ML040630687

to WCAP-15161, Vogtle Electric Generating Plant, Unit 2, Heatup and Cooldown Limit Curves for Normal Operation.

ML040630687
Person / Time
Site:	Vogtle
Issue date:	02/29/2004
From:	Ghergurovich J, Laubham T Westinghouse
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
WCAP-15161, Rev 3
Download: ML040630687 (46)

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Westinghouse Non-Proprietary Class 3 WCAP-15161 February 2004 Revision 3 Vogtle Electric Generating Plant Unit 2 Heatup and Cooldown Limit Curves for Normal Operation Westinghouse i

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-15161, Revision 3 Vogtle Electric Generating Plant Unit 2 Heatup and Cooldown Limit Curves for Normal Operation T. J. Laubham February 2004 Approved: &i fv  ! 7 J 4 J. Ghergurovich, Manager '

Reactor Component Design & Analysis Westinghouse Electric Company LLC Energy Systems P.O. Box 355 Pittsburgh, PA 15230-0355 02004 Westinghouse Electric Company LLC All Rights Reserved

Hi PREFACE This report has been technically reviewed and verified by:

Reviewer: K. G.Knight Hi n ? it 4A Record of Revision Revision 1:

Updated all pressure-temperature curves using the 1996 App. G to Section Xl of the ASME Code, Kic from Code Case N-640 and the removal of the flange requirement per WCAP-15315. All calculations for adjusted reference temperature remain unchanged from Revision 0. Text has been updated to support the use of the '96 App. 0. K1c and elimination of the flange notch.

Revision 2:

The reference to WCAP-14040-NP-A, Revision 2 has been revised to WCAP-14040-A, Revision 4 to reflect the latest NRC approved version. The reference to WCAP-15315 has been revised to WCAP-16142 to reflect the Vogtle Units I and 2 flange elimination justification rather than the generic flange elimination justification contained in WCAP-15315. In addition, the thermal stress intensity factors wvere added for the highest heatup and cooldown rate.

Revision 3:

Updated Reference 11, WCAP- 16142, to Revision 1.

Revision 3

iv TABLE OF CONTENTS PREFACE .............................................. iii LISTOFTABLES..........................................................................................................................................LV LIST OF FIGURES ............................................... vii EXECUTIVE

SUMMARY

............................................... iii I INTRODUCTION .1-I 2 PURPOSE .2-1 3 CRITERIA FOR ALLOWABLE PRESSURE-TEMPERATURE RELATIONSHIPS .3-1 4 CALCULATION OF ADJUSTED REFERENCE TEMPERATURE .4-1 5 HEATUP AND COOLDOWN PRESSURE-TEMPERATURE LIMIT CURVES 5 -I 6 REFERENCES .... I APPENDIX A THERMAL STRESS INTENSITY FACTORS ............................................... A-1 Revision 3

V LIST OF TABLES Table 4-1 Summary of Peak Pressure Vessel Neutron Fluence Values at 26 EFPY used for the calculation of ART Values (n/cm 2, E > 1.0 MeV) ......................................................... 4-2 Table 4-2 Summary of Peak Pressure Vessel Neutron Fluence Values at 36 EFPY used for the calculation of ART Values (n/cm2 , E > 1.0 MeV) .................................. 4-3 Table 4-3 Calculated Integrated Neutron Exposure of the Vogtle Unit 2 Surveillance Capsules Tested to Date........ 4-4 Table 4-4 Measured 30 ft-lb Transition Temperature Shifts of the Beltline Materials Contained in the Surveillance Program .4-5 Table 4-5 Reactor Vessel Beltline Material Unirradiated Toughness Properties .4-6 Table 4-6 Calculation of Chemistry Factors using Vogtle Unit 2 Surveillance Capsule Data. 4-7 Table 4-7 Summary of the Vogtle Unit 2 Reactor Vessel Beltline Material Chemistry Factors Based on Regulatory Guide 1.99, Revision 2. Position 1.1 and Position 2.1 ................. 4-8 Table 4-8 Summary of the Calculated Fluence Factors used for the Generation of the 26 EFPY Heatup and Cooldown Curves......................................................................... 4-9 Table 4-9 Summary of the Calculated Fluence Factors used for the Generation of the 36 EFPY Heatup and Cooldown Curves..4-101 Table 4-10 Calculation of the ART Values for the 1/4T Location @ 26 EFPY . 4-11 Table 4-11 Calculation of the ART Values for the 3/4T Location @ 26 EFPY .. 4-1' Table 4-12 Calculation of the ART Values for the 1/4T Location @ 36 EFPY .. . . I Table 4-13 Calculation of the ART Values for the 3/4T Location @ 36 EFPY . 4-14 Table 4-14 Summary of the Limiting ART Values used in the Generation of the Vogtle Unit 2 Heatup/Cooldown Curves ................. 4- 1, Table 5-1 Vogtle Unit 2 Heatup Data at 26 EFPY Without Margins for Instrumentation Errors.....................................................................................................5-5 Revision 3

vi LIST OF TABLES - (Continued)

Table 5-2 Vogtle Unit 2 Cooldown Data at 26 EFPY Without Margins for Instrumentation Errors ............................................................ 5-6 Table 5-3 Vogtle Unit 2 Heatup Data at 36 EFPY Without Margins for Instrumentation Errors ...5-9 Table 5-4 Vogtie Unit 2 Cooldown Data at 36 EFPY Without Margins for Instrumentation Errors . 5-10 Revision 3

vii LIST OF FIGURES Figure 5-1 Vogtle Unit 2 Reactor Coolant System Heatup Limitations (Heatup Rates of 60 and I 00 0 F/hr) Applicable to 26 EFPY (Without Margins for Instrumentation Errors) ......... 5-3 Figure 5-2 Vogtle Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates of 0, 20, 40, 60 and I 00 0 F/hr) Applicable to 26 EFPY (Without Margins for Instrumentation Errors) ............................... 5-4 Figure 5-3 Vogtle Unit 2 Reactor Coolant System Heatup Limitations (Heatup Rates of 60 and 1000 F/hr) Applicable to 36 EFPY (Without Margins for Instrumentation Errors) ......... 5-7 Figure 5-4 Vogtle Unit 2 Reactor Coolant System Cooldoxwn Limitations (Cooldown Rates of 0, 20,40, 60 and 1000 F/hr) Applicable to 36 EFPY (Without Margins for Instrumentation Errors) ............................... 5-8 Revision 3

viii EXECUTIVE

SUMMARY

The purpose of this report is to generate pressure-temperature limit curves for Vogtle Electric Generating Plant Unit 2 for normal operation at 26 and 36 EFPY using the methodology from the 1996 ASME Boiler and Pressure Vessel Code, Section Xi, Appendix G Regulatory Guide 1.99, Revision 2 is used for the calculation of Adjusted Reference Temperature (ART) values at the 1/4T and 3/4T location. The 1/4T and 3/4T ART values are summarized in Table 4-14 and were calculated using the lower shell plate R8-1 (i.e. the limiting beltline region material). The pressure-temperature limit curves were generated without margins for instrumentation errors for heatup rates of 60 and 1000 F/hr and cooldow'n rates of 0. 20, 40, 60 and 1000 F/hr. These curves can be found in Figures 5-1 through 5-4. The Vogdle Electric Generating Plant Unit 2 heatup and cooldown pressure-temperature limit curves have been updated based on the use of the ASME Code Case N-640 110 1, which allows the use of the Kl, methodology, and the elimination of the reactor vessel flange temperature requirement (Ref, WCAP-161421 "1 ).

Revision 3

I-'

I INTRODUCTION Heatup and cooldown limit curves are calculated using the adjusted RTNDT (reference nil-ductility temperature) corresponding to the limiting beitline region material of the reactor vessel. The adjusted RTNDT of the limiting material in the core region of the reactor vessel is determined by using the unirradiated reactor vessel material fracture toughness properties, estimating the radiation-induced ARTNDT, and adding a margin. The unirradiated RTNDT is designated as the higher of either the drop weight nil-ductility transition temperature (NDTT) or the temperature at which the material exhibits at least 50 fl-lb of impact energy and 35-mil lateral expansion (normal to the major working direction) minus 60 0F.

