ML20117M427
| ML20117M427 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/31/1974 |
| From: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML20117M404 | List: |
| References | |
| FOIA-84-762 CEN-2(P), CEN-2(P)-01, CEN-2(P)-1, NUDOCS 8505170060 | |
| Download: ML20117M427 (51) | |
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GA>MA SPECTIGETRIC ANALYSIS
' OF PALISADES SECO.\~JARY CRUD SMIPLED DECDEER 1973 SlaiPLE LOCATION ISOTOPES A\'D A>DUNTS (PP.4'md_
S8 Co Co60*
- 1. Tube sheet, "B" generator 113 18
- 2. Support plate Ill (top) "B" generator 799 145
- 3. Support plate #2 (top) "B" generator 347 63 4 Support plate #3 (top) "B" generator 402 67 y 5. Composite w 392 69
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- eral vastage nature. Three separate general vastage 6eometrieG Ve e ud for testing
1 I
An ellipticci, spark dischar6e machined defect with a major axis of i 1-1/2 inches and a minor axis of 3/h inch.
A 1/2 inch, 360 milled defect.
t'..+."..*.-
A 1-1/2 .' . . . '. . , . f. 0 . . 4 .11 e m' _ d c a"a. . '. i n r. _' u' . ' e ' a s m- ,,~.'.S_'-
4 a testing of the actual Palisades tubing, it was found that the results bes.
related with those from the [ ]
i defects. as ex ected. .
1 1
).est cutset tube crackinc, could not be completelt ruled out pricr to 'tisu.1 .
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?rator tubir.g p-:iu:ed ci .her b t [ ] or by [ ].
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e- -e B. -!ST.3 P!eri r.t!cj3, (cc:.tinuc1)
This estinate va: ' derived on the baric of the r.aninu:.. burst prescure deviation observed from lot to lot in full vall tubinc.
In'ndditie.n, the neacured burst prenc':rcs at ror tt: : erature for the cracked t :t : :r: ; r e c e n . c': i n TOL '.e V hn d N ..:<e ' L . .nc u.t i . : .;
grett'.er i t. tr u.. dae. ta uncert .;:. tic: in .uuri:. : the in:.r.: er...
length. M 1 e r:.c% l engt:. : vere measured to enaur.: c:ncervat; n . . .
the' presented: renult a reprenent a conservative- ectimate of t!.e re; ..; -
ship _bett.Nen b.:r: pressure and .vall degrahtion. Iievert).elec.c , these resultn are ' sir.ilar to thore obtained for the [ ] dcreet, t:
repre.iented by the dached lines on Ficure h. T!.is behavior is ccn:ir.-:n vith th2 well-documented resistance c.' Incenc1 c00 to notch senci !vity.
Figures 1-5 allou an 'estinate of the allovable vall decradation fer the different defect cc =ctrien as a function of it.coced strecs. The her-izontal line on the crcph represents the curren'. primary cyntem mani :
pressure of 2150-p:1.
C. LOCA Shulation Collapco tents were conducted to determine the allovabic vall thickne::
in .the event of a LOCA. These tests vore perforced at ET. The re:ults were extra.r.oleted to 600*F ty neans of ratioing code calculations 1: E!
and at 600*T.- The expected collap:e pressure at 600 F is { Jof ths; at !?T. The c:lltp;c renults are precer.ted for the 360* and elli t ..:sl-defcetc in.Tahics VI, VI! and VIII. The re ulta are presentti 4. c hi:s'1; in Ficurec 5 and 6. The full vall tube results are taken fror: a prev;:us CF study.
The horizontal lines are drawn at 900 and 770 p:1 and indicate vall wastage in excocs Of [ } nay be safely sustained.- Upon collapse Of the
-[ ldofected tubes, ruptures only occurred in tubes with[ ] Or .
._ greater vall reduction.
A further con:Ideration in the effect of ovality on colle pse pres:urer.
This ic of particular ir.portance in U-tend re,.icnc where the fttri:iti:r.
proces in-lueen s :nall initial ovality. Tecte perforced previcu:1*-
indicate that in the U-hend recion, ccometrie ::iffonin Offsets the ovality cT:ced by forminq 30 that collapse pressurec cre identi:21 vit.:
thosc of utr1*ght tubes. In cencral, tnic'tectinc inli:ste tha*. the collap:e prcr.:ure Of a perfectly roun1 tube, P coul1 he related t: .ht:
of an oval tuta P ty:
P r
~
o L i
J P
vhero X ic t!.s percent ovtJ ity.
oe .
