ML18178A217

Enclosure 19 - APR1400-E-B-NR-16002-NP, Rev. 1, Evaluation of Safety Injection and Shutdown Cooling Piping Applied to the Graded Approach for the APR1400

ML18178A217
Person / Time
Site:	05200046
Issue date:	05/31/2018
From:	Korea Hydro & Nuclear Power Co, Ltd, Korea Electric Power Corp
To:	NRC/NRO/DNRL
Shared Package
ML18178A202	List: ML18178A212 ML18178A213 ML18178A214 ML18178A215 ML18178A217 ML18178A218 ML18178A220 ML18178A221 ML18178A222 ML18178A223 ML18178A224
References
MKD/NW-18-0091L APR1400-E-B-NR-16002-NP, Rev 1
Download: ML18178A217 (95)

Text

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Evaluation of Safety Injection and Shutdown Cooling Piping applied to the graded approach for the APR1400 Revision 1 Non-Proprietary May 2018 Copyright 2018 Korea Electric Power Corporation &

Korea Hydro & Nuclear Power Co., Ltd All Rights Reserved KEPCO & KHNP

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 REVISION HISTORY Revision Date Page Description July 0 All Standard Issue 2017 The descriptions of environmental fatigue ABSTRACT evaluation for DVI and SC piping subsystems NOMENCLATURE are added by the response to piping audit Pages 1, 9, 12, 4/4/2017 piping audit questions and comments 15 , 16 to be discussed with KHNP The Class 1 piping is changed to Fatigue Pages 4, 7 Evaluation to describe the sentence clearly May 1 The results of environmentally assisted fatigue 2018 analysis for DVI and SC piping subsystems are Pages 10, 11, 57, added by the response to piping audit 4/4/2017 58, 81, 82 piping audit questions and comments to be discussed with KHNP The referred documents in REFERENCE are Pages 84, 85 added for environmentally assisted fatigue analysis 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.

KEPCO & KHNP i

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 ABSTRACT This report is in response to the Question No. 03.12-2 in RAI No. 35-7955, and provides summary information on the piping analysis approach and results as well as methodology of the piping analysis, necessary to support safety determination of the Safety Injection (SI) and Shutdown Cooling (SC) piping systems. To demonstrate that the subject piping, which has been structurally evaluated based on the graded approach described in DCD Tier 2, Section 14.3.2.3, conforms to the requirements of ASME B&PV Code,Section III, mandated by 10CFR50.55a, the following information is provided:

A tabulated, quantitative summary of the calculated maximum stresses and fatigue usage factors (if applicable) with a comparison to ASME B&PV Code allowable for each Code equation.

For equipment nozzles, a tabulated quantitative summary of the calculated reaction loads compared to the specific nozzle allowable values.

For containment penetrations, quantitative maximum calculated results compared to the allowable values.

Additionally, environmental fatigue evaluation is performed by incorporating the life reduction of the metal components due to the effect of the light water reactor (LWR) environments.

Environmentally Assisted Fatigue (EAF) analysis is performed for the DVI and SC piping subsystems in accordance with Regulatory Guide 1.207.

Based on the review of summary information and component design drawings provided in this report, it is concluded that the APR1400 Safety Injection and Shutdown Cooling piping that are included in the scope of Class 1 piping system design based on the graded approach, demonstrates the conformance to the requirements of ASME B&PV Code,Section III.

KEPCO & KHNP ii

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 TABLE OF CONTENTS

1.0 INTRODUCTION

.................................................................................................. 1 1.1 Graded Approach............................................................................................................................ 1 1.2 Scope of Report .............................................................................................................................. 1 1.3 Piping Subsystem Description ........................................................................................................ 2 1.3.1 SI101 .............................................................................................................................................. 2 1.3.2 SI105 .............................................................................................................................................. 3 2.0

SUMMARY

OF RESULTS AND CONCLUSIONS .................................................... 4 2.1 Conclusions .................................................................................................................................... 4 2.2 Fatigue Evaluation of SI101 ........................................................................................................... 4 2.3 Fatigue Evaluation of SI105 ........................................................................................................... 7 2.4 Environmental Fatigue Evaluation of SI101 and SI105 .................................................................. 9 3.0 NOMENCLATURE .............................................................................................. 12 4.0 ASSUMPTIONS AND OPEN ITEMS .................................................................... 13 4.1 Assumptions ................................................................................................................................. 13 4.2 Open Items ................................................................................................................................... 13 5.0 ACCEPTANCE CRITERIA ................................................................................... 14 5.1 Primary Loads ............................................................................................................................... 14 5.2 Fatigue Design .............................................................................................................................. 15 5.3 Environmental Fatigue Design ..................................................................................................... 15 5.3.1 Environmental Fatigue Analysis Procedure .................................................................................. 16 5.3.2 Environmental Fatigue Analysis Method ...................................................................................... 16 5.4 High Energy Line Pipe Break Postulation Criteria ........................................................................ 17 6.0 LOAD AND LOAD COMBINATIONS .................................................................... 18 6.1 Design Basis for Primary Loads ................................................................................................... 18 6.1.1 Individual Mechanical Loadings .................................................................................................... 18 KEPCO & KHNP iii

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 6.1.2 Coincident Pressure Loadings ...................................................................................................... 21 6.1.3 Design Basis Combined Loadings ................................................................................................ 21 6.1.4 Functional Capability Criteria ........................................................................................................ 22 6.2 Fatigue Design Basis .................................................................................................................... 22 6.2.1 Design Basis Dynamic Loading History (DLH) ............................................................................. 22 6.2.2 Design Basis Number of Occurrences ......................................................................................... 24 6.2.3 Fatigue Design Load Combinations ............................................................................................. 25 7.0 DESIGN EVALUATION ....................................................................................... 27 7.1 PRIMARY LOAD DESIGN EVALUATION .................................................................................... 27 7.1.1 Procedure ..................................................................................................................................... 27 7.1.2 Structural Analysis ........................................................................................................................ 27 7.1.3 Primary Stress Evaluation ............................................................................................................ 27 7.2 FATIGUE DESIGN EVALUATION ................................................................................................ 36 7.2.1 Procedure Used ............................................................................................................................ 36 7.2.2 Structural Analysis ........................................................................................................................ 36 7.2.3 NB-3653 Stress Range Check and Fatigue Analysis ................................................................... 36 7.3 STRUCTURAL ANALYSIS ........................................................................................................... 36 7.3.1 Dead Weight Analysis ................................................................................................................... 36 7.3.2 Thermal Expansion Analysis ........................................................................................................ 37 7.3.3 Uniform Response Spectra Analysis ............................................................................................ 37 7.3.4 Forced Displacement Analysis ..................................................................................................... 37 7.3.5 Support Excitation Time History Analysis ..................................................................................... 38 7.3.6 Forced Vibration Time History Analysis ........................................................................................ 39 8.0 ANANYSIS RESULT ........................................................................................... 40 8.1 SI101 ............................................................................................................................................ 40 8.1.1 Subsystem Plot ............................................................................................................................. 40 8.1.2 Pipe Data Sheet ............................................................................................................................ 41 KEPCO & KHNP iv

