ML20215H607
| ML20215H607 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/10/1987 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8704200447 | |
| Download: ML20215H607 (82) | |
Text
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'Af Telephone (412) 393-6003 Nuclear Grcup P.O. Box 4 Shippingport, PA 15077-0004 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Additional Information Gentlemen:
Enclosed is a copy of the calculation packages developed to determine the revised radiation monitor setpoints provided in proposed Technical Specification Change No. 124. This information is provided in response to a verbal request during a telephone conversation of April 8, 1987 between Duquesne Light Company staff and the NRC Region 1 staff reviewer concerning the subject setpoints in the Technical Specification Change Request.
Very truly yours, AILW J. D. Sieber
[VicePresident, Nuclear cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 8704200447 B70410 0g 8
\
e
. Benvar Vollsy Pow 3r Station, Unit No. 1
- Docket No. 50-334, License No. DPR-66 Additional Information Page 2 i
, cc: Mr. Peter S. Tam U. S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555
- Mail Stop 316 Addressee only U. S. Nuclear Regulatory Commission Attn: R. Struckmeyer Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Pennsylvania Dept. of Environmental Resources P.O. Box 2063 Harrisburg, PA 17120 k
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t-r4 RADIOL ICAL CONTROLS udt ;
SUBJECT CALC. No: 'n GASEOUS EFFLUENT MONITOR EFFICIENCY DATA ERS-SFL-85-0 paon L og REFERENCE -------N/A-------------------------
DCP EM JO CO OTHER OA CATEGORY i I Nuclear Safety R elated O il O lll O oin.,
PURPOSE The purpose of this calculation package is to document nuclide-specific instrument J efficiencies for the gaseous effluent radiation monitors. This package incorporates data obtained since the original efficiencies were released, corrects previous !
crrors, incorporates corrections for atmospheric pressure differentialu (SA9/SA10 and Victorcen only), incorporates corrections for upstream charcoal cartridges I that are part of the sample stream (SpING and SA9/SA10 only), and provides nomo derived data heretofor unavailable (Ch 5 nuclide specific).
l 1
This calculation package is formatted into five major attachments, each with one or more taba. Each attachment addresses one type of monitor. Each attachment i documents the derivation of the data contained therein. In the section to follow, a brief summary of the attachments is provided, l
Revision 1 added Ar-41 to Attachment 5 b
- Attachments are numbered individually stortin; with puo 1 l
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e DOCUMENT CONTROL IERS-neal @furpose G' Code tat l e F[eh O<U*P I "' @ 8"
Is JAKosmal G Mett)odology/Derevatione Ad Data Sheett e RMVento se EASchnell Ofn# 01flustrations e NDTD gg[put,,,Data Conti ;
e RSP FILE e a D.K. Yourd G1Teferen(et j R.R. Schilling S.F. 1.aVic '
P.F. Cangwisch !
I K. Wintor
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g EMS SFL-85-031 pe,e 2 org t = wonmeness i r_ M sessey Attachment 1. Eberline SpING Ch 9 and SA9 monitors There was much confusion regarding the officiencies for those monitorn due to unclear vendor documentation. The vendor was asked to resolve these concerns. As a result of his suggestions and discussions with Radcon personnel. It was decided to use the factory prototype officiencies for Xu133 and Kr85 specifically for those nuclidos, and use the nominni prototype value to determino all other nuclides.
For the SA9 monitors a nominal prennuro dif ferential correction was added to their derived efficiencies.
For all SA9 and Ch 9 monitors, the officiences were reduced to account for 95% filtration of lodino in the sample stream by the charcon1 cartridges installed in the sample Linus.
Attachment 2. Eberline Sp1NG Ch 7 monitors As with the Ch 9 monitora, there woro nome problems with the vendor documentation. The final nuc11do-specific officiencies are based on the factory prototypo Xol33. Kr85, and nominal officienciou na was explained for the Ch 9 monitorn.
An todino correction was applied, but there was no pressure correction duo to the automatic pressure compennation added as part of DCp-400.
Attachment 3. Eberlino SAIO monitorn For the SA10 monitors, the nuclido specific of ficiencies woro based on the Xo!33. Kr85, and nominni values. pressuro corrections and lodino cartridge corrections woro incorporated.
Attachment 4. Eborlino SplNG Ch 5 monitorn This packago providen the first nuclido-upecific of ficienclos available for thoso channeln. No prennure correction was necomanry, but an todino correction wan mado.
Attachment 5. Victorcen GW108tl. VS10lli. VS107B monitorn Although Victorcen had provided nuclido specific data na part of the nyntem documentation, thoro woro nuclidon minning. In addition, tho original data did not include prennuru correctionn to componnato betwoon tho actual detector prennuro and the atmonpherie prennuro into which the gan in ojected.
ADDITIONAI Of.NERAl. DISCthifi!0_N NRC Information Notico 82-49 required liconnees to ovalunto the of fect that vacuum in a nampler could havo on the monnured retcano rate. Due to dunnity changen and prennuro decreased, the detcetor indicated lonn activity than van actually being emitted. A modification was mado to the Sp!NG syntom to provido for automatic prennuro dif ferential componnat ion. For the ilA9/SA10 nnd Victorcon monitorn, a nominal correction, baned on observed prunnuro gano data,
g ERS SFt.-85-031 N'3 Y Ee,vwenmental E _* . -8 Se8ety was incorporated into the efficiency values.
There are charcoal cartridges installed upstream of these gas detectors as part of the monitoring subsystem. In as much as these cartridges filter out ,
upwards of 95% of the lodine activity in the sample stream, the monitor would ,
not indicate true release iodine activity. The iodine nuclido efficiencies were corrected for these conditions.
While the Victorcen monitors were installed with an upstream f11ter, those i filtern will be removed in accordance with a future technical specification ;
change. Therefore, the iodine correction was not incorporated for the Victorcen ;
monitorn. [
Nuclide eminnion energies were taken from the Beaver Valley Power Station L Radionuclide Database. (based on Kocher).
With the exception of the Victorcen monitors, for which it unnecessary, the ;
of ficiencien are based on the factory prototype calibration, with correction for !!VPS-installed monitor sonnitivity dif ferences. r i
l In as much as periodic calibrations have, as their basis, showing concurrence to the factory data, there should be little need to update these data. If significant shif ts in configuration or response occur, consideration should i be given to updating the af fected data.
USE OF DATA These data were generated to assist in EPP reinted calculations. These data wl11 also be used in the MIDAS system.
RE FERENCE!i.
I
- 1. Elc document 12000-OlA, Primary Calibration SA-9 liigh Range Detector
- 2. E!C document 12000-21. SA-13 1.ow Rangu Noble cas Beta Detector Primary Calibration with Noble Canes l 3. E1C document il000-A09. Can Calibration PING-lAS SA-10 Ontario liydro
- 4. Elc document 12000-03fl, Primary Calibration sal 2,SA13 Mid Range Gas Detector i
- 5. EtC document 12000-23 , Calibration Check sal 2, SA13 Mid Range Gas Detector j
- 6. E!C document flPING-4A Particulate, lodine Nobic Can Monitor DI,C forlegn print 8700-1.22-576*Al {
- 7. EtC document System Manual Calibration Data and System Specific information Duquenne Power and 1,lght Job 750205 i
E=wonmow a __. -;w seswy ERS- SFL-85-031 ,4 o, 4
- 8. EIC Certificate of Calibration dtd June 1980
- 9. Victorcon Document, Addendum to Duquesne Light Company Beaver Valley Power plants Specification BVS-414, Table V, dtd 10/7/74
- 10. ERS-SFL-82-021 (superceded by this document), SA9, SAIO, SA13 Efficiencies
- 11. ERS-SFL-84-011 (superceded by this document) Eberline SPING efficiencies
- 12. EIC Document 12000-Al2, Energy Response of the RDA-3A detector in a Noble Gas Monitor
- 13. NDlllPS 0149 December 28, 1984
- 14. ND1:SitP 403 March 4, 1985
- 15. ERS-SFL-84-003, RADFILE l
RESULTS The results tabulated in the attachments have been shown to be appropriate for use on the BVPS-1 gaseous effluent monitors, as the basis for:
- a. EPP/IP Errorgency action level determinations l b. EPP/IP Dose projection procedures
- c. MIDAS site-specific and unit specific databases l
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Ermronmental & Radiologeal Safety ERS- SFL 31 Attachment 1 pa9*
1 of 16 SA9 High Range Noble Gas Monitors DISCUSSION Since their installation, the Eberline SA9 monitors, both standalone and SPING Channel 9 versions, have been the topic of much discussion due to apparent discrepancies in the documentation of the calibration. Also, some modifications have been made since the original calibration. A recent physical inspection showed that the physical configuration was different between the three SPING channels. Discussions with Eber11ne identified that twoofthedetectorswe7ey8ng. With these situations, it was recdommended in NDlSHP:403 dtd March 4, 1985 that a gas calibration be performed on the SPING units. However, due to technical specification operability requirements, this will not be immediately possible. Thus, in the interim, an evaluated efficiency will be provided.
The most significant modification of the SPING units since their installation was the incorporation of automatic pressure compensation on monitor channels.
On the SPINGs, therefore, no such compensation is necessary in establishing efficiency values. For the stand-alone SA9s, no such automatic pressure compensation is available, and will have to be incorporated manually as part of the instrument's efficiency.
FACTORY PROTOTYPE CALIBRATION The SA9 units received a factory calibration that consisted of exposin8 the monitor detector to a free air source. The resulting CPM /mR/hr value is used to normalize the response of the entire monitor assembly in comparison with the factory prototype unit which was subjected to a gas calibration involving Kr85 and Xel33 in separate exposures and a free air exposure similar to that performed on the production unit. By comparing the free air exposures of the production unit and the prototype unit, differences in response between detectors can be addressed. This calibration protocol, known as a transfer calibration is an accepted technique.
Duquesne Light obtained a copy of the Eberline drawing 12000-OlA, " Primary Calibration SA-9 High Range Gas Detector" which documented in detail the primary calibration effort, and was provided with copies of Eberline document entitled " SYSTEM MANUAL - Calibration Data and System Specific Information for 3 SPING-4 and 1 CT-1 Duquesne Light Power and Light" which documented the factory transfer calibrations on our production units.
The primary calibration document provided three efficiency values:
Xe133 5.0E-3 CPM per Bq-MeV/cc Kr85 2.9E-2 CPM per Bq-MeV/cc Nominal 1.1E-2 CPM per Bq-MeV/cc The free-air source value was al.5 CPM per mR/hr. The calibration document described a process in which tFe Xe133 value was increased to compensate for sample tube attenutaion and in which the Kr85 value was decreased to compensate for bremmstrahlund, Loth to arrive at the nominal value of 1.1E-2 CPM-cc/Bq-MeV. Included were corrections to compensate for signal processing by electronics between the detector and the display unit.
- Ett Reoo -01 A
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A Erwetonmental & Radeologecal Safety ERS-SFL 31 Attachment 1 P*9' 2 16 On review, this process seemed invalid. The detector / sampler assembly was filled with a known quantity of gas and the display unit readout dorded.
The sample tube, lead shielding and all signal electronics were iO place.
This apparently the case, it was not clear why Eberline chose lto compensate for the effects of these items when,in use, these items would act on an actual sample stream as well. In fMlMNS:4124 dtd February 28, 1985, Duquesne Light requested clarification. In El-918153 dtd March 26, 1985 Eberline provided their response to our questions. The thrust of their responses can be summarized:
- 1. Eberline concurred that, on face value, it was improper to compensate for attenuation and shielding and bremmstrahlung. Eber11ne noted however, that this was done out of a concern that basing the efficiency on the Xe-133 response alone would underestimate the efficiency and cause overestimations of sample stream activity, and the converse for Kr85. The attenuation correction resulted in an efficiency of about 1.1E-2 CPM-cc/Bq-MeV and the bremmstrahlung correction resulted in a similar value. In as much as the detector of interest was energy compensated, it appeared appropriate to use this nominal value.
Note the units of the ef ficiency. These units were arrived at by mulitiplying the observed CPM /uCi/cc by the energy constant for Kr85 or Xel33 (as appropriate) in units of uCi/Bq-MeV. To obtain the efficiency of any nuclide of interest one simply divided by the energy constant for the nuclide of interest.
- 2. The multiply by two correction was designed to compensate for the divide by two signal processing that occurs in the interface box in providing a detector efficiency (ie: no electronic processing).
Eberline concurred with our assumption that we should use the uncorrected (ie: no multiply) efficiency in establishing the parameter files for the SA9 channels.
- 3. Eberline noted that the nominal efficiency handling might not be best for each application.
In light of the above, it was decided that the best approach for BVPS was to base the efficiency for the various nuclides on the nominal efficiency, but to use the actual reported Kr85 and Xel33 efficiencies for those two nuclides.
This decision was made on the realization that the majority of the BVPS source terms are high in either Kr85, Xel33 or both. Using the nominal efficiencyforthesenuclideswould)nderestimatetheXel33activityand overestimate the Kr85 activity.
TRANSFER CALIBRATIONS As mentioned above, there have been some difficulties regarding the transfer calibrations and the similar periodic calibrations performed at BVPS. These problems arise out of difficulty in establishing a reproduceable geometry and the physical differences between the units. In NDlHPS:0149 and ND1HPS:0156 K. Winter recommended a change in the calibration MSP to provide a more reproduceable geometry. While these proposed revisions would result in some i
AUd.
y g Emwonmental & Wd Se8 sty ERS SFL-85-031 Attachment 1 pe,e 3 of 16 loss of traceability, the proposed procedures are acceptable for the intended usa -- checking on the continued validity of the factory calibration. It would not be appropriate to base any efficiencies on the results of these periodic calibrations since there would be not direct link to the prototype ,
gas calibration. The ideal situation would be to establish the proposed '
methods as the transfer calibration when the gas calibration is done on the SPING units.
The following free-air exposure results were noted for the BVPS SPING units:
RM-VS-109 48.6 CPM /mR/Hr
+
RM-VS-110 60.1 CPM /mR/Hr g c, , gg RM-GW-109 48.5 CPM /mR/Hr l
In that the factory prototype transfer calibration result was 51.5 CPM, two l of the BVPS units have response close to that of the factory unit, while one unit is much more sensitive.
i For the original SA9 stand-alone units, Eberline repeated one step of the Kr-85 prototype calibration. As reported in Eberline drawing 12000-01A, the response of the prototype unit to the Kr85 vial was 2254.8 CPM. The j
BVPS production units had the following response:
! RM-VSil2HR 2140 CPM RM-VSillHR 2194 CPM cq - we ved RM-GW110HD 2190 CPM l
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l l AIR PRESSURE COMPENSATION l
The factory calibration results are reported normalized to 14.7 psia, in use f i
j the sample chambers are under a vacumn. With the reduced pressure comes reduced density, and with reduced density there is less activity per unit value. Without correction, the instrument underestimates the actual release stream activity (assumed to be near 14.7 psia).
I A modification was made to the SPING SA9s to provide for automatic compensatior :
for this condition. A pressure gage notes the pressure and corrects both the mass flow rate and the instrument display (CPM). With regard to the CPM '
reading:
ase Corrected Concentration-Measured Concentration x et r s,p l
am.,anmeiw a -_- y sawy g ERS- SFL 031 Attachment 1 N 4 o' 16 It is true that the BVPS atmospheric pressure is only 14.3 psia (due to increased elevation). However, this correction is concerned with the relativo difference rather than the absolute values.
It is noted that the factory prototypo calibration was normalized to 14.7 psia and the normal BVPS environs value is 14.3 psia, and that this difference results in a slight error in the officiency value. However, the automatic pressure correction will compensate for this.
For the standalone SA9s, there is no automatic pressure compensation, it is therefore necessary to include a nominal corection in the efficiency value.
During the period 11/1/84 through 2/28/85, there woro readings taken from installed vacumm gages on each SA9/SA10 combinction. The number of observations, 4 the standard deviation, and the mean of the vacumm for each channel woro:
---in Hg.--------
Monitor Observ. Mean S.D. ._
VS111 352 7.49 1.36 VSil2 358 4.55 .54 GW110 358 4.18 42 l In applying the correction, we need to recognize that the response of the i instrument will be lower than it should be, or that in reality more uC1/cc '
l is released than is indicated. Thus, we need to decreaso CPM-cc/Bq-MoV and increase Bq-MeV/ CPM-cc efficiencies. Also, the pressure noted above is ,
psig, 10: the difference from atmospheric pressure. Also, to be conservativo, we will add one 5.0. value to the mean and uso the sum as the nominal pressure.
Corrected CPM-cc/Bq-MeV = CPit-cc/Bq-MoV x 04.3 - n He * .49 1
- 3 l Corrected Bq-MeV/ CPM-cc - Bq-floV/ CPM-cc x (14.3 n Hg * .491))
l l For the BVPS SA9s in ili CPM-cc/Bq-MeV Bq-MeV/ CPM-cc egg & I S.D. Multiplier Multiplier VSill 7.49 t 1.36 0.696 1.437 VS112 4.55 + 0.54 0.825 1.212 ,
GW110 4.18 + 0.42 0.842 1.188
' fl0TE: Tho use of 14.3 as the constant in these formulao is correct. Although the pressure sensor was calibrated to 14.7 at calibration time, the release was also into 14.7 psta. The calibration gas values were normalized to 14.7. By using 14.3 here, we correct for the difference between the calibration conditions and BVPS conditions. Remember that it is the relative pressure that is of interest -- not the absoluto value.
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Ens- SFL 031 ATTACitMENT 1 pee. 5 of 16 NUCLIOE EFFICIENCIES The tabs to this attachment provide tabulations of the instrument officiencies .
for the SA9 monitors. As noted above.the factory prototype calibration !
provide three off1ctoncios:
Xo133 5.0E-3 CPM-cc/Bq-MeV i Kr85 2.9E-2 CPM-cc/Bq-MeV :
Nominal 1.1E-2 CPM-cc/Bq-MoV Those offtctonctes are at the detector and must bo divided by two to obtain ,
the values appropriate to the SPINGs and the SA9 as road through the CTI.
Thecor[octedofftc1 enc 1osarethon: [
Xo133 2.5E-3 CPM-cc/Bq-MoV Kr85 1.45E-2 CPM-cc/Bq-MeV ,
Nominal 5.5E-3 CPM-cc/Bq-MoV The codo which generated the attached table used the officienclos noted above for Xol33 and Kr85, and calculated the romaining officiencies from the nominal i offtctoney. The offtetency in CPM-cc/Bq-Mov is multiplied by the energy ,
constant for that nuclido to obtain CPM /uC1/cc. The energy constant is found by onorgy MoV x 3.7E4 0,q- ;
uY i This methodology is incorporated in the codo via Efficioney'= (Efftctoney
- CORR) / (Energy
- 3.7E4
- X) !
where Eff1ctoney'is in Bq-MoV/ CPM-cc l Eff tetency is uCt/cc/ cpm l is the relativo officiency(from transfer caltb) and pressuro CORR correction (SA9s only) l Energy is total MeV por disintegration l X ts an todino correction. set to 0.05 for todino nuclidos and 1.0 for noble gasos. Increases calculated releaso to account for l the charcoal cartridge upstream in tho samplo piping. Note that :
this is not a correction for the main filtor banks--just the filter internal to the SPING (nearby on SA9).
The offtctoney in CPM /uCt/cc ts the inverso of uCt/cc/ CPM. .
t Also in the printout is a relativo of f tetency. This valuo is used in tho !
MIDAS softwaro to normaltto the single overall offtciency for the various ,
nuclidos in the sample stroom. Since the XoI33 value is used for this ;
purpose in MIDAS, the relative valuos are reforonced to the uCt/cc/ cpm [
values for Xol33. To find the offtetency of another nuclido multiply its
, relativo value by tho Xo133 officiency in uC1/cc/ cpm Xo133 uC1/cc/ cpm x (x.xxxx [ h c PM ) X uCt/cc/ CPM l
Attachment I
._ a r _.g EMS-5fL-85-031 w 6 16 Since the officiency units are Bq-MeV/cc-CPM. the correction term values for each monitor are found as follows:
VS-109 51.5/48.6 - 1.06 VS-110 51.5/60,1 = 0.86 GW-109 51.5/48.5 - 1.06 VS1126tR 2254.8/2140 = 1.05 x 1.212 = 1.28 VS1116tR 2254.8/2194 = 1.03 x 1.437 - 1,48 GW110HR 2254.8/2190 - 1.03 x 1.188 - 1.22 (prossuro corr.)
for the purposes of hand proceduros, averano values are desired:
1.06 + 0.86 + 1.06 = 2.98/3 = 1.0 SPING Channel 9 1.28 + 1.48 + 1.22 = 3.98/3 = 1.33 SA9's iho current workshoot for both channel 9 and SA9 will have to be revised to account for the difforonce in responso.
