ML040630682

to WCAP-15068, Vogtle Electric Generating Plant, Unit 1, Heatup and Cooldown Limit Curves for Normal Operation.

ML040630682
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-15068, Rev 3
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Enclosure 11 Vogtle Electric Generating Plant Units I and 2 WCAPs 15068 Rev. 3 and 15161 Rev. 3

Westinghouse Non-Proprietary Class 3 WCAP-15068 February 2004 Revision 3 Vogtle Electric Generating Plant Unit 1 Heatup and Cooldown Limit Curves for Normal Operation

@)Westinghouse i[

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-15068, Revision 3 Vogtle Electric Generating Plant Unit 1 Heatup and Cooldown Limit Curves for Normal Operation T.J. Laubham February 2004 Approved: _9_If ry I/

J. Ghergurovich, Manager Reactor Component Design & Analysis Westinghouse Electric Company, LLC Energy Systems P.O. Box 355 Pittsburgh, PA 15230-0355

©2004 Westinghouse Electric Company LLC All Rights Reserved

PREFACE This report has been technically reviewed and verified by:

Reviewer: K. G Knight t; ,/t Record of Revision Revision l:

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-1 5315. All calculations for adjusted reference temperature remain unchanged from Revision 0. Text has been updated to support the use of the '96 App. G. Kic 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 WCAI'-

16142 to reflect the Vogtle Units I and 2 flange elimination justification rather than the generic flange elimination ustification contained in WCAP-15315. In addition, the thermal stress intensity factors %%erc added for the highest heatup and cooldown rate.

Revision 3:

In Table 4-4, the measured 30 ft-lb transition temperature shift for the surveillance program weld metal in Capsule Y has been adjusted to read 7.70 F. This is the ARTNDT without the ratio of 1.02 applied. The ARTNDT value for Capsule Y of the Intermediate Shell Plate B8805-3 (Transverse Orientation) was revised from 15.9 0 F to read 15.21F. Also, note (b) was added to provide an explanation for the 00 F 30 ft-lb transition temperature shifts. The material description for the Lower Shell Longitudinal Welds in Table 4-5 has been revised to be 10I -142A, B, & C. In Table 4-6, the ARTNDT with and without the ratio of 1.02 applied are presented for the Surveillance Weld Metal. Reference 11, WCAP-1 6142, was updated to Revision I as well.

Revision 3

iv TABLE OF CONTENTS PREFACE ............................................. iii LIST OF TABLES ............................................. v LIST OF FIGURES ............................................. vii EXECUTIVE

SUMMARY

.............................................. viii 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 CURVES .5-1 6 REFERENCES .6-1 APPENDIX A THERMAL STRESS INTENSITY FACTORS ............................................... A-I Revision 3

--- ,I 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/cm 2, E > 1.0 MeV) .................................. 4-3 Table 4-3 Calculated Integrated Neutron Exposure of the Vogtle Unit I 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 I Surveillance Capsule Data . 4-7 Table 4-7 Summary of the Vogtle Unit I 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 .4-10 Table 4-10 Calculation of the ART Values for the 1/4T Location @ 26 EFPY . 4-11 Table 4- 1 Calculation of the ART Values for the 3/4T Location @ 26 EFPY . 4-12 Table 4-12 Calculation of the ART Values for the 1/4T Location @ 36 EFPY. 4-1 3 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 I Heatup/Cooldown Curves ................ 4-15 Table 5-1 Vogtle Unit I Heatup Data at 26 EFPY Without Margins for Instrumentation Errors ................ 5-5 Revision 3

vi LIST OF TABLES -(Continued)

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

vii LIST OF FIGURES Figure 5-1 Vogtle Unit I Reactor Coolant System Heatup Limitations (Heatup Rates of 60 and I 000 F/lhr) Applicable to 26 EFPY (Without Margins for Instrumentation Errors) ......... 5-3 Figure 5-2 Vogtle Unit 1 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 1 Reactor Coolant System Heatup Limitations (Heatup Rates of 60 and I 00lFAOr) Applicable to 36 EFPY (Without Margins for Instrumentation Errors) . 5-7 Figure 5-4 Vogtle Unit I Reactor Coolant Systemr Cooldown Limitations (Cooldown Rates of 0, 20, 40, 60 and I 00 0 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 I for normal operation at 26 and 36 EFPY using the methodology, from the 1996 ASME Boiler and Pressure Vessel Code, Section Xl, Appendix G. Regulatory Guide 1.99, Revision 2 is used for the calculation of Adjusted Reference Temperature (ART) values at the l/4T and 3/4T location. The l/4T and 3/4T values are summarized in Table 4-14 and were calculated using the intermediate shell plate B8805-2 (i.e. the limiting beltline region material). The pressure-temperatire limit curves were generated without margins for instrumentation errors for heatup rates of 60 and l 00F/hr and cooldown rates of 0, 20, 40, 60 and l 00°FAir. These curves can be found in Figures 5-1 through 5-4. The Vogtle Unit I heatup and cooldown pressure-temperature limit curves havc been updated based on the use of the ASME Code Case N-6401"0 , which allows the use of the K1, methodology. and the elimination of the reactor vessel flange temperature requirement (Ref, WCAP-l 61421111).

Revision 3

I-I I INTRODUCTION 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-lb of impact energy and 35-mil lateral expansion (normal to the major working direction) minus 601F.

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"111.

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 cooldown pressure-temperature limit curves for normal operation. As a rgote, 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 Hieatup and Cooldown Limit Curves" 18 ].

The heatup and cooldowvn curves documented in this report were generated using the most limiting ART values and the NRC approved methodology documented in WCAP-14040-A, Revision 4181, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves" with one exception of the following. 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 1 "1 .