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.1.3 Piping Stress Evaluation Results .................................................................................................. 42 8.1.4 Environmental Fatigue Evaluation Results ................................................................................... 57 8.2 SI105 ............................................................................................................................................ 59 8.2.1 Subsystem Plot ............................................................................................................................. 59 8.2.2 Pipe Data Sheet ............................................................................................................................ 60 8.2.3 Piping Stress Evaluation Results .................................................................................................. 61 8.2.4 Environmental Fatigue Evaluation Results ................................................................................... 81 9.0 COMPUTER CODE ............................................................................................. 83 9.1 PIPESTRESS 3.9.0 ...................................................................................................................... 83 9.2 ANSYS 13.0 .................................................................................................................................. 83 10.0 REFERENCE ...................................................................................................... 84 KEPCO & KHNP v

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 LIST OF TABLES Table 2.2-1 Location of Five Highest Usage Factor in SI101 ................................................................ 5 Table 2.2-2 Location of Highest Thermal Stress Ratchet in SI101 ........................................................ 6 Table 2.3-1 Location of Five Highest Usage Factor in SI105 ................................................................ 7 Table 2.3-2 Location of Highest Thermal Stress Ratchet in SI105 ........................................................ 8 Table 2.4-1 Location of Eighteen Highest Environmental Fatigue Usage Factor in SI101 .................. 10 Table 2.4-2 Location of Eighteen Highest Environmental Fatigue Usage Factor in SI105 .................. 11 Table 5.1-1 Code Allowable ................................................................................................................. 14 Table 5.2-1 Allowable Stress Range .................................................................................................... 15 Table 5.4-1 Pipe Break Location .......................................................................................................... 17 Table 6.1-1 BLPB for Subsystem SI101 .............................................................................................. 19 Table 6.1-2 BLPB for Subsystem SI105 .............................................................................................. 20 Table 6.1-3 Pressure ............................................................................................................................ 21 Table 6.1-4 Load Combination ............................................................................................................. 21 Table 6.2-1 Individual Excitation Load ................................................................................................. 23 Table 6.2-2 Load Combination for Fatigue of SI101 ............................................................................ 25 Table 6.2-3 Load Combination for Fatigue of SI105 ............................................................................ 26 Table 7.1-1 Locations of Ten Highest Primary Stress in SI101 Design Condition............................... 28 Table 7.1-2 Locations of Ten Highest Primary Stress in SI101 Service Level B Condition ................. 29 Table 7.1-3 Locations of Ten Highest Primary Stress in SI101 Service Level C Condition................. 30 Table 7.1-4 Locations of Ten Highest Primary Stress in SI101 Service Level D Condition................. 31 Table 7.1-5 Locations of Ten Highest Primary Stress in SI105 Design Condition............................... 32 Table 7.1-6 Locations of Ten Highest Primary Stress in SI105 Service Level B Condition ................. 33 Table 7.1-7 Locations of Ten Highest Primary Stress in SI105 Service Level C Condition................. 34 Table 7.1-8 Locations of Ten Highest Primary Stress in SI105 Service Level D Condition................. 35 Table 7.3-1 Load Abbreviation ............................................................................................................. 39 Table 8.1-1 Criteria Check at R/V DVI Nozzle in SI101 ....................................................................... 42 KEPCO & KHNP vi

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.1-2 Criteria Check at Safety Injection Tank Actual Nozzle in SI101 ....................................... 43 Table 8.1-3 The Stress at the Head Plate Penetration Anchor ............................................................ 44 Table 8.1-4 Usage Factor at the Branch Pipe Connection .................................................................. 45 Table 8.1-5 Primary Stress at the Branch Pipe Connection ................................................................ 46 Table 8.1-6 The Stress at the Branch Pipe Connection ....................................................................... 47 Table 8.1-7 Usage Factor at the Pipe Support Location ...................................................................... 48 Table 8.1-8 Primary Stress at the Pipe Support Location (1/2) ........................................................... 49 Table 8.1-8 Primary Stress at the Pipe Support Location (2/2) ........................................................... 50 Table 8.1-9 The Stress at the Pipe Support Location .......................................................................... 51 Table 8.1-10 Usage Factor at the Valve Location(1/2) .......................................................................... 52 Table 8.1-10 Usage Factor at the Valve Location(2/2) .......................................................................... 53 Table 8.1-11 Primary Stress at the Valve Location ................................................................................ 54 Table 8.1-12 The Stress at the Valve Location (1/2).............................................................................. 55 Table 8.1-12 The Stress at the Valve Location (2/2).............................................................................. 56 Table 8.1-13 Results of Eighteen Highest CUFen using Simplified Method .......................................... 57 Table 8.1-14 Results of fifteen Highest CUFen using Detailed Method................................................. 58 Table 8.2-1 Criteria Check at H/L Shutdown Cooling Outlet Nozzle in SI105 ..................................... 61 Table 8.2-2 The Stress at the Head Plate Penetration Anchor ............................................................ 62 Table 8.2-3 Usage Factor at Branch Pipe Connection (1/2) ................................................................ 63 Table 8.2-3 Usage Factor at Branch Pipe Connection (2/2) ................................................................ 64 Table 8.2-4 Primary Stress at Branch Pipe Connection (1/2) .............................................................. 65 Table 8.2-4 Primary Stress at Branch Pipe Connection (2/2) .............................................................. 66 Table 8.2-5 The Stress at Branch Pipe Connection ............................................................................. 67 Table 8.2-6 Usage Factor at Pipe Support Location (1/2) ................................................................... 68 Table 8.2-6 Usage Factor at Pipe Support Location (2/2) ................................................................... 69 Table 8.2-7 Primary Stress at the Pipe Support Location (1/3) ........................................................... 70 Table 8.2-7 Primary Stress at the Pipe Support Location (2/3) ........................................................... 71 KEPCO & KHNP vii

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.2-7 Primary Stress at the Pipe Support Location (3/3) ........................................................... 72 Table 8.2-8 The Stress at Pipe Support Location ................................................................................ 73 Table 8.2-9 Usage Factor at Valve Location (1/2) ............................................................................... 74 Table 8.2-9 Usage Factor at Valve Location (2/2) ............................................................................... 75 Table 8.2-10 Primary Stress at the Valve Location (1/2) ....................................................................... 76 Table 8.2-10 Primary Stress at the Valve Location (2/2) ....................................................................... 77 Table 8.2-11 The Stress at Valve Location (1/2) .................................................................................... 78 Table 8.2-11 The Stress at Valve Location (2/2) .................................................................................... 79 Table 8.2-12 Flanged Joint with High Strength bolting check in SI105.................................................. 80 Table 8.2-13 Results of Eighteen Highest CUFen using Simplified Method .......................................... 81 Table 8.2-14 Results of Eleventh Highest CUFen using Detailed Method ............................................ 82 KEPCO & KHNP viii

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 LIST OF FIGURES Figure 1.3-1 Subsystem SI101 Boundary ............................................................................................... 2 Figure 1.3-2 Subsystem SI105 Boundary ............................................................................................... 3 Figure 8.1-1 Subsystem SI101 Plot ....................................................................................................... 40 Figure 8.1-2 Subsystem SI101 Pipe Data Sheet................................................................................... 41 Figure 8.2-1 Subsystem SI105 Plot ....................................................................................................... 59 Figure 8.2-2 Subsystem SI105 Pipe Data Sheet................................................................................... 60 KEPCO & KHNP ix

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1

1.0 INTRODUCTION

1.1 Graded Approach Design of Class 1, 2 and 3 piping and components contained in the piping subsystems shall comply with the requirements of ASME Section III (Reference 10.1), subsections NB, NC and ND, respectively, for the conditions described in Section 5.0 of this report. In determination of the scope of piping system and component design for APR1400 DC, the concept of graded approach consistent with SECY-90-377 is taken as documented in DCD Tier 2, Subsection 14.3.2.3.

