ML20132E981

Rev 1 to Stress Analysis for Demonstration of Operability of Purge & Vent Valves During Dbas

ML20132E981
Person / Time
Site:	Oyster Creek
Issue date:	05/09/1985
From:	Manning T, Rochino A, Sheu J GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20132E960	List: ML20132E954 ML20132E981
References
TDR-266, TDR-266-R01, TDR-266-R1, NUDOCS 8510010214
Download: ML20132E981 (20)

Text

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• . , Mg TDR NO. 266 REVISION NO. I BUDGET TECHNICAL DATA REPORT ACTIVITY NO. 3157n 1 PAGE 1 OF 18 e PROJECT DEPARTMENT /SECTION E&D/ Engineering tbchanics Oyster Creek Nuclear Station RELEASE DATE R/?1/A1 REVISION DATE S/4/RS DOCUMENT TITLE: Stress maalysis lor Uet.cnstration or operaclllty of hrge and Vent Valves Durin3 Design Basis Accidents ORIGINATOR SIGNATURE DATE DATE APPROVAL (S) SIGN age g g, T.G. Ma mina M N )J'M_ E/9/#C A. P. Rochino Mk[ M Y//f5

3. Shou b 5% fl9lET

/

APPRO,VA,t. fop EXTERNAL DISTRIBUT!ON DATE

//[fwL Does this TDR include recommendation (s)? Cyes ONo if yes, TFWR/TR F. No. AT .1312 6~-t 2 di o DISTRIBUTION ABSTRACT:

a. Erief Statement of Proble:n

• P. R. Clark The subject analysis has teen consequently perfonned per D. K. Croneherger References 6.7 and 6.18 to verify that when containnent D. M. Grace purge and vent valves, greater than 3" ncninal diameter, R. ". Keaten are 30 open or less, they will be capable of performing

.M. Laggart their intended function without damage to critical R. L. Lcrenzo valve components under combined seismic and DBA- W CA J. 7 . !'ahn conditions, and that it is available to close these T. G. !'x mning valves frcri 30 open when fluid dynamic torques are J. P. !'oore, Jr. introduced.

A. P. Rochino J. Shcu Per Robert E. Weltman's letter to John L. Sullivan, Jr.,

J. R. Tho:p3 dated May 16, 1980 (Reference 6.6), the valves analyzed T. Z. Tipton were:

N-[.fik3r3 2- "Cll" 1 Drywell Purge Valves V-23-13 and V-23-14.

2. Torus Purge Valves V-23-15 and V-23-16.

R. F. L'ilson

3. Torus Vent Valves V-28-17 a..d V-28-18.

P O _ .G O M 4. Drywell Vent Valves V-27-1 and V-27-2.

5. Drywell Purge Valves V-27-3 and V-27-4.

The torgae and stress analysis results for demonstration of operability of purge and vent valves per NRC guidelines as shown in References 6.8 and 6.17 are documented in Section 3.0 of this TDR.

b. Summary of Key Results The following results were obtained when valves are 30 open or less during WCA:

i 8510010214 850924 PDR P ADOCK 05000219 l PDR j I

oCOVER PAGE ONLY A0000030 4-83 l

_ __. . . =. __ .

TDR No. Eff Rev. 1 Page la

1. Each valve operator is aFle to restrain the total valve torque. which is tie sum of seating terque and ficid (ynaric torque (See Table 3 in Appendix).

2. Tre calculated stress levels of the valve conponents under combined seismic and LCCA conditions are less than the LCC/ allovable limits

' of 50 percent cf the yield strength of the material used (See Table 5 in Appendix).

c. Ccnclusion

. 1. Each valve operator can overccre the total valve torque when opening i tFe valve and rostrain the total valve terque when closing the valve.

