ML20126J695
| ML20126J695 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/31/1981 |
| From: | Gordon G, Gridley R, Lawler B GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20126J692 | List: |
| References | |
| 81NED255, IEB-79-26, NEDO-24325, NUDOCS 8105040523 | |
| Download: ML20126J695 (42) | |
Text
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i b NEDO-24325 l 81NED255 - Class I i March 1981 i k e i CONTROL BLADE-EXAMINATICN RESULTS A::D RESPONSE TO ITEM 4 0F IE BL'_LE!!N 79-26 ' r 4 i I s I t Approved, approvec:
's0 b r N h 4 ,b A's l & M B. E. Lawler, Manager G. M. Gordon,:L2 nager Nuclear Steam Supply Plant Materials Engineering
- System Design and Technology
. I Approved: -
R.ZCridley,piager Fuel and Services Licensing NUC EAR POWE A SYr?!MS OlvtSICN e 03NI A Al.,I'.2:: st.C C0vP ANY I
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.' DISCLAIMER OF RESPONSIBILITY _- ' This document was precared by or for the Generat Electnc Company, Neither the. ' --. l . General Electnc Company not any of the contnbutors to this document: l 5-- A. Makes any warranty or reoresentation. express or omohed. with respect to the accuracy. comotereness. or useturness of t e ontormation contained on tnis docu. ' ment, of that the use or any Information Cisclose0 on this document may not ininnge pnvately owned nghts; or B. Assumes any responstbahty forliabokty or damage of any kind which may result kom the use or any Information Cisclosed In this document. r f i ii. l .. l ll ,,
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-NEDO-24325-r -
i s CONTENTS-5 Paee i
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- 1. . SL?S!ARY. 1-1 ,
- 2. INTRODUCTION 2-1
- 3. ' PLANT E ABSOR3ER ROD ELWINATION 3-1 )* I 3.1'~ Absorber Rod Nonenclature 3-1 .i 3.2 Visual Inspec: ion 3-1 l 3.3' Eddy. Current Tes:ing 3-2 3.4 i Neutron Ra:,iography 3-2 ;
3.5 Boron Isoc;pic-Analysis for Burnup Decerzination 3-3 i 3.6 Summary 3-3 f
~
- 4. CONTROL BLADE DEPLE ION MODEL. 4-1 I "4.1 Monte Carlo Type Code 4-1 .
l 4.2 Depletion Model Development 4-2 ? 4.3 Plan: E Control Elade Deple:1on 4.4 . Correlations to Depletion Model 4-3 4-4
] e I
i
- 5. APPLICABILI!T OP ACCL?!L1ATED' DATA BASE TO CPERATING PLA'iTS !
IN TABLE 1-1 3-1 f 5.1 Data Base 5-1 I
'5.2 Response to Ices 4 of II Bulletin 79-26 5-2 "
- 6. REFERENCES 6-1 i P
DISTRI3CION D-1 ! i
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- General Electric Company proprietary information has been deleted. -{
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c:- ., , r NEDO-24325 l TABLIS-
- Table- Title Pace I
1-1 Operating Reactors 1-3 i i 30 Eddy' Current Examination Results - Plant E ' l 3 3-5 ] ' Control Blade Neutron' Radiography - Plant E '
, 'I 3-6 J !
"'3-3 Boron Isotopic Analyses - Plant E v 7 l 3-7 J .
4 Camulative Local Depletion (':) 4-7 4-2 Axial Boron-10 Depletion Profile - Plant E q , 4-8 J . 4-3 Calculated Nodal Boron-10 Depletion (*.) . - Plant E ' 4-9 '! 4-4 B.,.C Loss Comparison - Plant E I 4-10 4-5 Local Boron-10 Depletion Comparison - Plant E { 3 ! a-il 1 5-1 Plant Operating Para eters 5-5 ! 5-2 Operating Reactor Plant Parameters 5-6 x s b l b i 5 i E k I i I f
s 4 l l NEDO-24325 !
