ML19323F461

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Slide Presentation Entitled, Reactor Vessel Asymmetric Pressure Loads, from 800507 Meeting W/Util
ML19323F461
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 05/07/1980
From:
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:
Shared Package
ML19323F456 List:
References
NUDOCS 8005290048
Download: ML19323F461 (37)
v • d • e


Text

{{#Wiki_filter:0 s O ENCLOSURE 2 SLIDES PRESENTED IN MAY 7, 1980 MEETING WITH OPPD k l i 8 0052 90 M l

i s REACTOR VESSEL ASYMMETRIC PLANT PRESSURE LOADS GEOMEIRY 1r SS AND CALCULATE EVALUATE ENERGY i SUB-4 FOUNDATIONS l RELEASES CoMPAR ENT AND WALLS pR g E JL g 0 N EVALUATE LOADS SUPPORTS I START DEFINE DESCRIBE y PIPE ECCS PIPING BREAKS GEOMETRY 1 r 1 r 9 1r OEFINE DEFINE PLASTIC BEHAV1080p STRUCTURAL DETAIN . E CCS PtPl44 BCC$ PIPlNG PREPARE FOUNDATION -D RCS COMPONENT-# ANALYSl$ Colo LEG -5 4 -.D PROPERTIES SUPPORTS OF RCS PIPE MOTION ANALYSIS BVALUATION REPORTS 7 d L d b i JL JL JL OBTAIN 3 5 VESSEL ' -# W MOTION i T r .CliL'ATi'; M 'BLOWOOWN. g ~.NOEI kE v i 0 i

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STRUCTURAL ANALYSIS OF FORT CALHOUN REACTOR COOLANT SYSTEM REACTOR MODEL PLANT SPECIFIC REACTOR IHTERNALS MODEL PLANT SPECIFIC THRUST & JET IMPINGEMENT FORCES PLANT SPECIFIC SUBCOMPARTMENT PRESSURES PLANT SPECIFIC INTERHAL ASYMMETRIC LOADS SCALED FROM GEliERIC l

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6 POWER SYSTEMS Calculation Number Rev. CC8deuSDON DGP.EERPG IPC Page Number OPPO - REACTOR VESSEL SUPPORT FOOT TRNGENTIRL LORD COMPONENT PLUS SUPPORT STRUCTURE LORD (lo # LLS) Y.Y ) l %0 3.4 3.2 2.8 O 2.1 l 2.0 I.6 /.2 i O. S o .o7 .,y .u .2e .as .n . n .se .63 .70 7r DIS PL RCEMG NT UNCHES) ' 5.'l -... ~.. - L'. ~ :.~ ~.~

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B SYSTEMS .c.s i. tion sumb., a. POWER ~ COW 8uSTON ENGNEERE IC Pag. Number OPPD - REACTOR VESSEL SUPPORT FOOT RRDIAL LORD ContPONENT PLUS S UPPOR T STRUCTURE LOAD (lo' L bS) 4 8 8 x10' LbS ~ 98 9.1 %o 3.6 3,2 2,S 2.Y g 2.0 l.6 12 8 / ,y ./ .5 .6 7 8 .? /.o .I .2 .3 DISPLAC EMENT (INCHES)

FIGURE 4.6.3 OMAHA DETAILED LATERAL INTE RN A LS MODEL FRICTION NON LINEAR ii HYSTERESIS E ROTATIONAL ,w 2 / i t... io.. "~ 3 UGS 100' N E

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\\ m m w w 80 o 85 o 0 90 0 95 81 o 86 o 0 91 o gs 14 o e4 g SHROUDS CORE i SUPPORT l 82 87 o o 92 o 37 BARREL o ~ 15

5 B'l o 88 o o 93 o 98 OUTLET N0ZZLES 84 o 89 o o 94 o 99 16 o CORE FAP 33 SHROUD 24 H! - ' !H C2 0 53 i

hl36J, [--o 25 25 0-{ l lH663 o54 t PRESSURE 46 37 18 " 26*H' -73 ' j--o M 055 o--{ ! l}-o 26 VESSEL ) oh! !h>27 27 o-ll 74 ll--o 65 0 56 A B C j hl ll g7 .28 19 28 <Hj ,' Hp66 0 57 hl l}-o 29 6' 29 o-{l e67 0 58 30 o-{ l l l--o 68 0 59 l}-o 30 20 o 31 <Hj 78 l !hi31 i69 0 60 32 iH' -78 'Hp70 0 61 <Ml! ^ lh 32 CSP 34 ' 2 O8 FUEL CODES: g3 A = PERIPHERAL j B = FIRST INTERIOR LOWER SUPPORT 22 - l ', ': 9 C = INTERIOR STRU CTURE SNUB 8ERS l