ERS-SFL-85-031 l
[ . Attachment 1 7 /4 i l
l Tab 1 i
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CHANNEL: RM-VS-109 and RM-GN-109 SPING monitors CMf COARECTION FACTOR: 1.060 {
GAMMA EFFICIENCY EFFICIENCY RELATIVE l NUCLIDE MeV/ dis uCi/cc/ cpm cpm /uC1/cc uCi/cc/ cpm
..................................................................._ l Kr83m 0.0026 2.0032E+00 4.9920E-01 7.919 (
Kr85m 0.1577 3.3027E-02 3.0278C+01 0.131 l Kr85 0.0022 8.9814E-01 1.1134E+00 3.550 Kr87 0.7931 6.5670E-03 1.5220E+02 0.026 Kr88 1.9546 2.6646E-03 3.7528E+02 0.011 '
Kr89 1.8345 2.8391E-03 3.5222C+02 0.011 Kr90 1.2715 4.0962E-03 2.4413C+02 0.016 l
Xo131m 0.0201 2.5912E-01 3.8592C+00 1.024 '
Xo133m 0.0415 1.2550E-01 7.9600E+00 0.496 Xo133 0.0453 2.5297E-01 3.9531C+00 1.000 i Xc135m 0.4307 1.2093E-02 8.2695C+01 0.048 l Xo135 0.2479 2.1010E-02 4.7597E+01 0.083 ,
Xo137 0.1877 2.7748E-02 3.6038E+01 0.110 [
Xo138 1.1258 4.6263C-03 2.1615C+02 0.018 t 1131 0.3811 2.7333E-01 3.6586E400 1.080 l 1132 2.2913 4.5462C-02 2.1997C+01 0.180 l 1133 0.6067 1.7169E-01 5.8243E+00 0.679 I 1134 2.6253 3.9670E-02 2.5203E+01 0.157 1135 1.5751 6.6133C-02 1.5121Et01 0.261 l
IODINE cpm /uct/cc values decreased, uCl/cc/ cpm values increased ;
to account f or 0.90% upstream flitration in SPING itself. Nominal officiency=1.810E2 bq-MeV/cc-epm except for Xe133=4E2 f cnd Kr85a6.097El bq-MeV/cc-epm 1
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ERS-SFL-85-031 Attachmsnt 1 fkA i Tab 1 l r
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CHANNEL: RM-VS-110 ch9 SPING monitor $N T CORRECTION FACTOR: 0.860 I
GAMMA EFFICIENCY EFFICIENCY RELATIVE NUCLIDE MeV/ dis uC1/cc/ cpm cpm /uCi/cc uC1/cc/ cpm
- Kr83m 0.0026 1.6252E+00 6.1529E-01 7.919 l l Kr85m 0.1577 2.6795E-02 3.7320E+01 0.131 Kr85 0.0022 7.2868E-01 1.3724E+00 3.550 Kr87 0.7931 5.3280E-03 1.0769E+02 0.026 Kr88 1.9546 2.1619E-03 4.6256E+02 0.011 1
Kr89 1.8345 2.3034E-03 4.3414E+02 0.011 Kr90 '
1.2715 3.3233E-03 3.0090E+02 0.016 l Xo131m 0.0201 2.1023E-01 4.7567E+00 1.024
]
Xo133m 0.0415 1.0182E-01 9.8210E+00 0.496 Xo133 0.0453 2.0524E-01 4.8724E+00 1.000 l Xo135m 0.4307 9.8111E-03 1.0193E+02 0.048 Xo135 0.2479 1.7046E-02 5.8666E+01 0.083 i
Xo137 0.1877 2.2513E-02 4.4419E+01 0.110
] Xo138 1.1258 3.7534E-03 2.6642E+02 0.018
! 1131 0.3811 2.2176E-01 4.5094E+00 1.080
! 1132 2.2913 3.6884E-02 2.7112E+01 0.180
- 1133 0.6067 1.3930E-01 7.1788E+00 0.679 3.2192E-02 3.1064E+01 0.157 1134 2.6253
, 1135 1.5751 5.3655E-02 1.8637E+01 0.261 i
IODINE cpm /uct/cc values decreased, uCi/cc/ cpm values increased to account for 0.95% upstream filtration in SPING ltself. Nominal officiency=1.818E2 bq-MeV/cc-cpm except for Xe133=4E2 i cnd Kr05=G.897El bq-MeV/cc-cpm i e I
i i
i
ERS-SFL-85-031 9[l0 Attachment 1 Tab 1 CHANNEL: Ch9 SPING average of US109,VS110,GW109 CORRECTION FACTOR: 1.000 GAMMA EFFICIENCY EFFICIENCY RELATIVE NUCLIDE MeV/ dis uCi/cc/ cpm cpm /uCi/cc uCi/cc/ cpm Kr83m 0.0026 1.8898E+00 5.2915E-01 7.919 Kr 8&n 0.1577 3.1157E-02 3.2095E+01 0.131 Kr85 0.0022 8.4730E-01 1.1802E+00 3.550 Kr87 0.7931 6.1953E-03 1.6141E+02 0.026 Kr88 1.9546 2.5138E-03 3.9780E+02 0.011 Kr89 1.8345 2.6784E-03 3.7336E+02 0.011 Kr90 1.2715 3.8643E-03 2.5878E+02 0.016 Xo131m 0.0201 2.4445E-01 4.0908E+00 1.024 Xo133m 0.0415 1.1840E-01 8.4461E+00 0.496 Xo133 0.0453 2.3865E-01 4.1902E+00 1.000 Xo135m 0.4307 1.1408E-02 0.7656E+01 0.048 Xo135 0.2479 1.9821E-02 5.0453E+01 0.083 X0137 0.1877 2.6177E-02 3.8201E+01 0.110 Xo138 1.1258 4.3645E-03 2.2912E+02 0.010 l 1131 0.3811 2.5786E-01 3.8781E+00 1.080 l 1132 2.2913 4.2888E-02 2.3316E+01 0.180 1133 0.60G7 1.6198E-01 6.1730E+00 0.679 1134 2.6253 3.7432E-02 2.6715E+01 0.157 1135 1.5751 6.2390E-02 1.6028E+01 0.261 10 DINE cpm /uCi/cc values decreased, uCi/cc/ cpm values increased to account for 0.95% upstream filtration in SPING itself. Nominal officiency=1.010E2 bq-MeV/cc-cpm except for Xe133=4E2 cnd Kr85=6.097El bq-MeV/cc-cpm
ERS-SFL-85-031 Attachmsnt 1
/N Tab 1 CHAPNEL : RM-VS-111HR SA9 monitor CORRECTION FACTOR: 1.480 GAMMA EFFICIENCY EFFICIENCY RELATIVE NUCLIDE MeV/ dis uCi/cc/ cpm cpm /uCi/cc uCi/cc/ cpm Kr83m 0.0026 2.7969E+00 3.5754E-01 7.919 Kr85m 0.1577 4.6113E-02 2.1686E+01 0.131 Kr85 0.0022 1.2540E+00 7.9745E-01 3.550 Kr87 0.7931 9.1691E-03 1.0906E+02 0.026 Kr88 1.9546 3.7205E-03 2.6878E+02 0.011 Kr89 1.8345 3.9640E-03 2.5227E+02 0.011 Kr90 1.2715 5.7192E-03 1.7485E+02 0.016 Xo131m 0.0201 3.6179E-01 2.7640E+00 1.024 Xo133m 0.0415 1.7523E-01 5.7068E+00 0.496 Xo133 0.0453 3.5320E-01 2.8312E+00 1.000 Xo135m 0.4307 1.6884E-02 5.9227E+01 0.048 Xo135 0.2479 2.9334E-02 3.4090E+01 0.083 Xc137 0.1877 3.8743E-02 2.5811E+01 0.110 Xo138 1.1258 6.4594E-03 1.5481E+02 0.018 1131 0.3811 3.8163E-01 2.6203E+00 1.000 1132 2.2913 6.3475E-02 1.5754E+01 0.180 1133 0.6067 2.3972E-01 4.1715E+00 0.679 1134 2.6253 5.5399E-02 1.8051E+01 0.157 1135 1.5751 9.2337E-02 1.0830E+01 0.261 IODINE cpm /uCi/cc values decreased, uCi/cc/ cpm values increased to account for 0.95% upstream filtration in SPING itself. Nominal officiency=1.818E2 bq-MeV/cc-cpm except for Xe133=4E2 cnd Kr85=6.897El bq-MeV/cc-cpm I
.i x dlw ERS-SFL-85-031 '
Attachmsnt 1 Tab 1 .
a CHAPNEL: RM-US-112HR EA9 moni' tor
~ CORRECTION FACTOR: 1.280 GAMMA i EFFICIENCY EFFICIENCY RELATIVE NUCLIDE Meg / dis uCi/cc/ cpm cpm /uCi/cc uCi/cc/ cpm
,---r---------------------------------------------
Kr83m 0.0026 2.4190E+00 4.1340E-01 7.919 Kr85m 0.1577 3.9881E-02 2.5074E+01 0.131 Kr85 0.0022 1.0845E+00 9.2205E-01 3.550 Kr87 0.7931 7.9300E-03 1.2610E+02 0.026 Kr88 1.9546 3.2177E-03 ,3.1078E+02 0.011 Kr89
- 1.8345 3.4283E-03 2.9169E+02 0.011 Kr90 1.2715 ' 4.9464E-03 2.0217E+02 0.016
-Xo131m 0.0201 3.1290E-01 3.1959E+00 1.024 Xo133m 0.0415 1.5155E-01 6.5985E+00 0.496 Xo133 0.0453 3.0547E-01 3.2736E+00 1.000 Xc135m 0.4307 1.4603E-02 6.8481E+01 0.048 Xo135 0.2479 2.5370E-02 3.9416E+01 0.083 Xo137 0.1877 3.3507E-02 2.9844E+01 0.110 Xo138 1.1258 5.5865E-03 1.7900E+02 0.018 1131 0.3811 3.3006E-01 3.0298E+00 1.080 1132 2.2913 5.4897E-02 1.8216E+01 0.180 1133 0.6067 2.0733E-01 4.8233E+00 0.679 1134 2.6253 4.7913E-02 2.0871E+01 0.157 1135 1.5751 7.9859E-02 1.2522E+01 0.261 .,
IODINE cpm /uCi/cc values decreased, uCi/cc/ cpm values increased to account for 0.95% upstream filtration in SPING itself. Nominal officiency=1.818E2 bq-MeV/cc-cpm except for Xe133=4E2 end Kr85=6.897El bq-MeV/cc-epm '
t I
9
f .
ERS-SFL-85-031 l b Attachment 1 Tab 1 I
CHAPNEL: RM-GH-110HR SA9 monitor CORRECTION FACTOR: 1.220 GAbt% EFFICIENCY EFFICIENCY RELATIVE NUCLIDE MeV/ dis uCi/ce/ cpm cpm /uCi/cc uCi/cc/ cpm Kr83m 0.0026 2.3056E+00 4.3373E-01 7.919 Kr85m 0.1577 3.8012E-02 2.6300E+01 0.131 Kr85 0.0022 1.0337E+00 9.6740E-01 3.550 Kr87 0.7931 7.5583E-03 1.3230E+02 0.026 Kr88 1.9546 3.0669E-03 3.2607E+02 0.011 Kr89 1.8345 3.2676E-03 3.0603E+02 0.011 Kr90 1.2715 4.7145E-03 2.1211E+02 0.016 Xo131m 0.0201 2.9823E-01 3.3531E+00 1.024 Xo133m 0.0415 1.4445E-01 6.9230E+00 0.496 Xo133 0.0453 2.9115E-01 3.4346E+00 1.000 Xo135m 0.4307 1.3918E-02 7.1849E+01 0.048 Xo135 0.2479 2.4181E-02 4.1355E+01 0.083 Xo137 0.1877 3.1937E-02 3.1312E+01 0.110 Xo138 1.1258 5.3246E-03 1.8781E+02 0.018 1131 0.3811 3.1459E-01 3.1788E+00 N 1.080 1132 2.2913 5.2324E-02 1.9112E+01 0.180 1133 0.6067 1.9761E-01 5.0605E+00 0.679 1134 2.6253 4.5667E-02 2.1898E+01 ,0.157 1135 1.5751 7.6116E-02 1.3138E+01 0.261 e
IODINE cpm /uCi/cc values decreased, uCi/cc/ cpm values incrdased to account for 0.95% upstream filtration in SPING itself. ' Nominal officiency=1.818E2 bq-MeV/cc-cpm except for Xe133=4E2 cnd Kr85=6.897El bq-MeV/cc-cpm i \ I l 4 e
/
- ERS-SFL-85-031 Attachmsnt 1 t $
Tab 1
(
CHANNEL: average of SA9 US112,VS111,GH110 CORRECTION FACTOR: 1.330 GAMMA EFFICIENCY EFFICIENCY RELATIVE NUCLIDE MeV/ dis uCi/cc/ cpm cpm /uCi/cc uCi/cc/ cpm Kr83m 0.0026 2.5135E+00 3.9786E-01 7.919 Kr85m 0.1577 4.1439E-02 2.4132E+01 0.131 Kr85 0.0022 1.1269E+00 8.8739E-01 3.550 Kr87 0.7931 8.2398E-03 1.2136E+02 0.026 Kr88 1.9546 3.3434E-03 2.9910E+02 0.011 Kr89 1.8345 3.5623E-03 2.8072E+02 0.011 Kr90 , 1.2715 5.1396E-03 1.9457E+02 0.016 9
Xc131m 0.0201 3.2512E-01 3.0758E+00 1.024 Xo133m 0.0415 1.5747E-01 6.3504E+00 0.496 Xo133 0.0453 3.1740E-01 3.1506E+00 1.000 l
Xo135m' O.4307 1.5173E-02 6.5907E+01 0.048 Xo135 0.2479 2.6361E-02 3.7934E+01 0.083 Xo137 0.1877 3.4816E-02 2.8722E+01 0.110 Xo138 1.1258 5.8047E-03 1.7227E+02 0.018 1131 0.3811 3.4295E-01 2.9158E+00 1.080 1132 2.2913 5.7042E-02 1.7531E+01 0.180 1133 0.6067 2.1543E-01 4.6419E+00 0.679-1134 2.6253 4.9785E-02 2.0087E+01 0.157 1135 1.5751 8.2979E-02 1.2051E+01 0.261 IODINE cpm /uCi/cc values decreased, uCi/cc/ cpm values increased to cccount for 0.95% upstream filtration in SPING itself. Nominal officiency=1.818E2 bq-MeV/cc-cpm except for Xe133=4E2 cnd KrG5=6.897El bq-MeV/cc-cpm
d.
3tp5 M M Emironmental & Resologacal Safety ERS- SFL-85 031 Attachment 2 *1 *' 9 EBERLINE SPING Ch7 NOTE: Much of the data processing performed on the data for this monitor type is as described in Attachment 1 of this package.
The discussion in this package will be limited to establishing the nominal efficiency values, the BVPS corrections, and the nuclide specific values calculated as explained in Attachment 1 DISCUSSION The Ch 7 GM noble gas detector in the SPING is similar in construction to the Ch 9 (and SA9) detectors with one major exception: In the Ch 7 detectors, the detector is directly exposed to the sample gas, whereas in the Ch 9 (and SA9) detectors, the detector looks at a sample tube containing the sample gas. There is a conflict in data for these detectors:
Xe133 Kr85 Nominal Check CPM-cc/Bq-MeV CPM-cc/Bq-MeV CPM-cc/Bq-MeV Source l
New SPING technical l l
Manual (with Mass i flow change) 0.204 0.204 BVPS calibration sheets from factory ,
transfer calibration 0.415 0.415 37.2 l EIC 12000-38 0.205 0.307 45.2 l
l EIC 12000-23 0.241 0.366 45.9 To our knowledge there has been no change in the monitor configuration. The EIC 1200 package decribes the results of a field calibration at the l New Brunswick plant. In as much as the factory calibrations have been on the I same prototype unit, it is reasonable to assume that the EIC-12000-3B data are appropriate to our site, even though the data were revised in a later re-calibration subsequent to the shipment of the BVPS units.
A review of that package notes that the nominal Xe133 response to be 0.410 when corrected for the divide by two circuitry. As discussed in Attachment 1, the uncorrected value is appropriate to use at BVPS. It appears that the reported 0.415 value is indeed a corrected value and is therefore in error.
Thus, for the BVPS Ch 7 units, a nominal value will be obtained by averaging the Xe133 and Kr85 responses, and the Xel33 and Kr85 values will be used directly for those nuclides. For the check source, the difference in values is undoubtedly the function of the inability to obtain a reproduceable geometry in the free air exposure that is done. We will use the 45.2 value.
The EIC 12000-23 calibration was called a calibration check and the conclusion of the package noted the close correlation to the primary calibration (12000-3B). Thus, these values will not be used.
- m ynen uw
4.
7 4T g Ermronmental a Radknogical Safety ERS- SFL-85 031 Attachment 2 pag. 2 or 9 The BVPS factor transfer calibrations noted:
VS109 46.5 CPM /mr/hr GW109 39.4 CPM /mr/hr VS110 39.6 CPM /mr/hr Taking VS109 as an example, this monitor displayed a higher response than the factory prototype unit (45.2 CPM /mr/hr). Thus, it is more efficient, its CPM-cc/Bq-MeV value would be higher, and its Bq-MeV/cc-CPM value would be lower. Thus, the correction will be:
1 VS109 45.2/46.5 x Bq-MeV/cc-CPM = 0.972 x Bq-MeV/cc-CPM i GW109 45.2/39.4 x Bq-MeV/cc-CPM = 1.147 x Bq-MeV/cc-CPM VS110 45.2/39.6 x Bq-MeV/cc-CPM = 1.141 x Bq-MeV/cc-CPM
! The Ch 7 detector response is automatically corrected for pressure differential by the SPING microprocessor.
4 The efficiency values used in code are:
Xe133 0.205 CPM-cc/Bq-MeV = 4.878 Bq-MeV/cc-CPM Kr85 0.307 CPM-cc/Bq-MeV = 3.257 Bq-MeV/cc-CPM Nominal 0.256 CPM-cc/Bq-MeV 4.068 Bq-MeV/cc-CPM In as much as an average value is needed for the EPP/IP-2.6.1 worksheets, an additional case will be run using:
0.972 + 1.147 + 1.141 = 3.26/3 = 1.087 x Bq-MeV/cc-CPM
+ r<es Eic Ipoco -3B
ERS-SFL-85-031 Attachment 2 Tab 1 CHANNEL: Eberline SPING Ch7 US109 CORRECTION FACTOR: 0.972 GAMMA EFFICIENCY EFFICIENCY RELATIVE NUCLIDE MeV/ dis uCi/cc/ cpm cpm /uCi/cc uCi/cc/ cpm KrS3m 0.0026 4.1103E-02 2.4329E+01 14.530 Kr85m 0.1577 6.7766E-04 1.4757E+03 0.240 Kr85 0.0022 3.8892E-02 2.5712E+01 13.748 Kr87 0.7931 1.3475E-04 7.4213E+03 0.048 Kr88 1.9546 5.4675E-05 1.8290E+04 0.019 Kr89 1.8345 5.8254E-05 1.7166E+04 0 021 Kr90 1.2715 8.4048E-05 1.1898E+04 0.030 Xe131m 0.0201 5.3168E-03 1.8808E+02 1.879 Xo139m 0.0415 2.5751E-03 3.8833E+02 0.910 Xe133 0.0453 2.8288E-03 3.5350E+02 1.000 Xe135m 0.4307 2.4813E-04 4.0302E+03 0.088 Xe135 0.2479 4.3109E-04 2.3197E+03 0.152 Xs137 0.1877 5.6935E-04 1.7564E+03 0.201 Xe138 1.1258 9.4926E-05 1.0535E+04 0.034 1131 0.3811 5.6084E-03 1.7830E+02 1.983 1132 2.2913 9.3281E-04 1.0720E+03 0.330 1133 0.6067 3.5229E-03 2.8386E+02 1.245 1134 2.6253 8.1414E-04 1.2283E+03 0.288 1135 1.5751 1. 3570 E-03 7.3694E+02 0.480 IODINE cpm /uCi/cc values decreased, uCi/cc/ cpm values increased to account for 0.95% upstream filtration in SPING itself. Nominal efficiency =4.068 bq-MeV/cc-epm except for Xe133=4.878 and Kr85=3.257 bq-MeV/cc-cpm
4 ERS-SFL-85-031 Attachment 2
+ Tab 1 CHANNEL: Eberline SPING Ch7 US110 CORRECTION FACTOR: 1.141 RELATIVE GAMMA EFFI CI ENCY EFFICIENCY NUCLIDE MeV/ dis uCi/cc/ cpm cpm /uCi/cc uCi/cc/ cpm Kr83m 0.0026 4.8249E-02 2.0726E+01 14.530 Kr85m 0.1577 7.9549E-04 1.2571E+03 0.240 Kr85 0.0022 4.5654E-02 2.1904E+01 13.748 Kr87 0.7931 1.5817E-04 6.3221E+03 0.048 Kr88 1.9546 6.4181E-05 1.5581E+04 0.019 Kr89 1.8345 6.8383E-05 1.4624E+04 0.021 Kr90 1.2715 9.8662E-05 1.0136E+04 0.030 Xo131m 0.0201 6.2412E-03 1.6023E+02 1.879 Xc133m 0.0415 3.0229E-03 3.3081E+02 0.910 Xs133 0.0453 3.3207E-03 3.0114E+02 1.000 Xo135m 0.4307 2.9127E-04 3.4333E+03 0.088 Xa135 0.2479 5.0604E-04 1.9761E+03 0.152 XG137 0.1877 6.6834E-04 1.4962E+03 0.201 Xo138 1.1258 1.1143E-04 8.9742E+03 0.034 1131 0.3811 6.5835E-03 1.5190E+02 1.983 1132 2.2913 1.0950E-03 9.1324E+02 0.330 I133 0.6067 4.1354E-03 2.4181E+02 1.245 1134 2.6253 9.5569E-04 1.0464E+03 0.288 1135 1.5751 1.5929E-03 6.2779E+02 0.480 IODINE cpm /uCi/cc values decreased, uCi/cc/ cpm values increased to account for 0.95% upstream filtration in SPING itself. Nominal officiency=4.068 bq-MeV/cc-cpm except for Xe133=4.878
- nd Kr85=3.257 bq-MeV/cc-cpm
)
i l
n
LRS-SFL-85-031 '
Attachm nt 2 Tab 1 1
CHANNEL: Eberline SPING Ch7 GW109 CORRECTION FACTOR: 1.147 GAMMA EFFICIENCY EFFICIENCY RELATIVE NUCLIDE MeV/ dis uCi/cc/ cpm cpm /uCi/cc uCi/cc/ cpm Kr83m 0.0026 4.8503E-02 2.0617E+01 14.530 Kr85m 0.1577 7.9967E-04 1.2505E+03 0.240 Kr85 0.0022 4.5894E-02 2.1789E+01 13.748 Kr87 0.7931 1.5901E-04 6.2891E+03 0.048 Kr88 1.9546 6.4519E-05 1.5499E+04 0.019 Kr89 1.8345 6.8742E-05 1.4547E+04 0.021 Kr90 1.2715 9.9180E-05 1.0083E+04 0.030 Xe131m 0.0201 6.2740E-03 1.5939E+02 1.879 Xe133m 0.0415 3.0387E-03 3.2908E+02 0.910 Xo133 0.0453 3.3381E-03 2.9957E+02 1.000 XG135m 0.4307 2.9280E-04 3.4153E+03 0.088 Xo135 0.2479 5.0871E-04 1.9658E+03 0.152 Xo137 0.1877 6.7186E-04 1.4884E+03 0.201 Xs138 1.1258 1.1202E-04 8.9273E+03 0.034 I131 0.3811 6.6181E-03 1.5110E+02 1.983 1132 2.2913 1.1008E-03 9.0847E+02 0.330 I133 0.6067 4.1572E-03 2.4055E+02 1.245 1134 2.6253 9.6071E-04 1.0409E+03 0.288 1135 1.5751 1.6013E-03 6.2450E+02 0.480 IODINE cpm /uCi/cc values decreased, uCi/cc/ cpm values increased to account for 0.95% upstream filtration in SPING itself. Nominal efficiency =4.068 bq-MeV/cc-cpm except for Xe133=4.878 End Kr85=3.257 bq-MeV/cc-cpm
ERS-SFL-85-031 Attachm:nt 2 Tab 1 61 CHANNEL: Average of Eberline SPING Ch7 CORRECTION FACTOR: 1.087 GAMMA EFFICIENCY EFFICIENCY RELATIVE NUCLIDE MeV/ dis uCi/cc/ cpm cpm /uCi/cc uCi/cc/ cpm Kr83m 0.0026 4.5966E-02 2.1755E+01 14.530 Kr85m 0.1577 7.5784E-04 1.3195E+03 0.240 Kr85 0.0022 4.3493E-02 2.2992E+01 13.748 Kr87 0.7931 1.5069E-04 6.6362E+03 0.048 Kr88 1.9546 6.1144E-05 1.6355E+04 0.019 Kr89 1.8345 6.5146E-05 1.5350E+04 0.021 Kr90 1.2715 9.3992E-05 1.0639E+04 0.030 Xo131m 0.0201 5.9458E-03 1.6818E+02 1.879 Xe133m 0.0415 2.8798E-03 3.4725E+02 0.910 Xs133 0.0453 3.1635E-03 3.1610E+02 1.000 Xs135m 0.4307 2.7748E-04 3.6038E+03 0.088 Xc135 0.2479 4.8209E-04 2.0743E+03 0.152 Xc137 0.1877 6.3671E-04 1.5706E+03 0.201 Xc138 1.1258 1.0616E-04 9.4200E+03 0.034 I131 _
0.3811 6.2719E-03 1.5944E+02 1.983 1132 2.2913 1.0432E-03 9.5861E+02 0.330 1133 0.6067 3.9397E-03 2.5383E+02 1.245 I134 2.6253 9.1046E-04 1.0983E+03 0.288 I135 1.5751 1.5175E-03 6.5898E+02 0.480 IODINE cpm /uCi/cc values decreased, uCi/cc/ cpm values increased to account for 0.95% upstream filtration in SPING itself. Nominal efficiency =4.068 bq-MeV/cc-cpm except for Xe133=4.878 and Kr85=3.257 bq-MeV/cc-cpm
i ERS-SFL-85-031 1 4 typo EFFIC.CH7 At a hment 2 C23456789 C *=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=* ,
C* EFFIC
- 7 '
C*
- C G This program derives isotopic efficiency data for
- C
- SPING SA9/SA10/SA13 (mid range)
- C *****************************************************
1 C
- Rev History
- C* 1.0 S.F.LaVie VAX-11 version 2/85
- C*
- C *=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*
C C23456789 CHARACTER *6 FN(19)/'Kr83m','Kr85m','Kr85','Kr87',
1 'Kr88','Kr89','Kr90','Xe131m',
2 'Xe133m','Xe133','Xe135m','Xe135',
3 'Xe137','Xe138','I131','I132','I133',
4 'I134','I135'/
REAL*4 ENG(19)/0.0026,0.1577,0,0022,0.7931,1.9546, 1 1.8345,1.2715,0.0201,0.0415,0.0453, 2 0.4307,0.2479,0.1877,1.1258,0.3811, 3 2.2913,0.6067,2.6253,1.5751/
DIMENSION EFF2(19),EFF3(19),REL(19)
CHARACTER *3 P16/'[4w'/,P10/'[0w'/,LPTR/'[5i'/,SCR/'[41'/
INTEGER *2 ESC /27/
CHARACTER *70 DESCRIP 1 FORMAT ('O DESCRIPTION (70 CHARS)')
2 FORMAT (' CORRECTION FACTOR (N.N)')
3 FORMAT ('1 CHANNEL: ' A70,/' CORRECTION FACTOR: ',
1 F7.3) 4 FORMAT (20X,' GAMMA EFFICIENCY ',3X,' EFFICIENCY ',5X, 1 ' RELATIVE' / ' NUCLIDE',10X,' MeV/ dis ' ,1X, 2 'uCi/cc/ cpm',4X,' cpm /uCf/cc',5X,'uCi/cc/ cpm' / 1X,68(1H-))
5 FORMAT (1X,A6,13X,F6.4,2(4X,1PE10.4),6X,0PF7.3) 6 FORMAT (' ')
7 FORMAT ('0 IODINE cpm /uCi/cc values decreased, uCi/cc/ cpm',
1 values increased'/' to account for 0.95%' ,
2 '
upstream filtration in SPING itself. Nominal' /
3 '
efficiency =4.068 bq-MeV/cc-cpm except for Xe133=4.878'/
4 and Kr85=3.257 bq-MeV/cc-cpm ')
8 FORMAT (A70) 9 FORMAT (F10.4) 99 FORMAT (' ' ,A1,A3)
HRITE(6,1)
READ (5,0) DESCRIP WRITE (6,2)
READ (5,9) CORR C
C -----CALCULAT E EFFI CI ENCY C -----EFF2(I)=EFF/(ENG(I)*3.7E4) l I
'Af DuquesneLisit Environmental & Radiological Safety Programs SUBJECT CALC.No: #
Accident Analysis X/Q values ERS SFL-83 015 - l- N -.fi6 REFERENCE ___________---N/A--------------- .
