summary stress report for primary pipingthis technical report contains a summary of the stress...

Summary Stress Report for Primary Piping APR1400-H-N-NR-14005-NP Rev.2

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Summary Stress Report for

Primary Piping

Revision 2

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September 2016

Copyright ⓒ 2016

Korea Electric Power Corporation & Korea Hydro & Nuclear Power Co., Ltd

All Rights Reserved


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REVISION HISTORY

Revision Date Page (Section) Description

0 July. 2015 All Original Issue

1 December.2015

All 7 8,10 7,8,14,56,58,59, 60,62 thru 65 68,70,71,72,75, 77 thru 83 85 thru 91,93,94,95,98 56 Appendix A

- Revised revision number. - Added shape factor α. - Added “Hydrostatic Test”. - Editorially revised. - Added pressure calculation. - Added Elastic-Plastic Evaluation of Surge Line.

2 September. 2016

All 7,12 12 18 42 Appendix A6

- Revised revision number. - Revised “α” was “1.5”. Added the description of α. - Revised “PL+Pb” was “Pm+Pb”. - Added the method of decoupling. - Added the description of correction factor(Ec/Eh). - Simplified elastic – plastic evaluation was added.

U

This document was prepared for the design certification

application to the U.S. Nuclear Regulatory Commission and

contains technological information that constitutes intellectual

property of Korea Hydro & Nuclear Power Co., Ltd..

Copying, using, or distributing the information in this

document in whole or in part is permitted only to the U.S.

Nuclear Regulatory Commission and its contractors for the

purpose of reviewing design certification application

materials. Other uses are strictly prohibited without the

written permission of Korea Electric Power Corporation and

Korea Hydro & Nuclear Power Co., Ltd.


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ABSTRACT

This report contains a summary of the structural evaluation of the Primary Piping The evaluations were performed based on the loading conditions defined in the APR1400 Primary Piping Design Specification (Ref.B.1) and on the design procedures in accordance with the requirements ASME Boiler and Pressure Vessel Section III, 2007 Edition with through 2008 Addenda (Ref.A.1). The analyses and results presented demonstrate that seven parts of the Primary Piping that were evaluated satisfy all of the applicable structural limits of the ASME B&PV Code.


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TABLE OF CONTENTS

REVISION HISTORY ........................................................................................................................... i

ABSTRACT ........................................................................................................................................ ii

TABLE OF CONTENTS .................................................................................................................... iii

LIST OF TABLES ............................................................................................................................... v

LIST OF FIGURES ........................................................................................................................... vii

ACRONYMS AND ABBREVIATIONS ............................................................................................. viii

1. Introduction ............................................................................................................................ 1

2. Summary of Results .............................................................................................................. 2

3. Conclusions ............................................................................................................................ 5

4. Assumptions and Open Items .............................................................................................. 6

4.1 Assumptions ......................................................................................................................... 6

4.2 Open Items ........................................................................................................................... 6

5. Code Requirements ............................................................................................................... 7

5.1 Stress Limits for Components other than Bolts .................................................................... 7

5.2 Analysis of Piping products .................................................................................................. 9

5.3 Special Stress Limits .......................................................................................................... 11

5.4 Application of Plastic Analysis ............................................................................................ 11

6. Allowable Limits ................................................................................................................... 12

7. Design Input ......................................................................................................................... 13

7.1 Geometry ............................................................................................................................ 13

7.2 Material ............................................................................................................................... 13

7.3 Loads, Load Combinations, and Transients ....................................................................... 18

8. Methodology ......................................................................................................................... 52

8.1 Thermal Analysis ................................................................................................................ 52

8.2 Structural Analysis .............................................................................................................. 52

8.3 Fatigue Analysis ................................................................................................................. 53

9. Computer Programs Used .................................................................................................. 54

9.1 AFPOST ............................................................................................................................. 54

9.2 NOZPROG ......................................................................................................................... 54


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10. Structural Evaluation Results ............................................................................................. 55

10.1 Primary Pipes and Elbows ................................................................................................. 55

10.2 Surge Line .......................................................................................................................... 57

10.3 Surge Nozzle ...................................................................................................................... 61

10.4 Charging Inlet Nozzle ......................................................................................................... 69

10.5 Drain Nozzle ....................................................................................................................... 76

10.6 Spray Nozzle ...................................................................................................................... 84

10.7 Shutdown Cooling System Outlet Nozzle .......................................................................... 92

11. References ............................................................................................................................ 99

Appendix A ..................................................................................................................................... A1


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LIST OF TABLES

Table 2-1 Summary of Primary Pipes and Elbows Results .................................................. 3 Table 6-1 Allowable Limits .................................................................................................. 12 Table 7-1 Materials of Construction .................................................................................... 14 Table 7-2 Material Strength for SA-516 Gr. 70 ................................................................... 15 Table 7-3 Material Strength for SA-508 Gr. 1a ................................................................... 15 Table 7-4 Material Strength for SA-182 Gr. F316LN (t < 5 [in]) .......................................... 15 Table 7-5 Material Strength for SA-182 Gr. F347 (t < 5 [in]) .............................................. 16 Table 7-6 Material Strength for SA-376 TP 347 ................................................................. 16 Table 7-7 Material Strength for SA-403 WP 347 ................................................................ 16 Table 7-8 Material Strength for SB-166 N06690 ................................................................ 17 Table 7-9 Pressures and Temperatures ............................................................................. 18 Table 7-10 Force and Moments on Pipe Assembly P-1 ..................................................... 19 Table 7-11 Force and Moments on Pipe Assembly P-2 ..................................................... 21 Table 7-12 Force and Moments on Pipe Assembly P-3 ..................................................... 22 Table 7-13 Force and Moments on Pipe Assembly P-4 ..................................................... 24 Table 7-14 Force and Moments on Pipe Assembly P-5 ..................................................... 25 Table 7-15 RC Piping Nozzle Loads - Charging Inlet Nozzle ............................................. 28 Table 7-16 Piping Nozzle Loads - Spray Nozzle (Loop 2A) ............................................... 28 Table 7-17 Piping Nozzle Loads - Spray Nozzle (Loop 2B) ............................................... 29 Table 7-18 Piping Nozzle Loads - Drain and Letdown Nozzle (Loop 1A) .......................... 29 Table 7-19 Piping Nozzle Loads - Drain and Letdown Nozzle (Loop 1B) .......................... 30 Table 7-20 Piping Nozzle Loads - Drain and Letdown Nozzle (Loop 2A) .......................... 30 Table 7-21 Piping Nozzle Loads - Drain and Letdown Nozzle (Loop 2B) .......................... 30 Table 7-22 Piping Nozzle Loads - Shutdown Cooling Outlet (P-1) .................................... 31 Table 7-23 Piping Nozzle Loads - Shutdown Cooling Outlet (P-10) .................................. 32 Table 7-24 Piping Nozzle Loads - Hot Leg Surge Nozzle .................................................. 33 Table 7-25 Surge Line Piping Loads .................................................................................. 34 Table 7-26 RCS Design Transients .................................................................................... 46 Table 7-27 CVCS Design Transients .................................................................................. 47 Table 9-1 Computer Program Description .......................................................................... 54 Table 10-1 Structural Evaluation of Primary Pipes and Elbows ......................................... 56 Table 10-2 Design Evaluation of Surge Line ...................................................................... 58 Table 10-3 Level D Evaluation of Surge Line ..................................................................... 58 Table 10-4 Test Evaluation of Surge Line ........................................................................... 58 Table 10-5 Structural Evaluation of Surge Line .................................................................. 59 Table 10-6 Simplified Elastic-Plastic Evaluation of Surge Line .......................................... 60 Table 10-7 Contribution of Each Loading of Surge Line .................................................... 60 Table 10-8 Design Evaluation of Surge Nozzle .................................................................. 62 Table 10-9 Level D Evaluation of Surge Nozzle ................................................................. 63 Table 10-10 Test Evaluation of Surge Nozzle .................................................................... 64 Table 10-11 Triaxial stress Evaluation of Surge Nozzle ..................................................... 65 Table 10-12 Structural Evaluation of Surge Nozzle............................................................ 66 Table 10-13 Contribution of Each Loading of Surge Nozzle .............................................. 68 Table 10-14 Design Evaluation of Charging Inlet Nozzle ................................................... 70 Table 10-15 Level D Evaluation of Charging Inlet Nozzle .................................................. 70 Table 10-16 Test Evaluation of Charging Inlet Nozzle ........................................................ 71 Table 10-17 Triaxial stress Evaluation of Charging Inlet Nozzle ........................................ 72 Table 10-18 Structural Evaluation of Charging Inlet Nozzle ............................................... 73 Table 10-19 Design Evaluation of Drain Nozzle ................................................................. 77 Table 10-20 Level D Evaluation of Drain Nozzle ................................................................ 78 Table 10-21 Contribution of Each Loading of Drain Nozzle ............................................... 78 Table 10-22 Test Evaluation of Drain Nozzle ..................................................................... 79


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Table 10-23 Triaxial stress Evaluation of Drain Nozzle ...................................................... 80 Table 10-24 Structural Evaluation of Drain Nozzle............................................................. 82 Table 10-25 Design Evaluation of Spray Nozzle ................................................................ 85 Table 10-26 Level D Evaluation of Spray Nozzle ............................................................... 86 Table 10-27 Test Evaluation of Spray Nozzle ..................................................................... 87 Table 10-28 Triaxial stress Evaluation of Spray Nozzle ..................................................... 88 Table 10-29 Structural Evaluation of Spray Nozzle ............................................................ 90 Table 10-30 Design Evaluation of Shutdown Cooling System Outlet Nozzle .................... 93 Table 10-31 Level D Evaluation of Shutdown Cooling System Outlet Nozzle ................... 93 Table 10-32 Test Evaluation of Shutdown Cooling System Outlet Nozzle ......................... 94 Table 10-33 Triaxial stress Evaluation of Shutdown Cooling System Outlet Nozzle ......... 95 Table 10-34 Structural Evaluation of Shutdown Cooling System Outlet Nozzle ................ 96


