ML20148H594
| ML20148H594 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/13/1988 |
| From: | Cantlin J GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20148H541 | List: |
| References | |
| NUDOCS 8801270258 | |
| Download: ML20148H594 (28) | |
Text
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EN N REAC'IOR INTERNME VIBRATION 'IESTING AT PERRY IMIT 1 l-
[b h Prepared:
Ge al Electric Site Operations M& nager / Date a4 A Q,,4' kee tup Element supervisor / Date
(
8801270258 880115 PDR ADOCK 05000440 P
PDR 1
T Preliminary Report - Reactor Internals Vibration Testing at Perry Unit 1 The attached data cheets provide a summary of the preliminary evaluation of test results obtained during reactor internals vibration testing at Perry Unit'l.
The testing at Perry, although comprised of many ind!.vidual tests, was divided into five (5) sections:
1.
Preoperational (Prior to fuel loading) Testing 2.
Non-Nuclear Heatup (Post fuel loading) Testing 3.
Low (60%) Rod Line (Test Condition 3) Testing 4.
High (100%) Rod Line (Test Conditions 4, 5, and 6) Testing 5.
MEOD Rod Line (Test Conditions 7, and 8) Testing At the end of each test section the GE Vibration Engineer prepared the attached preliminary evaluation of test results. Based on these test results no anomalous data that could bear on the structural integrity of the reactor or reactor interna?.s has been identified therefore the preliminary results are considered acceptable.
The Final Report will be prepared by General Electric and will be submitted as required by Regulatory Guida 1.20 when co@le.te.
2
Preliminaq Results - Preoperational (Prior to fuel loading) Testing l
l I
t 3
l I
....t
~
GEN ER AL h ELECTRIC 03s2001 ss uo. 29 NUCLEAR ENERGY BUSINESS GROUP REV 0
- & (. 4....-
i '
TABLE 4.2-2 VIBRATION MEASUREMENIS REPORT REPORT OF REACTOR INTERNALS VIBRATION MEASUREMENTS (STI-34)
Plant / Site ' PERRY Test Identification TP / S/S - F -00 /
Test Period: Start I - O 86~
End This Report is M Preliminary Final Test Scope
.y Comeonent Cocumen t
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. Alt viisRA riow,s AME wr rM /W CA / TES/A f xC EPT fot SENsett3 wo7N'
==
Conclusions:==
Esc a ss worse, sur>*Ec RED.4HotW 0 a ffs. A u n Towa *TcQuitsw&
'AccEf7AtycE CR ITE R/A W/ rWfy<1//tR ftE3oL UTION, i,)
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Prepared by Final Report Reviewed By AW Tist Engineer
~
Reactor Vibration Analysis Unit
' S ~/2 - O ~b-Dato:
Date:
Sheet 1
of.
4 Distribution:
Startup Operations Manager at Site Site Manager at Site Lead Engineer STO at Site Lead Engineer STD and A at Site.
Manager, Reactor and Containment Design i
Ma na g e r, R e a c t or As s enb17 and Pr e s s ur e Ve s s e l De s i gn Manager, Reactor Equipment Design l
Xanager, Reactor Vibra tion Analysis and Instrumenta tion i
Proj ect Manager l-2C.407 A (6/80) 4 l
O:
t G E N ER A L h 'E LE CTRIC moss:ut mo. so NUCLEAR ENERGY
(
BU$1NES$ GROUP My o
- 5. (h TABLE 4.2-2 (Continued)
Sheet 2
of 4
See A/.so Sheet 2 a.
pgy Te st Ident ' fica tion 7 P 1813 - P - Oc> /
Test Conditions Date Tine
' ' Test #
Test Conditions Comments 5 -io-fr 2200 7
A uin B u. s.'
S-!3 -fr
//24
/
A tena xsx.B tems unx s->s-es
/6ss 2.
A n n.Bu,a o
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5 -/5-85 //0 0 5
A nsx 7a m ax " "0
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5-15-85 /f30 A xxx areio 5-/5-25 /6 20 A
/9sok B a.s.
5-l5-85
/f2.0 9
A 7s$. B n.e.
5-15-85 2 / 615
/9 A NE.' bia 5-15-85 2315
//
h MA N Bmi,4
.5 -/6 ~ 85 0820 20 A as. 'sso7.