RTNDT increases as the material is exposed to fast-neutron radiation. Therefore, to find the most limiting RTNDT at any time period in the reactor's life, ARTNDT due to the radiation exposure associated with that time period must be added to the unirradiated RTNDT(IRTNDT). The extent of the shift in RTNDT is enhanced by certain chemical elements (such as copper and nickel) present in reactor vessel steels. The Nuclear Regulatory Commission (NRC) has published a method for predicting radiation embrittlement in Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials"11 I.

Regulatory Guide 1.99, Revision 2, is used for the calculation of Adjusted Reference Temperature (ART) values (IRTNDT + ARTNDT + margins for uncertainties) at the 1/4T and 3/4T locations, where T is the thickness of the vessel at the beltline region measured from the clad/base metal interface. The most limiting ART values are used in the generation of heatup and cooldowh pressure-temperature limit curves for normal operation. As a note, calculated capsule and vessel fluence projections171 were used in determination of the most limiting ART values. The fluence evaluation in Reference 7 used the ENDF/B-VI scattering cross-section data set. This is consistent with the methods presented in WCAP-14040-A, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves" 18 1.

The heatup and cooldown curves documented in this report were generated using the most limiting ARTI values and the NRC approved methodology documented in WCAP- 14040-A, Revision 418X, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves" with one exception. The neutron fluence calculations used Equation 3 of Regulatory Guide 1.190 rather than Equation 4 to perform the flux synthesis. As discussed in Section 1.3.4 of Regulatory Guide 1.190, this approach tends to over predict the maximum flux at the pressure vessel, therefore resulting in slightly conservative calculated results. The reactor vessel flange temperature requirement has also been eliminated. Justification has been provided in WCAP-16142 111 .

Intrducton evison Introduction Revision 3

2-1 2 PURPOSE Southern Nuclear contracted Westinghouse to generate new heatup and cooldown curves for 26 and 36 EFPY using the latest Code Methodologies and the elimination of the flange requirement. The heatup and cooldown curves were generated without margins for instrumentation errors. The curves include a hydrostatic leak test limit curve from 2485 to 2000 psig.

The purpose of this report is to present the calculations and the development of the Southern Nuclear Vogtle Electric Generating Plant Unit 2 heatup and cooldown curves for 26 and 36 EFPY. This report documents the calculated adjusted reference temperature (ART) values following the methods of Regulatory Guide 1.99, Revision 2111, for all the beltline materials and the development of the heatup and cooldown pressure-temperature limit curves for normal operation.

Revision 3 Purpose Revision 3

3-1 3 CRITERIA FOR ALLOWABLE PRESSURE-TEMPERATURE RELATIONSHIPS 3.1 Overall Approach The ASME approach for calculating the allowable limit curves for various heatup and cooldown rates specifics that the total stress intensity factor, K1, for the combined thermal and pressure stresses at any time during heatup or cooldown cannot be greater than the reference stress intensity factor, Kl,, for the metal temperature at that time. KI, is obtained from the reference fracture toughness curve, defined in Code Case N-640, "Alternative Reference Fracture Toughness for Development of PT Limit Curves for Section Xl" 3 & 101 of the ASME Appendix G to Section Xl. The Kic curve is given by the following equation:

2 K, . =33.2+20.734*elOO '?ilIl Al ( )

where, K1, reference stress intensity factor as a function of the metal temperature T and the metal reference nil-ductility temperature RTNDT This KI, curve is based on the lower bound of static critical K, values measured as a function of temperature on specimens of SA-533 Grade B Class], SA-508-1, SA-508-2, SA-508-3 steel.

3.2 Methodology for Pressure-Temperature Limit Curve Development The governing equation for the beatup-cooldown analysis is defined in Appendix G of the ASME Code as follows:

C* Kin, + Kit < K1 c (2)

where, Kin, - stress intensity factor caused by membrane (pressure) stress K, = stress intensity factor caused by tile thermal gradients K, = function of temperature relative to the RTNDT of the material C = 2.0 for Level A and Level B service limits C 1.5 for hydrostatic and leak test conditions during which the reactor core is not critical Revision 3 Criteria For Allowvable Pressure-Temperature Relationships Allowable Pressure-Temperature Relationships Revision 3

3J-2 For membrane tension, the corresponding K, for the postulated defect is:

KIm= M.x(pR /t) (3) where, Mm for an inside surface flaw is given by:

Mm = 1.85 for ft < 2, Mm = 0.92617 for 2*<17 < 3.464, Mm = 3.21 for 17 >3.464 Similarly, Mm for an outside surface flaw is given by:

Mm = 1.77 for Ft < 2, Mm = 0.893 F1 for 2 < a < 3.464, Mm = 3.09 for 1I > 3.464 and p = internal pressure, Ri = vessel inner radius, and t = vessel wall thickness.

For bending stress, the corresponding K, for the postulated defect is:

KIb = Mb

• Maximum Stress, where Mb is two-thirds of M,,,

The maximum K, produced by radial thermal gradient for the postulated inside surface defect of G-2120 is KI, = 0.953x] 0'3 x CR x t25 , where CR is the cooldowvn rate in 'F/hr., or for a postulated outside surface defect, KI, = 0.753xI O3 x HU x t25 , where HU is the heatup rate in 'F/hr.

The through-wall temperature difference associated with the maximum thermal K, can be determined from Fig. G-2214-1. The temperature at any radial distance from the vessel surface can be determined from Fig. G-2214-2 for the maximum thermal K1 .

(a) The maximum thermal K, relationship and the temperature relationship in Fig. G-2214-1 are applicable only for the conditions given in G-2214.3(a)(1) and (2).

(b) Alternatively, the K, for radial thermal gradient can be calculated for any thermal stress distribution and at any specified time during cooldown for a /4-thickness inside surface defect using the relationship:

KS,= (1.0359Co + 0.6322C, + 0.4753C2 + 0.3855C-) * (4)

Criteria For Allowable Pressure-Temperature Relationships Revision 3

3 or similarly. KIT during heatup for a '/,-thickness outside surface defect using the relationship:

Ki1 = (1.043Co + 0.630C, + 0.481C2 + 0.401C3)* (5) where the coefficients C0, Cl, C2 and C3 are determined from the thermal stress distribution at any specified time during the heatup or cooldown using the form:

a(x) = Co + Ci(x / a) + C2(x / a)2 + Ci(x / a)' (6) and x is a variable that represents the radial distance from the appropriate (i.e., inside or outside) surface to any point on the crack front and a is the maximum crack depth.

Note, that equations 3, 4 and 5 were implemented in the OPERLIM computer code, which is the program used to generate the pressure-temperature (P-T) limit curves. No other changes were made to the OPERLIM computer code with regard to P-T calculation methodology. Therefore, the P-T curve methodology is unchanged from that described in WCAP-14040, "Methodology used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves" 181 Section 2.6 (equations 2.6.2-4 and 2.6.3-1) with the exceptions just described above.

At any time during the heatup or cooldown transient, KI, is detennined by the metal temperature at the tip of a postulated flaw at the 1/4T and 3/4T location, the appropriate value for RTNDT, and the reference fracture toughness curve. The thermal stresses resulting from the temperature gradients through the vessel wall are calculated and then the corresponding (thermal) stress intensity factors, KI,, for the reference flaw are computed. From Equation 2, the pressure stress intensity factors are obtained and.

from these, the allowable pressures are calculated.

For the calculation of the allowable pressure versus coolant temperature during cooldown, the reference flaw of Appendix G to the ASME Code is assumed to exist at the inside of the vessel wvall. During cooldown. the controlling location of the flaw is always at the inside of the wall because the thermal gradients produce tensile stresses at the inside, which increase with increasing cooldown rates.

Allowable pressure-temperature relations are generated for both steady-state and finite cooldown rate situations. From these relations, composite limit curves are constructed for each cooldown rate of interest.

Tile use of the composite curve in the cooldown analysis is necessary because control of the cooldown procedure is based on the measurement of reactor coolant temperature, whereas the limiting pressure is actually dependent on the material temperature at the tip of the assumed flaw. During cooldown, the 1/4T vessel location is at a higher temperature than the fluid adjacent to the vessel inner diameter. This condition. of course. is not tnie for the steady-state situation. It follows that, at any given reactor coolant temperature. the AT (temperature) developed during cooldown results in a higher value of K1 , at the 1/4T location for finite cooldown rates than for steady-state operation. Furthermore, if conditions exist so that the increase in KI, exceeds KIt, the calculated allowable pressure during cooldown will be greater than the stcadv-state value.

