ML20064E835
| ML20064E835 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/31/1982 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20064E793 | List: |
| References | |
| PROC-821031, NUDOCS 8301060148 | |
| Download: ML20064E835 (187) | |
Text
_..
i i
r OFFSITE DOSE CALCULATION MANUAL FOR DAVIS-BESSE NUCLEAR POWER STATION e
4 October, 1982 i
}
i 4
P i
l ODCM TABLE OF CONTENTS Page INTRODUCTION..
. iv 1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Fetisints
. 1.0-1 1.1.1 Liquid Radwaste Eifluent Line Monitors..
1.0-1 1.1.2 Turbine Building (Floor Drains) Sump Effluent Line
. 1.0-6 1.2 Dose Calculation for Liquid Effluents
. 1.0-10 1.3 Projected Personal Maximum Dose
. 1.0-12 2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints.
. 2.0-1 2.1.1 Station Vent Monitor.
. 2.0-1 2.1.2 Waste Gas Decay System and Containment Purge Monitors.
. 2.0-3 2.2 Gaseous Effluent Dose Calculations.
. 2.0-5 2.2.1 Unrestricted Area Boundary Dose
. 2.0-5 2.2.2 Unrestricted Area Dose to Individual.
. 2.0-8 2.3 Meteorological Model..
. 2.0-10 I
2.3.1 Long Term Atmospheric Dispersion.
. 2.0-10 2.3.2 Long Term Deposition.
. 2.0-14 2.4 Gaseous Radwaste Treatment System 2.5 Definitions of Gaseous Effluents Parameters
. 2.0-14 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING.
. 3.0-1 3.1 Land Use Census
. 3.0-1 3.2 Sample Analyses
. 3.0-2 DAVIS BESSE, UNIT 1 i
ODCM Table of Contents (Continued)
Page APPENDIX A Figures 1.
Calibration curve for Liquid Effluent Monitors.... A-1 2.
Open terrain correction factor.
... A-2 3.
Plume depletion effect for ground-level releases... A-3 4.
Plume depletion effect for 30-m releases.
. A-4 5.
Plume depletion effect for 60-m releases...
.. A-5 6.
Plume depletion effect for 100-m releases
.. A-6 7.
Vertical standard deviation of material in a plume.. A-7 8.
Relative deposition for ground-level releases
... A-8 9.
Relative deposition for 30-m releases
.. A-9 10.
Relative deposition for 60-m releases
... A-10 11.
Relative deposition for 100-m releases........ A-11 12.
Map of sampling locations on the plant periphery... A-12 13.
Map of sampling locations greater than 1.5 miles from site
.. A-13 14.
Davis-Besse Gaseous Discharge
.. A-14 15.
Davis-Besse Liquid Discharge.
... A-15
- 16. Maps of individual sampling locations
.. A-16 APPENDIX B Tables 1.
Bioaccumulation factors
... B-1 2.
Ingestion dose factors for adults
... B-2 3.
Site related ingestion dose commitment factor
... B-5 4.
Dose factors for exposure to semi-infinite cloud of noble gases.
... B-7 5.
Pathway dose parameter factors for implementing 10 CFR Part 20.................... B-8 DAVIS BESSE, UNIT 1 ii
ODCM Table of Contents (Continued)
Page 6.
Pathway dose parameter factors for implementing 10 CFR 50
............. B-20 7.
Controlling receptors, locations, and pathways.... B-59 8.
Atmospheric dispersion parameters for technical specification 4.11.2.4.1............... B-60 9.
Sampling 1.ocations.................. B-61 APPENDIX J Justifications Safety Evaluation..................... J-1 Service Water System-Radiological Effluent Monitoring Requirements
.... J-4 Radioactive Effluent Instrumentation -
- Automatic Isolation Feature
.............. J-5 Technical Bases for Eliminating Curie Inventory Limit for Gaseous Waste Decay Tanks..................... J-6 Lower Limit of Detection-Decay Correction Factor...................,. J-9 Technical Basis for Liquid Radwaste System Operations
................ J-13 Waste Gas Decay System and Ventilation System-Operability Requirements
..................... J-16 i
Radiological Effluent Dose Analysis-Meteorology for Short Term Releases
................... J-18 Radiological Environmental i
Reporting Levels
..................... J-19 Technical Basis for Eliminating Curie Inventory Limit of Outside Liquid Tanks
..................... J-20 Sampling Frequency for I-131:
Significance.of Power Changes and Increases in Coolant Activity Levels
........... J-21 i
t l
l Condensate Demineralizer Backwash Receiving Tank - Radioactivity Control
....... J-24 DAVIS BESSE, UNIT 1 iii L_
i INTRODUCTION This OFFSITE DOSE CALCULATION MANUAL (ODCM) describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alare/ trip setpoints. The ODCM also contains a list and graphic description of the specific sample locations for the radiological environmental monitoring program.
The ODCM will be maintained at the Station for use as a reference guide and training document of accepted methodologies and calculations.
Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas.
The methodology stated in this manual is acceptable for use in demonstrat-ing compliance with 10 CFR 20.106, 10 CFR 50 Appendix I, and 40 CFR 190.
i Only the dose attributable to the Davis-Besse Nuclear Power Station is considered in demonstrating compliance with 40 CFR 190.
1 1
More conservative calculation methods and/or conditions (eg, location and/or exposure pathways expected to yield higher computed doses) than appropriata for the maximally exposed person may be assumed in the dose evaluations.
i For the calculation of individual doses from gaseous effluents, the receptor is selected on the basis of applicable exposure pathways identi-fied in the land use census. Methodologies and pathways considered in NUREG 0133 are consistent with those in the ODCM.
For liquid releases, doses are evaluated for the drinking water and freshwater fish pathways.
In the Great Lakes region, invertebrates do not constitute a direct ingestion pathway to man.
DAVIS-BESSE, UNIT 1 iv
1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints 1.1.1 Liquid Radwaste Effluent Line Monitors Liquid Radwaste Effluent Line-Monitors provide alarm and automatic termination of release prior to exceeding the concentration limits specified in.10 CFR 20, Appendix B, Table II, Column 2 at the release point to the unrestricted.
area.
To meet this specification, the alarm / trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:
F+f (1-1) cf.< C, r
where:
the effluent concentration' limit (RETS, section C
=
3.11.1) implementing 10 CFR 20.106 for the site, in pCi/ml l
~
l f
the setpoint, in pCi/ml, of the radioactivity I,
c
=
l monitor measuring the radioactivity.chncentration 4-l in the effluent line prior to dilution and sub-sequent release; the setpoint, which is prepor-tional to the volumetric flow of the eff1uent line and inversely prcpr:rtional to'the volumetric flow of the d_iluticn stream plus the effluent stream, represcats.a'value which, if exceeded, j
would result in <cacentrations exceeding the limits of~10 CFR 20.106 in the unrestricted area
\\
i l'
I
~'
DAVIS-BESSE, UNIT 1 1.0-1
r
f
=
the flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below the dilution water flow setpoint as measured A
F
=
prior to the release point in volume per unit time.
At Davis-Besse Unit 1, the available dilution water flow (F) is constant for a given release, and the waste tank flow (f) and monitor setpoint (c) are set to meet the condition of Equation 1-1 for a given effluent concentra-i tion, C.
The method by which this is accomplished is as follows:
1)
The isotopic concentration for a waste tank to be released is determined by the analyses required in RETS Table 4.11-1.
The ratio of the concentration to the unrestricted area MPC (10 CFR 20, Appendix B, Table II, Column 2) is calculated with the equation:
C (1-2) 8 gph U
FMPC = I i
i i
i where:
FMPC =
fraction of the unrestricted area MPC C
concentration of each radionuclide i measured
=
gg in each tank prior to release (pCi/ml) b i~
unrestricted area MPC for each radionuclide MPC =
i j
g i from 10 CFR 20, Appendix B, Table II, Column 2.
For dissolved and entrained noble l
gases a value of 2 x 10-4 pCi/ml shall be used.
