ML20216F162
| ML20216F162 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/29/1997 |
| From: | Launi C COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20216F120 | List: |
| References | |
| BRW-97-0798-M, BRW-97-0798-M-R00, BRW-97-798-M, BRW-97-798-M-R, NUDOCS 9709110175 | |
| Download: ML20216F162 (28) | |
Text
i Braidwood Calculation No. BRW.97-0798 M Allowable Leakrate Calculation for Steam Generator Interim Plugging Criteria Revision 1 September 3,1997 b
5 e
9'709110175 970902 DR ADOCK 0500 4 6 K:nitb> bud'etmgen%rwdil31
SMGENY&LUNDY 23V12 ID: 312-269-3753 Rub 29"97 1?:Ab No.Uvc r.ve l
PREPARATION, REVIEW AND APPROVAL OF CALCULATIONS l
CALCULATION TITLE PAGE Calculation No:_BRW.97-0798.M DESCRIPTION CODE: R02 DISCIPLINE CODE:
M DRAIDWOOD STATION UNITS 1&2 SYSTEM CODE:
RC.MS TITLE:
AllqwAhle Leaktate Calculation for.Sicam Generator Interjm Pluggine Criteria
,.._X__ Safety Related Augmented Quality Non-Snrety Related REFERENCE NUMBERS Type Number Type Number COMPONENT EPN DOCUMENT NUMDERS:
EPN Compt Type Doc Type / Subtype Document Number REMARKS:
REV.
REVISING APPROVED DATE ORGANIZATION PRIJ(T/ SIGN d.//. LAM /fI//f& '
f-Z9-77 o
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/ G I
6
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AG 29 '97 17:25 312 2d5 3755
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~ ~ SMGENi&LUNDY 23V11' XD:V12-269-Ff55 RU N TT: W Mo NUF V.UV COMMONWEALTH EDISON COMPANY CALCULATION REVISION PAGE CALCULATIONNO. BRW-97-0798 M PAGE NO.: 2 REVISION SUMMARIES REV: 0 REVISION
SUMMARY
Original issue, pages 1-23 Electronic Calculation Data Files:
(Ny.
N.m., VA ra.r==.mma nu)
None Prepared by: E.1 Johnson /
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N N89/O 7 Pri Sfg'n/fg/ ~
Daty Reviewed by: R. G. Chow /
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- /z9/97 Pfnt/Sikn 7
IIate Type ofReview
[ X ] Detailed
[ ] Alternate
[ ] Test DO ANY ASSUMPTIONS IN TIES CAILULATION REQUIRE lATER VERIDCATION [ ] YES [X)NO Tracked by:
REV:
REVISION SUhedARY:
4 Electronic Calculation Data Files:
< % m s v % ra... w w. e>
Prepared by:
Print / Sign Date Reviewed by:
Print / Sign Date Type ofReview I ] Detailed
[ ] Altemate
[ ] Test DO ANY ASSUMPIl0NS IN THS CA14UIAT10N REQUIREIATERVDUFICATION [ ]YES ( )NO Tracked by:
QUG 29 '97 17:26 312 269 3753 PAGE 03 J
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COMMONWEALTH EDISON COMPANY l
CALCULATION TABLE OF CONTENTS CALCULATION NO, BRW 97-0798 M REV NO. O PAGE NO. 3 lECTRfN PAGE NO.
SUB-PAGE NO.
111LE PAGE 1
REVISION
SUMMARY
2 TABLE OF CONTENTS 3
PURPOSE / OBJECTIVE 4
METHODOLOGY AND ACCEPTANCE CRITERIA 4
ASSUMPTIONS 5
DESIGN INPUT 5
REFERENCES 6
CALCULATIONS 7
SUMMARY
AND CONCLUSIONS 24 ATTACHMENTS N/A AUG 29 '97 17:26 312 269 3753 PAGE.04
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PAGE NO. 4 l
PURPOSE AND OBJECTIVO The purpose of this calculation is to Generate the maxirnum allowable primary to secondary sieem Generator tube leak rate during a postulated main steam line break using 24% plugging criteria design data. The evaluation was performed for both a pre socident and accident initiatrad lodine spike. The release of lodine and the resulting thyroid dose at the Exclusion Ares Boundary and Low Population Zone were considered in the leak rate determination, Whole body dose due to noble gas 1:nmersion Is less limillno than thyrold dose as documented in UFSAR Table 15.011, Given the large margin to the 25 rem whole body dose limit, whole body dose was not re-evaluated.
METHODOLOGY.AND.ACCERTANCE CRITERIA; The Main Steam Line Break (MSLB) occident is considered the most limiting off-site dose accident because the event causes a sustained large pressure difference across the 6 team 0enerator tubes providing a motive force for steam release. The Technical Specification limit for steam generator (SG) tube leakage is 150 gpd (0.1 Opm) for each SG. The dose attributed to a 1 gpm leak rate from the reador coolant system was calculated. This value was then used to determine the allowable leak rate without exceeding the Standard Review Plan dose critoria.
The acilvity released to the environment due to a e,.LB is analyzed In two distinct releasos:
1.
The release of the lodine activity that has been established in the secondary coolant prior to the accident, and 2.
The release of the primary coolant lodine activity due to tube leakage.
The methodolo0y used for calculatin0 the Radiological Consequences of a MSLB with prtmary to secondary leaka0e is consistent with the Standard Review Plan (NUREG 0800),15.1.5 Appendix A.
