ML051790035
| ML051790035 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/31/2004 |
| From: | Burton C Westinghouse |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WCAP-16305-NP, Rev 0 | |
| Download: ML051790035 (44) | |
Text
Westinghouse Non-Proprietary Class 3 WCAP-1 6305-NP Revision 0 August 2004 V. C. Summer Heatup and Cooldown Limit Curves for Normal Operation Westinghouse
WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-16305-NP Revision 0 V. C. Summer Heatup and Cooldown Limit Curves for Normal Operation C. M. Burton AUGUST 2004 Approved:
Zff/
Ad CA n Ghergurovichqnager reactor Component esign & Analysis Westinghouse Electric Company LLC Energy Systems P. 0. Box 355 Pittsburgh, PA 15230-0355
©2004 Westinghouse Electric Company LLC All Rights Reserved
WCAP-1 6305-NP ii PREFACE This report has been technically reviewed and verified by:
T. J. Laubham RECORD OF REVISION Revision 0:
Original Issue
WCAP-1 6305-NP fii TABLE OF CONTENTS LIST OF TABLES..........................................
iv LIST OF FIGURES...........................................
vi EXECUTIVE
SUMMARY
vii
- 1.
INTRODUCTION & PURPOSE.1
- 2.
FRACTURE TOUGHNESS PROPERTIES
.2
- 3.
CRITERIA FOR ALLOWABLE PRESSURE-TEMPERATURE RELATIONSHIPS
.7
- 4.
CALCULATION OF ADJUSTED REFERENCE TEMPERATURE
.12
- 5.
HEATUP AND COOLDOWN PRESSURE-TEMPERATURE LIMIT CURVES.20
- 6.
REFERENCES.30 APPENDIX A: THERMAL STRESS INTENSITY FACTORS 31
WCAP-16305-NP iv WCAP-1 6305-NP iv LIST OF TABLES Table I Summary of the Best Estimate Cu and Ni Weight Percent and Initial RTNDT Values for the V. C. Summer Reactor Vessel Materials............................................. 3 Table 2 Calculated Integrated Neutron Exposure of the Surveillance Capsules @ V. C.
Summer............................................................
4 Table 3 Calculation of Chemistry Factors using V. C. Summer Surveillance Capsule Data.... 5 Table 4 Summary of the V. C. Summer Reactor Vessel Beltline Material Chemistry Factors............................................................
6 Table 5 Summary of the Peak Pressure Vessel Neutron Fluence Values at the Clad/Base Metal Interface (n/cm 2, E > 1.0 MeV)...........................................................
13 Table 6 Summary of the Vessel Surface, 1/4T and 3/4T Fluence Values used for the Generation of the 32 EFPY Heatup/Cooldown Curves............................................ 13 Table 7 Summary of the Vessel Surface, 1/4T and 3/4T Fluence Values used for the Generation of the 56 EFPY Heatup/Cooldown Curves............................................ 14 Table 8 Calculation of the 1/4T and 3/4T Fluence Factor Values used for the Generation of the 32 EFPY Heatup/Cooldown Curves...........................................................
14 Table 9 Calculation of the 1/4T and 3/4T Fluence Factor Values used for the Generation of the 56 EFPY Heatup/Cooldown Curves............................................................
15 Table 10 Calculation of the ART Values for the 1/4T Location @ 32 EFPY............................ 16 Table 11 Calculation of the ART Values for the 3/4T Location @ 32 EFPY............................ 17 Table 12 Calculation of the ART Values for the 1/4T Location @ 56 EFPY............................ 18 Table 13 Calculation of the ART Values for the 3/4T Location @ 56 EFPY............................ 19 Table 14 Summary of the Limiting ART Values Used in the Generation of the V. C.
Summer Heatup/Cooldown Curves...........................................................
19 Table 15 32 EFPY Heatup Curve Data Points Using 1998 Appendix G Methodology (without Uncertainties for Instrumentation Errors).26 Table 16 32 EFPY Cooldown Curve Data Points Using 1998 Appendix G Methodology (without Uncertainties for Instrumentation Errors).27
WCAP-1 6305-NP v
LIST OF TABLES (Continued)
Table 17 56 EFPY Heatup Curve Data Points Using 1998 Appendix G Methodology (without Uncertainties for Instrumentation Errors).................................. 28 Table 18 56 EFPY Cooldown Curve Data Points Using 1998 Appendix G Methodology (without Uncertainties for Instrumentation Errors).................................. 29
WCAP-1 6305-NP vi WCAP-1 6305-NP vi LIST OF FIGURES Figure 1 V. C. Summer Reactor Coolant System Heatup Limitations (Heatup Rates of 50 and 1 00F/hr) Applicable for 32 EFPY (Without Margins for Instrumentation Errors) Using 1998 Appendix G Methodology.......................................................... 22 Figure 2 V. C. Summer Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 1 OO 0 F/hr) Applicable for 32 EFPY (Without Margins for Instrumentation Errors) Using 1998 Appendix G Methodology.......................................................... 23 Figure 3 V. C. Summer Reactor Coolant System Heatup Limitations (Heatup Rates of 50 and 1000F/hr) Applicable for 56 EFPY (Without Margins for Instrumentation Errors) Using 1998 Appendix G Methodology.......................................................... 24 Figure 4 V. C. Summer Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 1 00F/hr) Applicable for 56 EFPY (Without Margins for Instrumentation Errors) Using 1998 Appendix G Methodology.......................................................... 25
WCAP-1 6305-NP vii WCAP-1 6305-NP vii EXECUTIVE
SUMMARY
This report provides the methodology and results of the generation of heatup and cooldown pressure temperature (PT) limit curves for normal operation of the V. C. Summer reactor vessel. The PT curves were generated based on the latest available reactor vessel information and updated calculated fluences. The new V. C. Summerheatup and cooldown pressure-temperature limit curves were generated using the "axial flaw" methodology of the 1998 ASME Code, Section Xl through the 2000 Addenda 64]. Included in this methodology, is the use of the K1c stress intensity factors, which was formerly documented under ASME Code Case N-641 [63].
The material with the highest adjusted reference temperature (ART) was the Intermediate shell plate A9154-1. The PT limit curves were generated for 32 and 56 EFPY using heatup rates of 50 and 100F/hr and cooldown rates of 0, 25, 50 and 100F/hr. These curves can be found in Figures 1, 2, 3 and 4.
- 1. INTRODUCTION & PURPOSE Heatup and cooldown limit curves are calculated using the adjusted RTNDT (reference nil-ductility temperature) corresponding to the limiting beltline 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 ft-lbs of impact energy and 35-mil lateral expansion (normal to the major working direction) minus 600F.
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" 16'l. 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 heatup and cooldown curves documented in this report were generated using the most limiting ART values and the NRC approved methodology documented in WCAP-14040-NP-A, Revision 4
, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves".
The purpose of this report is to present the calculations and the development of the V. C.
Summer heatup and cooldown curves for 32 and 56 EFPY. This report documents the calculated ART values and the development of the PT limit curves for normal operation. The PT curves herein were generated without margins for instrumentation errors. The PT curves include a hydrostatic leak test limit curve from 2485 psig to 2000 psig, along with the pressure-temperature limits for the vessel flange region per the requirements of 10 CFR Part 50, Appendix G16q.