Piping subsystems analyzed for design certification are selected based on the safety significance. Piping subsystem for one SI piping with DVI (Direct Vessel Injection) and another for SC piping are selected as the representative Class 1 piping subsystems for the RCS (Reactor Coolant System) branch lines, based on the pipe size. The other lines are smaller in size and have no significant impact to RCS integrity. Out of the four direct vessel injection lines and the two shutdown cooling lines, which have symmetric arrangements, only one line for each system is analyzed as a representative case. This report summarizes the analysis results for RCS branch piping comprised of Class 1 and 2 piping based on the graded approach.

1.2 Scope of Report The scope of this report consists of the documentation of Code (NB/NC-3650) compliance of the Class 1 and 2 piping components identified on the analytical drawings for the two representative piping subsystems, namely, SI101 and SI105 including fatigue analysis of Class 1 piping components for which usage factors are calculated using S-N curve provided in ASME Boiler and Pressure Vessel Code (Reference 10.1). Also, environmental fatigue analysis is performed using new S-N curve based on NUREG/CR-6909 (Reference 10.6) in accordance with USNRC Regulatory Guide 1.207 (Reference 10.7). Boundaries for subsystems SI101 and SI105 are described in Figure 1.3-1 and 1.3-2, respectively.

KEPCO & KHNP 1

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 1.3 Piping Subsystem Description 1.3.1 SI101 The subject piping subsystem is routed from Reactor Vessel DVI nozzle to containment shell penetration . It also branches off to Safety Injection Tank Nozzle. TS Figure 1.3-1 Subsystem SI101 Boundary KEPCO & KHNP 2

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 1.3.2 SI105 This subject piping subsystem consists of the suction line of shutdown cooling system and the hot leg injection line of safety injection system. This subsystem is routed from the shutdown cooling system outlet nozzle on hot leg of reactor coolant system to containment shell penetrations.

TS Figure 1.3-2 Subsystem SI105 Boundary KEPCO & KHNP 3

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 2.0

SUMMARY

OF RESULTS AND CONCLUSIONS 2.1 Conclusions In this report, summary information on the piping analysis approach and results as well as methodology necessary to support safety determination of the Safety Injection (SI) and Shutdown Cooling (SC) piping are provided.

Based on the information provided in this report, it is concluded that the APR1400 SI and SC piping comprised of Class 1 and 2 piping and included in the scope of Class 1 piping system and component design, demonstrates the conformance to the requirements of ASME B&PV Code,Section III, mandated by 10CFR50.55a, based on the graded approach.

2.2 Fatigue Evaluation of SI101 The NB-3653 stress intensity ranges and usage factors calculated at the most highly stressed locations in the subsystem SI101 are listed in Table 2.2-1. The design of this subsystem meets all stress limitations specified in paragraphs NB-3653 and NB-3654. For all pairs of load sets, thermal stress ratchet is evaluated based on NB-3653.7 or NB-3222.5. The highest data points of thermal stress ratchet are listed in Table 2.2-2.

KEPCO & KHNP 4

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 TS Table 2.2-1 Location of Five Highest Usage Factor in SI101 KEPCO & KHNP 5

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 2.2-2 Location of Highest Thermal Stress Ratchet in SI101 TS KEPCO & KHNP 6

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 2.3 Fatigue Evaluation of SI105 The NB-3653 stress intensity ranges and usage factors calculated at the most highly stressed locations in the subsystem SI105 are listed in Table 2.3-1. The design of this subsystem meets all stress limitations specified in paragraphs NB-3653 and NB-3654. For all pairs of load sets, thermal stress ratchet is evaluated based on NB-3653.7 or NB-3222.5. The highest data points of thermal stress ratchet are listed in Table 2.3-2 Table 2.3-1 Location of Five Highest Usage Factor in SI105 TS KEPCO & KHNP 7

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 2.3-2 Location of Highest Thermal Stress Ratchet in SI105 TS KEPCO & KHNP 8

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 2.4 Environmental Fatigue Evaluation of SI101 and SI105 Environmentally assisted fatigue evaluation has been performed for DVI and SC piping subsystems in accordance with the requirements of Regulatory Guide 1.207. Piping locations where CUFs exceed 1.0 using simplified method are further evaluated using detailed method.

The eighteen highest EAF analysis results of DVI and SC piping subsystems are provided in Tables 2.4-1 and 2.4-2.

KEPCO & KHNP 9

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 2.4-1 Location of Eighteen Highest Environmental Fatigue Usage Factor in SI101 TS KEPCO & KHNP 10

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 TS Table 2.4-2 Location of Eighteen Highest Environmental Fatigue Usage Factor in SI105 KEPCO & KHNP 11

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 3.0 NOMENCLATURE DVI Direct Vessel Injection SI Safety Injection SC Shutdown Cooling Coefficient of thermal expansion C1,C2,C3 Secondary stress indices E Modulus of elasticity of the material K1,K2,K3 Local stress indices ni Number of cycles of load set Ni Allowable number of stress cycles Poissons ratio Sp Peak stress intensity T1 Absolute value of the range of the temperature difference between the temperature of the outside T0 and the temperature of the inside surface T1 of the piping product assuming moment generating equivalent linear temperature distribution.

T2 Absolute valve of the range for that portion of the nonlinear thermal gradient through the wall thickness not included in T1.

Sm Allowable stress intensity Sy Yield strength Pm General primary membrane stress intensity y' Maximum allowable range of thermal stress computed on an elastic basis divided by the yield strength Sn Primary plus secondary stress intensity Se Nominal value of expansion stress Fen Environmental fatigue correction factor Strain Strain rate

' Transformed strain rate DO Dissolved oxygen contents of coolant water O' Transformed dissolved oxygen T' Transformed temperature CUFen Cumulative usage factor in LWR environment KEPCO & KHNP 12

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 4.0 ASSUMPTIONS AND OPEN ITEMS 4.1 Assumptions The vendor information in this report is assumed based on the reference plant.

4.2 Open Items The small bore branch piping of the main line is not included in this analysis based on the decoupling criteria, which is not design in DC design stage. The small bore piping should be evaluated after the design is accomplished.

KEPCO & KHNP 13

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 5.0 ACCEPTANCE CRITERIA 5.1 Primary Loads The primary load combination definitions and acceptance criteria described in this article are used in conjunction with NB-3652 Equation 9, articles NB-3652 and NB-3654 through NB-3657.

The specified condition/service loadings are described in terms of each individual pipe element response moments and the associated coincident internal pressure.

Associated with each loading condition is an acceptance criterion that limits the Equation 9 stress intensity to condition dependent allowable values as indicated below.

Table 5.1-1 Code Allowable Source of Allowable Condition Criterion Stress Intensity NB-3652 1.5 Sm Design NB-3654 1.8 Sm and 1.5 Sy (1) Service Level B NB-3655 2.25 Sm and 1.8 Sy (1) Service Level C NB-3656 3.0 Sm and 2.0 Sy (1) Service Level D (2) 1.35 Sy NB-3657 Test 2.15 Sy - 1.2 Pm (3)

Notes : (1) Lesser of the two quantities (2) for Pm < 0.67 Sy (3) for 0.67 Sy < Pm < 0.9 Sy KEPCO & KHNP 14

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 5.2 Fatigue Design The allowable stress intensity range and usage factor acceptance criteria specified in paragraph NB-3653 are used to evaluate component designs covered by this report, for the design conditions itemized in this article.