TID 14844 dose conversion factors were used to determine dose equivalent lodine concentrations, which is i
consistent with the Technical Specification definition of dosa (quivalent lodine. The TID values are based on ICRP 2, " Permissible Dose for intemal Radiation,1959.*
The off site dose assessment uses ICRP 30, ' Limits for intakes of Radionuclides by Workers,1979' dose l
conversion factors. ICRP 30 is al.so the basis for Federal Guldence Report No.11, " Limiting Values of Radlonucilde intake and Air Concentration and Dosa Conversion Factors for Inhalation, Submersion, and inoestion,' dated 1988. This report provides the dose conversion factors for the Station's Off-site Dose Calculadon Manual for Inhalation dose at the site boundary due to airborne effluents, l
l The dose Acceptance Criteria are based on the Guldance of Standard Review Plan (NUREG-0800) Section 15.1.5, Appendix A. For a MSLB with a postulated pre-accident lodine spike, the calculated doses should not exceed the guideline values of 10CFR Part 100 Section 11. The numerical values used for these doses are 25 rem to the whole body and 300 rom to the thyroid from lodine exposure for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following the accident. For a M8LB with an accident initleted lodine spike, the calculated doses should not exceed a small fraction of the 10 l
CFR 100 guideline values, i.e. 2.5 rem and 30 rem resoodively for the whole body and thyroid doses.
l t
I REVISION NO.: 0 l
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PAGE NO. 5 l
ASSUMPTIONS:
1)
The offed of boron on the RCS density is assumed to be no0ll0lble since the boron mess is less then 1%
of the total RC8 mass at the beginning of core life.
DESIGN INPUTS:
The following doelen inputs were transmitted in Reference 5.
8 1.
The total volume of the RCS is 12,082 ft. (Reference 1) 2.
The full power RCS temperature and pressure are 586.2 Y and 2250 pela. (Ref 1 and 2) 3.
The RCS specific volume at full power is 0.02258 ft'Abm. (Ref. 3) 4 4.
The lodine decay constant for 1131 is 9.96E.7 sec (Ref. 4) 5.
The Purification System temperature and pressure are 130 Y and 2300 psia (Ref 1).
6.
T..L Purification System specific volume is 0.01614 ft'llbm. (Ref. 3) 7.
Breathin0 rate la 3.47E 4 m'/sec. (Ref. 6) 8.
Atmospheric Dilution Factors, X/Q, are taken from UFSAR Table 15.0-14. (Ref.7) 9.
RCS lodine concentrations are based on UFSAR Table 11.12 without the 1% felled fuel contribution.
(Ref. 8) 10.
The initial steam release from the defective and intact steam Generators are taken from UFSAR Table 15.13. (Ref. 9) 11.
The secondary side faulted steem generator has a partition fraction of 1.0 and the intact steam generators have partition fraction of 0.1. (Reference 15) 12.
The half life for i 131 is 6.04 days,1132 is 2.30 hrs, i 133 is 20.6 hrs, i 134 is 52.6 min, and i 135 is 6.61 hrs. (Ref.21) 13.
The Initial primary coolant edivity dose equivalent lodine concentration is 60 pCl/0. (Ref.14) 14.
The initial secondary coolant adivity is 0.1 pCl/g. (Ref.14) 15.
The duration of the spike is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (Ref.12) 16.
No fuel failure attributeble to the accident is assumed. (Ref.12) 17.
lodine partition coefficients for all SGs are 1.0 for primary to-secondary leaka0s. (Ref.15) 18.
Nonnelletdown purification flow is 75 gpm. (Ref 11) l REVISION NO.: 0 l
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PAGE NO 6 l
19.
Letdown temperature le 130*F and 2300 pela. (Ref 11) 20.
Spedfic volume of letdown is 0.01614 ft'/lbm. (Ref 3) 21.
Decon Factor, DF, for mixed bed domineralizer is 10. (Ref 13) 22.
The lodine release rete spike fedor is 500. (Ref 12)
REFERENCES:
1)
B/B UFSAR Table 11.1 1, Revision 0 2)
B/B UFSAR Taule 5.1 1. Revision 0 3)
ASME Steam Table, Fifth Edition 4)
The Hee:th Physics and Radiological Health Handbook, Revised Edition, Revised 5)
SRW-DIT 97 278, Inputs into Offsite Dose Calculation to Support Unit 1 Reduced RCS DE l 131 Activity Umii 6)
B/B UFSAR Table 15A 1, Revision 0 7)
B/8 UFSAR Table 15.014, Revision 0 8)
B/B UFSAR Table 11,12, Revision 0 9)
B/B UFSAR Table 15.13, Revision 6 10)
Introdudory Nudoar Physica by Kenneth S, Krane,1988 11)
B/B UFSAR Table 0.3 2, Revision 0 12)
Standard Review Plan (NUREG 0800),15,1.5 Appendix A 13)
B/B UFSAR page 9.3-43 Revision 0 14)
Technical Specifications 3.4.8 (Amendment 77),3.7.1.4 (Original), 3.4.6.2 (Amendment 67) 15)
WCAP 14046, 'Breldwood 1 Technical Support for Cyde 5 Steam Generator interim Plugging Criteria,"
dated May,1994 18)
ICRP Publication 2 Report of Committee 11 on PermissitWe Dose for Intemal Radiation,1959 17)
ICRP Publication 30, Umits for intakes of Radionuclidos by Workers,1979 18)
Adams hnd Atwood Report,7he lodine Spike Release Rate During a Steam Generator Tube Rupture,*
Odober 18,1990
~
l ItEVISION NO.: 0 l
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PAGE NO. 7 l
19)
Westinghouse Letter CAE 97171, dated July 21,1997, portilning to the Roador Coolant Water Density Used in Determining Byron and Braidwood Altomate Tube Plu90ln0 Limit.
20)
Federal Guldence Report No.11, " Limiting Values of Radionudide Intake and Air Concentration and i
Dose Conversion Feders For Inhalation, Submersion, and Ingestion,1944 21)
NUREG/CR 1413, 'A Radionudide Decay Data Bees - Index ord Summary Table,' 1960 e
VARIABLE AND CONSTANT DEFINITIONS:
M RCS mass [ ibm]
u.,,
steem oenerator steam reiene mass lib)
V RCS volume [ft']
RCS spedfic volume [ft'/lbm)]
y RCS leak rate constant [sec' 4
i 4,(
Fuel Release constant [Cl/see) 4 lootope Decay Constant [ soc)
j ko Letdown Purification Removat Constant (sec"]
d 4
Total lodine Removal Rate [ soc ]
t Time [sec)
As RCS lodine activity [Cl]
C lodine Concentration [Cl/ or pCl/0) i 0
C.
Inittel lodino Concentration [Cl/0 or pCL/01 F,
Letdown Purification Flow [g/sec)
Q.
