Text

Draft Rev 0 to Advanced BWR Feedwater Loop a Piping & Equipment Loads
	ML20090B216
Person / Time
Site:	05000605
Issue date:	02/29/1992
From:	Herzog M, Raju Patel; GENERAL ELECTRIC CO.
To:	;
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ML20090B190	List: ML20090B188; ML20090B208; ML20090B216;
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k (MDC-XXXXX DRF No. A00-05137

- DP AFT -

February 1992 Revision 0 ADVANCED BOILING WATER REACTOR FEEDWATER LOOP A PIPING AND EQUIPMENT LOADS Prepared by:

/ hk h

'%i-M. Heriog, Senior EncJinVer Piping Design and Analysis Approved by:

R D. Patel, Manager Piping Design and Analysis 1

l 9203030253 920224 PDR ADOCK 05000605 A

PDR

NEDC vXXXX TABLE OF CONTENTS P_iLRR 1.

INTRODUCTION gi 1.1 Purpsse J

1.2 Documentation J

1.3 Scope 2 g 2.

SUMMARY

gl 2.1 Model J

2.2 Analysis

.3 2.3 Results 2v 3.

REQUIREMENTS AND BASIS XE 3.1 Configuration 3.2 Loads 4

3.3 Load Combinations A v 4.

METhvDS X3 4.1 Equipment Modeling h3 4.2 Dynamic Analysis E3 4.3 Thermal Analysis X Ip 4.4 Computer Programs

4 5.

RESULTS IS 5.'

Design for Pressure (NB-3640)

/

5.2 Structural Analysis Ji 5.3 Piping Component Analysis J

5.4 Piping System Equipment Leads J v 6.

REFERENCES y6 TABLES i

Prope<+ies of Materials 7

2-M ateria\\

A\\\\owables -

7

-3 PiF ej Dimen sional Pro pertid.

e i

l+

- Definition oF Thermi Lynsion Cases..

9 5

NOmesc\\atue o&

Loads 10

/c NomencAatu.re. for APPedceS -

/1

'i-

NEDC-XXXXX APPENDICES TABLE OF CONTENTS f_A32 A.

Load Combinations Al Pipe

[3 A2 Snubbers g

A3 RPV Nozzles gg A4 Valve Accelerations 16 A5 Guides

[

A6 Anchors (Read TifM )

J B.

Summary of Results 81 Pipe Stresses (Highest to Lowest Stress) 19 B2 Snubber Loads gg B3 RPV Nozzle Loads 23 B4 Valve Accelerations B5 Guide Loads 19 B6 Anchor Loads (Nead Fiffnj)

Z[

Zo C.

Detailed Equipment Interface Loads Cl Snubber Loads gg C2 RPV Nozzle Loads C3 Valve Accelerations C4 Guide Loads' NO C5 Anchor Loads (Neo/ fiffinJ) 47-D.

Piping Displacements DI Pipe Displacements by Node due to Normal Operation 46 Conditions E.

Piping System Geometry El List of Global Coordinates by Node 4fl E2 Stress Isometric (Node) Diagram q

-ii-

HEDC-XXXXX 1.

INTRODUCTION 1.1 Purcose.

The purpose of this Design Report is to show compliance with Article NB-3600 of the ASME Boiler and Pressure Vessel Code Section 111 (hereinafter referred to as ASME III) of the feedwater Loop A piping configuration in the Advanced Boiling Water Reactor Power Plant.

1.2 Documentation 1.2.1 This document:

(a) provides a summary of the most severe stress intensities throughout the piping system for the design and operatli g-Methods conditions defined in the Design Criteria and Analysis Pencadere r Document (Reference 1); (b) shows that all pipe and fittings in the piping system satisfy the pressure design requirements of Article NB 3600 of ASME III for the conditions specified it, the Design Specification; (c) summarizes the loads acting on tht. component supports, the vessel nozzle, feedwater penetration, and all pipe mounted equipment; and (d) compares the total loading on equipment to the allowable loads, where applicable. The detailed supporting computer output and calculations are contained in internal GE Design Record Files (DRF).

