ML19261E195
| ML19261E195 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/30/1979 |
| From: | NORTHEAST UTILITIES |
| To: | |
| Shared Package | |
| ML19261E192 | List: |
| References | |
| CDF-C112, PROC-790630, TAC-8116, NUDOCS 7907050261 | |
| Download: ML19261E195 (88) | |
Text
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cdf-cll2 OFFSITE DOSE CALCULATION MANUAL FOR THE MILLST01.E NUCLEAR POWER STATION UNITS 1 & 2 DOCKETS:
No. 50-245 No. 50-336 June 1979 790EdhoNS
OFFSITE DOSE CALCULATION ttANUAL TABLE OF CONTENTS Section Page No.
Rev. No.
Date?
A.
Introduction A-1 0
B.
Responsibilities B-1 0
C.
Liquid Dose Calculations C-1 0
C1.
Quarterly - Total Body Dose C-1 0
a.
tiethod 1 - Either Unit C-1 0
b.
?!ethod 2 - Either Unit C-2 0
c.
flethod 3 - Either Unit C-3 0
C2.
Quarterly - tiaximum Organ Dose C-4 0
a.
flethod 1 - Either Unit C-4 0
h.
tiethod 2 - Either Unit C-5 0
C3.
Annual - Total Body Dose C-6 0
C4.
Annual - tiaximum Organ Dose C-7 0
C5.
?!onthly Dose Proj e c tions a.
Unit 1 C-8 0
b.
Unit 2 C-9 0
C6.
Quarterly Dose Calculations for Semi-Annual Ra<iioactive Effluent Report C-10 0
D.
Gaseous rose Calculations Dl.
10CFR20 Limits (" Instantaneous")
D-1 0
a.
Noble Gases D-1 0
b.
lodines, Particulates and Other D-2 0
U2.
Appendix I - Noble Gas Limit:
D-3 0
a.
Quarterly Air Dose - t!cthod 1 D-3 0
b.
Quarterly Air Dose - tiethod 2 D-4 0
c.
Annual Air Dose D-5 0
&Rev. 0 = June 1979 q,
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TABLE OF CONTENTS (Centinued)
Section Page No.
Rev. No.
Datea D3.
Appendix I - Iodines +
Particulates D-6 0
a.
Quarterly Doses - Unit 1 D-6 0
b.
Quarterly Doses - Unit 2 D-7 0
D-8 0
c.
Annual Doses - Both Units D-9 0
D4.
Flonthly Dose Projections D-10 0
a.
Unit 1 D-10 0
D-11 0
b.
Unit 2 D-12 0
D5.
Quarterly Dose Calculations for Semi-Annual Report D-13 u
D6.
Compliance with 40CFR190 D-14 0
E.
Liquid Plenitor Setpoint Calculations E-1 0
El.
til Liquid Radwaste Ef fluent Line E-1 0
E2.
til Service Water Ef fluent Li,e E-2 0
E3.
F12 Clean Liquid Radwaste Effluent Line E-3 0
'4 F12.'.erated Liquid Radwaste Ef fluent Line E-4 0
E5.
t!2 Steam Generator Blowdown tionitor E-5 0
E6.
t12 Condenser Air Ejector flonitor E-6 0
E7.
F12 Rx B l d g. Closed Cooling Water tionitor E-7 0
E8.
ft2 RWST and Condensate Surge Tank Level Indicators E-8 0
F.
Gaseous - flonitor Setpoint Calculations F-1 0
Fl.
til llydrogen tionitor F-1 0
7:Rev. 0 - June 1979 2',y J
TABLE OF CONTENTS (Continue <l)
Section Page No.
Rev. No.
Date' F2.
til SJAE Off Gas tionitor F-2 0
F3.
M1 Blain Stack Nobb' Gas tionitor F-3 0
F4.
M1 Main Scack Sampler Flow Rate flon i to r F-4 0
FS.
M2 Stack Noble Gas ?!onitor F-5 0
l'Re v. 0 = June 1979
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APPENDICES Re,
No.
Datei Appx. A - Decivation of Factors for Section C.1 - Liquid Doses 0
Appx. B - Derivation of Factors for Section C.2 - Livluid Doses 0
Appx. C - Li<1uid Dose Calculations - LAD TAP 0
Appx. D - Derivation of Factors for Section D -
Gaseous Doses 0
Appx E - Gaseous Dose Calculations - GASPAR 0
Appx. F - Gaseous Dose Calculations - AIREM C
Rev. 0 = June 1979 m
j G
I
Rev. O A.
INTRODUCTION The purpose of this manu, is to provide the parameters and methodology to be used in calculating offsite doses and effluent monitor setpoints at the Flillstone Nuclear Power Station.
Included are methods for determining maximum indP idual whole body and organ doser due to liquid and gaseous effluents to assure compliance with the dose limitations in the Technical Specifications.
Also included are methods for performing dose projections to assure compliance with the liquid and gaseous treat-ment system operability sections of the Technical Specifications.
The manual also includes the methods used for determining quarterly individual and population doses for inclusion in the Semiannual Radioactive Effltents Release Report.
Another section of this manual discusses the methodology to be used in determining eftluent monitor alarm / trip setpoints to be used to ensure compliance with the instantanecus release rate limits in the Technical Specifications.
The bases for some of the factors used in this manual are included as appendices to this manual.
This manual does not include the surveillance procedures and forms required to document compliance with the surveillance requirements in the Technical Specifications.
All that is included here is the methodology to be used in performance of the surveillance requ.rements.
Most of the calculations in this manual have two or three methods given f or the calculation of the same pa rame te r.
These metbods are arranged in order o.
simplicity and conservatism, Method 1 being the easiest and most conservative.
As long as releases remain low, one should be able simple estimate of the dose.
If release calculations to use Method I as a approach the limit however, more detailed yet less conservative calculations may be used.
a more detailed calculation may be used in lieu of a simple At any time calculation.
This manual is written common to both Units I and 2 since some release pathways are shared and there are also site release limits involved.
These facts make it impossible to completely separate the two unit calculations.
9 o
o a
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J A-1
Rev. O B.
RESPONSIBILITIES All changes to this manual shall be reviewed by the Site Operations Review Committe e prior to implementation.
All changes and their rationale shall be documented in a monthly operating report within 90 days of the date of SORC review.
It shall be the responsibility of the Station Superintendent to ensure that this manual is used in performance of the surveillance requirements specified in the Technical Specifications.
9
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B-1
Rev. O C.
LIQUID DOSE CALCULATIONS C.l.a Quarterly - Total Body Dose - Method 1 - Either Unit Step 1-Determine C = total gross curies of fission and activation p
products, excluding tritium and dissolved noble gases, released during the calendar quarter.
Step 2-Determine C total curies of tritium released during the T
calendar quarter.
Step 3-Determine D
= quarterly dose to the total bm,
_a mrem.
D 1.4 x 10-
- CF + 4.9 x 10~
- CT (S Note 1)
T Step 4 -
If D
> 0.5 mrem, go to Method 2.
(Note 1) - See Appendix A for derivation cf these factors.
y tc, u cp a
C-1
e s
Rev. O C.1.b Quarterly - Total Body Dose - Method 2 - Either Unit Step 1-Determine the following curie release totals for the calendar quarter:
C
= Curies of Cs-134 134 C
= ur s of Os-1M 137 Curies of Co-58 58 C
= ur s
-60 60 C
= u es of Fe-M 59 C
= Curies of H-3 T
Step 2 - Determine V = total volume of dilution water discharged :!uring the calendar quarter, in gallons.
This should include all dilution flow and not just that during periods of discharge.
Step 3-Determine D
= quarterly total body dose, in mrem:
9 8
1/V (1.9 x 10 C134 + 1.5 x 10 C137 +
D x 10 C58 +
=
9 1.6 x 10 C60 +
x 10 C59 +
T (See Appendix A for derivatio.. of these factors)
Step 4 -
If D
> 1.0 mrem, go to Method 3.
9
,n
.l.;. q) q..-
i C-2
Rev. O C.I.c r]uarterly - Total Body Dose - Method 3 - Ei.her Unit if the calculated dose using Method 2 is greater than 1 mrem, use the NRC computer code LADTAP to calculate the liquid doses. The use of this code, and the input parameters are given in Environmental Programs Branch Procedure #EPB-IV-5-8, Liquid Dose Calculations - LADTAP.
This procedure is attached as Appendix C to the manual.
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C-3
Rev. O C.2.a Quarterly - Maximum Organ Dose - Method 1 - Either Unit Step 1-Determine C - total gross curies of fission and activation p
products, excluding tritium and dissolved noble gases, released during the calendar quarter - same as Step C.1.a.
Step 2 - Determine D
= qu er y se to the madmum organ in mrem.
QO F (See Appendix B for derivation of factor)
D
~
QO Step 3-If D
- " ' E QO O
r.
.. )
[
e Rev. O C.2.h Quarterly - Maximum Organ Dose - tiethod 2 - Either Unit if the calculated dose using flethod 1 is greater than 2 mrem, use the NRC computer code LADTAP to calculate the liquid doses.
The use of this code, and the input parameters are given in Environmental Programs Branch Procedure #EPB-IV-5-8, Liquid Dose Calculations - LADTAP.
This procedure is attached as appendix C to the manual.
-ou.
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C-s
Rev. O C.3 Annuai - Total Body Dose - Either Unit se to the total body for the calendar year as follows:
Determine D
=
YT D
=[D where the sum is over the first quarter through the present quarterLOfalbodydoses.
YT The following should be used as D T' (1)
If the detailed quarterly dose calculations requi ed per Section C.6 for the semiannual effluent report are compl'*e for any calendar quarter, use that result.
(2)
If the detailed calculations are not complete for a particular quarter, use the results as determined in Section C.I.
If D 3 mrem and any D determined as in Section C.1 was not (3) calcN,a>tedusingmethod3ofthatsection, Or recalculate D using QT Method 3 if this could reduce D to less than 3 mrem.
YT m-
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v C-C
Rev. O C.4 Annual - Maximum Organ Dose - Either Unit
=
se to the maximum organ for the calendar year as follows:
Determine DYO 8
9""#
"E*
D ph0 " " quarter maxinum organ doses.
YO
(
e sent The following guicelines should be used:
(11 If the detailed quarterly done calculations required per Section C.6 for the seniannual ef fluent report are complete for any calendar quarter, use that result.
(2)
If the detailed calculations are not complete for a particular c'ia r t e r, use the results as determined in Section C.2.
(3)
If different organs are the maxirtua for different quarters, they may be summed together and D can be recorded as a less than value longasthevalueislesskhan10 mrem.
Y as If D 10 mrem and any value used in its determination was (4) calcha)tedas in Section C.2 but not with Method 2, recalculate that value using Method 2 if this could reduce D t
1 ss than YO 10 mrem.
(I I ' d r3
[',3 C-7
Rev.
v k)
C.5.a Monthly Dose Projections - Total Body & Maximum Organ -
Unit 1 total body dose from the last typical
- Determine D' g =leted month as calculated per the methods Step 1-previously comp in Section C.1.
Step 2 - Determine D'MO = maximm' rgan dose from the last typical
- previously completed month as calculated per the methods in Section C.2.
Step 3-Estimate R = ratio of the total estimated valure of liquid batches to be released in the present month to the volume released in the past month.
Step 4 - Estimate R, = ratio of est.nated primary coolant activity for the present month to that for the past month.
Step 5 - Determine F = factor to be applied to estimate ratio of final curic release if there are expected differences in treatment of liquid waste for the present month as opposed to the past month (e.g., bypass of filters or demineralizers).
NUREC-16 or pmst experience should be used to determine the effcct of each form of treat at which will vary.
F = 1 if there are no expected diffe
..e s.
E estimated montly total body dose as f.
ws:
Step 6 - Determine D
=
MT D
= D'MT 1
2
- R
- R
- F MT E
estimated monthly maximum organ doce as follows:
Step 7-Determine D
=
MO
= D'MO 1
2
- R
- R
- F DM0
- - The last typical month should bn one without significant operational differences from the projected month.
For example, if the plant was down for refueling the entire month of February and startur is scheduled for Fbrch 3, use the last month of operation as the base month to estimate Fbrch's dose.
Oc, if there were no releases during September, do not use September as the base month for October if it is estimated that there will be releases in October.
o i -
- ,G G'
C-8
y Rev. O C.S.h Monthly Dose _Proj ections - Total Body + Maximum Organ -
Unit 2
=t tal body dose from the last typicalf Step _1 - Determine D'MT previously completed..onth as calculated per the method in Section C.I.
Step 2 - Determine D'MO = maximum organ dose from the last typ i ca l'A previously completed month as calculated per the methods in Section C.2.
- See footnote in Section C.5.a.
Step 3 - Estimate R = ratio of the total estimated volume of liquid y
batches to S released in the present month to the volume released in the past month.