WCAP-1 6305-NP 2
- 2.
FRACTURE TOUGHNESS PROPERTIES The fracture-toughness properties of the ferritic materials in the reactor coolant pressure boundary are determined in accordance with the NRC Standard Review Plant 6 61. The beltline material properties of the V. C. Summer reactor vessel are presented in Table 1.
Best estimate copper (Cu) and nickel (Ni) weight percent values used to calculate chemistry factors (CF) in accordance with Regulatory Guide 1.99, Revision 2, are provided in Table 1.
Additionally, surveillance capsule data is available for five capsules (Capsules U, V, X, W and Z) already removed from the V. C. Summer reactor vessel. This surveillance capsule data was also used to calculate CF values per Position 2.1 of Regulatory Guide 1.99, Revision 2 in Table
- 3. These CF values are summarized in Table 4.
The Regulatory Guide 1.99, Revision 2 methodology used to develop the heatup and cooldown curves documented in this report is the same as that documented in WCAP-14040, Revision 416.2]
WCAP-1 6305-NP 3
TABLE 1 Summary of the Best Estimate Cu and Ni Weight Percent and Initial RTNDT Values for the V. C. Summer Reactor Vessel Materials Material Description Cu (%)
Ni(%)
Initial RTNDT° l Closure Head Flange 5297-V1l(b) l l
l 10F(b)
Vessel Flange 5301-V-1 1
Fb)
Intermediate Shell Plate A9154-1 0.10 0.51 300F Intermediate Shell Plate A9153-2 0.09 0.45
-200F Lower Shell Plate C9923-1 0.08 0.41 10F Lower Shell Plate C9923-2 0.08 0.41 100F Intermediate Shell Longitudinal Weld Seams 0.05 0.91
-440F BC & BD Intermediate Shell Longitudinal Weld Seams 0.05 0.91
-440F BA& BB Intermediate to Lower Shell Plate 0.05 0.91
-440F Circumferential Weld Seam AB Surveillance Program Weld Metal 0.04 0.95 (a) The initial RT NDT values for the plates and welds are based on measured data per WCAP-1 2867 1671 (b) In the past the closure head flange was reported as Heat A9231 with an IRTNDT of -200F. Based on a review of Westinghouse files, the correct data is Heat # 5297-V1 with an IRTNDT of 10F. Also, the vessel flange reported an IRTNDT of 100F., however, based on a review Westinghouse files, the correct IRTNDT is 01F.
1I_
WCAP-1 6305-NP 4
The chemistry factors are calculated using Regulatory Guide 1.99 Revision 2, Positions 1.1 and 2.1. Position 1.1 uses the Tables from the Reg. Guide along with the best estimate copper and nickel weight percents. Position 2.1 uses the surveillance capsule data from all capsules withdrawn to date. The fluence values used to determine the CFs in Table 3 are the calculated fluence values at the surveillance capsule locations. Hence, the calculated fluence values were used for all cases. Included in Table 2 are the calculated fluence values for V. C. Summer. All capsule fluence values were determined using ENDF/B-VI cross-sections and followed the guidance in Regulatory Guide 1.1901 101.
It should be noted that in the calculation of chemistry factor in Table 3, the ratio was applied to account for chemistry differences between the vessel weld material and the surveillance weld material. As for temperature adjustments, the V. C. Summer data does not require any adjustments since it is being applied to its own plant.
TABLE 2 Calculated Integrated Neutron Exposure of the Surveillance Capsules © V. C. Summer Capsule Fluence(a)
U 6.77 x 1018 n/cm2, (E > 1.0 MeV)
V 1.56 x 1019 n/cm 2, (E > 1.0 MeV)
X 2.53 x 1019 n/cm2, (E > 1.0 MeV)
W 4.63 x 1019 n/cm2, (E > 1.0 MeV)
Z 6.54 x 1019 n/cm2, (E > 1.0 MeV)
(a)
Per Capsule Z Report, WCAP-16298
81
TABLE 3 Calculation of Chemistry Factors using V. C. Summer Surveillance Capsule Data Material Capsule Capsule FFzb)
ARTNDT(C)
FF*ARTNDT FF2 Intermediate Shell U
0.677 0.891 36.1 32.2 0.793 Plate A9154-1 V
1.56 1.123 53.2 59.7 1.261 (Longitudinal)
X 2.53 1.249 38.3 47.8 1.560 W
4.63 1.387 66.2 91.8 1.924 Z
6.54 1.452 98.9 143.6 2.108 Intermediate Shell U
0.677 0.891 14.5 12.9 0.793 Plate A9154-1 V
1.56 1.123 32.1 36.0 1.261 (Transverse)
X 2.53 1.249 26.7 33.3 1.560 W
4.63 1.387 57.8 80.2 1.924 Z
6.54 1.452 87.0 126.3 2.108 SUM:
663.8 15.292 CFA9,s4_1= X(FF RTNDT) + X:( FF2) = (663.8) + (15.292) = 43.4°F Surveillance Weld U
0.677 0.891 28.6 (22.7)(d) 25.4 0.793 Material V
1.56 1.123 59.2 (4 7.0 )(d) 66.5 1.261 X
2.53 1.249 28.6 (2 2.7)(d) 35.7 1.560 W
4.63 1.387 54.8 (43.5)(d) 76.0 1.924 Z
6.54 1.452 82.2 (65.2)(d) 119.3 2.108 SUM:
323.0 7.646 CF Sur. Weld = E(FF
- RTNDT) + X:( FF2) = (323.0) + (7.646) = 42.2°F (a) f = fluence. See Table 2, [x I 019 n/cm2, E > 1.0 MeV]
(b)
FF = fluence factor = f(O28-0.1logQ)
(c)
ARTNOT values are the measured 30 ft-lb shift values taken from Capsule Z Report, WCAP-162981685, Appendix B [OF]
(d)
The Surveillance Weld ARTNDT values have been adjusted by a ratio of 1.26, Pre-adjusted values in parenthesis
U-WCAP-1 6305-NP 6
WCAP-1 6305-NP 6
TABLE 4 Summary of the V. C. Summer Reactor Vessel Beltline Material Chemistry Factors Material Reg. Guide 1.99, Rev. 2 Reg. Guide 1.99, Rev. 2 Position 1.1 CF's Position 2.1 CF's Intermediate Shell Plate A9154-1 65.0F 43.40Fta)
Intermediate Shell Plate A9153-2 58.00F Lower Shell Plate C9923-1 51.0°F Lower Shell Plate C9923-2 51.00F Intermediate Shell Longitudinal 68.00F 42.20F<a)
Weld Seams BC & BD Lower Shell Longitudinal Weld 68.0F 42.2°F~
8 )
Seams BA & BB Intermediate to Lower Shell Plate 68.0F 42.2oF(a)
Circumferential Weld Seam AB (a)
See Capsule Z Report, WCAP-1 6298(681, for the credibility evaluation of the V.C. Summer Unit 1 surveillance data. The Intermediate Shell Plate A9154-1 was deemed "non-credible' while the weld was deemed 'credible".
WCAP-1 6305-NP 7
- 3.