DAVIS-BESSE, UNIT'l 1.0-2 l
l
The total or gross beta or gamma activity alone may be used to conservatively determine the MPC fraction by the equation:
C FMPC =
t (1-3) 1x10-#
Where:
C = the total or gross beta or gamma activity t
1 x 10-7 = MPC value for an unidentified mixture of radionuclides (from footnote 3.b to 10 CFR 20, Appendix B).
2)
The MPC fraction (FMPC) as determined for each batch used to calculate a Dilution Factor, D.F., which is the ratio of total dilution flow rate to tank flow rate required to assure that the limiting concentra-tion of 10 CFR 20, Appendix B, Table II, Column 2 are met at the point of discharge.
D.F. = FMPC (1-4)
S.F.
where:
D.F. =
dilution factor S.F. =
an administrative safety factor normally applied at Davis-Besse which causes the cal-culated Dilution Factor to be 3.33 times larger than the dilution factor required for compliance with 10 CFR 20 limits.
DAVIS-BESSE, UNIT 1 1.0-3 l
la
i 3)
The maximum permissible waste tank flow rate, f, is d
calculated based on a fixed dilution flow rate, F d d+ Ids d for d >> Id F
F fd=
(1-5)
D.F.
D.F.
where:
0.9 x (dilution flow rate), as readout in F
=
d control room f
=
maximum Permissible waste tank flow rate d
D.F. =
Dilution Factor from Step 2.
NOTE that the equation is valid only for D.F. >1; for D.F. <1, the waste tank concentration meets the limits of 10 CFR 20 without dilution, and f may take on any d
desired value.
4)
The minimum dilution flow (F), and waste tank maximum flow rate setpoint (f) are calculated as follows:
F=F = 0.9 x actual dilution flow rate as observed d
from.the control room readout, f = 0.9 x fd = 0.9 calculated maximum waste tank flow rate for the stated release conditions.
A control room alarm occurs if the dilution flow rate falls below the preset flow rate, or if the tank flow rate exceeds 0.9 of the preset flow rate, and the release is terminated.
o DAVIS-BESSE, UNIT 1 1.0-4
5)
The monitor setpoint may now be specified based on the values of F, and f which were specified to assure that releases are maintained below the concentrations of 10 CFR 20, Appendix B, Table II, Column 2.
The monitor setpoint in counts per minute (cpm) is taken from the monitor calibration graph (e.g. Figure 1) to correspond to three times the concentration in the batch.
S.P. = 3 x A (pCi/ml)
(1-6) where:
S.P. =
the monitor setpoint obtained from the calibration curve for the monitor (cpm) total radioactivity concentration in the A
=
batch A=IC I
i i
or, if based on gross or total beta or gamma
- analysis, A=C g Normally, only one liquid release is conducted at a time.
If more than one release of radioactive effluents is conducted simultaneously, the setpoints for the individual radiation monitors for the combined releases will be set to prevent exceeding the concentra-tions of 10 CFR 20, Appendix B, Table II, Column 2 in the environment.
I DAVIS-BESSE, UNIT 1 1.0-5
NOTE that the setpoint contains a factor of conserva-tism, even if the calculated setpoint tank flow rate is attained, since the calculated rate contains the factors as shown:
0.3 x 0.9 x 3 = 0.81 1
I I
I l
l l
l__ fraction of limit for trip setpoint i
I I
l l
l__ multiplier for setpoint from equation (1-4) l I
l l__ waste tank rate margin I
l__ dilution factor margin In practice, the actual tank flow rate normally is many times less than the calculated tank flow rate, thus providing an additional safety factor during a release.
1.1.2 Turbine Building (Floor Drains) Sump Effluent Line (Applicable upon completion of modification) i The purpose of the monitor for the turbine building sump effluent line (or Unit Storm Sewer Outlet) is to detect abnormal radionuclide concentrations in the sump effluent system.
Because the only sources to the sump effluent system are from the secondary steam system, activity is expected in the turbine building sump effluent system only if a significant primary-to-secondary leak is present.
If a primary-to-secondary leak is present, the activity in the sump effluent system would be comprised of only those radionuclides found in the secondary system, but with reduced activity from decay and dilution.
DAVIS-BESSE, UNIT 1 1.0-6
Until activity is measured in the secondary system, it will not be practical to select radionuclides on which to cal-culate the setpoint of the inline monitor. The monitor is, therefore, operated normally as a gross gamma detector at the lowest practical activity level to prevent false alarms.
The lowest practical level has been determined to be three times the background count rate of the monitor when filled with clean water.
When activity above the level specified in RETS Table 4.11-1 is detected in the secondary system, the principal nuclide or nuclides comprising a major fraction of the activity in the secondary system condensate will be identi-fied by gamma ray spectroscopy in the laboratory. The monitor setpoint will then be determined as follows:
1)
The isotopic concentration for the turbine building sump effluent is determined by the sampling and analytical requirements per RETS Table 4.11-1 (only required when secondary system concentration exceeds 10-5 pCi/ml). The ratio of the concentration to the unrestricted area MPC is calculated with the equation:
C (1-7) 8 3ph_
FMPC = I i
i Where:
FMPC =
fraction of the unrestricted area MPC C
concentration of each radionuclide i measured
=
gg in each grab sample unrestricted area MPC for each radionuclide i MPC
=
g from 10 CFR 20, Appendix B, Table II, Column 2.
For dissolved and entrained gases, a value of 2x10-4 pCi/ml shall be used.
DAVIS-BESSE, UNIT 1 1.0-7
If based on gross or total beta or gamma analysis, the unrestricted area MPC fraction is simply:
(1-0)
FMPC = t 1x10-'
C = the total or gross beta or gamma activity g
1x10-7 = MPC value for an unidentified mixture of radio-nuclides (from footnote 3.b to 10 CFR 20, Appendix B).
2)
The actual dilution factor from fixed flow rates of the turbine building sump effluent flow rate and dilution flow rate is as follows:
actual dilution factor = f + F f
where:
f turbine building sump effluent flow rate
=
(gpm) dilution flow rate (gpm)
F
=
3)
The concentration in the turbine building sump which corresponds to an unrestricted area MPC value after dilution is calculated from the previously defined quantities, and is:
A
,f+F (1-9) c = FMPC f
where:
concentration corresponding to the un-c
=
restricted area MPC value after dilution DAVIS-BESSE, UNIT 1 1.0-8
total radioactivity concentration (pCi/ml)
A
=
A=IC E
i i
or, if based on total or gross beta or gamma
- analysis, A=C t
The calibration curve for the monitor (eg, Figure 1) is then used to determine the count rate (cpm) cor-responding to the radionuclide concentration (c).
The monitor setpoint is the sum of the calculated count rate plus the observed background count rate of the monitor.
To simplify the determination of setpoint or in the event that the concentration of radioactive material in the sample from the turbine building sump is below measurable levels (ie, less than 5 x 10-7 pCi/ml for principal gamma emitters), the value of I x 10-7 pCi/ml may be sub-stituted for the factor A (ie, A
= 1 x 10-7).
FMPC FMPC It may conservatively be assumed that the radionuclide concentrations in the secondary system are identical to those in the turbine building sump.
Therefore, the results of the sampling and analysis of the secondary system may be used in conservatively determining the values of FMPC and c, above.
DAVIS-BESSE, UNIT 1 1.0-9
1.2 Dose Calculation for Liquid Effluents e
Technical Specification 4.11.1.2.1 requires that an assessment be r
I performed at least once every 31 days in any quarter in which radio -
active effluent is discharged to determine whether the dose or dose commitment to a person offsite due to radioactive material released in liquid effluent calculated on a cumulative basis exceeds Specifi-cation 3.11.1.2..The requirement is satisfied by computing the accumulated dose commitment to the most exposed organ and to the.
total body of a hypothetical person exposed by eating fish and drinking water taken from Lake Erie.
The dose contribution from all radionuclides identified in liquid effluents released to unrestricted areas is calculated using the following expressions:
1 4
D = IA.I I At C.