1.3 Scope.

This Design Report covers only the Feedwacer Loop A piping and the welds used for attaching this piping to the Reactor P essure Vessel (RPV),

pipe suspension, feedwater pipe penetration and pipe mounted equipment.

1.3.1 The feedwater piping consists of two loops designated as Loop A and Loop B.

These two loops are symmetrical.

Only !.oop A was analyzed and therefore, only Loop A analysis results are presented in this Design Report.

2.

SUMMARY

2.1 Model.

The mathematical model of the piping system used in the analysis includes all of the feedwater loop piping, the feedwater valves and the suspension system for the piping system. All other lines such as sample lines and instrument lines are too small to affect the feedwater piping and were not included in the piping model.

2.2 Anal ysi s.

GE's proprietary computer program, PISYS, was used to calculate the response of the piping system to all of the static and dynamic loads defined in the Design Criteria and Analysis Methods Document.

The output from the PISYS program was evaluated by another GE proprietary computer program, ANS17, tc solve the stress intensity equations of ASME III Subarticle NB-3650 and to calculate combined loads on all equipment mounted on or interfacing with the piping.

2.3 Results 2.3.1 ASME Ill Code Comoliance. All of the piping satisfies the requirements of Article NB-3600 of ASME III. A summary of the results obtained by solution of the Subarticle NB-3650 equations for all significant joints in the piping system is contcined in Appendix B.

1

3 MEDC XXXXX 2.3.2 Desian Specifi'.ation Comoliance.

This report doc cents compliance with allowable loads on equipment-identified in the Design Critaria and Analysis Methods Document as shown in Appendices A through C of this report.

3.

REQUIREMENTS AND BASIS The input requirements used in the analysis are defined in the Design Criteria and Analysis Methods document, drawings and other documents referenced in this Design Report.

These input documents are addressed in the paragraphs below.

3.1 Confiauration 3.1.1 The configuration of the piping and suspension is defined by the feedwater piping and suspension drawings (References 2, 3 and 4).

Snubber sizes greater than those specified in Reference 3 were used in the analysis.

The snubber sizes used in the analysis are given in Appendix Cl.

3.1.2 All data needed for modeling GE supplied pipe mounted equipment were obtained from equipment data sheets. These data sheets provide information such as weights, dimensions, center of gravity, and stiffness.

3.1.3 The properties of the materials used are shown in Tables 1 and 2, and the prop 9 tits of the piping are shown in T4ble 3.

3.1.4 An 1sometric joint diagram and a list of the joint coordinates of the complete piping mathematical model are shown in Appendix E.

3.2 Loads. The Design Criteria and Analysis Methods Document centains a complete listing and description of_ all static and dynamic loads-acting on the piping system. A complete listing of these loads-is also contained in Table 5.

3.2.1 Static loads and Pressure-Temoerature Duty Cycles.

The pressure, thermal, and dead weight loads acting on the piping-system are defined in the Design Criteria and Analysis Methods Document

-The definition of thermal

-exp'ansion cases is presented in Table 4.

3.2.2 Dynamic Loads. Vibratory building loads acting on the piping system are caused by the response of the reactor building structure and reactor pressure vessel to dynamic loads. The analysis of~the reactor building and

_-pressure vessel is performed by Others and the results of this analysis i

provide amplified response spectra and maximum. displacements at or near all points to which the pipe or pipe supports are attached to the-structure. lhe input response spectra for applicable attachment points are specified in the Design Criteria and Analysis Methods Document.

3.3 Load Combinations. Many of the static and dynamic loads acting on the piping system act concurrently.

The load combinations used for pipe, suspension, and pipe mounted equipment, and the acceptance criteria (allowable stress, allowable acceleration, allowable force or moment) for each combination are defined in the Design Criteria and Analysis Methods Document and presented in Appendix A.

2 i

NEDC-XXXXX 4.

METHODS 4.1 [qqfpment Modelina.