. , l I
I' ILLUSTRATIONS'. i t
; rieure Title Page l
. ~$
3-1 ' Average 34C Loss. , Plant'E-
'3-9 -
i t 4 - 1". ModellDimensions 4-12 ' 4-2 Self-Shielding Effect in a Fresh B4C Tube 4-13 I
. . . s 3 Absorption Distribution for a Fresh B4C.. Tube 4-14 l 4-4 Absorption Distribution in a Fresh BeC Tube '
4-15 l 4-5' Centrol Blade Axial Boron-10. Depletion Profile - Plant E i! 4-16 ] 4-6 Local 3oron-10 Depletion for Absorber Rod 1 - Flant E 4-7
~4-17 ]
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B4C Loss .froin Control Blade - Plant E 4-18 _ l
'4-8 Local. Boron-10 Depletion from Absorber Rod 12 Wing 3 -
1 Plant E 4-19 ] I i: L i I I I i
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..- . 1E90-24325 4 I a CONTRI3tTORS K. W. Bray =an c K. M. Douglas P. van Diemen L . l . ,. u. ., ., Y a t t I r 0 i h r
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i 1 NEDo-24325
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- 1. SDDIARY During the destructive examina 1en of a control blade from an operating Boiling k'ater Reactor (3'JR) perfor:ed in a hot cell in 1978-79, it was discovered that there was cracking of the absorber tubes and some loss of boron carbide
'(B;C) fr:s the tubes. Additional het cell exa=inations of absorber tubes fr:: ;
other operating reactors have also shown cracking and Bj C loss. The mechaniss has been identified as swelling of the boron carbide under irradiation anc I subsequent stress corrosion cracking of the tube. The B;C loss has been correlated with degree of burnep. The B.,C loss . is a slow predictable process which has been modeled and accounced for in control blade lifetime evaluations. Accounting for this mechanism has resulted in a 20% reduction in control blade life (i.e., 34% average Boron-10
, depletion). This reduction in life assures no safety impact on plant operation.
l References 1 and 2 pres 6ac the results* of a review of current plant operating ' parameters. The results of this review clearly show enat potential control l blade degradation due to this mechaniss, for plants which have blades beyond the reduced lifetime, does not affect plant operation. Evaluations also shew that there is no significant effett on plant operating para =eters and no safety implications attributable to this =cchanism. i r This report presents recent post-irradiation examination data for the most i highly exposed control blade from Plant E . This data pro-
] j vides further substantiation of the conclusions presented previously in ;
References 1 and 2. , i i t For the absorber rods from the most highly exposed Plant E ~ control blade , the specific detailed tasks requested in Item 4 of IE , [ Bulletin 79-26 (Reference 3) are presented in the following sections: '
+
i
- References 1 and 2 are iden:ical excert Reference 1 ::ntains third pcr:v i pr:prie:arv infernatien.
6 1-1 l i
P 50 - NEDO-24325 L 4 Tssk Section j
- a. . Tube number or identification' 3.1 i f
- b. Elevation of each crack in the' tubing 3.0 ;
- c. Calculated Boron-10 loss versus elevation 4.3 !
for each tube I
.d. Measured Boron-10 loss versus elevat:ca 3.4 -l t
for each cuee ; I i
- e. Maxi =um local depletion for tubes having 3.5 l no cracks- f
+
- f. Maximu= local depletion for ' cubes having 3.5 i i
no loss. of boren r This report establishes that, when the additional data from the Plant E , f r absorber rods are added to the existing absorber red data [
~ :
from three operating reactors, the correlatiens arrived at in References 1 : and 2_are directly applicable to the operating reactors in Table 1-1. The i correlation derived can be ditectly applied to the operating reactors in j Table 1-1 to predict the behavior of their control blades, since the plant l 1 operating parameters and control blade designs are equivalent to the control i blades exa=ined. l
)
l Therefore,'chis report satisfies the requirements in Itas i of II Bulle-da I 79-26 (Ref erence 3) for all the operating reactors listed in !able 1-1. i h l J I I 1-2 1 I er, . , - - - - - e +- e ,r- ~-,- y
NEDO-24325-t Table 1-1 t OPERATI!;G REACTORS F t 6 8 I r t I r l h r r i r P t 1-3/1-4 5
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1 .* .- .1 NEDD-24325 ' i I i
.2. INTRODUCTION l This report responds'to Tten a.(parts a-f) of IE. Bulletin No'. 70-26, Revisicn r
1, forLthe operating reactors in Table 1-1. The response for the operating [ reactors in Table 1-l'is secomplished by demonstrating the applicability'of the' destructive',(post-irradiation) examinations perfor=ed on absorber rods 5
- of. similar f abrication 'and operational history from the following operating reactors:
i e , ?lant D . : e- ., Plant.B- i e i
, Plant C '
e ,1 Plant E i The results for Plant D , Plant B , and Plant C 1 ; absorber-rod post-irradiation examinatiens are presented in Reference 1. I Results of the sost recent absorber red post-irradiatien examination fr:: (
?lant E's highest exposed centrol blade are presented in - i t
this report. ~ i a The computer model for deteenining boron depletion in each absorber red in a . control blade as a function of elevation is described and the calculated Boron-10 depletion for the Plant E control blade using the l i depletien model'is presented. Correlations are presented between the calculated l Boron-10 depletion and.the results of the post-irradiation exa:1 nation of the absorber rods frem Plant E .