Revision 3 Introduction 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 I 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 specifies 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, Kit, for the metal temperature at that time. K1, 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"I3 & 101 of the ASME Appendix G to Section Xl. The K1c curve is given by the following equation:

K,. =33 .2 +2 0.7 3 4 *eIO2(ARiVDT)I (I

where, Kic 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 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-cooldowvn analysis is defined in Appendix G of the ASME Code as follows:

C* Kim + K1, < K1, (2)

where, Kin, = stress intensity factor caused by membrane (pressure) stress Ki, = stress intensity factor caused by the thermal gradients K1, = 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 Allowable Pressure-Temperature Relationships Allo'vable Pressure-Temperature Relationships  ; Revision 3

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

K it = M,,, x (pRi / 1) (3) where, Mm for an inside surface flaw is given by:

Mm = 1.85 for /i < 2, M = 0.9264f for 2< If<3.464, M = 3.21 for Ft > 3.464 Similarly, Mm for an outside surface flaw is given by:

Mm = 1.77 for FI <2, Mm = 0.893 Ft for 2< ft < 3.464, Mm = 3.09 for Fi >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 Mm 11 The maximum Ka produced by radial thermal gradient for the postulated inside surface defect of G-2 120 is K1 , = 0.953x 10'3 X CR x t2 .5, where CR is the cooldown rate in 'F/hr., or for a postulated outside surface defect, K1, = 0.753xl0 3 x HU x t2 5, 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-22 14-1. The temperature at any radial distance from the vessel surface can be determined from Fig. G-22 14-2 for the maximum thennal K, .

(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) Altemnatively; the K1 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 + 0.6322C1 + 0.4753C2 + 0.3855Cs)

• a (4)

Revision 3 Pressure-Temperature Relationships Criteria For Allowable Pressure-Temperature Relationships  ; Revision 3

3-3 or similarly, KIT during heatup for a l/4-thickness outside surface defect using the relationship:

K,, = (1.043Co + 0.630Ci + 0.48 IC2 + 0.401C3)

• A/; (5) where the coefficients Co, C1, C2 and C3 are determined from the thermal stress distribution at any specified time during the heatup or cooldown using the form:

ur(x) = Co + Ci(x / a) + C2(x / a)2 + C3(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 tile 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"I1I 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, K1, is determined by the metal temperature at tile 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 throulgi the vessel wall are calculated and then the corresponding (thermal) stress intensity factors. K1,. 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 flawv is always at the inside of the wall because the thernal 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.

The use of the composite curve in the cooldown analysis is necessary because control of the cooldo%'n 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 K1, at the 1/41 location for finite cooldown rates than for steady-state operation. Furthermore, if conditions exist so that the increase in K1 , exceeds K1,, the calculated allowable pressure during cooldown will be greater than the steady-state value.

Criteria For Allowable Pressure-Temperature Relationships Revision;3

3-4 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 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 I/4T defect at the inside of the wvall. The heattip 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 I14T crack during heatup is lower than the K1 , for the 1I4T crack during steady-state conditions at tile 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 KI, 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.

The second portion of the heatup analysis concerns the calculation of the pressure-temperature limitations for the case in which a l/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 tinder 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 1200 F for normal operation when the pressure exceeds 20 percent of the preservice hydrostatic test pressure (3106 psi), which is 621 psig for tile Vogtle Electric Generating Plant Unit 1. However, per WCAP-16142, "Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Vogtle Units I and 2 "I'", this requirement is no longer necessary when using the Fo loal rsueTmeaueRltosisRvso Criteria Criteria For Allowable Pressure-Temperature Relationships Revision 3

3-5 methodology of Code Case N-640 1"'). Hence, the Vogtle Electric Generating Plant Unit I heatup and cooldown limit curves wvill be generated without flange requirements included.

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

4-1 4 CALCULATION OFADJUSTED 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 = InitialRTNDT + A RTA,97 + M'argin (7)

Initial RTNDT is the reference temperature for the unirradiated material as defined in paragraph NB-233 1 of Section 111 of the ASME Boiler and Pressure Vessel Codell. 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 RTNI) - (8)

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

f {iepiiil.= f

• e ' (9) where x inches (vessel beltline thickness is 8.625 inches151) 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 projections171 and the results are presented in Section 6 of WCAP-15067 . The evaluation used the ENDF/B-VI scattering cross-section data set. This is consistent wvith 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 I reactor vessel. Additionally, the calculated surveillance capsule fluence values are presented in Table 4-3.

Revision 3 Reference Temperature 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)

Material Surface* / T 3/4 T Intermediate Shell Plate B8805-1 1.52 x 10o9 0.906 x IO'8 0.322 x 1018 Intermediate Shell Plate B8805-2 1.52 x 1O' 9 0.906 x 101" 0.322 x IO"s Intermediate Shell Plate B8805-3 1.52 x 1o09 0.906 x 101 0.322 x 10'"

Lower Shell Plate B8606-1 1.52 x I o'9 0.906 x 1018 0.322 x 10' Lower Shell Plate B8606-2 1.52 x 10'9 0.906 x lOIS 0.322 x 1018 Lower Shell Plate B8606-3 1.52 x 1019 0.906 x lOIS 0.322 x I0's Intermediate Shell Longitudinal 0.848 x 1O'9 0.505 x 1O" 0.180 x I0" Weld Seam 101-124A (00 Azimuth)

Intermediate Shell Longitudinal 1.52 x l0'9 0.906 x I018 0322 x lOts Weld Seam 101-124B & C (1200 &240°Azimuth)

Intermediate to Lower Shell 1.52 x 10'9 0.906 x 1O" 0.32'2 x\ '

Circumferential Weld Seam 101-171 Lower Shell Longitudinal 1.52 x 1019 0.906 x IO" 0.322x 10g Weld Seams 101-142A & C (600 & 3000 Azimuth)

Lower Shell Longitudinal 0.848 x 1019 0.505 x 1I0S 0.180 x 10" Weld Seam 101-142B (1800 Azimuth)

• Surface fluence values are calculated.

