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{{#Wiki_filter:ODCM Rev. 9 Page 1 of 126 O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)
REV. 9 DOCKET No. 50-282 and 50-306 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA OPERATIONS COMMITTEE FINAL REVIEW DATE:
[4 - A 7-7 Y REVIEWED BY:
[
Cd4A ~
DATE: (o-J3-37 APPROVED BY:
[
/
LcI DATE: N0 h7 Supt Rad Prot
~
pa'A88a8888gp IBM
 
ODCM Rev. 9 Page 2 TABLE OF CONTENTS
;p) k-Section Title Page Table of Contents...................................
2 List of Figures....................................
3 List of Tables.....................................
4 Record of Revisions................................
5
 
==1.0 INTRODUCTION==
6 l
2.0 LIQUID EFFLUENTS.....................
....................... 6
]
2.1 Monitor Alarm Setpoint Determination....................
6 2.2 Liquid Effluent Concentration - Compliance with 10 CFR 20.........................................
14 2.3 Liquid Effluent Doses - Compliance with 10 CFR 50..............................................
15 i
References.............................................
19 I
(^)
l 3.0 GASEOUS EFFLUENTS...........................................
22 3.1 Monitor Alarm Setpoint Determination...................
22 3.2 Gaseous Effluent Dose Rate - Compliance with 10 CFR 20..............................................
28 3.3 Gaseous Effluent Doses - Compliance with 10 CFR 50..............................................
32 References.............................................
37 4.0 INFORMATION RELATED TO 40 CFR 190 and 40 CFR 141............
58 5.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM..................
60 APPENDIX A - Meteorological Dispersion Parameters........... 68 APPENDIX B - Joint Frequency Distribution Tables...........
107 APPENDIX C - Dose Parameters for Radiciodines, Particulate and Tritium......................
115
{}
IBM E---_-------__--------_-------
 
ODCM Rev. 9 Page 3 LIST OF FIGURES Figure Page j
5.1-1 Prairie Island Nuclear Generating Plant j
Radiation Environmental Monitoring Program........
65 5.1-2 Site Boundary TLD Locations.......................
66 5.1-3 4-5 Mile Ring, Control, and Special Interest TLD Locations............................
67 1
1 (v
1 l
l l
1 i
a I
IBM j
 
i ODCM Rev. 9 Page 4 j
LIST CF TABLES O)
~
(,
Tables Pag _e 2.1-1 Liquid Source Terms for PNGP......................
13 2.3-1 A
Value s fo r the PNGP............................ 2 0 g
3.1-1 Monitor Alarm Setpoint Determination for PNGP..... 26
)
3.1-2 Gaseous Source Terms for PNGP.....................
27 3.1-3 Dose Factors and Constants........................
27
,3.2-1 P
value s fo r the PNGP............................ 31 g
3.3-1 Dose Factors for Noble Gases and Daughters........ 38 3.3-2 R
Values for the PNGP - Ground, All Ages.........
39 f
3.3-3 R
Values for the PNGP - Vegetable, Adult.........
40 1
3.3-4 R
Values for the PNGP. Vegetable, Teen.......... 41 f
3.3-5 R
Values for the PNGP - Vegetable, Child.........
42 f
3.3-6 R
Values for the PNGP - Meat, Adult..............
43 f
3.3-7 R
Values for the PNGP - Meat, Teen...............
44 g
j 3.3-8 R
Values for the PNGP - Meat, Child..............
45 j
1 3.3-9 R. Values for_the PNGP - Cow Milk, Adult..........
46 3.3-10 R
Values for the PNGP - Cow Milk, Teen...........
47 3.3-11 R. Values for the PNGP - Cow Milk, Child..........
48 1
3.3-12 R Values for the PNGP - Cow Milk, Infant.........
49 g
3.3-13 R
Values for the PNGP - Goat Milk, Adult.........
30 1
3.3-14 R
Values for the PNGP - Goat Milk, Teen..........
51 1
3.3-15 R
Values for the PNGP - Goat Milk, Child.........
52 g
3.3-16, R
Values for the PNGP - Goat Milk, Infant........
53 1
3.3-17 R
Values for the PNGP - Inhalation, Adult........
54 g
3.3-18 R
Values for the PNGP - Inhalation, Teen.........
55 f
3.3-19 R. Values for the PNGP - Inhalation, Child........
56 1
3.3-20 R. Values for the PNGP - Inhalation, Infant.......
57 1
i 5.1-1 PNGP - Radiation Environmental Monitoring Program Sampling Locations........................
61 O
IBM
 
ODCM Rev. 9 Page 5 RECORD OF REVISIONS
%-)
Revision No.
Date Reason for Revision Original June 7, 1979 1
April 15, 1980 Incorporation of NRC Staff I
comments and correction of miscellaneous errors 1
2 August 6, 1982 Incorporation of NRC Staff comments 3
February 21, 1983 Change in milk sampling j
location j
4 November 14, 1983 Change in milk sampling location and change in j
cooling tower blowdown
]
5 March 27, 1984 Change Table 3.2-1 6
February 14, 1986 Change in location to collect l
cultivated crops (leafy l
green veg.) and removal of l
('';
meat animals from the j
N s' land use census.
j m
7 July 31, 1986 Retype and format ODCM.
I No change in' content.
8 January-8, 1987 Addition of Discharge Canal Monitor Setpoint calculation.
9 June 29, 1987 Change inhilation dose factor to child and j
address change in land I
use survey.
(3 l \\_]
l IBM
 
'4 ODCM Rev. 9' Page 6
 
==1.0 INTRODUCTION==
\\-)
This Offsite Dose Calculation Manual (ODCM) provides the information and methodologies to be used by the Prairic Island Nuclear Generating Plant (PNGP) to assure. compliance with certain portions of PNGP's Operating Technical Specification.
These portions are those related to liquid 1'
and gaseous radiological effluents.
They are intended to show complian'en with 10 CFR 20, 10 CFR 50.36A, 10 CFR 50, Appendix A (GDC 60 & 64) and Appendix I, and 40 CFR 190.
This ODCM is : based on " Radiological Effluent Technical Specifications for PWR's (NUREG-0472, Octcber, 1978),"
" Preparation of Radiological Effluent Technical Specifica-i tions for Nuclear Power Plants (NUREG-0133, October 1978),"
and other inputs from the Nuclear Regulatory Commission (USNRC).
Specific plant procedures for implementation of i
this manual are provided elsewhere.
These procedures will be utilized by the operating staff of the PNGP to assure compli-ance with the T.cchnical Specifications.
Also included in this manual is information,related to the i
Radiological Environmental Monitoring Program (REMP) in the l
form of Figtres 5.1-1, 5.1-2, 5.1-3 and Table 5.1-1.
These l
figures and table designate specific sample types and locations
{
l currently used to satisfy the technical specification require-
~
i ments for the REMP.
They are subject to change based on the
('\\-)
results of the periodic land use census.
I Although the ODCM has been prepared as generically as possible in order to minimize the need for future revisions, some changes to the ODCM may be required in the future.
Any l
I such changes will be properly reviewed.and approved as required by the PNGP Technical Specifications.
l l
2.0 LIQUID, EFFLUENTS j
2.1' Moni, tor Alarn Setpoint Determination This procednre determines the monitor alarm setpoint I
that indicates if the concentration of radionuclides in i
i the liquid effluent released at the site boundary exceeds the concentrations specified in 10~CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a l
concentration of 2 x 10-4 pCi/ml for dissolved or entrained noble gases.
Since Fe-35, Sr-89, Sr-90, and alpha concentrations, are determined from composite samples, the liquid
("J monitor setpoint determinations should be completed T
N using the nost recent available composite sample l
: results, f
IBM u
 
ODCM Rsv. 9 Pago 7 Monitor high ala*m or isolation setpoints will be
]' /
. '')
established in one of these ways:
s-a.
Monthly calculation of setpoints using the l
I methodology of Sections 2.1.1 and 2.1.3.
b.
Calculation of alarm setpoint based on analysi's prior i
to discharge using methodology of Section 2.1.2.
Alarm setpoint determined using methodology of c.
Sections 2.1.1 and 2.1.3 assuming all radionuclides have an MPC af lE-7 pCi/ml.
No recalculation of setpoints.is necessary unless an increase in alarm setpoint is desired.
PWR GALE Code source terms (Table 2.1-1) may be used if there were no detectable isotopes in the grevious month ur in the analysis prior to release.
If the newly calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new 1
value.
If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or increased to the new value.
2.1.1 Liquid Effluent Monitor Setpoints
('T The following method applies when determining
(_)
the isolation setpoints for the Waste Effluent Liquid Monitor (R-18), Steam Generator Blowdown Liquid Mpnitor - Unit 1 (1R-19), and Steam Generator Blowdown Liquid Monitor - Unit 2 i
(?R-19) during all operational conditions when the radwaste discharge flow rate is maintained
)
constant at the maximum design flow rate.
1 l
2.1.1.1 Determine the " mix" (radionuclides and composition) of the liquid effluent.
3 a.
Determine the liquid source terms that are representative of the
" mix" of the liquid effluent.
Liquid source terms are the total curies of each isotope released during the previous month.
Table 2.1-1 source terms may be used if l
there have been no liquid releases.
b.
Determine S (the fraction of the l
total radioactivity in the liquid effluent comprised by radionuclides "i") for each individual radionuclides
(~N in the liquid effluent.
%-]
IBM
 
ODCM Rev. 9 Page 8 Il A1 k/
Sg=I (2.1-1)
)
A.1 i
f = The radioactivity of radionuclides
)
A "i" in the liquid effluent.
j i
2.1.1.2 Determine C (the maximum acceptable total radioactivity concentration of all l
radionuclides in the liquid effluent j
prior to dilution (pCi/ml)).
1 C
=
F g
f S
i i
l (2.1-2) l MPC f F = Dilution water flow rate (gpm)
= 67,300 gpm from cooling tower blowdown f = The maximum attainable discharge j
flow rate prior to dilution (gpm)
= 60 gpm from the ADT tank pump ( )'
= 100 gpm from the CVCS tank pump (2)
)
l
= 60 gpm from the SGBD tank pump (2) l MPCf = The liquid effluent radioactivity concentration limit for radionuclides "i" (pci/ml) from Table 2.1-1 or
)
if not listed in Table 2.1-1, l
obtained from Reference 3.
2.1.1.3 Determine C (the maximum acceptable total radioactivity concentration of the radionuclides (minus tritium) in the liquid discharge prior to dilution (pCi/ml)).
- (C S )
(2.1-3)
C, = Cg tg H = The fraction of the total radioactivity S
in the liquid effluent contributed by tritium and other radionuclides l C that do not emit gamma or X-ray I
radiation.
IBM
 
ODCM Rev. 9 Page 9 2.1.1.4 Determine C.R. (the calculated monitor
(~)
count rate above background attributed
\\/
to the radionuclides (nepm)).
~
C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file.
C.R.
is the count rate that corresponds to the " adjusted" total radioactivity concentration (C '''
m 2.1.1.5 Determine HSP (the monitor high alarm setpoint above background (nepm)).
HSP = T,C.R.
(2.1-4)
T* = Fraction of the radioactiv'.ty from l
the site that may be released via each release point to ensure that the site boundary dose rate limit is not exceeded due to simultaneous releases from several release points.
= 0.90 for the Waste Effluent Liquid Monitor (R-18) r~s
= 0.05 for the Steam Generator Blowdown
(_
Liquid Monitor - Unit 1 (lR-19)
= 0.05 for the Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19)
T values may be revised from the sIlues given above.
The summation I
of all the T values for active release poinEs shall not be greater than unity.
I 2.1.1.6 The monitor high alarm setpoint above background (acpm), shall be set at or below the HSP value.
2.1.2 Setpoint Based on Analysis of Liquid Prior to Discharge (Optional) l This method may be used in lieu of the method in Section 2.1.1 to determine the setpoints for the maximum acceptable discharge flow rate prior to dilution and to determine the associated high l
alarm setpoint based on this flow rate for the Waste Effluent Liquid Monitor (R-lb), Steam
(~N Generator Blowdown Liquid Monitor - Unit 1
(
(lR-19), and Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19), during all operational conditions.
IBM
 
f ODCM Rev. 9 Page 10
~
2.1.2.1 Determine f (the maximum acceptable discharge flow rate prior to dilution
's (gpm)).
0.8 F T f
-=
m C
(2.1-5) 1 MPC f F = Dilution water flow rate (gpm) 3
= 67,3000 gpm from cooling tower blowdown i
C1: Concentration of radionuclides "i" in the liquid effluent prior to 1
dilution (pCi/ml) from analysis of 1
the liquid effluent to be released.
j i
MPC. = The liquid effluent radioactivity 1
concentration limit for radionuclides "1"
(pCi/ml) from Table 2.1-1 or if not listed in Table 2.1-1 from Reference 3.
/'')
T* = Fraction of the radioactivity from
(/
the site that may be released via each release point to ensure that the site boundary limit is not exceeded due to simultaneous releases from several release points.
Refer to Section 2.1.1.5.
2.1.2.2 Determine the monitor setpoint based on i
the radionuclides mix of the liquid effluent.
a.
Determine C.R. (the calculated monitor count rate above background attributed to the radionuclides (nepm)).
C.R.
is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file.
C.R.
is the count rate point that corresponds to the " adjusted" total radioactivity concentration (C,).
IBM j
 
ODCM i
Rev. 9 Page 11 C* = The total radioactivity concen-r^j tration of the radionuclides
(_/
(minus tritium and other I
radionuclides that are only beta emftters) in the liquid discharge prior to dilution f
(pCi/ml) as determine using Equation 2.1-3. (C and S beingdeterminedbyanalyNis
{
of undiluted liquid effluents.)
j b.
Determine HSP (the monitor high alarm setpoint above background (nepm)).
HSP = C.R.
(2.1-6) l 0.8 0.8 = A correction factor to increase the monitor setpoint to prevent spurious alarms caused by deviations in the mixture of radionuclides that affectr monitor response.
q c.
The monitor high alarm setpoint i
above background shall be aet at or gN (j
below this HSP value when thic optional method is selected.
The i
maximum discharge flow shall not exceed the value of f as determined in Section 2.1.2.1 when this optional method is selected.
l 2.1.3 Discharge Canal Monitor The following method determines the high alarm setpoint for the Discharge Canal Monitor (R-21) during all operational conditions.
2.1.3.1 Determine the " mix" (radionuclides and composition) of the liquid effluent.
a.
Determine the liquid source terms that are representative of the
" mix" of all liquids released into the discharge canal.
Liquid source l
terms are the total curies of each i
isotope released during the previous month.
Table 2.1-1 source terms may be used if there have been no r~;
liquid releases.
V IBM c__-_-__-_
 
1 ODCM-Rev. 9 Pege 12
)
b.
Determine Si (the fraction of the
/~ '
total radioactivity of all liquids released into the discharge canal compriced by radionuclides "i") for l
each individual radionuclides / released' l
1 into the discharge canal.
IX i
{
The radioactivity of radionuclides Ai
=
"i" released into the discharge canal.
2.1.3.2 Determine cd (the maximum acceptable diluted radioactivity concentration of all radionuclides' released'into the discharge canal (pCi/ml)).
Cd
=
1
[2. Si i
MPCi The liquid effluent radioactivity MPCi
=
concentration limit for radionuclides "i" (pCi/ml) from Table 2.1-1 or.if
.not listed in Table 2.1-1, obtained from reference 3.
2.1.3.3 Determine Cm (the maximum acceptable
;otal radioactivity concentration of the radionuclides (minus tritium) released i
into the discharge canal (pci/ml)).
Cm
=
Cd-Cd sh The fraction of the total radioactivity Sh
=
i released into the discharge canal l
comprised of tritium and other radionuclides that do not emit-tamma or X-ray radiation.
2.1.3.4 Determine C.R. (the calculated monitor count rate above background attributed to the radionuclides (ncpm)).
C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file..
C.R. is the count.
rate that corresponds to the " adjusted" O-total radioactivity concentration (Cm).
2.1.3.5 The monitor high alarm setpoint above background.
(nepm) shall be set at or above the C.R. value. l IBM I
 
ODCM
)
Rev. 9 Page 13 TABLE 2.'l-1 LIQUID SOURCE TERMS WASTE EFFLUENT SGBD-RADIONUCLIDES MPC (pCi/ml)
(A.)(Ci/Yr)
(A;)(Ci/Yr)
Mo-99 4E-5 6.42E 1.415E-2 I-131 3E-7 3.061E 4.11E-2 Te-132 2E-5 2.12E-3 3.61E-3 I-132 8E-6 2.83E 1.88E-2 1-133 1E-6 2.365E-2 4.856E-2 Cs-134 9E-6 1.464E-1 4.047E-2 I-135 4E-6 4.84E-3 1.792Ea2 Cs-136 6E-5 5.743E-2 1.862E-2 Cs-137 2E-5 8.214E-2 2.69E-2 i
All Others 1E-7 0
2E-5 1
H-3 3E-3 1.89E2
: 1. 41E2 -
Noble gases 2E-4 3
Total 1.894E2 1.412E2 f
4 q
($)
a O
4 1
IBM i
3
 
l ODCM Rev. 9 Page 14 2.2 Compliance With 10 CFR 20 k-)
In order to comply with 10 CFR 20, the concentrations of radionuclides in liquid effluents will not exceed the maximum permissible concentrations (MPC) as defined in Appendix B, Table II of 10 CFR 20.
For continuous releases, I
the alarm trip setpoints discussed in Section 2.1 will f
assure that these concentrations are not exceeded.
For i
batch releases, concentrations of radioactivity in effluents l
prior to dilution will be determined, providing protection l
in addition to the alarm trip setpoint discussed in Section 2.1 Concentration in diluted effluents will be calculated using these results.
2.2.1 Continuous Releases i
Continuous liquid releases can occur from PNGP through steam generator blowdown.
The alarm I
trip setpoints discussed in Section 2.1 will assure that releases from this pathway will not l
exceed the limits of 10 CFR 20.
j Other minor releases of a continuous nature have occurred at PNGP through the turbine building sump system.
These releases were minor and are I
not expected to occur in the future.
However, a (N /^')
continuous composite sampler will be maintained i
at the discharge from the turbine building sump l
with samples being taken and analyzed weekly.
I If these samples indicate detectable levels of radionuclides, the methodologies given in l
Section 2.2.2 will be applied to the turbine
{
sump weekly releases and the limit in Equation l
2.2-2 will be lowered to account for this source term.
2.2.2 B,atch Releases To further show compliance with 10 CFR 20, the l
radioactivity content of each batch release will be determined prior to release.
The i
concentration of the various radionuclides in l
the batch release prior to dilution, is divided l
by the minimum dilution flow to obtain the concentration at the site boundary.
This i
calculation is shown in the following equation:
t C
R i
(2.2-1) j Cone
=
f MDF (O
where
%-)
f = concentration of radionuclides i at the Cone site boundary, pCi/ml;
)
IBM
-_--__-___,I
 
ODCM Rev. 9 Page 15 C
= concentration of radionuclides i in the i
("}
potential batch release, pCi/ml; V
R
= release rate of the batch MDF
= minimum dilution flow (=67,300 gpm)
The projected concentration at the site boundary is compared to the MPCs in Appendix B, Table II of 10 CFR 20 which sre given in Table 2.1-1.
Before a release may occur, Equation 2.2-2 must be met for all isotopes, p
Conc i u
0.9 (2.2-2) i MPC f
Maximum permissible concentration MPC.
=
1 of radionuclides i from Appendix B, Table II of 10 CFR 20. pCi/ml The summation has been reduced from 1.0 to 0.9 to account for simultaneous continuous releases from steam generator blowdown as given in Section 2.1.1.5.
As noted earlier, this fraction may be
,r T adjusted based on experience.
The summation of
(_)
all source terms shall not be greater than 1.0 of the 10 CFR 20 limit.
2.3 Liquid Effluent Doses - Compliance with 10 CFR 50 Doses resulting from liquid effluents will be calculated monthly to show compliance with 10 CFR 50.
A cumulative summation of total body and organ doses for each calendar quarter and calendar year will be maintained as well as projected doses for the next month.
Since Fe-55, Sr-89, Sr-90, and alpha concentrations are determined from composite samples, the monthly liquid effluent dose calculations and comparisons to quarterly and annual limits should be completed using the most recent available composite sample results.
The quarterly and annual dose calculations shall be completed using the actual composite sample results.
1 l
The limits of 10 CFR 50 are on a per reactor unit basis.
The liquid radwaste system at PNGP is shared by both reactor units making it impossible to separate the releases of the two units.
The releases that can be
(~)
separated by unit, steam generator blowdown and turbine
\\_/
building sump releases, contribute a very small portion of the total liquid releases from PNGP.
Therefore, for compliance with 10 CFR 50 the releases from both units will be summed and the limits of Appendix 1 will be doubled.
IBM
\\
 
'ODCM Rev. 9 Page 16 2.3.1 Determination of Liquid Effluent Dilution
.To determine doses from liquid' effluents the near field average dilution factor for the period of release must.be calculated..This dilution factor must.be calculated for each batch release and each continuous release mode.
The dilution factor is determined by:
1 R
k (2.3-1)
F
=
k X ADFk where release rate of the batch or R
=
k J
continuous releases during the period,-k, gal; 1
actual dilution flow during the ADF
=
k tiie period of release k, gal.
The value of X is the site specific factor for
.j the mixing effect of the PNGP discharge 1
i This value is.10-for PNGP while (1)
("3 structure.
(/
operating in the closed cycle cooling mode.
TheproductofXandADFuislimitedto1000-j cfs (4.5 x 10 gpm).
Therefore, since blowdown the5 enominator l
flow in closed cycle is 150 cfs, d
of Equation 2.3-1 is always 4.5 x 10 in closed j
cycle.
In once through or helper mode, the j
value of X is reduced to 1.0.
1 2.3.2 Dose Calculations
)
The dose contribution from the release of liquid i
effluents will be calculated monthly.
The dose contribution will be calculated using the following equation:
where:
DI
=
IIA t
F (2.3-2) gz k
ik k-ki where:
the dose commitment to the total-I Dt
=
body or any orgc.n I, from the liquid effluents for the period of release,. mrem;
]
IBM
.l
.J
 
ODCM Rev. 9 l
Paga 17 the average concentration of-C
=
ik (N
radionuclides, i, in undiluted Ll liquid effluent for liquid release k, pCi/ml; the site related ingestion dose A
=
tz commitment factor to the total body or any organ I for each 1
identified principal gamma and beta emitter, mrem /hr per pCi/ml; i
the near field average dilution
)
F
=
k factor for C during liquid effluentrelbsek,
{
I the duration of release k, hours.
j t
=
k The dose factor A was calculated for an adult foreachisotopeblingthefollowingequation:
)
1.14 x 105 [21BF DFft]
(2.3-3)
A
=
1 17 where:
5 6
3 10 pCi x 10 ml x 1 yr 1.14 x 10
=
pCi
~T 8760 hr C()
21
=
adult fish consumption, Kg/yr; bioaccumulation factor for BF.
=
1 radionuclides i in fish from Table A-1 of Regulatory Guide 1.109 Rev. 1 (5) pCi/Kg per.pCi/1; dose conversion factor for DF *
=
i radionuclides i for adults for a particular organ I from Table E-ll of Regulatory Guide 1.109 Rev. 1, (s), mrem /pC1.
values for an adult at the PNGP A table of A *in Table 2.3-1.
arepresenteb Mississippi River water is not used as a potable water supply within 300 miles downstream of the PNGP.
Wells are used for irrigation downstream of the plant.
O 1BM
 