}a f The report : encl'udes by establishing the applicability of the entire abscrber !
i rod pest-irradiation e:ca=ination data base to the contrci blades in the k operating reactors listed in Table 1-1. I l f 6 I f i
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2-1/2-2 k i i f l
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- 3. PLA:T E ABSOR3ER ROD ELWI!;A!!O!;
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In addition to.:he pos:'irradia:1on' examination (results presentec in Refer- ! _ence 1), absorber-rods from three wings (63' rods total)'of the highest
-exposed control blade at Plant E were exa=ined. ~he control blade selec:ed was 1 ;
, which was:ac an average blade depletion I of'34 k based on :he ou:put.cf'the process coeputer array that tracks control
- blade burnup. -
f Of the'high power density St:Rs, Plant E was specift: ally I
' i selected because Flant E had the highest depleted cun:rol !
blade available at the :ime of selection. By adding the Plant E l control' blade to the data base, the data base provides a com- - plate cross section of data from all domestic 3'.iR types now in opera:icn. The post-irradiatien examina:1on of the 63 absorber rods from the Plan: E control blade included visual inspeccion, eddy curren: :es:-} ing, neutron radiography and boron isotopic analysis. The resul:s are pre-sented in the remainder of this section. 3.1 A3S3RSER ROD !;CP.E:C1 C RE For the purpose of this document the absorber rods in each wing of a con-trol blade are nu.bered sequentially from 1 to 21, starting at the edge of the wing and working inward toward the center of the control blade. There are four wings per control blade and 21 absorber rods per wing. The wings are numbered from 1 to 4 Therefore, the nomenclature for the edge red on wing 3 would be 0-1).. 3.2 VisiAL IN5?ECT CN Iach absorber rod was visually inspected in the hot cell. ;othing unusual was' noted during :he visual inspection of the absorber rods. Only :wo cracks 3-1 w _-
)
3 , 1NEDO-24325 I I 1 . . i
~in the tubing material were_noted as being visible. These cracks were located in the high burnup regions of edge absorber rods. It was also noted that the -
absorber rods were very clean (i.e., no' evidence of crud buildup). , 3.3 EDDY CURRENT TESTING The absorber rods were all, nondestructively examined using eddy current method , for: the purpose of checking for the presence of cracking. The areas where significant crack indications occurred,'and their elevation, are given in i Table 3-1. In general, the significant crack indications were in the high ; burnup regions of the absorber rods, cs was expected. On wing 1, a few potentially significant eddy current signals were noted in the low burnup regions. Of these isolated cases, representative absorber l rods with the largest signals were sectioned at the elevation of the signal to determine if a crack was present. Cross sections of the absorber tubing were examined metallographically. In all cases examined, no cracks vere found. t 3.4 NEUTRON Vd)IOGRAPhl* A series of neutron radiographs of the 63 absorber rods was made at the 1 Nuclear Test Reactor at General Electric's Vallecitos Nuclear Center. Table 3-2 shows the amount of boron carbide lost in each absorber rod as measured from the neutrographs. A plot of the average boron carbide loss (Figure 3-1) shows that the boron carbide loss was limited to the three (1, 2 and 3)' edge absorber rods in the high burnup region. In determining the distance to which boron carbide was missing, the point selected was the max-imum point at which measurable loss of boron carbide was seen. This means that some boron carbide still remained in some'of the regions shown as missing boron carbide. This procedure is, therefore, conservative. The boron loss profile is consistent with previous data (References 1 and 2) since the boren loss is in the high burnup region and the loss' profile has the same shape as the expected Boron-10 depletion profile. . I 3-2 1
. i
~ . _
'NEDO-24325.
