ML20210L720
| ML20210L720 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 09/24/1986 |
| From: | Chan T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-61405, NUDOCS 8610020275 | |
| Download: ML20210L720 (43) | |
Text
{{#Wiki_filter:m e Szptember 24, 1986 o Docket No. 50-344 DISTRIBUTION (Docket (11e, S. Varga NRC~PDR " T. Chan LICENSEE: Portland General Electric Company (PGE) Local PDR OGC PD#3 Rdg. E. Jordan FACILITY: Trojan Nuclear Plant J. Partlow B. Grimes ACRS(10) G. Bagchi
SUBJECT:
MEETING
SUMMARY
REGARDING THE MAY 29, 1986 MEETING D. Terao ON RESTRAINED THERMAL GROWTH OF THE RCS H. Brammer R. Ballard R. Kiessel C. Crews J. Fair A meeting was held in Bethesda, MD on May 29, 1986 with Portland General Electric Company (PGE) to discuss inoperable steam generator (SG) hydraulic snubbers and its relation to restrained thermal growth of the reactor coolant system (RCS). LER 85-13 (January 7, 1986), LER 85-13 Rev. 1 (April 1, 1986) and PGE letters dated May 9 and 21, 1986 provided background information on this topic. A list of attendees is provided in Enclosure 1. PGE provided a presentation on the subject, with supplemental details being provided by their technical representatives. Enclosure 2 contains PGE's presentation handouts. Discussions centered on the causes and findings of snubber degradation, restricted gap clearances on the SG upper and lower supports guides and the necessary corrective actions, observed movement of the pressurizer surge line, and damage to pipe whip support members and shims. PGE attributed the steam generator snubber failures to oversensitive hydraulic control valves. These valves were found to contain contaminants in the hydraulic l fluid which caused plugging of the bleed orifice, and worn check valve springs l which caused the check valves to seat prematurely. PGE said the snubber control j valves were to be replaced with self cleaning type control valves before startup. The new valve design would cause activation at a higher velocity and therefore
- would not be as susceptible to activation during thermal expansion. Enclosure 3 provide diagrams of the original steam generator snubber hydraulic control system.
The staff requested that PGE provide the final results of testing done on the original control valves in the as found condition, with a discussion of the cause of the snubber failures, and the model number and experience data of the new hydraulic control valves. PGE discussed their inspection findings of the steam generator upper and lower l support guides which revealed insufficient gap clearances, and stated that insufficient gap clearances might have contributed to the thermal growth restraint. Although stresses applied to the RCS piping were bounded by the lock-up of the steam generator snubbers, PGE postulated that a combination of thermal growth restraint by the support guides and snubber lock-up was more realistic. The staff requested that PGE provide a description of the postulated scenario of events leading to the restrained RCS thermal expansion. PGE stated that they l' would be readjusting gap clearances during heat-up prior to power operation to ensure adequate clearances. ] l I l 8610020275 860924
> PDR ADOCK 05000344 S PDR h
/
P s PGE's consultant (Impell) presented the results of analyses of the stresses on the RCS piping. The IMPELL worst case analyses assumed thermal expansion with snubbers locked and hot leg binding with the hot leg pipe whip restraint for the 28 cycles since Trojan began operation. IMPELL discussed their preliminary evaluation but said the final results were still being worked on. The staff indicated that they would like to review Impel?'s final analysis before Trojan resumed power operation. The staff also requested PGE to evaluate the effects of hot leg binding with the hot leg rupture restraint, specifically, the possibility of concrete cracking at the base of the rupture restraint. Bechtel Corporation, which had been retained by PGE to perform an independent review of the Impell analysis, stated that they concurred with the analysis so far performed by Impell, and would provided a report to PGE. The staff indicated that they would like to review this report along with the Impell analysis. PGE also discussed their program to prevent future restraint of RCS piping. Their program included reevaluating the needed clearances on the support guides and pipe whip restraints, and monitoring the clearances during future operation. The staff indicated that they would like to see the plant procedure on thermal expansion monitoring prior to heat-up and would like to see the results of the ~ monitoring program before power operation commences.