Criteria For Allowable Pressure-Temperature Relationships Revision 3

34 The above procedures are needed because there is no direct control on temperature at the I/4T location and, therefore, allowable pressures may unknowingly be violated if the rate of cooling is decreased at various intervals along a cooldown ramp. The use of the composite curne eliminates this problem and ensures conservative operation of the system for the entire cooldown period.

Three separate calculations are required to determine the limit curves for finite heatup rates. As is done in the cooldown analysis, allowable pressure-temperature relationships are developed for steady-state conditions as well as finite heatup rate conditions assuming the presence of a 1/4T defect at the inside of the wall. The heatup results in compressive stresses at the inside surface that alleviate the tensile stresses produced by internal pressure. The metal temperature at the crack tip lags the coolant temperature; therefore, the K1, for the I/4T crack during heatup is lower than the Kic for the I14T crack during steady-state conditions at the same coolant temperature. During heatup, especially at the end of the transient, conditions may exist so that the effects of compressive thermal stresses and lower K1, values do not offset each other, and the pressure-temperature curve based on steady-state conditions no longer represents a lower bound of all similar curves for finite heatup rates when the I/4T flaw is considered. Therefore, both cases have to be analyzed in order to ensure that at any coolant temperature the lower value of the allowable pressure calculated for steady-state and finite heatup rates is obtained.

The second portion of the heatup analysis concerns the calculation of the pressure-temperature limitations forthe case in wvhich a I/4T flaw located at the 1/4T location from the outside surface is assumed. Unlike the situation at the vessel inside surface, the thermal gradients established at the outside surface during heatup produce stresses which are tensile in nature and therefore tend to reinforce any pressure stresses present. These thermal stresses are dependent on both the rate of heatup and the time (or coolant temperature) along the heatup ramp. Since the thermal stresses at the outside are tensile and increase with increasing heatup rates, each heatup rate must be analyzed on an individual basis.

Following the generation of pressure-temperature curves for both the steady-state and finite heatup rate situations. the final limit curves are produced by constructing a composite curve based on a point-by-point comparison of the steady-state and finite heatup rate data. At any given temperature, the allowable pressure is taken to be the lesser of the three values taken from the curves under consideration. The use of the composite curve is necessary to set conservative heatup limitations because it is possible for conditions to exist wherein, over the course of the heatup ramp, the controlling condition switches from the inside to the outside, and the pressure limit must at all times be based on analysis of the most critical criterion.

3.3 Closure Head/Vessel Flange Requirements 10 CFR Part 50. Appendix G addresses the metal temperature of the closure head flange and vessel flange regions. This rule states that the metal temperature of the closure flange regions must exceed the material unirradiated RTNDT by at least 1207F for normal operation when the pressure exceeds 20 percent of the preservice hydrostatic test pressure (3 106 psi), which is 621 psig for the Vogtle Electric Generating Plant Unit 2. However, per WCAP- 16142, 'Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Vogtle Units I and 2[ 11,this requirement is no longer necessary when using the Fo Aloal CriteriarsueTmeaueRltosisRvso Criteria For Allowable Pressure-Temperature Relationships Revision 3

3-5 methodology of Code Case N-64011 ' ). Hence, the Vogtle Electric Generating Plant Unit 2 heatup and cooldown limit curves will be generated without flange requirements included.

Revision 3 Criteria For AlIovable Pressure-Temperaturc Relationships Allowable Pressure-Temperature Relationships Revision 3

4-1 4 CALCULATION OF ADJUSTED REFERENCE TEMPERATURE From Regulatory Guide 1.99, Revision 2, the adjusted reference temperature (ART) for each material in the beltline region is given by the following expression:

ART = Initial RTXD7 + A RTNDT + Margin (7)

Initial RTNDT is the reference temperature for the unirradiated material as defined in paragraph NB-233 1 of Section III of the ASME Boiler and Pressure Vessel Code 6 1. If measured values of initial RTNDT for the material in question are not available, generic mean values for that class of material may be used if there are sufficient test results to establish a mean and standard deviation for the class.

ARTNDT is the mean value of the adjustment in reference temperature caused by irradiation and is calculated as follows:

A RTA',n- =CF*ff0.28.o0v1o0.O (8)

To calculate ARTNDT at any depth (e.g., at 1/4T or 3/4T), the following formula must first be used to attenuate the fluence at the specific depth.

=

=f * )(9) where x inches (vessel beltline thickness is 8.625 inches131) is the depth into the vessel wall measured from the vessel clad/base metal interface. The resultant fluence is then placed in Equation 8 to calculate the ARTNDT at the specific depth.

The Westinghouse Radiation Engineering and Analysis group evaluated the vessel fluence projections and the results are presented in Section 6 of WCAP-151591 7 1. The evaluation used the ENDF/B-VI scattering cross-section data set. This is consistent with the methods presented in WCAP-14040-A.

"Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves"18 1. Tables 4-1 and 4-2, herein, contain the calculated vessel surface fluence values along with the Regulatory Guide 1.99, Revision 2, 1/4T and 3/4T calculated fluences used to calculate the ART values for all beltline materials in the Vogtle Unit 2 reactor vessel. Additionally, the calculated surveillance capsule fluence values are presented in Table 4-3.

Calculation of Adjusted Reference Temperature Revision 3

4-2 TABLE 4-1 Summary of the Peak Pressure Vessel Neutron Fluence Values at 26 EFPY used for the Calculation of ART Values (n/cm2 , E > 1.0 MeV) 3 Material Surface(b) '/4 T /4 T Interrnediate Shell Plate R4-1 1.46 x IO" 8.70 x 1018 3.09 x IO's Intermediate Shell Plate R4-2 1.46 x i0'9 8.70 x 108 3.09 xI Intermediate Shell Plate R4-3 1.46 x 10'9 8.70 x 1018 3.09 x 1018 Lowner Shell Plate B8825-1 1.46 x 10'9 8.70 x 1018 3.09 x 1018 Lowver Shell PlateB8-1 1.46 x 1O'9 8.70 x 1 3.09 x 0" Lower Shell Plate B8628-1 1.46 x 1019 8.70 x 10" 3.09 x 10"8 Interrnediate Shell Longitudinal 1.46 x 1019 8.70 x 1018 3.09 x 10's Weld Seams 101-124A, B, C(a)

Lower Shell Longitudinal 1.46 x 10'9 8.70 x I 0" 3.09 x lOts Weld Seams 101-142A, B, C(a)

Intermediateto Lower Shell Circ. 1.46x 10'9 8.70x I0'8 3.09x 1018 Weld Seam 101-171(a)

Notes:

(a) It was conservatively assumed that all the welds would see the peak vessel fluence at 300.

(b) Surface fluence values are calculated.

R fere f ce Calc laton emp ratue Adustd R vison Calculation of Adjusted Reference Temperature Revision 3

4-3 TABLE 4-2 Summary of the Peak Pressure Vessel Neutron Fluence Values at 36 EFPY used for the Calculation of ART Values (n/cm2 , E > 1.0 MeV)

Material Surface b) 1/4 T 3/4 T Intermediate Shell Plate R4-1 2.01 x 1019 1.20 x IO" 4.26 x IO's Intermediate Shell Plate R4-2 2.01 x 1019 1.20 x 1019 4.26 x 10' 8

Intermediate Shell Plate R4-3 2.01 x l0'9 1.20 x 1019 4.26 x 10l" LowerShell Plate B8825-1 2.01 x 1019 1.20x 1019 4.26x 108 Lower Shell Plate R8-1 2.01 x IO 1.20 x 10'9 4.26 x IO Lower Shell Plate B8628-1 2.01 x 1019 1.20 x lI0' 4.26 x lO's Intermediate Shell Longitudinal 2.01 x 1019 1.20 x 1O' 9 4.26 x lIO' Weld Seams 10I -124A, B, C0)

Lower Shell Longitudinal 2.01 x 1019 1.20 x 10'9 4.26 x I0O Weld Seams 101-142A, B. C(a)

Intermediate to Lower Shell Circ. 2.01 x 10'9 1.20 x lO'9 . 4.26 x 10" Weld Seam 101 -171 Notes:

(a) It was conservatively assumed that all the welds would see the peak vessel fluence at 300.