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in !!.e er.nt<r ef the r 21 er.. T. .- r c. '.es vere der al d urin; tr.c : lear.ing y -- , . . .. , . . . . .- . , . , , , , . t .:. . . . . . . . . . _
,.0,...
., .. . . ... 3. . . ....... . , . .. n.. ta . . . .. . . . . .
after t r .:r.- in : rt entel in F1 cure 7. L'. : c:: rt;ir : c (
) v.ere included. 'i.e n. :ured lu'ai pre: curcs cr.1 r. idy currer.t 1:m :t. i r,r.: : ' the nnxinu . vall r.Cu:t i:n are pri. rented in . b' e IX. .
Ecfore ur,c, corre: tion for the strain hardenin , that oc::urred durin- the tute fullir 3 oport.tien r. art be redet Ac shown in Ficure 6, a se .ple vas se:titr.ed loncitu :nall;. and a h .rdness traverse =ade. Thic traver:e include-a region unich hin. Euffered n( } vall reduction. These htrdnect reasure-etnt: then were ured to pred.ct the local increace in tensile strer.r.n caused by the local strain hardening. The r.axir.un hardne:s variation obterlet was f-a Rockwell B (R 3 ) of ( ) in the undisturbed regicn increasirg to a R3 of (
in the nost heavily vasted area. As presented in Eicure 8, this repecsents a tencile ctrength enriation of fren [ ] to [ } Ksi or of(- ). Bated en thic
. result, all reasurec rupture strengths en defceted cubing were redu::i by
[ }, as chcen in Tatic IX. The corrected data is plotted in Figures 9 cad 10 in cor. pari on uith the 1-1/2, 360 defect data and with the combined elliptica:
and 1/2", 360 defe:t resultc. Agrrrement is seen to be better with .he i ) defect results. This direct correir. tion of tube burst pr ;erties fron actual deccaded tubing with those from the artificially defectea tubing establiches that .he laboratory results are directly applicable for deterr.ir.i the allceable ant.unt of vall reductior., Figure ( Jand[ ] vill te ucci for determinin; allevable vall reduction under turst cr collapse conditi:ns.
IV. CO::CLUST::S The allovable vc11 thinning for a variety 6f reactor conditions are presentti in Tcble X. These results are based on the expericental results which inclui tests on b:th artificially- defected tubes and actual tubes renoved fr:n the Tali:: des "3" ste = generator. These results indi:a e that vall reducticn of [ }could with:tand either a MCI.3 or a LOCA.
4 f
p e .: .
4
_T./.N._f . I Inconel 003 Tiihi:vr - I' at ID.!T.M 3/4 " x 0. W," i. :11 . i in. )
'g -
, 0.7/,5" x 0.0..i" !! ail Ac to.1 fuoing le,ted i -
lt . + . 001
' Sa:.::11 e v X , - iiii t . , i n .
Hall _, luoduced , in. i; 1.'all Detr. X", fin'l ir
-l O.730 0.043 15.7
.2 0.730 0.043 15.7 3 .710 0.033 ,
35.3 4 0.710 0.033 35.3 5- 0.690- 0.023 54.9 6 0.690 0.02.3 54.9
.7 0.674 0. 01 5 . 70.6 -
8 0.'674 0. 01 5 70.6 Odd nurd>e: ed ct.uples - Cc11t.pse Tcst .
Even nunbercd sr.:.:ples - Durst Test -
- e II-s
e _ .. ,
- p. .
BL!!;ST TEST.S_
!!0::0EGP/.0ED TU:;II:G 0.750" 00, 0.013" to 0.C51" UALL RO0il TEi!PERATURE
' BURST PRESSUPES , psi Lot A - Lot B 0
600*F' BURST PRESSURES, osi
~
Lot A Lot B 6
9 s
' s II-6
vu,.. .....
ELLIPTICAL DEFECTS R00:1 TEl:PERATURE BURST SAflPLE l10. I 1.'ALL DEGR/ DATI0il PRESSUE , csi 21 66 29 66 30 68 7 76
-9 78 -
16 86 20 86 600*F BURST SAMPLE 110. %tlALL DEGRADATI0tl PRESSURE, osi 23 70 24 68 25 70 28 68 1
78 2 80 4 80 12 84 -
5 , 86 15 88 s 18 90 19 88
- e. .
