ML20093D448

Rev a to Seismic Analysis of 4 Inch,150 Lb Carbon Steel Motor Operator Gate Valve

ML20093D448
Person / Time
Site:	Catawba
Issue date:	04/09/1979
From:	Brown S, Chen L BYRON JACKSON PUMP
To:
Shared Package
ML20093D318	List: ML20093D315 ML20093D335 ML20093D349 ML20093D360 ML20093D381 ML20093D406 ML20093D418 ML20093D448
References
NSR-401JBB3-4, NSR-401JBB3-4-RA, NUDOCS 8410110243
Download: ML20093D448 (58)

Text

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Nudlear Valve Division s [on"s +n a men d

E"sy RECCRT NC. NSR uC1JBB3 3 Eausament pAGE 1 of 53 Scrg.Wamer Ccrocration 7500 Tyrone Ave., Van Nuys, Cahfornia 91409 DATE 7 FEB 79 REVISION A

,TE 9 APR 79 my A?330VED

==== ons DUKE POWER CO.

37g. JUL 131979

s. x. DLACKLEY. JR.

M POWER COMPAMV CHigF ENGINEER EM MINHmM By: MECHANICAL DlVISION Nuclear Safety Related l STATUS!

INIT.

! CATE n

DIV SEISiIC ANALYSIS CF civit u INCH, 150 LB

\\-\\V\\\\

CARSCN STEEL CCH D 3 MCTCR CPERATCR

~~

GATE VALVE ctEcT r

I' <

FCR

' '(/)

'O 'th f

CUKE PCWER CCMPANY

' /' O CATAWBA NUCLEAR STATICN f

4, 4 r,,

</~,,[;,l UNITS 1 AND 2

' / (,,'jk

' ~ ll.

BY NUCII.AR VALVE DIVISICN BCRG-WARNER CCRPCRATICN 7500 Tyrone Avenue Van Nuys, California 91u09 J N M

'205 00-0 669 8410110243 841011 PDR ADOCK 05000413 P

PDR

\\

REPORT NO. NSR401 JBB3-004

.i ' NuclearValve Div..ision PAGE 1.1 REVISION A

CH ANGE RECORD SHEET o^rz 9 ^Pa 7a REVISIONS PAGES AFFECTED REV DATE DESCRIPTION APPROVED BY kiVISED

'ADDED REMOVED LTR APR 1.1 Added Change Record Sheet

,T-d' A

9 1979 1

Revised title page changed from N/C A

to Rev. A 4 ttach Added Attachment 1 Static Deflection A

1 test results i

Prepared by:.

3)"

m.v> t/

S. M. Brown Engineering Test Lab Supe rvisor ha Lh D409?f Approved by:

Llwel Chen Project Engineer i

s

+.-r+

,-w-n

..ne,,..-,-,,n,,,,,,,-----v-,g,,,

.----n-,m,,,-v,-

-e,--a,,,-,-,an,m,--we

-,,----,mg.,-.,en-m-.-

w.---

C Nuglear Valve Division s "ons Engy REPCRT N0e NSR 301JBD3 u teammeR Equipment WARM Borg-Warner Corporation PAGE 2

7500 Tyrone Ave., Van Nuys, Cahfornia 91409

- The following seismic analysis report has been prepared in accordance with the design requirements prescribed in Duke Power Company, Catawba Nuclear

-Station, Units 1 and 2, Specification No.

CNS-1205.00-6, Addendun 6,

- December,1978, ASME Section III Carbon Steel Gate, Globe and meck Valve.

VALVE IDENTIFICATICN BCRG-WARNER CO. N.V.D.

DUKE PCWER CO.

MILL PCWER SUPPLY CO.

PART NO ITB4 NO.

LIST NO.

301JBB3_n 02B-400 CN-0150- 12 P

Prepared by:

p )

&y J.-f~ ~l9 ALMw-Shou-Jen

'ang

(

Analytical Engineer Paviewed by: M'-

or.o7/7 Liwei men Project Engineer Approved by:

R. E.

Holder Manager, Advanced Design g

r s

Nuclear Valve Division m

Energy REPCRT NC. NSR n01JBB3.u

~. - -

e.

Equipment PAE Borg-Warner Corporation 3

7500 Tyrone Ave.. Van Nuys, California 91409 TABE CF CCNTENTS SECTICN DESCRIPTION PA E 1.

INTRCDUCTICN 7

2..

SLNMARY 9

3 VALVE ASSEMBLY 10 31 Valve Body-13 3.1.1 Loading 13 3.1.2 Cross Sectional Properties 18 3.1.3 Stresses 18 3.2 Yoke 29 3.2.1 Leading 29 3.2.2.

Cross Sectional Properties 30 3.2.3 Stresses 33

-3.?

Body and Bonnet Joint 37 3

MAXIMlN EFECTICN CF CPERATCR 45 5.

NATURAL FREQJENCY CF VALVE ASSDiBLY 47 6

CONCIUSION 53

-- -5 6e. peg, WY y

I 4

..a Nuclear Valve Division _

g Energy REPCRT NO. NSR h01JBB3 u PAGE 4

Borg-Warner Corporation

.7500 Tyrone Ave., Van Nuys, Califomia 91409 '

NCMENCLATURE 2

A

= area (in )

a

= angle (degree) b

= angle (degree)

C

= pull (kip) d-

= diameter of a circle (in) d

= deflection (10 8 in)

E

= modulus of elasticity (ksi)

.F

= thrust (kip)

F

= flexibility (in/lb) f.

= natural frequency (Hz) 2 g

= acceleration (in/sec )

I

= moment of inertia (in")

J'

= polar mcznent of inertia (in")

L

= length (in)'

M

= moment (in-kip)

M

= c: ass (lb) m

= weight- (Ib) m

= reciprocal of Poisson's ratio P

= pressure (ksi)

PI

= 3.1a159265, ratio of ciretsnference to diameter of a circle R

= reaction force (kip) r s

r

= radius of circle (in)

S

= shear force (kip)

--e

-~-,-~------.--.-,---.4.

9 s,y.

c- - -,..,

r-

--.,y,,

~,.4

..~me,-

m.

,.p Nuclear V:lve Division Ewgy REPCRT NO. NSR 301JBB3 u man enemme Equipment pg 5

Borg-Warner Corporation 7500 Tyrone Ave.. Van Nuys, California 91409 s

= stress (ksi)

SIE

= seismic load factor S(N

= sumation T

= torque (ft-lb, or in-kip)

-t

= thickness ~(in) y

= mode shape w

= natural frequency (radian per sec.)

x,y,z = space coordinates in cartesian system x

= distance (in) y

= distance (in)

Z

= section modulus (in3)

[F]

= flexibility matrix

[I]

= unit matrix-

.[M]

= mass matrix

'[v]

= mode shape superscript:

T

= transpose of a matrix 4

subscript:

I a

= axial b

= bending, bolt i

= inside, internal i

= row index of matrix j

= colunn index of matrix J

s.

..m..

r

s

.. *. Nucieer Valve Elvision~

R annen Energy REPCRT NO. NSR 401JBB3 3 m Equipment PAE

_ Borg-Wamer Corporation 6

7500 Tyrone Ave., Van Nuys, California 91409 m

= meridian

-max-

= maximal ~ - value o

= outside piping p

=

r

= radial s

= shear tangential t

=

y

=. yoke 1,2,3- = sectional. conditions f

e f

aW-p',

y

=., ;

..:.u

. Nuclear Valve Division E muuMR Energy REPORT NO. NSR h01JBB3 u -

Equipment PAGE Borg-Warner Corporation 7

7500 Tyrone Ave.. Van Nuys, Cahfornia 91409 4

1..

