NL-15-2034, Calculation No. 1001527.305, Revision 2, Hatch Unit 2 P-T Curve Calculation for 37 and 50.1 EFPY
Text
-Stru ctural Integrity Associates, Inc.
File No.: 1001527.305 l/*
Project No.: 1400365 CALCULATION PACKAGE
{Quality Program: [] Nuclear [] Commercial PROJECT NAME:
Plant Hatch Unit 1&2 P-T Curve Evaluation CONTRACT NO.:
P0: SNC 19354, Rev. 1 CONTRACT: 19354, Rev. 4 CLIENT:
PLANT:
Southern Nuclear Operating Co.
Hatch Nuclear Plant, Unit 2 CALCULATION TITLE:
Hatch Unit 2 P-T Curve Calculation for 37 and 50.1 EFPY Document Affected Project Manager Peae~)&Cekrs Reiin PgsRevision Description Approval Peae~)&Cekrs Reiio agsSignature
& Date Signatures & Date 01
- 45 Initial Issue Responsible Engineer A-i -A-3 B-i - B-46 D. V. Sommerville 12/30/2011 C. Oberembt 12/30/2011 Responsible Verifier D. V. Sommerville 12/30/2011 116 Citations for References Responsible Engineer
[1] and [2] have been updated to show citation for NRC approved D.V.t Sommerville M. Qin Versions. Citation for 9/19/20 139//23 Reference [9] has been updated to show current Responsible Verifiers revision. Reference [9]
was revised for the same reason as identified above for References [1] and
[2]. No technical D. V. Sommerville changes are made for this9//23 revision.
Page 1 of 45 F0306-01RI
V S*tructural Integrity Associates, Inc. File No.: 1001527.305 C L U A INP C A EProject No.: 1001527 CALCUL TION P CKAGEQuality Program: [] Nuclear
[-- Commercial CALCULATION TITLE:
Hatch Unit 2 P-T Curve Calculation for 37 and 50.1 EFPY Document Affected Project Manager Preparer(s) & Checker(s)
Revision Description ApprovalSintrs&De Revision Pages Signature & DateSintrs&De 2
6, 7, 13, 14, 15, Revised to incorporate Responsible Engineer 17 -45 updated fluence data and*w
//
A-2, A-3 to address NRC condition B B-46 for SI!R-05-044-Rev. 1-A regarding lowest service D. V. Sommerville temperature.
9/10/2014 D. V. Sommerville for C. J. Oberembt 9/10/2014 Responsible Verifier D. V. Sommerville 9/10/2 014 Page 2 of 45 F0306-01R1
VStructural Integrity Associates, Itcof Table of Contents
1.0 INTRODUCTION
........................................................................... 6 2.0 METHODOLOGY........................................................................... 6 3.0 ASSUMPTIONS........................................................................... 11 4.0 DESIGN INPUTS.......................................................................... 13 5.0 CALCULATIONS.................. i...................................................... 14 5.1 Pressure Test (Curve A)........................................................... 15 5.2 Normal Operation - Core Not Critical (Curve B)............................... 15 5.3 Normal Operation - Core Critical (Curve C).................................... 16
6.0 CONCLUSION
S........................................................................... 16
7.0 REFERENCES
............................................................................. 17 APPENDIX A : P - T CURVE INPUT LISTING............................................. A-I APPENDIX B:* SUIPPORTING CALCULATIONS.......................................... B-i File No.: 1001527.305 Revision: 2 Page 3 of 45 F0306-01R1
Structural Integrity Associates,/Ino.*
List of Tables Table 1: Summary of Minimum Temperature Requirements for P-T Limit Curves..................
18 Table 2: HNP-2 Beltline Region, Curve A, for 37 EFPY............................................... 19 Table 3: HNP-2 Beitline Region, Curve A, for 50.1 EFPY............................................. 20 Table 4: HNP-2 Bottom Head Region, Curve A, for All EFPY........................................ 21 Table 5: HNP-2 Non-Beltline Region, Curve A, for All EFPY......................................... 21 Table 6: HNP-2, Beltline Region, Curve B, for 37 EFPY and 1000F/hr Thermal Transient......... 22 Table 7: HNP-2, Beltline Region, Curve B, for 50.1 EFPY and 100OF/hr Thermal Transient......
23 Table 8: HINP-2, Beltline Region, Curve B, for 37 EFPY and 2000F/hr Thermal Transient......... 24 Table 9: HNP-2, Beltline Region, Curve B, for 50.1 EFPY and 200°F/hr Thermal Transient......
25 Table 10: HNP-2 Bottom Head Region, Curve B for All EFPY and lO0OF/hr Thermal Transient... 26 Table 11: HNP-2 Bottom Head Region, Curve B for All EFPY and 2000F/hr Thermal Transient... 27 Table 12: HNP-2 Non-Beltline Region, Curve B, for All EFPY and 100OF/hr Thermal Transient.. 28 Table 13: HNP-2 Non-Beltline Region, Curve B, for All EFPY and 2000F/hr Thermal Transient.. 28 Table 14: HNP-2, Beltline Region, Curve C, for 37 EFPY and l00OF/hr Thermal Transient.......29 Table 15: HNP-2, Beltline Region, Curve C, for 50.1 EFPY and l00OF/hr Thermal Transient.....
30 Table 16: HNP-2, Beltline Region, Curve C, for 37 EFPY and 2000F/hr Thermal Transient........ 31 Table 17: HNP-2, Beitline Region, Curve C, for 50.1 EFPY and 200°F/hr Thermal Transient.....32 Table 18:.HNP-2 Bottom Head Region, Curve C for All EFPY and.100°F/hr Thermal Transient... 33 Table 19: HNP-2 Bottom Head Region, Curve C for All EFPY and 200°F/hr Thermal Transient... 34 Table 20: HNP-2 Non-Beitline Region, Curve C, for All EFPY and lOO°F/hr Thermal Transient.. 35 Table 21: HNP-2 Non-Beitline Region, Curve C, for All EFPY and 200°F/hr Thermal Transient.. 35 File No.: 1001527.305 Page 4 of 45 Revision: 2 F0306-01 R1
VStructural Integrity Associates, IncY List of Figures Figure 1 : HNP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 37 EFPY...................... 36 Figure 2:HI-NP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 50.1 EFPY.................... 37 Figure 3: J-NP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 100°F/hr....38 Figure 4: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 100°F/hr.. 39 Figure 5: ITNP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 2000F/hr....40 Figure 6:HJ-NP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 200°F/hr.. 41 Figure 7: HNP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 100°F/hr......... 42 Figure 8: I-NP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 100°F/hr......43 Figure 9: HNP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 200°F/hr......... 44 Figure 10: INP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 200°F/hr.....45
- File No.: 1001527.305 Revision: 2 Page 5 of 45 F0306-01RI
VStructural Integrity Associates, Inc.Y
1.0 INTRODUCTION
This calculation package develops pressure-temperature (P-T) limit curves for the beitline, bottom head, and non-beitline regions of the Hatch Nuclear Plant, Unit 2 (HNP-2) reactor pressure vessel (RPV). The P-T curves are developed for 37 and 50.1 effective full power years (EFPY) of operation, and for 100°F/hr and 200°F/hr thermal transients. The P-T curves are prepared using the methods documented in the Boiling Water Reactor Owner's Group (BWROG3) Licensing Topical Reports (LTRs), "Pressure Temperature Limits Report Methodology for Boiling Water Reactors" [1] and "Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations" [2]. These LTRs satisfy the requirements of 10CFR50 Appendix G3 [3] and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Non-mandatory Appendix G3 [4].
2.0 METHODOLOGY A full set of P-T curves, applicable to the followingplant conditions, are prepared:
- 1. Pressure Test (Curve A),
- 2. Normal Operation - Core Not Critical (Curve B), and
- 3. Normal Operation - Core Critical (Curve C).
For each plant condition above, separate curves are provided for each of the following three regions of the RPV as well as a composite curve for the entire RPV:
- 1. The beitline region,
- 2. The bottom head region,
- 3. The non-beltline region,
- 4. Composite curve (bounding curve for all regions)
In some cases, a region may contain more than one component which is considered for development of the associated P-T curve. For HNP-2, the curve for each vessel region identified above is composed from the bounding P-T limits determined for the following components:
- 1. Beltline:
- a. Beltline shell
- b. Water level instrument (WLI) nozzle, N16
- 2. Non-beltline
- b. 10CFR50 Appendix G limits [3]
- 3. Bottom Head:
- a. Bottom head penetrations (in-core monitor housings, control rod drive housings)
Consequently, separate curves are prepared for each component considered for each region then a bounding curve is drawn from the individual curves.
File No.: 1001527.305 Page 6 of 45 Revision: 2 F0306-01R1
Structural Integrity Associates, lnc:*
Complete sets of P-T curves, as identified above, are provided for a 100 °F/hr and 200 °F/hr thermal transient at 37 and 50.1 EFPY of operation.
The methodology for calculating P-T curves, described below, is taken from Reference [1 ] unless specified otherwise. Additional guidance regarding analysis of WLI nozzles is taken from Reference
[2].
The P-T curves are calculated by means of an iterative procedure, in which the following steps are performed:
Step 1: A fluid temperature, T, is assumed. The P-T curves are calculated considering a postulated flaw with a 6:1 aspect ratio that extends 1/4 of the way through the. vessel wall. The temperature at the postulated flaw tip is assumed equal to the coolant temperature.
Step 2: The static fracture toughness, K10, is computed using the following equation:
K10 33.2 + 20.734. eO'O2(T-ART)
(1)
Where:
Ki0
= the lower bound static fracture toughness (ksi*/n).
T
=the metal temperature at the tip of the postulated 1/4 through-wall flaw (0F).
=the Adjusted Reference Temperature (ART) for the limiting material in the RPV region under consideration (0F).
Step 3: The allowable stress intensity factor due to pressure, K1p, is calculated as:
Kip -
(2)-Ki SF(2 Where:
Kip
= the allowable stress intensity factor due to membrane (pressure) stress (ksi\\1in).
Kit the lower bound static fracture toughness calculated in Eq. (1)
(ksi*/in).
K1it the thermal stress intensity factor (ksi*/in) from through wall thermal gradients.
SF
=the ASME Code recommended safety factor, based on the reactor condition. For hydrostatic and leak test conditions (i.e., P-T Curve A), SF = 1.5. For normal operation, both core non-critical and core critical (i.e., P-T Curves B and C), SF = 2.0.
When calculating values for Curve A, the thermal stress intensity factor is neglected (Kit = 0),
since the hydrostatic leak test is performed at or near isothermal conditions (typically, the rate of temperature change is 25°F/hr or less).
File No.: 1001527.305 Page 7 of 45 Revision: 2 F0306-01IR1
Structural Integrity Associates, IncY~
For Curve B and Curve C calculations, Kit is computed in different ways based on the evaluated region. For the beitline, with the exception of nozzles, and bottom head regions, Kit is determined using the following equation:
K1, =O0.953 x10-3**CR. t2 5 (3)
Where:
CR
=
the cool-down rate of the vessel (0F/hr).
t
=
the RPV wall thickness (in).
For the FW nozzle, Kit is obtained from the stress distribution output of a plant specific finite element analysis (FEA). A polynomial curve-fit is determined for the through-wall stress distribution at the bounding time point. The linear elastic fracture mechanics solution for Kit is:
K1, =
lz{0.706C0
+ 0.537KjCi, +0.448 -*-C 2, + 0.393(4a c3 (4)
Where:
a
=1/4 through-wall postulated flaw depth, a = 1/4 t (in).
t
= thickness of the cross-section through the nozzle at the limiting path near the inner blend radius (in).
C~,l,= thermal stress polynomial coefficients, obtained from a curve-C2 t,C 3 t fit of the extracted stresses from a transient FEA.
The thermal stress polynomial coefficients are based on the assumed polynomial form of or(x) = CO + C1
- x + C2
- x + C3 *. x3. In this equation, "x" represents the radial distance in inches from the inside surface to a point on the crack face.
For the WLI nozzle, the nozzle assembly consists of an insert attached to the RPV with a partial penetration weld. The nozzle material is not ferritic and does notneed to be specifically evaluated. However, the effect of the penetration on the adjacent shell must be considered.
Reference [2, Equation 8-2] provides the following simplified solution for the thermal stress intensity factor caused by a 1 00°F/hr thermal transient:
Kj~ranm = 874, 844 [a (t* +t,)]-20.715 (5)
Where:
KI-ramp
= the K1t (thermal stress intensity factor from through wall thermal gradients) for a WLI nozzle subjected to 1000F/hr thermal transient (ksi,/in).
at
= the instrument nozzle material coefficient of thermal expansion at the highest thermal ramp temperature (in/in/0F).
tv = the vessel thickness (in).
tn = the nozzle thickness (in).
File No.: 1001527.305 Page 8 of 45 Revision: 2 F0306-01RI
VStructural Integrity Associates, IncY Larger heat-up/cool-down rates are conservatively considered by scaling the stress intensity factor obtained using Eq. (5) by the ratio of the desired heat-up/cool-down rate to 100 0F/hr.
Since the P-T curves are applicable to all Level A/B events, the bounding Level A/B events, for each region and component, identified from the vessel and nozzle thermal cycle diagrams
[7], are considered when calculating the K1 t above.
Step 4: The allowable internal pressure of the RPV is calculated differently for each evaluation region.
For the beltline region, with the exception of nozzles, the allowable pressure is determined as follows:
PaIo~o (6)
Where:
Pallow
= the allowable RPV internal pressure (psig).
Kp
= the allowable stress intensity factor due to membrane (pressure) stress, as defined in Eq. (2) (ksi~in).
t
= the RPV wall thickness (in).
Mm
= the membrane correction factor for an inside surface axial flaw:
Mm =1.85 for *t <2 Mm = 0.926 +/ for 2 <*Jt <*3.464 Mm =3.21 for /t> 3.464.
Ri
= the inner radius of the RPV (in).
For the bottom head region, the allowable pressure is calculated with the following equation:
2.K
. t aOW-SCF. M,, *R (7)
Where:
SCF conservative stress concentration factor to account for bottom head penetration discontinuities; SCF = 3.0 per Reference [1].
Pailow, K1 p, t, Mm and Ri are defined as in Eq. (6).
For the FW nozzle, the allowable pressure is determined from a ratio of the allowable and applied stress intensity factors. The applied factor can be determined from a FEM that determines the stresses due to the internal pressure on the nozzle and RPV. The methodology for this approach is as follows:
File No.: 1001527.305 Page 9 of 45 Revision: 2 F0306-01RI
Structural Integrity Associates, Inc.*
Where:
Pref RPV internal pressure at which the FEA stress coefficients (Eq.
(9)) are determined (psi).
Klp-app
= the applied pressure stress intensity factor (ksi*in).
Pailow and Kip are defined as in Eq. (6).
The applied pressure stress intensity factor is determined using a polynomial curve-fit approximation for the through-wall pressure stress distribution from a FEA, similar to the methodology of Eq. (4):
K-llap
{Oi.706C 0 p -a) 057-lp-.48-C2)p-[ 0.393I-
,C 3p j (9)
Where:
a
= 1/4/ through-wall postulated flaw depth, a =1/4 t (in).
t
= thickness of the cross-section through the nozzle at the limiting path near the inner blend radius (in).
C~,l,= pressure stress polynomial coefficients, obtained from a curve-C2 p,,C 3 p fit of the extracted stresses from a PEA.
For the WLI nozzle, the nozzle material is not ferritic and does not need to be specifically evaluated. However, the effect of the penetration on the adjacent shell must be considered.
The allowable pressure is determined from the ratio of the allowable and applied stress intensity factors given in Eq. (8). The applied stress intensity factor, for a 1000 psig load case, is calculated generically as follows [2, Equation 8-1]:
K+p*,r = 2.9045 F~L +/-t]l--,
-4.434 (10)
Where:
KI-pressure
=generic Kipapp for the instrument nozzle (ksi*/in).
R
= RPV nominal inside radius (in).
t, and tn, are described as in Eq. (5).
Step 5: Steps 1 through 4 are repeated in order to generate a series of P-T points; the fluid temperature is incremented with each repetition. Calculations proceed in this iterative manner until 1,300 psig. This value bounds expected pressures.
File No.: 1001527.305 Page 10 of 45 Revision: 2 F0306-01RI
Structural Integrity Associates, IncY Step 6: Table 1 summarizes the minimum temperature requirements contained in 10OCFR50, Appendix G [3, Table 1], which are applicable to the material highly stressed by the main closure flange bolt preload (non-beltline curve). SI also includes additional minimum temperature requirements for bolt-up as shown in Table 1 below.
Note that a minimum bolt-up temperature of 60 0F, is used here, consistent with the position given in Reference [1]. Further, some utilities specifically request that the minimum moderator temperature used in the plant shutdown margin evaluation be applied as a minimum bolt-up temperature requirement; therefore, it is also included in Table 1.
Step 7: Uncertainty in the RPV pressure and metal temperature measurements is incorporated by adjusting the P-T curve pressure and temperature using the following equations:
TTpr= T +UT (11)
P-=T = Fallow - P*-
U(12)
Where:
Tp-T
= The allowable coolant (metal) temperature (0F).
= The coolant temperature instrument uncertainty (0F).
PPT = The allowable reactor pressure (psig).
PH
=The pressure head to account for the water in the RPV (psig).
Can be calculated from the following expression: PH = P"Ah.
p
= Water density at ambient temperature (lb/in3).
Ah
= Elevation of full height water level in RPV (in).
Up
= The pressure instrument uncertainty (psig).
Steps 1 through 7, above, are implemented for all components, in all regions, for each heat-up/cool-down rate, and at all EFPY.
3.0 ASSUMPTIONS The 10OCFR50 Appendix G [3] and ASME Code [4] requirements and methods are considered to be supported in their respective technical basis documentation; therefore, the assumptions inherent in the ASME B&PV Code methods utilized for this evaluation are not specifically identified and justified in this calculation. Only those assumptions specific to this calculation are identified and justified here.
The following assumptions are used in preparation of the HNP-2 P-T curves:
- 1. The static head contributed by coolant inside the RPV is calculated using the full height of the RPV.
This assumption is conservative in that the static head at the non-beltline and beltline regions is slightly lower than for the bottom head curve; however, the difference in static head is small; therefore, the added complexity in considering different static head values for each region of the vessel is not considered beneficial.
File No.: 1001527.305 Page 11 of 45 Revision: 2 F0306-01RI
VStructural Integrity Associates, Inc.Y
This assumption is made because:
- a. The geometric discontinuity caused by the nozzle penetration in the RPV shell causes a stress concentration which results in larger pressure induced stresses than would be calculated in the shell regions of the RPV,
- b. The FW nozzle experiences more severe thermal transients than most of the other nozzles because of the FW injection temperature which causes larger thermal stresses than are experienced in the shell regions of the RPV,
- c. Although some other nozzles can experience thermal transients which would cause thermal stresses larger than those calculated for the shell regions of the RPV and some nozzles are larger diameter than the FW nozzle, which could result in a slightly larger Kip, the combined stresses from the applied thermal and pressure loads are considered to bound all other non-beitline discontinuities.
- 3. Application of a SCF = 3.0 to the membrane pressure stress in the bottom head bounds the effect of the bottom head penetrations on the stress field in this region of the vessel.
It is recognized that the penetrations in the bottom head will introduce a geometric discontinuity into the bottom head hemisphere which creates a stress intensification. This effect must be considered in calculating the stress intensity factor from internal pressure. Rather than performing a plant specific analysis, SI applies a conservative SCF for a circular hole in a flat plate subjected to a uniaxial load to the membrane stress in the shell caused by the internal pressure. This assumption is conservative because:
- a. It applies a peak SCF to the membrane stress which essentially intensifies the stress through the entire shell thickness and along the entire face of the postulated flaw rather than intensify'ing the stress local to the penetration and considering the stress attenuation away from the penetration,
- b. Review of SCFs for circular holes in plates subjected to an equi-bi-axial stress state as well as SC~s for arrays of circular holes in shells, shows that the SCF is likely closer to 2-2.5 rather than 3.0.
Consequently, the method utilized by SI is expedient, as intended, and conservatively bounds the expected effect of bottom head penetrations because a bounding SCF is used and applied as a membrane stress correction factor.
- 4. ASME XI, Non-mandatory Appendix G, Paragraph G-22 14.3 [4] is used to calculate the thermal stress intensity factor for heat-up / cool-down rates greater than I100°F/hr.
The ASME Code [4] acknowledges that this methodology is conservative when applied to rapid heat-up / cool-down rates (i.e. greater than 100°F/hr); therefore, the results obtained using this method for 200°F/hr heat-up / cool-down rate are conservative. Conservatism can be removed, if necessary, by solving the thermo-elastic problem for the stresses in the vessel shell then calculating the stress intensity factor using the plant specific stress distribution.
File No.: 1001527.305 Page 12 of 45 Revision: 2 F0306-01R1
Structural Integrity Associates, Inc?
- 5. A shutdown margin temperature of 68°F is assumed.
SI experience is that GE designed BWRs typically consider a moderator temperature of 68°F in the shutdown margin evaluation; therefore, this value is assumed for H-NP-2. This assumption affects only the minimum bolt-up temperature. However, to address the NRC condition regarding lowest service temperature in Reference [1], the minimum temperature is set to 90 °F, which is equal to the RTNDT,max + 60 °F. This value is consistent with the previous minimum temperature limits developed in [ 10], and the minimum bolt-up temperature specified in [ 11].
4.0 DESIGN INPUTS The design inputs used to develop the IHNP-2 P-T curves are discussed below. Design inputs are also summarized in the input listings in Appendix A.
Non-be ltline:
Bottom Head:
Beltline:
37 EFPY:
50.1 EFPY:
WLI Nozzle (in Beltline):
37 EFPY:
50.1 EFPY:
30 0F 50 0F 72.6 0F 79.2 0F 69.5 0F 74.6 0F Lower Shell #2 Plate (G6603-2)
Lower Shell #2 Plate (G6603-2)
Lower-Int Shell #3 Plate (G6601-4)
Lower-Int Shell #3 Plate (G6601-4)
- 2. Shutdown Margin Temperature: 68 0F
- 3. RPV Dimensions:
Full vessel height [6]:
RPV inside radius [6]:
RPV shell thickness [5]:
Bottom head inside radius [6]:
Bottom head shell thickness [6]:
See Assumption 5.
836.75 inches (Used to calculate maximum water head during pressure test and conservatively applied for normal operation as well) 110.375 inches 6.375 inches (Lower Shell #2 Plate) 5.375 inches (Lower-Tnt Shell #3 Plate) 110.5 inches 6.813 inches (Corresponds to the thicker portion of the shell in which the penetrations exist. This bounds the thinner portion of the shell with no penetrations)
- 4. Heat-up / Cool-down Rates [8]:
100 °F/hr 200 "F/hr
- 5. Nozzle Stress Intensity Factors:
FW Nozzle [9]:
1 ksi Pressure:
100 0F/hr:
78.9 ksi-in° 5 12.9 ksi-in° 5 File No.: 1001527.305 Page 13 of 45 Revision: 2 F0306-01R1
VStructural Integrity Associates, Inc?
200 °F/hr:
25.8 ksi-in° 5 450 0F down shock:
46.8 ksi-in° 5 WLI Nozzle [9]:
1 ksi Pressure:
80.0 ksi-in°5 100 *F/hr:
19.9 ksi-in°5 200 0F/hr:
39.9 ksi-in° 5
- 6. Design Pressure [7]:
1250 psig
- 7. Pre-service Hydro-test pressure [7]:
1563 psig (Taken as 1.25 *Design pressure = 1563 psig)
- 8. Instrument uncertainties [8]:
Pressure:
0 psig Temperature:
O°F 5.0 CALCULATIONS The P-T curves in this calculation were developed using an Excel spreadsheet, which is independently verified for use on a project-specific basis in accordance with SI's Nuclear QAprogram. Four cases are evaluated, corresponding to two EFPY values (37 and 50.1) and two thermal transients (100 and 200
°F/hr). P-T limits are calculated from 0 to 1300 psig. Supporting calculations for all curves are included in Appendix B.
