ML20090D889
| ML20090D889 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/18/1973 |
| From: | Broman R, Del Bene F, Keever R NUCLEAR SERVICES CORP. |
| To: | |
| References | |
| ROC-01-01, ROC-1-1, NUDOCS 8303110171 | |
| Download: ML20090D889 (45) | |
Text
_. _ __ _. __
O August 18, 1973 ROC-01-01 PRELIMINARY REPORT DYNAMIC ANALYSIS OF FEEDWATER PIPING FOR WATER HAMMER LOAD ROBERT E. GINNA PLANT O
Prepared for Rochester Gas & Electric Corp.
by Nuclear Services Corporation CAhtPBEU., CALIFORNIA Prepared by '
4 Approved by, b--ofi, ht 4h F. A. Del Bene '
R. Brom4 "
Reviewed by /. M/ t/) -
Issued by ,
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8303110171 730818 PDR ADOCK 05000244 P PDR
m Nuclear Services Corporation
.O TABLE OF CONTENTS M
i
1.0 INTRODUCTION
1 2.0 PIPING SYSTEM DESCRIPTION 5 3.0 DESIGN CRITERIA 7 4.0 LOADING CONDITIONS 8 5.0 ANALYTICAL PROCEDURES 12
- 51 Static Analysis 13 52 Dynamic Response Analysis lh j 5.3 Stress Analysis 17 6.0 SUWARY AND CONCLUSIONS 19 70 REFERENCES 21 O
APPENDIX A Tabulated Data 22 1
i s
l O
Nuclear Services Corporation 9
1.0 INTRODUCTION
This report, prepared for Rochester Gas and Electric Company, describes results of dynamic response analyses of the main and auxiliary feedwater piping systems to steam generator 1B at Robert E. Ginna Nuclear Generating Station. Isometric drawings of the piping analyzed are given in Figures 1-1,1-2 and 1-3.
The feedwater piping system was subjected to an abnormal transient loading condition on July 22, 1973, when a failure occurred in the stem to disc connection within Feedwater Control Valve 476 causing a sudden decrease in feedwater flow to steam generator 1B. Following the incident, the plant O wee drought to e ehutdown conditions, end en inepection of the piping ves made. Evidence was seen indicating that significant deflections had taken place in the main feedwater line to steam generator 1B and in the line from motor driven auxiliary feedwater pump 1B to this main feedwater line.
A decision was made to continue with a more detailed examination of the piping and to perform dynamic analyses to determine the magnitude of stresses resulting from the transient.
l l
The analyses have been made based on a time history water hammer forcing function computed by (conservatively) assuming an instantaneous and complete closure of the valve. The results of the analyses report herein include maximum values of stresses, deflections and support loads during the transient.
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.; 9 NucleerServices Corporation '
GINN A - FEEDWATER LINE INSIDE CONTAIN ME NT
. MAT. HEMATLCAL MODEL
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Nuclear Services Corporation v? 2.0 PIPING SYSTEM DESCRIPTION The main feedvater system carries water from the condensate system to the steam generators. In the Ginna plant the feedvster leaving the two high pressure feedvater heaters is joined in a single line. This line termi-nates at an anchor to the turbine building intermediate floor just outside the intermediate building. From this anchor individual lines branch, leading to the two steam generators inside containment. The main feedvater piping included in this analysis runs from the turbine building anchor, through portions of the turbine, intermediate, and containment buildings, to steam generator 1B. Configuration of the piping and support system was taken from reference 1 , and is shown on the isometric drawings Figures 1-1 4 and 1-2. The auxiliary feedvater system supplies water to the steam generators in the event of a loss of normal feedvater. The system consists of one steam turbine driven and two motor driven pumps, and piping connecting these pumps to the main feedvater lines. The auxiliary feedvater piping included in this analysis runs from motor driven auxiliary feedvater pump 1B, located on the basement floor of the intermediate building, to a connection to the main feedvater line to steam generator 1B. Configur-ation of the piping and support system was taken from marked copies of l reference 1 supplied by Rochester Gas & Electric, and is shown on the l l icometric drawing Figure 1-3. l [ O v _5-
Nuclear Services Corporation O The main feedvater piping is 14" schedule 100, and the auxiliary feedvater piping is 3" schedule 80. Both main and auxiliary feedvater piping are i I made from A106 Grade C material. Piping properties are summarized in Table A-1 of this report. ) l 4 'O 1 0
1 , O Nuclear Services Corporation 3.0 DESIGN CRITERIA The design specification for this piping is given in reference 5. The main feedwater piping is safety Class 1 between the steam generators and isolation check valves R0-6, and has no safety classification beyond these valves. The main feedwater piping has been designed to meet Class 1 seicnic requirements not only in the Class 1 portion itself, but also from the valves R0-6 to the common anchor in the turbine building. The auxiliary feedwater piping is safety Cla:;s 1 throughout. Code requirements for the piping are given by the ANSI B31.1.0 Code for Power Piping (Reference 2). O
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Nuclear Services Corporation O 4.0 LOADING CONDITIONS 4.1 Temperature and Pressure Conditions The main feedvater is supplied at h32 F and 905 psia in the full load operating condition (Reference 5). The auxiliary feedvater is supplied at 100 F (maximum) and 1250 psia (Reference 5). h.2 Weight Data The deadweight and dynamic analyses have considered the distributed weight of piping, insulation and contained water, as well as concentrated weights of valves and flow elements. Eccentric veight of valve operators has been considered Veere appropriate. Distributed weight data is sum-marized in Table A-1 and concentrated weight values are given in Table A-2. 4.3 Time History Dynamic Forcing Function For the time history dynamic analyses, the forcing function has been derived using formulas for water ham =er effects and assuming instan-taneous and complete closure of the feedvater control valve 476. Following the valve closure, there is a sudden decrease in flow down-stream of the valve, and an expansion wave moves from the valve toward the steam generator at acoustic velocity. The pressure change across this vave is given by, Nuclear Services Corporation AP = sAc (Reference 8) I l where (4 = Initial flow rate = 913 lb/sec ! C = Acoustic velocity for water at 432 F and 905 psia
= 3500 ft/see 2
g e