(b) Surface fluence values are calculated.

Calculation of Adjusted Reference Temperature Revision 3

4-4 TABLE 4-3 Calculated Integrated Neutron Exposure of the Vogtle Unit 2 Surveillance Capsules Tested to Date Capsule Fluencc U 3.97 x I 08 n/cm 2 , (E > 1.0 MeV)

Y 1.27 x 10'9 n/cm 2, (E > 1.0 MeV)

X 2.01 x 10'9n/cm 2, (E> 1.0MeV)

Margin is calculated as, M = 2 oa2 + a.? . The standard deviation for the initial RTNDT margin term, a,,

is 07F when the initial RTNDT is a measured value, and 17'F when a generic value is used. The standard deviation for the ARTNDT margin term, a,%, is I 7'F for plates when surveillance capsule data is not used and 8.51F for plates when surveillance capsule data is used. For welds, cS is 281F when surveillance capsule data is not used and 14'F when surveillance capsule data is used. In addition, a, need not exceed one-half the mean value of ARTNDT.

Revision 3 Reference Temperature Calculation of Adjusted Reference Temperature Revision '3

4-5 Contained in Table 4-4 is a summary of the Measured 30 ft-lb transition temperature shifts of the beltline materialst 7 l. These measured shift values were obtained using CVGRAPH, Version 4.1141, which is a hyperbolic tangent curve-fitting program.

TABLE 4-4 Measured 30 ft-lb Transition Temperature Shifts of the Beltline Materials Contained in the Surveillance Program Material Capsule Measured 30 ft-lb Transition Temperature Shift(')

Lower Shell Plate B8628-1 U 2.120 F Y 5.760 F (Longitudinal Orientation) X 29.350 F Lower Shell Plate B8628-1 U 0.OoFlb)

Y I.930 F (Transverse Orientation) X 29.720 F Surveillance Program U OOoF(h)

Weld Metal Y 18.590 F X 20.070 F U O.OOF(b)

Heat Affected Zone Y O.OoFNb)

V O.OOF(b)

Notes:

(a) Calculated using measured Charpy data and plotted using CVGRAPH141 (b) Actual values for ARTNDT are -7.14 (Plate), -17.49 (Weld), -24.05 (IIAZ Cap. U). -9.86 (HAZ Cap. Y) and -2.1 (HAZ Cap. X). This physically should not occur, therefore for conservatism a value of zero will be used.

Temperature Revision 3 Adjusted Reference Calculation of Adjusted Reference Temperature Revision 3

4-6 Table 4-5 contains a summary of the weight percent of copper, the wveight percent of nickel and the initial RTNDT of the beltline materials and vessel flanges. The weight percent values of Cu and Ni given in Table 4-5 wvere used to generate the calculated chemistry factor (CF) values based on Tables I and 2 of Regulatory Guide 1.99, Revision 2, and presented in Table 4-7. Table 4-6 provides the calculation of the CF values based on surveillance capsule data, Regulatory Guide 1.99, Revision 2, Position 2.1, which are also summarized in Table 4-7.

TABLE 4-5 Reactor Vessel Beltline Material Unirradiated Toughness Properties' 5 &9]

Material Description Cu (%) Ni(%) Initial RTNDTt '

Closure Head Flange R7-1 100 F Vessel Flange RI-i --- -600 F Intermediate Shell Plate R4-1 0.07 0.63 10F Intermediate Shell Plate R4-2 0.06 0.61 10F Intennediate Shell Plate R4-3 0.05 0.60 30 0 F Lower Shell Plate B8825-1 0.06 0.62 40 0 F Lower Shell Plate R8-1 0.07 0.63 400 F Lower Shell Plate B8628-1 0.05 0.59 500 F Intermediate Shell Longitudinal Weld 0.05 015 -10 0 F Seams 101-I 24A. B & C Lower Shell Longitudinal Weld Seams 0.05 0.15 -10T 101-142A. B & C Intermediate to Lox er Shell Plate 0.05 0.15 -30 0 F Circumferential Weld Seam 101-171 Surveillance Weldlb) 0.04 0.13 Note s:

(a) The initial RTNDT values for the plates and welds are based on measured data.

(b) The weld material in the Vogtle Unit 2 surveillance program was made of the same wire and flux as the reactor vessel intermediate to lower shell girth seam weld (101-171). These welds were fabricated using weld wire heat no. 87005, Linde 124 Flux, lot no. 1061. The intermediate shell longitudinal weld seams (101-124A,B,C) and the lower shell longitudinal weld seams (101-142A,BC) were fabricated using weld wire heat no. 87005, Linde 0091 Flux, lot no. 0145. Hence the surveillance weld is representative of all beltline welds.

Calculation of Adjusted Reference Temperature Revision 3

4-7 TABLE 4-6 Calculation of Chemistr) Factors using Vogtle Unit 2 Surveillance Capsule Data Material Capsule Capsule jo) FFb)l ARTNDT" l FF*ARTNDT FF2 Lower Shell U 0.397 0.744 2.1 1.6 0.554 Plate B8628-1 Y 1.27 1.07 5.8 6.2 1.14 (Longitudinal) X 2.01 1.19 29.4 35.0 1.42 Lower Shell U 0.397 0.744 0.0() 0 0.554 Plate B8628-1 Y 1.27 1.07 1.9 2.0 1.14 (Transverse) X 2.01 1.19 29.7 35.3 1.42 SUM: 80.1 6.228 CFXS628.1=:(FF *RTNDr) 2:( FF 2 )=(80.1) (6.228) 12.97F Surveillance Weld U 0.397 0.744 0.0(e) 0 0.554 Material Y 1.27 1.07 22 .1(1 8 .6 )"' 23.6 1.14 X 2.01 1.19 2 3 . 9 ( 2 0 .1 )Id, 28.4 1.42 SUM: 52.0 3.114 CFsLI. Bad = X;(FF

• RTNDT) * ( FF2) = (52.0) . (3.114) = 16.70 F Notes (a) f= Calculated fluence from capsule X dosimetry analysis results 17), (x 1019 n!cm 2 , E > 1.0 MeV).

(b) FF = fluence factor= pO.2 -. lorI)

(c) ARTNDT values are the measured 30 ft-lb shift values from App. B of Ref. 7, rounded to one decimal point.

(d) The surveillance weld metal ARTNDT values have been adjusted by a ratio factor of 1. 19.

(e) Actual values for ARTNDT are -7.14 (Plate) and -17.49 (Weld). This phy)sicall) should not occur, therefore for conservatism a value of zero will be used.

Calculation of Adjusted Reference Temperature Revision 3

4-8 TABLE 4-7 Summary of the Vogtle Unit 2 Reactor Vessel Beltline Material Chemistry Factors Based on Regulatory Guide 1.99, Revision 2, Position 1.1 and Position 2.1 Material Chemistn- Factor Position 1.1(') Position 2.1")

Intermediate Shell Plate R4-1 44.0F ---

Intermediate Shell Plate R4-2 37.0 0 F l ---

Intermediate Shell Plate R4-3 31.0 0 F l Lower Shell Plate B8825-1 37.0F ---

Lower Shell Plate R8-1 44.0 0 F1 Lower Shell Plate B8628-1 31.0 0F 12.9 0 F Intermediate Shell Longitudinal Welds, 43.3 0 F 16.7 01-101-124A, B & C Lower Shell Longitudinal Welds 43.3 0 F 16.7 0 F 101-142A, B & C Circumferential Weld 101-171 43.3 0 F 16.701 Surveillance Program Weld Metal 36.4`F Notes:

(a) Regulatory Guide 1;99, Revision 2, Position 1. I or Position 2.1 mnethodology.

Revision 3 Reference Temperature Calculation of Adjusted Reference Temperature Revision 3

4-9 Contained in Tables 4-8 and 4-9 are summaries of the fluence factors (FF) used in the calculation of adjusted reference temperatures for the Vogtle Electric Generating Plant Unit 2 reactor vessel beltline materials for 26 EFPY and 36 EFPY.

