ML20090B208
| ML20090B208 | |
| Person / Time | |
|---|---|
| Site: | 05000605 |
| Issue date: | 02/29/1992 |
| From: | Herzog M, Raju Patel GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20090B190 | List: |
| References | |
| NUDOCS 9203030246 | |
| Download: ML20090B208 (34) | |
Text
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- DRAFT-NEDC-XXXXX DRF No.
February 1992 Revision 0 ABWR SSAR MAIN STEAM, FEEDWATER AND SRVDL PIPING SYSTEMS DESIGN CRITERIA AND ANALYSIS METHODS Prepared By:
///(MW
M c'1 M.'Herzog,' Senior Engineer ' -t Piping Design and Analysis Approved By:
R.D. Patel, Manager Piping Design and Analysis 9203030246 920224 PDR ADOCh 05000605 A
r.
IMPORTANT NOTICE REGARDING THE CONTENTS OF THIS REPORT Please read carefully The use of this information for any purpose other than that for which it is intended is not authorized; and with respect to any unauthorized use, GE Nuclear Energy makes no representation or warranty, and assumes no liability as to the completeness, accuracy or usefulness of the information contained in this document, or_that its use may not infringe privately owned rights, i
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TABLE OF CONTENTS Section Pace No.
1.0 PURPOSE 1
2.0 MAIN LiEAM P! PING 1
2.1 Description 1
2.2 Boundaries 1
1 2.3 Pipe Attached Components 1
3.0 SAFETY / RELIEF VALVE DISCHARGE PIPING 2
3.1 Description 2
3.2 Boundaries 2
3.3 Pipe Attached Components 2
4.0 FEEDWATER PIPING 3
4.1 Description 3
4.2 Boundaries 3
4.3 Pipe Attached Components 3
5.0 DESIGN REQUIREMENTS 4
5.1 Design Conditions 4
5.2 ASME Code Classification and Requirements 4
5.3 Analytical Methods 5
5.4 Design Loads 9-5.5 Load Combinations and Acceptance Criteria 11 5.6 Materials 12 6.0 REFERENCE DOCUMENTS 14 ii L
1.0 PURPOSE The purpose of this engineering report is to document the engineering requirements used in design and analysis of the advanced BWR (ABWR) main steam, safety / relief valve discharge and feedwater piping systems.
2.0 MAIN STEAM PIPING 2.1 Descriotion The main steam piping addressed in this report is main steam line A, which runs from the reactor pressure vessel nozzle through the drywell and containment penetration to the outboard main steam isolation valve.
2.2 Boundaries The boundaries of the main steam piping include the following:
a.
The circumferential welded joints at the reactor pressure vessel nozzle and at the inboard isolation valve, b.
The containment sleeve head fitting connection to the main steam p4ing.
c.
The face of the first flange in bolted safety-relief valve connections (the bolts shall be part of.the valve),
d.
The branch connections where the branch pipes weld to the branch nozzles on the main steam pipes.
2.3 Pioe Attached Components The main steam isolation valves and safety / relief valves shall be included in the analysis.
Small branc.h lines such as instrument and drain lines are not included in the analysis, i
1
3.0 SAFETY /REllEF VALVE DISCHARGE PIPlf4G 3.1 DntriEUQD The piping addressed in this report consists of four safety / relief valve discharge lines attached to main steam line A, and each one extending from the flange connecting to the safety / relief valve to the first anchor at the diaphragm floor penetration.
One wetwell safety / relief valve discharge line h
extending from the d.aphragm floor penetration to the x quencher in the suppression pool is also addressed in this report.
3.2 Boundaries The boundaries of the SRV discharge
! ping includt the following:
a.
The discharge piping from the safety / relief valve discharge flange to the penetration anchor at the diaphragm floor.
This includes the piping connecting the vacuum breaker, b.
The discharge piping from the penetration at the diaphragm floor to the X quencher in the suppression pool, c.
The diaphragm floor penetration sleeve head fitting connection to the safety / relief valve discharge pipe.
3.3 Pipe Attached Components The valves, vacuum breakers and X quenchers shall be included in the analysis.
Small branch lines such as instrument and drain lines are not included in the analysis.
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4.0.
FEE 0 WATER PIPING 4.1 Descriotion The piping addressed in this report consists of feedwater Line A running from the reactor pressure vessel to the containment penetration anchor.
4.2 Boundarks The boundaries of the feedwater piping include the following:
a.
The circumferential welded joint at the reactor pressure vessel nozzle.
b.
The circumferential welded joints to all intermediate valves in the feedwater piping.
l c.
The containment sleeve head fitting connection to the feedwater piping.
d.
The weld at branch connections where the branch pipe welds to the branch nozzle on the run pipe.