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/cm 2 , E > 1.0 MeV)

Material Surface* l T 3/4 T Intermediate Shell Plate B8805-1 2.09 x 1019 1.25 x 1019 0.442 x I0"8 Intermediate Shell Plate B8805-2 2.09 x 1O'9 1.25 x 1i0'9 0.442 x 108 Intermediate Shell Plate B8805-3 2.09 x 1019 1.25 x I0'9 0.442 X 10"8 Lower Shell Plate B8606-1 2.09 x i'9 1.25 x 0.442 x Lower Shell Plate B8606-2 2.09 x 1O' 9 1.25 x IO'9 0.442 x 10" Lower Shell Plate B8606-3 2.09 x 109 1.25 x IO'9 0.442 x 10:8 Intermediate Shell Longitudinal 1.17 x 1019 0.697x 10O9 0.248 x 10" Weld Seam 101 -124A (00 Azimuth)

Intermediate Shell Longitudinal 2.09 x 1019 1.25 x 0.442 x 108 Weld Seam 101-124B & C (1200 & 240°Azimuth) _

Intermediate to Lower Shell 2.09 x 10'9 1.25 x 10O9 0.442 x 10:8 Circumferential Weld Seam 101-171 Lower Shell Longitudinal 2.09 x 1019 1.25 x 10O9 0.442 x 10:8 Weld Seams 101 -142A & C (600 & 300° Azimuth)

Lower Shell Longitudinal 1.17 x 1019 0.697x 1O09 0.248 x 10:8 Weld Seam 101-142B (1800 Azimuth)

• Surface fluence values are calculated.

Calculation of Adjusted Reference Temperature Revision;3

44 TABLE 4-3 Calculated Integrated Neutron Exposure of the Vogtle Unit I Surveillance Capsules Tested to Date Capsule Fluence U 3.691 x 1 8 n/cm 2 , (E > 1.0 MeV)

Y 1.276 x 1019 n/cm 2 , (E > 1.0 MeV)

V 2.178 x 1019 n/cm 2 , (E > 1.0 MeV)

Margin is calculated as, Al = 2Ir, 2 + fi72. The standard deviation for the initial RTNDT margin term, CT, is 00 F 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, cy., is 177F for plates when surveillance capsule data is not used and 8.51F for plates when surveillance capsule data is used. For welds, a, is 280 F when surveillance capsule data is not used and 14WF when surveillance capsule data is used. In addition, ors need not exceed one-half the mean value of ARTNDT.

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

4-5 Contained in Table 4-4 is a summary of the Measured 30 fl-lb transition temperature shifts of the beltline materials'l 1 . These measured shift values were obtained using CVGRAPH, Version 4.114, 'which is a hyperbolic tangent curve-fitting program.

TABLE 44 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<')

Intermediate Shell Plate B8805- U 13.6 0 F 3 Y 31.9 0F (Longitudinal Orientation) V 42.7 0F Intermediate Shell Plate B8805- U O.OOF(b) 3 Y 15.2 0 F (Transverse Orientation) V 33.8 0F Surveillance Program U 25.0F Weld Metal Y 7.7 0F IV U 0.OOF(b)

Heat Affected Zone Y 20.80 F V 42.1OF Notes:

(a) Calculated using measured Charpy data and plotted using CVGRAPHI'l (b) Actual values forARTNDT are -9.13 (Plate), -1.3 (Weld), -19.35 (HAZ Capsule U). This physically should not occur; therefore for conservatism a value of zero will be used.

Calculation of Adjusted Reference Temperature Revision 3

4-6 Table 4-5 contains a summary of the weight percent of copper, the weight 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 were 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 15 & 9)

Material Description Cu (%) Ni(%) Initial RTsDT~~

Closure Head Flange B8801-1 0.70 200F Vessel Flange B8802-1 0.71 0F Intermediate Shell Plate B8805-1 0.083 0.597 0F Intermediate Shell Plate B8805-2 0.083 0.61 200 F Intennediate Shell Plate B8805-3 0.062 0.598 300 F Lower Shell Plate B8606-1 0.053 0.593 200 F Lower Shell Plate B8606-2 0.057 0.60 20OF Lowver Shell Plate B8606-3 0.067 0.623 10F Intermediate Shell Longitudinal 0.042(c) 0.102 -80T WVelds, 101-124A, B & C(b)

Lower Shell Longitudinal Welds, 0.042(c) 0.102 -80 0 F 101-142A, B & C(b)

Circumferential Weld 1 0 1 -1 7 1 (b) 0.042(c) 0.102 -80 0 F Surveillance Program Weld Metal 0.040 0.102 Notes:

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

(b) All welds, including the surveillance weld, were fabricated with weld w-ire heat number 83653, Linde 0091 Flux, Lot No. 3536. Per Regulatory Guide 1.99, Revision 2, "weight percent copper " and "weight percent nickel" are the best-estimate values for the material.

which will normally be the mean of the measured values for a plate or forging or for weld samples made with the weld wire heat number that matches the critical vessel weld."

(c) The copper weight percent of 0.042 was obtained using all available data for that heat of weld wire per reference 9. This value is more conservative than that documented (0.039) in Vogtle Electric Generating Plant's "Pressure and Temperature Limits Report".

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

4-7 TABLE 4-6 Calculation of Chemistry Factors using Vogtle Unit I Surveillance Capsule Data Material Capsule Capsule i<') FFob) ARTNDT( ) FF*ARTND FF2 T

Intermediate Shell U 0.3691 0.725 13.6 9.9 0.526 Plate B8805-3 Y 1.276 1.068 31.9 34.1 1.141 (Longitudinal) V 2.178 1.211 42.7 51.7 1.467 Intermediate Shell U 0.3691 0.725 0(e) 0.0 0.526 Plate B8805-3 Y 1.276 1.068 15.2 16.2 1.141 (Transverse) V 2.178 1.211 33.8 40.9 1.467 SUM 152.8 6.268 CFBS80 5 s. = X(FF

• RTNDT) +. E(FF2) = (I 52.8) + (6.268) = 24.41F Surveillance Weld U 0.3691 0.725 2 5 .5(2 5 .0 )(d) 18.5 0.526 Metal Y 1.276 1.068 7 .9( 7 .7 )(d) 8.4 1.141 V 2.178 1.211 0() 0.0 1.467 SUM 26.9 3.134 l CFWded = X (FF

• RTNDT) -- Y(FF2 ) = (26.9) * (3.134) = 8.6° F Notes:

(a) f= Calculated fluence from capsule V dosimetry analysis results°7 ), (x 1019 n/cm2 , E > 1.0 MeV).