INTRCDUCTION:

Re seismic and operability analysis report of the following valves has been performed for the designs detailed in Nuclear Valve Division of Borg-Warner Corporation ' drawing ntsnbers, as shown.

Design specifications 'are prescribed in Duke Power Company, Catawba Station, Units 1 and

2. Specification No.

CNS-1205.00 6, Addendte 6, December, 1978, ASME Section III Carbon Steel Gate, Globe and meck Valve.

Re valve assembly is built to the criteria of ASME, B & PV Code,Section III, Class 2 or 3 Nuclear Valves and Duke Pour Company Safety Class B or C.

VALVE. PRESSURE -

MATERIAL VALVE OPERATCR N. V. D.

SIZE RATING TYPE ASSB4BLY (INCH) (LB)

DWG. NO.

u 150 CARBCN STEEL MOTCR GATE 801JBB3 3 In ~accordance with the design requirements, the valve (s) and appurtenance (s) shall be qualified by the procedures and guidelines of the Duke Power Company, Seismic Design Manual. Basically, two

- modes of operation are considered: Upset Mode and Faulted Mode. For

- Faulted Mode (Safe Shutdown Earthquake), a seismic load factor (SU) of 3.0 g' shall be applied in each of two orthogonal horizontal

- directions in combination with a SLF o f 2.0 g in the vertical direction, all action simultaneously.

Re Upset Mode (Operational Basic Earthquake) is similar to Faulted Mode, except that the SU values shall be taken as 8/15 of the respective values of the Safe Shutdown Earthquake.

Seismic Design Manual, Section 3.2 outlines a procedure for qualifying rigid system by the " equivalent static analysis" method.

Re method consists of perfoming a static structural analysis of the equipment under equivalent static forces conservatively representing the actual dynamic loadings.

Seismie forces or. each component of the equipnent are obtained by concentrating its mass at its center of gravity and multiplying by the appropriate seismic load factors (SV). Rigid systems are defined as systems W ich have no natural frequency less than 33 cycles per second.

All the values used within this analysis are the actual dimensions taken from the detail prints.

In - all cases, the values are greater a,

-...u..

4 Nuclear Valve Division g Energy FIPCRT NO. NSR u01JBB3 3 i'"'"'

PAGE P

Borg-Warner Corporation 8

7500 Tyrone Ave., Van Nuys, California 91409 1.

INTRCDUCTICN:

than respective d and t values required by ASME Boiler &

Pressure Vessel C8de, Table NC 3511-1.

m Standard engineering practice shall be used to determine the maximun stress conditions in all portions of the equipnent.

It shall be demonstrated that the maximun stresses meet the -acceptance criteria for the selected valve assembly materials defined in Section 6.0 of the Seismic L4 sign Manual.

NVD has used the 1000F pressure rating of the applicable valve pressure class along with faulted mode loading W.en calculating stress levels. As a conservative approach, upset allowable stress limits are compared to faulted loading, thus substantiating the design under all faulted and upset conditions.

The ASME Class 2 valve design criteria is based upon the rules of ASME, B & PV Code, NC-3200 and standard engineering practices. The allowable stress limits of 1.0 s$d (local) primary membrane plus and 1.5 s shall be taken m

for the primary membrane (P ) a primary bending ( (Pg or

)+P) stress categories, B

respectively, for. pressure b undry components. The design stress intensity values s for Class 1 components are cited in Table U

I-1.1 through I-1.3, ASME B & PV Code. For non-pressure boundary ccmponents, the stress limits are taken as

0. 6 s,l ( AISC allowable working stress limit) for upset mode and 0.9 s for y

emergency and faulted modes.

An. idealized structure system shall be modeled to simulate the vibratory mode of the valve assembly.

The calculated minimun natural frequency of vibration shall be examined to satisfy the specification limit of 33 cycles per second.

s v

-4,..,,..,.,,y,w--

r w, -,

Nuclear Valve Division Enwgy REPORT NC. NSR E01JBB1.3 4

Equipment i

erg-wamw corporate PAGE 9

7500 Tyrone Ave Van Nuys, California 91409 2.

SlNMARY:

ASSDiBLY DRAWING NO.

_ _ MMMF ^ -

MATERIAL ALLCWABL5

' CALCULATED UPSET MCDE FAULTED MCDE VALVE SECTION SPECIFICATICN (KSI)

(KSI)

BCDY, MAIN RUN SA182 F316 27.00 18.01 BCDY, NECK SA182 F116 27.00 1.50 YCKE,ErS SA182 F?16 18.00 7.0a BCLT,BCNNET A56u TY 630 115.00 22.39 FLANG,BCNNET SA182 F316 27.00 17.82 REQJIRED CALCULATED DESCRIPTICN CF MINIMLN FREQJENCY NATURAL FREQJENCY VALVE SECTICN (CYCE/SEC)

(CYCLE /SEC)

VALVE ASSDiBLY 31.00 42.52 1

mgg_m_________-___-_____ N -----------*"*****

e 0

/

i t

3-~m.

-_<-,,-m~

c.

Nuclear Valve Division '

m REPCRT NO. NSR h01JBB3 u y Energy A

Borg Warner Corporation 10 7500 Tyrone Ave., Van Nuys, California 91409 3

VALVE ASSEMBLY:

The valve. assembly has the general configuration which can be represented -in a simplified sketch as shown in Figure 3-1.

The approximate center of mass for each component is referenced with respect to the valve body main run.

An evaluation of the structural integrity is made by reviewing the state of stress at critical sections as designated in Figure 3-1.

A conservative estimate of the ccmponent dead load weight and

. basic physical dimensions is obtained from the drawings and tabulated in Table 3-1.

As required in the seismic design specification, an evaluation shall consider tw modes of operation - upset mode and faultM mode. In this stress analysis, a conservative approach is taken

'by qualifying the structure to th'e maximm. design acceleration and using the -acceptance limits for the upset mode.

This maximm acceleration 'is based upon the seismic load factors for the faulted mode, and expressed as smax = [ SLFH + SLFH + (1.0 g + SLFy )]

gmax = ( 3.0 g + 3.0 g + 3.0 g ).= 5.20 g Since the structure may assume any arbitrary position, the maximm design acceleration shall be applied simultaneously along the orthogonal axes of the valve assembly.

In addition, the valve shall consider the maximm operational j

stem thrust (Fat) and torque (T ) imposed by the a

. operator.

Tq = (Fst)(stem factor) tere stem factor is determined basically in accordance with the stem thread dimension assming the coefficient of friction being

~0.15.

For the case of manual operated valve, a 150 lb (max.)

operator pull (C) is considered to be applied at the rim of the hand teel.

4

=

Nu.:

REPORY NO. NSR401JBB3-4 Musteer Valve Division 11 aces-womer comoratkm PAE 7500 Tyrorie Ave., Van Nuys. Cahfomia 91400 3

VALW ASSEMBLY:

~

3 center or m as h

Operator 9

1 r"

gl1 Y1 l

l i

Yoke 4

Stas

./

Y l

t 2

W

-Bonnet 76

,4,

1. 1. 1. s g

SI@

1 3

w wn G -- ww-g g y7 7

l r

i l

Valve Y

l 5

Body Y5 l

Datus Nss!"

• 1 1

5

• 2 O

t FIGJRE. 3-1 VALE ASSDtBLY i

- -. - +.,,

,e,-,.