F I
l f
- i
- p=1 (1-8)
{
where:
D
= dose or dose commitment to organ I, including total body (mrem).
7 A
_y + U BF DF, the site-related ingestion dose commitment g7,g D,
F 1
i factor from radionuclide i (from Table 3) in mrem /hr pCi/ml th Atg = length of the A time period over which C and F are averaged gg g
for all liquid releases, in hours.
i t
8 i
i DAVIS-BESSE, UNIT I 1.0-10 r
Cit =
average concentration of radionuclide i observed in undiluted liquid effluent during time period At from any liquid g
release, in pCi/ml.
Concentrations are detarmined primarily from a gamma isotopic analysis of a liquid effluent sample.
For Fe-55, Sr-89, Sr-90, and H-3, the last measured value will be used in dose calculations.
near-field average dilution factor for C during any liquid F
=
g f
effluent release.
Defined as the ratio of the average undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times the near-field dilution factor of 10 times the collection box factor of 1.0 (Ref. 2).
average undiluted liquid waste flow F
=
g average flow from the site discharge x 10 x 1.0 units conversion factor 1.14 x 103 K
=
3 N
+ 8,760 5)
(10s pCi 10 pCi liter yr U,
adult water consumption (730 liters /yr) (Ref. 3)
=
dilution factor from the near-field area within one-quarter D
=
mile of the release point to the potable water intake for adult water consumption.
D is (57/(10 x 1.0)) = 5.7, where 57 = lowest dilution factor corresponding to beach wells located approximately 0.6 miles NW of the discharge point (Ref. 2).
The near-field dilution factor of 10, represents the mixing effect of the discharge structure (Ref. 2).
DAVIS-BESSE, UNIT 1 1.0-11
adult fish consumption (21 kg/yr) (Ref. 3).
U
=
p bioaccumulation factor for nuclide, i, in fish, in pCi/kg BF
=
g per pCi/ liter from Table 1 (taken from reference 3, Table A-1).
a dose conversion factor for nuclide, i, for adults in DF
=
g preselected organ, I, in mrem /pC1, from Table 2 (taken from reference 3, Table E-11).
1.3 Projected Personal Maximum Dose The dose commitment to a person offsite due to radioactive material released in liquid effluent may be projected by cal-culating the extrapolated total body and most exposed organ dose commitments to a hypothetical person exposed by eating fish and drinking water.
The potential dose' commitments to organs and to the total body are computed separately.
The dose commitment to a maximally exposed hypothetical person will be projected by calculating the doses accumulated during the most recent three months according to the method described in Section 1.2 and by assuming that the result represents the projected doses during the current quarter.
Alternatively, the quarterly dose commitment may be projected by using the equation:
P = 91 D (1-11) 7 X
where:
projected dose commitment (mrem) to organ I (including P
=
7 total body) for the current quarter number of days in a quarter 91
=
DAVIS-BESSE, UNIT 1 1.0-12
1 1
number of days to date in current quarter X
=
accumulated personal dose to data during the current D
=
quarter via radioactive material in liquid effluent (mrem).
l l
l i
5 l
l l
l i
k i
i DAVIS-BESSE, UNIT 1 1.0-13 i
REFERENCES TO 1.0 LIQUID EITLUENTS 1.
J.S. Boegli, W.L. Britz, R.R. Bellamy, and R.L. Waterfield.
1978.
" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133, Office of Nuclear Reactor Regula-tion, U.S. Nuclear Regulatory Commission.
2.
D.W. McDougall.
1980.
" Aquatic Dilution Factors within 50 miles of the Davis-Besse Unit 1 Nuclear Power Plant." Stone & Webster Engineer-ing Corporation.
3.
United States Nuclear Regulatory Commission.
1977.
" Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Regulatory Guide 1.109, Revision 1.
i l
DAVIS-BESSE, UNIT 1 1.0-14
2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints 2.1.1 Station Vent Monitor The station vent is the only normal radioactive gaseous release point.
For the purpose of implementation of section 3.3.3.10 of the RETS, the alarr, setpoint level for the station vent noble gas monitor will be calculated as follows:
0.5 x R' x 500 the lesser of J or (2-1) i S
=
V I 0.5 x R x 3000 I,
s where:
count rate of station vent noble gas monitor at S
=
y alarm setpoint level safety factor allowing 100% margin for cumulative 0.5 =
uncertainties of measurements c unt rate per mrem /yr to the total body R
=
t l
R, count rate per mrem /yr to the skin.
=
The values of R and R, are dependent on the radionuclide distribution and are derived by the equations:
R C
[ X/Q l K. (Q )]
(2-2) i i
t g
DAVIS-BESSE, UNIT 1 2.0-1 1
R, C + [ X/Q x I (Li+ 1.1M)k]
(2-3)
=
t i
1 where:
C
=
count rate of the station vent monitor correspond-ing to grab sample radionuclide concentrations (cpm)
X/Q highest sector annual average atmospheric disper-
=
sion at the unrestricted area boundary 4.63 x 10-s sec/m in the north sector 3
=
K
=
total body dose factor due to gamma emissions g
3 from isotope i (mrem /yr per pCi/m ) from Table 4.
6 rate of release of each noble gas radionuclide i
=
1 identified by the sampling and analysis per RETS Table 4.11-2 (pCi/sec).
L
=
skin dose factor due to beta emissions from i
3 isotope i (mrem /yr per pCi/m ) from Table 4 1.1 =
mrem skin dose per mrad air dose M
=
air dose factor due to gamma emissions from g
3 isotope i (mrad /yr per pCi/m ) from Table 4 A more conservative setpoint may be calculated to minimize requirements for adjustment of the monitor by using the equations:
DAVIS-BESSE, UNIT 1 2.0-2
R' = C' + [X/Q x K]
(2-4)
R' = C'
[X/Q x (L + 1.1M)]
(2-5) where:
R' conservative count rate per arem/yr to the total
=
body (Xe-133 detection, Kr-89 dose) conservative count rate per mres/yr to the skin R'
=
(Xe-133 detection, Kr-89 dose)
C'
=
count rate of station vent monitor for an effluent concentration of Xe-133 corresponding to 1.0 pCi/sec release rate of Xe-133 total body dose factor for Kr-89, from Table 4 K
=
skin dose factor for Kr-89, from Table 4 L
=
air dose factor for Kr-89, from Table 4 M
=
2.1.2 Waste Gas Decay System and Containment Purge Monitors The waste gas decay tank releases and containment purges, in addition to being monitored by the station vent monitor, are controlled individually to provide additional assurance that releases do not exceed the limits of Technical Specifi-cations 3.11.2.1.
The setpoint level (S ) f r discharge through the waste gas d
decay system monitor will be calculated in a corresponding manner:
/.5 x r x 500 0
t the lesser ofi or (2-6)
S
=
d 0.5 x r, x 3000 DAVIS-BESSE, UNIT 1 2.0-3
where:
S
=
count rate of waste gas decay system monitor at d
alarm setpoint level count rate per mrem /yr to the total body r
=
g c unt rate per mrem /yr to the skin r
=
s The values of r and r, are dependent on the radionuclide g
distribution and are derived by the equations:
k]
(2-7)
[X/Qx{Ki r
=
c i
t 1
=
c
[ X/Q x I (L + l lM() qi]
(2-8) r, i
i where:
count rate of the waste gas decay system monitor c
=
for radionuclide concentrations to be discharged qi rate of release of noble gas radionuclide i
=
(pCi/sec)
For a more conservative, simpler setpoint for the waste gas system monitor, the equations are:
r' = c' + [X/Q x K]
(2-9) r' = c' + [X/Q x (L + 1.1M)]
(2-10) s DAVIS-BESSE, UNIT 1 2.0-4
where:
c'
=
conservative count rate per mrem to the total body (Xe-133 detection, Kr-89 dose) r' conservative count rate per mrem to the skin
=
(Xe-133 detection, Kr-89 dose) c'
=
count rate of the waste gas deczy system monitor for an effluent concentration corresponding to 1.0 pCi/sec release rate for Xe-133 The setpoint level for the containment purge noble gas monitor will be calculated using the same methodology as indicated for the waste gas decay system, utilizing the appropriate corresponding count.and release rates.