(b) FF = fluence factor = f (0 28 -. 1'log f (c) ARTNDT values are the measured 30 ft-lb shift values.

(d) The surveillance weld metal ARTNDT values have been adjusted by a ratio factor of 1.02.

(e) Actual values for ARTNDT are -9.58 (Plate) and -1.34 (Weld). This physically should not occur:

therefore for conservatism a value of zero will be used for this calculation.

Calculation of Adjusted Reference Temperature Revision 3

4-8 TABLE 4-7 Summary of the Vogtle Unit I Reactor Vessel Beltline Material Chemistry Factors Based on Regulatory Guide 1.99, Revision 2, Position 1.1 and Position 2.1 Material Chemistry Factor Position 1.12) Position 2.1(2)

Intermediate Shell Plate B8805-1 53.1OF Intermediate Shell Plate B8805-2 53.1 OF Intermediate Shell Plate B8805-3 38.4 0 F 24.4 0 F Lower Shell Plate B8606-1 32.8 0 F Lower Shell Plate B8606-2 35.2 0 F Lower Shell Plate B8606-3 41.9°F Intermediate Shell Longitudinal Welds. 34.5 0 F 8.6 0 F 101-124A, B & CI')

Lower Shell Longitudinal Welds. 34.5 0 F 8.60F 101-442A, B & C"'

Circumferential Weld 101-171734.5WF 8.6WF Surveillance Program Weld Metal"` 33.7 0 F Notes:

(a) Regulatory Guide 1.99, Revision 2, Position 1.1 or Position 2.1 methodology.

(b) All welds, including the surveillance wveld, were fabricated with weld wire heat numbers 83653, Linde 0091 Flux, Lot No. 3536.

Temperature Revision 3 ofAdjusted Calculation of Reference Temperature Adjusted Reference 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 I 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 Cooldow'n Curves Material 14 T f 1/4 T FF 2 ' 3/4 Tf 3/4 T FF(b) 2 2 (nlcm , E > 1.0 (n/cm . E >1.0 NIcV')

_lel')

Intermediate Shell Plate B8805-1 0.906 x 10"9 0.972 0.322 x 10") 0.689 Intermediate Shell Plate B8805-2 0.906 x 1019 0.972 0.322 x 10"' 0.689 Intermediate Shell Plate B8805-3 0.906 x 109e 0.972 0.322 x 10") 0.689 Lower Shell Plate B8606-1 0.906 x 1019 0.972 0.322 x 10"' 0.689 Lower Shell Plate B8606-2 0.906 x 1019 0.972 0.322 I10" 0.689 l Lower Shell Plate B8606-3 0.906 x 109 0.972 0.322 x I 0"' 0.689 Intermediate Shell Longitudinal 0.505 x 1019 0.809 0.1 80 x I0"' 0.545 Weld Seam 101-124A (00 Azimuth)

Intermediate Shell Longitudinal 0.906 x 10"9 0.972 0.3'2 x 10"' 0.689 Weld Seams 101-124B & C (1200 & 2400 Azimuth)

Intermediate to Lower Shell 0.906 x 10o9 0.972 0.322 x 10"' 0.68X)

Circumferential Weld Seam 101-171 Lower Shell Longitudinal Weld 0.906 x 1019 0.972 0.322 x 10"' 0.689 Seams 101-142A & C (600 & 3000 Azimuth)

Lower Shell Longitudinal Weld 0.505 x 1019 0.809 0.180 x I0o" 0.545 Seam 101-142B (1800 Azimuth)

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

4-10 TABLE 4-9 Summary of the Calculated Fluence Factors used for the Generation of the 36 EFPY Heatup and Cooldown Curves Material  %/4T f 1/4 T FF'a) 3/4 Tf 3/4 T FF

2 2 (n/cm , E > 1.0 (n/cm , E > 1.0 MeV') MeV')

Intermediate Shell Plate B8805-1 1.25 x 10' 9 1.06 0.442 x 1O'9 0.773 Intermediate Shell Plate B8805-2 1.25 x IO'9 1.06 0.442 x l0'9 0.773 Intermediate Shell Plate B8805-3 1.25 x 10' 9 1.06 0.442 x 10'9 0.773 Lower Shell Plate B8606-1 1.25 x IO'9 1.06 0.442 x iO'9 0.773 Lower Shell Plate B8606-2 1.25 x 10'9 1.06 0.442 x I0"' 0.773 Lower Shell Plate B8606-3 1.25 x 1O'9 1.06 0.442 x 1019 0.773 Intermediate Shell Longitudinal 0.697 x 1019 0.899 0.248 x 10'9 0.622 Weld Seam 101-124A (00 Azimuth)

Intermediate Shell Longitudinal 1.25 x 10'9 1.06 0.442 x 10'9 0.773 Weld Seams 101-124B & C (1200 & 2400 Azimuth)

Intermediate to Lower Shell 1.25 x 10' 9 1.06 0.442 x 10'9 0.773 Circumferential Weld Seam 101-171 Lower Shell Longitudinal Weld 1.25 x 10'9 1.06 0.442 x 10' 0.773 Seams 101-142A & C (600 & 3000 Azimuth)

Lower Shell Longitudinal Weld 0.697 x 1019 0.899 0.248 x 10'9 0.622 Seam 101-142B (1800 Azimuth)

Notes:

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

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

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

4-11 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 cooldowvn curves.