4.3 P_{y, Attached Comoonents The inboard check and gate valves shall be included in the analysis.
Small branch lines such as instrument and drain lines are not included in the analysis.
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5.0 DESIGN REQUIREMENTS 5.1 Desian Conditions 5.1.1 Picina Desian Pressures and Temperatures The design and operating pressures and temperatures for the main steam, safety / relief valve discharge and feedwater piping are given in Table 2 and are referenced from the document listed in Paragraph 6.n.
5.1.2 Pressure-Temocrature Duty Cycles for main steam and safety /relitf valve discharge piping, the pressure-temperature duty cycles to be used in the fatigue analysis ar9 specified in reference document 6.d.
For feedwater piping, the pressure temperature duty cycles to De used in the fatigue analysis are specified in reference document 6.e.
5.2 ASME Code Classification and Reauirements 5.2.1 The main steam pipe connecting the Reactor Pressure Vessel to the isolation valve outside the containment (within the boundaries defined in Paragraph 2.2) is classified as Class 1, Seismic Category I piping and shall meet the requirements for ASME Section !!!, Class I piping components as specified in reference documents 6.a and 6.b.
5.2.2 The feedwater pipe connecting the Reactor Pressure Vessel to the isolation check valve outside the containment (within the boundaries defined in Paragraph 4.2) is classified as Class 1, Seismic Category I piping and shall meet the requirements for ASME Section 111, Class 1 piping components as specified in reference documents 6.a and 6.b.
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5.2.3 The main steam and feedwater piping supports are classified as Class 1, Seismic Category I supporting structures and shall meet the requirements of ASME Section 111. NF per reference documents 6.a and 6.b.
5.2.4 The safety / relief (S/R) valve discharge piping from the flange connecting to the S/R valve to the diaphragm floor penetration anchor is classified as Class 3. Seismic Category I piping and shall meet the requirements for ASME Section 111. Class 3 piping components as specified in reference documents 6.a and 6.b.
5.2.5 The safety / relief valve discharge piping supports for the piping described in Paragraph 5.2.4 are classified as Class 3, Seismic Category I supporting structures and shall meet the requirements of ASME Section 111, NF per reference documents 6.a and 6.b.
5.2.6 The safety / relief valve discharge piping from the diaphragm floor penetration to the quencher in the suppression pool is classified as Class 2, Seismic Category I piping and shall meet the requirements for ASME Section 1
111, Class 2 piping components as spccified in reference documents 6.a and 6 b.
- 5.2.7 The safety / relief valve discharge piping supports for the piping described in Paragraph 5.2.6 are classified as Class 2, Seismic Category I-supporting structures and shall meet the requirements of ASME Section !!!, NF per reference documents 6.a and 6 b.
5.3 Analytical Methpd1 5.3.1 General All static and dynamic analysis of piping covered by this specification
-s ah ll be done in accordance with reference documents 6.a 6.b and 6.c.
5 w av.,
5.3.2 Modelina 5.3.2.1 Mathematical models for piping systems shall be constructed to reflect the dynamic characteristics of the system.
The continuous system shall be modeled as an assemblage of pipe elements (straight sections, elbows, and bends) supported by hangers and anchors, and restrained by pipe guides, struts and snubbers.
Pipe and hydrodynamic masses are lumped at the nodes and connected by the weightless elastic beam elements which reflect the physical j
properties of the corresponding piping segment.
The node points are selected to coincide with the locations of large masses, such as valves, and with locations of significant geometry changes. All concentrated weights on the piping system, such as the valves, are modeled as lumped mass rigid systems if their fundamental frequencies are greater than the cut off frequency. The torsional effects of valve operators and other equipment with offset centers of gravity with respect to the piping center line shall be included in the analytical model, 5.3.2.2 If a branch pipe is small, such that the ratio between pipe diameters of branch line to main l'ine is less than one-third, the branch line can be excluded from the piping model of the main line.
5.3.2.3 All pipe guides, restraints and snubbers shall be modeled with a representative stiffnass.
The stiffness of the supporting structures shall be considered in the analysis.
5.3.3 Cut-Off Freauency for Ovnamic Analysis 5.3.3.1 For seismic loads, the dynamic analysis shall include all modes up to a frequency of 33 Hertz.
5.3.3.2 For all other dynamic loads, the dynamic analysis shall include all modes up to a-frequency of 60 Hertz.
5.3.3.3 High frequency modes (modes with frequencies greater than 60 Hz) are included in accordance with reference 6.c.
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4 5.3.4 Inout Response Soecta for a subsystem analysis of a secondary system, the input floor response spectra, obtained from a time history analysis of the primary system, shall be peak broadened by 110 percent to account for modeling uncertainties in the primary and secondary systems.