2. The structural integrity of the valves is assured if tFe valve openings are limited te 30* or less.

d. Recentendatiens

1. To ensure structural integrity, the valve opening rust be limited to 0* open er less.

2. To cnsure scaling integrity, the velve seats must be visuelly inspected and te replaced as required.

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• 1 DOCUMENT NO.

. Nuclear - no. 2ee TITLE Stress Analysis for Denonstration of Operability of Purge and Vent Valves Durina Nmim R,nin hi ao*

REV

SUMMARY

OF CHANGE APPROVAL DATE

1. The conservatism of the calculated valve torqueswas eliminated by using M $k -

I/#lff

1. The curves of drywell and torus pressure transients during DBA as shmin in Figure 2,

2. The valve response time following a IDCA and ),

each valve closing time as indicated in /

References 6.13 and 6.14 respectively, as well () k 5

- [fr e

as, .g 1

()

3. Mass and momentum ecuations to solve for i ,)

velocity and pressure drop across each valve. 'f The valve torques are compared with the allowable operator torques in terms of available safety factors. Thsy are in turn compared with the NRC required safety factors as shown in Table 3.

In addition, more references have been added in

• Section 6.

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3 2

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N a

O A000003612 83

. 114EH TDR No. 200

. Rev. 1 Page 2 of 10

?

4 0YSTER CREEK NUCLEAR STATICH i

STEESS ANALYSIS FOR DEF.0NSTPATION CF CPERABILITY OF PURGE AND YENT VALVES CURING CESIGN CASIS ACCIDENTS Table of Centents Title Page Atstract

a. Brief Statetent of Problem 1 ,

b. Sumary of Key Results 1 I

c. Conclusien la

, d. Ecccmtndations la Secticn 1.0 Purpose and Sum ary 3 2.0 ficthcds 5

< 3.0 Eesults 7

/. 0 Conclusion 7 E.0 Teceprendations 7 f.0 Referencc-s 7 7.0 Appendir. C a

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114EH TDR No. 266

. Rev. 1 Page 2 of 10 1.0 PLRPCSE AND SUfT.ARY The purpose of this -TER is to document the results of the analysis for the containment purge and vent valves regarding structural adequacy to withstard the fluid dynamic torques which would occur during the faulted condition of a loss of coolant accident (LOCA) within the containment vessel (References 0.10, 6.11 and 0.12), and the design basis seismic loads per design specification (Reference 6.4).

Per Reference C.6, valves V-23-13 and V-23-13 (Drywell Purge),'Y-23-15 and V-23-16 (Torus Purge), V-28-17 and V-28-18 (Torus Vent), V-27-1 and V-27-2 (Drywell Vent), and V-27-3 and V-27-4 (Drywell Purge), as slovn in Figure 1, were analyzed.

The NFC guidelines for denonstration of operability of purge and vent valves dated C/27/70 (Reference 0.8) and the NRC ccrrents made during tLe reeting 1. eld on 2/12/85 in Betbesda, l'aryland (reference f.17) have been incorporated in this evaluetion.

A. Consideratiers Per 1.FC guidelines (References C.0 and 6.17) tFe following iters have been considered:

1. Yalve cicsure rate is constant per Reference C.E. The valve respense tire follcuing a LCCA and each valve closing tire ray be cbtcined frcr reference f.13 and 0.14 respectively. TFe fluid dyncric terques tend to c1csc the valve. and the bearing fricticn terques always resist the operatcr.

2. Tc qualify valyc fron er opening of 30* to the fully closed pcsition, the fluid velocity and of fferential pressure across the valve et a specified disc position may be generated fror rass censcrvrtion and revertur couations (Feference f.1E).,

3. The setjcct valves do not use accurulators.

4. There are ro toroue limiting (evices for the air operated valves at Cyster Creek Nuclear Station.

E. Friction losses at fittings and valves in the piping systces tere considered in the analysis.

. 114 Dl '

TDR No. 260 Rev. 1 Page 4 of 10 C. The required safety factors are 1.5 and 3.0 for valve.sFaft in plane and out of plane respectively as long as the valve is located within five pipe diameters after the elbov (Reference 6.17 ) .