{

.: - - i I Nuclear Valve Division g Enwgy

- REPCRT NO. NSR 301JBB3 3 PAGE

- 12 sorg warnercorporation

. 7500 Tyrone Ave., Van Nuys California 91409

3.-

VALVE ASSDiBLY:

TABLE 3-1

.CCMPCNENT LOADS AND PHYSICAL DIMENSICNS

-3 m

(1b) 206.000 3

2 (1b) 50.000 m

3 (1b) 38.000 m

m.

(1b) 95.000 a

m5 (1b) 8.000 total (1b) 397 000 m

.y3 (in) 30.100 (in) 18.750

72 73 (in) 7.600 ya (in).

1.500 75 (in) 3.000 Y-(in) 11.850 6

y7 (in) 6.000 x3 (in) 6.000 1.500 2

(in) x x

(in)

.750-3 z3

-(in)

2. 81 3

.T (ft-lb) 19.200 q

F (kip) 2.250 st 0.000

-C (kip)..

s

-T-i-

7 y

y-%

m r.m c

,..,,_,,.y

,,,y 7

_m,

I-i i Nuclear Vah[e Division

-@ h Energy REPORT NO. NSR 801J383 u annan Equipment PAGE 13 Borg-Warner Corporation 7500 Tyrone Ave.. Van Nuys, Caiifornia 91409 3

VALVE ASSEMBLY:

-3.1 Valve Body:

An evaluation of the maximun body stresses shall be made for the zones denoted on the preceding valve body sketch.

The valve body cross sections are located in the main run and neck.

3 1.1

. Loading:

A measure ' of the maximun force resultants at each zone is obtained by applying the maximun accelerations g along max the orthogonal axes, simultaneously.

.3.1.1.1 Plane 1-1: (Valve Body - main run)

- Assuming simple support conditions at the weld ends as shown in Figure 3-2.1, the force resultants at the crotch region can be derived as follows:

Mmax = Tmax = net exterral moment and torque (m y3+m272*373*uYu 3

+(*1x3, m3z3) max) Emax z

R

= simple support reaction

=Mmax /2x3 + (mgun2*n3+muurg)Smax/2 F

3

= thrust = (m3*n2*n3eaur5)gmax/2

.S

= shear R + C 3

M

= moment. Rx2 3

T

= torque = Tmax/2 3

The.nunerical values are tabulated in Table 3-2.1.

W 4

.,.._,y-

T

(-

Q

- Nuclear Valve Division R wan un Enern REPORT NO NSR 301JBB3 3 Equipment - PAE M

- Borg-Warner Corporation 7500 Tyrone Ave Van Nuys, California 91409

- 3.

- VALVE ASSEMBLY:

3.1.1.2

' Plane-2-2: -(Valve Body - neck)

At plane.2-2, the force resultants, deternined by asstning-the neck weight is one third of the total valve body weight

'(Figure 3-2.2), and can be expressed, as:

F2 = thrust = Fst.+ (m3+m2+m3+mu/3

+mS) 8 max

_ S2 = shear = (m3*n2+m3*nu/3) Emax + c M2 = cement - (m3 (y3-y5)+m2(Y2-Y5)+m3(y3-Y5)

(1/3)m (y3-y5)] Emax

+

a T2 = torque = m3(x3, z3) max 8 max

'&.e numerical values are tabulated in Tab 1'e 3-2.2.

w h"

0 y

.,3-5,,4 -t

--,,n-

,,.,...-.4 n,--

. - - -,, - -.,, -, ~

e-

- i. -- Nuclear V:lve Division s "ans -namun Energy REPCRT NO. NSR 801JBB3 3 Equipment PAGE Borg-Warner Corporation -

15

. 7500 Tyrone Ave., Van Nuys, California 91409 3.-

VALVE ASSEMBLY:

3.1.1 3 Plane 3-3:

The force-resultants at plane 3-3 (see Figure 3-2.3) are

- derived as follows:

+

F3 = thrust. Fat + (mg+m2'33 *5 8 max 3

.S3 = shear = (m3+m2+m3) 8 max + c M ' = moment = [m3 (y3-y7)+m2(Y2-Y7) 3

+m CY3-Y )3 Emax 3

7 T = torwe = m3(x3, 3} max 8 max 3

The ntnerical values are tabulated in Table 3-2.3 s

t 6

i s

I e

\\

@ s.

4

%J'

-f e

w

.,.., ~. -.,,,,,,

-,.,,n-..

,,,,,,,,,,.,,,.,.,,-~-n,,

-Nuclear VCiv0 Division Energy REPORT NO.NSR401JBB3-Equipment Borg-Warner Corporation PAGE 16 4

7500 Tyrone Ave., Van Nuys, California 91409 3

VALVE ASSEMBLY:

x2

=

lb I

J (i

i l

l l@ U 7Ytr h

R 2x 3

FIGJRE 3-2.1 MAIN Rtal SECTION

'1 Operator "2

Yo h & Stas

'3 lbnnet

'4/3 v0 Valve !bdy g _ _ __ __ _ __ __ g FIGNtE 3-2.2 IECK SECTIoll ug Operator Yoke & Stem up g

Bonnet m3 g _..__ __ ____ _ _ g FIGURE 3-2 3 THREAD RELIEF SECTION

.w

-s

+~,

. Nucieer Valve Division y Energy REPCRT NO. NSR 801JBB3 3 sene

'17

"'8 PAGE Borg-Warner Corporation.

7500 Tyrone Ave Van Nuys, California 91409 3

VALVE ASSEMBLY:

TABII 3-2.1' SEISMIC LOAD RESULTANTS AT PLANE 1-1 F

(kip) 1.032 3

S (kip)'

u.a77 g-M (in-kip) 6.715 g

T (in-kip) 20.667 3

TABLE 3-2.2 SEISMIC LOAD RESULTANTS AT PLANE 2-2 F.

(kip).

3.985 2

S (kip) 1.693 2

M (in-kip) 33 751 2

T (in-kip) 3.013 2

TABLE 3-2.3 SEISMIC IfAD RESUL;AffrS AT PLANE 3-3 F.

(kip) 3.520 3

S (kip) 1.529 3-

(in-kip) 28.307 i

M3.

T (in-kip) 3.013 3

q' gr

--pw iv y.

-m-+w-w e m..

e am---,ypy.,yy.,

3,.,,y-,

-w..-

-7

_g--.vw, m.

,p%,-+.y,,5 9

m y

Nuclear Valve Division R g Energy REPCRT NO. NSR n01JBB3 3 s

"i"*"'

PAGE 18 Borg-WarnerCorporation.

7500 Tyrone Ave., Van Nuys, California 91409 -

'3.

VALVE ASSEMBLY:

3.1.2 Cross Sectional Properties:

For the critical zones on the valve body, the cross section area and inertia properties are computed as follows, (Figure 3-3)

A = Area = [(r )2 - (r )2](PI) g g

max : Imin = [(r )" - (r )"](PI/h)

I=I o

f J=2I mb Were ro = outside radius r1 = inside radius All the numerical values are tabulated in Table 3-3 3.1. 3 Stresses:

3.1 3.1 Due to Seismic Imads:

-Seismic stresses are derived for the valve body, by using the following expressions sa = axial stress : F/A + M r /I o

3 = shear stress = S/A + T r /J s

o where F,S.M,T are force resultants (see Section 3.1.1.

Table 3-2) and A,I,J are cross section properties (see Section 3 1.2 Table 3-3 ).

All the nts:erical values are tabulated in Table 3 u.

l

.-e-~.-

~, - - -

.w

,.e.