DCP EM JO CO Alara Review OA CATEGORY X@X Nuclear Safety Related O si O ill O Other - -
PURPOSE The purpose of this calculation package is to document the derivation of the X/Q values used in the re-analysis of the DBA, and the analysis of tiie realistic case LOCA. The X/Q values were determined from the 10 meter joint frequency distribution (JFDs) data from the BVPS meteorology tower for the period 1-1-82 to 12-31-82.
The data base included 8260 hourly average readings, including identified calms. This represents a 94.3% collection of available data.
The calculation herein utilizes X/Q values determined through the use of a brief computer code (Attachment 2),'and manual data fitting on log-normal probability paper. The analysis performed is in accordance with the provisions of RG1.145, Abnospheric Dispersion Models for Potential Accident Consequence Assessments at Nuefcar Power Peants"lil .
It is.noted that the anal original SAR analysis (2T ,ysis in thatperformed more current herein differs guidance regulatory from that was performed used. for the 3
2 . A 1 \/#
for the RSC 0C 53/ G h,Ktfew C./23/M hM Mdec 7-174 3 Rev. PREPARED BY / DATE CHECKED BY / DATE NDEPENDENT REVIEW / DATE l DISTRIBUTION Checklist At tachments a DOCUMENT CONTROL lERS-xxxl n rpose WCode List 3 JDSieber gsumptions int . outs a WFWirth 5 JAKosmal Methodology / Derivations Data Sheets sE Il put Data strations a NDTD gg,'sults/Conci '
y rences I a D.K. Yourd j s S.F. La Vie 1 0.J. Miller l l
. \
- CALCULATION ERS SFL-83-015 .L 66 -
- DISCUSSION
~
NOTE: The original attempt to solve this problem involved justification and use of the X0QD0Q code. Although it was possible to justify the use of this code (through careful selection of user options, etc) for accident analyses, even though the code is clearly identified as not being for accident calculations. Card decks were prepared and runs made on the corporate computer. These runs provided X/Q values versus frequency, and X/Q values versus calculated probabilities. A short BASIC code was prepared to take the ordered pairs of X/Q and frequency U- and fit the data using least squares to a log-normal probability plot (necessary since X0QD0Q doesn't evaluate the 0.5%-tile or the 5%-tile
- site average). When this data was run it was noted that the X/Q values
_ were coming out much higher than expected (although comparable to the X0QD0Q results greater than 1%). To evaluate the descrepancy, the ordered pairs were plotted against frequency, and the calculated probability also plotted versus X/Q. The X0QD0Q code incorporates a 2a shif t of the distribution to ensure that an upper bounds is described by the curve solution. Because of the particular choice of wind speed
- groups, the actual data distribution of ten can be characterized as two
_ steep slopes connected by a level plateau. The attempt to fit, by least 20-squares, a smooth curve to this data produces a curve that overshoots the data greatly. This is further compounded by the standard deviation shift. The standard deviation is determined by the difference between the actual data and the fitted data. With the overshoot observed, the
- standard deviation is increased, thus increasing the shif t.
~
_ A close review of the X0QD0Q calculated distributions for several sectors showed this effect. In some sectors, the peak X/Q value occurred, not at 1%-tile (...value of X/Q reached or exceeded by specified frequency...)
but at some intermediate point between the high (supposed) end and the low end.
so The data was thus determined to be invalid. Attachment 1 illustrates the magnitude of the error. Since the overshoot occurred near the desired l 0.5%-tile data, the X/Q values would have been extremely overconservative.
The X0QD0Q data printout is filed in the ERS files with the original and review copies of this package.
~
- 1. REQUIREMENTS 1.1 Regulatory Guide 1.145 fil
}
NOTE: Only the provisions related to ground level releases are co- discussed here as the release is assummed to be ground level
_ for the LOCA.
~
1.1.1 Paragraph 1.1, Meteorological Data Input
.. .nceded fo1 X/Q calculatzmts include wb1dspeed, wbid direction,
- and s tability. . .should .1eptesent liourty avetages per RG1.23 I3%.... ,
- wbtd direction should be classed into 16 sectors.... stability by I delta-T. . . . calms should be assigned value based on startbtg l
i-h <
CALCULATION ERs SFL-83-015 m _g6 3 speed of anemometet... wind direckon daung calms should be assigned .in ptoportion to the directional dhtr.ibution for non-calm...
~
The BVPS meteorological monitoring program complies with the provisions of RG1.23, and provides the data identified above.
The monitoring system records 15-min averages fcr all parameters.
This data is reduced to hourly averages by NUS Corporation and
- joint frequency data provided. The JFD data was written into the code used herein (Attachment 2 lines 230-370). The first n_ wind speed group is reserved for calms. Thus, there is no data for the first group. Hours of calm are assigned in line 102.
Also, the JFD data showed no occurences of wind speed group 7.
To reduce array size, WS=7 is not assigned.
- Calms are assigned using an algorithm paraphrased from a similar
_ algorithm in pat /AN:An Abnospiteric Dbpetsion Program For Euatuab.ng Design Basb Acciderttat Retcases of Radioactive Matenats from Nuclear Power Stations,IM and incorporated as lines 590-690. The input data is converted into percent data from the input hours.
20- The hourly average and percent distribution matrices are printed (or bypassed: lines 405,805). A review of these matrices against similar matrices in the X0QD0Q run on the same data showed 1::1 correlation.
}
Average wind speed for each wind speed group was determined from the stated maximum speed in each group. This data was
- calculated outside of the code and entered as a data array.
Attachment 3 tabulates the wind speed array, and other input constants to the code.
1.1.2 Paragraph 1.2 Determination of Distances 30-
_ ...for eacli sector, X/Q values for eacit significant retease poirtt should be calculated at an apptoptiate exclusion area boundary
~
distance and outet LPZ boundary...the dhtance for the EAB or LPZ sitould be the mistanum dhtance from the stack or building penetration wt.kitin a 45 degrce scctor centered on the directicn o f intetest. . . .
As set forth in the BVPS FSARr21, the minimum EAB distance is 610 meters (2000 feet) and the LPZ outer boundary is 3.6 miles (5800 meters). Since the minimum distance applies 360 , the 450 sector provision does not apply. The release of interest
'0-is a stack release (SLCRS). However, this stack does not meet the 2 times adjacent solid structure provision. The stack exit
- is at 47 meters, while the containment is 44 meters. These two
_ assumptions are conservative, in that the owner-controlled area extends beyond the EAB in several sectors and that ground level dispersion is more conservative than elevated releases.
. e.
. CALCULATION ERs.SFL-83-015 po h_6_6_
_ 1.1.3 Paragraph 1.3 Calculation of X/Q at EAB
~
...one hour avetage X/Q are assumed to apply to 0-2 hours...
(guide ptovides formatae) .... evaluate meandet when the wind speed b iess than 6 meters /sec and the stabildy class is 0,E,F, or G. Highet value of expressions 1 and 2 is taken as the X/Q value if meander b not costsidered. If meander h cousidered, Die highet of exptessiorts 1 and 2 is compared to the result of exptession 3, and tute loc: value of this second comparb on used....
19-The formulae provided by RG1.145 and usui cercin are:
~ 1 (1)
X/O U3g(no o + A/2) 1
- X/O Ui g(3no o ) (2) yZ
~
1
=
2
,3- x/Q U nr o (3)
_ 10 yZ Where:
U ig = average windspeed for the wind speed group at 10 meters, m/sec
_ n = 3.14159
~
o = lateral plume spread, in m (values taken Y
from Figure 1, RG1.145 30-Z
= Vertical plume spread, in m (values taken
_ from Figure 2, RGl.145 E = Lateral plume spread with meander and building Y wake correction:
for the EAB ry = May
_ for the LPZ* I = (M-1)o + o Y 7610 Y5800 M = Meander coefficient (from Figure 3, RG1.145)
A = Vertical cross-section of building = nr , where 2
r= 44/2 meters (44 meters is height of building) result rounded to 1600 m2 (equivalent circular area ).
_ *RG1.145 allows credit for meander out to 800 meters. However, to reduce data array requirements, the o array for 610 meters is used. As this results in lower meander correction,Ythe resulting X/Q value is higher.
. CALCULATION ERs- SFL-83-015 ,, 5, 6 6
~
_ The subprogram, CALC, determines the requisite X/Q values using the methodology of the formulae above. Attachment 3 to this package documents the input data arrays.
1.1.4 Paragraph 1.4 Calculation of X/Q at LPZ
~
- ...ko-lwur X/Q values slwuld be calculated for outer LPZ bour1dartj ushtg tite metlwds described for EAB...aut aututuai average slwaid be calculated ush19 metlwds of RG1.111. ..
U- The process described above for the EAB was repeated using input data arrays appropriate to the increased distance.
~
The annual average was determined through the use of a routine included in PAVAN: N. This routine is incorporated as the subprogram ANNUAL in Attachment 2. The formulae used are:
.02032
/
Xg=
RF
- x k (Fijk) U g , go/ + cDZ/w (4) ij LJ J 22-x/g = .02032qp (Fj .h)(1/ (1.732051- U3 o , ,. z . ) ) (5) j ij *1 Where:
k sector poi >tter, i= wind speed pohtter, j stabilitt)
- poirttet
~
x = downwind distance, meters F = frequency, in whole percents (ie: 10% not 0.1)
RF = Terrain recirculation factor. Site specific values
- taken from the X0QD0Q input deck and tabulated in Attachment 3.
c = 0.5 D = Height of building for which wake correction
- applies, in meters (44 meters)
(At this point, it is noted that expressions 1 through 5 are identical to the expressions in X0QD0Q--if the user options for deposition, decay, and depletion were bypassed.)
e W
e 6
w_______-_
. CALCULATION ERS- SFL-83-015 6 d6 1.1.5 Paragraph 2.1.1 EAB Maximum Sector X/Q
...using Inourly X/q data, a cwnutative ptobability distribution of X/Q values sliculd be construeted for eacit af tite 16 sectors....
~
X/Q versus probability of titat value being exceeded...a plot sliculd be draun and a carve draien to form an upper bound of Die
- data points....from tine 16 curves, Die value Dia.t is exceeded
_ 0.5% of Ble total time sitould be selected... Die liigliest of . tite
_ 16 sectors is tite maximum sector X/Q....
U- The computer code listed in Attachment 2, determines the X/Q values using Subroutine CALC and subroutine ANNUAL. The X/Q values from CALC are ordered in subroutine ORDER. ORDER sorts the X/Q values in descending order, combines the frequencies of any X/Q values repeated in a sector, and makes the data available to the subroutine PRNTS. PRNTS prints the ordered X/Q values, their associated frequencies, and the cumulative frequency for that sector.
- These ordered values were then plotted on log-normal distribution
_ graph paper. A curve was fitted to this data, and the 0.5%
X/Q value obtained. As a result of these efforts, it was 20-identified that the maximum 0.5% sector value as 8.9E-4 sec/m3, which occurred in the NW sector. Attachment 4 is the printouts and Attachment 5 is the plots.
_ 1.1.6 Paragraph 2.2.1 Outer LPZ Boundary
~
- ... Sector X/Q values for LPZ sliculd be determined for . tite various time periods ....for a given sector, tite X/Q values sitould be apptoximated by a toga.titlimic intetpotation bettecen die tix Itour sector X/Q and tite annual avetage (8760 Itour) X/Q
- for tite same sector...Itigitest sectot value is selected....
so-
~
Using the methodology previously described, the maximum 0.5%
value was determined to be 9.5E-5 and occurred in the.NW sector.
The associated annual average for this sector was 2.56E-6. This was the maximum annual average at the LPZ. A review of the 0.5% data and the annual average data for all sixteen sectors
- revealed that the highest slope and highest intercept values occurred in this sector. Thus, interpolation for all sectors is not necessary. Attachment 6 tabulates the determination of the the sector X/Q values and attachment 7 provides the plots to detennine the 0.5% values.
4o. PAVANN and X0QD0Q f 51 provide the following algorithm for
_ performing this interpolation:
[ QUOTNT=(Annual Avg X/Q)/(0.5% X/Q)
SLOPE = Ln(QUOTNT)/Ln(8760)
X/Q = (Annual Avg X/Q)*(T/8760)(SLOPE) e
. CALCULATION ERs.SFL-83-015 , J_ ,66_
=
_ SLOPE Ln(2.56E-6/9.5E-5)/Ln(8760)
SLOPE = -0.398 Solving for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> (31 days):
.398 4.15E-5 X/Q (2.56E-6)(8/8760)
=
c- X/Q 24 (2.56E-6)(24/8760).398 = 2.68 E-5 X/Q744 = (2.56E-6)(744/8760)-0.398 6.83E-6 sec/m3
=
l
~
I 1
_ 1.1.7 Paragraph 3 Determination of 5% Overall Site X/Q Value l
- l
- ... Tite X/Q values Diat are exceeded no more utan 5% of tite time l around Die EA8 and around Die LPZ sitould be determined....usittg {
ptevious data a cumulative ptobability plot for att directions combined sitould be consttucted...a plot of XIQ versus ptobability
_ sitoald be made... upper bound curve... Die X/Q value exceeded 5%
,n_ of tlic time is citosen...tinese 5% values sitould be used along )
witli Die annual average sector values to determine tite X/Q for j caelt time period. . . .
The CALC subroutine was modified slightly to determine the X/Q values for all sectors at once. The remainder of the code
_ operated as before and provided a cumulative distribution of da ta . This data was plotted on log-normal paper and the 5%
value determined. For the EAB, this was 7.1E-4 in comparison to the 8.9E-4 for the maximum sector. For the LPZ, the value was 8.0E-5, in comparison to 9.5E-5. Further analysis is not
_ necessary in that the 0.5% values are more conservative. Attach- l 30- ment 8 is the EAB and LPZ printouts and attachment 9 is the plots '
of these data.
1.1.8 Paragraph 4 Selection of X/Q Values to be Used in Evaluations
... tite X/Q values fo1 tlic EAB or LPZ slicaid bc Die maximum sector X/Q or Ric 5% overalt site X/Q values.... direction dependertt
_ data sitould be ptovided. . . .
The 0.5% values are higher anl therefore will be used. This calculation package provides all of the data used in the analysis. In addition, this directional data is summarized 4o- below:
W m
l we W
CALCULATION ERs SFL-83-015 p. 8_ , 6_6_
Direction Dependent Data Summary Downwind ---EAB----- ----LPZ----
Direction 0.5% Avg 0.5% Avg
_ S 8.0E-4 4.7E-6 8.0E-5 1.2E-7 SSW 8.5E-4 4.8E-6 8.4E-5 1.4E-7 SW 8.5E-4 8.3E-6 8.9E-5 2.5E-7 WSW 8.5E-4 1.1E-5 8.6E-5 3.9E-7 10- W 8.4E-4 1.9E-5 9.2E-5 5.0E-7 WNW 8.?E-4 3.8E-5 9.3E-5 1.3E-6
_ NW +8.9E-4+ +7.1E-5+ +9. 5E- 5+ +2. 6 E-6+
NNW 8.9E-4 2.8E-5 9.4E-5 9.3E-7 N 8.4E-4 1.1E-5 9.0E-5 3.5E-7 NNE 7.2E-4 7.5E-6 8.3E-5 2.3E-7 6.7E-4 4.5E-6 7.8E-5 1.5E-7 NE ENE 4.8E-4 4.8E-6 4.4E-5 1.6E-7
_ E 4.3E-4 5.6E-6 3.5E-5 1.3E-7
_ ESE 4.9E-4 4.2E-6 4.3E-5 1.1E-7
~
SE 6.2E-4 4.1E-6 6.8E-5 1.0E-7 SSE 6.4E-4 3.7E-6 4.1E-5 9.1E-8 20-Direction Independent Data Summary EAB LPZ 7.1E-4 8.0E-5
- Maximum Sector Data Summary EAB -LPZ
}
0-2 hrs 8.9E-4 9.5E-5
_ 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ------
4.2E-5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ------
2.7E-5 31 days ------
6.8E-6 m
M M
e M
e e
CALCULATION ERs. SFL-83-015 9 ,66
~
1.2 Standard Review Plan Section 2.3.4 (61 1.2.1 Paragraph II, Acceptance Criteria
....sitould ptovide consetuative estimates of abnospiteric
- transport at apptop11 ate distar es...sitouid ptovide tite
_ foliotaing:
. . . . description o f modet. . .
e- As set forth in RG1.145f il
. . . . . met data us ed. . . .
Source of data identified above. Tables of JFDs included in Attachments 4 and 6.
. . . . discussion o f dif fusion parametets. . . .
As set forth in RG1.145fil
. . . .cummutative ptobability distributions for EAB, LPZ. . .
20- metitods used sitoald be described...
Distributio'ns attached. Methods described above.
. . . . relative concentrations . . . .
Tabulated above.