The piping system is mathematically mooeled to realistically reflect the static and dynamic reacticns of the piping.

The piping and equipment are represented in the model as a series of mass points (nodes) and interconnecting weightless springs.

The mass points are generally selected so that their location coincides with the location of large masses.

Mass points are spaced so that the elements between them will be of no greater length than a simple supported beam with uniformly C stributed mass having a natural frequency equal to the cut off frequency of the analysis.

4.1.1 Snubbers.

Each snubber is modeled as a linear spring with an equiva.U.t stiffness based on vehdor supplied data.

4.1.2 Pice Mounted Eouioment. The mathematical models used for the valves are based on information supplied by the responsible GE Equipment Engineer.

The model of all pipe mounted equipment is verified to realistically represent weight, stiffness, and dynamic properties of the equipment.

The weight and center of gravity (CG) location of valve operators are considered in applicable valve models.

4.1.3 RPV Nozzles.

The RPV nozzles are very stiff compared with the piping system and are th,erefore modeled as rigid anchors.

4.1.4 Sprina Hanaers.

Variable spring hangers are modeled as upward forcer in the dead weight analyses.

Since their stiffness in comparison with snubbers and nozzles is very small, spring hangers are not included in any of the analyses for dynamic loads.

4.1.5 Anchors. Other than the RPV nozzles, the only anchor in the piping system is at the containment penetration. This penetration anchor is modeled as boundary elements with stiffnesses equivalent to rigid.

l 4.1.6 Guide. The guide near the feedwater valves is modeled as a boundary element with both t anslational and rotational stiffnessas.

4.2 Ovnamic Analysis.

The dynamic analysis was performed using two methods.

The inertia effects of each of the governing dynamic loads are evaluated using the Multiple Support Response Spectra Analytical Method, also known as Independent Support Motion (ISM) Method.

Since the piping system is supported at several points and the excitation at each point is different, the ISM permits applying different excitation at each of the separate points, thereby eliminating the conservatism of Enveloped Response Spectra Method, also known l

as Uniform Support Motion (USM) Method. The inertia effects of the non-governing loads are evaluated using the Enveloped Response 3pectra Method.

The dynamic loads are listed in Table 5.

Earthquake, Annu'us Pressurization and Condensation Oscillation were analyzed using the Multiple Support Response Spectra method. Chugging and safety relief valve basemat acceleration for all valves were analyzed using the Enveloped Response Spectra method.

3

NEDC-XXXXX 4.2.1 Some other important dynamic criteria used in the analysis are tabulated below:

111d CRITERIA Damping:

Seismic OBE/SSE Reg. Guidt 1.61 Dynamic Loads Reg. Guide 1.61 Cutoff frequencies Acceleration Seismic - 33 Hz Response Spectra (ARS)

Other dynamic loads - 60 H7 Combination of 3 Direction Components Square Root of the Sum of the Squares (SRSS)

Combination of Primary and Secondary SRSS Loads and Stresses Response Spectrum Peak Broadening Plus or minus 10 7?

Modal Combir,ation Double Sum Method which accounts for effects of any closely soaced modes per Reg. Guide 1.92.

4.3 Thermal Analysis.

Thermal gradients are conservatively calculated using the ANS17 computer program by assuming an infinite heat transfer film coefficient with a linear process fluid temperature change equal to the step change defined for the load set. The radial gradients are computed idealizing the pipe wall as a flat plate.

Longitudinal gradients are co.'uted by separately analyzing two sections and selecting the greatest emperature difference that occurs during the transient.

4.4 Comouter Procrams.

The computer programs used in the piping stress analysis are described-below.

All of these programs were written by and meet the Quality Control Standards of GE. All programs have been approved for production use after independent review and verification, Any changes to these programs-required verification and approval in accordance with the NRC approved GE Quality Assurance Program.

4.4.1 E1111 PISYS performs static and dynamic analysis of piping systems.

The analysis modules of PISYS were derived directly from the SAP 4G pragram.