TABLE 4-8 Summary of the Calculated Fluence Factors used for the Generation of the 26 EFPY Heatup and Cooldown Curves Material %T r 1/4 T FF(2) 3

/4T f 3 4 T FFb) 2 2 (n/cm , E > 1.0 (n/cm , E >1.0 Mel')

__NW MeV)

Intennediate Shell Plate R4-1 8.70 x 1018 0.961 3.09 x IO'8 0.678 Intermediate Shell Plate R4-2 8.70 x IO" 0.961 3.09 x I0"' 0.678 Intermediate Shell Plate R4-3 8.70 x I0" 0.961 3.09 x 1O18 0.678 Lower Shell Plate B8825-1 8.70 x 1O08 0.961 3.09 x 1018 0.678 Lower Shell PlateB8-1 8.70 x 1018 0.961 3.09 x 1I0 0.678 Lower Shell Plate B8628-1 8.70 x 1018 0.961 3.09 x 1018 0.678 Intermediate Shell Longitudinal 8.o x 1O,8 0.961 3.09 x l0' 0.678 Weld Seams 101-124A, B, C Lower Shell Longitudinal 8.70 x 1018 0.961 3.09 x 108 0.678 Weld Seams 101-142A, B, C Intermediate to Lower Shell 8.70 x I0O" 0.961 3.09 x lI0' 0.678 Circ.

Weld Seam 101-171 Notes:

(a) Fluence Factor at the 1/4T vessel thickness location.

(b) Fluence Factor at the 3/4T vessel thickness location.

empratue f Adustd Rferece Calclaton Rvison Calculation of Adjusted Reference Temperature Revision;3

4-10 TABLE 4-9 Summary of the Calculated Fluence Factors used for the Generation of the 36 EFPY Heatup and Cooldown Curves Material %T r %T FF"'I %Tf 3/ T FFb 2 2 (n/cm , E > 1.0 (n/cm , E > 1.0 nr i S la) x.2e6x)

Intermediate Shell Plate R4-1 1.20 x l 09 1.051 4.26 x IO"S 0.763 Intermediate Shell Plate R4-2 1.20 x 1019 1.051 4.26 x 11O8 0.763 oIntermediate Shell Plate R4-3 1.20 x 10'9 1.051 4.26 x I 0" 0.763 Lower Shell Plate B8825-1 1.20 x 10O9 1.051 4.26 x I0' 8 0.763 Lower Shell Plate R8-1 1.20 x i '9 1.051 4.26 x 10"' 0.763 l Lowver Sllell Plate B8628-1 1.20 x 1O'9 1.051 4.26 x 10"8 0.763 Intermediate Shell Longitudinal 1.20 x 1019 1.051 4.26 x 1018 0.763 Weld Seams 101- 124A, B, C Lower Shell Longitudinal 1.20 x 10'9 1.051 4.26 x 1018 0.763 Weld Seams 101-142A. B, C Intermediate to Lower Shell 1.20 x l0'9 1.051 4.26 x Il0 0.763 Circ. Weld Seam 101 - 171 Notes:

(a) Fluence Factor at the 1/4T vessel thickness location.

(b) Fluence Factor at the 3/4T vessel thickness location.

Calculation of Adjusted Reference Temperature Revision 3

4-1l Contained in Tables 4-10 through 4-13 are the calculations of the ART values used for the generation of the 26 EFPY and 36 EFPY heatup and cooldown curves.

TABLE 4-10 Calculation of the ART Values for the 1/4T Location @ 26 EFPY Material RG 1.99 R2 CF FF IRTNDT" ) ARTNDT4 1 Margin ART(b)

Method (OF)

Intermediate Shell Plate R4-1 Position 1.1 44.0 0.961 10 42.3 34 86 Intermediate Shell Plate R4-2 Position 1.1 37.0 0.961 10 35.6 34 80 Intermediate Shell Plate R4-3 Position 1.1 31.0 0.961 30 29.8 29.8 90 Lower Shell Plate B8825-1 Position 1.1 37.0 0.961 40 35.6 34 110 Lower Shell Plate 18-1 Position 1.1 44.0 0.961 40 42.3 34 116 Lower Shell Plate B8628-1 Position 1.1 31.0 0.961 50 29.8 29.8 110 Position 2.1 12.9 0.961 50 12.4 12.4 75 Intermediate Shell Longitudinal Position 1.1 43.3 0.961 -10 41.6 41.6 73 Weld Seams 101-124A, B, C Position 2.1 16.7 0.961 -10 16.0 16.0 22 Lower Shell Longitudinal Position 1.1 43.3 0.961 -10 41.6 41.6 73 Weld Seams 101-142A, B, C Position 2.1 16.7 0.961 -10 16.0 16.0 22 Intermediate to Lower Shell Position 1.1 43.3 0.961 -30 41.6 41.6 53 Circ. Weld Seam 101-171 Position 2.1 16.7 0.961 -30 16.0 16.0 Notes:

(a) Initial RTNDT values are measured values (see Table 4-5).

(b) ART = Initial RTNDT + ARTNDT + Margin (IF); (Rounded per ASTM E29, using the "Rounding Method")

(c) ARTNDT = CF

• FF Revision 3 Calculation of Reference Temperature Adjusted Reference of Adjusted Temperature Revision 3

4-12 TABLE 4-11 Calculation of the ART Values for the 3/4T Location @ 26 EFPY Material RG 1.99 R2 CF FF IRTNTz'a ARTNDT(C) Margin ART"b' Method ('F)

Intermediate Shell Plate R4-1 Position 1.1 44.0 0.678 10 29.8 29.8 70 Intermediate Shell Plate R4-2 Position 1.1 37.0 0.678 10 25.1 25.1 60 Intermediate Shell Plate R4-3 Position 1.1 31.0 0.678 30 21.0 21.0 72 Lower Shell Plate B8825-1 Position 1.1 37.0 0.678 40 25.1 25.1 90 Lowver Shell Plate R8-1 Position 1.1 44.0 0.678 40 29.8 29.8 100 Lower Shell Plate B8628-1 Position 1.1 31.0 0.678 50 21.0 21.0 92 Position 2.1 12.9 0.678 50 8.7 8.7 67 Intermediate Shell Longitudinal Position 1.1 43.3 0.678 -10 29.4 29.4 49 Weld Seams 101- 124A, B, C Position 2.1 16.7 0.678 -10 11.3 11.3 13 Lower Shell Longitudinal Position 1.1 43.3 0.678 -10 29.4 29.4 49 Weld Seams 101-142A, B, C Position 2.1 16.7 0.678 -10 11.3 11.3 13 Intermediate to Lower Shell Position 1.1 43.3 0.678 -30 29.4 29.4 29 Circ. Weld Seam 101-171 Position 2.1 16.7 0.678 -30 11.3 11.3 -7 Notes:

(a) Initial RTNDT values are measured values (see Table 4-5).

(b) ART = Initial RTNDT + ARTNDT + Margin (F) ; (Rounded per ASTM E29, using the "Rounding Method")

(c) ARTNDT = CF

• FF Calculation of Adjusted Reference Temperature t oRevision 3

4-13 TABLE 4-12 Calculation of the ART Values for the 1/4T Location @ 36 EFPY Material RG 1.99 R2 CF FF IRTNDTz ' ARTNDT( ) Margin ART b)

Method (°F)

Intermediate Shell Plate R4-1 Position 1.1 44.0 1.051 10 46.2 34 90 Intermediate Shell Plate R4-2 Position 1.1 37.0 1.051 10 38.9 34 83 Intenmediate Shell Plate R4-3 Position 1.1 31.0 1.051 30 32.6 32.6 95 Lower Shell Plate B8825-1 Position 1.1 37.0 1.051 40 38.9 34 113 Lower Shell Plate R18- I Position 1.1 44.0 1.051 40 46.2 34 120 Lower Shell Plate B8628-1 Position 1.1 31.0 1.051 50 32.6 32.6 115 Position 2.1 12.9 1.051 50 13.6 13.6 77 Intennediate Shell Longitudinal Position 1.1 43.3 1.051 -10 45.5 45.5 81 Weld Seams 101-124A, B. C Position 2.1 16.7 1.051 -10 17.6 17.6 25 Lower Shell Longitudinal Position 1.1 43.3 1.051 -10 45.5 45.5 81 Weld Seams 101-142A B, C Position 2.1 16.7 1.051 -10 17.6 17.6 25 Intermediate to Lower Shell Position 1.1 43.3 1.051 -30 45.5 45.5 61 Circ. Weld Seam 101 - 171 Position 2.1 16.7 1.051 -30 17.6 17.6 5 Notes:

(a) Initial RTNDT values are measured values (see Table 4-5).