~
4e, - Te ence L. Chan, Project Manager Project Directorate #3 Division of PWR Licensing-A
Enclosures:
As stated , cc: G. Bagchi R. Ballard D. Terao S. Richards, RV G. Kellund, RV J. Crews, RV J. Fair, IE R. Kiessel, IE PD#3 TChan
]d-a 9/23/86 / r/86
/
Enclosure 1 LIST OF ATTENDEES
'May 29, 1986 Restrained Thermal Growth of the RCS NAMES ORGANIZATION T. Chan NRC S. Varga NRC G. Bagchi NRC D. Terao NRC H. Brammer NRC R. Kiessel NRC J. Fair NRC R. Ballard NRC K. Johnston NRC J. Crews NRC J. Pires BNL M. Reich BNL G. DeGrassi BNL C. Yundt PGE G. Zimmerman PGE R. Wehage PGE D. Keuter PGE T. Liu WESTINGHOUSE R. Jagels BECHTEL T. Bostrom BECHTEL R. Fosse BECHTEL W. McLeod IMPELL W. Bak IMPELL J. Roberts IMPELL l
l l { i,.---_---
i , Enclosure 2 EVALUATION OF REACTOR COOLANT LOOP FOR RESTRAINED THERMAL EXPANSION
- TROJAN NUCLEAR PLANT
. PORTLAND GENERAL ELECTRIC PRESENTATION T0:
I NUCLEAR REGULATORY COMMISSION MAY 29, 1986 i l
l i
~
OUTLINE - 0 DESCRIPTION OF PROBLEM 0 SUMMAR.Y OF PRELIMINARY EVALUATION 0 OUTLINE OF TECHNICAL PROGRAM FOR FINAL RESOLUTION OF PROBLEM e DETAILED PRESENTATION OF TECHNICAL APPROACHES AND RESULTS FOUR-LOOP ELASTIC ANALYSIS ONE LOOP NONLINEAR ANALYSIS PLASTIC ELB0W ANALYSIS COMPONENT QUALIFICATION SUPPORT QUALIFICATION
~
DESCRIPTION OF PROBLEM 0 INDICATIONS OF RESTRAINED THERMAL GROWTH RESULTS OF SNUBBER TESTING AND INSPECTION DAMAGE TO LATERAL SUPPORTING MEMBER OF VERTICAL HOT LEG WHIP RESTRAINT UNDERSIZED COLD GAPS AT LOWER AND UPPER STEAM GENERATOR SUPPORT FRAMES MOVEMENT OF PRESSURIZER SURGE LINE
4 t h-CONCEPTUAL SKETCH OF TYPICAL <a . - . . . . w :: ~< _ ,ce, 5 1 '.): W TROJAN REACTOR COOLANT LOOP pq
-u
,.4 i
,e,C'lr' h
,i 9
'r
- #, 0 * '
, ,s8
< ,.g' '
f,/f
,c -
.~
'Q.Q- >>. /-{ ^7 ".
s.
..3I_ \
~;> u
. -t
. ~
; i .
i g hd*
. .s'.!
e# f .- --
. .l. .e-
<? [' ! e *
, t n
l p .>
- l. 4,.6 ',I
~~
/ s
. !)
'1 i ,g,. !
e h'. l
,. 'j*,(*4.'j&
d b t -
*s ,
\&'Y] .
- . t. .
.2. 2- ,-
'c jm ,
}
,,.f':v
,s y u'
- i se u.a h.* y I 64 l
- 4 K) g P.
g *O i I (, 3
' gl
;;:;g %/q,. a ' -
1 I g i l 1 % i l g l -""~. , 'n,%.3v
, , . .g i 1, .
, .. cj/-
t . i e - . l b 3t 3, .s .< u
's .,
+'
I I I _. __ - - -
Trojsn Nuclect Plant Mr. Steven A. Vargs
; Docket 50-344 May 21, 1986 ,
i License NPF-1 Attcclunent A Page 8 of 15 . , l 1 ' 1
- o. 8,1S*. o.t M
- o.lal* o. W l
1 N a r n- . r POMP SIPE ; l
@ 4 0.12.S *
+ 0.oto'
,,, SS2f/
B-B A-A B - Aa , E-pcpores isourse ccorr4cr (rm) o.9 o.9
@ coa' aw- o.its' l
of azs A 3 r'o.io 3 r o.co' m^b
- - - .. +
NN)'
-- aooy M 1 00' coa)
J moo
- y.,z. ** aar serwcEn C-C D-D
! - 5/4 4 A96-9#M L to %* cos.p oos *-[ g g g y,,w ,ggy,,,7 , cc,3,g3ges ,gy sN.N 3 Ata room con 4EKG OF EACH BdMPElt (TTF) 1 7 oc aoo- o. '
-k %e %s a S, (cour4c7 It o. DIS' t0.0Z0'
) .N - 'iaus=s
" ~
o.oo' , _ Peeftse,eegtaa_t Itttfilet te. tcour^co o mu ua-
' o oo 'A' STEAM GENERATOR l
(couvec O} LATERAL SUPPORT RING 4 o.339 HoTES: a CLEARANCES l
@taow i,
- sec pw6. c 372. rom srEcirter . oc . -
h3'A'4/6 vat.UES. .. - A4 l AE SEE DW6 C *>T3 PETAit, 4 . .a c c...