7. The drywell and torus pressure transients during DEA-LOCA were obtained from Reference 6.12 and shown in Figure 2.

B. Operator Evaluation In evaluating the structural integrity of the valve operator, the calculated torque during LCCA v:as compared with the allowable torque rating of the operator per manufacturer's data ~to see if the available safety factor is higher than the required per Reference 0.17.

C. Stress Ar,alysis Cased on the valve torque data (Fef. C.9) even mere conservative than those shown in Table 3, stresses gercrated at valve cceponents under combined sefsnic and LCCA conditions were analyzed using the design rules for Class 1 valves as detailed in Paragraph hE-3E40 of Section -III of the ASf'E Boiler and Pressure Vessel Code (Reference 6.1, hereaf ter referred to as the Code).

The calculated stress lcvels were. compared tc the code allowables, if possible, or the LCCA allowables of S0% of the yield strength of the raterial t! sed.

L. Sealinc Intcgrity The EPCf: seats for valves V-27-1,-V-27-2, V-27-3, and V-27 4 have the meximur cuculative radiation resistarce of F x 107 rads, and the . Nitron seats for V-28-17, Y-2P-lC, V-22-13, V-23-14, V-23-15, arid V-23-1C have 1 x 105 reds per renufacturer's information.

Lecer.tatiration chemicals have very little effect en these valve seats.

Valves at outside erbient temperature below C*F, if not properly acjusted, r:ay have leakage due to thereal contraction of tFe clastotcr. However, during LCCA, tFe valve internal temperature would he expected to be higher than tFe arbient, Ubich tends to incre u sealing capability after valve clesure. Since the prese.: of debris or dstage .to .the seats would impeir sealing, the scats cust be visually inspected and be replaced as required to ensurt sealing integrity.

114EH TDR l'o. 2f6 Rev. 1 Page 5 of 18 2.0 i;ETHCDS This study consists of fluid dynamic torque calculations, valve stress analysis, and operator evaluation. 14ethods are depicted as follows:

2.1 Torque Calculations The method described in Reference E.3.fer calculating torques of butterfly valves is employed in this analysis.

The valve torques arc calculated using the following formulas:

2 (1 )

Ts = Cs D Tb = 4.71 CE df 4 p (2)

Td=Ct C 4P (3)

Tp = 3.00 0 4 (4) tierc :

a Ts = seatirg torque in ft.-lbs.

Tb= bearing torque ir. ft.-lbs.

Td= fluid dynamic torque ft.-lbs.

Th= hydrostatic torque in ft.-lbs.

L= ~d iameter of valve in ft.

d= diameter of staft in inches.

ap= pressure drop across valve in psi.

Cs = coefficient of seating torque.

Ct = coefficicnt of dynamic torque.

f = bearing fricticn coefficient = 0.?E The torque coefficierts r'ay be obtained from the valve manufacturers (F.ef. 6.E). With the given drywell and torus pressure transients during DEA and valvo closing characteristics, the fluid velocity and the pressure drop across each valve at a specified disc opening engic betveen 0* and 30', can te generated from mass conservation ard momentum equations. Tte total valve torque is either a combination of bearir,g, seatirg and 1.ydrestatic tcrques when valve is closed or a combinaticn cf tearing.ar.d fluid dyreric torques tter valve is cpen.

l l -

1145H TDR No. 2E6

. Rev. 1 Fege 6 of 1C (Tc)) = Tp + Ts + Tp (disc in the closed position) (5)

(Tc)2 = 1.2 Tb+Td (disc in the open position) (f)

The NEC required safety factors are 1.5 and 3 for valve Lbaft in plane and out of plane respectively as long as the valve is located vithin E pipe diameters after the elbows (Reference 6.17).

The detailed torque calculations and available safety factors were documented in Eeference 6.1E.