CRITERIAFORALLOWABLE PRESSURE-TEMPERATURE RELATIONSHIPS 3.1 OVERALL APPROACH The ASME approach for calculating the allowable limit curves for various heatup and cooldown rates specifies that the total stress intensity factor, K,, for the combined thermal and pressure stresses at any time during heatup or cooldown cannot be greater than the reference stress intensity factor, Kc, for the metal temperature at that time. K1c is obtained from the reference fracture toughness curve, defined in Code Case N-641, uAltemative Pressure-Temperature Relationship and Low Temperature Overpressure Protection System Requirements Section Xl, Division 1"1nB3 & 6,41 of the ASME Appendix G to Section XI. The Kjc curve is given by the following equation:
Kk =3 3.2 +2 0.7 34 *ero 02(T-RRTm)1 (1)
- where, Kc=
reference stress intensity factor as a function of the metal temperature T and the metal reference nil-ductility temperature RTNDT This Kjc 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 Classl, SA-508-1, SA-508-2, SA-508-3 steel.
3.2 METHODOLOGY FOR PRESSURE-TEMPERATURE LIMIT CURVE DEVELOPMENT The governing equation for the heatup-cooldown analysis is defined in Appendix G of the ASME Code as follows:
C* Kim + Kit < K1c (2)
- where, Kim
=
stress intensity factor caused by membrane (pressure) stress Kit=
stress intensity factor caused by the thermal gradients Kc=
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
U-WCAP-16305-NP 8
For membrane tension, the corresponding K, for the postulated defect is:
Kim = Mm x (pRil t)
(3) where, Mm for an inside surface flaw is given by:
Mm
=
1.85 for -
< 2 Mm
=
0.926 4 for 2 < 4
< 3.464 Mm
=
3.21 for 4t > 3.464 Similarly, Mm for an outside surface flaw is given by:
Mm
=
1.77 for 4
< 2 Mm
=
0.893 4 for 2 < 4 < 3.464 Mm
=
3.09 for 47 > 3.464 and p = internal pressure, Ri = vessel inner radius and t = vessel wall thickness.
For bending stress, the corresponding Ke for the postulated defect is:
KIb = Mb
- Maximum Stress, where Mb is two-thirds of Mm The maximum K, produced by radial thermal gradient for the postulated inside surface defect of G-2120 is Kit = 0.953x104 x CR x t25, where CR is the cooldown rate in OF/hr., or for a postulated outside surface defect, K,, = 0.753x104 x HU x t25, where HU is the heatup rate in OF/hr.
The through-wall temperature difference associated with the maximum thermal K, can be determined from Figure G-2214-1. The temperature at any radial distance from the vessel surface can be determined from Figure G-2214-2 for the maximum thermal Ki.
(a)
The maximum thermal Kg relationship and the temperature relationship in Figure 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 1/4-thickness inside surface defect using the relationship:
WCAP-1 6305-NP 9
Kr, = (1.0359Co+ 0.6322CI + 0.4753C2 + 03855C3) *
(4) or similarly, KrI during heatup for a %-thickness outside surface defect using the relationship:
Kit = (1.043Co + 0.630Ci + 0.48 1C2+O.401C3) * ;m (5) where the coefficients C0, C,, C2 and C3 are determined from the thermal stress distribution at any specified time during the heatup or cooldown using the form:
v(x) = Co+ Ci(x/a)+ C2(x/a)2 + C3(x/a)3 (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"16.21 with the exceptions just described above.
At any time during the heatup or cooldown transient, KIc is determined 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, Kit, 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 wall. 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
WCAP-1 6305-NP 10 WCAP-1 6305-NP 10 steady-state and finite cooldown rate situations. From these relations, composite limit curves are constructed for each cooldown rate of interest.
The 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 true 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 K10 at the 114T location for finite cooldown rates than for steady-state operation. Furthermore, if conditions exist so that the increase in Kir exceeds Kit, the calculated allowable pressure during cooldown will be greater than the steady-state value.
The above procedures are needed because there is no direct control on temperature at the 1/4T 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 curve 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 intemal pressure. The metal temperature at the crack tip lags the coolant temperature; therefore, the K,: for the 1/4T crack during heatup is lower than the Kic for the 1/4T 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 K1c 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 1/4T 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.
WCAP-16305-NP 11 WCAP-1 6305-NP 11 The second portion of the heatup analysis concerns the calculation of the pressure-temperature limitations for the case in which a 1/4T 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 HEADNESSEL FLANGE REQUIREMENTS 10 CFR Part 50, Appendix G16851 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 120OF for normal operation when the pressure exceeds 20 percent of the pre-service hydrostatic test pressure (3106 psi),
which is 621 psig for V. C. Summer. The limiting unirradiated RTNDT of 100F occurs in the closure head flange of the V. C. Summer reactor vessel, so the minimum allowable temperature of this region is 1300F at pressures greater than 621 psig. This limit is shown in Figures 1, 2, 3 and 4 wherever applicable.
WCAP-1 6305-NP 12 WCAP-1 6305-NP 12
- 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 RTNDT + ARTNDT + Margin (7)
Initial RTNDT is the reference temperature for the unirradiated material as defined in paragraph NB-2331 of Section III of the ASME Boiler and Pressure Vessel Code16.9l. 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 should be calculated as follows:
ARTNDT = CF
- f(O.28 -0.10 log?)
(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(depth x) = fsurface
- e (424X)
(9) where x inches (vessel beltline thickness is 7.75 inches) 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 of the calculated peak fluence values at various azimuthal locations on the vessel clad/base metal interface are presented in Table 5. The evaluation used the ENDF/B-VI scattering cross-section data set. This is consistent with methods presented in WCAP-14040-NP-A. Tables 6 and 7 contain the 1/4T and 314T calculated fluences and fluence factors, per the Regulatory Guide 1.99, Revision 2, used to calculate the ART values for all beltline materials in the V. C. Summer reactor vessel at 32 and 56 EFPY.
