ML20024D191

From kanterella
Jump to navigation Jump to search
Rev a to Seismic Qualification Rept of Masoneilan Control Valve
ML20024D191
Person / Time
Site: Maine Yankee
Issue date: 05/17/1983
From: Habel J, Hull P, Kramer E
MCGRAW-EDISON CO.
To:
Shared Package
ML20024D182 List:
References
1141, 1141-RA, NUDOCS 8308030284
Download: ML20024D191 (8)


Text

.. - -.

3 kBRAHil3Oli PAGE 1

OF 4 Mcsonailcn NUCLEAR OPERATION SEISMIC OUALIFICATION REPORT a

5 E

OF m

O MASONEILAN CONTROi. VALVE

'-=o N.

FOR

-c

'>z z<

MAINE YANKEE ATOMIC POWER COMPAn'

<E

c. w h0 PURCHASE ORDER NUMBEL MY-163 7

+,

u o zo3 VALVE TAG NUMBER HCV-6008

$z o=

w3 MASONEILAN WORK ORDER NUMBER H-38917-84 5w

<c go REPORT NO. 1141 ue Er z@

2 53 55 CEO a<

A Go fI

[- hh3 b$

PREPARED BY: [f.

.h DATE:

EO

  • 4 E'o l

e C o RIVIEWED BY:

/2 (

DATE: M -OE

/

, c.

5w ca

c. <

WE

w Y
  • bI*

APPROVED BY:

DATE:

L @

zG:

c vs w=

=E z e Cz r<

Ec:

O w

0Ohohh9 PDR TITLE SY DATE 7ebruary 19' 19 8

MAINE YANKEE ATOMIC POWER CO.

CHEC DOCUMENT 1D' H-38917-84 l

114l SEISMIC QUALIFICATION REPORT APPR O Masoneilan Division McGraw Edison. Norwood, Massachusetts and Montebello, California

,a

' ; nun PAGE 2

op 4

.Mr.sonailan NUCLEAR OPERATION a

5

.z 8

E STATUS SEEET zou

  • 6 d5 23 2C 0"2o REVIE'w'ED APPROVED zoD REVISION DATE BY BY BY DESCRIPTION

$z oc wG

!y 2/19/83 Original Issue 50 vH 2H zb ACCELERATIO N LEVELS cWo To o 2se's H(v 9=2 A

5/'s/ss 4).

p y 'gb J.

roa. o.ne 4 s.ss s

2 f.I3 93 mm 3

secoes esmsen.

2:5 m zO 3E Gc zw O i!"

w o

<u E C 8oo E$

c. c-OW

\\

cO

a. <

l w2 5E a-l z@

e t; wa2 z o 9z w<

<2c l

8 l

z l

3a i

U V INE YANKEE ATOMIC POWER CO.

CW ENU D H-38917-84

'"'('[Q HG A

SEISMIC QUALIFICATION REPORT apppovgo i

Masoneilan Division McGraw Edison i Norwood, Massachusetts and Montebello, California

~

PAGE 3 op 4 M C S O n 'Sil C n NUCLEAR OPERATION I

a<

TABl.E OF CON'"ENTS Ez w=

Czoo f/3.

PAGE

.c

>z z<

<2

c. w 2O Title Pag.

1 0 2 U O g$

Revision Status Sheet 2

"2 35 Table of Contents.

3 5C j=

Abstract.

4 o

E D Introduction.

4 9E "a

Discussion.

4

>~

5a z5 Conclusion.

4 t=

J<

wQ$*

APPENDICES

=6

<u E C C

o I.

Seismic Stress Analysis Calculations II.

Typical Bonnet Stress Analysis - NE 155 Revision C c

c. -

Ow cc III. Valve Closure Calculations

c. <

g2

-w r u 22 +

,o l

z i

=w c m

$3

-2 l

2e 9z w<

<2c O

w E

.2 I

J l

lV.

TITLE BY DATE Februarv 19' loc' MAINE YANKEE ATOMIC POWER CO.

H-38917-84 l ' D DOCUMENTID~

CHEC fN SEISMIC QUALIFICATION REPORT APPROVE D Masoneilan Division McGraw Edison. Norwood, Massachusetts and Montebello, California

~

mantggs PAGE i

OF 4 M CC@DC5lCD NUCLEAR OPERATION ABSTRACT

$c A seis=ic analysis was performed to determine if a valve purchased under

'2 Maine Yankee Atomic Power Co., Purchase Order MY-163 is capable of 9

withstanding a seismic event. Analyses show that the valve meets the E

stress limits and specified seismic design recuirements for structual 8

integrity.

Calculations are also included to demonstrate that the m,,e actuator is capable of closing the valve under design conditions.

'z 2

IhTRODUCTION

c. w Eo o z Seismic analyses were performed for both Operating Basis Earthquake (OBE) z2 and Safe Shutdown Earthquake (SSE) conditions.

The seismic accelerations

@U as specified by Maine Yankee Atomic, are as follows:

oe

  • 3 OBE = 0.25 g's Horizontal & 0.25 g's Vertical g$

((

5o SSE = 0.25 g's Horizontal & 0.25 g's Vertical ur 2w z8 The analyses and results are included in the appendicies.

9us2 5 17:

DISCUSSION oM

.I j@

The seismic analyses in Appendix I have been evaluated for both OBE & SSE

\\

.d <

conditions.