(b) ART = Initial RTNDT + ARTNDT + Margin (fF); (Rounded per ASTM E29, using the "Rounding, Method")

(c) ARTNDT= CF

• FF Revision 3 Calculation of of Adjusted Reference Temperature Adjusted Reference Temperature Revision 3

4-14 TABLE 4-13 Calculation of the ART Values for the 314T Location @ 36 EFPY Material RG 1.99 R2 CF FF IRTNDTP') ARTNDT(C) Margin ART'b)

Method (OF)

Intermediate Shell Plate R4-1 Position 1.1 44.0 0.763 10 33.6 33.6 77 Intennediate Shell Plate R4-2 Position 1.1 37.0 0.763 10 28.2 28.2 66 Intermediate Shell Plate R4-3 Position 1.1 31.0 0.763 30 23.7 23.7 77 Lower Shell Plate B8825-1 Position 1.1 37.0 0.763 40 28.2 28.2 96 Lower Shell Plate R8-1 Position 1.1 44.0 0.763 40 33.6 33.6 107 Lower Shell Plate B8628-1 Position 1.1 31.0 0.763 50 23.7 23.7 97 Position 2.1 12.9 0.763 50 9.8 9.8 70 Intenmediate Shell Longitudinal Position 1.1 43.3 0.763 -10 33.0 33.0 56 Weld Seams 101-124A, B. C Position 2.1 16.7 0.763 -10 12.7 12.7 15 Lower Shell Longitudinal Position 1.1 43.3 0.763 -10 33.0 33.0 56 Weld Seams 101 -142A, B, C Position 2.1 16.7 0.763 -10 12.7 12.7 IS Intenmediate to Lower Shell Position 1.1 43.3 0.763 -30 33.0 33.0 36 Circ. Weld Seam 101-171 Position 2.1 16.7 0.763 -30 12.7 12.7 .5 Notes:

(a) Initial RTNDT values are measured values (see Table 4-5).

(b) ART = Initial RTNDT + ARTNDT + Margin (IF); (Rounded per ASTM E29. using the "Rounding Method")

(c) ARTNDT = CF

• FF Calculation of Adjusted Reference Temperature Revision 3

4-15 The Lower Shell Plate R8-1 is the limiting beltline material for all heatup and cooldown curnes to be generated. Contained in Table 4-14 is a summary of the limiting ARTs to be used in the generation of the Vogtle Electric Generating Plant Unit 2 reactor vessel lieatup and cooldown curves.

TABLE 4-14 Summary of the Limiting ART Values Used in the Generation of the Vogule Unit 2 Heatup/Cooldown Curves EFPY 1/4T Limiting ART 3/4T Limiting ART 26 116 0 F lOOTF I3 36120°F 107°F Revision 3 Adjusted Reference Calculation of Adjusted Temperature Reference Temperature Revision 3

5-I 5 HEATUP AND COOLDOWN PRESSURE-TEMPERATURE LIMIT CURVES Pressure-temperature limit curves for normal heatup and cooldown of tile primary reactor coolant system have been calculated for the pressure and temperature in the reactor vessel beltline region using the methods discussed in Section 3 and 4 of this report. This approved methodology is also presented in WCAP-1 4040-A18 1 .

Figures 5-1 and 5-3 present the heatup curves with no margins for possible instrumentation errors for heatup rates of 60 and 100 0 F/hr. These curves are applicable for 26 EFPY and 36 EFPY respectively. for the Vogtle Unit 2 reactor vessel. Additionally, Figures 5-2 and 5-4 present the cooldown curves with no margins for possible instrumentation errors for cooldown rates of 0, 20, 40. 60, and I 000 F/hr. These curves are also applicable for 26 EFPY and 36 EFPY, respectively3 for the Vogtle Electric Generating Plant Unit 2 reactor vessel. Allowable combinations of temperature and pressure for specific temperature change rates are below and to the right of the limit lines shown in Figures 5-1 through 5-4.

This is in addition to other criteria which must be met before the reactor is made critical, as discussed in the following paragraphs. O The reactor must not be made critical until pressure-temperature combinations are to the right of the criticality limit line shown in Figures 5-1 and 5-3 (for the specific heatup rate being utilized). The straight-line portion of the criticality limit is at the minimum permissible temperature for the 2485 psig inservice hydrostatic test as required by Appendix G to 10 CFR Part 50. The governing equation for the hydrostatic test is defined in Appendix G to Section Xl of the ASME CodePI 3 as follows:

1.5K; i. < K. (10)

where, Kim is the stress intensity factor covered by membrane (pressure) stress, K1 ,= 33.2 + 20.734e 10 02 (T -RTNDT)]

T is the minimum permissible metal temperature, and RTNDT is the metal reference nil-ductility temperature The criticality limit curve specifies pressure-temperature limits for core operation to provide additional margin during actual power production as specified in Reference 2. The pressure-temperature limits for core operation (except for low power physics tests) are that the reactor vessel must be at a temperature equal to or higher than the minimum temperature required for the inservice hydrostatic test. and at least 40'F higher than the minimum permissible temperature in the corresponding pressure-temperature curve for heatup and cooldown calculated as described in Section 3 of this report. The vertical line drawn from these points on the pressure-temperature curve, intersecting a curve 40'F higher than the pressure-temperature limit curve, constitutes the limit for core operation for the reactor vessel.

Revision 3 Heatup and Cooldown Pressure Ileatup Limit Curves Temperature Limit Pressure Temperature Curves Revision 3

5-2 Figures 5-1 through 5-4 define all of the above limits for ensuring prevention of nonductile failure for the Vogtle Electric Generating Plant Unit 2 reactor vessel. The data points for tile heatup and cooldown pressure-temperature limit curves shown in Figures 5-1 through 5-4 are presented in Tables 5-1 through 5-4, respectively.

Revision 3 Heatup and Cooldo Pressure Temperature CooldownNm Pressure Limit Curves Temperature Limit Curves  ; Revision 3

• 5-3 MATERIAL PROPERTY BASIS LIMITING MATERIAL: LOWER SHELL PLATE R8-1 LIMITING ART VALUES AT 26 EFPY: I /4T, 116F 3/4T, 1000 F 2500 2250 2000 1750 XL 1500 2! 1250 0.

I-0, U

750 500 250 0

0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)

FIGURE 5-1 Vogtle Unit 2 Reactor Coolant System -Heatup Limitations (Heatup Rates of 60 and 100 0F/hr) Applicable to 26 EFPY (Without Margins of for Instrumentation Errors)

Limit Curves Revision 3 Pressure Temperature Heatup and Cooldown Pressure Temperature Limit Curves Revision 3

5-4 MATERIAL PROPERTY BASIS LIMITING MATERIAL: LOWER SHELL PLATE R8-1 LIMITING ART VALUES AT 26 EFPY: 1/4T, 11 60 F 3/4T, 100 0 F 2500 2250 2000 1750 CL 1500 01 2!

in 1250 IL i 1000 U

M.