= 32.2 ft/sec A = Feedwater pipe flow area
= 115 5 in applying the formula, we find O
v AP = 859.2 psi As the wave passes in the main feedvater piping from the valve to the steam generator, unbalanced forces exist successively in each straight run of l piping during traversal of the wave from beginning to end of the straight run. The forcing function for each straight run has the form of a square pulse, with an instantaneous rise as the wave passes the beginning of the run, a maximum value as the wave traverses the run and an instantaneous decrease to zero as the wave passes the end of the run. The maximum value of the unbalanced force for the main feedvater is given by F = APA = 859.2 (115 5) = 99,000 lbs O _9_
Nuclear Services Corporation
- O and traversal time for each run is given by
=
at 1/e i where 1 = Length of run c = Acoustic velocity = 3500 ft/see When the wave passes the auxiliary feedwater connection, a similar wave with the same pressure drop will begin traveling back toward the auxiliary feedwater pumps, causing transient forces in the auxiliary feedwater piping similar to those in the main feedwater. The maximum value for these forces is given by 4 O
, F = APA I
where AP = 859.2 psi ) A = Flow area of auxiliary feedwater pipe ,
= 6.6 in thus F =
(859.2) (6.6) = 5671 lbs The procedure for computing wave transit times for auxiliary feedwater is similar to that for main feedwater, except that acoustic velocity for water at 100 F is 1987 ft/sec (Reference 9). 1 1 1 O Nuclear Services Corporation The maximum forces and times thus computed were applied to the piping in a time history dynamic response analysis. The forcing functions input in this analysis are summarized in Table A-3. It should be noted that the point of application of a force pulse along a given straight run of pipe is arbitrary, since axial response of the piping is negligible. 4 0 I I iO
Nucl ar Services Corporation 50 ANALYTIC.AL PROCEDURES The method of analysis used was the finite element stiffness approach. In accordance with this, the continuous piping is mathematically ideal-ized as an assembly of clastic structural members connecting discrete nodal points. Nodal points were placed in such a manner as to isolate particular types of piping elements, such as straight runs or pipe, elbows, valves, etc., for which force-deformation characteristics could be categorized. Also, nodal points were placed at discontinuities, such as piping supports, concentrated weights, branch. lines, and changes in cross section. O System loads such as weights, equivalent thermal forces, and dynamic inertia forces were applied at the nodal points. Stiffness characteris-tics of the interconnecting members are related to the effective shear area and moment of inertia of the pipe. The stiffness of piping elbows was modified to account for local deformation effects by the flexibility factors suggested in the MISI B31.1.0 Code for Power Piping (Reference 2) l l The equation of equilibrium for this idealized system may be written, in matrix form, as follows: MU + CU + KU = P-Q + F& (1) vhere: U = Nodal acceleration vector = U (t)
Nuclear Services Corporation 9 U = Nodal velocity vector = U (t) U = Nodal displacement vector = U (t) M = Mass matrix for assembled system C = Damping matrix for assembled system K = Stiffness matrix for assembled system P = External forces, weights, etc. Q = Equivalent thermal forces = /EaTdV F = Dynamic Forces 51 Static Analysis The static equation of equilibrium for the idealized syst6m may be written in matrix form, as follows: KU = P-Q (2) The nodal unknown displacements can be obtained by solving these simul-taneous equations using the Gauss-Siedel method. The nodal displacements ( ! are then applied to the individual members, and member stiffnesses used I i l to find internal forces. The nodal displacements at support locations l can be used along with the support stiffnesses to determine support reactions.
Nuclear Services Corporatimy 5.2 Dynamic Analysis A. Mathematical Model For the dynamic analysis, the mathematical model is described as a lumped mass, . multi-degree of freedom model. The distributed piping mass is lumped at the system nodal points. For the dynamic analysis the equation of equilibrium for the system is: MU + CU + KU = F (3) where , M = Mass matrix for assembled system C = Damping matrix for assembled system U = Nodal acceleration vector = U(t)
= Nodal velocity vector = O(t)
F = Applied dynamic forces = F(t)
= MU For earthquake 8
U = Ground acceleration = U8 (t) 8 This equation is solved for the system dynamic response as follows. First, the frequency equotion, obtained by removing the forcing and damping terms from equation ( 3), is solved for the system natural frequencies and mode shapes. Next, the natural mode shapes are used to affect an orthogonal transformation of equation (3), yielding a series of independe,nt equations of motion uncoupled in the system modes. Then, the uncoupled equations are solved by step-by-step integration to obtain system response in each mode, and the individual modal results are combined to detemine the total system dynamic response. The mathematical formulation of these steps is as follows: B. Natural Frecuencies and Mode Shanes The ciSenvalues (natural angular frequencies u a) and the eigenvectors (mode O , shapes O n quency equation: 1 14 -
Nuclear Services Corporation 0 . [K - wn M]'{$n}
= {0} (b) where th e = Natural frequency in n mode n
K = Stiffness matrix M = Mass matrix 4 = Mode shape vector in n mode 0 = Null vector The eigenvalues and ei6envectors are obtained using the Householder - QR algorithm. C. Dynamic Resnonse Pre-/and, post-multiplication of equation ~ (3) by [4], the square matrix of mode shape vectors, constitutes an orthogonal transformation, from which the uncoup-led equations of motion shown below are obtained. 5n 4 2wnnn A i +wn Y n
= P n ( 5) where th- mode Y = Generalized (modal) displacement coordinate for the n
" =
(U 4 n th
- A, = Damping ratio for the n mode expressed as percent of critical damping K
n
= Generalized stiffness for the n mode
=
4nK4 n th P n
= Generalized force for the n mode ] = 4 F i
0 Nuclear Services Corporation 9 Solution to these differential equations.-may be obtained by direct integra-tion, as follows: . D.. Time History Integration ,, To determine dynamic response using direct time history integration, equation (5) is written for finite time increments, for each normal mode, as follows.