f l
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.3.5 BORON ISOTOPIC ANALYSIS FOR BURNUP DETERMINATION i i
t Boron carbide specimens ' vere taken from selected absorber rods at various { axial locations for.boren isotopic analysis to determine'the amount of local l t burnup..-The results of the boron isotopic analyses performed are given in j i Table 3-3. The data are labeled to identify which absorber rods did or did ;
?
not have boron carbide loss. ! i i 3.6 uSEK3ARY -fI i t The, post-irradiation examination results for the 63. absorber rods from three f wings of the Plant E control blade were ]
'in agreement with the previous control blade post-irradiation examination i results reported in Reference 1. i I
Some cracking, including throughwall cracking cf the absorber rods, was i evident.. Cracking associated with B;C loss was located in the high exposure regiens of the r'ods near the edge where neutron exposure was highest. ; Neutron radiography showed loss of boren carbide from the absorber rods in some of the areas where cracking occurred. The bcron less profile ha's the ! t same shape as the expected Boron-10 depletion profile. ! The results of the boron isotopic analyses were in good agreement with the 7 conclusion that 50* local ~ Boron-10 depletion is the threshold for boron loss, f t r I
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3-3/3-4 I
NED0-243:5 Table 3-1 r EDDY CURRE::T EX.U!INATION 3*StLTS - PLA:n ; ; J 7 i e, i I i
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NEDO-24325 f i Table 3-3 BOR0" ISOTOPIC ANALYSIS - PLx;T E ~ j I I i I P l
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NEDO-24325 4 CONTROL BL.CE DEPL: TION MODEL The control blade depletion model described in this secticr. was specif1: ally developed for a con:rol blade wi:h the characteristics shown in Figure 4-1. This type of centrol blade design and lat:1ce arrangement is :ypical of :he design used in all the operating plan:s listed in Table 1-1 and Plan: C Note that Plant E is included in Table 1-1.
] l The cen:rol blade depletion model requires the use of two cceputer programs.
The two-di=ensional radial eff e::s en the control blade were si ulated using the Monte Carlo progra=, and :he axial core effec:s were si ula:ed ] using the 3-D 3WR Si=ulator Code (References 4 and 5). 4.1 MONTE CARLO P'10Gp'J1
]
The Monte Carlo program is a pregrns for solving the linear neutron ] transper: equation as a fixed source or an eigenvalue pr ble: in the :hree-dimensional space. This progras is especially wri cen for :he analyses of fuel lattices in the thermal nuclear reac:crs or experimental cri:1cals. The Monte Carlo progra: uses cross sections processed fr:c the INDF!
]
B-IV library files (Ref erence 6) . These cross sections are processed in the 100 group format, and those in resenance energy region may have the for= of resenance para =e:ers er Deppler broadened multigroup cress se::1cns. The F.arvood thermal scat:ering kernel is used for the water scattering. Types of resc:icns considered in the Monte Carlo program are fissien, elas:ic ] and inelastic sca::ering and (n,2n); absorption is i=clici:ly trea:ed by reduc-ing :he vei;h: applied :o the nonabsorpti n probabili:y in eac.. ceili;ian. The Mente Caric program has been qualified f:: applicatiens in 3'.iR ] la:: ice design, fuel ra:k cesign and in:ernal : ore s: rue:ure neutr:n fluence estiestion. This qualification of the Mon:e Carlo program res:s upen ] extensive qualification studies basec en C3EUG thermal reactor benchmarks,
NEDO-24325 36W "0 3
.and Puo, criticals (Reference 7), ga==a scan experimen: [
and BUR gadoliniu critical experiments, and, in addi:icn, cc parison sich alternate calcula:1onal me: hods. 4.2 DEPLETION MODEL DEVELOPMENT t i e i. I i t I i { an-
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~he local Bor:n-10 deple-'o. o.< each absorber ::d in :.e Plant g control blade as a functien of ele.eation can be cete:-.ined bv' uti.izing the de:ple:1on model results (Se--de, - s- . i