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LIST OF FIGURES

Figure 1-1 General Configuration of PPG ............................................................................ 1 Figure 7-1 RC Piping Sections/End Locations and Coordinate System for Loads (P-1) ... 20 Figure 7-2 RC Piping Sections/End Locations and Coordinate System for Loads (P-2) ... 21 Figure 7-3 RC Piping Sections/End Locations and Coordinate System for Loads (P-3) ... 23 Figure 7-4 RC Piping Sections/End Locations and Coordinate System for Loads (P-4) ... 24 Figure 7-5 RC Piping Sections/End Locations and Coordinate System for Loads (P-5) ... 26 Figure 7-6 Charging Inlet Nozzle Load Conventions ......................................................... 28 Figure 7-7 Drain and Letdown Nozzle Load Conventions ................................................. 31 Figure 7-8 Hot Leg Surge Nozzle Load Conventions ........................................................ 33 Figure 7-9 Local coordinate system for Surge Line Pipe Loads (Straight element) .......... 43 Figure 7-10 Local coordinate system for Surge Line Pipe Loads (Elbow element) ........... 43 Figure 7-11 Location of Surge Line Loads ......................................................................... 44 Figure 10-1 Areas of Interest in Primary Pipes and Elbows ............................................... 55 Figure 10-2 Configuration of Surge Line ............................................................................ 57 Figure 10-3 Areas of Interest and Finite Element model in Surge Nozzle ......................... 61 Figure 10-4 Areas of Interest and Finite Element model in Charging Inlet Nozzle ............ 69 Figure 10-5 Areas of Interest and Finite Element model in Drain Nozzle .......................... 76 Figure 10-6 Areas of Interest and Finite Element model in Spray Nozzle ......................... 84 Figure 10-7 Areas of Interest and Finite Element model in SCO Nozzle ........................... 92


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ACRONYMS AND ABBREVIATIONS Pm General Primary Membrane Stress [ksi] PL Local Primary Membrane Stress [ksi] Pb Primary Bending Stress [ksi] Q Secondary Stress [ksi] SI Stress Intensity [ksi] Sm Design Stress Intensity [ksi] Sy Yield Strength [ksi] Su Tensile Strength [ksi] APR1400 Advanced Power Reactor 1400 BLPB Branch Line Pipe Break CUF Cumulative Fatigue Usage Factor CVCS Chemical and Volume Control System DWT Dead Weight EFVO Economizer Feedwater Valve Opening IRWST In-containment Refueling Water Storage Tank I.D.(ID) Inside Diameter NOP Normal Operation NPS Nominal Pipe Size O.D.(OD) Outside Diameter POSRV Pilot Operated Safety Relief Valves PPG Primary Piping RC Reactor Coolant RCS Reactor Coolant System RTD Resistance Temperature Detector RPCS Reactor Power Cutback System SAM Seismic Anchor Motion SCF Stress Concentration Factor SCO Shutdown Cooling Outlet SIS/SCS Safe Injection System/Shutdown Cooling System SRSS Square-Root-of-the-Sum-of-the-Squares SSE Safe Shutdown Earthquake


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1. Introduction

This technical report contains a summary of the stress analysis results for the APR1400 Primary Piping. The content of this report follows the ASME guidelines for Design Reports as specified in Section III Division 1 Non-mandatory Appendix C. Figure 1-1 shows a general configuration of the PPG. This report provides the structural evaluation for seven parts of PPG. This technical report summarizes the stress results based on the detailed analyses that demonstrate the validity of the Primary Piping to meet the requirements of the ASME Boiler and Pressure Vessel Code (Ref.A.1).

Figure 1-1 General Configuration of PPG

Primary Pipe and Elbow

Drain Nozzle

Charging Inlet Nozzle

Shutdown Cooling Outlet Nozzle

Spray Nozzle

Surge Line

Surge Nozzle


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2. Summary of Results

All the stresses and cumulative fatigue usage factors (CUF) are satisfactory and meet all the requirements of the ASME Boiler and Pressure Vessel Code, Section III, 2007 Edition with through 2008 Addenda (Ref.A.1). Therefore, the structural integrity of the APR1400 PPG has been justified. Table 2-1 summarizes the most significant structural evaluation results and the detailed evaluation for each part is presented in the corresponding section noted in the tabled.


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Table 2-1 Summary of Primary Pipes and Elbows Results

(Section) Part Condition Area of Interest Criteria Ratio(1)

(10.1) Primary Pipe and Elbow

Design Level D

Service Level A, B

(10.2) Piping Surge Line

Design Level D

Service Level A, B

Test

(10.3) Surge Nozzle

Design

Level D

Service Level A, B

Test

(10.4)Charging Inlet Nozzle

Design

Level D

Service Level A, B

Test

(10.5)Drain Nozzle

Design

Level D

Service Level A, B

Test

TS


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Table 2-1 Summary of Primary Pipes and Elbows Results (Cont`d)

(Section) Part Condition Area of Interest Criteria Ratio(1)

(10.6)Spray Nozzle

Design

Level D

Service Level A, B

Test

(10.7)Shutdown Cooling Outlet

Nozzle

Design

Level D

Service Level A, B

Test

Notes)

(1) Ratio = (Calculated Stress or CUF) / (Allowable). (2) Since the total stress ranges of some load pairs contributing this CUF exceed 2*Sy, the

requirements of NB-3227.6 are applied to adjust the Poisson`s ratio and fatigue usage factors.

(3) Since the range of primary plus secondary stress intensities exceeds the allowable of 3*Sm. It is alternatively justified in accordance with the simplified elastic-plastic analysis set forth in NB-3653.6 of Ref A.1

TS


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3. Conclusions

The APR1400 PPG is designed to the requirements of the ASME Boiler and Pressure Vessel Code, 2007 Edition up to and including 2008 Addenda for those loads specified in the Design Specification (Ref.B.1).


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4. Assumptions and Open Items

4.1 Assumptions

1. The material strength for the allowable limit is obtained at the design temperature for conservatism, otherwise noted.

2. All the dimensions consider the most adverse effect of tolerances on diameter/radii and thickness to maximize the pressure radius and to minimize the metal volume.

4.2 Open Items

There are no items to be identified.


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5. Code Requirements

5.1 Stress Limits for Components other than Bolts

NB-3220 of Ref.A.1 presents limits for components other than bolts. For Service Level D condition, the rules of Appendix F of Ref.A.1 apply. Design Condition Pm ≤ Sm PL ≤ 1.5*Sm Pm + Pb ≤ α*Sm

PL + Pb ≤ α*Sm

(α is the shape factor, α = 16𝑟𝑟03𝜋𝜋

∗ 𝑟𝑟03−𝑟𝑟𝑖𝑖3

𝑟𝑟04−𝑟𝑟𝑖𝑖4 The value of α is not exceed 1.5, α ≤ 1.5)

Service Level A Condition (Normal) Maximum Range of PL + Pb + Q ≤ 3*Sm (including Service Level B and Test conditions) Cumulative Fatigue Usage Factor ≤ 1.0 (including Service Level B and Test conditions) Thermal Stress Ratchet (NB-3222.5) To ensure that the possibility of large distortions developing due to ratchet action will not occur, the maximum cyclic thermal stress range for components loaded by internal pressure is limited. The maximum cyclic thermal stress range must be shown to be less than the calculated limit, which is: maximum range ≤ y'*Sy For linear variation of temperature through the shell wall, y' = 1/x for 0 < x < 0.5 = 4*(1-x) for 0.5 < x < 1.0 For parabolic constantly increasing or constantly decreasing variation of temperature through the shell wall, y' = 4.65 for x = 0.3 = 3.55 for x = 0.4 = 2.70 for x = 0.5 = 5.2*(1-x) for 0.615 < x < 1.0 where, x = Pm /Sy (or PL/Sy is sometimes used for conservatism). Service Level B Condition (Upset) Pm ≤ 1.1*Sm PL ≤ 1.1(1.5*Sm) Pm + Pb ≤ 1.1(α*Sm)

PL + Pb ≤ 1.1(α*Sm)

(α is the shape factor, α = 16𝑟𝑟03𝜋𝜋

∗ 𝑟𝑟03−𝑟𝑟𝑖𝑖3

𝑟𝑟04−𝑟𝑟𝑖𝑖4, The value of α is not exceed 1.5, α ≤ 1.5)

Service Level D Condition (Faulted) For Non-ferritic materials: Pm ≤ Lesser of 2.4*Sm or 0.7*Su PL ≤ Lesser of 3.6*Sm or 1.05*Su PL + Pb ≤ Lesser of 3.6*Sm or 1.05*Su For Ferritic materials: Pm ≤ 0.7*Su


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PL ≤ 1.05*Su PL + Pb ≤ 1.05*Su Test Condition (Hydrostatic Test) Pm ≤ 0.9*Sy Pm + Pb ≤ 1.35*Sy for Pm ≤ 0.67*Sy or Pm + Pb ≤ (2.15*Sy - 1.2*Pm) for 0.67*Sy < Pm < 0.90*Sy Maximum Range of (Pm or PL) + Pb + Q ≤ greater of 3*Sm or 2*Sy (when at least one extreme of the stress intensity range is determined by the test loadings) Cumulative Fatigue Usage Factor ≤ 1.0 (included with Service Level A and B conditions) .