"*"* ""' 9 / I'8 [ O
- 1. dArs ARE SPEctFIED THE SAME FUK e,c Me p 5/4*S s.Et.ATus i To stA. PEETCH I %l
trojcn Nucicar PIEnt Mr. Stev:n A. V[rga . Docket 50-344 ' May 21, 1986 ' . License NPF-1 - Attcchsnent A ' Page 12 of 15 .I I NOTES: N -
- i. *- s ee v
- a. c-3 2 z ro a >r ectrie -
VALUES. . .rgegAgy COCLANT POMP 2. RELATfvE TO -fME Ft./V, ALL SPECIFIEP GAF'S Aa:E fnE SAME FOK THE ornes -rniere sAs s,c. Ane p. tb / ~ l -
.1.
- a,63-i k 1 OlI 1 0.020' j tooto' ActuAu W 0. 35V bctGALs gge 30,020' '
- f. C,' ACTdAL
! o.34 so j R 2..*A*i' . j 1 t ooto' ACTUALt 4 . I
- l. S*
j SA
# 0.084** .'
i io.020' 4 D.I20 8 ' l A c,TU A U , -IO.OZd' O.04,* k.TGA U i g N 0 064* H g .. - . . een i remitnoe s.inisat sticisc ca. w .senese Iseowe eductEAR PtANT
- d 'A' STEAM GENERATOR.
j LOWER LATERAL FRAME i BUMPER CLEARANCES l meonovea s sc e i p.4.g m-- a me eup,
-- u c.ec. oe,
- w ==. e o o='s 9/Zf / ale c e eswas e .
.o .
SRETCH*5 e
. ?
, w 'r N .s. o ,o c i
Lp N %f w O , 4 . at
, =. $
k Ik I 'O b M j 1% i t. i
*? '
s -
- r*. i .
2x ., 9-T **! %
~ ~ ~~~
v i ~~ 1' ' ~E~? . l (( iN I l - - 5 \ h" *o , l i I I ha m
,n T +<
i
. I -. I G -
G =$ n pf- si w o
,, ) --
& ,I 7
-[K* \
\ l',/
g -i 1
/ .
~
gi .i Q c .y
% 'O h r 5 &) is. .
., p
, ) ~s .
v>
.4... a,y n G. w a.s % g .: . . w pa, ,e .
.. s ,
, p ,
p' m. a t - g
. o l' o E sii
=
Lji f44(3 W >4
, q' ~
,,Mo ,s a r\
ei ~ : 4 l lf,.qy
)- '
_ _,4 ,
~.
m,A - r Q--4 $ Wg- >_ =i" ,1' f55V
.a 3 e ,
%_ 9 i
kN! k *
.I
.#~G $[-=4I.h**)tti'sp'7[=>,.J4
, I E 5
$Y u
)
y 'Lft' s r .I e43 5' m. k .N ~,oD p y5 f , 4 f ,% ' t
'4 u ,o - -
e' u s;g ~ ww;T cou
'sRe _
#* _1 --
%g
~
m. s n _ 4 9 e
SUMMARY
OF PRELIMINARY EVALUATION _ 8 2-D MODEL OF HOT LEG FROM RPV TO SG O WORST-CASE LOADING IDENTIFIED AS SNUBBERS LOCKED IN COLD POSITION WITH HOT LEG WHIP RESTRAINT CONTACT i
. -0 RESULTS INDICATE EXCEEDANCE OF CODE ALLOWABLES AT FOLLOWING LOCATIONS:
HOT LEG ELB0W AT STEAM GENERATOR CAP SCREWS ON VERTICAL STEAM GENERATOR SUPPORTS ANCHOR BOLTS ON VERTICAL STEAM GENERATOR . SUPPORTS O THERMAL EXPANSION IMPACTS PRIMARILY FATIGUE EVALUATION OF COMPONENTS AND HOT LEG ELB0W USAGE SHOWN TO BE SMALL (U = 0.1) O CAP SCREWS AND ANCHOR BOLTS ARE BELOW COMPONENT YIELD STRENGTHS FOR THIS BOUNDING WORST-CASE ANALYSIS 8 RCL-ATTACHED PIPING STRESSES DEMONSTRATED TO BE LOW DUE TO THERMAL ANCHOR MOTIONS IMPOSED BY RESTRAINED THERMAL GROWTH CONDITION
9
;W 4"
py 4 Zz 'Weg. , Y 8, JD Iq' (g) 51.- Y, I I>
,,jM p6
@ ,/I,j'll.(
1 4'- kAQ O
# u'
- I
#,;&;;g p p ls 4'- ,) pb 4
& vp S It 5 p ,, -4 ,
g A h EL LGo" / y*; Q' .,. . , s" +^ off %g@t -- ( PRELIMINARY EVALUATION MODEL
- ?