5-/& -85 N/ 25 2l A u.s. B 7s7, 5-/& -Br
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B 1007, xse coxnereo ove ro 5 rump MoroR FA tt JR 2 s -/4-85 2000
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5-5I-Bs
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AnANEmsy 5-3I-85 /330
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- /VoT ENERG / z O MAc e /o oj's AATED Yo t'. uMETR? & C CdC YL 0 ki
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- PER C CH7 V A LUES A R E.*]o kt M A L VA LUES O uso.4er s nieo 4 4 + M'o r A t /!OMINA L VALUE
i G ENER AL @ ELECTRIC nasa 2wt sa uo. 3o NUCt. EAR INER GY
(
SUSINESS GROUP MEV 0
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(
h TABLE 4.2-2 (Continued)
Sheet 2 a.
of 4
P1 sac
?SSSY f P / 8/ 3 - F-0 0/
Te st Identification Test Conditions Dato Time
'Teit #
Test Conditions Comnent A MAX O mon 5-31-85
/500
//
6-/- 85 0005
/o Anix B off 6- /-85.
40300 13.
A M//V BMAx 6- /~85 Osis gg y,,g g c
4-I-85 07/o jg A gg, g y,7,
" " *M Th/7 QEK 6 -/~85
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6-2-85 0//5
/5 AMAX B 5 0 9o 6-2-85
/208
- 2. 9 A MA SM
?RioR To 2 PUMP YgIP 6-2-85
/215 8l
%o % P Tn p 6-2-95
/HB 27 AsoZ ~Benx 6-1-25 202o
/7 A m x, %Ay 6-5-85
]530
/3 AMax Bsweep 4-5-85 2/45 25 S m.w A SWEEP e
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GEN ER AL h ELECTRIC 0382 *1 sm. 31 NUCLEAR ENERGY BU$1 NESS GROUP REV g Ll.
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Ss TABLE 4.2-2 (Continued)
^
Sheet 3
of 4
Plant ER R Y Test Identification T P i B I S - P-oo l I
h S I'en i fie n n t Results.
'Ibese results represent the maximum vibration stress amplitudes or the dominant v.ibration responses which were measured for each class of comp'onents. The maximum allowable peak stress amplitude is the Level 2 criterion for the material of the reactor component.
Test No./
.GRP.2 Condition Sensors Amn11tude Frecuency % Crit erl s' Comments
- P'~P s)
.. JET IO Q /oog d
o.
g, PuM P
'B n.s.
S%
ig.,a ar.
- e.,
375Ad 4.f.
17.2.
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/* G./*f
/j'. 7 RPECTRA 2* / *
/06.
2-7"o ret.
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V 5S ne
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2E 7; RRvSH hou3t
^!fl 000
$ #hd
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- ""E C ORE SPRA Y 2Qgig * $97
- 2. yng 8y 4.5
. _.._.. L WE SH!M 2.726 73 9
I 3S l31
/7
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I
-rerAt. 7/a %_ _..SPECTRAg L. UPPER
/6/AMAA
. 3ks*LS-. %15
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- 9. ::' s'
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' Indicate irhether p p vaines were measured from Brush records, oscillograph records, or estimated from spectrum records.
4/0 78S ?./ V'!.e s.t d e a r e tu o **ea //v /e es eMee /be f is ln shile</ Al!'> nl""'"" O I"#
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G EN ER AL @ ELECTRIC osa2coi u m, 32 NUC!. EAR ENERGY
- q BUSINESS GROUP may o
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C TABLE 4.2-2 (Continued)
Sheet 4
of a
Plant IE R R Y -
Test Identification T P / 813 - F ~oo l Reference Document Design Specification 22 A V3 64 Rev. %
Test Procedure Specification 2P A67/ Y Rev. V Vibration Criteria 3N N A f 77 Rev.
' Installation SpecNica tions
'2 / A 888Y Rev 7-Installation Dvss. Internal IJ 9Ef6 9 Rev. D External 80 9 6f 7/
i Rev. U
(.
Connection Drawings
/S 7 C S 7/I Rev. O
/S'? c 57/9
/59 c5 717 g
_pe 8
i
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Preliminary Results - Non-Nuclear Heatup (Post fuel load) Testing l
9
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0 t.sst=t2 onove i
l TABLE 4.2-2 VDE.ATICH N'T5 REPORT
- /
rd hg;?
REPotT CF REAcrot INTERNALS YDRATION NF.ASUt2MENTS l'.?