_ 1.3 Regulatory Guide 1.4 f 71
~
NOTE: RG 1.4 provides a model for determining X/Q for the LOCA analysis, but notes that the model be used until adequate site meteorological data are obtained.
- 1.4 Standard Review Plan Section 15.6.5 Radiological Consequences of LOCArai
[ 1.4.1 Paragraph II Acceptance Criteria
....Tlic acceptabitity of tite X/Q values is determined under SRP Section 2.3.4 r61,
_ METHODOLOGY 40-This calculation involved hand calculations and computer code runs. The computer code was modeled after that of PAVAN f 41, and was briefly described above. A further description of the code follows:
MAIN PROGRAM The main program loads the JFD data in hours and the
_ number of hours per stability class for calms. The code distributes the calms to the 16 sectors and to wind speed group 1 based on the distribution of occurences in WS=2.
'\
z
- f
_o (
. CALCULATION ERs.SFL-83-015 1Q66
~
In this distribution process, the data are converted to percent. The distributions, in hours and then in percent are printed out. Note that the input hour sector designations are based on wind direction, whereas, the designations for the percent table and all further reference
_ are to the downwind sector. The main program then loads )
the arrays necessary for the calculation of X/Q. The main i program calls the following subprograms: j 13)-
- CALL ANNUAL for S=1 to 16 A CALL
_ CALC CALL 20- ORDER I
~
CALL HEADER CALL
_ PRNTS 30- r HEADER Prints the calculation package heading
[ CALC Calculates the X/Q values for each combination of windspeed and stability class with a frequency greater than 0. These values are assigned to an array, as is the value of the frequency for each value. A printline is included as line 12320 for the purposes of code checking.
- In lines 12285,12295, and 12300 this line is bypassed for
_ actual code runs. The subprogram returns:
- ~
XQS(numb) = X/Q for combination " numb" FQS(numb) = frequency (whole percent) for combination " numb" FQT = The total frequency observed in this sector.
TT = maximum number of observed combinations.
e
CALCULATION ERsSFL-83-015 paae lla. _
- Site specific data is entered on line 12040. The distance at which values are calculated is triggered by the local parameter "D", set by the calling program.
PRNTS Prints out the collected data, as ordered pairs of X/Q, frequency of observation (of the distribution as a whole),
- and cumulative frequency for the sector of interest. Also
_ printed are the annual average and the frequency of occurence in that sector.
'3-ORDER ORDER takes the output of CALC and orders the data. Lines 15096 to 15140 is a subroutine which sorts the data by
- ascending XQS(numb) values. The subroutine maintains the association of XQS(numb) to FQS(numb). Lines 15032 to 15046 invert the sort into descending order (highest value first). Lines 15048 to 15094 identify any repeats of XQS() values, combines these into one value, with the FQS()
value increased appropriately. The subprogram returns XQS() and FQS() ordered by XQS value.
_ ANNUAL ANNUAL calculates the annual average X/Q for each sector 20-and returns the results as the array ANAV(S). Line 16100 and Line 16120 provide the site specific values for recirculation.
_ VERIFICATION Hand calculations were performed on the results of the EAB run. The initial run incorporated the 12320 print line. The final runs included herein suppressec this printout in favor of reducing printout. For the LPZ, the printline was used in the SSE sector only. Handcalculations were performed to verify the
- code output. These calculations are filed with the ERS file copy of this 3o_ calculation package. Also, the results were compared to the faulted X0QD0Q run (discussed above). The results obtained herein are higher for WS>4 and stability class <4, but lower for other cases (due primarily to meander correction). The X0QD0Q code uses a polyncmial fit on the o and a curves.
Thus, some differences were to be expected. Theannualaverdge Y calculation for the EAB was checked by hand calculation.
COMPARISON TO PRIOR VALUES The SWEC calculation for the DBA consequence analysis'91used values of 7.8E-4 for the EAB and 5.75E-5 for the LPZ. The NRC SER provided values of 1.3E-3 for the EAB and 1.3E-4 at the LPZ. The NRC, however, based their analysis on l 40- the model provided in RG 1.4'71 l 99
. CALCULAT80N !
@ ERs.SFL-83-015 12 66 REFERENCES
- 1. USi1RC Regulatory Guide 1.145, "AbnospIteric pispersion Modets for Potential Accident Consequence Assessments at Nuclear Power Plants".Rev i
USNRC Regulatory Guide 1.23, "Onsite Meteorological Programs",
to- 4. USNRC fiUPEG/CR-2858, " pat /AN: An Abnospiteric Dispetsion Program for Evaluatity
- Design Basis Accidental Retcases of Radioactive Hatenais from Nacicar Power Stations". November 1982
- 5. USNRC fiUREG/CR-2919, "XOQD0Q: Computer Program for tite Meteorologicat Evaluation of Routine Ef fluent Releases at Nuclear Power Stations".
September 1982.
(Also reviewed was the DLC corporate computer listing of the DLC implementation of this code.)
- 6. USNRC NUREG-0800 Standard Review Plan 2.3.4, "SItort-term Dispersion 23- Estirates for Accidental Abnosplieric Releases".
- 7. USNRC Regulatory Guide 1.4, " Assumptions Used for Evaluating tite Potentxaf Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors".
8.
USNRC fiUREG-0800 Standard Review Plan 15.6.5, " Radiological Consequences of a Design Basis Loss of Coolant Accident including Containment Leakage Contribution".
[ 9. SWEC Calculation Package 11700-RP-012-1, 2, 3, "DBA Titgroid Dose".
30-M e
6 m
M M
M m
W W
W e
d 6
'Af
%ICAL CONTROLSUdit RADIOL SUBJECT CALC. No:
SPING-4 Alarm Setpoints ERS-SFL-86-004 "" T " 1 REFERENCE ----------N/A--------
DCP EM JO CO OTHER Review Category xMkxRsC Review Required O 11 O lll 0 other PURPOSE The purpose of this calculation package is to document the derivation of the administrative and technical specification alarm setpoints used on the Eberline SPING-4 monitors.
This package is an expansion on ERS-SFL-85-032, as it builds upon the emergency action levels established therein. Reference is therefore made to that package for the derivation of the underlying methodology.
This package supercedes the following packages:
ERS-SFL-82-003 SPING -4 Alarm Setpoint Determination ERS-SFL-82-014 SPING-4 Alarm Setpoints 3
2 , t 1 // 16 ,
L u b kr Yh kbucl7$bak J/7/K W 2%W 'Wvi Rev. hREPARED BY / DATE CHECKED hY / DATE APPROVED BY / oATE DISTRIBUTION Checklist At tachments DOCUMFNT CONTROL IERS-xxxl G' Purpose A Code List
[a J A Kosmal [ ptions Print . outs ad Ith ology / Derivations Mta sheets d ng Data d illustrations N NDTD dsults/Conct 5 Calc File V Author S.F. LaVie
- O
,gQ TE A M Radlological Controls Department ERS-SFL-86-004 2 6 DISCUSSION Calculation package ERS-SFL-82-003 established the alarm setpoints for the channel 7 and channel 9 monitors in the SPING system. Since that time, various events have developed that make revision necessary. In summary:
- 1. Calculation package ERS-SFL-85-031 documented the derivation of revised instrument efficiencies for these monitors. These revisions were undertaken to address several advances in our knowledge and understanding of the SPING system, specifically:
- a. Mass flow and pressure correction mechanisms were installed on the three SPING skids to address the concerns of IE Information Notice 82-49,
- b. Correction factors were determined and applied against the efficien-cies for the SA9, SA10, and Victoreen monitors for which automatic flow and pressure corrections were not applied.
- c. Efficiencies were determined for the low range noble gas channel (5).
- d. Some of the original SPING efficiencies were revised on the basis of updated information.
I
- 2. The original alarm setpoints were based on the maximum expected FSAR source term for each effluent pathway. This protocol created problems in that some of the accident source terms used in dose projection procedures could yield offsite doses higher than those associated with maximum expected FSAR source term.
- 3. The X/Q values used in the original alarm setpoint determinations were .
based on the worst observed value in the year previous to the calculation.
In 1983, the accident X/Q value for BVPS was re-determined in support of the re-analysis of the DBA LOCA.
- 4. ERS-SFL-85-032 provided numerical values for the readings on the various effluent monitors that would be a symptom that an EAL might be exceeded.
These values were based on the data above. Some of the values determined in this package were offscale low on the monitor to which they were to apply.
- 5. In 1985, the EAL for radioactive effluent releases was revised downward to 125 mrem /hr whole body and 600 mrem /hr child thyroid.
i This package addresses these considerations.
METHODOLOGY i
The 125 mrem /hr and 600 mrem /hr site boundary dose rate values are based on an
! assumed eight hour release. In that most BVPS postulated accidents do not have a release duration over one hour, this EAL provided a conservative margin allowing for differences in source term, X/Q, and monitor response. These values, when exceeded.would trigger dose projection calculations using
MY w Duquesne @ ERS-SFL-86-004 P***
3 *' 6 Radiological Controts Department actual meteorology. These results would then be compared to the primary 1 rem and 5 rem EALs.
NUREG-0737 required Duquesne Light to identify alarm setpoints for the high range noble gas monitors and to place operability and surveillance requirements for these monitors into the Unit I technical specifications. Since the requisite NUREG-0737 range was covered by channels 7 and 9 in the SPING, only those channels were identified in the technical specification, with a single alarm setpoint per channel pair on each of the three effluent paths. SPING channel 5s, and the SA10 and SA9 noble gas monitors were not addressed, i
It was desired to follow a similar protocol here. However, as noted above, the reading associated with a general emergency release did not come onscale on Channel 7 on the SPING on the ventilation vent and on SLCRS.
In RSC 1-86, the Radiation Safety Subcommittee of the OSC discussed this situation and came to a tentative agreement that calculations would be
- performed to support two alarm setpoints per SPING assembly. This would
! correspond to the ALERT (yellow console warning light) and HIGH (red console warninglight). The basis and meaning of each was decided upon as:
child ALERT Would be based on 125 mr/hr whole body or 600 mr/hr A thyroid at the site boundary, and, signify that "...a general emergency condition might exist if the release continues at it's current rate for l eight hours..." This would be an ADMINISTRATIVELY controlled set point.
HIGH This would be based on 1 R/hr whole body and 5 R/hrthyroid at the site boundary, and, signify that "...a general emergency condition likely exists - perfonn dose assessments...."* This setpoint would be established as the technical specification alarm setpoint for the units (one setpoint each unit).
ALERT and HIGH alarm setpoints might be possible on other SPING channels, and on the SA9/SA10 monitors. These would be administratively controlled.
Since the calculations in ERS-SFL-85-033 are linear in nature, it is possible to extrapolate the 125 mr/hr and 600 mr/hr results of that package to the 1 r/hr and 5 r/hr values needed herein, by multiplying the monitor reading by a factor of 8.0 and 8.3333 respectively. The ventilation vent and SLCRS
- SPING unit alarm setpoints are based on the'LOCA -- no core damage' source mix as being most restrictive, and t % dose rate as most limiting. For
- gaseous waste, the most restrictive source term is the steam generator tube rupture (via air ejector) and the target organ being the whole body.
l Table 1 provides a tabulation of the calculated alarm setpoint values. Table i 2 provides a tabulation of the alann setpoints that can be extracted from Table 1 and its associated calculations.
l
- with the intent of providing protective action recommendations L
MY 74 5 Duquesne @ ERS-SFL-86-004
- 4 *' 6 Radiological Controls Department i RESULTS Table 2 lists the possible alare setpoints, both T/S and administrative.
REFERENCES
- 1. ERS-SFL-82-003 l 2. ERS-SFL-82-014
! 3. ERS-SFL-85-031
- 4. ERS-SFL-85-033
- 5. RSC-01-86 l
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$$%L AP OUQM M 7 T Radiological Controts Department ERS-SFL-86-004 Table 1
- 5 *' 6 CALCULATED ALARM SETPOINT VALUES, CPM l VENTILATION VENT SLCRS GASEOUS WASTE i 85-032 1-br 85-032 1-hr 85-032 1-hr VS109 VS110 GW109 Ch 5 7.05E4 5.88E5 1.07E5 8.92E5 1.38E9 1.10E10 Ch 7 6.64E0 5.53E1 7.98E0 6.65El 1.59E5 1.27E6 Ch 9 1.30E-1 1.00E0 2.26E-1 1.88E0 3.85E3 3.08E4 VS111 VS112 GW110 SA10 7.25E2 6.04E3 1.15E3 9.58E3 2.22E7 1.78E8 SA9 9.29E-2 7.74E-1 1.52E-1 1.27E0 3.34E3 2.67E4 LOCA-THYROID LOCA-THYROID SGTR-WHOLE BODY 600 5 r/hr 600 5 r/hr 125 1 r/hr mr/hr mr/hr mr/hr
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7 45 mg ERS-SFL-86-004 Table 2 page 6 of 6 l Radiological Controts Department PROPOSED ALARM SETPOINT VALUES, CPM l VENTILATION VENT SLCRS GASEOUS WASTE ALERT HIGH ALERT HIGH ALERT HIGH VS109 VS110 GW109 Ch 5 7.0E4 5.8E5 1.1ES 8.9E5 N/A N/A ADMIN ADMIN ADMIN ADMIN Ch 7 N/A 5.5El N/A 6.6El 1.5E5 '
N/A T/S T/S ADMIN Ch 9 N/A N/A N/A N/A 3.8E3 3.1E4 l ADMIN T/S i
VS111 VS112 GW110 SA10 7.2E2 6.0E3 1.1E3 9.5E3 N/A N/A ADMIN ADMIN ADMIN ADMIN f
SA9 N/A N/A N/A N/A 3.3E3 2.6E4 i ADMIN ADMIN LOCA-THYROID LOCA-THYROID SGTR-WHOLE BODY l 600 5 r/hr 600 5 r/hr 125 1 r/hr I cr/hr mr/hr mr/hr l l
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Environmental & Radiological Safety Programs SUBJECT CALC.No:
Geseous Effluent Monitor Emer;ency Action Levels ERS- SFL-85-0 pm--40F W REFERENCE N/A DCP EM JO CO Alara Review OA CATEGORY Nuclear Safety Related O si O ni O Other 4
PURPOSE The purpose of this calculation packase is to document the derivation of the emergency action levels for the gaseous (noble gases only) radiation monitors at the BVPS-1. These emergency action levels (EAls) are based on the activity release which would cause a donwind dose rate (or downwind thyroid commitment) equivalent to one of the emergency action levels.
This re-analysis of the EALs was initiated in order to address the following consider'ations applicable to the current EALs:
- 1. Changes in the accident X/Q values since the initial values were prepared;
- 2. Re-analysis of the monitor efficiencies per ERS-SFL-85-031. (Includes revisions necessary to address pressure differentials per IE Notice 82-49, corrections to vendor data, etc);
- 3. Selection of the most limiting source term from Chapter 14 of the UFSAR j rather than the expected source terms of UFSAR chapter 11; '
- 4. Improvement in documentation of the bases (current EALs were by liUS) J l
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/ s/S/C6 bd ]%w() Jk3/SL 'dl 2fB'sG 3/s Ifri e x h - h [J kud Hel8s Y,DI[# l l
Rev. PREPARED BY / DATE CHECKED BY / DATE APPROVED BY / DATE DISTRIBUTION _ Checklist Attachments e DOCUMENT CONTROL IERS-xxxl O Purpose GT, ode List
, wp O$sumptions O Print . outs a JAKosmal O Methodology / Derivations O Sheets a RMVento y
.. 5 EASchnell ^
D input Data O Itiustrations E ~ N' DM M ppp bP its/ Conce e
O F.J. Pavlechko O' References O
See Addendum on page 8 for R1 k RSP-3-A -1 f
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7Ars Duquetsnet @ ERS- SFL-85-032 P*o* 2 of f[( '
Environmental & Radiolog6 cal Safety l LIMITATION l
The emergency action levels documented herein must be considered as " symptoms" of possible conditions, not as definite prognosis of the condition. These EAls are based on assumptions of source terms and assumptions of dispersion conditions, either of which could be markedly different in an actual release situation from those assumed herein.
For the unusual event and alert EAls, the EAL'is valid only to unplanned releases. It is possible under the provisions o f the Radiological Effluent Technical Specifications (RETS) and the Offsite Dose Calculation Manual (0DCM) to have short term releases that will eiceed the EAls, but will constitute neither an emergency, or a violation. This situation is due to the time frame of the effluent limits (based on quarterly or annual totals), and the dose averaging inherent to such a system of limitation, as opposed to the immediate situation involved with an emergency release.
The ODCM provides conservative alarm setpoints for the effluent monitors, and provides a means to establish release-specific alarm setpoints. These setpoints should be used as EAls for planned releases for the unusual event -
category.
The EAls calculated herein assume that the entire release activity
- passes by the monitor, or is otherwise available for sampling. As such, accident scenarios involving unmonitored pathways, either partially or in whole, are not completely addressed by these EALs. They are, hoever, addressed by the plant-condition EAls.
I METHODOLOGY The input activity A. of each radionuclide, i, is first summed and ratioed to determine the fraction S$ of the total activity A , which is attributable to 3
j that radionuclide:
A.
S. =
(1)
' 4A.
c 1 Since the activity is converted to a unitless fraction, the input activity can be expressed in any normal activity units. It should be noted that the input activity is used strictly to determine the activity ratios -- the absolute value or units of the input activity has no meaning in this calculation.
The downwind dose rate at a point is equivalent to:
DR t
" Ot (X/Q)(DCF g )(1.1408E-4 yr/hr) (2) where:
DR t
=
Dose rate in mrem /hr
- Except LOCA which assumes 10% activity bypass, 90% collection.
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Ervitcoenantal & Rad 6ciogical Safety ERS ' SFL-85-032 l
N 3 $ f Qt - Release rate, uCi/sec Dispersion, sec/m'
~~
=
X/Q DCF = Dose conversion, mrem-m'/uCi-yr 3
Re-arranging to solve for release rate:
DR Ot "
(X/Q)(DC )1.1408E-4
()
The dose rate conversion factors for a mixture of nuclides is the sum of the normalized DCF 3 for each nuclide i DCF = f S.DCF. (4) t j 1 i Su!situting expression 4sinto expression 3:
'DR Ot "
1.i408E-4(X/Q)fS.DCF. (5) g 1 1 Once the release necessa ry to obtain the desired total dose rate is determined, it can be ratioed by S to obtain Q , the activity of nuclide i:
$ 4
=
Qj Q ti io obtain the release concentration, divide by the release flow:
C =
2.12E-3 Q i 3 (7)
Flow To obtain the monitor count rate:
a CR =
E5 C; (8) f 3 where 'E . is the efficiency'(CPM /uCi/cc) of the monitor to nuclide i. The count rate for the release as a whole is:
CR = CR 3
(9)
In the computer code used in this calculation package, an additional factor was coded in to expression 7 to provide a means to handle miscellaneous corrections to the calculated release activity. Such a correction might be to handle a release situation in which only part of the release stream was monitored, eg: a LOCA with containment release direct to atmosphere. The i revised expression 7 was l 2.12E-3 OjK C
3
=
fjo, (7a) I
_Q
3d%#.
4 3ge s Duquessw@ ERS-SFL-85-032 peee 4 or g Environmental a Radiological Safety Expression 5 above is valid for either the whole body dose or the thyroid dose, provided the appropriate dose conversion factors are used. In order for the thyroid dose-related monitor reading to be valid, all nuclides must be included in thedetermination of S.. While only radioiodines contribute to dose, the noble gas nuclides nevertheless contribute to the monitor reading.
A brief computer code was written to perform the repetitive calculations involved in determining the EALs. For this code, there are two files that provide input data. One, named SOURCEIN, contains the activity for each nuclide in the particular accident being monitored, repeated for all such accidents. The second file, named MONEFFIN, contains the efficiency data for each nuclide for each monitor. Also provided are the flow rate and X/Q appropriate to that path. The code reads in each monitor's data and then cycles through the source terms.
To simplify coding, no attempt was made to have the code distinguish between invalid combinations of monitors and source terms. This discrimination was performed manually in reviewing the printouts.
INPUT FILE STRUCTURE SOURCEIN Record 1: Format A70 descriptive string Record 2: FORMAT 2(F10.0) Field 1: Noble gas fraction (normally=1)
Field 2: Iodine fraction (normally=1)
Record 3: FORMAT 7(F10.0) field 1-19 nuclide activities MONEFFIN Record 1: FORMAT A70 descriptive string Record 2: FORMAT 2(F10.0) Field 1: Release flow (cfm)
Field 2: Path X/Q (sec/m')
Record 3: FORMAT 7(F10.0) Field 1-19 nuclide efficiencies (CPM /uCi/cc)
The order of nuclides expected in the code is 1: Kr83M 8: Xel31M 15: 1131 2: Kr85M 9: Xel33M 16: 1132 3: Kr85 10: Xe133 17: 1133 4: Kr87 11. Xel35M 18: 1134 5: Kr88 12. Xel35 19: 1135 6: Kr89 13. Xel37 ,
7: Kr90 14. Xel38 l
DERIVATION OF INPUT DATA The input data used in this calculation came from several sourcses as follows:
Monitor Efficiencies The monitor ef ficiencies used in the creation of the MONEFFIN file were taken from the calculation package ERS-SFL-85-031. This package provided
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d.
'7 4 T Erwitonmental & Radiological Safety g ERS- SFL-85-032 pas. 5 or 31f ,
documentation for the efficiencies. The significant aspects of these efficiencies are:
- 1. Either automatic pressure differential correction is provided by the monitor hardware, or a nominal correction for such differentials was included in the efficiency value.
k
- 2. Were appropriate, correction for the capture of sample stream i*odine by upstream iodine samplers (effectively reduces monitor efficiency to iodine) was included in the efficiency value. This correctiononlyappiestofiltersonthesamplepipingandnot to those filtes on the release piping. (correction applied to the ,
source term in this latter case)
Attachment 3 provides a printout of the MONEFFIN file used in these calculations.
Release Rate Flow Rates The nominal valu.es of the various release flows were based on FSAR, Operating Manual, and test documentation. While the actual value of the flow may vary from surveillance test to surveillance test, and may vary from these test values during actual conditions, the following historical nominal values were used:
60,000 cfm Ventilation vent 42,500 cfm SLCRS 1000 cim Gaseous waste Any differences between these values and the actual values will be within the I tolerance of the flow instrumentation and/or the radiation monitor instrument As the monitor reading is a function of concentration i
(uCi/cc)a% nd notion.
release rate (uCi/sec), a reduction in release flow would result in lower actual offsite consequences in comparison to those that would be postulated by the unchanged monitor reading.