QUI _LINE OF TECHNICAL PROGRAM FOR RESOLUTION OF RESTRAINED. THERMAL GROWTH ISSUE 0 PERFORM FOUR-LOOP ELASTIC SYSTEM ANALYSIS TO DETERMINE CROSS-0VER EFFECTS OF STEAM GENERATOR SNUBBER LOCKUP ON ONE LOOP TO ANOTHER LOOP O PERFORM' NONLINEAR ANALYSIS OF ONE-LOOP TO ACCURATELY PREDICT COMPONENT STRESSES AND STRAINS, SUPPORT LOADS, AND GAP EFFECTS 0 PERF.0RM CONFIRMATORY EVALUATION OF HOT LEG ELBOW AT STEAM GENERATOR TO ACCURATELY DETERMINE COMPONENT STRAINS AND FATIGUE USAGE e PERFORM COMPONENT FATIGUE EVALUATIONS AND SUPPORT LOAD QUALIFICATIONS
6 FOUR-LOOP ELASTIC ANALYSIS O PURPOSE: TO DEFINE CROSSOVER EFFECTS OF CNE LOOP ON ANOTHER FOR VARIOUS COMBINATIONS OF SNUBBER LOCKUP 8 MODEL DEVELOPED AND RUN ON IMPELL COMPUTER PROGRAM -- SUPERPIPE 8 ASSUME LOOP B SNUBBERS LOCKED AND CALCULATE MAXIMUM VESSEL MOVEMENT FOR OTHER LOOPS LOCKED 1 l l
s a
+'
-- l ..
, 11es I a& *
\ et -
..s . .v + ,
. _ut =< ...- A. '
__. , .j g . - . . t , .i
.; e ** * ~--
-%.. .- &.-:.--=- .,. ., . - . G*-.^ .- s\
y 3 I .. ... p g isme \ ." I ,
...$/ 4 ,._.!.d
+-=** ' e,,m,.
9 .'i, , 4 s-
+- ~" ;
- -. .. . . . f.'h
%m.s ,.
,\ h ,
~.
. '& /-
f .
~ , D. r.'
s f'. $$.'9 , a .- . v/ . m% ~
's (p I'r
.'.' u, \.[\.'-
i T .--
4
- 1./. . .,
( - . r. -, ;. % x 4 y
\'t- - 90' ;,4 -
.._,,. j a--n.y tY SQ.
.e.~y M2.
h? i C;b. - w. - . & me % . ' s u l 9>A ., . s yg ' N p .. \sg/ 4 '
, j e
.V.sV.T o s
_ *.e .' .. g Cfy==.*e h/i .y =.=..a
,g y s. , -. 9, <
I . r t. l ,
,, p 3
1
. . . ~.4 _ . ,
.- ) ,,,
.e--- ---+--
. . .n ,
.*
- s.== s'.* A* y .
..w, "4
Z7 Eg'..
- 4. y/j( '
,,.. ' -*"*,.... =.=.
g L.. e 6 = .,
*~. Q~'
, S f<' .v. .';%. .r.:::p~:*
y,..
.s
.:-[',s ,. :. N *
. ,. 4 ., - .
o g'l&..
) . r'= h '
e,/. :3
,.=,. - -
% / 6.. .=n th4 , .un 6's 3v.- La s ., ' s .A:. .=.n -
g- -
,,..v., M . :L e
.e
. i
.~w - .
n.s .
. s. .,.> i c,
-. . a .s . . *-
.=u - .. <- % ... %, .
a.
;t.cn ' ~~
g . , ,'., u -. ,. --.
.@ m ..-.
s
---e+!...]Q'.'tg@,s/s.-
@@@ ; .p s .
y
, f. . .
e;--' .
. f .4Jp f .~,-~ f . < 3.;.f". 9. . ' ] ~'
.t. g.
y >., . j . . .