Table 5.2-1 Allowable Stress Range Source of Requirement Acceptance Criteria

1. Sn 3.0 Sm NB-3653.1 or NB-3653.6 2. Eq. 12 (Se) 3.0 Sm and NB-3653.7 Eq. 13 3.0 Sm and T1 range ySy C4/ 0.7E (2)

NB-3222.4 (e) Cumulative Usage NB-3653.5 U 1.0 Note : (1) See applicable Code paragraphs for nomenclature.

(2) Calculated per Reference 10.1.

5.3 Environmental Fatigue Design The environmental fatigue usage factor acceptance criteria specified in USNRC regulatory guide 1.207 are used to evaluate component designs covered by this report.

The effects of reactor coolant water environments on the fatigue life of structural materials are expressed in terms of an environmental fatigue correction factor, Fen, which is defined as the ratio of fatigue life in air at room temperature (Nair,RT) to that in water at the service temperature (Nwater):

Fen = Nair,RT/Nwater For Environmentally Assisted Fatigue(EAF), usage factor in air at room temperature is calculated in accordance with ASME Section III code with the new fatigue S-N curve provided in NUREG/CR-6909, Appendix. A Figure A.3 and multiplied by Fen to determine the usage factor in the LWR environment.

The acceptance criteria is that the cumulative usage factor in the LWR environment, CUFen, shall not exceed the limit of 1.0 as following; CUFen = U1*Fen,1 + U2*Fen,2 + U3*Fen,3 + Ui*Fen,i + Un*Fen,n 1.0 KEPCO & KHNP 15

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 5.3.1 Environmental Fatigue Analysis Procedure TS 5.3.2 Environmental Fatigue Analysis Method NUREG/CR-6909 Appendix A, section A2 provides methodology for calculating the nominal environmental fatigue correction factor, Fen,nom, which is defined in Eq. A.1 of Reference 10.7.

For Austenitic Stainless Steels, Fen,nom is given by the following expression in Eq. A.9 of NUREG/CR-6909.

Fen,nom = exp(0.734- T' * '

• O')

where, T', ' and O' are transformed temperature, strain rate, and dissolved oxygen (DO) level, respectively, defined as follow:

T' = 0 T < 150°C T' = (T -150)/175 150°C T < 325°C T' = 1 T 325°C

' = 0 > 0.4%/s

' = ln( /0.4) 0.0004 0.4%/s

' = ln(0.0004/0.4) 0.0004%/s O' = 0.281 All DO Levels KEPCO & KHNP 16

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 5.4 High Energy Line Pipe Break Postulation Criteria In addition to the ASME Section III Code criteria described above, the portions of the subsystem designated as High Energy Lines requiring break postulation per Reference 10.10 are designed using the acceptance criteria specified below.

Table 5.4-1 Pipe Break Location Source of Requirement Acceptance Criteria

1. Sn 2.4 Sm or Reference 10.10

2. Eq. 12 (Se) 2.4 Sm and Eq. 13 2.4 Sm (2)

Cumulative Usage Reference 10.10 U 0.1 Note : (1) See applicable Code paragraphs for nomenclature.

(2) Calculated per Reference 10.1 KEPCO & KHNP 17

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 6.0 LOAD AND LOAD COMBINATIONS 6.1 Design Basis for Primary Loads 6.1.1 Individual Mechanical Loadings The individual mechanical loadings used for the primary load design of the subject piping are described below.

6.1.1.1 Normal Operation Weight Loading (WGHT)

Normal Operation Weight Loading is that loading due to the weight of the pipe metal, insulation and its contents during the subsystem normal operating service conditions, all valves and in-line equipment, and any significant support or restraint hardware that is directly supported by the pipe.

6.1.1.2 IRWST Hydro Dynamics Inertia Loading (IRWST)

IRWST Hydro Dynamics Inertia Loading is the inertia portion of the total loading induced by POSRV operation. The inertia loading is the result of excitation amplified by building response motion. (Reference 10.14 and 10.18).

6.1.1.3 Safe Shutdown Earthquake Inertia Loading (SSE)

Safe Shutdown Earthquake Inertia Loading is the inertia portion of the total loading induced by Safe Shutdown Earthquake excitation amplified by building response motion (Description in Reference 10.11 and 10.14).

6.1.1.4 RCS Branch Line Pipe Break Loading (BLPB)

Branch Line Pipe Break Loading is the total loading that is induced by the vibration of unbroken RCS branch line. The subject vibration is the result of excitations of reactor vessel, hot and cold legs, pressurizer and steam generator caused by a RCS branch line pipe break.

KEPCO & KHNP 18

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 TS Table 6.1-1 BLPB for Subsystem SI101 KEPCO & KHNP 19

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 TS Table 6.1-2 BLPB for Subsystem SI105 KEPCO & KHNP 20

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 6.1.2 Coincident Pressure Loadings Three coincident internal pressure loading cases are used for primary load design. These three cases are listed below. Specific descriptions concerning the combination of these pressure loading conditions with the individual primary loadings identified are contained in Article 6.1.3.

Table 6.1-3 Pressure Load Description Abbreviation Individual component design pressure or peak pressure per DPRE or PPRE Reference 10.6 Individual component peak pressure coincident with service OPRS level being considered per Reference 10.6 Individual component hydrotest pressure per Reference HPRS 10.6 6.1.3 Design Basis Combined Loadings The combined loadings described in Table 6.1-4 are used as a design basis for all NB-3650 Equation 9 and NB-3657 primary load evaluations. These conditions address all requirements specified in Reference 10.6.

TS Table 6.1-4 Load Combination Combination Condition Load Combination No.

1 Design DPRE + WGHT PPRS(2) + WGHT + IRWST for SI101 2 Service Level B PPRS(2) + WGHT + [IRWST2+FFTH2]1/2 for SI105 3 Service Level C N/A 4 (1) Service Level D PPRS(2) + WGHT + [SSE2 + IRWST2 +DBE12] 1/2 5 Test HPRS + HWGT 6 NB-3656(b)(4) TRNG + SSBD + SSHD Notes : (1) Load combination shall repeated for each one of the branch line pipe break loadings (BLPB described in article 6.1.1.4 in place of DBE1 (2) PPRS is service level dependent.

KEPCO & KHNP 21

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 6.1.4 Functional Capability Criteria These piping subsystems (or a portion of this piping subsystem) are designated as Required for Safe Shutdown per Section 902 of the system PSDS(Reference 10.6). The requirements for assurance of functional capability are provided in Section 902 of the general PSDS(Reference 10.6).

a. Piping functional capability is assured by verifying that the maximum stress in Eq.(9) of ASME B&PV Code,Section III NB/NC-3650, regardless of service level, does not exceed Service C limits.

b. Based on NUREG-1367, functional capability of a piping system is assured by meeting the present code(ASME B&PV Code,Section III NB/NC/ND-3650) Eq.(9),

Level D, stress limit of 2Sy, provided that:

• Dynamic loads are reversing. This includes loads due to earthquake and pressure wave loads(not slug-flow fluid hammer).

• Dynamic moments are calculated using an elastic response spectrum analysis with +/-15% peak broadening and not more than 5% damping.