5.3.5 Ovnamic Analysis 5.3.5.1 The response of the piping system to all seismic and dynamic loads filtered through the building structure shall be determined by use of one of the following methods:
a.
A response ' spectrum analysis using an envelope of the response spectra of all of the piping support points for each orthogonal direction of excitation.
b.
A multiple response spectrum analysis using the individual response spectrum at each pipe support point for each orthogonal direction of excitation.
Tne response between two or more support groups may be combined by the SRSS method if a support grvup is defined by
~
supports that have the same time history input.
c.
A time history analysis using either the direct integration or modal superposition method.
5.3.5.2 The response of the piping system to dynamic loads not filtered through.the building structure (such as pressure waves inside the piping) shall be by direct integration time history analysis.
5.3.5.3 Damping coefficients in terms of percent critical damping to be used in the dynamic-analysis are given in Table 1 and are referenced from reference documents 6.a. 6.c, and 6.o.
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5.3.6 Resoonse Soectrum Analysis 5.3.6.1 The response spectrum method is a modal superposition analysis in which only the peak values of the inertial response are obtained.
The modal responses are combined using the square root of the sum of squares (SRSS) rule to get the total inertial response.
Closely spaced modes are combined in accordance with reference 6.c.
5.3.6.2 The support movement of multiple supported piping subject to seismic and hydrodynamic loads shall be considered.
The maximum displacement of each support point can be computed by either time history analysis or response i
spectrum analysis for the supporting structures.
The support displacement loads shall be computed from static analyses in which the displacements are j
applied at the supports.
5.3.6.3 The inertia and displatement loads are dynamic in nature and their peak values are not expected to occur at the same time.
Therefore, the inertia and displacement loads are combined by the SRSS method, l
5.3.7 Seismic loads 5.3.7.1 The seismic analysis shall be performed using the multiple response spectra analysis method. The piping seismic input loads are the appropriately damped and peak broadened horizontal and vertical response spectra at all piping support attachment points.
Three sets of inertial results, one for each of the two horizontal seismic excitations and one for the vertical excitation shall be calculated.
5.3.7.2 The total seismic inertial response shall be calculated by combining the colinear responses due to the three orthogonal components of seismic excitation by the square root of the sum of the-squares (SRSS) method.
5.3.7.3 The seismic differential building movement analysis shall be performed for each of the three orthogonal directions and the results shall be combined by the-SRSS method.
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5.3.8 liydtpdynamic loads 5.3.8.1 The piping systems shall be analyzed for the hydrodynamic loads due to reactor building vibration (RBV) caused by S/R valve blowdown and LOCA events.
The Hydrodynamic loads analysis shall be performed using the envelope or multiple response spectra method.
The analysis for each Hydrodynamic load shall be performed using the three orthogonal components of response spectra at all support attachment paints.
f 5.3.8.2 The total inertial response shall be calculated by combining the colinear responses due to the three orthogonal components of excitation by the l
SRSS method.
5.3.8.3 The differential building movement analysis shall be performed for i
each hydrodynamic load case in all three ortnogonal directions and the results shall be combined by the SRSS method.
5.3.9 Concurrent Dynamic loads 5.3.9,1 The colinear responses of concurrent dynamic loads shall be combined by the SRSS method.
5.3.10 Thermal Analysis The thermal expansion; analysis of the piping shall account for the predicted radial and vertical movement of the RPV nozzle and building structure due to the temperature and pressure changes in the vessel.
5.4 Desian Loah 5.4.1 Seismic loads l
The Safe Shutdown Earthquake (SSE) response spectra and building displacements to be used for the design of the piping systems are contained in the documents referenced in Paragraph 2.f.
The operating basis earthquake 1-9 i
1
)
(ORE) retponse spectra shall be one half of SSE response spectra.
The piping fatigue analysis shall be based on five OBE events with 10 stress cycles per event.
5.4.2 tlydrodynamic Loads Response spectra and building displacements for Hydrodynamic loads due to S/R valve blowdown and LOCA:
a.
SRV loads are contained in the document referenced in Paragraph 6.g.
b.
LOCA loads are contained in the document referenced in Paragraph 6.g.
5.4.3-Other Loads 5.4.3.1 Safety / Relief Valve Lift Acoustic Load Safety / relief valve opening time of 20 msec shall be used to calculate the safety relief valve discharge forcing function actir.g on the piping.
The safety /relie, valve set pressure and flow rate are given in the document referenced in Paragraph 6.m.
5.4.3.2 Turbine Stop V&lve Closure Acoustic load Turbine stop valve closure time and steam flow rate are given in the document referenced in Paragraph 6.m and shall be used to calculate the loads on the piping system due to turbine stop valve closure.
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5.4.4 Flooded load l
The main steam line shall be designed such that it may be flooded with cold water. The weight analysis shall confirm that this flooded load condition is acceptable.