TABLE 4-1 0 i i

Calculation of the ART Values for the 1/4T Location @ 26 EFPY Material RG 1.99 R2 CF FF IRTNDT t ') ARTNDTIC) Margin ART~b)

Method (OF)

Intermediate Shell Plate B8805-1 Position 1.1 53.1 0.972 0 51.6 34 86 i Intermediate Shell Plate B8805-2 Position 1.1 53.1 0.972 20 51.6 34 106 i Intermediate Shell Plate B8805-3 Position 1.1 38.4 0.972 30 37.3 34 101 i i

i Position 2.1 24.4 0.972 30 23.7 17 71 Lower Shell Plate B8606-1 Position 1.1 32.8 0.972 20 31.9 31.9 84 Lower Shell Plate B8606-2 Position 1.1 35.2 0.972 20 34.2 34 88 Lower Shell Plate B8606-3 Position 1.1 41.9 0.972 10 40.7 34 85 i

i Inter. Shell Longitudinal Weld Position 1.1 34.5 0.809 -80 27.9 27.9 -24 Seam 10 I- 124A(0 0 Azimuth) Position 2.1 8.6 0.809 -80 7.0 7.0 -66 i i

I Inter. Shell Long. Weld Seams Position 1.1 34.5 0.972 -80 33.5 33.5 -13 i

101-124B,C (1200, 2400 Azimuth) Position 2.1 8.6 0.972 -80 8.4 8.4 -63 I Intermediate to Lower Shell Position 1.1 34.5 0.972 -80 33.5 33.5 -13 i

Girth Weld Seam 101-171 Position 2.1 8.6 0.972 -80 8.4 8.4 -63 Lower Shell Long. Weld Seams Position 1.1 34.5 0.972 -80 33.5 33.5 -1, i

10I-142A,C (600, 3000 Azimuth) Position 2.1 8.6 0.972 -80 8.4 8.4 -6..3 Lower Shell Long. Weld Seam Position 1.1 34.5 0.809 -80 27.9 27.9 -24 101-142B (1800 Azimuth) Position 2.1 8.6 0.809 -80 7.0 7.0 -66 Notes:

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

(b) ART = Initial RTNDT + ARTNDT + Margin (7F); (Rounded per ASTM E29, using the "Rounding Method")

(c) ARTNDT = CF

• FF Temperature Revision 3 Calculation of Ca.1culation Adjusted Reference of Adjusted Reference 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 IRTNDT t') &RTNDT(C) Margin ARTzb)

Method (OF)

Intermediate Shell Plate B8805-1 Position 1.1 53.1 0.689 0 36.6 34 71 Intermediate Shell Plate B8805-2 Position 1.1 53.1 0.689 20 36.6 34 91 Intermediate Shell Plate B8805-3 Position 1.1 38.4 0.689 30 26.5 26.5 83 Position 2.1 24.4 0.689 30 16.8 16.8 64 Lower Shell Plate B8606-1 Position 1.1 32.8 0.689 20 22.6 22.6 65 Lower Shell Plate B8606-2 Position 1.1 35.2 0.689 20 24.3 24.3 69 Lower Shell Plate B8606-3 Position 1.1 41.9 0.689 10 28.9 28.9 68 Inter. Shell Longitudinal Weld Position 1.1 34.5 0.545 -80 18.8 18.8 -42 Seam 101 -124A(00 Azimuth) Position 2.1 8.6 0.545 -80 4.7 4.7 -71 Inter. Shell Long. Weld Seams Position 1.1 34.5 0.689 -80 23.8 23.8 -32 101 -124 B,C (1200, 2400 Azimuth) Position 2.1 8.6 0.689 -80 5.9. 5.9 -68 Intermediate to Lower Shell Position 1.1 34.5 0.689 -80 23.8 23.8 -32 Girth Weld Seam 101 - 171 Position 2.1 8.6 0.689 -80 5.9 5.9 -68 Lower Shell Long. Weld Seams Position 1.1 34.5 0.689 -80 23.8 23.8 -3 101-142A,C (600, 3000 Azimuth) Position 2.1 8.6 0.689 -80 5.9 5.9 *b8 Lower Shell Long. Weld Seam Position 1.1 34.5 0.545 -80 18.8 18.8 -42 101- 142B (I80°Azimuth) Position 2.1 8.6 0.545 -80 4.7 4.7 .71 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

4-13 TABLE 4-12 Calculation of the ART Values for the 1/4T Location @ 36 EFPY Material RG 1.99 R2 CF FF IRTNDT12) ARTNDTf ) Margin ARTb)l Method ('F)

Intermediate Shell P.late B8805- Position 1.1 53.1 1.06 0 56.3 34 90 Intermediate Shell Plate B8805-2 Position 1.1 53.1 1.06 20 56.3 34 110 Intermediate Shell Plate B8805-3 Position 1.1 38.4 1.06 30 40.7 34 105 Position 2.1 24.4 1.06 30 26.0 17 73 Lower Shell Plate B8606-1 Position 1.1 32.8 1.06 20 34.8 34 89 Lower Shell Plate B8606-2 Position 1.1 35.2 1.06 20 37.3 34 91 Lower Shell Plate B8606-3 Position 1.1 41.9 1.06 10 44.4 34 88 Inter. Shell Longitudinal Weld Position 1.1 34.5 0.899 -80 . 1.0 31 -18 0

Seam 101 -124A(0 Azimuth) Position 2.1 8.6 0.899 -30 7.7 7.7 -65 Inter. Shell Long. Weld Seams Position 1.1 34.5 1.06 -80 36.6 36.6 -7 10I-124B,C (120°, 240° Azimuth) Position 2.1 8.6 1.06 -80 9.1 9.1 -62 Intermediate to Lower Shell Position 1.1 34.5 1.06 -80 36.6 36.6 -7 Girth Weld Seam 101-171 Position 2.1 8.6 1.06 -80 9.1 9.1 -62 Lower Shell Long. Weld Seams Position 1.1 34.5 1.06 -80 36.6 36.6 -7 10I-142A,C (600, 300° Azimuth) Position 2.1 8.6 1.06 -80 9.1 9.1 -62 Lower Shell Long. Weld Seam Position 1.1 34.5 0.899 -80 31.0 31 -IX 101-142B (1800 Azimuth) Position 2.1 8.6 0.899 -80 7.7 7.7 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 3/4T Location @ 36 EFPY Material RG 1.99 R2 CF FF IRTNDTz ARTNDT! )Margin ART(b)

Method (°F)