4.4.2 ANSI 7.

The ANSI 7 program calculates stresses and cumulative usage factors for Class 1, 2 and 3 piping components in accordance with Article N8-3600 and Subarticle NC-3652_ of ASME III. This program also calculates ccmbined loads on piping equipm/nt in accordance with the equipment load combinations given in the piping Design Criteria and Analysis Methods Document and compares them with the allowable loads where applicable.

l 1

4

NEDC-XXXXX 5.

RESULTS 5.1 Qcsion for Pressure (NB 3640) 5.1.1 Straiaht Pioe and Pioe Bends. Membrane protection for these items is provided by meeting the minimum wall requirements of Paragraphs NB 3641 and NB-3642 of ASME III.

The comparison of minimum wal' calculations with the values specified on the piping Drawing (Reference 2) are contained in Table 3.

5.1.2 Elbows.

Long radius elbows are manufactured in accordance with ANSI B16.9 Standard.

The minimum wall requirements for long radius elbows are the same as for straight pipe; therefore, the minimum wall thickness tabulated in Table 3 for straight pipe applies to elbows.

5.2 Structural Analysis. The forces, moments and deflections of the pipe at

^

each joint in the piping system identified on the stress analysis diagram for the thermal, dead weight and dynamic loading are calculated.

The summary of calculated data for applicable load combinations by service level is presented in Appendix B.

5.3 Pioina Comoonent Analysis 5.3.1 ASME Code Evaluation. The piping components were analyzed in accordance with the requirements of ASME III, Subarticle NB-3650 by the ANS!7 computer program.

The analysis showed that all of the requirements of Subarticle ! d-3650 of ASME III have been met.

5.3.2 Summary of Analytical Evaluation.

A summary of the analytical evaluation of tha piping components is given in Appendix B.

The summary consists of stresses, usage factors, and ratios to allowable.

5.4 Pioina System Eouioment loads. Accendices A throuah C.

The loads acting on equipment and supports interfacing with the piping are presented in Appendices A through C of this' report. Appendix A provides the load combinations, Appendix B contains a summary of results, and Appendix C provides the detailed interface loads for the following-equipment.

5,4.1 Reactor Pressure Vessel (RPV1 Nozzles.

These appendices present calculated forces and moments on the Reactor Pressure Vessel nozzles.

5.4.2 Valve Eauinment. These appendices give interface information for the l

valve equipment components.

The center of gravity (CG) accelerations are compared with their allowables.

l 5

NEDC-XXXXX 5.4.3 Suspension and Structural Attachments.

These appendices give the loading criteria and calculated loads for the piping suspension.

This includes snubbers, guides, and penetrations.

The location of, and coordinates for the suspension are given in Appendix E.

The calculated loads for each support component are compared with their allowable loads for all service levels.

5.5 Thermal Disolacements. Accendix 0.

Appendix D presents the thermal displacements for the normal operating condition for all significant nodes in the piping system.

6.

REFERENCES 1.

GE, "ABWR Main Steam, Feedwater and SRVDL Piping Systems Design Criteria and Analysis Methods", GE Document No. NEDC XXXX.

2.

GE, "Feedwater Loop Piping", K7, Drawing No. 103 Ell 88.

3.

GE, "Feedwater Piping Suspension", K7, Drawing No. 103E1437, 4.

GE, "Feedwater and Main Steam Penetrations", K7, Drawing No. 103E1422.

I 6

NEDC-XXXXX TABLE 1 PROPERTIES OF MATERIALS Modulus of 3

3 Material lemperature m

y Elasticity Material Type

(*F)

(psi)

ASME SA-333 1

421 (3) 19800 29500 29.5E6 (1)

Gr. 6 Carbon Steel Pioing 575 (41 17700 26500 27.6E6 (2)

ASME SA-420 2

421 (3) 19800 29600 29.5E6 (1) 575 (4) 17/00 26500 27.6E6 (2)

(1)

Ec - Modulus of Elasticity at 70*F (2)

Eh Modulus of Elasticity at 421*F (3)