The flooded load condition shall be included in the.
piping fatigue analysis per reference 6.d.
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5.4.5 Thermal Stratification toad The feedwater line shall be analyzed for two thermal stratification load cases:
(1) thermal stratification in the piping at the RPV nozzle, and (2) thermal stratification in the feedwater header pipinn.
Thase loads are to be included in the piping fatigue analysis per reference 6.e. and are also to be included in the evaluations of the head fitting and RPV nozzles.
The temperature differences for each load are given in reference 6.e.
5.5 Load Combinations and Acceotance CrJteria 5.5.1 P_ip_ing Table 3 contains the primary stress load combinations and acceptance criteria for ASME Section !!!,-Classes 1 and 3 (drywell) piping.
Table 4 -
contains the load combinations and acceptance criteria for ASME Section III, Class 2 (wetwell) piping.
5.5.2 Head Fittinas Table 5 contains the load combinations for the Main Steam Head fitting.
Table 6 contains the load combinations for the feedwater Head fitting.
Table 7 contains the load combinations for the Otaphragm Floor Head fitting.
5.5.2 Snubbers and Struts Tables 8 and 14 contain the load combinations and acceptance criteria for snubbers and struts.
The acceptance criteria are per ASME-111, Subsection NF and Appendix F (referenced in Paragraph 6.b).
5.5.4 Glida The load combinations for the guide are-listed in Table 9.
The guide shall be provided by the reactor building designer.
The calculated guide loads shall be used to design the Guide, 11 l
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5.5.5 Main Steam Isolation Vali1 The load combinations and acceptance criteria for MSIV end loads are given in Table 10.
5.5.6 feedwater Valves The load combinations and acceptance criteria for feedwater valve accelerations are given in Table 11.
5.5.7 Safety Relief Valves The load combinations and acceptance criteria for safety relief valve flange moments are given in Table 12.
5.5.8 Reactor Pressure Vessel Nozzles The load combinations and acceptance criteria are given in Table 13.
5.6 Materials 5.6.1 Main Steam Pipina The material for the piping shall be as listed below, a.
Piping - ASTM /ASME SA333 Gr. 6 b.
Fittings - ASTM /ASME SA420 c.
Forged Fittings and Flanges ASTM /ASME SA350 LF2 P
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5.6.2 Safetv/ Relief Valve Discharae Pioina The material for the piping shall be as listed below.
Drywell Pidina Wetwell Pioina a.
Piping -
ASTM /ASME SA333 Gr. 6 ASTM /ASME SA 376 smls.
Sch. 80 TP316
.05% max. carbon b.
Fittings -
A3TM/ASME SA420 ASTM /ASME SA 403 TP 316
.05% max. carbon c.
Forged Fittings ASTM /ASME SA350 LF2 and Flanges -
5.6.3 Feedwater Pio).ng The material for the piping shall be as listed below, a.
Piping - ASTM /ASME SA333 Gr. 6, Schedule 100
-b.
Fittings - ASTM /ASME SA420 c.
Forged fittings and Flanges - ASTM /ASME 3A350 LF2 l.
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)
6.0 REFERENCE DOCUMENTS a.
American Society of Mechanical Engineers (ASME) Boller and Pressure Vessel Code 1986 Edition Section 11. Material Specifications Section 111, Nuclear Power Plant Components, Division 1 (1) Subsection NCA, General Requirements (2)
Subsection NB, Class 1 Components (3)
Subsection NC, Class 2 Components (4)
Subsection ND, Class 3 Components (5)
Subsection NF, Component Supports (6) Appendix f c.
USNRC Regulatory Guide 1.61, " Damping Values for Seismic Design of Nuclear Power Plants" USNRC Regulatory Guide 1.92, " Combination of Closely Spaced Modes in Response Spectrum Method of Analysis" USNRC SRP Section 3.7.2, Rev. O August 1989, High frequency Modes d.
" Reactor Cycles," G.E. Document No. 796E243
" Main Steam and RCIC Press / Temp Cycle Chart and Load Set," G.E.
l Document No. 103E1415 e.
"feedwater MITI Class 1 and 3 Piping Cycles " G.E. Document No.
796E852 l
l l
t 14 l
"Feedwater Press / Temp Cyc Chart and Load Set," G.E. Document No.
103E1414 f.
" Seismic Soil - Structure intoraction Analysis for Reactor Building Complex of ACWR Standard Plant," G.E. Document No. xxxxx g.
" Response of Structures to Containment Loads " G.E. Document No.
299X700 001 h.
Reactor Vessel Assembly Drawing, G.E. Doc. No. 795E997 i
1.
Reactor Vessel Nozzles Drawing, G.E. Doc. No. 112D3124 j.
-Main Steam Isolation Valve - ERS, G.E. Doc. No. 23A6241 k.