-,,.m-,

!EE*at

?EPOST ID.NSR401JBB3-4

' Nuclear Valve Division sorg warner corporanon PAGE 19 7500 Tyrone Ave.. Van Nuys CaMornia 91409 Y

e

=

_X i

I

, yj

-r

',t

\\

% @$l'/

/

h H

'jQf ' ~r

~

ji:

' ' :ll/,'l!

i

/,

s 1 *_

r PLANE 1-1 i

I

-r PLANE 2-2 FIGURE 3-3 CROSS SECTIONS OF VALVE BODY t

}

e 1 =a FIGlmt 3 4.1 MEMBRANE STRESS AT PLAE 1-1 r g s

81t FICuat 3-4.2 MEMBRAE STRESS AT PLA E 2-2

~~

'.:. Nuclear Valve Division l y Enesy

-REPCRT NO. NSR 801JBB3 3 m

sorg-wamer corporanon PAE 20 7500 Tyrone Ave., Van Nuys, California 91409 3.

VALVE ASSEMBLY:

TABE 3-3.1

. CRCSS SECTICNAL PRCPERTIES AT PLANE 1-1

.r

.(in) 2.560 o

ri (in) 1.990 I

' ( in")

21.u16 o.

2 A

(in )

8,1u8 o

J (in")

32.831 o

TABE 3-3.2 CROSS SECTIONAL PRCPERTIES AT PLANE 2-2 r

(in) 3.6h0 o

ri (in) 2.810 I

' (in")

88.910 o

2

.A (in ).

16.819 o

J.

' ( in")

177.820 o

}4 1

' Nuclear Valve Division

["sasWMem 'nugy REPORT NO. NSR 301JBB3 u E

e

'" W PAE 21

' Borg Wamer Corpcration

- 7500 Tyrone Ave., Van Nuys, Cakfornia 91409 3.

' VALVE ASSEMBLY:

-TAB 2-3 2.1

. SEISMIC STRESSES AT PLANE 1-1 s

(ksi).

.929 a

3 (ksi) 1 785 3

TABE 3 3.2 SEISMIC STRESSES AT PLANE 2-2 1

t s

l(ksi) 1.619 a

s (ksi)

.162 s

O s

I b

w w*

t e

y,--,-

g,,,wve.r g.,,e-n-+----r.,e e-e,+r,w,-

a _ m,n. e w p, m e p s.,, g,-mgm,,,s,,,m-n_,,g.w--,re

,-,~~--,y,gmm_-.-,r,~

L 1

'l Nuclear Valve Divisiswa Energy REPCRT NO. NSR 301JBB3 3 m

PAE sorg-werner corporauon 22 7500 Tyrone Ave., Van Nuys, California 91409 3

iVALVE ASSEMBLY:

3.1.?.2 Due to Internal Pressure, Piping Rection and F.ermal Effect:

Stress due to internal pressure, and piping reaction themal effect and other sustained or occasional loads on each plane can be obtained as follows 3.1 3.2.1 Plane 1-1:

(Valve Body - main run)

A.

Internal Pressure:

?.e membrane stresses due to internal pressure in the meridian, tangent and radial directions are calculated by following three equations respectively:

3 ri (2t) 81m = P

/

~

sit = P3 ri/t sir = - P /2 3

where rt = inside radius (see Table 3-3) t = wall thickness : r -ri (see Table 3-3) o P3 = standard calculated pressure (cr design pressure)

B.

Piping Reaction:

The moment applied simultanecusly in Plane 1-1 due to piping reaction is detemined b/:

M s (Bending moment) p=Zp Tp = 1. 2 Zp s (Torsional moment)

The stress (ksi) in meridian direction and shear stress due to piping reaction will be:

,.,.--,e m..,,_,nm--pe,-,-r

-,e-w.-r-n+---w~w-,--a--

~

!L Neuleer Valve Division

@ muunn Enwgv REPCRT NO. NSR u01JBB3 a m Equipment PAGE 23 Borg-Warner Corporation 7500 Tyrone Ave., Van Nuys, California 91409 3

VALVE ASSD4BLY:

s

= M r /I p

p o s

= T r /J 3

p o where Zp=I/rp p

o

= section modulus of the pipe and s is yield strength of the pipe.

3 C.

Rermal Effect:

Re thermal secondary stresses due to transient effect shall be calculated en the basis of a continuous ranp 0

change in fluid temperature at 100 F/ hour.

Per ASME Code, ND-3585.2, the thermal secondary stress s7 can be determined by:

• T 8t1 + 8t2 where stl = stress component resulting from wall temp.

gradient ( ASME III, Fig. NB-3585.2 (c)-2) t2 = stress ccmponent resulting frcm wall thickness s

variation

=K K1 dT 2

K

= product of Young's modulus and linear thermal 2

expansion coefficient K

= stress index due to structural discontinuity g

( ASME III, Fig. NB-35u5.2(c)-3) dT = mayhn a temperature difference between thick and tnin walls ( ASME III, Fig. NB-3535.2(c) a)

For those valves with higher temperature change rates than 1000F/ hour, the thermal secondary stress will be determined per NB-3553, where the value of di in the above fonnula is obtained as the product of Cu and

U

.g

~

Nuclear Valve Division my Energy REPCRT NO. NSR 301JBB3 u PAGE 24

. Borg-Warner Corporation 7500 Tyrone Ave. Van Nuys, California 91409

3. --

' VALVE ASSEMBLY:

dT 4te3xs W.ich are the maximun magnitude of the diff4rendein average wall temperatures and the maximun specified step change in fluid temperature respectively (see NB-3533).

D.

Stress Intensities:

Stress intensities can then be calculated as:

8m: 8a+81m + 8p + 8T 8t: 31t + 8T

/" + 8 3 m + 8 )/2 + [(s -8t s

sg = (a t

m m + 8 )/2 - [(s -8 ) /" + 8 3 s2 : (8 t

m t s

83: 81r-812: 81 - 82 a 3: 82 - 83 2

833= 33 - sg The stress intensities under both piping reaction manents (bending, torsional) are checked, and the worst condition which is due-to bending mcment in this case is tabulated in Table 3-5.1.

From Table 3-5.1 the maximun stress satisfies the allowable li2 nit of the specified material (see Sumary),

therefore the valve is assured of operability and successful perfonnance during and after the seismic event and piping load.

In addition, the requirements for structural integrity are met by satisfying the acceptance criteria in Section 6.0 of Duke Power Co., Seismic Design Manual. It is checked that the piping loadings (bending and torsional mcments) capability of the valve body is greater than the adjacent piping,i.e.

R = [Z s ]/[Z s ] > 1.2 y y p p anW

Nur. lear Valve Division Energy-REPCRT NO. NSR 301JBB3 u

["ons s

neue Equywnent PAGE 25 Borg-Warner Corporation

' 7500 Tyroes Ave., Van Nuys. California 91409 3

VAI.VE ASSEMBLY:

3.1.-3.2.2 Plane 2-2: (Valve Body - neck)

The membrane stresses are due to internal pressure in three orthogonal directions and are shown as follows:

(Figure 3 8.2)

Pi(2t5 Sim : Ps

/

1t : P ri/t 8

3 Sir : - P /2 s

where ri = inside radius (see Table 3-3) t

= wall thickness = r -ri (see Table 3-3) o P3 = standard calculated pressure (or design pressure)

In addition, there is a stress due to a thrust which is caused by main-seat as:

/

-r E 8th = Fat [(PI)(Po i

R.e thermal secondary stresses are the same as those determined in Plane 1-1 (see Section 3.1.3.2.2.c.)

Stress intensities are then as follows:

.sm 8a+81m

• 8th + OT 8t 81t + 8T g = ( g+st)/2 + ((s -8 ) #" + 8 s

m t s

(8 +8 )/2 - [(s -8 ) #" + 8 I !

32:

m t m t 3

8 3 81r 8 12= sg-s2 823 82-83 L__.