2.2 Valve Stress Analysis This analysis used the design rules for class 1 valves as described in paragraph HB-3540 of Section III of the ASVE Boiler and Pressure Vessel Ccde (Reference 0.1). The requirements for class 1 valves are auch more explicit than those for either class 2 or 3 valves. The analysis is conservative since the design rules for class 2 and 3 valves are exceeded by those for class 1 valves.

Yalve cecponents were analyzed based on the conservative toroues cbtained by considering the maxirun containrent design pressure as the pressure ictediately in front of the valve during LOCA (Refercoce 0.S). The SSE seismic accelerations were sicultaneously applied in each of three mutually perpendicular dircctions.

Scismic loads uere conservatively taken as 1.5 times of the acceleration levels given in Reference 6.4. . The acceleratien constants gx, gy, and gz represent accelerations in the x, y, z directions respectively. In the coordincte system the x exis is defined along the pipe axis, the z exis along the shaft axis, and the y axis r.utually perpendicular to the x and z axes. Yalve orientation with respect te gravity was taken into account by adding an equivalent lg 1ccd to the seismic lead in the proper dirccticn. The acceleratien constants used are surcarized in Teble 1 in Appendix.

As sbcwn in Reference C.9, the calculated stress values vere-compared with the code ellevables, if possible, or the LOCA allowables of 00% of the yield strength of the materials used.

Code allowable stress levels are Sr fcr tensile stresses and 0.6 Se for sherr stresses. Ubere Sm is the design stress intensity value as defined in Appendix I, Table I-1.1 of Section III of the Code. The valve component materials are listed in Table 2 in Appendix.

3; -

~ll45H TDR No. 206 Rev. 1 Page 7 of 18 2.3 Cperator Evaluation To evaluate the structural adequacy of the valve operators, the LOCA induced operating torques for valves at different disc positions have to be compared with the allowable torques for operators to see if the available safety factors are higher than the required.

3.0 RESULTS The calculated torques and thc evailable safety factors are summarized in Table 3 in Appendix. The maximum torque absorption capability based on manufacturer's data is also presented in the same Table.~ It shews that the operators are structurally adequate for valve closing fror 30* open.

Teble 4 in Appendix compares tFe minimum valve body wall thicknesses with the. code required minimun thicknesses. All the valves satisfy the minimum wall thickness reouf rement of the Code.

The calculated stress levels of the main elements of the valves are

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listed in Table 5'in Appendix. Results indicate that all the valve cctpenents stresses meet the code allowable stress limits, or the LOCA allevable limits of 00% of the yield strength.

4.0 CCI:CLUSICE All ten (10) valves are structurally adequate if the valve opening angles are limited to 30* cr less under cerbined LCCA, pressure, and DEA seiscic loads. Structural adequacy is assured for the operators ar.d the vtive components.

E.0 EECCfEEf;DATICI:S

1. To ensure structural integrity, the valve openings must be limited to 20* cpen er less .frcr the closed positier.

2. To ensure sealing integrity, the valve -seats must be visually

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inspected and be replaced as required.

C.0 REFEREl:CES C.1 ASt'E Eciler and Pressure Vessel Code,Section III,1000 Edition.

6.2 Steel Valvcs, A!!SI ElC. 34-1977.

~

ll(5H TDr. No. 206 Rev. 1 Page C of 18 6.3 AWWA Stcndard for Rubber-Sected Butterfly Valves, ANSI /AWA C504-CO.

6.4 Procurcment Specification No. 492-7, Air Operated Butterfly Valycs, Non-N Stamped ASf'E III, Nuclear Safety Related - Class lEW, Oyster Creek Nuclear Generating Station, Revision 1, Date 4/8/01.

6.5 Valve, Applicable Data from Manufacturers, A.C. Shiau letter to A. P. Rcchino dated 5/15/01.

6.6 Robert E. Weltman letter to John L. Sullivan, Jr. dated itay 16, 1500.

C.7 Jin Knubel letter to D. K. Croneberger dated 11/1/00.