Piping (Reactor) Operating Temperature (4)

Piping Design Temperature TABLE 2 MATERIAL ALLOWABLES Level Design Level B Level C Level D Eq. 12 413 Material Lesser 1.5 Sm 1.8 Sm 2.25 Sm 3.0 Sm 3.0 Sm Type of the 1.5 Sy 1.8 Sy 2.0 Sy I and 2 Allow psi 26550 31860 39825 53100 53100 7

NEDC-XXXXX TABLE 3 PIPING DIMENSIONAL PROPERTIES-feedwater Loop A Nom. Pipe Size (in) 12 22 Nom._ Pipe OD (in) 12.539 22.0 Nom. Pipe ID (in) 10.853 19.25 Min Wall tmc (2) 0.530 0.840 Nom. Wall tnom (in) 0.843 1.375 Material Type'(1) 1 1

Weight (lb/ft) (3) 157.9 453.9 Notes:

(1) Refer to Table 1 (2) Minimum Wall Requirements Calculated per ASME III, Section NB-3640 (3) Weight equals pipe weight plus water weight plus insulation weight 8

^

NCDC-XXXXX TABLE 4 DEFINITION OF THERMAL EXPANSION CASES

Temperature (degrees F)

Case 1 Case 2 Case 3 Case 4 Feedwater Piping 421 50 200 300 RPV Upper Section A 552 552 552 552 RPV Upper Section 8 528 528 528 528 RPV Skirt Section D 247 247 247 246 Case 1 is normal operating conditions.

Case 2 is loss of feedwater conditions.

Case 3 is normal operating conditions with low feedwater flow.

Case 4 is intermediate feedwater temperature conditions.

These thermal cases envelope all thermal conditions shown in Pressure /

Temperature Cycles referenced.in the Design Criteria and Analysis Methods Document.

9 l

NEDC-XXXXX TABLE 5 NOMENCLATURE OF LOADS Load Type Case Ident Dir***

Description P0 Operating Pressure PD Design Pressure PP Peak Pressure Thermal 1

TEl Nnrmal Operating Condition Thermal 2

TE2 Loss of Feedwater Thermal 3

TE3 Normal Operating with Low Feedwater Flow Thermal 4

TE4 Intermediate Feedwater Temperature Conditions Thermal TEMAX Greatest of Thermal 1, 2, 3, or 4 Weight 1

WT1 Dead Weight Seismic 1

OBEI X

Operating Basis Earthquake -

Inertia Effect Seismic 2

Y Operating Basis Farthquake -

Inertia Effect Z

Operating Basis Earthquake -

Seismic 3

a Inertia Effect OBE D 1

OBED*

X Operating Basis Earthquake - Anchor Displacement OBE D 2

OBED*

I Operating Basis Earthquake - Anchor Displacement SSEI 1

SSEI X

Safe Shutdown Earthquake - Inertia Effect SSEI 2

SSEI Y

Safe Shutdown Earthquake - Inertia Effect SSFI 3

SSEI Z

Safe Shutdown Earthquake - Inertia Effect SSED 1

SSED*

X Safe Shutdown Earthquake - Anchor Displacement SSED 2

SSED*

Z Safe Shutdown Earthquake - Anchor Displacement A.P.I.

1,7 APl**

HOR Annulus Pressurization Inertia Effect - Postulated Recirculation Break A.P.I.

2,8 APl**

HOR Annulus Pressurization Inertia Effect - Postulated Feedwater Break i

A.P.I.

3,9 APl**

HOR Annulus Pressurization Inertia Effect - Postulated Main Steam Break A.P.D.

1,7 APD Annulus Pressurization Anchor Displacement, Maximum of Recirculation, Feedwater and Main Steam Pipe Break.