Er= w REPCRT _NO. NSR n01JBB3 u

- "*- iNuclear Valve Division Equipment PAE

9. 8

Borg-Wamer Corporation 7500 Tyrone Ave Van Nuys, Califomia 91409

.3.

VALVE ASSDiBLY:

-831: 83-8.1 The ntnerical values are tabulated in Table 3-5.2.

e r

s,

, r

..---___,.-,,,,.,-,,,,._._...._,,.-c_-m.

.,_,_,,,-,-,----__,.m,,,..

,.-,._.._~--...,r...-,..,,..---

y Enwgy REPCRT NO. NSR u03JBB3 u Nuclear Valve Division sam E**

PAE 27 sorg wamwcorporanon

-. 7500 Tyrone Ave Van Nuys, Cali'ornia 91409

~ 3.

VALVE ASSD4BLY:

TABII' 3-5.1 PLANE 1-1 r

(in) 2.250 op rip (in) 2.02a Z

. (in )'

3.088 3

p S

(ksi) 11.075 p

K-

.500 3

K

.230 2.

'dT (O )

1.000 F

T (ksi) 1.120 S

P-(ksi)

.275 3

r

.(in)-

2.560 o

ri (in) 1.990 s

(ksi) 13.873 3

2 (ksi) 1.810 s

s (ksi)

.138 3

12 (ksi) 12.06u s

s23 (ksi) 1.gu8 31 (ksi)

-13.012 s

L

1. w Energy DEPORT NO. NSR 301JBB3 u

~*

- Nuclear Valve Division

{='m E*"'"*"'

PAGE 28

.so,g.w.rner corporauon 7500 Tyrone Ave., Van Nuys. Califemia 91409

.3i:

VALVE ASSEMBLY:

-TAB E 3-5.2 PLANE 2-2

'P

- (ksi)

.275 3

r

' (in) 3.6a0 o

ri (in) 2.810 s

- (ksi) 3.358 g

2 (ksi) 2.031

's s3

. (ksi)

.138

.s2- (ksi) 1.327 1

23 (ksi) 2.168 s

3.a96 31 (ksi) 8 r

I s

e t

=e-r*-rw-y.w-e pip-imm.g_

=p

,w, 9-py-7

,,,--Cyrw-v Wp---yw t--

yvwty -e+wr-wwwwgygwwym-9 7-pVv w*rrw--remW p WT-v vg - yee w g m %w g--e

- v v+-eem W WW - e d

y Enwgv REPCRT NO. NSR h01JBB3 n Nuclear Valve Division' sene 4"""'

PAGE 29 sorg warnercorporauon 7500 Tyrone Ave., Van Nuys, Cahfornia 91409

3. -

VALVE ASSDiBLY:

3. 2 Yoke:

As required in the Specification, the yoke is analyzed for the maximtz seismic acceleration..-

An-analysis of the yoke structure is perfomed with the yoke and operator mass located at each center of gravity as shown in Figure 3-5.

3.2.1 Loading

The gross stresses in the yoke structure shall be investigated for the critical zones as shown on the sketch in Figure 3-5.

As a conservative approach, the maximin force resultants at the specified zone can be expressed as Fy = thrust = Fst + (m3+m2) gmax Sy = shear = (m3wr2) Emax + C Y

My = coment = [mg(y -y6)+m2 Y -Y6Il 8 max 2

g

+ C (y -y6) g Ty = torque = Tq + (m3x3,mgz3) max 8 max All the ntnerical values are tabulated in Table 3-6.

e i

ro Nuclear Valve DivM g Energy REPORT NC. NSR 301JBB3 3 PAGE 30

' sorg-warner Corneration 7500 Tyrone Ave., Van Nuys, California 91409 3.

VALVE ASSDiBLY:

3.2.2 Cross Sectional Properties:

The yoke legs have the cross section as shown in Figure 3-6, and the cross ~ sectional properties can be determined as follows:

A1A = area = 2.(a b + agbg)

A3A = shear area = 2 A 1A 3 (approximation)

/

3 3

I1A = 2[(ab ) + (agb3 )]/12 Z1A = section modulus = Igg /(b/2)

For a bent type structure, each colten has sectional properties as follows: (asstning that the neutral axis 2-2 lies at the middle of the larger area "a b" )

3 3 12 + a bgdj )

/

2 2A = ba /12 + (b a3 1

g g

A2A = A1A/2 Z2A I2A (a/2)-

/

k.ere dj = (a + aj)/2 The ntnerical values are tabulated in Table 3.7 1

+

.w.

s

%ess 7,,,

REPORT NO. NSR401JBB3-4 M.Werner Corporatet PAGE 31 7500 Tyrone Ave Van Nuys California 91409 3,

VALVE ASSDiBLY?

FIGURE 3-5 YOKE B

A I

I Yoke Operawr I

i N

I i

M 2'3 l

t i

{

l

• 3

')

1 I

I B

A Y ~Y6 J

2 n

Y ~Y6 1

=

=

e FIGURE 3-6 CRmS SECTION OF WKE EGS PLANE A-A l

_a i

ll

/

y i)f I /I I

d

eW.

Nuclear Valve Division g Enwgy REPCRT NO. NSR 301JBB3 u PAGE 32

sorg-werner corporation 7500 Tyrone Ave Van Nuys, California 91409

?.-

VALVE ASSEMBLY:

TABE 3-6 LCADING-YCKE '

F (kip) 3.581 y

S

- (kip) 1.331 y

.M (in-kip) 20.303 y

T (in-kip) 3.2nu y

TABE 3-7 CRCSS SECTICNAL PRCPERTIES--YCKE a

(in) 1.050 b-

.(in) 3.620 a

(in) 0.000 g

b

.(in) 0.000 3

I

( in")

8.302 gg A

(in )

7.602 1A 2

A (in )

5.068 3g 3

Z (in )

n.587 1A d

(in) 1.280 a

'Ia (in )

.3ng 2

-A (in )

3.801 2A 3

Z (in )

.665 2A 4

w

D Nuclear Valve Division -

g Enwgy REPCRT NC. NSR 301JBB3 u Borg-Warner Corporation PAGE 33 7500 Tyrone Ave., Van Nuys, California 91409 3.

VALVE ASSEMBLY:

3.2.3 Stress

3.2.3.1 Yoke:

Considering the yoke structure as a cantilever beam, the

-maximum stresses are derived by using the following expressions:

a,bm = F /A1A + M /Z1A s

y y

3: S /AsA + T /(d)(AsAI 3

y y

Another possible behavior is illustrated by the bent-type structure, where the two yoke legs are assumed to have rotational restraints at both ends. (See Figure 3-7)

The possible maximm ccrresponding stress can be expressed as:

a,bt = Pmax/(A2A) + M/(Z2AI s

where P

h/(x) max = F /(2) + Sy y

M

= V L/2 V

= S /2 y

The maximm principal stresses s1 and s2 and shear stress s, max for the yoke are obtained from the s

formula:

s

= (s I/2 + [(8 ) I

+8 g

a a

3 s

(8 )/2 -'[(s l

• *s 2

a a

s, max

• E (8 } #8 + *s s

a where sa (8a,M ' 8a,bt max I

The nmerical values are tabulated in Table 3-8.

m_

Nuclear Valve Division Mm REPORT NO.NSR4013BB3-

.Borg WarnerCorporanon PAGE 34 4

7500 Tyrone Ave.. Van Nuys, California 91409 3

VALE ASSEMBLY:

&l////D Sy e

a Fy L

3 s Swar F a Thrust Ig 1

y 3

3

~'7777 7Ts7 Operstor h

Y V

+

d o

V F

g

, mar y

I _

_n x

~,

P, (o.y N

o L

o FIGUBE 3-7 Boff TYPE STRUCTURE y

& 10Et o

Pman I

p i

. c '* ' * ' pluoteer Valve Division e Jge E'**v REPCRT NO. hSR n01JBB?.u PAE 35

- e.,,.wamer corporanon

- 7500 Tyrone Ave Van Nuys California 91409 3.