S t e p '. - Estimate R = ratio of the total estimated volume of steam generator blowdown to be released in present month to the volume released in the past month.
fraction of curies released last month coming Step 5 - Estimate F
=
7 from steam generator blowdown.
curies from blowdown I
turies from blowdown + curies from batch tanks blep 6 - Estimate H, atiu of estimated secondary coolant activity for the present month to that for the past month.
Step _7 - Estimate R4 = ratio of estimated primary coolant activity for the present month to that for the past month.
Step 8 - Determine F = f etcr to be applied to estimate ratio of 2
final curie release if there are expected differences in treatment of liquid waste for the present month as opposed to the past month (e.g., bypass of filters or demineralizers).
NUREG-17 or past experience should be used to determine the effect of each form of treatment which will vary.
F = 1 2
if there are nc 'xpected differences.
F St<>p 9 - Determine Dg = estimated monthly total body dose ce follows:
F R, F
+F R R]
D 'T D'MT [(1 - F ) R1 4
2 1 2 3
=
M 1
F Step 10
' 2termine D
= estimated monthly maximum organ dose as follows:
M0 F
=
R F R R]
D '0 D'MO [(1 - F ) R1 4 2+F1 2 3 M
1 9
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C-9 L
Rev. O C.6 Quarterly Dose Calculations for Semi-Annual Radioactive Effluent ESFart Detaileil <1uarterly dose calculations required for the semi-annual Radioactive Effluent Report shall be done using the NRC computer code LADTAP-The use of this code, and the input parameters are given in Environmental Progra.;s Branch Procedure //EPB-IV-5-8, Liquid Dose Calculations - 1.ADTAP-This procedure is attached as Appendix C to this manual.
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C-10
Rev. O D.
CASEOUS DOSE CALCULATIONS D.l.a Instantaneous Noble Gas Release Rate Limits - Both Units The instantaneous noble gas release rate limit from the site shall be:
9 9
1 7
830,000 + 260,000 I where Q = Noble gas release rate from MP1 stack (fLCi/sec) 7 (j Ci/sec)
Q N ble gas release rate from MP2 vent u
2 See Appendix D for derivation of this limit.
As long as the above is 6 1, the doses will be 6 500 mrem to the total body and s 3000 mrem to the skin.
~ry n
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Rev. O D.1.b Release Rate Limit - I-131, Particulates With llalf Lives Greater Than 8 Days, and Radionuclides Other Than Ncble Gases With llalf Lives Greater Than 8 Days - Both Units (1) The release rate limit of I-131 from the site shall be:
9 Q,
1 10.8 + 0.58 -
- where, Q = Release rate of I-131 from ffP1 Stack - (p Ci/sec) 1 Q = Release rate of I-131 from MP2 Stack - (p Ci/sec) 2 (2) The.elease rate limit for particulates with half lives greater than 8 days from the site shall be:
1 2
g +3.5 I
Q = Release rate of total particulates with half lives greater 7
than 8 days from the MP1 Stack (p Ci/sec).
Q, = Release rate of total particulates with half lives greacer than8daysfromtheMP2 Stack (pCi/sec).
(3) The release rate limit of H-3 from the site shall be:
0 1
2 3
- where, 6 + 4.0 x 10 4
4.3 x 10 Q = release race of tritium from MP1 stack ( p Ci/sec)
Q = release rate of tritium from MP2 stack ( p C1/sec) 2 With releases within the above limits, the dose rate to the maximum organ will be less than 1500 arem/ year.
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u Rev. O D.2 Appendix I Noble Gas Limits D.2.a guarterly Air Dose - Method 1 - Both Units Total curies of noble gas released from Unit Step 1 -
Determine C,q =lendar quarter.
1 during th'e ca Step 2 - Determine C
= Total curies of noble gas released from Unit p
2 during th'e" calendar quarter.
Include all sources - ventilation, containment purges and waste gas tanks.
Step 3-Determine D ua y ga m se hom Unh 1 6raO.
QG1 D
QG1 "
N1 QB1 " 9"#
7 8"
(* #
Step 4 - Determine D D
QB1 N1 Step 5-Determine D
= quarterly gamma air dose from Unit 2 (mrad).
QG2 D
= 1.8 x 10 C
QG2 N2 Step 6 - Determine D
= quarterly beta air dose from Unit 2 (mrad).
D QB2 N2 Step 7-I rD mrad; or D 7 5 mr d, go to QG2 QB1 QB2
- See Appendix D for derivation of factors.
n-0 V- '
D-3
Rev. O D.2.b Quarterly Air Dose - Method 2 - Both Units MP2 -
For MP2 dose calculations use the GASPAR computer cede to determine the critical site boundary air doses. The procedure to use this code is given in Appendix E.
For the Special Location, enter the following worst case quarterly average meteorology:
X/Q's - 0.13 x 10 ' sec/m
( " ^EE " '*
-6
-2 D/Q
- 0.15 x 10 m
If the calculated air dose exceeds the Tech Spec limit use real time meterology.
MP1 -
For FTl dose calculations use the AIREM computer code to determine the critical location air doses.
The procedure to use this code is given in Appendix F.
The _. quarter 1978 joint frequency data should be used es input for the AIREM code.
The reason for this is given in Appendix D.
If the calculated air dose exceeds the Tech Spec limit, ese real time meteorology.
D-4
Rev. O D.2.c Annual Air Dose Limit Due to Noble Cases - Both Units Determine Dygy, DYG2' YB1 YB2
= g mm ar se and beta air dose for the calender year for Unit 1 or 2 as follows:
YG1 "
QC1' YB1 J
QB1 ""
YC2 QC2' YB2 "
QB2 where the sum is over the first quarter through the present quarter doses.
The fcilowing should be used as the quarterly doses:
(1)
If the detailed quarterly do'.e calculations reqyired per the section for the semi-annual effluent report are complete for any calendar quarter, use those results.
(2)
If the detailed calculations are not complete for a particular quarter, use the results as determined above in Section D.2.a or D.2.b.
quar [dbly#dbse was not caleb$btOb bs>ing Section D.2.0 -
> 10 mrad or D 20 mrad and any corresponding (3)
If D real time meteorology, rmcaltalate the quarterly dose using real time meteorology.
1 m
t a
c.a D-5
Rev. 0 D.3 Append ix I - Iodine and Particulate Doses D.3 a Quarterly Doses - Unit 1 (1) t!ethod 1 - Unit 1 Stro 1 - Determine C) = total curies of I-131 released in gaseous effluents from Unit I during the <ina rte r.
Sten _2 - Determine C = total curies of particulates with half p
lives greater than 8 days released in gaseous effluents from Unit I during the calendar quarter as follows:
Ste d - Determine D
= qu rterly thyroid dosr QT D
= 8.4 Cy (See Appendix D)
T Step _4 - Determine D quanerly dose to the maximum organ ( <
r thanthethh0roid:
u
=
1.' Cp (See Appendix D)
QO Sten _5 - The maximum organ dose is the greater of D rD it is greater than 5 mrem, go to Method 2. T QO' Wj ffethod 2 - Unit 1 Use the GASPAR code, as given in Appendix E, to determine the maximum organ dose.
For the Special Location, enter the following worst case quarterly average meteorology as taken from Appendix D:
3 X/Q's = 7.1 x 10' SEC/F1 D/Q
= 7.9 x 10 M~
Use the goat milk, vegetation and inhalation pathway in totaling the dose.
If the maximum organ dose is greater than 7.5 mrem, go to t!ethod 3.
(3) ffethod 3 - Unit 1 Use the GASPAR code with actual locations, real-time meteorology and the pathways which actually exist. at the time at those locations.
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D-6
Rev. O D.3.b Quarterly Doses - Unit 2 (1) Method 1 Step 1-Determine C = total curies of I-131 released in gaseous 7
effluents from Unit 2 during the quarter.
Step 2 - Determine C = total curies of particulates with half p
lives greater than 8 days released in gaseous effluents from Unit 2 during the calendar quarter.
Step 3-Determine C = total curies of tritium released in gaseous T
ef f' _ents from Unit 2 during the calendar quarter.
Step 4 - Determine D,= quarterly thyroid dose as follows:
D
= 250 C + 1.8 x 10-CT (See Appendix D) 7 Step 5 - Determine D
= quarterly dose to the maximum organ other than be thyroid:
D (Se App ndix D)
QO P
T Step 6 - The maximum organ dose is the greater of D rD T
QO' If greater than 5 mrem, go to Method 2.
(2) Method 2 Use the GASPAR code, as given in Appendix E, to determine the maximum organ dose.
For the Special Location, enter the following worst case quarterly average meteor, logy as taken from Appendix D:
X/Q's = 0.13 x 10-sec/M
-6 D/Q
= 0.15 x 10 M-As shown in Appendix D, the sar e meteorology can be used for both continuous and batch releases.
Therefore, the program need only be run once using the total curies from all releases from Unit 2.
fne procedure to use the GASPAR code is given in Appendix E.
Use the goat milk, vegetation and inhalation pathways in totaling the dose.
If the maximum organ dose is greater than 7.5 mrem, go to Method 3.
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D-7
Rev. 0
,3)
Method 3 - Uni _t- _2 Use the GASPAR code with actual locations, real-time metiorlogy and the pathways which actually exist at the time at these locations.
The code should be run separately for ventilation teleases, contain-ment purges and waste gas tank releases.
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U D-8
Rev. O b.3.c M..imand zan - Annua 1 Doses - Both Units Det' :ane D and D
= maximum organ dose for the calendar year for
.nlgl gyg2eh as f o Hows -
Y unit.
3D
= sum of quarterly madam organ doses where the sum D
=
isoverfhefirsk0 quarter through the present quarter doses.T yg g The following guidelines should be emed for use of D QO (1)
If the detailed quarterly dose calculations required per the section for the semi-annual effluent -^nort are complete for any calendar quarter, use those results.
(2)
If the detailed calculations are not complete for a particular quarter, ese the results as determined above in Section D.3.a or D.3.b.
is greater than 15 mrem and any quarterly dose was not (3)
IfD,,katedusingMethod3ofSectionD.3.aorD.3.b, recalculate cc. lc u the quarterly dose using Method 3.
(4)
If different organs are the maximum organ for different quarters, thcy can be summed together and D recorded as a less than value y
as long as the value is less than 5 mrem.
If it is not, the su.n for eaci. organ involved should be determined.
'l si e
1 D-9
Rev. O D.4 Caseous Effluent Menthly Dose Projecticns D.4.a Unit 1 (1) Due to Gaseous Radwaste Treatrient System (Offgas)
Step 1 - If it is expected that the augmented offgas treatment system will be out of service during the month, go to Step 7.
Otherwise, continue with Stepe 2 through 6.
Step 2 - Determine C'
= number of curies of noble gas released during the most recent month of operation from the augmented offgas system.
Step 3-Estimate R = ratio of expected full power offgas rate y
at the air ejector for the upcoming month compared to the reference month of Step 2.
Step 4 - Estimate R, u ratio of expected unit production capacity for the upcoming month compared to the reference month of Step 2.
E Step 5-Determine D
= s a
mn yg ma air dose.
MG D G (mr d) = 4.8 x 10-C'N 1 2 (Factor is from Appendix D)
E Step 6 - Determine D stimated monthly beta air dose.
=
MB iB N 1 2 (Factor is from Appendix D)
D Step 7-If the augmented offgas system is expected to be out of service during the month, determine the following:
Estimated curies /sec at the air ejector at Q
=
expected maximum power for the month.
estimated curie reduction factor from air r
=
ejector to stack via 30 minute holdup line (in decimal fraction).
d estimated number of days 30 minute holdup
=
pipe will be used.
E stimated mondily gamma air dose.
D
=
MG 4.8 x 10[ mrad /Ci x Q Ci/sec x rx d (day) x
=
8.6 x 10 sec/ day.
E D
MG m ' ' 'l
} },0 D-10
Rev. O E
D a ma n
y aar se.
MB E
0.04 x Q x r x d D
=
MB (2) Due to Ventilation System Releases Step 1 - For the last quarter of operation, determine D r
T D
as determined per Section D.3.a.**
QO Step 2 - Estimate R = expected ratio of primary coolant iodine levelfarkhecomingmonthascomparedwiththeaverage level during the quarter used in Step 1.
Step 3-Estimate R, = expacted ratio of primary leakage rate for the co$ing month as compared with the average leakage rate during the quarter used in Step 1.
E stimated monthly dose to the maximum Step 4 - Determine D
=
MO organ.
E D
(#
MO 1 2 QO QT
- - Ubichever was greater
- - Section D.3.b for Unit 2 eo
.o s,
')
D-ll
Rev. 0 D.4 b Unit 2 (1) Due to Gaseous Radwaste Treatment System E
the number of curies of noble gas to be Step 1-Estimate C
=
N released from the waste gas storage tanks during the next month.
E 9tep_2 - Determine D Y E#**"
MG D
(*
IG N
(Factor is from Appendix D for the Unit 1 stack releases since the Unit 2 waste gas tanks are discharged via the Uni-1 stack.
This factor should be conservative as the isotopic mix would only be the longer lived noble gases which would have lower dose conversion factors than the typical mix f rom Unit 1.)
y Step 3-DetermineDyB = estimated moathly beta air dose.