The calculated setpoint values will be regarded as upper bounds for the actual setpoint adjustments (ie, setpoint adjustments are not required to be performed if the existing setpoint level corresponds to a lower count rate than the calculated value).
2.2 Gaseous Effluent Dose Rate and Dose Calculations 2.2.1 Unrestricted Area Boundary Dose Rate a.
Technical Specification 3.11.2.la limits the dose rate in the unrestricted area due to noble gas releases from the station to 5500 mrem /yr, total body and $3000 mrem /yr, skin. Radiation monitor ala'rm setpoints are established to assure that these release limits are not exceeded.
In the event any gaseous releases from the station results in the alarm setpoints being ex-ceeded, an evaluation of the unrestricted area dose rate resulting from the release shall be performed using the following equations:
DAVIS-BESSE, UNIT 1 2.0-5
X/Q I K h (2-11)
D
=
tb i i 1
X/QI(L.+1.1M.)6 (2-12)
'~
D
=
s 1
1 1
where:
total body dose rate (mrem /yr)
D
=
tb D,
skin dose rate (arem/yr)
=
X/Q highest sector annual average atmospheric
=
dispersion at the unrestricted area boundary 3
4.63x10-5 sec/m in the north sector.
=
b.
For I-131 and particulates with half-lives greater than 8 days, Technical Specification 3.11.2.1.b limits the dose rate to <1500 mrem /yr to any organ. To demonstrate compliance with this limit, an evaluation is performed at a frequency corresponding to the sampling and analysis time period (eg, normally once per 7 days for I-131). The following equation may be used for evaluation:
W I (P. Q'i)
(2-13)
D
=
o 1
g where:
D, average organ dose rate over the sampling
=
time period (mrem / year)
DAVIS-BESSE, UNIT 1 2.0-6
controlling sector annual average atmospheric W
=
dispersion at the site boundary for the inhalation pathway.
3 X/Q for inhalation = 4.63 x 10-s sec/m in
=
the north sector dose parameter for radionuclide i, (mrem /yr P
=
g 3
per pCi/m ) for inhalation pathway from Table 5.
Values for P are derived in g
accordance with the methods described in NUREG 0133 Q'f average release rate over the appropriate
=
sampling period and analysis frequency for isotope i, I-131 or other radionuclide in particulate form with half-life greater than eight days (pCi/sec).
By substituting 1500 mrem /yr for D, (equation 2-13) and solving for 7, an allowable release rate for I-131 can be determined.
Based on the annual average meteorological dispersion (4.63 x 10-s 3
sec/m ) and the child inhalation pathway (Pg = 1.62 x 3
107 mrem /yr per pCi/m ), the release rate for I-131 is 1.6 pCi/sec.
An added conservatism factor of 0.8 has been included in this calculation to account for any potential dose con-tribution from other radioactive particulate material. For a 7 day period which is the sampling and analysis frequency l
for I-131, the cumulative allowable release is 0.97 Ci.
t l
Therefore, as long as the I-131 releases in any 7 day period l
do not exceed 0.97 Ci, no additional analyses are needed to verify compliance with the Technical Specification 3.11.2.1.b limits on allowable release rate.
l DAVIS-BESSE, UNIT 1 2.0-7
2.2.2
. Unrestricted Area Dose to Individtal a.
Technical specification 4.11.2.2 requires at least a monthly assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of 15 mrad, gamma-air dose and $10 mrad, beta-air dose.
The following equations may be used to calculate the gamma-air and beta-air doses:
3.17 x 10-8 3.[X/Q'
]
(2-14)
D
=
Y 1
t 3.17 x 10-8 IN [X/Q'Q ]
(2-15)
D
=
g g
i I
where:
D
=
air dose due to gamma emissions for noble gas radionuclide i (mrad)
X/Q' =
dispersion parameter for unrestricted areas 1.20 x 10-s sec/m3
=
cumulative release of noble gas radionuclide Q
=
1 i over the period of interest (pCi)
D
=
air dose due to beta emissions from noble g
gas radionuclide 1 (mrad)
N
=
air dose factor due to beta emissions from g
noble gas radionuclide i (mrad /yr per 3
pCi/m ) from Table 4.
3.17x10-8 =
conversion factor (yr/sec)
DAVIS-BESSE, UNIT 1 2.0-8
b.
Technical Specification 4.11.2.3 requires an assess-ment at least once per 31 days to evaluate compliance with the quarterly dose limit of <7.5 mrem to any organ. The following equation may be used to evaluate the maximum organ dose due to releases of I-131 and particulates with half-lives greater than 8 days.
3.17 x 10-8 I R.(W'Q'f)
(2-16)
D
=
P 1
i where:
D
=
dose or dose commitment to organ p, includ-p ing the total body, from I-131 and radio-nuclides in particulate form with half-life greater than eight days (mrem)
W'
=
dispersion parameter for unrestricted areas for long-term releases (X/Q'=
1.20 x 10-s sec/m for inhalation 3
pathway and H-3 dose contribution via other pathways D/Q' =
2.10 x 10-7 m vegetation path-
-2
(
way dose factor for radionuclide i, (mrem /yr per R
=
g pCi/m ) or (m2 - mrem /hr per pCi/sec) from 3
Table 6.
Values for R were derived in g
accordance with the methods described in NUREG 0133.
f DAVIS-BESSE, UNIT 1 2.0-9
Q'1 cumulative release of radionuclide i of
^
=
I-131 or material in particulate form in long-term releases over the period of interest (pCi).
The location of exposure pathways and the maximum organ dose may be based on the available pathways in the sur-rounding environment of Davis-Besse as identified by the annual land-use census (Technical Specification 3.12.2).
Table 7 will be supplemented yearly by including in the Semi-Annual Radioactive Effluent Report the applicable exposure pathways as identified by the census.
Otherwise, the dose will be evaluated based on the predetermined controlling pathways of inhalation (0.6 mile, W) and vegetation (0.7 mile, WSW) by using the historical meteoro-logical dispersion parameter of 1.20 x 10-s sec/m and 3
deposition parameter of 2.10 x 10-7
-2, respectively.
m c.
For the purpose of implementing RETS Technical Spec-ification 3.11.3 on the EPA environmental radiation dose standard and 6.9.1.13 on reporting, dose cal-culations will be performed using the above equations with the substitution of average or actual meteoro-logical parameters for the period of interest and applicable pathways.
2.3 Meteorological Model 2.3.1 Long-Term Atmospheric Dispersion Atmospheric dispersion for long-term releases is calculated using a mixed-mode, wake-split form of the straight line flow model.
DAVIS-BESSE, UNIT 1 2.0-10
3 X/Q =
atmospheric dispersion (sec/m )
h2)+ E (2-17) 2.03 k6 1-E eXP ( 337 ua uI r
8_
where:
k
=
open terrain recirculation factor at distance r from Figure 2.
l 6
=
plume depletion factor at distance r for appro-priate stability class and effective height from Figures 3-6.
E
=
fraction considered as ground level v 11.0 1.0 for 2.58-1.58 y for 1.0< v $1.5 u
u 0.3-0.06 v for 1.5< v
<5.0 u
u
{
>5.0 0
for station vent exit velocity (m/sec) v
=
wind speed at vent height (m/sec) (75m) u
=
wind speed at ground level (m/sec)(10m) u
=
8 vertical standard deviation of the plume at a
=
distance r for effective height under stability category indicated by i (m) from Figure 7.