ODCM Rev. 9 Page 18 l
2.3.3 Cumulation of Doses p_
k-)
Doses calculated monthly will be summed for comparison with quarterly and annual limits.
j The monthly results should be added to the doses cumulated from the other months in the quarter of interest and in the year of interest for the i
combined releases of both reactor units.
The following relationships should hold:
For the quarter, D
3.0 mrem total body (2.3-4)
D 10 mrem any organ (2.3-5) 7 1
For the cal.endar ye,u,
)
i D
6.0 mrem total body (2.3-6) z D
20 mrem any organ (2.3-7)
)
7 I
1 The quarterly limits given above represent one half of the annoal design objective.
If these quarterly or annual limits are exceeded, a special report should be submitted to the USNRC identifying the
('');
cause and corrective action to be taken.
If
' (-
twice the quarterly or s.inual limits are exceeded, i
a special report shall 'n
'ubmitted showing compliance with 40 CFR 'A 2.3.4 Projection of Doses Anticipated doses resulting from the release of liquid effluents will be projected monthly.
If the projected doses for the month exceed 2 percent of Equation 2.3-6 or 2.3-7, additional components of the liquid radwaste treatment system will be used to process waste.
The projected doses will be calculated using Equation 2.3-2.
The dilution factor, F "ill be calculated by replacing the term ADFk'in Equation 2.3-1withthetermMDFfromEkuation 2.2-1.
The total source term utilized for the most recent dose calculation should be used for the projections unless information exists indicating tnat actual releases could differ significantly in the next month.
In this case, the source term would be adjusted to reflect this information and the justification for the adjustment noted.
This adjustment should f'/)
account for any radwaste equipment which was operated during the previous month that could be x_
out of service in the coming month.
1 IBM l
 
ODCM 1
.Rev 9-Page 19-REFERENCES.
1.
" Prairie Island Final Environmental ~ Statement,"'USAEC, May, 1973, p. V-26.
2-
"NSP - Prairie Island Nuclear Generating Plant, Appendix I Analysis - Supplement No. 1 -. Docket No. 50-282 and 50-306,"
Table 2.1-1.
3.
"10 CFR 20," Appendix B, Table II,. column 2.
4.
"NSP - Prairie Island Nuclear. Generating Plant, Appendix I Analysis --Supplement No. 1 - docket 50-282 and 50-306," July 21, 1976, Table 2.1-2.
5.
U. S. Nuclear Regulatory Commission. " Regulatory Guide 1.109
- Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Compliance with 10 CFR.50, Appendix 1," Rev. 1, 1977.
I IBM
 
l ODCM i
Rev. 9 j
Page 20 j
TABLE 2.3-1 j
(]
A VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT l
V (MREM /HR PER pCI/ML) 1 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 4
i 1H 3
0.00E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 l
6C 14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 J
11NA 24 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 24CR 51 0.00E-01 0.00E-01 1.27E 00 7.61E-01 2.81E-01 1.69E 00 3.20E 02 s
25MN 54 0.00E-01 4.38E 03 8.35E 02 0 00E-01 1.30E 03 0.00E-01 1.34E 04 l
25MN 56 0.00E-01 1.10E 02 1.95E 01 0.00E-01 1.40E 02 0.00E-01 3.51E 03 26FE 55 6.58E 02 4.55E 02 1.06E 02 0.00E-01 0.00E-01 2.54E 02 2,61E 02 26FE 59 1.04E 03 2.44E 03 9.36E 02 0.00E-01 0.00E-01 6.82E 02 8.14E 03 27CO 58 0.00E-01 8.92E 01 2.00E 02 0.00E-01 0.00E-01 0.00E-01 1.81E 03 q
27C0 60 0.00E-01 2.56E 02 5.65E 02 0.00E-01 0.00E-01 0.00E-01 4.81E 03 28NI 63 3.11E 04 2.16E 03 1.04E 03 0.00E-01 0.00E-01 0.00E-01 4.50E 02 l
28NI 65 1.26E 02 1.64E 01 7.49E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 j'
l 29CU 64 0.00E-01 9.97E 00 4.68E 00 0.00E-01 2.51E 01 0.00E-01 8.50E 02 30ZN 65 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.00E-01 4.64E 04 307N 69 4.93E 01 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 l
35BR 83 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.82E 01 35BR 84 0.00E-01 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 4.11E-04 35BR 85 0.00E-01 0.00E-01 2.15E 04 0.00E-01 0.00E-01 0.00E-01 1.01E-15 37RB 86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 37RB 88 0.00E-01 2.90E 02 1.54E 02 0.00E-01 0.00E-01 0.00E-01 4.0.0E-09
(]
37RB 89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 i V 38SR 89 2.21E 04 0.00E-01 6.35E 02 0.00E-01 0.00E-01 0.00E-01 3.55E 03 1
38SR 90 5.44E 05 0.00E-01 1.34E 05 0.00E-01 0.00E-01 0.00E-01 1.57E 04 l
f 38SR 91 4.07E 02 0.00E-01 1.64E 01 0.00E-01 0.00E-01 0.00E-01 1.94E 03 385R 92 1.54E 02 0.00E-01 6.68E 00 0.00E-01 0.00E-01 0.00E-01 3.06E 03
)
39Y 90 5.76E-01 0.00E-01 1.54E-02 0.00E-01 0.00E-01 0.00E-01 6.10E 03 39Y 91M 5.44E-03 0.00E-01 2.11E-04 0.00E-01 0.00E-01 0.00E-01 1.60E-02 39Y 91 8.44E 00 0.00E-01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 4.64E 03 39Y 92 5.06E-02 0.00E-01 1.48E-03 0.00E-01 0.00E-01 0.00E-01 8.86E 02 39Y 93 1.60E-01 0.00E-01 4.43E-03 0.00E-01 0.00E-01 0.00E-01 5.09E 03 40ZR 95 2.40E-01 7.70E-02 5.21E-02 0.00E-01 1.21E-01 0.00E-01 2.44E 02 40ZR 97 '
1.33E-02 2.68E-03 1.22E-03 0.00E-01 4.04E-03 0.00E-01 8.30E 02 41NB 95 4.47E 02 2.48E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 42MO 99 0.00E-01 1.03E 02 1.96E 01 0.00E-01 2.34E 02 0.00E-01 2.39E 02 j
43TC 99M 8.87E-03 2.51E-02 3.19E-01 0.00E-01 3.81E-01 1.23E-02 1.48E 01 43TC101 9.12E-03 1.31E-02 1.29E-01 0.00E-01 2.37E-01 6.72E-03 3.95E-14 44RU103 4.43E 00 0.00E-01 1.91E 00 0.00E-01 1.69E 01 0.00E-01 5.17E 02 l
44RU105 3.69E-01 0.00E-01
' 46E-01 0.00E-01 4.76E 00 0.00E-01 2.26E 02 44RU106 6.58E 01 0.00E-01 8.33E 00 0.00E-01 1.27E 02 0.00E-01 4.26E 03 47AG110M 8.81E-01 8.15E-01 4.84E-01 0.00E-01 1.60E 00 0.00E-01 3.33E 02 52TE125M 2.57E 03 9.30E 02 3.44E 02 7.72E 02 1.04E 04 0.00E-01 1.02E 04 52TE127M 6.48E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 52TE127 1.,05E 02 3.78E 01 2.28E 01 7.80E 01 4.29E 02 0.00E-01 8.31E 03 52TE129M 1.10E 04 4.11E 03 1.74E 03 3.78E 03 4.60E 04 0.00E-01 5.54E 04 52TE129 3.01E 01 1.1.?E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01
~3 52TE132M 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E-01 8.04E 04 (V
52TE131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.26E 01 0.u0E-01 2.67E 00 l
52TE132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.38E 04 53I 130 2.71E 01 8.01E 01 3.16E 01 6.79E 03 1.25E 02 0.00E-01 6.89E 01 53I 131 1.49E 02 2.14E 02 1.22E 02 7.00E 04 3.66E 02 0.00E-01 5.64E 01 l
f IBM
 
i f
ODCM Rev. 9 Page 21 TABLE 2.3-1 (CONT.)
/7 A
VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT
'I
(_,)
(MREM /HR PER pCI/ML)
RUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 53I 132 7.29E 00 1.95E 01 6.82E 00 6.82E 02 3.11E 01 0.00E-01 3.66E 00 53I 133 5.10E 01 8.87E 01 2.70E 01 1.30E 04 1.55E 02 0.00E-01 7.97E 01 53I 134 3.81E 00 1.03E 01 3.70E 00 1.79E 02 1.64E 01 0.00E-01 9.01E-03 53I 135 1.59E 01 4.17E 01 1.54E 01 2.75E 03 6.68E 01 0.00E-01 4.70E 01 55CS134 2.98E 05 7.09E 05 5.79E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 1
55CS136 3.12E 04 1.23E 05 8.86E 04 0.00E-01 6.85E 04 9.38E 03 1.40E 04 55CS137 3.82E 05 5.22E 05 3.42E 05 0.00E-01 1.77E 05 5.89E 04 1.01E 04 55CS138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E 01 2.23E-03 56BA139 9.29E-01 6.62E-04 2.72E-02 0.00E-01 6.19E-04 3.75E-04 1.65E 00 56BA140 1.94E 02 2.44E-01 1.27E 01 0.00E-01 8.30E-02 1.40E-01 4.00E 02 56BA141 4.51E-01 3.41E-04 1.5 2E-02 0.00E-01 3.17E-04 1.93E-04 2.13E-10 56BA142 2.04E-01 2.10E-04 1.28E-02 0.00E-01 1.77E-04 1.19E-04 2.37E-19 57LA140 1.50E-01 7.54E-02 1.99E-02 0.00E-01 0.00E-01 0.00E-01 5.54E 03 57LA142 7.66E-03 3.48E-03 8.68E-04 0.00E-01 0.00E-01 0.00E-01 2.54E 01 58CE141 2.24E-02 1.522-02 1.72E-03 0.00E-01 7.04E-03 0.00E-01 5.79E 01 58CE143 3.95E-03 2.92E 00 3.2S5-04 0.00E-01 1,29E-03 0.00E-01 1.09E 02 58CE144 1.17E 00 4.88E-01 6.27E-02 0.00E-01 2.90E-01 0.00E-01 3.95E 02 59PR143 5.51E-01 2.21E-01 2.73E-02 0.00E-01 1.27E-01 0.00E-01 2.41E 03 59PR144 1.80E-03 7.48E-04 9.16E-05 0.00E-01 4.22E-04 0.00E-01 2.59E-10 60ND147 3.76E-01 4.35E-01 2.60E-02 0.00E-01 2 54E-01 0.00E-01 2.09E 03 gg 74W 187 2.96E 02 2.47E 02 8.65E 01 0.00E-01 0.00E-01 0.00E-01 8.10E 04
(,)
93NP239 2.85E-02 2.80E-03 1.54E-03 0.00E-01 8.74E-03 0.00E-01 5.75E 02 l
I r(
IBM J
 
o 1
1 ODCM Rev. 9 Page 22 j
J 3.0 GASEOUS EFFLUENTS l
N-)
i 3.1 Monitor Alarm Setpoint Determination
]
This procedure determines the monitor alarm setpoint that indicates if the dose rate at or beyond the site i
boundary due to noble gas radionuclides in the gaseous J
effluent released from the site exceeds 500 mrem / year j
to the whole body or exceeds 3000 mrem / year to the skin.
l Monitor high alarm or isolation setpoints will be established in one of the following ways:
3 Monthly calculation of setpoint using the methodology
)
a.
of Section 3.1.1 for continuous releases using previous month releases as source term.
j b.
Prior to each containment purge, recalculation of j
the setpoint using the methodology of Section 3.1.1 1
based on the sample taken prior to purging.
{
i c.
In lieu of (a) and (b) above, alarm setpoints may be established using the methodology of Section 3.1.1 using conservative assumptions (e.g., 100%
Kr-89).
No recalculation of setpoints is necessary unless an incr. ease is desired.
PWR GALE Code source terms (Table 3.1-2) may be used if there were no detectable isotopes in the previous month or in the analysis prior to purging.
If the newly calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value.
If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or increased to the new value.
3.1.1 Effluent Monitors The following method applies when determining the isolation or high alarm setpoint for the monitors listed in Table 3.1-1.
3.1.1.1 Determine the " mix" (noble gas radio-nuclides and composition) of the gaseous effluent.
a.
Determine the gaseous source terms that are representative of the gaseous e f fluent.
Gaseous source terms are the total cut.ss of each noble gas released during the previous month or a repre-
,C]~
sentative analysis of the gaseous effluent.
\\
Table 3.1-2 source terms may be used l
if the releases for the previous month were below the lower limits of detection (LLD).
IBM
 
q 4
q ODCM i
Rev. 9-Page'23 m -
b.
Determine S., (the' fraction of the c
L total radioactivity in the gaseous-effluent' comprised by noble. gas radionuclides "1") for each individual noble gas radionuclides in the gaseous effluent.
1 (3.1-1)
IA f
i 1
The radioactivity of noble A.
=
1 gas radionuclides "i" in the j
gaseous effluent from Table 3.1-2.
3.1.1.2 Determine Q (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent (pCi/sec)) based upon the whole-body-exposure limit.
J
=
500 (3.1-2)
Q t (x/Q) I KS fg O
The highest calculated annual (x/Q).
=
average-relative concentration of effluents released via the plant vents for any_ area at or beyond the site boundary for 3
all sectors (sec/m ) from the-
"x/Q" column in Table 3.1-l'.
The total whole body dose factor due i
K
=
g to gamma emissions from noble gas 3 3
4 radionuclides "i" (mrem / year /pC1/m )
from Table 3.1-3.
3.1.1.3 Determine Q based upon the skin exposure t
limit.
=
3000 (3.1-3)
Q t (x/Q) I (Li + 1.1 M )
S g,
i i
The total skin dose factor L1 + 1.1 H.
=
1 due to emissions from noble
.O*
gas radionuclides "i" (mrem /
year /pCi/m )'from Table 3.~1-3.
3
' IBM
 
ODCM
-Rev. 9' Page 24 f.
1 3.1.1.4. Determine C (the maximum acceptable total radio 3ctivity concentration of all
{}.
noble gas radionuclides'in the gaseous effluent (pCi/cc)).
Q (3.1-4)
C
=
2.12 E-3 t
t F
NOTE:
Use the. lower of the.Q values j
obtained in Sections 391.1.2 l
and 3.1.1.3.
F = The maximum effluen't. flow rate i
at the point of release (cfm)
'l from the " Effluent' Flow Rate" a
column in Ta.ble 3.1-1.
2.12 E-3 = Unit conversion constant to-convert pCi/sec/cfm to pCi/cc.
3.1.1.5 Determine C.R..(the calculated monitor.
l count rate above background attributed to the noble gas radionuclides (nepm)).-
C.R. is obtained by using the applicable l
Effluent Monitor Efficiency Curve located l
in the Radiation Monitor Calibration-file.
C.R. is the count rate point that. corresponds to the total radioactivity. concentration (C ).
g 3.1.1.6 Determine HSP (the monitor-high alarm setpoint above background (ncpm)).
HSP = T,C.R.
(3.1-5)
T*
= Fraction of the. total radicain ivity 1
from the site that.may be released via each release paint to ensure that the site boundary limit'is not exceeded due to simultaneous releases from several release J
points from the~" Release Fraction" l
column in Table 3.1 :1, 3.1.1.7 The isolation or high alarm setpoints 1
above background:(nepm) for.the monitors should be set at or below the HSP values.
3.1.2 Air Ejector Monitors Radiation monitors 1R-15 and 2R-15 provide an indication of gross noble gas activity'at the main condenser air ejector of Unit 1 and Unit:2, respectively.
These monitors are provided.to IBM
 
1
:0DCM l
Rev. 9 Page 25
)
give rapid indication of' steam generator tube
'f) leakage.
They are not effluent monitors since v
the air ejectors are vented'to the auxiliary building vents during normal plant' operation and releases are monitored by the auxiliary building vent monitoring system.
l l
l i
4 O
e O
IBM
_ _ _ _ _ _ = - _ _ _ - _ -
 
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t eg wg nl a 3
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1 l
 
ODCM Rev. 9 Page'27 l
TABLE 3.1-2 GASEOUS SOURCE TERMS (1)
~
' AUX. BLDG SHIELD BLDG.
AIR EJECTOR
. Ci/Yr)
(A ) (Ci/Yr)
(A ) (Ci/Yr)
RADIONUCLIDES (A )
(
1 f
g 2EO
'Kr-85m 3E0 Kr-85 2EO
: 2. 2El-Kr-87 1EO Kr-88 SEO'
-1EO 3E0 Xe-131m 2EO 2.1E1.
1EO Xe-133m SEO 2E1 3E0 Xe-133 3.7E2 2.7E3 2.3E2 Xe-135 8EO 6EO SEO Xe-138 1EO Total 3.97E2 2.77E3 2.44E2
" " indicates that the release is less than 1 Ci/yr.
O i
9 IBM
---------.-.__-_a-----
-a
 
]
ODCM Rev. 9 Page 28 TABLE 3.1-3
)
DOSE FACTORS AND CONSTANTS i
SKIN TOTAL WHOLE BODY DOSE FACTOR DOSE FACTOR (L
+ 1.lM ) 3 3
(mrkm/yr/pC1/m)
RADIONUCLIDES (K ) (mrem /yr/pCi/m )
g Kr-83m 7.56E-2 2.12El Kr-85m 1.17E3 2.81E3 Kr-85 1.61El 1.36E3 Kr-87 5.92E3 1.65E4 Kr-88 1.47E4 1.91E4 Kr-89 1.66E4 2.91E4 Kr-90 1.56E4 2.52E4 Xe-131m 9.15El 6.48E2 1
Xe-133m
: 2. 52.E2 1.35E3 l
Xe-133 2.94E2 6.94E2 j
Xe-135m 3.12E3 4.41E3 1
Xe-135 1.81E3 3.97E3 Xe-137 1.42E3 1.39E4 Xe-138 8.83E3 1.43E4 Ar-41 8.84E3 1.29E4 r-3.2 Gaseous Effluent Dose Rate - Comoliance with 10 CFR 20
(_
Dose rates resulting from the release of noble gases, and radiciodines and particulate must be calculated to show compliance with 10 CFR 20.
The limits of 10 CFR 20 must be met on an instantaneous basis at the hypothetical worst case location, and apply on a per site basis.
Since Sr-89 and Sr-90 concentrations are determined from composite samples, the pre-release, weekly and monthly airborne dose calculations and comparisons to quarterly and annual limits should be. completed using the most recent available composite sample results.
The quarterly dose values and critical receptors reported semi-annually to the USNRC shall be calculated using the actual composite results.
q
/
O IBM
 
ODCM Rev. 9 Page 29 3.2.1 Noble Gases gg The dose rate at the site boundary resulting from noble gas effluents i: limited by 10 CFR 20 to 500 mrem /yr to the total body and 3000 arem/yr to the skin.
The setpoint determinations discussed in the previous section are based en the dose calculational method presented in NUREG-0133.(2) 3 They represent a backward solution to the limiting dose equations in NUREG-0133.
Setting alarm set trip points in this manner will assure that the limits of 10 CFR 20 are met for noble gas releases.
Therefore, no routine dose calculations for noble gases will be needed to show compliance with this part.
Routine calculations will be made for doses from noble gas releases to show compliance with 10 CFR 50, Appendix I as discussed in Section 3.3.1.
3.2.2 Radiciodine, Radioactive Particulate, and Other Radionuclides The dose rate at the site boundary resulting from the release of radioiodines and particulate with half lives greater than 8 days is limited by 10 CFR 20 to 1500 mrem /yr to any organ.
Calculations 9
showing compliance with this dose rate limit will be performed for batch releases prior to the release and weekly for all releases.
The calculations will be based on the results of sample analyses obtained pursuant to the PNGP Technical Specifications.
To show compliance, Equations 3.2-1 will be evaluated for I-131, tritium, and radioactive particulate with half-lives greater than eight days.
I P
(x/Q )
Qgy
< 1500 mrem /yr (3.2-1) g y
i I
where s
P infant critical organ dose parameter for i
=
y radionuclides i for the inhalation pathway, 3
mrem /yr per pCi/m (Table 3.2-1);
annual average relative deposition for (X/Q)v
=
long-term release at the critical location, l
3 sec/m (Appendix A, Table A-4);
I IBM
 
ODCM
.Rev. 9 Page 30 annual average relative deposition for (D/Q)v
=
long-term release at the critical (Appendix A, Table A-5);
2
\\-
location, 1/m the total release rate of radionuclides i Q
=
iv from all vents from both units for the batch 1
or week of interest, pCi/sec;
)
Radioiodines, tritium, and radioactive particulate will be released from up to.six individual vents all within 300 feet of each other.
For showing com-pliance with 10 CFR 20, calculations based on Equa-tion 3.2-1 will be made once per week.
The source terms (Qgy) will be determined from the results of analysis of vent particulate filters and charcoal canisters and vent flow rate.
These source terms include all' gaseous releases from PNGP.
Significant short-term batch releases of long-lived a
radioactive particulate and tritium will result from
)
containment purges.
Calculations will be made for these 1
releases separately to further assure compliance with 10 CFR l
Part 20 prior to release.
These calculations will be used only to determine whether or not the purge release will be q
allowed to occur.
Source terms will be determined from the
("T results of isotopic analyses of samples from containment
)
(_)
prior to release.
Equation 3.2.1 will be used.in conjunction j
with the following relationship to demonstrate that the batch a
release does not exceed the dose rate limit:
D)
(3.2-2)
BL =
1500 - (D y
p where i
BL =
limiting dose rate for the. batch, mrem /yr; previous week's doses from all vent D
=
v releases, mrem /yr; previous week's doses from all purge D
=
p releases mrem /yr.
3.2.3 Critical Receptor Identification The atmospheric dispersion parameters given in Appendix A will be used to identify the critical receptor.
Compliance with Part.20 will always be shown at the site boundary location.with the highest X/Q.
As discussed previously, weekly and batch dose calculations will be performed at this O
location.
The critical site boundary. location, based upon long term ground level releases x/Q (Table A-3), is 0.36 miles in the WNW sector.
4 IBM
 
.0DCM Rev.'9
.Pege 31-1
.]
TABLE 3.2-1 j
Values for Child P ty-l l
mrem /yr l
3 l
ISOTOPE l'
P
'pCi/m g
17 I
I I
l H-3.
.l 1.12 E 3 l
l Cr-51 l
1.70'E 4 l
1 Mn-54 l
1.58'E 6 l
l l
Fe-59
-l
: 1. L2 E 6 l
l Co-58 l
1.11.E 6 l
l-Co-60 1
7.07 E 6 l-l Zn-65 l
9.95 E 5 l
l l
Rb-86 l
1.98 E-5 l
l Sr-89 l
2.16 E 6-l j
l Sr-90 l
1.01-E 8 l
l Y-91 l
2.63 E 6 l
O i
zr-95 i
2.23 E e i
l Nb-95 l
6.14 E 5
'l l
Ru-103 l
6.62 E 5.
l j
l Ru-106 l
1.43 E.7-l l
l Ag-110m 1
5.48 E 6 l
l Te-127m 1
1.48 E 6 l
1 l
Te-129m l
1.76 E 6 l
l Cs-134 1
1.01 E 6 l
1 Cs-136 l
1.71 E 5 l
l Cs-137 l
9.07 E 5 l
^
l Ba-140 l
1.74 E 6 l
l Ce-141 l
5.44 E 5 l
l l
Ce-144 l
1.20.E 7 l
l I-131 l
1.62 E 7 l
1 I
I O
IBM.
 