(ST1-s4)
SEKYY[ Test Identitiesties lU ~ ? $ ~ 0.14 (USCKt7kA 0
)
91 ant / Site IB /
8I 7 IN End Test Ferled: Start 8
This Report is X Prelialmary Final Test Scope Ceament Convenent 4.i9 C.Af 7M IA Ext t? T 'rpret All Y/bAAT!*"? A94 wrTWeN Cess 1ssiens:
w t T N Ear C t/f An:s//4, Juf,*s c.fsc 0 A w as~st* Gr6J.o 4 wp owe.r4 0 E A s*r g frM M ( N /.,f.
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Btmak Report Reviewed By Prepared W M-WA k/M afAAW/
'B.a. W()
Test Engineer M c
_J Reaster Vibratios Analysis Walt T
II, Date:
Date:
is.st 1
.c 4
".h (
a
- A s Distributies
i Startsp Operations Naasser at Site Sits Emmager at Site Lead Engineer 870 at Site Lead Engineer STD and A at Site Ramager, Besster an' Cassissent Design Em ma ge r, Re e st or As a esb17 and Pre s s ur e Ye s s e l De s i gn Ramaser, lesster Etsipsest Design Manager Essetor Tibesties Analysis and Instrumentation Project Manager V:.' '
) dadh.ee?A Mel v
10
Nuc.t r t. I NE Acv
.1 h A A :. 4 E i - s.
Y10035'001 na ao. 3 0 i
.s
' susintit c AcVP cgy g TABLE 4.2-2 (Contissed)
N
+
'i:)f Sheet 1
of 4
Plant NE04Y I
Test Identificaties hT -- F4 / - o34 NNT2CA L \\
Test Conditions Date Time Test #
Test Conditions Consents
.8ls~/96 10 :34 II AmBm a
v.
9/5-l84 19:oo L
AM 8m
~.:
9/c/sg 03: 2_4 13 A us Bro, 2/4/96 oh.'47 i
Ai Bus" 9lC/86 se os 3
A e.<, Bus s/6/ar,
- 14.ra 3
J' ~ Aa B,s I
f 9/6/84
/ 7:4.t 4
Am Ba 2/4/9L d s: c o e'
% B4 9/7/26 of:3o 7
A a Bw-s ya4p -
ra
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y nr s. -. n s
e -a - ~ wa 2 7 9l7/96 c7.'3 o 9
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- 9: Is' Io Am a w.
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ggy g BUSIht33 CDCUP i
TA31.Z 4.2-2 (Costissed)
- /.<
GN Sheet 1
et 4
' O 1
Flaat NNY
/
S"T I - F4 r - 6 3 /.e.
Teet Identifiestion L
Binnifienst Results.
These results represent the assiana vibraties stress saplitudes or the demissat vibraties respesses which were seessted for essh elssa of eenpesents. The assimum allevable pesh
.zi stress say11tsde is the Level 2 eriterlea for the asterisl of the c..
..j,{
resster componest.
Test No./
- 1332. Conditlen 5"emiers A.an11tsde Freesenev Scriteria Causests *
(rp)
(Es)
.,.p 4
.3 3 3 3 *7
.sgg.
seps N
Mbe )
Alpa G 3g 4-6 '/.
4"A 6pe 44, eM*f #A.
I(
- "P. 9u6 64 48 8 %
h = M 2 % 4.5PecrnA) i EP8CMg TPS
/4 pe 63
/4 9 9[,
z")
temaSDie %vk) 003 II.%g.
g.g a. t er, 9.rj e i3 34 4%
3M = 9 f 4'A. WN) i rpe sagt
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- 43 *A
.737 w cad,s. Off40 45ue
~4 2 9 o ')L
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t.0 ue is t. Ri
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SET-eu.v,e csAE smer
(. N6 S:erwrCAN7
/gn.sApeasG j N.I.
UNcJ!A 4 /,ae. p b> )
l}m,
3.%
mg
.4 eons vuess
( M.4 SkMSest.S F u sa *,JEEi6 To h *hui! Wrp/ OThat AANTL *J.N 3.T. )
can N(
prest.svena yp9 f.39 au.
sp 9g 0I a.7s a:1
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47 % (SO2.>
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II.1 d4 *A
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- "5*
- W M. *,
.rren.us e rsa av Nozrs. W *23NWF t Ise se uma.
pp ussa.m as negs,cs<sm :n, h :rc. tali.
'Indients whether y y valses vers messated from 3rssh records.
ossi11egraph records, or estimated frem speetria reeerds, "p: veer.g Vatsaa,; cA,t:n.r a.r fo r-13. I ud Is. t H b M4 g
- Nr Wp.4, A
A CE s.t.
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. W.