DAVIS-BESSE, UNIT 1 2.0-11
i temperature differential with vertical separation
=
(*K/100m) h
=
effective height of release (m)
=
h
+h
-h v
pr t
h
=
height of station vent y
=
75.3m b
=
additional height due to plume rise (m) pr 2/3 1/3 the lesser of 1.44 v d
-c
=
y or 3 vd u
subject to, for stable conditions (i > - 0.5 *K/100m):
h
<4
'Fai k l
pr
,S,
and i/3 h
- 1.5 Fm 1/s pr -
g 1
3.
d
=
diameter of station vent
=
2.12 m DAVIS-BESSE, UNIT 1 2.0-12
correction for low vent exit velocity (m) c
=
y g
3 1.5 - v d for v 5 1.5 l
=
d
=
I f0 for v < 1.5
(
u 4
2 F,
momentum flax parameter (m /sec )
=
( )
=
S
=
restoring acceleration per unit vertical displace-ment for adiabatic motion in the atmosphe e 8.7 x 10-4 sec for i 5 1.5
-2 1.75 x 10-3 sec for i 5 4.0
-2 2.45 x 10-3 sec for i > 4.0
-2 height of terrain at distance r in sector of h
=
g interest (m) l downwind distance (m) r
=
I
=
vertical standard deviation of the plume with building wake correction (m)
(-
b2 g
z+3
=
the lesser of lo j
or h0 I-l k
l DAVIS-BESSE, UNIT 1 2.0-13
b
=
height of reactor building
=
73.5m 2.3.2 Long Term Deposition Relative deposition per unit area for long term releases is calculated for a mixed mode release.
relative deposition per unit area (m-2)
D/Q
=
=
2.55k (1-E) D + ED (2-18)
I r
where:
D, relative deposition rate for elevated-releases
=
from Figures 9 through 11.
relative deposition rate for ground level releases D
=
g from Figure 8.
2.5 Definitions of Gaseous Effluents Parameters height of reactor building (2.3.1) b
=
count rate of the station vent monitor corresponding to C
=
grab sample radionuclide concentrations (2.1.1) l l
C'
=
count rate of station vent monitor corresponding to a 1.0 l
pCi/sec release rate of Xe-133 (2.1.1) count rate of the waste gas decay system monitor for c
=
radionuclide concentrations to be discharged (2.1.2)
DAVIS-BESSE, UNIT 1 2.0-14
J t
c'
=
count rate of the waste gas decay system monitor correspond-ing to a 1.0 pCi/sec release rate of Xc-133 (2.1.2) correction for lov vent exit velocity (m) (2.3.1) c
=
y
- t D,
relative deposition rate-for elevated releases from Figure
=
6 (2.3.2)
D
=
relative deposition rate for ground level releases from 8
Figure 7 (2.3.2) a average organ dose rate (mrem / year) (2.2.1.b)
D
=
g 3
dose or dose commitment to organ p, includin'g the total D
=
P body, from I-131 and radionuclides in particulate form, with half-life greater than eight days (mrem) (2.2.2.b) e D,
average skin dose rate (arem/ year)'(2.2.1.a)
=
average total body dose rate (aree/ year) (2.2.1.a),
D
=
tb D
=
air dose due to beta emissions from noble gas radionuclide -
p i (arad) (2.2.2.a)
D
=
air dose due to gamma emissions from noble gas radionuclide i (mrad) (2.2.2.a) relative deposition per unit area (m-2) (2.3.2)
D/Q
=
d
=
diameter of station vent (2.3.1) l 6
=
plume depletion factor at distance r for appropriate l
l stability class and effective height from Figures 3 and 4 l
(2.3.1) l i
l DAVIS-BESSE, UNIT 1 2.0-15
c pi
,4 c
!s "
C 3
Jit ;.-
E,.
fraction of release considered as ground level (2.3.1)
=
y
=
4 2
F, momentum flux parameter (m / cec ) (2.3.1) p.
h
=
effective height of release (m) (2.3.1) h
=
height of terrain at distance r in sector of interest (m)
(2.3.1) h
=
height of station vent (2.3.1) y h
- =
additional height due to plume rise (m) (2.3.1) 95 3
K
=
total body dose factor for Kr-89, (mrem /yr per pCi/m ) from Table 4 (2.1.1)
-v
, K
=
total body dose factor due to gamma emissions from radio-g 3
nuclide (mres/yr per pCi/m ) from Table 4 (2.1.1) k
=
open terrain recirculation factor at distance r from Figure 2 (2.3.1) y L
=
skin dose factor for Kr-89, the most restrictive radio-nuclide, from Table 4 (2.1.1)
- i ~ 'L skin dose factor due to beta emissions from radionuclide 1
=
1 3
(mrem /yr per pCi/m ) from Table 4 (2.1.1)
M
=
air dose factor for Kr-89, the most restrictive radio-nuclide, from Table 4 (2.1.1) i t
DAVIS-BESSE, UNIT 1 2.0-16 4
m
air dose factor due to gamma emissions from radionuclide 1 M
=
g 3
(arad/yr per pCi/m ) from Table 4 (2.1.1) air dose factor due to beta emissions from noble gas radio-N
=
g 3
nuclide 1 (mrad /yr per pCi/m ) from Table 4 (2.2.2.a) 3 dose parameter for radionuclide 1, (mres/yr per pCi/m ) for P
=
g inhalation from Table 5 (2.2.1.b) 6g rate of release of noble gas radionuclide i (pCi/sec)
=
(2.1.1)
Q'g average release rate over appropriate sampling period of
=
isotope i of I-131 or other radionuclide in particulate form, with half-life greater than eight (8) days (pCi/sec) (2.2.1.b) 6 cumulative release of noble gas radionuclide i over
=
g the period of interest (pC1) (2.2.2.a)
$'t
=
cumulative release of radionuclide i of I-131 or material in particulate form over the period of interest (pCi)
(2.2.2.b)
[1g rate of release of noble gas. radionuclide i (pCi/sec)
=
(2.1.2) 3 dose factor for radionuclide i, (mrem /yr per pCi/m ) or R
=
g (m2 - mrem /yr per pCi/sec) from Table 6 (2.2.2.b)
R, count rate per mrem /yr to the skin based on current isotope
=
distribution (2.1.1)
DAVIS-BESSE, UNIT 1 2.0-17
R
=
count rate per mrem /yr to the total body based on current g
isotope distribution (2.1.1)
R',
conservative count rate per mres/yr to the skin (Xe-133
=
detection Kr-89 dose) (2.1.1)
R
=
c nservative c unt rate per mrem /yr to the total body (Xe-133 t
detection, Kr-89 dose) (2.1.1) downwind distance (m) r
=
r, count rate per mrem /yr to the skin based on waste gas decay
=
system isotope distribution (2.1.2) count rate per mrem /yr to the total body based on current r
=
g waste gas decay system isotope distribution (2.1.2)
I r',
ccuservative count rate per mrem to the skin for waste gas
=
decay system only (2.1.2) r'
=
conservative count rate per mrem to the total body for waste gas decay system only (2.1.2)
DAVIS-BESSE, UNIT 1 2.0-18
S
=
restoring acceleration per unit vertical displacement for adiabatic motion in the atmosphere (2.3.1)
S
=
d c unt rate of waste gas decay system noble gas monitor at alarm setpoint level (2.1.2)
S
=
count rate of station vent noble gas monitor at alarm y
setpoint level (2.1.1)
I
=
vertical standard deviation of the plume with building wake correction (m) (2.3.1) i vertical standard deviation of the plume at distance r for o
=
effective height under stability category indicated by i from Figure 5 (m) (2.3.1) i temperature differential with vertical separation (*K/100m)
=
(2.3.1) wind speed at vent height (m/sec) (2.3.1) (75m) u
=
wind speed at ground level (m/sec) (10m) u
=
g plant vent exit velocity (m/sec) (2.3.1) v
=
W
=
controlling sector annual average atmospheric dispersion at l
the site boundary for the appropriate pathway (2.2.1.b) l l
l W'
=
relative concentration for releases to unrestricted areas (2.2.2.b) 3 atmospheric dispersion (sec/m ) (2.3.1)
X/Q
=
DAVIS-BESSE, UNIT 1 2.0-19
highest sector annual average atmospheric dispersion at the X/Q
=
3 unrestricted area boundary (sec/m ) (2.1.1)
X/Q' =
atmospheric dispersion ~for releases to unrestricted areas 8
(sec/m ) (2.2.2)
DAVIS-BESSE, UNIT 1 2.0-20
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING Sampling locations as required in Section 3/4.12.1 of the Radio-logical Effluent Technical Specifications are described in Table 9 and shown on maps in Appendix A, pages A-12 through A-50.