U-WCAP-16305-NP 13 TABLE 5 Summary of the Peak Pressure Vessel Neutron Fluence Values(a) at the Clad/Base Metal Interface (n/cm2, E > 1.0 MeV)
Azimuthal Location EFPY 00 150 300 450 32 3.92 x 1019 2.41 x 1019 1.85 x 1019 1.36 x 10'9 56 6.80 x 10'9 4.15 x 10'9 3.18 x 10'9 2.35 x 10' 9 (a) Obtained from the Capsule Z Report, WCAP-16298 1681. These fluence projection are the calculated fluence projections determined following the methodology of Reg. Guide 1.1 90 f6lj TABLE 6 Summary of the Vessel Surface, 1/4T and 3/4T Fluence Values used for the Generation of the 32 EFPY Heatup/Cooldown Curves Material Surface 114T 3/4T (nlcm2, E > 1.0 MeV)
(nICm 2, E > 1.0 MeV)
(n/cm2, E > 1.0 MeV)
Intermediate Shell Plate A9154-1 3.92 x 10'9 2.46 x 10'9 0.97 x 1013 Intermediate Shell Plate A9153-2 3.92 x 10'9 2.46 x 10'9 0.97 X 1019 Lower Shell Plate C9923-1 3.92 x 1019 2.46 x 10'9 0.97 x 10'9 Lower Shell Plate C9923-2 3.92 x 10'9 2.46 x 1019 0.97 x 10'9 Intermediate to Lower Shell 3.92 x 10'9 2.46 x 10'9 0.97 x 10'9 Circumferential Weld Seam AB Intermediate Lower Shell Longitudinal 1.36 x 10'9 0.85 x 10'9 0.34 x 10'9 Weld Seam BC, BD, BA & BB (450 Azimuth)
WCAP-16305-NP 14 WCAP-1 6305-NP 14 TABLE 7 Summary of the Vessel Surface, 1/4T and 3/4T Fluence Values used for the Generation of the 56 EFPY Heatup/Cooldown Curves Material Surface 114T 3/4T
- (nlcm 2, E > 1.0 MoWV)
(nlcm2, E > 1.0 MoWV)
(n/cm2, E > 1.0 MWV)
Intermediate Shell Plate A9154-1 6.80 x 10"'
4.27 x 1019 1.69 x 10'9 Intermediate Shell Plate A9153-2 6.80 x 1 o19 4.27 x 1 o19 1.69 x 10 o
Lower Shell Plate C9923-1 6.80 x 10"'
4.27 x 1019 1.69 x 10'9 Lower Shell Plate C9923-2 6.80 x 1i09 4.27 x 10"'
1.69 x 1019 Intermediate to Lower Shell 6.80 x 1019 4.27 x 10"'
1.69 x 1 0'9 Circumferential Weld Seam AB Intermediate Lower Shell Longitudinal 2.35 x 10"'
1.48 x 1019 0.58 x 1019 Weld Seam BC, BD, BA & BB (450 Azimuth)
Contained in Tables 8 and 9 is a summary of the fluence factor (FF) values used in the calculation of adjusted reference temperatures for the V. C. Summer reactor vessel beltline materials for 32 and 56 EFPY.
TABLE 8 Calculation of the 1/4T and 3/4T Fluence Factor Values used for the Generation of the 32 EFPY Heatup/Cooldown Curves Material 1/4T F(a) 1/4T FF 3/4T F(a) 3/4T FF Intermediate Shell Plate A9154-1 2.46 x 1019 1.242 0.97 x 1 0'9 0.991 Intermediate Shell Plate A9153-2 2.46 x 1019 1.242 0.97 x 1019 0.991 Lower Shell Plate C9923-1 2.46 x 1019 1.242 0.97 x
~
0.991 Lower Shell Plate C9923-2 2.46 x 1019 1.242 0.97 x 1019 0.991 Intermediate to Lower Shell 2.46 x 10"'
1.242 0.97 x 1019 0.991 Circumferential Weld Seam AB Intermediate Lower Shell Longitudinal 0.85 x 1019 0.954 0.34 x 10's 0.703 Weld Seam BC, BD, BA & BB (450 Azimuth)
(a) Units: n/cm2, E > 1.0 MeV
_ _ _- U -
WCAP-16305-NP 15 TABLE 9 Calculation of the 1/4T and 3/4T Fluence Factor Values used for the Generation of the 56 EFPY Heatup/Cooldown Curves Material 1/4T F(a) 1/4T FF 3/4T F(a) 3/4T FF Intermediate Shell PlateA9154-1 4.27 x 1019 1.370 1.69 x 1019 1.144 Intermediate Shell Plate A9153-2 4.27 x 1019 1.370 1.69 x 109 1.144 Lower Shell Plate C9923-1 4.27 x 109 1.370 1.69 x 1019 1.144 Lower Shell Plate C9923-2 4.27 x 10'9 1.370 1.69 x 1019 1.144 Intermediate to Lower Shell 4.27 x 10'9 1.370 1.69 x 1019 1.144 Circumferential Weld Seam AB Intermediate Lower Shell Longitudinal 1.48 x 1019 1.109 0.58 x 1019 0.848 Weld Seam BC, BD, BA & BB (450 Azimuth)
(a) Units: n/cm2, E > 1.0 MeV Margin is calculated as, M = 2 a2 + a.
The standard deviation for the initial RTNDT margin term, is ai 00F when the initial RTNDT is a measured value, and 170F when a generic value is available. The standard deviation for the ARTNDT margin term, aa, is 170F for plates or forgings, and 8.50F for plates or forgings when surveillance data is used. For welds, GA is equal to 280F when surveillance capsule data is not used, and is 140F (half the value) when credible surveillance capsule data is used. EA need not exceed 0.5 times the mean value of ARTNDT.
Contained in Tables 10 and 11 are the calculated ART values used for the generation of the heatup and cooldown curves at 32 EFPY. Contained in Tables 12 and 13 are the calculated ART values used for the generation of the heatup and cooldown curves at 56 EFPY.
WCAP-16305-NP 16 WCAP-1 6305-NP 16 TABLE 10 Calculation of the ART Values for the 1/4T Location @ 32 EFPY Material Reg. Guide CFa)
% T FF IRTNDT b)
ARTNDT(C)
M(d)
ART(*)
1.99 Rev. 2 (OF)
(OF)
('F)
(OF)
(OF)
Method Intermediate Shell Plate Position 1.1 65.0 1.242 30 80.73 34.0 145 A9154-1 Position 2.1 43.4 1.242 30 53.90 34.0(0 118 Intermediate Shell Plate Position 1.1 58.0 1.242
-20 72.04 34.0 86 A9153-2 34.0 Lower Shell Plate C9923-1 Position 1.1 51.0 1.242 10 63.34 34.0 107 Lower Shell Plate C9923-2 Position 1.1 51.00 1.242 10 63.34 34.0 107 Intermediate to Lower Shell Position 1.1 68.0 1.242
-44 84.46 56.0 96 Circumferential Weld Seam Position 2.1 42.2 1.242
-44 52.41 28.0 36 AB Intermediate Lower Shell Position 1.1 68.0 0.954
-44 64.87 56.0 77 Longitudinal Weld Seam BC, Position 2.1 42.2 0.954
-44 40.26 28.0 24 BD, BA & BB (450 Azimuth) taken frm T e 4 (a)
Chemistry Factors taken from Table 4 (b)
(c)
(d)
(e)
(f)
Initial RTNDT values are measured values; see Table I ARTNDT = CF
- FF Margin = 2*(ao2 +CA2)1M ART = IRTNDT + ARTNOT + M (This value was rounded per ASTM E29, using the "Rounding Method")
Surveillance Plate Data is not-credible, thus the full ca was used
L---U-WCAP-16305-NP 17 WCAP-1 6305-NP 17 TABLE 11 Calculation of the ART Values for the 3/4T Location @ 32 EFPY Material Reg. Guide CF(a) a T FF IRTNDT (b)
ARTNDT( W M(d)
ART~
e 1.99 Rev. 2 (0F)
(OF)
(OF)
(OF)
(0F)
Method Intermediate Shell Plate Position 1.1 65.0 0.991 30 64.42 34.0 128 A9154-1 Position 2.1 43.4 0.991 30 43.01 34.0(f 107 Intermediate Shell Plate Position 1.1 58.0 0.991
-20 57.48 34.0 71 A9153-2 34.0 Lower Shell Plate C9923-1 Position 1.1 51.0 0.991 10 50.54 34.0 95 Lower Shell Plate C9923-2 Position 1.1 51.00 0.991 10 50.54 34.0 95 Intermediate to Lower Shell Position 1.1 68.0 0.991