.+$p D' E 'h IMAGE EVALUATION d
/////
24 g
,E,,,--
l.0
;; m tu m
?c e \\\\11n lj 2
* hN l.8 1.25 1.4 1.6 l
4 150mm 4
6"
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4
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ODCM Rev. 9 Pega 32 a
3.3 Gaseous Effluents - Compliance with 10 CFR 50
;,m,
(_).
Doses'resulting from the release of noble gases, and radioiodines &nd particulate must be calculated.to show compliance with Appendix 1 of 10 CFR 50.
The calculations will be performed monthly for all gaseous effluents.
1
~ The limits of 10 CFR 50 are on a per reactor unit basis.
The f
gaseous radwaste treatment system and the auxiliary building at PNGP is shared by both reactor units making.it impossible to separate the releases of the two units.
The releases that can be separated by unit contribute a very small portion of the total gaseous releases from PNGP.
Therefore, for compliance with 10 CFR 50 the releases from both units
{
will be summed and the limits of Appendix 1 w_.1 be doubled.
j i
Since Sr-89 and Sr-90 concentrations are determined from
(
~
composite samples, the pre-release, weekly and monthly u
airborne dose calculations and comparisons to quarterly and annual limits should be completed using the most recent
(
available composite. sample results.
The quarterly dose l
values and critical receptors reported semi-annually to the USNRC shall be calculated using the actual composite results.
f 3.3.1 Noble Gas Ai_)
3.3.1.1 Dose Equations The air dose at the critical receptor due to noble gases released in gaseous effluents is determined by Equations 3.3-1 and 3.3-2.
The critical receptor will be identified as described in Section 3.3.4.
)
For gamma radiation:
3.17 x 10-8 y 3
(xfq)v giv + (xjq)v iv j
q i
< 10 mrad for any calendar quarter
< 20 mrad for any calendar year (3.3-1)
L For beta radiation:
1 3.17 x 10-8 I N
(X/Q)y Qiy + (X/4)y41y f
[
< 20 mrad for any calendar quarter t
()
< 40 mrad for any. calendar year (3.3-2)
L
.lBM
 
ODCM R
Rcv. 9 Paga 33 where:
$Q i
1 The air dose factor due to gamma. emission A_/
M
=
g for each identified noble gas radionuclides i, mrad /yr per pCi/m3; (Table 3.3-1) the air dose factor due to beta emissions N
=
g for each identified n3ble gas. radionuclides i, mrad /yr per pCi/m ; (Table 3.3-1) 3 the annual average relative concentration i
(x/Q)y
=
for areas at or beyoid the restricted area l
boundary for long-term vent releases 3
L (greater than 500 hr./ year), sec/m (Appendix A, Table A-4);
the relative concet:. ration for areas at or (x/q)y
=
beyond the restricted area boundary for short-term vent releases (equal to or less 3
than 500 hrs / year), sec/m (Appendix A, Table A-7);
qfy the total release of noble gas radionuclides
=
i in gaseous effluents for short-term vent releases from both units (equal to or less than 500 hrs / year), pCi; i
Qgy the total release of noble gas radionuclides l
=
i in gaseous effluents for long-term vent releases from both units (greater than 500 j
hrs /yr), pCi; j
3.17 x 10-8 the i'nverse of the number of seconds in
=
a year.
Noble gases will be released from PNGP from up to nine vents.
l Long-term x/Q's were given in Appendix A.
Short-term x/q's were calculated using the USNRC computer code "XOQDOQ" assuming 100 hours per year short term releases and are given in Appendix A (Table A-7).
Values of M and N were calculated using the methodology presented in NUREG-0133 and are given in Table 3.3-1.
3.3.1.2 Cumulation of Doses Doses calculated monthly will be summed for comparison with quarterly and annual limits.
The monthly results will be
/'^s ~
added to the doses cumulated from the e
A_,/
other months in the quarter of interest in the year of interest and compared to i
IBM
 
ODCM Rev. 9 Page 34 the limits given in Equations 3.3-1 and
~
3.3-2.
If these limits are exceeded, a special report will be submitted to the USNRC in accordance with the PNGP Technical Specifications.
If twice the limits are exceeded, a special report showing compliance with 40 CFR 190 will be submitted.
3.3.2 Radiciodine, Particulate, and Other Radionuclides 1
3.3.2.1 Dose Equations The worst case dose to an individual from 1-131, tritium, and radioactive particulate with half-lives greater than eight days in gaseous effluents released to unrestricted areas is determined by the following expressions:
During any calendar quarter cn: year-3.17 x 10-8 R
V9v 1v + "v 1v 9
ij ak J 1
~
< 15 mrem (per quarter)
< 30 mrem (per calendar year)
(3.3-3) llk where:
release of radionuclides i for long-term Q
=
1v vent releases from both units (greater than 500 hrs /yr), pCi; releast of radionuclides i for short term
=
qiv purge releases from both units (equal to or less than 500 hrs /yr); pCi; the dispersion parameter for estimating W
=
y the dose to an individual at the controlling location for long-term vent releases (greater than 500 hrs /yr);
the dispersion parameter for estimating the v
=
V dose to an individual at the controlling location for short-term vent releases (equal to or less than 500 hrs /yr);
-8 the inverse of the number of seconds in 3.17 x 10
=
a year; R
O ijak =
the dose factor for each identified radionuclides i, pathway j, age group a, and organ k, m mrem /yr per pCi/sec or mrem /yr 3
per pCi/m.
 
ODCM R v. 9 Pega 35 The above equation will be applied to each
.s r^T combination of age group and organ.
Values of
(_)
R have been calculated using the methodology gkd8binNUREG-0133andaregiveninTables3.3-2 through 3.3-20.
Dose factors for isotopes not listed will be determined in accordance with the methodology in Appendix C.
Equation 3.3-3 will be applied to a controlling location which will have one or more of the following:
residence, vegetable garden and milk animal.
The selection of the actual receptor is discussed in Section 3.3.4.
The source terms and dispersion parameters in Equation 3.3-3 are obtained in the same manner as in Section 3.2.
The W 3
values are in terms of x/Q(sec/m ) for the inhalction pathways and for tritium (Tables 2
A-4 and A-5) and in terms of D/Q(1/m ) for all other pathways (Tables A-7 and A-8).
3.3.2.2 Cumulation of Doses Doses calculated monthly will be summed for comparison with quarterly and annual limite.
The monthly results should be added to the doses cumulated from the other months in the quarter of interest 73 and in the year of interest and compared
()
with the limits in Equation 3.3-3.
If these limits are exceeded, a special
, report will be submitted in accordanct with the PNGP Technical Specifications.
If twice the limits are exceeded, a special report showing compliance with 40 CFR 190 will be submitted.
3.3.3 Project. ion of Doses Doses resulting from the release of gaseous i
effluents will be projected monthly.
The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month.
In this case the source terms will be adjusted to reflect this information and the justification for the adjustment noted.
If the projected release of noble gases for the month exceeds 2 percent of the calendar year limits of equation 3.3-1 or 3.3-2, additional waste gas treatment will be provided.
If the projected release of I-132, tritium, and radioactive particulate with half-lives greater than 8 days r~'
exceeds 2 percent of the calendar year limit of
(
equation 3.3-3, operation of the ventilation exhaust treatment equipment is required if not currently in use.
IBM
 
ODCM Rev. 9 Page 36' 3.3.4 Critical Receptor Identification The critical receptors for compliance with 10 CFR 50, Appendix I will be identified.
For the noble gas specification the critical location will be based on the beta,and gamma air doses
)
I only.
This location will be the offsite location with the highest long term vent x/Q and will be I
selected using the X/Q values given in Appendix A, Table A-3.
This location will remain the same unless meteorological data is reevaluated or the site boundary changes.
The critical location for the 1-131, tritium, and long-lived particulate pathway will be selected once each year.
The selection will follow the annual land use census performed within 5 miles of the PNGP.
Each of the following locations will be evaluated as potential critical receptors prior to implementation of the Radioactive Effluent Technical Specifications:
: 1. Residence in each sector
: 2. Vegetable garden producing leafy green vegetables
: 3. All identified milk animal locations Following the annual survey, doses will be calculated using Equation 3.3-3 for all new identified receptors and those receptors whose characteristics have changed significantly. The calculation will include appropriate information about each new location.
The dispersion parameters given in this manual should be employed.
The total releases reported for the previous calendar year should be used as the source terms.
O IBM
 
ODCM Rev. 9 Pege 37 1
; O REFERENCES l NJ-l l
(1)
"NSP-Prairie Island Nuclear Genecc. ting Plant, Appendix I Analysis'- Supplement No. 1 - Docket No. 50-282 and 50-306",
Table 2.1-4.
1 I
i 1
I I
l i
l l
/~
s IBM
 
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it r
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f Ac e
E E E E E E E E E E E E E E E a
a p
3 3 2 7 2 3 3 6 7 3 6 2 1
1 0
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E F
0 0 0 0 0 0 0 0 0 0 0 0 0 0 E
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RE ilIllIi1l11II1lIlIIlIIlI11I III P
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L
 
ODCM Rcv. 9 Pego 58 4.0 INFORMATION RELATED TO 40 CFR 190 and 40 CFR 141
,m
( ')
The PNGP Technical Specifications indicate that if twice the per unit limits of 10 CFR 50, Appendix I are exceeded, a
'~
special report is required.
Therefore, if twice the annual limits of Equations 2.3-6, 2.3-7, 3.3-1, 3.3-2 or 3.3-3 are exceeded, the licensee shall prepare and submit a Special Report to the Commission and limit subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over 12 consecutive months.
This special Report is to include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the standards in 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations.
If analysis indicates that releases resulting in doses that exceed the 40 CFR 190 Standard may have occurred, then a variance from the Commission to permit such releases will be obtained.
The Standard Technical Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3 consider doses to a real individual and apply to each reactor but do not include any other portion of the uranium fuel cycle or direct shine from the reactor.
(/~\\
The " Uranium fuel cycle" is defined in 40 CFR Part 190.02(b)
_j as:
" Uranium fuel cycle means the operations of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle."
The Special Report will contain:
1)
A determination of which uranium fuel cycle facilities or operations, in addition to the nuclear power reactor units at the site, contribute to the annual dose to the maximum exposed member of the public.
Only those other fuel cycle facilities within 5 miles of PNGP need be considered.
No such facilities exist or are planned at f-present.
(
IBM
 
ODCM Rcv. 9 Paga 59 2)
A determination of the maximum exposed member of the P'
public as given for determining compliance with 10 CFR
(
50, Appendix I.
3)
A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents using the methodologies described for compliance with 10 CFR 50, Appendix I in this ODCM.
Where additional information on pathways and nuclides is needed, the best available information will be used and documented.
4)
A determination of the dose resulting from direct radiation from the plant and storage facilities.
The various organ doses resulting from liquid effluents from the PNGP will be summed with the organ doses resulting from releases of nobic gases, radioiodines and particulate.
These doses will be based upon releases from the PNGP during the past 3 quarters and from the quarter in which twice the specification was exceeded.
The doses from the PNGP will be summed with the doses to the maximum exposed individual contributed from other operations of the uranium fuel cycle.
The direct dose components will be determined by either calculation er actual measurement.
The N-16 component of direct radiation may be calculated using SKYSHINE. A Computer r~
()g Procedure Evaluhting Effects of Structure Design on N-16 Gamma-Ray Dose Rates.
Radiation Research Associates, Inc.
Report RRA-T7209, November 1972.
.(Available in the NSP-NSS Library).
The calculation or actual measurement will be documented in this Special Report.
If the quarterly or annual doses due to liquid releases exceed the values listed in Section 2.3.3, a special report shall be submitted to the USNRC and shall include information related to 40 CFR 141 such as analysis of Mississippi River water and an analysis of possible impacts through the drinking water pathway.
IBM l
 
ODCM Rcv. 9 Pega 60 5.0 RADIATION' ENVIRONMENTAL MONITORING PROGRAM (q
r 5.1 Sampling
_j Table 5.1-1 and Figures 5.1-1, 5.1-2, and 5.1-3 specify the current sampling locations based on the latest land use census.
If it is learned from an annual census that milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those i
previously sampled, the new milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable.
Sample locations (except the control) having lower calculated doses may be dropped from the program at the end of the grazing or growing season (October 31) to keep the total number of sample locations constant.
An annual land use survey will be conducted to determine whether corn fields are irrigated with water taken from the Mississippi River between the plant and a point 5 miles downstream.
If corn fields are being irrigated with Mississippi River water, appropriate samples will be collected and analyzed per Technical Specifications, Table 4.10-1.
73i' ')
5.2 Interlaboratory Comparison Program Analyses shall be performed on radioactive samples supplied by the EPA crosscheck program.
This program involves the analyses of samples provided by a control laboratory and comparison of results with those of the control laboratory as well as with other laboratories which receive portions of the same samples.
Media used in this program (air, milk, water, etc.) shall be limited to those found in the radiation environmental monitoring program.
The results of analyses performed as a part of the crosscheck program shall be included in the Annual Radiation Environmental Monitoring Report.
IBM
 
g ODCM Rev. 9 Page 61 TABLE 5.1-1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT l
RADIATION ENVIRONMENTAL MONITORING PROGRAM l
SAMPLING LOCATIONS Type of Sample Code Collection Site Location River Water P-S Upstream of Plant 0.6 mi @ 602/ENE c
River Water P-6 Lock & Dam #3 1.6 mi @ 129*/SE Drinking Water P-ll City of Red Wing 7.1 mi @ 135*/SE c
Well Water P-25 Kinneman Farm 11.1 mi @ 331*/NNW Well Water P-6 Lock & Dam #3 1.6 mi @ 129 /SE Well Water P-8 Kinney Store 2.0 mi 9 280 /W Well Water P-9 Plant Well #2 0.3 mi @ 306 /NW Sediment-River P-5 Upstream of Plant 0.6 mi @ 60 /ENE C
Sediment-River P-6 Lock & Dam #3 1.6 mi 0 129 /SE Sediment-Shoreline F-12 Recreation Area 3.4 mi @ 116 /ESE Periphyton or P-S Upstream of Plant 0.6 mi @ 60 /ENE e
O xecrei vertedrete-e-6 tecx & oe
#2 1.e mi e 12e SE Fish P-5 Upstream of Plant 0.6 mi @ 60 /ENE C
Fish P-6 Lock & Dam #3 1.6 mi @ 129*/SE Milk P-25 Kinneman Farm 11.1 mi @ 331 /NNW c
Milk P-14 Gustafson Farm 2.2 mi @ 168*/SSE Milk P-16 Johnson Farm 2.6 mi @ 60 /ENE Milk P-17 Place Farm 3.5 mi @ 25 /NNE Milk P-18 Christensen Farm 3.7 mi @ 88*/E IBM
 
ODCM Rsv. 9 Pcgn 62 TABLE 5.1-1 (Continued) c.
h
~I PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS I
Type of Sample Code Collection Site Location Cultivated Crops (Leafy Green Veg)
P-25c Kinneman Farm 11.1 mi @ 331*/NNW P-24 Suter Residence 0.6 mi @ 158 /SSE (Corn)
P-25" Kinneman Farm 11.1 mi 0 331 /NNW P-14 Gustafson Farm 2.2 mi @ 168*/SSE c
Particulate and P-1 Air Station P-1 16.5 mi @ 348 /NNW Radioiodine (air)
Particulate and P-2 Air Station P-2 0.5 mi @ 294*/WNW Radiciodine (air) p(,)
Particulate and P-3 Air Station P-3 0.8 mi @ 313 /NW Radiciodine (air)
Particulate and P-4 Air Station P-4 0.4 mi @ 359*/N Radiciodine (air) l Part.iculates and P-6 Air Station P-6 1.6 mi @ 129 /SE' Radioiodine (air)
Direct Radiation 1
(TLD)
POlA Property Line 0.4 mi @ 359 /N I
Direct Radiation (TLD)
PO2A Prope/ty Line 0.3 mi @ 19 /NNE i
Direct Radiation (TLD)
PO3A Property Line 0.5 mi @ 183*/S Direct Radiation j
(TLD)
PO4A Property Line 0.4 mi @ 204 /SSW l Direct Radiation (TLD)
POSA Property Line 0.4 mi @ 225c/SW f)i
\\,
IBM
 
ODCM Rev. 9 Pega 63 TABLE 5.1-1 (Continued) g
.y
[
' PRAIRIE ISLAND NUCLEAR GENERATING PLANT
's ~
RADIATION-ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type of Sample Code Collection-Site Location
. Direct Radiation (TLD)
PO6A Property Line' O.4'mi @ 249*/WSW Direct-Radiation (TLD)
PO7A Property Line 0.4 mi @ 268*/W Direct Radiation (TLD)
PO8A Property Line 0.4 mi-@ 291*/WNW Direct Radiation (TLD)
PO9A Property Line 0.7 mi @ 317 /NW Direct Radiation
-(TLD)
P10A Property Line 0.5 mi @ 333 /NNW' Direct Radiation (TLD)
PolB Tom Killian Res.
4.7 mi @ 355 /N 5
Direct Radiation (TLD)
PO2B Roy Kinneman Farm 4.8 mi @ 17*/NNE Direct Radiation (TLD).
PO3B Wayne Anderson Farm 4.9 mi @ 46 /NE Direct Radiation (TLD)
PO4B Nelson Drive (Road) 4.2,mi @ 61*/ENE Direct Radiation (TLD)'
PO5B County Rd E & Coulee 4.1 mi 9 97 /E Direct Radiation (TLD)
PO6B William Houschildt Res.
4.4 mi @ 112*/ESE Direct Radiation (TLD)
PO7B Red Wing Service Center 4.7 mi 0 140*/SE Direct Radiation (TLD)
PO8B David Wnuk Res.
4.1 mi @ 165 /SSE Direct Radiation (TLD)
PO9B Hwy 19 South 4.2 mi @ 187 /s Direct Radiation
-(TLD)
P10B Cannondale Farm 4.9 mi @ 200 /SSW
. IBM
 
ODCM R:v. 9 P:go 64 TABLE 5.1-1 (Continued) j 7,
s t
)
PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type af Sample
_ Code Collection Site Location Direct Radiation (TLD)
P11B Wallace Weberg Farm 4.5 mi @ 221 /SW Direct Radiation (TLD)
P12B Roy Gergen Farm 4.5 mi @ 247a/WSW Direct Radiation (TLD)
P13B Thomas O'Rourke Farm 4.4 mi @ 270 /V l
Direct Radiation (TLD)
P14B David Anderson Farm 4.9 mi @ 3C6*/NW Direct Radiation (TLD)
P15B Holst Farms 4.2 mi @ 347 /NNW Direct Radiation (TLD)
P0lS Federal Lock & Dam #3 1.6 mi @ 129 /SE
,3
' ''-)
Direct Radiation (TLD)
P02S Charles Suter Res.
0.5 mi @ 155 /SSE Direct Radiation (TLD)
P03S Carl Gustafson Farm 2.2 mi @ 168 /SSE Direct Radiation (TLD)
P04S Richard B rt Res.
2.0 mi 0 228 /SW Direct Radiation (TLD)
POSS Kinney Store 2.0 mi @ 270 /W Direct Radiation (TLD)
P06S Earl Flynn Farm 2.5 mi @ 299 /WNW Direct Radiation (TLD)
P01C Robert Kinneman Farm 11.1 mi @ 331 /NNW l l
* "c" denotes control location.
All other locations are indicators.
The letters af ter numbered TLD's are as follows:
"A" denotes locations in the general area of the site boundary.
g3 "B" denotes locations about 4 to 5 miles distance from the plant.
"S" denotes special interest locations.
IBM I
l
 
ODCM Rev. 9 Pege 65 s
FIG URE 5.1-1
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ODCM Rev. 9 Figurs 5.1-3 Page'67 NOF.IEI?.:' STX"IS PGli?. COMPls n*
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ODCM Rcv. 9 Pega 68 APPENDIX A - METEOROLOGICAL ANALYSES
[r''N i'')
Table A-1 Release Conditions Table A-2 Unrestricted Area Boundaries Table A-3 Long Term - Ground Level - Unrestricted Area Boundary - X/Q and D/Q.
Table A-4 Long Term - Ground Level.- Standard Distances - X/Q Table,A-5 Long Term - Ground Level - Standard Distances - D/Q
-Table A-6 Short Term - Ground Level - Unrestricted Area-Boundary - X/q and D/q Table A-7 Short Term - Ground Level - Standard Distances - X/4 Table A-8 Short Term - Ground Level - Standard Distances - D/q 6
l
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IBM I
 
ODCM Rev. 9 Peg 2 69 APPENDIX - A
.,m
)
'~'
Summary of Dispersion Calculational Procedures Undepleted, undecayed dispersion parameters were computed using the computer program XOQDOQ (Sagendorf and Goll, 1977).
Specifically, sector average x/Q and D/Q values were obtained for a sector width of 22.5 degrees.
Building wake corrections were used to adjust calculations for ground-level releases.
Standard open terrain recirculation correction factors were also applied as available as default values in XOQDOQ.
Dispersion calculations were based on ground level releases for the shield buildings, turbine building, and auxiliary building (hereafter referred to as the plant complex).
A summary of release conditions used as input to XOQDOQ is presented in Table A-1 and controlling unrestricted boundary distances are defined in Table A-2.
Computed x/Q and D/Q values for unrestricted area boundary locations (relative to release points) and for standard distances (to five miles from the source in 0.1 mile increments) are presented in Tables A-3 through A-8.
Onsite meteorological data for the period April 1, 1977 through March 31, 1978 (as presented in Appendix B) were used as input to
(~;
XOQDOQ.
Data were collected and AT stability classes were
(,)
defined in conformance with NRC Regulatory Guide 1.23.
Dispersion calculations for the plant complex were based on AT 42.7-12.2m and 12.2 meter wind data (joint data recovery of 96 percent).
r~m I
U IBM a
 
ODCM Rev. 9 Pega 70 C'N REFERENCES
.G,M),.
(_/
l.
Sagendorf, J.F. and Goll, J.T.,
XOQDOQ Program for the Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG-0324, U.S. Nuclear Regulatory Commission, September 1977.
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ODCM
-Rav. 9 Page 72 TABLE A-2 s -
e es.
D Distances (Miles) To Controlling. Unrestricted Area. Boundary Locations As Measured from Edge of Plant' Complex Sector Distance N
0.28-NNE 0.26 NE 0.84*
i ENE 0.62*
E 0.59*
ESE 0.61*
SE 0.67 SSE 0.43 i
S 0.43 i
SSW 0.40 SW 0.40 l
WSW 0.37 l
W 0.36 WNW 0.36 1
NW 0.43 NNW 0.48
* Over-water distances O
IBM
 