3.1 Land Use Census A land use census shall be conducted annually for the purpose of identifying changes in the use of the offsite area surrounding Davis-Besse which may substantially affect the radiological dose assessment or which may indicate needed adjustments to the Program. This census satisfies the criteria of 10 CFR Part 50, Appendix I, Section IV.B.3.
The census will include land within 5 miles of Davis-Besse and will be conducted at least annually.
It will be conducted by either a door-to-door survey, aerial survey, or by consulting local agricultural authorities or by a combination thereof.
The locations of 1) the nearest milk animal, 2) the nearest vegetable garden, and 3) the nearest resident within 5 miles of Davis-Besse in each of 16 sectors in cardinal directions from the plant are to be identified in the census.
If a milk animal is not identified in a sector within 5 miles, one may be assumed to be located at the 5-mile distance for purposes of evaluating maximum potential organ dose and identifying the controlling pathway except in those sectors over Lake Erie.
If the land use census identifies a location (s) at which the dose or dose commitment calculated at the time is greater than the maximum calculated dose associated with the like pathway (s) at a location where sampling is conducted as specified by the monitoring program, then the pathways having maximum exposure potential at the newly identified location will be added to the DAVIS-BESSE, UNIT 1 3.0-1
Program if samples are reasonably obtainable at the new loca-tion.
Like pathways monitored (sampled) at a location, excluding control station location (s), having a lower associated calcu-lated personal dose may be deleted from the Program at the time the new pathway (s) and location (s) are added.
3.2 Sample Analyses Radioactivity in environmental samples described in Table 9 may be analyzed either at Davis-Besse or at an offsite laboratory.
In order to provide a comparative check on the accuracy and precision of these analyses, the laboratory participates in the USEPA Interlaboratory Comparison Program by analyzing radio-active samples distributed for the purpose.
DAVIS-BESSE, UNIT 1 3.0-2
0 APPENDIX A Figures l
i l
l l
l l
..w n
.-g-~_..,
.a-
.-u
.n-----.
=a..-..
5
- 1 -
l 1
til I e 8 ! sie t
e i ole l 1 s 31:si i t : e e s,l
. i.:-
ll l I I illli i
t illi i l l l l111 I l l illli l l I : l l s_.
. lei.l.
ill
=
Figure 1 Calibration Curve 3
i;iG-for Liquid Effluent Monitors
- ',' l ' l ',j
...lh I i 18 8' e ' 8 (RE 1770 A & B. RE 1878,A & B) i lllll l ll From Victoreen Instruction Manual i I i1Ilid I i Ia!!!'
l for Model l
h..
.ll l
j 10-1
=
1 1
.....a
': 1 I t I t tiff 4
8 8 I i s.fi 4
8 8 i l i f el i t t.....I
. t i *....
lll l t I lill!
l l l lI!ll l' I I l illll i I I lilli ! /l I i ',II:
i
!/
j i l:
l l.
l i.!
,c'.
...o f..
U i illi e 3 e t a t38 8 ? l l t s ll t t 4 I I I e -l l /. I 6 8 I t.l s 3...;,l Illii i i l i !!il i l l "Iill
.I l l i Illil
/ I I I til:1 1 l l:r!!
l 1
j l
j/
[
ji l!
E 1o,3
/
i
.,i 4
g l
s i ni
. : :...i i iii....
./3.....
- : ii..q
[
lI ill i i i !Ill!l i I Il til:
A/l 1111:1 I I I l il!Il i I I liti:
l
/ i*
ll l
j l.i,i!
o i.
I I 10-8 e
M i i t illi l t 843;l 6 / t a I t.
4l t. l I t.:t 8 I e ?... it
. s.
.....l IL illi i i tilliik
/ I l l !!Ill i I i.l lllil i i 111111 1 I I I Hi! '
l.'
l/
I I
il I
I!!!!-
go-5.
i e i,.
,,,,,,,.i lllll
/ l 1 lilli i i l llill i I I t illil i l l !!II:
I I I tiliil l lI/
l
.l l-l li lo-s
. /.
..w.
.s......
l, _,_,
ei.iis i < r :..:.
. i i i..ri e i e i n s i;;
i i. i r.:
i...:
I ll111 1 I lllill l l l llill l
i l1!lli l l l Ilil:
1 I f lili:
j./
i I
l d.I 10-7f 3
10 1o2 103 io4 ros ios 107 COUNTS PER MINUTE DAVIS-BESSE, UNIT 1
~
l E
to
- 5 YM I
Mr' E
4
=1
\\
~
h N e0 U
s e
\\ \\
8 t
P 1*0 u
w L
l ou 1
0.1 0.1 1.0 10 100 DISTANCE lKILOMETERS) 9We 2 Open Terrain Correction Factor l
I
S
- 5
[
1.0 C
N XI N
0.9 N
Ea N
0.8
\\
-o b
N s d
\\
z 0.7 A
b 0.6 6
i TN\\
w E
0.5 A
2
'N 9
\\
D 0.4
\\
E 0.3 0.2 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 3 Plume Depletion Effect for Ground Level Releases (All Atniospheric Stability Classes)
I
o' I
o 2
g r
r 1
i 7 7
e f f F
a Lf f g
1
/
///
y$~ y//=8
/
35 E
r wE 4
o ci $
I r r c
I IJ f
3 II E
11 y
//
z
@ //
//
o W
s}
VI
^~
.s
//
m E
3 m
g e
~
II II II II l
II I
S l
9 l
C 9
M N
9 9
v.
9 N
n e
o o
o o
o o
o o
o 3 Wold NI DNINIYW3B NOl10VUd DAVIS-BESSE, UNIT l A-4 i
l c
P=
- 5
?
m m
1.0 STABLE E,F,G) l c
g h
0.9 h
NEUTRAL su 0.8 K
n.
0.7
\\
3
-UNSTABLE
.g y
.g (A,B,C)
% g g 0.6
\\
u 3
s b
y 0.5 N
s 6
N b 0.4
\\
E 0.3 0.2 0.1 l
l' O.1 1.0 10.0 N
PLUME TRAVEL DISTANCE (KILOMETERS)
Mgure 5 Plume Depletion Effect for 604n Releases (Letters denota Pasquill Stability Class)
g
- 5y 1.0 N
^
NEUTRAL (D) 0.9 9
E
- % s
\\
g 0.8 w
3 UNSTABLE
' O.7 (A,B,C)
N z
b STABLE (E,F,G) h
>5 NO DEPLETION 0.6
\\(
(FRACTION REMAINING = 1.0)
E 0.5 z
3
$ 0.4
(
E 0.3 0.2 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 6 Plume Depletion Ef fect for 100-m Releases (Letters denote Pasquill Stabilip Class)
1000 I
j
~
I J
/
/
/
y'
/
/
i f
r J
l A
/
/
/
/
l l
/
l
/
A 100 j
,/
/
/
/
j
/
/
7 g
_f
-/"
p w
f
,,e
/
r
/
/
/
y-/
C j
f'
/;
/
/
f a
g
/,/ /
/
f/
y
/
f o
g
. /
/
l
/
/
/
/
/ /
f n
/
,/
F
/
Gf 10 J
./
1 1
1 s
s
/
/
j r
r
/
/
/
/
l
/
/
' /
/
/,/
/
1 0.1 1.0 10 100-PLUME TRAVEL DISTANCE (KILOMETERS)
Fig. 7
. Vertscal Standard Deviation of Material in a Plume (Letters denote Pasquill Stability Claed i
1 OAVIS-BESSE, UNIT I A-7 l
l em o e,
..m
104 10-4
\\
s N
e w
( '
>=
(
5 5
N s
=
\\
!E N\\
e
$ 104
%(
p x
E X
k
\\
wQ
\\
\\
P N
3
\\
E
\\
10-6
\\
I 10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 8 Relative Deposition for Ground Level Releases (All Atmospheric Stability Classes)
DAVIS'-BESSE, UNIT 1 A-8
1d t-t'-
.t
+
~
UNSTABLE (h,B.C) f.