VALVE ASSEMBLY:.

l TABE ?-8 STRESSES-YOKE STRUCTURE L

(in) 12.390 h

(in) 6.250 x

(in)'

7.500 s,tm (ksi) u.698 s

(ksi)

.763 s

a,bt'(ksi) 6.%2 s

.. ksi) 7.0au

(

sj s2

-(ksi)

.083 s, max (ksi) 3.56u S

e e

w, v.w. owi.i.a iiiiXEE C L i um m. nsa4oun83-4 Borg Warner Corporation M

36 7500 Tyrone Ave.. Van Nuys. Cahfornia 91403 3

VALIE ASSDM3:

I.

'l.

1 c

A (dia.)

=

G (dia.)

//

8 u

3 u

3 (dia.)

n 9

~ s,

~

~

c (dia.)

F1 cunt 3-9 FLAMI (Aer: A3st 8 4 PT Code, Figwe U-3120=1)

I e

b e

0 e

m.

' '. ' thselaer Valve Olvielen g taaer REPCRT NO. NSR 301JBB1 2 PAGE 37 7soo Ty,ene Aw., Van Nuys, CeWomie 914o0 3.'

VALVE ASSENBLY:

i

3. 3 Bolted Body-Bonnet Joint:

331 Loading:

~ Re criteria for the body to bonnet flange joint is governed by the rule Mi-?687.1 and NC-3647.1, and Article XI-3000, Subsection -

- NA,Section III of the ASME. Boiler and Pressure Vessel Code. A yoke with operator constitutes an extended structure and the i

seiamic forces impose a mment and thrust on the bolted flange joint. Neerical value 3 for these components are derived at

~ Plane 3-3 (see Section 3 1.1.3), and resumarized in Table 3-10.

332 Stress:

3 3 2.1 Bolt Stresa:

R e fundanental dimensions of the flange, as shown in Figure

?-9 are tabulated-in Table 3-11. (refer to ASME. Boiler and i

Pressure Vessel Code, Figure XI-3120-1). Some other paraneters and dimensions Wich are defined as follows are also tabulated in the same table.

l gasket paraneters:

b, s N/2

( b, )0.5 / 2 if b )0.25" b

o b :b otherwis.

e (d,-d )/2 dere N :

t d e outside diameter of gasket f

o di inside diameter of gasket i

moment amas (per Table XI-3230-1, ASME Code)

R s (C-8)/2 - 3 3 hD R + 0.5 st i

ho n (C G)/2 i

ht n (R + 31 + ha)/2 All the notations used in this section are in accordance with those defined in Section XI-11?O. ASME Code,$ubsection NA.

t i

j

y Ermgr REPCRT NO. NSR n01JBB3 3

Nuclear Velve Division sone PAT 38 Borg-Wamer Corporation -

' 7500 Tyrone Ave., Van Nuys Califomia 91409 3

VALVE ASSEMBLY:

i The flange design pressure per NB-36h7.1 and NC-36u7.1 is:

7 ((pI)c )

2 3

3 + 16 M /((PI)G ) + 3 F P

/

FD =_ P 3

1. 4ere P3 = design pressure Flange design bolt load (W) then is computed by the procedures of XI-3221.1:

W = 0.785 G2pFD + 2b(3.1u G m PFD) 2.ere m = 3 0 per Table XI-3221.1 For a total bolt cross sectional area A, the average b

bolt stress-is:

sb W/Ab The nunerical values are tabulated -in Table 3-11.

r i

n

. ky

(

_J,,_

i-m.

m._.

Nuclear V:lvd Division gm Erstgy REPCRT NO. NSR h01JBB3 u l

PAq -

39

sorg wamer corporanon

. 7500 Tyrone Ave., Van Nuys, Cahfomia 91409 3.-

VALVE' ASSEMBLY:'

TABLE ?-10 LCADING--PLANE 3-3 F

, (kip) 3.820 3

S

.(kip) 1.529 3

.M.

(in-kip)_

28.no7 3

T

. (in-kip) :

3.013 3

(

• MK,'O g?'

4 g.,

d er g*.,b

• ~

Nuclear Valv3 Division g Energy REPCRT NO. NSR 301JBB3 3 PAT 40 I

. sorg-wamer corporation 7500 Tyrone Ave., Van Nuys, Cahfornis 91409

~ 3. -

VALVE ASSDiBLY:

TABLE 3-11 BCLT STRESSES r

8 3 (in) 1.125

82. (in) 800

. B

.(in) 5.500

- G (in) 6.713 t

(in) 1.250

- A (in) 10.625

- C (in)-

9.250 h-(in) 818 N

(in) 573 b

268 R

(in) 750 h

(in) 1.268 s-h (in) 1.313 D

h (in)-

1.572 T

P (psi).

275.000 3

2 A

- (in )

2.663 b

P (psi)-

861.182 pp W.

(kip) 59.631 8

(ksi) 2i.393 b.

1p 4

5 9--

y

?m' ertm -te w -

9 '

re-

'""~

7-NE-

-w--w-p y

6---*----M

-w-+'trM38 g**

v' v y

• F-w---

'--#*Y

Y Nuclear Valve Division g Ewgy REPORT NO. NSR 801JBB3 3

~

PAGE~

41

)

Borg-Warner Corporation

' 7500 Tyrone Ave.. Van Nuys, California 91409 3.

VALVE ASSEMBLY:

3.3.2.2 Flange Stress:

The flange ecment (M ) is computed by the precedures of XI-3230 as shown in 8he following formula:

Mo=MD+MT+Mg where MD = H@D' MT = H8T ' MG : H@G HD = 0.785 B2pFD H = 0 785 G2pFD Ha=W-H HT=H-HD Stresses in the body flange and neck shall be determined for the design ecnditions per XI-32u0.

The method of analysis utilizes a neber of parmeters which are prescribed in the ASME Boiler and Pressure Vessel Code. Cn Figure XI-32u0-6, the parmeter f is a function of the ratios gl tr. rough

/gn and h/h.

Likewise, Figures XI-3280-XI 32h0-3 provide the other par m eters (T, Y, F, Z, U,' V) required for the computation.

Cther parmeters are:-

D, e = F/h d=Uh o gg o

L'= (te + 1)/T + t3 d

/

Finally, the maximum stresses are longitudinal hub stress:

H: (%)/(L81 B) + (P )B/(u go) 8 3

-Radial flange stress:

2 R = (1.33 te + 1) M /(Lt B) s o

Tangential flange stress:

2 sT Y M /(t B) - Z sR o

All the neerical values are tabulated in Table 3-12.

+

Nuclear Valve Division s"ans anoma Equipment REPCRT NO. NSR h01JBB3 u Engy pgg Borg Wamer Corporate 42

' 7500 Tyrone Ave.. Van Nuys, Califomia 91409 3

' VALVE ASSDiBLY:

TABE 3-12 FLANG STRESSES r

2.200 F-

.780 V ~

.170 U

?.h22 T.

1.532 Y.

3.11u Z

1.732 d

u.777 e.

.526 L-1.390 M.

(in-kip) 79.581 o

H (ksi) 17.821

.s g

. (ksi) 11.636 s

sT.

(ksi) 8.666 m.

'h

,.,,e

,-nw,

-w,.