- . 2 AY + 2w A AY +u n AY n
- O n (6) -
By assuming linear variation of accelerations during a time step, and making use of kinematic relationships between accelerations, velocities and displace-ments, equations can be written for the generalized acceleration and velocity O -iaere= ente vitnia a time step, es ro11ove-AE = 66Y ,6in -35 (7) D DO At at Ain at
~
no
- " (0)
Where the zero subscript refers to conditions at the beginning of the time step. Substituting these equations into equation (6) ve obtain 6e ** (6 nn+ 2 * + no + 2+ At n ' n n At no fat AtY '
+ 2WynA 3ig +
2 ' (9)
. This equation can be solved directly for the generalized displacement, which can in turn be used to find the generalized velocity and acceleration increments O using equations (7) and (8). The increments can then be added to the initial
- l'6-
Nuclear Services Corporation O conditions for the current time step to find initial conditions for the next time step. The total generalized displacement, which is maintained as a running sum of the increments, is expanded using the mode shape vector to form the system total displacement vector. This expansion is performed for each mode for each time step. These modal displacements are then applied to the system to determine internal forces, moments and reactions for each mode for each time step. Finally, the modal responses at each time step are combined directly to form total response for each time step. 5.3 Stress Analysis The results of the static and dynamic analyses were used, along with input pressure and te=perature information, to calculate stresses at the system nodal points. The stresses were calculated in accordance with the require-ments of the ANSI B31.1.0 code for Power Piping (Reference 2). O Stresses in the piping due to bending and tvisting are computed by the formula: U S g= Sy + hS t where S E Resultant stress in piping S b Resultant bending stress
=
(iMbp) * (ibh) Z S t = Torsional stress = g "t M = Bending moment in plane of member bp i Nuclear Services Corporation 9 M t
= Torsional moment Z = Sectional modulus of pipe i = Stress intensification factor for elbows, tees and certain other piping elements Stresses due to internal pressure are given by (See page 10, Reference 2):
Pd 1p 2 D -d o where S = Longitudinal pressure stress, psi P = Internal design pressure, poi d = Nominal inside dia. of the pipe, in. D = Nominal outside dia. of the pipe, in. All the required static, dynamic and stress analyses were conducted using Nuclear Services Corporation computer code IUPIPE, Reference 7 l t 1 l O i
Nuclear Services Corporation o O
6.0 CONCLUSION
S AND RECOMMENDATIONS In accordance with the ANSI B31.1.0 Code for Power Piping (Reference 2) the allowable primary stress for the piping material at operating temper-ature is 21,000 psi (1.2 Shot) and the yield stress at operating temper-ature is 40,000 psi. During the week following the incident, preliminary analyses were made for the main feedwater piping, which indicated that this piping exceeded allowable stress, but not yield, at the containment penetration and at hydraulic snubbers W-82 and W-83. These results vere reported to Rochester Gas and Electric on July 26, 1973, so that they could begin examination of the highly stressed areas of the piping. Subsequently, the analytical
*) model was expanded to include the auxiliary feedwater piping, and additional analyses were performed. The latter analyses, reported herein, indicate high stresses in the auxiliary feedvater line near its intersection with main feedwater, in addition to the locations on main feedwater summarized above. It is recommended that piping be examined for damage in the highly stressed areas mentioned. A complete summary of calculated stresses is given in Table A-4.
Substantial loads were calculated for the piping anchors in the turbine building, at the containment penetration #h04, and at the steam gener-ators. These anchors should also be inspected. Calculated anchor loads are summarized in Table A-5. O a _19 - l
Nuclear Services Corporation p\ ) Reaction forces calculated in the analyses indicated an overload on hydraulic snubbers W-82 and W-83, and significant loads on hydraulic cnubbers W-30 and W-80. These snubbers should also be inspected. A summary of calculated piping support loads is given in Table A-6. Peak deflections calculated were about 2-1/2 inches for the main feedwater line and 5 inches for the auxiliary feedwater line. A summary of calcu-lated deflections is given in Table A-7 and a comparison of calculated deflections with some deflections observed by inspecting the piping after the transient (Reference 6) is given in Table A-8. The observed deflec-1 tions were taken with the pipe in its hot position, were estimated by noting crushing of piping insulation caused by pipe contact with adjacent O etructure, end ere, of couree, epproximete. O
Nuclear Services Corporation n v
7.0 REFERENCES
- 1. Westinghouse Electric Corporation, Drawing D-304-086, Rev. VII
" Auxiliary Feedwater Pump Discharge, Plan and Sections, Intermediate Building".
- 2. American Society for Mechanica1 Engineers " Power Piping Code",
ANSI B31.1.0-1967
- 3. Flow Diagram-Westinghouse Electric Corporation, D302-192I.
- h. Westinghouse Electric Corporation, Drawings D-304-093, Rev. VII and D-304-084, Rev. IV, "Feedvater Pump Suction and Discharge".
5 Gilbert Associates, Inc. Technica1 Specifications, " Fabricated Piping and Supports", SP5291, revision dated October 2, 1967
- 6. Telecon R. E. Smith (Rochester Gas & Electric) to R. Broman (Nuclear Services Corporation) July 23, 1973.