750 500 250 0

0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)

FIGURE 5-2 Vogtle Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates of 0, 20, 40, 60 and 1007F/hr) Applicable to 26 EFPY (Without Margins for Instrumentation Errors)

Revision 3 Hentup and Cooldown 1-leatup Pressure Temperature Cooldo~vn Pressure Limit Curves Temperature Limit Curves Revision 3

5-5 TABLE 5-1 Vogtle Unit 2 Heatup Data at 26 EFPY Without Margins for Instrumentation Errors 60°Flhr Ileatup 60OF/hr Criticality 100 0F/hr Hleatup 1000F/hr Critical. Leak Test Limit Limit T Limit T P T P T P I-T P T r 60 0 176 0 60 0 176 0 159 2000 60 731 176 744 60 709 176 709 176 2485 65 740 176 749 65 709 176 709 70 740 176 742 70 709 176 709 75 740 176 740 75 709 176 709 80 740 176 743 80 709 176 709 85 743 176 749 85 709 176 709 90 749 176 758 90 709 176 709 95 758 176 771 95 709 176 711 100 771 176 787 100 711 176 715 105 787 176 806 105 715 176 722 110 806 176 829 110 722 176 732 115 829 176 855 115 732 176 745 120 855 176 885 120 745 176 760 125 885 176 919 125 760 176 779 130 919 176 957 130 779 176 801 135 957 180 1000 135 801 180 826 140 1000 185 1048 140 826 185 854 145 1048 190 1101 145 854 190 887 150 1101 195 1159 150 887 195 923 155 1159 200 1224 155 923 200 964 160 1224 205 1297 160 964 205 1010 165 1297 210 1376 165 1010 210 1062 170 1376 215 1465 170 1062 215 1119 175 1465 220 1562 175 1119 220 1182 180 1562 225 1670 180 1182 225 1252 185 1670 230 1789 185 1252 230 1330 190 1789 235 1921 190 1330 235 1417 195 1921 240 2066 195 1417 240 1512 200 2066 245 2226 200 1512 245 1617 205 2226 250 2403 205 1617 250 1734 210 2403 210 1734 255 1862 215 1862 260 2004 220 2004 265 2161 225 2161 270 2333 230 2333 &

Heatup and Cooldown Pressure Temperature Limit Curves Revision 3

5-6 TABLE 5-2 Vogtle Unit 2 Cooldown Data at 26 EFPY Without Margins for Instrumentation Errors Steady State 2 0 1F/hr 401F/hr 60'F/hr 100°F/hr T P T P T P T P T P 60 0 60 0 60 0 60 0 60 0 60 731 60 691 60 651 60 612 60 533 65 744 65 705 65 667 65 628 65 554 70 759 70 721 70 684 70 647 70 576 75 775 75 738 75 703 75 668 75 602 80 792 80 757 80 724 80 691 80 630 85 812 85 779 85 747 85 716 85 661 90 833 90 802 90 773 90 745 90 696 95 857 95 828 95 801 95 776 95 734 100 883 100 857 100 833 100 811 100 777 105 912 105 889 105 868 105 850 105 825 110 944 110 924 110 906 110 892 110 877 115 979 115 963 115 949 115 940 115 936 120 1018 120 1006 120 997 120 992 125 1062 125 1053 125 1049 130 1109 130 1106 135 1162 140 1221 145 1285 150 1356 155 1435 160 1522 165 1618 170 1725 175 1842 180 1972 185 2116 190 2274 195 2449 Revision 3 and Cooldown Heatup and Pressure Temperature Cooldowvn Pressure Limit Curves Temperature Limit Curves Revision 3

5-7 MATERIAL PROPERTY BASIS LIMITING MATERIAL: LOWER SHELL PLATE R8-1 LIMITING ART VALUES AT 36 EFPY: 1/4T, 120WF 3/4T, 107-F 2500 2250 2000 1750 1500 1250 If I5 n 1000 60 750 500 250 0

0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)

FIGURE 5-3 Vogtle Unit 2 Reactor Coolant System Heatup Limitations (Heatup Rate of 60 and 100IF/hr) Applicable to 36 EFPY (Without Margins of for Instrumentation Errors)

Revision 3 1-leatup and Cooldown Heatup Pressure Temperature Cooldowtn Pressure Limit Curves Temperature Limit Curves Revision;3

5-8 MATERIAL PROPERTY BASIS LIMITING MATERIAL: LOWER SHELL PLATE R8-1 LIMITING ART VALUES AT 36 EFPY: I /4T, I 20 0 F 3/4T, 1070 F 2500 2250 2000 1750 R 1500 g 1250 0 1000 750 500 250 0

0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)

FIGURE 5-4 Vogtle Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates of 0, 20, 40, 60 and 1000 F/hr) Applicable to 36 EFPY (Without Margins for Instrumentation Errors)

Revision 3 Heatup and Cooldown Hcatup Pressure Temperature Cooldo'vn Pressure Limit Cunes Temperature Limit Curves Revision 3

5-9 TABLE 5-3 Vogtle Unit 2 Heatup Data at 36 EFPY Without Margins for Instrumentation Errors 601Fh Ietp 0 rLim it y 100 0 F/hr Ileatup 100 0 F/hr Critical. Leak Test Limit Limit I Limit t o p T fAMA * - T r T P 6U U 1o 0 60 0 180 0 163 2000 60 717 180 734 60 684 180 684 180 2485 65 717 180 727 65 684 180 684 70 717 180 720 70 684 180 684 75 717 180 717 75 684 180 684 80 717 180 717 80 684 180 684 85 717 180 721 85 684 180 684 90 721 180 729 90 684 180 684 95 729 180 739 95 684 180 684 100 739 180 753 100 684 180 686 105 753 180 769 105 686 180 691 110 769 180 788 110 691 180 699 115 788 180 811 115 699 180 709 120 811 180 837 120 709 180 722 125 837 180 866 125 722 180 737 130 866 180 *899 130 737 180 756 135 899 180 936 135 756 180 777 140 936 185 977 140 777 185 801 145 977 190 1023 145 801 190 829 150 1023 195 1074 150 829 195 860 155 1074 200 1130 155 860 200 896 160 1130 205 1193 160 896 205 935 165 1193 210 1262 165 935 210 979 170 1262 215 1339 170 979 215 1029 175 1339 220 1424 175 1029 220 1084 180 1424 225 1517 180 1084 225 1144 185 1517 230 1621 185 1144 230 1212 190 1621 235 1735 190 1212 235 1287 195 1735 240 1861 195 1287 240 1369 200 1861 245 2000 200 1369 245 1461 205 2000 250 2154 205 1461 250 1562 210 2154 255 2324 210 1562 255 1673 215 2324 215 1673 260 1796 220 1796 265 1932 225 1932 270 2082 230 2082 275 2248 235 2248 280 2430 240 2430 J. L

.1.

Revision 3 Temperature Limit Curves Heatup Heatup and Pressure Temperature Cooldown Pressure and Cooldown Limit Curves Revision 3

5-10 TABLE 54 Vogdle Unit 2 Cooldown Data at 36 EFPY Without Margins for Instrumentation Errors Steady State 2 0 1F/hr 401F/hr 60 'F/hr 100IF/hr T P T P T P T P T P 60 0 60 0 60 0 60 0 60 0 60 722 60 681 60 640 60 599 60 518 65 734 65 694 65 654 65 614 65 , 537 70 747 70 708 70 670 70 632 70 557 75 762 75 724 75 687 75 651 75 581 80 778 80 742 80 706 80 672 80 606 85 796 85 761 85 728 85 695 85 635 90 816 90 783 90 752 90 721 90 667 95 838 95 807 95 778 95 750 95 703 100 862 100 833 100 807 100 782 100 742 105 889 105 863 105 839 105 818 105 786 110 918 110 895 110 875 110 858 110 834 115 951 115 931 115 914 115 901 115 888 120 987 120 971 120 958 120 950 120 948 125 1027 125 1015 125 1007 125 1003 125 1003 130 1071 130 1063 130 1060 130 1060 135 1120 135 1117 140 1173 145 1233 150 1299 155 1371 160 1452 165 1541 170 1639 175 1747 180 1867 185 2000 190 2146 195 2308 Heatup and Cooldown Pressure Temperature Limit Curves Revision 3

6-1 6 REFERENCES 1 Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials", U.S.

Nuclear Regulatory Commission, May, 1988.

2 10 CFR Part 50, Appendix G."Fracture Toughness Requirements", Federal Register, Volume 60, No. 243, dated December 19, 1995.

3 Section XI of the ASME Boiler and Pressure Vessel Code, Appendix G."Fracture Toughness Criteria for Protection Against Failure.", Dated December 1995.