104
' ; [,
/
\\
mw 1
x H
/
'k a
w 3
~
'h I
/
[
\\\\
NEUTRAL
/
XN s
s f
N h e
/ NEUTRAL (D) gg 2
h 10-5
/
Q STABLE m
l
,'M o
i
'y x't a.
I
/%
/
/
NY
\\
/
/
NN
\\
m w
/
/
N
' ' ~
a
/
/
N x
s STABLE (E,F,G) 10-6 l
1 l
l I
I I
I f
I J
/
/
10-7 l,
0.1 1.0 10.0 100.0 20 PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 9 Relative Deposition for 30-m Releases (Letters denote Pasquill Stability Clau) l i
DAVIS-BESSE, UNIT I A-9
104 i
e w
UNSTABLE (A,B,C)
[
\\
/
\\
f f
104
/
NEUTRAL (D)
(
r r
-a r
x ew I
I W
g
/
/
NNJ 2
/
\\
N UNSTABLE 5
/
\\
N NEUTRAL N,
\\
B
/
N N
f
\\-
291
^
w x
I J
e l
(
O I
l 5
l P
5 J
=
1, 10-7 STABLE IE.F G)
I I
I I
I I
I I
I I
I l
T 104 0.1 1.0 10.0-100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 10 Relative Deposition for 60e Releases (Letters denote Pasquill Stability Class)
DAVIS-BESSE, UNIT 1 A--10
"104 UNSTABLE (A,B,C) f 3
N \\ NQ 10-5 j
p
/
i Nx
[ NEUTRAL (D)
-E I
NN f
f yg I
/
/
N N
w g
/
/
N N
i
/
/
N N__
x s
n
(
10-8
/
e i
E I
l S
I f
\\
l E
I
[
s
/
/
f 4
Y a
j y
STABLE (E F,G)
NO DEPLETION 10-7 i
I I
/
I
/
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PLUME TRAVEL DISTANCE (KILOMETERS)
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4 APPENDIX B Tables I
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TABLE 1 BI0 ACCUMULATION FACTORS (pCi/kg per pCi/ liter)
FRESHWATER ELEMENT FISH H
9.0E-01 C
4.6E+03 NA 1.0E+02 P
3.0Z+03 CR 2.0E+02 MN 4.0E+02 FE 1.0EM2 CO 5.0E+01 NI 1.0E+02 CU 5.0E401 ZN 2.0E+03 BR 4.2E+02 RB 2.0E+03 SR 3.0E+01 Y
2.5E+01 ZR 3.3E+00 NB 3.0E+04 MO 1.0E+01 TC 1.5E+01 RU l.0E+01 RH 1.0E+01 TE 4.0E+02 I
1.5E+01 CS 2.0E+03 l
BA 4.0E+00 I
LA 2.5E+01 CE 1.0E+00 PR 2.5E+01 ND 2.5E+01 W
l.2E+03 NP 1.0E+01
- Values in this Table are taken from Regulatory Guide 1.109 l
except for Phosphorus which is taken from NUREG/CR-1336.
I DAVIS-BESSE, UNIT 1 B-1
Table 2 INGE5 f t0?4 DOSE F ACTORS FOR 40utr$
I" REM PE4 *CI INGESTED) riuCL I L E 80NE L!vEn T.800Y THYR 0!O K!DNEY LUNG GI-LLI H
3 NO DATA 1.05E-07
- 1. 05 E-0 7 1.05i-07 1.056-07 1.05E-07 1.05E-07 C 14 2.94E-06 5.68E-07
- 5. 6 8 E-0 7 5.68E-07 5.685-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06
- 1. 70 E-0 6 1.T0E-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.9JE-04 1.20E-05
- 7. 46 E-0 6 NO DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA
- 2. 6e E-0 9 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.575-06 9 72E-0 7 NO DATA 1.36E-06 No DATA 1.40E-05 MN 56
.No CATA 1.150-07 2.045-08 No DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06
- 1. 6 7 E-0 6 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14F-06
- 4. 72 C-0 6 No DATA NO DATA NO DATA 4.02E-05 91 63 1.30E-04 4.01E-06 6.36E-06 NO DATA NO DATA NO DATA 1 88E-06 NI 65 5.2SE-07 6.86E-08 3.13 E-0 8 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.335-08 3.91E-06 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 o. 9e E-0 6 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08
- 1. 3 7 E -0 9 No DATA 1.28E-08 NC OATA 2.96E-09 84 83
'40 D A T A NO DATA
- 4. 02 E-0 8 No DATA NO DATA NO DATA 5.79E-08 BR 54 NO DATA NO DATA
- 5. 21 E -0 8 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14 E -0 9 NO DATA NO DATA NO DATA LT E-24 R8 86 NO DATA 2.115-05
- 9. 8 3 E-0 6 No DATA NO DATA NO DATA 4.16E-06 48 88 NO DATA 6.055-08
- 1. 21 E-0 8 NO DATA NO DATA NO DATA 8.36E-19 45 89 NO OATA 4.015-08
- 2. 8 2 E-0 8 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA
- 8. 8 4 E-0 6 NO DATA NO DATA NO DATA - 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NC CATA NC DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 90 CATA NC DATA NO DATA 2 70E-05 SR 92 2.15E-06 NO DATA 9 30E-09 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO OATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.*12-0.7 NO DATA 3.775-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1 48E-05 DAVIS-BESSE, UNIT 1 B-2
. Table 2 Continued INGESTION 005E F ACT005 FC3 ACULTS IMREM PE4 #CI INGESTEDI NUCLICE SONE LIVER T.50CY THYR 0!C
<!ONEY LUNG GI-(L!
Y 93 2.68E-01 No DATA 7.4 l-11 NO DATA NO DATA NO CATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO CATA 1.53E-08 NO CATA 3.09E-05 IR 97 1.68E-09 3.392-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 98 95 6.22E-09 3.66E-09 1.862-09 NO CATA 3.42E-09 NO DATA 2.10E-05 MO 19 NO DATA 4.31E-06 8.2 0E-0 7 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 19M 2.47E-10 6.985-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC101 2.54E-10 3 66E-10
- 7. 9 7 E -0 8 NO DATA 7.06E-07 NO DATA 2 16E-05 RU10$
1.54E-08 NU CATA
- 6. 08 E-0 9 NO DATA 1.99E-07 NO DATA 9.42E-06 1U106 2.75E-06 NO CATA
- 8. 79 E-0 8 NO QATA 2 91E-07 NO DATA 6.04E-05 TE125M 2.61E-06 9.71E-07
- 3. 59 E-0 7 8.06E-07 1.09E-05 NO CATA 1.07E-05 TE127" 6.77E-06 2.42E-06
- 8. 2 5 E-0 7 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08
- 2. 3 8 E-0 8 8.15E-08 4.48E-07 NO OtfA 8.68E-06 TE129" 1.15E-05 4.29E-00
- 1. a 25-0 6 3.952-06 4.80E-05 NC CATA 5.79E-05 TE129 3 14E-08 1.18E-08
- 6. 22 E-0 9 1.62E-08 3.63E-08 NO CATA 2.79E-09 TE132 2.52E-06 1.63E-06
- 1. 53 E-0 6 1.80E-06 1.57E-05 NO DATA 7.71E-05 t 130 7.56E-07 2.23E-06
- 8. 80 E-0 7 1.89E-04 3.48E-06 NO DATA 1.92E-06 t 131 4 16E-06 5.95E-06
- 3. 41 E-0 6 1.15E-03 1.02E-05 NO DATA 1.57E-06 1 132 2 03E-07 5.43E-07
- 7. 5 3 E-0 7 3.63E-04 4.31E-06 NO DATA 2.22E-06
! 134 1.06E-07 2.88E-07
- 1. 03 E-0 7 4.99E-06 4.58E-07 NO CATA 2.51E-10
! 135 4.43E-07 1.16E-06 4.2 SE-0 7 7.65E-05 1.96E-06 NO CATA 1 31E-06 C5134 6.22E-05 1.68E-04
- 1. 21 E -0 4 NO DATA 4.79E-05 1.59E-05 2.!9E-06 C5136 6.51E-06 2.57E-05
- 5. 40 E-0 8 NO DATA 8.01E-08 7.91E-09 4.65E-13 8A139 9.70E-08 6.11E-11
- 2. 84 E-0 9 NO DATA 6.46E-11 3.92E-11 1.72E-07 DAVIS-BESSE. UNIT 1 B-3
Table 2 Continued INGESTION 00$E FACTOR $ FCA AOULTS
(" REM P CR PC1 INCESTE01 10CLicE SONE LIVER T.80CY THYRO 10 (10NEY LUNG G1-LL!