-44 67.39 56.0 79 Circumferential Weld Seam Position 2.1 42.2 0.991
-44 41.82 28.0 26 AB Intermediate Lower Shell Position 1.1 68.0 0.703
-44 47.80 56.0 60 Lotd Wel 4 Amuh Position 2.1 42.2 0.703
-44 29.67 28.0 14 80, BA & BB (45C Azimuth) taken from Tab (a)
Chemistry Factors taken from Table 4 (b)
(c)
(d)
(e)
(f)
Initial RTNDT values are measured values; see Table 1 ARTNDT =CF*FF Margin = 2*(oy,2 +CaA 2)112 ART = IRTNDT + ARTNDT + M (This value was rounded per ASTM E29, using the "Rounding Method")
Surveillance Plate Data is not-credible, thus the full a, was used
WCAP-16305-NP 18 WCAP-1 6305-NP 18 TABLE 12 Calculation of the ART Values for the 1/4T Location © 56 EFPY Material Reg. Guide CF(a)
% T FF IRTND ob)
ARTNDTOc)
M(d)
ART(e) 1.99 Rev. 2 (OF)
(OF)
(OF)
(OF)
(OF)
Method Intermediate Shell Plate Position 1.1 65.0 1.370 30 89.05 34.0 153 A9154-1 Position 2.1 43.4 1.370 30 59.46 34.0w0 123 Intermediate Shell Plate Position 1.1 58.0 1.370
-20 79.46 34.0 93 A9153-2 34.0 Lower Shell Plate C9923-1 Position 1.1 51.0 1.370 10 69.87 34.0 114 Lower Shell Plate C9923-2 Position 1.1 51.00 1.370 10 69.87 34.0 114 Intermediate to Lower Shell Position 1.1 68.0 1.370
-44 93.16 56.0 105 Circumferential Weld Seam Position 2.1 42.2 1.370
-44 57.81 28.0 42 AB Intermediate Lower Shell Position 1.1 68.0 1.109
-44 75.41 56.0 87 Longitudinal Weld Seam BC Position 2.1 42.2 1.109
-44 46.80 28.0 31 BD, BA & BB (450 Azimuth) taken frm T e 4 (a)
Chemistry Factors taken from Table 4 (b)
(c)
(d)
(e)
(f)
Initial RTNDT values are measured values; see Table 1 ARTNOT = CF - FF Margin = 2*(o;2 +0a2)"
ART = IRTNDT + ARTNDT + M (This value was rounded per ASTM E29, using the Rounding Method")
Surveillance Plate Data is not-credible, thus the full ofa was used
U-WCAP-16305-NP 19 WCAP-1 6305-NP 19 TABLE 13 Calculation of the ART Values for the 3/4T Location @ 56 EFPY Material Reg. Guide CFUla)
T FF IRTNDT(b)
ARTNOT C Mcd)
ARTte) 1.99 Rev. 2 (OF)
('F)
(OF)
('F)
('F)
Method Intermediate Shell Plate Position 1.1 65.0 1.144 30 74.36 34.0 138 A9154-1 Position 2.1 43.4 1.144 30 49.65 34.0Q(
114 Intermediate Shell Plate Position 1.1 58.0 1.144
-20 66.35 34.0 80 A9153-2 34.0 Lower Shell Plate C9923-1 Position 1.1 51.0 1.144 10 58.34 34.0 102 Lower Shell Plate C9923-2 Position 1.1 51.00 1.144 10 58.34 34.0 102 Intermediate to Lower Shell Position 1.1 68.0 1.144
-44 77.79 56.0 90 Circumferential Weld Seam Position 2.1 42.2 1.144
-44 48.28 28.0 32 AB Intermediate Lower Shell Position 1.1 68.0 0.848
-44 57.66 56.0 70 Longitudinal Weld Seam BC, Position 2.1 42.2 0.848
-44 35.79 28.0 20 BD, BA, BB (450 Azimuth) taken from T e 4 (a)
Chemistry Factors taken from Table 4 (b)
(c)
(d)
(e)
(f)
Initial RTNDT values are measured values; see Table 1 ARTNDT =CF*FF Margin = 2*(cai 2 +0a 2 )11 2 ART = IRTNDT + ARTNDT + M (This value was rounded per ASTM E29, using the Rounding Method")
Surveillance Plate Data is not-credible, thus the full ao was used The Intermediate Shell Plate A9154-1 is the limiting beltline material for all the PT limit curves to be generated. Contained in Table 14 is a summary of the limiting ART values to be used in the generation of the V. C. Summer reactor vessel PT limit curves. These limiting curves will be presented in Section 5.
TABLE 14 Summary of the Limiting ART Values Used in the Generation of the V. C. Summer Heatup/Cooldown Curves EFPY
/4 T Limiting ART
% T Limiting ART 32 145 128 56 153 138
- 5. HEATUP AND COOLDOWN PRESSURE-TEMPERATURE LIMIT CURVES Pressure-temperature limit curves for normal heatup and cooldown of the primary reactor coolant system have been calculated for the pressure and temperature in the reactor vessel beltline region using the methods discussed in Sections 3 and 4 of this report. This approved methodology is also presented in WCAP-14040-NP-A, Revision 4.
Figures 1 and 3 present the limiting heatup curves without margins for possible instrumentation errors using heatup rates of 50 and 100F/hr applicable for 32 and 56 EFPY. These curves were generated using the1998 ASME Code Section Xl, Appendix G with the limiting ART values. Figures 2 and 4 present the limiting cooldown curves without margins for possible instrumentation errors using cooldown rates of 0, 25, 50 and 1000F/hr applicable for 32 and 56 EFPY. Again, these curves were generated using thel998 ASME Code Section Xl, Appendix G with the limiting ART values. Allowable combinations of temperature and pressure for specific temperature change rates are below and to the right of the limit line shown in Figures 1, 2, 3 and 4. This is in addition to other criteria, which must be met before the reactor is made critical, as discussed below in the following paragraphs.
The reactor must not be made critical until pressure-temperature combinations are to the right of the criticality limit line shown in Figure 1. 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 the 1998 ASME Code164 1 as follows:
1.5 Klm < Kic
- where, Kim is the stress intensity factor covered by membrane (pressure) stress Kjc = 33.2 + 20.734 eI0.02 (f - RNDT)N T is the minimum permissible metal temperature 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 [6.5]. The pressure-temperature limits for core operation (except for low power physics tests) are that the reactor
IL WCAP-16305-NP 21 vessel must be at a temperature equal to or higher than the minimum temperature required for the inservice hydrostatic test, and at least 400F higher than the minimum permissible temperature in the corresponding pressure-temperature curve for heatup and cooldown calculated as described in Section 4 of this report. For the heatup and cooldown curves without margins for instrumentation errors, the minimum temperatures for the in service hydrostatic leak tests for the V. C. Summer reactor vessel at 32 EFPY is 2020F and at 56 EFPY is 21 00F. The vertical line drawn from these points on the pressure-temperature curve, intersecting a curve 400F higher than the pressure-temperature limit curve constitutes the limit for core operation for the reactor vessel.