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12
m~
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G E N E R /.i. @ E LE CT R I C nasm
..32 aucuaR aucacy i
any g f
suslNESS GROUP
- cq,f
' TA31.E 4.2-2 (Contissad)
Sheet 4
et 4
Plant MC-R A T
/
87'I-N/-0 4 Test Identifiestion Reference Document d a A M 8 4-Rev.
4
.I Design Speelflesties
, f::
Test Procedare Specification MA87/9 Rev.
o Yibration Criteria 384NA971 Rev.
o 1
Insta11stica Specifications S/ A386 4 Rev.
O Installaties Dogs. Internal 84.4 EM 9 Rav.
D Iaternal 9496871 Rev.
n Cassecties Desvians
/49 CST /F Rev.
O i
I fM C&7th I k 9 C & 7s '7
'i' Attachments Centrol Roan Data Sheets Chamael Assignments Tape Los f
We Nbee?A(&/%ej 13
i I
l Pmlininary Results - Low (60%) Rod Line (Test Condition 3) Testing I
i 1
i i
14 1
N GENERAL MD ELEC7RIC 22'* * *
= =. 2 8 muet:4n zwanov Bus NESS G".OUP tav 0 t9i TABLE 4.2-2 Y23RATICN IEASURIIGNTS REPET 11,
-4 s
REPORT OF REACTOR INTIRMALS TIBRATION MEASURDENTS (STI-34)
Plaat/ Site M4W /
Yest Id stifiesties 377 FA/- o 34 ( fu% 4.2. N3 Test Period: Start
.t//6/s 1 End 4//7/87 This Report is X Preliaisary Final'
- TC. ***b e / M 4 W.*
' OM L'~^
Ad Toat Seope M gry w% c,;C 4 s '7.
r' sol..l2, a CAA ).
Connonent 1g3R32.1 M h.wes azset BnAG 4. hrsst>sGt Cavrear Aab gut >t-Tuss
.rN-co ARE keuttn dr cons speAv Line Ubecis 5%eous suALL upese duzas Atzwe t.ausM smususu 4,u % '
sa
-s h 4 A w h.w h ** a--
- k. &a 2dA[,
Cessissions:
e=W h ha. he aaf c % e.... b tax Q Armena
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e.a.A.nctiv 9 Q Lse v H W."um.dar Msd ft..a ae-anum, set,a vtLo.nt,%
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~
q Prspared by 44ee4 Repert Revieved By
_^ l'"he
[,,
f4 3.c. m r Test Easinser Raastor Yibration Analysis Unit b 9 N ")
d[/ 7!d7 Date:
Date:
Sheet i
of 4
- ?'
N
.aSe=ee?A (4/sen 1
.15
mucuan an:RGY GENERAL-ILICTRIC m *8 "
= =. 8
- I susmansenou, aev e e:.a,.'l*
~
Ib'
- r' TABLE 4.2=2 (Castissed)
Sheet 1 of 4
Plant,
ABI!RY I
Test Identifiestion M-N/ - 03 4 IM 4 L h3 Test Canditions
-u 4t Date Time Test #
Test Conditions Ceanents 6.
?'
S/i7/s t o 3,io 4,.
/
A4 5. 8.,.
A 3:cvA h 4
4-lnle~r as:1o bs
.1 A wt Baat t/isls ~r 124rbs 3
A est. B m.
tl3ll37 oEsso bs A M B,,n, s
j 6/if/g*1 Ma:sr k s c
'A' m tr u M A mB m
l.
s/4/e,
is su L,-s 6
AEb me.
O sin /a 1 a3:as s v
's"n tere, % Am nss.
a 4//7/87 03:3e bs Afa,_ B us 4fn/97 1o.1r ies 9
1:.a m kru % Ame,Bm to kspeL ea w
-t.
o.,ce W A cv ** "
elo:A
?> A-Af_ 3 5
1
- A 4% w i AndeswrAdrE SMSWb e# AAmo coes 700 CF 104 A48/h*.
l.
.s:NG Aa-Coo m : Astrwn%s aMec en Antee W A42VP Puu. OF 4433o GN raa teen, i-NE :
M o7-ENeat.AZ Ef6,
k M7 A (6/Se$
16 e-
--,----,.n,
.~
GEN ERAL @ ELICTRIC mamm n_
l
.aAA EMERGY
,,4NS33 CROUP mgv o s.a..
"y...
TABLE 4.2-2 (Cestissed) 5<
Sheet 1
et 4
Plant AG50A.Y I
Test Identifiestles STI-A' - DM C 4* % A.4. 71F47.)