E
-7 E
MB (
D N
(2)
Due to Ve-ation Releases Use the.
method as given in Section D.4.2.(2) for Unit 1.
Poui{
O,.O d '; 0 D-12
Rev. O D.5 Ouarterly Dose Calculations for Semi-Annual Report Detailed quarterly dose calculations required for the Sc.ai-Annual Radioactive Effluent Report shall be done using the computer codes GASPAR and AIREM. The use of these codes and required input parameters are attached as Appendices E and F.
e,
,. /]
U D-13
Rev. O D.6 Compliance with 40CFR190 The following sources should be considered in determining the total dose to a real individual from uranium fuel cycle sources:
a)
Gaseous Releases frota Units 1 and 2 b)
Liquid Releases from Units 1 and 2 c)
Direct Radiation from the Site d)
Since all other uranium fuel cycle sources are grecter than 20 miles away, they need not be considered.
'. i "J s
2.!3 D-14
Fev. O E.
LIQUID MONITOR SETPOINTS E.1 M1 Liquid Radwaste Effluent Line The tr.p/ alarm setting on the liquid radwaste disca,rge line depends on dilution water flow, radwaste discharge flow, the isotopic composition of the liquid, the background count rate of the monitor and the efficiency of the monitor.
Due to the variability these carameters, an alarm / trip se* point will be deter ined prior to the release of each batch.
The following methodology will be used:
Ste d - From the tank isotopic analysis and the MPC values for each identified nuclide (including noble gases) determine the required reduction factor, i.e.
T Ci/ml of nuclide i R = Reduction Factor = 1 Y MPC of nuclide i Step 2 - Determine the existing dilution flow = D = # CIRC pumps x 100,000 gpm + # sc rvice water pumps x 10,000 gpm.
Step _3 - Determine the allowable disch rge flow = F F=0.1xRxD Note that discharging at this flow rate would yield a discharge concentration 10% of the Tech Spec Limit due to the safety factor of 0.1, Step 4 - Determine the total p Ci/ml in the tank.
Step 5 - Using the latest monitor calibration curve, determine the
" cps" corresponding to two times the total p Ci/ml determined in Step 4.
This will be the trip setpoint.
Note If discharging at the allowable dischacge rate as determined in Step 3, this would yield a discharge concentration 20% of the Tech Spec limit.
Step 6 - The allowable discharge flow rate calculated in Step 3 may be increased by up to a f actor of 5 wit h appropriate admin-istrat.ive controls.
0 E-1
'[-
U v
Rev. 0 E.2 fil Service Water Ef fluent Line The til Service Water Monitor Ili alarm setting is approximately 1.5 times the ambient background and the lii-Ili Alarm is approximately 2 times the ambient background reading on the monitor in counts per second.
r~
f*
i E-2
Rev. 0 E.3 t!2 Clean Lirluid Radwaste Effluent Line S. me' as S ion E.I for the r!1 Liquid Radwaste Monitor except for D - # CIRC Pumps x 135,000 gpm + # Service Water P n' s x 4 0
p) pag c.
u E-3
Rev. 0 E.4 f!2 Aerated Liquid Radwaste Effluent Line Same as E.3 for Clean Liquid flonitor.
j f 'i l -
f[ h ) U E-4
Rev. 0 E.5 M2 Steam Generatcr Blowdown Monitor Maximum possible total S.G. blowdown flow rate = 250 gpm Minimum possible circ water dilution flow during periods of blowdown =
270,000 gpm (2 pumps)
Unidentified MPC for unrestricted area = 1 x 10~ joCi/ml Therefore, the alarm setpoint should correspond to a concentration of:
x 1 x 10~
1.1 x 10jtCi/ml Alarm (ftCi/ml)
ghSS The latest monitor calibration curve should be used to determine the alarm setpoint in epm corresponding to 1.1 x 10 "ja Ci/ml.
~
This setpoint may be increased through proper administrative controls if the steam generator blowdown rate i: maintained less than 250 gpm and/or more than 2 circulating water pumps are available.
The percent increase would correspond to the ratio of the flows to those assumed above.
Note:
The Steam Generator Rlowdown alarm criteria is in practice based on setpoints required to detect allowable levels of primary to secondary leakage.
This alarm criteria is typic:lly more restrictive than that required to meet discharge limits.
This fact should be verified however whenever the alarm setpoint is recalculated.
A
- O
' ' ' t ',)
r, i
[I O E-5
+
Rev. 0 E.6 M2 Condenser Air Ejector Monitor This monitor is included as a liquid monitor since tue reason it's in the Technical Specifications is for control of the Steam Generator Blowdown liquid activity.
It can be used in conjunct on with or in place of the blowdown monitor t.o ensure that the blowdown concentration is within 10CFR20 limits.
Gateous release limits are not controlled by this monitor but rather by the monitor at the fn.al discharge point.
A detailed study was performed to determine the equilibrium steam generator blowdown activity as a function of blowdown rate and primary to secondary leakage rate.
It turns out that in order to reach 10CFR20 limits as 'letermined in Section E-5 the minimum primary to secondary leakage rate required is 0.4 gpm.
The air ejector monitor is set to alarm at a level corresponding to approximately 0.2 gpm leakage. Thus it ensures adequate control of blowdown.
The above values are for the primary coolant activity level used at the time of the study.
However, if the coolant activity increased such that the leakage rate requi red t o reach 10CFR20 limits was less, there would be an equal increase in the sensitivity of the air ejector monitor.
O m
eo
. 'O E-6
Rev. 0 E.7
@_F(fii_ctor Bldg._ Closed Cooling Water ffonitor alarm s(?tting is
- 1) proximately 2 times the ambient background O
eo e
L.,o u-E-7
Rev. 0 E.8 M2 RWST and Condensate Surge Tank Level Indicators Tank level alarms are set as follows.
Refueling Water Storage Tank:
High Level Alarm - Approximately 97 Percent of Tank Capacity Condensate Surge Tank:
Ifigh Level Alarm - Approximately 90 Percent of Tank Capacity
.s' I 's i
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- y E-8
Rev. 0 9
F.
GASEOUS MONITOR SETPOINTS F.1 M1 Hydrogen Monitor Per Section 3.8.D.6 of the Technical Specifications, the alarm setpoint shall be $ 4% hydco3,en by volume.
f.
{}
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F-1
e Rev. O F.2 M1 Steam Jet Air Ejector Of f f'as Monitor Per Section 3.8.D.7 of the Technical Specifications, the raxigum allowed nobic gas in-process activity rate shall not exceed 1.47 x 10 ft C1/sec.
This value will be more limiting than the instantaneous stack release rate limit.
Usingthelatestoffgasmonitorcalfbrationcurve,determinethereading in mR/IIR corresponding to 1.47 x 10 ftCi/sec. The alarm setpoint should be set at less than or equal to this value.
M
.)
[,
F-2
Rev. O F.3 M1 Stack Noble Gas Monitor Per Technical Specification 3.3.D.1 and ODCM Section D.1.a.
the instan-taneous release rate limit from the site shall be:
Q Q
l 2
830,000 + ~260,000
$ I f ror MP1 s tack (jt Ci/sec)
=
n o..: gas release rate where Q 7 noble gas release rate from MP2 ( <Ci/sec)
Q
=
/,ssume 50% of the limit is from MP1 stack.
Therefore Q should be less than 415,000 g Ci/sec.
The M1 stack noble gas monitor calibration curve (given as /sC1/sec per eps) is determined by assuming a maximum ventilation flow of 170,000.
Therefore, the alarm setpoint should be set at or below the " cps" corresprnding to 415,000 ftCi/sec from the calibration curve.
The alarm setpoint may be increased if the Unit 2 stack setpoint is at a level correspending to less than 50% of the site limit.
h g]
j E'
U, F-3
Rev. O F.4 til flain Stack Sampler Flow Rate t!onit or the til main stack sampler flew control alarms on low pressure indicating iuss of flow, or on high pressure indicating restricted flow.
The alarm w;!1 occur with either-a)
Pressure Switch (l1 < 2" lig or b)
Pressure Switch #1 > 18" lig and Pressure Switch #2 < 20" lig L
a g
F-4
i Rev. O F.5 MP2 Vent - Not,le Gas Monitor Per Section D.l.a of this manual, the instantaneous release rate limit fron the site shall bc:
Q Q
I 2
4 g
830,000 + 260,000 Assumi:ig 507. of the limit is from the Unit 2 vent, the release rate limit for Unit 2 is 130,000 ftCi/sec.
The MP2 vent noble gas monitor calibration curve (given as jeCi/sec per cpm) is determined by assuming the maximum possible ventilation flow for various fan combinations.
Curves for 3 different fan combinations are normally given.
The " cpm" corresponding; to 130,000 je Ci/sec should be determined from the appropriate curve.
The alarm setpofnt should be set at less than or equal rtis value.
e to The alarm setpoint may be increased if the Unit 1 stack setpoint is at level corresponding to less than 50% of the site limit.
a n
(, -
.Q s
L-F-5
Rev. O APPENDIX A DERIVATION OF FACTORS FOR SECTION C.1 - LIQUID DOSES 1.
Section C.1.a - Step 3 Millstone 1 - Liquid Doses C
D C
D Year Qtr.
F QT(F)
(mrem /Ci)
_H QT(H)
(mrem /Ci) 1976 1
8.60 7.6(-2) 8.8(-3) 5.12 ND 2
0.053 1.3(-4) 2.5(-3) 9.19 2.l(-6) 2.3(-7) 3 0.48 6.8(-3) 1.4(-2) 1.33 ND 4
0.15 1.3(-3) 8.7(-3) 4.42 1.9(-6) 4.3(-7) 1977 1
0.12 1.l(-3) 9.2(-3) 3.11 7.3(-7) 2 '1(-7) 2 0.36 4.6(-3) 1.3(-2) 0.64 1.3(-7) 2.0(-7) 3 0.012 1.1(-4) 9.2(-3) 0.002 8.0(-10) 4.0(-7) 4 0.028 1.5(-4) 5.4(-3) 0.66 2.3(-7) 3.5(-7) 1978 1
0.119 1.3(-3) 1.1(-2) 0.98 3.9(-7) 3.9(-7) 2 0.049 5.2(-4) 1.l(-2) 1.29 2.9(-7) 2.2(-7)
Millstone 2 - Liquid Doses
)
C D
C D
Year Qtr.
F QT(F)
(mrem /Ci)
H QT(H)
(mrem /Ci) 1976 1
0.102 1.8(-4) 1.8(-3) 34.7 1.2(-5) 3.4(-7) 2 0.179 2.4(-4) 1.3(-3) 87.3 2.7(-5) 3.1(-7) 3 0.037 0.9(-4) 2.4(-3) 70.0 2.0(-5) 2.8(-7) 4 0.025 1.0(-4) 4.0(-3) 85.4 3.7(-5) 4.3(-7) 1977 1
0.217 7.0(-4) 3.2(-3) 60.1 2.l(-5) 3.4(-7) 2 0.802 6.l(-3) 7.6(-3) 73.3 3.0(-5) 4.1(-7) 3 0.035 1.6(-4) 1.6(-4) 42.1 1.5(-5) 3.5(-7) 4 0.509 1.9(-3) 3.7(-3) 35.0 1.1(-5) 3.3(-7) 1978 1
0.432 5.2(-3) 1.2(-2) 1.8 8.9(-7) 4.9(-7) 2 1.27 6.6(-3) 5.2(-3) 43.6 1.2(-5) 2.7(-7)
- where, Curies of fission and activation products released C
=
F during calendar quarter.
Calculated total body &
' o the maximum individual D
=
F)
(mrem) due to fission and ivation products.
Dose calculated using computer cooe LADTAP.
'i v-Rev. O Curies of tritium released during calendar quarter.
C
=
H Calculated total body dose to the maximum individual D.
=
(mrem) due to tritium releases.
Dose calculated using computer code LADIAP-
- Unit 1 = 1.4 x 10-mrem /Ci Maximum Value of D p)/CF
_^
Unit 2 = 1.2 x 10 ' mrem /Ci
- Unit 1 = 9.3 x 10' mrem /Ci Average Value of D F)/Cp
-3 Unit 2 = 4.6 x 10 mrem /Ci
- Unit 1 = 4.3 x 10-mrem /Ci Maximum Value of D g)/CH Unit 2 = 4.9 x 10-mrem /Ci
- Unit 1 = 3.1 x 10~
mrem /Ci Average Value of D H)/CH Unit 2 = 3.6 x 10~
mrem /Ci
/C and D
/C are SincethemaximumvaluesobservedofD[bdambfacto9badbbused not much different forthetwounits,k for both units for simplicity.
Also, since the maximum values are less than 3 times the average values, this says that the dose per total curie does not fluctuate greatly, hence this method is not over-conversative.
-2 1.4 x 10 mrem /Ci D. F)/CF
=
4.9 x 10~
mrem /Ci g)/C D
=
H ri (9
g.,o e
~
Rev. 0 2.