Dispersion X/Q The value for dispersion for ground level was taken from ERS-SFL-83-015, in which the 0.5% X/Q value was determined. Since a similar analysis has not been performed for the elevated release path (gaseous waste), the value used in ERS-SFL-82-003 for the first determination of the alarm setpoints will be used. This value was taken from the X0Q/D0Q run for 1/81-1/82 for the NNW sector at 0.89 niles -- the most restrictive location in the direction of population. The value chosen was exceeded only 5% of the time. While this value is not as restrictive as the ground X/Q (5% versus 0.5%), the lower significance of the process waste stream as an accident release point does not warrant performing an analysis such as that done in ERS-SFL-83-015 for the ground X/Q. The values to be used S, therefore:
Ground level: 8.9E-4 sec/m' Elevated: 1.55E-5 sec/m'
Nd.
ng Duquesne @ ERS- SFL-85-032 peo* 6 of lif Environmental & Radiological 'afety f
l Dose Conversion Factors The dose conversion factors used in this calculation package were taken from I ERS-SFL-82-017 with unit conversions applied to obtain DCFs in
- mrem-m'/uCi-yr from the values provided in mrem-m'/pCi-yr. These dose conversion factors are based on NRC RG1.109. With regard to iodine, whole body DCFs for submersion in iodine clouds were used. For the thyroid ingestion DCFs, the child DCFs and breathing rate are assumed. Also, 50% of the day's inhalation was assumed to occur in the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during which th(
accide^t occurs.
Source Term The source terms for this calculation were derived from ERS-SFL-82-023 with the exception of the no ESF LOCA case, which was taken from ERS-SFL-83-016 Attachment 1 (containment activity at T=0). This latter case was disregarded due to its obvious overconservatism as an EAL.
There was an attempt to use the new FSAR LOCA results from ERS-SFL-83-016 and ERS-SFL-83-0117 However, in both these cases, collection of containment release activity is assumed either not to occur (DBA case) or only partially (realistic case). If the release activity is not collected, there is no release via a monitored pathway and therefore no EAL. The DBA case and the realistic case in the FSAR are not completely suitable for EPP purposes due to the extensive conservative assumptions that went into the analyses. In a real emergency, the parameters represented by these conservative I assumptions can be quantified. In the event that a true DBA occurs, the l
plant condition protective action flow chart will trigger protective actions l without regress to dose projections.
l {
NOTE: The text above was revised after the initial runs were made. Thus, for each monitor there are two sets of LOCA data. The relevent LOCA data
- are on sheets carrying a note declaring their applicability. The data for f the other accidents were unchanged.
ERS-SFL-82-023 assumed 90% SCLRS collection and 99% filtration efficiency for iodine. These parameters were used in this analysis also, and were
( implemented by setting the "k" value in expression (7a) to:
0.9 for noble gases (10% of release bypasses monitor and is therefore not recorded. To account for this, we lower EAL by 10%)
0.0825 for iodine (10% of iodine is released without collection or filtration, while the 90% that is collected is reduced by 99% by the filter banks prior to reaching the monitor. The monitor " sees" 0.009 of the iodine. The tote 1 iodine released is 0.1 + 0.009 or 0.109 of which 0.009 is seen by monitor. k=.009/.109 = 0.08257*)
Pathway / monitor / source term matrix Ventilation LOCA 100% Gap SLCRS: LOCA 100% Gap GW: SGTR LOCA no F.F LOCA no F.F. WGDT VCT GST FHA, VCT
- value used in code was 0.0825 rather the correct OA02(o The error is negligio e
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4% g Environmental & Radiological Safety ERS- SFL-85-032 p.ee 7 or g
[
l RESULTS Attachment 1 summarizes the EALs chosen from the individual printout sheets in Attachment 5. Some general conclusions:
- l. For the process gas pathway, the SGTR accident sequence gave rise to the more restrictive EALs when compared to the WGDT sequence. Thyroid based.
2.. For the ventilation vent and SLCRS pathways, the most restrictive EALs were for the thyroid exposure pathway and were from the LOCA with no core damage. While this might seem strange, in this accident sequence, ERS-SFL-82-023 assummed no containment sprays and assumed that the iodine would be at equillibrium. With no elevated temperatures there is no reason to assume Cs-I reactions as was done for the 100% gap case. As a result, the I/NG ratio is higher here than in the gap case.
In that the EALs must be applied to instruments with limited meter scale resolution (particularly the Victoreen instruments) the EALs are rounded to the nearest 0.5 decade (eg: 1.0, 1. 5, 2. 0, 2. 5, 1. 5El , 1. 5E3, etc).
GENERAL CONDITIONS OF USE The EALs developed herein may be used in emergency planning applications subject to the following conditions of use. If the EALs are transferred to any other document, that document must contain wording that reflects the conditions of use specified below.
- 1. The EALs are symptoms that a possibly significant release has occurred, and nat definite evidence that such a release has occurred, and nat G0/N0G0 protective action triggers. The response of personnel to a radiation monitor reading (or alarm) that exceeds an EAL is to perform dose projections and/or other accident assessment analyses. The declaration of emergency conditions or protective action recommendations is based on the result of the dose projection when compared to the four emergency classification dose levels.
IF, however, dose projections or other analyses do not show within 15 minutes of the alarm condition or monitor reading that the emergency classification dose levels have n_ot been exceeded, plant personnel shall assume that the condition has indeed been exceeded and taken appropriate action.
- 2. The EAL value should be compared to a steady monitor reading, and not to momentary spikes. The Eberline equipment (SPINGs, SA9/SA10s) performs 1 minute averaging of collected monitor counts, and has 10 minute average displays available. The ARERAS system averages all radiation monitor data over 15 minutes. The Victoreen effluent monitors, being analog devices,have no automatic averaging. Plant personnel should remain alert to increasing trends (Victoreen chart recorders) SPING trend alarms, etc. If an increasing trend shows that one of the EALs is likely to sxceeded in a short time, action should be taken at the pointthetr(endisidentified.
7Tg 4 g g Erwironmerdal & Radiological Safety ERS- SFL-85-032 g page 8 or #
- 3. For routine releases under the provision of a RWDA-G, if the ODCM alarm setpoint is greater than the UE or Alert EAL provided herein, the ODCM alarm setpoints supplant the EALs.* An Unusual Event will be considered to have occurred if the ODCM alarm setpoint is exceeded during the duration of the planned release. Such occurrences will be assessed under ODCM or RCM procedures rather than EPP dose projection procedures.
REFERENCES
- 1. ERS-SFL-85-031 Gaseous Effluent Radiation Monitor Efficiencies
- 2. ERS-SFL-83-015 Accident Calculation X/Q values
- 4. ERS-SFL-82-003 SPING-4 Alarm Setpoint Determination (superceded by this calculation package)
- 6. ERS-SFL-82-017 00SELOAD subroutine
- 7. ERS-SFL-82-023 Dose Projection Source Terms F Fe m- Titt I)0RATich CT THC- PL ,m sed (2tytmSE ADDENDUM (RI)
In RSC 01-86, an alarm setpoint protocol was established in which there would be two general emergency alarms on an effluent monitor, if possible. The Alert or Hi alarm was"be set on the basis of 125 mr/hr whole body or 600 mr/hr thyroid. The High or High-High alarm would be set on the basis of 1000 mr/hr 4 or 5000 mr/hr. These alarms would be interpreted as:
Alert /Hi If the release continued at that rate for eight hours, offsite dose consistent with a general emergency would result.
High/Hi-Hi This release will likely require offsite protective actions if it continues for one hour.
On the SPING console (all SPINGs and SA9/SA10s) an Alert alarm is indicated by a yellow alarm light. The High alarm is indicated by a red alarm light. For RM-MS100 A,B,C, RM-MS-101, and RM-RM-219A,B, there are two alarms, the Hi and the Hi-Hi. Alarm indication is similar.
Attachment 1 was revised to show, for the affected monitors, the two alarm set points calculated in ERS-SFL-86-004.
-i A 4.
7 4T gg ERS- SFL-85-032 g Attachment 1 pne. 9 or fjf Environmental & Radiological Safety Suggested Monitor EALs (all values greater than background)
Ventilation V nt U.E. Alert Site General VS101B 100 cpm 350 cpm 3500 cpm 1.0E5 cpm _
VS109 Ch 5 50 cpm 250 cpm 2500 cpm 7.0E4/5 8E5 cpm VS109 Ch7 Minimal NA /5.5E1* cpm VS109 Ch9 Minimal VS111 LR ---Minimal --,-- 25 cpm 7.1E2/6.0E3 cpm )
w -
VS111 HR --- Minimal --
SLCRS VS107B 200 cpm 700 cpm 7000' cpm 2.0E5 cpm _ h VS110 Ch 5 100 cpm 350 cpm 3500 cpm E5/8.9ES cpm VS110 Ch 7 Minimal NA /6.6E1* cpm i VS110 Ch 9 Minimal -
VS112 LR Minimal 40 cpm cpm }
]E3/9. E3 VS112 HR ---- Ninimal -
Gaseous Waste GW108B offscale high=
GW109 Ch 5 offscale high _
X g
GW109 Ch 7 250 cpm 1000 cpm 1.0E4 cpm 1.fE5/NA 3 GW109 Ch 9 Minimal 25 cpm 250 cpm g3.TE3/3.1rt$ cpm 3.5E4 1.5E5 cpm GW110 LR ---offscale high---
f GW110 HR Minimal 20 cpm 200 cpm E3/2.6E4 cpm For General Emergency; Alert / Hi SPINGs,SA9/SA10
- = this alarm setpoint is T/S
Pego 1
/g y7 XRADMON. FORs 10 2-JUN-1985 16: 37
- ERS-SFL-85-032 C) c = = = := = = = = := = = = = = = := : = = = : = : = = = = = = = = = = : = = = = = c = = =c= c = ==o A tta c hm: n t 2 C0 XRADMON
- Co
- C o This program calculates the effluent radiation
- C o monitor alarm setpoint associated with a given
- C o offsite dose rate -- whole body or thyroid. Location
- C o of receptor is defined by X/G input. All input data
- C o is-read from an input file, XRADMON.DAT
- Co
- C o LOGICAL UNITS: FOR008 All output reports
- Co SOURCEIN Source term data
- Co MONEFFIN Monitor Efficiency Data
- Co XRAD Debug switch
- Co if (XRAD=' Test') debug
- C 00*****************************************************
C o Revision History
- Co 0.0 based on TI-99 BASIC version in ERS-SFL-82-003
- Co 1.0 S.F.LaVie 2/85 VAX-11 FORTRAN
- Co 1.1 S.F.LaVie 5/85 VAX-11 FORTRAN
- Co
- C c=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*
C2345678 C
REAL*4 DCF(2,19),SI(19),EFF(19),SK(19),G(19),C(19),CR(19)
REAL*4 SOURCE (19),SCR(2)
INTEGER *2 IRUN,I CHARACTER *60 DESCRIPT,DESCRIPT2 CHARACTER *6 FN(19)/'Kr83m','Kr85m','Kr85','Kr87','Kr88',
1 'Kr89','Kr90','Xe131m','Xe133m','Xe133', ,
2 'Xe135m','Xe135','Xe137','Xe138',
3 'I131','I132','I133','I134','I135'/
DATA (DCF(1,I) I=1,19)/.756E-1 117E+4,.161E+2,.592E+4, 1 .147E+5,.166E+5,.156E+5,.915E+2, 2 .251E+3,.294E+3,.312E+4 181E+4, 3 .142E+4,.883E+4,.290E+4,.160E+5, 4 .490E+4,.180E+5,.110E+5/
DATA (DCF(2,1) I=1,19)/ 14*0.0,.244E+B,.291E+6,.578E+7, 1 .761E+5. 119E+7/
CHARACTER *4 XRAD/'XRAD'/
CHARACTER *4 XRADBUF INTEGER *4 IISTATUS 1 FORMAT ('1XRADMON VERSION 1.1 5/05 S.F.LAVIE' )
2 FORMAT ('O',22X,' ACTIVITY',8X,'DCF',8X,' EFFEC.DCF',2X, 1 ' RELEASE RELEASE',5X,' EFFICIENCY COUNT RATE' /
2 ' NUCLIDE ACTIVITY RATIO',12X, 3 ' mrem-m3/uci-gr ',6X, 'uC i /s ec uCi/cc',6X, 4 ' cpm /uCi/ce ',4X, ' cpm /mr/hr ' / 107(1H=))
3 FORMAT (' ')
4 FORMAT (1X.A6,4X.2(1PE10.3),4X,E10.3,4X,3(E10.3),2(4X,E10.3))
5 FORMAT (' totals =',2X,1PE10.3,28X.2(E10.3),28X,E10.3) 6 FORMAT (' MONITOR ID: ',A60,4X,'EAL WHOLE DODY THYROID' /
1 ' RELEASE MIX: ', A60,4X, 'O. 5 ',2(1PE10.2) /
2 ' RELEASE FLOW: ',1PG10.3,' CFM ',G10.3,' CC/SEC '
3 ' X/G: ', E 10. 3, ' SEC /M3 ', 6X, '2. 0 ',2(1PE10.2) /
4 ' N.O. FRACTION:',010.4,' IODINE FRACTION: ,010 4. '
- 24X,'20.0 ',2(1PE10.2) / 75X,'125.0 ' 2(1PE10.2), ,
5 ' 600.0' / 06X, ' CPM ',7X, ' CPM ' )
7 FORMAT (A60) 71 FORMAT (1X A60) 8 FORMAT (4(F10.0))
01 FORMAT (1X.4(1PE10.3))
X:ADMON.FORs10 1-JUN-1985 16: 37 Pcgo 2
ERS-SFL-85-032 9 FORMAT (7(F10.0)) Attachm:nt 2- O$
91 FORMAT (1X,7(1PE10.3))
11 FORMAT (A60) 12 FORMAT (7F10.0) 13 FORMAT (I4)
C C ---Open Data files C
OPEN(UNIT =9, FILE ='SOURCEIN', STATUS ='OLD',RECL=80, 1 ORGANIZATION ='SEGUENTIAL',RECORDTYPE=' VARIABLE',
2 READONLY, ERR =2900)
OPEN(UNIT =10, FILE ='MONEFFIN'. STATUS ='OLD',RECL=80, .
1 ORGANIZATION =' SEQUENTIAL',RECORDTYPE=' VARIABLE',
2 READONLY, ERR =2900)
C C ---Loop on Monitor, then accident type C
C ---read in monitor data C
101 WRITE (8,1)
READ (10,11. ERR =2800) DESCRIPT READ (10,8, ERR =2800) FLOW,XG READ (10,12, ERR =2800) (EFF(K),K=1,19)
C C ---read in source data C
201 READ (9,11, ERR =2700) DESCRIPT2 READ (9,8, ERR =2700) FRAC HFRAC READ (9,12, ERR =2700) (SOURCE (K),-K=1,19)
C C -----get activity ratios C
ACTTOTAL=0.0 DO 100 I=1,19 ACTTOTAL=ACTTOTAL+ SOURCE (I) 100 CONTINUE DO 200 I=1,19 SI(I)= SOURCE (I)/ACTTOTAL 200 CONTINUE IRUN=1 211 SSK=0.0 C
C -----Get effective DCF C
DO 300 !=1,19 SK(I)=SI(I)*DCF(IRUN,1)
SSK=SSK+SK(I) 300 CONTINUE C
C -----Get total release activity for 1 mrem /hr C
GT=0.
IF (SSK.NE.O.) GT=8765.8/(XG*SSK) )
SCR(IRUN)=0.0 l C I C -----main isotope loop i
C DO 400 !=1,19 l O(!)=GT*SI(I) ! isotopic release rate IF (I.LE.14) THEN ! isotopic concentration C(I)=(2.12E-3eG(I)* FRAC)/ FLOW
XRADM0N.FOR;10 1-JUN-1985 16: 37 Pcgs @
ELSE Attachment 2 C(I)=(2.12E-3OO(I)cHFRAC)/ FLOW ENDIF CR(I)=C(I)*EFF(I) ! monitor count rate SCR(IRUN)=SCR(IRUN)+CR(I) ! total monitor c. r.
COO CONTINUE C
C -----print report C
C2305678 C
C -----test to see if full print desired C
TEST =. FALSE.
XRADBUF='
IISTATUS=SYS$TRNLOG(XRAD,,XRADBUF,,,)
IF (IISTATUS.NE.0) CALL LID $STOP(% VAL (IISTATUS))
IF ((XRADBUF.NE.' TEST').AND.(IRUN.EG.1)) GOTO 4001 IF ((XRADBUF.NE.' TEST').AND.(IRUN.NE.1)) GOTO 4000 WRITE (8,2)
DO 500 I=1,19 IF ((I.EG.8).OR.(I.EG.15)) WRITE (8,3)
WRITE (8,4) FN(I), SOURCE (I),SI(I),DCF(IRUN,I),SK(I),
1 G(I),C(I),EFF(I),CR(I) 500 CONTINUE WRITE (8,5) ACTTOTAL,SSK,GT,SCR(IRUN)
C C ------if whole body just done, loop for thyroid C
COO 1 IF (IRUN.LT.2) THEN IRUN=2 COTO 211 ENDIF C
C ------
SUMMARY
REPORT C
4000 WRITE (8.6) DESCRIPT,DESCRIPT2,SCR(1)/2..SCR(2)/2.,
1 FLOW, FLOW *471.95,XG.SCR(1)*2. SCR(2)*2.,
2 FRAC HFRAC.SCR(1)*20. SCR(2)*20,SCR(1)*125.,
3 SCR(2)*600.
C C ------wrap up C
C ------test for another source term?
C READ (9,13) IOPT IF (IOPT.NE.0) THEN IF ( XR ADBUF. EG. ' TEST ' ) WRITE (8,1)
GOTO 201 ENDIF C
C ------test for another monitor?
C READ (10,13) NOPT IF (NOPT.NE.0) THEN REWIND 9 !we're going around again-rewind SOURCEIN GOTO 101 ENDIF WRITE (6,*) ' %%XRADMON-S-PROCESSING COMPLETE' GOTO 3000 2700 WRITE (6,*) ' %%XRADMON-F-FILE ERROR IN SOURCEIN'
~
XRADMON.FORs10 1-DUN-1985 16537 Pcgo 4 ERS-SFL-85-032 S[
COTO 3000 Attachment 2 2000 WRITE (6,0) '
7.XXRADMON-F-FILE ERROR IN MONEFFIN' QOTO 3000 2900 WRITE (6,*) '
FILE OPEN ERROR' 3000 CLOSE( 10 STATUS = ' KEEP ' )
CLOSE(9, STATUS =' KEEP')
STOP END 1
' - -- e.--
MONEFFIN.DAT18 31-MAY-1985 09: 30 Pego 1 ERS-SFL-85-032 RM-VS-109 SPING CH5 (ASSUMES AUTO-PRESS COR.s UPSTREAM FILTER) Attachmsnt 3 60000 8.9E-4 0 2.3866E+7 2.4717E+7 2.9532E+7 2.1100E+7 2.9290E+7 3.0530E+7 1.5617E+7 1.9359E+7 1.2358E+7 5.7043E+6 2.9097E+7 2.9571E+7 2.6573E+7
.9.4234E+5 1.4399E+6 1.4505E+6 1.4872E+6 1.3151E+6 1111111 RM-VS-110 SPING CH5 (ASSUMES AUTO-PRESS COR.s UPSTREAM FILTER) 42500 8.9E-4 0 2.5741E+7 2.6659E+7 3.1853E+7 2.2758E+7 3.1592E+7 3.2938E+7 1.6844E+7 2.0881E+7 1.333OE+7 6.1527E+6 3.1384E+7 3.1895E+7 2.8662E+7 1.0164E+6 1.5530E+6 1.5645E+6 1.6041E+6 1.4185E+6 11111111 RM-VS-109 SPING CH7 (ASSUMES AUTO-PRESS COR.s UPSTREAM FILTER) 60000 8.9E-4 2.4329E+1 1.4757E+3 2.5712E+1 7.4213E+3 1.8290E+4 1.7166E+4 1.1898E+4 1.8808E+2 3.8833E+2 3.5350E+2 4.0302E+3 2.3197E+3 1.7564E+3 1.0535E+4 1.7830E+2 1.0720E+3 2.8386E+2 1.2283E+3 7.3694E+2 11111111 RM-VS-110 SPING CH7 (ASSUMES AUTO-PRESS COR.s UPSTREAM FILTER) 42500 8.9E-4 2.0726E+1 1.2571E+3 2.1904E+1 6.3221E+3 1.5581E+4 1.4624E+4 1.0136E+4 1.6023E+2 3.3081E+2 3.0114E+2 3.4333E+3 1.9761E+3 1.4962E+3 8.9742E+3 1.5190E+2 9.1324E+2 2.4181E+2 1.0464E+3 6.2779E+2 11111111 RM-VS-109 SPING CH9 (ASSUMES AUTO-PRESS COR.s UPSTREAM FILTER) 60000 8.9E-4 4.9920E-1 3.0278E+1 1.1134E+0 1.5228E+2 3.7528E+2 3.5222E+2 2.4413E+2 3.C592E+0 7.9680E+0 3.9531E+0 8.2695E+1 4.7597E+1 3.6038E+1 2.1615E+2 3.6586E+0 2.1997E+1 5.8243E+0 2.5203E+1 1.5121E+1 11111111 RM-VS-110 SPING CH9 (ASSUMES AUTO-PRESS COR.s UPSTREAM FILTER) 42500 8.9E-4 6.1529E-1 3.7320E+1 1.3724E+0 1.8769E+2 4.6256E+2 4.3414E+2 3.OO90E+2 i 4.7567E+O 9.8210E+0 4.8724E+0 1.0193E+2 5.8666E+1 4.4419E+1 2.6642E+2 4.5094E+0 2.7112E+1 7.1788E+0 3.1064E+1 1.8637E+1 11111111 RM-VS-111HR SA9 (ASSUMES UPSTREAM FILTERS NOMINAL PRESS COR.)