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5.2 Analysis of Piping products

NB-3650 of Ref.A.1 presents evaluation for piping products. Design Condition The primary stress intensity shall be satisfied equation (1). 𝐵𝐵1

𝑃𝑃𝐷𝐷𝑜𝑜2𝑡𝑡

+ 𝐵𝐵2𝐷𝐷𝑜𝑜2𝐼𝐼𝑀𝑀𝑖𝑖 ≤ 1.5𝑆𝑆𝑚𝑚 eq. (1)

Where, 𝐵𝐵1,𝐵𝐵2 = primary stress indices for the specific product under investigation in NB-3680 of Ref.A.1 𝐷𝐷𝑜𝑜 = outside diameter of pipe, in. (mm) I = moment of inertia, in4 (mm4) 𝑀𝑀𝑖𝑖 = resultant moment due to a combination of design mechanical loads, in.−lb.(N ⋅ mm) P = Design Pressure, psi (MPa) 𝑆𝑆𝑚𝑚 = allowable design stress intensity value, psi (MPa) t = nominal wall thickness of product, in. (mm) Service Level A Condition (Normal) Primary plus secondary stress intensity ranges due to all pair of load sets shall be satisfied equation (2). (including Service Level B and Test conditions) 𝑆𝑆𝑛𝑛 = 𝐶𝐶1

𝑃𝑃𝑜𝑜𝐷𝐷𝑜𝑜2𝑡𝑡

+ 𝐶𝐶2𝐷𝐷𝑜𝑜2𝐼𝐼𝑀𝑀𝑖𝑖 + 𝐶𝐶3𝐸𝐸𝑎𝑎𝑎𝑎 × |𝛼𝛼𝑎𝑎𝑇𝑇𝑎𝑎 − 𝛼𝛼𝑎𝑎𝑇𝑇𝑎𝑎| ≤ 3𝑆𝑆𝑚𝑚 eq. (2)

Where, 𝐶𝐶1,𝐶𝐶2,𝐶𝐶3 = secondary stress indices for the specific component under investigation in NB-3680 of Ref.A.1 𝐷𝐷𝑜𝑜 , 𝑡𝑡, 𝐼𝐼, 𝑆𝑆𝑚𝑚 = as defied for eq. (1) 𝐸𝐸𝑎𝑎𝑎𝑎= average modulus of elasticity of the two sides of a gross structural discontinuity or Material discontinuity at room temperature, psi (MPa) 𝑀𝑀𝑖𝑖 = resultant range of moment which occurs when the system goes from one service load set to another, in.−lb. (N ⋅ mm) 𝑃𝑃𝑜𝑜 = range of service pressure, psi (MPa) 𝑇𝑇𝑎𝑎(𝑇𝑇𝑎𝑎) = range of average temperature on side a(b) of gross structural discontinuity or material discontinuity, °F (°C). For generally cylindrical shapes, the averaging of T (NB-3653.2) shall be over a distance of �𝑑𝑑𝑎𝑎𝑡𝑡𝑎𝑎 for 𝑇𝑇𝑎𝑎 and over a distance �𝑑𝑑𝑎𝑎𝑡𝑡𝑎𝑎 for 𝑇𝑇𝑎𝑎. 𝛼𝛼𝑎𝑎(𝛼𝛼𝑎𝑎) = coefficient of thermal expansion on side a(b) of a gross structural discontinuity or material discontinuity, at room temperature, 1/ °F (1/°C) Cumulative Fatigue Usage Factor ≤ 1.0 (including Service Level B and Test conditions) Thermal Stress Ratchet (NB-3653.7) For all pair of load sets, the value of the range of ∆𝑇𝑇1 cannot exceed that calculated as follows:

∆𝑇𝑇1 range ≤ 𝑦𝑦′𝑆𝑆𝑦𝑦

0.7 𝐸𝐸𝛼𝛼𝐶𝐶4

where 𝐶𝐶4 = 1.1 for ferritic material = 1.3 for austenitic material 𝐸𝐸𝛼𝛼 = modulus of elasticity (E) times the mean coefficient of thermal expansion (𝛼𝛼) both at room temperature, psi /°F (MPa/°C) P = maximum pressure for the set of conditions under consideration, psi (MPa) 𝑆𝑆𝑦𝑦 = yield strength value, psi (MPa), taken at average fluid temperature of the transient under consideration x = (P𝐷𝐷𝑜𝑜

2𝑡𝑡)( 1𝑆𝑆𝑦𝑦

)

𝑦𝑦′ = 3.33, 2.00, 1.20, and 0.80 for xp0.3, 0.5, 0.7, and 0.8, respectively Service Level B Conditions (Upset) The primary stress intensity shall be satisfied equation (3).


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𝐵𝐵1𝑃𝑃𝐷𝐷𝑜𝑜2𝑡𝑡

+ 𝐵𝐵2𝐷𝐷𝑜𝑜2𝐼𝐼𝑀𝑀𝑖𝑖 ≤ 1.8𝑆𝑆𝑚𝑚 ≤ 1.5𝑆𝑆𝑦𝑦 eq. (3)

Where, 𝐵𝐵1,𝐵𝐵2,𝐷𝐷𝑜𝑜 , I, t, 𝑆𝑆𝑚𝑚 = as defined for eq. (1) Mi = resultant moment due to a combination of level B mechanical loads, in.−lb. (N ⋅ mm), which do not include reversing dynamic load. P = level B pressure, psi (MPa) 𝑆𝑆𝑦𝑦 = as defined for eq. (3) Service Level D Condition (Faulted) The primary stress intensity shall be satisfied equation (5). 𝐵𝐵1

𝑃𝑃𝐷𝐷𝑜𝑜2𝑡𝑡

+ 𝐵𝐵2𝐷𝐷𝑜𝑜2𝐼𝐼𝑀𝑀𝑖𝑖 ≤ 3.0𝑆𝑆𝑚𝑚 ≤ 2.0𝑆𝑆𝑦𝑦 eq. (5)

Where, 𝐵𝐵1,𝐵𝐵2,𝐷𝐷𝑜𝑜 , I, t, 𝑆𝑆𝑚𝑚 = as defined for eq. (1) 𝑀𝑀𝑖𝑖 = resultant moment due to a combination of service level D mechanical loads, in.−lb. (N ⋅ mm), which do not include reversing dynamic load. P = Service level D pressure, psi (MPa) 𝑆𝑆𝑦𝑦 = as defined for eq. (3) If the effects of anchor motion, 𝑀𝑀𝐴𝐴𝐴𝐴 , from reversing dynamic loads are not considered in level B condition, then following requirements shall be satisfied.

𝐶𝐶2𝑀𝑀𝐴𝐴𝐴𝐴𝐷𝐷𝑜𝑜

2𝐼𝐼< 6.0 𝑆𝑆𝑚𝑚

𝐹𝐹𝐴𝐴𝐴𝐴𝐴𝐴𝐴𝐴

< 𝑆𝑆𝑚𝑚

Where, 𝐴𝐴𝐴𝐴 = cross–sectional area of metal in the piping component wall, in.2 (mm2) Piping displacements shall satisfy design specification limitation. (Ref.B.1) Test Condition (Hydrostatic Test) Pm ≤ 0.9*Sy Pm + Pb ≤ 1.35*Sy for Pm ≤ 0.67*Sy or Pm + Pb ≤ (2.15*Sy - 1.2*Pm) for 0.67*Sy < Pm < 0.90*Sy Maximum Range of (Pm or PL) + Pb + Q ≤ greater of 3*Sm or 2*Sy (when at least one extreme of the stress intensity range is determined by the test loadings) Cumulative Fatigue Usage Factor ≤ 1.0 (included with Service Level A and B conditions)


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5.3 Special Stress Limits

NB-3227 of Ref.A.1 presents the special stress limits. These limits are applicable for components other than bolts. The rules of Appendix F of Ref.A.1 also apply here for the Service Level D condition. Tri-axial Stresses (NB-3227.4) The algebraic sum of the three primary principal stresses (s1, s2, s3) shall be limited as shown below except for Service Level D loading conditions. s1 + s2 + s3 < 4*Sm s1 + s2 + s3 < 4.8*Sm (For Service Level C Condition as per NB-3224.3) Applications of Elastic Analysis for Stresses beyond the Yield Strength (NB-3227.6) NB-3227.6 of Ref.A.1 is applicable when total stress range exceeds twice the yield strength of material. If total stresses exceed the yield strength, the Poisson’s ratio correction is applicable to the local thermal stress with following expression.

𝜈𝜈∗ = 0.5 − 0.2 ∗𝑆𝑆𝑦𝑦𝑆𝑆𝑎𝑎

, 𝑏𝑏𝑏𝑏𝑡𝑡 𝑛𝑛𝑛𝑛𝑡𝑡 𝑙𝑙𝑙𝑙𝑙𝑙𝑙𝑙 𝑡𝑡ℎ𝑎𝑎𝑛𝑛 0.3

where, Sa : Value obtained from the applicable design fatigue curve for the specified number of cycles of the condition being considered

Sy : Yield strength of the material at the mean value of the temperature of the cycle

5.4 Application of Plastic Analysis

NB-3228 of Ref.A.1 provides guidance in the application of plastic analysis and some relaxation of the basic stress limits which are allowed if plastic analysis is used. Simplified Elastic-Plastic Analysis (NB-3228.5) The 3*Sm limit on the range of primary plus secondary stress intensity (NB-3222.2) may be exceeded provided that the requirements of NB-3228.5 are met. Simplified Elastic-Plastic Analysis (NB-3653.6) If NB-3653.1 eq.(10) cannot be satisfied for all pairs of load sets, the alternative analysis described below may still permit qualifying the component under NB-3650. Only those pairs of load sets which do not satisfy eq. (10) need be considered. The requirements of NB-3653.6 are met


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6. Allowable Limits

The allowable stress limits according Ref.A.1 are summarized in Table 6-1.

Table 6-1 Allowable Limits

Condition Code Criteria

Design(1)

Pm Sm PL 1.5*Sm Pm + Pb α*Sm PL + Pb α*Sm Triaxial 4*Sm

Service(1) Level A, B P+Q Range 3*Sm Fatigue -

Service Level D(2) Pm 2.4*Sm or 0.7*Su PL 3.6*Sm or 1.05*Su PL + Pb 3.6*Sm or 1.05*Su

Test(1)

Pm 0.9*Sy Pm + Pb

(3) 1.35*Sy Pm + Pb

(4) 2.15*Sy – 1.2*Pm Triaxial 4*Sm

P+Q Range 3*Sm

2*Sy(5)

Notes) (1) See Section 5.2 for the use of NB-3600 of Ref. A.1. (2) See Section 5.1 for the ferritic and non-ferritic materials. (3) For Pm ≤ 0.67*Sy (4) For 0.67*Sy < Pm < 0.90*Sy (5) Greater of 3*Sm or 2*Sy when at least one extreme of range is determined by test loadings. (6) The value of α is not exceed 1.5, α ≤ 1.5


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7. Design Input

7.1 Geometry

The APR1400 PPG component design drawings used for the analyses are taken from Ref.F. Figures describing the detailed geometry and dimensions of the parts evaluated are provided in the Section 10.