Section C.I.b - Justification for Only Using Only Particular Nuclide flillstone 1 Liquid Doses - Nuclide Breakdown Percent of Dose Year Qtr.
Cs-134 Cs-137 Co-60 Mn-54 Ba-140 Co-58 Fe-59 1976 1
48 46 1
1 1
1 1
2 29 41 14 1
2 5
2 3
1 1
10 3
1 1
84 4
1 1
45 7
1 1
39 1977 1
26 30 33 4
1 1
1 2
42 47 9
1 1
1 1
3 38 45 9
1 1
1 1
4 24 35 18 1
1 19 1
1978 1
5 12 64 2
1 13 1
2 2
1 77 2
1 3
11 Avg.
22 26 28 2
1 4
14 tiillstone 2 Liquid Doses - Nuclide Breakdown Percent of Dose Year Qtr.
Cs-134 Cs-137 Co-60 Co-08 H-3 Fe-59 Mn-54 Zn-65 1976 1
1 4
7 35 8
38 3
1 2
1 30 5
17 11 30 1
1 3
1 5
10 38 28 3
1 9
4 2
7 4
31 37 16 1
1 1977 1
1 1
11 39 3
43 1
1 2
1 1
60 25 1
10 1
1 3
1 2
43 33 15 1
1 1
4 13 12 30 36 1
1 3
1 1978 1
3 3
68 20 1
1 4
1 2
5 5
56 21 1
3 5
1 Avg.
3 7
29 30 10 14 2
1 Listed above, are all of the nuclides which have contributed more than 1% to the quarterly total body dose during the past 2-1/2 years.
The only nuclides which have ever contributed more than 10% of the total body dose are for Unit 1:
Cs-134, Cs-137, Co-58, Co-60, and Fe-59 For Unit 2:
Cs-134, Cs-137, Co-58, Co-60, Fe-59, and 11-3 The average percent of the total body dose accounted for by these few nuclides is:
For Unit 1:
94%
For Unit 2:
93%
')
<;',9
(,,
i J
g Rev. O The minimum 1)ercent of the total body dose accounted for by these few nuclides in any one quarter is:
For Unit I-86%
For Unit 2:
84%
Therefore, using only these few nucIides fo r Method 2, the real dose should not exceed (1.0)/0.84=1.2 mrem.
P')
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L.
Rev. 0 3.
Section C.l.b - Step 3 13
) x 1012 pCi/Ci x 0.26 gal / liter x 1/5 x Dose due to Cs-134 =
7 1
x [21/4 kg x 4.0 x 10 pCi/kg per p Ci/ liter x 1.2 x 10~
mrem /pC +
1
-4 5/4 kg x 2.5 x 10 PCi/kg per pC/ liter x 1.2 x 10 mrem /pCi
-b 2
+ 100 1/m day x 67/4 hr x 0.5 x 748 day x 1.2 x 10 mrem /hr per pCi/m j
= 5.2 x 10 Cl34 [2.5 x 10~
+ 0.37 x 10'
+ 0.75 x 10-2) 10 V
9 1.9 x 10 Cl34/V
=
- where, Near field dilution factor (LADTAP) 1/5
=
Quarterly asage factor - Adult fish (Reg.
21/4
=
Guide 1.109)
Quarterly usage factor - Adult shellfish 5/4
=
Quarterly shoreline usage - teen (Reg. Guide 67/4
=
1.109) 1 Cs bioaccumulation factor - saltwater fish 4.0 x 10
=
Cs bioaccumulation factor - saltwater shellfish 2.5 x 10
=
(Reg. Guide 1.109) 1.2 x 10 Cs-134 ingestion dose conversion factor - adult total body (Reg. Guide 1.109)
Proportionality factor from Reg. Guide 1.109 100
=
Shore width factor (Reg. Guide 1.109) 0.5
=
Half life of Cs-134 748 days
=
1.2 x 10' External dose factor for shoreline pathway for
=
Cs-134 - total body - (Reg. Guide 1.109)
P
\\
,;. ]
v" L
Rev. O Likewise, dose due to Cs-137 1
= 5.2 x 10 137 [21/4 x 4.0 x 101 10 x 7.1 x 10-5 + 5/4 x 2.5 x 10 4
-9
.692 x 15
-5 + 100 x 67/4 x 0.5 x 1.1 x 10 x 4.2 x 10 x (1-e -
x 7.1 x log 30 l1.5 x 10
^C
=
l37
- where,
-5 Cs-13'i ingestion dose conversion factor - adult 7.1 x 10
=
total body (Reg. Guide 1.109) 1.1 x 10 IIalf life of Cs-137 in days
=
-9 4.2 x 10 External dose factor for shoreline pathway
=
for Cs-137 - total bedy (Reg. Guide 1.109) 15 Period of time sediment is exposed to the
=
contaminated water, in years - from Reg.
Guide 1.109.
30 Half life of Cs-137 in years all other terms
=
are defined above.
Likewise, dose due to Co-58 10 2
= 5.2 x 10
[21/4 x 1.0 x 10 x 1.67 x 10-6 + 5/4 x 1.0 x 10 x 1.67 x 10-6 + 100 x 67/4 x 0.5 x 71 x 7.0 x 10~9) 1.8 x 10
- C
/, where
=
58 1.0 x 10
=
Co bioaccumulation factor - saltwater fish (Reg.
Guide 1.109) 1.0 x 10 Co bioaccumulation factor - saltwater shellfish -
=
-6 1.67 x 10 Co-58 ingestion dose conversion factor - adult
=
total body - (Reg. Guide 1.109) 71
=
Half life of Co-58 in days.
7.0 x 10' External dose factor for shoreline pathway for
=
Co total body (Reg. Guide 1.109) 9 n
'}
(u -
s Rev. O All other terms are defined above.
Likewise, dose due to Co-60
)10 C60 [21/4 x 1.0 x 10 x 4.7 x 10-6 + 5/4 x 1.0 x 2
= 5.2 /
7 x 10 x 4.7 x 10
+ 100 x 67/4 x 0.5 x 1.9 x 10 x 1.7 x 10~
.693x15g l-e 5.2 9
=
1.6 x 10 x C !
60
- where,
-6 4.7 x 10 Co-60 ingestion dose conversion factor - adult
=
total body (Reg. Guide 1.109)
IIalf life of Co-60 in days 1.9 x 10
=
1.7 x 10~
External dose factor for shoreline pathway for
=
Co total body (Reg. Guide 1.109)
IIalf life of Co-60 in years.
5.2
=
All other terms are defined above.
Likewise, dose due to Fe-59 0
3
= 5.2 x 10 C59/V [21/4 x 3.0 x 10 x 3.9 x 10"
+ 5/4 x 2.0 x 10 x 3.9 x 10-6 + 100 x 67/4 x 0.5 x 45 x 8.0 x 10-9]
8.3 x 10 C_9/V
=
3 where 3.0 x 10 Fe bioaccumulation factor - saltwater fish (Reg.
=
Guide 1.109) 2.0 x 10 Fe bicaccumulation factor - saltwater shellfish
=
(Reg. Guide 1.109) 3.9 x 10 Fe-59 ingestion dose conversion factor - adult
=
total body (Reg. Guide 1.109) 45 IIalf life of Fe-59 in days.
=
8.0 x 10' External dose factor for shoreline pathway
=
for Fe total body (Reg. Guide 1.109)
{
"'i
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Rev. O Likewise, dose due to H-3, 10
-1
= 5.2 x 10 CT/V [21/4 x 9.0 x 10 x 1.05 x 10~
+ 5/4 x 9.3 x 10 x 1.05 x 10~7]
-1 3.2 x 10
CT/V
=
- where,
~1 H-3 bioaccumulation factor - saltwater fish 9.0 x 10
=
~1 H-3 bioaccumulation factor - saltwater shellfish 9.3 x 10
=
-7 11-3 ingestion dose conversion factor - adult 1.05 x 10
=
total body (Reg. Guide 1.109)
^
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Rev. O APPENDIX B DERIVATION OF FACTORS FOR SECTION C2 - LIQUID DOSES 1.
Section C.2.a - Step 2 flillstone 1 - Liquid Doses Year Qtr.
F tiax. Organ QO Q0 F 1976 1
8.60 GI (LLI) 0.054 0.0062 2
0.053 GI (LLI) 0.0003 0.0056 3
0.48 GI (LLI) 0.059 0.123 4
0.15 GI (LLI) 0.0057 0.038 1977 1
0.12 GI (LLI) 0.0021 0.018 2
0.36 GI (LLI) 0.0041 0.011 3
0.012 GI (LLI) 0.00017 0.014 4
0.028 GI (LLI) 0.00086 0.031 1978 1
0.119 GI (LLI) 0.024 0.202 2
0.049 GI (LLI) 0.0031 0.063 tiillstone 2 - Liquid Doses D
D Year Qtr.
F_
tlax. Organ QO QO F 1976 1
0.102 GI (LLI) 0.0017 0.016 2
0.179 GI (LLI) 0.0051 0.028 3
0.037 GI (LLI) 0.0024 0.065 4
0.025 GI (LLI) 0.00075 0.030 1977 1
0.217 GI (LLI) 0.012 0.055 2
0.802 GI (LLI) 0.036 0.045 3
0.035 GI (LLI) 0.0014 0.040 4
0.509 GI (LLI) 0.012 0.024 1978 1
0 432 GI (LLI) 0.039 0.090 2
1.27 GI (LLI) 0.13 0.120
- where, C
=
Curies of fission and activation products released F
during calendar quarter.
GI (LLI)
=
Gastro - Intestinal Tract - Lower Large Intestine.
9
, a en Rev. O Calculated critical organ dose to the maximum individual D
=
QO (mrem) fo; the calendar quarter.
Dose was calculated using the computer code LADTAP.
Tritium has never contributed more than 1% to the Note
=
maximum organ dose and thus is not included in the calculation.
Maximum Value of D /C - Unit 1 - 0.202 mrem /Ci QO p Unit 2 - 0.120 mrem /Ci Average Value of D /C - Unit 1 - 0.055 mrem /Ci QO F Unit 2 - 0.050 mrem /Ci Since the maximum value of D /C is within a factor of two for both units, thesamefactorb0anbeusedforbothunits for simplicity.
Also, since the maximum value is within a factor of 4 of the average value, this says that the dose per total curies does not fluctuate greatly, hence this method is not over-conservative.
0.2 mrem /Ci Thus, D !
=
Q0 F
- )
P.J L'
[O Rev. 0 APPENDIX C LIQUID DOSE CALCULATIONS - LADTAP A.
PURPOSE This procedure may be used to calculate the quarterly (or any other time period) doses to both the maximum individual and the 50 mile population due to radionuclides released in liquid effluents from either Connecticut Yankee or Millstone Units 1 or 2.
The procedure involves the use of the computer code LADTAP which was developed by the NRC in order to perform dose calculations in accordance with Regulatory Guide 1.109.
B.
REFERENCES 1.
User's Manual for the LADTAP Program - 8 page printout.
2.
U.S. N.R.C. Regulatory Guide 1.109.
3.
U.S. N.R.C. Regulatory Guide 1.113.
4.
Millstone 3 - Demonstration of Compliance with 10CFR50, Appendix I - Pzrt 2B - Nov. 76.
5.
Final Environmental Statements - CY and Millstone 1 and 2.
C.
PREREQUISITES The plant must supply the total number of Curies released for each radionuclide during the time period involved.
D.
PRECAUTIONS None.
E.
LIMITATICNS AND ACTIONS None.
F.
PROCEDURE 1.
Review the plant curie tables for accuracy and completeness.
If the strontium results are not yet arailable, but the calculations must be performed in order to meet the semiannual effluent report schedule, the code may be run without the strontium values and the doses due to strontium ratioed by hand by comparison with the previous quarter's results.
2.
Obtain the computer deck for the proper site - there is one deck for Connecticut Yankee and one deck for Millstone.
The Millstone deck may be used for both Units 1 and 2, however the quarterly doses must be calculated for each plant separately.
67
/
u Rev. 0 3.
The following control cards are required for either deck:
// 082), 'CRANDAl.l', MSGl.EVEl. = 1, Cl. ASS = ll
//STEPl EXEC PGM = PFLADTAP
//FT10F001 DD DSN= FANG. DOSE. FACTOR.FOR.PFLADTAP, DISP =0LD
//FT06F001 DD SYSOUT = A
//FT05F001 DD
'e INPUT CARDS
/*
4.
The deck should be in the order as used during the previous quarter.
If not, refer to reference 1 to ensure the proper input cards are used.
Pay particular attention to the number of blank cards required.
5.
The fol:oving values are incorporated in the input cards and need not 2:.e revised routinely.
Check the basis as given below used to generate these values.
If there has not been a change in the basis, preceed to step 6 - if there has been a change, revise the appropriate card (and the procedure if the change is permanent).
Card 2 Site type - CY = 0 = fresh MP = 1 = salt a.
b.
Release multiplier - CY & MP = 1 - calculation done for 1 unit at a time.