The change in thickness within the beltline affects the P-T curves for the beltline plates. Both beltline plates are evaluated using their respective ART values. The thinner plate thickness and associate ART value is limiting for Curve A, but the thicker plate and associated ART is limiting for Curves B and C.
However, the WLI (Ni16) nozzle provides the most limiting results within the beltline region for all curves. Therefore, the composite beltline curves are unaffected by the change in beltline shell thickness.
The thin region of the bottom head torus and the cylindrical portion or the RPV below the beltline are not limiting in this analysis; thus, the thick portion of the bottom head yields bounding bottom head P-T curves for HNP-2.
Because BWR operation is typically along the saturation curve, the limiting K1t for the FW nozzle is scaled to reflect the worst-case step change due to the available temperature difference between the saturation temperature at a given pressure and the 100 0F FW temperature. It is recognized that at low temperatures, the available temperature difference is insignificant, which could result in a near zero Kit.
Therefore, a minimum Kit is calculated for both the 1 00°F/hr and 200°F/hr thermal transients; scaling of the FW nozzle K1t based on the available temperature difference is not allowed below the minimum K1 t corresponding to the cool-down rate being evaluated.
The composite P-T curves are extended below 0 psig to -14.7 psig based on the evaluation documented in Reference [ 12], which demonstrates that the P-T curves are applicable to negative gauge pressures.
- Since the P-T curve calculation methods used do not specifically apply to negative values of pressure, the tabulated results start at 0 psig. However, the minimum RPV pressure is -14.7 psig.
File No.: 1001527.305 Page 14 of 45 Revision: 2 F0306-01R1
Structural Integrity Associates, Inc.*
5.1 Pressure Test (Curve A)
The assumed minimum bolt-up temperature of 900 F, see Assumption 5, is applied to all regions as the initial temperature in the iterative calculation process. The static fracture toughness (K1 o) is calculated for all regions using Eq. (1). The resulting value of K10, along with a safety factor of 1.5 is used in Eq.
(2) to calculate the pressure stress intensity factor (K1p). The allowable RPV pressure is calculated for the beitline, bottom head and non-beltline regions using Eq. (6, 7, and 8), as appropriate. For the non-beltline region, the additional constraints specified in Step 6 of Section 2.0 are applied. Final P-T limits for temperature and pressure are obtained from Eq. (12 and 13), respectively.'
Since the thermal stress intensity factor is taken as zero for Curve A, the thermal transients considered do not affect the results for Curve A.
Values for the composite beltline region curves for 37 and 50.1 EFPY are listed in Table 2 and Table 3, respectively. Additionally, more detailed data for the composite beltline are provided in Appendix B.
Data for the composite bottom head region curve for all EFPY are listed in Table 4. Data for the composite non-beltline (FW nozzle / upper vessel) region curve, including the 10CFR50 Appendix G [3]
limits, for all EFPY are listed in Table 5. The data for each region is graphed, and the resulting composite Curve A for 37 and 50.1 EFPY are provided in Figure 1 and Figure 2, respectively.
Additional data and curves for each region are included in Appendix B.
5.2 Normal Operation - Core Not Critical (Curve B)
The assumed minimum bolt-up temperature of 90°F (see Assumption 5), is applied to all regions as the initial temperature in the iterative calculation process. The static fracture toughness (K10) is calculated for all regions using Eq. (1). The thermal stress intensity factor (K1 t) is calculated for the beltline plate and bottom head regions using Eq. (3), for the FW nozzle using Eq. (4), and for the WLI (NI16) nozzle using Eq. (5).
The resulting values of K10 and K1t, along with a safety factor of 2.0, are used in Eq. (2) to calculate the pressure stress intensity factor (Kip). The allowable RPV pressure is calculated for the beltline, bottom head, and non-beltline regions using Eq. (6, 7, and 8), as appropriate. For the non-beltline region, the additional constraints specified in Step 6 of Section 2.0 are applied. Final P-T limits for temperature and pressure are obtainedfrom Eq. (12 and 13), respectively.
The data resulting from each P-T curve calculation are tabulated. Values for the composite beltline region with a 100OF/hr thermal transient at 37 and 50.1 EFPY are listed in Table 6 and Table 7, respectively. Values for the composite beltline region with a 200°F/hr thermal transient at 37 and 50.1 EFPY are listed in Table 8 and Table 9, respectively. Data for the bottom head region with 1 00°F/hr and 200°F/hr thermal transients are listed in Table 10 and Table 11, respectively. Data for the non-beltline region with 100°F/hr and 200°F/hr thermal transients are listed in Table 12 and Table 13, respectively. The data for each region is graphed, and the resulting composite Curve B for 37 and 50.1 EFPY with a 1 00°F/hr thermal transient are provided in Figure 3 and Figure 4, respectively. The resulting composite Curve B for 37 and 50.1 EFPY with a 200°F/hr thermal transient are provided in File No.: 1001527.305 Page 15 of 45 Revision: 2 F0306-01R1
Structural Integrity Associates, Inc.*
Figure 5 and Figure 6, respectively. Additional data and curves for each region are included in Appendix B.
5.3 Normal Operation - Core Critical (Curve C)
The pressure and temperature values for Curve C are calculated in a similar manner as Curve B, with several exceptions. The initial evaluation temperature is calculated as the limiting non-beltline RTNDT that is highly stressed by the bolt preload (in this case, that of the closure flange region: 30°F per Section 3.0) plus 60°F, resulting in a minimum critical temperature of 90°F. When the pressure exceeds 20% of the pre-service system hydrostatic test pressure (20% of 1,563 psig =313 psig), the P-T limits are specified as 40°F higher than the Curve B values. The minimum temperature above the 20% of the pre-service system hydrostatic test pressure is always greater than the reference temperature (RTNDT) of the closure region plus 160°F, or is taken as the minimum temperature required for the hydrostatic pressure test. The final Curve C values are taken as the absolute maximum between the regions of the beltline, the bottom head, and the non-beltline.
The data resulting from each P-T curve calculation are tabulated. Values for the composite beltline region with a 100°F/hr thermal transient at 37 and 50.1 EFPY are listed in Table 14 and Table 15, respectively. Values for the composite beltline region with a 200°F/hr thermal transient at 37 and 50.1 EFPY are listed in Table 16 and Table 17, 'respectively. Data for the bottom head region with 1 00°F/hr and 200°F/hr thermal transients are listed in Table 18 and Table 19, respectively. Data for the non-beltline region with l00°F/hr and 200°F/hr thermal transients are listed in Table 20 and Table 21, respectively. The data for each region is graphed, and the resulting composite Curve C for 37 and 50.1 EFPY with a 10OOF/hr thermal transient are provided in Figure 7 and Figure 8, respectively. The resulting composite Curve C for 37 and 50.1 EFPY with a 200°F/hr thermal transient are provided in Figure 9 and Figure 10, respectively. Additional data and curves for each region are included in Appendix B.
6.0 CONCLUSION
S.
P-T curves are developed for HNP-2 using the methodology, assumptions, and design inputs defined in Sections 2.0, 3.0, and 4.0. P-T curves are developed for the beltline, bottom head, and non-beltline regions, considering a 100 °F/hr and 200 0F/hr thermal transient at 37 and 50.1 EFPY, for the following plant conditions: Pressure Test (Curve A), Normal Operation - Core Not Critical (Curve B), and Normal Operation - Core Critical (Curve C). Tabulated pressure and temperature values are provided for all regions and EFPYs in Tables 2 through 21. The accompanying P-T curve plots are provided in Figures 1 through 10.
File No.: 1001527.305 Page 16 of 45 Revision: 2 F0306-01RI
Structural Integrity Associates, IncY
7.0 REFERENCES
- 1. Structural Integrity Associates Report No. SIR-05-044, Revision 1-A, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," June 2013, SI File No. GE-10Q-401.
- 2. Structural Integrity Associates Report No. 0900876.40 1, Revision 0-A, "Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations," May 2013.
- 3. U. S. Code of Federal Regulations, Title 10, Energy, Part 50, "Domestic Licensing of Production and Utilization Facilities," Appendix G, "Fracture Toughness Requirements," (60 FR 65474, Dec.
19, 1995; 73 FR 5723, Jan. 2008).
- 4. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components. Appendix G, "Fracture Toughness Criteria for Protection Against Failure," 2001 Edition including the 2003 Addenda.
- 5. Structural Integrity Associates Calculation No. 1001527.302, Rev 1, "RPV Material Summary and ART Calculation."
- 6. Combustion Engineering Drawing No. E-1 1570-871-001, Revision 1, "General Arrangement Elevation for 218" I.D. BWR," SI File No. GPCO-44Q-205.
- 7. GE Drawing No. 761E246, *"Reactor Vessel Thermal Cycles (Including Black Start)," Sheet 1, Revision 1, 51 File No. 1001527.211.
- 8. Design Input Requests.
1001527.201.
- 9. Structural Integrity Associates Calculation No. 1001527.303, Revision 1, "Feedwater, Water Level Instrument, and Core DP Nozzle Fracture Mechanics Evaluation for Hatch Unit 1 and Unit 2 Pressure-Temperature Limit Curve Development."
- 10. General Electric Document No. GE-NE-B 1100827-00-01, "Plant Hatch Units 1 & 2 RPV Pressure Temperature Limits License Renewal Evaluation," March 1999, SI File No. 1400365.202.
- 11. NRC Docket No. 50-321, "Issuance of Amendment No. 177 to Facility Operating License DPR-57 and Amendment No. 118 to Facility Operating License NPF Edwin I. Hatch Nuclear Plant, Units 1 and 2," Amendment No. 177, License No. DPR-57, ADAMS Accession No. ML012990100, SI File No. 1400365.202.
File No.: 1001527.305 Page 17 of 45 Revision: 2 F0306-01RI
VStructural Integrity Associates, Inc.Y Table 1: Summary of Minimum Temperature Requirements for P-T Limit Curves
,Crv r Range Minimum Metal Temperature P-T Limits..
Maximum of:
ASME Appendix G [4]
P<O P RTNDT, max, requirements A
- 60'F [1],
TSDM P > 20% Ph RTNDT,max + 90 'FAME peniG[4
_________________________requirements Maximum of:
ASME Appendix G [4]
P<0P RTNDT, max, requirements B
- 60 'F[1],
TSDM
> 20 Ph TNDTrnax+/- 12 'FASME Appendix G [4]
requirements Maximum of:
ASME Appendix G [4]
P<0P RTNDT, max + 60 'F, requirements + 40 'F
- 60°F [1],
C TSDM Maximum of:
ASME Appendix G [4]
P > 20% Ph RTNDT,max + 160 'F, requirements + 40 'F TISHT_________________
Where:
This table is largely taken from Reference [3] with modifications as described in Step 6 of Section 2.0.
Ph is the pre-service hydrotest pressure, 1563 psig RTNDT,max is the maximum RTNDT of the vessel materials highly stressed by the bolt preload.
TSDM is the temperature used in the shutdown margin evaluation Tismr is the temperature at which the full in-service hydrotest pressure is allowed per Curve A Note that the minimum bolt-up temperature of 60°F, is used here, consistent with the position given in Reference [1]. Further, some utilities specifically request that the minimum moderator temperature used in the plant shutdown margin evaluation be applied as a minimum bolt-up temperature requirement; therefore, it is also included in Table 1 above. However, to address NRC condition regarding lowest service temperature in Reference [1], the minimum temperature is set to 90 0F, which is equal to the RTNDT, max + 60 0F. This value is consistent with the previous minimum temperature limits developed in
[ 10], and the minimum bolt-up temperature specified in [ 11].
File No.: 1001527.305 Revision: 2 Page 18 of 45 F0306-01R1
Structural Integrity Associates, Inc.Y Table 2:HINP-2 Beltline Region, Curve A, for 37 EFPY
°F psi 90.0 0.0 90.0 506.7 98.5 554.7 105.7 602.7 112.0 650.7 117.6 698.8 122.7 746.8 127.3 794.8 131.5 842.8 135.3 890.8 138.9 938.8 142.3 986.8 145.4 1034.9 148.4 1082.9 151.2 1130.9 153.8 1178.9 156.3 1226.9 158.7 1274.9 161.0 1322.9 File No.: 1001527.305 Page 19 of 45 Revision: 2 F0306-01RI
Structural Integrity Associates, Inc.6 Table 3:HINP-2 Beltline Region, Curve A, for 50.1 EFPY OF psi 90.0 0.0 90.0 481.5 99.5 530.6 107.5 579.8 114,3 628.9 120.4 678.1 125.8 727.3 130.7 776.4 135.1 825.6 139.2 874.7 142.9 923.9 146.4 973.1 149.7 1022.2 152.8 1071.4 155.7 1120.6 158.4 1169.7 161.0 1218.9 163.5 1268.0 165.8 1317.2 File No.: 1001527.305 Page 20 of 45 Revision: 2 F0306-01IRI
Structural Integrity Associates, Inc.*~
Table 4: HNP-2 Bottom Head Region, Curve A, for All EFPY "F
psi 90.0 0.0 90.0 869.3 94.5 918.9 98.7 968.4 102.5 1018.0 106.1 1067.5 109.4 1117.1 112.5 1166.6 115.4 1216.2 118.2 1265.7 120.8 1315.3 Table 5: HNP-2 Non-Beltline Region, Curve A, for All EFPY
- F psi 90.0 90.0 120.0 120.0 0.0 312.6 312.6 1310.2 File No.: 1001527.305 Revision: 2 Page 21 of 45 F0306-01IR1
Structural Integrity Associates, Inc.Y Table 6: HNP-2, Beitline Region, Curve B, for 37 EFPY and 10OOF/hr Thermal Transient
°F psi 90.0 90.0 101.1 110.2 117.9 124.6 130.5 135.7 140.5 144.9 148.9 152.6 156.0 159.2 162.3 165.1 167.8 170.4 172.8 175.1 177.4 179.5 181.5 183.5 0.0 248.1 296.8 345.5 394.2 442.9 491.6 540.3 589.0 637.7 686.4 735.1 783.8 832.5 881.2 929.9 978.6 1027.3 1076.0 1124.7 1173.4 1222.1 1270.8 1319.5 File No.: 1001527.305 Revision: 2 Page 22 of 45 F0306-01IRI1
~jStructural Integrity Associates, Inc:e Table 7: HINP-2, Beltline Region, Curve B, for 50.1 EFPY and 100OF/hr Thermal Transient TempraUre Pesr
°F psi 90.0 0.0 90.0 229.2 102.4 278.6 112.2 328.0 120.5 377.4 127.6 426.8 133.8 476.2 139.3 525.6 144.3 575.0 148.8 624.4 153.0 673.8 156.8 723.2 160.3 772.6 163.7 822.0 166.8 871.4 169.7 920.8 172.5 970.2 175.1 1019.6 177.6 1069.0 180.0 1118.4 182.2 1167.8 184.4 1217.2 186.5 1266.6 188.5 1316.0 File No.: 1001527.305 Page 23 of 45 Revision: 2 F0306-01RI
Structural Integrity Associates, Inc.2 Table 8: HNP-2, Beitline Region, Curve B, for 37 EFPY and 200°F/hr Thermal Transient OF psi 90.0 0.0 90.0 123.1 101.3 172.8 110.6 222.4 118.3 272.1 125.1 321.7 131.0 371.4 136.3 421.0 141.1 470.7 145.5 520.3 149.5 570.0 153.3 619.6 156.7 669.3 160.0 718.9 163.0 768.6 165.9 818.2 168.6 867.9 171.2 917.5 173.6 967.2 175.9 1016.8 178.2 1066.5 180.3 1116.1 182.3 1165.8 184.3 1215.4 186.2 1265.1 188.0 1314.7 File No.: 1001527.305 Page 24 of 45 Revision: 2 F0306-01 RI
Structural Integrity Associates, Inc~e Table 9: HNP-2, Beltline Region, Curve B, for 50.1 EFPY and 200°F/hr Thermal Transient
°F psi 90.0 90.0 102.2 112.0 120.1 127.2 133.3 138.8 143.8 148.3 152.4 156.2 159.7 163.0 166.1 169.1 171.8 174.4 176.9 179.3 181.6 183.7 185.8 187.8 189.7 191.5 193.3 0.0 104.2 152.8 201.5 250.1 298.7 347.3 396.0 444.6 493.2 541.8 590.5 639.1 687.7 736.4 785.0 833.6 882.2 930.9 979.5 1028.1 1076.7 1125.4 1174.0 1222.6 1271.2 1319.9 File No.: 1001527.305 Revision: 2 Page 25 of 45 F0306-01 R1
~jjStructural Integrity Associates, IncY Table 10: HNP-2 Bottom Head Region, Curve B for All EFPY and 100°F/hr Thermal Transient OF psi 90.0 0.0 90.0 546.3 95.8 594.7 101.0 643.1 105.7 691.5 110.1 739.9 114.0 788.4 117.7 836.8 121.1 885.2 124.3 933.6 127.3 982.0 130.2 1030.4 132.9 1078.8 135.4 1127.3 137.9 1175.7 140.2 1224.1 142.4 1272.5 144.5 1320.9 File No.: 1001527.305 Page 26 of 45 Revision: 2 F0306-01 RI
~Structural Integrity Associates, Inc.
Table 11: HNP-2 Bottom Head Region, Curve B for All EFPY and 200°F/hr Thermal Transient 5
9 9
90.
90.0 95.8 101.0 105.8 110.1 114.1 117.7 121.2 124.4 127.4 130.2 132.9 135.5 137.9 140.2 142.4 144.5 146.6 148.5 psi 0.0 448.1 496.6 545.1 593.5 642.0 690.5 739.0 787.4 835.9 884.4 932.8 981.3 1029.8 1078.3 1126.7 1175.2 1223.7 1272.2 1320.6 File No.: 1001527.305 Revision: 2 Page 27 of 45 F0306-O1R1
jjStructural Integrity Associates, Inc.*
Table 12: HNP-2 Non-Beltline Region, Curve B, for All EFPY and 100°F/hr Thermal Transient "F
psi 90.0 0.0 90.0 312.6 150.0 312.6 150.0 1313.5 Table 13: HNP-2 Non-Beitline Region, Curve B, for All EFPY and 200°F/hr Thermal Transient P-T Curve 90.0 90.0 150.0 150.0 Prsure psi 0.0 312.6 312.6 1313.5
.tT~
4....
Revision: 2 Page 28 of 45 F0306-01RI
~jjStructural Integrity Associates, IncY Table 14: HNP-2, Beltline Region, Curve C, for 37 EFPY and 1000F/hr Thermal Transient e
°F 90.0 90.0 112.2 127.5 139.2 148.7 156.7 163.6 169.6 175.0 179.9 184.3 188.4 192.1 195.6 198.9 202.0 204.9 207.6 210.2 212.7 215.0 217.2 219.4 221.5 223.4 PS, 0.0 140.6 189.6 238.7 287.7 336.8 385.8 434.9 483.9 533.0 582.0 631.1 680.1 729.2 778.2 827.3 876.3 925.4 974.4 1023.5 1072.5 1121.6 1170.6 1219.7 1268.7 1317.8 File No.: 1001527.305 Revision: 2 Page 29 of 45 F0306-01IRI
~jStructural Integrity Associates, Inc.8 Table 15: HNP-2, Beltline Region, Curve C, for 50.1 EFPY and 100°F/hr Thermal Transient
- 9.
9
-/-
90.0 90.0 114.2 130.5 142.7 152.5 160.7 167,8 173.9 179.4 184.4 188.9 193.0 196.9 200.4 203.7 206.8 209.7 212.5 215.1 217.6 220.0 222.2 224.4 226.5 228.5 psi 0.0 132.1 181.4 230.8 280.1 329.5 378.8 428.1 477.5 526.8 576.2 625.5 674.8 724.2 773.5 822.9 872.2 921.6 970.9 1020.2 1069.6 1118.9 1168.3 1217.6 1266.9 1316.3 File No.: 1001527.305 Revision: 2 Page 30 of 45 F0306-01RI
Structural Integrity Associates, Inc.6 Table 16: HNP-2, Beltline Region, Curve C, for 37 EFPY and 200°F/hr Thermal Transient e.
90F 90.0 112.5 128.0 139.8 149.3 157.3 164.2 170.3 175.7 180.6 185.0 189.1 192.9 196.4 199.7 202.7 205.6 208.4 211.0 213.5 215.8 218.1 220.2 222.3 224.2 226.1 228.0 PSI 0.0 15.6 65.6 115.5 165.4 215.3 265.2 315.1 365.0 415.0 464.9 514.8 564.7 614.6 664.5 714.4 764.4 814.3 864.2 914.1 964.0 1013.9 1063.9 1113.8 1163.7 1213.6 1263.5 1313.4 File No.: 1001527.305 Revision: 2 Page 31 of 45 F0306-01RI
St~3ructural Integrity AscaeIncY Table 17: HNP-2, Beitline Region, Curve C, for 50.1 EFPY and 200°F/hr Thermal Transient
- e.
e
°F 90.0 90.0 113.9 130.0 142.2 152.0 160.2 167.2 173.4 178.8 183.8 188.3 192.4 196.2 199.7 203.1 206.2 209.1 211.8 214.4 216.9 219.3 221.6 223.7 225.8 227.8 229.7 231.5 233.3 psi 0.0 7.1 55.8 104.4 153.0 201.6 250.2 298.9 347.5 396.1 444.7 493.3 542.0 590.6 639.2 687.8 736.4 785.1 833.7 882.3 930.9 979.5 1028.2 1076.8 1125.4 1174.0 1222.7 1271.3 1319.9 in...
kT..
4 0n4...........
Revision: 2 Page 32 of 45 F0306-01RI
jjStructural Integrity Associates, Inc.Y Table 18: HNP-2 Bottom Head Region, Curve C for All EFPY and 100OF/hr Thermal Transient 90F 90.0 102.3 112.2 120.5 127.5 133.7 139.3 144.2 148.7 152.9 156.7 160.3 163.6 166.7 169.6 172.4 175.0 177.5 179.9 182.1 184.3 psi 0.0 330.2 379.5 428.8 478.1 527.5 576.8 626.1 675.4 724.7 774.0 823.3 872.6 922.0 971.3 1020.6 1069.9 1119.2 1168.5 1217.8 1267.1 1316.4 File No.: 1001527.305 Revision: 2 Page 33 of 45 F0306-01 RI1
Structural Integrity Associates, Inc:
Table 19: HNP-2 Bottom Head Region, Curve C for All EFPY and 200°F/hr Thermal Transient e.
90.
90.0 102.3 112.2 120.5 127.5 133.7 139.2 144.2 148.7 152.9 156.7 160.3 163.6 166.7 169.6 172.4 175.0 177.5 179.9 182.1 184.3 186.4 188.4 psi 0.0 232.1 281.4 330.6 379.9 429.2 478.5 527.8 577.1 626.4 675.7 725.0 774.3 823.6 872.9 922.2 971.5 1020.8 1070.1 1119.4 1168.6 1217.9 1267.2 1316.5 File No.: 1001527.305 Revision: 2 Page 34 of 45 F0306-01RI
jjStructuraI Integrity Associates, Inc.
Table 20: HNP-2 Non-Beitline Region, Curve C, for All [FPY and 100°F/hr Thermal Transient
°F psi 90.0 90.2 101.6 110.6 118.2 190.0 190.0 0.0 193.0 232.9 272.7 312.6 312.6 1313.5 Table 21: HNP-2 Non-Beltline Region, Curve C, for All EFPY and 200°F/hr Thermal Transient P-TCre 90.0 90.2 101.6 110.6 118.2 190.0 190.0 psi 0.0 193.0 232.9 272.7 312.6 312.6 1313.5 File No.: 1001527.305 Revision: 2 Page 35 of 45 F0306-01RI
Structural Integrity Associates, IncY Curve A - Pressure Test, Composite Curves
-Be e.--Bottom Head
-- -- Non-Beitline
-Overall 1300 1200 1100 1000 900
'~800
- ,700 600 4.