7 Nuclear Services Corporation, "NUPIPE: Computer Code for Stress Analysis of Nuclear Piping", revision dated June 1, 1972. O 8. Streeter v. L., "r1uia Meche ics" 1962. 9 Zemansky, " Heat Transmission". O
m
- O Nuclear Services Corporation
' APPENDIX A TABULATED DATA
. TABLE DESCRIPTION A-1 PIPE DATA A-2 CONCENTRATED WEIGHTS A-3 TIME HISTORY FORCING FUNCTIONS A-b PIPING STRESS SUWARY A-5 ANCHOR LOADING
SUMMARY
A-6 PIPING SUPPORT LOADS Q A-7 PIPE DEFLECTION SUmfARY ! A-8 DEFLECTION COMPARISON I l O I l
A TABLE A-1: PIPE DATA , E5 MM Wt. Of QQ Wall Matl. Pipe & Wt. Of Design Design @o@ $ Line From To 0.D. Thick ASTM Fluid Temp. Insul. Press. @g@ No. Point Point (In.) (In.) Spec. Fluid ( Lb . /Ft.) ( Lb. /Ft.) (Dec.F) (PSIG) @s% g e ! A106 *8 14.0 ro N .m 5 295 0 937 Water 180 7 10.7 450 1,550 g GR C . e g s o A106 9y@ 5 115 1,065 35 0.3 Water 13.1 100 2,065 E 1.25 ggg GR C A106 MO 5 1,065 1,075 2.375 0.218 Water
@ >6 o Q 6.3 1.10 100 2,065 3S$ 5::
GR C A106 WHpJ 3 1,045 1,165 35 0.3 Water 13.1 1.25 100 2,065 @ko $y y GR C
- M y @
1,165 1,175 2 375 0.218 A106 Water 6.3 1.10 100 2,065 ggh * @ GR C mg9 ra g x g
, 5 696 14.0 0 937 A106 180.7
$$5 $
Water 10.7 450 1,550 ,e ca ro GR C eU W A106 WN Q O 8 696 710 18.0 1.157 Water 291.7 12.3 GR C 450 1,550 Qe M k 5-3 v. A
{Nucleger Services Corporation PROJECT ROBERT E. GIIMA NUCLEAR STATION SHEET OF SUBJECT FEEDWATER LINE FROM STEAM GENERATOR 1B TO MAIN HEADER AND AUXILIARY FEEDWATER LINE FROMEL288.p'TOMOTORDRIVEPUMPS1A&1B
/
TABLE A-2: CONCEITI' RATED WEIGHTS . Point Weight Eccentricity (In.) No. Description (Lbs.) From E Pipe 135 Valve, Ro-1 3,300 27.0
+
140 Valve, RO-6 2,400 a 155 Flow Meter 70 262 Valve, RO-2 h,170 25 5 271 Valve, FCV 476 3,400 27 996 281 Valve, R0-2 4,170 25 5 805 Valve,R0-18 , 145 1035 Valve, R0-86 355 27 0 1060 Valve, R0-20 145 1085 Valve, RO-16 220 15 0 1135 Valve, R0-16 .220 15 0 1160 Valve, R0-20 145 1145 Line Section - Tee 157 115 Line Section - Tee 191 Nuclear Services Corporation O pnojccy ROBERT I:. GINNA NUCLEAR STATION suaJtcr FEEDWATER LINE FROM STEAM GENERATOR 1B
'IO NAIN HEADER AND AUXILIARY FEEDWATER f.INE FROM EL 288.5' TO MOTOR DRIVE PUMPS 1A & IB M -
- at.
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/ TABLE A-3: TIFE HISTORY FORCING FUNCTIONS tr Node L At t,inal Maximum Point (ft) (sec) Useci Force (1b) REMARKS 256 7.6 .002 .002 99.000 2h6 12.0 .00342 .00542 99,000 235' 5.0 .00142 .00684 99,000 190 15 0 .00428 .01112 99,000 146 52.0 .01485 .02597 99,000 O no 17.9u . 00512 .0313 99,000 90 31.0 . 00885 .0h02 99,000 56 93.0 . 0265 .667 99,000 -
25 6.5 . 0019 .0686 99,000 3 15 12.0 . 003h .0720' 99,000 4 805 2.7 . 00054 .0273 5,6'v1 i j 820 55 . 0011 .0284 5,671 830 17.5 . 0036 .0320 5,671 ! 850 8.0 . 0016 .0336 5,671 l 910 76.1 . 0152 .0488 5,671 965 28.2 . 0057 .05h5 5,671 ! 990 20.0 . 004 .0585 5,671 i 1015 14.0 -
. 0028 .0613 5,671 1040 3.8 . 0008 .0621 5,671 l
25 -
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~
Nuclear Services Corporation PROJCCT ROBERTE.dINNAIUCLEARSTATION
- SHEET OF suoJtcr FEEDWATER LINE FROM STEAM GENERATOR 1B TO MAIN IIEADER AND AUXILIARY FEEDWATER LINE FROM EL 288.5' TO MOTOR DRIVE PUMPS l'A & IB f1 48 g7 .-
[/[h g TABLE A-3: TI!E HISTORY FORCING FUNCTIONS tr (continued) Node L 4t t final Maximum Point (ft) (sec) (see) Force-(1b) REMARKS 1050 1.5 .0003 .0624 5,671 1060 1.5 .0003 .0627 5,671 - 1070 1.2 .0003 .0630 , 5,671 1095 12.5 .0025 .0646 5,671 1110 8.25 .0017 .0663 5,671 1130 13.8 .0027 .0690 5,671 1160 1.0 .0004 .0694 5,671 1170 1.2 .0002 .0696 5,671 , 605 18.0 .0051 .0737 99,000 615 16.0 .00h57 .0785 99,000 630 14.0 .004 .0823 99,000 6ho 7.0 .002 .08h3 99,000 655 11.0 .0031 .0874 99,000 670 13.0 .0037 .0911 99,000 680 6.0 .0017 .0928 .99,000 690 6.0 .0017 .1045 99,000 C) .
_. - __ =. lVuclear Services Corporation ,
^ JECT
,tt0 RODERT E. GINNA NUCLEAR STATION Or
'SHECT i
hUDJECT FEEDWATER LINE FROM STEAM GENERATOR 1B TO MAIN HEADER AND AUXILIARY FEEDWATER LINE - FROM EL 288.5' TO MOTOR DRIVE FUMPS 1A and 1B' TABLE A-4 PIPING STRESS'SU95!ARY* Piping Systcra Feedvater , Allowable Strensen (PSI): Scold
- 1I'5
- 0 hot u 7.5 ksi , E _26.25 ksi A
1.2 S g= 21.0 ksi s = h0.0 ksi l Water Press. + Wt. Node Thernal Precoure P M.iuelcht Hex.mer I + Water . No. Streer. Stress Stress Stress He.n:rer Strest C0!?EUTS 5 1,253 2,718 333 5,7h9 8,800 10 1,745 2,718 106 23,507 26,331 15 2,h51 2,718 276 1h,227 17,221 20 2,389 2,718 262 11,169 14,149 25 2,013 2,718 137 8,955 11,810 LO 1,759 2,718 97 13,396 16,211 h1 1,031
- 2,718 53 8,154 10,925 h5 896 2,718 263 6,h77 9,458 h6 588 2,718 389 6,315 9,422 h9 285 2,718 h29 6,598 9,7h5 -
51 238 2,71 8 684 6,991 10,393 50 h1 2,718 293 8,677 11,688 - 53 371 2,718 338 5,916 8,972 Sh 570 2,718 596 10,0h9 13,h62 56 617 2,718 906 11,058 1h,682 55 815 2,718 187 6,551 9,456 _ 58 1,226 2,718 h60 10,321 13,h99 ,
.59 1,hh1 2.718 h56 9.767 12.9h'1
, 27 -_ _ _ . _ _ _ . _ _ _ _ _ _ . . _ .__
Nuclear Services Corporation Pit 0 JECT ROBERT E. GINNA NUCLEAR STATION . ' SHEET Or _., SUDJECT FEEDWATER LINE FROM STEAM O'ENERATOR 1B TO MAIN HEADER AND AUXILIARY FEELVATER LINE , FROM EL 288.5' TO MOTOR LRIVE PUMPS 1A and 1B . TABLE A-4 PIPING STRESS 'SU'31!AIlY
- Piping System Feedvater A11ovable Stresses (PSI): S cold = 17. 5 ksi S
hot " - I'5 *b 0A = 2025 ksi 1.2 S hot 21.0 ksi S yield " *
- Water Press. + Wt.