Activity Released of nudido,I[Cl]
R Activlty Released of nuclide, l[CI) 4 D
Thyroid Inhalation Dose [ rom)
B Breathing Rate [m*/sec)
S X/Q Atmospheric Dilution Fador[sec/m J DEFINE UNIT 8:
l Cl = 1 curte pCl = 1E-8 Ci 1 lbm = 484 g -
1 ft* = 7.48 gal 1 min = 60 sec 1.
CALCULATION OF DOSE DUE TO STEADY STATE AQTIVITY IN 8ECONDARY SIDE The first dose component to be calculated will be the dose from the secondary side. The secondary side eativity is conservatively taken as the Technical Specification limM of 0.1 pCl/g (Reference 14). TNs value is the same for both the pro accident and accident initiated events. The steam release for the 1
faulted steam generator (SG) is 96,000 lbs (Reference 9) which is the entire initlei GG water mass. The faulted SG is assumed to steam dry in 1015 minutes so all of the lodine is available for release. The -
combined 0 2 hr steem release for the three intact steam generators is 406,716 lbs (Reference 9). The j
l REVISION NO.:
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PAGE NO. 8 l
combined 2-C hr steam release for the three Inted SGs is 930,604 lbs (Reference 9). For the three lntact 80s a partition fador of 0.1 is used (Design input 11).
The lodine concentrations are obtained from UFSAR Table 15.0-9 and are converted to Cl/lb, s.
since the steam release is defined in Ibs.
i C,
1b, = C.
x 454 x SE - 6 b-Equation 1.s
,g,
,1b,
, pCl, TABLE 1.s
?
\\
l131 0.066 3.00E-5 1132 0.024 1.09E-5 l-133 0.106 4.81E 5 l134 0.016
'l.26E 6 1135 0.058 2.63E-5 I
iREVISION NO.: 0 l
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[ CALCULATION NO. BRW 97-0798 M PROJECT NO.
PAGE NO. O l
b.
The iodine concentration for each nuclide, Ci from Table 1.a. Is multiplied by the mass of steam released (96,000 lbs for the faulted CG and 406,716 lb6 for the three intact SGs) to obtain the total amount of curies available to be released, A, for 0 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The activity available for i
release in the intact GGs is then multiplied by the partition factor. 0.1, to determine the amount of activity actually roleased.
Al*lCl)= C, x M7,,,*[lb)x 1.0 Equation 1b.1 Af*d[Cl)= C x ML"llb)x 0.1 Equation 1b.2 TABLE 1.b EBRMBERMBR l-131 2.88E0 1.22E0 1132 1.0$E0 4.43E-1 1133 4.0250 1.96E0 1-134 6.97E 1 2.95E-1 1135 2.52E0 1.07E0 The activity released, A, determined above,is multiplied by the ICRP-30 Dose Conversion c.
Factor, DCFi, (Reference 17) for each lodine isotope and then summed separately for the faulted SG and intact SGs.
Of*(rem)= A[*(Ci)xDCF, Equation 1.c.1 Dl*(rem)= AP(Cl)wDCF, Equation 1.c.0 Cl.
l REVISION NO.: 0 l
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COMMONWEALTH EDISON COMPANY l CALCULATION NO. BRW 97 0798-M PROJECT NO.
PAGE NO.10 l TABLE 1.c i
1131 1.06E6 3.11E6 1.32E6 l132 6.44E3 6.76E3 2.65E3 1133 1.60E5 8.32E5 3.53E5 l134 1.07E3 7.46E2 3.16E2 1135 3.13E4 7.89E4 3.35E4 is'aT4(siti:DixDdfsE?
4.03E6 1.71E6 The 0-2 hour exclaslon area boundary total dose released from the faulted and the three intact SGs is 6.74E6 ram (4.03E0 + 1.71E6 rem). This total dose can also be defined as LD,xDCF.i The total DE l 131 activity released is the total dose from Table 1.c divided by the 1 131 doso conversion factor. Numerically this is 5.31 CI (5.74E6 rem /1.08E6 rem /ci) d.
The off-site thyroid Inhalation dose at the exclusion area boundary, Dm, and at the low population zono, Dm, are calculated in accordance with UFSAR equation 15A-2.
Exclusion Area Doundary Dose (0 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) f D,[ rem}= f u
xBx D, x DCF Equation 1.d.1
<Gau,
= 7.7E-4 x 3.47E-4 x 5.74E6(rem]
.m,
,, sec,
= 1.53 [ rem]
I REVISION NO.: O l
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PAGE NO.11 l 2.
CALCULATION OF DOSE DUE TO PRIMARY TO-SECONDARY LEAKAGE DURihlGERE-ACCIDENT INITIATED SPIKE in accordance with Reference 12, the pn> accident case occurs when the reador is operating at the maximum value permitted by the Technical specifications priorto the postulated MSLB The radioactive lootopes are assumed to be evenly distributed throughout the RCS. The lodine activity changes over time due to radioedive decay and the rate at which edivity leaves the RCS due to primary to secondary tube leakage.
a.
The RCS mass inventory, M, will be calculated given the hot full power volume and specific volume.
3 RCS Volume:
V=12062 ft (design input 1)
RCS spoolfic volume v=0.02256 ft'/lbm (design input 3)
(g} = -
=454 Equation 2.s
- m..
12062 ft' gg 0.02258
= 2.42E8 (g]
b.
The RCS activity needs to be calculated for 60 pCl/g. UF8AR Table 11.12 is used to obtain RCS adivity, which is based on 1% fuel clad defods per UFSAR Table 11,1-1. The totallnitial RCS adivity la calculated by multiplying the initial concentration by the RCS mass. The initial DE l-131 adivity la then determined by multiplying each isotope's activity by its dose convers!on factor, summing the values for each nuclide and dividing the sum by the 1131 dose conversion factor to normalize the activity to I 131. This DE l-131 activity is the contribution due to 1% fuel clad defects. To determine the activity at 1 pCl/g, the fraction of each Isotopes contribution to the DE l 131 is calculated and then multipiled by the RCS mass to obtain the correded total adivity in the RCS at 1 pCl/g. To obtain the total activity at 80 pCl/g, each Isotope activity is mu!!! plied by 60.
l REVISION NO.: 0 l
. JG 29 '97 17:31 312 269 3753 PAGE.12
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PAGE NO.12 l A[Ci]=C, S xM[g] Equation 2.b.1 i
8 D (rem)= A (Ci]xDCF, Equation 2.b.2 i
i
. Ci.