E S500 IU
& 40 300 200 100L 0
Minimum Reactor Vessel Metal Temperature ('F)
Figure 1: HNP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 37 EFPY File No.: 1001527.305 Revision: 2 Page 36 of 45 F0306-01I R]
Structural Integrity Associates, IncYc Curve A - Pressure Test, Composite Curves
-Be..ne Bottom Head Non-Beitline Overall 1300 1200 1100 1O00 900 8
I 00 a.
- ,70
& 400 300 200 100 0
Minimum Reactor Vessel Metal Temperature ('F)
Figure 2: HNP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 50.1 EFPY File No.: 1001527.305 Revision: 2 Page 37 of 45 F0306-01RI
Structural Integrity Associates, Inc.t.
Curve B - Core Not Critical, Composite Curves
-Beitline Bottom Head
- -l Non-Beltline
-vrl 1300 1200 1100 1000 900 S800 J 600 E
500 300 200 100 0
Figure 3: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 1O0°F/hr File No.: 1001527.305 Revision: 2 Page 38 of 45 F0306-01RI
Structural Integrity Associates, Inc Curve B - Core Not Critical, Composite Curves
-Bel...e---Bottom Head Non-Beltline
-Overall 1300 1200 1100 1000 900 8 00
- 600
-2 500......
&- 400....
300 200 100 0
Minimum Reactor Vessel Metal Temperature ('F)
Figure 4:HINP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 100°F/hr File No.: 1001527.305 Revision: 2 Page 39 of 45 F0306-01 R1
Structural Integrity Associates, Inc.2 Curve B - Core Not Critical, Composite Curves
-Bet..ne---Bottom Head Non-Beltline
-Overall 1300 1200 1100 1000 900 800 61 600 4.,
E S500 400 300 200 100 Minimum Reactor Vessel Metal Temperature I(F)
Figure 5: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 200°F/hr File No.: 1001527.305 Revision: 2 Page 40 of 45 F0306-01 R1
Structural Integrity Associates, Inc.Y Curve B - Core Not Critical, Composite Curves
-. e...e Bottom Head Non-Beltline
,-mOverall 1300 1200 1100 1O00 900
~800 0.
"= 5003
&" 400 300 200 100 0
Minimum Reactor Vessel Metal Temperature ('F)
Figure 6: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 200°F/hr File No.: 1001527.305 Revision: 2 Page 41 of 45 F0306-01 RI
jjStructural Integrity Associates, Inc.
Curve C
- Core Critical, Composite Curves
-. et.ne.--Bottom Head Non-Beltline
-=mOverall 1300 1200}
1100 1000 900 S800 a.
E 500 A-400 300 200 100 0
Minimum Reactor Vessel Metal Temperature (*F)
Figure 7: HNP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 1OO°F/hr File No.: 1001527.305 Revision: 2 Page 42 of 45 F0306-01IRI1
~jStructural Integrity Associates, Inc:
Curve C - Core Critical, Composite Curves ie Bottom Head
-- -- Non-Beltline
-mmOverall 1300 1200 1100 1O00 900 800
.5
- 700 E
-1 500 tU
& 400 300 200 100 Minimum Reactor Vessel Metal Temperature (*F)
Figure 8: HNP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 10O°F/hr File No.: 1001527.305 Revision: 2 Page 43 of 45 F0306-01 RI
jjStructural Integrity Associates, IuicY Curve C - Core Critical, Composite Curves
-Beitline Bottom Head 1 Non-Belthine
-. ilOverall 1300 1200 1100 1O00 900 800 "a
- , 00 "l
5001
&: 400 300 200 100 0
Minimum Reactor Vessel Metal Temperature (*F)
Figure 9: HNP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 200°F/hr File No.: 1001527.305 Revision: 2 Page 44 of 45 F0306-01RI
Structural Integrity Associates, IncY Curve C
- Core Critical, Composite Curves e...e Bottom Head Non-Beltline
,,,,,-Overall 1200 +/--
1100 1--
1000 900 800 E
ElI A-400 300 200 100 0
Figure 10: HNP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 200°F/hr File No.: 1001527.305 Revision: 2 Page 45 of 45 F0306-0 tR I
jjJStructural Integrity Associates, Inc~e APPENDIX A:
P - T CURVE INPUT LISTING File No.: 1001527.305 Revision: 2 Page A-Il of A-3 F0306-01R I
Structural Integrity Associates, Inc Table A-i: HNP-2 Stress Intensity Factors for Feedwater and WLI Nozzles [9]
Feedwater 78.9 46.8 12.9 25.8 WLI J
80.0 N/A 19.9 39.9 Notes:
- 1. K1 in units of ksi-in°05
- 2. 200 °F/hr results are scaled from 100 °F/hr assuming response is linear Table A-2: HNP-2 P-T Curve Input Listing P-T Curve Inputs....
General Parameters English Unit System for Tables and Plots 0
Temperature Instrument Uncertainty Adjustment (°F) 0 Pressure Instrument Uncertainty Adjustment (psig) 62.4 Water Density (Ibm/ft 3) 836.75 Full-Vessel Water Height (in) 1.5 Safety Factor for Curve A 2
Safety Factor for Curves B and C 90 Minimum bolt-up temperature (OF) 30 ART of Closure Flange Region (°F) 5 Default Temperature Increment for Tables (OF) 50 Default Pressure Increment for Composite Tables (psig)
Beltline Parameters 69.5 Adjusted Reference Temperature, Lower-lnt Shell #3 Plate (G6601-4), 37 EFPY 72.6 Adjusted Reference Temperature, Lower Shell #2 Plate (G6603-2), 37 EFPY 74.6 Adjusted Reference Temperature, Lower-lnt Shell #3 Plate (G6601-4), 50.1 EFPY 79.2 Adjusted Reference Temperature, Lower Shell #2 Plate (G6603-2), 50.1 EFPY 110.375 Vessel Radius (in) 5.375 Vessel Thickness, Curve A (in) 6.375 Vessel Thickness, Curves B & C (in) 100 Heat-up / Cool-down Rate (°F/hr) 200 Heat-up / Cool-down Rate (°F/hr)
Generic Type of Static Pressure Head Addition N/A Specific Water Height for Static Pressure Head Addition (in)
Generic Type of Temperature Increment for Tables 5
Specific Temperature Increment for Tables (=F)
File No.: 1001527.305 Page A-2 of A-3 Revision: 2 F0306-01 RI
Structural Integrity Associates, Inc.
Si ! iii!
i!i iii~i iiii
~!! P-Tli!iiiii ii C urve Iiin p u ts i 'l Instrument Nozzle Parameters 69.5 Adjusted Reference Temperature, 37 EFPY (°F) 74.6 Adjusted Reference Temperature, 50.1 EFPY (°F) 110.375 Vessel Radius (in) 5.375 Vessel Thickness (in)
See Table Applied Pressure Stress Intensity Factor (ksi*in^0.5)
A-i Applied Thermal Stress Intensity Factor (ksi*inA0.5) 7.69E-06 Coefficient of Thermal Expansion (in/in/°F) 1000 Reference Pressure (psig)
Generic Type of Static Pressure Head Addition N/A Specific Water Height for Static Pressure Head Addition (in)
Generic Type of Temperature Increment for Tables 5
Specific Temperature Increment for Tables (°F)
Bottom Hea(
S0 110.5 6.8125 100 200 3
Generic N/A Generic 5
IParameters Adjusted Reference Temperature (°F)
Vessel Radius (in)
Vessel Thickness (in)
Heat-up / Cool-down Rate (°F/hr)
Heat-up / Cool-down Rate (°F/hr)
Stress Concentration Factor Type of Static Pressure Head Addition Specific Water Height for Static Pressure Head Addition (in)
Type of Temperature Increment for Tables Specific Temperature Increment for Tables (0F)
Non-Beltline ( Feedwater Nozzle) Parameters 30 Adjusted Reference Temperature (°F)
See Table Applied Pressure Stress Intensity Factor (ksi*in^0.5)
A-i Applied Thermal Stress Intensity Factor (ksi*inA0.5)
Minimum Thermal Stress Intensity Factor (ksi*in^0,5)
Yes 100 550 1000 Generic N/A Generic 5
File No.: 1001527.305 Revision: 2 Scale Krr based on Saturation Temperature?
Minimum Transient Temperature ('F)
Maximum Transient Temperature (°F)
Reference Pressure for Thermal Transient (psig)
Type of Static Pressure Head Addition Specific Water Height for Static Pressure Head Addition (in)
Type of Temperature Increment for Tables Specific Temperature Increment for Tables (°F)
Page A-3 of A-3 F0306-01RI
$~tructural Integrity Associates, Inc.Y APPENDIX B:
SUPPORTING CALCULATIONS File No.: 1001527.305 Revision: 2 Page B-I1 of B-46 F0306-01RI
Structural Integrity Associates, Inc.Y Table B-I: HNP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve A Calculations, for 37 EFPY
-~
S.
'3"
°ksi*inAO.5
°ksi*inAO.5 psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 62.6 62.6 65.7 69.1 72.8 77.0 81.6 41.7 41.7 43.8 46.0 48.6 51.3 54.4 90.0 90.0 95.0 100.0 105.0 110.0 115.0 0.0 1000.2 1051.0 1107.2 1169.3 1238.0 1313.9 Table B-2: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve A Calculations, for 37 EFPY A
9-Gage Fuid STemperture 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0
°ksi*inAO.5
°ksi*inAO.5 64.4 43.0 64.4 43.0 67.7 45.2 71.4 47.6 75.4 50.2 79.8 53.2 84.7 56.5 90.1 60.1 P-T Curve Tempeaure 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 psi 0.0 944.3 994.0 1048.9 1109.6 1176.7 1250.8 1332.7 File No.: 1001527.305 Revision: 2 Page B-2 of B-46 F0306-01 R1
Structural Integrity Associates, Inc~e Table B-3: HNP-2, WLI (NI6) Nozzle Beltline Region, Curve A Calculations, for 37 EFPY
-A
°F ksi*inA0.5
°ksi*inA0.5 ps 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 64.4 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 147.8 159.9 43.0 43.0 45.2 47.6 50.2 53.2 56.5 60.1 64.1 68.5 73.4 78.8 84.7 91.3 98.6 106.6 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 0.0 506.7 534.1 564.3 597.8 634.7 675.6 720.7 770.6 825.7 886.6 954.0 1028.4 1110.6 1201.5 1302.0 File No.: 1001527.305 Revision: 2 Page B-3 of B-46 F0306-01RI
Structural Integrity Associates, Inc.y Table B-4: HNP-2, Beitline Region (Lower Shell #2 Plate, t = 6.375"), Curve A Calculations, for 50.1 EFPY A
I
- aeFld
°ksi*inA0.5
°ksi*in^0.5
°F ~n' Pressure psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 58.9 58.9 61.6 64.6 67.9 71.6 75.6 80.1 85.0 39.3 39.3 41.1 43.1 45.3 47.7 50.4 53.4 56.7 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 0.0 940.4 984.9 1034.2 1088.6 1148.8 1215.3 1288.8 1370.0 Table B-5: HINP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve A Calculations, for 50.1 EFPY A
Temperture 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0
°ksi*inA0.5
°ksi*inAO.5 61.4 40.9 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 40.9 42.9 45.1 47.5 50.2 53.1 56.4 60.0 P-T Crv Temperature
°F 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 P-T Curve Presure psi 0.0 898.5 943.4 992.9 1047.7 1108.3 1175.3 1249.2 1331.0 File No.: 1001527.305 Revision: 2 Page B-4 of B-46 F0306-01R 1
Structural Integrity Associates, IncY Table B-6: HINP-2, WLI (N16) Nozzle Beitline Region, Curve A Calculations, for 50.1 EFPY iiiiiiii% iii~ ~iiiiiiiii*iiiiiii~
i!i~!-
A
- iiiii
-:~
iil Tepeatr "ksi*inAO.5 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 61.4 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 136.7 147.6 159.6 172.9
°ksi*inA0.5 40.9 40.9 42.9 45.1 47.5 50.2 53.1 56.4 60.0 64.0 68.4 73.3 78.6 84.6 91.1 98.4 106.4 115.3
°F 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 psi 0.0 481.5 506.2 533.5 563.7 597.1 634.0 674.7 719.8 769.5 824.6 885.4 952.6 1026.8 1108.9 1199.6 1299.9 1410.7 File No.: 1001527.305 Revision: 2 Page B-5 of B-46 F0306-01 R1
Structural Integrity Associates, IncY Table B-7: HNP-2, Bottom Head Region, Curve A Calculations, All EFPY
.A U.
°F ksi*inA0.5
°ksi*in^d 90.0 79.3 52.9 90.0 79.3 52.9 95.0 84.2 56.1 100.0 89.6 59.7 105.0 95.5 63.7 110.0 102.0 68.0 115.0 109.3 72.9 120.0 117.3 78.2 125.0 126.1 84.1 0.5
° 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 psi 0.0 869.3 924.3 985.1 1052.3 1126.6 1208.7 1299.4 1399.6 File No.: 1001527.305 Revision: 2 Page B-6 of B-46 F0306-01R I
~jStructural Integrity Associates, lnc.'
Table B-8: HNP-2, FW Nozzle / Non-Beltline, Curve A Calculations, All EFPY A *
-i~
°F eksi*inAO.5
°ksi*inAlO.5
°Fpsi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 102.0 102.0 109.3 117.3 126.1 135.9 146.7 158.6 68.0 68.0 72.9 78.2 84.1 90.6 97.8 105,8 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 0.0 832.0 893.1 960.7 1035.5 1118.0 1209.3 1310.2 File No.: 1001527.305 Revision: 2 Page B-7 of B-46 F0306-01RI
Structural Integrity Associates, lncY Table B-9: HNP-2, Beitline Region (Lower Shell #2 Plate, t = 6.375"), Curve B Calculations, for 37 EFPY and lO0°F/hr Cool-down
-z GaeFli
°ksi*inA0.5
°ksi*inAO.5 P-!T Curve i Tepeatr psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 62.6 62.6 65.7 69.1 72.8 77.0 81.6 86.7 92.3 98.6 105.4 113.0 121.4 26.4 26.4 27.9 29.6 31.5 33.6 35.9 38.5 41.3 44.4 47.8 51.6 55.8 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 0.0 621.8 659.9 702.1 748.7 800.2 857.1 920.0 989.5 1066.3 1151.2 1245.0 1348.7 Table B-10: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve B 37 EFPY and 100°F/hr Cool-down Calculations, for
°F
@ksi*inAO.5
°ksi*inA0.5
°Fpsi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 64.4 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 29.0 29.0 30.7 32.5 34.5 36.7 39.2 41.9 44.9 48.2 51.8 55.9 60.3 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 0.0 628.3 665.5 706.7 752.2 802.5 858.1 919.6 987.5 1062.5 1145.5 1237.1 1338.4 File No.: 1001527.305 Revision: 2 Page B-8 of B-46 F0306-01RI
~jjStructural Integrity Associates, Inc.'e Table B-Il1: HNP-2, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 37 EFPY and 1000F/hr Thermal Transient 9
- ksi~in^0.5 "ksiPin^0.5 psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 64.4 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 147.8 159.9 173.2 187.9 204.2 222.2 242.1 22.3 22.3 23.9 25.7 27.7 30.0 32.4 35.1 38.1 41.4 45.1 49.1 53.6 58.5 64.0 70.0 76.7 84.0 92.2 101.2 111.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 0.0 248.1 268.6 291.3 316.4 344.1 374.8 408.6 446.0 487.4 533.1 583.6 639.4 701.1 769.2 844.6 927.8 1019.8 1121.5 1233.9 1358.2 File No.: 1001527.305 Revision: 2 Page B-9 of B-46 F0306-01RI
~jjStructural Integrity Associates, IncY Table B-12: HNP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve B Calculations, for 50.1 EFPY and 1000F/hr Thermal Transient
.~
0F 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0
°ksi*inA0.5 58.9 58.9 61.6 64.6 67.9 71.6 75.6 80.1 85.0 90.5 96.5 103.1 110.5 118.6
°ksi*in^0.5 24.6 24.6 25.9 27.4 29.1 30.9 32.9 35.2 37.6 40.3 43.4 46.7 50.4 54.4 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 psi 0.0 576.9 610.4 647.3 688.1 733.2 783.1 838.2 899.1 966.5 1040.9 1123.1 1213.9 1314.4 150.0 Table B-13: HNP-2, Beltline Region (Lower-Int Shell #3 Plate, t = 5.375"), Curve B Calculations, for 50.1 EFPY and 100°F/hr Thermal Transient
.5
- 9.
9 9
"F
°ksi*in^0.5
°ksi*in^0.5 P-T Crv TepeaFr 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 61.4 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 27.5 27.5 29.0 30.6 32.5 34.5 36.7 39.1 41.8 44.8 48.1 51.8 55.8 60.2 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 P-TCuv psi 0.0 593.9 627.6 664.8 705.9 751.3 801.5 857.0 918.3 986.1 1061.0 1143.7 1235.2 1336.3 File No.: 1001527.305 Revision: 2 Page B-10 of B-46 F0306-01R I
Structural Integrity Associates, Inc.
Table B-14: HINP-2, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 50.1 EFPY and 1O00F/hr Thermal Transient
.5 e
(Sage Fluid P-T Curve P-T Curve Temperature Temperature Pressure 90.
90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0
°ksi*inAO.5 61.4 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 136.7 147.6 159.6 172.9 187.6 203.9 221.8 241.7 oksi*inAO.5 20.8 20.8 22.2 23.9 25.7 27.7 29.9 32.4 35.1 38.0 41.3 45.0 49.0 53.5 58.4 63.9 69.9 76.5 83.9 92.0 101.0 110.9 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 psi 0.0 229.2 247.7 268.2 290.9 315.9 343.5 374.1 407.9 445.2 486.5 532.1 582.5 638.2 699.8 767.8 843.0 926.1 1017.9 1119.4 1231.6 1355.5 File No.: 1001527.305 Revision: 2 Page B-11 of B-46 F0306-01 R1
Structural Integrity Associates, Inc.*
Table B-15: HNP-2, Bottom Head Region, Curve B Calculations, for All EFPY and 1000F/hr Thermal Transient
-z a
"F ksi*inAO.5
°ksi*inAO.5 psI 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 79.3 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 33.9 33.9 36.3 39.0 42.0 45.2 48.9 52.9 57.3 62.2 67.6 73.5 80.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 0.0 546.3 587.5 633.1 683.5 739.2 800.8 868.8 944.0 1027.1 1119.0 1220.4 1332.6 File No.: 1001527.305 Revision: 2 Page B-12 of B-46 F0306-01 RI
Structural Integrity Associates, lnc.*
Table B-16: HNP-2, FW Nozzle / Non-Beltline, Curve B Calculations, for All EFPY and 100°F/br Thermal Transient
.~
e Gage Fluid P-T Curve P-T Curve Temperature KIC Temperature Pressure 90.
90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0
°ksi*inA0.5 102.0 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 202.5 220.3 240.0 261.8
°ksi*inAO.5 44.6 33.2 36.3 39.8 43.7 48.1 52.9 58.3 64.3 71.0 78.4 86.6 95.8 106.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 psi 0.0 390.5 430.1 474.4 523.7 578.8 640.1 708.4 784.5 869.1 963.2 1067.9 1184.2 1313.4 File No.: 1001527.305 Revision: 2 Page B-13 of B-46 F0306-01RI
Structural Integrity Associates, Inc Table B-17: HINP-2, Beitline Region (Lower Shell #2 Plate, t = 6.375"), Curve B Calculations, for 37 EFPY and 2000F/hr Thermal Transient e
Gage Fluid P-T Curve P-T Curve Temperature Temperature Pressure 9
1(
°F ksi*inA0.5
@ksi*in^0.5 40.0 62.6 21.5
'0.0 62.6 21.5
'5.0 65.7 23.0 00.0 69.1 24.8 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 72.8 77.0 81.6 86.7 92.3 98.6 105.4 113.0 121.4 130.7 26.6 28.7 31.0 33.6 36.4 39.5 42.9 46.7 50.9 55.6 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 psi 0.0 501.0 539.1 581.3 627.9 679.4 736.3 799.2 868.7 945.5 1030.4 1124.2 1227.9 1342.5 Table B-18: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve B Calculations, for 37 EFPY and 2000F/hr Thermal Transient
~.z 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0
°ksi*inA0.5
°ksi*inA0.5 64.4 25.8 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 25.8 27.5 29.3 31.3 33.5 36.0 38.7 41.7 45.0 48.6 52.7 57.1 62.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 psi 0.0 555.9 593.1 634.3 679.8 730.1 785.7 847.2 915.1 990.1 1073.1 1164.7 1266.0 1378.0 File No.: 1001527.305 Revision: 2 Page B-14 of B-46 F0306-01 RI
jjStructuraI Integrity Associates, Inc~e Table B-19: HNP-2, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 37 EFPY and 200°F/hr Thermal Transient
.5
- a.
a a
-/-.
"kSI,'irIO.5 "lKsPifln^U.5
-1" psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 64.4 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 147.8 159.9 173.2 187.9 204.2 222.2 242.1 264.1 12.3 12.3 13.9 15.7 17.7 20.0 22.4 25.1 28.1 31.4 35.1 39.1 43.6 48.5 54.0 60.0 66.7 74.0 82.2 91.2 101.1 112.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 0.0 123.1 143.7 166.4 191.4 219.2 249.8 283.6 321.1 362.4 408.1 458.6 514.4 576.1 644.3 719.6 802.9 894.9 996.6 1109.0 1233.2 1370.5 File No.: 1001527.305 Revision: 2 Page B-15 of B-46 F0306-01 RI
jjStructural Integrity Associates, Inc.'
Table B-20: HNP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve B Calculations, for 50.1 EFPY and 2000F/hr Thermal Transient
.5 e
9
°F oksi*inA0.5
°ksi*inA0.5
-1" ps, 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 58.9 58.9 61.6 64.6 67.9 71.6 75.6 80.1 85.0 90.5 96.5 103.1 110.5 118.6 127.6 19.7 19.7 21.0 22.5 24.2 26.0 28.0 30.3 32.7 35.5 38.5 41.8 45.5 49.5 54.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 0.0 456.1 489.6 526.5 567.3 612.5 662.3 717.4 778.4 845.7 920.1 1002.3 1093.2 1193.6 1304.6 File No.: 1001527.305 Revision: 2 Page B-16 of B-46 F0306-01 R1
~jjStructural Integrity Associates, Inc.*
Table B-21: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve B Calculations, for 50.1 EFPY and 2000F/hr Thermal Transient I
3-t
°ksi*inAO.5
°ksi*inA0.5 7-psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 61.4 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 136.7 24.3 24.3 25.8 27.4 29.3 31.3 33.5 35.9 38.6 41.6 44.9 48.6 52.6 57.1 62.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 0.0 521.5 555.2 592.4 633.5 678.9 729.1 784.6 845.9 913.7 988.6 1071.3 1162.8 1263.9 1375.6 File No.: 1001527.305 Revision: 2 Page B-17 of B-46 F0306-01RI
~jjStructural Integrity Associates, Inc5 Table B-22: HNP-2, WLI (N16) Nozzle Beitline Region, Curve B Calculations, for 50.1 EFPY and 200°F/hr Thermal Transient
.~
3-I 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0
°ksi*inAO.5 61.4 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 136.7 147.6 159.6 172.9 187.6 203.9 221.8 241.7 263.6 "ksPin^0~L.5 "F
ps 10.8 10.8 12.2 13.9 15.7 17.7 19.9 22.4 25.1 28.0 31.3 35.0 39.0 43.5 48.4 53.9 59.9 66.5 73.9 82.0 91.0 100.9 111.8 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0 0.0 104.2 122.8 143.2 165.9 190.9 218.6 249.2 282.9 320.3 361.5 407.1 457.5 513.2 574.8 642.8 718.0 801.1 893.0 994.5 1106.6 1230.6 1367.6 File No.: 1001527.305 Revision: 2 Page B-18 of B-46 F0306-01 RI
~jStructural Integrity Associates, Inc.*
Table B-23: HNP-2, Bottom Head Region, Curve B Calculations, for All EFPY and 200°F/hr Thermal Transient
.5 9-9 I
°F ksi*inAO.5
°ksi*inA0.5 ps 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 79.3 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 28.1 28.1 30.6 33.2 36.2 39.5 43.1 47.1 51.5 56.4 61.8 67.8 74.4 81.7 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 0.0 448.1 489.4 535.0 585.4 641.1 702.6 770.7 845.9 929.0 1020.8 1122.3 1234.5 1358.4 File No.: 1001527.305 Revision: 2 Page B-19 of B-46 F0306-01 RI
Structural Integrity Associates, Inlc.