Figures 1, 2, 3 and 4 define all of the above limits for ensuring prevention of non-ductile failure for the V. C. Summer reactor vessel for 32 and 56 EFPY. The data points used for the heatup and cooldown pressure-temperature limit curves shown in Figures 1, 2, 3 and 4 are presented in Tables 15, 16, 17 and 18.
WCAP-16305-NP 22 WCAP-1 6305-NP 22 MATERIAL PROPERTY BASIS:-
Limiting Material: Intermediate Shell Plate A9154-1 Limiting ART Values @ 32 EFPY: 1/4T: 145°F, 3/4T: 128°F 2500-2 Opedrim Version:5.2 Run:28577 Opedim.ds Version: 5.2 2250 Leak Test mit I
1
-7r l
Unacceptable l
Acceptable 2000 Operation Operation 1750 X 50-lHeatup Rate l SL
-/-
50 Dog. FIr Critical Limit
.0 Heatup Rate 10 Deg.
FIHr 100 Deg. FlHr 1
0al Lii I
la I
I0 Deg.
I I
500-250 Boltup Criticality Limit based on 1
Temp.
l Inservice hydrostatic test l
I temperature (202 F) for the O..
I service period up to 32 EFPYl 0
50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)
Figure 1 V. C. Summer Reactor Coolant System Heatup Limitations (Heatup Rates of 50 and 100°Flhr) Applicable for 32 EFPY (Without Margins for Instrumentation Errors) Using 1998 Appendix G Methodology
WCAP-16305-NP 23 WCAP-1 6305-NP 23 MATERIAL PROPERTY BASIS:
Limiting Material: Intermediate Shell Plate A9154-1 Limiting ART Values @ 32 EFPY: 1/4T: 1450F, 3/4T: 1280F 2500 2250 2000 1750 CD, aL 1500 a)
U) 3 2Z 1250 CL a.
= 1000 C.)
750 500 250 0
0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)
Figure 2 V. C. Summer Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 1000F/hr) Applicable for 32 EFPY (Without Margins for Instrumentation Errors) Using 1998 Appendix G Methodology
WCAP-16305-NP 24 WCAP-1 6305-NP 24 MATERIAL PROPERTY BASIS:
Limiting Material: Intermediate Shell Plate A9154-1 Limiting ART Values @ 56 EFPY: 1/4T: 1531F, 314T: 1381F 1Opedlim Version:5.2 Run:17345 Operlim.ds Version: 5.2 1 2500 2250 2000 1750 IL 1500 CD L-o un un 2 1250 IL la
,, 1000 U
C.)
750 500 250 0
0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)
Figure 3 V. C. Summer Reactor Coolant System Heatup Limitations (Heatup Rates of 50 and 100"F/hr) Applicable for 56 EFPY (Without Margins for Instrumentation Errors) Using 1998 Appendix G Methodology
U-WCAP-16305-NP 25 MATERIAL PROPERTY BASIS:
Limiting Material: Intermediate Shell Plate A9154-1 Limiting ART Values @ 56 EFPY: 1/4T: 1530F, 3/4T: 138 0F 2500 2250 2000 1750 X 1500 Cu a 1250 a-c) a.0 a)
- 0 1000 C.)
M.
750 500 250 0
0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)
Figure 4 V. C. Summer Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100 0F/hr) Applicable for 56 EFPY (Without Margins for Instrumentation Errors) Using 1998 Appendix G Methodology
WCAP-16305-NP 26 WCAP-1 6305-NP 26 TABLE 15 32 EFPY Heatup Curve Data Points Using 1998 Appendix G Methodology (without Uncertainties for Instrumentation Errors) 50 Heatup Critical. Limit 100 Heatup Critical. Limit Leak Test Limit T (OF)
P (psig)
T (OF)
P (psig)
T (OF)
P (psig)
T (OF)
P (psig)
T (OF)
P (pslg) 60 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 130 135 140 145 150 155 160 165 170 175 180 185 190 195 200 205 210 215 220 225 0
621 621 621 621 621 621 621 621 621 621 621 621 621 621 621 862 891 923 958 997 1041 1089 1142 1201 1266 1337 1416 1504 1600 1707 1824 1937 2062 2199 2351 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 205 210 215 220 225 230 235 240 245 250 255 260 265 0
621 621 621 621 621 621 621 621 621 621 621 621 621 621 862 891 923 958 997 1041 1089 1142 1201 1266 1337 1416 1504 1600 1707 1824 1937 2062 2199 2351 60 60 65 70 75, 80 85 90 95 100 105 110
.115 120 125 130 130 135 140 145 150 155 160 165 170 175 180 185 190 195 200.
205 210 215 220 225 230 235 240 245 0.
621 621 621 621 621 621 621 621 621 621 621 621 621 621 621 723 739 757 778 801 828 858 891 929 970 1016 1067 1123 1186 1255 1331 1416 1509 1612 1725 1851 1989 2141 2310 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 202 205 210 215 220 225 230 235 240 245 250 255 260 265 270 275 280 285 0
621 621 621 621 621 621 621 621 621 621 621 621 621 621 723 739 757 778 801 828 858 891 929 970 1016 1067 1123 1186 1255 1331 1416 1509 1612 1725 1851 1989 2141 2310 184 202 2000 2485
LU WCAP-16305-NP 27 TABLE 16 32 EFPY Cooldown Curve Data Points Using 1998 Appendix G Methodology (without Uncertainties for Instrumentation Errors)
Steady State 25 0F1hr.
50°F/hr.
1000F1hr.
T (OF)
P (psig)
T (OF)
P (psig)
T (OF)
P (psig)
T (OF)
P (psig) 60 0
60 0
60 0
60 0
60 621 60 621 60 617 60 524 65 621 65 621 65 621 65 535 70 621 70 621 70 621 70 546 75 621 75 621 75 621 75 559 80 621 80 621 80 621 80 574 85 621 85 621 85 621 85 590 90 621 90 621 90 621 90 608 95 621 95 621 95 621 95 621 100 621 100 621 100 621 100 621 105 621 105 621 105 621 105 621 110 621 110 621 110 621 110 621 115 621 115 621 115 621 115 621 120 621 120 621 120 621 120 621 125 621 125 621 125 621 125 621 130 621 130 621 130 621 130 621 130 928 130 904 130 881 130 846 135 959 135 938 135 919 135 892 140 993 140 975 140 960 140 944 145 1031 145 1017 145 1006 145 1001 150 1073 150 1063 150 1057 150 1057 155 1119 155 1114 155 1114 155 1114 160 1170 160 1170 160 1170 160 1170 165 1226 165 1226 165 1226 165 1226 170 1288 170 1288 170 1288 170 1288 175 1357 175 1357 175 1357 175 1357 180 1433 180 1433 180 1433 180 1433 185 1517 185 1517 185 1517 185 1517 190 1610 190 1610 190 1610 190 1610 195 1712 195 1712 195 1712 195 1712 200 1825 200 1825 200 1825 200 1825 205 1951 205 1951 205 1951 205 1951 210 2089 210 2089 210 2089 210 2089 215 2242 215 2242 215 2242 215 2242 220 2411 220 2411 220 2411 220 2411
WCAP-16305-NP 28 WCAP-1 6305-NP 28 TABLE 17 56 EFPY Heatup Curve Data Points Using 1998 Appendix G Methodology (without Uncertainties for Instrumentation Errors) 50 Heatup Critical. Limit 100 Heatup Critical. Limit Leak Test Limit T (,F)
P (psig)
T (,F)
P (psig)
T (,F)
P (psig)
T (OF)
P (pslg)
T (,F)
P (psig) 60 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 130 135 140 145 150 155 160 165 170 175 180 185 190 195 200 205 210 215 220 225 230 235 0
621 621 621 621 621 621 621 621 621 621 621 621 621 621 621 810 833 859 888 920 956 995 1039 1087 1140 1198 1263 1334 1413 1500 1597 1703 1820 1950 2092 2250 2415 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 215 220 225 230 235 240 245 250 255 260 265 270 275 0
621 621 621 621 621 621 621 621 621 621 621 621 621 621 810 833 859 888 920 956 995 1039 1087 1140 1198 1263 1334 1413 1500 1597 1703 1820 1950 2092 2250 2415 60 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 130 135 140 145 150 155 160 165 170 175 180 185 190 195 200 205 210 215 220 225 230 235 240 245 250 255 260 0.