-> and :n.e clade avera e R
-3 ;
NEDO-24325 axial depletion. profile. The deple: ion model results provide :he local 3cron-10 deplezien. t an individual abscrber red at a specified planar average depletion. Therefore, :o obtain the local Scron-10 depletien, the 5 average depletion as a function of eleva: ion is requirec. 4
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t l t d Y I t
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I > l > l ! I e i ! f 1 i i l l i I . I a 4.4 CORRI1s 'T:: ;5 70 OE?'. ETIC!! MCOE;. The resul:s of :ne ?lant E ~ con:rol bla e des:ructive exacina , tien r,5e::icn 3; Jan be :encarec :: .:he ::n:::1 3;ade ceolecion mede; resul:s >
'Tacle 4-31
!cr:n Icsa :an be es::mc:a: by :ensidering 3;l teren 2: 30,
NEDO-243:5 local Baron-10 depletion or greater to be no 1 cager present. Table 4-4 com-pares the expected boren carbide loss from the depletion model to the bor:n carbide loss as determined from the neutron radiography results. Absorber Rod 1.has the largest discrepancy with the analytical model, due to absorber Rod 1 in ving 3 as explained in Table 3-2. The axial depletion profile for absorber Rod 1 is shown in Figure 4-6. The depletion profile for this rod has a definite plateau down to N60 inches. Therefore, any slight increase increase in peaking for this rod could have a sienificant effect on the I cmount of boron loss up to an axial position of about 60 inches. Consider-ing the uncertainties that exist and the fact that there is no precharacteriza-tion of these absorber rods, the agreement is very good. Figure 4-7 compares the calculated boren carbide loss to the three-ving average ber:n loss from the neutron radiography results (Table 3-2). Table 4-3 ce= pares the Soron-10 depletion as predicted by the depletion model to the results of the bcron isotopic analyses. Figure 4-6 shows a graphical representation of the calculated depletion in absorber Red 12 ce= pared to the isotopic analyses of Red 10. The results of the correlation of the absorber red pest-irradiation examina- , tien data and the calculated Boron-10 depletion model for the highest exposed Plant E control blade further substantiate the conclusions ] ; drawn in References 1 and 2, and extend these conclusions to high pewer den- ' sity B'JR reactors. ' i 1-3 %-o 1
t NEDO-24325' , t Table !.-1 : r CL7R.MTIVI LOCAL DE?LET CN (T;) - f
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- 5. APPLICA3ILITT OF ACCU:!CLATED DATA 3ASE TO OPERAT!::G PLA.'!S I:; TAELE 1-1 This section establishes the applicability of the results of the absorber red post-irradiation examinations perfor=ed and cne correlations ths: this da:a base supports to the operating reactors listed in Table 1-1. .-
i 5.1 DATA EASE i The data base supporting the analytical correlations derived to redefine con-trol blade life consists of the following: i i
~
Quanti:y of Quanti:7 ef < Plan: Blades Absorber Reds Plant C 1 13 I Plant B 1 45 Plant D 1 31 Plant E 1 63 Total 4 152 Although four control blades have been examined fr:m i:ur operating plan:s, this represents a substantial cross section of existing variables. From the four control bisdes,152 absorber rods were examined. Each absorber rod provides an exposure his:ery indica:ive of :he perfernance of control blades cc various exposures throughout the core. The exposure of each absorber red varies axially and yields information on exposure dependency. Each absorber red vi:hin a ving exhibi:s a differen: sbsorber history be:suse exposure varies radially as well as axially. The absoroet rocs e:::nined aise represen: dis-tinct periods in the =snufac:uring cycle of :he absor:e reds 'hich p;cvices process variacili:y. Althougn :he precess varisbili:y :J .n:: he quantified, i: does exist by virtue of displace =en: in :ine. The ds:e and place of isb-rics: ton of the control bisdes are: 5-1 t,w .
7
.h i- NEDO-24325 t i
.- 3
. i, 1 ,
't i - i. -!