Table B-24: HNP-2, FW Nozzle / Non-Beltline, Curve B Calculations, for All EFPY and 200°F/hr Thermal Transient
-5
°F ksi*inAO.5
°ksi*in^0.5 psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 102.0 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 202.5 220.3 240.0 261.8 38.1 33.2 36.3 39.8 43.7 48.1 52.9 58.3 64.3 71.0 78.4 86.6 95.8 106.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 0.0 390.5 430.1 474.4 523.7 578.8 640.1 708.4 784.5 869.1 963.2 1067.9 1184.2 1313.4 File No.: 1001527.305 Revision: 2 Page B-20 of B-46 F0306-01RI
Structural Integrity Associates, In~
Table B-25: HNP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve C Calculations, for 37 EFPY and 100 0F/hr Thermal Transient 9-9 "1"
-(si~fl,,I.5
-ks1 1fn"U.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 46.4 46.4 47.8 49.3 51.0 52.9 55.0 57.2 59.8 62.6 65.7 69.1 72.8 77.0 81.6 86.7 92.3 98.6 105.4 113.0 121.4 18.3 18.3 19.0 19.8 20.6 21.6 22.6 23.7 25.0 26.4 27.9 29.6 31.5 33.6 35.9 38.5 41.3 44.4 47.8 51.6 55.8 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 0.0 422.0 439.2 458.1 479.1 502.2 527.8 556.0 587.3 621.8 659.9 702.1 748.7 800.2 857.1 920.0 989.5 1066.3 1151.2 1245.0 1348.7 File No.: 1001527.305 Revision: 2 Page B-21 of B-46 F0306-01RI
Structural Integrity Associates, IncY Table B-26: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve C Calculations, for 37 EFPY and 100°F/hr Thermal Transient
- F oksi*inA0.5
°ksi*inA0.5
°Fpsi 50.0 47.2 20.4 90.0 0.0 50.0 47.2 20.4 90.0 433.1 55.0 48.7 21.2 95.0 449.9 60.0 50.3 22.0 100.0 468.4 65.0 52.1 22.9 105.0 488.9 70.0 54.1 23.9 110.0 511.5 75.0 56.3 25.0 115.0 536.4 80.0 58.8 26.2 120.0 564.0 85.0 61.5 27.5 125.0 594.6 90.0 64.4 29.0 130.0 628.3 95.0 67.7 30.7 135.0 665.5 100.0 71.4 32.5 140.0 706.7 105.0 75.4 34.5 145.0 752.2 110.0 79.8 36.7 150.0 802.5 115.0 84.7 39.2 155.0 858.1 120.0 90.1 41.9 160.0 919.6 125.0 96.1 44.9 165.0 987.5 130.0 102.7 48.2 170.0 1062.5 135.0 110.0 51.8 175.0 1145.5 140.0 118.1 55.9 180.0 1237.1 145.0 127.1 60.3 185.0 1338.4 File No.: 1001527.305 Page B-22 of B-46 Revision: 2 F0306-01 R1
Structural Integrity Associates, Inc.=
Table B-27: HNP-2, WLI (N16) Nozzle Beltline Region, Curve C Calculations, for 37 EFPY and 100°F/hr Thermal Transient e.
°ksi'in^0.5
°ksi~in^0.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75,0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 47.2 47.2 48.7 50.3 52.1 54.1 56.3 58.8 61.5 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 147.8 159.9 173.2 187.9 204.2 222.2 242.1 13.7 13.7 14.4 15.2 16.1 17.1 18.2 19.4 20.8 22.3 23.9 25.7 27.7 30.0 32.4 35.1 38.1 41.4 45.1 49.1 53.6 58.5 64.0 70.0 76.7 84.0 92.2 101.2 111.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0 200.0 205.0 210.0 215.0 220.0 225.0 0.0 140.6 149.8 160.0 171.3 183.7 197.5 212.7 229.5 248.1 268.6 291.3 316.4 344.1 374.8 408.6 446.0 487.4 533.1 583.6 639.4 701.1 769.2 844.6 927.8 1019.8 1121.5 1233.9 1358.2 File No.: 1001527.305 Revision: 2 Page B-23 of B-46 F0306-01RI
$jJtructural Integrity Associates, lncY Table B-28: HINP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve C Calculations, for 50.1 EFPY and 100°F/hr Thermal Transient 9
"ksi~inA0.5 Oksi'inA0.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 44.8 44.8 46.0 47.3 48.8 50.4 52.3 54.3 56.5 58.9 61.6 64.6 67.9 71.6 75.6 80.1 85.0 90.5 96.5 103.1 110.5 118.6 17.5 17.5 18.1 18.8 19.5 20.3 21.2 22.2 23.4 24.6 25.9 27.4 29.1 30.9 32.9 35.2 37.6 40.3 43.4 46.7 50.4 54,4 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 0.0 401.9 416.9 433.5 451.9 472.1 494.5 519.3 546.7 576.9 610.4 647.3 688.1 733.2 783.1 838.2 899.1 966.5 1040.9 1123.1 1213.9 1314.4 File No.: 1001527.305 Revision: 2 Page B-24 of B-46 F0306-01RI
S7~trctural Integrity Associates, lnc?
Table B-29: HNP-2, Beitline Region (Lower-mat Shell #3 Plate, t = 5.375"), Curve C Calculations, for 50.1 EFPY and 100°F/hr Thermal Transient
- e.
9
°ksi*inA0.5
°ksi*inA0.5 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 45.9 45.9 47.2 48.7 50.3 52.1 54.1 56.3 58.7 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 19.7 19.7 20.4 21.2 22.0 22.9 23.9 25.0 26.2 27.5 29.0 30.6 32.5 34.5 36.7 39.1 41.8 44.8 48.1 51.8 55.8 60.2 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 psi 0.0 417.7 432.8 449.5 468.0 488.4 511.0 535.9 563.5 593.9 627.6 664.8 705.9 751.3 801.5 857.0 918.3 986.1 1061.0 1143.7 1235.2 1336.3 File No.: 1001527.305 Revision: 2 Page B-25 of B-46 F0306-01R 1
Structural Integrity Associates, Inlc~e Table B-30: HNP-2, WLI (N16) Nozzle Beitline Region, Curve C Calculations, for 50.1 EFPY and 100°F/hr Thermal Transient I
e ksi*inAO.5 "ksi*inAO.5 "Fpsi 50.0 45.9 13.0 90.0 0.0 50.0 45.9 13.0 90.0 132.1 55.0 47.2 13.7 95.0 140.4 60.0 48.7 14.4 100.0 149.6 65.0 50.3 15.2 105.0 159.8 70.0 52.1 16.1 110.0 171.0 75.0 54.1 17.1 115.0 183.5 80.0 56.3 18.2 120.0 197.2 85.0 58.7 19.4 125.0 212.4 90.0 61.4 20.8 130.0 229.2 95.0 64.4 22.2 135.0 247.7 100.0 67.7 23.9 140.0 268.2 105.0 71.3 25.7 145.0 290.9 110.0 75.3 27.7 150.0 315.9 115.0 79.7 29.9 155.0 343.5 120.0 84.6 32.4 160.0 374.1 125.0 90.0 35.1 165.0 407.9 130.0 96.0 38.0 170.0 445.2 135.0 102.6 41.3 175.0 486.5 140.0 109.9 45.0 180.0 532.1 145.0 118.0 49.0 185.0 582.5 150.0 126.9 53.5 190.0 638.2 155.0 136.7 58.4 195.0 699.8 160.0 147.6 63.9 200.0 767.8 165.0 159.6 69.9 205.0 843.0 170.0 172.9 76.5 210.0 926.1 175.0 187.6 83.9 215.0 1017.9 180.0 203.9 92.0 220.0 1119.4 185.0 221.8 101.0 225.0 1231.6 190.0 241.7 110.9 230.0 1355.5 File No.: 1001527.305 Page B-26 of B-46 Revision: 2 F0306-01R 1
Structural Integrity Associates, IncY Table B-31: HNP-2, Bottom Head Region, Curve C Calculations, for All EFPY and 100°F/hr Thermal Transient e-9 Gage Fluid P-T curve P-T Curve Temperature Temperature Pressure 50.
50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0
°ksi*inA0.5 53.9 53.9 56.1 58.5 61.2 64.1 67.4 71.0 75.0 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8
°ksi*inaO.5 21.2 21.2 22.3 23.5 24.8 26.3 27.9 29.7 31.7 33.9 36.3 39.0 42.0 45.2 48.9 52.9 57.3 62.2 67.6 73.5 80.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 psi 0.0 330.2 348.8 369.2 391.9 416.9 444.6 475.2 508.9 546.3 587.5 633.1 683.5 739.2 800.8 868.8 944.0 1027.1 1119.0 1220.4 1332.6 File No.: 1001527.305 Revision: 2 Page B-27 of B-46 F0306-01 RI
Structural Integrity Associates, Inc.Y Table B-32: HINP-2, FW Nozzle / Non-Beltline, Curve C Calculations, for All EFPY and 100°F/hr Thermal Transient e
Gage Fluid P-T curve P-T Curve Temperature K16 Temperature Pressure 50.
50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0
°ksi*in^0.5 64.1 64.1 67.4 71.0 75.0 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 202.5 220.3 240.0 261.8
°ksi*inA0.5 25.6 17.6 18.9 20.3 21.9 23.7 25.7 27.9 30.4 33.2 36.3 39.8 43.7 48.1 52.9 58.3 64.3 71.0 78.4 86.6 95.8 106.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 psi 0.0 193.0 209.1 227.0 247.1 269.7 295.0 323.3 355.0 390.5 430.1 474.4 523.7 578.8 640.1 708.4 784.5 869.1 963.2 1067.9 1184.2 1313.4 File No.: 1001527.305 Revision: 2 Page B-28 of B-46 FO306-01RI
Structural Integrity Associates, Inlc~
Table B-33: HNP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve C Calculations, for 37 EFPY and 200°F/hr Thermal Transient D
Gage Fluid P-T Curve P-T Curve Temperature K1 Temperature Pressure 50.
50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0
°ksi*inAO.5 46.4 46.4 47.8 49.3 51.0 52.9 55.0 57.2 59.8 62.6 65.7 69.1 72.8 77.0 81.6 86.7 92.3 98.6 105.4 113.0 121.4 130.7
°ksi*inAO.5 13.4 13.4 14.1 14.9 15.7 16.7 17.7 18.8 20.1 21.5 23.0 24.8 26.6 28.7 31.0 33.6 36.4 39.5 42.9 46.7 50.9 55.6 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 psi 0.0 301.3 318.4 337.3 358.3 381.4 407.0 435.2 466.5 501.0 539.1 581.3 627.9 679.4 736.3 799.2 868.7 945.5 1030.4 1124.2 1227.9 1342.5 File No.: 1001527.305 Revision: 2 Page B-29 of B-46 F0306-01RI
Structural Integrity Associates, Inc.?
Table B-34: HNP-2, Beltline Region (Lower-lnt Shell #~3 Plate, t = 5.375"), Curve C Calculations, for 37 EFPY and 200°F/hr Thermal Transient e-e "F
ksi'in^0.5 "ksi~inA0.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 47.2 47.2 48.7 50.3 52.1 54.1 56.3 58.8 61.5 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 17.2 17.2 18.0 18.8 19.7 20.7 21.8 23.0 24.4 25.8 27.5 29.3 31.3 33.5 36.0 38.7 41.7 45.0 48.6 52.7 57.1 62.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 0.0 360.8 377.5 396.0 416.5 439.1 464.0 491.6 522.2 555.9 593.1 634.3 679.8 730.1 785.7 847.2 915.1 990.1 1073.1 1164.7 1266.0 1378.0 File No.: 1001527.305 Revision: 2 Page B-30 of B-46 F0306-01R I
Structural Integrity Associates, Inc.t Table B-35: HNP-2, WLI (N16) Nozzle Beltline Region, Curve C Calculations, for 37 EFPY and 200°F/hr Thermal Transient e-
°F ksi~inA0.5 "ksi~in^0.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 47.2 47.2 48.7 50.3 52.1 54.1 56.3 58.8 61.5 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 147.8 159.9 173.2 187.9 204.2 222.2 242.1 264.1 3.7 3.7 4.4 5.2 6.1 7.1 8.2 9.4 10.8 12.3 13.9 15.7 17.7 20.0 22.4 25.1 28.1 31.4 35.1 39.1 43.6 48.5 54.0 60.0 66.7 74.0 82.2 91.2 101.1 112.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0 200.0 205.0 210.0 215.0 220.0 225.0 230.0 0.0 15.6 24.9 35.1 46.3 58.8 72.5 87.8 104.6 123.1 143.7 166.4 191.4 219.2 249.8 283.6 321.1 362.4 408.1 458.6 514.4 576.1 644.3 719.6 802.9 894.9 996.6 1109.0 1233.2 1370.5 File No.: 1001527.305 Revision: 2 Page B-31 of B-46 F0306-01RI
~jStructural Integrity Associates, IncY Table B-36: HNP-2, Beitliee Region (Lower Shell #2 Plate, t = 6.375"), Curve C Calculations, for 50.1 EFPY and 2000F/hr Thermal Transient
- 9.
9 GaeFli
°ksi*inAO.5 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 44.8 44.8 46.0 47.3 48.8 50.4 52.3 54.3 56.5 58.9 61.6 64.6 67.9 71.6 75.6 80.1 85.0 90.5 96.5 103.1 110.5 118.6 127.6
°ksi*inAO.5 12.6 12.6 13.2 13.9 14.6 15.4 16.4 17.4 18.5 19.7 21.0 22.5 24.2 26.0 28.0 30.3 32.7 35.5 38.5 41.8 45.5 49.5 54.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0 psi 0.0 281.1 296.1 312.7 331.1 351.3 373.8 398.5 425.9 456.1 489.6 526.5 567.3 612.5 662.3 717.4 778.4 845.7 920.1 1002.3 1093.2 1193.6 1304.6 File No.: 1001527.305 Revision: 2 Page B-32 of B-46 F0306-01RI
~j~Structural Integrity Associates, Iflc.e Table B-37: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve C Calculations, for 50.1 EFPY and 200°F/hr Thermal Transient e
oF ksi*inAO.5
°ksi*inAO.5
°Fpsi 50.0 45.9 16.6 90.0 0.0 50.0 45.9 16.6 90.0 345.3 55.0 47.2 17.2 95.0 360.4 60.0 48.7 18.0 100.0 377.1 65.0 50.3 18.8 105.0 395.6 70.0 52.1 19.7 110.0 416.0 75.0 54.1 20.7 115.0 438.6 80.0 56.3 21.8 120.0 463.5 85.0 58.7 23.0 125.0 491.1 90.0 61.4 24.3 130.0 521.5 95.0 64.4 25.8 135.0 555.2 100.0 67.7 27.4 140.0 592.4 105.0 71.3 29.3 145.0 633.5 110.0 75.3 31.3 150.0 678.9 115.0 79.7 33.5 155.0 729.1 120.0 84.6 35.9 160.0 784.6 125.0 90.0 38.6 165.0 845.9 130.0 96.0 41.6 170.0 913.7 135.0 102.6 44.9 175.0 988.6 140.0 109.9 48.6 180.0 1071.3 145.0 118.0 52.6 185.0 1162.8 150.0 126.9 57.1 190.0 1263.9 155.0 136.7 62.0 195.0 1375.6 File No.: 1001527.305 Page B-33 of B-46 Revision: 2 F0306-01 RI
jjStructural Integrity Associates, lnc5 Table B-38: HINP-2, WLI (NI6) Nozzle Beltline Region, Curve C Calculations, for 50.1 EFPY and 200°F/hr Thermal Transient U
°F 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0
°ksi*inA0.5 45.9 45.9 47.2 48.7 50.3 52.1 54.1 56.3 58.7 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 136.7 147.6 159.6 172.9 187.6 203.9 221.8 241.7 263.6
°ksi*inAO.5 3.0 3.0 3.7 4.4 5.2 6.1 7.1 8.2 9.4 10.8 12.2 13.9 15.7 17.7 19.9 22.4 25.1 28.0 31.3 35.0 39.0 43.5 48.4 53.9 59.9 66.5 73.9 82.0 91.0 100.9 111.8 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0 200.0 205.0 210.0 215.0 220.0 225.0 230.0 235.0 psi 0.0 7.1 15.5 24.7 34.8 46.1 58.5 72.3 87.4 104.2 122.8 143.2 165.9 190.9 218.6 249.2 282.9 320.3 361.5 407.1 457.5 513.2 574.8 642.8 718.0 801.1 893.0 994.5 1106.6 1230.6 1367.6 File No.: 1001527.305 Revision: 2 Page B-34 of B-46 F0306-01RI
Structural Integrity Associates, lnc.?
Table B-39: HNP-2, Bottom Head Region, Curve C Calculations, for All EFPY and 2000F/hr Thermal Transient 9-e
°F oksi*inA0.5
°ksi*inA0.5 p~si 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 53.9 53.9 56.1 58.5 61.2 64.1 67.4 71.0 75.0 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 15.4 15.4 16.5 17.7 19.0 20.5 22.1 23.9 25.9 28.1 30.6 33.2 36.2 39.5 43.1 47.1 51.5 56.4 61.8 67.8 74.4 81.7 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 0.0 232.1 250.6 271.1 293.7 318.8 346.4 377.0 410.8 448.1 489.4 535.0 585.4 641.1 702.6 770.7 845.9 929.0 1020.8 1122.3 1234.5 1358.4 File No.: 1001527.305 Revision: 2 Page B-35 of B-46 F0306-01RI
Structural Integrity Associates, Inc.Y Table B-30: HNP-2, FW Nozzle / Non-Beltline, Curve C Calculations, for All EFPY and 2000F~hr Thermal Transient a
°F ksi'inA0.5
°ksi~inA0.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 64.1 64.1 67.4 71.0 75.0 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 202.5 220.3 240.0 261.8 19.2 17.6 18.9 20.3 21.9 23.7 25.7 27.9 30.4 33.2 36.3 39.8 43.7 48.1 52.9 58.3 64.3 71.0 78.4 86.6 95.8 106.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 0.0 193.0 209.1 227.0 247.1 269.7 295.0 323.3 355.0 390.5 430.1 474.4 523.7 578.8 640.1 708.4 784.5 869.1 963.2 1067.9 1184.2 1313.4 File No.: 1001527.305 Revision: 2 Page B-36 of B-46 F0306-01RI
~jStructural Integrity Associates, Inc.'
Curve A - Pressure Test, All Components
-BL1 BL2 N16 BH
-FWN IOCFR50 a.0 E
61 1300 1200 1100 1000 9O0f 800 700r 6OOk 500 400K......
300 ~
200 100 50 0
100 150 Minimum Reactor Vessel Metal Temperature (°F) 200 250 Figure B-I: HNP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 37 EFPY Note: BL is Beitline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-37 of B-46 F0306-01 RI
Structural Integrity Associates, Inc.*
Curve A - Pressure Test, All Components
-BLl BL_2....-
-BH FWN IOCFR50 wJ 11 a-E
-S 1300 1200 1100 +--....
900 -
700 -i 600 500-400 T......
300 -.
201 100 0
0 50 100 150 Minimum Reactor Vessel Metal Temperature (oF) 200 250 Figure B-2: HNP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 50.1 EFPY Note: BL is Beltline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-38 of B-46 F0306-01R I
~jStructurul Integrity Associates, IncY Curve B - Core Not Critical, All Components
-BL1 BL2 N16 BH FWN 10CFR50 a.
-I
'I C4..
100 150 Minimum Reactor Vessel Metal Temperature (°F) 250 Figure B-3: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 1O00F/hr Note: BL is Beltline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-39 of B-46 F0306-01RIl
~jStructural Integrity Associates, Inc.Y Curve B - Core Not Critical, All Components
-BLl N16 BH FWN IOCFR50O....BL2 a.
E 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 U
0 50 100 150 200 250 Minimum Reactor Vessel Metal Temperature ("F)
Figure B-4: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 100°F/hr Note: BL is Beltline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-40 of B-46 F0306-01R 1
~jjStructural Integrity Associates, Inc.e Curve B - Core Not Critical, All Components
-BL1....BL2 N16 1 BH 1-
-FWN
-1.
OCFR50 a.
E U9
&r 50 100 150 Minimum Reactor Vessel Metal Temperature (°F) 250 Figure B-5: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 200°F/hr Note: BL is Beitline, BH is Bottom Head and FW~N is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-41 of B-46 F0306-01JR I
~jStrcturailonegrity Associates, IncY Curve B - Core Not Critical, All Components
-BL1 BL2 N16 BH
-FWN IOCFR50 hA El
-1 S
50 I00 150 Minimum Reactor Vessel Metal Temperature ('F) 250 Figure B-6: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 200°F/hr Note: BL is Beitline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-42 of B-46 F0306-01R 1
Structural Integrity Associates, Inc.
Curve C - Core Critical, All Components
-BL1....BL2 N16 BH
-FWN I(XCFR50 1300 1200(
1100 900 S800
- 1 E
@1 400 300 200 100 0
50 100 150 200 Minimum Reactor Vessel Metal Temperature (0F) 250 Figure B-7: HINP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 100°F/hr Note: BL is Beitline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-43 of B-46 F0306-01R 1
jjStructural Integrity Associates, /nc.*
Curve C - Core Critical, All Components
-BL1.
81..B2....
N16 BH
-FWN IOCFR50 0.
61 C
E U
100 150 Minimum Reactor Vessel Metal Temperature (OF) 250 Figure B-8: HNP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 1O0°F/hr Note: BL is Beitline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-44 of B-46 F0306-01RI
Structural Integrity Associates, IncY u
Curve C - Core Critical, All Components
-8
- 11.
81..B2....
N16 BH FWN 10CFR50 a.
7.
E O1 a:
1 3OO0 t 1200
- 110 900-700 600 300 200%
100 50 100 150 Minimum Reactor Vessel Metal Temperature (°F) 200 250 Figure B-9:HINP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 200°F/hr Note: BL is Beltline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-45 of B-46 F0306-01 RI
Structural Integrity Associates, Inc.Y Curve C - Core Critical, All Components
-BL1 BL2 N16 BH
-FWN IOCFR50 1300 1200 1100 1000 900 6700 4OO 2O 100 0
50 100 150 Minimum Reactor Vessel Metal Temperature (*F) 200 250 Figure B-10: HNP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 200°F/hr Note: BL is Beitline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-46 of B-46 F0306-01 RI
Edwin I. Hatch Nuclear Plant Response to Request for Additional Information Regarding Application for Amendment to Technical Specifications for Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-41 9-A Corrected Table 3 to the Unit 1 PTLR
Hatch Unit 1 PTLR Revision 0 Page 28 of 40 Table 3: HNP-1 P-T Curve C (Normal Operation - Core Critical) for 38 EFPY (continued)
Non-Beltline Region P-T Curve P-T Curve Temperature Pressure "F
psi 76.0 0.0 76.0 97.6 98.0 140.6 112.1 183.6 122.6 226.6 130.9 269.6 137.9 312.6 212.0 312.6 212.0 1563.0
-Stru ctural Integrity Associates, Inc.
File No.: 1001527.305 l/*
Project No.: 1400365 CALCULATION PACKAGE
{Quality Program: [] Nuclear [] Commercial PROJECT NAME:
Plant Hatch Unit 1&2 P-T Curve Evaluation CONTRACT NO.:
P0: SNC 19354, Rev. 1 CONTRACT: 19354, Rev. 4 CLIENT:
PLANT:
Southern Nuclear Operating Co.