.--,.,.,..,,,na

-e,

.,m.,,,.

,m-

Nuclear Valve Division g - Energy REPCRT NC. NSR n01JBB1 u Equipment pggg 43

. Borg-Warner Corporation 7500 Tyrone Ave., Van Nuys. California 91409 3

VALVE ASSEMBLY:

3.?.2.3 Dome Shape Bonnet:

The rcquired minimtun thickness of the head and flange of a

- dome shape bonnet with bolting flange is determined by the rules of NC-3326.2,Section III of the ASME, Boiler.and Pressure Vessel Code.

A calculation.is performed to show that the sufficient wall thickness in N.V.D.

design satisfies the requirements.

Head thickness (ministan) th = (5 P L)/(6 sAI Flange thickness (minimtrn) tr = Q + [1.875 Mo (C4)/[sg B(7C-5B)))O.5 where Q = [(P L)/(n s )][(C+B)/(3C-B)]

g P = design pressure L = inside radius of the head s = allowable stress of the material C = bolt circle diameter B = inside diameter of flange Mo = total moment (see Table 3-12)

The ntrnerical values are tabulated in Table 3-13

- e r

r a

n

~

Nuclear Valve Division REPCRT NO. NSR 301JBB3 3 y Energy sene 4"'"

~ PAE 44

_ sorg wamercorporation

- 7500 Tyrone Ave Van Nuys, California 91409 13.

VALVE ASSEMBLY:

~TABII ?-13 DCME SHAPE BCNNET P'

-(ksi)

.275

L

.(in) 2.700

-C

' (in) -

9.250 B-(in) 5.u00 A

(ksi)-

18.000 8

M

'(in-kip) 79.581 o

t (in).

.03u h

t (in) 779 r

ik. design (in)

.M0 tf, design (in) 1.250 a

o

' t;-

f i

a:

4 z_-.

~

.m-,,

r=

9 Energy REPORT NO. NSR401JBB3-4 Nt: clear V lve Division s "ons wannen Equipment PAGE 45 Borg-Wamer Corporation

' 7500 Tyrone Ave., Van Nuys, California 91409 u.

MAXIMUM EEFECTION CF CPERATCR:

The deflection of the operator and. the valve assembly is computed by using the static analysis of the finite element computer progran SAP 6.

The structural model is presented in Section 5 of ' this report.

The corresponding values of acceleration in X, Y and Z directions as specified in tra specification are used in the computer progran, asstrning acting

' simultaneously. Table 3-1 tabulated the results of the displacement in X, Y and Z directions obtained from SAP 6 output printout, and the resultant maxistan displacement of each nodal point.

The maximtrn displacements shown in the table indicate that they are sufficiently small and will not limit the operation of the stem and operator. A review was made to assure that machining tolerances do adequately accccmodate the movements.

8 L'n

r r

Nuclear Valve Division

@ wenn Energy REICRT NO. NSR401JBB3-4 Equipment PA E 46 s

Borg-Warner Corporation 7500 Tyrone Ave. Van Nuys. Califomia 91409

.TABE u-1 DEFECTIONS -

NCDE DX(IN)

DY(IN)

DZ(IN)

DMAX(IN) 0093

.0018

.0132 0162 20 19 0082 0001

.0129 0153

- 18 '

0068 0001

.0083 0108

' 17 -

0063 0001

.0066 0091

~6 0063

.0003

.0060 0087 1

15 0063-0005

.0073 0096 lu 0035

.0002

.0038 00ng 13-0035 0003

.00u0 0053 12 0012

.0003

.0020 002n 11 0012 000n

.0021 0025 10 0012 0002

.0020 0023 9

0012_

0003

.0021 0023 0012 0001

.0021 002u 8-

~

7 0007 0001

.0013 0015 6

0002 0001

.0005 0005 5-0000 0001

.0001 0001 C000

.0000 0000 a

0000 3

0000 0001

.0000 0001

+r--ee-.

y 9-w y

v,e-

--myr'w-y-'9-v---

---vow-

%vg#9- - + *y q

Energy REPCRT NO. NSR401JBB3 4 Nuclear Valve Division

%h Equipment PAGE g

Borg WarnerCorporation

. 7500 Tyrone Ave., Van Nuys, California 91409 5.

NATURAL FREQJENCY:

The natural frequency for the valve assembly is detemined by idealizing the structure as a multi-mass system interconnected by structural members as denoted in Figure 5-1.

A finite element computer program, SAP 6 -- Structural Analysis Progra for static and dynamic analysis, is used to calculate both the deflections and natural frequencies.

Details for the use and interpretation of the SAP 6 computer program are available in the User Manual, by SAP Users Group, Civil Engineering Department, University of Southern California, Nov.1977 In the structural model,- 20 nodal points are assigned to represent various components of the valve assembly,. along with 13 concentrated Itaped masses.

The structural characteristics are described by means of geometrical properties for 10 designated cross sections. These quantities are calculated for the beam members (MTYP=2) on the dynamic model.

The whole system is considered. to be restrained only at the two weld ends of the body main run, and have six degrees of freedom at each other nodal point (3 translational.

3 rotational).

The description of the nodal points is shown below:

Nodal Point Mass Point Description 1,2 weld ends of body main run 3,n a,b valve body main run 5

e valse body center + gate / disc / seat

+ 1/5 stem 6

d valve body neck + 1/5 stem

-7 e

valve body neck flange + bonnet

+ 1/5 stem 8

center of yoke-body / bennet joint 9,10 dtmy nodes 11,12 f,g yoke flange + 1/5 stem +clmps/ bolts 13,1a h,i yoke " leg" 15,16 j,k yoke top + 1/5 stem 17 center of yoke top 18 1

adapter / yoke-operator joint 9

dtmy node 1

20 m

C.G. of operator

i Nuclear Valve Division Enwgy REPORT NO. NSR401JBB3-4

["ons,wannen s

'""'""" Ecuspment pggg 4g

' Borg-Warner Corporation 7500 Tyrone Ave.. Van Nuys, California 91409 5.

NATURAL FREQJENCY:

Due to the fact that the geometry varies throughout its lengh, each structural member is defined by the minimtn geometrical properties for the segment.

Solutions derived with this approximation will result in the lowest natural frequency as a conservative approach. The dtany nodes 9 & 10 are justified to account for the curvature effect of the yoke leg, and dteny node 19' is to serve the transaction from node 18 (adapter or yoke-operator joint) to node 20 (center of gravity of operator).

For shell type yoke design, the equivalent cross section properties to beams are used (beams 8 & 9).

The mass moments of inertia for all mass points except operator are computed by an engineering approximation of the actual mass distribution and the radius of gyration. Slight discrepancies in data will have negligible effects on the final. computer results.

The mass moment of inertia of the operator, however, is provided directly from the supplier.

Table 5-2 through Table S J list the input data of the nodal point coordinates, the geometrical properties of the structural members as well as the masses and mass moments of inertia. The first three modes of the natural frequency are tabulated in Table 5-1.

4

Nucirr Vciva Division s "ons nanan Enwgy REPORT NO.NSR401JBB3

- Equipment Boro-Warner Corocration PAGE 49 4

.l 7500 Tyro,e Ave. Van Nuys Ca.. torn.a 91409 FIGURE 5-1 BM10 19 20(m)

BMll h18(1) l 15(j)h P l6(k)

^

f d,

BM10 17 BM10 M9 Bih i

13(h) 14(i)

BM8 BM8

~~

~

Bg10 Btjl0 i

12(g) ll(f) g i

BM6 BM6 h7(e) i i

/

s i

i

~

BM4

,y.

6(d)

T f

l l

l i

l l.