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.L 4
f APPENDIX - B
[
Prairie Island 12.2m Wind an-d AT 42.7-12'.2m 8t*Di1IU7
-Joint Frequency Distributions (4/1/77 - 3/31/78)
I i
IBM
 
l-
-ODCM I
-Rsv. 9 Page 108
/*
NORTHERN STATES POWER COMPANY PRAIRIE ISLAND' NUCLEAR GENERATING PLANT j
SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:
4/1/77 THROUGH 3/31/78 STABILITY CLASS A
{
ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION
'1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N
7 22 29 11 0
0 69 NNE 13 19 20 4
0 0
56 l
NE 11 35 16 1
0 0
63-DE 11 33 20 0
0 0
64 E
14 37 24 0
0 0
75 ESE 4
45 49 7
2 0
107 SE 4
10 22 13 1
0 50 SSE 1
7 19 12 2
0 41 S
2 23 45 27 0
0 97 SSW 1
22 39 14 0
0 76 SW 2
17 30 3
0 0
52
~
WSW 0
21 25 11 0
0 57 W
1 29 46 18 2
0 96 WNW 6
34 64 56 20 1
181 NW 12 42 72 53 20 0
199 NNW 11 43 49 20 2
0 125 VAR 0
0 0
0 0
0 0
(
TOTAL HOURS THIS CLASS 1408 HOURS OF CALM THIS CLASS 0
~
PERCENT OF ALL DATA THIS CLASS 16.81 IBM
 
ODCM Rcv. 9 '
.Pcga 109-
~.
NORTHERN STATES POWER COMPANY
.' /9
. PRAIRIE ISLAND NUCLEAR GENERATING PLANT V
SITE METEOROLOGY'- FREQUENCY DISTRIBUTION TABLES-HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:
4/1/77 THROUGH 3/31/78, STABILITY CLASS B ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL
-DIRECTION 1 TO 3 4 TO 7 8 TO 12
-13 TO 18 19 TO 24 ABOVE 24 TOTAL j
N O
3 5
1 0
0 9
NNE 1
2 1
1 0
0 5
NE O
2 0
0 0
0 2
ENE O
3 2
0 0
0' 5
E O
1 1
0 0
0 2
ESE 1
5 10 6
1 0
23 SE 2
2 8
4 0
0
.16 SSE O
3 4
3 0
0 10 S
1 0
7 9
0
.0 17.
SSW 0
1 7
0 0
0 8
SW 0
4 1
0 0
0 5
WSW 1
2 5
1 0
0 9
W 0
8 7
3 0
0
-18 WNW 1
5 8
6 3
0 23 NW 2
4 11 10 1
0 28 1
NNW 1
5 3
1 0
1 11 VAR 0
0 0
0 0
0 0
e TOTAL HOURS THIS CLASS 191 A
HOURS OF CALM THIS CLASS 0
PERCENT OF ALL DATA THIS CLASS 2.28 IBM-
 
ODCM Rsv. 9 Pags 110 "x
NORTHERN STATES POWER COMPANY
.f'j PRAIRIE ISLAND NUCLEAR GENERATING PLANT
\\s SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:
4/1/77 THROUGH 3/31/78 STABILITY CLASS C ELEVATION 40 FT I
WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL ' l N
2 4
4 1
0 0
11 NNE 2
3 1
0 0
0 6
NE 1
5 1
0 0
0 7
ENE O
3 1
0 0
0 4
E 1
8 3
0 0
0 12
,A ESE 0
7 11 2
0 0
20
(
SE O
2 5
6 0
0 13 SSE O
2 6
7 1
0 16 S
0 2
10 4
0 0
16 SSW 1
6 4
0 0
0 11 l
l SW 2
2 3
2 0
0 9
l WSW 1
6 5
1 2
0 15 W
0 2
11 4
1 0
18 WNW 1
3 6
7 1
0 18 L
NW 2
7 11 16 6
1 43 NNW 3
5 7
3 3
0 21 VAR 0
0 0
0 0
0 0
TOTAL HOURS THIS CLASS 240
.O)
N HOURS OF CALM THIS CLASS 0
PERCENT OF ALL DATA THIS CLASS 2.87 IBM
 
ODCM.
Rev. 9 Pega 111.
NORTRERN STATES POWER COMPANY.
.<m I f~'C PRAIRIE ISLAND NUCLEAR GENERATING PLANT I
b SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:
4/1/77 THROUGH 3/31/78 STABILITY CLASS D' ELEVATION 40 FT WIND SPEED (MPH) AT 40 IT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N
9 24 11 8
0 0
52 NNE 6
22 9
0 0
0 37 NE 16 26 4
0 0
0 46 ENE 11 41 4
0 0
0 56 E
11 95 27 0
0 0
133 TN ESE 8
57 154 19 0
0 238
\\
SE 10 30 90 38 5
0 173 SSE 8
40 59 51 10 0
168.
l S
1 51 72 17 4
0 145 SSW 5
29 30 12 0
0 76 j
SW 4
15 17 4
0 0
40 WSW 5
23 31 21 3
4 87 W
6 53 61 28 6
1 155 WNW 14 57 76 75 21 0
243 NW 14 44 72 110 41 0
281 NNW 16 22 41 25 13 0
117 VAR 0
0 0
0 0
0 0
i 7
TOTAL HOURS THIS CLASS 2051
.\\
HOURS OF CALM THIS CLASS 4
l PERCENT OF ALL DATA THIS CLASS 24,49 e
IBM
 
ODCM
'l Rcv. 9 Pega 112 NORTHERN STATES POWER COMPANY
[,m.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT A.
SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:
4/1/77 THROUGH 3/31/78 STABILITY CLASS E ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL j
N 22 30 9
11 1
0 73 NNE 18 29 7
0 0
0
$4' l
l NE 22 26 7
1 0
0 56 ENE 19 30 5
1 0
0 55 E
25 96 10 0
0 0
131 O
ESE 28 144 140 27 0
0 349 b
SE 24 107 125
-41 2
0 299 l
.a SSE 21 67 74 23 0
0 185 S
11 56 73 29 1.
0 170 SSW 3
26 29 40 1
0 99 SW 14 22 17 12 0
0 65 WSW 14 24 24 11 1.
0 74 W
26 73 48 18 1
0 166 WNW 46 136 127 44 4
0 357 NW' 46 98 101 62 8
0 315 l
.i NNW 43 53 48 10 3
0 157 VAR 0
0 0
0 0
0 0
TOTAL HOURS THIS CLASS 2612 N '
HOURS OF CALM THIS CLASS 7
PERCENT OF ALL DATA THIS CLASS 31.18 IBM i
 
ODCM.
s.
Rsv. 9
.Page 113 A.
NORTERN' STATES POWER COMPANY.
PRAIRIE ISLAND NUCLEAR GENERATING' PLANT j[
SITE ETEOROLOGY - FREQUENCY DISTRIBUTION TABLES 3
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:- 4/1/77 THROUGH 3/31/78 STABILITY CLASS'F ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL-DIRECTION
.1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N
18 8
3 0
0 0'
29 NNE-11 6
1 0
0 0
18 NE 11 5
2 0
0 0
18 ENE 13 7
0 0
0 0
20 E
29 33 2-0 0
0 64 ESE 39 61 9
1 0
0 110 SE 38 69 36
'3.
0 0
146
'SSE 27 32 17 2
1 0
79.
S 12 16 21 7
0 0
56
'SSW 6
.11 17.
6 0.
0 40 SW 5
3 9
4 0
0 21 WSW 8
8 8
0 0
0 24 W
25 39 12
'2 0
0 78 WNW 56 63 12 0
0 0
131 NW
.66 71 16 3
0
-0 156 s
NNW-29 19 6
2 0
0 56 VAR 0
0 0
0 0
0 0
TOTAL HOURS THIS CLASS 1053 HOURS OF CALM THIS CLASS 7
PERCENT OF ALL DATA THIS CLASS 12.57 IBM
 
ODCM Rsv. 9 Page 114 NORTHERN STATES POWER COMPANY y'-.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES-HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS G ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N
14 5
0 0
0 0
19 NNE 13 2
1 0
0 0
16 NE 12 2
1 0
0 0
15 ENE 22 1
2 0
0 0-25 E
52 8
2 0
0 0
62 O
.ESE 50 17 1
0 0
0 68 l
Ag SE 37 23 8
1 0
0 69 SSE 18 8
7 2
0 0
35 S
11 4
4 0
0 0
19 I
SSW 13 2
2 0
0 0
17 SW 15 5
1 0
0 0
21 WSW 10 1
1 0
0 0
12 W
41 19 1
0 0
0 61 WNW 75 50 0
0 0
0 125 NW 80 66 3
0 0
0 149 NNW 47 19 5
0 0
0 71 VAR 0
0 0
0 0
0 0
l TOTAL HOURS THIS CLASS 821 HOURS OF CALM THIS CLASS 37 PERCENT OF ALL DATA THIS CLASS 9.80 IBM
_ _ - ___ L
 
'l ODCM
-Rsv. 9 Page 115 fbm.)i '
i APPENDIX _Q DOSE PARAMETERS FOR RADIOIODINES, PARTICULATE AND TRITIUM This appendix contains the' methodology.which was used to calculate the dose parameters for radioiodines, particulate, and tritium to show compliance with 10 CFR 20 and Appendix I of 10 CFR 50 for gaseous effluents.
These dose parameters, P and-R, were 1
calculatedusingthemethodologyoutlinedinNURkG-0133along with Regulatory Guide 1.109 Revision 1.
The following sections provide the specific methodology which was utilized in calculating the P and R values for the various exposure g
g pathways.
C.1 Calculation of Pj The parameter,'P, contained in the radiciodine,and particulatesporbionofSection3.2,includespathway
(]
transport parameters of the ith radionuclides, the receptor's N-usage of the pathway media and the dosimetry of the exposure.
Pathway usage rates and the internal dosimetry are functions of the receptor's age: however, the youngest age grcup, the infant, will always receive the maximum dose under the exposure conditions assumed.
C.1.1 Inhalation Pathway K'(BR) DFA (C.1-1)
P
=
f g
I where:
dose parameter for radionuclides i for the P
=
3 g
inhalation pathway, mrem /yr per pCi/m ;
I K'
=
a constant of unit conversion:
6
=
10 pCi/pCi; tgebreathingrateoftheinfantagegroup, BR
=
m fyr; i
the maximum organ inhalation dose factor
>\\
DFA.
=
1 for the infant age group for radionuclides i, mrem /pci.
IBM
 
ODCM R v. 9 Page 116 fant group.
The infant's The age group considered is the ig/yr from Table E-5 of d
breathing' rate is taken as 1400 m Regulatory Guide 1.109-Revision 1.
The inhalation dose factors for the infant, DFA are presented in Table E-10 ofRegulatoryGuide1.109ik,unitsofmrem/pci.
The total body is considered as an organ in the selection of DFA.
Theincorporationofbreathingrateofaninfantandthe unit conversion factor results in the'following:
9 1.4 x 10 DFA (C.1-2)
P
=
f f
I C.2 Calculation of R.
The radioiodine and particulate Technical Specification is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs.
The inhalation and ground plane exposure pathways shall be considered to exist at all locations.
The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are considered based on their existence at the various locations.
R values have been calculated for the adult, 4
teen, child, and infant age groups for the ground plane, cow milk, goat milk, vegetable and beef ingestion pathways.
The CV) methodology.which was utilized to cElculate these values is presented below.
4 C.2.1' Inhalation Pathway 0 (BR),(DFA ),
(C.2-1)
/
R
=
g f
I where:
dose factor for each identified R
=
i radionuclides i of the organ of interest, 3
t mrem /yr per pCi/m ;
a constant of unit conversion:
K'
=
6
=
10 pCi/pCi; of the receptor of (BR),
breathing ratg/yr:
=
age group a,m g
organ inhalation dose factor for (DFA )#
=
g radionuclides i for the receptor of age group a, mrem /pCi.
The breathing rates (BR) for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109 Revision 1.
IBM i
 
"N i
i" i
'.ODCM 4
Rev. 9
'Page 117 Age Group (a)
Breathing Rate (m /yr)
Infant 1400 Child 3700 Teen-8000 Adult 8000 Inhalation dose factors (DFA )
for the various age groups 4
are given in Tables E-7 throog$ E 10 of Regulatory Guide 1.109 Revision 1.
C.2.2 Ground Plane Pathway
-A t I K'K"(SF)DFG (1-e i )/x (C.2-2)
R
=
f f
1 G
where:
dose factor for the ground plane pathway R
=
g for each identified radionuclides i for G
the organ of @terest, mram/yr per pCi/sec per m ';
e constant of unit conversion; K'-
=
6
=
10 pCi/pci; a constant of unit conversion; K"
=
8760 hr/ year;
=
the radiological decay' constant'for A
=
i radionuclides i, sec~l; the exposure time, see; t
=
8 4.73 x 10 see (15 years);
=
the ground plane dose conversion factgr DFG
=
f for radionuclides i; mrem /hr per pCi/m ;
the shielding factor (dimensionless);
SF
=
factor to account for fractional I
=
i deposition of radionuclides 1.
For radionuclides other than iodine, the factor I.
is For radiciodines, the value of I diay i
equal to one.
However,avalueof1.0wasusedincaleblating vary.
the R values in Table 3.3-2.
IBM
 
ODCM Rev. 9
:Pega.-118 ym Q.
A shielding factor;of 0.7 is suggested in Table.E-15 of Regulatory Guide-1.109 Revision 1.
A tabulation.
of DFG4 values is presented in Table E-6 of Regulatory' Guide 1.109 Revision 1.
C.'2. 3 Grass-Cow or Goat-Milk Pathway l
4 *b)-
-A t
1 Iiv(1~*
if r(1-e i*)'+
+
R Fsp,N ),e f f, 73 pz
. 3 g ; "' I K'Q F
1
~
g p
~
g PE i
-A
~
*(1-*
I )
B (1-e i b)',-A e
.(c.2-3)
E g
<(1-f f )-
+:
gy o
Ps L
Y,AE.
PA
!,a.
i 1
.Odere:
R.t
. dose factor for the cow milk or goat milk
=
'M-pathway, for each identified radionuclides i-f mrem /yr per for the organ,,9; interest,
'pCi/see per m a constant.of unit conversion; K'
=
6
=-
10 pCi/pci; Qp the cow's or goat's feed consumption rate, f
'i
's
=
l kg/ day (wet weight);
i the receptor's milk consumption rate t'or age U
=
ap group a, liters /yr; i
the agricultural productivity by unit area Y
=
p-of pasture feed grass, kg/m ;
theagriculturalprojuctivitybyunitarea Y
=
3 of stored feed, kg/m ;
the stable element transfer coefficients, F*
=
pCi/ liter per pCi/ day;
.s fraction of deposited activity retained on l
r
=
cow's feed grass; i
the organ ingestion dose factor for (DFL )j
=
g radionuclides i for the receptor in age group 7'
: t., mres/pCi; 1x
'' ir
~ o,,
IBM m
 
L ODCM Rsv.:9 Pega-119 2N A
=
Ai+A'
(
E w
.. _j the radiological decgy constant for A
=
f radionuclides i,.sec the decay constant for removal of activity A
=
W on 1gaf and plant surfaces by weathering, sec 5.73 x 10-7
~1 (corresponding to a sec
=
14 day half-life);
the transport time from feed to cow or goat t
=
g to milk, to receptor, see; the transport time from' harvest, to cow or t
=
h goat, to consumption, sec; period of time that sediment is exposed to t
b gaseous effluents sec; concentration factor for uptake of B
=
iv radionuclides i from the soil by the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg.(dry soil);
f) effectlye surface density for soil, (dry
's / '
P
=
soil)/m ;
fraction of the year that the cow or goat f
=
p is on pasture;
~
fraction of the cow feed that is pasture f
=
s grass while the cow is on pasture; I
t, period of pasture grass and crop exposure
=
during the growing season, sec; factor to account for fractional deposition I
=
f of radionuclides i.
For radionuclides other than iodine, the factor 14 is equal to one.
For radioiodines, the value of Ig may l
[
vary. However, a value of 1.0 was used in calculating t
the R values Tables 3.3-9 through 3.3-16.
i l
Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds.
Following the development in Regulatory Guide 1.109 Revision 1, the value of f was considered unity in
[~').
lieu of site-specific information.
The valt.e of f p
\\s was 0.667 based upon an 8-month grazing period.
IBM l
 
l ODCM Rcv. 9'
)
Page 120 i
Table C-1 contains the appropriate parameter values and-their source in Regulatory Guide 1.109 Revision 1.
The concentration of tritium in milk is based on the airborne concentration rather than the deposition.
Therefore, the R is based on X/Q:
1 K'K"'F,QpQp,p(DFL ),
0.75(0.5/H)
(C.2-4)
U R
=
g T
where:
dose factor for the cow or goat milk pathway R
=
T for tritium for tge organ of interest, M
mrem /yr per pCi/m ;
a constant of unit conversion; K"'
=
3 10 gm/kg;
=
3 absolute humidity of the atmosphere', gm/m ;
H
=
the fraction of total feed that is water; 0.75
=
the ratio of the specific activity of the 0.5
=
feed grass water to the atmospheric water.
and other parameters gnd values are given above.
A value of H of 8 grams / meter, was used in lieu of site-specific information.
C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore:
E Biv(1-e i b).
-A t gs r(1-i e)
+
I K'Q U,pF (DFL ), e ff R
=
g p
g "A *b)
~
-A t
i
#fl~*
i )
iv (
e ih (C.2-5)
(1-f f )
+
ps Y,AE g
PA I
where:
dose factor for the meat ingestion pathway R.
=
l f interest, for radionuclides i for any2;rgan
(
B mrem /yr per pCi/sec per m IBM
 
mg 1'
ODCM-Rev. 9'
:Pege 121
~
F
=.
the stable: element' transfer coefficients, f
.pCi/Kg per pCi/ day;-
.the receptor's meat consumption rate.for age-
~U
=-
ap group a, kg/yr; t,
the transport time.from slaughter to
=
consumption, sec; the transport time from harvest to animal t
=
h.
consumption,=see; I
t*
period.of pasture grass and' crop' exposure
=
during the growing season, sec;..
factor to account for fractional deposition I
=
f of: radionuclides i.
For radionuclides other than iodine, the factor 14 is equal to one.
For radioiodines,.the value of.1 ms.y vaty.
4 However, a value of 1.0 was used in calculating the R values in Tables'3.3-6 through 3.3-8.
All~other terms remain the same as defined in Equation C.2-3.
Table C-2 contains the values which'were used in calculating R for the meat pathway.
f The concentration of tritium in meat is based on its airborne concentration rather than the deposition.
Therefore, the R is based on X/Q.
f K'K"'F Q U,p(DFL ),
0.75(0.5/H)
(C.2-6)
R
=
f7 f
T where:
dose factor for the meat ingestion pathway R
=
T for tritium for agy organ of interest, mrem /yr per pCi/m All other terms are defined in Equation C.2-4 and C.2-5, above.
C.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor.
Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:
~ IBM
 
{
[
1 ODCM l
Rev. 9
)
Page.122 f~
\\
-A t
*t
_x g
L iL r (1-e g e),Bgy(1-e g b)
-A E E
I K,(DFL )a Uf e R
=
1 1
aL YA PA iy yE g
1.
~
-A t
Biv(
i b) -
-A g r(1-e i
(C.2-7) i ) +
O e Uf ag YA i
yE i
1 where:
dose factor for vegetable pathway for R
=
b radionuclides i for the organ of injerest, mrem /yr per pCi/sec per m
a constant of unit conversion:
K'
=
6
=
10 pCi/pci; b
the consumption rate of fresh leafy U
=
vegetation by the receptor in age group a, kg/yr; S
the consumption rate of stored U,
=
vegetation by the receptor in age group a, kg/yr; the fraction of the annual intake of f
=
b fresh leafy vegetation grown locally; the fraction of the annual intake of f
=
E stored vegetation grown locally; the average time between harvest of t
=
g leafy vegetation and its consumption, sec; the average time between harvest of t
=
h stored vegetation and its consumption, sec; the vegetation areal density, kg/m2; Y
a y
period of leafy vegetable exposure t
=
8 during growing season, sec; I.
=
factor to account for fractional 1
N deposition of radionuclides i.
IBM
 
r ODCM
+
Rev. 9 Page 123-
~
!/
* For radionuclides other than iodine, the factor I is d
equal to one.. For radioiodines, the value1 of'I. bay However, a 7alue of 1.0 was used.in calediating-vary.
.the R. values in' cables 3.3-9 through 3.3-12.
L All other' factors were defined above.
Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision.l.
In ' lieu of site-specific data default values for fg and f, 1.0 and 0.76, respectively were used in the cIl(.ulation of R These values were obtained from
:TableE-15ofReku.latory Guide 1.109 Revision 1.
The concentration of tritium in vegetation is based on the airborne concentration rather than the depositien.
Therefore, the R is based on X/Q:
t Ujf
'(DFL ), 0.75(0.5/H)
(C.2-8)
\\
R K'K"'
Uf
+
T
=
y y
g where:
O dese fecter for the vesetes1e gathwer for R
=
T tritium fp any organ of interest, mrem /yr per pCi/m All other terms remain the same as those in Equations C.2-4 and C.2-7.
9 IBM
 
ODCM Rev. 9 Pega'124-
. TABLE C-1 Parameters For. Cow and Goat Milk Pathways Parameter Value Reference (Reg. Guide 1.109 Rev. 1 QF ( g/ ay) 50 (cow).
Table E-3 6 (goat)
Table E-3 2
Yp (kg/m )
0.7-Table E-15 L
5 2 days)
Table E-15
(
f (seconds) 1.73 x 10 t
1.0 (radiciodines)
Table E-15 r
0.2 (particulate)
Table E-15 (DF.L ), (mrem /pCi)
Each radionuclides Tables E-11 to E-14 f
F, (pCi/ day per pCi/ liter)
Each stable element Table'E-1 (cow)
Table E-2 (goat) 3 (seccads) 4.73 x 108 (15 yr)
Table E-15 t
2 2.0 Table E-15 Y, (kg/m )
2 0.7 Table E-15 p (kg/m )
Y h (see uds) 7.78 x 100 (90 days)
Table E-15 t
.330 infant Table E-5 ap (liters /yr)
U 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 2.59 x 106 (pasture)
Table E-15
* (seconds) t 5.18 x 10 (stored feed)
B (pCi/Kg (wet weight)
Each stable element Table E-1 fy per pCi/Kg (dry soil))
P (Kg (dry soil /m )
240 Table E-15 IBM
 
ODCM Rsv. - 9
'Pega 125 y3[]
TABLE C-2
%./
Parameters For The Meat Pathway
/
Parameter Value Reference (Reg.. Guide 1.109 Rev. 1 r
1.0 (radioiodines)
Table E-15 0.2 (particulate)
Table E-15 i
Ff (pCi/Kg per pCi/ day)
Each stable element Table E-1 O infant Table E-5 ap (Kg/yr).
U 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFL ), (mrem /pCi)
Each radionuclides Tables E-11 to E-14 g
2 0.7 Table E-15 p (kg/m )
Y
/'
2 Y, (kg/m )
2.0 Table E-15 b (see uds) 4.73 x 108 (15 yr)
Table E-15 t
t,(seconds) 1.73 x 10 (20 days)
Table E-1_5 h (see nds) 7.78 x 10 (90 days)
Table E t
* (seconds) 2.59 x 106 (pasture)
Table E-15 t
5.18 x 10 (stored feed)
)
Qf (kg/ day) 50 Table E-3 B
(pCi/Kg (wet weight)
Each stable element Table E-1 fy per pCi/Kg (dry soil))
P (Kg (dry soil)/m )
240 Table E-15 Om IBM
 
.ODCM LRsv.1 9 Pegs 126-TABLE C-3 Parameters For The Vegetable' Pathway Parameter Value Reference (Reg. Guide 1.109 Rev.!1 r (dimensionless) 1.0 (radioiodines)
Table E-1 0.2 (particulate)
Table E-1
.(DFL ), (arem/Ci)
Each radionuclides Tables E-11 to E-14' g
((kg/yr)
- Infant 0
Table E-5
- Child 26 Table E-5
- Teen.
42 Table E-5 l
- Adult 64 Table E-5 i
8 U.(kg/yr) - Infant 0
Table E-5
- Child 520 Table E-5
- Teen 630 Table E-5
- Adult 520 Table E-5 g (seconds) 8.6 x 10' (1 day).
Table E-15 t (seconds) 5.18 x 106 (60 days)
Table E-15 h
Y (kg/m )
2.0 Table E-15 y
t,(seconds) 5.18 x 100 (60 days)
Table E-15 8'(15 yr)
Table E-15
.t3 (seconds) 4.73 x 10 P(Kg(dry. soil)/m )
240 Table E-15 Bgy(pCi/Kg(wet weight)
Each stable element Table E-1 per pCi/kg;(dry soil))
IBM m}}

Latest revision as of 18:38, 22 May 2025

Rev 9 to Offsite Dose Calculation Manual
ML20238A866
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/29/1987
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20238A816 List:
References
PROC-870629, NUDOCS 8708310247
Download: ML20238A866 (124)
v • d • e


Text

ODCM Rev. 9 Page 1 of 126 O

PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)

REV. 9 DOCKET No. 50-282 and 50-306 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA OPERATIONS COMMITTEE FINAL REVIEW DATE:

[4 - A 7-7 Y REVIEWED BY:

[

Cd4A ~

DATE: (o-J3-37 APPROVED BY:

[

/

LcI DATE: N0 h7 Supt Rad Prot

~

pa'A88a8888gp IBM

ODCM Rev. 9 Page 2 TABLE OF CONTENTS

p) k-Section Title Page Table of Contents...................................