Hatch Nuclear Plant, Unit 2 CALCULATION TITLE:
Hatch Unit 2 P-T Curve Calculation for 37 and 50.1 EFPY Document Affected Project Manager Peae~)&Cekrs Reiin PgsRevision Description Approval Peae~)&Cekrs Reiio agsSignature
& Date Signatures & Date 01
- 45 Initial Issue Responsible Engineer A-i -A-3 B-i - B-46 D. V. Sommerville 12/30/2011 C. Oberembt 12/30/2011 Responsible Verifier D. V. Sommerville 12/30/2011 116 Citations for References Responsible Engineer
[1] and [2] have been updated to show citation for NRC approved D.V.t Sommerville M. Qin Versions. Citation for 9/19/20 139//23 Reference [9] has been updated to show current Responsible Verifiers revision. Reference [9]
was revised for the same reason as identified above for References [1] and
[2]. No technical D. V. Sommerville changes are made for this9//23 revision.
Page 1 of 45 F0306-01RI
V S*tructural Integrity Associates, Inc. File No.: 1001527.305 C L U A INP C A EProject No.: 1001527 CALCUL TION P CKAGEQuality Program: [] Nuclear
[-- Commercial CALCULATION TITLE:
Hatch Unit 2 P-T Curve Calculation for 37 and 50.1 EFPY Document Affected Project Manager Preparer(s) & Checker(s)
Revision Description ApprovalSintrs&De Revision Pages Signature & DateSintrs&De 2
6, 7, 13, 14, 15, Revised to incorporate Responsible Engineer 17 -45 updated fluence data and*w
//
A-2, A-3 to address NRC condition B B-46 for SI!R-05-044-Rev. 1-A regarding lowest service D. V. Sommerville temperature.
9/10/2014 D. V. Sommerville for C. J. Oberembt 9/10/2014 Responsible Verifier D. V. Sommerville 9/10/2 014 Page 2 of 45 F0306-01R1
VStructural Integrity Associates, Itcof Table of Contents
1.0 INTRODUCTION
........................................................................... 6 2.0 METHODOLOGY........................................................................... 6 3.0 ASSUMPTIONS........................................................................... 11 4.0 DESIGN INPUTS.......................................................................... 13 5.0 CALCULATIONS.................. i...................................................... 14 5.1 Pressure Test (Curve A)........................................................... 15 5.2 Normal Operation - Core Not Critical (Curve B)............................... 15 5.3 Normal Operation - Core Critical (Curve C).................................... 16
6.0 CONCLUSION
S........................................................................... 16
7.0 REFERENCES
............................................................................. 17 APPENDIX A : P - T CURVE INPUT LISTING............................................. A-I APPENDIX B:* SUIPPORTING CALCULATIONS.......................................... B-i File No.: 1001527.305 Revision: 2 Page 3 of 45 F0306-01R1
Structural Integrity Associates,/Ino.*
List of Tables Table 1: Summary of Minimum Temperature Requirements for P-T Limit Curves..................
18 Table 2: HNP-2 Beltline Region, Curve A, for 37 EFPY............................................... 19 Table 3: HNP-2 Beitline Region, Curve A, for 50.1 EFPY............................................. 20 Table 4: HNP-2 Bottom Head Region, Curve A, for All EFPY........................................ 21 Table 5: HNP-2 Non-Beltline Region, Curve A, for All EFPY......................................... 21 Table 6: HNP-2, Beltline Region, Curve B, for 37 EFPY and 1000F/hr Thermal Transient......... 22 Table 7: HNP-2, Beltline Region, Curve B, for 50.1 EFPY and 100OF/hr Thermal Transient......
23 Table 8: HINP-2, Beltline Region, Curve B, for 37 EFPY and 2000F/hr Thermal Transient......... 24 Table 9: HNP-2, Beltline Region, Curve B, for 50.1 EFPY and 200°F/hr Thermal Transient......
25 Table 10: HNP-2 Bottom Head Region, Curve B for All EFPY and lO0OF/hr Thermal Transient... 26 Table 11: HNP-2 Bottom Head Region, Curve B for All EFPY and 2000F/hr Thermal Transient... 27 Table 12: HNP-2 Non-Beltline Region, Curve B, for All EFPY and 100OF/hr Thermal Transient.. 28 Table 13: HNP-2 Non-Beltline Region, Curve B, for All EFPY and 2000F/hr Thermal Transient.. 28 Table 14: HNP-2, Beltline Region, Curve C, for 37 EFPY and l00OF/hr Thermal Transient.......29 Table 15: HNP-2, Beltline Region, Curve C, for 50.1 EFPY and l00OF/hr Thermal Transient.....
30 Table 16: HNP-2, Beltline Region, Curve C, for 37 EFPY and 2000F/hr Thermal Transient........ 31 Table 17: HNP-2, Beitline Region, Curve C, for 50.1 EFPY and 200°F/hr Thermal Transient.....32 Table 18:.HNP-2 Bottom Head Region, Curve C for All EFPY and.100°F/hr Thermal Transient... 33 Table 19: HNP-2 Bottom Head Region, Curve C for All EFPY and 200°F/hr Thermal Transient... 34 Table 20: HNP-2 Non-Beitline Region, Curve C, for All EFPY and lOO°F/hr Thermal Transient.. 35 Table 21: HNP-2 Non-Beitline Region, Curve C, for All EFPY and 200°F/hr Thermal Transient.. 35 File No.: 1001527.305 Page 4 of 45 Revision: 2 F0306-01 R1
VStructural Integrity Associates, IncY List of Figures Figure 1 : HNP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 37 EFPY...................... 36 Figure 2:HI-NP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 50.1 EFPY.................... 37 Figure 3: J-NP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 100°F/hr....38 Figure 4: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 100°F/hr.. 39 Figure 5: ITNP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 2000F/hr....40 Figure 6:HJ-NP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 200°F/hr.. 41 Figure 7: HNP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 100°F/hr......... 42 Figure 8: I-NP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 100°F/hr......43 Figure 9: HNP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 200°F/hr......... 44 Figure 10: INP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 200°F/hr.....45
- File No.: 1001527.305 Revision: 2 Page 5 of 45 F0306-01RI
VStructural Integrity Associates, Inc.Y
1.0 INTRODUCTION
This calculation package develops pressure-temperature (P-T) limit curves for the beitline, bottom head, and non-beitline regions of the Hatch Nuclear Plant, Unit 2 (HNP-2) reactor pressure vessel (RPV). The P-T curves are developed for 37 and 50.1 effective full power years (EFPY) of operation, and for 100°F/hr and 200°F/hr thermal transients. The P-T curves are prepared using the methods documented in the Boiling Water Reactor Owner's Group (BWROG3) Licensing Topical Reports (LTRs), "Pressure Temperature Limits Report Methodology for Boiling Water Reactors" [1] and "Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations" [2]. These LTRs satisfy the requirements of 10CFR50 Appendix G3 [3] and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Non-mandatory Appendix G3 [4].
2.0 METHODOLOGY A full set of P-T curves, applicable to the followingplant conditions, are prepared:
- 1. Pressure Test (Curve A),
- 2. Normal Operation - Core Not Critical (Curve B), and
- 3. Normal Operation - Core Critical (Curve C).
For each plant condition above, separate curves are provided for each of the following three regions of the RPV as well as a composite curve for the entire RPV:
- 1. The beitline region,
- 2. The bottom head region,
- 3. The non-beltline region,
- 4. Composite curve (bounding curve for all regions)
In some cases, a region may contain more than one component which is considered for development of the associated P-T curve. For HNP-2, the curve for each vessel region identified above is composed from the bounding P-T limits determined for the following components:
- 1. Beltline:
- a. Beltline shell
- b. Water level instrument (WLI) nozzle, N16
- 2. Non-beltline
- b. 10CFR50 Appendix G limits [3]
- 3. Bottom Head:
- a. Bottom head penetrations (in-core monitor housings, control rod drive housings)
Consequently, separate curves are prepared for each component considered for each region then a bounding curve is drawn from the individual curves.
File No.: 1001527.305 Page 6 of 45 Revision: 2 F0306-01R1
Structural Integrity Associates, lnc:*
Complete sets of P-T curves, as identified above, are provided for a 100 °F/hr and 200 °F/hr thermal transient at 37 and 50.1 EFPY of operation.
The methodology for calculating P-T curves, described below, is taken from Reference [1 ] unless specified otherwise. Additional guidance regarding analysis of WLI nozzles is taken from Reference
[2].
The P-T curves are calculated by means of an iterative procedure, in which the following steps are performed:
Step 1: A fluid temperature, T, is assumed. The P-T curves are calculated considering a postulated flaw with a 6:1 aspect ratio that extends 1/4 of the way through the. vessel wall. The temperature at the postulated flaw tip is assumed equal to the coolant temperature.
Step 2: The static fracture toughness, K10, is computed using the following equation:
K10 33.2 + 20.734. eO'O2(T-ART)
(1)
Where:
Ki0
= the lower bound static fracture toughness (ksi*/n).
T
=the metal temperature at the tip of the postulated 1/4 through-wall flaw (0F).
=the Adjusted Reference Temperature (ART) for the limiting material in the RPV region under consideration (0F).
Step 3: The allowable stress intensity factor due to pressure, K1p, is calculated as:
Kip -
(2)-Ki SF(2 Where:
Kip
= the allowable stress intensity factor due to membrane (pressure) stress (ksi\\1in).
Kit the lower bound static fracture toughness calculated in Eq. (1)
(ksi*/in).
K1it the thermal stress intensity factor (ksi*/in) from through wall thermal gradients.
SF
=the ASME Code recommended safety factor, based on the reactor condition. For hydrostatic and leak test conditions (i.e., P-T Curve A), SF = 1.5. For normal operation, both core non-critical and core critical (i.e., P-T Curves B and C), SF = 2.0.
When calculating values for Curve A, the thermal stress intensity factor is neglected (Kit = 0),
since the hydrostatic leak test is performed at or near isothermal conditions (typically, the rate of temperature change is 25°F/hr or less).
File No.: 1001527.305 Page 7 of 45 Revision: 2 F0306-01IR1
Structural Integrity Associates, IncY~
For Curve B and Curve C calculations, Kit is computed in different ways based on the evaluated region. For the beitline, with the exception of nozzles, and bottom head regions, Kit is determined using the following equation:
K1, =O0.953 x10-3**CR. t2 5 (3)
Where:
CR
=
the cool-down rate of the vessel (0F/hr).
t
=
the RPV wall thickness (in).
For the FW nozzle, Kit is obtained from the stress distribution output of a plant specific finite element analysis (FEA). A polynomial curve-fit is determined for the through-wall stress distribution at the bounding time point. The linear elastic fracture mechanics solution for Kit is:
K1, =
lz{0.706C0
+ 0.537KjCi, +0.448 -*-C 2, + 0.393(4a c3 (4)
Where:
a
=1/4 through-wall postulated flaw depth, a = 1/4 t (in).
t
= thickness of the cross-section through the nozzle at the limiting path near the inner blend radius (in).
C~,l,= thermal stress polynomial coefficients, obtained from a curve-C2 t,C 3 t fit of the extracted stresses from a transient FEA.
The thermal stress polynomial coefficients are based on the assumed polynomial form of or(x) = CO + C1
- x + C2
- x + C3 *. x3. In this equation, "x" represents the radial distance in inches from the inside surface to a point on the crack face.
For the WLI nozzle, the nozzle assembly consists of an insert attached to the RPV with a partial penetration weld. The nozzle material is not ferritic and does notneed to be specifically evaluated. However, the effect of the penetration on the adjacent shell must be considered.
Reference [2, Equation 8-2] provides the following simplified solution for the thermal stress intensity factor caused by a 1 00°F/hr thermal transient:
Kj~ranm = 874, 844 [a (t* +t,)]-20.715 (5)
Where:
KI-ramp
= the K1t (thermal stress intensity factor from through wall thermal gradients) for a WLI nozzle subjected to 1000F/hr thermal transient (ksi,/in).
at
= the instrument nozzle material coefficient of thermal expansion at the highest thermal ramp temperature (in/in/0F).
tv = the vessel thickness (in).
tn = the nozzle thickness (in).
File No.: 1001527.305 Page 8 of 45 Revision: 2 F0306-01RI
VStructural Integrity Associates, IncY Larger heat-up/cool-down rates are conservatively considered by scaling the stress intensity factor obtained using Eq. (5) by the ratio of the desired heat-up/cool-down rate to 100 0F/hr.
Since the P-T curves are applicable to all Level A/B events, the bounding Level A/B events, for each region and component, identified from the vessel and nozzle thermal cycle diagrams
[7], are considered when calculating the K1 t above.
Step 4: The allowable internal pressure of the RPV is calculated differently for each evaluation region.
For the beltline region, with the exception of nozzles, the allowable pressure is determined as follows:
PaIo~o (6)
Where:
Pallow
= the allowable RPV internal pressure (psig).
Kp
= the allowable stress intensity factor due to membrane (pressure) stress, as defined in Eq. (2) (ksi~in).
t
= the RPV wall thickness (in).
Mm
= the membrane correction factor for an inside surface axial flaw:
Mm =1.85 for *t <2 Mm = 0.926 +/ for 2 <*Jt <*3.464 Mm =3.21 for /t> 3.464.
Ri
= the inner radius of the RPV (in).
For the bottom head region, the allowable pressure is calculated with the following equation:
2.K
. t aOW-SCF. M,, *R (7)
Where:
SCF conservative stress concentration factor to account for bottom head penetration discontinuities; SCF = 3.0 per Reference [1].
Pailow, K1 p, t, Mm and Ri are defined as in Eq. (6).
For the FW nozzle, the allowable pressure is determined from a ratio of the allowable and applied stress intensity factors. The applied factor can be determined from a FEM that determines the stresses due to the internal pressure on the nozzle and RPV. The methodology for this approach is as follows:
File No.: 1001527.305 Page 9 of 45 Revision: 2 F0306-01RI
Structural Integrity Associates, Inc.*
Where:
Pref RPV internal pressure at which the FEA stress coefficients (Eq.
(9)) are determined (psi).
Klp-app
= the applied pressure stress intensity factor (ksi*in).
Pailow and Kip are defined as in Eq. (6).
The applied pressure stress intensity factor is determined using a polynomial curve-fit approximation for the through-wall pressure stress distribution from a FEA, similar to the methodology of Eq. (4):
K-llap
{Oi.706C 0 p -a) 057-lp-.48-C2)p-[ 0.393I-
,C 3p j (9)
Where:
a
= 1/4/ through-wall postulated flaw depth, a =1/4 t (in).
t
= thickness of the cross-section through the nozzle at the limiting path near the inner blend radius (in).
C~,l,= pressure stress polynomial coefficients, obtained from a curve-C2 p,,C 3 p fit of the extracted stresses from a PEA.
For the WLI nozzle, the nozzle material is not ferritic and does not need to be specifically evaluated. However, the effect of the penetration on the adjacent shell must be considered.
The allowable pressure is determined from the ratio of the allowable and applied stress intensity factors given in Eq. (8). The applied stress intensity factor, for a 1000 psig load case, is calculated generically as follows [2, Equation 8-1]:
K+p*,r = 2.9045 F~L +/-t]l--,
-4.434 (10)
Where:
KI-pressure
=generic Kipapp for the instrument nozzle (ksi*/in).
R
= RPV nominal inside radius (in).
t, and tn, are described as in Eq. (5).
Step 5: Steps 1 through 4 are repeated in order to generate a series of P-T points; the fluid temperature is incremented with each repetition. Calculations proceed in this iterative manner until 1,300 psig. This value bounds expected pressures.
File No.: 1001527.305 Page 10 of 45 Revision: 2 F0306-01RI
Structural Integrity Associates, IncY Step 6: Table 1 summarizes the minimum temperature requirements contained in 10OCFR50, Appendix G [3, Table 1], which are applicable to the material highly stressed by the main closure flange bolt preload (non-beltline curve). SI also includes additional minimum temperature requirements for bolt-up as shown in Table 1 below.
Note that a minimum bolt-up temperature of 60 0F, is used here, consistent with the position given in Reference [1]. Further, some utilities specifically request that the minimum moderator temperature used in the plant shutdown margin evaluation be applied as a minimum bolt-up temperature requirement; therefore, it is also included in Table 1.
Step 7: Uncertainty in the RPV pressure and metal temperature measurements is incorporated by adjusting the P-T curve pressure and temperature using the following equations:
TTpr= T +UT (11)
P-=T = Fallow - P*-
U(12)
Where:
Tp-T
= The allowable coolant (metal) temperature (0F).
= The coolant temperature instrument uncertainty (0F).
PPT = The allowable reactor pressure (psig).
PH
=The pressure head to account for the water in the RPV (psig).
Can be calculated from the following expression: PH = P"Ah.
p
= Water density at ambient temperature (lb/in3).
Ah
= Elevation of full height water level in RPV (in).
Up
= The pressure instrument uncertainty (psig).
Steps 1 through 7, above, are implemented for all components, in all regions, for each heat-up/cool-down rate, and at all EFPY.
3.0 ASSUMPTIONS The 10OCFR50 Appendix G [3] and ASME Code [4] requirements and methods are considered to be supported in their respective technical basis documentation; therefore, the assumptions inherent in the ASME B&PV Code methods utilized for this evaluation are not specifically identified and justified in this calculation. Only those assumptions specific to this calculation are identified and justified here.
The following assumptions are used in preparation of the HNP-2 P-T curves:
- 1. The static head contributed by coolant inside the RPV is calculated using the full height of the RPV.
This assumption is conservative in that the static head at the non-beltline and beltline regions is slightly lower than for the bottom head curve; however, the difference in static head is small; therefore, the added complexity in considering different static head values for each region of the vessel is not considered beneficial.
File No.: 1001527.305 Page 11 of 45 Revision: 2 F0306-01RI
VStructural Integrity Associates, Inc.Y
This assumption is made because:
- a. The geometric discontinuity caused by the nozzle penetration in the RPV shell causes a stress concentration which results in larger pressure induced stresses than would be calculated in the shell regions of the RPV,
- b. The FW nozzle experiences more severe thermal transients than most of the other nozzles because of the FW injection temperature which causes larger thermal stresses than are experienced in the shell regions of the RPV,
- c. Although some other nozzles can experience thermal transients which would cause thermal stresses larger than those calculated for the shell regions of the RPV and some nozzles are larger diameter than the FW nozzle, which could result in a slightly larger Kip, the combined stresses from the applied thermal and pressure loads are considered to bound all other non-beitline discontinuities.
- 3. Application of a SCF = 3.0 to the membrane pressure stress in the bottom head bounds the effect of the bottom head penetrations on the stress field in this region of the vessel.
It is recognized that the penetrations in the bottom head will introduce a geometric discontinuity into the bottom head hemisphere which creates a stress intensification. This effect must be considered in calculating the stress intensity factor from internal pressure. Rather than performing a plant specific analysis, SI applies a conservative SCF for a circular hole in a flat plate subjected to a uniaxial load to the membrane stress in the shell caused by the internal pressure. This assumption is conservative because:
- a. It applies a peak SCF to the membrane stress which essentially intensifies the stress through the entire shell thickness and along the entire face of the postulated flaw rather than intensify'ing the stress local to the penetration and considering the stress attenuation away from the penetration,
- b. Review of SCFs for circular holes in plates subjected to an equi-bi-axial stress state as well as SC~s for arrays of circular holes in shells, shows that the SCF is likely closer to 2-2.5 rather than 3.0.
Consequently, the method utilized by SI is expedient, as intended, and conservatively bounds the expected effect of bottom head penetrations because a bounding SCF is used and applied as a membrane stress correction factor.
- 4. ASME XI, Non-mandatory Appendix G, Paragraph G-22 14.3 [4] is used to calculate the thermal stress intensity factor for heat-up / cool-down rates greater than I100°F/hr.
The ASME Code [4] acknowledges that this methodology is conservative when applied to rapid heat-up / cool-down rates (i.e. greater than 100°F/hr); therefore, the results obtained using this method for 200°F/hr heat-up / cool-down rate are conservative. Conservatism can be removed, if necessary, by solving the thermo-elastic problem for the stresses in the vessel shell then calculating the stress intensity factor using the plant specific stress distribution.
File No.: 1001527.305 Page 12 of 45 Revision: 2 F0306-01R1
Structural Integrity Associates, Inc?
- 5. A shutdown margin temperature of 68°F is assumed.
SI experience is that GE designed BWRs typically consider a moderator temperature of 68°F in the shutdown margin evaluation; therefore, this value is assumed for H-NP-2. This assumption affects only the minimum bolt-up temperature. However, to address the NRC condition regarding lowest service temperature in Reference [1], the minimum temperature is set to 90 °F, which is equal to the RTNDT,max + 60 °F. This value is consistent with the previous minimum temperature limits developed in [ 10], and the minimum bolt-up temperature specified in [ 11].
4.0 DESIGN INPUTS The design inputs used to develop the IHNP-2 P-T curves are discussed below. Design inputs are also summarized in the input listings in Appendix A.
Non-be ltline:
Bottom Head:
Beltline:
37 EFPY:
50.1 EFPY:
WLI Nozzle (in Beltline):
37 EFPY:
50.1 EFPY:
30 0F 50 0F 72.6 0F 79.2 0F 69.5 0F 74.6 0F Lower Shell #2 Plate (G6603-2)
Lower Shell #2 Plate (G6603-2)
Lower-Int Shell #3 Plate (G6601-4)
Lower-Int Shell #3 Plate (G6601-4)
- 2. Shutdown Margin Temperature: 68 0F
- 3. RPV Dimensions:
Full vessel height [6]:
RPV inside radius [6]:
RPV shell thickness [5]:
Bottom head inside radius [6]:
Bottom head shell thickness [6]:
See Assumption 5.
836.75 inches (Used to calculate maximum water head during pressure test and conservatively applied for normal operation as well) 110.375 inches 6.375 inches (Lower Shell #2 Plate) 5.375 inches (Lower-Tnt Shell #3 Plate) 110.5 inches 6.813 inches (Corresponds to the thicker portion of the shell in which the penetrations exist. This bounds the thinner portion of the shell with no penetrations)
- 4. Heat-up / Cool-down Rates [8]:
100 °F/hr 200 "F/hr
- 5. Nozzle Stress Intensity Factors:
FW Nozzle [9]:
1 ksi Pressure:
100 0F/hr:
78.9 ksi-in° 5 12.9 ksi-in° 5 File No.: 1001527.305 Page 13 of 45 Revision: 2 F0306-01R1
VStructural Integrity Associates, Inc?
200 °F/hr:
25.8 ksi-in° 5 450 0F down shock:
46.8 ksi-in° 5 WLI Nozzle [9]:
1 ksi Pressure:
80.0 ksi-in°5 100 *F/hr:
19.9 ksi-in°5 200 0F/hr:
39.9 ksi-in° 5
- 6. Design Pressure [7]:
1250 psig
- 7. Pre-service Hydro-test pressure [7]:
1563 psig (Taken as 1.25 *Design pressure = 1563 psig)
- 8. Instrument uncertainties [8]:
Pressure:
0 psig Temperature:
O°F 5.0 CALCULATIONS The P-T curves in this calculation were developed using an Excel spreadsheet, which is independently verified for use on a project-specific basis in accordance with SI's Nuclear QAprogram. Four cases are evaluated, corresponding to two EFPY values (37 and 50.1) and two thermal transients (100 and 200
°F/hr). P-T limits are calculated from 0 to 1300 psig. Supporting calculations for all curves are included in Appendix B.
The change in thickness within the beltline affects the P-T curves for the beltline plates. Both beltline plates are evaluated using their respective ART values. The thinner plate thickness and associate ART value is limiting for Curve A, but the thicker plate and associated ART is limiting for Curves B and C.
However, the WLI (Ni16) nozzle provides the most limiting results within the beltline region for all curves. Therefore, the composite beltline curves are unaffected by the change in beltline shell thickness.
The thin region of the bottom head torus and the cylindrical portion or the RPV below the beltline are not limiting in this analysis; thus, the thick portion of the bottom head yields bounding bottom head P-T curves for HNP-2.