- = i i y
m La
+
\"
?. "- ~ ~ ' . . n I
REACTOR COOLANT LOOP
~
O REACTOR PRESSURE VESSEL DISPLACEMENT RESULTS LOAD CASE X-DISPL Z-DISPL TOTAL DISPL (IN) (IN) (IN) LOOPS A"a D LOCKED 0.017 0.00I4 0.017 I I O CONCLUSION: RESULTANT DISPLACEMENTS ARE VERY SMALL AND WILL NOT HAVE A SIGNIFICANT IMPACT ON ONE LOOP ANALYSIS. FLEXIBILITIES IN EACH LOOP ARE SUFFICIENT TO PRODUCE NO SIGNIFICANT CROSSOVER EFFECT TO ANOTHER LOOP IN CASE OF SNUBBER LOCKUP.
ON LOOP NONLIN AR' N LYSIS O PURPOSE: TO ACCURATELY PREDICT COMPONENT STRESSES AND STRAINS, SUPPORT LOADS AND GAP EFFECTS DUE TO WORST-CASE RCL CONDITION 4 KEY FACTORS AND ASSUMPTIONS: CROSS 0VER EFFECTS FROM ACTION ON OTHER LOOPS IS INSIGNIFICANT FLEXIBILITY OF ATTACHED RCL PIPING IS SUFFICENT TO PRECLUDE ANY MAJOR IMPACT ON RCL RESPONSE THERMAL TRANSIENT EFFECTS ARE CONSIDERED SMALL AND DO NOT SIGNIFICANTLY IMPACT FATIGUE RESULTS EVALUATION IS PERFORMED TO ADDRESS CONCERNS ON FATIGUE USAGE-TO-DATE TROJAN HAS EXPERIENCED 28 HEATUP AND C00LDOWN CYCLES TO DATE
9 MODELLING ASSUMPTIONS (GE0 METRY) - GE0 METRIC DATA FOR LOCATION OF EQUPMENT, SUPPORTS, AND PIPING ARE BASED ON ORIGINAL PLANT DRAWINGS FLEXIBILITIES OF RPV N0ZZLES, SG N0ZZLES AND PUMP N0ZZLES ARE CONSIDERED i GAPS ARE CONSIDERED ON:
.- CROSS 0VER LEG FAILURE SUPPORTS TANGENTIAL BUMPERS ON LOWER AND UPPER STEAM GENERATOR SUPPORTS HOT LEG WHIP RESTRAINT -
RADIAL BUMPERS ON LOWER STEAM GENERATOR SUPPORTS SUPPORT FLEXIBILITIES ARE CONSIDERED
O ANSYS COMPUTER PROGRAM UTILIZED FOR THE EVALUATION . 0 ELEMENTS USED ARE: PLASTIC PIPE ELEMENT (STIF 20) PLASTIC ELB0W ELEMENT (STIF 60)
" ELASTIC STRAIGHT PIPE ELEMENT (STIF 9)
~
GAP ELEMENTS (STIF 39) v l 'l
The element e-z coordinates [ are parallel to the I. J. K plane.
,f -
a-% g- - K y
- ,J T(180)
RADIUS OF CURVATURE
/ 7 a
\ / ,
\
. TAVG I _ "y
.- p
*T(90)
>Y The element lies in the plane of nodes I, J, and K X
Figure 4.60.1 Plastic Elbow - z 2 J4 END 2 [ N I
- - ae :x l
-+- I > y I
9 i
. l
- e O NONLINEAR MATERIAL PROPERTIES ARE USED FOR PIPING ELEMENTS -
O MATERIAL PROPERTIES ARE BASED ON L.D. BLACKBURN'S < WORK: "ISOCHRONOUS STRESS-STRAIN CURVJS FOR , AUSTENITIC STAINLESS STEEL." THESE CURVES WERE USED TO GENERATE DATA IN CODE CASE N47. O MATERIAL PROPERTIES AT HOT TEMPERATURE BASED
~
ON BLACKBURN CORRELATIONS AND MATERIAL PROPERTIES AT AMBIENT TEMPERATURES BASED ON RAMBERG-0SG0OD C.0RRELATIONS I
\
[ i
6
~
0 BLACKBURN CORRELATIONS (TIME INDEPENDENT)
~
f=t @E+(4_sp/g)1/g WHERE (f' = STRESS E = 3.3675E7 - 13823T(*K) Sp = Sy=12198 + 6.7093T(*K)
-- Sy = 25850.5-12.8179T(*K)
K = 69964-25.4491T(*K)
~
/nt = 0.25824 + 7.749E-5T(*K) -
0 RAMBERG-0SG0OD CORRELATION
~
( E/g o) = x (C/Sy )^ WHERE JhD Sy/E ok = 2.847 st? = 4.023 i i
O O S
- O se se
> Om (wu) 7 70'f 9
O 3e -- 7~s 4/4 6 'f 20 <- lC - P/projg ;}, A ygg,4 g Y [ 0 , 0 c.1 0. V d. to o, e /0 Jir's o r ', 'l
~
Ye) MATERIAL STRESS-STRAIN CURVES o * {
1 - -ua.- . m - -4 .a., ____g 8 e O 9 Y d me St u t,S (kd ) go - - 9 e# 40 - i 7: 7o 'f yo . . 1 ' 4 TE 6 / 6 e 0 *f
, 20 --
i
/0 --
ELAck) Md7tb 4 L c , , C , s, .y 4 . g i. 0 i NM #A)y [ ( /c ) i MATERIAL STRESS-STRAIN CURVES i l
4 __ ._. _ --h.e - 1.-_8. - _ _r _ 4.- a-23 -. _ w - , a . _ mm e
* ?