60000 8.9E-4 3.5754E-1 2.1686E+1 7.9745E-1 1.0906E+2 2.6978E+2 2.5227E+2 1.7485E+2 2.7640E+0 5.7068E+0 2.8312E+O 5.9227E+1 3.4090E+1 2.5811E+1 1.5481E+2 2.6203E+0 1.5754E+1 4.1715E+0 1.8051E+1 1.0830E+1 1111111 RM-VS-112HR SA9 (ASSUMES UPSTREAM FILTERS NOMINAL PRESS COR.)
42500 8.9E-4 4.1340E-1 2.5074E+1 9.2205E-1 1.2610E+2 3.1078E+2 2.9169E+2 2.0217E+2 3.1959E+O 6.5985E+0 3.2736E+0 6.8481E+1 3.9416E+1 2.9844E+1 1.7900E+2 3.0298E+0 1.8216E+1 4.8233E+0 2.0871E+1 1.2522E+1 11111111 RM-VS-111LR SA10 (ASSUMES UPSTREAM FILTER; NOMINAL PRESS COR.)
60000 8.9E-4 2.6928E+3 1.6333E+5 2.7787E+3 8.2141E+5 2.0244E+6 1.9000E+6 1.3169E+6 2.0817E+4 4.2981E+4 3.4498E+4 4.4607E+5 2.5675E+5 1.9440E+5 1.1660E+6 1.9735E+4 1.1865E+5 3.1418E+4 1.3595E+5 8.1566E+4 1111111 RM-VS-112LR SA10 (ASSUMES UPSTREAM FILTERS NOMINAL PRESS COR.)
42500 8.9E-4 3.1183E+3 1.8914E-5 3.2178E+3 9.5121E+5 2.3443E+6 2.2OO2E+6 1.5250E+6 2.4107E+4 4.9773E+4 3.9949E+4 5.1656E+5 2.9732E+5 2.2512E+5 1.3502E+6 2.2854E+4 1.3740E+5 3.6382E+4 1.5743E+5 9.4455E+4 1111111
, RM-VS101B VICTOREEN ( ASSUMES NOMINAL PRESS COR. s NO FILTER)
^ ~ ~
MONEFFIN.'DATi0 ~ 31-MAY-1985 09: 30 Pcgd~ 2 ERS-SFL-85-032 60000 0.9E-4 Attachmint 3 O 9.7954E+7 3.C750E+5 7.3758E+7 1.1389E+O 1.3896E+3 1.3037E+0 IS[Ig7 2.2529E+6 1.2610E+7 1.OO51E+7 7.1543E+7 1.1214E+8 3.1638E+7 1.1528E+8 1.0161E+8 2.3721E+8 8.9840E+7 2.3597E+8 1.0146E+8 ,
1111111 RM-VS107B VICTOREEN ( ASSUMES NOMINAL PRESS COR. s NO FILTER )
42500 8.9E-4 0 5.1622E+7 5.0414E+7 9.6048E+7 5.1622E+7 9.5923E+7 9.8690E+7 2.9393E+7 4.1684E+7 2.2852E+7 1.5071E+7 6.4221E+7 1.0523E+8 7.3530E+7 4.4068E+7 7.3090E+7 6.8938E+7 8.0638E+7 6.3026E+7 11111111 RM-CW-109 SPING CH5 (ASSUMES AUTO-PRESS COR.s UPSTREAM FILTER) 1000 1.55E-5 0 2.4260E+7 2.5125E+7 3.OO21E+7 2.1449E+7 2.9775E+7 3.1043E+7 1.5375E+7 1.9680E+7 1.2563E+7 5.7987E+6 2.9578E+7 3.OO60E+7 2.7013E+7 9.5793E+5 1.4637E+6 1.4745E+6 1.5119E+6 1.3369E+6 11111111 RM-CW-109 SPING CH7 (ASSUMES AUTO-PRESS COR.; UPSTREAM FILTER) 1000 1.55E-5 2.0617E+1 1.2505E+3 2.1789E+1 6.2891E+3 1.5499E+4 1.4547E+4 1.OO83E+4 1.5939E+2 3.2900E+2 2.9957E+2 3.4153E+3 1.9658E+3 1.4884E+3 8.9273E+3
] 1.5110E+2 9.0847E+2 2.4055E+2 1.0409E+3 6.2450E+2 11111111 RM-CW-109 SPING CH9 (ASSUMES AUTO-PRESS COR.; UPSTREAM FILTER) 1000 1.55E-5 4.9920E-1 3.0278E+1 1.1134E+0 1.5228E+2 3.7528E+2 3.5222E+2 2.4413E+2 3.C592E+0 7.9680E+0 3.9531E+0 8.2695E+1 4.7597E+1 3.6038E+1 2.1615E+2 3.6586E+O 2.1997E+1 5.8243E+0 2.5203E+1 1.5121E+1 11111111
! RM-tW-110HR SA9 (ASSUMES UPSTREAM FILTER: NOMINAL PRESS COR.)
l 1000 1.55E-5 4.3373E-1 2.6308E+1 9.6740E-1 1.3230E+2 3.2607E+2 3.0603E+2 2.1211E+2 3.3531E+0 6.9230E+0 3.4346E+0 7.1849E+1 4.1355E+1 3.1312E+1 1.8781E+2 3.1788E+0 1.9112E+1 5.0605E+0 2.1898E+1 1.3138E+1 11111111 RM-fW-110LR SA10 (ASSUMES UPSTREAM FILTERsNOMINAL PRESS COR.)
1000 1.55E-5 2.0759E+3 1.7444E+5 2.9677E+3 8.7727E+5 2.1620E+6 2.0292E+6 1.4064E+6 2.2233E+4 4.5904E+4 3.6844E+4 4.7641E+5 2.7421E+5 2.0762E+5 1.2453E+6 2.1077E+4 1.2672E+5 3.3554E+4 1.4520E+5 8.7113E+4
- 1111111 .
RM-CW108D VICTOREEN (ASSUMES NOMINAL PRESS COR.sNO FILTER)
- 1000 1.55E-5 0 9.OO48E+7 3.5623E+5 6.7805E+7 1.0470E+8 1.2775E+8 1.2324E+8
! 2.0711E+6 1.1592E+7 9.2400E+6 6.5769E+7 1.0300E+8 2.9084E+7 1.0597E+8 l 9.3400E+7 2.1806E+8 8.2589E+7 2.1692E+8 9.3274E+7 0000000 i
SOURy3IN.DATs0 25-JUN-1985 13: 42 Pcgo 1 ERS-SFL-85-032 LOCA-100% GAP ACTIVITY --- ER3-SFL-82-C23 TBL 7 TAB 1 Attachm:nt 4
- 0. 9 0.0825 page 16/38 C.378 1.52 5.54 1.31 3.17 0.0491 0. 0 0.224 0.749 45.3 0.194 3.22 0. 0 0.612 0.0473 7.54E-3 0.0348 7.53E-3 0.0177 1
LDCA-NO CORE DAMAGE --- ERS-SFL-82-023 TBL 7 TAB 2 1
- 0. 9 0.0825
- 0. 0 0.0144 0.0864 0.00734 0.0226 0. 0 0. 0 C. O O.0242 0.212 0.00302 0.0245 0. 0 0.00171 <
5.C2E-4 1.64E-4 8.61E-4 8.13E-5 4.30E-4 l C 1 LOCA-NO ESFs --- ERS-SFL-83-016 Attachment 1 (cont. Act)
- 1. 0 1. 0 i 1.27E7 7.75E5 3.06E7 5.89E7 8.30E7 1.08E8 0. 0 l 5.18E5 4.00E6 1.58E8 4.24E7 4.31E7 1.39E8 1.39E8 l 3.42E7 5.20E7 7.65E7 8.95E7 6.95E7 1
SQ TUBE RUPTURE -- ERS-SFL-02-023 Table 4
- 1. 0 1. 0
- 0. 0 115. 655. 72. 192. 0. 0 0. 0
- 0. 0 187. 1610. 65. 195. 0. 0 0. 0 0.31 0.106 0.478 0.066 0.254 1
I WGDT RELEASE --- ERS-SFL-82-023 Table 5 l l 1. 0 1. 0 i 1.00E-6 0.164 4230, 5.83E-10 2.78E-3 0. 0 0. 0 0.93 0.133 218. 1.40E-2 1.85E-2 0. 0 0. 0
- 0. 0 0. 0 0. 0 0. 0 0. 0 1
FUEL HANDLING ACCIDENT --- ERS-SFL-82-023 Table 1 l
- 1. 0 1. 0
! O. 0 0. 0 2890. 0. 0 0. 0 0. 0 0. 0 l 17000. 1000, 89100. 0. 0 5.06 0. 0 0. 0 l 0.C54 0.584 0.0218 0. 0 0. 0 0. 0 0. 0 l 1 1
MAIN STEAM LINE DREAK --- ERS-SFL-82-023 Table 6 l 1. 0 1. 0 l
4.95E-5 2.72E-4 3.70E-4 1.39E-4 4.95E-4 1.24E-5 0. 0 l 2.72E-4 5.56E-4 4.34E-2 3.09E-5 8.36E-4 2.20E-5 1T05E-4 l 5.94E-5 1.66E-5 7.62E-5 3.30E-6 3.36E-5 l 1
! VCT RUPTURE --- ERS-SFL-82-023 Table 2 l 1. 0 1. 0 1.41 11.1 6000, 6.00 10.4 0. 0 0. 0 l 1.39 10. 450. 6.24 10.6 0. 0 1.63
- 0. 0 0. 0 0. 0 0. 0 0. 0 1
C3T RUPTURE --- ERG-GFL-82-023 TABLE 3
- 1. 0 1. 0 4.01E-7 6.55E-2 1690. 2.33E-10 1,11E-3 0. 0 0. 0 3.C4E-1 5.30E-2 87. 5.60E-3 7.40E-3 0. 0 0. 0
- 0. 0 0. 0 0. 0 0. 0 0. 0 0
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1 X"ADMON VERSION 1.1 SIBS S.F.LAVIE .
l MONITOR ID: RM-VS1013 VICTDREEN 4 ASSUMES NOMINAL PRESS COR. 4 NO FILTER) EAL WHOLE SODY THYROID
- RELEASE MIX:LOCA-100% GAP ACTIVITY - ER3-SFL-82-023 TSL 7 TAB 1 0. 5 2.88E #.3 1.73E+02
! RELEASE FLOW: 6 OOOE+04 CFM 2.832E+07 CC/SEC X/S: G.900E-04 SEC/M3 2. O 1.15E+04 6.V4E+02 ,
j N. O. FR ACTION: O. 9000 IODINE FRACTION: 8.2500E-02 20.O 1.15E+05 6.94E+03 -
t 125.O 7.19E+05 2.08E+05 600.O CPM CPM 1 MONITCR ID: RM-VS1013 v!CTOREEN (ASSUMES NOMINAL PRESS COR.aNO FILTER) EAL WHOLE BODY THYROID RELEASE MII:LOCA-NO CORE DAMACE - ERS-SFL-82-023 TEL 7 TAS 2 O. 5 2.92E+03 8.49E+01 /
$ RELEASE FLOW: 6.OOOE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. O 1.17E+04 I
)
N.G. FRACTION:O.9000 IODINE FRACTION: 8.2500E-02 20.O 125.O 3.40E+02[/
1.17E+05 3.40E+03
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X2ADMON VERSIDN 1. 1 5/25 S.F.LAVIE .
ACTIVITY DCF EFFEC.DCF CELEASE RELEASE EFFICIENCY COUNT EATE ACTIVITY RATIO aree-m3/uCi-gr uC1/sec uC1/cc cp:/uC1/cc cp:/mr/hr NUCLIDE ,
Kr23m 3.780E-01 6.060E-03 7.560E-02 4.581E-04 4.477E+01 1.424E-06 0.OOCE+00 0.OOCE+00 Kr;5m 1.520E+00 2.437E-02 1.170E+03 2.851E+01 1.800E+02 5.725E-06 2.387E+07 1.366E+02 nrO5 3.540E+00 8.881E-02 1.610E+01 1.43OE+00 6.561E+02 2.087E-05 2.472E+07 5.157E+02 KrG7 1.310E+00 2.100E-02 5.920E+03 1.243E+02 1.552E+02 4.934E-06 2.953E+07 1.457E+02 Krf8 3.170E+00 5.082E-02 1.47CE+04 7.470E+02 3.754E+02 1.194E-05 2.110E+07 2.519E+02 KrC9 4.910E-02 7.871E-04 1.66CE+04 1.307E+01 5.815E+00 1.849E-07 2.929E+07 5.416E+00 nrGO O.OOCE+00 0.OOCE+00 1.560E+04 0.OOOE+00 0.OOOE+00 0.OOCE+00 3.054E+07 0.OOCE+00 X2131m 2.240E-01 3.591E-03 9.150E+01 3.286E-01 2.653E+01 8.437E-07 1.562E+07 1.318E+01 Xe133m 7.490E-01 1. 201E-02 2.510E+02 3.014E+00 8.871E+01 2.821E-06 1.936E+07 5.461E+01 Xo133 4.530E+01 7.262E-01 2.940E+02 2.135E+02 5.365E+03 1.706E-04 1.236E+07 2.108E+03 Xo135m 1.940E-01 3.110E-03 3.120E+03 9.703E+00 2.298E+01 7.307E-07 5.704E+06 4.168E+00 Xa135 3.220E+00 5.162E-02 1.810E+03 9.343E+01 3.814E+02 1.213E-05 2.910E+07 3.529E+02 Xe137 0.OOCE+00 0.OOCE+00 1.420E+03 0.OOOE+00 0.OOOE+00 0.OOCE+00 2.957E+07 0.OOOE+00 Xa138 6.120E-01 9.811E-03 8.830E+03 8.663E+01 7.248E+01 2.305E-06 2.657E+07 6.125E+01 1131 4.730E-02 7.582E-04 2.900E+03 2.199E+00 5.602E+00 1.633E-08 9.423E+05 1.539E-02 1132 7.540E-03 1.209E-04 1.600E+04 1.934E+00 8.930E-01 2.603E-09 1.440E+O6 3.748E-03 1133 3.480E-02 5.579E-04 4.900E+03 2.734E+OO 4.122E+00 1.201E-08 1.451E+06 1.743E-02 1134 7.530E-03 1.207E-04 1.BOCE+04 2.173E+00 8.918E-01 2.600E-09 1.487E+06 3.866E-03 1135 1.770E-02 2.837E-04 1.100E+04 3.121E+00 2.096E+00 6.111E-09 1.315E+06 8.036E-03 totals = 6.238E+01 1.333E+03 7.388E+03 3.650E+03 ACTIVITY DCF EFFEC.DCF RELEASE RELEASE EFFICIENCY COUNT RATE ACTIVITY RATIO mrem-m3/uct gr uC1/sec uCi/cc cpm /uci/cc cpm /mr/hr NUCLIDE 0.OOCE+00 r%
Kr83m 3.780E-01 6.060E-03 3.oOOE+00 0.OOOE+00 2.700E+00 S.585E-08 0.OOOE+00 Kr85m 1.520E+00 2.437E-02 3 OOCE+00 0.000E+00 1.086E+01 3.452E-07 2.387E+07 8.239E+00 G , c. y >m Kr85 5.540E+00 9.881E-02 0.OOCE+00 0.OOCE+00 3.957E+01 1.258E-06 2.472E+07 3.110E+01 g% ggg gg KrB7 1.310E+00 2.100E-02 0.OOCE+00 0.COOE+00 9.356E+00 2.975E-07 2.953E+07 8.786E+00 u g)
T
- > * *a Kr88 3.170E+00 5.082E-02 0.OOCE+00 0.OOCE+00 2.264E+01 7.199E-07 2.110E+07 2.929E+07 1.519E+01 3.266E-01 y g4 pg {p,&
Kr89 4.910E-02 7.871E-04 0.OOCE+00 0.OOCE+00 3.507E-01 1.115E-08 u *"
Kr90 0.OOCE+00 0.COOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.054E+07 0.OOOE+00 eg "T D %E *8 0.OOCE+00 1.600E+00 5.087E-08 1.562E+07 7.945E-01 g E N Xe131m 2.240E-01 3.591E-03 0.OOOE+00 gi Xs133m 7.490E-01 1.201E-02 0.OOCE+00 0.OOCE+00 5.349E+00 1.701E-07 1.936E+07 3.293E+00 gs a 4.530E+01 7.262E-01 0.OOOE+00 0.OOCE+00 3.235E+02 1.029E-05 1.236E+07 1.271E+02 , g1 Xo133 **
Xo135m- 0.OOOE+00 0.OOCE+00 1.386E+00 4.406E-08 5.704E+O6 2.513E-01 1.940E-01 3.110E-03 0.COCE+00 2.3OOE+01 7.313E-07 2.910E+07 2.128E+01 (;g "[Uf' y, Xo135 3.220E+00 5.162E-02 0.OOOE+00
- g Xe137 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOCE+00 0.OOOE+00 0.OOOE+00 2.957E+07 0.OOOE+00 Xe138 6.120E-01 9.811E-03 0.OOCE+00 0.OOOE+00 4.371E+00 1.390E-07 2.657E+07 3.693E+00 ,
d3 1131 4.730E-02 7.582E-04 2.440E+07 1.850E+04 3.378E-01 9.847E-10 9.423E+05 9.279E-04 1132 7.540E-03 1.209E-04 2.910E+05 3.517E+01 5.385E-02 1.570E-10 1.440E+06 2.260E-04 h $2' I133 3.480E-02 5.579E-04 5.780E+06 3.224E+03 2.485E-01 7.245E-10 1.451E+06 1.051E-03 Os 3134 7.530E-03 1.207E-04 7.610E+04 9.186E+00 5.378E-02 1.568E-10 1.487E+06 2.331E-04 1135 1.770E-02 2.837E-04 1.190E+06 3.377E+02 1.264E-01 3.685E-10 1.315E+06 4.846E-04 tocals= 6.238E+0! 2.211E+04 4.455E+02 2.201E+02 MONITOR ID: RM-VS-109 SPINO CH5 (ASSUMES AUTO-PRESS COR.s UPSTREAM FILTE EAL WHOLE BODY THYROID #
RELEASE MIX: LOCA-100% CAP ACTIVITY --- ERS-SFL-82-023 TBL 7 TAB 1 0. 5 1.82E+03 1.10E+02 RELEASE FLOW. 6.OOOE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. 0 7.30E+03 4.40E+02 '
N. C. FR ACTION: 0. 9000 IODINE FR ACTICN: 8. 2500E-02 e 20.0 7.30E+04 4.40E+03 '
125.0 4.56E+05 1.32E+05 600.0 CPM CPM
.w.i.e + e%.au. ..
-__..-_____.~._m - _ _ _ _ _ _______...m 4 _ . ~ _ _ - _ _ - __ _- -~~
4 X3ADMON VE%2 ION 1.1 5/05 5. F.LAVIE a
1 ACTIVITY DCF EFFEC.DCF EELEASE EELEASE EFFICIENCY COUNT RATE NUCLIDE ACTIVITY RATIO mese-m3/uCi gr uC1/sec uC1/ c c . cpa/uC1/cc cpa/Er/hr g ....... ..... -.................... ...... ....... ... . ..... ... -.................... ,
MrC3m O.OOOE+00 O.OOOE+00 7.560E-02 0.000E+00 0.000E+00 0,000E+00 0.OOOE+00 0.000E+00 ,
, McC5m 1.440E-02 3.616E-02 1.170E+03 4.231E+01 2.599E+02 8.264E-06 2,387E+07 1.972E+02
' 1.610E+01 3.493E+00 1.559E+03 4.958E-05 2.472E+07 1.226E+03 MrCS 8.640E-02 2.170E-01 KrS7 7.340E-03 1.843E-02 5.920E+03 1.091E+02 1.325E+02 4.212E-06 2.953E+07 1.244E+02
}j McC8 2.260E-02 5.675E-02 1.470E+04 8.342E+02 4.078E+02 1.297E-05 2.110E+07 2.736E+02 Kr89 0.OOOE+00 0.000E+00 1.660E+04 0.000E+00 C.OOOE+00 C.OOOE+00 2.929E+07 0.OOOE+00 '
Mr90 0.OOOE+00 0.000E+00 1.560E+04 0.OOOE+00 0.OOOE+00 0.000E+00 3.054E+07 0.OOOE+00 Xe131m O.000E+00 0.000E+00 9.150E+01 0.000E+00 O.000E+00 O.OOOE+00 1.562E+07 0.000E+00 Xe133m 2.420E-02 6.077E-02 2.510E+02 1.525E+01 4.367E+02 1.389E-05 1.936E+07 2.688E+02 i Xe133 2.120E-01 5.323E-01 2.940E+02 1.365E+02 3.826E+03 1.217E-04 1.236E+07 1.503E+03 Xe135m 3.020E-03 7.583E-03 3.120E+03 2.366E+01 5.450E+01 1.733E-06 5.704E+06 9.886E+00 Xe135 2.450E-02 6.152E-02 1.810E+03 1.114E+02 4.421E+02 1.406E-05 2.910E+07 4.091E+02 Xe137 0.000E+OO 0.000E+00 1.420E+03 0.000E+00 O.000E+00 0.000E+00 2.957E+07 0.OOOE+00 Xe138 1.710E-03 4.294E-03 8.830E+03 3.791E+01 3.086E+01 9.813E-07 2.657E+07 2.608E+01 i
.. 1131 5.420E-04 1.361E-03 2.900E+03 3.947E+00 9.781E+00 2.851E-08 9.423E+05 2.687E-02 !