[D,(rem) 1.39E9(rem DE ll31[Ci)=
.=
t = 939.2 (Ci)
DCF,
1.48E6 n3. Ci.
. Ci.
Ci A'(Ci]
Isotope Fraction at 1 DE Il31[Ci] Equation 2.b.3
=
g
~
~
Ci Ci
' 1 Ci RCS Activity at 1 8 (Ci)= Equation 2.b.3 x M[g]x1 Equation 2.b.4 x
8
.lE6 C.
Ci RCS Activity at 60
= Equation 2.b.4[Ci]x 60 Equation 2.b.S 8
TABLE 2.b g,-
usN SUNkD W NW9.@190.!$3S3E@fN MBOISiggjha,$
donchqt;q g-
.%;g [$gMgggg_@ql[N$gge ggs iWACMr$
[AWd g
4 @@Wn !((jip!pdWopy%dq g& g% W hiIg 4 sy
==L%g qcpg)g;W@gg[r a:ir m hn=1 gi=hagc44 g}3N g&gp64
=ri g.., gg uta ocrg g
ag
~E pg$
g gg##N[dE5h}$45$$$k 9E as##(#n
$1Wr 56sid@@@h in un#
!MEi$
1131 2.5E 6 605 1.48E6 8.95E8 0.645 156.1 9.36E3 1132 2.8E-6 678 5.35E4 3.63E7 0.722 174.8 1.05E4 1133 4.0E-8 ses 4.00E5 3.87E8 1.032 249.7 1.50E4 l134 6.0E-7 145 2.50E4 3.63E6 0.155 37.5 2.25E3 1135 2.2E-6 532 1.24Eb 8.60E7 0.587 137.3 8.23E3 M[fdsj$@
1.39E9 iREVISON NO.: 0 l
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t COMMONWEALTH EDISON COMPANY l CALCULATION NO. BRW 974798 M PROJECT NO.
PAGE NO.13 l The two removal mechanisms for this accident are due to decay and leakrate to the secondary c,
side of 1 OPm. The time dependent adivity after two hours with the removal constants can be calculated using the basic decay equation rnethodology (Reference 10).
R*
- A,C(n - A C
g (o
~
C C(t) d tr
-t Ad+A Ir,
C(0 = C e Where : t = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> = 7200 soo I SPm A
ir Volume of RCS gg mio.
'[mio:-
i 12062 A
7 48 [883) 60(noc [
3
-I
= 1.85E - 7 aoc d.
Since the lootope concentration is assumed to remain evenly distributed throughout the RCS volume, then the rate at which the isotope concentration leaks from the RCS, R(0, is simply the RCS leakrate times the concentration. The total activity released during a given time Interval is the integration of the release rate over that interval, in this case,2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
R(t) = Aw x C(t)
R(t) = 1, x C e(4*M o
f R(t)dt = f AeC,e(N'4I dt e
o A C'
-(A, + A,) -(A. + Ae)e-'I4'4Iot
=
'U*
-e-'(4'4)} Equation 2.d R=
l REVISION NO.: 0 g
QUG 29 '97 17:33 312 269 3753 PAGE.14
SMGEMiliMMTV 23918 Nf312 'f6Y-3r'S3 AUti ifV77 1 ?DK Mo.W.W
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COMMONWEALTH EDISON COMPANY l_ CALCULATION NO. BRW 97-0798 M PROJECT NO.
PAGE NO.14 l TABLE 1.d l
..r. e ?-
1,:.... ;
l l
l lI.
i.
.U.
fl.r y ntW N
}g
{,.03,'
J I
U d
l yy.
e l131 9.38E3 9.97E 7 1.24E1 l
1132 1.05E4 8.37E 5 1.0SE1 1133 1.50E4 9.25E 6 1.93E1 113'.
2.25E3 2.20E-4 1.50E0 l135 8.23E3 l
2.91E 5 9.88E0 Calculate the thyroid inhalation dose at the Exclusion Ares' Boundary (EAB) using the equation e.
from UFSAR 15A 4.
Table 2.e j
I131 1.24E1 1.08E6 1.34E7 l
l132 l
1.05E1 6.44E3 6.76E4 l
l133 l
1.93E1 1.60E5 3.47E8 l
l134 l
1.50E0 1.07E3 1.60E3 l
l135 l
9.88E0 3.13E4 3.09E5 l
E n E h nm s.c._f B 1.72E7 The total DE I 131 actJvity released is the total dose from Table 2.e divided by the 1-131 dose i
convenzion factor Numerically this is 15.9 CI(1.72E7 rem /1.08E8 rem /ci).
j Exclusion Area Boundary Dose for a 1 com Leakrate l
f D,[ rem]= X' i
u xBx (R, x DCF;)a, Equation 2.e.l S ass l
= 7.7E-4 x 3.47E-4 x1.72E7[ rem]
M,,
,, $eC,
= 4.60[ rem]
I
[REVIS!ON NO.: 0 l
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PAGE NO.15 l f.
Calculate the thyrold inhalation dose at the Low PopulaGon Zone (LPZ) usino the equation from UFSAR 15A.4. The activity released during the accident from 2 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> was obtained from UFSAR Table 15.14. This activity includes the dose contribution from a 9.4 Opm leak in the faulted SG, TABLE 2.f.1 b.
J ;.? x ;.;.c.,
. 's /) >
.:.. s v.x.
\\
- Tc L
. %:-Wf J[
j h'
- e w..,. I w(.s k i gr
- w'.- is[ '.;"fM b f.,
' J'M J 1
s %q 9..
i s:
..?
L,u i'a,.
..,. c.u u
- . 1.rten p m..