Percentage dose printout - CY & MP = 1 - prints nuclide c.
breakdown of dose.
Card 3 56 mile population - CY = 3.83E+06 - 1980 population estimate-ER a.
MP = 3.03E+06 - 1980 population estimate-ER b.
Change the standard population distribution - CY & MP = 0
= NO Assumes population around CY & MP in typical as far at fraction which is adult, teenager and child.
Card 6 a.
CY = no reconcentration - river site - blank card, b.
MP = Model #2 - ocean site.
Cycle Time = 12 hr. - total cycle.
Recycle Fraction = 0.025 - from MP 1&2 FES.
O o
,no v'
L-
6 Rev. 0 Card 7 a.
Change the standard usage factors CY & MP = 1 - factors must be changed.
b.
Shorewidth factor -
CY = 0.1 - canal shorewidth factor from reference 1 -
using for max ir.dividual dose.
MP = 0.5 - ocean site from reference 1.
c.
Dilution for aquatic foods -
CY = 1 - From table A-1 of Reg Guide 1.109 - Surface -
Low Velocity discharge.
MP = 5 - From table A-1 of Reg Guide 1.109 - Surface -
High Velocity discharge.
d.
Dilution for shoreline -
CY = 1 - Same as 7c.
MP = 5 - Same as 7c.
Dilution for drinking water -
e.
CY = 5 - Arbitrary number since usage factor is zero.
MP = 5 - Arbitrary numbc since usage factor is zero.
f.
Discharge transit time.
CY = 1 hr - From FES canal transit time is 50-100 min.
MP = 1 hr - Estimated quarry transit time from chlorine tudy.
g.
Transit time to drinking water intake.
CY = 5 hr - arbitrary number since usage factor is zero.
MP = 5 hr - arbitrary number since usage factor is zero.
Card 7a - Adult usage factor - max individual Fish consumption - CY & MP = 21 kg/yr - from reference 1.
a.
b.
Invertebrate consumption -
CY = 0 - river site.
MP = 5 kg/yr - from reference 1.
Algae consumption - CY & MP = 0 - no body eats algae.
c.
d.
Water - CY & MP = 0 - no drinking water source for either plant.
Shoreline - CY & MP - 12 hr/yr - from reference 1.
e G?l d
o
,coo
s 3ev. 0
()
f.
Swimming - CY & MP - 12 hr/yr - assume the same as shoreline recreation.
g.
Boating - CY & MP - 52 hr/yr - from Reg Guide 1.109.
Card 7b Teenager usage factors - max individual (basis are the same as 7a).
a.
Fish consumption - CY & MP = 16 kg/yr.
b.
Invertebrate consumption - CY = 0 MP = 3.8 kg/yr c.
Algae consumptien - CY & MP = 0 d.
Water - CY & MP = 0 e.
Shoreline - CY & MP = 67 hr/yr f.
Swimming CY & MP - 67 hr/yr g.
Boating CY & MP - 52 hr/yr Card 7c - Child ucage factors - max individual (basis are tia same as 7a).
a.
Fish consumption - CY & MP = 6.9 kg/yr b.
Invertebrate consumption - CY = 0 MP = 1.7 kg/yr c.
Algae consumption - CY & MP = 0 d.
Water - CY & MP = 0 e.
Shoreline - CY & MP = 14 hr/yr f.
Swimming - CY & FT = 14 hr/yr g.
Boating - CY & MP = 29 hr/yr Card 7d - Infant usag2 factors - max individual.
a.
Fish consumption - CY & MP = 0 - infants don't eat fish.
b.
Invertebrates consumption - CY & MP = 0 - infants don't eat invertebrates.
c.
Algae consumption - CY & Fm = 0 - infants don't eat algae.
d.
Water - CY & MP = 0 - na drinking water supply.
c 0
s Rev. 0 e.
Shoreline - CY & MP = 14 hr/yr - assume same as child, f.
Swimming - CY & MP = 0 g.
Boating - CY & MP = 29 hr/yr - assume same as child.
Card 8 - Leave blank unless special calculation is desired.
Card 9 - Sport fish harvest.
a.
Fish harvest.
CY - 83,000 kg/yr Based on pg. 109 - The Connecticut River Ecological Study - Merriman & Thorpe Jan.-Jun. 1973 - 16,00r fish caught in discharge canal.
Add 30% for July-16,000 x 1.3 = 20,800 fish.
Dec. =
Assume 4 kg/ fish = 83,000 kg/yr.
MP = 1.54 E + 05 kg/yr.
Based on U.S. Dept. of Interior - Comraercial Landing Record for New London Count.y 1971-1973.
Usc1 1973 data (highest of 3 yegrs).
Commercial fish (excluding menhaden) = 1.54 x 10 kg/yr.
Assume an equal amount of sport fish.
b.
Dilution.
CY = 1 - dilution factor for discharge canal.
MP = Based on Section 1.3 of reference 4.
Assume 50% caught - near field dilution = 5 50% caught - far field dilution = 18.6 Average dilution factor = 11.8.
c.
Transit Time.
CY = 0.5 hrs. - half way through canal.
MP = 1 hr. = quarry transit time.
Card 10 - Commercial fish harvest.
a.
Fish harvest.
CY - 470,000 kg/yr 9
21 ;a-
,dIb
" ' [y][
Rev. 0 Based on U.S. Dept. of Interior Commercial fish Landing Records for 1972 and 1973 @ Middlesex County.
Avg. of 2 years = 470,000 kg/yr.
MP - 1.54 E + 0.5 - See card 9 for basis.
b.
Dilution.
CY = 5 - assumed dilution for Conn. River.
MP = 11.8 - See card 9.
c.
Transit Time.
CY = 1 hr. - canal transit time.
MP - I hr.
quarry transit time.
Card 11 - Sport Invertebrate harvest.
a.
CY - Blank card - no significant invertebrate catch.
MP - harvest 8.6 x 10' kg/yr.
b.
Based on U.S. Dept. of Interior Commercial Shellfish catch for New London County for 1973.
5 Commercial catch = 5.72 x 10 kg/yr.
Assume sport catch = 15% of commercial catch.
Dilution = 11.8 - see card 9.
Transit Time = 1 hr.
Card 12 - Commercial Invertebrate liarvest.
a.
CY - Blank card - see card 11.
5 b.
MP - Harvest = 5.72 x 10 kg/yr.
See card 11.
Dilution = 11.8 - See card 9.
Transit Time = 1 hr.
Card 13 - Population Drinking Water.
CY & MP - Blank card - no drinking water source for either site Caro 14 - Population Shoreline.
a.
Usage (manhours).
CY = 100,000 manhours.
e 2-
- 2.,
oo
~ '
Rev. O Based on 2 Parks - Gilette Castle State Park and Selden Neck State Park 26 weeks x 1000 persons /wk x 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> / person = 104,000 manhours.
6 Millstone = 1.5 x 10 manhours.
Based on table 1.1.2-5 of reference 4.
b.
Dilution.
CY = 5 - Assumed river dilution.
MP = 11.6 - Average dilution factor for 7 beaches -
See Table 1.3.2-1 of reference 4.
c.
Transit Time-llrs.
CY = 10 hrs. - assumed river transit time to 2 beaches.
MP = 1 hr.
quarry transit time.
d.
Shorewidth factor.
CY = 0.2 - river shorewidth factor.
MP = 0.5 - ocean shorewidth factor.
c.
Location Identification CY & MP - Parks - rather than doing each park separately, this card combines them all and uses average dilution f actor.
Card 15 - Population Swimming a.
CY - blank card - no swimming in Connecticut River.
b.
MP - Usage - 1.4 x 10 manhours - Table 1.1.2-4 of reference 4.
Dilution = 11.6 - See card 14.
Transit Time = 1 hr. - See card 14.
Location ID = Beaches.
Card 16 - Population Boating Usage a.
CY - 100,000 manhours = from Environmental Statement.
MP - 5.8 x 10 manhours = from Table 1.1.2-3 of reference 4.
b.
Dilution CY = 5 - See card 13.
<j,' 0 07, L ;U V '
s Rev. 0 MP = 11.8 - See card 9.
c.
Transit Time CY = 10 hrs. - See card 13.
MP = 1 hr.
quarry transit time.
d.
Location ID CY = river MP = ocean Cards 17 & 18 - Irrigated Foods CY & MP - blank card - no irrigation pathway.
Card 19 - Biota a.
Dilution CY = 5 MP = 11.8 b.
Transit time CY = 1 hr.
MP = 1 hr.
6.
The following input cards must ce changed routinely for each quarterly run of the program:
Card _1 - Title card - Format - 2X, A78 Enter the plant name, " Liquid Dose Calculation", and the time period of the dose calculation.
Card 2 - Colamns 11 Format E10 - Dilution Flow.
Determine the average dilution flow rate (ft 3/sec) for the quarter by:
a.
Determine the total dilution volume for the quarter.
This should be the total dilution volume for the entire quarter and not just for the periods of discharge.
It should be on the order of 1 x 10" liters.
b.
Divide by the number of seconds in the quarter.
c.
Convert liters /sec to ft /sec by dividing by 28.32.
For CY the normal full power flow is 882 ft /sec.
!n -
is i I)
'I
[7)O
6 Rev. 0 3 For M1 plus M2 the normal full power flow is 2265 ft
/sec.
Card 4 - Source term identification - Format 2X, A78.
Identify the time period of the releases.
Cards 5.1, 5.2 - Source terms - Format 2X, A2, AS, 1X, E10 One card is required for each nuclide.
Enter the nuclides chemical symbol beginning in column 3 -left justified.
Enter the isotopes number beginning in column 5 - lef t justified.
Enter the number of curies released in scientific notation beginning in column 11 and ending in column 20.
Be sure to sum the totals from all continuous and batch release tables.
Examples:
1 2
Column No:
1 2 3 4 5 6 7 8 9 0 1 2 3 4 5 6 7 8 9 0 H
3 2
6 2 E + 0 3 I
1 3 1 6
9 9 E - 0 4 gg C 0 6 0 1
8 0 E - 0 2 There is no need to enter the dissolved noble gases as they will not be included in the calculation. The last nuclide is followed by a blank card.
7.
Save the old cards for approximately 1 year in case doses must be recalculated.
8.
Submit the cards in order to run the program on the IBM-370.
G.
ACCEPTANCE CRITERIA None.
H.
CHECKLISTS None I.
DEFINITIONS LADTAP = Liquid Annual Doses to all Persons.
J.
RESPONSIBILITY Environmental Programs Branch.
R~'s
/..n5y v.
s
Rev. O APPENDIX D DERIVATION OF FACTORS FOR SECTION D 1.
X/Q's, D/Q's Millstone - Unit. 1 Stack Elevated X/Q's, D/Q's Quarterly Averages - Maximum Values Year Quarter Maximum X/Q Maximum D/Q 1976 1
2.7E-08 1.3E-09 2
2.8E-08 2.lE-09 3
4.7E-08 5.5E-09 4
2.6E-08 7.9E-09 1977 1
2.3E-08 1.4E-09 2
4.lE-08 4.2E-10 3
4.8E-08 2.2E-09 4
5.4E-08 4.8E-09 1978 1
4.7E-08 6.6E-09 2
5.3E-08 1.2E-09 3
4.0E-08 2.2E-09 4
7.lE-08 4.3E-09 Maximum Quarterly Average X/Q =
7.1 x 10~
Sec/M Maximum Quarterly Average D/Q =
7.9 x 10~
M'
,3 0
)
o Rev. O Millstone - L'n i t 2 - Vent Quarterly Average X/Q's - D/Q's flaximum Values t'aximum X/Q Maximum D/Q Year Quarter Continuous Batch Continuous Batch 1976 1
5.0E-06 ND 4.3E-08 ND 2
1.3E-05 ND 6.7E-08 ND 3
4.4E-06 8.lE-06 4.5E-08 8.0E-08 4
2.2E-06 5.9E-06 2.5E-08 6.5E-08 1977 1
2.8E-06 4.lE-06 3.2E-08 5.4E-08 2
1.9E-06 1.4E-06 1.3E-08 1.3E-08 3
8.2E-06 7.5E-06 1.5E-07 1.5E-07 4
3.5E-06 2.6E-06 6.9E-08 5.2E-08 1978 1
2.5E-06 ND 4.3E-08 ND 2
5.3E-06 1.6E-06 8.7E-08 2.9E-08 3
9.lE-06 8.2E-06 1.4E-07 1.lE-07 4
3.3E-06 4.2E-06 8.7E-08 8.0E-08
-5 Maximum Quarterly Average X/Q =
1.3 x 10 Sec/M Maximum Quarterly Average D/Q =
1.5 x 10' M~
From the above data we can also see that the batch releases are of random enough nature such that the batch release meteorology a
approximates the continuous meteorology as shown by the average of the above values:
-6 Average Max. Q t. r. X/Q - Continuous Release - 5.1 x 10
-6 Average Max. Qtr. X/Q - Batch Releases -
4.8 x 10 Average Max. Qtr. D/Q - Continous Releases - 6.7 x 10~
Average Max. Qtr. D/Q - Batch Releases -
7.0 x 10' Therefore, the same X/Q's and D/Q's can be used for both batch and continuous releases.