8 ALTERNATE MATERIAL PROPERTIES WERE ALSO DEVELOPED AND USED TO DETERMINE SENSITIVITY OF RESULTS TO MATERIAL PROPERTIES 4 O RAMBERG-0SGOOD PROPERTIES DEVELOPED FOR ALL TEMPERATURES d e } 6 1 I I I
n _. -_ a x -A-- - .A % , . , ,, s . 4 a es ge (k.ti) go __ T* 70 */ 30 --
. T*4/4,3'8 t
i / zo --
/
- /0 f/Pf 4167641 A L.,
e , , , 5 o e.2 oY s. 6 s. 6 ^0 Jrtsso) { i (%) 2 i i 1 ALTERNATE MATERIAL STRESS-STRAIN CURVES i t
i
^
strar cust ) So
'40 . 7= 7o */*
32 r- c.ic.. s F 20
/0
?/Pf 1716 7 E As A L e c. z av au o. c i. o
.cw . , , i c%)
I
- ALTERNATE MATERIAL STRESS-STRAIN CURVES
8 LOADING CASES CONSIDERED . LOAD CASE NO. I CU L TION 1 2 3 4 5 6 GRAVITY X X X X X X PRESSURE X X X X X X HOT TEMPERATURE X X X X SNUBBERS LOCKED-COLD X X X X SNUBBERS LOCKED-HOT X HOT LEG WHIP RESTRAINT CONTACTED X X X RADIAL S.G. BMUMPERS CONTACTED X X CROSS 0VER LEG FAILURE RESTRAINTS CONTACTED X l l
. r ComPomeur Quxursra rsosu
~
- 7xE2 mal SxPArAfron Lo Ahiac, s/AJ saa s ensa per-ON Cob 6 QUA V f/ C A r/ CM p'c st, fowC wrJG C H f(xd S t gi a c v.sAgc :fA c.~Aor-6 4 f!rt/ 7 d b L,,O A D IN G Cs9JE So s11 A 3 0 G. con /ccans /J FA7/606 t/.$ A G G Y0tv35CO MS^J T Qt)A&tC/fA T/OM 4h4al, 86 8A!6b ON G Ac.c u c A ri H G osass FAcrotz., p r c,e./rient t.oca rio r.> s 4d :
Lly,r w (d; + A Lt d~ AO e Os~yrNo. / Jhd.f /Yp os-C All = uJ4ge h ek r~ c/ue k m u,~a k /~"" nna 7~<. L SO t*f c.lfJ
. r e
M N O R I M
- l U l Y
% M LO 6Y O L
% R H A
' C e t
LREP r a u E P c c ( K C O I C*F A g 0r y N 4 0 1 N0o pEK Glu L 8f a y f
- L C
- EI ENI Nmr .
g
- = T- Do SDEFe p p
me C NA CEarvu ; v I
,X dC n )
e T s
~ s I Y Eai s g o, OTsh y lou eT f g
~ . SA LNlao u
. S Vn o A w MEdi
- URett a 3 0 I
MTup Ualo l ~ 0 F OAb r (y 1 ERRae VHE Tn t t. RCPsin . o v
= U CN Et Mia C
% n ERO To C UI R 'g G O1
% T L I
E F 9- u AK I e 6
% FC l
/
I b T
' NN T a
A G , Y ~
\
I SO / 2 EL 0 1 DL _. , 2. A
% 9-1 m' G I
- N F - 6 0 1 A X 0 E: 6 T 2 A' - 0 1 NE O= 3 O' 7 0 W 0 c 1 1 2 s^ d o 3; l : i I l ' il
l l
.r l Mor c.s c, J ren m Gsasizaroa ScoocJ l
- d e ri e n t. dongpossar /brarisito gy pasumiana y Eswun riom -
* /rraxinwm s 772.A ia Rsagg sue ro poiruurrea
. tacaJr - en rr u s b w cr :
e, = 07% ( rnub k /ocLup ,a cuid padica 5 Sc, /ower dumpw 6d hd /ey cahp reafru at Con keh d ) Ez = o. y y., ( sa ,i w Jockup ,~ As posi //o~ ) , Srnunu
= /* l fo
- UJA&E f A r 7 C rl fsQ L.C ut.A 76 0 *.