Intermediate Shell Plate B8805-1 Position 1.1 53.1 0.773 0 41.0 34 75 Intermediate Shell Plate B8805-2 Position 1.1 53.1 0.773 20 41.0 34 95 Intermediate Shell Plate B8805-3 Position 1.1 38.4 0.773 30 29.7 29.7 89 Position 2.1 24.4 0.773 30 18.9 17 66 Lower Shell Plate B8606-1 Position 1.1 32.8 0.773 20 25.4 25.4 71 Lower Shell Plate B8606-2 Position 1.1 35.2 0.773 20 27.2 27.2 74 Lower Shell Plate B8606-3 Position 1.1 41.9 0.773 10 32.4 32.4 75 Inter. Shell Longitudinal Weld Position 1.1 34.5 0.622 -8021.5 21.5 -37 Seam 101-124A(0 0 Azimuth) Position 2.1 8.6 0.622 -80 5.3 5. -69 Inter. Shell Long. Weld Seams Position 1.1 34.5 0.773 -80 26.7 26.7 -27 10I-124B,C (1200, 2400 Azimuth) Position 2.1 8.6 0.773 -80 6.6 6.6 -67 Intermediate to Lower Shell Position 1.1 34.5 0.773 -80 26.7 26.7 -27 Girth Weld Seam 101-171 Position 2.1 8.6 0.773 -80 6.6 6.6 -67 Lower Shell Long. Weld Seams Position 1.1 34.5 0.773 -80 26.7 26.7 -27 101 -142A,C (600, 3000 Azimuth) Position 2.1 8.6 0.773 -80 6.6 6.6 -67 Lower Shell Long. Weld Seam Position 1.1 34.5 0.622 -80 21.5 21.5 -37 10I-142B (180° Azimuth) Position 2.1

• 8.6 0.622 -80 5.3 5.3 -69 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 Reference Temperature Adjusted Reference of Adjusted Temperature Revision 3

4-15 The intermediate shell plate B8805-2 is the limiting beltline material for all heatup and cooldown curves 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 I reactor vessel heatup and cooldown curves.

TABLE 4-14 Summary' of the Limiting ART Values Used in the Generation of the Vogtle Unit I Heatup/Cooldown Curves EFPY 1/4T Limiting ART 3/4T Limiting ART 26 1060 F 910 F 36 1H10F 950 F Revision 3 Reference Temperature Calculation of Adjusted Reference Temperature Revision 3

5-1 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 Section 3 and 4 of this report. This approved methodology is also presented in WCAP- 14040-Ai'8.

Figures 5-1 and 5-3 present the heatup curves with no margins for possible instrumentation errors for heatup rates of 60 and 1000 F/hr. These curves are applicable for 26 EFPY and 36 EFPY respectively, for the Vogtle Unit I 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 l 00T/hr. These curves are also applicable for 26 EFPY and 36 EFPY. respectively for the Vogtle Electric Generating Plant Unit I 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.

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 Xi of the ASME Code13l as follows:

1.5K irn <Kit (10)

where, K, is the stress intensity factor covered by membrane (pressure) stress.

K1 33.2 + 2 0. 7 3 4 e10

}= 2(TRTNDT)1 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 heattip 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.

Heatup and Cooldown Pressure Temperature Limit Curves Revision 3

5-2 Figures 5-1 through 54 define all of the above limits for ensuring prevention of nonductile failure for the Vogtle Electric Generating Plant Unit I reactor vessel. The data points for the heatup and cooldown pressure-temperature limit curves shown in Figures 5-1 through 54 are presented in Tables 5-1 through 5-4, respectively.

tieatup and Cooldown Pressure Temperature Limit Curves Revision 3 Heatup and cooldoxvri Pressure 1-cmperature Limit Curves Revision 3

5-3 MATERIAL PROPERTY BASIS LIMITING MATERIAL: INTERMEDIATE SHELL PLATE B8805-2 LIMITING ART VALUES AT 26 EFPY: I/4T, 1060 F 3/4T, 91 -F 2500 2250 2000 1750 a 1500 en E 1250 35 1000 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 I Reactor Coolant System Heatup Limitations (Heatup Rates of 60 and I 000 F/hr) Applicable to 26 EFPY (Without Margins of for Instrumentation Errors)

Limit Curves Revision 3 Heatup and Cooldo%%m Temperature Limit Pressure Temperature Cooldown Pressure Curves  ; Revision 3

5-4 MATERIAL PROPERTY BASIS LIMITING MATERIAL: INTERMEDIATE SHELL PLATE B8805-2 LIMITING ART VALUES AT 26 EFPY: 1/4T, I 060 F 3/4T, 91OF 2500 2250 2000 1750 X, 1500 co 0

e I 1000 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 I 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)

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

5-5 TABLE 5-1 Vogtle Unit I Heatup Data at 26 EFPY Without Margins for Instrumentation Errors 601F/hr Ileatup 60 °F/hr Criticality 100F/hr Ileatup 100°Flhr Critical. Leak Test Limit Limit I Limit T P T P T P T P T P 60 0 166 0 60 0 166 0 149 2000 60 759 166 775 60 748 166 748 166 2485 65 775 166 782 65 748 166 748 70 777 166 777 70 748 166 748 75 777 166 777 75 748 166 748 80 777 166 781 80 748 166 748 85 781 166 790 85 748 166 748 90 790 166 802 90 748 166 748 95 802 166 819 95 748 166 752 100 819 166 839 100 752 166 759 105 839 166 863 105 759 166 769 110 863 166 891 110 769 166 782 115 891 166 923 115 782 166 799 120 923 166 959 120 799 166 818 125 959 170 1000 125 818 170 842 130 1000 175 1046 130 842 175 868 135 1046 180 1097 135 868 180 899 140 1097 185 1154 140 899 185 934 145 1154 190 1218 145 934 190 974 150 1218 195 1289 150 974 195 1018 155 1289 200 1367 155 1018 200 1068 160 1367 205 1453 160 1068 205 1124 165 1453 210 1549 165 1124 210 1186 170 1549 215 1655 170 1186 215 1254 175 1655 220 1772 175 1254 220 1331 180 1772 225 1901 180 1331 225 1415 185 1901 230 2044 185 1415 230 1509 190 2044 235 2201 190 1509 235 1613 195 2201 240 2375 195 1613 240 1727 200 2375 200 1727 245 1854 205 1854 250 1993 210 1993 255 2147 215 2147 260 2317 220 2317 L I -&