2 h '. b bi/
Rev. 0 2.
Section D.I.a - Noble Gas Release Rate Limits M1 Gaseous Releases - Curies vs. Dose Max. Individual mrem per Avg. Noble Gas Dose (mrem)
W.ftCi/Sec Year Quarter Release Rate (pCi/Sec)
W.B.
Skin B. and Skin 1976 1
17,400 1.9 1.9 1.1 (-4) 2 25,600 4.2 4.3 1.6 (-4) 3 20,100 3.4 3.4 1.7 (-4) 4 2,600 0.3 0.3 1.0 (-4) 1-4 16,400 9.8 9.9 6.0 (-4) 1977 1
11,600 1.1 1.1 8.6 (-5) 2 13,000 1.9 1.9 1.5 (-4) 3 24,000 4.6 4.6 1.9 (-4) 4 29,700 2.2 2.2 7.4 (-5) 1-4 19,600 9.8 9.8 5.0 (-4) 1978 1
50,800 4.4 4.4 8.7 (-5) 2 20,800 3.1 3.1 1.5 (-4) 3 350 0.04 0.04 1.3 (-4) 4 530 0.03 0.03 6.4 (-5) 1-4 18,100 7.6 7.6 4.2 (-4)
M2 Stack Gaseous Releases - Curies vs. Dose Max. Individual mrem per Avg. Noble Gas Dose (mrem)
/tCi/Sec Ratio Year Quarter Release Rate (pCi/Sec)
W. B.
Skin W.B.
Skin /W.B.
1976 1
0.63 0.00016 0.00047 2.5 (-4) 2.9 2
83 0.058 0.16 7.0 (-4) 2.8 3
54 0.015 0.055 2.8 (-4) 3.7 4
63 0.022 0.035 3.5 (-4) 1.6 1-4 50 0.095 0.25 1.9 (-3) 2.6 1977 1
134 0 023 0.058 1.7 (-4) 2.5 2
70 v.007 0.018 1.0 (-4) 2.8 3
39 0.019 0.056 4.9 (-4) 2.9 4
69 0 010 0.030 1.4 (-4) 3.0 1-4 78 0.059 0.162 7.6 (-4) 2.7 1978 1
10 0.0068 0.012 6.8 (-4) 1.8 2
91 0.019 0.05b 2.1 (-4) 3.1 3
313 0.13 0.37 4.2 (-4) 2.8 4
21 0.0054 0.011 2.6 (-4) 2.0 1-4 109 0.16 0.45 1.5 (-3) 2.8 0"j
,.,.o
[l> U Rev. O Maximum value of mrem / year per jtCi/sec telease rate is for 1976 for both units.
These values are for whole body doses:
ML:
6.0 x 10 mrem /yr. per jsci/sec M2:
1.9 x 10~
mrem /yr. per p Ci/sec The 10CFR20 limit is 500 mrem to the whole body and 3000 mrem to the skin.
Since the skin dose has never been as much as six times the whole body dose for Unit 1 or Unit 2 releases, we can use the 500 mrem as the limiting dose.
Therefore, the release rate limits would be:
830,000 pCi/sec Ml: 500/6.0 x 10
=
-3 260,000 pCi/sec M2:
500/1.9 x 10
=
However, 10CFR20 is a site limit, therefore the limit is:
Q1 Q2 830,000, 260,000
-4 y
- where, 7
from MP1 stack (g Ci/sec)
Q = noble gas release rate (pCi/sec)
Q = noble gas release rate from MP2 vent Justification for Above Method The above method of determining instantaneous release rates will ensure compliance with 10CFR20 for the following reasons:
1.
The doses presented for Millstone 1 were calculated using the EPA AIREM code, which uses a finite cloud model similar to that in Reg. Guide 1.109.
This code has compared very favorably with data actually measured at the critical site boundary with a pressurized ion chamber.
Plant related quarterly doses measured by the ion chamber were calculated using a model developed by ERDA's Health and Safety Lab.
These doses have always been within 30% of those calculated by AIREM.
The average difference has been 14%, with the AIREM code calculating the higher dose.
Thus, we are ensured that the AIREM code yields reasonable, if not slightly conservative, estimates of the maximum individual whole body dose.
2.
The doses presented for Millstone 2 were calculated using the NRC GASPAR code which uses the methodology of Reg. Guide 1.109.
{ T !)
</. qqu Rev. 0 3.
The dose per curie released can be seen from the tables not to vary significantly from one quarter to the next.
-5 Ml:
Minimum Value - 6.4 x 10 mrem /qtr. per p Ci/sec Average Value - 1.2 x 10 mrem /qtr.
per Ci/sec
-4 Maximum Value - 1.9 x 10 mrem /qtr. per p Ci/sec
-4 M2:
Minimum Value - 1.0 x 10 mrem /qtr. per pCi/sec Average Value - 3.4 x 10 mrem /qtr. per p Ci/sec Maximum Value - 7.0 x 10' mrem /qtr. per Ci/sec It can be seen that the maximum value observed is only a factor of 2 greater than the average value even though there have been significant changes in the isotopic compositions of the releases and/or the meteorological frequencies.
The isotopic changes include significant operational changes such as:
Operation with and without the recombiner-charcoal delay a.
system on the Unit 1 off gas.
b.
Periods when a unit was down the entire quarter for refueling.
Quarters with many M2 containment purges and quarcers c.
with no purges.
d.
Quarters with relatively high and relatively low fuel leakage from Unit 1.
Thus, the dose per curie released is not that sensit ive to operational changes such that a gross curie release ratio can be used.
We have been conservative in taking the worst annual ratio observed.
4.
It should also be recognized that there is a great deal of conservt.cism between this method and the actual requirements of 10CFR20 for the following reasons:
a.
10CFR20 states that release rates may be averaged over a year, however we are using this as an instantaneous release rate limit.
b.
10CFR20 limits are ground level concentration limits, which for elevated releases from the Unit 1 stack would be less restrictive than the use of the elevated finite cloud model as used here.
'[ h h)
T I
Rev. 0 5.
It must also be recognized that the type of empiracal method given above is the only practical operational method. The use of a method similar to that given in NUREG-0133 would be an operational nightmare, would be next to impossible to implement and could yield allowable release rates many times that given above.
For example, releases from the Unit 1 stack could include any of the following releases:
MP1 ventilation from radiological areas MP1 off gas releases from the off gas treatment system MPl off gas releases via the 30 minute holdup pipe MP1 mechanical vacuum pump MP1 gland seal condenser MP2 waste gas tank discharge MP2 containment purges MP2 ventilation f rom radiological areas MP2 condenser air ejector MP2 mechanical vacuum pump These sources may exist in any possible combination and each has its own particular, but changing, nuclide mixtures.
- Thus, the ratio of nuclides being released is a constantly changing parameter.
It is impractical to recalculate a stack release rate based on isotope specific dose conversion factors each time a source stream is initiated or terminated or a new isotopic analysis is performed on any of the source streams.
This could require 4 or 5 recalculation and monitor set point changes each day.
The plant could not operate in this manner.
It would also be unnecessarily restrictive to assume the worst possible mixture and use that as the limit for all situations.
The only practical solution is to use a conservatively determined empirical method as given above.
{'i
<l. n
,y uG \\
A Rev. 0 3.
Section D.l.h - Iodine, Particulate and Other Limits a.
lodine lodine Releases vs. Dose - M1 Thyroid Curies Dose Year Quarter I-131 mrem mrem /Ci 1976 1
0.58 0.6 1.0 2
0.75 3.8 5.1 3
0.58 4.9 8.4 4
0.29 0.6 2.1 1-4 2.20 9.9 4.5 1977 1
0.38 0.3 0.8 2
0.59 1.2 2.0 3
1.57 5.4 3.4 4
2.11 4.6 2.2 1-4 4.65 11.5 2.5 1978 1
- 1. 'i o 8.7 5.I 2
1.15 3.1 2.7 3
0.18 0.6 3.3 4
0.16 0.3 1.9 l-6 3.19 12.7 4.0 Iodine Release vs. Dose - M2 Thyroid Curies Dose Year Quarter I-131 mrem mrem /Ci 1976 1
3.3 (-3) 0.015 4.5 2
4.0 (-3) 0.076 19.0 3
1.8 (-3) 0.077 43.7 4
4.2 (-4) 0.023 54.8 1-4 9.5 (-3) 0.191 20.1 1977 1
2.6 (-4) 0.010 38.5 2
1.8 (-3) 0.047 26.1 3
6.9 (-4) 0.037 53.6 4
2.5 (-3) 0.064 25.6 1-4 5.2 (-3) 0.158 30.4 1978 1
6.9 (-4) 0.024 34.8 2
1.0 (-?)
0.031 51.0 3
5.7 (-3) 0.52 91.'
4 6.7 (-5) 0.017 253.8 1-4 7.
( 3) 0 6t2 81.6
(
)
6 Rev. O Maximum Value for M1 is for 1976
- 4.4 mrem /Ci I-131 Maximum Value for M2 is for 1978
= 81.6 mrem /Ci 1-131 Limit is 1500 mrem /yr. to the thyroid M1 allowable release rate
-8 p i/Ci x 3.17 x 10 yr/sec = 10.8pCi/sec
= 1500 mrem /4.4 mrem x 10 C
M2 allowable release rate 6
-8
= 1500 mrem /81.6 mrem x 10 3.17 x 10
= 0.58 p Ci/sec Since this is a site limit, the allowable release rate is:
9 0
1 2
10 8 + 0.58 II b.
Particulates with IIalf Lives Greater Than 8 Pays Particulate Releases vs Dose - M1 Total Curves Max. Organ Max. Organ Year Quarter Particulates Ex. Thyroid Dose mrem /Ci 1976 1
0.040 Bone 7.9 (-3) 0.20 2
0.043 Bone 2.1 (-2) 0.49 3
0.051 Bone 1.7 (-2) 0.33 4
0.014 Bone 1.1 (-2) 0.79
'4 0.148 S.7 (-2) 0.39 1977 1
0.009 Bone 3.2 (-3) 0.36 2
0.014 Liver 4.3 (-3) 0.31 3
0.075 Bone 1.8 (-2) 0.24 4
0.103 Bone 5.0 (-2) 0.49 l-4 0.201 7.6 / -2) 0.38 1978 1
0.156 Bone 1.6 (-1) 1.02 2
0.963 Bone 9.5 (-2) 0.10 3
0.131 Bone 2.7 (-2) 0.21 4
0.105 Bone 2.8 (-2) 0.27 1-4 1.355 3.1 (-1) 0.23 e
, ()
V s
Rev. O Particulate Releases vs Dose - M2 Total Part.
Max. Organ Max. Organ Year guarter Curies Ex. Thyroid Dose mrem /Ci 1976 1
5.5 (-4)
GI (LLI) 1.7 (-3) 3.1 2
7.0 (-5)
Liver 6.0 (-4) 8.6 3
1.2 (-5)
Bone 6.7 (-4) 55.8 4
4.6 (-4)
Bone 1.2 (-2) 26.1 1-4 1.1 (-3) 1.5 (-2) 13.6 19/7 1
2.5 (-4)
Bone 1.8 (-3) 7.2 2
1.0 (-4)
Liver 2.1 (-4) z.1 3
1.5 (-5)
Bone 2.7 (-4) 18.0 4
4.4 (-4)
Bone 1.2 (-3) 2.7 1-4 8.1 (-4) 3.5 (-3) 4.3 1978 1
8.1 (-4)
G1 (LLI) 1.1 (-3) 1.4 2
2.7 (-4)
Boce 2.2 (-3) 8.1 3
1.0 (-4)
Bone 2.8 (-3) 28.0 4
3.9 (-4)
Bone 6.0 (-4) 0.4 1-4 1.6 (-3) 6.7 (-3) 4.2
?!aximum Value for M1 is for 1976
= 0.39 mrem /Ci Maximum Value "or M2 is for 1976 13.6 mrem /Ci
=
Limit is 1500 mrem /yr to the maximum organ M1 allowable release rate 6
-8 1500 mrem /0.39 mrem /Ci x 10
=
jr.Ci/Ci x 3.17 x 10 yr/ rec =
122.Ci/sec
?!2 allowable release rate
= 1500/13.6 x 10 x 3.17 x 10~
3.5jiCi/sec
=
Since this is a site limit, the allowable release rate is:
1 2
122 3.5 I
p ", ?
.n
[
O Cs p
Rev. O c.