• Steady-state(e.g., weight) stresses including non-reversing dynamic loads do not exceed 0.25 Sy.

• Do/t(pipe outer diameter divided by thickness) does not exceed 50.

• External pressure does not exceed internal pressure.

6.2 Fatigue Design Basis The definitions, loading combinations, and acceptance criteria described in this article are used as a design basis for the fatigue evaluation required by paragraphs NB-3653 and NB-3654. The design basis consists of the following sets of data:

a. A design basis Pressure-Temperature-Transient History (PTTH) for the subsystem.

b. A design basis Dynamic Loading History (DLH) for the subsystem.

c. The acceptance criteria used to evaluate the design.

6.2.1 Design Basis Dynamic Loading History (DLH)

The design basis DLH for the subsystem is a history of dynamic loading conditions that are used, in combination with the design basis PTTH, for the fatigue design of the subsystem. The design basis DLH consists of a number of loading conditions that are described in terms of each individual excitation. All loading conditions designated as ASME Code Service Levels A and B are addressed. The resulting individual piping excitation response associated with that dynamic excitation event includes both primary and secondary response components, which has its own cyclic range reversals as well.

KEPCO & KHNP 22

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 6.2.1.1 Individual Loadings The individual excitation response loading used for the fatigue evaluation of the subject piping subsystem is described in this article. The excitation consists of three independent components.

These three components are combined before use in the fatigue evaluation. They are listed in the Table below.

Table 6.2-1 Individual Excitation Load Component Classification Description Inertia Inertia loading induced by building and 1 Primary Component RCS header excitation Building Loading induced by relative movement 2 Displacement Secondary of attachments of building structure Component RCS Header Loading induced by movement of branch 3 Displacement Secondary connections to external headers Component The following individual excitation response loadings are used for the fatigue design.

(a) Safe shutdown earthquake inertia loading (SSE)

(b) Seismic anchor motion loading (SAM)

Seismic anchor motion is consisted with Safe shutdown earthquake building displacement loading (SSBD) and RCS header displacement loading (SSHD).

Safe shutdown earthquake building displacement loading is that loading induced by relative movement between the piping systems attachment points to the main building structure Safe shutdown earthquake RCS header displacement loading is that loading induced by dynamic movement of external pipe header that the subsystem may be attached to at its terminal points. The movement of the header is a result of safe shutdown earthquake excitation. If the subject subsystem does not terminate at a branch connection to a larger header, this loading is not applicable.

(c) IRWST hydro dynamics Inertia loading (IRWST)

KEPCO & KHNP 23

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 6.2.2 Design Basis Number of Occurrences 6.2.2.1 Earthquake Inertia and Seismic Anchor Motion Loading Two SSE events with 10 maximum stress cycles per event (20 full cycles) are considered (Reference 10.8).

Alternatively, equivalent number of SSE fractional earthquake cycles to that of 20 full SSE cycles may be used (but with an amplitude not less than one-third of the maximum SSE amplitude) as following (Reference 10.8). A total of 120 cycles (12 events with 10 cycles) for 1/2 SSE which are equivalent of 20 maximum stress cycles 6.2.2.2 IRWST Hydro Dynamics Inertia Loading 2010 IRWST events (Service level A and B) are occurred during the life of plant (Reference 10.6). And 10 cycles per event are assumed. Therefore, 20100 cycles are considered.

6.2.2.3 Fluid Force Time History Loading The Fluid Force Time History Loading is induced by the hydrodynamic loading due to the LTOP valve actuation in subsystem SI105. Fluid Force Time History Analysis is performed in accordance with Reference 10.19.

Not applicable for the subsystem SI101 KEPCO & KHNP 24

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 6.2.3 Fatigue Design Load Combinations The loading combinations identified in the table below are used for fatigue design of the subsystem using the NB-3653 design rules.

Table 6.2-2 Load Combination for Fatigue of SI101 TS KEPCO & KHNP 25

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 6.2-3 Load Combination for Fatigue of SI105 TS KEPCO & KHNP 26

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 7.0 DESIGN EVALUATION 7.1 PRIMARY LOAD DESIGN EVALUATION 7.1.1 Procedure A primary load evaluation of all piping products, used in the design of this subsystem, is performed in accordance with the design rules specified in Articles NB-3652, NB-3654, NB-3655, NB-3656 and NB-3657. The design basis and acceptance criteria itemized in Section 5.0 of this report are used as a basis for the calculations. The evaluation is performed using the following procedure.

7.1.2 Structural Analysis A structural analysis of the subsystem is performed for each one of the individual mechanical loadings identified in Reference 10.6. These calculations result in a set of internal loadings (Bending Moments) for each individual mechanical load. The procedures used to perform the structural analyses are described in Section 5.0 of this report.

7.1.3 Primary Stress Evaluation Using the bending moments produced in Section 5.1, NB-3650 Equation 9 and NB-3657 stress intensity values are calculated for each of the design basis loading conditions specified in Reference 10.6. These values are then reviewed against specified acceptance criteria (Section 2.1).

KEPCO & KHNP 27

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 7.1-1 Locations of Ten Highest Primary Stress in SI101 Design Condition TS KEPCO & KHNP 28

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 7.1-2 Locations of Ten Highest Primary Stress in SI101 Service Level B Condition TS KEPCO & KHNP 29

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 7.1-3 Locations of Ten Highest Primary Stress in SI101 Service Level C Condition TS KEPCO & KHNP 30

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 7.1-4 Locations of Ten Highest Primary Stress in SI101 Service Level D Condition TS KEPCO & KHNP 31

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 7.1-5 Locations of Ten Highest Primary Stress in SI105 Design Condition TS KEPCO & KHNP 32

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 7.1-6 Locations of Ten Highest Primary Stress in SI105 Service Level B Condition TS KEPCO & KHNP 33

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 7.1-7 Locations of Ten Highest Primary Stress in SI105 Service Level C Condition TS KEPCO & KHNP 34

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 7.1-8 Locations of Ten Highest Primary Stress in SI105 Service Level D Condition TS KEPCO & KHNP 35

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 7.2 FATIGUE DESIGN EVALUATION 7.2.1 Procedure Used A fatigue design evaluation of all piping products used in the design of this subsystem is performed in accordance with the design rules specified in paragraphs NB-3653 and NB-3654.

7.2.2 Structural Analysis A structural thermal expansion analysis is performed for the thermal expansion modes. A dynamic structural analysis and static forced displacement analysis, as appropriate, are performed for each individual excitation loading. These calculations produce the internal bending moments required for NB-3653 stress intensity range calculations.

7.2.3 NB-3653 Stress Range Check and Fatigue Analysis The thermal transient stress, along with structural stress data described above, the loading combination definitions and the acceptance criteria described in Section 5.0 and 6.0 are used to perform all design calculations required by paragraphs NB-3653 and NB-3654 for the subsystem. The procedures specified in Reference 10.1 are used to perform the calculations.

The calculations for standard piping products are performed using the PIPESTRESS computer program (Reference 10.7).

7.3 STRUCTURAL ANALYSIS A structural analysis of the subsystem is performed for each one of the individual static dead weight, thermal expansion and dynamic excitation loadings identified in Sections 6.0 of this report. The analyses are performed to determine the response bending moments for use in Code calculations, and to calculate interface loadings that are used for the design of components that interface with this subsystem. Table 7.3-1 contains a listing of those loadings and the procedures used to analyze them. The procedures used are described below. All structural analyses calculations are performed using the PIPESTRESS computer program (Reference 10.7).