.... :.1..t
....~:<
1-131 1.9E3 1.06E6 2.05E9 l
l132 l
3.8E1 l
6.44E3 2.45E5 l
1133 l
1.8E3 l
1.80E5 3.24E8 l
l-134 l
3.7E0 l
1.07E3 3.96E3 l
l135 l
3.8E2 3.13E4 1.19E7 2.39E9 The total 2-40 hour dose calculated above in Table 2.f.1 is separated into specific time periods of 2-8 hrs, 8-24 hrs,24-40 hrs. This is based on scaling the total 2-40 hour dose by the fraction of steam released during the same time period. The 2 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> steam release was obtained from UFSAR Table 15.13.
TABLE 212 a:
,n,
- n...
e.a..;,.,
?
h 2-8 br 939,604 0.30 2.39E9 7.17E8 l 8-24 hr l
1.234,515 0.30 l
2.39E9 9.32E6 24-40 hr 960,806 0.31 l
2.39E9 7.41E8 3,154,925 The atmospheric dilution factors (X/Q) for 0-8 hrs,6-24 hrs, and 24-40 hrs values were obtained from UFSAR Table 15.014. The breathing rates for 0-6 hrs,8 24 hrs and 24-40 hrs were ottained fmm UFSAR Table 15A 1. Calculate the thyrold Inhalation dose at the Low Population Zone (LPZ) using the equation from UFSAR 15A.4.
f Don [ rem] = f x B x Z A x DCF Equation 2.f.1 O pr
/L k
l l REVIS!ON NO.: 0 l
l AUG 29 '97 17 35 312 269 3753 PAGE.16
SARGENiti.Vi4DY 23V12
~ ID 312-2f39-3753 f4UG 29497 TFThV Mo~.1@M V.Tr----
4 COMMONWEALTH EDISON COMPANY l CALCULATION NO. BRW.97 0798 M PROJECT NO.
PAGE NO.16 I 4
TABLE 2.f.8
. M.
' q.,,,q.... y, j p ~,ip.
> ' [... mi D(., g'L.. -
., '..ty
.,; - :a,
.y..
> '. r
.[q..
, s.,
I
.. ~.
.j-..
it' n
~,.
Ty
..* ; j ',
- x...
r i'i. "
\\'
'l,4
,. ' ll,'
- i e
,' r.
d..',.., 4. r. la 1. '.'.:
'V' ih.,.
.w.:
,,.u.
v.s
. ) ;. ]* ', [, M q j,,.l.,
.i 0 2 hr 7.1E 6 3.47E.4 1.62E8' 3.99 l 2 8 hr l 7.1E-5 l
3.47E.4 l
7.17E8 l
17.06 l
l s 24 l
1.4E-5 l
1.76E-4 l
9.23E8 l
2.26 l
L2m l..
l 2.3E.4 7.41E8 1.21 7.1E-4
- From Table 2.s x 9.4 25.14 1
l 3.
MULATION OF DOSE DUE TO PRIMARY TO SECONDARY LEAKAGE DURING ACCIDENI l
INITIA1ED RPIKE The occident inilleted spike model is the same es the pre socident model except en additionellodine appearance rate term is added for fuel release role into the RCS. In accordance with the Stenderd Review Plan, the toscior trip end/or pdmary system depressurization associated with the MSLB creates on lodine epike in the primary system. The spiking model assumes that the lodine reloose rate from the fuel rods to the primary coolant increases to e value 600 times greater then the Technical Specification limit. This factor adds en additional release rate factor for lodine activity, W.
Cebulate the total removal rete of lodine, h, through letdown purification and radioactive decay.
e.
Equation 2 of Reference 18 defines this total es:
soo", = A ohe, + 1, soc Equation 3.e.1 As t
F, g
3 Ao sed
Whers :
t
=
1 - DFj Equation 3.e.2 h(0}
a l
l REVISK)N NO.: 0 l
AUG 29 '97 17 36 312 269 3753 Pi:GE.17
S ARGENTP.L.UNDV 23011 ID 312-269-3753 AUG 29'97 1P 2P No.006 P.28
'~
l COMMONWEALTH EDISON COMPANY l CALCULATION NO. BRW.97 0794.M PROJECT NO.
PAGE NO.17 l The 75 gpm letdown purification flow, F,. ls converted from gpm to grams / son at letdown operating parameters (Desien Input 2 and 3 above).
'gol' f If,' '
~
llb
~
~
~ 54 g', ' I min g',l',3 4
- sec,
', min,
(,7.48 gal,
,0.01614 ft'
. Ib,
60 sec
= 4701 8---
.sec, Substituting the unlues of F,,M and DF int o Equation 3.a.2 gives :
4701 I-r 3
2.42E8[g \\
j
= 1.75E-5 sec,
Values of 4 for each isotope are obtained from Reference 4.
y;,, 1 1 1 1 ll 1
n team 4 m t
u 5
h
[
llM i131 1.76E 5 9.97E 7 1.86E 5 i 1.*2 1.75E 5 8.37E.5 1.01 E-4 I it' 1.75E 5 9.25E 6 2.67E 5 l134 1.76E.5 2.20E-4 2.38E-4 1135 1.76E S 2 91E 5 4.6665 b.
The fuel release rate, W. Is defined as the product of the RCS activity and the total lodine removal rate for each isotore:
4 lCl/sec) = A,[Cl) x 4
[sec") EquaUon 3b l REVISION NO.: 0 l
AUG 29 '97 17:36 312 269 3753 PAGE.19
SARGENV&LUNDY 23Vla 8D 313-269-3F53 AUG 29'9F AF 38 No.006 P,89
'~
COMMONWEALTH EDISON COMPANY l CALCULATION NO. BRW.97 0798 M PROJECT NO.
PAGE NO.18 l Each fuel release rate is multiplied by 600 (Design input 6) to obtain the spiked release rate.
Table 3.b I...,...i-9 y,,,.:
jlu,;.;
- g.,y ai,. ;
pMV
. ]
s s:v
- ..;,, r.
,,4 ; -..
' 49%j a
.1, t.,
'f',
I. *.
(,
h i 131 1.85E.5 2.89E.3 1.45 1132 l
1.01 E-4 l
1.77E 2 l
8.65 1133 l
2.67E.5 l
6.87E.3 l
3.34 11H l
2.36E 4 l
8.92E 3 l
4.40 1135 l
4.66E.5 l
6.39E.3 l
3.20 c.