Hodc Thern21 Pressure Deaducicht Hemmer + Water . No. Stress Stress Stress Stress Ham.cr Strest CO!?EUTS 61 1,h56 2,718 Shh 9,7h9 13,011 62 1,688 2,718 56 9,666 12,hho
^
6s 1,9h3 2,718 192 12,380 15,290 70 2,971 2,718 106 14,018 16,842 80 2,908 2,718 512 8,239 . 11,h69 85 1,663 2,718 670 26,617 30,005 86 1,309 2,718 562 18,198 21,478 , . 90 972 2,718 470 10,207- 13,332 1 91 747 2,718 65h T,176 10,548 , 95 729 2,718 1,37h 8,633 12,725 l 100 963 2,718 1,311 10,321 lb,350 l 116 630 2,718 Shh 8,2h'3 11,505 - 110 hbl 2,718 372 31,077 3h,167 1 111 h63 2.718 372 28.939 32.029 i 115 1,065 2,718 387 10,621 13,723 1h" run 9 115 15.122 2,738 2,026 35,98h h0,748 3" branch 115 1,096 2,718 364 10,873 13,955 14" run 120 1,378 2,718 5h9 13,133 16,h00 l'
- 2B -
JVucicar barvices Corporation l l'it0 JECT ROBERT E. GINNA NUCLEAR STATION or
.suttr FEEDWATER LINE FROM STEAM GENERATOR 1B CSUDJECT TO MAIN HEADER AND AUXILIARY FEEDWATER LINE -
FROM EL 288.5' TO MOTOR DRIVE PUMPS 1A and 1B . TABLE A-4
. PIPINO STRESS SU 5fAllYf Piping Syste:2 vo n % + .,.
A11ovable Strer.ces (PSI): S cold * '7' **I S = 17.5 ksi M SA = 26.25 ksi 1.2 S hot = 21.0 ksi = 40.0 ksi Water Press. +'Wt. Node Thernal Prescitre Denducicht Hcemer + Water . lio. Strecn Stress Stress Stress Ho.r.er Strent 00!OEUTS 130 1,369 2,718 1,132 16,513 20.363 136 709 2,718 h3h 11.335 ' 1h .h87 139 633 2,718 296 9,781 12,795 0 1h1 h92 2,718 916 7,358 10,992 145 h91 2,718 933 7,3h6 '10,997 147 h78 2,716 277 9,146 12,1h1 1h6 531 2,718 325 11,9'18 1h,961 150 561 2,718 297 11,198 1h,213 155 582 2,718 276 11,109 1h,103 160 605 2,718 275 10,501 13,h9h - 170 653 2,718 h21 9,409 12,5h8 171 872 2,718 h82 9,715 12,915 - 175 1,11h 2,718 612 6,193 9,523 180 1,8k6 2,718 hh0 7,6h0 10,798 1 190 1,767 2,718 200 7,612 __10,530 200 1,503 2,718 292 7,393 10,403 21 0 1,h67 2,718 310 7,hh'6 10,474 215 863 2.718 217 7,168 10,103
. - _ _ _ _ _ - - - . - -- 29 , _ _ . . o
1suctcar acruices t.,orporation
] MtoftCT ROBERT,E. GINNA NUCLEAR STATION .
SHEET OF SUDJECT FEEDWATER LINE FROM STI:AM GENERATOR 1B TO MAIN HEADER AND AUXILIARY FEEDWATER LINE , *
'. FROM EL 288.5' TO MOTOR DRIVE PUMPS 1A and 1B -
TABLE A-h PIPING STRESS 'SU95!AtlY_* Piping Syste:2 Feedwater
~
A11ovable Stresses (PSI): S g = 17.5 w , S = 17.5 ksi S = 26.25 ksi 1.2 S hot = 21.0 ksi S = 40.0 ksi
. yield Water Press. +.Wt.
Hode Therr_al Pressure Deaducicht Hexmer + Water .
- No. Strens Stress Stress Stress He.=r.er Stresc CO'MUTS 220 999 2,718 356 12,3h9 15,423 i 230 810 2,718 141 12,610 15,h78 235 697 2,718 296 11,608 14,622 C 2h5 456 2,718 354 9,h61 12,533 i
246 240 2,718 233 5,780 , 8,731 250 571 2,718 3h8 16,037 19,103 } 256 369 2,718 1,140 17,0'04 20,862 1 260 243 2,718 762 15,026 18,506 285 1,390 2,718 522 10,790 1h,030 , 290 1,613 2,71 8 1,805 11,031 15,55h - ) i 295 612 2,869 87h h,010. 7,753 800 10,215 2,738 678 32,3hh' 35,760 - 810 15,456 2,738 592 33,1h2 36,h72 815 lb,625 2.738 535 30,515 33,788 I 820 19,761 2,738 677 18,928 22,3h3 e 825 20.868 2.738 Th5 21.2h3 2h.726 830 2,530 2,738 215 13,602 16,555
- 835 5,965 2,738 300 16,2h8 19,28'6 i _ _ _ .-____., ._. ._._._._.._ -_.-.__ _ . .
- 30 .
. , _ _ _ . , _ _ _ _,__,____u_
.__ ._ . .=. _ __ . _ _
Nucicar Services Corporation.
! PRORCT ROBERT E. GINNA NUCLEAR STATION .
. SHEER or UDKCT FEELWATER LINE FROM STEAM OENERATOR 1B *
; TO MAIN HEADER AND AUXILIARY FEEDWATER LINE .
FROM EL 288 5' TO MOTOR DRIVE PUMPS 1A and 1B - TABLE A-4 PIPING STRESS 'SUNJ!AilY
- Piping Syste:3 Feadwat er A11ovable Strecsco (FSI): S 17 5 k"4 S = 26.25 ksi cold
- OM = 17.5 ksi A 1.2 S hot e 21.0 ksi S = h0.0 ksi yield Water Press. + Ut.