! I132 1.640E-04 4.118E-04 1.600E+04 6.589E+00 2.960E+00 8.627E-09 1.440E+O6 1.242E-02 I
l 1133 8.610E-04 2.162E-03 4.900E+03 1.059C+01 1.554E+01 4.529E-08 1.451E+06 6.570E-02 1134 8.130E-05 2.041E-04 1.800E+04 3.675E+00 1.467E+00 4.277E-09 1.487E+06 6.360E-03 i I135 4.300E-04 1.OGOE-03 1.100E+04 1.188E+01 7.760E+00 2.262E-08 1.315E+06 2.975E-02 i totale= 3.982E-01 1.370E+03 7.187E+03 4.038E+03
$' ACTIVITY DCF EFFEC.DCF RELEASE . RELEASE EFFICIENCY COUNT RATE i
I NUCLIDE ACTIVITY RATIO aree-m3/uci gr uCi/sec uC1/cc cpe/uci/cc cym/ar/hr ,
4 '
. Mr83m O.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7' Kr85m 1.440E-02 3.616E-02 O.000E+00 0.000E+00 7.557E+00 2.403E 2.387E+07 5.736E+00 . r- w wm l
- Mr85 8.640E-02 2.170E-01 0.000E+00 0.000E+00 4.534E+01 1.442E-06 2.472E+07 3.564E+01 y "O TM M
0.000E+00 3.852E+00 1.225E-07 2.953E+07 3.618E+00 I N&
$g Mr87 7.340E-03 1.843E-02 0.OOOE+00 i l Kr88 2.260E-02 5.675E-02 O.000E+00 0.OOOE+00 1.186E+01 3.772E-07 O.OOOE+00 O.000E+00 O.000E+00 2.110E+07 2.929E+07 7.95BE+00 O.000E+00
- $YeI f. =En f Kr89 O.000E+00 0.OOOE+00 O.OOOE+00 Kr90 0.OOCE+00 0.000E+00 0.000E+00 O.OOOE+00 O.000E+00 0.OOOE+00 3.054E+07 0.000E+00 0 33D *[']
a
+c w l
- Xe131m O.OOOE+00 O.000E+00 O.000E+00 0.OOOE+00 O.000E+00 C.000E+00 1.562E+07 O.000E+00 4 j 15
!)
Xe133m 2.420E-02 6.077E-02 0.OOOE+00 .O.000E+00 1.270E+01 4.039E-07 1.936E+07 7.819E+00 ob 2 l l Xe133 2.120E-01 5.323E-01 0.000E+00 0.000E+00 1.113E+02 3.53GE-06 1.236E+07. 4.372E+01 R2
[p* !
Xe135m 3.020E-03 7.583E-03 O.000E+00 0.OOOE+00 1.585E+00 5.040E-08 5.704E+06 2.875E-01 i
) Xe135 2,450E-02 6.152E-02 0.OOOE+00 0.000E+00 1.286E+01 4.089E-07 2.910E+07 1.190E+01 }g I Xe137 O.OOCE+00 O.000E+00 0.000E+00 0.000E+00 O.000E+00 0.OOOE+00 2.957E+07 O.OOOE+00 M <e j Xe138 1.710E-03 4.294E-03 O.OOOE+00 0.OOOE+00 8.974E-01 2.854E-08 2.657E+07 7.584E-01 3.jh C
{* Q I131 5.420E-04 1.361E-03 2.440E+07 3.321E+04 2.845E-01 8.292E-10 9.423E+05 7.814E-04 g 1132 1.640E-04 4.118E-04 2.910E+05 1.198E+02 8.607E-02 2.509E-10 1.440E+06 3.613E-04 1133 8.610E-04 2.162E-03 5.780E+06 1.250E+04 4.519E-01 1.317E-09 1.451E+06 1.911E-03 co 9
I134 8.130E-05 2.041E-04 7.610E+04 1.554E+01 4.267E-02 1.244E-10 1.487E+06 1.850E-04 rR j
1135 4.300E-04 1.080E-03 1.190E+06 1.285E+03 2.257E-01 6.578E-10 1.315E+06 8.651E-04 @
i, totals = 3.982E-01 4.712E+04 2.090E+02 1.174E+02 i MONITOR ID: RM-VS-109 SPING CHS (ASSUMES AUTO-PRESS COR.a UPSTREAM FILTE EAL WHOLE BODY THYROID f KELEASE MIX:LOCA-NO CORE DAMAGE - ERS-SFL-e2-023 T8L 7 TA8 2 0. 5 2.02E+03 5.87E+01 '
EELEASE FLOW: 6.000E+04 CFM 2.832E+07 CC/SEC X/G: 8.900E-04 SEC/M3 2. O 8.08E+03 '2.35E+02#'
I N. C. FR ACTION: O. 9000 IODINE FRACTION:8.2500E-02 20.O 8.08E+04 2.35E+03 j J , 125.O 5.05E+05 7.05E+04'600.O i i CPM CPM t
XRADMON.LISs3 Pege 1 -
31-MAY-198509p12 X2ADMON VE2SION 1.1 5/05 S.F.LAVIE N j/
MONITCM ID: RM-VS-109 SPING CH5 ( ASSUMES AUTO-PRESS CORRECTIONS UPSTREAM EAL WHOLE BODY THYROID (.o781 RELEASE MIX:LOCA-DESIGN DASIS --- ERS-SFL*B3-016 Attachment 1 0. 5 4.91E+02 5.01E+00 h bE2 2.47 t3 RELEASE FLOW: 6.OOOE+04 CFM 2.832E+07 CC/SEC /X/G: 8.900E-04 SEC/M3 2. 0 1.96E+03 2.01E+01 l' OEI 2.*df N.C. FRACTION;O.9000 IODINE FRACTION: B 2500E-03 20.0 1.96E+04 2.01E+02 7.3C CI
- 1. 2 6.02E+03 600 O Ef
}25.O _
MONITCR ID: RM-VS-109 SPINO CH3 (ASSUMESsAUTO-PRESS CORRECTIONS UPSTREAM EAL WHOLE DODY THYROID f.00E3 g. 43 EL RELEASE MIX:LOCA-100% CAP ACTIVITY --- ERS-SFL-83-016 Attachment 1 0. 5 5.02E+02 2.09E+00 4.et E I g,yggg_
RELEASE FLOW: 6.COOE+04 CFM 2.832E+07 CCXSEC X/G: 8.900E-04 SEC/M3 2. 0 2.01E+03 8.35E+00 4Al'Y 2* 5+ ES N. C. FR ACTION: 0. 5000 IODINE FRACTJON:9'.9000E-03 20.0 2.01E+04 8.35E+01 2 5158 125.0 1.26E+05 2.51E+03 600.0 CPM CPM MONITOR ID: RM-VS-109 SPINO CH5 (ASSUMES AUTO-PRESS CORRECTIONS UPSTREAM EAL WHOLE DODY THYROID RELEASE MIX: LOCA-NO ESFs --- ERS-SFL-83-016 At tac hment 1 (cont. Act) 0. 5 3.83E+02 2.42E+00 RELEASE FLOW: 6.OOCE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. 0 1.53E+03 9.69E+00 (GNCEE N. C FR ACTION: 1.000 IODINE FRACTION: 1.000 20.0 1.53E+04 9,69E+01 125.0 9.57E+04 2.91E+03 600.0 CPM CPM MONITOR ID: RM-VS-109 SPING CH3 (ASSUMES AUTO-PRESS CORRECTION: UPSTREAM EAL WHOLE BODY THYROID ft0T A RELEASE MIX:SQ TUDE RUPTURE -- ERS-SFL-82-023 Table 4 0. 5 1.58E+03 6.OOE+02 V alt E)
RELEASE FLOW: 6.OOOE+04 CFM 2.832E+07 CC/SEC X/G: 8.900E-04 SEC/M3 2. 0 6.31E+03 2.40E+03 I)FTN N. G. FR ACTION: 1.000 IODINE FRACTION: 1.000 20.0 6.31E+04 2.40E+04 125.0 3.95E+05 7.20E+05 600.0 CPM CPM MONITOR ID: RM-VS-109 SPINO CHS (ASSUMES AUTO-PRESS CORRECTIONS UPSTREAM EAL WHOLE BODY THYROID N OT 4 RELEASE MIX:WGDT RELEASE --- ERS-SFL-82-023 Tab le 5 0. 5 1.41E+05 0.OOE+00 V AC @
RELEASE FLOW: 6.OOOE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. 0 5.63E+05 0.OOE+00 Pwf#
N.C. FRACTION: 1.000 IODINE FRACTION: 1.000 20.0 5.63E+06 0.OOE+00 125.0 3.52E+07 0.OOE+00 600.0 CPM CPM MONITOR ID: RM-VS-109 SPING CHS (ASSUMES AUTO-PRESS CORRECTIONS UPSTREAM EAL WHOLE BODY THYROID gc7 4 RELEASE MIX: FUEL HANDLINO ACCIDENT --- ERS-SFL-82-023 Table 1 0. 5 9.04E+03 1.20E+04 yp(ip RELEASE FLOW: 6.OOCE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. 0 3.61E+04 4.80E+04 g N.C. FRACTION: 1.000 IODINE FRACTION: 1.000 20. 0 3.61E+05 4.80E+05 125.0 2.26E+06 1.44E+07 600.0 CPM CPM MONITOR ID: RM-VS-109 SPING CH5 ( ASSUMES AUTO-PRESS CORRECTIONS UPSTREAM EAL WHOLE BODY TRTRUTb NOT A RELEASE MIX: MAIN STEAM LINE DREAK --- ERS-SFL-82-023 Table 6 0. 5 4.19E+03 5.49E+01 v NL t])
RELEASE FLOW: 6.OOCE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 EEC/M3 2. 0 1.67E+04 2.19E+02 DWTH 3. -
N. C. FR ACTION: 1.000 IODINE FRACTION: 1.000 20.0 1.67E+05 2.19E+03 e=
125.0 1.05E+06 6.58E+04 600.0 EU CPM C15M MONITOR ID: RM-VS-109 SPING CHS (ASSUMES AUTO-PRESS CORRECTIONS UPSTREAM EAL WHOLE DODY THYROID 4.38E+04 0.OOE+00
{h@[
ey RELEAEE MIX: VCT RUPTURE --- ERS-SFL-82-023 Tab le 2 0. 5 PELEASE FLOW: 6.OOOE+04 CFM 2.832E+07 CC/SEC X/0: 8.900E-04 SEC/M3 2. 0 1.75E+05 0 OOE+00 N. C. FR ACTION: 1.000 IODINE FRACTION: 1.000 20.0 1.75E+06 O OOE+00 #t3[m Nk Do 125.0 1.09E+07 0.OOE+00 600.0 CPM CPM MONITCR ID: RM-VS-109 SPING CH5 ( ASSUMES AUTO-PRESS CORRECTION; UPSTREAM EAL WHOLE BODY THYROID ggy RELEASE MIX:GST RUPTURE --- ERS-SFL-82-023 TADLE 3 0. 5 1.41E+05 0.OOE+00 g q(f RELEASE FLOW: 6.OOCE+04 CFM 2.832E+07 CC/SEC X/G: 8.900E-04 SEC/M3 2. 0 5.63E+05 0.OOE+00 N G. FR ACTION: 1.000 IODINE FRACTION: I.OOO 20.0 5.63E+06 0.OOE+00 125.0 3.52E+07 0.OOE+00 600.0 CPM CPM
I XIADMON VER210N 1.1 5/05 S.F.LAVIE '
MONITOR ID: 7M-VS-109 SPINO CH7 (ASSUMES AUTO-PT.ESS COR. UPMREAM FILTE EAL WHOLE 80DY THYXOID
- I:ELEASE MIX:LOCA-100% OAP ACTIVITY -- E;iS-SFL-C2-023 TSL 7 TA3 1 05 1.C2E-01 1.16E-02 RELEASE FLOW: 6.OOOE+03 CFat 2.832E+07 CC/SEC X /0:- S.TOOE-04 SEC/M3 2. O 7.68E-31 4,63E-02 N. O. FM ACTION:O.9000 IODINE FRACTION:8.2500E-02 .*
20.O 7.68E+00 4.63E-01 125.O 4.80E+01 1.39E+01 600.O CPM CPM
! MONITOR ID: RM-VS-109 SPINO CH7 (ASSUMES AUTO-P9ESS COR.s UPSTREAM FILTE EAL WHOLE 80DY THYROID RELEASE MIX: LOCA-NO CORE DAMAGE - ERS-SFL-82-023 TSL 7 TAB 2 RELEASE FLOW: 6.OOOE+04 CFM 2.832E+07 CC/SEC X/G: 8.900E-04 SEC/M3
- 0. 5
- 2. O 1.90E-01 5.53E-03 7.61E-01 2.21E-02 gfb t p 4";
3h- gy gg i N. G. FR ACTION: O. 9000 IODINE FRACTION: 8. 2500E-02 20.O 7.61E+00 r,, a SC 125.O 4.75E+01 2.21E-01 CPM 6.64E+00 CPM
[600.O iT f
g* 33
- w En is M 9
l (P9 fp 4[
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T 1
5
XRADMOR LISs3 31-MAY-1945 09: 12 Page 4 XRADMON VENION 1.1 5/05 S.F.LAVIE s y .
MONITOR ID: EM-VS-109 SPINO CH7 ( ASSUMES. AUTO-PRESS CORRECTION 4 UPSTREAM EAL WHOLE BODY THYROID RELEASE MIX:LOCA-DESIGN BASIS --- ERS-SFL-83-016 Attachment 1 0. 5 1.4LE-01 1.49E-03 l
- k 2
RELEASE FLOW: 6.OOCE+04 CFM 2.832E+07 CC/BEC N.C. FRACTION:0.9000 ICDINE FR ACTIONf 8. 2500E-03 X(0: 8.900E-04 SEC/M3 2. 0 20.0 5.82E-01 15. 94E-03 5.82E+00 5.94E-02 b][h 0-d
/ 125.0 3 64E+01 1.78E+00 600.0 -
% / CPM MONITCR ID: RM-VS-109 SPING CH7 (ASSUMES AUTC-PRESS CORRECTIONa UPSTREAM EAL WHOLE BODY THYROID , P, f.9V ~ b 7 RELEASE MIX:LOCA-100% CAP ACTIVITY --- ER5 / SFL-83-016 Attachment 1 0. 5 9.38E-02 3.90E-04 /.5664 RELEASE FLOW: 6.COOE+04 CFM 2.832E+07 CO'/SECN X/Q: 8.900E-04 SEC/M3 2. 0 3.7 E-01 1.56E-03 [Lk2[b9-N.C. FRACTION:0.5000 IODINE FRACTIOM: 9.9000E-03 20.0 3.75E+00 1.56E-02 '7 ,,,9( 73 6/
125.0 2.34E+01 4.68E-01 600.0 CPM CPM MONITOR ID: RM-VS-109 SPING CH7 (ASSUMES AUTC-PRESS CORRECTIONS UPSTREAM EAL WHOLE BODY THYROID RELEASE MIX: LOCA-No ESFs --- ERS-SFL-83-016 Attac hment 1 (cont. Act) 0. 5 1.22E-01 7.69E-04 16NCEE RELEASE FLOW: 6.OOCE+O4 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. 0 4.86E-01 3.08E-03 N. C. FR ACTION: 1.000 10 DINE FR/.CTION: 1.000 20.0 4.86E+00 3.08E-02 125.0 3.04E+01 9.23E-01 600.0 CPM CPM MONITOR ID: RM-VS-109 SPING CH7 (ASSUMES AUTO-PRESS CORRECTIONa UPSTREAM EAL WHOLE BODY THYROID RELEASE MIX: SQ TUBE RUPTURE -- ERS-SFL-82-023 Tab le 4 0. 5 2.18E-01 8.28E-02 b " U3' RELEASE FLOW: 6.OOCE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. 0 8.72E-01 3.31E-01 P*T" N. G. FR ACTION: 1.000 IODINE FRACTION: 1.000 20.0 8.72E+00 3.31E+00 125.0 5.45E+C1 9.94E+01 600.0 F CPM CPM MONITOR ID: RM-VS-109 SPINO CH7 (ASSUMCS AUTO-PRESS CORRECTIONS UPSTREAM EAL WHOLE BODY THYROID Ug g RELEASE MIX: WCDT RELEASE --- ERS-SFL-82-023 Table 5 0. 5 2.45E-01 0.OOE+00 RELEASE FLOW: 6.OOCE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. 0 9.78E-01 0.OOE+00 VMAP PNN N. C FR ACTION: 1.000 IODINE FRACTION: 1.000 20.0 9.78E+00 0.OOE+00 125.0 6.1 E+01 0.OOE+00 600.0 CPM SPM MONITOR ID: RM-VS-109 SPINO CH7 (ASSUMES AUTO-PRESS CORRECTIONa UPSTREAM EAL WHOLE BODY sHYROID N C1 A RELEASE MIX: FUEL HANDLING ACCIDENT --- ERS-SFL-82-023 Table 1 0. 5 2.18E-01 2.90E-01 V etG RELEASE FLOW: 6.OOCE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. 0 8.72E-01 1.16E+00 P rnN N. C. FR ACTION: 1.000 IODINE FRACTION: 1.000 20.0 8.72E+00 1.16E+01 125.0 5.45E+01 3.47E+02 6DQ-Q, CPM OPM MONITOR ID: RM-VS-109 SPING CH7 (ASSUMES AUTC-PRESS CORRECTION; UPSTREAM EAL WHOLE BODY THYROID RELEASE MIX: MAIN STEAM LINE BREAK --- ERS-SFL-82-023 Tab le 6 0. 5 2.03E-01 2.66E-03 NU 4 RELEASE FLOW: 6.OOOE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. 0 8.13E-01 1.07E-02 ydep
- N. C. FR ACTION: 1.000 IODINE FRACTION: 1.000 20.0 8.13E+00 1.07E-01 pq7g gg 125.0 5.08E+01 3.20E+00 600.0 gy CPM CPM ay M3NITOR ID: RM-VS-109 SPINO CH7 (ASSUMES AUTO-PRESS CORRECTIONa UPSTREAM EAL WHOLE BODY THYROID [7 RELEASE MIX:VCT RUPTURE --- ERS-SFL-82-023 Table 2 0. 5 2.26E-01 0.OOE+00 =m RELEASE FLOW. 6.OOCE+04 CFM 2.832E+07 CC/SEC X/Q: 8.900E-04 SEC/M3 2. 0 9.02E-01 O OOE+00 N. G FR ACTION: 1.000 IODINE FRACTION: 1.000 20.0 9.02E+00 0.OOE+00 9,r((g scA 125.0 5.64E+01 0.OCE+00 600.0 CPM CPM MONITOR ID: RM-VS-109 SP ING CH7 (ASSUMES AUTO-PRESS CORRECTION. UPSTREAM EAL WHOLE BODY THYROID N'T RELEASE MIX: CST RUPTURE --- ERS-SFL-82-023 TABLE 3 0. 5 2.45E-01 0.OOE+00 JAl g D RELEASE FLOW: 6.OOCE+04 CFM 2.832E+07 CC/SEC X/O: 8.900E-04 SEC/M3 2. 0 9.79E-01 0.OCE+00 N G FR ACTION: 1.000 IODINE FRACTION: 1.000 20.0 9.79E+00 0.OOE+00 125 0 6.12E+01 0.OCE+00 600.0 CPM CPM
I, I
I l X ADMON VERSION 1.I S/C5 S.F.LAVIE +
l MONITOR ID: RM-VS-109 SPING CH9 (ASSUMES AUTO-PRESS COR.s UPSTREAM FILTE EAL WHOLE BODY THY 2OID RELEASE MIX:LOCA-100% GAP ACTIVITY - EOO-SFL-82-023 TEL 7 TAs 1 0. 5 3.47E-C3 2.21E-04 **
EELEASE FLOW: 6.OOOE+04 CFM 2.832E+07 CC/SEC X/G: 8.900E-04 SEC/M3 2. O !.47E-02 8.84E-04 N.G. FRACTION:O.9000 IODINE FRACTION: 8.2500E-02 20.O 1.47E-01 8.84E-03 125.O 9.16E-01 2.65E-01 600.O CPM CPM MONITOR ID: RM-VS-109 SPING CH9 (ASSUMES AUTO-PRESS COR.s UPSTREAM FILTE EAL WHOLE SODY THYROID RELEASE MIX:LOCA-NO CORE DAMAGE - ERS-SFL-82-023 TBL 7 TAS 2 0. 5 3.72E-03 1.08E-04 KELEASE FLOW: 6.OOOE+04 CFM 2.832E+07 CC/SEC X/G: 8.900E-04 SEC/M3 2. O 1.49E-02 4.32E-04 N. G. FRACTION: O. 9000 IODINE FRACTION: 8.2500E-02 20.O 1.49E-01 4.32E-03 125.O 9.29E-01 1.30E-01 600.O CPM CPM i
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DuquesneUdt RADIOL ICAL CONTROLS SUBJECT CALC. No; In-Containment Hi-Range ARM Alarm set point ERS-SFL-82-002 swoe op -
REFERENCE DCP 303 EM JO CO OTHER Review Category X@XRsc Review Required O ll O ill O Oth.,
PURPOSE NOTES TO REVISION 1 Revision 1 was initiated to address several considerations that necessitate (
a change to the previously calculated alarm setpoints. These were:
- 1. A need for a consistent alarm setpoint basis for all emergency monitors was determined. Most effluent monitors were set on the basis of general emergency. The hi-range containment monitors were set for site emergency.
- 2. The EALs for general emergency were revised in 1985.
- 3. A less restrictive X/Q value was detennined in the work involved with the re-analysis of the DBA LOCA .
APPENDIX 1 implements this revision.
3 2
1 0 (S E E 0R1G1 NAL APPR0 VAL SH EET)
Rev. PREPARED BY / DATE CHECKED BY / DATE APPROVED BY / DATE DisTRl0ViloN Checklist Attachments a DOCUMFNT CONinoL lens-san! O Purpose /# Code List h rnal
[r RedHealth g6 Assumptions afro Print outs p[ Methodology / Derivations O Data sheets ha NOTD g dinput Data illustrations
'Results/ Conct u ho References (f'
g,p g yjg 0
., e
'Af Duquesm @
Environenental & Radiological Safety Programs [
SUOJECT CALC. No: #4 In-Containment Hi-Range ARM Alarm Set Point ERS-SFL-82-002 ,maad REFERENCE DCP EM JO CO Alara Review QA ATEGoRY IZ3 l Nuclear Safety Related O li O sil O oin.,
PURPOSE The aurpose of this calculation packane is to document the derivation of the ligh range in-containment radiation monitor alarm set point.
The calculation was based on that alarn settina that corresponded to an in-containment activity, which if released via penetrations, etc,to the environment, would cause downwind exposures at the site boundary to exceed the emergency action levels EAL) for a site area emer child thyroid ((assume one hour release ))gency (20 mrem /hr whole body,170 m This calculation encompassed several assunptions. In all cases, the assumption
. would result in an under-estimation of the monitor reading. Thus, with an actual instrument reading, the amount of activity within.the containment, the amount of activity released, and the downwind dose will' be conservative.