621 621 621 621 621 621 621 621 621 621 621 621 621 621 621 684 697 711 728 747 768 792 819 850 883 921 962 1008 1059 1115 1178 1247 1323 1407 1500 1602 1715 1840 1978 2129 2297 2481 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 210 215 220 225 230 235 240 245 250 255 260 265 270 275 280 285 290 295 300 0
621 621 621 621 621 621 621 621 621 621 621 621 621 621 684 697 711 728 747 768 792 819 850 883 921 962 1008 1059 1115 1178 1247 1323 1407 1500 1602 1715 1840 1978 2129 2297 2481
'192 210 2000 2485 J
I I
I
-L WCAP-16305-NP 29 WCAP-1 6305-NP 29 TABLE 18 32 EFPY Cooldown Curve Data Points Using 1998 Appendix G Methodology (without Uncertainties for Instrumentation Errors)
Steady State 250F/hr.
50°F/hr.
100°F/hr.
T (OF)
P (psig)
T (OF)
P (psig)
T (OF)
P (psig)
T (OF)
P (psig) 60 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 130 135 140 145 150 155 160 165 170 175 180 185 190 195 200 205 210 215 220 225 230 0
621 621 621 621 621 621 621 621 621 621 621 621 621 621 621 885 911 940 972 1008 1047 1091 1139 1192 1250 1315 1386 1465 1553 1649 1756 1874 2004 2148 2308 2484 60 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 130 135 140 145 150 155 160 165 170 175 180 185 190 195 200 205 210 215 220 225 230 0
621 621 621 621 621 621 621 621 621 621 621 621 621 621 621 856 885 917 952 991 1035 1082 1136 1192 1250 1315 1386 1465 1553 1649 1756 1874 2004 2148 2308 2484 60 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 130 135 140 145 150 155 160 165 170 175 180 185 190 195 200 205 210 215 220 225 230 0
604 611 619 621 621 621 621 621 621 621 621 621 621 621 621 828 860 896 935 978 1026 1079 1136 1192 1250 1315 1386 1465 1553 1649 1756 1874 2004 2148 2308 2484 60 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 130 135 140 145 150 155 160 165 170 175 180 185 190 195 200 205 210 215 220 225 230 0
508 517 527 538 550 564 579 596 615 621 621 621 621 621 621 781 820 864 912 966 1025 1079 1136 1192 1250 1315 1386 1465 1553 1649 1756 1874 2004 2148 2308 2484
WCAP-16305-NP 30 WC-635N 30
- 6.
REFERENCES 6.1 Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials,"
U.S. Nuclear Regulatory Commission, May 1988 6.2 WCAP-14040-NP-A, Revision 4, "Methodology used to Develop Cold Overpressure Mitigating system Setpoints and RCS Heatup and Cooldown Limit Curves", J.D.
Andrachek, et. al., May 2004 6.3 ASME Code Case N-641, "Alternative Pressure-Temperature Relationship and Low Temperature Overpressure Protection System Requirements Section Xl, Division 1",
January 17, 2000.[Sub Reference 1:ASME Code Case N-640, 0AItemative Reference Fracture Toughness for Development of P-T Limit Curves for Section Xl, Division 1 ", February 26, 1999]
6.4 ASME Code 1998 Edition through the 2000 Addenda of Section Xl, Appendix G 6.5 Code of Federal Regulations, 10 CFR Part 50, Appendix G, "Fracture Toughness Requirements", U.S. Nuclear Regulatory Commission, Washington, D.C., Federal Register, Volume 60, No. 243, dated December 19, 1995 6.6 "Fracture Toughness Requirements", Branch Technical Position MTEB 5-2, Chapter 5.3.2 in Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, LWR Edition, NUREG-0800,1981 6.7 WCAP-12867, -Analysis of Capsule X from the South Carolina Electric & Gas Company Virgil C. Summer Unit I Reactor Vessel Radiation Surveillance Program", J. M. Chicots, et. al., March 1991 6.8 WCAP-16298-NP, "Analysis of Capsule Z From The South Carolina Electric & Gas Company, V. C. Summer Reactor Vessel Radiation Surveillance Program", C. M. Burton, et. al., August 2004 6.9 1989 Section III, Division 1 of the ASME Boiler and Pressure Vessel Code, Paragraph NB-2331, "Material for Vessels" 6.10 Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence", March 2001
WCAP-1 6305-NP 31 APPENDIX A Thermal Stress Intensity Factors (Kit)
WCAP-1 6305-NP 32 Thermal Stress Intensity Factors In order to aid in the review and approval process, the NRC has typically requested that the thermal stress intensity factors be provided. This request was performed under the condition that only the thermal stress intensity factors for the maximum heatup and cooldown rates would be supplied for information. In recent history, this was accomplished via a letter report after the issuance of the PT limit curve. Now that it is known that the NRC will request this information upon each PT limit curve submittal, Westinghouse has decided to include the thermal stress intensity factors directly in the WCAP Report.
Presented in Tables Al through A4 are the thermal stress intensity factors for the maximum heatup and maximum cooldown rates for the 32 and 56 EFPY PT limit curves. Note the following:
Vessel Radius to the 1/4T and 3/4T Locations are as follows:
/ Y4T Radius = 80.563" 3/4T Radius = 84.438"
WCAP-1 6305-NP 33 WCAP-1 6305-NP 33 TABLE Al Kjt Values for 1001F/hr Heatup Curve (32 EFPY)
Water Vessel 1/4T Thermal Vessel 3/4T Thermal Temp.
Temperature @
Stress Temperature @
Stress
(°F) 1/4T Location for Intensity Factor 3/4T Location for Intensity Factor lOO0 F/hr Heatup (KSI SQ. RT. IN.)
100°F/hr Heatup (KSI SQ. RT. IN.)
