 363.55 368.42 373.08 377.53 381.80 385.91 389.88 393.70 397.39 400.97 404.44 407.80 411.07 414.25 417.35 431.73 444.60-456.28 467.01 476.94 486.20 494.89 503.08 510.84 518.21 525.24 531.95 538.39 544.58 212.10 213.13 227.89 250.07 266.89 280.62 292.32 302.55 311.69 319.96 327.54 334.54 341.06 347,16 352.91 358.34 363.49 368.40 373.08 377.57 381.87 386.01-390.00 393.84 397.56 401.16 404.65 408.03 411.32 414.51 417.62 432.06 444.97 456.67 467.39 477.30 486.54 495.19 503.33 511.03 518.34 525.31 531.95 538.32 544.43 0.10 0.10-0.07-0.27-0.36-0.40-0.39-0.38-0.35-0.32-0.28-0.25-0.21-0.17-0.13-0.09-0.06-0.02 0.00 0.04 0.07 0.10 0.12 0.14 0.17 0.19 0.21 0.23 0.25 0.26 0.27 0.33 0.37 0.39 0.38 0.36 0.34 0.30 0.25 0.19 0.13 0.07 0.00-0.07-0.15.0.05%0.05%-0.03%-0.11%-0.13%-0.14%-0.13%-0.13%-0.11%-0.10%-0.09%-0.07%-0.06%-0.05%-0.04%-0.03%-0.02%-0.01%0.00%0.01%0.02%0.03%0.03%0.04%0.04%0.05%0.05%0.06%0.06%0.06%,0.07%0.08%0.08%0.08%0.08%0. 08%0.07%0.06%0.05%0.04%0.03%0.01%0.00%-0.01%-0.03%File No.: FITZ-1OQ-302 Revision:

0 Page B2 of B4 F0306-01 RO Structural Integrity Associates, Inc.Curve Fit for Saturated Steam

Reference:

Steam Table data obtained from "Steam Tables, Properties of Saturated and Superheated Steam," CE Power Systems, 7th Printing.Curve Fit: Tsat = 1 1 9.3"(0.7 9 8 7)(1IPsat)

.Psat 0.2 1 9 8 Pressure Psat (psia)Temperature Tsat (OF)Curve Fit Tsat ('F)Difference Error (*F) (%)1050 1100 1150 1200 1250 1300 1350 1400 1450 1500 1550 1600 1650 1700.1750ý1800 1850 1900 1950 2000 2100 2200 2300 2400 2500 550.53 556.28 561.82 567.19 572.38 577.42 582.32 587.07 591.70 596.20 600.59 604.87 609.05 613.13 617.12 621.02 624.83 628.56 632.22 635.80 642.76 649.45 655.89 662.11 668.11 550.31 555.97 561.43 566.71 571.83 576.78 581.59 586.26 590.80 595.22 599.53 603.73 607.83 611.84 615.75 619.58 623.32 626.99 630.58 634.10 640.94 647.53 653.89 660.04 665.99-0.22-0.31-0.39-0.48-0.55-0.64-0.73-0.81-0.90-0.98-1.06-1.14-1.22-1.29-1.37-1.44-1.51-1.57-1.64-1.70-1.82-1.92-2.00-2.07-2.12 0.39-2.12-0.41 0.71-0.04%-0.06%-0.07%-0.08%-0.10%-0.11%-0.13%-0.14%-0.15%-0.16%-0.18%-0.19%-0.20%-0.21%-0.22%-0.23%-0.24%-0.25%-0.26%-0.27%-0.28%-0.30%-0.30%-0.31%-0.32%0.08%-0.32%-0.07%0.12%Maximum =Minimum =Average =Std. Deviation File No.: FITZ-1OQ-302 Revision:

0 Page B3 of B4 F0306-0I RO V Structural Integrity Associates, Inc.Curve Fit for Saturated Steam Conditions 800 700 600 CL E 500 0.E400 I-0 300 C,,.200 100 0 500 1,000 1,500 2,000 Saturation Pressure (psia)2,500 File No.: FITZ-1OQ-302 Revision:

0 Page B4 of B4 F0306-O1RO

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