ELili TEE.
CIRCU!.AR DEFECTS R00:1 TE:'PERATURE 1-1/2" AXI AL lei GTH CEFE CT BURST SAP.PLE 1:0. %tIALL DEGRADATIC:1 PRESStnE, esi 50- 70 51 70 52 70 53 70 60 80 61 80 62 80 63" 80 70 90 71 88
~72 90 73 90 600*F BURST SAMPLE !!0. %!!ALL DEGRADATIO;l PRESSURE,osi
'54, 72,
'57 ,
72 58 72
.59 70 64 80 65 80
'66 80 67 80 75 90
04 3 ITE L- s '.~ f '. '. . . .' )
1/2" AXI/-L LE"GTi! DEFECT i:
600 F SAf'PLE fl0. % llALL DEGRANTIC:l B URST P T.E 55 Ui-E , P 5 L 115 70 116 70 117 70 118 70 -
119 70 124 80 125 80 126 80 127 ,80 128 80 134 90 135 90 137 90
'138 90 s 139 94 I!-9
T/.2 ; ',
BURST TTSTS INTERGr?JH Lf ELY CRVt;E D Sf'~LES ROCM TEr?EPATURE i
% WALL DEGRADATIOl BURST PRESSURE , PSI l 85 75 75 73 73 71 69 '
i 55 l
1 i
l l
II-10 l _. . _ . . - . - - - - - - _ , - _ . ._--- . - - - - - . _ _ .
1
- ca ,. .
COLLA?3E TE573 I t
ELLIPTICAL CEFECTS - 70~ 1lALL der.nt. DATIO.*i 8 R00:1 TE ' PEP.Ait!RE -
4 SA'tPLE i;0. C_0LLAPSE PRESSURE, psi I i
81
- 82 83 .
84 l 1
-85 j 86 87 i'
88 i
89 .
1-1/2" CIR_CULAR DEFECTS - 70#, !!ALL DEGRADATIO:!
_R00f1 TEl'PERATur.E_
55 !
1 56 {
1/2" CIRCULAR DEFECTS - 70'.: !!ALL DEGPADATIO.'l_ i R00'i TEi?E RATL'FI 110 111 112 -
113 114 II-11
- _ . . - . .. = _ _ - _ - - _ _ - - . . _ - -
- e. ,-
l L .s . .
COLLt. 5E TEST E L L I P TI C/> L CE rE CTS - EC' i:AL L DE G F A E P 'IO.'i ROOM TE!*PE RATL':E .
SA!'PLE NO. COLLAPSE PPESS'JRE , PSI 90 l
l 91 92 i
93 94 95 s 96
- 97 i 98 l
99 1
1/2" CIRCULAR DEFECTS - BOS tlALL DEGRADATION ROOM TE!?ERATURE 120 121 122 123 II-12
COLLC: E T_E S T ELLII'TI Cf'. CE FE CTS - 90 1.'A L L CC Gi l.~ AT ! G';
P00 TEI'.DE P ATUPE SN? LE 110. COLLAP5E PRE 55'JPE , PSI 100 101 102 103
- 104 i
105 i 106 1 108 109 I
1/2" CIRCULAR CEFECTS - 90" !.'ALL DEGRACAT10:1 i
ROOM TE!'DERATURE i 130 .
l
]
131 132 133 l
11-13
4 mes _ m._AA* d d d d-23 " - - -----.s----Mm ---J*.4- -& 4h .---4 m e-A a---ma 2.-_,. _.---a w _Aa- - ---
_ _ - . e a.- _mA_ A.---------,-. -
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EyPE P:!'E r;TTL T!'~E C'.*ji /*10 CCLLIPSE C'TA PRIl'ARY SE C0r!DARY ALLO 17CLE 1ALL PRESSUPi OE GRADATIC.'i POSTULATE D PRESS UP.E (PSI) (%)
~
0 770 LOCA.