7.2 Material

The materials of construction of the PPG are listed in Table 7-1. The material properties used in the stress evaluation are provided in Tables 7-2 through 7-8, below. All the material properties are excerpted from ASME Section II (Ref.A.2).


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Table 7-1 Materials of Construction

Part or Assembly Material Specification Base metal for 42” and 30” elbow SA-516 Grade 70

SA-508 Grade 1a

Base metal for 42” and 30” pipe SA-508 Grade 1a

Surge line SA-376 TP347 (Pipe) SA-403 WP347 (Elbow) SB-166 (N06690) (Instrument Nozzles)

Surge Nozzle SA-508 Grade 1a (Nozzle) SA-182 F347 (Safe End)

Charging Inlet Nozzle SA-508 Grade 1a (Nozzle) SB-166 N06690 (Safe End)

Drain Nozzle SA-508 Grade 1a (Nozzle) SA-182 F316LN (Safe End)

Spray Nozzle SA-508 Grade 1a (Nozzle) SA-182 F316LN (Safe End)

Shutdown Cooling Outlet Nozzle SA-508 Grade 1a (Nozzle) SA-182 F316LN (Safe End)

Cladding SFA-5.4 Type 308L and/or Type 309L SFA-5.9 Type 308L and/or Type 309L SFA-5.22 Type 308L and/or Type 309L (Type 309L is used for the first layer of cladding), or Ni-Cr-Fe alloy(UNS W86152 and UNS N06052 of reference 3.1.1.2(Ref.B.1) or UNS N06054 of Reference 3.1.4.1(Ref.B.1))


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Table 7-2 Material Strength for SA-516 Gr. 70

Temperature [oF] Sm [ksi] Sy [ksi] Su [ksi]

70 23.30 38.00 70.00 100 23.30 38.00 70.00 200 23.20 34.80 70.00 300 22.40 33.60 70.00 400 21.60 32.50 70.00 500 20.60 31.00 70.00 600 19.40 29.10 70.00 700 18.10 27.20 70.00

Table 7-3 Material Strength for SA-508 Gr. 1a

Temperature [oF] Sm [ksi] Sy [ksi] Su [ksi] 70 23.30 36.00 70.00 100 23.30 36.00 70.00 200 22.00 33.00 70.00 300 21.20 31.80 70.00 400 20.50 30.80 70.00 500 19.60 29.30 70.00 600 18.40 27.60 70.00 700 17.20 25.80 70.00

Table 7-4 Material Strength for SA-182 Gr. F316LN (t < 5 [in])


70 20.00 30.00 75.00 100 20.00 30.00 75.00 200 20.00 25.50 75.00 300 20.00 22.90 70.70 400 18.60 21.00 67.10 500 17.50 19.50 64.60 600 16.60 18.30 63.30 700 15.80 17.30 62.40


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Table 7-5 Material Strength for SA-182 Gr. F347 (t < 5 [in])


70 20.00 30.00 75.00 100 20.00 30.00 75.00 200 20.00 27.60 71.70 300 20.00 25.70 65.90 400 20.00 24.00 62.10 500 20.00 22.60 60.00 600 19.30 21.50 59.10 700 18.70 20.70 58.80

Table 7-6 Material Strength for SA-376 TP 347


Table 7-7 Material Strength for SA-403 WP 347



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Table 7-8 Material Strength for SB-166 N06690


70 23.30 35.00 85.00 100 23.30 35.00 85.00 200 23.30 31.70 85.00 300 23.30 29.80 84.00 400 23.30 28.60 82.00 500 23.30 27.90 80.80 600 23.30 27.60 80.20 700 23.30 27.50 79.80


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7.3 Loads, Load Combinations, and Transients

The loads, load combinations, and transients are defined the Design Specification (Ref.B.1). Following is the summary of those used for the PPG structural evaluations. All branch pipe lines are eliminated from the RCS model because the mass and rigidity of the piping do not significantly influence the dynamic behavior of the RCS. This dynamic decoupling is in accordance with the decoupling criteria for the seismic analysis specified in NUREG-0800, SRP 3.7.2 (Ref. A.3). a. Pressure Loads and Temperature

Table 7-9 Pressures and Temperatures

Parameter Value Design Pressure 2500 psia (2485 psig) Nominal Operating Pressure 2250 psia (2125 psig) Design Temperature (Hot & Cold Legs) 650 oF Design Temperature (Surge Line) 700 oF Normal Operating Hot Leg Temperature 615 oF Normal Operating Cold Leg Temperature 555 oF Normal Operating Surge Line Temperature

- Hot Leg End 615 oF

Normal Operating Surge Line Temperature - Pressurizer End

652.7 oF


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b. Mechanical Loads

Table 7-10 Force and Moments on Pipe Assembly P-1

Loading End or Section

Force [kips] Moment [ft*kips] Fa Fb Fx Ma Mb Mc

Dead Weight

A B C D

Normal

NOP 1

A B C D

NOP 2

A B C D

NOP 3

A B C D

NOP 4

A B C D

NOP 5

A B C D

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Table 7-10 Force and Moments on Pipe Assembly P-1(Cont’d)



Seismic(SSE)

A B C D

BLPB

A B C D

IRWST

A B C D

Figure 7-1 RC Piping Sections/End Locations and Coordinate System for Loads (P-1)

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Dead Weight A B

Normal

NOP 1 A B

NOP 2 A B

NOP 3 A B

NOP 4 A B

NOP 5 A B

Seismic(SSE) A B

BLPB A B

IRWST A B

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Dead Weight

A B C D E

Normal

NOP 1

A B C D E

NOP 2

A B C D E

NOP 3

A B C D E

NOP 4

A B C D E

NOP 5

A B C D E

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Table 7-12 Force and Moments on Pipe Assembly P-3 (Cont’d)



Seismic(SSE)

A B C D E

BLPB

A B C D E

IRWST

A B C D E


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Dead Weight A B

Normal

NOP 1 A B

NOP 2 A B

NOP 3 A B

NOP 4 A B

NOP 5 A B

Seismic(SSE) A B

BLPB A B

IRWST A B


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Dead Weight

A B C D

Normal

NOP 1

A B C D

NOP 2

A B C D

NOP 3

A B C D

NOP 4

A B C D

NOP 5

A B C D

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Table 7-14 Force and Moments on Pipe Assembly P-5 (Cont’d)



Seismic(SSE)

A B C D

BLPB

A B C D

IRWST

A B C D


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Notes)

1. a) The Force and Moments listed on Table 7-10 through 7-14 are for the reactor coolant piping subassemblies located as shown on Table 9(page 3 of 20) of Ref B.1. These tables also provide the Forces and Moments at intermediate nozzle sections.

b) Intermediate nozzle sections are intersection points of RCS main loop piping center line at nozzle locations.

2. The coordinate system and sign convention for the data provided is Local as shown in Table 9 (page 3 through 5 of 20) of Ref B.1.

3. The end identification for the forces and moments on piping subassemblies is shown on Table 9(page 3 of 20) of Ref B.1.

4. The section identification for the forces and moments of the piping assemblies at intermediate nozzle locations is provided on Table 9(page 3 of 20) of Ref B.1.

5. The seismic loadings tabulated on the following pages are combined loads accounting for the simultaneous application of three mutually perpendicular components of earthquake excitation.

6. The sign of each component of seismic, IRWST discharge, and branch line pipe break loads should be chosen such that the combination results in the most sever loading.

7. NOP 1 = Dead Weight + Thermal w/o friction at full power NOP 2 = Dead Weight with friction at start of heat up NOP 3 = Dead Weight + Thermal with friction at end of heat up NOP 4 = Dead Weight + Thermal with friction at start of cooldown NOP 5 = Dead Weight with friction at end of cooldown

8. SSE, BLPB and IRWST do not include NOP loads. 9. Unsigned Loads are + 10. Applied forces and moments of assemblies in loop 1B, 2A, and 2B are identical to those of

assemblies in loop 1A respectively except for the sign convention as follows: a) Sign conventions of assemblies P-6 through P-9 are symmetric to those of assemblies

P-2 through P-5 about global X-axis. b) Sign convention of assembly P-10 is symmetric to that of assembly P-1 about global X

and Z-axis. c) Sign conventions of assemblies P-11 through P-14 are symmetric to those of

assemblies P-2 through P-5 about global X and Z-axis. d) Sign conventions of assemblies P-15 through P-18 are symmetric to those of

assemblies P-2 through P-5 about global Z-axis.


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Table 7-15 RC Piping Nozzle Loads - Charging Inlet Nozzle

Loading Force [lbs] Moment [ft-lbs]

Fa Fb Fx Ma Mb Mc

Normal Operation

Dead Weight (DWT)

Thermal SAM

Seismic (SSE) Inertia IRWST BLPB

Notes)

1. Tabulated loads are located at the safe end of the nozzle. 2. The Seismic (SSE) loads are considered separately such as inertia and Sam effects. 3. Unsigned loads are absolute values. Their sign must be chosen either + or – to give the

most severe loading combination. Positive forces act in the direction shown, negative forces act in the opposite direction.

Figure 7-6 Charging Inlet Nozzle Load Conventions

Table 7-16 Piping Nozzle Loads - Spray Nozzle (Loop 2A)

Loading(1) Force [lbs] Moment [ft-lbs]

Fa Fb Fx Ma Mb Mc

Normal Operation

Dead Weight (DWT)

Thermal SAM


Valve Operation(2)

TS

TS


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Table 7-17 Piping Nozzle Loads - Spray Nozzle (Loop 2B)


Fa Fb Fx Ma Mb Mc

Normal Operation

Dead Weight (DWT)

Thermal SAM


Valve Operation(2)

Notes) 1. See RC Piping Nozzle Loads – Charging Inlet Nozzle (Table 9, Page 11 of Ref B.1) for

coordinate system and notes. 2. Valve Operation loads shall be combined for Level A and B conditions as follows:

Level A : NOP* + Valve Operation Level B : NOP* + [(1/2 SSE)2 + (IRWST + Valve Operation)2]1/2

* ; NOP loads means Dead weight for nozzle safe end, Dead weight and Thermal load for reinforcement region and nozzle to primary piping.