Slesiffennt Results.
Dese restits represent the assissa vibration stress amplitudes er the demissat vibration respeases which were measured for each elass of seaposeats. De masiana allowable peak stress saplitsde is the Level 2 eriteries for the material of the
./.
resotor easposent.
f
.c Test No./
ige 2, Condition j,g112Z1 Aanlitade Freesenev %f4L).t2.11 h*
(F 7)
(Is) ww 73 4
.- 22.?ps Ja
'I
- * *
- U ne s, bees) ***ll'
$3.sa n
19
.r
- .ts.3p4
.tv. r ( 3 i.1
- T.
a v.4 u.
44 J2 f:
t
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+
78754. = 13 % 69Westm 3_
r3.s.,
.: 44.+
s'
~
(
Cearpau ene osaac roar J.2 2.
( Ae 220*<D2 caw 7 4E5MadE 7 A LA.
amens 4 64-)
/
=w-ca a r-e #
w I*vrzu & l' = s.,a 1 313
.rt-4 y e
- 4. S' 94 rordt. s 11*7. C.S!CC'tu** )
8 4.e J o.s' 22 WW TPa A2 Pause 4 c.4
, a, 3 f31/Ji
- 4. ps o,
4,..,
ag te.9y
+4e 3
7.o ut.
4 s. e
/p s.9 be.o S-
- 9.
- pr 4 r 5'
/i To7A t. = 4 4 */. C.srEcptuw) u e.
telh,, g4 9/ C -
.11 W WY TPl L: pre (Ag,, 8 g5.g, 3
.?4 7 73 f.,3, 2 f, y
4.hy IW=T 1e T9 Thi.
- 7 S *L (.19tg*,. RU a'4 )
(.teste menwee rpf WAu.
(aeg 8% )
8/
- /84
- 78 TD7AL 74"A f.8tVSM AS4*40) 4/me ct 4 *Ja t O
- A4 S:nGavAa s cuatrau=Movesh AY **ctEar. M sp e.TP 9 C md. W '",
LawSt r**=se endu.
ara &At
':N.Same 333E NWP4
.tnGatA4. IBGL3 N Ae64 2PJ e r<a<..
- Indicate whether p p valses were asassred frea Ersah records.
seeillograph records, er estimated from speetraa rece ds.
,. 4
.,c a., s u.2 b a. n & %m _
< d u %e % M)R4 cA:t:x/'tm.
.L.<
t.,
cam na.r ve.tt.sa..4 A 4 4 M.8
- 4M ;w.n.M & aR Au sa.
a *~ w.
t l
j u_
.l
-.= co.CY GENIRALOitectnic
- > = " '
.'.JCLEAG ENER
.l II y g:
TABLR 4.2-2 (Continued)
.y Sheet 4
et 4
.I Plant
- MAY /
Test Identification 97"r - Mi - o 3 4
( M 7o A.I.. Test )
1aler nta_Documeni l
Desiga Spesifisation 11A 43 M Rev.
~6 Test Procedure Speelfisation N 8719 Rev.
o Tibration Criteria 3E 44 9 ~79 Rev.
0 Installation Specifications A/ A 38f4-Rev.
2 Iastalla'; ion Dvss. Isteraal 819 E-f4 S Rev.
/
Eaternal 8.19657I Rev.
Ceaseetles Drawinge 189 C6 7/T Rev.
O J
(
13-4 c. $-7 /4 hv.
O
/MC c7t 7 Aav.
O 4
1 8848 6 4 47 A (4/ eft i
18
4 Preliminary Results - 111gh (100%) Rod Line (Wst Conditions 4, 5, 6)
Testing 19
GENERAL h ELECTRIC 2
- 3
- o1
= u 28 l
NbCLEAR ENEOCY SUSINESS GRCUP try 0
.s h:
TABLE 4.2-2 VIBRATION MEASVIEMIhTS REPORT RIPotT OF REACTOR INTTI.W VIBRATION MEASU12MENTS (FII-34) i Flant/ Site APERY /
Test Identification S7 r - N -o 24 rc 6 (.ioo% e.t. )
Test Period: Start s/07/S7 End Io/04 /47 This Report is X Pr elimina ry Final Ts t 3eope 7LA Jh
- f *** c evW 6^ fa^^4 cl. -/fo o, 'aA6he ed.
- " P""f W M'"
M *^d M 106 '4 Med LE^a..