2 List of Figures....................................

3 List of Tables.....................................

4 Record of Revisions................................

5

1.0 INTRODUCTION

6 l

2.0 LIQUID EFFLUENTS.....................

....................... 6

]

2.1 Monitor Alarm Setpoint Determination....................

6 2.2 Liquid Effluent Concentration - Compliance with 10 CFR 20.........................................

14 2.3 Liquid Effluent Doses - Compliance with 10 CFR 50..............................................

15 i

References.............................................

19 I

(^)

l 3.0 GASEOUS EFFLUENTS...........................................

22 3.1 Monitor Alarm Setpoint Determination...................

22 3.2 Gaseous Effluent Dose Rate - Compliance with 10 CFR 20..............................................

28 3.3 Gaseous Effluent Doses - Compliance with 10 CFR 50..............................................

32 References.............................................

37 4.0 INFORMATION RELATED TO 40 CFR 190 and 40 CFR 141............

58 5.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM..................

60 APPENDIX A - Meteorological Dispersion Parameters........... 68 APPENDIX B - Joint Frequency Distribution Tables...........

107 APPENDIX C - Dose Parameters for Radiciodines, Particulate and Tritium......................

115

{}

IBM E---_-------__--------_-------

ODCM Rev. 9 Page 3 LIST OF FIGURES Figure Page j

5.1-1 Prairie Island Nuclear Generating Plant j

Radiation Environmental Monitoring Program........

65 5.1-2 Site Boundary TLD Locations.......................

66 5.1-3 4-5 Mile Ring, Control, and Special Interest TLD Locations............................

67 1

1 (v

1 l

l l

1 i

a I

IBM j

i ODCM Rev. 9 Page 4 j

LIST CF TABLES O)

~

(,

Tables Pag _e 2.1-1 Liquid Source Terms for PNGP......................

13 2.3-1 A

Value s fo r the PNGP............................ 2 0 g

3.1-1 Monitor Alarm Setpoint Determination for PNGP..... 26

)

3.1-2 Gaseous Source Terms for PNGP.....................

27 3.1-3 Dose Factors and Constants........................

27

,3.2-1 P

value s fo r the PNGP............................ 31 g

3.3-1 Dose Factors for Noble Gases and Daughters........ 38 3.3-2 R

Values for the PNGP - Ground, All Ages.........

39 f

3.3-3 R

Values for the PNGP - Vegetable, Adult.........

40 1

3.3-4 R

Values for the PNGP. Vegetable, Teen.......... 41 f

3.3-5 R

Values for the PNGP - Vegetable, Child.........

42 f

3.3-6 R

Values for the PNGP - Meat, Adult..............

43 f

3.3-7 R

Values for the PNGP - Meat, Teen...............

44 g

j 3.3-8 R

Values for the PNGP - Meat, Child..............

45 j

1 3.3-9 R. Values for_the PNGP - Cow Milk, Adult..........

46 3.3-10 R

Values for the PNGP - Cow Milk, Teen...........

47 3.3-11 R. Values for the PNGP - Cow Milk, Child..........

48 1

3.3-12 R Values for the PNGP - Cow Milk, Infant.........

49 g

3.3-13 R

Values for the PNGP - Goat Milk, Adult.........

30 1

3.3-14 R

Values for the PNGP - Goat Milk, Teen..........

51 1

3.3-15 R

Values for the PNGP - Goat Milk, Child.........

52 g

3.3-16, R

Values for the PNGP - Goat Milk, Infant........

53 1

3.3-17 R

Values for the PNGP - Inhalation, Adult........

54 g

3.3-18 R

Values for the PNGP - Inhalation, Teen.........

55 f

3.3-19 R. Values for the PNGP - Inhalation, Child........

56 1

3.3-20 R. Values for the PNGP - Inhalation, Infant.......

57 1

i 5.1-1 PNGP - Radiation Environmental Monitoring Program Sampling Locations........................

61 O

IBM

ODCM Rev. 9 Page 5 RECORD OF REVISIONS

%-)

Revision No.

Date Reason for Revision Original June 7, 1979 1

April 15, 1980 Incorporation of NRC Staff I

comments and correction of miscellaneous errors 1

2 August 6, 1982 Incorporation of NRC Staff comments 3

February 21, 1983 Change in milk sampling j

location j

4 November 14, 1983 Change in milk sampling location and change in j

cooling tower blowdown

]

5 March 27, 1984 Change Table 3.2-1 6

February 14, 1986 Change in location to collect l

cultivated crops (leafy l

green veg.) and removal of l

(;

meat animals from the j

N s' land use census.

j m

7 July 31, 1986 Retype and format ODCM.

I No change in' content.

8 January-8, 1987 Addition of Discharge Canal Monitor Setpoint calculation.

9 June 29, 1987 Change inhilation dose factor to child and j

address change in land I

use survey.

(3 l \\_]

l IBM

'4 ODCM Rev. 9' Page 6

1.0 INTRODUCTION

\\-)

This Offsite Dose Calculation Manual (ODCM) provides the information and methodologies to be used by the Prairic Island Nuclear Generating Plant (PNGP) to assure. compliance with certain portions of PNGP's Operating Technical Specification.

These portions are those related to liquid 1'

and gaseous radiological effluents.

They are intended to show complian'en with 10 CFR 20, 10 CFR 50.36A, 10 CFR 50, Appendix A (GDC 60 & 64) and Appendix I, and 40 CFR 190.

This ODCM is : based on " Radiological Effluent Technical Specifications for PWR's (NUREG-0472, Octcber, 1978),"

" Preparation of Radiological Effluent Technical Specifica-i tions for Nuclear Power Plants (NUREG-0133, October 1978),"

and other inputs from the Nuclear Regulatory Commission (USNRC).

Specific plant procedures for implementation of i

this manual are provided elsewhere.

These procedures will be utilized by the operating staff of the PNGP to assure compli-ance with the T.cchnical Specifications.

Also included in this manual is information,related to the i

Radiological Environmental Monitoring Program (REMP) in the l

form of Figtres 5.1-1, 5.1-2, 5.1-3 and Table 5.1-1.

These l

figures and table designate specific sample types and locations

{

l currently used to satisfy the technical specification require-

~

i ments for the REMP.

They are subject to change based on the

('\\-)

results of the periodic land use census.

I Although the ODCM has been prepared as generically as possible in order to minimize the need for future revisions, some changes to the ODCM may be required in the future.

Any l

I such changes will be properly reviewed.and approved as required by the PNGP Technical Specifications.

l l

2.0 LIQUID, EFFLUENTS j

2.1' Moni, tor Alarn Setpoint Determination This procednre determines the monitor alarm setpoint I

that indicates if the concentration of radionuclides in i

i the liquid effluent released at the site boundary exceeds the concentrations specified in 10~CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a l

concentration of 2 x 10-4 pCi/ml for dissolved or entrained noble gases.

Since Fe-35, Sr-89, Sr-90, and alpha concentrations, are determined from composite samples, the liquid

("J monitor setpoint determinations should be completed T

N using the nost recent available composite sample l

results, f

IBM u

ODCM Rsv. 9 Pago 7 Monitor high ala*m or isolation setpoints will be

]' /

. )

established in one of these ways:

s-a.

Monthly calculation of setpoints using the l

I methodology of Sections 2.1.1 and 2.1.3.

b.

Calculation of alarm setpoint based on analysi's prior i

to discharge using methodology of Section 2.1.2.

Alarm setpoint determined using methodology of c.

Sections 2.1.1 and 2.1.3 assuming all radionuclides have an MPC af lE-7 pCi/ml.

No recalculation of setpoints.is necessary unless an increase in alarm setpoint is desired.

PWR GALE Code source terms (Table 2.1-1) may be used if there were no detectable isotopes in the grevious month ur in the analysis prior to release.

If the newly calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new 1

value.

If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or increased to the new value.

2.1.1 Liquid Effluent Monitor Setpoints

('T The following method applies when determining

(_)

the isolation setpoints for the Waste Effluent Liquid Monitor (R-18), Steam Generator Blowdown Liquid Mpnitor - Unit 1 (1R-19), and Steam Generator Blowdown Liquid Monitor - Unit 2 i

(?R-19) during all operational conditions when the radwaste discharge flow rate is maintained

)

constant at the maximum design flow rate.

1 l

2.1.1.1 Determine the " mix" (radionuclides and composition) of the liquid effluent.

3 a.

Determine the liquid source terms that are representative of the

" mix" of the liquid effluent.

Liquid source terms are the total curies of each isotope released during the previous month.

Table 2.1-1 source terms may be used if l

there have been no liquid releases.

b.

Determine S (the fraction of the l

total radioactivity in the liquid effluent comprised by radionuclides "i") for each individual radionuclides

(~N in the liquid effluent.

%-]

IBM

ODCM Rev. 9 Page 8 Il A1 k/

Sg=I (2.1-1)

)

A.1 i

f = The radioactivity of radionuclides

)

A "i" in the liquid effluent.

j i

2.1.1.2 Determine C (the maximum acceptable total radioactivity concentration of all l

radionuclides in the liquid effluent j

prior to dilution (pCi/ml)).

1 C

=

F g

f S

i i

l (2.1-2) l MPC f F = Dilution water flow rate (gpm)

= 67,300 gpm from cooling tower blowdown f = The maximum attainable discharge j

flow rate prior to dilution (gpm)

= 60 gpm from the ADT tank pump ( )'

= 100 gpm from the CVCS tank pump (2)

)

l

= 60 gpm from the SGBD tank pump (2) l MPCf = The liquid effluent radioactivity concentration limit for radionuclides "i" (pci/ml) from Table 2.1-1 or

)

if not listed in Table 2.1-1, l

obtained from Reference 3.

2.1.1.3 Determine C (the maximum acceptable total radioactivity concentration of the radionuclides (minus tritium) in the liquid discharge prior to dilution (pCi/ml)).

- (C S )

(2.1-3)

C, = Cg tg H = The fraction of the total radioactivity S

in the liquid effluent contributed by tritium and other radionuclides l C that do not emit gamma or X-ray I

radiation.

IBM

ODCM Rev. 9 Page 9 2.1.1.4 Determine C.R. (the calculated monitor

(~)

count rate above background attributed

\\/

to the radionuclides (nepm)).

~

C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file.

C.R.

is the count rate that corresponds to the " adjusted" total radioactivity concentration (C

m 2.1.1.5 Determine HSP (the monitor high alarm setpoint above background (nepm)).

HSP = T,C.R.

(2.1-4)

T* = Fraction of the radioactiv'.ty from l

the site that may be released via each release point to ensure that the site boundary dose rate limit is not exceeded due to simultaneous releases from several release points.

= 0.90 for the Waste Effluent Liquid Monitor (R-18) r~s

= 0.05 for the Steam Generator Blowdown

(_

Liquid Monitor - Unit 1 (lR-19)

= 0.05 for the Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19)

T values may be revised from the sIlues given above.

The summation I

of all the T values for active release poinEs shall not be greater than unity.

I 2.1.1.6 The monitor high alarm setpoint above background (acpm), shall be set at or below the HSP value.

2.1.2 Setpoint Based on Analysis of Liquid Prior to Discharge (Optional) l This method may be used in lieu of the method in Section 2.1.1 to determine the setpoints for the maximum acceptable discharge flow rate prior to dilution and to determine the associated high l

alarm setpoint based on this flow rate for the Waste Effluent Liquid Monitor (R-lb), Steam

(~N Generator Blowdown Liquid Monitor - Unit 1

(

(lR-19), and Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19), during all operational conditions.

IBM

f ODCM Rev. 9 Page 10

~

2.1.2.1 Determine f (the maximum acceptable discharge flow rate prior to dilution

's (gpm)).

0.8 F T f

-=

m C

(2.1-5) 1 MPC f F = Dilution water flow rate (gpm) 3

= 67,3000 gpm from cooling tower blowdown i

C1: Concentration of radionuclides "i" in the liquid effluent prior to 1

dilution (pCi/ml) from analysis of 1

the liquid effluent to be released.

j i

MPC. = The liquid effluent radioactivity 1

concentration limit for radionuclides "1"

(pCi/ml) from Table 2.1-1 or if not listed in Table 2.1-1 from Reference 3.

/)

T* = Fraction of the radioactivity from

(/

the site that may be released via each release point to ensure that the site boundary limit is not exceeded due to simultaneous releases from several release points.

Refer to Section 2.1.1.5.

2.1.2.2 Determine the monitor setpoint based on i

the radionuclides mix of the liquid effluent.

a.

Determine C.R. (the calculated monitor count rate above background attributed to the radionuclides (nepm)).

C.R.

is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file.

C.R.

is the count rate point that corresponds to the " adjusted" total radioactivity concentration (C,).

IBM j

ODCM i

Rev. 9 Page 11 C* = The total radioactivity concen-r^j tration of the radionuclides

(_/

(minus tritium and other I

radionuclides that are only beta emftters) in the liquid discharge prior to dilution f

(pCi/ml) as determine using Equation 2.1-3. (C and S beingdeterminedbyanalyNis

{

of undiluted liquid effluents.)

j b.

Determine HSP (the monitor high alarm setpoint above background (nepm)).

HSP = C.R.

(2.1-6) l 0.8 0.8 = A correction factor to increase the monitor setpoint to prevent spurious alarms caused by deviations in the mixture of radionuclides that affectr monitor response.

q c.

The monitor high alarm setpoint i

above background shall be aet at or gN (j

below this HSP value when thic optional method is selected.

The i

maximum discharge flow shall not exceed the value of f as determined in Section 2.1.2.1 when this optional method is selected.

l 2.1.3 Discharge Canal Monitor The following method determines the high alarm setpoint for the Discharge Canal Monitor (R-21) during all operational conditions.

2.1.3.1 Determine the " mix" (radionuclides and composition) of the liquid effluent.

a.

Determine the liquid source terms that are representative of the

" mix" of all liquids released into the discharge canal.

Liquid source l

terms are the total curies of each i

isotope released during the previous month.

Table 2.1-1 source terms may be used if there have been no r~;

liquid releases.

V IBM c__-_-__-_

1 ODCM-Rev. 9 Pege 12

)

b.

Determine Si (the fraction of the

/~ '

total radioactivity of all liquids released into the discharge canal compriced by radionuclides "i") for l

each individual radionuclides / released' l

1 into the discharge canal.

IX i

{

The radioactivity of radionuclides Ai

=

"i" released into the discharge canal.

2.1.3.2 Determine cd (the maximum acceptable diluted radioactivity concentration of all radionuclides' released'into the discharge canal (pCi/ml)).

Cd

=

1

[2. Si i

MPCi The liquid effluent radioactivity MPCi

=

concentration limit for radionuclides "i" (pCi/ml) from Table 2.1-1 or.if

.not listed in Table 2.1-1, obtained from reference 3.

2.1.3.3 Determine Cm (the maximum acceptable

otal radioactivity concentration of the radionuclides (minus tritium) released i

into the discharge canal (pci/ml)).

Cm

=

Cd-Cd sh The fraction of the total radioactivity Sh

=

i released into the discharge canal l

comprised of tritium and other radionuclides that do not emit-tamma or X-ray radiation.

2.1.3.4 Determine C.R. (the calculated monitor count rate above background attributed to the radionuclides (ncpm)).

C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file..

C.R. is the count.

rate that corresponds to the " adjusted" O-total radioactivity concentration (Cm).

2.1.3.5 The monitor high alarm setpoint above background.

(nepm) shall be set at or above the C.R. value. l IBM I

ODCM

)

Rev. 9 Page 13 TABLE 2.'l-1 LIQUID SOURCE TERMS WASTE EFFLUENT SGBD-RADIONUCLIDES MPC (pCi/ml)

(A.)(Ci/Yr)

(A;)(Ci/Yr)

Mo-99 4E-5 6.42E 1.415E-2 I-131 3E-7 3.061E 4.11E-2 Te-132 2E-5 2.12E-3 3.61E-3 I-132 8E-6 2.83E 1.88E-2 1-133 1E-6 2.365E-2 4.856E-2 Cs-134 9E-6 1.464E-1 4.047E-2 I-135 4E-6 4.84E-3 1.792Ea2 Cs-136 6E-5 5.743E-2 1.862E-2 Cs-137 2E-5 8.214E-2 2.69E-2 i

All Others 1E-7 0

2E-5 1

H-3 3E-3 1.89E2

1. 41E2 -

Noble gases 2E-4 3

Total 1.894E2 1.412E2 f

4 q

($)

a O

4 1

IBM i

3

l ODCM Rev. 9 Page 14 2.2 Compliance With 10 CFR 20 k-)

In order to comply with 10 CFR 20, the concentrations of radionuclides in liquid effluents will not exceed the maximum permissible concentrations (MPC) as defined in Appendix B, Table II of 10 CFR 20.

For continuous releases, I

the alarm trip setpoints discussed in Section 2.1 will f

assure that these concentrations are not exceeded.

For i

batch releases, concentrations of radioactivity in effluents l

prior to dilution will be determined, providing protection l

in addition to the alarm trip setpoint discussed in Section 2.1 Concentration in diluted effluents will be calculated using these results.

2.2.1 Continuous Releases i

Continuous liquid releases can occur from PNGP through steam generator blowdown.

The alarm I

trip setpoints discussed in Section 2.1 will assure that releases from this pathway will not l

exceed the limits of 10 CFR 20.

j Other minor releases of a continuous nature have occurred at PNGP through the turbine building sump system.

These releases were minor and are I

not expected to occur in the future.

However, a (N /^')

continuous composite sampler will be maintained i

at the discharge from the turbine building sump l

with samples being taken and analyzed weekly.

I If these samples indicate detectable levels of radionuclides, the methodologies given in l

Section 2.2.2 will be applied to the turbine

{

sump weekly releases and the limit in Equation l

2.2-2 will be lowered to account for this source term.

2.2.2 B,atch Releases To further show compliance with 10 CFR 20, the l

radioactivity content of each batch release will be determined prior to release.

The i

concentration of the various radionuclides in l

the batch release prior to dilution, is divided l

by the minimum dilution flow to obtain the concentration at the site boundary.

This i

calculation is shown in the following equation:

t C

R i

(2.2-1) j Cone

=

f MDF (O

where

%-)

f = concentration of radionuclides i at the Cone site boundary, pCi/ml;

)

IBM

-_--__-___,I

ODCM Rev. 9 Page 15 C

= concentration of radionuclides i in the i

("}

potential batch release, pCi/ml; V

R

= release rate of the batch MDF

= minimum dilution flow (=67,300 gpm)

The projected concentration at the site boundary is compared to the MPCs in Appendix B, Table II of 10 CFR 20 which sre given in Table 2.1-1.

Before a release may occur, Equation 2.2-2 must be met for all isotopes, p

Conc i u

0.9 (2.2-2) i MPC f

Maximum permissible concentration MPC.

=

1 of radionuclides i from Appendix B, Table II of 10 CFR 20. pCi/ml The summation has been reduced from 1.0 to 0.9 to account for simultaneous continuous releases from steam generator blowdown as given in Section 2.1.1.5.

As noted earlier, this fraction may be

,r T adjusted based on experience.

The summation of

(_)

all source terms shall not be greater than 1.0 of the 10 CFR 20 limit.

2.3 Liquid Effluent Doses - Compliance with 10 CFR 50 Doses resulting from liquid effluents will be calculated monthly to show compliance with 10 CFR 50.

A cumulative summation of total body and organ doses for each calendar quarter and calendar year will be maintained as well as projected doses for the next month.

Since Fe-55, Sr-89, Sr-90, and alpha concentrations are determined from composite samples, the monthly liquid effluent dose calculations and comparisons to quarterly and annual limits should be completed using the most recent available composite sample results.

The quarterly and annual dose calculations shall be completed using the actual composite sample results.

1 l

The limits of 10 CFR 50 are on a per reactor unit basis.

The liquid radwaste system at PNGP is shared by both reactor units making it impossible to separate the releases of the two units.

The releases that can be

(~)

separated by unit, steam generator blowdown and turbine

\\_/

building sump releases, contribute a very small portion of the total liquid releases from PNGP.

Therefore, for compliance with 10 CFR 50 the releases from both units will be summed and the limits of Appendix 1 will be doubled.

IBM

\\

'ODCM Rev. 9 Page 16 2.3.1 Determination of Liquid Effluent Dilution

.To determine doses from liquid' effluents the near field average dilution factor for the period of release must.be calculated..This dilution factor must.be calculated for each batch release and each continuous release mode.

The dilution factor is determined by:

1 R

k (2.3-1)

F

=

k X ADFk where release rate of the batch or R

=

k J

continuous releases during the period,-k, gal; 1

actual dilution flow during the ADF

=

k tiie period of release k, gal.

The value of X is the site specific factor for

.j the mixing effect of the PNGP discharge 1

i This value is.10-for PNGP while (1)

("3 structure.

(/

operating in the closed cycle cooling mode.

TheproductofXandADFuislimitedto1000-j cfs (4.5 x 10 gpm).

Therefore, since blowdown the5 enominator l

flow in closed cycle is 150 cfs, d

of Equation 2.3-1 is always 4.5 x 10 in closed j

cycle.

In once through or helper mode, the j

value of X is reduced to 1.0.

1 2.3.2 Dose Calculations

)

The dose contribution from the release of liquid i

effluents will be calculated monthly.

The dose contribution will be calculated using the following equation:

where:

DI

=

IIA t

F (2.3-2) gz k

ik k-ki where:

the dose commitment to the total-I Dt

=

body or any orgc.n I, from the liquid effluents for the period of release,. mrem;

]

IBM

.l

.J

ODCM Rev. 9 l

Paga 17 the average concentration of-C

=

ik (N

radionuclides, i, in undiluted Ll liquid effluent for liquid release k, pCi/ml; the site related ingestion dose A

=

tz commitment factor to the total body or any organ I for each 1

identified principal gamma and beta emitter, mrem /hr per pCi/ml; i

the near field average dilution

)

F

=

k factor for C during liquid effluentrelbsek,

{

I the duration of release k, hours.

j t

=

k The dose factor A was calculated for an adult foreachisotopeblingthefollowingequation:

)

1.14 x 105 [21BF DFft]

(2.3-3)

A

=

1 17 where:

5 6

3 10 pCi x 10 ml x 1 yr 1.14 x 10

=

pCi

~T 8760 hr C()

21

=

adult fish consumption, Kg/yr; bioaccumulation factor for BF.