Because BWR operation is typically along the saturation curve, the limiting K1t for the FW nozzle is scaled to reflect the worst-case step change due to the available temperature difference between the saturation temperature at a given pressure and the 100 0F FW temperature. It is recognized that at low temperatures, the available temperature difference is insignificant, which could result in a near zero Kit.
Therefore, a minimum Kit is calculated for both the 1 00°F/hr and 200°F/hr thermal transients; scaling of the FW nozzle K1t based on the available temperature difference is not allowed below the minimum K1 t corresponding to the cool-down rate being evaluated.
The composite P-T curves are extended below 0 psig to -14.7 psig based on the evaluation documented in Reference [ 12], which demonstrates that the P-T curves are applicable to negative gauge pressures.
- Since the P-T curve calculation methods used do not specifically apply to negative values of pressure, the tabulated results start at 0 psig. However, the minimum RPV pressure is -14.7 psig.
File No.: 1001527.305 Page 14 of 45 Revision: 2 F0306-01R1
Structural Integrity Associates, Inc.*
5.1 Pressure Test (Curve A)
The assumed minimum bolt-up temperature of 900 F, see Assumption 5, is applied to all regions as the initial temperature in the iterative calculation process. The static fracture toughness (K1 o) is calculated for all regions using Eq. (1). The resulting value of K10, along with a safety factor of 1.5 is used in Eq.
(2) to calculate the pressure stress intensity factor (K1p). The allowable RPV pressure is calculated for the beitline, bottom head and non-beltline regions using Eq. (6, 7, and 8), as appropriate. For the non-beltline region, the additional constraints specified in Step 6 of Section 2.0 are applied. Final P-T limits for temperature and pressure are obtained from Eq. (12 and 13), respectively.'
Since the thermal stress intensity factor is taken as zero for Curve A, the thermal transients considered do not affect the results for Curve A.
Values for the composite beltline region curves for 37 and 50.1 EFPY are listed in Table 2 and Table 3, respectively. Additionally, more detailed data for the composite beltline are provided in Appendix B.
Data for the composite bottom head region curve for all EFPY are listed in Table 4. Data for the composite non-beltline (FW nozzle / upper vessel) region curve, including the 10CFR50 Appendix G [3]
limits, for all EFPY are listed in Table 5. The data for each region is graphed, and the resulting composite Curve A for 37 and 50.1 EFPY are provided in Figure 1 and Figure 2, respectively.
Additional data and curves for each region are included in Appendix B.
5.2 Normal Operation - Core Not Critical (Curve B)
The assumed minimum bolt-up temperature of 90°F (see Assumption 5), is applied to all regions as the initial temperature in the iterative calculation process. The static fracture toughness (K10) is calculated for all regions using Eq. (1). The thermal stress intensity factor (K1 t) is calculated for the beltline plate and bottom head regions using Eq. (3), for the FW nozzle using Eq. (4), and for the WLI (NI16) nozzle using Eq. (5).
The resulting values of K10 and K1t, along with a safety factor of 2.0, are used in Eq. (2) to calculate the pressure stress intensity factor (Kip). The allowable RPV pressure is calculated for the beltline, bottom head, and non-beltline regions using Eq. (6, 7, and 8), as appropriate. For the non-beltline region, the additional constraints specified in Step 6 of Section 2.0 are applied. Final P-T limits for temperature and pressure are obtainedfrom Eq. (12 and 13), respectively.
The data resulting from each P-T curve calculation are tabulated. Values for the composite beltline region with a 100OF/hr thermal transient at 37 and 50.1 EFPY are listed in Table 6 and Table 7, respectively. Values for the composite beltline region with a 200°F/hr thermal transient at 37 and 50.1 EFPY are listed in Table 8 and Table 9, respectively. Data for the bottom head region with 1 00°F/hr and 200°F/hr thermal transients are listed in Table 10 and Table 11, respectively. Data for the non-beltline region with 100°F/hr and 200°F/hr thermal transients are listed in Table 12 and Table 13, respectively. The data for each region is graphed, and the resulting composite Curve B for 37 and 50.1 EFPY with a 1 00°F/hr thermal transient are provided in Figure 3 and Figure 4, respectively. The resulting composite Curve B for 37 and 50.1 EFPY with a 200°F/hr thermal transient are provided in File No.: 1001527.305 Page 15 of 45 Revision: 2 F0306-01R1
Structural Integrity Associates, Inc.*
Figure 5 and Figure 6, respectively. Additional data and curves for each region are included in Appendix B.
5.3 Normal Operation - Core Critical (Curve C)
The pressure and temperature values for Curve C are calculated in a similar manner as Curve B, with several exceptions. The initial evaluation temperature is calculated as the limiting non-beltline RTNDT that is highly stressed by the bolt preload (in this case, that of the closure flange region: 30°F per Section 3.0) plus 60°F, resulting in a minimum critical temperature of 90°F. When the pressure exceeds 20% of the pre-service system hydrostatic test pressure (20% of 1,563 psig =313 psig), the P-T limits are specified as 40°F higher than the Curve B values. The minimum temperature above the 20% of the pre-service system hydrostatic test pressure is always greater than the reference temperature (RTNDT) of the closure region plus 160°F, or is taken as the minimum temperature required for the hydrostatic pressure test. The final Curve C values are taken as the absolute maximum between the regions of the beltline, the bottom head, and the non-beltline.
The data resulting from each P-T curve calculation are tabulated. Values for the composite beltline region with a 100°F/hr thermal transient at 37 and 50.1 EFPY are listed in Table 14 and Table 15, respectively. Values for the composite beltline region with a 200°F/hr thermal transient at 37 and 50.1 EFPY are listed in Table 16 and Table 17, 'respectively. Data for the bottom head region with 1 00°F/hr and 200°F/hr thermal transients are listed in Table 18 and Table 19, respectively. Data for the non-beltline region with l00°F/hr and 200°F/hr thermal transients are listed in Table 20 and Table 21, respectively. The data for each region is graphed, and the resulting composite Curve C for 37 and 50.1 EFPY with a 10OOF/hr thermal transient are provided in Figure 7 and Figure 8, respectively. The resulting composite Curve C for 37 and 50.1 EFPY with a 200°F/hr thermal transient are provided in Figure 9 and Figure 10, respectively. Additional data and curves for each region are included in Appendix B.
6.0 CONCLUSION
S.
P-T curves are developed for HNP-2 using the methodology, assumptions, and design inputs defined in Sections 2.0, 3.0, and 4.0. P-T curves are developed for the beltline, bottom head, and non-beltline regions, considering a 100 °F/hr and 200 0F/hr thermal transient at 37 and 50.1 EFPY, for the following plant conditions: Pressure Test (Curve A), Normal Operation - Core Not Critical (Curve B), and Normal Operation - Core Critical (Curve C). Tabulated pressure and temperature values are provided for all regions and EFPYs in Tables 2 through 21. The accompanying P-T curve plots are provided in Figures 1 through 10.
File No.: 1001527.305 Page 16 of 45 Revision: 2 F0306-01RI
Structural Integrity Associates, IncY
7.0 REFERENCES
- 1. Structural Integrity Associates Report No. SIR-05-044, Revision 1-A, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," June 2013, SI File No. GE-10Q-401.
- 2. Structural Integrity Associates Report No. 0900876.40 1, Revision 0-A, "Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations," May 2013.
- 3. U. S. Code of Federal Regulations, Title 10, Energy, Part 50, "Domestic Licensing of Production and Utilization Facilities," Appendix G, "Fracture Toughness Requirements," (60 FR 65474, Dec.
19, 1995; 73 FR 5723, Jan. 2008).
- 4. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components. Appendix G, "Fracture Toughness Criteria for Protection Against Failure," 2001 Edition including the 2003 Addenda.
- 5. Structural Integrity Associates Calculation No. 1001527.302, Rev 1, "RPV Material Summary and ART Calculation."
- 6. Combustion Engineering Drawing No. E-1 1570-871-001, Revision 1, "General Arrangement Elevation for 218" I.D. BWR," SI File No. GPCO-44Q-205.
- 7. GE Drawing No. 761E246, *"Reactor Vessel Thermal Cycles (Including Black Start)," Sheet 1, Revision 1, 51 File No. 1001527.211.
- 8. Design Input Requests.
1001527.201.
- 9. Structural Integrity Associates Calculation No. 1001527.303, Revision 1, "Feedwater, Water Level Instrument, and Core DP Nozzle Fracture Mechanics Evaluation for Hatch Unit 1 and Unit 2 Pressure-Temperature Limit Curve Development."
- 10. General Electric Document No. GE-NE-B 1100827-00-01, "Plant Hatch Units 1 & 2 RPV Pressure Temperature Limits License Renewal Evaluation," March 1999, SI File No. 1400365.202.
- 11. NRC Docket No. 50-321, "Issuance of Amendment No. 177 to Facility Operating License DPR-57 and Amendment No. 118 to Facility Operating License NPF Edwin I. Hatch Nuclear Plant, Units 1 and 2," Amendment No. 177, License No. DPR-57, ADAMS Accession No. ML012990100, SI File No. 1400365.202.
File No.: 1001527.305 Page 17 of 45 Revision: 2 F0306-01RI
VStructural Integrity Associates, Inc.Y Table 1: Summary of Minimum Temperature Requirements for P-T Limit Curves
,Crv r Range Minimum Metal Temperature P-T Limits..
Maximum of:
ASME Appendix G [4]
P<O P RTNDT, max, requirements A
- 60'F [1],
TSDM P > 20% Ph RTNDT,max + 90 'FAME peniG[4
_________________________requirements Maximum of:
ASME Appendix G [4]
P<0P RTNDT, max, requirements B
- 60 'F[1],
TSDM
> 20 Ph TNDTrnax+/- 12 'FASME Appendix G [4]
requirements Maximum of:
ASME Appendix G [4]
P<0P RTNDT, max + 60 'F, requirements + 40 'F
- 60°F [1],
C TSDM Maximum of:
ASME Appendix G [4]
P > 20% Ph RTNDT,max + 160 'F, requirements + 40 'F TISHT_________________
Where:
This table is largely taken from Reference [3] with modifications as described in Step 6 of Section 2.0.
Ph is the pre-service hydrotest pressure, 1563 psig RTNDT,max is the maximum RTNDT of the vessel materials highly stressed by the bolt preload.
TSDM is the temperature used in the shutdown margin evaluation Tismr is the temperature at which the full in-service hydrotest pressure is allowed per Curve A Note that the minimum bolt-up temperature of 60°F, is used here, consistent with the position given in Reference [1]. Further, some utilities specifically request that the minimum moderator temperature used in the plant shutdown margin evaluation be applied as a minimum bolt-up temperature requirement; therefore, it is also included in Table 1 above. However, to address NRC condition regarding lowest service temperature in Reference [1], the minimum temperature is set to 90 0F, which is equal to the RTNDT, max + 60 0F. This value is consistent with the previous minimum temperature limits developed in
[ 10], and the minimum bolt-up temperature specified in [ 11].
File No.: 1001527.305 Revision: 2 Page 18 of 45 F0306-01R1
Structural Integrity Associates, Inc.Y Table 2:HINP-2 Beltline Region, Curve A, for 37 EFPY
°F psi 90.0 0.0 90.0 506.7 98.5 554.7 105.7 602.7 112.0 650.7 117.6 698.8 122.7 746.8 127.3 794.8 131.5 842.8 135.3 890.8 138.9 938.8 142.3 986.8 145.4 1034.9 148.4 1082.9 151.2 1130.9 153.8 1178.9 156.3 1226.9 158.7 1274.9 161.0 1322.9 File No.: 1001527.305 Page 19 of 45 Revision: 2 F0306-01RI
Structural Integrity Associates, Inc.6 Table 3:HINP-2 Beltline Region, Curve A, for 50.1 EFPY OF psi 90.0 0.0 90.0 481.5 99.5 530.6 107.5 579.8 114,3 628.9 120.4 678.1 125.8 727.3 130.7 776.4 135.1 825.6 139.2 874.7 142.9 923.9 146.4 973.1 149.7 1022.2 152.8 1071.4 155.7 1120.6 158.4 1169.7 161.0 1218.9 163.5 1268.0 165.8 1317.2 File No.: 1001527.305 Page 20 of 45 Revision: 2 F0306-01IRI
Structural Integrity Associates, Inc.*~
Table 4: HNP-2 Bottom Head Region, Curve A, for All EFPY "F
psi 90.0 0.0 90.0 869.3 94.5 918.9 98.7 968.4 102.5 1018.0 106.1 1067.5 109.4 1117.1 112.5 1166.6 115.4 1216.2 118.2 1265.7 120.8 1315.3 Table 5: HNP-2 Non-Beltline Region, Curve A, for All EFPY
- F psi 90.0 90.0 120.0 120.0 0.0 312.6 312.6 1310.2 File No.: 1001527.305 Revision: 2 Page 21 of 45 F0306-01IR1
Structural Integrity Associates, Inc.Y Table 6: HNP-2, Beitline Region, Curve B, for 37 EFPY and 10OOF/hr Thermal Transient
°F psi 90.0 90.0 101.1 110.2 117.9 124.6 130.5 135.7 140.5 144.9 148.9 152.6 156.0 159.2 162.3 165.1 167.8 170.4 172.8 175.1 177.4 179.5 181.5 183.5 0.0 248.1 296.8 345.5 394.2 442.9 491.6 540.3 589.0 637.7 686.4 735.1 783.8 832.5 881.2 929.9 978.6 1027.3 1076.0 1124.7 1173.4 1222.1 1270.8 1319.5 File No.: 1001527.305 Revision: 2 Page 22 of 45 F0306-01IRI1
~jStructural Integrity Associates, Inc:e Table 7: HINP-2, Beltline Region, Curve B, for 50.1 EFPY and 100OF/hr Thermal Transient TempraUre Pesr
°F psi 90.0 0.0 90.0 229.2 102.4 278.6 112.2 328.0 120.5 377.4 127.6 426.8 133.8 476.2 139.3 525.6 144.3 575.0 148.8 624.4 153.0 673.8 156.8 723.2 160.3 772.6 163.7 822.0 166.8 871.4 169.7 920.8 172.5 970.2 175.1 1019.6 177.6 1069.0 180.0 1118.4 182.2 1167.8 184.4 1217.2 186.5 1266.6 188.5 1316.0 File No.: 1001527.305 Page 23 of 45 Revision: 2 F0306-01RI
Structural Integrity Associates, Inc.2 Table 8: HNP-2, Beitline Region, Curve B, for 37 EFPY and 200°F/hr Thermal Transient OF psi 90.0 0.0 90.0 123.1 101.3 172.8 110.6 222.4 118.3 272.1 125.1 321.7 131.0 371.4 136.3 421.0 141.1 470.7 145.5 520.3 149.5 570.0 153.3 619.6 156.7 669.3 160.0 718.9 163.0 768.6 165.9 818.2 168.6 867.9 171.2 917.5 173.6 967.2 175.9 1016.8 178.2 1066.5 180.3 1116.1 182.3 1165.8 184.3 1215.4 186.2 1265.1 188.0 1314.7 File No.: 1001527.305 Page 24 of 45 Revision: 2 F0306-01 RI
Structural Integrity Associates, Inc~e Table 9: HNP-2, Beltline Region, Curve B, for 50.1 EFPY and 200°F/hr Thermal Transient
°F psi 90.0 90.0 102.2 112.0 120.1 127.2 133.3 138.8 143.8 148.3 152.4 156.2 159.7 163.0 166.1 169.1 171.8 174.4 176.9 179.3 181.6 183.7 185.8 187.8 189.7 191.5 193.3 0.0 104.2 152.8 201.5 250.1 298.7 347.3 396.0 444.6 493.2 541.8 590.5 639.1 687.7 736.4 785.0 833.6 882.2 930.9 979.5 1028.1 1076.7 1125.4 1174.0 1222.6 1271.2 1319.9 File No.: 1001527.305 Revision: 2 Page 25 of 45 F0306-01 R1
~jjStructural Integrity Associates, IncY Table 10: HNP-2 Bottom Head Region, Curve B for All EFPY and 100°F/hr Thermal Transient OF psi 90.0 0.0 90.0 546.3 95.8 594.7 101.0 643.1 105.7 691.5 110.1 739.9 114.0 788.4 117.7 836.8 121.1 885.2 124.3 933.6 127.3 982.0 130.2 1030.4 132.9 1078.8 135.4 1127.3 137.9 1175.7 140.2 1224.1 142.4 1272.5 144.5 1320.9 File No.: 1001527.305 Page 26 of 45 Revision: 2 F0306-01 RI
~Structural Integrity Associates, Inc.
Table 11: HNP-2 Bottom Head Region, Curve B for All EFPY and 200°F/hr Thermal Transient 5
9 9
90.
90.0 95.8 101.0 105.8 110.1 114.1 117.7 121.2 124.4 127.4 130.2 132.9 135.5 137.9 140.2 142.4 144.5 146.6 148.5 psi 0.0 448.1 496.6 545.1 593.5 642.0 690.5 739.0 787.4 835.9 884.4 932.8 981.3 1029.8 1078.3 1126.7 1175.2 1223.7 1272.2 1320.6 File No.: 1001527.305 Revision: 2 Page 27 of 45 F0306-O1R1
jjStructural Integrity Associates, Inc.*
Table 12: HNP-2 Non-Beltline Region, Curve B, for All EFPY and 100°F/hr Thermal Transient "F
psi 90.0 0.0 90.0 312.6 150.0 312.6 150.0 1313.5 Table 13: HNP-2 Non-Beitline Region, Curve B, for All EFPY and 200°F/hr Thermal Transient P-T Curve 90.0 90.0 150.0 150.0 Prsure psi 0.0 312.6 312.6 1313.5
.tT~
4....
Revision: 2 Page 28 of 45 F0306-01RI
~jjStructural Integrity Associates, IncY Table 14: HNP-2, Beltline Region, Curve C, for 37 EFPY and 1000F/hr Thermal Transient e
°F 90.0 90.0 112.2 127.5 139.2 148.7 156.7 163.6 169.6 175.0 179.9 184.3 188.4 192.1 195.6 198.9 202.0 204.9 207.6 210.2 212.7 215.0 217.2 219.4 221.5 223.4 PS, 0.0 140.6 189.6 238.7 287.7 336.8 385.8 434.9 483.9 533.0 582.0 631.1 680.1 729.2 778.2 827.3 876.3 925.4 974.4 1023.5 1072.5 1121.6 1170.6 1219.7 1268.7 1317.8 File No.: 1001527.305 Revision: 2 Page 29 of 45 F0306-01IRI
~jStructural Integrity Associates, Inc.8 Table 15: HNP-2, Beltline Region, Curve C, for 50.1 EFPY and 100°F/hr Thermal Transient
- 9.
9
-/-
90.0 90.0 114.2 130.5 142.7 152.5 160.7 167,8 173.9 179.4 184.4 188.9 193.0 196.9 200.4 203.7 206.8 209.7 212.5 215.1 217.6 220.0 222.2 224.4 226.5 228.5 psi 0.0 132.1 181.4 230.8 280.1 329.5 378.8 428.1 477.5 526.8 576.2 625.5 674.8 724.2 773.5 822.9 872.2 921.6 970.9 1020.2 1069.6 1118.9 1168.3 1217.6 1266.9 1316.3 File No.: 1001527.305 Revision: 2 Page 30 of 45 F0306-01RI
Structural Integrity Associates, Inc.6 Table 16: HNP-2, Beltline Region, Curve C, for 37 EFPY and 200°F/hr Thermal Transient e.
90F 90.0 112.5 128.0 139.8 149.3 157.3 164.2 170.3 175.7 180.6 185.0 189.1 192.9 196.4 199.7 202.7 205.6 208.4 211.0 213.5 215.8 218.1 220.2 222.3 224.2 226.1 228.0 PSI 0.0 15.6 65.6 115.5 165.4 215.3 265.2 315.1 365.0 415.0 464.9 514.8 564.7 614.6 664.5 714.4 764.4 814.3 864.2 914.1 964.0 1013.9 1063.9 1113.8 1163.7 1213.6 1263.5 1313.4 File No.: 1001527.305 Revision: 2 Page 31 of 45 F0306-01RI
St~3ructural Integrity AscaeIncY Table 17: HNP-2, Beitline Region, Curve C, for 50.1 EFPY and 200°F/hr Thermal Transient
- e.
e
°F 90.0 90.0 113.9 130.0 142.2 152.0 160.2 167.2 173.4 178.8 183.8 188.3 192.4 196.2 199.7 203.1 206.2 209.1 211.8 214.4 216.9 219.3 221.6 223.7 225.8 227.8 229.7 231.5 233.3 psi 0.0 7.1 55.8 104.4 153.0 201.6 250.2 298.9 347.5 396.1 444.7 493.3 542.0 590.6 639.2 687.8 736.4 785.1 833.7 882.3 930.9 979.5 1028.2 1076.8 1125.4 1174.0 1222.7 1271.3 1319.9 in...
kT..
4 0n4...........
Revision: 2 Page 32 of 45 F0306-01RI
jjStructural Integrity Associates, Inc.Y Table 18: HNP-2 Bottom Head Region, Curve C for All EFPY and 100OF/hr Thermal Transient 90F 90.0 102.3 112.2 120.5 127.5 133.7 139.3 144.2 148.7 152.9 156.7 160.3 163.6 166.7 169.6 172.4 175.0 177.5 179.9 182.1 184.3 psi 0.0 330.2 379.5 428.8 478.1 527.5 576.8 626.1 675.4 724.7 774.0 823.3 872.6 922.0 971.3 1020.6 1069.9 1119.2 1168.5 1217.8 1267.1 1316.4 File No.: 1001527.305 Revision: 2 Page 33 of 45 F0306-01 RI1
Structural Integrity Associates, Inc:
Table 19: HNP-2 Bottom Head Region, Curve C for All EFPY and 200°F/hr Thermal Transient e.
90.
90.0 102.3 112.2 120.5 127.5 133.7 139.2 144.2 148.7 152.9 156.7 160.3 163.6 166.7 169.6 172.4 175.0 177.5 179.9 182.1 184.3 186.4 188.4 psi 0.0 232.1 281.4 330.6 379.9 429.2 478.5 527.8 577.1 626.4 675.7 725.0 774.3 823.6 872.9 922.2 971.5 1020.8 1070.1 1119.4 1168.6 1217.9 1267.2 1316.5 File No.: 1001527.305 Revision: 2 Page 34 of 45 F0306-01RI
jjStructuraI Integrity Associates, Inc.
Table 20: HNP-2 Non-Beitline Region, Curve C, for All [FPY and 100°F/hr Thermal Transient
°F psi 90.0 90.2 101.6 110.6 118.2 190.0 190.0 0.0 193.0 232.9 272.7 312.6 312.6 1313.5 Table 21: HNP-2 Non-Beltline Region, Curve C, for All EFPY and 200°F/hr Thermal Transient P-TCre 90.0 90.2 101.6 110.6 118.2 190.0 190.0 psi 0.0 193.0 232.9 272.7 312.6 312.6 1313.5 File No.: 1001527.305 Revision: 2 Page 35 of 45 F0306-01RI
Structural Integrity Associates, IncY Curve A - Pressure Test, Composite Curves
-Be e.--Bottom Head
-- -- Non-Beitline
-Overall 1300 1200 1100 1000 900
'~800
- ,700 600 4.
E S500 IU
& 40 300 200 100L 0
Minimum Reactor Vessel Metal Temperature ('F)
Figure 1: HNP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 37 EFPY File No.: 1001527.305 Revision: 2 Page 36 of 45 F0306-01I R]
Structural Integrity Associates, IncYc Curve A - Pressure Test, Composite Curves
-Be..ne Bottom Head Non-Beitline Overall 1300 1200 1100 1O00 900 8
I 00 a.
- ,70
& 400 300 200 100 0
Minimum Reactor Vessel Metal Temperature ('F)
Figure 2: HNP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 50.1 EFPY File No.: 1001527.305 Revision: 2 Page 37 of 45 F0306-01RI
Structural Integrity Associates, Inc.t.