c t i k i
~I
- The absorber rods ' examined have built-in variabili:les such as.nethod of f ab-- i i
<rication, density of 3.,C, tubing supplier, :elerance variations and design
. changes made.over :he period of :L=e involved. Therefore, the prauent da:a f I
! 6 base'does encompass a significantly large ti e period. f I
-l 3.2 ; RESPONSE TO ITDI 4 OT IE BULLETIN 19-26 i
-t The absorber reds examined are from four differen: 5WR reactor designs wi:h {
three differen: control blade designs. . The control blades in Plant C- ' ( and Plant E are identi:a1 :o the control blades used . t
- in all the plants in Table 1-1, k
l One of the unknowns in the cracking of the absorber :ubes and the subsequen: loss of boren carbide is defining the mechanism that_ physi: ally :ranspor:s' { the boron carbide'out of the absorber rods. Although there are a number of -I potencial : anspor: rechanisms, the actual mechanism has not been de:er=ined. f The correlation which was derived and presented in References 1 and 2 es:sb-f 11shed that the less of beren carbide is a func: ion of local Boren*10 burnup, ! i regardless of :he actual transper: =e:hanism. Considering all da:a ga:hered ' since Referen:es 1 and 2 were published :nis c:rrel: tion is still valid f:: e t centrol blades exposed- up :o their original design life. The addi:ional da:a i gathered include Plant E ' _. 't results, which extend this direct correlation w1:hLiecal Zoren-10 turnup :: hi;h f1:w and nigh power dens ty 3%? { plants. i i r
.t 9
f-2 , i l e -
l
'NED0-h4325 1
By examining theLplant operatint; parameters in Table 5-1 of Plant B ~ Plant.C; ,. Plant D , and Plant E ,
~
vhich are c'he plants whose control blades make up the data base, it can be seen ! that there is significant variabili:y in the plant parameters.- Listed in ! Table 5-1 are the plant opersting parameters which could potentially cause ! variability in the loss rate of boron carbide. All control blades destruc-tively examined from these four p1snes had consistently predictable boron loss. Therefore, it'can be inferred that no single plant. operating parameter had a ! Predominant or deleterious effect.' If the operating plants in Table 1-1 have operating parameters that are within'the range of the operating parameters of ; the four plants in Table 5-1,.then they would not expect to experience any f additional loss beyond the amount that would be predicted by the correlation
~
to boron-10 burnup (References 1 and 2). Table 5-2 provides the minimum and ; maximum values from Table 5-1, and compares these values to the plant operat- ! ing parameters for the operating _ reactors in Table 1-1. All of the operating t parameters of the operating plants in Table 1-1 are acceptably in the range of maximum and minimum values established by the plants in Table 5-1. There is'no reason to believe that the correlations presented in References 1 and 2 vill be altered in any.way for the plants in Table 1-1. i The control blades in the operating plants listed in Table 1-1 and the four i control blades destructively examined are all fabricated by the same vendors. . Two of the four control blades destructively examined are identical to those in the operating plants listed in Table 1-1. Their operating parameters are similar to -the plants whose control blades were destructively examined. There-fore, the examinations performed will satisfy Item 4 of IE Bulletin 79-26 for f the operating plants in Table 1-1 and the onset of boron carbide loss at 50:: ! local depletion is unaffected by plant operating parameters. l l
?
i I I l f 5-3/5-4 l
r NEDO-24325 Table 5-1 PLANT OPERATI::C - P.m!E*E?.3 f m b t I. t 5 i i e r i k P r i l : I i 9 h
) :
3 ? 6 6 6 6 f a t, p s h r
?
i T,?
- e er 1
h i I t e
- c. ..-. NEDO-24'325 '
. ,l ' .e ;
i .. 6,
.,,I-a.' i' s. .
- - , . .. E
- g;
., . ' - --- ,' ; -. -< j- i s
,, ...6 . . s. . s i
4 J - a p
- 1
, J . et, a,.. 93m-
- 3 I
- , P,
=t .
4- 3 <
.P e . ' =m ae *' a. s .$ g t j
, p s e . . i.
, e, s, '
..s.a-
" .e el . . , .-
J -
.. s 8
. 3
? g . . .-
*=4 J. .e. g ., e. m, .e. s, - $
. 1l' .=.
3
.A . =.= . .e .
=.
s'!. s e, m
=
os a=
=
w
' .p 4 d .s m.
y e, - a
=.
g
.= .
= E = .= s-3 ... 3. .;
3 h- . er ' e9
# ' 4 I.
- . . . . e.
p.... : p
..=. .= 3.e.
m J 5 r 5a l ,
- '3. ,
( f .o . 4 s p=.,. .
.e
,*l
.=l
.l-
=.
=
- v. .a .e e *a
.=.
-k
.e =. .ens
. , , j , , 7 .e- . s .! 3 I 3
. y
- (*( s.
e. p.
. f
.- -= .m s. -e l
i -
- .% = c ;
( l .
'. . t 3
- 1, i -
e . e.
. ' _' . e- ... e g i e t/) - . ,,l
= ' ' + ! ,
4
=
g . c.3. l
., - e -
s 13,1 - { 4
.I' 's i.
l e
. . r s p l l l l me
- e. a e. e. .c,. -# .#
as =$ L e e e ,
.E il f'g
- es P
e me
= 3 e
.? ' .
