ML050980112
| ML050980112 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek |
| Issue date: | 04/01/2005 |
| From: | Bird E, Carroll D, Keating R MPR Associates |
| To: | Office of Nuclear Reactor Regulation, Public Service Enterprise Group |
| References | |
| Task No. 1108-0502-0002-00 C-0142, Attach 17 | |
| Download: ML050980112 (13) | |
Text
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- CALCULATION TITLEPAGE
'PSEGNuclear LLC P.
Ie'l13 Project:-.
Task No.
.~.
.Decontaminiation Port vAA kJ dr e
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,l108-0502-0002-,00.
Tiele:
Calculation,o.i
.~j ic alysis of Loop tB' Port A
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- 1 0. - URPOSE -;,!-.
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The purpose of this calculation is to estimate thealt'nat
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-Hope reeketorRrciculiation oop -'Bd 'ct in ionot'for aunit inup sin us oid
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thf e R ecirculattonipipin.Du ng or apl t
'. ope'at~io s, the port'is sealed wih a boiledbla k flange.'--'-,,' :
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SUMMARY
O RESULTS The -'.,'
alternating stress is'3 ksi for an su d 1 g harmonic vibration at thefirst mode natural
"." ; ue'ncy.
4.0 ANALYTIC PROACH
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'The alternating stressiwassdetermined by. a haiionic forced response analysis The'harmonic
.aialysis techniqueixi d' to'determine the'teady-state forceresponse of alinear strctue^ to' a' load that variessinusoidally Wha onic ly) ifi time; A unit sinusoida (haonic) load'ofl g;'
' was
'piie at p
the first mode naturalfiruency of 122 ferene 1).Thehamnic ana ysiseis
' linear' conseq u'entlythess rs ts i'm 'this'clculation can'be ratioe to sinusoida input h:-
,olevelsotherh 1g;--.
.The'analysis wasperformed wit a three dimensional finite element model oftheport'and.a
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model reprsents one-half of te Port ta e of
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inite Element Model forOriginasl becontainauon Port
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Forasinu oidldis acemnent withthe form:-,
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.To determine the sinusodal displacement at a frequencyf 122 hzthat will result n an-acceleration f 1g. ot that.
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4 4 4 51 Dap ng Reglatry uid 1.1;Rferenice3, prov'i es rccoiiimmedddmigvle4fr`ini~iiyi ofipg ysems. Basd onth inoi m
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he stress a ysisim tssare provided in lor ontou p Figure
- Icomponent in the direction of the dontamination iine axisSy is sho wn. his stress component-
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pipe wall he-stress varies from 3.6 ksi'on the pipeinside diameter to 30 ksi on the pipe outside diameter.
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'REFERENCES
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- ' Pr evson'
- 1. PRCakl-io o-oC0142;,"~NaiutraFPrequ:e'ncyo~o
-2.
.Teteitiidelanwithth ANSYS Fi iwte ElIemet
. :.-AhAnsis p'rogram version 8.1.:The-AYsis was perform'edon 280R ser ing
.:;'".'tbeSolaris:8 operating stem.'eh SS tinstallation verifi atioi is doc entd'in
\\,.tA-:Q 8,141.'.
.3.
u Guide1.61, "Dampngs or eismic Design of Nuclear ower 4
Computi'ou files 1108 05O21 and i O65-6b-2-2 I '
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