Curve B - Core Not Critical, Composite Curves
-Beitline Bottom Head
- -l Non-Beltline
-vrl 1300 1200 1100 1000 900 S800 J 600 E
500 300 200 100 0
Figure 3: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 1O0°F/hr File No.: 1001527.305 Revision: 2 Page 38 of 45 F0306-01RI
Structural Integrity Associates, Inc Curve B - Core Not Critical, Composite Curves
-Bel...e---Bottom Head Non-Beltline
-Overall 1300 1200 1100 1000 900 8 00
- 600
-2 500......
&- 400....
300 200 100 0
Minimum Reactor Vessel Metal Temperature ('F)
Figure 4:HINP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 100°F/hr File No.: 1001527.305 Revision: 2 Page 39 of 45 F0306-01 R1
Structural Integrity Associates, Inc.2 Curve B - Core Not Critical, Composite Curves
-Bet..ne---Bottom Head Non-Beltline
-Overall 1300 1200 1100 1000 900 800 61 600 4.,
E S500 400 300 200 100 Minimum Reactor Vessel Metal Temperature I(F)
Figure 5: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 200°F/hr File No.: 1001527.305 Revision: 2 Page 40 of 45 F0306-01 R1
Structural Integrity Associates, Inc.Y Curve B - Core Not Critical, Composite Curves
-. e...e Bottom Head Non-Beltline
,-mOverall 1300 1200 1100 1O00 900
~800 0.
"= 5003
&" 400 300 200 100 0
Minimum Reactor Vessel Metal Temperature ('F)
Figure 6: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 200°F/hr File No.: 1001527.305 Revision: 2 Page 41 of 45 F0306-01 RI
jjStructural Integrity Associates, Inc.
Curve C
- Core Critical, Composite Curves
-. et.ne.--Bottom Head Non-Beltline
-=mOverall 1300 1200}
1100 1000 900 S800 a.
E 500 A-400 300 200 100 0
Minimum Reactor Vessel Metal Temperature (*F)
Figure 7: HNP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 1OO°F/hr File No.: 1001527.305 Revision: 2 Page 42 of 45 F0306-01IRI1
~jStructural Integrity Associates, Inc:
Curve C - Core Critical, Composite Curves ie Bottom Head
-- -- Non-Beltline
-mmOverall 1300 1200 1100 1O00 900 800
.5
- 700 E
-1 500 tU
& 400 300 200 100 Minimum Reactor Vessel Metal Temperature (*F)
Figure 8: HNP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 10O°F/hr File No.: 1001527.305 Revision: 2 Page 43 of 45 F0306-01 RI
jjStructural Integrity Associates, IuicY Curve C - Core Critical, Composite Curves
-Beitline Bottom Head 1 Non-Belthine
-. ilOverall 1300 1200 1100 1O00 900 800 "a
- , 00 "l
5001
&: 400 300 200 100 0
Minimum Reactor Vessel Metal Temperature (*F)
Figure 9: HNP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 200°F/hr File No.: 1001527.305 Revision: 2 Page 44 of 45 F0306-01RI
Structural Integrity Associates, IncY Curve C
- Core Critical, Composite Curves e...e Bottom Head Non-Beltline
,,,,,-Overall 1200 +/--
1100 1--
1000 900 800 E
ElI A-400 300 200 100 0
Figure 10: HNP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 200°F/hr File No.: 1001527.305 Revision: 2 Page 45 of 45 F0306-0 tR I
jjJStructural Integrity Associates, Inc~e APPENDIX A:
P - T CURVE INPUT LISTING File No.: 1001527.305 Revision: 2 Page A-Il of A-3 F0306-01R I
Structural Integrity Associates, Inc Table A-i: HNP-2 Stress Intensity Factors for Feedwater and WLI Nozzles [9]
Feedwater 78.9 46.8 12.9 25.8 WLI J
80.0 N/A 19.9 39.9 Notes:
- 1. K1 in units of ksi-in°05
- 2. 200 °F/hr results are scaled from 100 °F/hr assuming response is linear Table A-2: HNP-2 P-T Curve Input Listing P-T Curve Inputs....
General Parameters English Unit System for Tables and Plots 0
Temperature Instrument Uncertainty Adjustment (°F) 0 Pressure Instrument Uncertainty Adjustment (psig) 62.4 Water Density (Ibm/ft 3) 836.75 Full-Vessel Water Height (in) 1.5 Safety Factor for Curve A 2
Safety Factor for Curves B and C 90 Minimum bolt-up temperature (OF) 30 ART of Closure Flange Region (°F) 5 Default Temperature Increment for Tables (OF) 50 Default Pressure Increment for Composite Tables (psig)
Beltline Parameters 69.5 Adjusted Reference Temperature, Lower-lnt Shell #3 Plate (G6601-4), 37 EFPY 72.6 Adjusted Reference Temperature, Lower Shell #2 Plate (G6603-2), 37 EFPY 74.6 Adjusted Reference Temperature, Lower-lnt Shell #3 Plate (G6601-4), 50.1 EFPY 79.2 Adjusted Reference Temperature, Lower Shell #2 Plate (G6603-2), 50.1 EFPY 110.375 Vessel Radius (in) 5.375 Vessel Thickness, Curve A (in) 6.375 Vessel Thickness, Curves B & C (in) 100 Heat-up / Cool-down Rate (°F/hr) 200 Heat-up / Cool-down Rate (°F/hr)
Generic Type of Static Pressure Head Addition N/A Specific Water Height for Static Pressure Head Addition (in)
Generic Type of Temperature Increment for Tables 5
Specific Temperature Increment for Tables (=F)
File No.: 1001527.305 Page A-2 of A-3 Revision: 2 F0306-01 RI
Structural Integrity Associates, Inc.
Si ! iii!
i!i iii~i iiii
~!! P-Tli!iiiii ii C urve Iiin p u ts i 'l Instrument Nozzle Parameters 69.5 Adjusted Reference Temperature, 37 EFPY (°F) 74.6 Adjusted Reference Temperature, 50.1 EFPY (°F) 110.375 Vessel Radius (in) 5.375 Vessel Thickness (in)
See Table Applied Pressure Stress Intensity Factor (ksi*in^0.5)
A-i Applied Thermal Stress Intensity Factor (ksi*inA0.5) 7.69E-06 Coefficient of Thermal Expansion (in/in/°F) 1000 Reference Pressure (psig)
Generic Type of Static Pressure Head Addition N/A Specific Water Height for Static Pressure Head Addition (in)
Generic Type of Temperature Increment for Tables 5
Specific Temperature Increment for Tables (°F)
Bottom Hea(
S0 110.5 6.8125 100 200 3
Generic N/A Generic 5
IParameters Adjusted Reference Temperature (°F)
Vessel Radius (in)
Vessel Thickness (in)
Heat-up / Cool-down Rate (°F/hr)
Heat-up / Cool-down Rate (°F/hr)
Stress Concentration Factor Type of Static Pressure Head Addition Specific Water Height for Static Pressure Head Addition (in)
Type of Temperature Increment for Tables Specific Temperature Increment for Tables (0F)
Non-Beltline ( Feedwater Nozzle) Parameters 30 Adjusted Reference Temperature (°F)
See Table Applied Pressure Stress Intensity Factor (ksi*in^0.5)
A-i Applied Thermal Stress Intensity Factor (ksi*inA0.5)
Minimum Thermal Stress Intensity Factor (ksi*in^0,5)
Yes 100 550 1000 Generic N/A Generic 5
File No.: 1001527.305 Revision: 2 Scale Krr based on Saturation Temperature?
Minimum Transient Temperature ('F)
Maximum Transient Temperature (°F)
Reference Pressure for Thermal Transient (psig)
Type of Static Pressure Head Addition Specific Water Height for Static Pressure Head Addition (in)
Type of Temperature Increment for Tables Specific Temperature Increment for Tables (°F)
Page A-3 of A-3 F0306-01RI
$~tructural Integrity Associates, Inc.Y APPENDIX B:
SUPPORTING CALCULATIONS File No.: 1001527.305 Revision: 2 Page B-I1 of B-46 F0306-01RI
Structural Integrity Associates, Inc.Y Table B-I: HNP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve A Calculations, for 37 EFPY
-~
S.
'3"
°ksi*inAO.5
°ksi*inAO.5 psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 62.6 62.6 65.7 69.1 72.8 77.0 81.6 41.7 41.7 43.8 46.0 48.6 51.3 54.4 90.0 90.0 95.0 100.0 105.0 110.0 115.0 0.0 1000.2 1051.0 1107.2 1169.3 1238.0 1313.9 Table B-2: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve A Calculations, for 37 EFPY A
9-Gage Fuid STemperture 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0
°ksi*inAO.5
°ksi*inAO.5 64.4 43.0 64.4 43.0 67.7 45.2 71.4 47.6 75.4 50.2 79.8 53.2 84.7 56.5 90.1 60.1 P-T Curve Tempeaure 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 psi 0.0 944.3 994.0 1048.9 1109.6 1176.7 1250.8 1332.7 File No.: 1001527.305 Revision: 2 Page B-2 of B-46 F0306-01 R1
Structural Integrity Associates, Inc~e Table B-3: HNP-2, WLI (NI6) Nozzle Beltline Region, Curve A Calculations, for 37 EFPY
-A
°F ksi*inA0.5
°ksi*inA0.5 ps 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 64.4 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 147.8 159.9 43.0 43.0 45.2 47.6 50.2 53.2 56.5 60.1 64.1 68.5 73.4 78.8 84.7 91.3 98.6 106.6 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 0.0 506.7 534.1 564.3 597.8 634.7 675.6 720.7 770.6 825.7 886.6 954.0 1028.4 1110.6 1201.5 1302.0 File No.: 1001527.305 Revision: 2 Page B-3 of B-46 F0306-01RI
Structural Integrity Associates, Inc.y Table B-4: HNP-2, Beitline Region (Lower Shell #2 Plate, t = 6.375"), Curve A Calculations, for 50.1 EFPY A
I
- aeFld
°ksi*inA0.5
°ksi*in^0.5
°F ~n' Pressure psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 58.9 58.9 61.6 64.6 67.9 71.6 75.6 80.1 85.0 39.3 39.3 41.1 43.1 45.3 47.7 50.4 53.4 56.7 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 0.0 940.4 984.9 1034.2 1088.6 1148.8 1215.3 1288.8 1370.0 Table B-5: HINP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve A Calculations, for 50.1 EFPY A
Temperture 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0
°ksi*inA0.5
°ksi*inAO.5 61.4 40.9 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 40.9 42.9 45.1 47.5 50.2 53.1 56.4 60.0 P-T Crv Temperature
°F 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 P-T Curve Presure psi 0.0 898.5 943.4 992.9 1047.7 1108.3 1175.3 1249.2 1331.0 File No.: 1001527.305 Revision: 2 Page B-4 of B-46 F0306-01R 1
Structural Integrity Associates, IncY Table B-6: HINP-2, WLI (N16) Nozzle Beitline Region, Curve A Calculations, for 50.1 EFPY iiiiiiii% iii~ ~iiiiiiiii*iiiiiii~
i!i~!-
A
- iiiii
-:~
iil Tepeatr "ksi*inAO.5 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 61.4 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 136.7 147.6 159.6 172.9
°ksi*inA0.5 40.9 40.9 42.9 45.1 47.5 50.2 53.1 56.4 60.0 64.0 68.4 73.3 78.6 84.6 91.1 98.4 106.4 115.3
°F 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 psi 0.0 481.5 506.2 533.5 563.7 597.1 634.0 674.7 719.8 769.5 824.6 885.4 952.6 1026.8 1108.9 1199.6 1299.9 1410.7 File No.: 1001527.305 Revision: 2 Page B-5 of B-46 F0306-01 R1
Structural Integrity Associates, IncY Table B-7: HNP-2, Bottom Head Region, Curve A Calculations, All EFPY
.A U.
°F ksi*inA0.5
°ksi*in^d 90.0 79.3 52.9 90.0 79.3 52.9 95.0 84.2 56.1 100.0 89.6 59.7 105.0 95.5 63.7 110.0 102.0 68.0 115.0 109.3 72.9 120.0 117.3 78.2 125.0 126.1 84.1 0.5
° 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 psi 0.0 869.3 924.3 985.1 1052.3 1126.6 1208.7 1299.4 1399.6 File No.: 1001527.305 Revision: 2 Page B-6 of B-46 F0306-01R I
~jStructural Integrity Associates, lnc.'
Table B-8: HNP-2, FW Nozzle / Non-Beltline, Curve A Calculations, All EFPY A *
-i~
°F eksi*inAO.5
°ksi*inAlO.5
°Fpsi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 102.0 102.0 109.3 117.3 126.1 135.9 146.7 158.6 68.0 68.0 72.9 78.2 84.1 90.6 97.8 105,8 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 0.0 832.0 893.1 960.7 1035.5 1118.0 1209.3 1310.2 File No.: 1001527.305 Revision: 2 Page B-7 of B-46 F0306-01RI
Structural Integrity Associates, lncY Table B-9: HNP-2, Beitline Region (Lower Shell #2 Plate, t = 6.375"), Curve B Calculations, for 37 EFPY and lO0°F/hr Cool-down
-z GaeFli
°ksi*inA0.5
°ksi*inAO.5 P-!T Curve i Tepeatr psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 62.6 62.6 65.7 69.1 72.8 77.0 81.6 86.7 92.3 98.6 105.4 113.0 121.4 26.4 26.4 27.9 29.6 31.5 33.6 35.9 38.5 41.3 44.4 47.8 51.6 55.8 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 0.0 621.8 659.9 702.1 748.7 800.2 857.1 920.0 989.5 1066.3 1151.2 1245.0 1348.7 Table B-10: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve B 37 EFPY and 100°F/hr Cool-down Calculations, for
°F
@ksi*inAO.5
°ksi*inA0.5
°Fpsi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 64.4 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 29.0 29.0 30.7 32.5 34.5 36.7 39.2 41.9 44.9 48.2 51.8 55.9 60.3 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 0.0 628.3 665.5 706.7 752.2 802.5 858.1 919.6 987.5 1062.5 1145.5 1237.1 1338.4 File No.: 1001527.305 Revision: 2 Page B-8 of B-46 F0306-01RI
~jjStructural Integrity Associates, Inc.'e Table B-Il1: HNP-2, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 37 EFPY and 1000F/hr Thermal Transient 9
- ksi~in^0.5 "ksiPin^0.5 psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 64.4 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 147.8 159.9 173.2 187.9 204.2 222.2 242.1 22.3 22.3 23.9 25.7 27.7 30.0 32.4 35.1 38.1 41.4 45.1 49.1 53.6 58.5 64.0 70.0 76.7 84.0 92.2 101.2 111.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 0.0 248.1 268.6 291.3 316.4 344.1 374.8 408.6 446.0 487.4 533.1 583.6 639.4 701.1 769.2 844.6 927.8 1019.8 1121.5 1233.9 1358.2 File No.: 1001527.305 Revision: 2 Page B-9 of B-46 F0306-01RI
~jjStructural Integrity Associates, IncY Table B-12: HNP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve B Calculations, for 50.1 EFPY and 1000F/hr Thermal Transient
.~
0F 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0
°ksi*inA0.5 58.9 58.9 61.6 64.6 67.9 71.6 75.6 80.1 85.0 90.5 96.5 103.1 110.5 118.6
°ksi*in^0.5 24.6 24.6 25.9 27.4 29.1 30.9 32.9 35.2 37.6 40.3 43.4 46.7 50.4 54.4 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 psi 0.0 576.9 610.4 647.3 688.1 733.2 783.1 838.2 899.1 966.5 1040.9 1123.1 1213.9 1314.4 150.0 Table B-13: HNP-2, Beltline Region (Lower-Int Shell #3 Plate, t = 5.375"), Curve B Calculations, for 50.1 EFPY and 100°F/hr Thermal Transient
.5
- 9.
9 9
"F
°ksi*in^0.5
°ksi*in^0.5 P-T Crv TepeaFr 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 61.4 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 27.5 27.5 29.0 30.6 32.5 34.5 36.7 39.1 41.8 44.8 48.1 51.8 55.8 60.2 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 P-TCuv psi 0.0 593.9 627.6 664.8 705.9 751.3 801.5 857.0 918.3 986.1 1061.0 1143.7 1235.2 1336.3 File No.: 1001527.305 Revision: 2 Page B-10 of B-46 F0306-01R I
Structural Integrity Associates, Inc.
Table B-14: HINP-2, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 50.1 EFPY and 1O00F/hr Thermal Transient
.5 e
(Sage Fluid P-T Curve P-T Curve Temperature Temperature Pressure 90.
90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0
°ksi*inAO.5 61.4 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 136.7 147.6 159.6 172.9 187.6 203.9 221.8 241.7 oksi*inAO.5 20.8 20.8 22.2 23.9 25.7 27.7 29.9 32.4 35.1 38.0 41.3 45.0 49.0 53.5 58.4 63.9 69.9 76.5 83.9 92.0 101.0 110.9 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 psi 0.0 229.2 247.7 268.2 290.9 315.9 343.5 374.1 407.9 445.2 486.5 532.1 582.5 638.2 699.8 767.8 843.0 926.1 1017.9 1119.4 1231.6 1355.5 File No.: 1001527.305 Revision: 2 Page B-11 of B-46 F0306-01 R1
Structural Integrity Associates, Inc.*
Table B-15: HNP-2, Bottom Head Region, Curve B Calculations, for All EFPY and 1000F/hr Thermal Transient
-z a
"F ksi*inAO.5
°ksi*inAO.5 psI 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 79.3 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 33.9 33.9 36.3 39.0 42.0 45.2 48.9 52.9 57.3 62.2 67.6 73.5 80.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 0.0 546.3 587.5 633.1 683.5 739.2 800.8 868.8 944.0 1027.1 1119.0 1220.4 1332.6 File No.: 1001527.305 Revision: 2 Page B-12 of B-46 F0306-01 RI
Structural Integrity Associates, lnc.*
Table B-16: HNP-2, FW Nozzle / Non-Beltline, Curve B Calculations, for All EFPY and 100°F/br Thermal Transient
.~
e Gage Fluid P-T Curve P-T Curve Temperature KIC Temperature Pressure 90.
90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0
°ksi*inA0.5 102.0 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 202.5 220.3 240.0 261.8
°ksi*inAO.5 44.6 33.2 36.3 39.8 43.7 48.1 52.9 58.3 64.3 71.0 78.4 86.6 95.8 106.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 psi 0.0 390.5 430.1 474.4 523.7 578.8 640.1 708.4 784.5 869.1 963.2 1067.9 1184.2 1313.4 File No.: 1001527.305 Revision: 2 Page B-13 of B-46 F0306-01RI
Structural Integrity Associates, Inc Table B-17: HINP-2, Beitline Region (Lower Shell #2 Plate, t = 6.375"), Curve B Calculations, for 37 EFPY and 2000F/hr Thermal Transient e
Gage Fluid P-T Curve P-T Curve Temperature Temperature Pressure 9
1(
°F ksi*inA0.5
@ksi*in^0.5 40.0 62.6 21.5
'0.0 62.6 21.5
'5.0 65.7 23.0 00.0 69.1 24.8 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 72.8 77.0 81.6 86.7 92.3 98.6 105.4 113.0 121.4 130.7 26.6 28.7 31.0 33.6 36.4 39.5 42.9 46.7 50.9 55.6 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 psi 0.0 501.0 539.1 581.3 627.9 679.4 736.3 799.2 868.7 945.5 1030.4 1124.2 1227.9 1342.5 Table B-18: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve B Calculations, for 37 EFPY and 2000F/hr Thermal Transient
~.z 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0
°ksi*inA0.5
°ksi*inA0.5 64.4 25.8 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 25.8 27.5 29.3 31.3 33.5 36.0 38.7 41.7 45.0 48.6 52.7 57.1 62.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 psi 0.0 555.9 593.1 634.3 679.8 730.1 785.7 847.2 915.1 990.1 1073.1 1164.7 1266.0 1378.0 File No.: 1001527.305 Revision: 2 Page B-14 of B-46 F0306-01 RI
jjStructuraI Integrity Associates, Inc~e Table B-19: HNP-2, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 37 EFPY and 200°F/hr Thermal Transient
.5
- a.
a a
-/-.
"kSI,'irIO.5 "lKsPifln^U.5
-1" psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 64.4 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 147.8 159.9 173.2 187.9 204.2 222.2 242.1 264.1 12.3 12.3 13.9 15.7 17.7 20.0 22.4 25.1 28.1 31.4 35.1 39.1 43.6 48.5 54.0 60.0 66.7 74.0 82.2 91.2 101.1 112.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 0.0 123.1 143.7 166.4 191.4 219.2 249.8 283.6 321.1 362.4 408.1 458.6 514.4 576.1 644.3 719.6 802.9 894.9 996.6 1109.0 1233.2 1370.5 File No.: 1001527.305 Revision: 2 Page B-15 of B-46 F0306-01 RI
jjStructural Integrity Associates, Inc.'
Table B-20: HNP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve B Calculations, for 50.1 EFPY and 2000F/hr Thermal Transient
.5 e
9
°F oksi*inA0.5
°ksi*inA0.5
-1" ps, 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 58.9 58.9 61.6 64.6 67.9 71.6 75.6 80.1 85.0 90.5 96.5 103.1 110.5 118.6 127.6 19.7 19.7 21.0 22.5 24.2 26.0 28.0 30.3 32.7 35.5 38.5 41.8 45.5 49.5 54.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 0.0 456.1 489.6 526.5 567.3 612.5 662.3 717.4 778.4 845.7 920.1 1002.3 1093.2 1193.6 1304.6 File No.: 1001527.305 Revision: 2 Page B-16 of B-46 F0306-01 R1
~jjStructural Integrity Associates, Inc.*
Table B-21: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve B Calculations, for 50.1 EFPY and 2000F/hr Thermal Transient I
3-t
°ksi*inAO.5
°ksi*inA0.5 7-psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 61.4 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 136.7 24.3 24.3 25.8 27.4 29.3 31.3 33.5 35.9 38.6 41.6 44.9 48.6 52.6 57.1 62.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 0.0 521.5 555.2 592.4 633.5 678.9 729.1 784.6 845.9 913.7 988.6 1071.3 1162.8 1263.9 1375.6 File No.: 1001527.305 Revision: 2 Page B-17 of B-46 F0306-01RI
~jjStructural Integrity Associates, Inc5 Table B-22: HNP-2, WLI (N16) Nozzle Beitline Region, Curve B Calculations, for 50.1 EFPY and 200°F/hr Thermal Transient
.~
3-I 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0
°ksi*inAO.5 61.4 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 136.7 147.6 159.6 172.9 187.6 203.9 221.8 241.7 263.6 "ksPin^0~L.5 "F
ps 10.8 10.8 12.2 13.9 15.7 17.7 19.9 22.4 25.1 28.0 31.3 35.0 39.0 43.5 48.4 53.9 59.9 66.5 73.9 82.0 91.0 100.9 111.8 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0 0.0 104.2 122.8 143.2 165.9 190.9 218.6 249.2 282.9 320.3 361.5 407.1 457.5 513.2 574.8 642.8 718.0 801.1 893.0 994.5 1106.6 1230.6 1367.6 File No.: 1001527.305 Revision: 2 Page B-18 of B-46 F0306-01 RI
~jStructural Integrity Associates, Inc.*
Table B-23: HNP-2, Bottom Head Region, Curve B Calculations, for All EFPY and 200°F/hr Thermal Transient
.5 9-9 I
°F ksi*inAO.5
°ksi*inA0.5 ps 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 79.3 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 28.1 28.1 30.6 33.2 36.2 39.5 43.1 47.1 51.5 56.4 61.8 67.8 74.4 81.7 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 0.0 448.1 489.4 535.0 585.4 641.1 702.6 770.7 845.9 929.0 1020.8 1122.3 1234.5 1358.4 File No.: 1001527.305 Revision: 2 Page B-19 of B-46 F0306-01 RI
Structural Integrity Associates, Inlc.