7.3.1 Dead Weight Analysis To determine the subsystem response to its dead weight loading, the entire subsystem, with its suspension system (Constant and Rigid Hangers and Rigid Restraints), is modeled as connected finite beam elements and analyzed using the stiffness matrix frontal solution method.

The following weight loadings are accounted for :

a. The weight of the pipe and its fluid contents.

b. Insulation weight.

c. The weight of all valves, fittings and the fluid contents.

d. The weight of any in-line equipment and its fluid contents.

e. Significant restraint hardware weight directly supported by the pipe.

KEPCO & KHNP 36

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 7.3.2 Thermal Expansion Analysis To determine the effects of thermal expansion loading, the entire subsystem, with its restraint system (Rigid Hangers and Rigid Restraints) is modeled as connected finite beam elements and analyzed using the stiffness matrix frontal solution method. Consistent thermal forces, based on the temperature distribution within the model are calculated and applied to the model. The following effects are taken into account for each operating mode analyzed.

a. Thermal expansion growth of all piping assemblies based on the temperature distribution of the subsystem associated with the operating mode being analyzed and Code material coefficients of thermal expansion and the elastic modulus, ASME Section II Part D, 2007 Edition with 2008 Addenda.

b. The thermal expansion displacements and rotations of the piping system's anchors that are associated with the operating mode being analyzed.

c. The thermal stratification loads are associated with the operating mode being analyzed.

7.3.3 Uniform Response Spectra Analysis The procedure described below is used to determine the inertia (primary) response of all base excitation dynamic loadings.

a. The entire subsystem, with its restraint system (Rigid Hangers and Rigid Restraints) is modeled as multi-degree of freedom finite beam elements.

b. Subsystem modal analysis is performed to determine the dynamic model characteristics of this subsystem.

c. The response of the subsystem to each one of three mutually perpendicular excitations are calculated (North-South, East-West, Up-Down). The three excitations are constructed by enveloping the individual response spectra associated with all points of attachment to the building structure. The response of the system to the three directional excitations is combined using the Square Root of the Sum of the Squares (SRSS) (Reference 10.16) to determine the final design response associated with the loading.

d. The responses of the individual modes are combined using the Der Kiureghian Method (Reference 10.16). Rigid modes are combined using the Left out force method. The resultant response due to the flexible and rigid modes is calculated by using the Absolute Sum method 7.3.4 Forced Displacement Analysis 7.3.4.1 RCS Header Displacement Analysis KEPCO & KHNP 37

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 The procedure described below is used to determine the header displacement (Secondary) effects of the SSE base excitation dynamic loadings,

a. The entire subsystem, with its restraint system (Rigid Hangers and Rigid Restraints) is modeled as connected finite beam elements.

b. Six static forced displacement analyses are performed for each header connection.

Each analysis determines the effects of forcing the displacement amplitude along one of the six degrees of freedom at the header connection.

c. The results of the individual analyses (for each degree of freedom amplitude) are combined using the Square Root of the Sum of the Squares Method to determine the final design response.

7.3.4.2 Building Displacement Analysis The procedure described below is used to determine the building displacement (secondary) effects of the SSE base excitation dynamic loadings.

a. The entire subsystem, with its restraint system (Rigid Hangers and Rigid Restraints) is modeled as connected finite beam elements.

b. A static forced displacement analysis is performed for each restrained degree of freedom. Each analysis determines the effect of forcing the maximum displacement amplitude regardless of time, along one of the restrained degree of freedom at each restrained node point.

c. The results of the individual analyses (for each restrained degree freedom amplitude) are combined using the Square Root of the Squares Method to determine the design response.

7.3.5 Support Excitation Time History Analysis The procedure described below is used to analyze the subsystem for each RCS branch line pipe break loading case. Both the primary and secondary components of the loading are accounted for in the calculations.

a. The entire subsystem, with its restraint system (Rigid Hangers and Restraints) is modeled as multi-degree of freedom finite beam elements.

b. Unique displacement-time histories due to RCS branch line pipe break are assigned as boundary conditions at each unbroken RCS branch nozzle modeled as an anchor in the subsystem.

c. The response of the piping system resulting from the excitation is calculated based KEPCO & KHNP 38

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 on modal super position techniques for time dependent excitations. The 4% critical damping per Regulatory Guide 1.61, Rev.1 is used for the calculations described in Reference 10.4.

7.3.6 Forced Vibration Time History Analysis The procedure described below is used to analyze the subsystem for LTOP valve transient loading case during operation.

Both the primary and secondary components of the loading are accounted for in the calculation.

a. The entire subsystem, with its restraint system (Rigid Hangers and Restraints) is modeled as multi-degree of freedom finite beam elements.

b. Force-time histories resulted from RELAP analysis is applied on each pipe segment along the discharge flow path.

c. The response of the piping system resulting from the excitation is calculated based on direct integration method with proportional damping for time dependent excitations.

Table 7.3-1 Load Abbreviation Article Load Description Describing Abbreviation Procedure 1 WGHT Dead Weight 7.3.1 2 TH Thermal Expansion 7.3.2 3 IRWST POSRV Operation Inertia Loading 7.3.3 SSE Header Displacement Loadings and Relative 4 SAM 7.3.4.

Building Displacement Loadings 5 SSE SSE Inertia Loading 7.3.3 RCS Branch Line Pipe Break Loadings 6 BLPB 7.3.5 (See Table 6.1-1 and 6.1-2)

LTOP Valve Actuation Transient Loading for 7 FFTH 7.3.6 Subsystem SI105 KEPCO & KHNP 39

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.0 ANANYSIS RESULT 8.1 SI101 8.1.1 Subsystem Plot TS Figure 8.1-1 Subsystem SI101 Plot KEPCO & KHNP 40

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.1.2 Pipe Data Sheet TS Figure 8.1-2 Subsystem SI101 Pipe Data Sheet KEPCO & KHNP 41

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.1.3 Piping Stress Evaluation Results 8.1.3.1 Nozzle Load The purpose of this evaluation is to check the loads at safe-end of the reactor vessel DVI nozzle and safety injection tank actual nozzle against maximum nozzle load criteria.

8.1.3.1.1 R/V DVI Nozzle Load Check (Class 1 Piping)

TS Table 8.1-1 Criteria Check at R/V DVI Nozzle in SI101 Based on the above evaluation, it can be concluded that loads on the reactor vessel DVI nozzle safe ends in Subsystem 1SI101 are acceptable.

KEPCO & KHNP 42

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.1.3.1.2 Safety Injection Tank Actual Loads Check (Class 2 Piping)

TS Table 8.1-2 Criteria Check at Safety Injection Tank Actual Nozzle in SI101 Based on the above evaluation, it can be concluded that loads on the Safety Injection Tank Nozzle in Subsystem 1SI101 are acceptable.

KEPCO & KHNP 43

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.1.3.2 Head Plate Penetration Anchor (Class 2 Piping)

The stresses at the head plate penetration anchor are listed in Table 8.1-3. The stress for each Code equation is tabulated below. The stresses at the head plate penetration anchor meet all stress limitations specified in paragraphs NC-3650.