The analyses are based on Masoneilan's Procedure NE 155, Rev.

EO C, typical Bonnet Stress Analysis which is enclosed in. Appendix II.

The 3$

allowable stress limits have been met in accordance with the applicable gu codes.

The allowable stresses are shown on the analyses as " Norm. Design g5 Allowable.1.2S" for. the OBE conditions and " Abnormal Allow., 1.8S" for ljg^

3g the SSE conditions, ec: C w2 Th'e calculations for valve closure are found in Appendix III.

These-Og calculations show that the actuator has sufficient force to shut-off

c. <

against the design conditions and to maintain seat tightness.

wE U

CONCLUSION es l

0 z 2 g

The valve covered by this report meets the design & seismic requirements 5g specified.

2 z o Oz y<

Ec:

8 2

-l<

l L

TITLE BY DATE February 19, 1983 MAINE YANKEE ATOMIC POWER CO.

c KED DOCUMENTID H-38917-84 J

g SEISMIC QUALIFICATION REPORT APPROV ED 1141' Masoneilen Division McGraw Edison. Norwood, Massachusetts and Montebello, California

8 EO O

e D

4 APPENDIX I

_TO REPORT NUMBER 1141 SEISMIC STRESS ANALYSIS CALCULATIONS i

I I

I

?

l

i f.'

- r

.7

""o t:ltW2tt!00.?lMt' *

~

S p

. M NI-OR DE R. NO. H 3 6 91 T = 8 4. -. _-

j VALVE Site

8. 0014 C 41 TYPE 20521 RAllMG 600LB.

ACTUATOR 18.5R iW 0

)e 81118: {ieU NatoAE,VALVEIANag5]"

109-NUC AR 280: 4 WlIlVW4eiilHEeAAY7o+8:!!8 1

c 3

BONNET FLANGE A4&Lrf515 p

"iO '#$l$30lN

~

~'

b aN8! bEdI*N'hkiss' #* D $16

~~

~ ~ ' '

II}"gliqFIRgs,12!':lig'"5 5' ~ " ' "5 "5 V8 8:"

t r

~

b Cik hD A

'j! $h.

8.

o s ha lhAP na8m

""" ~~u a8-I

_....._. _ __ _. HU S-.T H I C (N E 5 5._ G A -- 1.

00IN.

' O UPERATING CON 0!110NS b

MatiMUM STRE MORM. DES N ALLOd48LEr,1.25 ABNORMat. A LOW,1.80S

~ ~ ~

kY h

~

~ ~ ~ ~

~

8bhl h II ~ ~ ~~'"~~~ ~~~ ~ ~~~~ " $.

!b hf~

SR 8)$. P5; 21000. PSI 31500. PSI i

j p

. G A $ 4 E f. $ 6 A i ! N G. _.._ ___.__... _. _.

,N ALLOW 40t.Eie l. ZS A8NORMAV ALLOW 1.803 MAtlMUM TRESS 40R4. DE51[l000.

3150g.P p

SH 68 U.

PS 2

P5 g.g g..

g_

l s m eLA w.,;. es Pe...

l

~t j

in

+38917 84 S E I S MI C C ALC5.. PG.

2.

l lf%

i BODY TO BONNE.I BULil 11G. -....--

1 4Cid&L B 3 L'T 4 R E'A II.60350.lN 12 25011.

REJVIRED S UL>T ARE4 1.46750.11 BOLT 51lEl

.m Od49TITY VALUE OF W.

36676'.LBS.

-.- 5 V ALU E. & i T E M P..---.. - 25000. PSI

)g-M4(IMUM SIRESS NORMe DESIGN ALLOW 4BLEi,1.05 48NORMALiAi. LOW,1.0 5 4

SB 3107. PSI 25000. PSI 25000. PSI

~~~

MININui HDLil'EU560E~'

1 58. F i.'L 5 5 ' E U F H i 6 k U' ~i E 5 E ~ ~ ' '

~ " ~ ~ ~

~

MaxlMUM 00 L'T 10100E 692. FT.LB5

p ACTUATOR ANALYSIS jr IDfH....---4e IN.

IGH 06 N.

. Y OK El-

-bElDIM.

- 30 95 R.WIlGHT.-.

?j>f8.

C.h041 4

AC f.

IN.

O H

61 N

2 9

IN.

YbkiolM. 4000. PSI (QOlyALENT AR 6 f0AIDA PRESS del (l4 9.PSID 5 VALUE AbI.

.. K E-r..

f A

MAXIMUM STRES$

NOR94 tis 5 t GN ALLOW 49LEtt 1 25 48NORMlif'5I'[UN,'1.865 j

SA 989.P51' 4800 851 72006 P 51;

,r-YOKEL TU 8ONNET JOINT ANALYSIS j p

- -- --- -. - g N.--.--..---.----

AM ER 8 507 J.N l

NOT SH t'ARE&

lp 5 VALUE,iEMP 20000. PSI MAXIMUM SIRES $

NORM. DESIGN AL(0W4BLEi,0.65 49NORMALiALLOWr

.6 5 o

SC 626,P51 12000 PSI 12000. PSI

.p

'b 04TE PERFORMED 3131 L&5T REVISION 9285 l

)

COS T 3'4E R I4G NO.5 HGV-6008-.

APP NDIX II E

REPORT NUMBER 1141 TYPICAL BONNET STRESS ANALYSIS - NE 155 REVISION C e

._,