0 900 LOCA 9
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P = internal pressure 1 , R = inner tube radius = 0.327 inch P = xternal pressure l 2 l Use of this equation 1 cads to the results presented in Table I for differen. ; operations 1 conditiens. It should be noted that a primary systen pressure . of 1850 psi is intended for the near future. The 2150 psi maxinun prinary ' pressure is included for future application. The 2300 psi is included as a reference calculation. - t i . -3. Stresses imposed during a main steam line break (MSL3) or a loss of ; ) coolant accident (LOCA) shall not exceed 70% of those required fqr _either i l collapse or rupture. The 705 value was selected on the basis of the margin of safety provided by the ASME pressure vessel code under faulted , conditions. Application of this condition leads to the results presented in Te.ble II. The MSL3 results were taken from Figure [ ]and the LOCA nunbers frs: FiGurel 3. The mininum nu bers derived from the normal oper_. ion and tecident analysis for the two pertinent reactor conditions are presented ' in Table III. For near tern operation, the allovable vall degradation is found to be 75% The plugging of all tubes with 60% or greater degradaticn therefore yields a high degree of conservatism, since the available vall thickness is 605 greater than required above. r e 9 m 9
TABE I ALLOWABLE WALL DEGRADATION BASED ON TUBE PLUGGING CRITERION FOR STEADY STATE CONDITION ALLOWABLE PRIMARY SECONDARY DIFFERENTIAL WALL M PR ESSUR E PR ESSURE PRESSURE R EDUCTION 7 w (PSI) (PSI) (PSI) (%) 2300 770 1530 2150 770 1380 . 1850 770 1080
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-TABLE II i
j ALLOWABLE WALL DEGRADATION BASED ON TU3E PLUGGING CRITERION FOR ACCIDENT CONDITION PRIMARY SECONDARY ALLOWABLE POSTULATED PRESSURE PRESSURE W ALL s ACCIDENT (PSI) (PSO REDUCTION U i MSLB 1850 0 , MSLB 2150 0 . MSLl3 2300 o LOCA 0 770 l l 0 900 I l i I , l
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& SECONDARY PRESSURE 770 PSI 770 PSI ALLOWABLE WALL REDUCTION .
AFFE:iDIX IV EFFECTS OF VIBF.ATIC i ::: DE3RADO TUBI::G CF PALISADES STEAR GE:;E .ATDCS The apprcac'r Of the C-E vibration analysis of the Talisa. des stec generator is to densns . rate that either the natural frequencies of tube spans are remove.1 frc= the exciting frequency by a significant separation factor or that the stresses en tubes resulting from vibratory excitaticn are s=all with respect to the endurance limit of Inconel. This approach is still valid when considering the tubes in a degraded condition. In this repcrt stresses are evaluated with c onsideration given to the decrease in strength due to 60". tube degradation. The results of this study indicate that no vibratory damage will occur to tubes of 60% or less degradation. l l l 1 I -_
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- Plugging of all tubes with 607, and greater eddy current test indications will remove an additional ( ) tubes from heat trann fer service in the A s team t;enera ter,{ )
- tubes in the 3 s team generator. In combination with the tubes previously plugged (Rows 1 - 11) the active heat i trans fer surface has been reduced to approximatelv
( [. ] ft 2-in the A steam generator and [ the B-steam generator.
]ft 2 in The Palisades steam generators, as originally installed,
.had considerable excess heat trans fer sur face. Ccns ide ring the operating parameters specified in the original equip-m.ent specification, a large margin of excess heat tr nsfer
! surface still rema~ ins , mere than [ ] tubes in each steam generator. The original operating parameters are: a. ,i Q = 4.181 x 10 9 Btu /hr Wp = 62.25 x 10 6 lb/hr
~
That = 598.5 F Tcold = 547 F Primary Pressure = 2100 psia Secondary Pressure = 770 1-The operating -limitations currently imposed on the Palisades Plant result in operating parameters as listed below: Q = 3.775 x 10 9 Btu /hr (2200 MWt) Wp =[ ] x 10 6 lb/hr* Tcold = 530 F uaximum Primary Pressure = 1800 psia
+ -
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_ *'The primary fic.w rate 1tstea is;a _ conservative.esti. mate. ' Measured primary ficw prior to shutdown tras
'[~ - ]: x 106 lb/hr. ,
- Wish ; all L tubes contci.ning 607.: and greater ECT. indications .
plugged, CE es t i. mates 's team pressures under the, above cond i.t-ions 'to bc .(- ~l ps la' for- the A.'s team generator and (L ) ps!.a - for the . B is team genera tor. m G 6 6
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