STRQ(N 1

STRAK N Thermal stratification in the piping at the RPV nozzle STRAK H 1

STRAF W Thermal stratification in the feedwater header piping 10

NEDC-XXXXX TABLE 5 NOMENCLATURE OF LOADS (Continued)

Load Type Case Ident Dir***

Description CHUG. I 1,3 CHUGI HOR Chugging Load - Inertia Effect CHUG. I 2

CHUGI Y

Chugging Load - Inertia Effect COND. I 2

CONDI Y

Condensation Oscillation - Inertia Effect RV2 SVll 1,3 X,Z Single Safety Relief Valve -

Inertia Effect RV2 SVII 2

Y Single Safety Relief Valve -

Inertia Effect RV2 I 1,3 RV2 1 X,Z All Safety Relief Valves Basemat Acceleration - Inertia Effect RV2 1 2

RV2 I Y

All Safety Relief Valves Basemat Acceleration - Inertia Effect

OBED cases 1 and 2 were combined using the SRSS method.

SSED cases 1 and ? were combined using the SRSS method.

- For API, the higher of the Recirculation, Feedwater, or Main Steam Breaks is used.

- - The X-direction is east / west, the 7-direction is north / south, and Y is vertical.

11

NEDC XXXXX TABLE 6 NOMENCLATURE FOR APPENDICES Allowable horizontal acceleration (g)

AAH Allowable vertical acceleration (g)

AAV Calculated horizontal acceleration (g)

AH

=

Allowable force (lb) or moment (in-lb)

ALLOW

=

Anchor identification in structural analysis ANC Calculated vertical acceleration (g)

AV Acceleration in X, Y, Z directions (lb)

AX, AY, AZ Service level equation number as shown on load combination table COMB Local force in A, B, C directions (lb)

FA, FB, FC*

Force (ib) and moment (in-lb)

F/M Global force in X, Y, Z directions (lb)

FX, FY, FZ

=

Global guide identification in structural ualysis GGD Guide identification in structural analysis GUD

=

Calculated load (lb)

LOAD Local moment in A, B, C directions (in-lb)

MA, MB, MC*

=

Global moment in X, Y, Z directions (in-lb)

MX, MY, MZ Guide or anchor identification in structural analysis NELM Calculated load or stress divided by allowable 'oad or stress RATIO Snubber identification in structural analysis SNB

There are two types of elements that the PISYS computer program uses to form the pipe model. One is the straight or tangent element and the other is a planar bend element.

Each element has local coordinate axes that orient the element in the global coordinate system and identify force and moment components at a joint with respect to element axes. Moreover, joint displacement and rotation require a knowledge of the local axes.

The convention for the orientation of these local axes is as follows:

(1) Tangent elements parallel to the global Y-axis (vertical axis) have their local B-axis diverted to and in the same direction as the global Z axis.

(2) Tangent elements not parallel to the global Y-axis have their local B-axis contained in a vertical (global) plane such that local B-axis projects positively on the positive global Y-axis.

(

(3) For bend elements, the local B-axis is directed positively toward and intersects the center of curvature of the bend (i.e., radius vector).

(4) The local A-axis is tangent to the arc of the bend or straight element l

and is directed positively from the FROM joint to the TO joint.

l l

12

Ud i I Wif J TABLE Al 2 oAn rannxA Tuh - ccAss i

i'iPiNo ABWR K7 22 INCH FEEDWATER PIPE THE LOADING COMBINATION USED FOR THE ANALYS13 ee lese ARE AS FOLLOW DESIGN I

PD + Wil LEVL 8 i PP + Wil

SORT ((OSEI le=2

+ i RV28 le=2 i

L Et1L C I PP + Wil

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+ g Rygt lee 2 i

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+ SORTitSSEI l**2

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)

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!==2

+ t i f.'. I l==2

+ ( Rv21 i=*2 I

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. SORTi(SSES le=2

+ i A6 a l==2 I

eesNOTE=== ALL UNITS ARE IN POUNDS, INCHES EXCEPT NOTED seeMOTE*== IF NO USER INPUT PRESSURE FOR EACH LOAD COMBINAfl0N, PEAK PRESSURE WILL BE USED FOR LEVEL B,C AND D I

s 1

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+ t RV28 le=2 i

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