Comeonest Con =ent Jef M Akse.r. Bme.a < b Hwt~
Cm R.odO@ M W - C= "A Hs a
~
Cooo. Cruy L.La P
Uw h u.L M
Uppe.r. egeta. %ao w sw e.
==
Conclusions:==
M AcNmE4 S#^4 *r 1 8/*
- d dA *W 8 4
('
h k 4~,s % 1=-
M.* u w h%w___4 A c mb, vnMA i
s ' ok h ow_ot br.es. -_ - L r.A24 corn. MQ V
Prepared b Final Report Reviewed B7 A. $cua W (
N/A Test Engineer Reactor Vibration Analysis Unit N/A Date:
/D/lS~/8 7 Date:
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TABLE 4.2-2 (Contissed) 1 Sheet
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Plant N
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Te at Identification M - FAl- 034 TC6 C toe 9. 4.t_ i Test Conditions
%4 Date Time Test #
Test Conditions Consents 4/s r/81
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TABLE 4.2-2 (Contissed) s Sheet 3
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Plant N 't
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(too /. R.L.h Test Identification S7".T - Al-o 3/4 Tc (.
e Stanif tetut Resnit s. i Dese results represent the naziana vibration stress amplitudes or the doniaant vibration responses which were assasred for each class of components. De assiana allowable peak stress nap 11tude is the Level 2 criterion for the material of the reactor component.
Test No./
,C,gg2 Condition Sensors Are11tude Freciency % Criteria Consents
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'TARI.I 4.2-2 (Contiased) '
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Test Identification S72 - F4r - o14, TC 6 G to o g /t./.. )
Reference Document
- .i Desiga Spesification
_ 3 2 A 4 3 S Rev.
4 Test Procedure Specification 22As7/9 Rev.
D Yibration Criteria 3964A977
- ter, o
Installation Specifications J/ A3 8&4.
Rev.
Q
.. Installation Dvss. Internal.
819 G ts 9 ter. '
I i
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. External ' S19 BS"7 l' Rev.
C r
Comasstion Dravings
/ti C#7 IS' Rev.
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Preliminary Results - NE00 Rod Line (Test Coniiton 7, 8) Testing 24
GEN ER AL h ELECTRIC m us:"1
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NUCLEAR ENERGY suslNESS GROUP mtv 0 h
VIBEATION MEASURDENTS REPORT
.f TABLE 4.2-2 REPot? 0F RZACTOR INTIL'uLS VIBRATION MEASUREMENTS (STI-34)
Plant / Site efMY I Test Identification fc-m - o34 Tc 7 '7c8 ( Nrsoo )
Test Period: Start
/0 /29[9 7 End i r /2-/4 7 This Report is X Preliminary Final A
Test Scopa 74.atg cavu-4 hy M is. stn w w +
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Conciselons:
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cAfn.i-to Prepared by Final Report Reviewed By nn 5.WCHwsJ-N(A Test Engineer Reactor Vibration Analysis Unit Date:
l'/1/87 Date:
MA Sheet i
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l G EN ER AL $ ILECTRIC T1*3 m*1
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.e TABLE 4.2-2 (Contissed) i
$heet 2
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Fisst AEERAY l
Teat Identification S7r-Al-oh, Tc 1 <. TcG ( u E c.o T Test Conditions Date Time Test #
Test Conditions *
- Consents to/30lq~1 9:Ig h.m I
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TABI.E 4.2-2 (Comtlassd) 3.:
Sheet 3
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Plant AM
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S TT - F-w - o 3 4 "PC T 4 TC 8
(.N Goa)
Tost IdestifLestion l
Sirsifiesnt Results.
Dese results represent the nazissa vibration streas amplitudes or the dominant vibration responses which were seasured for each elass of components, ne masiana allowable peak stres s say11tude is the Lovel 2 eriterion for the material of the reactor component.
Test No./
fdtE2. Condition Sensors Aare11tud e Freenenet % Criteria Comments e (P"))
(32) pw g
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3,.s 7
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SG es?A (6/ee) 27
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TAB!J 4.2-2 (Continned) 9 Sheet 4,, of 4
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Test Identification
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Reference Document
.c.,.
Desiga Specification 31A4384 Rev.
4 Test Procedure Spesification 41A 3719 Rev.
0 Vibration Criteria 3 96 HA974 Esv.
O Installation Specifications 1/ A 3 9f 4-
_ ter.
2 Installation Dvss. Isterasi 9 M ES'i Eevs
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'Esternal 9295*7i Rev.
O Comaaetion Drsvings
/% 9 CS 7tf Rev.
0 IT4 Ch7 4 kav.
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