Hode Thernal Pressure Denducicht Haimer + Water . No. Strecc Strecc Stress Stress Ham:.er Strect CO!OEUTS 840 7,124 2,738 380 10,112 13,230 8h5 6,807 2,738 289 9,932 12,959 3,656 2,738 14,546 17,591 - g 850 307 855 3,570 2,738 99 14,985 17,822 860 1,267 2,738 1,556 13.214 '17,508 870 h67 2,738 1,053 7.122 10,913 875 624 2,738 1,563 5,579 10,180 l - 880 928 2,738 983 9,132' 12,853 885 976 2,738 982 10,h36 14,156 , 890 701 2,738 8hh 3,399 6,981 * . 895 683 2,738 609 3,451 6,798 I 900 hok 2,738 688 5,28h' 8,710 - < l
- 905 260 2,738 653 2,h7h 5.865 910 133 2,738 283 1,h53 h,h74
- 915 80 2,738 194 6,294 -9,226 920 90 2,738 673 5,861 9,272
- 925 202 2,738 3ho 3,111 6,189 1
- 930 566 2,738 94 3,017 5 , 81i9
. . _ . . . - . _ _ . . , _ . _- -...._ _ ._-. _ .__ _ .___ _ 1 3 _ E .. , _ _. - _ _ _ . - 2- . _ ..- _ _ .
_ _ _ - - . .-. . ~ _ . - . - - . - . - . . _ - _ . - - - - IVuclear Services Corpration PitoKCT ROBERT E. GINNA NUCLEAR STATION ,
. SHEET or CsuoxCr rEEwATER unE rROM STEmuEnERATOR 18 TO MAIN HEADER AND AUKILIARY FEEDWATER LINE .
FROM EL 288.5' TO MOTOR LRIVE PUMPS 1A and 1B ,
~
TABLE A-4 - PIPING STRESS SU 5!ARY_* Piping Systen Feedvater A11ovable Stresses (PSI): S cold
- 17 5 k"i U
m = 17.5 ksi s = 26.25 ksi 1.2 Sg= 21.0 ksi s = h0.0 ksi Water Press. + Wt. l Node Therr.21 Pressure Deaducicht Hc=acr + Water . No. Strecs Stress Stress Stress Harzer Strest COSEUTS
.935 578 2,738 202 3,003 5,943 9ho 1,312 2,738 228 h,838 7,804
_ 9h5 1,301 2,738 165 'h,906 7,809 950 585 2,738 595 3,518 6,851 955 31h 2,738 371 h,019 . 7,128 i l 960. 188 2,738 1,475 - 4,608 8,821 965 93 2,738 597 5,057 t.392 970 hh1 2.738 1,h11 2.385 6.53h 975 1.131 2.738 los 5,682 8,525 ,
'980 1,145 2,738 2h7 5,856 5,841 -
985 785 2,738 718 5,219 8,675 990 523 2,738 131 3,h3k' 6,303 - 991 h69 2,738 .3 3,431 9,247 995 315 2,738 735 h,288 7,761 1000 571 2,738 260 6,561 9,559 1005 556 2,738 18h 6,h9h 9,h16 4 1010 208 2,738 127 3,836 6,701 1015 297 2,738 112 h,869 '7,719
- . _ . - - . - . . . . . . - . _ . - . . . - . ._-35 - ... .- . _ _ _ - ,. _.
JVuclear bervices Corporation PROJECT ROBERT,E. GINNA NUCLEAR STATION . SHEET OF SUDJECT FEEDWATER LINE FROM STEAM GENERATOR 1B TO MAIN HEADER AND AUXILIARY FEEDWATER LINE -
, FROM EL 288.5' TO MOTOR DRIVE PUMPS 1A and 1B -
TABLE A-4 PIPING STRESS 'SU6!ARY
- Piping SystenFeedvater A11ovable Stresses (PSI): S cold
= _17. 5 ksi S g = 17.5 ksi Sg = 26.25 ksi 1.2 S hot = 91.o m S yield = h0.0 ksi Water Press. +'Ut.
Hode Thern21 Pressure Deaducicht Hemmer + Water . No. Strern Stress Stress Stress Harter Strest COMEUTS 1020 836 2,738 144 9,601 12,h83 1025 669 2,738 h76 9,135 12,349 _ 1030 399 2,738 938 7,h89 11,165 10ho 875 2,738 710 5,039 8,h87 10h5 1,721 2,738 1,337 5,15h , 9,229 1050 1,718 2,738 792 2,690 6,220
^
1055 1 ,051 2,738 809 2,9'67 6,514 1065 8h1 2,738 369 3,098 6,205 t l 1070 3,227 2,h99 823 9,8h3 13,165 1075 l h,851 2,h99 2,557 9,hhh 14,50- - 1080 607 2,738 1,832 h,105 8,675 l 1090 533 2,738 295 3,248 6,281 - 1095 179 2,738 35h 2,807 5,899 1100 hh6 2,738 Sho 3,655 6,933 l 1105 495 2,738 1,38h 3,801 7,923 4 l 1110 111 2,738 316 979 4,033 1115 2hh 2,738 850 2,971 6,559 1120 651 2,738 596 3,109 6,443 L - - . .
Nuclear Services Corporation , l'ROKCT ROBERT E. GINHA HUCLEAR STATION .
. sm- - m
- OsuoxCr rEEDu nR uuE rROM STE m OEnERn0R 18 TO !&IN HEADER AND AUXILIARY FEEDWATER LINE .
FROM EL 288.5' TO MOTOR DRIVE PUMPS 1A and 1B . ! TABLE A-4 PIPING STRESS'SU$ AttYf Piping System Feedwater A11ovable Strocues (PSI): S cold 0 hot " 8.= A 26.25 ksi 1.2 S g= 21.0 ksi S g
= 40.0 ksi k'ater Press. + Ut, Node Thernal Preocure Deaducicht Hetmer + Water .