Based 01 the data from Table 3.e and Table 3.b, it can be conduded that the fuel rolesee rate is much larger then the effects of radiomotive deoey orleak rete removal, so A and A, are not 4
considered in calculatin0 the initial concentration of lodine in the RCS,
= -A.C(t)- A,C(t) + Aw c
\\
j dC(t) = [ Awdt c,
o C(t) = 0, + Awt Equation 3c d.
Since the isotope concentrollon, C(t) la assumed to remain eventy distributed throughout the RC8 volume, then the rete at whloh the isotope concentration leaks from the RCS, R(t), is the RCS leak role multipiled by the concentration determined by Equation 3.0. The total activity released during the event is calculated by Inte0rsting the release rate over the time interval.
R(t) = 1 C(t)
= A,(0, + Awt) t R(t)dt = A,(C + Awt)H R = Aw C,t + b" Equation 3.d 2
r s
I REVISION NO.t 0 l
AUG 29 '97 17 37 312 269 3753 N3E.19
SAQGENV&LUNDY 23V11 ID 312-269-WPJ AUG 39'9Y 1Y 3@ No.dW V ?lb COMMONWEALTH EDISON COMPANY l CALCULATION NO. BRW 97-0798 M PROJECT NO.
PAGE NO.19 I TABLE 3.d ll.Offh i
. J !l ; f 1 y m'," O',d*,'
'd,f..
g INT I131 168.1 1.45 7.16 l
l132 l
174.8 8.05 l
4.27E1 l
l133 l
249.7 3.34 l
1.63E1 l_
l134 l
37.5 4.46 l
2.14E1 l
l135 l
137.2 3.20 l
1.55E1 e.
Coloulete the thyroid inhalation dose et the Enduelon Area soundary and Low Population Zone using the equation from 8/B UFSAR 15.A.4.
TABLE 3.e
- :l ' Y Uh.hEk.h "k hk'.' 4 f k'
- h..
h 1131 7.16 1.08E6 7.73E6 1132 4.27E1 4.44E3 2.75E5 1133 1.63E1 1.00E5 2.93E6 1134 2.14E1 1.07E3 2.29E4 1135 1.55E1 3.13E4 4.85E5 ER,xDCF 1.14E7 The total DE l 131 edivity relnesed is the total does from Toble 3.e divided by the 1131 doca conveiston fedor. Nutnerically this is 10.6 Cl(1.14E7 rem /1,00E6 rem /ct).
Fa@ggjon Area B;undary Dose for a 1 nom Leaktate:
ff Dw[ rem}aas Bx R, x DCF, Equation 3.e.1 x
3 l
r 7.7E-4 @=.
x 3.47E-4."ex1.14E7(rem]
1 c.
= 3.05 [rtml REVISION NO.t 0 l
l
'?
[
s A iEG iFriT & L U t4 D Y 2 3 V 1 1 1D:312-269-3753 AUG 29'9?
1?! N l
COMMONWEALTH EDISON COMPANY
[ CALCULATION NO. IBRWD-0798 M PROJECT NO.
PAGE MO. 20 l f.
Calculate the thyroid inhalation dose at the Low Population Zone (LPZ) using the equation from UFSAR 15A.4. The adivity released during the soddent from 2 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> was oM61ned from UFSAR Table 15.14. This adivity includes the dose contribution from a 9.4 gpm leak In the fauhed SG.
TABLE 3.f.1 E
IEE l
l l
1 l131 2.1 E3 1.08E6 2.27E9 1132 l
1.0E3 8.44E3 6.44E8 1133 l
2.9E3 1.80E5 5.22E8 1134 l
1.4E2 1.07E3 1.50E5
~
1135 l
1.2E3 3.13E4 3.78E7 W 00101. nam M RI@
2.84E9 The total 2-40 hour dose calculated above in Table 3.f.1 is separated into specific time periods of 2 8 his,6 24 hrs, and 2440 hrs. This is based on scaling the total 2-40 hour dose by the fredlon of steam released durin0 the same time period. The 2 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> steam release woo obtained from UFSAR Table 15.1 3.
TABLE 3.f.2 2-8 hr 939,604 0.30 2.84E9 8.52E8 8 24 hr 1,234,515 0.39 2.84E9 1.11E9 2440 hr 980.806 0.31 2.84E9 8.80E8 horgg 3,154,92!
The atmospheric dilution fadors (X/Q) for 0 8 hrs,6-24 hrs, and 24 40 hrs values were obtained from UFSAR Table 15.014. The breathing rates for 0 8 hrs,6 24 hrs and 24 40 hrs were obtained from UFSAR Table 15A.1, Calculate the thyrold inhalation dose at the Low Population Zone (LPZ) using the equation from UFSAR 15A.4.
i l
l i
l REVISION NO.: 0
]
l
" 29 '97 # 33 31 3
SNGENYF.LUNt)Y 23V11 XD:312-20T-3753 MUG 2T'T7 87831 Wo.00b P.22 COMMONWEALTH EDISON COMPANY l _ CALCULATION NO. DRW.97-0798 M PRO LECT NO.
PAGE NO. 21 l Dm(rem]=
- < s x 0 w Z A DCP Equation 3.f.1 0
r nn TABLE 3.f.3 EEMBERE 0-2 hr 7.1 E.6 3.47E 4 1.07E8*
2.64 2 0hr 7.1 E-$
3.47E 4 6.52E0 20.99 8 24 1.4E 8 1.75E-4 1.11E9 2.27 24 40 7.1E6 2.3 E.4 8.80E8 1.4 fi R 00thd
- From Table 3.e x 9.4 27.70 4.
CALCULATION OF BITE ALLOWABLE LEAKRATE a.