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

5-6 TABLE 5-2 Vogtle Unit 1 Cooldown Data at 26 EFPY Without Margins for Instrumentation Errors Steady State 201F/hr 40WF/hr 60OF/hr 1000F/hr T P T P T P T P T P 60 0 60 0 60 0 60 0 60 0 60 759 60 721 60 684 60 648 60 578 65 775 65 739 65 703 65 669 65 603 70 792 70 758 70 724 70 692 70 631 75 812 75 779 75 747 75 717 75 662 80 833 80 802 80 773 80 746 80 697 85 857 85 828 85 802 85 777 85 735 90 883 90 857 90 833 90 812 90 778 95 912 95 889 95 868 95 850 95 825 100 944 100 924 100 907 100 893 100 878 105 979 105 963 105 950 105 940 105 936 110 1018 110 1006 110 997 110 993 115 1062 115 1053 115 1049 120 1109 120 1106 125 1162 130 1221 135 1285 140 1356 145 1435 150 1522 155 1618 160 1725 165 1842 170 1972 175 2116 180 2274 185 2449 Revision 3 Heatup and Cooldown Heatup and Pressure Temperature Cooldowvn Pressure Limit Curves Temperature Limit Curves Revision 3

5-7 MATERIAL PROPERTY BASIS LIMITING MATERIAL: INTERMEDIATE SHELL PLATE B8805-2 LIMITING ART VALUES AT 36 EFPY: 1/4T, II 0F 3/4T, 950 F 2500 2250 2000 1750 R 1500 1 1250

• 5 1000 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 I Reactor Coolant System Heatup Limitations (Heatup Rate of 60 and 1000 F/hr) Applicable to 36 EFPY (Without Margins of for Instrumentation Errors)

Curves Limit Curves Revision 3 Heatup and CooldoNm Pressure Temperature Coaldown Pressure Temperature Limit Revision 3

5-8 MATERIAL PROPERTY BASIS LIMITING MATERIAL: INTERMEDIATE SHELL PLATE B8805-2 LIMITING ART VALUES AT 36 EFPY: 1/4T, II OcF 3/4T. 950 F 2500 2250 2000 1750 1500 1250 a

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 I Reactor Coolant System Cooldownii Limitations (Cooldown Rates of 0, 20, 40, 60 and I 00 0 F/hr) Applicable to 36 EFPY (Without Margins for Instrumentation Errors)

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

5-9 TABLE 5-3 Vogtle Unit I Heatup Data at 36 EFPY Without Margins for Instrumentation Errors 60°Flhr Ileatup 60 °F/hr Criticality 100°F/hr lleatup I00°F/hr Critical. Leak Test Limit Limit Limit T P T P T P T 1. T P 60 0 170 0 60 0 170 0 153 2000 60 747 170 760 60 730 170 730 170 2485 65 760 170 763 65 730 170 733 70 760 170 770 170 730 170 739 75 760 170 782 75 730 170 747 80 760 170 796 80 730 170 759 85 763 170 815 85 730 170 774 90 770 170 836 90 730 170 791 95 782 170 862 95 730 170 812 100 796 170 891 100 733 175 837 105 815 170 925 105 739 180 865 110 836 170 962 110 747 185 897 115 862 175 1005 115 759 190 933 120 891 180 1052 120 774 195 974 125 925 185 1105 125 791 200 1020 130 962 190 1163 130 812 205 1071 135 1005 195 1228 135 837 210 1128 140 1052 200 1300 140 865 215 1191 145 1105 205 1380 145 897 220 1261 150 1163 210 1468 150 933 225 1339 155 1228 215 1566 155 974 230 1426 160 1300 220 1674 160 1020 235 1521 165 1380 225 1793 165 1071 240 1627 170 1468 230 1925 170 1128 245 1743 175 1566 235 2070 175 1191 250 1872 180 1674 240 2231 180 1261 255 2014 185 1793 245 2408 185 1339 260 2171 190 1925 190 1426 265 2344 195 2070 195 1521 200 2231 200 1627 205 2408 205 1743 210 1872 215 2014 220 2171 225 2344 Limit Curves Revision 3 Heatup and Pressure Temperature Cooldown Pressure and Cooldowm Temperature Limit Curves Revision 3

5-10 TABLE 5-4 Vogtle Unit I Cooldowvn Data at 36 EFPY Without Margins for Instrumentation Errors Steady State 2 0 1F/hr 401F/hr 601F/hr 100 0 F/hr T P T P T P T P T P 60 0 60 0 60 0 60 0 60 0 60 747 60 709 60 670 60 633 60 559 65 762 65 725 65 688 65 652 65 582 70 778 70 742 70 707 70 673 70 608 75 796 75 762 75 728 75 696 75 637 80 816 80 783 80 752 80 722 80 668 85 838 85 807 85 778 85 751 85 704 90 862 90 834 90 807 90 783 90 743 95 889 95 863 95 840 95 819 95 787 100 918 100 895 100 875 100 858 100 835 105 951 105 931 105 915 105 902 105 889 110 987 110 971 110 959 110 950 110 948 115 1027 115 1015 115 1007 115 1004 I

120 1071 120 1063 120 1061 I 125 1120 125 1117 130 1173 i 135 1233 i i

i 140 1299 I I

145 1371 I 150 1452 i 155 1541 160 1639 165 1747 i i

170 1867 175 2000 180 2146 185 2308 Limit Curves Revision 3 1-Ieatup and Heatup Pressure Temperature Cooldown Pressure and Cooldown Temperature Limit Curves i 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 Xl of the ASME Boiler and Pressure Vessel Code, Appendix G. "Fracture Toughness Criteria for Protection Against Failure.", Dated December 1995.