Um x o./ ou= */wo = 0.00 arm- = W <. i. o 0, /$
I
. P
- tvo N L su EA st
~
A n a cy.t t.s A EJ u t r.: Jcest
)?6A40NA6LE 'BMfb c4 Con 1PAA /J OM 7b rur harx
- G/Z.f4NJ7xCG T 7E.!r.;;T cA) ELG o M Ont~ JrA nUUJ T 57E G L /%db d b/* .) eA7iO .Dmi t.w To
'hY L.& 6 E660M I
e/foM = b 3"
/ e/6cd * $1000 0 E' =
0,z3fo m ! M A/NJ 7?f?4 M TEJT bAW i
4 j
- P 7
I a 5 o e . p i, U
! ='- 3
. E 8
.. 5 O
E E. Tv a
\ :t .
< i
$. "4 a r
1 ;;' ;; x . 1 > i i 5 g J Q 3
. x h - $!
+ .3 ; x :;-
-=> gg{ k gv
. 1 .
n.s > n'
. I t - .. :s 3 )
t a .I. 9.,j.. . . ,. n R.
$' e %
U ! 4 g ger ! i, J g b I
- d. -
gi i
. w g .
. m N\
I ' k=@f=T====C , ' . 5 $ s j i f e s a q l I-*=-D. 'g a , e t __ - ___ _. . : , j [ a 4
l
)
. ,a 6 - C#4L DurG 77 70590 EXTRADOS
. t l
SF OUTSIDE INSIDE G8 A5 A5 j i A-4 A.4 A3 A.3 E- '--- 2708
, 908 - < A.2 A2 A.1 A.t j A+1 A*1 A*2 A+2 Illo A3 A.3 gygo A*4 A.4
, A*5 .A*5 150'
. _' # \ /
tel PE.17 INTAADOS . EXTRADOS
~
E4 08 300 450
'0UTSiOE 145tDE A.5 A4 i A3 A.2 q->-- 2700 908 - ,- p < A.g B . 90 jf A+1 A*2 A*3 A+4 13$0 6 Ae$
150* tse tel PE-18 INTRADOS Fig. 7. Strain-sese locations on 45' cross-sectional planes of PE-18 and -19. 64Cli^)Erntf 7 77Jrs - .5MAirJ mcAsve4ye c;
T 1 v , l .i l l e i l i l l - on s -Ow c n .soest j 12.000
. __ . me v " A ;J -oo-
- e ?
7
/
I 10.000 C'"-" g # ! A s y~ xs#" l
/
8000 - 2-0 0 OIAL INDICATOR I
- A DI AL INDICATOR 2 3
4000 # -
/ a f
2000 / / l t l l 0 [ ' "
/ "
/
l 0 0.2 0.4 0.8 0.8 1.0 1.2 1.4 1.8 1.8 2.0 2.2 2.4 2.6 2.8 DEFLECTION iin.1 i F18 19. Imad-deflection curves for in-plane bendin8 (-98,) of i specimen PE-18 (1 in. = 25.4 aus; 1 lbg = 4.448 H). j fo "ScN S o 6 / doca JJ 1 i ) Gt/fdAo J77t Ef r A6JUL 7.C - fs* Abs lbff CGf U.*~ ' CU!/ Vfd i, I i l
m
=
- e tubst: IP?.r. PP pereg to ooo n
. syn x -
g ;____ A gnone .. . / . . .- I S.aoa
/
/- - .__ _ . .---
j
! StaA 4 6&G( A . P
/
e / o saa mo anno anos sono e m . staam s, e Fig. 32. Imad-strain data for in-plane bending (-tf )8 of specimen PE-18 (1 in. = 25.4 mm; 1 lbg = 4.448 N). 626E+3 3 77L4s7~ TG.ir 26:uL7
~
Y H T L G' sL6W' V LO4TI6N 1 PURPOSE: TO PROVIDE CONFIRMATION OF~ STRAIN RESOLTS IN STEAM GENERATOR HOT LEG ELB0W
. 8 KEY FACTORS AND ASSUMPTIONS STEAM GENERATOR N0ZZLE STIFFNESS IS SUFFICIENT TO KEEP ELB0W ROUND AT N0ZZLE END
*' MODEL EXTENDED (RT)1/2 ON HOT LEG SIDE TO PRECLUDE END EFFECTS ON THE ELB0W HALF MODEL OF ELBOW DEVELOPED SINCE PREDOMINANT LOADING IS IN-PLANE ,
- _ . ~ _ . _ _ _ , . . . . . _ - . , - - - , - _ .