No. Strecr. Stress Stress Stress He.rter Strest CO!MENTS 1125 312 2,738 395 2,91h 6,047 1130 L15 2,738 32) 2,142 5,205 11ho h86 2,738 1,h03 2,391 6,532 1145 539 2,738 1,387 2,437 6,562 1150 841 2,738 1,886 3,797 8,421 1155 726 2,738 1,702 h,153 8,593 1165 1,h88 2,738 615 h,21h 7,567 1170 3,960 2,h99 869 12,755 16,123 1175 h,253 2,h99 3,857 11,792 18.,1h8 ! 5 3,253 2,718 h5 13,881 16,6hh . 1 ! 605 2,508 2,718 59 16,336 19,113
- 610 2,470 2,718 hk 15,226' 17,988 -
615 2,623 2,718 70 10,686 13,h74
- 620 2,317 2,718 18h 9,676 12,578
, 625 2,018 2,718 19h 5,883 8,795 630 3,538 2,718 128 9,589 12,435 l'
l 635 3,8h6 2,718 27h 9,937 12,929 6h0 2,915 2,718 227 10,380 13,325
helcar Services Corporation enoJccr ROBERT E. GINNA NUCLEAR STATI0Il . SH ET OF (C SUDJECT FEEDWATER LINE FROM STEAM GEIERATOR 1B TO MAIU HEADER AND AUXILIARY FEEDWATER LIHE . FRCM EL 288.5' TO MOT 6R DRIVE PUMPS 1A and 1B . TABLE A-h PIPING STREES~SU'5!AtlY-PipJng Systen Feedvater A11ovable Stresses ~ (PSI): S ' 8
- U
- cold hot
- A -
1.2 S = 21.0 ksi S
- yield Water Press. + Ut.
Mode Therrn1 Pressure Deaducicht Hermer + Water . No. Streca Stress Stress Stress Ham.cr Stress CO!OEUTS 6h5 2,127 2,718 h61 10,250 13,h29 650 6h7 2,718 695 7,998 11,h11
, 655 Sho 2,718 290 11,219 14,227 660 1,h53 2,718 233 1h,781 17,732 670 2,520 2,718 259 11,006 , 13,983 675 2,080 2,718 227 10,268 13,213 680 1,560 2,718 218 10,5'83 13,519 685 1,320 2,718 184 13,334 16,236 690 764 2,718 189 15,366 18,273 ,
695 329 2,718 191 17,158 20,067 .- , 696 221 2,718 130 15,h53 18,301 700 582 2,858 135 13,90d 16,899
- 705 1,18h 2,858 388 16,792 20,038 710 677 2,858 326 11,230 1h,hlh 9
Nuclear Services Corporation o PROJECT ROBERT E. GINNA NUCLEAR STAT'ICII SHEET OF SUDJECT FEEDWATER LINE FROM STEAM GENERATOR 1B 10 !!AIN HEADER AI;D AUXILIARY FEEDWATER LINE FROM EL 288.5' TO MOTOR DRIVE PUMPS 1A and 1B TABLE A-5: ANCHOR LOADING SUI"4ARY Y WATER HA!C!ER ANALYSIS , . Il 3 f' K T _4 O
.X Force (lb) Moment (in-lb)
!! ode p p p- g g Point Location X Y Z g
X Y Z Outside containment - l h5 Pen. #h0h 27,707 1,1h3 31,170 1,913 56,268 Inside containment 3.768 5 Pen. khoh 6,628 11,226 1.1,3h 3 130,303 30,758 25,233 295 Pipe header 16,892 1h,054 3,983- 99 ,011 19,656 h5,6hl 1075 Motor Drive Pump 1B 275 22h 273 142 556 36 1175 Motor Drive Pump 1A 127 209 370 536 h24 220 71 0 stean Genern+cr .in 48,358 22,597 27,766 53,553 137,833 LT1,897 Q&n %'* M L F l
Nuclear Services Corporation 0- - M.OJECT ROBERT E. GINNA NUCLEAR STATION SHEET OF SUDJECT FEEDWATER LINE FROM STEAM GENERATOR 1B TO MAIN HEADER AND AUXILIARY FEEDWATER LINE FROM EL 288.5' TO MOTOR DRIVE PUMPS 1A and 1B I TABLE A-6: PIPING SUPPORT LOADS ACHON CUSTOMER SPRING NODE SUPPORT DIRECTION CONSTANT AM 1.tARIC . PT* NO. TYPE #/IN HAICIER (LES) 10 PEU-40h Penetration Lateral Rigid 75,518 25 W-11 Hanger Y Rigid 3,151 45 W-12 Hanger Y Rigid 4,640 56 W-80 Snubber Inclined -- 22,130 l l$ 65 W-16 Hanger Y Rigid 5,661 65 W-81 Snubber Inclined -- 24,938 85 W-82 Snubber Z - 74,372 110 W-83 Snubber X -- 78,622 145 W-29 Spring Hanger Y 1,080 2,h50 l l 1L6 W-30 Snubber Z -- 13,h88 1 i 1 70 W-31 Spring Hanger Y~ 1,600 3,951 l 175 W-32 Spring Hanger Y 800 1,253 220 W-33 Spring Hanger Y 600 370 l 250 l Vertical -- Hanger Y Rigid 17,58h 250 Lateral -- Hanger Z Rigid 18,951 i 825 W-37 Hanger Y Rigid 1,hh5 l 635 l West -- Hanger X Rigid 853 l 035 North -- Hanger Z Rigid 80h l l 850 W-36 Hanger Y Rigid 249 875 W-35 Hanger Y Rigid 166 L - , _ _ - _ . _ _ . . , _ . _ . .. ._-_-. _-_ . . 37 - ,;_, . _ _ _ _ _ , _ , _ _ , _ , _ ,,
Nuclear Services Corporation
%OJECT E0 BEET E. GI U!A NUCLEAR STATI0II SHEET OF su M cT FEEDWATER LINE FROM STEAM GENERATOR 1B TO 1%IN HEADER AND AUXILIARY FEEDWATER LINE FROM EL 288.5' TO MOTOR DRIVE PUMPS 1A and 1B TABLE A-6:
PIPING SUPPORT LOADS CUSTOMER SPRING N0DE TO SUPPORT TION R MARK CONSTANT PT. NO. TYPE #/IN HAMMER (LES) 880 W h7 Lateral Z Rigid h91 A00 W 7h Hancer Y Rigid 9h 905 FW-33 Hanger Y Rigid 52 915 l l Vertien1 W h8 Built-up Y Rigid 134 915 3.8 x 10 3 i Horizontal ' W h8 Built-up Z 398 l 920 W-32 Hanger Y Rigid 115 l l 935 W-31 Hanger Y Rigid 2 9h5 W-30 Hanger Y Rigid 5 955 h Vertical W h9 Built-up Y 9 x 10 10h 9>5 6 North FW h9 Built-up Z 2.1 x 10 60 960 FW-29 Hanger Y Rigid 90 985 W-28 Hanger Y Rigid 66 991 FW-27 Hanger Y Ri Sid 199 1005 W-26 Hanger Y Rigid 700 1115 W-5 3 Hanger Y Rigid 152 610 W-10 Hanger Y Rigid 88 625 W-61 Hanger Y Rigid 1,326 650 W-80 Hanger Y Rigid 267 660 Laterel -- Snubber Lateral -- 19.550 Nuclear Services Corporation OmOJECT ROBERT E., GINNA NUCLEAR STATION OF SHEET SUDJECT FEEDWATER LINE FR0!4 STEAM GENERATOR 1B - TO IMIN HEADER AND AUXILIARY FEEDWATER LINE FR0!! EL 288.5' TO MOTOR DRIVE PUMPS 1A and 1B TABLE A-6: PIPIEG SUPPORT LOADS CUSTOMER SPRING OE SUPPORT g, DIRECTION CONSTANT Am PT. NO. TYPE #/IN HUIMER (LBS) 675 W-7 Spring Hanger Y 2h1 1h9 l l l ? i 39 -- t . - - . . .- ..-..._ .-. ... _- - _.-. _ - - .-- .-- . . - - . - - - - . . - . - - -
Nuclear Services Corporation ( ; enoJLcr ROBERT E. GINHA NUCLEAR STATION suttr- or suBJtcT FEEDWATER LINE FROM STEAM GENERATOR 1B TO MAIN HEADER AND AUXILIARY FEEDWATER LINE FROM #L 288.5' TO MOTOR DRIVE PUMPS 1A & 1B TABLE A-7 PIPE DEFLECTIO!! SU: GARY Node Deflec' ion (in) Themal Expjansion - I t!ater Hamn.er !!esponse Point. AX AY AZ AX* aY* AZ* 25 .324 .0 .180 .148 .003 .863 h5 .626 .0 .06 404 .005 1.055 51 1.292 .0 .602 1.136 .279 1.058 56 2.225 .0 -1.305 .051 .339 1.056 p v 61 2.872 .0 -1 995 781 .211 1.oh7 65 2 982 .0 -2.351 .117 .006 1.0h0 90 2.438 .001 -2.001 .h12 1.686 1.031 95 2.155 .002 -1.665 .k12 2.0h1 2.420 vert 250 .h67 .001 .0 .121 .018 .019 Lat'l 250 .h67 .001 .0 .121 .018 .c19 825 1 581 .0 -1.391 1.680 .0 1 984 West 835 .0 .03 .0 .0 .0 .0 North 835 .0 .03 .0 .0 .0 .0 850 .913 .0 796 - h.961 .0 1.139 875 .965 .0 .256 .0 5.025 1.2h4 a All Values are h0 -
Nuclear Services Corporation Paojtcr ROBERT E. GINNA NUCLEAR STATION OF SHEET suojtcT FEEDUATER LINE FROM CTEAM GENERATOR 1B TO !%IN HEADER AND AUXILIARY FEEDWATER LINE FROM EL 288.5' To MOTOR DRIVE PUMPS 1A & 1B TABLE A-7 PIPE DEFLECTIO:1 SUl01ARY Deflection (in) flode Thqr"ul Expansion I Water Hammer Response Point AX AY AZ AX
- AY
- AZ" ~
North 880 .986 .025 .0 5.025 .154 ,o 890 .988 .0 .142 5 077 .o .699 905 -1.028 .o .111 5.077 .o 775 Vert g 915 -1.056 .0 .o 5.077 .o .105 Lat'l 915 -1.056 .o .o
~
5.077 .o .105 920 -1.057 .0 .006 5.077 .o .092 935 -1.092 .0 .105 5.077 .o .335 9h5 -1.112 .0 .03 5.054 .0 .o Vert 955 .776 .0 .o 4.099 .001 .o North 955 .776 .o .o h.099 .001 .o 960 .680 .o .007 3 900 .o .o 985 .066 .o .09 1.603 .o .215 991 .091 .o .209 1.603 .o 1.061 g 1005 .120 .0 .235 1.577 .0 1.522 1105 .199 .o .03 .078 .o .786 k1 - O - All Values are
Nuclear Services Cmporation
~, ' ' rnoltcT ROEERT E. GIU"A NUCLEtJ1 STATION gggty or SUDJECT FEEDUATER LINE FROM STEAM GENERATOR 1B TO MAIN HEADER AND AUXILIARY FEEDWATER LINE FROM EL 288.5' TO MOTOR DRIVE PUMPS 1A & 1B TABLE A-7 PIPE DEFLECTION Suf0'ARY Deflection (in) flode Thenm l Expansion Water liaimr.or 1:esponse Point oX tY AZ AX* AY* AZ*
1115 .2h6 .0 .053 .229 .0 .786 610 -0.079 -0.062 -0.0h0 0.053 0.052 0.073 625 0.093 -0.350 0.335 1.794 1.376 0.878 g 650 0.09h -0.210 0.212 1.304 1.107 0.216 675 -0.009 -0.054 -0.139 0.936 0.617 0.485 l l 8 h2 - C - All values are 1
Nuclear Services Corpration O PRojtcr ROBERT E. GINNA NUCLEAR STATION suo>tcy FEEDUATEP. LINE FROM CTEA!! GENERATOR 1B TO MAIN HEADER & AUXILIARY FEEDWATER LINE FROM EL 288.5 TO MOTOR DRIVE PUMPS 1A & 1B TABLE A-8: PIPING DEFLECTION COMPARISON Deflection (Inches) Field Observation Calculated Location (Hot Condition) ater Hamer AX AY I AZ AX l AY 67, 11 feet couth of FWH-lh -1.25 ---- --- 1.089 .349 1.059 i.181 Near FWH-15 -----
+.937 ----
d.211 1.047 t fn y g g etration ----- -----
-1.375 .h12 1.686 1.031
(, V At FWH-7 il.0 10 5 ---- 936
- 617
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, 477 Division Street -
Campbell, California 95008 r -
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