Table 7-18 Piping Nozzle Loads - Drain and Letdown Nozzle (Loop 1A)


Fa Fb Fx Ma Mb Mc

Normal Operation

Dead Weight (DWT)

Thermal SAM


TS

TS


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Table 7-19 Piping Nozzle Loads - Drain and Letdown Nozzle (Loop 1B)


Fa Fb Fx Ma Mb Mc

Normal Operation

Dead Weight (DWT)

Thermal SAM


Table 7-20 Piping Nozzle Loads - Drain and Letdown Nozzle (Loop 2A)


Fa Fb Fx Ma Mb Mc

Normal Operation

Dead Weight (DWT)

Thermal SAM


Table 7-21 Piping Nozzle Loads - Drain and Letdown Nozzle (Loop 2B)


Fa Fb Fx Ma Mb Mc

Normal Operation

Dead Weight (DWT)

Thermal SAM


Notes)

1. See RC Piping Nozzle Loads – Charging Inlet Nozzle (Table 9, Page 11 of Ref B.1) for coordinate system and notes.

2. Fb is parallel to Hot Leg. It is not parallel to Suction Leg.

TS

TS

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Figure 7-7 Drain and Letdown Nozzle Load Conventions

Table 7-22 Piping Nozzle Loads - Shutdown Cooling Outlet (P-1)


Fa Fb Fx Ma Mb Mc

Normal Operation

Dead Weight (DWT)

Thermal 1 Thermal 2 Thermal 3 Thermal 4 Thermal 5 Thermal 6 Thermal 7

SAM Seismic (SSE) Inertia

IRWST BLPB

SRTH(2)

TS


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Table 7-23 Piping Nozzle Loads - Shutdown Cooling Outlet (P-10)


Fa Fb Fx Ma Mb Mc

Normal Operation

Dead Weight (DWT)

Thermal 1 Thermal 2 Thermal 3 Thermal 4 Thermal 5 Thermal 6 Thermal 7

SAM Seismic (SSE) Inertia

IRWST BLPB

SRTH(2) Notes)

1. See RC Piping Nozzle Loads – Charging Inlet Nozzle (Table 9, Page 11 of Ref B.1) for coordinate system and notes, except that the NOP loads (i.e., Dead Weight and Thermal) are algebraic values.

2. SRTH (LTOP valve discharge thrust) loads shall be combined for Level B condition as follows;

3. Level B : NOP* + [1/2 SSE]2 + (IRWST + SRTH)2]1/2 4. * ; NOP loads mean Dead weight for nozzle safe end, Dead weight and Thermal load for

reinforcement region and nozzle to primary piping. 5. For a fatigue analysis, 180 full load cycles of the SRTH (i.e, LTOP valve discharge thrust)

loads shall be used.

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Table 7-24 Piping Nozzle Loads - Hot Leg Surge Nozzle

Loading(1) Force [kips] Moment [in-kips]

Fa Fb Fx Ma Mb Mc

Normal

Dead Weight Thermal at 653°F

Start. Flow (38°F δT)(5) Start. Flow (67°F δT)(5) Start. Flow (98°F δT)(5) Start. Flow (103°F δT)(5) Start. Flow (340°F δT)(5) SSE Inertia SSE SAMs

IRWST Inertia IRWST Anchor Motion Branch Line Pipe Break

Notes)

1. Tabulated loads are located at the safe end of the nozzle. 2. Unsigned loads are absolute values. Their sign must be chosen either + or – to give the

most sever loading combination. Positive forces act in the direction shown, negative forces act in the opposite direction.

3. Thermal loads excluding dead weight reflect the maximum effects of uniform expansion. 4. Stratified flow loads exclude dead weight. 5. See page 42 for load definition

Figure 7-8 Hot Leg Surge Nozzle Load Conventions

Plan View

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Table 7-25 Surge Line Piping Loads

Location(*)

Load Case

Piping Moments, in-kips 1 10

Ma Mb Mc Ma Mb Mc

Normal

Dead Weight

Thermal at

653°F

Start. Flow

(38°F δT)(5)

Start. Flow

(67°F δT)(5)

Start. Flow

(98°F δT)(5)

Start. Flow

(103°F δT)(5)

Start. Flow

(340°F δT)(5)

SSE Inertia

SSE SAMs

IRWST Inertia

IRWST Anchor Motion

Branch Line Pipe Break

TS


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Table 7-25 Surge Line Piping Loads (Cont’d)

Location(*)

Load Case

Piping Moments, in-kips 2 211 S1X H1Y

Ma Mb Mc Ma Mb Mc Ma Mb Mc Ma Mb Mc

Normal

Dead Weight

Thermal

at 653°F

Start. Flow

(38°F δT)(5)

Start. Flow

(67°F δT)(5)

Start. Flow

(98°F δT)(5)

Start. Flow

(103°F δT)(5)

Start. Flow

(340°F δT)(5)

SSE Inertia

SSE SAMs

IRWST Inertia

IRWST Anchor Motion

Branch Line Pipe

Break

TS


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Location(*)

Load Case

Piping Moments, in-kips 5 511 61 611


Normal

Dead Weight

Thermal

at 653°F

Start. Flow

(38°F δT)(5)

Start. Flow

(67°F δT)(5)

Start. Flow

(98°F δT)(5)

Start. Flow

(103°F δT)(5)

Start. Flow

(340°F δT)(5)

SSE Inertia

SSE SAMs

IRWST Inertia

IRWST Anchor Motion

Branch Line Pipe

Break

TS


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Location(*)

Load Case

Piping Moments, in-kips 62 622 H2Y S2Y


Normal

Dead Weight

Thermal

at 653°F

Start. Flow

(38°F δT)(5)

Start. Flow

(67°F δT)(5)

Start. Flow

(98°F δT)(5)

Start. Flow

(103°F δT)(5)

Start. Flow

(340°F δT)(5)

SSE Inertia

SSE SAMs

IRWST Inertia

IRWST Anchor Motion

Branch Line Pipe

Break

TS


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Location(*)

Load Case

Piping Moments, in-kips 71 711 72 722


Normal

Dead Weight

Thermal

at 653°F

Start. Flow

(38°F δT)(5)

Start. Flow

(67°F δT)(5)

Start. Flow

(98°F δT)(5)

Start. Flow

(103°F δT)(5)

Start. Flow

(340°F δT)(5)

SSE Inertia

SSE SAMs

IRWST Inertia

IRWST Anchor Motion

Branch Line Pipe

Break

TS


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Location(*)

Load Case

Piping Moments, in-kips S3Z H3Y 73 74


Normal

Dead Weight

Thermal

at 653°F

Start. Flow

(38°F δT)(5)

Start. Flow

(67°F δT)(5)

Start. Flow

(98°F δT)(5)

Start. Flow

(103°F δT)(5)

Start. Flow

(340°F δT)(5)

SSE Inertia

SSE SAMs

IRWST Inertia

IRWST Anchor Motion

Branch Line Pipe

Break

TS


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Location(*)

Load Case

Piping Moments, in-kips 8 811 R1X 9


Normal

Dead Weight

Thermal

at 653°F

Start. Flow

(38°F δT)(5)

Start. Flow

(67°F δT)(5)

Start. Flow

(98°F δT)(5)

Start. Flow

(103°F δT)(5)

Start. Flow

(340°F δT)(5)

SSE Inertia

SSE SAMs

IRWST Inertia

IRWST Anchor Motion

Branch Line Pipe

Break

TS


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Location(*)

Load Case

Piping Moments, in-kips 911

Ma Mb Mc

Normal

Dead Weight Thermal at 653°F

Start. Flow (38°F δT)(5) Start. Flow (67°F δT)(5) Start. Flow (98°F δT)(5) Start. Flow (103°F δT)(5) Start. Flow (340°F δT)(5) SSE Inertia SSE SAMs

IRWST Inertia IRWST Anchor Motion Branch Line Pipe Break

Notes)

1. Tabulated loads are located at the safe end of the nozzle. 2. Unsigned loads are absolute values. Their sign must be chosen either + or – to give the

most severe loading combination. Positive forces act in the direction shown, negative forces act in the opposite direction.

3. Thermal loads excluding dead weight reflect the maximum effects of uniform expansion. 4. Stratified flow loads excluded dead weight. 5. Asterisk mark(*) is the location corresponding to Figure 7-11 6. See Page 11 of Figure 6 for supports location (H1Y, H2Y, H3Y, S1X, S2Y, S3Z & R1X).

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c. Notes to Surge Line Pipe Loads

1. Units are kips and in-kips. 2. Loads are provided in local coordinate systems defined on Page 43. 3. Load cases are defined as:

a) Dead Weight – Weight loads at cold shutdown condition which include the weight of the piping, water, and insulation.

b) Thermal at 653°F - Thermal normal operating condition without stratified flow. c) Strat. Flow (38°F) – Thermal stratified flow normal, upset, and faulted operating

conditions with temperature delta of 38°F. d) Strat. Flow (67°F) – Thermal stratified flow normal operating condition with

temperature delta of 67°F. e) Strat. Flow (98°F) – Thermal stratified flow condition with temperature delta of 98°F.

This case shall be used for normal, upset and faulted operating conditions except δT = 340°F during heatup and cooldown.

f) Strat. Flow (103°F) – Thermal stratified flow upset operating condition with temperature delta of 103°F.

g) Strat. Flow (340°F) – Thermal stratified flow condition with temperature delta of 340°F to be used during heatup and cooldown transients.

h) SSE – Seismic SSE condition which includes the effects of anchor and support displacements.

i) BLPB – Maximum branch line pipe break loads from all potential BLPB conditions. j) IRWST – In-Containment Refueling Water Storage discharge condition.

4. Each of the stratified flow conditions corresponds to a steady state cross-section

temperature distribution in the piping which results from the application of the fluid condition in the surge line for the event. The temperature distribution produces a section rotation which induces bending in the surge line and produces the piping moments. The temperature distribution is non-linear which also imposes local thermal stresses which shall be considered in the design of the piping.