=

1 radionuclides i in fish from Table A-1 of Regulatory Guide 1.109 Rev. 1 (5) pCi/Kg per.pCi/1; dose conversion factor for DF *

=

i radionuclides i for adults for a particular organ I from Table E-ll of Regulatory Guide 1.109 Rev. 1, (s), mrem /pC1.

values for an adult at the PNGP A table of A *in Table 2.3-1.

arepresenteb Mississippi River water is not used as a potable water supply within 300 miles downstream of the PNGP.

Wells are used for irrigation downstream of the plant.

O 1BM

ODCM Rev. 9 Page 18 l

2.3.3 Cumulation of Doses p_

k-)

Doses calculated monthly will be summed for comparison with quarterly and annual limits.

j The monthly results should be added to the doses cumulated from the other months in the quarter of interest and in the year of interest for the i

combined releases of both reactor units.

The following relationships should hold:

For the quarter, D

3.0 mrem total body (2.3-4)

D 10 mrem any organ (2.3-5) 7 1

For the cal.endar ye,u,

)

i D

6.0 mrem total body (2.3-6) z D

20 mrem any organ (2.3-7)

)

7 I

1 The quarterly limits given above represent one half of the annoal design objective.

If these quarterly or annual limits are exceeded, a special report should be submitted to the USNRC identifying the

();

cause and corrective action to be taken.

If

' (-

twice the quarterly or s.inual limits are exceeded, i

a special report shall 'n

'ubmitted showing compliance with 40 CFR 'A 2.3.4 Projection of Doses Anticipated doses resulting from the release of liquid effluents will be projected monthly.

If the projected doses for the month exceed 2 percent of Equation 2.3-6 or 2.3-7, additional components of the liquid radwaste treatment system will be used to process waste.

The projected doses will be calculated using Equation 2.3-2.

The dilution factor, F "ill be calculated by replacing the term ADFk'in Equation 2.3-1withthetermMDFfromEkuation 2.2-1.

The total source term utilized for the most recent dose calculation should be used for the projections unless information exists indicating tnat actual releases could differ significantly in the next month.

In this case, the source term would be adjusted to reflect this information and the justification for the adjustment noted.

This adjustment should f'/)

account for any radwaste equipment which was operated during the previous month that could be x_

out of service in the coming month.

1 IBM l

ODCM 1

.Rev 9-Page 19-REFERENCES.

1.

" Prairie Island Final Environmental ~ Statement,"'USAEC, May, 1973, p. V-26.

2-

"NSP - Prairie Island Nuclear Generating Plant, Appendix I Analysis - Supplement No. 1 -. Docket No. 50-282 and 50-306,"

Table 2.1-1.

3.

"10 CFR 20," Appendix B, Table II,. column 2.

4.

"NSP - Prairie Island Nuclear. Generating Plant, Appendix I Analysis --Supplement No. 1 - docket 50-282 and 50-306," July 21, 1976, Table 2.1-2.

5.

U. S. Nuclear Regulatory Commission. " Regulatory Guide 1.109

- Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Compliance with 10 CFR.50, Appendix 1," Rev. 1, 1977.

I IBM

l ODCM i

Rev. 9 j

Page 20 j

TABLE 2.3-1 j

(]

A VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT l

V (MREM /HR PER pCI/ML) 1 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 4

i 1H 3

0.00E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 l

6C 14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 J

11NA 24 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 24CR 51 0.00E-01 0.00E-01 1.27E 00 7.61E-01 2.81E-01 1.69E 00 3.20E 02 s

25MN 54 0.00E-01 4.38E 03 8.35E 02 0 00E-01 1.30E 03 0.00E-01 1.34E 04 l

25MN 56 0.00E-01 1.10E 02 1.95E 01 0.00E-01 1.40E 02 0.00E-01 3.51E 03 26FE 55 6.58E 02 4.55E 02 1.06E 02 0.00E-01 0.00E-01 2.54E 02 2,61E 02 26FE 59 1.04E 03 2.44E 03 9.36E 02 0.00E-01 0.00E-01 6.82E 02 8.14E 03 27CO 58 0.00E-01 8.92E 01 2.00E 02 0.00E-01 0.00E-01 0.00E-01 1.81E 03 q

27C0 60 0.00E-01 2.56E 02 5.65E 02 0.00E-01 0.00E-01 0.00E-01 4.81E 03 28NI 63 3.11E 04 2.16E 03 1.04E 03 0.00E-01 0.00E-01 0.00E-01 4.50E 02 l

28NI 65 1.26E 02 1.64E 01 7.49E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 j'

l 29CU 64 0.00E-01 9.97E 00 4.68E 00 0.00E-01 2.51E 01 0.00E-01 8.50E 02 30ZN 65 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.00E-01 4.64E 04 307N 69 4.93E 01 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 l

35BR 83 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.82E 01 35BR 84 0.00E-01 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 4.11E-04 35BR 85 0.00E-01 0.00E-01 2.15E 04 0.00E-01 0.00E-01 0.00E-01 1.01E-15 37RB 86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 37RB 88 0.00E-01 2.90E 02 1.54E 02 0.00E-01 0.00E-01 0.00E-01 4.0.0E-09

(]

37RB 89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 i V 38SR 89 2.21E 04 0.00E-01 6.35E 02 0.00E-01 0.00E-01 0.00E-01 3.55E 03 1

38SR 90 5.44E 05 0.00E-01 1.34E 05 0.00E-01 0.00E-01 0.00E-01 1.57E 04 l

f 38SR 91 4.07E 02 0.00E-01 1.64E 01 0.00E-01 0.00E-01 0.00E-01 1.94E 03 385R 92 1.54E 02 0.00E-01 6.68E 00 0.00E-01 0.00E-01 0.00E-01 3.06E 03

)

39Y 90 5.76E-01 0.00E-01 1.54E-02 0.00E-01 0.00E-01 0.00E-01 6.10E 03 39Y 91M 5.44E-03 0.00E-01 2.11E-04 0.00E-01 0.00E-01 0.00E-01 1.60E-02 39Y 91 8.44E 00 0.00E-01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 4.64E 03 39Y 92 5.06E-02 0.00E-01 1.48E-03 0.00E-01 0.00E-01 0.00E-01 8.86E 02 39Y 93 1.60E-01 0.00E-01 4.43E-03 0.00E-01 0.00E-01 0.00E-01 5.09E 03 40ZR 95 2.40E-01 7.70E-02 5.21E-02 0.00E-01 1.21E-01 0.00E-01 2.44E 02 40ZR 97 '

1.33E-02 2.68E-03 1.22E-03 0.00E-01 4.04E-03 0.00E-01 8.30E 02 41NB 95 4.47E 02 2.48E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 42MO 99 0.00E-01 1.03E 02 1.96E 01 0.00E-01 2.34E 02 0.00E-01 2.39E 02 j

43TC 99M 8.87E-03 2.51E-02 3.19E-01 0.00E-01 3.81E-01 1.23E-02 1.48E 01 43TC101 9.12E-03 1.31E-02 1.29E-01 0.00E-01 2.37E-01 6.72E-03 3.95E-14 44RU103 4.43E 00 0.00E-01 1.91E 00 0.00E-01 1.69E 01 0.00E-01 5.17E 02 l

44RU105 3.69E-01 0.00E-01

' 46E-01 0.00E-01 4.76E 00 0.00E-01 2.26E 02 44RU106 6.58E 01 0.00E-01 8.33E 00 0.00E-01 1.27E 02 0.00E-01 4.26E 03 47AG110M 8.81E-01 8.15E-01 4.84E-01 0.00E-01 1.60E 00 0.00E-01 3.33E 02 52TE125M 2.57E 03 9.30E 02 3.44E 02 7.72E 02 1.04E 04 0.00E-01 1.02E 04 52TE127M 6.48E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 52TE127 1.,05E 02 3.78E 01 2.28E 01 7.80E 01 4.29E 02 0.00E-01 8.31E 03 52TE129M 1.10E 04 4.11E 03 1.74E 03 3.78E 03 4.60E 04 0.00E-01 5.54E 04 52TE129 3.01E 01 1.1.?E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01

~3 52TE132M 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E-01 8.04E 04 (V

52TE131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.26E 01 0.u0E-01 2.67E 00 l

52TE132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.38E 04 53I 130 2.71E 01 8.01E 01 3.16E 01 6.79E 03 1.25E 02 0.00E-01 6.89E 01 53I 131 1.49E 02 2.14E 02 1.22E 02 7.00E 04 3.66E 02 0.00E-01 5.64E 01 l

f IBM

i f

ODCM Rev. 9 Page 21 TABLE 2.3-1 (CONT.)

/7 A

VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT

'I

(_,)

(MREM /HR PER pCI/ML)

RUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 53I 132 7.29E 00 1.95E 01 6.82E 00 6.82E 02 3.11E 01 0.00E-01 3.66E 00 53I 133 5.10E 01 8.87E 01 2.70E 01 1.30E 04 1.55E 02 0.00E-01 7.97E 01 53I 134 3.81E 00 1.03E 01 3.70E 00 1.79E 02 1.64E 01 0.00E-01 9.01E-03 53I 135 1.59E 01 4.17E 01 1.54E 01 2.75E 03 6.68E 01 0.00E-01 4.70E 01 55CS134 2.98E 05 7.09E 05 5.79E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 1

55CS136 3.12E 04 1.23E 05 8.86E 04 0.00E-01 6.85E 04 9.38E 03 1.40E 04 55CS137 3.82E 05 5.22E 05 3.42E 05 0.00E-01 1.77E 05 5.89E 04 1.01E 04 55CS138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E 01 2.23E-03 56BA139 9.29E-01 6.62E-04 2.72E-02 0.00E-01 6.19E-04 3.75E-04 1.65E 00 56BA140 1.94E 02 2.44E-01 1.27E 01 0.00E-01 8.30E-02 1.40E-01 4.00E 02 56BA141 4.51E-01 3.41E-04 1.5 2E-02 0.00E-01 3.17E-04 1.93E-04 2.13E-10 56BA142 2.04E-01 2.10E-04 1.28E-02 0.00E-01 1.77E-04 1.19E-04 2.37E-19 57LA140 1.50E-01 7.54E-02 1.99E-02 0.00E-01 0.00E-01 0.00E-01 5.54E 03 57LA142 7.66E-03 3.48E-03 8.68E-04 0.00E-01 0.00E-01 0.00E-01 2.54E 01 58CE141 2.24E-02 1.522-02 1.72E-03 0.00E-01 7.04E-03 0.00E-01 5.79E 01 58CE143 3.95E-03 2.92E 00 3.2S5-04 0.00E-01 1,29E-03 0.00E-01 1.09E 02 58CE144 1.17E 00 4.88E-01 6.27E-02 0.00E-01 2.90E-01 0.00E-01 3.95E 02 59PR143 5.51E-01 2.21E-01 2.73E-02 0.00E-01 1.27E-01 0.00E-01 2.41E 03 59PR144 1.80E-03 7.48E-04 9.16E-05 0.00E-01 4.22E-04 0.00E-01 2.59E-10 60ND147 3.76E-01 4.35E-01 2.60E-02 0.00E-01 2 54E-01 0.00E-01 2.09E 03 gg 74W 187 2.96E 02 2.47E 02 8.65E 01 0.00E-01 0.00E-01 0.00E-01 8.10E 04

(,)

93NP239 2.85E-02 2.80E-03 1.54E-03 0.00E-01 8.74E-03 0.00E-01 5.75E 02 l

I r(

IBM J

o 1

1 ODCM Rev. 9 Page 22 j

J 3.0 GASEOUS EFFLUENTS l

N-)

i 3.1 Monitor Alarm Setpoint Determination

]

This procedure determines the monitor alarm setpoint that indicates if the dose rate at or beyond the site i

boundary due to noble gas radionuclides in the gaseous J

effluent released from the site exceeds 500 mrem / year j

to the whole body or exceeds 3000 mrem / year to the skin.

l Monitor high alarm or isolation setpoints will be established in one of the following ways:

3 Monthly calculation of setpoint using the methodology

)

a.

of Section 3.1.1 for continuous releases using previous month releases as source term.

j b.

Prior to each containment purge, recalculation of j

the setpoint using the methodology of Section 3.1.1 1

based on the sample taken prior to purging.

{

i c.

In lieu of (a) and (b) above, alarm setpoints may be established using the methodology of Section 3.1.1 using conservative assumptions (e.g., 100%

Kr-89).

No recalculation of setpoints is necessary unless an incr. ease is desired.

PWR GALE Code source terms (Table 3.1-2) may be used if there were no detectable isotopes in the previous month or in the analysis prior to purging.

If the newly calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value.

If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or increased to the new value.

3.1.1 Effluent Monitors The following method applies when determining the isolation or high alarm setpoint for the monitors listed in Table 3.1-1.

3.1.1.1 Determine the " mix" (noble gas radio-nuclides and composition) of the gaseous effluent.

a.

Determine the gaseous source terms that are representative of the gaseous e f fluent.

Gaseous source terms are the total cut.ss of each noble gas released during the previous month or a repre-

,C]~

sentative analysis of the gaseous effluent.

\\

Table 3.1-2 source terms may be used l

if the releases for the previous month were below the lower limits of detection (LLD).

IBM

q 4

q ODCM i

Rev. 9-Page'23 m -

b.

Determine S., (the' fraction of the c

L total radioactivity in the gaseous-effluent' comprised by noble. gas radionuclides "1") for each individual noble gas radionuclides in the gaseous effluent.

1 (3.1-1)

IA f

i 1

The radioactivity of noble A.

=

1 gas radionuclides "i" in the j

gaseous effluent from Table 3.1-2.

3.1.1.2 Determine Q (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent (pCi/sec)) based upon the whole-body-exposure limit.

J

=

500 (3.1-2)

Q t (x/Q) I KS fg O

The highest calculated annual (x/Q).

=

average-relative concentration of effluents released via the plant vents for any_ area at or beyond the site boundary for 3

all sectors (sec/m ) from the-

"x/Q" column in Table 3.1-l'.

The total whole body dose factor due i

K

=

g to gamma emissions from noble gas 3 3

4 radionuclides "i" (mrem / year /pC1/m )

from Table 3.1-3.

3.1.1.3 Determine Q based upon the skin exposure t

limit.

=

3000 (3.1-3)

Q t (x/Q) I (Li + 1.1 M )

S g,

i i

The total skin dose factor L1 + 1.1 H.

=

1 due to emissions from noble

.O*

gas radionuclides "i" (mrem /

year /pCi/m )'from Table 3.~1-3.

3

' IBM

ODCM

-Rev. 9' Page 24 f.

1 3.1.1.4. Determine C (the maximum acceptable total radio 3ctivity concentration of all

{}.

noble gas radionuclides'in the gaseous effluent (pCi/cc)).

Q (3.1-4)

C

=

2.12 E-3 t

t F

NOTE:

Use the. lower of the.Q values j

obtained in Sections 391.1.2 l

and 3.1.1.3.

F = The maximum effluen't. flow rate i

at the point of release (cfm)

'l from the " Effluent' Flow Rate" a

column in Ta.ble 3.1-1.

2.12 E-3 = Unit conversion constant to-convert pCi/sec/cfm to pCi/cc.

3.1.1.5 Determine C.R..(the calculated monitor.

l count rate above background attributed to the noble gas radionuclides (nepm)).-

C.R. is obtained by using the applicable l

Effluent Monitor Efficiency Curve located l

in the Radiation Monitor Calibration-file.

C.R. is the count rate point that. corresponds to the total radioactivity. concentration (C ).

g 3.1.1.6 Determine HSP (the monitor-high alarm setpoint above background (ncpm)).

HSP = T,C.R.

(3.1-5)

T*

= Fraction of the. total radicain ivity 1

from the site that.may be released via each release paint to ensure that the site boundary limit'is not exceeded due to simultaneous releases from several release J

points from the~" Release Fraction" l

column in Table 3.1 :1, 3.1.1.7 The isolation or high alarm setpoints 1

above background:(nepm) for.the monitors should be set at or below the HSP values.

3.1.2 Air Ejector Monitors Radiation monitors 1R-15 and 2R-15 provide an indication of gross noble gas activity'at the main condenser air ejector of Unit 1 and Unit:2, respectively.

These monitors are provided.to IBM

1

0DCM l

Rev. 9 Page 25

)

give rapid indication of' steam generator tube

'f) leakage.

They are not effluent monitors since v

the air ejectors are vented'to the auxiliary building vents during normal plant' operation and releases are monitored by the auxiliary building vent monitoring system.

l l

l i

4 O

e O

IBM

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1 l

ODCM Rev. 9 Page'27 l

TABLE 3.1-2 GASEOUS SOURCE TERMS (1)

~

' AUX. BLDG SHIELD BLDG.

AIR EJECTOR

. Ci/Yr)

(A ) (Ci/Yr)

(A ) (Ci/Yr)

RADIONUCLIDES (A )

(

1 f

g 2EO

'Kr-85m 3E0 Kr-85 2EO

2. 2El-Kr-87 1EO Kr-88 SEO'

-1EO 3E0 Xe-131m 2EO 2.1E1.

1EO Xe-133m SEO 2E1 3E0 Xe-133 3.7E2 2.7E3 2.3E2 Xe-135 8EO 6EO SEO Xe-138 1EO Total 3.97E2 2.77E3 2.44E2

" " indicates that the release is less than 1 Ci/yr.

O i

9 IBM

.-.__-_a-----

-a

]

ODCM Rev. 9 Page 28 TABLE 3.1-3

)

DOSE FACTORS AND CONSTANTS i

SKIN TOTAL WHOLE BODY DOSE FACTOR DOSE FACTOR (L

+ 1.lM ) 3 3

(mrkm/yr/pC1/m)

RADIONUCLIDES (K ) (mrem /yr/pCi/m )

g Kr-83m 7.56E-2 2.12El Kr-85m 1.17E3 2.81E3 Kr-85 1.61El 1.36E3 Kr-87 5.92E3 1.65E4 Kr-88 1.47E4 1.91E4 Kr-89 1.66E4 2.91E4 Kr-90 1.56E4 2.52E4 Xe-131m 9.15El 6.48E2 1

Xe-133m

2. 52.E2 1.35E3 l

Xe-133 2.94E2 6.94E2 j

Xe-135m 3.12E3 4.41E3 1

Xe-135 1.81E3 3.97E3 Xe-137 1.42E3 1.39E4 Xe-138 8.83E3 1.43E4 Ar-41 8.84E3 1.29E4 r-3.2 Gaseous Effluent Dose Rate - Comoliance with 10 CFR 20

(_

Dose rates resulting from the release of noble gases, and radiciodines and particulate must be calculated to show compliance with 10 CFR 20.

The limits of 10 CFR 20 must be met on an instantaneous basis at the hypothetical worst case location, and apply on a per site basis.

Since Sr-89 and Sr-90 concentrations are determined from composite samples, the pre-release, weekly and monthly airborne dose calculations and comparisons to quarterly and annual limits should be. completed using the most recent available composite sample results.

The quarterly dose values and critical receptors reported semi-annually to the USNRC shall be calculated using the actual composite results.

q

/

O IBM

ODCM Rev. 9 Page 29 3.2.1 Noble Gases gg The dose rate at the site boundary resulting from noble gas effluents i: limited by 10 CFR 20 to 500 mrem /yr to the total body and 3000 arem/yr to the skin.

The setpoint determinations discussed in the previous section are based en the dose calculational method presented in NUREG-0133.(2) 3 They represent a backward solution to the limiting dose equations in NUREG-0133.

Setting alarm set trip points in this manner will assure that the limits of 10 CFR 20 are met for noble gas releases.

Therefore, no routine dose calculations for noble gases will be needed to show compliance with this part.

Routine calculations will be made for doses from noble gas releases to show compliance with 10 CFR 50, Appendix I as discussed in Section 3.3.1.

3.2.2 Radiciodine, Radioactive Particulate, and Other Radionuclides The dose rate at the site boundary resulting from the release of radioiodines and particulate with half lives greater than 8 days is limited by 10 CFR 20 to 1500 mrem /yr to any organ.

Calculations 9

showing compliance with this dose rate limit will be performed for batch releases prior to the release and weekly for all releases.

The calculations will be based on the results of sample analyses obtained pursuant to the PNGP Technical Specifications.

To show compliance, Equations 3.2-1 will be evaluated for I-131, tritium, and radioactive particulate with half-lives greater than eight days.

I P

(x/Q )

Qgy

< 1500 mrem /yr (3.2-1) g y

i I

where s

P infant critical organ dose parameter for i

=

y radionuclides i for the inhalation pathway, 3

mrem /yr per pCi/m (Table 3.2-1);

annual average relative deposition for (X/Q)v

=

long-term release at the critical location, l

3 sec/m (Appendix A, Table A-4);

I IBM

ODCM

.Rev. 9 Page 30 annual average relative deposition for (D/Q)v

=

long-term release at the critical (Appendix A, Table A-5);

2

\\-

location, 1/m the total release rate of radionuclides i Q

=

iv from all vents from both units for the batch 1

or week of interest, pCi/sec;

)

Radioiodines, tritium, and radioactive particulate will be released from up to.six individual vents all within 300 feet of each other.

For showing com-pliance with 10 CFR 20, calculations based on Equa-tion 3.2-1 will be made once per week.

The source terms (Qgy) will be determined from the results of analysis of vent particulate filters and charcoal canisters and vent flow rate.

These source terms include all' gaseous releases from PNGP.

Significant short-term batch releases of long-lived a

radioactive particulate and tritium will result from

)

containment purges.

Calculations will be made for these 1

releases separately to further assure compliance with 10 CFR l

Part 20 prior to release.

These calculations will be used only to determine whether or not the purge release will be q

allowed to occur.

Source terms will be determined from the

("T results of isotopic analyses of samples from containment

)

(_)

prior to release.

Equation 3.2.1 will be used.in conjunction j

with the following relationship to demonstrate that the batch a

release does not exceed the dose rate limit:

D)

(3.2-2)

BL =

1500 - (D y

p where i

BL =

limiting dose rate for the. batch, mrem /yr; previous week's doses from all vent D

=

v releases, mrem /yr; previous week's doses from all purge D

=

p releases mrem /yr.

3.2.3 Critical Receptor Identification The atmospheric dispersion parameters given in Appendix A will be used to identify the critical receptor.

Compliance with Part.20 will always be shown at the site boundary location.with the highest X/Q.

As discussed previously, weekly and batch dose calculations will be performed at this O

location.

The critical site boundary. location, based upon long term ground level releases x/Q (Table A-3), is 0.36 miles in the WNW sector.

4 IBM

.0DCM Rev.'9

.Pege 31-1

.]

TABLE 3.2-1 j

Values for Child P ty-l l

mrem /yr l

3 l

ISOTOPE l'

P

'pCi/m g

17 I

I I

l H-3.