Tritium M1 Tritium Releases - Curies vs. Dose Tritium Dose (mrem) Due Year Quarter Curies to Tritium mrem /Ci 1976 1
3.71 2.5 (-5) 6.7 (-6) 2 1.47 8.1 (-6) 5.5 (-6) 3 11.4 8.2 (-5) 7.2 (-6) 4 12.1 6.2 (-5) 5.1 (-6) 1-4 28.7 1.8 (-4) 6.3 (-6) 1977 1
7.17 3.2 (-5) 4.5 (-6) 2 9.24 7.5 (-5) 8.1 (-6) 3 19.3 1.8 (-4) 9.4 (-6) 4 29.5 1.9 (-4) 6.3 (-6) 1-4 65.2 4.8 (-4) 7.4 (-6) 1978 1
16.8 1.7 (-4) 1.0 (-5) 2 7.68 8.6 (-5) 1.1 (-5) 3 13.1 1.1 (-4) 8.5 (-6) 4 11.1 1.7 (-4) 1.5 (-5) 1-4 48.7 5.4 (-4) 1.1 (-5)
M2 Tritiu, Releases - Curies vs. Dose Tritium Dose (mrem) Due Year gua_r t e r Curies to Tritium mrem /Ci 1976 1
0.2 1.7 (-4) 8.5 (-4) 2 2.2 3.0 (-3) 1.4 (-3) 3 5.6 3.2 (-3) 5.7 (-4) 4 3.7 1.7 (-3) 4.5 (-4) 1-4 11.
8.1 (-3) 6.9 (-4) 1977 1
11.2 5.1 (-3) 4.5 (-4) 2 2.9 7.3 (-4) 2.5 (-4) 3 7.4 1.1 (-2) 1.5 (-3) 4 2.7 1.3 (-3) 4.8 (-4) 1-4 24.2 1.8 (-2) 7.4 (-4) 1978 1
0.0003 2
2.2 8.5 (-4) 3.9 (-4) 3 23.4 4.2 (-2) 1.8 (-3) 4 23.2 1.6 (-2) 7.0 (-4) 1-4 48.8 5.9 (-2) 1.2 (-3)
Maximum VAlue for M1 is for 1978
-5
= 1.1 x 10 mrem / Curie H-3
^ ;;
t,o m<.
p Rev. O tiaximum Value for t12 is for 1978 1.2 x 10' mrem / curie 3
=
I.im i t is 1500 mrem /yr to the maximum organ til allowable release rate 6
(1500 mrem /l.1 x 10 '5 iarem/Ci) x 10 Ci/Ci x 3.17 x
=
10' yr/sec = 4.3 x 10' p Ci/sec
!!2 allowable release rate 6
(1500/1.2 x 10' ) x 10 x 3.17 x 10'
= 4.0 x 10 tC./sec
=
Since this is a site limit, the allowable release rate is:
9 0
1 2
. +
< 1 4.3 x 10
4.0 x 10
~
4.
Sec_ tion D.2.a - Noble Gas - Quarterly Air Dose - tiethod 1 (1) t!illstone Unit 1 From Table in Section 2 of this Appendix, thg maximum quarterly value of mrem /qtr. per This value is the whole body.p Ci/sec is 1.9 x 10 To convert to mrad air dose we must mrem to multiply by 2 because there is a factor of 0.7 to go from mrad to whole body mrem and also a factor of 0.7 for building shielding and occupancy used to originally calculate the whole body results.
Therefore, the conversion factor for the air dose is:
3.8 x 10 mrad /qtr. per Ci/sec or 3.8 x 10~
h" x 10'pCi/Cix 1.26 x 10' qtr./sec
= 4.8 x 10 mrad /Ci This is the gamma air dose at the critical location.
Since the critical location is the site boundary and is only 0.5 miles from a 375 foot stack, the beta air dose at the critical location is near zero as the dose is from the overhead finite 2!,0 b.U A
Rev. 0 9
-loud.
The beta air dose at the critical location has always been less than 0.01 times the gamma dose.
Thus, the beta dose can be recorded as:
1 4.8 x 10' mrad /Ci (2) Millstone Unit 2 Likewise, for Unit 2 the maximum quarterly value of mrem /qtr.
perpCi/ rec is 7.0 x 10
- Converting to mrad /Ci we have 7.0 x 10 ' x 2 x 106 x 1.26 x 10'
=
I
-4 l1.8 x 10 mrad /Ci
=
This is the gamma air dose.
The following is the ratio of the beta air dose to the gamma air dose at the critical location as calculated by the GASPAR code:
Ratio 1976 1977 1978 lst. qtr.
2.9 3.1 6.9 2nd. qtr.
2.9 3.0 2.8 3rd. qtr.
3.5 2.5 3.0 4th. qtr.
3.0 3.0 3.0 The average ratio = 3.3 Beta air dose =
5.9 x 10 mrad /Ci O
m f
s J
- A Rev. 0 5.
Section D.2.b til Finite Cloud Code Cutles Dose @ 600m NE Year Quarter Xe-138 Due to Xe-138 Dose / Curie 4
1976 1
2.4 x 10 0.29 1.2 (-5) 2 3.9 x 10 0.61 1.6 (-5) 3 3.3 x 10 0.52 1.6 (-5) 4 7.5 x 10 0.08 1.0 (-5) 1977 1
2.1 x 10 0.19 8.9 (-6) 2 1.9 x 10 0.22 1.2 (-5) 3 3.4 x 10 0.52 1.5 (-5) 4 3.4 x 10 0.22 6.4 (-6) 1978 1
6.5 x 10 0.31 4.8 (-6) 4.7x10f 0.57 1.2 (-5) 2 3
9.0 x 10' O.019 2.1 (-5) 4 1.6 x 10 0.015 9.2 (-6)
The above table normalizes the dose for each quarter to the same location f rom a part icular radionuclide.
Thus, the only variance in dose per curie should be due to the quarterly meteorology.
Using this method, we can determine that the worst case meteorology occurred during the 3rd quarter 1978.
Thus, the 3rd quarter joint frequencies should be used as input for the AIREM code.
6.
Section D.3 a.
Millstone - Unit 1 The only significant contributor to the thyroid dose is I-131.
If the particulates were significant a different organ would be limiting.
Tritium releases have never contributed more than 1% of the doses from Unit 1.
Thus, to determine the quarterly thyroid dose we can use the maximum quarterly value observed of mrem / curie of I-131 as presented in Section 3 of this appendix.
This maximum value is:
8.4 mrem / curie - I-131 The critical organ dose due to particulates with half lives greater than 8 days can also be determined from the maximum quarterly dose per curie given in Section 3 of this appendix.
. $1 l*
,,j
- ') g - (U
- '~
L'1 Rev. O This maximum value is:
1.1 mrem / curie of pat _culates b.
Flillstone - Unit 2 For Unit 2, we must consider tritium in both the calculation of the thyroid and other organ doses.
The dose factor for all organs for t ritium is the same The maximum values of mrem per curie as presented in Section 3 of the appendix are as follows:
For I-131, 250 mrem /Ci - I-131 For Particulates 55 mrem /Ci - Particulates
-3 For Tritium 1.8 x 10 mrem /Ci 3 m.in j,. I '- )
?
o '.
A Rev. 0 APPENDIX E GASEOUS DOSE CALCULATIONS - GASPAR A.
PURPOSE This procedure is used to implement the NRC computer code GASPAR in order to calculate the maximum individual and population doses due to radionuclides released in gaseous effluents.
The code implements the semi-infinite cloud model and the dose calculation models of Reg Guide 1.109 and is used to calculate the following:
1.
All maximum individual and population doses from Connecticut Yankee 2.
All maximum individual and population doses from Millstone Unit 2.
3.
Population doses from Millstone Unit 1.
4.
Maximum individuel organ doses from Millstone Unit 1.
The maximum individual whole body and skin doses due to elevated releases from Millstone 1 should be calculated using the finite cloud model as performed by the EPA code AIREM.
A more detailed description of the GASPAR code can be found in reference 1.
B.
REFERENCES 1.
GASPAR dose code manuals - dated 10/17/75 and 2/20/76.
2.
U.S. NRC Regulatory Guide 1.109.
3.
U.S. NRC Regulatory Guide 1.111.
iR_EREQUISITES C
f 1.
The plant must supply the total number of Curies released for each radionuclide during the time period involved.
2.
The meteorological programs must be run to generate the required input cards for X/Q, decayed X/Q, depleted X/Q and D/Q.
D.
PRECAUTIONS None.
E.
LIMITATIONS AND ACTIONS None.
9 2: U C76/
Rev. 0 F.
P.ROCEDURE 1.
Review the plant curie ralease tables for accuracy and completeness.
If the strontium results ire not yet available, but the calculations must be performed in order to meet the semi-annual effluent report schedule, the code may be run without the strontium values and the doses due to strontium ratioed by hand by comparison with the previous quarters results.
2.
Obtain the computer deck for the GASPAR code for the nuclear site involved.
3.
The deck should be in the following order:
// 082), 'CRANDALL', MSGLEVEL=1, CLASS =B
// STEP 1 EXEC PGM=PFGASPAR
// FT06F001 DD SYSOUT=A
// FT05F001 DD
- Adult, teenager, child and infant dose factor cards.
Blank Card.
Input cards as discussed below.
3 blank cards
/
4.
Due to different meteorology calculations, the code must be run separately for each of the following cases:
a.
CY - continuous, semi-elevated releases - ventilation, b.
CY - batch mode, semi-elevated releases - waste gas tanks.
M1 - continuous, elevated releases - ventilation and off c
- gas, d.
M2 - continuous, semi-elevated releases - ventilation.
M2 - batch mode, semi-elevated releases - containment e
purges.
f.
M2 - batch mode, elevated releases - waste gas tanks and some containment purges.
The resulting doses must then be summed by hand for each unit.
5.
The input cards at4 as follows.
Those parameters which must be changed each quarter are enclosed in blocks /
~
/.
a.
CARD 1
- Title card - Format - 2X, 78Al ketitifyReleaseTypel Millstone Unit One
- Gaseous l lst Quarter l 19 76.
..o
(' O i c
I;Q U
i
Rev. 0 b.
CARD 2 - Job control card - Format 1012.
Column 2=0 - will calculate population doses and maximum individual.
Column 4=1 - number of source terms - done for each unit separately.
Column 6=1 - a rbi t ra ry i f number in column 4 is 1.
c.
CARD 3 - Site parameters - Format 10E8.0 - Same for CY and Millstone.
Columns 1-5=500.0 - distance from site to NE corner of U.S.
Columns 14-16=1.0 - fraction of fresh leafy vegetation grown locally.
Columns 22-24=0.5 - fraction of year m'lk animals on pasture.
Columns 29-22:0.76 - f raction of veg. intake grown in garden - from Reg Guide 1.109.
Columns 38-40=1.0 - fraction of animals intake from pasture when on pasture.
3 Columns 46-48=8.0 - air water concentration (g/m ),
d.
CARD 4 - Population title card - Format = 2X, 78Al.
Population Data e.
CARD 4.1 - Population data format - Format 3I5.
Column 5=0 - Population data starts ir. north sector.
Column 10=5 - Number of radial locations for which data is supplied on first card.
Columns 14&l5:10 - Total number of radial locations.
f.
CARDS 4.2---4.33 32 cards of population data - based on 1980 population estimates from Conn. Yankee and Millstone Environmental Reports.
g.
CARD 5 - Milk data title card - Format = 2X, 78Al.
Milk data - NRC Memo 15 State of CT.
h.
CARD 5.1 - Milk data format.
Columns 9&l0 = 16 - Dummy number since using defaul t values.
i.
CARD 5.2 - Milk data.
Columns 3-10=4.4E + 08 - 50 mile milk usage from reference 1.
j.
CARDS 6-6.2 - Same as 5-5.2 except for meat instead of milk usage factor = 2.0E+07.
f3 ('i 'i
^o!
U"'
Ls u
A Rev. 0 k.
CARDS 7-7.2 - Same as 5-5.2 except for vegetation instead of milk usage factor = 3.2E+07.
1.
l CARD 8-Sourcetermtitlecard-Format - 2X, 78Al.
Source Terms -
I S'I QllARTER 1976.
ra.
CARD 8.1 - Source description - Format = (E10, 2(9X,II)).
Columns 8-10 = 1.0 - release point multiplier Column 20 = 0 - see reference 1.
Column 30 = 0 - see reference 1.
l CARDS 8.2-8.X-Sourcedata-Format =2X,A2, sal,1X, n.
E10.0.
Enter total curies released for each nuclide for the particular release mode as listed in step 4 of this procedure.
One card per nuclide.
Isotope chemical symbol and atomic number and curies released are all lef t justified.
The following are examples of the input format:
1 2
Column No.
1 2 3 4 5 6 7 8 9 0 1 2 3 4 5 6 7 8 9 0 I
L 3 1 0
5 7 9 H
3 3
7 1 K R 8 5 M 7
1 2 0 0
K R 8 7 1
9 0 0 0 0
C 0 6 0 0
0 0 0 8 9 CARD 8.n - blank card following source data.
o.
p.
CARD 9 - X/Q title card.
q.
CARD 9.1 - X/Q format - Format = 3I5.
Column 5=0 - Data starts with north as the downwind sector (south wind).
Column 10=5 - There are 5 X/Q values on the first card for each _ector.
Column 14&l5=10 - There are a total of 10 X/Q values for each sector.