5. Unsigned loads are +. 6. The pipe moment for the load case titled Thermal at 653°F and the Stratified cases except

the nozzle location 1 and 10 were multiplied by Ec/Eh (Cold elastic modulus/Hot elastic modulus).

7. The bending moments developed at location 1 and 10 by thermal contraction and expansion are to be multiplied by Ec/Eh, according to Para. NB-3672.5 of Ref.A,1 Instead of multiplying the moment values, the coefficients of Mi, Mi*, Mi’, were multiplied by the ratio of Ec/Eh.


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d. Local coordinate system for Surge Line Pipe Loads

Figure 7-9 Local coordinate system for Surge Line Pipe Loads (Straight element)

1. Straight element

(1) The positive “a” direction is always along the element, directed from the hot leg toward the pressurizer, the pressurizer, the positive “b” direction is up, and the positive “c” direction is according to the right hand rule.

(2) If the direction “a” is vertical, the directions “b” and “c” shall be such that the positive “b’ direction is parallel to the global “(-)x” defined on Figure 7-11.

Figure 7-10 Local coordinate system for Surge Line Pipe Loads (Elbow element)

2. Elbow element (1) At any point in an elbow element, the positive “a” direction is tangent to the curve,

directed from the hot leg toward the pressurizer, the positive “c” direction is toward the center of curve, and the positive “b” direction is according to the right hand rule.

Note: a) Point A is corresponding to locations 2, 5, 61, 62, 71, 72, 8 and 9 in Figure 7-11. b) Point B is corresponding to locations 211, 511, 611, 622, 711, 722, 811 and 911

in Figure 7-11.


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Figure 7-11 Location of Surge Line Loads

e. Transient Loads The design transients used in the structural evaluations are listed in Table 7-26 and 7-27. These transients are determined based on a 60-year plant operating period and are classified as Service Level A (Normal), Service Level B (Upset), and Service Level D (Faulted), and Test conditions. There are no design basis events which result in Service Level C (Emergency) loads as specified in the Design Specification (Ref.B.1). Figure 4 of Ref.B.1 graphically presents the pressure, temperature, and flow rate information of each transient and the transients are grouped into seven regions in the PPG as shown below.


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Group No. Locations / Parts of Steam Generator

2 - Hot Leg Nozzles - Sampling & Press. Measurement Nozzles

3 - Cold Leg Nozzles

- Spray Nozzles Letdown & Drain Nozzles

5A - Hot Leg Nozzles

5B - Surge Line Nozzles

15 - SCS Outlet Nozzles

19 - Charging Inlet Nozzle (CVCS DBE)


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Table 7-26 RCS Design Transients

Transient Description Occurrences(1)

Service Level A

(Normal)

1A 1B 2A 2B 3A 3B 3C 4A 4B 5 6 7 8 9

Test

Service Level B (Upset)

1 2 3 4 5 6

Service Level D

(Faulted)

1 2 3 4 5

Notes)

TS

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Table 7-27 CVCS Design Transients


Service Level A

(Normal)

1 2

3-1

3-2

4

5

6-1

6-2

6-3

7-1

7-2

7-3

8

9 10

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Table 7-27 CVCS Design Transients (Cont`d)


Service Level A

(Normal)

11-1

11-2

Test

Service Level B (Upset)

1 2 3 4

5

6

7

8

9

Service Level D

(Faulted)

1

2 3 4

Notes) (1) Total number of occurrences over 60 years for design purpose. (2) This transient indicates the Group 19(Charging Inlet Nozzle) of Figure 4(Ref.B.1)

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f. Load Combinations

The loading combinations included in Design, Service Level A, Level B, Level C, Level D and Test Conditions are to be combined and categorized as defined below. Additional requirements of the loading, load combination and fatigue analysis are defined on Table 10 through Table 7-14, as applicable. The resultant stresses shall be within the allowable service limits as defined in ASME Section III, NB-3220 of Ref. E1

1. Design Condition Mechanical loads as provided within Ref.B.1 shall be combined as defined in ‘A’ through ‘C’ below. A. Design pressure + dead weight (DWT) B. Design pressure + full power normal operation (NOP)(*) C. Design pressure + DWT + IRWST discharge loads (including IRWST discharge

anchor motion loads for surge line piping). (*) When required by Ref.B.1, such as at integral supports and at reinforcement regions of nozzles, use design pressure plus normal operation plus IRWST discharge loads.

2. Service Level A (Normal) Condition

Normal operation loads including dead weight as provided in Tables 9 & 10 of Ref.B.1 in conjunction with the normal transients (Table 5, Figure 4, and Section 6.5.1.5 of Ref.B.1) plus the pump vibratory excitations (Section 6.5.1.4 of Ref.B.1).

3. Service Level B (Upset) Condition Normal operation (including dead weight), SSE(3)(4) and IRWST discharge loads as provided in Tables 8 & 9 of Ref.B.1 in conjunction with the upset transients (Table 5, Figure 4, and Section 6.5.1.5 of Ref.B.1).

4. Service Level C (Emergency) Condition There are no plant design basis events which result in Service Level C loads.

5. Service Level D (Faulted) Condition(1)(2)(3) Normal operation (including dead weight), SSE, IRWST discharge and BLPB and other accident loads as provided in Tables 9 & 10 of Ref.B.1 and the faulted transients (Table 5, Figure 4, and Section 6.5.1.5 of Ref.B.1) shall be combined as defined below. A. NOP + [SSE2 + (BLPB + IRWST)2]1/2 in conjunction with the faulted transients. B. NOP + SSE in conjunction with the faulted transients.

6. Test Condition

The test loading conditions are defined per Tables 5 and Figure 4 of Ref.B.1.

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Note: (1) Service Level D loads which include the combined effects of BLPB, SSE, IRWST

discharge, faulted transients and normal operation shall be used in the design of the reactor coolant system pipe assemblies with the Service Level D service limit of ASME Section III, Appendix F of Ref.A.1

(2) The system or subsystem analysis performed to establish the loadings included in Service Level D loads is based upon elastic methods. Accordingly, elastic methods should be used in the design calculations performed to demonstrate the suitability of the reactor coolant system pipe assemblies to withstand the Level D service limit.

(3) Seismic, BLPB and IRWST discharge loads not provided by Table 9 & 10 of Ref.B.1 are defined by the loads which result from the response spectra of Figures 7,8 and 9 of Ref.B.1

(4) The following changes and additions to ASME Section III, NB-3650 are required for the elimination of OBE loads from the design basis. The equations referred below are those specified in ASME Section III, NB. a) For primary stress evaluation in ASME Section III, NB-3654.2 earthquake loads are

not required to be evaluated for consideration of Level B service Limits for Equation (9).

b) For satisfaction of primary plus secondary stress intensity range in ASME Section III, NB-3653.1, in Equation (1), Mi shall be either (1) the resultant range of all loads considering on-half the range of the safe-shutdown earthquake or (2) the resultant range of moment due to the full range of the safe-shutdown earthquake alone, whichever is greater. The use of the safe-shutdown earthquake is intended to provide a bounding design for the cumulative effects of earthquakes of a lesser magnitude and is therefore to be included in consideration of Level B Service Limits for Equation (10)

c) For satisfaction of peak stress intensity in ASME Section III, NB-3653.2 the load sets developed in ASME Section III, NB-3653.1 shall be used in calculating the peak stress intensity, Sp, and the alternating stress intensity, Salt, for evaluating the fatigue effects and cumulative damage.

d) For simplified elastic-plastic discontinuity analysis in ASME Section III, NB-3653.6 if Equation (10) cannot be satisfied for all pairs of load sets, then the alternative analysis as described in ASME Section III, NB-3653.6 shall be followed. In addition, the following condition shall be satisfied: Ssam = C2 Do (Mi

* + Mi**) / 2I < 6.0 Sm

Where: Ssam is the nominal value of seismic anchor motion stress Mi* is the same as Mi

* in Equation (12) Mi** is the same as Mi in Equation (10) except that it includes only moments due to seismic anchor motion displacements caused by a safe shutdown earthquake.


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The combined moment range (Mi* + Mi

**) shall be either (1) the resultant range of thermal expansion and thermal anchor movements plus on-half the range of the safe-shutdown earthquake anchor motion or (2) the resultant range of moment due to the full range of the safe-shutdown earthquake anchor motion alone, whichever is greater.


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8. Methodology

8.1 Thermal Analysis

The thermal information is obtained using the computer program ANSYS (Ref.A.1) which is a large scale and general purpose computer program for solution of several types of engineering problems. The ANSYS uses the wave front (or frontal) direct solution method for the system of simultaneous linear equations developed by the matrix displacement method. The ANSYS produces a nodal temperature distribution for given input lists including the nodal network descriptions, boundary conditions, and material properties. The post-processing procedure generates an equivalent linear gradient from the actual radial temperature distribution. The temperature differences along with nodes at each area of interest are output for selected transient times.

8.2 Structural Analysis

The stresses in the components are produced by the internal pressure, mechanical load, thermal transient load, and dynamic load. The pressure and thermal stresses are obtained using the ANSYS. The stresses caused by the mechanical loads are calculated by the classical equations of beam theory for cuts in the nozzle wall and by the Bijlaard Method for cuts in the nozzle (or opening)-vessel intersection. The most significant structural behavior in the nozzle (or opening)-vessel intersection is the variation of the shell membrane forces around the circumference of the nozzle. It is possible to represent this variation in terms of the membrane forces, or stresses, which have a secondary harmonic variation about the axis of the nozzle in addition to an axisymmetric component. These forces, or stresses, can then be applied to an axisymmetric finite element model which allows harmonically varying loads. Primary stress is evaluated for Design, Service Level B, Service Level D, and Test Conditions. Those stresses are obtained by superimposing the appropriate stress components from the pressure and mechanical loads specified for each condition, then calculating the principal stresses and stress intensities at each area to be investigated. Primary plus secondary stress evaluation is performed for Service Level A, Service Level B, and Test Conditions. Those stresses are calculated by superimposing the appropriate stress components from the pressure, mechanical load, and thermal transient loads. The thermal stresses are calculated by the ANSYS. Temperature distributions from the thermal calculation are input to the structural model for the calculation of thermal stresses. The primary plus secondary stress intensity is calculated by the procedures of NB-3222, NB-3653 or AFPOST (Ref A.1 or Ref.E.2)


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8.3 Fatigue Analysis

Total stresses are obtained by adding peak stresses to the primary plus secondary stresses. These peak stresses result from the effect of geometrical stress concentration at local structural discontinuities and from the non-linear potion of the radial (through wall) thermal gradients. Several methods are used to calculate fatigue strength reduction factors or stress concentration factors at geometrically discontinuous locations. The methods are selectively used according to the geometry of each component. The alternating stresses intensities are derived as per NB-3216 of Ref.A.1 and the cumulative fatigue usage factors are calculated by NB-3222.4 or NB-3653 of Ref.A.1.