4 CVGRAPH, Hyperbolic Tangent Curve-Fitting Program, Version 4.1, developed by ATI Consulting, March 1996.

5 WCAP-14533, "Vogtle Electric Generating Plant (VEGP) Unit 2 Heatup and Cooladown Limit Curves for Normal Operation", P.A. Grendys, February 1996.

6 1989 Section III, Division 1 of the ASME Boiler and Pressure Vessel Code, Paragraph NB-2331, "Material for Vessels".

7 WCAP-15159, "Analysis of Capsule X from the Southern Nuclear Vogtle Electric Generating Plant Unit 2 Reactor Vessel Radiation Surveillance Program", T. J. Laubham, et al., January 1999.

8 WCAP-14040-A, Revision 4, "Methodology used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves", J. D. Andrachek, et al., XXXX 2003.

9 CE NPSD-1039, Rev. 2, "Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds, Appendix A, CE Reactor Vessel Weld Properties Database, Volume 1," CEOG Task 902, June 1997.

10 ASME Code Case N-640, "Alternative Reference Fracture Toughness for Development of P-T Limit Curves for Section XI, Division 1", February 26, 1999.

11 WCAP-16142, "Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation For Vogtle Units 1and 2", Revision 1, W. Bamford, et.al., February 2004.

Revision 3 References References Revision 3

A-]

APPENDIX A Thermal Stress Intensity Factors (K1 t)

The following page contain the thermal stress intensity factors (Kb,) for the maximum heatup and cooldown rates at 26 and 36 EFPY. The vessel radius to the 4T and 3/4T locations are as follows:

• 1/4TRadius= 88.812"

• 3/4T Radius = 93.125" Revision 3

A-2 TABLE Al Ki, Values for 100°F/hrHeatup Curve (26 EFPY)

Vessel Temperature 1/4T Thermal Vessel Temperature 3/4T Thermal Water @ 1/4T Location for Stress @ 3/4T Location for Stress Temp. 1001F/hr Heatup Intensity Factor 100 0 F/hr Heatup Intensity Factor (OF) I ( 0 F) (KSI SQ. RT. IN.) (OF) (KSI SQ. RT. IN.)

60 55.99 -0.9954 55.04 0.4731 65 58.56 -2.4522 55.29 1.4378 70 61.62 -3.7125 55.96 2.4257 75 64.90 -4.9101 57.10 3.3563 80 68.45 -5.9455 58.65 4.1903 85 72.11 -6.8918 60.59 4.9375 90 75.95 -7.7139 62.86 5.5992 95 79.90 -8.4650 65.44 6.1920 100 83.97 -9.1227 68.28 6.7187 105 88.13 -9.7209 71.36 7.1893 110 92.39 -10.2475 74.64 7.6093 115 96.72 -10.7283 78.10 7.9875 120 101.12 -11.1541 81.71 8.3272 125 105.58 -11.5441 85.47 8.6336 130 110.09 -11.8911 89.36 8.9098 135 114.65 -12.2102 93.35 9.1601 140 119.25 -12.4955 97.44 9.3868 145 123.89 -12.7594 101.61 9.5932 150 128.56 -12.9966 105.86 9.7812 155 133.26 -13.2173 110.18 9.9534 160 137.98 -13.4168 114.56 10.1112 165 142.73 -13.6038 118.98 10.2566 170 147.50 -13.7740 123.46 10.3908 175 152.28 -13.9346 127.97 10.5153 180 157.08 -14.0817 132.52 10.6310 185 161.89 -14.2217 137.10 10.7391 190 166.71 -14.3508 141.71 10.8404 195 171.55 -14.4746 146.35 10.9357 200 176.39 -14.5897 151.01 11.0256 205 181.25 -14.7007 155.68 11.1109 210 186.11 -14.8048 160.38 11.1919

.1 .1 I.

• Note: The 100 0 F/hr Heatup Curve is limited entirely by the 3/4T Location Revision 3

A-3 TABLE A2 K11 Values for 1000 F/hr Cooldown Curve (26 EFPY)

Vessel Temperature 100 0 F/hr Cooldown Water @ 1/4T Location for 1/4T Thermal Stress

.0 Temp. 100°F/hr Cooldown Intensity Factor (OF) (OF) (KSI SQ. RT. IN.)

195 221.79 16.9334 190 216.70 16.8646 185 211.61 16.7952 180 206.53 16.7262 175 201.44 16.6565 170 196.35 16.5873 165 191.27 16.5176 160 186.18 16.4483 155 181.09 16.3786 150 176.00 16.3093 145 170.92 16.2396 140 165.83 16.1704 135 160.74 16.1008 130 155.65 16.0317 125 150.56 15.9623 120 145.48 15.8933 115 140.39 15.8240 110 135.30 15.7553 105 130.22 15.6862 100 125.13 15.6177 95 120.04 15.5488 90 114.95 15.4805 85 109.87 15A120 80 104.78 15.3439 75 99.69 15.2756 70 94.61 15.2078 65 89.52 15.1398 60 84.44 15.0715 I.

Revision 3

A-4 TABLE A3 K,, Values for 100 0F/hr Heatup Curve (36 FIPY)

Vessel Temperature 1/4T Thermal Vessel Temperature 314T Thermal Water @ 1/4T Location for Stress @ 3/4T Location for Stress Temp. 1000 F/hr Heatup Intensity Factor 100°F/hr Heatup Intensity Factor (0 F) (OF) (KSI SQ. RT. IN.) (OF) (KSI SQ. RT. IN.)

60 55.99 -0.9954 55.04 0.4731 65 58.56 -2.4522 55.29 1.4378 70 61.62 -3.7125 55.96 2.4257 75 64.90 -4.9101 57.10 3.3563 80 68'.45 -5.9455 58.65 4.1903 85 72.11 -6.8918 60.59 4.9375 90 75.95 -7.7139 62.86 5.5992 95 79.90 -8.4650 65.44 6.1920 100 83.97 -9.1227 68.28 6.7187 105 88.13 -9.7209 71.36 7.1893 110 92.39 -10.2475 74.64 7.6093 115 96.72 -10.7283 78.10 7.9875 120 101.12 -11.1541 81.71 8.3272 125 105.58 -11.5441 85.47 8.6336 130 110.09 -11.8911 89.36 8.9098 135 114.65 -12.2102 93.35 9.1601 140 119.25 -12A955 97.44 9.3868 145 123.89 -12.7594 101.61 9.5932 150 128.56 -12.9966 105.86 9.7812 155 133.26 -13.2173 110.18 9.9534 160 137.98 -13.4168 114.56 10.1112 165 142.73 -13.6038 118.98 10.2566 170 147.50 -13.7740 123.46 10.3908 175 152.28 -13.9346 127.97 10.5153 180 157.08 -14.0817 132.52 10.6310 185 161.89 -14.2217 137.10 10.7391 190 166.71 -14.3508 141.71 10.8404 195 171.55 -14.4746 146.35 10.9357 200 176.39 -14.5897 151.01 11.0256 205 181.25 -14.7007 155.68 11.1109 210 186.11 -14.8048 160.38 11.1919 215 190.97 -14.9059 165.09 11.26.93 Note: The 100F/hr Heatup Curve is limited entirely by the 314T Location Revision 3

A-5 TABLE A4 K1 t Values for 1001F/hr Cooldown Curve (36 EFPY)

Vessel Temperature 1000 F/hr Cooldown Water @ 114T Location for 114T Thermal Stress Temp. 100°F/hr Cooldown Intensity Factor (0 F) (0 F) (KSI SQ. RT. IN.)

195 221.79 16.9334 190 216.70 16.8646 185 211.61 16.7952 180 206.53 16.7262 175 201.44 16.6565 170 196.35 16.5873 165 191.27 16.5176 160 186.18 16.4483 155 181.09 16.3786 150 176.00 16.3093 145 170.92 16.2396 140 165.83 16.1704 135 160.74 16.1008 130 155.65 16.0317 125 150.56 15.9623 120 145.48 15.8933 115 140.39 15.8240 110 135.30 15.7553 105 130.22 15.6862 100 125.13 15.6177 95 120.04 15.5488 90 114.95 15.4805 85 109.87 15A4120 80 104.78 15.3439 75 99.69 15.2756 70 94.61 15.2078 65 89.52 15.1398 60 84.44 15.0715 Revision 3