NOTE WELL There are two possible computer codes used to generate the X/Q cards - one was written by the NRC (X0QD0Q) and one by NUSCO (PFAADRG).
The NRC code punches cards such that they start with the south downwind sector and have 7 values on the first card and 3 on the second.
h Changing 0 to 1 in column five will designate that south is the first sector, and changing 5 to 7 in column ten will indicate that there are 7 values on the first card, also change 005
,[,, cd q
+
u
Rev. 0 cards 10.1, 11.1 and 12.1.
The NUSCO code should start with the north downwind sector and have five values per card.
ICARDS 9.2 to 9.13
- X/Q Data - Format - Alternate (5X, 7E10.0) r.
and (8E10.0) insert the 32 X/Q cards as generated by the meteorological program.
Be certain the sectors are in the proper order as required by card 9.1.
CARD 10 - Decayed X/Q title card, s.
t.
CARD 10.1 - Same as 9.1 except for decayed X/Q's.
u.
CARDS 10.2 to 10.33
- Same as 9.2 to 9.33 expect for decayed X/Q's.
v.
CARD 11 - Depleted X/Q title card.
CARD 11.1 - Same as 9.1 except for depleted X/Q's.
w.
x.
CARDS 11.2 to 11.33 - Same as 9.2 to 9.33 except for depleted X/Q's.
y.
CARD 12 - D/Q title card.
CARD 12.1 - Same as 9.1 except for D/Q.
z.
CARDS 12.2 to 12.33 - Same as 9.2 to 9.33 except for D/Q.
aa.
bb. ! CARDS 13.1 to 13.n - Special locations for Maximum Individual.
These cards are submitted to calculate whole body and organ doses to the maximum individual.
One card is required for each location at which these doses are to be calculated. A maximum of 5 is all that can be done.
The meteorological program outputs the X/Q, decayed X/Q, depleted X/Q, and D/Q for the site boundary, nearest land, nearest residence and vegetable garden, goat farms and cow farms in each sector.
The following locations should be entered:
1)
The nearest land with highest decayed X/Q.
2)
The nearest residence with highest depleted X/Q.
3)
The goot farm with highest D/Q - 2nd & 3rd quarters only.
4)
The cow farm with highest D/Q - 2nd & 3rd quarters only.
<.,n pO L>>0 v
Rev. 0 The GASPAR program will calculate the whole body and organ doses for each pathway at each location.
There is no way to control this with the input, but ra t he r the final results will have to be selectively analyzed.
For example, for the nearest residence location, one should only sum the dose due to the plume, ground deposition, inhalation and vegetation pathways and not from the cow's milk, goat's milk, and meat pathways.
NOTE 1:
For elevated releases from the Millstone 1 stack, the nearest land boundary and nearest residence may not be the location of highest X/Q's.
Therefore the meteorological output table of X/Q's from 0-50 miles must be used and interpolated to determine these locations.
NOTE 2:
For CY and M2 which have more than one type of release (batch, continuous, semi-elevated),
the locations of highest X/Q's or D/Q's for one type of release may not be the same as the locations for a different type of release.
It that case, the location of highest X/Q or D/Q for one type of release should also be entered for the other eleases along with their highest locations, such that the total sum from all releases may determined at each location to determine the location of maximum dose.
However, a maximum of 5 locations can be done.
- Thus, to prevent using the program more than once, some pre-judgement might be necessary.
The format for the Special Location cards is as follows:
Column 2= 1 - Eliminates pages of printout of nuclide breakdown for each pathway and age group.
Columns 3 Location name - Example - Nearest Land.
Columns 19 Compass direction - Example - ENE Columns 23 Distance in miles - Example - 1.9.
Columns 30 X/Q for that location - rirht justified -
Example 0.273 E-07.
Columns 40 Same as 30-39 except for decayed X/Q.
Columns 50 Same as 30-39 except for depleted X/Q.
Columns 60 Same as 30-39 except for D/Q.
Col umn s 70, 71, 72, 73, 74, 75 and 76 - 0 in each column -
controls printout.
9 Last special location card is followed by 3 blank cards.
Oi! l f..n r
- U v
A Rev. 0 6.
Save the old cards for approximately 1 year in case doses must be recalculated.
7.
Submit the cards in order to run the program on the IBM-370.
G.
ACCEPTANCE CRITERIA None 11.
Cill-[CKI.I STS None I.
DEFINITIONS None
.J.
RESPONSIBILITY Environmental Programs Branch.
e, D,
U
e.
1 APPENDI's F CASEOUS DOSE CALCULATIONS - AIREM A.
PURPOSE This procedure is used to implement the EPA computer code AIREM in order to calculate the quarterly maximum individual whole body and skin doses due to elevated releases from the Millstone Unit I stack.
All other doses due to gaseous radioactive releases are calculated using the NRC computer code CASPAR.
B.
REFERENCES 1.
AIREM Program Manual
, EPA-520/1-74-004 - U.S.
EPA - May 1974.
2.
U.S. NRC Regulatory Guide 1.109.
3.
WASH 1258 - Volume 2 - Pages F-53 Table A-4.
C.
PREREQUISITES 1.
The plant must suppl' the total number of curies (gaseous) released for each rt.dionuclide during the quarter.
2.
The meteorological program PFEDNJFQ must be run with AIREM=YES for the Millstone 447' elevation in order to generate the necessary meteorological cards.
D.
_P.'.ECAUT I ON S None.
L.
LIMITATIONS AND ACTIONS N o r. e.
F.
PROCEDURE 1.
Review the plant curie release tables for accuracy and ccmpleteness.
2.
Obtain the computer deck for the AIREM code.
3.
The deck should be in the following order.
// 082), 'CRANDALL', MSCLEVEL=1, CLASS =B
// STEP EXEC PGM=PFAIREM
// FT06F001 DD SYSOUT=A
// FT03F001 DD SYSOUT=A, DCB= (LRECL=133,RECFM=US,BLKSIZF ' '3)
// FT01F001 DD
- INPUT CARDS AS GIVEN BELOW CARDS FROM EGAD-DOSE INTEGRAL RESULTS
/*
,o-
4.
4.
The input cards are as follows.
Those parameters which may change each quarter are enclosed in blocks V
a.
CARD 1
- Title Card - Formar SA4, F5.0, LX, A4, 15, 1X,
A4, IS, F10.
Columns 2 Facility name = Millstone Unit One Columns 21 Number of months of data = 3 Columns 27 Beginning month APR Columns 31-3 5 - Beginning year 1976 Columns 37 Ending month J UNE Colum.
41 Ending year 1976 Columns 46 The rmal energy generated (MWD) -
100,000 This number is not used in the calculation - it is only a reference number.
If not readily available - enter 100,000, b.
lCAPD 2
- Parameters - Format = 4I5, 2 F10, 3E10.
All numbers should be right justified.
Columns 2 Number of sectors = 16 Columns 6 Number of classes = 6 Columns 11 Number of radii = 12 Columns 16 Number of isotopes = ld The maximum number of isotopes the program will accept is y
20.
If an isotope is used for more than one organ it must be coun t ed each time.
Since we are only interested in whole body and skin doses with this program, we can enter 10 isotopes for the whole body and 10 isotopes for the skin.
The tritium, lodines and particulates need not be entered for they are insignificant compared to the noble gases when performing a finite cloud whole body dose calculation, lloweve r, Rb-88 and CS-138 (daughter products of Kr-88 and Xe-138) are generally significant and should be entered as 2 of the isotopes.
Thus, with present operation without an off gas treatment system the 10 most significant nuclides usually are:
Kr85m, Kr87, Kr88, Rb88, Xe133, Xel33m, Xe135, Xe135m, Xel38, and CS-138.
Sometimes the plant will not report the curies f or Xe-133m or Xe-135m but they will be included under a column called "other noble gases".
Since they are generally a very small contribution to the dose it does not matter.if pgbu they are omi tt ed, hur then the number of isotopes should W
be changed to 16 or whatever is appropriate.
%/
2bO
e If it is determined that more than 10 isotopes are significant, then the code must be run twice.
V W'en the off gas treatment system goes into service, tie significant nuclides will change.
Columns 21 Stack height in meters = 150.
Includes plume rise.
Columns 31 SIGMAX (m) = 760.
Columns 41 Inplant holdup time = blank-activity reported already includes holdup correction.
Columns 51 Rainfall frequency = blank-not using code for iodine deposition.
Columns 61 Washout factor = blank-not using code for iodine deposition.
l CARDS 3.1-3.16-Windfrequencycards-Format = 6F10 c.
Wind frequency by stability class (only 6 classes) in One card f or each sector.
First card is for the north as the downwind sector and then go clockwise.
Note:
These cards are generated by the meteorological program PFEQNJFQ but will be in the wrong order j
as they will start with south as the downwfad sector.
Order of cards shall be rearranged to 9, 10, 11, 12, 13, 14, 15, 16, 1, 2, 3, 4, 5, 6, 7,.8.
d.
CARDS 4.1-4.16 - Wind speed cards - Format = 6F10 Same as for wind frequency. Again cards generated by PFEDNJFQ will be in wrong order.
c.
CARDS 5.1-5.24 - Population Carcs - Format = 8F10 Based on 1980 population estimate in M3 Environmental Report.
f.
CARDS 6.1-6.12 - Radii distances - Format 3F10 The distance in meters to the midpoint, lower and upper radii for each of the 12 radial sectors.
g.
CARDS 7.1-7.4 - Particulate deposition velocity coefficients -
6E10 Format
=
6' aince we are not using the program for deposition, use the default values of all 0.01 values on the first card s,,/
followed by 3 blank cards.
r,..q p n i; LaU v
h.
CARDS 8.1-8.4 - Halogen deposition velocity coef ficients -
h Fo nnat 6E10.
Same as for particulates.
w i.
CARD 9
- Number of isotopes per organ - Format 4I5.
Normally - 10 10 0 0 All right justified.
A maximum of 4 organs and 20 isotopes are possible. We will normally use 10 for the whole body and 10 for the skin and none for other organs.
J.
ISOTOPE CARDS There will be two to four cards for each isotope. Thus if a maximum of 20 isotopes are used there could be as many as 80 cards.
Finite cloud whole body doses are done only for the first set of isotope cards (in our example the first 10 cards).
These isotopes will have 3 or 4 cards per isotope depending on the number of gammas emitted.
The next set of cards (in our example the 10 isotopes for the skin dose calculation) will only have 2 cards per isotope.
FIkST CARD FOR EACH ISOTOPE - Format IX, A4, 1X, A/, 1X, A4, F10, E10, 315 Columns 2 Isotope symbol - Example Xe Columns 7 Mass number - Example 135m Columns 11 Critical organ - Example WB 3
Columns 16 Dose conversion f actor - mrem /s per Ci/m From Reg Guide 1.109 Table d-1 for noble gases and WASH 1258 for Cs and Rb with appropriate conversion of units.
This is the dose conversion f actor for the particular organ as specified in columns 11-15.
Columns 26 Decay constant in (sec~ ) Example 0.15E-05 should be right justified.
Columns 36 Deposition call code - Leave blank if not using deposition Set = 1 for particualtes - Rb88 and Cs138 - Right justified.
Columns 41 Finite cloud call code.
For whole body dose calculation enter the number of gammas to be considered on cards 2 or 2 and 3 for that isotope. The maxiemm number of gammas possible is 10.
For skin dose the semi-infinite claud model and hence the dose conversion factor will be used.
l Therefore enter 0.
All numbers are right j us tif ied.
4 ;,u
.,%~ hhh Columns 46 Daughter call code.
g/
Enter 0 for noble gases - enter 1 for Rb 88 and Cs 138. The isotope cards for Rb88 and Cs 138 must immediately follow the isotope cards for Kr88 and Xe138 respectively.
2nd CARD OR 2nd & 3rd CA?DS FOR WHOLE BODY ISOTOPEE Fo rma t = 12F6 The energy and abundance for each gamma.
If 3 gammas are specified in columns 41-45 of first card, then there must Ei, %)f Es$0 %d,, E 1 be 3 pairs of numbers,
.9
.3
.0009 3'6043
.03 Example for Xe-135:
.250 l LAST CARD FOR EACH ISOTOPE-Format = F10, E10 Enter in columns 1-10 the curies of the isotope released Example 8400.
- Right justified.
Columns 11 In plant decontamination facter - leave bl a nk.
For Cs-138 and Rb88, the curies released will be zero.
A blank catd will work okay.
b.
EC AD CARDS i
j These cards are the results of the dose integral program EGAD for finite cloud calculations for an elevated release of 150 meo rs.
5.
Save the old cards for approximately 1 year in case the doses must be recalculated.
6.
Submit the cards in order to run the program on tbr IBM 370.
G.
ACCEPTANCE CRITERIA Nene.
H.
CHECKLI ST S None.
I.
D FT INITIONS
!b ne.
J.
R ESPONSI BI LITY Environmentt.1 Programs B ra nc h.
n, i c.
r, ya
- . '}
,I
,