Text

Nonproprietary Palisades Steam Generator Tube Exam & Repair
	ML20117M427
Person / Time
Site:	Palisades
Issue date:	01/31/1974
From:	; ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	;
Shared Package
ML20117M404	List: ML20117M412; ML20117M427; ML20117M435; ML20117M441;
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

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Three separate general vastage 6eometrieG Ve e ;eral vastage 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.

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defects. as ex ected.

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e ac1c..

tests were perforned on 0.750" CD, 0.0!.8" noninal vall Inconel 600 ' ste:::

?rator tubir.g p-:iu:ed ci.her b t

[

] or by [

].

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-),

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-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

..:sl-t 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

i o

L J

~

P vhero X ic t!.s percent ovtJ ity.

oe

"..'...>.r..

.r.,..-.. c...

c....-

r..

1..

A r -.. '...-

~

-Ta.-i: ales "B"

ste.. r r it.

F r - i n.-

e, 10-2!. inch 1

.,tutc't.r..

,.,..t..,

.c. -,, -,......,1

.n..,

,... o

, e...

..,...n...

9..

a.. r. e...,...

... :.. g in !!.e er.nt<r ef the r 21 er..

T..- r c. '.es vere der al d urin; tr.c : lear.ing

,,,,. t.:...

y --

3..

.....,... n.

ta

,.0,........

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 ) of (

) in the undisturbed regicn increasirg to a R3 of (

3 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

81 i

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.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

106 108 1

109 I

1/2" CIRCULAR CEFECTS - 90" !.'ALL DEGRACAT10:1 i

ROOM TE!'DERATURE 130 i

l

]

131 132 133 l

11-13

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e. e. P = internal pressure 1 R = inner tube radius = 0.327 inch xternal pressure l P = 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 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 (PSI) (PSI) (PSI) (%) w 2300 770 1530 2150 770 1380 1850 770 1080

i i -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 l U i MSLB 1850 0 MSLB 2150 0 MSLl3 2300 o l LOCA 0 770 l l 0 900 I l i I l ~ I t 6 i. 3 i

........... ~.. -y t I i T/WLE III TUBE PLUGGING CRITERION FOR NEAR-TERM OPERATION WHERE: PRIMARY PRESSURE 2150 PSI 1850 PSI g M 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 1 I

oo' T 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 2 ( [. ] ft 2-in the A steam generator and [ ]ft in the B-steam generator. 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. 9 Btu /hr ,i Q = 4.181 x 10 6 Wp = 62.25 x 10 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: 9 Q = 3.775 x 10 Btu /hr (2200 MWt) 6 lb/hr* W =[ ] x 10 p Tcold = 530 F uaximum Primary Pressure = 1800 psia

+ w- ..o.. % = -. ^

'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 1-4 g.; 5 4 H e fh-

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m-- --a a a --+,.m-- m --m.a 6 .h-me to o8 END ~ DATE FILMED q / i, / 774; i i l .}}

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