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9. Computer Programs Used

Table 9-1 provides the computer program used in the structural evaluation.

Table 9-1 Computer Program Description No. Program Version Ref. Description

1 ANSYS 12.1 E.1 ANSYS is a general purpose finite element computer program. The elements and options used in the analysis are well-established and fully verified.

2 AFPOST 2 E.3 AFPOST is 3-dimensional structural and fatigue evaluation program in accordance with ASME Code, Section III.

3 NOZPROG 1 E.4 NOZPROG calculates the stresses due to pressure and external load in a nozzle or nozzle-vessel intersection.

9.1 AFPOST

AFPOST is a computer program for 3-dimensional structural and fatigue evaluation for pressure vessels in accordance with the requirements of the ASME Code, Section III. The program combines thermal stresses resulting from ANSYS run with stresses from other sources of loads, calculates primary plus secondary stresses, total stresses and their ranges, and performs fatigue evaluation in accordance with the procedure as described in NB-3222.4.(e) of Ref.A.1. The program can be used to evaluate the simplified elastic-plastic analysis as stipulated in NB-3228.5 of Ref.A.1 for nozzle and shell structure. This program reads the linearized stresses produced by ‘prsect’ command of ANSYS, calculates the range of primary plus secondary stress intensity, and provides a table of primary plus secondary stresses, total stresses, and cumulative fatigue usage factors.

9.2 NOZPROG

NOZPROG is a computer program which calculates stresses due to pressure and external load stresses in a nozzle or a nozzle-vessel intersection and calculates primary stresses and primary plus secondary stresses, except for thermal stresses. The load considered by the program are internal pressure, run pipe load, and external loads applied to the nozzle. The program formulates all possible combinations of the applied forces and moments (typically 64 load cases), considers each case, lists the results for the most severe case, and optionally prints all the considered sets of loads and stresses. At each cut, stresses are calculated using strength of materials formula. Pressure stresses are calculated with equations for thin cylindrical shells. Nozzle load stresses outside the limits of reinforcement are calculated by beam stress equations for a beam with a hollow circular cross-section. Nozzle load stresses in a nozzle-vessel intersection are calculated by the Bijlaard Method.


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10. Structural Evaluation Results

This section summarizes the results of the analyses

10.1 Primary Pipes and Elbows

a. Modeling and Areas of Interest

Figure 10-1 Areas of Interest in Primary Pipes and Elbows

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b. Structural Evaluation Results

Table 10-1 Structural Evaluation of Primary Pipes and Elbows

Condition Code Criteria Area of Interest(1) Calculated Allowable Ratio(2)

Design NB-3652

Level D F-1430(b)

Service Level A and

B

NB-3653.1

NB-3653.2-5

Thermal Ratchet

Notes) (1) See Figure 10-1 for the location (2) Ratio = (Calculated Stress or CUF) / (Allowable). (3) Hot Leg Allowable limit is obtained at temperature of Design 650 °F, Level D and Service

615°F. Cold Leg Allowable limit is obtained at temperature of Design 650 °F, Level D and Service 555°F.

(4) Allowable pressure is calculated in accordance with NB-3656(a)(1)

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10.2 Surge Line


Figure 10-2 Configuration of Surge Line

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Table 10-2 Design Evaluation of Surge Line

Condition Code Criteria Area of Interest(1) Calculated Allowable(3) Ratio(2)

Design NB-3652

Eq.(9)

Table 10-3 Level D Evaluation of Surge Line


Level D NB-3652 & NB-3656(b)

Eq.(9)

Table 10-4 Test Evaluation of Surge Line


Test NB-3657 & NB-3226

Notes) (1) See Figure 10-2 for the location. (2) Ratio = (Calculated Stress) / (Allowable). (3) Allowable limit is obtained at temperature of Design 700 °F, Level D 653°F and Test 400 °F.

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Table 10-5 Structural Evaluation of Surge Line


Service Level A & B

P+Q Range Homogeneous

Flow

P+Q Range Stratified Flow

Fatigue Homogeneous

Flow

Fatigue Stratified Flow

Thermal Ratchet

Notes) (1) See Figure 10-2 for the location. (2) Ratio = (Calculated Stress or CUF) / (Allowable). (3) Allowable limit is obtained at operating temperature 653 °F (4) Since the range of primary plus secondary stress intensities exceeds the allowable of 3*Sm. It is

alternatively justified in accordance with the simplified elastic-plastic analysis set forth in NB-3653.6 See Table 10-6 for the detailed evaluation.

(5) Since the value differs from the allowable limit by less than 10 percent, the contribution of each of the loading categories tis provided in Table 10-7

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Table 10-6 Simplified Elastic-Plastic Evaluation of Surge Line


Service Level A & B

NB-3653.6 Eq(12)

NB-3653.6 Eq(13)

Notes) (1) See Figure 10-2 for the location. (2) Ratio = (Calculated Stress or CUF) / (Allowable).

Table 10-7 Contribution of Each Loading of Surge Line

Area of Interest Pressure Thermal

Expansion load

Seismic load

Thermal Transient

load Total stress

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10.3 Surge Nozzle


Figure 10-3 Areas of Interest and Finite Element model in Surge Nozzle

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Table 10-8 Design Evaluation of Surge Nozzle


Design

PL

PL+Pb

Notes) (1) See Figure 10-3 for the location (2) Ratio = (Calculated Stress) / (Allowable). (3) Allowable limit is obtained at temperature of 650 °F

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Table 10-9 Level D Evaluation of Surge Nozzle


Level D

PL

PL+Pb


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Table 10-10 Test Evaluation of Surge Nozzle

Condition Code Criteria Area of Interest(1) Calculated Allowable(3)(4) Ratio(2)

Test Pm+Pb

Notes) (1) See Figure 10-3 for the location (2) Ratio = (Calculated Stress) / (Allowable). (3) Allowable limit is obtained at temperature of 400 °F (4) The stress intensity compare with “Pm” allowable value for conservatism.

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Table 10-11 Triaxial stress Evaluation of Surge Nozzle


Design

PL

PL+Pb

Test Pm+Pb

Notes) (1) See Figure 10-3 for the location (2) Ratio = (Calculated Stress) / (Allowable). (3) Allowable limit is obtained at temperature of Design 650°F and Test 400 °F

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Table 10-12 Structural Evaluation of Surge Nozzle


Service Level A and

B P+Q Range

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Table 10-12 Structural Evaluation of Surge Nozzle (Cont’d)


Service Level A and

B Fatigue

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Table 10-12 Structural Evaluation of Surge Nozzle (Cont’d)


Service Level A and

B

Thermal Ratchet

Notes) (1) See Figure 10-3 for the location (2) Ratio = (Calculated Stress or CUF) / (Allowable). (3) Allowable limit is obtained at temperature of 615°F (4) Since the value differs from the allowable limit by less than 10 percent, the contribution of each

of the loading categories tis provided in Table 10-13

Table 10-13 Contribution of Each Loading of Surge Nozzle

Area of Interest Pressure Thermal External load Total stress

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10.4 Charging Inlet Nozzle


Figure 10-4 Areas of Interest and Finite Element model in Charging Inlet Nozzle

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Table 10-14 Design Evaluation of Charging Inlet Nozzle


Design

PL

PL+Pb

Table 10-15 Level D Evaluation of Charging Inlet Nozzle


Level D

PL

PL+Pb

Notes) (1) See Figure 10-4 for the location (2) Ratio = (Calculated Stress) / (Allowable). (3) Allowable limit is obtained at temperature of Design 650°F Level D 555°F

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Table 10-16 Test Evaluation of Charging Inlet Nozzle


Test Pm+Pb

Notes) (1) See Figure 10-4 for the location (2) Ratio = (Calculated Stress) / (Allowable). (3) Allowable limit is obtained at temperature of 400°F (4) The stress intensity compare with “Pm” allowable value for conservatism.