Safety / Relief Valve - ERS, G.E. Doc. No. 23A6074 1.
Feedwater Check and Gate Valves ERS, G.E. Doc. No. 23A6089 m.
Nuclear Boiler System - Design Specification, G.E. Doc. No. 22A8446 n.
Nuclear Boiler System P&lD, G.E. Doc. No. 795E877 o.
ASME Code Case N 411-1, Alternative Damping Values for Response Spectra Analysis of Class 1, 2, and 3 Piping,Section III, Division 1.
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L-.
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i Table 1 DAMPING VALUES i
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_Damoina Value (Percent)*
I Component level B Lgvel D Smaller diameter piping systems 1.0 2.0
(<!2 inch diameter)
Pump. Valve, and large diameter piping 2.0 3.0 systems i
Snubber 4.0 7.0-r Strut 4.0 7.0 Ar.chor, Guide, Hanger 1.0 2.0
- 0amping values of ASME code case N 411-1 (Ref. 6.0) may be used with the Enveloped response spectra method of analysis.
t 16
f Table 2 l
DESIGN AND OPERATING PRESSURES AND TEMPERATURES Pressure (osia)
Temperature t'F) t Normal Normal System Desian Operatina Desian Operating i
Main Steam 1250 1050 575 552 feedwater 1250 1100 575 420-Safety Relief Valve 540 0
480 135 Discharge Line i
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A Table 3 LOAD COMBINATIONS AND ACCEPTANCE CRITERIA FOR ASME SECTION 111 CLASS 1 AND 3 (DRYWELL) PIPING Acceptance Criteria Service level Lqad Combination 1 Class 1
[1111_1 Design PD+W l.5 Sm 1.5 Sh Level O PP+W+RVl+0BE 1.8 Sm 1.8 Sh PP+W+RV2+0BE 1.5 Sy 1.5 Sy PP+W+TSV+0BE Level C PP+W+ CHUG +RV1 2.25 Sm 2.25 Sh PP+W4 CHUG +RV2 1.8 Sy 1.8 Sy Level D PP+W+5SE+ CHUG +RV1 3.0 Sm 3.0 Sh PP+W+SSE+ CHUG +RV2 2.0 Sy 2.0 Sy PP+W+SSE+C0+RV1 PP+W+SSE+C0+RV2 PP+W+SSE+TSV PP+WFSSE+AP PP+W+RVl+TSV PP+W+RV2+TSV NOTES:
1.
Dynamic loads combined by SRSS.
(SSAR refers to NUREG 0484, Revision 1) 2.
Anchor Motions not included in above load combinations.
3.
Level C loads are for SBL. This includes VLC and Chugging.
C$ugging controls.
4.
Load definition legend given on sheet 30 i
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4 Table 4 LOAD COMBINATIONS AND ACCEPTANCE CRITERIA FOR ASME SECTION !!! CLASS 2 WETWELL PIPING 1ervice level.
Load Combination ecceptance Criteria Design PD+W l.S Sh Level A&B PP, W RVI, OBE 1.8 Sh PP, W. RV2, ADJQ, OBE 1.5 Sy PP, W. AIRC, OBE PP, W, W.1ET, OBE Level C PP, W CHUG, CHUGW, RV1 2.25 Sh PP, W. CHUG, CHUGW, RV2, ADJQ l.8 Sy PP, W CHUG, CHUGW, AIRC PP, W, CHUG, CHUGW, WJET Level D PP, W SSE, CHUG, CHUGW, RV2, ADJQ 3.0 Sh PP, W. SSE, CHUG, CHUGW, RV1 2.0 Sy PP, W, SSE, CHUG, CHUGW, AIRC PP, W, SSE, CHUG, CHUGW, WJET PP, W, SSE, CO, C0W, RV1 PP, W. SSE, CO, COW, RV2, ADJQ PP, W. SSE, CO, COW, AIRC PP, W. SSE, CO, C0W, WJET PP, W, SSE, WJETHV PP, W. SSE, AIRBB, PSWLY PP, W. SSE, AP NOTES:
1.
Dynamic loads combined by SRSS.
(SSAR refers to NUREG-0484, Rey, 1) 2.
Anchor Motions not included in above load combinations.
- 3.. Level C loads are for SBL.
This includes VLC and Chugging.
Chugging I
controls.
4.
Load definition legend given on sheet 30.