Table B-24: HNP-2, FW Nozzle / Non-Beltline, Curve B Calculations, for All EFPY and 200°F/hr Thermal Transient
-5
°F ksi*inAO.5
°ksi*in^0.5 psi 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 102.0 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 202.5 220.3 240.0 261.8 38.1 33.2 36.3 39.8 43.7 48.1 52.9 58.3 64.3 71.0 78.4 86.6 95.8 106.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 0.0 390.5 430.1 474.4 523.7 578.8 640.1 708.4 784.5 869.1 963.2 1067.9 1184.2 1313.4 File No.: 1001527.305 Revision: 2 Page B-20 of B-46 F0306-01RI
Structural Integrity Associates, In~
Table B-25: HNP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve C Calculations, for 37 EFPY and 100 0F/hr Thermal Transient 9-9 "1"
-(si~fl,,I.5
-ks1 1fn"U.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 46.4 46.4 47.8 49.3 51.0 52.9 55.0 57.2 59.8 62.6 65.7 69.1 72.8 77.0 81.6 86.7 92.3 98.6 105.4 113.0 121.4 18.3 18.3 19.0 19.8 20.6 21.6 22.6 23.7 25.0 26.4 27.9 29.6 31.5 33.6 35.9 38.5 41.3 44.4 47.8 51.6 55.8 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 0.0 422.0 439.2 458.1 479.1 502.2 527.8 556.0 587.3 621.8 659.9 702.1 748.7 800.2 857.1 920.0 989.5 1066.3 1151.2 1245.0 1348.7 File No.: 1001527.305 Revision: 2 Page B-21 of B-46 F0306-01RI
Structural Integrity Associates, IncY Table B-26: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve C Calculations, for 37 EFPY and 100°F/hr Thermal Transient
- F oksi*inA0.5
°ksi*inA0.5
°Fpsi 50.0 47.2 20.4 90.0 0.0 50.0 47.2 20.4 90.0 433.1 55.0 48.7 21.2 95.0 449.9 60.0 50.3 22.0 100.0 468.4 65.0 52.1 22.9 105.0 488.9 70.0 54.1 23.9 110.0 511.5 75.0 56.3 25.0 115.0 536.4 80.0 58.8 26.2 120.0 564.0 85.0 61.5 27.5 125.0 594.6 90.0 64.4 29.0 130.0 628.3 95.0 67.7 30.7 135.0 665.5 100.0 71.4 32.5 140.0 706.7 105.0 75.4 34.5 145.0 752.2 110.0 79.8 36.7 150.0 802.5 115.0 84.7 39.2 155.0 858.1 120.0 90.1 41.9 160.0 919.6 125.0 96.1 44.9 165.0 987.5 130.0 102.7 48.2 170.0 1062.5 135.0 110.0 51.8 175.0 1145.5 140.0 118.1 55.9 180.0 1237.1 145.0 127.1 60.3 185.0 1338.4 File No.: 1001527.305 Page B-22 of B-46 Revision: 2 F0306-01 R1
Structural Integrity Associates, Inc.=
Table B-27: HNP-2, WLI (N16) Nozzle Beltline Region, Curve C Calculations, for 37 EFPY and 100°F/hr Thermal Transient e.
°ksi'in^0.5
°ksi~in^0.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75,0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 47.2 47.2 48.7 50.3 52.1 54.1 56.3 58.8 61.5 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 147.8 159.9 173.2 187.9 204.2 222.2 242.1 13.7 13.7 14.4 15.2 16.1 17.1 18.2 19.4 20.8 22.3 23.9 25.7 27.7 30.0 32.4 35.1 38.1 41.4 45.1 49.1 53.6 58.5 64.0 70.0 76.7 84.0 92.2 101.2 111.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0 200.0 205.0 210.0 215.0 220.0 225.0 0.0 140.6 149.8 160.0 171.3 183.7 197.5 212.7 229.5 248.1 268.6 291.3 316.4 344.1 374.8 408.6 446.0 487.4 533.1 583.6 639.4 701.1 769.2 844.6 927.8 1019.8 1121.5 1233.9 1358.2 File No.: 1001527.305 Revision: 2 Page B-23 of B-46 F0306-01RI
$jJtructural Integrity Associates, lncY Table B-28: HINP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve C Calculations, for 50.1 EFPY and 100°F/hr Thermal Transient 9
"ksi~inA0.5 Oksi'inA0.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 44.8 44.8 46.0 47.3 48.8 50.4 52.3 54.3 56.5 58.9 61.6 64.6 67.9 71.6 75.6 80.1 85.0 90.5 96.5 103.1 110.5 118.6 17.5 17.5 18.1 18.8 19.5 20.3 21.2 22.2 23.4 24.6 25.9 27.4 29.1 30.9 32.9 35.2 37.6 40.3 43.4 46.7 50.4 54,4 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 0.0 401.9 416.9 433.5 451.9 472.1 494.5 519.3 546.7 576.9 610.4 647.3 688.1 733.2 783.1 838.2 899.1 966.5 1040.9 1123.1 1213.9 1314.4 File No.: 1001527.305 Revision: 2 Page B-24 of B-46 F0306-01RI
S7~trctural Integrity Associates, lnc?
Table B-29: HNP-2, Beitline Region (Lower-mat Shell #3 Plate, t = 5.375"), Curve C Calculations, for 50.1 EFPY and 100°F/hr Thermal Transient
- e.
9
°ksi*inA0.5
°ksi*inA0.5 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 45.9 45.9 47.2 48.7 50.3 52.1 54.1 56.3 58.7 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 19.7 19.7 20.4 21.2 22.0 22.9 23.9 25.0 26.2 27.5 29.0 30.6 32.5 34.5 36.7 39.1 41.8 44.8 48.1 51.8 55.8 60.2 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 psi 0.0 417.7 432.8 449.5 468.0 488.4 511.0 535.9 563.5 593.9 627.6 664.8 705.9 751.3 801.5 857.0 918.3 986.1 1061.0 1143.7 1235.2 1336.3 File No.: 1001527.305 Revision: 2 Page B-25 of B-46 F0306-01R 1
Structural Integrity Associates, Inlc~e Table B-30: HNP-2, WLI (N16) Nozzle Beitline Region, Curve C Calculations, for 50.1 EFPY and 100°F/hr Thermal Transient I
e ksi*inAO.5 "ksi*inAO.5 "Fpsi 50.0 45.9 13.0 90.0 0.0 50.0 45.9 13.0 90.0 132.1 55.0 47.2 13.7 95.0 140.4 60.0 48.7 14.4 100.0 149.6 65.0 50.3 15.2 105.0 159.8 70.0 52.1 16.1 110.0 171.0 75.0 54.1 17.1 115.0 183.5 80.0 56.3 18.2 120.0 197.2 85.0 58.7 19.4 125.0 212.4 90.0 61.4 20.8 130.0 229.2 95.0 64.4 22.2 135.0 247.7 100.0 67.7 23.9 140.0 268.2 105.0 71.3 25.7 145.0 290.9 110.0 75.3 27.7 150.0 315.9 115.0 79.7 29.9 155.0 343.5 120.0 84.6 32.4 160.0 374.1 125.0 90.0 35.1 165.0 407.9 130.0 96.0 38.0 170.0 445.2 135.0 102.6 41.3 175.0 486.5 140.0 109.9 45.0 180.0 532.1 145.0 118.0 49.0 185.0 582.5 150.0 126.9 53.5 190.0 638.2 155.0 136.7 58.4 195.0 699.8 160.0 147.6 63.9 200.0 767.8 165.0 159.6 69.9 205.0 843.0 170.0 172.9 76.5 210.0 926.1 175.0 187.6 83.9 215.0 1017.9 180.0 203.9 92.0 220.0 1119.4 185.0 221.8 101.0 225.0 1231.6 190.0 241.7 110.9 230.0 1355.5 File No.: 1001527.305 Page B-26 of B-46 Revision: 2 F0306-01R 1
Structural Integrity Associates, IncY Table B-31: HNP-2, Bottom Head Region, Curve C Calculations, for All EFPY and 100°F/hr Thermal Transient e-9 Gage Fluid P-T curve P-T Curve Temperature Temperature Pressure 50.
50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0
°ksi*inA0.5 53.9 53.9 56.1 58.5 61.2 64.1 67.4 71.0 75.0 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8
°ksi*inaO.5 21.2 21.2 22.3 23.5 24.8 26.3 27.9 29.7 31.7 33.9 36.3 39.0 42.0 45.2 48.9 52.9 57.3 62.2 67.6 73.5 80.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 psi 0.0 330.2 348.8 369.2 391.9 416.9 444.6 475.2 508.9 546.3 587.5 633.1 683.5 739.2 800.8 868.8 944.0 1027.1 1119.0 1220.4 1332.6 File No.: 1001527.305 Revision: 2 Page B-27 of B-46 F0306-01 RI
Structural Integrity Associates, Inc.Y Table B-32: HINP-2, FW Nozzle / Non-Beltline, Curve C Calculations, for All EFPY and 100°F/hr Thermal Transient e
Gage Fluid P-T curve P-T Curve Temperature K16 Temperature Pressure 50.
50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0
°ksi*in^0.5 64.1 64.1 67.4 71.0 75.0 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 202.5 220.3 240.0 261.8
°ksi*inA0.5 25.6 17.6 18.9 20.3 21.9 23.7 25.7 27.9 30.4 33.2 36.3 39.8 43.7 48.1 52.9 58.3 64.3 71.0 78.4 86.6 95.8 106.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 psi 0.0 193.0 209.1 227.0 247.1 269.7 295.0 323.3 355.0 390.5 430.1 474.4 523.7 578.8 640.1 708.4 784.5 869.1 963.2 1067.9 1184.2 1313.4 File No.: 1001527.305 Revision: 2 Page B-28 of B-46 FO306-01RI
Structural Integrity Associates, Inlc~
Table B-33: HNP-2, Beltline Region (Lower Shell #2 Plate, t = 6.375"), Curve C Calculations, for 37 EFPY and 200°F/hr Thermal Transient D
Gage Fluid P-T Curve P-T Curve Temperature K1 Temperature Pressure 50.
50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0
°ksi*inAO.5 46.4 46.4 47.8 49.3 51.0 52.9 55.0 57.2 59.8 62.6 65.7 69.1 72.8 77.0 81.6 86.7 92.3 98.6 105.4 113.0 121.4 130.7
°ksi*inAO.5 13.4 13.4 14.1 14.9 15.7 16.7 17.7 18.8 20.1 21.5 23.0 24.8 26.6 28.7 31.0 33.6 36.4 39.5 42.9 46.7 50.9 55.6 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 psi 0.0 301.3 318.4 337.3 358.3 381.4 407.0 435.2 466.5 501.0 539.1 581.3 627.9 679.4 736.3 799.2 868.7 945.5 1030.4 1124.2 1227.9 1342.5 File No.: 1001527.305 Revision: 2 Page B-29 of B-46 F0306-01RI
Structural Integrity Associates, Inc.?
Table B-34: HNP-2, Beltline Region (Lower-lnt Shell #~3 Plate, t = 5.375"), Curve C Calculations, for 37 EFPY and 200°F/hr Thermal Transient e-e "F
ksi'in^0.5 "ksi~inA0.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 47.2 47.2 48.7 50.3 52.1 54.1 56.3 58.8 61.5 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 17.2 17.2 18.0 18.8 19.7 20.7 21.8 23.0 24.4 25.8 27.5 29.3 31.3 33.5 36.0 38.7 41.7 45.0 48.6 52.7 57.1 62.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 0.0 360.8 377.5 396.0 416.5 439.1 464.0 491.6 522.2 555.9 593.1 634.3 679.8 730.1 785.7 847.2 915.1 990.1 1073.1 1164.7 1266.0 1378.0 File No.: 1001527.305 Revision: 2 Page B-30 of B-46 F0306-01R I
Structural Integrity Associates, Inc.t Table B-35: HNP-2, WLI (N16) Nozzle Beltline Region, Curve C Calculations, for 37 EFPY and 200°F/hr Thermal Transient e-
°F ksi~inA0.5 "ksi~in^0.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 47.2 47.2 48.7 50.3 52.1 54.1 56.3 58.8 61.5 64.4 67.7 71.4 75.4 79.8 84.7 90.1 96.1 102.7 110.0 118.1 127.1 136.9 147.8 159.9 173.2 187.9 204.2 222.2 242.1 264.1 3.7 3.7 4.4 5.2 6.1 7.1 8.2 9.4 10.8 12.3 13.9 15.7 17.7 20.0 22.4 25.1 28.1 31.4 35.1 39.1 43.6 48.5 54.0 60.0 66.7 74.0 82.2 91.2 101.1 112.1 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0 200.0 205.0 210.0 215.0 220.0 225.0 230.0 0.0 15.6 24.9 35.1 46.3 58.8 72.5 87.8 104.6 123.1 143.7 166.4 191.4 219.2 249.8 283.6 321.1 362.4 408.1 458.6 514.4 576.1 644.3 719.6 802.9 894.9 996.6 1109.0 1233.2 1370.5 File No.: 1001527.305 Revision: 2 Page B-31 of B-46 F0306-01RI
~jStructural Integrity Associates, IncY Table B-36: HNP-2, Beitliee Region (Lower Shell #2 Plate, t = 6.375"), Curve C Calculations, for 50.1 EFPY and 2000F/hr Thermal Transient
- 9.
9 GaeFli
°ksi*inAO.5 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 44.8 44.8 46.0 47.3 48.8 50.4 52.3 54.3 56.5 58.9 61.6 64.6 67.9 71.6 75.6 80.1 85.0 90.5 96.5 103.1 110.5 118.6 127.6
°ksi*inAO.5 12.6 12.6 13.2 13.9 14.6 15.4 16.4 17.4 18.5 19.7 21.0 22.5 24.2 26.0 28.0 30.3 32.7 35.5 38.5 41.8 45.5 49.5 54.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0 psi 0.0 281.1 296.1 312.7 331.1 351.3 373.8 398.5 425.9 456.1 489.6 526.5 567.3 612.5 662.3 717.4 778.4 845.7 920.1 1002.3 1093.2 1193.6 1304.6 File No.: 1001527.305 Revision: 2 Page B-32 of B-46 F0306-01RI
~j~Structural Integrity Associates, Iflc.e Table B-37: HNP-2, Beltline Region (Lower-lnt Shell #3 Plate, t = 5.375"), Curve C Calculations, for 50.1 EFPY and 200°F/hr Thermal Transient e
oF ksi*inAO.5
°ksi*inAO.5
°Fpsi 50.0 45.9 16.6 90.0 0.0 50.0 45.9 16.6 90.0 345.3 55.0 47.2 17.2 95.0 360.4 60.0 48.7 18.0 100.0 377.1 65.0 50.3 18.8 105.0 395.6 70.0 52.1 19.7 110.0 416.0 75.0 54.1 20.7 115.0 438.6 80.0 56.3 21.8 120.0 463.5 85.0 58.7 23.0 125.0 491.1 90.0 61.4 24.3 130.0 521.5 95.0 64.4 25.8 135.0 555.2 100.0 67.7 27.4 140.0 592.4 105.0 71.3 29.3 145.0 633.5 110.0 75.3 31.3 150.0 678.9 115.0 79.7 33.5 155.0 729.1 120.0 84.6 35.9 160.0 784.6 125.0 90.0 38.6 165.0 845.9 130.0 96.0 41.6 170.0 913.7 135.0 102.6 44.9 175.0 988.6 140.0 109.9 48.6 180.0 1071.3 145.0 118.0 52.6 185.0 1162.8 150.0 126.9 57.1 190.0 1263.9 155.0 136.7 62.0 195.0 1375.6 File No.: 1001527.305 Page B-33 of B-46 Revision: 2 F0306-01 RI
jjStructural Integrity Associates, lnc5 Table B-38: HINP-2, WLI (NI6) Nozzle Beltline Region, Curve C Calculations, for 50.1 EFPY and 200°F/hr Thermal Transient U
°F 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0
°ksi*inA0.5 45.9 45.9 47.2 48.7 50.3 52.1 54.1 56.3 58.7 61.4 64.4 67.7 71.3 75.3 79.7 84.6 90.0 96.0 102.6 109.9 118.0 126.9 136.7 147.6 159.6 172.9 187.6 203.9 221.8 241.7 263.6
°ksi*inAO.5 3.0 3.0 3.7 4.4 5.2 6.1 7.1 8.2 9.4 10.8 12.2 13.9 15.7 17.7 19.9 22.4 25.1 28.0 31.3 35.0 39.0 43.5 48.4 53.9 59.9 66.5 73.9 82.0 91.0 100.9 111.8 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 195.0 200.0 205.0 210.0 215.0 220.0 225.0 230.0 235.0 psi 0.0 7.1 15.5 24.7 34.8 46.1 58.5 72.3 87.4 104.2 122.8 143.2 165.9 190.9 218.6 249.2 282.9 320.3 361.5 407.1 457.5 513.2 574.8 642.8 718.0 801.1 893.0 994.5 1106.6 1230.6 1367.6 File No.: 1001527.305 Revision: 2 Page B-34 of B-46 F0306-01RI
Structural Integrity Associates, lnc.?
Table B-39: HNP-2, Bottom Head Region, Curve C Calculations, for All EFPY and 2000F/hr Thermal Transient 9-e
°F oksi*inA0.5
°ksi*inA0.5 p~si 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 53.9 53.9 56.1 58.5 61.2 64.1 67.4 71.0 75.0 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 15.4 15.4 16.5 17.7 19.0 20.5 22.1 23.9 25.9 28.1 30.6 33.2 36.2 39.5 43.1 47.1 51.5 56.4 61.8 67.8 74.4 81.7 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 0.0 232.1 250.6 271.1 293.7 318.8 346.4 377.0 410.8 448.1 489.4 535.0 585.4 641.1 702.6 770.7 845.9 929.0 1020.8 1122.3 1234.5 1358.4 File No.: 1001527.305 Revision: 2 Page B-35 of B-46 F0306-01RI
Structural Integrity Associates, Inc.Y Table B-30: HNP-2, FW Nozzle / Non-Beltline, Curve C Calculations, for All EFPY and 2000F~hr Thermal Transient a
°F ksi'inA0.5
°ksi~inA0.5 psi 50.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 64.1 64.1 67.4 71.0 75.0 79.3 84.2 89.6 95.5 102.0 109.3 117.3 126.1 135.9 146.7 158.6 171.8 186.4 202.5 220.3 240.0 261.8 19.2 17.6 18.9 20.3 21.9 23.7 25.7 27.9 30.4 33.2 36.3 39.8 43.7 48.1 52.9 58.3 64.3 71.0 78.4 86.6 95.8 106.0 90.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 185.0 190.0 0.0 193.0 209.1 227.0 247.1 269.7 295.0 323.3 355.0 390.5 430.1 474.4 523.7 578.8 640.1 708.4 784.5 869.1 963.2 1067.9 1184.2 1313.4 File No.: 1001527.305 Revision: 2 Page B-36 of B-46 F0306-01RI
~jStructural Integrity Associates, Inc.'
Curve A - Pressure Test, All Components
-BL1 BL2 N16 BH
-FWN IOCFR50 a.0 E
61 1300 1200 1100 1000 9O0f 800 700r 6OOk 500 400K......
300 ~
200 100 50 0
100 150 Minimum Reactor Vessel Metal Temperature (°F) 200 250 Figure B-I: HNP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 37 EFPY Note: BL is Beitline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-37 of B-46 F0306-01 RI
Structural Integrity Associates, Inc.*
Curve A - Pressure Test, All Components
-BLl BL_2....-
-BH FWN IOCFR50 wJ 11 a-E
-S 1300 1200 1100 +--....
900 -
700 -i 600 500-400 T......
300 -.
201 100 0
0 50 100 150 Minimum Reactor Vessel Metal Temperature (oF) 200 250 Figure B-2: HNP-2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 50.1 EFPY Note: BL is Beltline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-38 of B-46 F0306-01R I
~jStructurul Integrity Associates, IncY Curve B - Core Not Critical, All Components
-BL1 BL2 N16 BH FWN 10CFR50 a.
-I
'I C4..
100 150 Minimum Reactor Vessel Metal Temperature (°F) 250 Figure B-3: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 1O00F/hr Note: BL is Beltline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-39 of B-46 F0306-01RIl
~jStructural Integrity Associates, Inc.Y Curve B - Core Not Critical, All Components
-BLl N16 BH FWN IOCFR50O....BL2 a.
E 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 U
0 50 100 150 200 250 Minimum Reactor Vessel Metal Temperature ("F)
Figure B-4: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 100°F/hr Note: BL is Beltline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-40 of B-46 F0306-01R 1
~jjStructural Integrity Associates, Inc.e Curve B - Core Not Critical, All Components
-BL1....BL2 N16 1 BH 1-
-FWN
-1.
OCFR50 a.
E U9
&r 50 100 150 Minimum Reactor Vessel Metal Temperature (°F) 250 Figure B-5: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 37 EFPY and 200°F/hr Note: BL is Beitline, BH is Bottom Head and FW~N is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-41 of B-46 F0306-01JR I
~jStrcturailonegrity Associates, IncY Curve B - Core Not Critical, All Components
-BL1 BL2 N16 BH
-FWN IOCFR50 hA El
-1 S
50 I00 150 Minimum Reactor Vessel Metal Temperature ('F) 250 Figure B-6: HNP-2 P-T Curve B (Normal Operation - Core Not Critical), 50.1 EFPY and 200°F/hr Note: BL is Beitline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-42 of B-46 F0306-01R 1
Structural Integrity Associates, Inc.
Curve C - Core Critical, All Components
-BL1....BL2 N16 BH
-FWN I(XCFR50 1300 1200(
1100 900 S800
- 1 E
@1 400 300 200 100 0
50 100 150 200 Minimum Reactor Vessel Metal Temperature (0F) 250 Figure B-7: HINP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 100°F/hr Note: BL is Beitline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-43 of B-46 F0306-01R 1
jjStructural Integrity Associates, /nc.*
Curve C - Core Critical, All Components
-BL1.
81..B2....
N16 BH
-FWN IOCFR50 0.
61 C
E U
100 150 Minimum Reactor Vessel Metal Temperature (OF) 250 Figure B-8: HNP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 1O0°F/hr Note: BL is Beitline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-44 of B-46 F0306-01RI
Structural Integrity Associates, IncY u
Curve C - Core Critical, All Components
-8
- 11.
81..B2....
N16 BH FWN 10CFR50 a.
7.
E O1 a:
1 3OO0 t 1200
- 110 900-700 600 300 200%
100 50 100 150 Minimum Reactor Vessel Metal Temperature (°F) 200 250 Figure B-9:HINP-2 P-T Curve C (Normal Operation - Core Critical), 37 EFPY and 200°F/hr Note: BL is Beltline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-45 of B-46 F0306-01 RI
Structural Integrity Associates, Inc.Y Curve C - Core Critical, All Components
-BL1 BL2 N16 BH
-FWN IOCFR50 1300 1200 1100 1000 900 6700 4OO 2O 100 0
50 100 150 Minimum Reactor Vessel Metal Temperature (*F) 200 250 Figure B-10: HNP-2 P-T Curve C (Normal Operation - Core Critical), 50.1 EFPY and 200°F/hr Note: BL is Beitline, BH is Bottom Head and FWN is Feedwater Nozzle File No.: 1001527.305 Revision: 2 Page B-46 of B-46 F0306-01 RI
Edwin I. Hatch Nuclear Plant Response to Request for Additional Information Regarding Application for Amendment to Technical Specifications for Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-41 9-A Corrected Table 3 to the Unit 1 PTLR
Hatch Unit 1 PTLR Revision 0 Page 28 of 40 Table 3: HNP-1 P-T Curve C (Normal Operation - Core Critical) for 38 EFPY (continued)
Non-Beltline Region P-T Curve P-T Curve Temperature Pressure "F
psi 76.0 0.0 76.0 97.6 98.0 140.6 112.1 183.6 122.6 226.6 130.9 269.6 137.9 312.6 212.0 312.6 212.0 1563.0