.l 1.12 E 3 l

l Cr-51 l

1.70'E 4 l

1 Mn-54 l

1.58'E 6 l

l l

Fe-59

-l

1. L2 E 6 l

l Co-58 l

1.11.E 6 l

l-Co-60 1

7.07 E 6 l-l Zn-65 l

9.95 E 5 l

l l

Rb-86 l

1.98 E-5 l

l Sr-89 l

2.16 E 6-l j

l Sr-90 l

1.01-E 8 l

l Y-91 l

2.63 E 6 l

O i

zr-95 i

2.23 E e i

l Nb-95 l

6.14 E 5

'l l

Ru-103 l

6.62 E 5.

l j

l Ru-106 l

1.43 E.7-l l

l Ag-110m 1

5.48 E 6 l

l Te-127m 1

1.48 E 6 l

1 l

Te-129m l

1.76 E 6 l

l Cs-134 1

1.01 E 6 l

1 Cs-136 l

1.71 E 5 l

l Cs-137 l

9.07 E 5 l

^

l Ba-140 l

1.74 E 6 l

l Ce-141 l

5.44 E 5 l

l l

Ce-144 l

1.20.E 7 l

l I-131 l

1.62 E 7 l

1 I

I O

IBM.

.+$p D' E 'h IMAGE EVALUATION d

/////

24 g

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  • hN l.8 1.25 1.4 1.6 l

4 150mm 4

6"

'4f

  1. $>,zk 4,;

4

_o_

ODCM Rev. 9 Pega 32 a

3.3 Gaseous Effluents - Compliance with 10 CFR 50

,m,

(_).

Doses'resulting from the release of noble gases, and radioiodines &nd particulate must be calculated.to show compliance with Appendix 1 of 10 CFR 50.

The calculations will be performed monthly for all gaseous effluents.

1

~ The limits of 10 CFR 50 are on a per reactor unit basis.

The f

gaseous radwaste treatment system and the auxiliary building at PNGP is shared by both reactor units making.it impossible to separate the releases of the two units.

The releases that can be separated by unit contribute a very small portion of the total gaseous releases from PNGP.

Therefore, for compliance with 10 CFR 50 the releases from both units

{

will be summed and the limits of Appendix 1 w_.1 be doubled.

j i

Since Sr-89 and Sr-90 concentrations are determined from

(

~

composite samples, the pre-release, weekly and monthly u

airborne dose calculations and comparisons to quarterly and annual limits should be completed using the most recent

(

available composite. sample results.

The quarterly dose l

values and critical receptors reported semi-annually to the USNRC shall be calculated using the actual composite results.

f 3.3.1 Noble Gas Ai_)

3.3.1.1 Dose Equations The air dose at the critical receptor due to noble gases released in gaseous effluents is determined by Equations 3.3-1 and 3.3-2.

The critical receptor will be identified as described in Section 3.3.4.

)

For gamma radiation:

3.17 x 10-8 y 3

(xfq)v giv + (xjq)v iv j

q i

< 10 mrad for any calendar quarter

< 20 mrad for any calendar year (3.3-1)

L For beta radiation:

1 3.17 x 10-8 I N

(X/Q)y Qiy + (X/4)y41y f

[

< 20 mrad for any calendar quarter t

()

< 40 mrad for any. calendar year (3.3-2)

L

.lBM

ODCM R

Rcv. 9 Paga 33 where:

$Q i

1 The air dose factor due to gamma. emission A_/

M

=

g for each identified noble gas radionuclides i, mrad /yr per pCi/m3; (Table 3.3-1) the air dose factor due to beta emissions N

=

g for each identified n3ble gas. radionuclides i, mrad /yr per pCi/m ; (Table 3.3-1) 3 the annual average relative concentration i

(x/Q)y

=

for areas at or beyoid the restricted area l

boundary for long-term vent releases 3

L (greater than 500 hr./ year), sec/m (Appendix A, Table A-4);

the relative concet:. ration for areas at or (x/q)y

=

beyond the restricted area boundary for short-term vent releases (equal to or less 3

than 500 hrs / year), sec/m (Appendix A, Table A-7);

qfy the total release of noble gas radionuclides

=

i in gaseous effluents for short-term vent releases from both units (equal to or less than 500 hrs / year), pCi; i

Qgy the total release of noble gas radionuclides l

=

i in gaseous effluents for long-term vent releases from both units (greater than 500 j

hrs /yr), pCi; j

3.17 x 10-8 the i'nverse of the number of seconds in

=

a year.

Noble gases will be released from PNGP from up to nine vents.

l Long-term x/Q's were given in Appendix A.

Short-term x/q's were calculated using the USNRC computer code "XOQDOQ" assuming 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year short term releases and are given in Appendix A (Table A-7).

Values of M and N were calculated using the methodology presented in NUREG-0133 and are given in Table 3.3-1.

3.3.1.2 Cumulation of Doses Doses calculated monthly will be summed for comparison with quarterly and annual limits.

The monthly results will be

/'^s ~

added to the doses cumulated from the e

A_,/

other months in the quarter of interest in the year of interest and compared to i

IBM

ODCM Rev. 9 Page 34 the limits given in Equations 3.3-1 and

~

3.3-2.

If these limits are exceeded, a special report will be submitted to the USNRC in accordance with the PNGP Technical Specifications.

If twice the limits are exceeded, a special report showing compliance with 40 CFR 190 will be submitted.

3.3.2 Radiciodine, Particulate, and Other Radionuclides 1

3.3.2.1 Dose Equations The worst case dose to an individual from 1-131, tritium, and radioactive particulate with half-lives greater than eight days in gaseous effluents released to unrestricted areas is determined by the following expressions:

During any calendar quarter cn: year-3.17 x 10-8 R

V9v 1v + "v 1v 9

ij ak J 1

~

< 15 mrem (per quarter)

< 30 mrem (per calendar year)

(3.3-3) llk where:

release of radionuclides i for long-term Q

=

1v vent releases from both units (greater than 500 hrs /yr), pCi; releast of radionuclides i for short term

=

qiv purge releases from both units (equal to or less than 500 hrs /yr); pCi; the dispersion parameter for estimating W

=

y the dose to an individual at the controlling location for long-term vent releases (greater than 500 hrs /yr);

the dispersion parameter for estimating the v

=

V dose to an individual at the controlling location for short-term vent releases (equal to or less than 500 hrs /yr);

-8 the inverse of the number of seconds in 3.17 x 10

=

a year; R

O ijak =

the dose factor for each identified radionuclides i, pathway j, age group a, and organ k, m mrem /yr per pCi/sec or mrem /yr 3

per pCi/m.

ODCM R v. 9 Pega 35 The above equation will be applied to each

.s r^T combination of age group and organ.

Values of

(_)

R have been calculated using the methodology gkd8binNUREG-0133andaregiveninTables3.3-2 through 3.3-20.

Dose factors for isotopes not listed will be determined in accordance with the methodology in Appendix C.

Equation 3.3-3 will be applied to a controlling location which will have one or more of the following:

residence, vegetable garden and milk animal.

The selection of the actual receptor is discussed in Section 3.3.4.

The source terms and dispersion parameters in Equation 3.3-3 are obtained in the same manner as in Section 3.2.

The W 3

values are in terms of x/Q(sec/m ) for the inhalction pathways and for tritium (Tables 2

A-4 and A-5) and in terms of D/Q(1/m ) for all other pathways (Tables A-7 and A-8).

3.3.2.2 Cumulation of Doses Doses calculated monthly will be summed for comparison with quarterly and annual limite.

The monthly results should be added to the doses cumulated from the other months in the quarter of interest 73 and in the year of interest and compared

()

with the limits in Equation 3.3-3.

If these limits are exceeded, a special

, report will be submitted in accordanct with the PNGP Technical Specifications.

If twice the limits are exceeded, a special report showing compliance with 40 CFR 190 will be submitted.

3.3.3 Project. ion of Doses Doses resulting from the release of gaseous i

effluents will be projected monthly.

The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month.

In this case the source terms will be adjusted to reflect this information and the justification for the adjustment noted.

If the projected release of noble gases for the month exceeds 2 percent of the calendar year limits of equation 3.3-1 or 3.3-2, additional waste gas treatment will be provided.

If the projected release of I-132, tritium, and radioactive particulate with half-lives greater than 8 days r~'

exceeds 2 percent of the calendar year limit of

(

equation 3.3-3, operation of the ventilation exhaust treatment equipment is required if not currently in use.

IBM

ODCM Rev. 9 Page 36' 3.3.4 Critical Receptor Identification The critical receptors for compliance with 10 CFR 50, Appendix I will be identified.

For the noble gas specification the critical location will be based on the beta,and gamma air doses

)

I only.

This location will be the offsite location with the highest long term vent x/Q and will be I

selected using the X/Q values given in Appendix A, Table A-3.

This location will remain the same unless meteorological data is reevaluated or the site boundary changes.

The critical location for the 1-131, tritium, and long-lived particulate pathway will be selected once each year.

The selection will follow the annual land use census performed within 5 miles of the PNGP.

Each of the following locations will be evaluated as potential critical receptors prior to implementation of the Radioactive Effluent Technical Specifications:

1. Residence in each sector
2. Vegetable garden producing leafy green vegetables
3. All identified milk animal locations Following the annual survey, doses will be calculated using Equation 3.3-3 for all new identified receptors and those receptors whose characteristics have changed significantly. The calculation will include appropriate information about each new location.

The dispersion parameters given in this manual should be employed.

The total releases reported for the previous calendar year should be used as the source terms.

O IBM

ODCM Rev. 9 Pege 37 1

O REFERENCES l NJ-l l

(1)

"NSP-Prairie Island Nuclear Genecc. ting Plant, Appendix I Analysis'- Supplement No. 1 - Docket No. 50-282 and 50-306",

Table 2.1-4.

1 I

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ODCM Rcv. 9 Pego 58 4.0 INFORMATION RELATED TO 40 CFR 190 and 40 CFR 141

,m

( ')

The PNGP Technical Specifications indicate that if twice the per unit limits of 10 CFR 50, Appendix I are exceeded, a

'~

special report is required.

Therefore, if twice the annual limits of Equations 2.3-6, 2.3-7, 3.3-1, 3.3-2 or 3.3-3 are exceeded, the licensee shall prepare and submit a Special Report to the Commission and limit subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over 12 consecutive months.

This special Report is to include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the standards in 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations.

If analysis indicates that releases resulting in doses that exceed the 40 CFR 190 Standard may have occurred, then a variance from the Commission to permit such releases will be obtained.

The Standard Technical Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3 consider doses to a real individual and apply to each reactor but do not include any other portion of the uranium fuel cycle or direct shine from the reactor.

(/~\\

The " Uranium fuel cycle" is defined in 40 CFR Part 190.02(b)

_j as:

" Uranium fuel cycle means the operations of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle."

The Special Report will contain:

1)

A determination of which uranium fuel cycle facilities or operations, in addition to the nuclear power reactor units at the site, contribute to the annual dose to the maximum exposed member of the public.

Only those other fuel cycle facilities within 5 miles of PNGP need be considered.

No such facilities exist or are planned at f-present.

(

IBM

ODCM Rcv. 9 Paga 59 2)

A determination of the maximum exposed member of the P'

public as given for determining compliance with 10 CFR

(

50, Appendix I.

3)

A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents using the methodologies described for compliance with 10 CFR 50, Appendix I in this ODCM.

Where additional information on pathways and nuclides is needed, the best available information will be used and documented.

4)

A determination of the dose resulting from direct radiation from the plant and storage facilities.

The various organ doses resulting from liquid effluents from the PNGP will be summed with the organ doses resulting from releases of nobic gases, radioiodines and particulate.

These doses will be based upon releases from the PNGP during the past 3 quarters and from the quarter in which twice the specification was exceeded.

The doses from the PNGP will be summed with the doses to the maximum exposed individual contributed from other operations of the uranium fuel cycle.

The direct dose components will be determined by either calculation er actual measurement.

The N-16 component of direct radiation may be calculated using SKYSHINE. A Computer r~

()g Procedure Evaluhting Effects of Structure Design on N-16 Gamma-Ray Dose Rates.

Radiation Research Associates, Inc.

Report RRA-T7209, November 1972.

.(Available in the NSP-NSS Library).

The calculation or actual measurement will be documented in this Special Report.

If the quarterly or annual doses due to liquid releases exceed the values listed in Section 2.3.3, a special report shall be submitted to the USNRC and shall include information related to 40 CFR 141 such as analysis of Mississippi River water and an analysis of possible impacts through the drinking water pathway.

IBM l

ODCM Rcv. 9 Pega 60 5.0 RADIATION' ENVIRONMENTAL MONITORING PROGRAM (q

r 5.1 Sampling

_j Table 5.1-1 and Figures 5.1-1, 5.1-2, and 5.1-3 specify the current sampling locations based on the latest land use census.

If it is learned from an annual census that milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those i

previously sampled, the new milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable.

Sample locations (except the control) having lower calculated doses may be dropped from the program at the end of the grazing or growing season (October 31) to keep the total number of sample locations constant.

An annual land use survey will be conducted to determine whether corn fields are irrigated with water taken from the Mississippi River between the plant and a point 5 miles downstream.

If corn fields are being irrigated with Mississippi River water, appropriate samples will be collected and analyzed per Technical Specifications, Table 4.10-1.

73i' ')

5.2 Interlaboratory Comparison Program Analyses shall be performed on radioactive samples supplied by the EPA crosscheck program.

This program involves the analyses of samples provided by a control laboratory and comparison of results with those of the control laboratory as well as with other laboratories which receive portions of the same samples.

Media used in this program (air, milk, water, etc.) shall be limited to those found in the radiation environmental monitoring program.

The results of analyses performed as a part of the crosscheck program shall be included in the Annual Radiation Environmental Monitoring Report.

IBM

g ODCM Rev. 9 Page 61 TABLE 5.1-1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT l

RADIATION ENVIRONMENTAL MONITORING PROGRAM l

SAMPLING LOCATIONS Type of Sample Code Collection Site Location River Water P-S Upstream of Plant 0.6 mi @ 602/ENE c

River Water P-6 Lock & Dam #3 1.6 mi @ 129*/SE Drinking Water P-ll City of Red Wing 7.1 mi @ 135*/SE c

Well Water P-25 Kinneman Farm 11.1 mi @ 331*/NNW Well Water P-6 Lock & Dam #3 1.6 mi @ 129 /SE Well Water P-8 Kinney Store 2.0 mi 9 280 /W Well Water P-9 Plant Well #2 0.3 mi @ 306 /NW Sediment-River P-5 Upstream of Plant 0.6 mi @ 60 /ENE C

Sediment-River P-6 Lock & Dam #3 1.6 mi 0 129 /SE Sediment-Shoreline F-12 Recreation Area 3.4 mi @ 116 /ESE Periphyton or P-S Upstream of Plant 0.6 mi @ 60 /ENE e

O xecrei vertedrete-e-6 tecx & oe

  1. 2 1.e mi e 12e SE Fish P-5 Upstream of Plant 0.6 mi @ 60 /ENE C

Fish P-6 Lock & Dam #3 1.6 mi @ 129*/SE Milk P-25 Kinneman Farm 11.1 mi @ 331 /NNW c

Milk P-14 Gustafson Farm 2.2 mi @ 168*/SSE Milk P-16 Johnson Farm 2.6 mi @ 60 /ENE Milk P-17 Place Farm 3.5 mi @ 25 /NNE Milk P-18 Christensen Farm 3.7 mi @ 88*/E IBM

ODCM Rsv. 9 Pcgn 62 TABLE 5.1-1 (Continued) c.

h

~I PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS I

Type of Sample Code Collection Site Location Cultivated Crops (Leafy Green Veg)

P-25c Kinneman Farm 11.1 mi @ 331*/NNW P-24 Suter Residence 0.6 mi @ 158 /SSE (Corn)

P-25" Kinneman Farm 11.1 mi 0 331 /NNW P-14 Gustafson Farm 2.2 mi @ 168*/SSE c

Particulate and P-1 Air Station P-1 16.5 mi @ 348 /NNW Radioiodine (air)

Particulate and P-2 Air Station P-2 0.5 mi @ 294*/WNW Radiciodine (air) p(,)

Particulate and P-3 Air Station P-3 0.8 mi @ 313 /NW Radiciodine (air)

Particulate and P-4 Air Station P-4 0.4 mi @ 359*/N Radiciodine (air) l Part.iculates and P-6 Air Station P-6 1.6 mi @ 129 /SE' Radioiodine (air)

Direct Radiation 1

(TLD)

POlA Property Line 0.4 mi @ 359 /N I

Direct Radiation (TLD)

PO2A Prope/ty Line 0.3 mi @ 19 /NNE i

Direct Radiation (TLD)

PO3A Property Line 0.5 mi @ 183*/S Direct Radiation j

(TLD)

PO4A Property Line 0.4 mi @ 204 /SSW l Direct Radiation (TLD)

POSA Property Line 0.4 mi @ 225c/SW f)i

\\,

IBM

ODCM Rev. 9 Pega 63 TABLE 5.1-1 (Continued) g

.y

[

' PRAIRIE ISLAND NUCLEAR GENERATING PLANT

's ~

RADIATION-ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type of Sample Code Collection-Site Location

. Direct Radiation (TLD)

PO6A Property Line' O.4'mi @ 249*/WSW Direct-Radiation (TLD)

PO7A Property Line 0.4 mi @ 268*/W Direct Radiation (TLD)

PO8A Property Line 0.4 mi-@ 291*/WNW Direct Radiation (TLD)

PO9A Property Line 0.7 mi @ 317 /NW Direct Radiation

-(TLD)

P10A Property Line 0.5 mi @ 333 /NNW' Direct Radiation (TLD)

PolB Tom Killian Res.

4.7 mi @ 355 /N 5

Direct Radiation (TLD)

PO2B Roy Kinneman Farm 4.8 mi @ 17*/NNE Direct Radiation (TLD).

PO3B Wayne Anderson Farm 4.9 mi @ 46 /NE Direct Radiation (TLD)

PO4B Nelson Drive (Road) 4.2,mi @ 61*/ENE Direct Radiation (TLD)'

PO5B County Rd E & Coulee 4.1 mi 9 97 /E Direct Radiation (TLD)

PO6B William Houschildt Res.

4.4 mi @ 112*/ESE Direct Radiation (TLD)

PO7B Red Wing Service Center 4.7 mi 0 140*/SE Direct Radiation (TLD)

PO8B David Wnuk Res.

4.1 mi @ 165 /SSE Direct Radiation (TLD)

PO9B Hwy 19 South 4.2 mi @ 187 /s Direct Radiation

-(TLD)

P10B Cannondale Farm 4.9 mi @ 200 /SSW

. IBM

ODCM R:v. 9 P:go 64 TABLE 5.1-1 (Continued) j 7,

s t

)

PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type af Sample

_ Code Collection Site Location Direct Radiation (TLD)

P11B Wallace Weberg Farm 4.5 mi @ 221 /SW Direct Radiation (TLD)

P12B Roy Gergen Farm 4.5 mi @ 247a/WSW Direct Radiation (TLD)

P13B Thomas O'Rourke Farm 4.4 mi @ 270 /V l

Direct Radiation (TLD)

P14B David Anderson Farm 4.9 mi @ 3C6*/NW Direct Radiation (TLD)

P15B Holst Farms 4.2 mi @ 347 /NNW Direct Radiation (TLD)

P0lS Federal Lock & Dam #3 1.6 mi @ 129 /SE

,3

' -)

Direct Radiation (TLD)

P02S Charles Suter Res.

0.5 mi @ 155 /SSE Direct Radiation (TLD)

P03S Carl Gustafson Farm 2.2 mi @ 168 /SSE Direct Radiation (TLD)

P04S Richard B rt Res.

2.0 mi 0 228 /SW Direct Radiation (TLD)

POSS Kinney Store 2.0 mi @ 270 /W Direct Radiation (TLD)

P06S Earl Flynn Farm 2.5 mi @ 299 /WNW Direct Radiation (TLD)

P01C Robert Kinneman Farm 11.1 mi @ 331 /NNW l l

  • "c" denotes control location.

All other locations are indicators.

The letters af ter numbered TLD's are as follows:

"A" denotes locations in the general area of the site boundary.

g3 "B" denotes locations about 4 to 5 miles distance from the plant.

"S" denotes special interest locations.

IBM I

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ODCM Rev. 9 Pege 65 s

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[rN i)

Table A-1 Release Conditions Table A-2 Unrestricted Area Boundaries Table A-3 Long Term - Ground Level - Unrestricted Area Boundary - X/Q and D/Q.

Table A-4 Long Term - Ground Level.- Standard Distances - X/Q Table,A-5 Long Term - Ground Level - Standard Distances - D/Q

-Table A-6 Short Term - Ground Level - Unrestricted Area-Boundary - X/q and D/q Table A-7 Short Term - Ground Level - Standard Distances - X/4 Table A-8 Short Term - Ground Level - Standard Distances - D/q 6

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Summary of Dispersion Calculational Procedures Undepleted, undecayed dispersion parameters were computed using the computer program XOQDOQ (Sagendorf and Goll, 1977).

Specifically, sector average x/Q and D/Q values were obtained for a sector width of 22.5 degrees.

Building wake corrections were used to adjust calculations for ground-level releases.

Standard open terrain recirculation correction factors were also applied as available as default values in XOQDOQ.

Dispersion calculations were based on ground level releases for the shield buildings, turbine building, and auxiliary building (hereafter referred to as the plant complex).

A summary of release conditions used as input to XOQDOQ is presented in Table A-1 and controlling unrestricted boundary distances are defined in Table A-2.

Computed x/Q and D/Q values for unrestricted area boundary locations (relative to release points) and for standard distances (to five miles from the source in 0.1 mile increments) are presented in Tables A-3 through A-8.

Onsite meteorological data for the period April 1, 1977 through March 31, 1978 (as presented in Appendix B) were used as input to

(~;

XOQDOQ.

Data were collected and AT stability classes were

(,)

defined in conformance with NRC Regulatory Guide 1.23.

Dispersion calculations for the plant complex were based on AT 42.7-12.2m and 12.2 meter wind data (joint data recovery of 96 percent).

r~m I

U IBM a

ODCM Rev. 9 Pega 70 C'N REFERENCES

.G,M),.

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Sagendorf, J.F. and Goll, J.T.,

XOQDOQ Program for the Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG-0324, U.S. Nuclear Regulatory Commission, September 1977.

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D Distances (Miles) To Controlling. Unrestricted Area. Boundary Locations As Measured from Edge of Plant' Complex Sector Distance N

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.L 4

f APPENDIX - B

[

Prairie Island 12.2m Wind an-d AT 42.7-12'.2m 8t*Di1IU7

-Joint Frequency Distributions (4/1/77 - 3/31/78)

I i

IBM

l-

-ODCM I

-Rsv. 9 Page 108

/*

NORTHERN STATES POWER COMPANY PRAIRIE ISLAND' NUCLEAR GENERATING PLANT j

SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:

4/1/77 THROUGH 3/31/78 STABILITY CLASS A

{

ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION

'1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N

7 22 29 11 0

0 69 NNE 13 19 20 4

0 0

56 l

NE 11 35 16 1

0 0

63-DE 11 33 20 0

0 0

64 E

14 37 24 0

0 0

75 ESE 4

45 49 7

2 0

107 SE 4

10 22 13 1

0 50 SSE 1

7 19 12 2

0 41 S

2 23 45 27 0

0 97 SSW 1

22 39 14 0

0 76 SW 2

17 30 3

0 0

52

~

WSW 0

21 25 11 0

0 57 W

1 29 46 18 2

0 96 WNW 6

34 64 56 20 1

181 NW 12 42 72 53 20 0

199 NNW 11 43 49 20 2

0 125 VAR 0

0 0

0 0

0 0

(

TOTAL HOURS THIS CLASS 1408 HOURS OF CALM THIS CLASS 0

~

PERCENT OF ALL DATA THIS CLASS 16.81 IBM

ODCM Rcv. 9 '

.Pcga 109-

~.