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Table 10-17 Triaxial stress Evaluation of Charging Inlet Nozzle


Design

PL

PL+Pb

Test Pm+Pb

Notes) (1) See Figure 10-4 for the location (2) Ratio = (Calculated Stress) / (Allowable). (3) Allowable limit is obtained at temperature of Design 650°F and Test 400°F

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Table 10-18 Structural Evaluation of Charging Inlet Nozzle


Service Level A and

B P+Q Range

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Table 10-18 Structural Evaluation of Charging Inlet Nozzle (Cont’d)


Service Level A and

B Fatigue

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Table 10-18 Structural Evaluation of Charging Inlet Nozzle (Cont’d)


Service Level A and

B

Thermal Ratchet

Notes) (1) See Figure 10-4 for the location (2) Ratio = (Calculated Stress or CUF) / (Allowable). (3) Allowable limit is obtained at temperature of 650°F (4) Since the total stress ranges of some load pairs contributing this CUF exceed 2*Sy, the


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10.5 Drain Nozzle


Figure 10-5 Areas of Interest and Finite Element model in Drain Nozzle

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Table 10-19 Design Evaluation of Drain Nozzle


Design

PL(3)

PL+Pb

Notes) (1) See Figure 10-5 for the location (2) Ratio = (Calculated Stress) / (Allowable). (3) Category “PL” stress intensity compare with “Pm” allowable value for conservatism. (4) Allowable limit is obtained at temperature of 650 °F

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Table 10-20 Level D Evaluation of Drain Nozzle


Level D

PL(3)

PL+Pb

Notes) (1) See Figure 10-5 for the location (2) Ratio = (Calculated Stress) / (Allowable). (3) Allowable limit is obtained at temperature of 650 °F (4) Category “PL” stress intensity compare with “Pm” allowable value for conservatism. (5) Since the value differs from the allowable limit by less than 10 percent, the contribution of each

of the loading categories tis provided in Table 10-21

Table 10-21 Contribution of Each Loading of Drain Nozzle

Area of Interest Pressure Thermal External load Total stress

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Table 10-22 Test Evaluation of Drain Nozzle


Test

Pm

Pm+Pb


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Table 10-23 Triaxial stress Evaluation of Drain Nozzle


Design

Pm

PL+Pb


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Table 10-23 Triaxial stress Evaluation of Drain Nozzle (Cont’d)


Test

Pm

PL+Pb


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Table 10-24 Structural Evaluation of Drain Nozzle


Service Level A and

B

P+Q Range

Fatigue

Notes) (1) See Figure 10-5 for the location (2) Ratio = (Calculated Stress or CUF) / (Allowable). (3) Allowable limit is obtained at temperature of 650 °F (4) Since the total stress ranges of some load pairs contributing this CUF exceed 2*Sy, the


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Table 10-24 Structural Evaluation of Drain Nozzle(Cont`d)


Service Level A and

B

Thermal Ratchet

Notes) (1) See Figure 10-5 for the location (2) Ratio = (Calculated Stress or CUF) / (Allowable).

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10.6 Spray Nozzle


Figure 10-6 Areas of Interest and Finite Element model in Spray Nozzle

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Table 10-25 Design Evaluation of Spray Nozzle


Design

PL(3)

PL+Pb


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Table 10-26 Level D Evaluation of Spray Nozzle


Level D

PL(3)

PL+Pb


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Table 10-27 Test Evaluation of Spray Nozzle


Test

Pm

Pm+Pb


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Table 10-28 Triaxial stress Evaluation of Spray Nozzle


Design

PL(3)

PL+Pb

Notes) (1) See Figure 10-6 for the location (2) Ratio = (Calculated Stress) / (Allowable) (3) Category “PL” stress intensity compare with “Pm” allowable value for conservatism. (4) Allowable limit is obtained at temperature of 650 °F

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Table 10-28 Triaxial stress Evaluation of Spray Nozzle (Cont’d)


Test

Pm

Pm+Pb

Notes) (1) See Figure 10-6 for the location (2) Ratio = (Calculated Stress) / (Allowable) (3) Allowable limit is obtained at temperature of 400 °F

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Table 10-29 Structural Evaluation of Spray Nozzle


Service Level A and

B

P+Q Range

Fatigue

Notes) (1) See Figure 10-6 for the location (2) Ratio = (Calculated Stress or CUF) / (Allowable) (3) Allowable limit is obtained at temperature of 650 °F (4) Since the total stress ranges of some load pairs contributing this CUF exceed 2*Sy, the


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Table 10-29 Structural Evaluation of Spray Nozzle(Cont`d)


Service Level A and

B

Thermal Ratchet

Notes) (1) See Figure 10-6 for the location (2) Ratio = (Calculated Stress) / (Allowable)

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10.7 Shutdown Cooling System Outlet Nozzle


Figure 10-7 Areas of Interest and Finite Element model in SCO Nozzle

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Table 10-30 Design Evaluation of Shutdown Cooling System Outlet Nozzle


Design

PL

PL+Pb

Table 10-31 Level D Evaluation of Shutdown Cooling System Outlet Nozzle

Condition Code Criteria Area of Interest Calculated Allowable(3) Ratio

Level D

PL

PL+Pb

Notes) (1) See Figure 10-7 for the location (2) Ratio = (Calculated Stress) / (Allowable) (3) Allowable limit is obtained at temperature of Design 650 °F and Level D 615°F

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Table 10-32 Test Evaluation of Shutdown Cooling System Outlet Nozzle


Test Pm+Pb

Notes) (1) See Figure 10-7 for the location (2) Ratio = (Calculated Stress) / (Allowable). (3) Allowable limit is obtained at temperature of 400°F (4) The stress intensity compare with “Pm” allowable value for conservatism.

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Table 10-33 Triaxial stress Evaluation of Shutdown Cooling System Outlet Nozzle


Design

PL

PL+Pb

Test Pm+Pb

Notes) (1) See Figure 10-7 for the location (2) Ratio = (Calculated Stress) / (Allowable) (3) Allowable limit is obtained at temperature of 400°F

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Table 10-34 Structural Evaluation of Shutdown Cooling System Outlet Nozzle


Service Level A and

B P+Q Range

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Table 10-34 Structural Evaluation of Shutdown Cooling System Outlet Nozzle (Cont’d)


Service Level A and

B Fatigue

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Table 10-34 Structural Evaluation of Shutdown Cooling System Outlet Nozzle (Cont’d)


Service Level A and

B

Thermal Ratchet

Notes) (1) See Figure 10-7 for the location (2) Ratio = (Calculated Stress or CUF) / (Allowable) (3) Allowable limit is obtained at temperature of 615°F

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11. References

A. Codes / Standards / Regulations

1. ASME Boiler and Pressure Vessel Code, Section III, Division 1, “Rules for

Construction of Nuclear Facility Components,” The American Society of Mechanical Engineers, 2007 Edition with 2008 Addenda except the following requirements: When applying Note(1) of Figure NB-3222.1 for Level B Service Limits, the calculation of Pb stresses must include reversing dynamic loads(including inertia earthquake effects) if evaluation of these loads is required by subparagraph NB-3223(b). For Class 1 piping, the material and D0 / t requirements of subparagraph NB-3656(b) shall be met for all Service Limits when the Service Limits include reversing dynamic loads, and the alternative rules for reversing dynamic loads are used

2. ASME Boiler and Pressure Vessel Code, Section II, “Materials”, The American Society of Mechanical Engineers, 2007 Edition with 2008 Addenda.

3. NUREG-0800, Standard Review Plan, Section 3.7.2, Seismic System Analysis, Rev.4, September 2013.

B. Specifications / Contract Documents

1. 11A60-ME-DS275-00, DPL-1, Rev.4, Design Specification for Reactor Coolant Pipe

and Fittings for APR1400 DC, KEPCO E&C, June. 2015.

C. Textbooks 1. Formulas for Stress and Strain, Raymond J.Roark, Fourth Edition. 2. Designing by Photoelasticity, R.B. Heywood, Chapman and Hall, Ltd., 1952. 3. Stress Concentration Design Factors, R. E. Peterson, John Willey and Sons, Inc.,

1974. 4. Strength of Material, Parts I And II, S. Timoshenko, Third Edition, D.Van Nostrand

Company, Inc. 5. Theory of Elasticity, S. Timoshenko and J. N. Goodier. 6. Design of Piping Systems, the M. W. Kellogg Company, John Wiley & Sons, Inc., New

York, 2nd Edition, 1956. 7. Theory of Plates and Shells, S. Timoshenko and S. Woinowsky -Krieger, Mcgraw-Hill,

1940. 8. Theory of Thermal Stresses, B. A. Boley and J. H. Weiner, John Wiley & Sons, Inc.,

1960.

D. Papers 1. “The Effect of Local Flexibilities on Stresses in a Structure”, W.J.O'Donnell, WPAD-

X(CE)-170, July 1961. 2. “Local Stresses in Spherical and Cylindrical Shells due to External Loads”, by

K.R.Wichman, A.G. Hopper and J.L. Mershon, Welding Research Bulletin No. 107, July 1970.

3. "How To Determine Bending Strength in the Plastic Range", by Richard Gavalis, Machine Design, Dated July 2, 1964.

4. "Local Stresses in Cylindrical Shells due to External Loadings on Nozzles - Supplement to WRC No.107 (Revision 1)," by J.L. Mershon, K.Mokhtarian, G.V.Ranjan and E.C.R. Dabaugh, Welding Research Bulletin No.297, September 1987.


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E. Computer Programs / Manuals

1. Computer Program, ANSYS, Version 12.1, Verification Document No. DAVM121, Rev.0, December 2010.

2. Computer Program, AFPOST, Version 2, Verification Document No. ND-G-CV-027, Rev.7, October 2014.

3. Computer Program, NOZPROG, Version 1, Verification Document No. ND-G-CV-006, Rev.10, October 2014.

F. Drawings

1. N11023-190CD-1102, Rev.1, Closure Piping. 2. N11023-190CD-2081, Rev.1, Hot Leg Nozzles. 3. N11023-190CD-2802, Rev.2, Cold Leg Nozzles. 4. N11023-190CD-4101, Rev.1, Cold Leg Piping P-5. 5. N11023-190CD-4102, Rev.1, Cold Leg Piping P-9. 6. N11023-190CD-4103, Rev.1, Cold Leg Piping P-14. 7. N11023-190CD-4104, Rev.1, Cold Leg Piping P-18. 8. N11023-190CD-5801, Rev.2, Surge Line 9. N11023-190CD-6201, Rev.1, Interfaces. 10. N11023-190CD-6202, Rev.1, Interfaces. 11. N11023-190CD-6203, Rev.1, Interfaces. 12. N11023-190CD-7101, Rev.1, Hot Leg Piping P-1. 13. N11023-190CD-7102, Rev.1, Hot Leg Piping P-10. 14. N11023-190CD-7201, Rev.1, Small Nozzles.


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Appendix A

Simplified Elastic-Plastic Evaluation of Surge Line

1. Surge Line Pipe and Elbow

The fatigue usage factor at Surge Line Pipe is calculated as below with equation (11) and (14) and the fatigue curves given in figure I-9.2.1 & I-9.2.2 (curves B and C as appropriate) of Ref.A

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2. Surge Line RTD Nozzle

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3. Surge Line RTD Nozzle - Weld

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4. Surge Line Sampling Nozzle

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5. Surge Line Sampling Nozzle - Weld

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