BM3 tg 3

s.

) kBH1 BN2 BM2 BMI 2

- __ ::_w e

h

'/

3

)

5 )

6 )

i-V h

Y d

r X

--~

t 9"

w"*

t'w' e-

"W

-e*v"'*

• Mf-e

- - - - + ' * *

• Nuclear Vcive Division '

y Enwgy REPCRT NO. NSR40lJBB3-4 m

• * ' PAGE 50

.Borg-wwner corporacon

. 7500 Tyrone Ave., Van Nuys, California 91409 TABII:5-1 NATURAL FREQJENCY

'MCDE' 1 n2.520 MCDE.2 53.300 MCDE 3 73.020 a

S f

b 4.

t 4

e Y

J y

REPORT NO. NSR 401JBB3-4 Nuclear Valve Division -

J Energy EquipmeM PAGE 51 sorg wamercorporauon 7500 Tyrone Ave., Van Nuys, California 91409 TABLE 5-2 NCDAL POINTS

-NCDAL POINT X-COORD.

Y CCCRD.

. ZLCCCRD.

.1

-6.00 0.00 0.00-2

-6.00 0.00 0.00 3

--3.98 0.00 0.00 a

3.98 0.00 0.00 5

0.00 0.00 0.00 6

0.00 3.00 0.00 7

0.00 8.00 0.00 8

0.00 11.85 0.00 9

-1.59 11.85 0.00

-10 1.59 11.85 0.00 11

-2.11' 11.85 0.00 12 2.11 11.85 0.00 13

-1.88.

16.65 0.00 la 1.88

- 16.65 0.00 15

-1.66 21.uS 0.00 16 1.66 21.85 0.00 17 0.00 21.h5 0.00

-18 0.00 23.85 0.00 19 0.00 30.10 0.00 20

.75 30.10 2.81 y'

g y

y ww~y*-e'**

yyW-N yw-N-v m'

• w'v'm

--wy" y

we

--'w-mer-T 7---MNT

-w=97

-m=-

- ww y g=w -

7-m-

rw-e=

-w'TW--'

n.

Energy REPORT NO. NSR 401JBB3-4

'. _ Nuclear V;lve Division

@ h Equipment wanan PAE Borg-Warner Corporation.

52 7500 Tyrone Ave., Van Nuys, California 91409 TABE 5-3 BEAM CRCSS SECTIONAL PROPERTIES BEAM NO.

. AREA TCRSICN J MCMENI Il MCMENT I2

.1.

'8.15 n2.83 2.1.n16 21.n16 2

8.15-82.83 -

21.u16 21.316 3

16.82 177.82 88.910 88.910 u.

23.8u 278.68 139.3u0 139.3no 5

'20.36 78.'1a 39.072 39.072 6

1000.00 20000.00 10000.000 10000.000 7

33.30-330.76 165.381 165.381 8

3.27 1.ca 3.068

.259 9-2.33

.53 1.550

.132 10 1000.00 20000.00 10000.000 10000.000

/

TABE 5 u MASS AND MASS MQiENT CF INERTIA NODE MASS M.M.I-X M.M.I-Y M.M.I-Z-3

.037 0.000

.02a 0.000 a

.037 0.000

.023 0.000 5

.128 0.000 '

.08u 0.000 6

.0uu 0.000

.059 0.000 7

.098 0.000

.152 0.000

-11

.022 0.000

.032 0.000 12

.022 0.000

.032 0.000 13-

. 01 8 0.000

.026 0.000 tu

.018 0.000

.026 0.000 15

.021 0.000

.030 0.000 16

.021 0.000

.030 0.000

.18

.008 0.000

.011 0.000 20

.532 13.356 36.052 29.980

~

Nucieer Valve Divisior.

Enmyy REPCRT NO. NSR 401JBB3-4 eens amme Equipment PAGE 53-l Borg-Wamer CorporaHon 7500 Tyrone Ave.. Van Nuys. Cahfomia 91409

)

6.

CCNCLUSICN:-

.I i

The following valves have been evaluated and qualified in accordance with the ASME Boiler and Pressure Vessel Code Section III, Nuclear Power Plant' Components, Division 1, Subsection NC, 197a and the requirements in Euke Power Company, Catawba Nuclear Station, Units 1 and 2 Specification No. CNS_1205.00-6, Addendte 6, Deceber,1978.

ASME Section III Carbon Steel Gate, Globe and Q eck Valve.

Qualification is based upon the analytical procedure defined in Duke Power Company, Seismic Design Manual for rigid mechanical systems In accordance with the design specifications, it has been deonstrated that the valve assembly satisfies the design criteria for stresses and deformations. A finite element computer program SAP VI has been used to evaluate the natural frequency of the valve as s embly. With conservative quantitles for mass and inertia, specift.

cation Ilmit of 33 cycles per second, which classifies the component

,i as a rigid system.

VALVE PRESSURE MATERIAL VALVE OPERATCR N. V. D.

SIZE RATING TYPE ASSDiBLY (INCH) (LB)

DWG NO.

u 150 CARBCN SIEEL MCTCR GATE 801JBB3 u N

i

,,,r.-

-+y

-,w-

---

.-.w,-

---

,---,----e er w3--

9 Ef 5 I.

1 Nuclear Vrive Division g E@M REPORT NO.NSR401JBB3-Ewsy 004 sorg-warnw corporation -

PAGE Attachment 1

7500 Tyrone Ave., Van Nuys, Cahfomia 91409 DATE 9 APR 79 REVISION A

STATIC DEFLECTION TEST RESULTS b

s e

Y

<-g

'y c

- ~ -, -

-,--r---

^

--,-,,-,-.---,---4i

,--.+,,-,y.---,,-,-m v,,,,.,,,,--,,,,q.,-,-wy-r, myvo~,-*+gi.ev.,

y-g,ry--wyy,-y--

-cy, - -

4

}

w 6,

REPORT NO NSR401JBB3-004 PAGE REVISION A

ATTACHMENT TO REPORT NO. Nf 4fo/d883- 00 4 i

i 4 -h *,

l,

.:f,

03$

.)

,l.

Y Gk m

I p

s<

7j f 3.... _ _ --

-...._.9 i

TEST SETTJP i

r a.

,,[ <..

k>

' Nuclear V:.lva Division -

- g,

ENUW.M@UN-Borg warner corporanon PAGE Attachment 1 004

- 7500 Tyrone Ave, Van Nuys, Cat.fornia 91409 REVISION A

ATTACI-fMENT TO REPORT NO. NSR 40/d888-00 Y The following active valve was tested per NVD Report No. 1681, as required by Duke Specification No.

CNS 1205.00-6.

RESULTS OF TEST NVD PART NO. Yd/ J88 3 -86 Y DUKE ITEM NO.

j8-Ydd SERIA L NO.

994 9F DESCRIPTION [#f SO/A, ggrq A/v, DIRECTION OF LOAD X

MAGNITUDE OF LOAD //58 Z M SEAT LEAKAGE TEST PRESSURE J/O PSIG CYCLE NUMBER TEST 1

2 3

OPEN TIME (Seconds) 9,2

.f,/

9,.2.

CLOSE TIME (Seconds) h,Y t/. '/

f. y SEAT LEAKAGE C. / cc.

4 SEAT LEAKAGE O, 3 e c

/

(Reverse)

Test Performed by: M.2 Witnessed by:

- eLh F

(

Photograph of setup on next page.

4-

...w-9 v

s-r-w-s e---*-

y

,*g r%--Fr'

-M-e m---

---e+--

sr-

-9

TF Seismic Analysis and Static Deflection Ttst for Valves VQ3B and VQ158

~

- - - - - - -