C.C The llF.C Guidelines for Lcmonstretion of Operability of Purge end Vent Yalves, dated C/27/70.

C.9 Cyster Creck Purge and Vent Valve Analysis Calculation Boot ,

Calculetion No.1202X-222C-A07.

0.10 OC-Plant Description l-!anual, Section 2.1.0 by GE and CEP, deted Occcaber 1572.

C.11 CC-Specification S-2ECE-CC, By BER.

C.12 1:PR-733, CC !!uclear Generating Station, liark 1 Containment Long

- Term Progran, Plart Unique Analysis Report, Suppression Chamber and Vent Systcc, August 1902.

C .15 Telecon bett.een S. R. Ccstadh t T. C. Fannirg, April 1CCE.

f.14 CC I;uclear Cereratirg Station Procedure Nc. C70.4.001, Rev.1, 10/lf/C<.

6.15 GPUl! Calculation 1.o. C-1302-022-5320-000.

6.1 C Cperability of CC Purge and Vent Velve During Design Basis Accident, T. G. I:anning letter to R. L. Lorenzo, dated 4/19/P5 (EM-05-1401 ) .

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6.17 Minutes of NFC/CPUN meeting on 0Cf.'GS Containment Vent and Purge Systen, P. F. Wells letter to l'. W. Laggart, dated 2/21/8E.

C.10 GPUN TR I:o. AT 4200.

li t.EM TDR No. 06f Rev. 1 Page e o f i f' 7.0- APPEEDIX Figures 1 and 2, as well as Tables 1 through 5 are presented in this Appendix.

'IDR No. 266

- Rev. 1 Page 10 of 18

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DIRECTIOi ACIIIINGICN ILES T

ACIIIDATIOi Shaft Axis is Vertical  ! haft axis is horizontal Values given Values usal ' Values given Valces uscd in Reference 6.4 in the Aralysis in Referer.ce 6.4 in the Ar.31ysis

't .

g, 3g 4.5g 3g 4.5g (pipe axis) gy 39 4.5g (bl)g (4,5+1)g 9z (3+1)g (4.5+1)g 3g 4.5g (shaft axis) e 9

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TARIE 2 MTERIAIS IVR VALVE CCNPCNENTS

• VALVE CINPCNENIS MmdAIS Group A (1)

Valves Group B (2)

Valves Group C (3)

Valves Body ASIM-Al26 Class B ASIM-A126 Class B Disc Carbon Steel - Plate ASIM-A536 SA351 CEBM Shaft Ni-resist No. 2 ASIM-A582 17-4 PII condition 1075, 316 S.S.

SA564 Shaft Key ASIM-A582 ASIM-A304, Grade 86-30H SAE1035 Bushirgs ASIN-B438, 'lype 2 Teflon Teflon 4 Disc Pins 304 S.S.

y 17-4 Pil condition 1075, 316 S.S.

SA564 Operator Bolts Carbon Steel SAE Grade 2 SAE Grade 2 Note: (1)

Group A valves are V-27-1, V-27-2, V-27-3, and V-27-4, the centerline 18" valves.

(2)

Group B valves are V-28-17 and V-28-18, the Fisher Gontrols 12" valves, (3)

Group C valves are V-23-13, V-23-14, V-23-15, and V-23-16, the Fisher Controls 8" valves .