( Because of the complexity of this calculation, the overall problem was divided into portions. This calculation package will discuss these individual nortions in the order they were performed. Where appropriate, each section will identi-fy the assumptions and references used in that portion of the calculation.
3 _ ,
2 s // /// _/j A _ oA f 1 t Mhlv/7/7/% Xhmd X%rGL/et G 222&4M .3n h c Rev.
. $ hhific-PR! PAREDBY / DATE 9M.N CHECKED BY / DATE AllNlb2 $ 6/n/a INDEPENDENT REVIEW / cATE DISTRIBUTION Checkli$t At tachments
- 0 Cf4Nrpose / A O Code List yp' j7g R.M. Vento d* *u'"a t'oa$
d'8atout*
J.A. Kosmal #Methodomy/oerivations ar6ata sn is E.A. Schnell O ERS- File Mnput Data GHilustrations E Author GPIesults/ concs S.F.
Central LaFiles Vie (3)(2):ch43 a Nst- rise (Asterences DV444 e contrai F,ies 12i b SGF Fhyrcir i
j ., :
CALCULATION 2- COL ow M
- ^ a s _F 1
- _ I. Determination of Release Source Tenn 1
A. Purpose This portion of the calculation determines the radionuclide ratios in the containment and in the release cloud.
[ D. Assumptions
- 1. Containnent activity is equally dispersed throughout the contain-S- nent.
- 2. To determine ratios , the total containment airborne conc. will be l _ assumed to be 1 pCi/cc. This will be ratioed upwards on the
- l _
basis of internediate results.
1 The source of the activity is assumed to be primary coolant with 3.
1% Failed Fuel as tabulated in BVPS 1 FSAR table 148-6 l _ 4. The distribution of radionuclides in the containment is assumed to
_ be the same as the distribution in the primary coolant as follows:
20- --
100% noble gas transfer 50% halogens transfer 50% of transferred halogens plateout t -
_ 5. 50% of the containment leakage is assumed to be filtered with a filter efficiency of 95% for halogens and 0% for noble gases.
- 6. The distribution of radionuclides in the release cloud is assumed to be the same as the distribution in the in-containment atmos-phere except as nodified in #5 above.
3a[ 7. The activity in the containment atmosphere and in the releases will reach maximum at T = 0 and further the activity in the l containment will not be depleted by the release (0.1% vo10me/ day).
No radioactive decay is considered.
l
_ C. fiethod
~
- 1. For the noble gases identified in Table 148-6, the activity, in pCi/cc, in the coolant is transferred to the containment and is subsequently released. The radionuclide distribution is not changed. Refer to table 1 of this package 4o. 2. For the halonens, 50% of the coolant activity is initially released,
_ and 25% platesout. Thus, 25% of the coolant halogen inventory is available for release. Of this, 50% is leaked without filtration.
The remaining halogen is released thru 95% efficient filters. Thus, only .05 x .5 or .025 of the halogen is released via this pathway.
The total halogen release is then .525 I o. Ilhere lo = containment a t?mpber*> hilogen. Refer to table 1 of this package.
G m
CALCULATION g z., paamd.opd II. Determination of Dose Conversion Factors (Whole Body & Thyroid)
- A. Purpose This portion of the calculation documents the derivation of the dose conversion factors used to equate downwind concentration to downwind dose. Both whole body and thyroid dose conversion factors are determined. The whole body dose includes the contribution due to submersion in the halogen cloud as well as the contribution due to to- noble gases.
~
B. Assumptions See section II.C
_ C. Methods / Discussion
~
~
Submersion cloud dose I -
Regulatory Guide 1.109 Table B-1 provides dose conversion factors versus nuclide for noble gas radionuclides in units of mrem-m3/pCi-yr. Since 20- the dose rate from submersion in a cloud of radioactive noble gases is
_ not affected by time-dependent processes (biological processes), but is simply a dosimetric consideration, the table 0-1 dose conv'ersion factors
( can be converted to the more appropriate units of mrem-m3 /Ci-sec by multiplying the table B-1 values by a factor of 3.169E4.
l mrem - m3 _
1012 pCi I yr mrem - m 3
- Ci - sec Ci 3.1557E7 sec pCi - yr
~
l
/ mrem - m 3h
= 3.169E4 I
\ pCi - yr)l 30- Table B-1 does not provide conversion factors for the halopens that nay be released. Since the source docunent referenced by RG 1.109
_ was not readily available, it was decided to plot the known dose conversion factors versus the MeV/ disintegration for that radionuclide, and detennine the halogen dose conversion factors from this plot.
Figure 1 provides that plot. A best fit plot was drawn through the individual points (visually). RG1.109 referenced Meek & Gilbert as a data source for the MeV/ dis values. In plotting the data, however, it was noticed that photon energies fgm other data sources provided
. a better data fit, and these da'ta'"yhere appropriate. Table 2 documents the final dose conversion factors thus obtained.
Child thyroid inhalation DCF RG1.109 provides inhalation DCFs in units of mren/pCi uptake. These
_ values are based on a continuous exposure, in which the nuclide reaches equillibrium in the body--a condition that is not reached in a short-term exposure. Thus, the conversions are based on a higher % of the uptake activity actually remaining in the body. This results in a higher dose, and is thus conservative in this application.
- )
CALCULATION S -
E PAGE.__CF III. Determination of X/Q The X0Q/D0Q run for short term, mixed mode releases for the NW sector at the site boundary for the period 1/1/81 through 12/31/81 provided that the X/Q value for that sector exceeded 1.58E-3 sec/m3 only 5% of the time. Thus, this will be the X/Q value used.
The NW sector was chosen since this sector impacts Midland--the only ig_ population area close in to the site. Further, a review of the annual average for the other sectors indicated that the NW sector was also the most restrictive on the standpoint of joint frequency distribution data.
IV. Correlation of Downwind Dose to Release Rate l
_ A. Purpose i
This portion of the calculation package documents the determination of l
the release activity and containment activity based on the downwind 1 dose. '
20- B. Assumptions j
~
l Specified in text where applicable. '
k -
C. Method / Discussion The dose at a point downwind is found by the expression: t
= x
, DRj X/Q DCFj x Qt x Sj (1)
Where:
so- DRj = Dose rate, mrem /sec, attributable to nuclide 1.
, X/Q = Dispersion, sec/m3 DCF j = Dose conversion factors, mrem-m3/Ci-sec Qt =
Total Release Rate , Ci/sec
=
_ S j Fraction of the release rate for nuclide i t6 the nix as
, a whole.
For halogens, the thyroid dose is found by:
40-DRj * =
X/Q x BR a x DCFai x Q t
- S i x 10 " (2)
. Where:
=
- DR*I Dose commitment, mrem for each second of inhalation (based on 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> release) t due to a single nuclide--the total dose is the sum of the individual dOSUS
s CALCULATION A p. & "E wh J
BR a
= Breathing rate, m3 /sec, for age group a (taken to be child)
DCF ai
=
Dose commitment factor for age group a and nuclide i, mrem /pci
- 1012 = unit conversions, Ci/sec to pCi Io-From RG1.109 Table E-5, the average child inhales 37003m /yr. This equates to 10.13 m / day. Since the breathing rate accelerates during 3
day time hours or under stress, it is further assumed that 50% of the day's air is inhaled in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The breathing rate in this period is thus 1.76 E-4 m3 /sec.
A brief computer code was generated to facilitate repetitive calculations ,
and to minimize mathematical errors (rounding, etc). Two runs were l performed:
20- 1. The first run was based on the whole body EAL of 20 mrem /hr.
- 2. The second run was based on the thyroid EAL of 170 mrem.An one g hour release is assumed, as the FSAR provides that containment pressure control will be regained in a maximum of one hour.
Other input data included:
_ -- DCF's from section II of this calculation l X/0 from section III of this calculation 30- Sj from section I of this calculation (Q =1thusSj= t Qj)
TDOSE taken as 20 mrem /hr or5.5568-3 mrem /sec Thyroid Dose taken as 170 mrem per hour of inhalation or 4.722E-2 mrem per sec of inhalation.
The first run was performed with formula (1) and a dose rate calculated.
_ This dose rate was compared to the EAL dose (TDOSE) and a ratio deter-
_ mined. Since the formula was non-exponential, this ratio was used to correct the release rate to determine the release rate which would have 40-produced the desired dose rate. Once this release rate, in Ci/sec, was determined, it was converted to activity by dividing by the release flow rate of 589.9 cc/sec to determine the Ci/cc which was then converted to I -
pCi/cc. 589.9 cc/sec is based on:
~
_ 589.9 cc/sec = .1% vol/ day x 5.097E10 cc x hr/86400 sec vol e
6 l .
% s CALCULATION y RAGE Op Since no processes act on the radionuclide ratios other than filtration
- on the radioiodines, the determined release activity, pCi/cc, is the
_ basis of the containment activity. For noble gases, the release activity is taken as the containment a'ctivity. For radioiodines, the release activity was divided by the iodine filtration factor determined in section I.C.2 to determine the containment activity, o- The second run was performed in a similar manner usinj formula (2). In
. _ this run, only the radioiodine dose rates were used to determine the
! ' thyroid dose rate which was compared to the EAL and used to determine l the correction ratio. , However ,' once determined, this correction ratio was applied to the noble gas' release rates also. In this manner, the ratio between the radioiodines and noble gases in the release rate was i maintained. The containment activity was determined as identified above. {
^
Attachment 4 and attachment s provide a print-out of the data. There is no branching performed'inthis code. All input and output data used or determined is documented on these print-outs. Thus, no separate QC review of the code is provided.
20-
, _ V. Determination of Exposure Rate at Monitor Location
( -
Purpose l
A. l The purpose of this section of the calculation package is to detennine the exposure rate (in air) at the nonitor location.
_ B. Assumations ,
- 1. The problem geometry is best defined by a spherical source having 30-its center located at the locus of the contaiment axis and a horizontal plane established by the top of the crane wall. The radius of the sphere is bounded by the inside radius of the crane wall l _
(51' r = 1554.48 cm ). The volume of this sphere is 1.573 E10 cm3 .
This represents 31% of the containment free volume. The flux .
contribution thru the crane wall is considered to be negligible
, since the 24" thickness is equivalent to about 4 tenth-thicknesses i -
(1 MeV uncollided flux). For similar reasons, there is no consider-ation given to flux from containment areas below 767-10. The nonitors of interest are locateu away from openinos in the 767-10
_ floor. Figure 2 Hiustrates the spherical model used. Figure 3
- illustrates the derivat4n of the dose receptor distance (a + R).
Attachment 8 is an excerpt from ROCKWELL.
- 2. As discussed previously, the model will assume that the cortain-ment activity is equally dispersed throughout the containment free
_ volume. The model, however, will analyze only that portion of
, the dispersed activity encompassed by the assumed sphere.
s a
CALCut.ATION A M gg z. PAGElW 3.
The models provided in section I-7.1 (p368) of ROCKWELL are assumed to be appropriate for this use. Consideration had been given to using a semi-infinite cloud model. Mowever, such models
_ are appropriate only if the radius of the cloud was large in .
_ relation to the photon mean free path (1/u). Since u is on the I order of 0.0004 cm-1, this condition does not exist in this appli-cation. The finite cloud models described in llASH-1400 and in Meteorology and Atomic Energy assume a dynamic situation (wind speed, etc) and are therefore not readily adaptable to this application.
,o_ C. Model Input Data
- 1. Attenuation Coefficient 1
The attenuation coefficient used in the model to determine the l self-absorption distance (Z) was determined for a water vapor- l
_ air mixture. Saturation was assumed.
l Section 14.3.4.1 of the BVPS FSAR provides that in a LOCA (double ended rupture with minimum ESFs), the maximum pressure in containment is 38 PSIG (52.7 PSIA) and a peak temperature of 2680 F. The initial l containment pressure and temperature were assumed to be 9 PSIA and 20- 1000F respectively.
~
With the infusion of the steam, the air mixture in the containment heats with a resulting increase in pressure:
Po _
Pf T~ T 9 P (100 + 460) _ (268 + 460)
Pf = 11.7 PSIA 3o-Since the total pressure equals the sum of the partial pressures, the vapor partial pressure is 52.7 - 11.7 or 41 PSIA. From the
- steam tables, Tsat = 268.80 for a pressure of 41 PSIA. 41 PSIA is numerically equivalent to 5904 lbm/ft 2. The mass associated with this partial pressure can be found as follows:
MjRjT
- Pj = y tihere: Pj = partial pressure, substance i, in Ibm /f t 2, 5904 40-Mj = Mass, Ibm Rj = Gas constant = 1546/(molecular weight)
- Marks Standard Handbook for tiechanical Engineers p4-18 M
6
m _ _ _ _ _
= CALCULATION
& *Aos o' T = Temperature (absolute) (728 O) R
- V = Volume, ft3 (1.8 E6)
[ This expression can be re-arranged to solve for the nass:
PjV Mj =
to-RT i
~
For water, Rj= 1546/18 = 85.89 Substituting:
~
- (5904)(1.8E6) = 1.7ES lbmvapor M4= (85.89)(728) 2 For air, Rj = 53.35*, P4 = 1684.8 lb/f t Mj = (1684.8)(1.8E6) =
20 (53.35)(728) 7.81 E4 lbma ir The trtal mass is 1.7E5 + 7.81E4 or 2.48E5 lbm. The density of
(
the r.oxture is 2.48E5/1.8E6 = 0.1378 lbm/ft3 or 2.208E-3 g/cc.
. The ratio of vapor to air by mass is:
~
1.7E5 7.81E4 2.48E5 2.48E5 = .685/.315 Values of the mass attenuation coeff., p/p (cm2 /g), for air and
- water at the various energies were taken fPom the Radiological 3o. Health Handbook (RHH) ppl38,139. Since the ROCKWELL models are based on linear attenuation, the RHH values for a given energy were multiplied by the mixture density of 2.208E-3 g/cc. These v'alues were then multiplied by the respective fractions and the two results summ'td to obtain the overall p for that particular energy. This was repeated for all energy groups. Attachment 9 documents this calculation.
- 2. Source Term The previously reviewed code "XSOURCETf1" (ERS-SFL-82-001) was used to convert the containment activity derived in section IV.C of this 40- calculation into the proper MeV/cc-sec source term required by the
_ model. Since the thyroid-related source term is more restrictive,
_ this source term was used in subsequent steps in this calculation.
Attachment 11 documents this calculation.
- Marks, IBID 6
6
catcutary DDuquesneLight F"5;j., 12g.
- 3. Build-up Factor.
See addendum #1
- 4. Self-absorption 10-
_ ROCKWELL provides empirical graphs of Z/R versus su (a + R) for various values of a/R. However, the graph does not extend to a + R) less than 1. Since the curve is reasonably values linear inof tpb(is region, linear regression was performed to determine values of Z/R. The linear regression was based on the expression:
. Z/R =
{ .054468){us (a + R)) + .692616 The numerical constants in this expression were determined thru the use of a TI sof tware module proaram. 16 points between 1 and 4.5 were used to define the line. The approximation is based on a 20- a/R of .3 (477.52/1554.48). Since ps(a + R) is eneroy dependent,
. Z/R, and Z are therefore energy dependent.
~
The self-absorption, usZ for each group was calculated. Refer to
[- Attachment 9.
- 5. Determination of Theta (e)
From ROCKHELL, the value of a can be shown to be equal to:
h
- e = arctan,[a +R Z l 30-Refer to Attachment 9.
_ 6. Attenuation ROCKWELL provides that the attenuation term is equivalent to:
El (b 2 ) - Ei (b2 sec e) where b2=b psZ .t With no external s shieTds, b l = ux, where x=a (477.52),y p +is the total mixture u
_ The values of the exponential integral E l(x) was found by the numerical approximation:*
'0-E (x) = ga +ax+ax2+ax3+ax4 g 3 2 3 q +axs 3 -In(x)
- Handbook of Mathematical Functions, Abramawitz and Stegun 15.1.53 t Code listing and prinout uses a different definition of b i, b 2, b 3. See
- footnotes on printout.
6 e
~
h y_ p__ PAGE CF where:
ao
= .57721566 ai = .99999193
_ a2 = .24991055 a3 = .05519968 a4 = .00976004 a5 = .00107857 The referenced document provides an error estimate of <2 E-7
- 7. Dose Conversion Factors
~
_ The flux to dose conversion factors are found as follows. Basic concepts:
-- 1 R equals 87.7 ergs in 1 gm of air 1.6 E-6 erg /MeV 20-DR = (k)(pir)(4)E a EEEDCF = (k) pair
- I R - gm N .6E-6 1 ergY3600 secV1000 mR\= 6.568E-2 mR - sec- gm k= i
( -
(87.7 ergp MeV A hr /( R ) hr-MeV j
[ Since ap ir = cm 2fg:
DCF = mR-sec-cm2 6.568E-2uir) a hr-MeV In this usage, u is the mass-energy absorption coeff in cm 2/g for 30, air, as determined from the RHH p140. The air dose is calculated in lieu of the usual tissue dose, since the detector is a parallel plate ionization detector which measures roentgen.
- 8. Final Calculation ROCKWELL provides:
} 4 =
2/3 BSy R{El (b2 ) - E (b y 2sece Incorporating the DCF: 4 DR = 2/3 BSy R{El(b2 ) - E l(b 2 sece}}DCF
~
Reviewing units: mR/hr = (MeV/cc-sec) x (cm) x(mR-sec-cm2/hr-MeV) Attachment 10 provides the tabular results of this calculation. 6 6
D CALCULATION g ERS-SFl.-82-002 b gg D. Results
}
The total exposure rate was determined to be 314 R/hr. This
- equates to a thyroid dose of 170 mrem per hour of inhalation
_ and a whole body submersion dose rate of 1.2 aren/ hour (less whole contribution due to radiciodine gas submersion). VI. Determination of Monitor Dose Rate from Exposure Rate to- The vendore response graph, Attachment 12 was used to determine the _ instrument response factor for each energy group. These response factors were multiplied by the respective exposure rate to determine the contribution of that energy group to the total instrument reading. Attachment 13 documents this calculation. The final instrument reading is 68-fr1 R/hr. So 97
- VII. Summary .
_ N Based on the work contained in this calculation packaae, it is recommended that the in-containment radiation monitor alarm be set at -3E1 li/hr.M ApysgM
- It is further recommended that the methodology contained herein be
_ applied in a procedure, providing for different source term mixes ( _ (normal coolant,1% FF,10% melt, DBA, etc) and incorporating real-time dispersion. e m W h 6 30-W M W W m e e O e e e 9 e m 6
o MS 7Radiological A 5 MUSEne @ Controls Department ERS-SFL-82-002 /1\ Appendix 1
- 24b '24 Revision to original results The nature of the needed revisions makes it possible to apply correction factors to the original results. Thus, it was unnecesary to revise any of the text of the original calculation package.
DISCUSSION The basis of the 31 R/hr alarm setpoint detennined in revision 0 of this package was 170 mrem thyroid dose conunitment for one hour (effectively 170 mr/hr) and the X/Q value was 1.59E-3 sec/m3, In 1985, the EALs were revised to: Whole Body Thyroid U.E. 0.5 0.5 mrem /hr i Alert 2.0 2.0 mrem /hr Site 20.0 20.0 mrem /hr General 125.0 600.0 mrem /hr ; 1000 mrem 5000 mrem In RSC 01-86, a decision was made to base the Hi or alert alarm on the dose rate criteria, and the dose criteria would be the basis of the High or High-High alarm, whenever possible. This would lead to a consistent interpretation of the alarms. In the re-analysis of the DBA LOCA in 1983, a new X/Q value was determined and new containment source terms developed. The new X/Q was 8.91E-4 sec/m3 While it might have been necessary to re-evaluate the source term used in this package the nuclide ratioes, upon which both of these package were based, rather than the actual magnitudes, did not change significantly enough to warrant a total recalculation of this package. It is noted that the new DBA did not take credit for any release filtration, whereas ERS-SFL-82-002 took credit for 50% filtration. In light of the other significant uncertainties inherent in this alarm set point calculation, this additional uncertainty is tolerable. If the X/Q decreases, the release rate must increase to counter the improved dispersion, if the offsite dose is to remain constant. If the offsite doses are to be reduced, the release rate and hence the monitor reading must also decrease, if we assume the leak rate to remain constant. ; We will assume that the leak rate would continue for only 1 hour. The inter-pretation of the two alarm levels is: Hi A general emergency could be occuring if the containment were to leak at greater than design leakrate. If the leak was at design rate, the site boundary dose rate would be 125 mr/hr whole body or 600 mr/hr thyroid. Hi-Hi If the containment leaks at the design rate
d5 7tg 4 g g ERS-SFL-82-002 /i\ Appendix 1 p.go 24co r 24 Radiological Controls Department protective actions will be necessary at the site boundary and a general emergency should be declared. CALCULATION 31 R/hr x 600/170 x 1.58E-3/8.91E-4 = 194.0 R/hr 31 R/hr x 5000/170 x 1.58E-3/8.91E-4 = 1616.8 R/hr RECOMMENDATION The Hi alarm should be set at 200 R/hr. The Hi-Hi alarm should be set at 1600 R/hr* (background is negligible on these monitors) Postcript A thumbrule can be derived from the data in this package to equate the high range monitor reading with offsite dose. This is only a thumb rule. The dome monitor reads 31 r/hr when the offsite dose was 170 mr/hr thyroid with a X/Q of 1.58E-3. Under these conditions, the associated whole body dose was 0.003306 mr/sec = 11.9 mr/hrt* We first divide out the X/Q value: 170 mr/hr / 1.58E-3 sec/m3 = 1.076E5 mr-m3/hr-sec 11.9 mr/hr / 1.58E-3 sec/m3 = 7.533E3 mr-m3 /hr-sec Divide out the dome monitor reading: 1.076E5{r- ec
- 31 R
=
3.471E3{- c- Thyroid 7.533E3 *# - s
- 31 R
=
2.430E2 [ - ec hr Whole Body These last two results can be applied to actual X/Q and dome readings as follows: X/Q x Dome Reading x Conversion = Offsite dose.
- rounded down due to the limited scale resolution (logarithmic scale).
** See attachment 5 of ERS-SFL-82-002 R0 to find the 0.003306 mr/sec value.
- _ _ _ . _ - . _ . _ _ _}}