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Table 5 LOAD COMBINATIONS FOR MAIN STEAM HEAD FITTING Service le ul _
load Combination _
Design /A&B W. RV2, OBE (Primary)
W, RVI, OBE W. TSV, OBE level A&B W, RV2, TE, OBE (Primary + Secondary)
W. TSV, TE, t Ac Level C (Primary)
W CHUG, RV2 W CHUG, RV1 W, CHUG, TSV Level 0 (Primary)
W, RV2, SSE W. RVI, SSE W. TSV, SSE Level 0 (Primary)
W. CHUG, SSE, RV2 W. CHUG, SSE, RV1
.W, CHUG,-SSE; TSVe-W. CO, SSE, RV2 W. C0, SSE, RV1
- W,-C0r SSE, TSV c W. SSE, AP W, RVI, TSV W, RV2, TSV N 556, TS J NOTES:
1.
Dynamic loads combined by SRSS method.
2.
Anchor Motions included in above primary plus secondary load combination.
3.
Level C loads are for SBL.
This includes VLC and Chugging, Chugging controls.
4.
Load definition legend is given on sheet 30, 20
I l
i Table 6 LOAD COMBINATIONS FOR FEEDWATER HEAD FITTING Service tevel load Combination Design /A&B W. RV2, OBE level A&B W. RV2, OBE, TE (Primary + Secondary)
W. TE, STRAH W. TE, STRAN Level C W. CHUG, RV2 Level 0 W, CHUG, SSE, RV2 W, CO, SSE, RV2 W. SSE, AP NOTES:
1.
Dynamic loads combined by SRSS method.
2.
Anchor Motions included in above primary plus secondary load combination.
3.
Level C loads are for SBL. This includes VLC and Chugging, Chugging controls.
4.
Load definition legend is given on sheet 30.
w l
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i Table 7 LOAD COMBINATIONS FOR DIAPHRAGM FLOOR HEAD flTTING Service Level Load Combination Design W. RVI, OBE level A&B W, ISV, OBE W, RV2, ADJ0. OBE t
W. AIRC, CBE W. WJET, )BE Level C W CHUG, CHUGW, RV1 W CHUG, CHUGW, RV2, ADJQ W CHUG, CHUGk', AIRC W. CHUG, CHUCW, WJET Level D W. SSE, CHUG, CHUGW, RV2, ADJQ W, SSE, CHUG, CHUGW, RV1 W. SSE, CHUG, CHUGW, AIRC W. SSE,-CHUG, CHUGW, WJET W. SSE, CO, COW, RV1 W, SSE, 00, COW, RV2, ADJQ W. SSE, 00, COW, AIRC W. SSE, CO, COW, WJET W. SSE, WJETMV W. SSE, AIRBB, PSWLY W, SSE, AP NOTES:
1.
Dynamic loads combined by SRSS.
(SSAR refers to NUREG 0484) 2.
Anchor fotions not included in above load combinations.
3.
Level C loads are for SBL.
This includes VLC and Chugging. Chugging controls.
4.
Load definition legend is given on sheet 30.
22
?
1 LOAD COMBINATIONS AND ACCEPTANCE CRITERIA FOR SNUBBERS lervice level load Combinations Acceptance Criteria j
Design RVl+0BE 1.0 x snubber rated load Level B RV240BE TSV+0BE i
level C CHUG +RV1 1.33 x snubber rated load CHUG +RV2 Level 0 SSE+ CHUG +RV1 1.5 x snubber rated load SSE+ CHUG +RV2 SSE+C0+RV1 SSC+C0+RV2-SSE+TSV SSE+AP RVl+TSV RV2+TSV NOTES; 1.
Dynamic loads combined by SRSS.
(SSAR refers to NUREG-0484) 2.
Anchor Motions are included in above load combinations.
3.
Level C loads are for SBL.
This includes VLC and Chugging.
Chugging controls.
4.
Load definition legend is given on sheet 30.
i 5
i-23
Table 9 LOAD COMBINAT!aNS FOR Gul0ES Service level Load Combinations Design W+TE+STRAH W+1 E+'ST RAN Level B W+TE+1SV+0BE W+TE+RVl+0BE W+TE+RV240BE Level C W+TE+ CHUG +RV1 W+TE+ CHUG +RV2 Level D W+TE+SSE+ CHUG +RV1 W+TE+5SE+ CHUG 4RV2 W+TE+SSE+C0+RV1 W+TE+SSE+C0+RV2 W+TE+SSE+TSV W+TE+SSE+AP W+TE+RVl+TSV W+TE+RV2+TSV NOTES:
a.
Dynsmic loads combined by SRSS.
(Per SSAR reference to NUREG 0484, Rey, 1) 2.
Anchor Motions are included in above load combinations.
3.
Level C loads are for SBl.
This includes VLC and Chugging, Chugging controls.
4.
Load definition legend given on sheet 30.