. - . . _ y _m .__.._...___,._,_----_,_,_-,-m-, , _ _ ,
O MODELLING ASSUMPTIONS (GE0 METRY) GE0 METRIC DATA TAKEN FROM ORIGINAL SPOOL PIECE DRAWINGS ANSYS PROGRAM USED FOR EVALUATION 16-N0DE THICK SHELL ELEMENT (STIF94)
~
USED FOR EVALUATION O b
4 6 0 e b 4 k a %
/'
k s l i. i r HOT LEG ELBOW MODEL
n 6
\
~ -
1 \
.. = ~
\
\\
hk p -
/\ .,
\ '
/
N^ 9 i- //
/h I \/
~
N l
$ 5 0' E L G o u M 0 b E L,,
L . . _ _ .____ - . . _. _.
T ee Z h y Bottom (M, N, 0, P Plane) N -0
/ ,'
S ../ K T SIGY 4/ SIGX V*
' M $1 Z R
~ v -G)
- N Top (I, J. K, L Plane) ,
Q Surface printout is given a: top (Fr-ce 1) and bottom (Face 2) Y X ANSYS THICK SHELL ELEMENT (STIF94)
~
si . ..~~ .~ . s. - .
. Enclosure 3 i A. ngsenvoin RESPECTIVE CONTROL N
?. VALVE COMPONENTS
' h
\ p J '- - - - - " -
SAME A5 SHOWN BELOW.
\ g
$:h x- g -
l
\'N -
O I mm seu
- 1. tO-/ j
- ' IEEE ELE ' N/
- \ p _n _ _. ._ _ .J L_ q
/
N' N N l %-<h*-v y l /j 3 I4 gi sis L J / sgN O 1 0i59 N (( (O
/'
- I s(N - ' am - assr N NN3
#g s ._. .;
ss p_n__ e_q {r
- t
\g N lb<
Iy d+4l -g I 7 _x _ _; #[/ us ' t_ __ - l gte s O I I el56 EtiDEL I
/[
(O Nlb .
' IEEEI MW N/
NN ( _v!.L
- - A* /
N / N Iconstetes caento. A - i L CONTROL VALVE
/
N scaa cm . // N
'NN-O I
' lRDs ecos sueenassm l
EtiMF (O N/ , _j j FIG. 4a. SCHEMATIC DIAGRAM OF CONTROL CIRCUlT Page 12c. 3b
P NCTE! ( CONT AOL VALVE 16 FURNilMED o WITH (4) CUTLEft (2 EA.5CE) To allow wouMYino (a) oR
,I. MORC luPPREll0RS IN MRALLtle RESERVOIR THE OUTLETS ARE #A0VIDr0 WITH CHECK $, SPRING SIAltD NORMALLY OPEN.
_ R E F. AI, A2,31 & B2. .
$ stt FIG. da. PAGE 12 m FOR I
.. ,Q TYP6 CAL CONTROL CIRCutie )
CAPPt0 . OUTLETS. _ __ _. _ _ _ q VI ) (R2 V2 n ,,x Of X F CONTROL l w VALVE. I vI U lv ^
^l A Q 2 l
l - L_. __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _. __ _J
. 'A g k\ NII L b._Y3 'h" h MM k J
\
k ' N
\
x ,
\
i , N N N r = g .;;=- _ 3g3_3. . = e- , _=g s N -__ - =. -_ x 3s N y 25_-st_2. _ _ 5_ _.:: ?_"=426:W_c _ . , A 6 TYPICAL SUPPRESSOR FIG. 4. SCHEMATIC DIAGRAM OF CONTROL VALVE 1 900K SUPPRESSOR 17 i Page 12, irim ,,.u.., .,, .. _ _ _ _ . _ _ _ _. . _ . . _ _ . _ _ _ _ . _ . _ . _ . . . _ , _ . _ _ . _ _ . . . _ _ . . , _ _ _ , . - _ , . _ , _ . . . _ _ _ _ . . . _ _ _ . _ _ _ , _ _ _ . _ _ _ _ _ , _ _ _ . - . - . . _ _ _ _ _ . _ ,}}