A. sh p a qae m 9 . me . 3 ne p
%. ,e l . . .
g" 6 = . i l- i ; } e. , p s 8 w e e .a m.. .m s .E ' s.
.N f 8 j e . .' -=
g i
- a. ' 4.g c .g .c ,
a i y e. e
- e. m w .e. a.
a.e.-e- .= 3
, .. .s e. >
.=.l z i l .
- a 3 -
.. s
.i .' <t. '
l ,
't . . I.
i
-.- ==
- r. '. .
.. . s.. -e
( be J i f l
.e . ,e e .a
-1 + .= . , , . ,
I =l , .1 e. ~ m .. .
.e. m . '.
. f =
- -- a .s s-r e
f = . . ,e sl e. e - E .P
- m ,
e e =ese. s. *
-em.s . =.
- t. r g, ;
# e .s.* * - E 3
e
. 1 1
I I g- e W' [# f t es.
. = *
.e. a= .e. *.,a..*
. i
=e.
L- . l
- .=. I we l $ e -s = .* z g
- .! p p
= = F
.#g. t v= # e n.
.e # = t
- t. t '
p' 4 (
. e ".
6 . : i 8 s' . - o : a t l '
= er
.l.
s
~
e .e e. s .3 I es. .
, e - e -
e . .,
.e v .e ef *
#. 8G W 9s a,*
=a 444 *
.%. .e f a..
3 r .B * *. . .E s . s 4 ,
. . .* 3
. a. # = .9 3
- er. 3m .**
p as g e e a e a. k
- t t t t t t 5 ., .M... m.m
?. }
. =. .,
I et e n. 2 P
=
., gl-
.e
- a. e. m.
. 3 .
R
. i
. .a . .. ,
r
.. = t ,3.
f _. , e s .* 3 ** 8 5
- b 4. 4et . a,. . d. .
.e.
iEl..
, . - I. .i i
. .e - - . . ..
=. . 3
.y .
. i aa.n J. g $
W .as } J s
- d's y. an 3 .m.- 3
-E . dJ E
=..o a..
& 8 3 * =3- .e. eg*e*
e ed e 3 1 m# o 1 d.8 d*j
- a.
- 4 9
e
. % -1 a = = ,
a --. g.
. -.J 4 4 . i ,= ,
4
.. d 8
.%v .s4,. e - a.. -
6,
.1.'... ' . al =. .. 3 5
6
.. =
., a, .
m - . 3 .,
,i i
j g j
. . - a. .- 14,2 1 g .6
. . m- <. .. . . . .d 3 4
5-6
,m. .
N. ,
~ . .
i
. NEDO-24325;
)
?
i
- 6. REFERE:CI5 !
- 1. K. W. Brayman and K. W. Cock, "Evaluatien.oi.Cencr:1 Blade Lifetime With !
Potential Loss of '3,C." NEDE-24226-? .(Proprietary)* and NEDO-24226, I December 1979; NEDE-24226-1-P-(Proprietary).*- ( l
?
- 2. K. W. Bray =an and K.? 2. Cook, " Control Slade *.iiecine Evaluatiens Account- ;
ing for Potential Loss of B C," NI00-:e232, January 1930.
- 3. " Boron Loss from BWR Control 31ades," II Eulletin No. 79-26, Rev. 1.,
August 29, 1980, USNRC Office of Inspection and Enforcement. Washington, > D.C.- t
- 4. - t J. A. . Wooley, "Three-Dimensional 3RR Core Simulator," Cencral Electric Co. ,
- NEDO-20953A, January 1977.
I r
- 3. . G. R. Parkes,'"3ER Simulator !ethods Vertii:stton," Ceneral Electric Company, NEDO-20946A, January 1977.
f i
.)
- 6. !
" Data Formats and Procedures for the E:OF ::eutr n Cr:ss 3ection Library,"
BNL-50274 (7-601), ENDF 102, Vol. 1, October 1??O. { 7.- t C. M. Kang, E. C. F.ansen, ENDT/3-!V Eencnmarx Analyses ith Tull Spectrum .i t Ihree-Dimensional Mente Carlo Models, ANS Transactions, Vol. 27, pg. 391-892, 1977. t I i i i b
. i i
t I t
*These documents 'are not ' publicly available hee m " L"' " c'ntain proprietary t information. j i
i
+-13-; i L- i l
t I lI ( I 1 . h
- , SED 0-24325 DISTRIBUTION M/C '
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