24
4 Table 10 LOAD COMBINATIONS AND ACCEPTANCE CRITERIA FOR MSIV AT VALVE ENDS Service level load Combinations Acceptance Criteria r
Design PD + W + TE MA/2Z<g+.755*
2 SQRT (MB MC ) < 0.75 Sm i
FA + P0/4t < 0.75 Sm level B PP, W. TE, RVI, OBE MA/2Z<j.0jm PP, W, TE, RV2, OBE SQRT (MB 4MC ) < 2.0 Sm PP, W. TE, TSV, OBE FA + P0/4t < 2.0 Sm level C PP, W. TE, CHUG, RV1 MA/2Z<j+.0jm PP, W, TE, CHUG, RV2 SQRT (MB MC ) < 2.0 Sm FA + PD/4t < 2.0 Sm Level D PP, W, TE, SSE, CHUG, RV1 MA/2Z<j+.0jm PP, W, TE, SSE, CHUG RV2 SQRT (MB MC ) < 2.0 Sm PP, W. TE, SSE, 00, RV1 FA + PD/4t < 2.0 Sm PP, W. TE, SSE, CO, RV2 PP, W TE, SSE, TSV PP, W, TE, SSE, AP PP, W, TE, RVI, TSV PP, W. TE, RV2, TSV NOTES:
1.
Dynamic loads combined by SRSS.
(SSAR refers to NUREG-04B4) 2.
Anchor Motions are included in above load combinations.
3.
Level C loads are for SBL.
This includes VLC and Chugging.
Chugging controls.
4.
Load definition legend is given on sheet 30, 25
Table 11 LOAD COMBINATIONS AND ACCEPTANCE CR11ERIA FOR FEEDWATER VALVES Acceptance Criteria Service level Load Combinations Fetdwater Valves Design RVl+08E 39 Ilmit in each of Level B RV240BE the three orthogonal directions Level C CHUG 4RV1 CHUG +RV2 Level D SSl+ CHUG +RV2 SSE+C0+RV2 SSE+AP NOTES:
- 1. _ Dynamic loads are combined by SRSS method.
2.
Level C loads are for SBL.
This includes VLC and Chugging, Chugging controls.
3.
Load definition legend is given on sheet 30.
1 i
i 26 i
P---e q
e' v
4+=r:t-
?
e--mu-*e-P
-U-M->
w e-Mr-e.'.he-Ik-e=>*
-aNnP-+Ww I'
s-e eFN's-e*
i Table 12 LOAD COMBINATIONS AND ACCEPTANCE CRITERIA l
FOR SAFETY RELIEF VALVE - INLET Ah3 OUTLET FLANGES j
Acceptance Criteria l
Purpose Operating Max. Applied Moment Of Limit Condition load Combinations (K-ini Basis of Acceptance Criteria l
Code Level A&B W+TE(MY&MZ)
Inlet:
355
.ASME III - Appendix XI Structural Outlet: 355 Integrity Ditto W+TE+RVI+0BE Inlet:
850 ASME III - NB 3658.I W+TE+RV2+0BE Outlet: 735 ASME III - ND 3658.1 W+TE+TSV+0BE Ditto Level C WeTE+ CHUG +RVI Inlet:
1350 ASME III - NB 3658.2 W+TE+ CHUG +RV2 Outlet: 1110 ASME III - ND 3658.7 Ditto Level D W+TE+SSE+ CHUG +RVI Inlet:
1350 ASME III - NB 3658.3 W+TE+5SE+ CHUG +RV2 Outlet: 1I10 ASME III - ND 3658.3 W+TE+SSE+C0+RVI W+TE+5SE+C0+RV2 W+TE+SSE+TSV W+TE+SSE+AP W+TE+RVI+TSV W+TE+RV2+TSV i
Leakage Level A&B W+TE (MX+MY+MZ)
Outlet: 215 Limit is 320 K-in ntnus 104 K-in for i
fitup Structural /
Level C W+TEMAX(MX+MY+MZ)
Inlet:
355 Same as Level A&B Operability Outlet: 355 Same as Level A&B p
Structural /
Level D W+TEMAX(MX+MY+MZ)
Inlet:
695 Limit - 800,000 in-lbs minus 104 K-in Operability for fitup t
Outlet: 495 Limit - 600,000 in-lbs minus 104 K-in for fitup 1
NOTES:
1.
Dynamic loads combined by SRSS.
(SSAR refers to NUREG-0484) r 2.
Anchor Motions are included in above.
3.
Level C loads are for SBL.
This includes VLC and Chugging. Chugging controls.
4.
Load definition legend is given on sheet 30.