NORTHERN STATES POWER COMPANY

.' /9

. PRAIRIE ISLAND NUCLEAR GENERATING PLANT V

SITE METEOROLOGY'- FREQUENCY DISTRIBUTION TABLES-HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:

4/1/77 THROUGH 3/31/78, STABILITY CLASS B ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL

-DIRECTION 1 TO 3 4 TO 7 8 TO 12

-13 TO 18 19 TO 24 ABOVE 24 TOTAL j

N O

3 5

1 0

0 9

NNE 1

2 1

1 0

0 5

NE O

2 0

0 0

0 2

ENE O

3 2

0 0

0' 5

E O

1 1

0 0

0 2

ESE 1

5 10 6

1 0

23 SE 2

2 8

4 0

0

.16 SSE O

3 4

3 0

0 10 S

1 0

7 9

0

.0 17.

SSW 0

1 7

0 0

0 8

SW 0

4 1

0 0

0 5

WSW 1

2 5

1 0

0 9

W 0

8 7

3 0

0

-18 WNW 1

5 8

6 3

0 23 NW 2

4 11 10 1

0 28 1

NNW 1

5 3

1 0

1 11 VAR 0

0 0

0 0

0 0

e TOTAL HOURS THIS CLASS 191 A

HOURS OF CALM THIS CLASS 0

PERCENT OF ALL DATA THIS CLASS 2.28 IBM-

ODCM Rsv. 9 Pags 110 "x

NORTHERN STATES POWER COMPANY

.f'j PRAIRIE ISLAND NUCLEAR GENERATING PLANT

\\s SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:

4/1/77 THROUGH 3/31/78 STABILITY CLASS C ELEVATION 40 FT I

WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL ' l N

2 4

4 1

0 0

11 NNE 2

3 1

0 0

0 6

NE 1

5 1

0 0

0 7

ENE O

3 1

0 0

0 4

E 1

8 3

0 0

0 12

,A ESE 0

7 11 2

0 0

20

(

SE O

2 5

6 0

0 13 SSE O

2 6

7 1

0 16 S

0 2

10 4

0 0

16 SSW 1

6 4

0 0

0 11 l

l SW 2

2 3

2 0

0 9

l WSW 1

6 5

1 2

0 15 W

0 2

11 4

1 0

18 WNW 1

3 6

7 1

0 18 L

NW 2

7 11 16 6

1 43 NNW 3

5 7

3 3

0 21 VAR 0

0 0

0 0

0 0

TOTAL HOURS THIS CLASS 240

.O)

N HOURS OF CALM THIS CLASS 0

PERCENT OF ALL DATA THIS CLASS 2.87 IBM

ODCM.

Rev. 9 Pega 111.

NORTRERN STATES POWER COMPANY.

.<m I f~'C PRAIRIE ISLAND NUCLEAR GENERATING PLANT I

b SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:

4/1/77 THROUGH 3/31/78 STABILITY CLASS D' ELEVATION 40 FT WIND SPEED (MPH) AT 40 IT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N

9 24 11 8

0 0

52 NNE 6

22 9

0 0

0 37 NE 16 26 4

0 0

0 46 ENE 11 41 4

0 0

0 56 E

11 95 27 0

0 0

133 TN ESE 8

57 154 19 0

0 238

\\

SE 10 30 90 38 5

0 173 SSE 8

40 59 51 10 0

168.

l S

1 51 72 17 4

0 145 SSW 5

29 30 12 0

0 76 j

SW 4

15 17 4

0 0

40 WSW 5

23 31 21 3

4 87 W

6 53 61 28 6

1 155 WNW 14 57 76 75 21 0

243 NW 14 44 72 110 41 0

281 NNW 16 22 41 25 13 0

117 VAR 0

0 0

0 0

0 0

i 7

TOTAL HOURS THIS CLASS 2051

.\\

HOURS OF CALM THIS CLASS 4

l PERCENT OF ALL DATA THIS CLASS 24,49 e

IBM

ODCM

'l Rcv. 9 Pega 112 NORTHERN STATES POWER COMPANY

[,m.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT A.

SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:

4/1/77 THROUGH 3/31/78 STABILITY CLASS E ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL j

N 22 30 9

11 1

0 73 NNE 18 29 7

0 0

0

$4' l

l NE 22 26 7

1 0

0 56 ENE 19 30 5

1 0

0 55 E

25 96 10 0

0 0

131 O

ESE 28 144 140 27 0

0 349 b

SE 24 107 125

-41 2

0 299 l

.a SSE 21 67 74 23 0

0 185 S

11 56 73 29 1.

0 170 SSW 3

26 29 40 1

0 99 SW 14 22 17 12 0

0 65 WSW 14 24 24 11 1.

0 74 W

26 73 48 18 1

0 166 WNW 46 136 127 44 4

0 357 NW' 46 98 101 62 8

0 315 l

.i NNW 43 53 48 10 3

0 157 VAR 0

0 0

0 0

0 0

TOTAL HOURS THIS CLASS 2612 N '

HOURS OF CALM THIS CLASS 7

PERCENT OF ALL DATA THIS CLASS 31.18 IBM i

ODCM.

s.

Rsv. 9

.Page 113 A.

NORTERN' STATES POWER COMPANY.

PRAIRIE ISLAND NUCLEAR GENERATING' PLANT j[

SITE ETEOROLOGY - FREQUENCY DISTRIBUTION TABLES 3

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD:- 4/1/77 THROUGH 3/31/78 STABILITY CLASS'F ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL-DIRECTION

.1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N

18 8

3 0

0 0'

29 NNE-11 6

1 0

0 0

18 NE 11 5

2 0

0 0

18 ENE 13 7

0 0

0 0

20 E

29 33 2-0 0

0 64 ESE 39 61 9

1 0

0 110 SE 38 69 36

'3.

0 0

146

'SSE 27 32 17 2

1 0

79.

S 12 16 21 7

0 0

56

'SSW 6

.11 17.

6 0.

0 40 SW 5

3 9

4 0

0 21 WSW 8

8 8

0 0

0 24 W

25 39 12

'2 0

0 78 WNW 56 63 12 0

0 0

131 NW

.66 71 16 3

0

-0 156 s

NNW-29 19 6

2 0

0 56 VAR 0

0 0

0 0

0 0

TOTAL HOURS THIS CLASS 1053 HOURS OF CALM THIS CLASS 7

PERCENT OF ALL DATA THIS CLASS 12.57 IBM

ODCM Rsv. 9 Page 114 NORTHERN STATES POWER COMPANY y'-.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES-HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS G ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N

14 5

0 0

0 0

19 NNE 13 2

1 0

0 0

16 NE 12 2

1 0

0 0

15 ENE 22 1

2 0

0 0-25 E

52 8

2 0

0 0

62 O

.ESE 50 17 1

0 0

0 68 l

Ag SE 37 23 8

1 0

0 69 SSE 18 8

7 2

0 0

35 S

11 4

4 0

0 0

19 I

SSW 13 2

2 0

0 0

17 SW 15 5

1 0

0 0

21 WSW 10 1

1 0

0 0

12 W

41 19 1

0 0

0 61 WNW 75 50 0

0 0

0 125 NW 80 66 3

0 0

0 149 NNW 47 19 5

0 0

0 71 VAR 0

0 0

0 0

0 0

l TOTAL HOURS THIS CLASS 821 HOURS OF CALM THIS CLASS 37 PERCENT OF ALL DATA THIS CLASS 9.80 IBM

_ _ - ___ L

'l ODCM

-Rsv. 9 Page 115 fbm.)i '

i APPENDIX _Q DOSE PARAMETERS FOR RADIOIODINES, PARTICULATE AND TRITIUM This appendix contains the' methodology.which was used to calculate the dose parameters for radioiodines, particulate, and tritium to show compliance with 10 CFR 20 and Appendix I of 10 CFR 50 for gaseous effluents.

These dose parameters, P and-R, were 1

calculatedusingthemethodologyoutlinedinNURkG-0133along with Regulatory Guide 1.109 Revision 1.

The following sections provide the specific methodology which was utilized in calculating the P and R values for the various exposure g

g pathways.

C.1 Calculation of Pj The parameter,'P, contained in the radiciodine,and particulatesporbionofSection3.2,includespathway

(]

transport parameters of the ith radionuclides, the receptor's N-usage of the pathway media and the dosimetry of the exposure.

Pathway usage rates and the internal dosimetry are functions of the receptor's age: however, the youngest age grcup, the infant, will always receive the maximum dose under the exposure conditions assumed.

C.1.1 Inhalation Pathway K'(BR) DFA (C.1-1)

P

=

f g

I where:

dose parameter for radionuclides i for the P

=

3 g

inhalation pathway, mrem /yr per pCi/m ;

I K'

=

a constant of unit conversion:

6

=

10 pCi/pCi; tgebreathingrateoftheinfantagegroup, BR

=

m fyr; i

the maximum organ inhalation dose factor

>\\

DFA.

=

1 for the infant age group for radionuclides i, mrem /pci.

IBM

ODCM R v. 9 Page 116 fant group.

The infant's The age group considered is the ig/yr from Table E-5 of d

breathing' rate is taken as 1400 m Regulatory Guide 1.109-Revision 1.

The inhalation dose factors for the infant, DFA are presented in Table E-10 ofRegulatoryGuide1.109ik,unitsofmrem/pci.

The total body is considered as an organ in the selection of DFA.

Theincorporationofbreathingrateofaninfantandthe unit conversion factor results in the'following:

9 1.4 x 10 DFA (C.1-2)

P

=

f f

I C.2 Calculation of R.

The radioiodine and particulate Technical Specification is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs.

The inhalation and ground plane exposure pathways shall be considered to exist at all locations.

The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are considered based on their existence at the various locations.

R values have been calculated for the adult, 4

teen, child, and infant age groups for the ground plane, cow milk, goat milk, vegetable and beef ingestion pathways.

The CV) methodology.which was utilized to cElculate these values is presented below.

4 C.2.1' Inhalation Pathway 0 (BR),(DFA ),

(C.2-1)

/

R

=

g f

I where:

dose factor for each identified R

=

i radionuclides i of the organ of interest, 3

t mrem /yr per pCi/m ;

a constant of unit conversion:

K'

=

6

=

10 pCi/pCi; of the receptor of (BR),

breathing ratg/yr:

=

age group a,m g

organ inhalation dose factor for (DFA )#

=

g radionuclides i for the receptor of age group a, mrem /pCi.

The breathing rates (BR) for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109 Revision 1.

IBM i

"N i

i" i

'.ODCM 4

Rev. 9

'Page 117 Age Group (a)

Breathing Rate (m /yr)

Infant 1400 Child 3700 Teen-8000 Adult 8000 Inhalation dose factors (DFA )

for the various age groups 4

are given in Tables E-7 throog$ E 10 of Regulatory Guide 1.109 Revision 1.

C.2.2 Ground Plane Pathway

-A t I K'K"(SF)DFG (1-e i )/x (C.2-2)

R

=

f f

1 G

where:

dose factor for the ground plane pathway R

=

g for each identified radionuclides i for G

the organ of @terest, mram/yr per pCi/sec per m ';

e constant of unit conversion; K'-

=

6

=

10 pCi/pci; a constant of unit conversion; K"

=

8760 hr/ year;

=

the radiological decay' constant'for A

=

i radionuclides i, sec~l; the exposure time, see; t

=

8 4.73 x 10 see (15 years);

=

the ground plane dose conversion factgr DFG

=

f for radionuclides i; mrem /hr per pCi/m ;

the shielding factor (dimensionless);

SF

=

factor to account for fractional I

=

i deposition of radionuclides 1.

For radionuclides other than iodine, the factor I.

is For radiciodines, the value of I diay i

equal to one.

However,avalueof1.0wasusedincaleblating vary.

the R values in Table 3.3-2.

IBM

ODCM Rev. 9

Pega.-118 ym Q.

A shielding factor;of 0.7 is suggested in Table.E-15 of Regulatory Guide-1.109 Revision 1.

A tabulation.

of DFG4 values is presented in Table E-6 of Regulatory' Guide 1.109 Revision 1.

C.'2. 3 Grass-Cow or Goat-Milk Pathway l

4 *b)-

-A t

1 Iiv(1~*

if r(1-e i*)'+

+

R Fsp,N ),e f f, 73 pz

. 3 g ; "' I K'Q F

1

~

g p

~

g PE i

-A

~

  • (1-*

I )

B (1-e i b)',-A e

.(c.2-3)

E g

<(1-f f )-

+:

gy o

Ps L

Y,AE.

PA

!,a.

i 1

.Odere:

R.t

. dose factor for the cow milk or goat milk

=

'M-pathway, for each identified radionuclides i-f mrem /yr per for the organ,,9; interest,

'pCi/see per m a constant.of unit conversion; K'

=

6

=-

10 pCi/pci; Qp the cow's or goat's feed consumption rate, f

'i

's

=

l kg/ day (wet weight);

i the receptor's milk consumption rate t'or age U

=

ap group a, liters /yr; i

the agricultural productivity by unit area Y

=

p-of pasture feed grass, kg/m ;

theagriculturalprojuctivitybyunitarea Y

=

3 of stored feed, kg/m ;

the stable element transfer coefficients, F*

=

pCi/ liter per pCi/ day;

.s fraction of deposited activity retained on l

r

=

cow's feed grass; i

the organ ingestion dose factor for (DFL )j

=

g radionuclides i for the receptor in age group 7'

t., mres/pCi; 1x

ir

~ o,,

IBM m

L ODCM Rsv.:9 Pega-119 2N A

=

Ai+A'

(

E w

.. _j the radiological decgy constant for A

=

f radionuclides i,.sec the decay constant for removal of activity A

=

W on 1gaf and plant surfaces by weathering, sec 5.73 x 10-7

~1 (corresponding to a sec

=

14 day half-life);

the transport time from feed to cow or goat t

=

g to milk, to receptor, see; the transport time from' harvest, to cow or t

=

h goat, to consumption, sec; period of time that sediment is exposed to t

b gaseous effluents sec; concentration factor for uptake of B

=

iv radionuclides i from the soil by the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg.(dry soil);

f) effectlye surface density for soil, (dry

's / '

P

=

soil)/m ;

fraction of the year that the cow or goat f

=

p is on pasture;

~

fraction of the cow feed that is pasture f

=

s grass while the cow is on pasture; I

t, period of pasture grass and crop exposure

=

during the growing season, sec; factor to account for fractional deposition I

=

f of radionuclides i.

For radionuclides other than iodine, the factor 14 is equal to one.

For radioiodines, the value of Ig may l

[

vary. However, a value of 1.0 was used in calculating t

the R values Tables 3.3-9 through 3.3-16.

i l

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds.

Following the development in Regulatory Guide 1.109 Revision 1, the value of f was considered unity in

[~').

lieu of site-specific information.

The valt.e of f p

\\s was 0.667 based upon an 8-month grazing period.

IBM l

l ODCM Rcv. 9'

)

Page 120 i

Table C-1 contains the appropriate parameter values and-their source in Regulatory Guide 1.109 Revision 1.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition.

Therefore, the R is based on X/Q:

1 K'K"'F,QpQp,p(DFL ),

0.75(0.5/H)

(C.2-4)

U R

=

g T

where:

dose factor for the cow or goat milk pathway R

=

T for tritium for tge organ of interest, M

mrem /yr per pCi/m ;

a constant of unit conversion; K"'

=

3 10 gm/kg;

=

3 absolute humidity of the atmosphere', gm/m ;

H

=

the fraction of total feed that is water; 0.75

=

the ratio of the specific activity of the 0.5

=

feed grass water to the atmospheric water.

and other parameters gnd values are given above.

A value of H of 8 grams / meter, was used in lieu of site-specific information.

C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore:

E Biv(1-e i b).

-A t gs r(1-i e)

+

I K'Q U,pF (DFL ), e ff R

=

g p

g "A *b)

~

-A t

i

  1. fl~*

i )

iv (

e ih (C.2-5)

(1-f f )

+

ps Y,AE g

PA I

where:

dose factor for the meat ingestion pathway R.

=

l f interest, for radionuclides i for any2;rgan

(

B mrem /yr per pCi/sec per m IBM

mg 1'

ODCM-Rev. 9'

Pege 121

~

F

=.

the stable: element' transfer coefficients, f

.pCi/Kg per pCi/ day;-

.the receptor's meat consumption rate.for age-

~U

=-

ap group a, kg/yr; t,

the transport time.from slaughter to

=

consumption, sec; the transport time from harvest to animal t

=

h.

consumption,=see; I

t*

period.of pasture grass and' crop' exposure

=

during the growing season, sec;..

factor to account for fractional deposition I

=

f of: radionuclides i.

For radionuclides other than iodine, the factor 14 is equal to one.

For radioiodines,.the value of.1 ms.y vaty.

4 However, a value of 1.0 was used in calculating the R values in Tables'3.3-6 through 3.3-8.

All~other terms remain the same as defined in Equation C.2-3.

Table C-2 contains the values which'were used in calculating R for the meat pathway.

f The concentration of tritium in meat is based on its airborne concentration rather than the deposition.

Therefore, the R is based on X/Q.

f K'K"'F Q U,p(DFL ),

0.75(0.5/H)

(C.2-6)

R

=

f7 f

T where:

dose factor for the meat ingestion pathway R

=

T for tritium for agy organ of interest, mrem /yr per pCi/m All other terms are defined in Equation C.2-4 and C.2-5, above.

C.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor.

Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:

~ IBM

{

[

1 ODCM l

Rev. 9

)

Page.122 f~

\\

-A t

  • t

_x g

L iL r (1-e g e),Bgy(1-e g b)

-A E E

I K,(DFL )a Uf e R

=

1 1

aL YA PA iy yE g

1.

~

-A t

Biv(

i b) -

-A g r(1-e i

(C.2-7) i ) +

O e Uf ag YA i

yE i

1 where:

dose factor for vegetable pathway for R

=

b radionuclides i for the organ of injerest, mrem /yr per pCi/sec per m

a constant of unit conversion:

K'

=

6

=

10 pCi/pci; b

the consumption rate of fresh leafy U

=

vegetation by the receptor in age group a, kg/yr; S

the consumption rate of stored U,

=

vegetation by the receptor in age group a, kg/yr; the fraction of the annual intake of f

=

b fresh leafy vegetation grown locally; the fraction of the annual intake of f

=

E stored vegetation grown locally; the average time between harvest of t

=

g leafy vegetation and its consumption, sec; the average time between harvest of t

=

h stored vegetation and its consumption, sec; the vegetation areal density, kg/m2; Y

a y

period of leafy vegetable exposure t

=

8 during growing season, sec; I.

=

factor to account for fractional 1

N deposition of radionuclides i.

IBM

r ODCM

+

Rev. 9 Page 123-

~

!/

  • For radionuclides other than iodine, the factor I is d

equal to one.. For radioiodines, the value1 of'I. bay However, a 7alue of 1.0 was used.in calediating-vary.

.the R. values in' cables 3.3-9 through 3.3-12.

L All other' factors were defined above.

Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision.l.

In ' lieu of site-specific data default values for fg and f, 1.0 and 0.76, respectively were used in the cIl(.ulation of R These values were obtained from

TableE-15ofReku.latory Guide 1.109 Revision 1.

The concentration of tritium in vegetation is based on the airborne concentration rather than the depositien.

Therefore, the R is based on X/Q:

t Ujf

'(DFL ), 0.75(0.5/H)

(C.2-8)

\\

R K'K"'

Uf

+

T

=

y y

g where:

O dese fecter for the vesetes1e gathwer for R

=

T tritium fp any organ of interest, mrem /yr per pCi/m All other terms remain the same as those in Equations C.2-4 and C.2-7.

9 IBM

ODCM Rev. 9 Pega'124-

. TABLE C-1 Parameters For. Cow and Goat Milk Pathways Parameter Value Reference (Reg. Guide 1.109 Rev. 1 QF ( g/ ay) 50 (cow).

Table E-3 6 (goat)

Table E-3 2

Yp (kg/m )

0.7-Table E-15 L

5 2 days)

Table E-15

(

f (seconds) 1.73 x 10 t

1.0 (radiciodines)

Table E-15 r

0.2 (particulate)

Table E-15 (DF.L ), (mrem /pCi)

Each radionuclides Tables E-11 to E-14 f

F, (pCi/ day per pCi/ liter)

Each stable element Table'E-1 (cow)

Table E-2 (goat) 3 (seccads) 4.73 x 108 (15 yr)

Table E-15 t

2 2.0 Table E-15 Y, (kg/m )

2 0.7 Table E-15 p (kg/m )

Y h (see uds) 7.78 x 100 (90 days)

Table E-15 t

.330 infant Table E-5 ap (liters /yr)

U 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 2.59 x 106 (pasture)

Table E-15

  • (seconds) t 5.18 x 10 (stored feed)

B (pCi/Kg (wet weight)

Each stable element Table E-1 fy per pCi/Kg (dry soil))

P (Kg (dry soil /m )

240 Table E-15 IBM

ODCM Rsv. - 9

'Pega 125 y3[]

TABLE C-2

%./

Parameters For The Meat Pathway

/

Parameter Value Reference (Reg.. Guide 1.109 Rev. 1 r

1.0 (radioiodines)

Table E-15 0.2 (particulate)

Table E-15 i

Ff (pCi/Kg per pCi/ day)

Each stable element Table E-1 O infant Table E-5 ap (Kg/yr).

U 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFL ), (mrem /pCi)

Each radionuclides Tables E-11 to E-14 g

2 0.7 Table E-15 p (kg/m )

Y

/'

2 Y, (kg/m )

2.0 Table E-15 b (see uds) 4.73 x 108 (15 yr)

Table E-15 t

t,(seconds) 1.73 x 10 (20 days)

Table E-1_5 h (see nds) 7.78 x 10 (90 days)

Table E t

  • (seconds) 2.59 x 106 (pasture)

Table E-15 t

5.18 x 10 (stored feed)

)

Qf (kg/ day) 50 Table E-3 B

(pCi/Kg (wet weight)

Each stable element Table E-1 fy per pCi/Kg (dry soil))

P (Kg (dry soil)/m )

240 Table E-15 Om IBM

.ODCM LRsv.1 9 Pegs 126-TABLE C-3 Parameters For The Vegetable' Pathway Parameter Value Reference (Reg. Guide 1.109 Rev.!1 r (dimensionless) 1.0 (radioiodines)

Table E-1 0.2 (particulate)

Table E-1

.(DFL ), (arem/Ci)

Each radionuclides Tables E-11 to E-14' g

((kg/yr)

- Infant 0

Table E-5

- Child 26 Table E-5

- Teen.

42 Table E-5 l

- Adult 64 Table E-5 i

8 U.(kg/yr) - Infant 0

Table E-5

- Child 520 Table E-5

- Teen 630 Table E-5

- Adult 520 Table E-5 g (seconds) 8.6 x 10' (1 day).

Table E-15 t (seconds) 5.18 x 106 (60 days)

Table E-15 h

Y (kg/m )

2.0 Table E-15 y

t,(seconds) 5.18 x 100 (60 days)

Table E-15 8'(15 yr)

Table E-15

.t3 (seconds) 4.73 x 10 P(Kg(dry. soil)/m )

240 Table E-15 Bgy(pCi/Kg(wet weight)

Each stable element Table E-1 per pCi/kg;(dry soil))

IBM m

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