Table 8.1-3 The Stress at the Head Plate Penetration Anchor TS KEPCO & KHNP 44

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.1.3.3 Branch Pipe Connection For the Class 1 piping, the NB-3653 stress intensity ranges and usage factors calculated at the branch pipe connection are listed in Table 8.1-4. The stress intensity ranges and usage factors calculated at the branch pipe connection meets all stress limitations specified in paragraphs NB-3653, NB-3654 and NB-3656(b)(4).

Table 8.1-4 Usage Factor at the Branch Pipe Connection TS KEPCO & KHNP 45

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 1 piping, the primary stresses at the branch pipe connection are listed in Table 8.1-5. The primary stresses calculated at the branch pipe connection meets all stress limitations specified in NB-3652 Equation 9, articles NB-3652 and NB-3654 through NB-3657.

Table 8.1-5 Primary Stress at the Branch Pipe Connection TS KEPCO & KHNP 46

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 2 piping, the stresses at the branch pipe connection are listed in Table 8.1-6. the stresses at the branch pipe connection meet all stress limitations specified in paragraphs NC-3650.

Table 8.1-6 The Stress at the Branch Pipe Connection TS KEPCO & KHNP 47

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.1.3.4 Pipe Support For the Class 1 piping, the NB-3653 stress intensity ranges and usage factors calculated at the pipe support location are listed in Table 8.1-7. The stress intensity ranges and usage factors calculated at the pipe support location meets all stress limitations specified in paragraphs NB-3653, NB-3654 and NB-3656(b)(4).

Table 8.1-7 Usage Factor at the Pipe Support Location TS KEPCO & KHNP 48

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 1 piping, the primary stresses calculated at the pipe support location are listed in Table 8.1-8. The primary stresses calculated at the pipe support location meets all stress limitations specified in NB-3652 Equation 9, articles NB-3652 and NB-3654 through NB-3657.

TS Table 8.1-8 Primary Stress at the Pipe Support Location (1/2)

KEPCO & KHNP 49

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 TS Table 8.1-8 Primary Stress at the Pipe Support Location (2/2)

KEPCO & KHNP 50

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 2 piping, the stresses at the pipe support location are listed in Table 8.1-9. The stresses calculated at the pipe support location meet all stress limitations specified in paragraphs NC-3650.

TS Table 8.1-9 The Stress at the Pipe Support Location KEPCO & KHNP 51

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.1.3.5 Valve For the Class 1 piping, the NB-3653 stress intensity ranges and usage factors calculated at the valve location are listed in Table 8.1-10. The stress intensity ranges and usage factors calculated at the valve location meets all stress limitations specified in paragraphs NB-3653, NB-3654 and NB-3656(b)(4).

TS Table 8.1-10 Usage Factor at the Valve Location(1/2)

KEPCO & KHNP 52

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.1-10 Usage Factor at the Valve Location(2/2) TS KEPCO & KHNP 53

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 1 piping, the primary stresses calculated at the valve location are listed in Table 8.1-11. The primary stresses calculated at the valve location meets all stress limitations specified in NB-3652 Equation 9, articles NB-3652 and NB-3654 through NB-3657.

TS Table 8.1-11 Primary Stress at the Valve Location KEPCO & KHNP 54

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 2 piping, the stresses at the valve location are listed in Table 8.1-12. The stresses calculated at the valve location meet all stress limitations specified in paragraphs NC-3650.

Table 8.1-12 The Stress at the Valve Location (1/2) TS KEPCO & KHNP 55

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.1-12 The Stress at the Valve Location (2/2) TS 8.1.3.6 Flanged Connection There is no flanged connection in this piping subsystem.

KEPCO & KHNP 56

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.1.4 Environmental Fatigue Evaluation Results Table 8.1-13 shows the results of eighteen highest CUFen using simplified method in DVI piping subsystem. And the data points where CUFen using simplified method exceed 1.0 are further evaluated using detailed method. The EAF analysis results using detailed method. Table 8.1-14 shows the results of fifteen highest CUFen using detailed method in DVI piping system.

Table 8.1-13 Results of Eighteen Highest CUFen using Simplified Method TS KEPCO & KHNP 57

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.1-14 Results of fifteen Highest CUFen using Detailed Method TS KEPCO & KHNP 58

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.2 SI105 8.2.1 Subsystem Plot TS Figure 8.2-1 Subsystem SI105 Plot KEPCO & KHNP 59

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.2.2 Pipe Data Sheet TS Figure 8.2-2 Subsystem SI105 Pipe Data Sheet KEPCO & KHNP 60

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.2.3 Piping Stress Evaluation Results 8.2.3.1 Nozzle Load The purpose of this evaluation is to check the loads at safe-end of the shutdown cooling outlet nozzle against maximum nozzle load criteria.

8.2.3.1.1 H/L Shutdown Cooling Outlet Nozzle Load Check Table 8.2-1 Criteria Check at H/L Shutdown Cooling Outlet Nozzle in SI105 TS 8.2.3.1.2 Conclusion Based on the above evaluation, it can be concluded that loads on the shutdown cooling outlet nozzle safe ends in Subsystem 1SI105 are acceptable.

KEPCO & KHNP 61

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.2.3.2 Head Plate Penetration Anchor (Class 2 Piping)

The stresses at the head plate penetration anchor are listed in Table 8.2-2. The stresses at the head plate penetration anchor meet all stress limitations specified in paragraphs NC-3650.

TS Table 8.2-2 The Stress at the Head Plate Penetration Anchor KEPCO & KHNP 62

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.2.3.3 Branch Pipe Connection For the Class 1 piping, the NB-3653 stress intensity ranges and usage factors calculated at the branch pipe connection are listed in Table 8.2-3. The design of the branch pipe connection meets all stress limitations specified in paragraphs NB-3653, NB-3654 and NB-3656(b)(4).

TS Table 8.2-3 Usage Factor at Branch Pipe Connection (1/2)

KEPCO & KHNP 63

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.2-3 Usage Factor at Branch Pipe Connection (2/2) TS KEPCO & KHNP 64

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 1 piping, the primary stresses calculated at the branch pipe connection are listed in Table 8.2-4. The primary stresses calculated at the branch pipe connection meets all stress limitations specified in NB-3652 Equation 9, articles NB-3652 and NB-3654 through NB-3657.

TS Table 8.2-4 Primary Stress at Branch Pipe Connection (1/2)

KEPCO & KHNP 65

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.2-4 Primary Stress at Branch Pipe Connection (2/2) TS KEPCO & KHNP 66

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 2 piping, the stresses at the branch pipe connection are listed in Table 8.2-5. the stresses at the branch pipe connection meet all stress limitations specified in paragraphs NC-3650.

TS Table 8.2-5 The Stress at Branch Pipe Connection KEPCO & KHNP 67

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.2.3.4 Pipe Support For the Class 1 piping, the NB-3653 stress intensity ranges and usage factors calculated at the pipe support location are listed in Table 8.2-6. The stress intensity ranges and usage factors calculated at the pipe support location meets all stress limitations specified in paragraphs NB-3653, NB-3654 and NB-3656(b)(4).

TS Table 8.2-6 Usage Factor at Pipe Support Location (1/2)

KEPCO & KHNP 68

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.2-6 Usage Factor at Pipe Support Location (2/2) TS KEPCO & KHNP 69

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 1 piping, the primary stresses calculated at the pipe support location are listed in Table 8.2-7. The primary stresses calculated at the pipe support location meets all stress limitations specified in NB-3652 Equation 9, articles NB-3652 and NB-3654 through NB-3657.