Table 13 LOAD COMBINATIONS AND ACCEPTANCE CRITERIA FOR REACTOR PRESSURE VESSEL N0ZZLES Operating III Condition Laid Combination Accentance Criteria Design PD, W. RV2, OBE M/Z+f/A+PS < l.5 Sm(2)
PD, W, TSV, OBE PD, W. RVI, OBE I3)
PP, W. RV2, TE, TSV, RVI, OBE M/Z+F/A+PS < 3.0 Sm Level B PP, TE, STRAH, STRAN Level C PP, W. CHUG, RV1 M/Z+F/A+PS < l.8 Sm and 1.5 Sy PP, W CHUG, RV2 Level O PP+W+SSE+ CHUG +RV1 M/Z+F/A+PS < Su PP+W+SSE+ CHUG +RV2 PP+W+SSE+C0+RV1 PP+W+SSE+C0+RV2 PP+W+SSE+TSV PP+W+SSE+AP PP+W+RVl+TSV PP+W+RV2+TSV NOTES:
1.
The term for bending stress in the acceptance criteria equations (M/Z) shall be increased by the addition of two factors:
(a) A shape factor to account for the geometry of the RPV nozzle at the point of consideration.
(b) A factor, not greater than 1.2, to ensure adequate margin in piping loads applied to RPV nozzle.
2.
The terms in the above stress equation are defined as follows:
MR = (MX,gy +MZ )0.5, is applied moment, HR, 2
2 2
-MR+{d)HR,2*)Bege:, is applied shear, and d is distance from point where M
(FB + FC HR is applied to section of RPV nozzle under consideration.
Z - Section modulus of RPV nozzle at location under consideration.
F Axial force at pipe nozzle interface A = Cross sectional area of RPV nozzle at location under consideration.
PS Longitudinal pressure stress plus radial pressure stress at locatic' of RPV nozzle under consideration.
3.
Anchor motions are included in Level B load combinations.
4.
Load definition legend is given on sheet 30.
28
Table 14 LOAD COMBINATIONS AND ACCEPTANCE CRITERIA FOR STRUTS Service Level load Combinations Acceptance Criteria Design W+TE 1.0 x Equipment Rating Level B W+1E+RV140BE 1.0 x Equipment Rating W+TE+RV2+A0JQ+0BE W+1E+AIRC+0BE W+TE+WJET+0BE level C W+TE+ CHUG +CHUGW+RV1 1.33 x Equipment Rating W+TE+ CHUG +CHUGW+RV2+ADJQ W+TE+ CHUG +CHUGW+AIRC W+TE+ CHUG +CHUGW+WJET Level 0 W+TE+SSE+ CHUG +CHUGW+RV2+ADJQ l.5 x Equipment Rating W+TE+SSE+ CHUG +CHUGW+RV1 W+TE+SSE+ CHUG +CHUGW+AIRC W+TE+SSE+ CHUG +CHUGW+WJET W+TE+SSE+C0+C0W+RV1 W+TE+SSE+C0+C0W+RV2+ADJQ W+TE+SSE+C0+C0W+AIRC W+TE+SSE+C0+C0W+WJET W+TE+SSE+WJETMV W+TE+SSE+AIRBB+PSWLY W+TE+SSE+AP NOTES:
1.
Dynamic loads combined by SRSS.
(Per SSAR reference to NUREG 04B4, Rev. 1) 2.
Anchor Motions are included in above load combinations.
3.
Level C loads are for SBl.
This includes VLC and Chugging, Chugging controls.
4.
Load definition legend given on sheet 30.
l I
29 I
.~~m--
-x-
-n
-. ~ < -.,, -
,e-g
-c-,
a w
LOAD DEFINITION LEGEND:
ADJQ Air clearing load from active quencher acting on adjacent inactive quencher
- [i AIRBB Air bubble from main vent opening g3 pr s
- y '
AIRC Air clearing load from active quencher acting on that same quencher's
- - w.1 gjy arms
- ~..
AP Reactor Building Vibration (RBV) loads from Annulus Pressurization loads duc to postulated main steam line, feedwater line and residual heat removal pipe breaks CHUG RBV dynamic loads on structures, systems and components induced by chugging CHUGW Chugging wetwell pressure load C0 Hydrodynamic loads from condensation oscillation C0W Condensation oscillation wetwell pressure load OBE Operating Basis Earthyaake PD Design Pressure PP Peak Presstre PSWLY P'ol Swell RV1 Safety Relief Valve lift fluid transient, applies only to main steam and safety / relief valve discnarge lines RV2 Hydrodynamic loads induced by discharge of all safety / relief valves 30
o O
LOAD DEf!NITION LEGEND (Continued)
SSE Safe shutdown earthquake STRAH Loads due to thermal stratification in the feedwater header piping STRAN Loads due to thermal stratification in the feedwater piping at the RPV nozzle TE-Thermal expansion TSV Turbine stop valve closure induced loads on main steam line VLC Vant Line Clearing Hydrodynamic load W
Weight WJET Water jet load from active quencher acting on adjacent inactive quencher WJETHV Water-jet from main vent opening I
L-L 1
o 1
31 l
e
-