(_F)1L (I
60 56.16
-0.9848 55.07 0.4968 65 58.99
-2.3617 55.45 1.4567 PT Curves are Limited by Steady State Conditions up to 65OF and 3/hT Limited for the Remainder of the Curve 70 62.22
-3.4855 56.39 2.3654 75 65.68
-4.5265 57.88 3.1790 80 69.41
-5.3899 59.83 3.8791 85 73.25
-6.1620 62.20 4.4877 90 77.29
-6.8111 64.93 5.0115 95 81.43
-7.3918 67.96 5.4680 100 85.70
-7.8834 71.25 5.8624 105 90.05
-8.3232 74.77 6.2068 110 94.49
-8.6987 78.47 6.5079 115 98.99
-9.0368 82.34 6.7728 120 103.56
-9.3271 86.35 7.0052 125 108.18
-9.5901 90.47 7.2108 130 112.84
-9.8175 94.70 7.3923 135 117.54
-10.0250 99.02 7.5542 140 122.28
-10.2059 103.42 7.6982 145 127.04
-10.3726 107.87 7.8277 150 131.82
-10.5191 112.39 7.9441 155 136.63
-10.6556 116.95 8.0498 160 141.45
-10.7767 121.56 8.1456 165 146.29
-10.8909 126.20 8.2336 170 151.14
-10.9932 130.87 8.3143 175 156.01
-11.0907 135.57 8.3892 180 160.88
-11.1791 140.29 8.4587 185 165.76
-11.2644 145.03 8.5239 190 170.65
-11.3425 149.78 8.5851 195 175.55
-11.4186 154.56 8.6430 200 180.45
-11.4891 159.34 8.6980 205 185.35
-11.5585 164.13 8.7507 210 190.26
-11.6233 168.94 8.8011 215 195.17
-11.6877 173.75 8.8498 220 200.09
-11.7483 178.57 8.8968 225 205.01
-11.8089 183.39 8.9426 230 209.93
-11.8665 188.22 8.9871 235 214.85
-11.9244 193.06 9.0307 240 219.77
-11.9798 197.89 9.0734 245 224.70
-12.0356 202.73 9.1154
L-WCAP-16305-NP 34 TABLE A2 K1, Values for 1 00F/hr Cooldown Curve (32 EFPY)
Water Vessel Temperature 100°F/hr Cooldown Temp.
@ 1/4T Location for 1/4T Thermal Stress (OF) 100OF/hr Cooldown Intensity Factor
( 0F)
(KSI SQ. RT. IN.)
220 241.83 13.0578 215 236.76 13.0038 210 231.68 12.9503 205 226.61 12.8962 200 221.54 12.8428 195 216.47 12.7888 190 211.40 12.7354 185 206.33 12.6815 180 201.26 12.6282 175 196.18 12.5745 170 191.11 12.5214 165 186.04 12.4678 160 180.97 12.4149 155 175.90 12.3615 100 0F Cooldown Rate is limited by the Steady State Condition from T = 155 0F to 220'F 150 145 140 135 130 125 120 115 110 105 100 95 90 85 80 75 70 65 60 170.83 165.76 160.69 155.62 150.55 145.47 140.40 135.33 130.26 125.19 120.12 115.05 109.98 104.92 99.85 94.78 89.71 84.64 79.57 12.3087 12.2556 12.2030 12.1501 12.0977 12.0450 11.9928 11.9403 11.8884 11.8362 11.7844 11.7325 11.6810 11.6292 11.5780 11.5265 11.4755 11.4242 11.3727 l-
WCAP-16305-NP 35 TABLE A3 K,t Values for 1000F/hr Heatup Curve (56 EFPY)
Water Vessel 1/4T Thermal Vessel 3/4T Thermal Temp.
Temperature @
Stress Temperature @
Stress (OF) 1/4T Location for Intensity Factor 3/4T Location for Intensity Factor 100OF/hr Heatup (KSI SQ. RT. IN.)
100°F/hr Heatup (KSI SQ. RT. IN.)
(F(OF)_
60 56.16
-0.9848 55.07 0.4968 65 58.99
-2.3617 55.45 1.4567 PT Curves are Limited by the '/hT Location up to 65°F and %/4T Limited for the Remainder of the Curve 70 62.22
-3.4855 56.39 2.3654 75 65.68
-4.5265 57.88 3.1790 80 69.41
-5.3899 59.83 3.8791 85 73.25
-6.1620 62.20 4.4877 90 77.29
-6.8111 64.93 5.0115 95 81.43
-7.3918 67.96 5.4680 100 85.70
-7.8834 71.25 5.8624 105 90.05
-8.3232 74.77 6.2068 110 94.49
-8.6987 78.47 6.5079 115 98.99
-9.0368 82.34 6.7728 120 103.56
-9.3271 86.35 7.0052 125 108.18
-9.5901 90.47 7.2108 130 112.84
-9.8175 94.70 7.3923 135 117.54
-10.0250 99.02 7.5542 140 122.28
-10.2059 103.42 7.6982 145 127.04
-10.3726 107.87 7.8277 150 131.82
-10.5191 112.39 7.9441 155 136.63
-10.6556 116.95 8.0498 160 141.45
-10.7767 121.56 8.1456 165 146.29
-10.8909 126.20 8.2336 170 151.14
-10.9932 130.87 8.3143 175 156.01
-11.0907 135.57 8.3892 180 160.88
-11.1791 140.29 8.4587 185 165.76
-11.2644 145.03 8.5239 190 170.65
-11.3425 149.78 8.5851 195 175.55
-11.4186 154.56 8.6430 200 180.45
-11.4891 159.34 8.6980 205 185.35
-11.5585 164.13 8.7507 210 190.26
-11.6233 168.94 8.8011 215 195.17
-11.6877 173.75 8.8498 220 200.09
-11.7483 178.57 8.8968 225 205.01
-11.8089 183.39 8.9426 230 209.93
-11.8665 188.22 8.9871 235 214.85
-11.9244 193.06 9.0307 240 219.77
-11.9798 197.89 9.0734 245 224.70
-12.0356 202.73 9.1154 250 229.62
-12.0893 207.58 9.1567 255 234.55
-12.1436 212.42 9.1976 260 239.48
-12.1962 217.27 9.2379
U-WCAP-16305-NP 36 TABLE A4 K1t Values for 1001F/hr Cooldown Curve (56 EFPY)
Water Vessel Temperature 100°F/hr Cooldown Temp.
@ 1/4T Location for 1/4T Thermal Stress
('F) 100 0F/hr Cooldown Intensity Factor (OF)
(KSI SQ. RT. IN.)
230 251.97 13.1653 225 246.90 13.1113 220 241.83 13.0578 215 236.76 13.0038 210 231.68 12.9503 205 226.61 12.8962 200 221.54 12.8428 195 216.47 12.7888 190 211.40 12.7354 185 206.33 12.6815 180 201.26 12.6282 175 196.18 12.5745 170 191.11 12.5214 165 186.04 12.4678 100F Cooldown Rate is limited by the Steady State Condition from T = 165 0F to 230 0F 160 155 150 145 140 135 130 125 120 115 110 105 100 95 90 85 80 75 70 65 60 180.97 175.90 170.83 165.76 160.69 155.62 150.55 145.47 140.40 135.33 130.26 125.19 120.12 115.05 109.98 104.92 99.85 94.78 89.71 84.64 79.57 12.4149 12.3615 12.3087 12.2556 12.2030 12.1501 12.0977 12.0450 11.9928 11.9403 11.8884 11.8362 11.7844 11.7325 11.6810 11.6292 11.5780 11.5265 11.4755 11.4242 11.3727 A.
A.