Results of the Pre Accident initiated lodine Spike Model The EAD doso for a 9.4 gpm leakrate is 43.14 rem (4.80 X 9.4). The tott.! LPZ doSo calculated in Table 2.f.3 is 25.14 rem. Therefore, the EAB dose is more limiting.
i The thyroid dose due to the release of activity In the secondary sido of all four steem generatora is 1.53 rom. The dose due 101 gpm primary to secondary leakage in 4 steam generators with a concentration of 60 pCl/g is 4.60 rem. Given that the dose limit in the Standard Review Plan is 300 rem for the pro accident model, the maximum alloweble leak rate without exceeding 300 rem is:
f i
Allowable Leak Rate #
4.60 ""
s Gm
= 64.88 pm l REVISION NO.: 0 l
RJ3 29 '97 17:40 312 269 3753 PA3E.22
SARGENTtLUNDY 23Via 19:312-269-3753 AUG 29'97 17:31 No.M M V 7/W l
l COMMONWEALTH EDISON COMPANY I CALCULATION NO. SRW.g7 0788 M PROJECT NO.
PAGE NO. 22 l Conesquently, the total EAD dose due le a 44 48 gpm leek durtn0 e MSL5 is 300 rom. Allowing 0.1 ppm por seeh of the three intoci stoom generators leavoe H.54 ppm (N.40.3) for the fauned loop.
Note that the H.44 ppm alloweblo leekrete le coloulated et RCs operating conditions. Should the allowetdo leekrete be desired to be ogressed at room temperature conditions, the H,00 ppm must be divided try 1.408 (Reference it) to sooount for RCS denelly differences.
Therefore, the room temperature allowetdo leek rete is 44.14 gpm.
b.
Results of the Acolderd initleted lodine Spike Model The EA8 does for a 9.4 ppm leekrete is 24.47 rom (3.05 x 9.4). The total LPZ dose coloulated in Table S.f.3 is 27.79 rom. Thorofore, the EA8 dooo is more limning.
The thyroid dose due to the release of edivMy in the escondary side of all four steem generetors is 1.53 tom. The does due to 1 ppm primary to secondary leakage in 4 steem Generators wHh a concentretion of 1 pCM le 3.0$ rom. Given that the dose limit in the Standard Review Plan is 30 G
rom for the ecoident inittsted splke model, the maximum alloweblo leak rate without exceeding 30femis:
r S
30 rem-1.$3 rem g
3.0$ " "
L PM
/
3
= 9.33 spm Consequently, the total EA8 dose due to a 9.31 gpm leek duttng a MSL5 is 30 rom. Allowing 0.1 epm por sech of the three intact steem generators leaves 9.03 gpm (0.33 0.3) for the faulted loop.
Note that the 9.33 gpm allowable leskrete is calculated et RCS operating conditions. Should the -
alloweblo leskrete is desired to be expressed at room temperature conditions, the G.33 Opm must be divided by 1.406 (Reference 19) to secount for RCS density differences. Therefore, the room temperature elloweblo leek rete is 6.63 Opm.
I REM $lON NO.: 0_
l L
M..' M 1 - _ _. _ _ _ _ _.312 2 p 53 __ PAGE.23
SW2 GENT &LUNDY 23911 W: 312-369-3753 AUd 79'97 17: 33 Mo.D05 E24 COMMONWEAL'rH EDISON COMPANY l CALCULATION NO. BRWI97-0798 M PROJECT NO.
PAO _E NO. 23 l 8.
Q&QULATION OF END OF CYCLE 7 PREDICTED D0flE8 in accordance wkh the requiroments for Draklwood Unll i voltage based repalt criteria (IPC) for outer diameter stress mrrosion cracking at tube support plates, the potsntial tube leakage during a MSLB event with containment bypass must be predicted at the end of the next operating period. In addition to the prodided IPC leakage, the MSLB leakego contribution from circumferential cracking at the top of the tubesteet must alt.o be factored into the end of cycle assessment. This combined predicted leskrate must be compared to and shown to be less than the madmum site allowable leakrate determined in Bection 4 above.
Braldwoort Ctation is currently propanno a request for Technical specification change to lower the RCS Dose Equivalent lodine-131 limit to 0.1 pCl/0. As documented in Gection 3, the site allowable leaktate of 0.63 Opm is based on an RCS DE 1131 limit of 1 pct /g. The alte allowable leakrate can be inertased proportional to a reduction in RCS DE 1131. Therefore by reducing the RCS DE 1131 limit t0 0.1 pCl/g, the allowable leskrate is increased to 66.3 ppm (6.63 Opm/0.1).
The predided end-of cycle 7 IPC leskrate 57,1 opm based on room temperature conditions (Reference 5). To this is added 5 opm to account for the contribution from circumferential cracking at the top of the tube shoot and operational leakage from three steam Generators (0.1 gpm per steam generator) for a totalleskrato of 82.4 Opm. This is bounded by the requested 66.3 Opm site allowable loskrete limit.
Thla sortion of the calculation determines the EAD and LPZ thyrold dose for the prodlded end-of cycle leakrate of 82.4 gpm to valkiste that the current operating conditions are bounded by existing calculations. The EAD and LPZ dose is bounded by Section 3 of this dooumont, which showed that the acoident initiated spike 15 the limiting acddent, s.
The most restrictive EAD thyroid dose limit is 30 rem per section 4.b. This dose ilmft corresponds to an allowable leakrate of 6.63 Opm at an RCS DE l 131 concentration of 1 pCilo.
The calculated EAB dose romalna the same wher: allowable leaka0e is increased to 68.3 gpm because RCS DE l 131 la decreased by a proportional amount. To calculate the EAB dose due to current cycle projected leakage of 68.3 Opm, Xt.a determine the fraction of projected leakage mmparvd to allowable loakage.
62.4 gpm, Xm 66.3 gpm 30 rem X,, c: 62.4 gpm 30 rem 66.3 spm Xu, = 28.2 em at a 0.1p Ci/g RCS DE1131 concentration Therefore, the end of cycle 7 prodleted EAB doso is within the 30 rem dose limit under end-of-cycle 7 operating conditions.
b.