TS Table 8.2-7 Primary Stress at the Pipe Support Location (1/3)

KEPCO & KHNP 70

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.2-7 Primary Stress at the Pipe Support Location (2/3) TS KEPCO & KHNP 71

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.2-7 Primary Stress at the Pipe Support Location (3/3) TS KEPCO & KHNP 72

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 2 piping, the stresses at the pipe support location are listed in Table 8.2-8. The stresses calculated at the pipe support location meet all stress limitations specified in paragraphs NC-3650.

TS Table 8.2-8 The Stress at Pipe Support Location KEPCO & KHNP 73

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.2.3.5 Valve For the Class 1 piping, the NB-3653 stress intensity ranges and usage factors calculated at the valve location are listed in Table 8.2-9. The stress intensity ranges and usage factors calculated at the valve location meets all stress limitations specified in paragraphs NB-3653 and NB-3654.

TS Table 8.2-9 Usage Factor at Valve Location (1/2)

KEPCO & KHNP 74

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.2-9 Usage Factor at Valve Location (2/2) TS KEPCO & KHNP 75

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 1 piping, the primary stresses calculated at the valve location are listed in Table 8.2-10. The primary stresses calculated at the valve location meets all stress limitations specified in NB-3652 Equation 9, articles NB-3652 and NB-3654 through NB-3657.

TS Table 8.2-10 Primary Stress at the Valve Location (1/2)

KEPCO & KHNP 76

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.2-10 Primary Stress at the Valve Location (2/2) TS KEPCO & KHNP 77

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 For the Class 2 piping, the stresses at the valve location are listed in Table 8.2-11. The stresses calculated at the valve location meet all stress limitations specified in paragraphs NC-3650.

TS Table 8.2-11 The Stress at Valve Location (1/2)

KEPCO & KHNP 78

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.2-11 The Stress at Valve Location (2/2) TS KEPCO & KHNP 79

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.2.3.6 Flanged Connection The purpose of this evaluation is to check flanged joints with strength bolting moments with respect to the allowables.

8.2.3.6.1 Flanged Joint with High Strength bolting check Table 8.2-12 Flanged Joint with High Strength bolting check in SI105 TS 8.2.3.6.2 Conclusion All flanged joints are per ANSI B16.5 flanges with high strength bolts. Based on the above evaluation, the loads at each flanged joints are acceptable.

KEPCO & KHNP 80

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 8.2.4 Environmental Fatigue Evaluation Results Table 8.2-13 shows the results of eighteen highest CUFen using simplified method in SC piping subsystem. And the data points where CUFen using simplified method exceed 1.0 are further evaluated using detailed method. The EAF analysis results using detailed method. Table 8.2-14 shows the results of eleventh highest CUFen using detailed method in SC piping system.

Table 8.2-13 Results of Eighteen Highest CUFen using Simplified Method TS KEPCO & KHNP 81

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 Table 8.2-14 Results of Eleventh Highest CUFen using Detailed Method TS KEPCO & KHNP 82

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 9.0 COMPUTER CODE 9.1 PIPESTRESS 3.9.0 PIPESTRESS is a piping analysis program that is applied to the static and dynamic analyses including response spectra and time-history analyses. PIPESTRESS is used for the analysis of ASME Section III, Class 1, 2, and 3 as well as ASME B31.1 and B31.3 piping systems.

9.2 ANSYS 13.0 ANSYS is a general-purpose linear and nonlinear finite element program with structural and heat transfer capabilities. Finite element analyses of reactor internal structures such as flanges and the lower support structure are performed the ANSYS to determine vertical and lateral stiffness. The program is also used to perform the static and dynamic analyses of the reactor internals to determine its structural stress responses.

KEPCO & KHNP 83

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1 10.0 REFERENCE

1. ASME B&PV Code Section III, 2007 Edition with 2008 Addenda.

2. APR1400 DC Piping Stress Reports for Subsystem 1SI101 and 1SI105 Calculation No. 1-313-P397-SI101, Rev. 7, dated 05/15/17.

Calculation No. 1-312-P397-SI105, Rev. 6, dated 04/20/17.

3. Environmentally Assisted Fatigue Evaluation Summary of Safety Injection and Shutdown Cooling Piping Applied to the Graded Approach for The APR1400, 1-310-P462-003, Rev.0, dated 08/04/16.

4. Piping and Instrumentation Diagram for SI/SC System and RC System:

Drawing No. 1-441-N105-001, Rev. 1, dated 02/09/17.

Drawing No. 1-441-N105-002, Rev. 1, dated 02/09/17.

Drawing No. 1-441-N105-003, Rev. 1, dated 02/09/17.

Drawing No. 1-441-N105-004, Rev. 1, dated 02/09/17.

Drawing No. 1-431-N105-004, Rev. 1, dated 09/30/13.

5. USNRC Regulatory Guide 1.61, Rev. 1.

6. Regulatory Guide 1.207, Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components due to the Effects of the Light-Water Reactor Environment for New Reactors, U.S Nuclear Regulatory Commission., March 2007.

7. NUREG/CR-6909, Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, U.S Nuclear Regulatory Commission., February 2007.

8. Piping Design Tables and Standard Details, 1-037-P443-001, Rev. 4, dated 08/25/15.

9. Piping System Design Specification (PSDS) :

General PSDS, 1-037-N407-001, Rev. 1, dated 12/30/14 IRWST System PSDS, 1-447-N407-001, Rev. 1, dated 02/28/12 SI/SC System PSDS, 1-441-N407-001, Rev. 2, dated 12/30/14 RC System PSDS, 1-431-N407-001, Rev. 1, dated 02/28/12

10. PIPESTRESS Computer Program / KEPCO E&C Register No. : E-P-PD-1338-3.9.0/DC, and Users Manual.

11. IEEE Std. 344-2004, Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generation Stations, Institute of Electrical and Electronics Engineers, 2005

12. Thermal and Hydraulic Responses to Design Basis Events, Reactor Coolant System, 11A60-SA-DE022-01, Rev. 1, dated 10/16/12.

Safety Injection/Shutdown Cooling System, 11A60-FS-DE022-02, Rev. 0, dated 10/16/12

13. Standard Review Plan, Section 3.6.2, Determination of Rupture Locations and Dynamic Effects Associated with the Postulated Rupture of Piping.

14. Containment BLDG Seismic Analysis Report, Report No., 1-310-C455-001, Rev. 2, dated 05/11/17.

15. Interface Requirements for RC System Branch Line Piping Nozzles, 11A60-ME-IR222-00, Rev. 1, dated 08/16/13.

KEPCO & KHNP 84

Non-Proprietary Evaluation of Safety Injection and Shutdown Cooling applied to the graded approach for the APR1400 APR1400-E-B-NR-16002-NP, Rev. 1

16. Design Criteria Manual, Doc. No. 0-037-B401-001, Rev.2, dated 05/28/13.

17. USNRC Regulatory Guide 1.92, Rev. 3.

18. Piping ISO DWG. No.

Drawing No. 1-313-P193-SI012, Rev. 2, dated 07/31/15.

Drawing No. 1-314-P193-SI012, Rev. 1, dated 07/31/15.

19. RCB Floor Response Spectra (FRS) by IRWST Hydro Dynamic Loads, DIT No. DIT-C-0003-00, dated 05/15/13.

20. Hydrodynamic Loads of SC Line due to LTOP Valve Actuation, DIT No. DIT-N-0014-01, dated 04/03/13.

KEPCO & KHNP 85