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ax*

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p;se at 3o* Dise at 15* Dise- at s* Dise at t*

b ret.\ Alle.~bl* C*futy S*faty Total AllemsI< Sataty fly, Valve C.fatt T. tat nib uka f hty S.faly Total Allmeblo s.t.ty s.pty 4,;g g,y v.Ius T. qui = Ts.ter fut.r v Iv.a r.1pafa p,ta futar v.Iu TageaV Tostoe k Ler Valan y<'fa (msta Mter

( ' *; Tap,)

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tle-6 (in-th) w & xa fin-th) t In-th) nas%w tin.5\ tia- th)

Tagua opeJw T**jna spada ^^'"

pwd Ter(*= ,

tin-tG tin-All M4=i4 V-17-l 2,ny is,zzJ 3 z,48l r.P v-17-1 18 783 ' '.n 3 ze.7 3 f.i 14,223 4.r 3 1,7d a. If,223 3 A

v-11-3 v-t7-4 18 774 l'<**I ***" 3 2,48' ' ', * *3 '*f 3 3,"l l',n3 .r.3 3 4187 p g,u3 4,8 3 v-2 8-17 1

B y.ss-Is t s. 78 4,8** il E 3 I,' ' 1 4,8eo 4.I 3 1,197 4,8co 3.7 3 g,3o3 4,g , 3,7 3 V-13-Il y.al-74 8 67I 4,8 " 71 3 671 4,8" 71 3 671 4,8 *o 72 3 671 4,d eo 71 J C

v-al-'t v-x3-Il O b7' 48n 71 3 iTI 4,8 00 7.1 3 61I 4,8 ao 71 3 61I 4,soo 71 3 Dise C a l Valv' V= g,,a ._r ataly cles<d Valua . a.

j, 4tourn, sty.1;., Sca< V=l** Tata f* fmeta y.se tial ()[5Yr."- ) W v-17-I i

y-s.1-2. Is 3,143 11,*T$ l'T I A

v- 27-3 y-sy -y is ),e16 iss ot8 3. l* I v-447 gxs

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I v-23-is 12 is55./ 4,3ee f.2 g ,$ $

V-ni-II '5 i v->3-se a Ytt 4,8=* 8.6 1 g

l y->3 -tr g v->J-ti 8  !!! 4,8** B6 i Teil's Eack Valva T*qua *~l S fy Ha+3;n l at Diff& ?rse iPosits' ens.

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TNIIE 4- MINIMM DCI)Y MEL DHCKNESS VALVE VALVE DESIGNATICN VALVE SIZE JCIUAL MINIMM (in.) 00tE RICUIRED MIN.

DODY Md1 TlHCENESS PER ANSI TIIICKNFW (in.) 16.34 (in.)

A V-27-1, V-27-2 18 0.728 0.48 V-27-3, V-27-3 B V-28-17, V-28-18 12 1.0 0.38 C V-23-13, V-23-14 8 0.75 0.31 i V-23-15, V-23-16 I

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TurE 5 fuewn m fmES ANMNSIS VAINE VAINE SIMSS SIM:SS 1EVEL ALIONKE SIMSS '

CH31P (IMUfNr NAME NO SYMVL (PSI) (PSI)

Primiry Martirane Pm 2423 600 , 2h000 -

Primary plus swordary Op stress due to inth 7012 '9a 0.9 ff pressure 12600 , 27000 P i pe Axial Pal 4574

% mcdon fh900 , h0 A stress Bentliny Peb 16631 1 5 Sn 09 lh900 , 2h00$

(- -

'Ibrsion Pet 8648 1 00 , 2 00 V-27-3, 1hermal secortlary Ot 444 V-27-4) Stress 3, o,99 12600 , 27000 Primsry plus Sn 23885 sectFR3ary stress 3 an 0.9 (f 37800 , 27000 Disc Ort 2irwd Ikniirvy S(l) 4032 Stress on disc caterline 0.9#f 40500

'!brsicrul shmr Stress Catairni Iher stress S(9)

S(6) 34 kM 6030 Og thaft Cabirn! bertlirvj S(5) 8884 stress 0.9%

36000 Cmbirni stress S(4) 11931 0.9%

(shear ard berditwJ) 36000

! haft Key Shear stress on S(16) 11664 O.9 My key 36000 Disc tapper thear stress in S(17) 23999 pins pins 0.9 (f 40500 Bushings thirinj stress in S(21) 2191 Orpressive allowable (shaft bearing) bushirJs 4000 Operator Tension in bolts Sl54) 0.9 (p Mountity; +S(55) 1530 51300 3 ntr dim? to S(57)