The LPZ calculated thyroid dose le 27.79 rem per Section 3.f. This dose limit corresponds to an ellowabla laakrate of 6.63 gpm at an RCS DE l-131 concentration of 1 Cl/0. which egain remains the same under the proposed allowable leakrate of 68.3 gprn because RCS DE I.131 is l REVISION NO.: 0 l
cu; 29 97 17:at 312 269 3753 Pa3E.24
Sf!OGl#6VBLUNDY 23911 1D:313-369-3753 AUG 39'97 a?t33 No.DD6 E.h5 COMMONWEALTH EDISON COMPANY l CALCULATION NO. BRW.97 0798 M PROJECT NO.
PAGE NO. 24 l proportionaNy reduced. The LPZ dose for projeded endaf cycle conditions, Xm, is calculated ty performing a retlo of calculated values to projeded values.
62.4 gpm,
Xn t
66.3 gpm 27.79 rem 0A 8P_m-27.79 rem Xm = 66.3 gpm Xm = 26.16 rem at a 0.1 Cl/g RCS DE1131 concentration Therefors, me end of. cycle 7 predicted LPZ dose is bound 6d by Section 3.f.
EUMMAMY AND.CONCLUS10fd it is conduded from Sedlon 4 that the accident initiated splke is more limitin0, therefore the maximum site allowable 80 leskrete during a postulated MSLD 18 9.3 9pm at RCS operating conditions (6.6 gpm at room temperature) with a RCS DE l 131 concentration of 1 pCVg. This value indudes the 0.1 gpm contribution from each of the three Inted SGs.
Section 5 determined that the Unit 1 end of-cycle 7 predided MSLB tube leakage results in off-sito thyroid doses that are less than a small fradion (10%) of 10CFR100 limits. Ths resulting EAD and LPZ doses, with a 0.1 CUQ RCS DE I 131 limit, are 28.2 rem and 27.79 rom, respedively, which are less than the 10 rem limit for the limitin0 sooldent inillated spike case.
FINAL -
l REVISION NO.: 0 l
Ai.fi 29 '97 17142 312 269 3753 PAGE.25
SENT BY:SARGEST & LLNDY 80E18 i S 3 37 : 3:16PM :
SARGLNT & LthDY-Blu 450 3535;U 8/ 1 i
PREPARATION, REVIEW AND APPROVAL OF CALCULATIONS CALCULATION TITLE PAGE Calculation No: DRW 97-0798 M DESCRIPTION CODER.J102 DISCIPLINE CODE:
M BRAIDWOOD STATION UNITS 1&2 SYSTEM CODE:
RC.MS TIT 1,E:__
AlJg_w3hlgjahatt_CAgghtion for StealDRcncrator iniffiDi PluPPjn3_Ctileria
_X_ Safety Related
_ Augmented Quality Non Safety Related REFERENCE NUMDERS Type Number Type Number COMPONENT EPN:
DOCUMENT NUMDERS:
EPN Compt Type Doc Type / Subtype Document Number REMARKS:
REV.
REVISING APPROVED DATE ORGANIZATION PRIJT/ SIGN 8..//f. ( AdM//I/N&a '
J'-B-7y O
S&L bk bN4f Y,hf
- hw.
- l WM f'5'~ll 7
(v v
Sera c3 9715 25 31226?2179 PA3E.02
SCN ' Y25AROT & LlADY 80E18 : S- 0 917 : 3:17PN :
SAROT & LLADY-el$ 458 N B
COMMONWEALTII EDISON COMPANY CALCULATION REVISION PAGE CALCULATION NO. BRW.97 0798.M PAGE NO.: 2 REVISION SUMMARIES REV: 0 REVISION
SUMMARY
Originalissue. pages 123 Electronic Calculation Data Files:
cer.y N.m.v. % ra.
.w. w : =>
None Prepared by: W. J Johnson /
/
IM No'7/4 ~1
- /2 97 Reviewed by: R. G. Chow /
14~
7 date
} Tint /SIAn Type ofReview
[ X ] Detailed
[ ] Alternate
[ ] Test DO ANYASSlNPIKNS N Tills CALCUIA110N KDQUEEIATIR VIRIHCAT10N [ ]iT3 [X}NO Tracked by:
REV: /
REVISION
SUMMARY
(y<et4 rcl1ypocJrnthow* I ewv chs p n*) ' "I -
Electronic Calculation Data Files:
(rr.y.= N.=. vm rue
.w.-. ;-)
Udn(
Prepared by: h/. TTM-em M/ M N/4/Cr7 Reviewed by: 26,.Oku f
drint/ Sigh
' Date Type ofResiew IXl Detailed I 1 Alternate i 1 Test DO ANY ASSthum0NS N Tills CAILMA110N RDQtXRE IAlUn1RIDCA110N [ ]YI5 W NO Tracked by-SED 03 '97 15:26 3122692179 WT;C.03
3 kWL9YUR04@
LW%tJh1 mmaj COMMONWEALTH EDISON COMPANY l CALCULATION NO. BRW 97-0798 M PROJECT NO.
PAGE NO. 24 l proportioneth redwood. The LPZ dose for projeded end-of cyde condhions, Xm, is calculated by performing a ratio of colouleted values to projeded values.
62.4 gpm,
Xm 66.3 spm 27.79 rem Xm = 62A gpm27.79 rem 66.3 apm Xm = 26.16 rem at a 0.1 Cl/g RCSDE1131 concentration Therefore, the endef-r:yolo 7 predidad LPZ does is bounded by Sedion 3.f.
Ay_MMARY AND CohCLullONS M is concluded from Section 4 that the socident initleted spike is more limiting, therefore the maximum site aNoweble SG leskrete during a postulated MSt.B is 9 3 Opm at itCS operating conditions (6.6 gpm at room temperature) wMh a RCS DE l 131 concentration of 1 pCUg. This value indudes the 0.1 Opm contribution from each of the three Inted SGs.
Section 8 determined that the Unit i end-of cycle 7 predided MGta tube leakage results in off site thyroid doses that are less then a arnall frao00n (10%) of 10CFR100 limits. The resultino EAD and LPZ doses, with a 0.1 pCllg RCS DE I.131 limit, are 28.2 rom and 26.18 rom, respectively, which are less than the 30 rem limit for the l
limitin0 accident Initiated spike case.
FINAL -
I REVISION NO.: 1 l
SEP 03 '9? 15320 3122692179 PCGE.04