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

5 WCAP-1 3931, Rev. 1, "Analysis of Capsule Y from the Georgia Power Company Vogtle Unit I Reactor Vessel Radiation Surveillance Program", M.J. Malone, et al., August 1995.

6 1989 Section 111, Division 1 of the ASME Boiler and Pressure Vessel Code, Paragraph NB-233l.

"Material for Vessels".

7 WCAP-15067, "Analysis of Capsule V from the Georgia Power Vogtle Electric Generating Plant Unit I Reactor Vessel Radiation Surveillance Program", T. J. Laubham, et al., September 1998.

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.

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 I1- CEOG lask 902, June 1997.

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

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

Revision 3 References Revision 3

A-l APPENDIX A Thermal Stress Intensity Factors (Kit)

The followving page contain the thermal stress intensity factors (Kit) 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:

• 1/4T Radius = 88.812"

• 3/4T Radius = 93.125" Revision 3 Keterences Keferences Revision 3

A-2 TABLE Al Kj, Values for I000 F/hr Heatup Curve (26 EFPY)

Vessel Temperature 1/4T':hermal Vessel Temperature 314T Thermal Water @ 1/4T Location for Stress @ 314T Location for Stress Temp. 100°F/hr Heatup intensity Factor 100°Flhr Heatup Intensity Factor (OF) I (0 ) (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 Note: The 100F/hr Heatup Curve is limited entirely by the 314T Location Revision 3 References Revision 3

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

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

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 15.4120 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 References Revision 3

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

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

60 55.99 -0.9954 55.04 0.4731 65 58.56 -2A522 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 I.

-14.7007 155.68

.1 11.1109 Note: The 100°F/hr Heatup Curve is limited entirely by the 3/4T Location Revision 3 References Revision 3

I A-5 TABLE A4 Kj1 Values for 100 0 F/hr Cooldown Curve (36 EFPY)

. Vessel Temperature 100lF/hr Cooldown Water @ 1/4T Location for 1/4T Thermal Stress Temp. 100l/hr Cooldown Intensity Factor (OF) (OF) (KSI SQ. RT. IN.)

sop I5 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 15.4120 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<elerences Revision 3 References Revision 3

Enclosure 5 Vogtle Electric Generating Plant Units 1 and 2 Affidavit for Withholding, Proprietary Information Notice, Copyright Notice

Westinghouse Westinghouse Electric Company Nuclear Services P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission Directtel: (412) 374-5282 Document Control Desk Direct fax: (412) 3744011 Washington, DC 20555-0001 e-mail: galemnjsewestinghouse.com Our ref: CAW-03-1736 November 13, 2003 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE

Subject:

WCAP-16142-P, "Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Vogtle Units I and 2" (Proprietary)

The proprietary information for which withholding is being requested in the above-referenced report is further identified in Affidavit CAW-03-1736 signed by the owner of the proprietary information, Westinghouse Electric Company LLC. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.790 of the Commission's regulations.

Accordingly, this letter authorizes the utilization of the accompanying affidavit by Southern Nuclear Operating Company.

Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-03-1736, and should be addressed to J. S. Galembush, Acting Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.

Very truly yours, of J. embush, Acting Manager Regulatory Compliance and Plant Licensing Enclosures cc: D. Holland B. Benney E. Peyton A BNFL Group company

CAW-03-1736 bcc: J. S. Galembush (ECE 4-7A) IL R. Bastien, IL, IA (Nivelles, Belgium)

C. Brinkman, IL, IA (Westinghouse Electric Co., 12300 Twinbrook Parkway, Suite 330, Iockville, MD 20852)

RCPL Administrative Aide (ECE 4-7A) I L, I A (letter and affidavit only)

A BNFL Group company

CAW-03-1736 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:

ss COUNTY OF ALLEGHENY:

Before me, the undersigned authority, personally appeared J. S. Galembush, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:

J. S. Galembush, Acting Manager Regulatory Compliance and Plant Licensing Sworn to and subscribed before me this j,3 day of 2003 Notary Public

• ~~~;h6AIO6EE,,,NotarWa Seal La Shaz L. od,NotaryPubLc W Mor o.

Mnej", Boro, Afleeny County

,P Conis.on Ex es January 29.2007 Member. Pen.nsnivala Assodation Of Notares

2 CAW-03-1736 (1) I am Acting Manager, Regulatory Compliance and Plant Licensing, in Nuclear Services, Westinghouse Electric Company LLC (Westinghouse), and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.

(2) 1am making this Affidavit in conformance with the provisions of 10 CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse "Application for Withholding" accompanying this Affidavit.

(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.

(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.

(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.

(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.

Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:

(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of

3 CANV-03-1736 Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.

(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.

(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.

(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.

(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.

(f) It contains patentable ideas, for which patent protection may be desirable.

There are sound policy reasons behind the Westinghouse system which include the following:

(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.

(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.

(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.

4 CAW-03-1 736 (d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.

(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.

(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Commission.

(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.

(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in WCAP-16142-P, "Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Vogtle Units I and 2," (Proprietary) dated November, 2003, being transmitted by Southern Nuclear Operating Company letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted for use by Westinghouse for Vogtle Units 1 and 2 is expected to be applicable for other licensee submittals in response to certain NRC requirements for justification of the elimination of the flange temperature requirement for the reactor vessel P-T limit curves.

This information is part of that which will enable Westinghouse to:

5 CAW-03-1736 (a) Support an exemption request to eliminate the flange temperature requirement.

(b) Document the basis for the postulated flaw size, the detail of the stress analyses, and the material properties.

(c) Provide the potential effect of thermal aging of the reactor vessel steel.

Further this information has substantial commercial value as follows:

(a) Westinghouse plans to sell the use of similar information to its customers for purposes of meeting NRC Requirements for Licensing documentation.

(b) Westinghouse can sell support and defense of elimination of the flange temperature requirement.

(c) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.

Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar calculations and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.

The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.

In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.

Further the deponent sayeth not.

PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant-specific review and approval.

In order to conform to the requirements of 10 CFR 2.790 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR 2.790(b)(1).

COIPYRIGIIT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.