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_Torgie_ on lolts 430s 0.9 (f [

51300 m Orbient stress in bolts S(53) 5463 Qgg O N

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VM.VE VALVE :meM S'IHESS 11 VEL ALIONitZ S!1ESS GOJP GNPOENT NAME AND SYMEL (PSI) (PSI)* ,

Printry Mrvrbrane Pm 1360 600 , h00 Prinuy plus socorduy Op 3825

• Btsess due to interrul 9n 0.9 g m sure 12600 , 2700 pit e Axial Pal 3820 I .5 fim 0.9 (p Body roiction . .

18900 - 27000 B ,

stress Berdiry Pob 9050 1.5 Sn 0.9 r, 19900 - 27006 1braion Pet 7211 1.5 an 0.9 r (V-28-17 ^ 27 V-28-18) 'therlml seconlary Ot 468 an o,9 rf D C88 12600 , 27000 Printry plus Sn 13237 3 an sectnLuy stress 0.9 C 37800 , 27 Disc Cbnbirni Ikniirn S(l) 2822 an Stress on disc centerline 17900 1brsiorul shear Stress S(9) 9869 0; an Cmbirni Smar stress S(6) 10134 Q95 Shaft Cmbirnt bendirn S(5) 6747 an stress 46000 Cmbirni stress S(4) 14054 an (shear ard bendirg) 46000 Shaft Key Shair stress on S(16) kcy 21531 0.9 F 7 90000 Disc tagper 9 mar stress in S(17) 27483 0.6 an Pins pim . 27600 Bushirns Ibarirn stress in S(21) 1349 Cmpressive allowable (shaft bearing) burhirns ,

10000 Operator Tension in bolts S(54) 27921 0.9f Peunting f

+S(55) 51300 Ega hr due to Tbrque on bolts S((57) 21899 0.9 Fr 51306 N*gZ(D Canbirxx1 stress in bolts S(53) 45613 Of38 U

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VALVE VALVE stics STi m 1EVEL ALIIM212 SIRESS GRWP CDSDOFF ?W E T @ SYMDOL (PSI) (PSI)- .

i 194  !"

Primuy Mrt> rant? Om yg Primuy plus stuxtl.uy Op.

3927 stress duo to interrul 500 pressiare 79 37 I pige Axial rus!

C  % reuction 21416 1.5 9n

. stress Dervilrs; INb y37g (V-23-13, V-21-14, w rsion Pet 16440 1.5 9n 21750 V-23-15, V-23-16) 'thermil socorvLiry Ot 419' 9n Staess 14500 Prirary plus Sn 25629 3 an soccniuy stress 43500 Disc Orbirwr1 Denjirv; S(1) 3246 0.9 yf Stress on disc centerlite 27000 Torsiorul sintr Stress Cabirni Shear stress S(9) 11988 OQ S(6) 12296 0.6 an smn 9mft Cmbinni lev 3irq S(5) 14599 su stress 22200 Cmbinal stress S(4) 21599 9n (shear an! bending) .22200

' Shaft Key Shear stress on S(16) 22318 0.9 #

key 50 Disc tapper shear stress in S(17). 30308 0.9 Q pins pins 31500-Bushings Bairing stress in S(21) 1612 Cmpressive allowable (shaft bearing) bushirns 10000 Operator Mxanting Tension in bolts S(54) 24010 0.9 513 yza gQQ

+SQ5) h die to

'Ibrque on bolts S (57) 30049 0.9 Fa y vf

• • 2 a -* O Ort)inud stress in bolts S(53) 50484 SIh? ^

m N CD

_ _