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F I G U F) E 4.6.9 OMAHA REDUCED LATERAL INTERNALS MODEL 22 UGSSP __ _T 1 --A y 22 CSB

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POWER SYSTEMS c.icuretion numb., n COueUSTON ENGNEEfuNG. INC Page Number OPP 0 - REACTOR VESSEL SUPPORT FOOT TANGENTIA L LORD COP 1PONEN T ONLY LOAO 60 6 LbS) y,y - y.O 3.6 I j 3.2

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E POWER SYSTEMS Calculadon Number Rev. COMSUSTCN ENGNEERNG. INC Page Number OPPD - REACTOR VE SSEL SUPPORT FOO T RA DIA L LOR D COM PONEN T ONLY LORD (to'Lb5) % SSXIo#L6S 4.8 i v.y 1

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i CIRCUMFERENTIAL CRACK OPENING 30". DIN 4ETER TERMINAL END - CRACK INCLUDED FLOW FLOW RATE (GPM) LENGTH ANGLE AREA Co =.6 CD =.3 OIJ') 8' 300 (.001) 1 5 16" 600 (.010) 10 5 ,1 20" 750 .04 40 20 24" 900 .10 100 50 32" 120 .40 \\a00 200 g-e O e me. N g k I E ( o )

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FFACTURE MECHAMICS EVAL.uATION OF FORT CALHOUN COLD LEG SAFE END I. DATA BASE - 1/2 CIRCUMFERENTIAL CRACK M MATFRIAL SA,516 GR70 JIC ~~ 2000 IN2

  • BASED Oil PRECRACKED INSTRUMEi1TED CHARPY (K

% 250 KSI ) IC t/lif PIPE 30" ID, 2.5" THK A. " FREE" PIPE J I OPEllINGARgA SUDDENLY APPEARING CRACK (DYNAMIC)

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"LEAKIHG" CRACK (STATIC) 2.6 IN B. SAFE END IN SYSTEM L/ID RATIO = 7.7 OPENING AREA J I 6' LEAKING" CRACK (STATIC) 1.36 IN2 325 ~ 2 SUDDENLY APPEARING CRACK W/SSE (DYNAMIC) 1.65 IN ' 440' l ' MAXIMUM OPENING AREA AND J I DUE TO PRESSURE ARE LARGER BUT BY THE TIME SEISMIC LOADINGS ARE TRANSMITTED DYNAMIC EFFECTS DUE TO PRESSURE HAVE CEASED.

i e i e ( n ,.oe 2. gh CLAD 2 1 B T ~SA-l82. P-3/6 ASTN1 AAsl SA s o 8-64 g4 c e PBM --J & ^ i ccA ss 2. f f 3/g C L A O i e /Vo hHE .s A PE ElvD flfE =T C ALH oo A) R\\/ lpWT No&W REGION i

P O W F-H I 1. l " ~ ' SYSTEMS ca aro. teim,<...c Cakwletaan Number Rev. ~.: wum .m ~ 4 '..,y, ~. v-y, \\ '.'".:p...ks.. nr f.! ~g .* '..,;:.f. f ;'.... ;.:g... .. s. 2. ~,.- .E ,9 %

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I'I. PROPOSED ANALYSES - " FREE PIPE - 1/2 CIRCUMFEREliCE CRACK, IR-LB A. MATERIAL - SA516 GR70 JIC= 2000 IN2 PIPE 24" ID, 2.4" THK 0PEilING AREA J i SUDDENLY APPEARING CRACK (DYNAMIC)

  • TO BE CALCULATED I(24")[J 24,[A J IC COMPARE A 30" J

I (30") JI (24") B. MATERIAL SA-182 F316 J IC - TO BE OBTAINED FROM PRECRACKED CHARPY OPENING AREA J i SUDDENLY APPEARING CRACK (DYNAMIC) + + +TO BE CALCULATED COMPARE J J i IC C. 24" SAFE END IN SYSTEM L/ID RATIO = 8.6 , APPLY RESULTS OF STUDY OF 30" PIPE Ill SYSTEM TO 24" PIPE. DESIGil BASIS: 0.~1 AREA CRACK WITH CPEillilG TIME = 12 M SEC.

g t ~ ) l GPt1 10 GPM N 40 GPM 152* (400GPM) \\ l 1 .k. .F 2 9' D I A P', E TE R C IR CUM F E R EN TI A L CRACK o 4 ( I 9 6 ) 4

STRUCTURAL EVALUATION (JULY 1 REPORT) RCS AllALYSIS THRUST FORCE 0.1 x EXISTING =- SUBC0f1PARTiiENT PRESSURE 0.2 x EXISTIi1G (HORIZONTAL) = 0.4 x EXISTING (VERTICAL) = INTERHAL HYDRAULICS EXISTIllG = RV INTERilALS & FUEL EXISTI'-lG (2A) BREAK i 9 1 .-}}

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