3A160 2.03C-05 2.555-08 1 3 3 E-0 6
'40 D A T A 8.6Tk-09 1.46E-08 4.1SE-05 RA141 4.71E-08 1.$6E-11 1.59E-09 NO DATA 3.312-11 2.02E-11 2.22E-17 9A142 2 13!-08 2.19 E-11 1 3*k-0 9 30 OATA 1.35E-11 1.24E-11 1.00E-26 L4160 2.bOC-09 1.262-09 J.33E-10 NU OATA NC OATA NO DATA 9.25E-05 LA142 1.28E-10 5.82E-11 1 45E-11 NO DATA NC OATA NO DATA 4.25E-07
- E141 9.36E-09 6.33E-09 7.19E-10 NO DATA 2.94E-09 NO DATA 2.62E-05 0E143 1.e5E-09 1.228-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE144 4.48E-07 2.04E-07 2 62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04
- A143 9.20E-09 3.692-09 4 56c-10 NO DATA 2.13E-09 NO DATA 4.03E-05 92144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 N0147 6.29E-09 7.275-09 4.35E-10 NO DATA 6.25E-09 NO DATA 3.49E-05 w 197 1.032-07 8.612-08 3 01E-08 NO DATA NO DATA NO CATA 2.825-05 49239 1.19E-09 1.17C-10 6.455-1,1 NO DATA 3.65E-10 NO OATA 2.40E-05 DAVIS-BESSE, Unit 1 B-4
TABLE 3 SITE RELATED INGESTION DOSE COMMITMENT FACTOR g, in mrem /hr per pCi/mi A
Page 1 of 2
~"~
NUCL1Di SONE L1VER TSODY '
THYR 010~
K!DNEY LONG 01'-LLI a-3 0.00E-01 1.7eE+00 1.7eE+00
. 1.7eE+00 1.7eE+00 1.7eE+00 1.7eE+00 C-14 3 13E+04 6.2eE+03 4.2eE+03 e.2eE+03 4.2eE+03 4.2eE+03 4.2eE+03 NA-24 4.32E+02 4.32E+02 4 32E+02 4.32E+02 4.32E+02 4.32E+02 4.32E+02 CR-51 0.00E-01 0.00E-01 1 31E+00
.7.85E-01 2.89E-01 1.77E+00 3.30E+02 MN-54 0.00E-01 4.44E+03 9.48E+02 0.00E-01 1.32E+03 0.00E-01 1.34E+04 MN-Se.
0.00E-01 1 12E+02 1 99Et01 0.00E-01 1 42E+02 0 00E-01'
~ 3.57E+03 FE-55 e.9st+02 4.83E+02 1.13E+02 0 00E-01 0.00E-01 2.49E+02
. 2 77E+02 FE-59 1 10E+03 2.59E+03 9.93E+02 0.00E-01 0.00E-01 7.24E+02 8.44E+03 CD-Se 0 00E-01 1.00E+02 2.24E+02 0 00E-01 0.00E-01 0.00E-01'
~2.03E+03 CO-40 0.00E-01 2.87E+02 a.34E+02
.0.00E-01.
0.00E-01 0.00E-01... 5.40C+03 N1-59 2.48E+03 8.51E+02 4 14E+02 0 00E-01 0.00E-01 0 00E-01 1.75E+02
~
^
N1-4J 3 30E+04 2 29E+03 1.11Et03 0.00E-01'
'O.00C-01 0.00E-01
4.79E+02 N1-65 1.34E+02 1.74E+01 7.95E+00 0 00E-01 0.00E-01 0.00E-01.. 4.42Et02 CU-64 0.00E-01 1 12E+01 5.25E+00 0 00E-01 2.82E+01 0.00E-01 9.54E+02 ZN-65 2.32E+04 7.40E+04 3 34E+04
" O.00E-01 "4.95E+04~
'O.00E-01
' "4.44E+04~
~
9R-84 0.00E-01 0.00E-01 5.31E+01 0 0GE-01 0.00E-01 0.00E-01.
.4 17E-04 RS-80 0.00E-01 2.91E+02 1.54E+02 0.00E-01 0.00E-01 0.00E-01 4.01E-09 RS-89 0.00E-01 1 93E+02 1.35E+02 0.00E-01' O.00E-01 0.00E-01 1 12E-11
~
SR-89 2.eeE+04 0 00E-01 7.44E+02 0.00E-01 0.00E-01 0.00E-01 4.27E+C3 SR-90 e.5:E+05 0.00E-01 1 61E+05 0.00E-01 0.00E-01 0 00E-01 1 99E+04 SR-91 4.90E+02 0.00E-01 1.90E+01 0.00E-01 0.00E-01 0.00E-01 2 33E+03 SR-92 1.SeE+02 0.00E-01 W.04Et00 0.00E-01
. 0 00E-01 0.00E-01 3.eaE+03 Y-90 7.1eE-01 0.00E-01 1.92E-02 0 00E-01 0 00E-01 0.00E-01 7.59E+03 Y91M 4.77E-03 0.00E-01 2.e:E-04 0.00E-01 0.00E-01 0.00E-01 1.99E-02 Y-91 1.05E+01 0 00E-01 2 91E-01 0.00E-01 0.00E-01 0.00E-01 5.79E+03 Y-92 4.29E-02 0.00E-01 1 94E-03 0.00E-01 0.00E-01 0.00E-01 1.10E+03 2R-95 6.84E-01 2.19E-01 1 49E-01 0.00E-01 3.44E-01 0.00E-01 e.95E+02 ZR-97 3.79E-02 7.43E-03 3 49E-03 0.00E-01 1 15E-02 0.00E-01 2.3eE+03 NS-95 4.47E+02 2.49E+02 1.34E+02 0 00E-01 2.4eE+02 0.00E-01 1.51E+0e 0.00E-01 0.00E-01 0.00E-01 0.00E-01 2.8?E+03 NS-97 0.00E-01 0 00E-01 MO-99 0.00E-01 1.e4E+02 3 1eE+01 0.00E-01 3.77E+02 0.00E-01 3.85E+02 i
DAVIS-BESSE, UNIT 1 B-5
TABLE 3 SITE REI.ATED INGESTION i
DOSE COMMITMENT FACTOR i
Ag, in mrem /hr per pC1/ml i
Page 2 of 2 TC99M 1 25E-02 3 53E-02 4.49E-01 0 00E-04 5 35E=01 1 73E-02 2 09EM1 Au=&O3 7.13E900 0.00E-01 3 07E+00 0.00E-01 2 72Et01 0.00E-01
' 8.32Et02#
Atk&oe 4 06Et02 0.005-04 4.34EM4 0 005-04 2.03EM2 0.005-04.-.
4.SeE*03 A0&&en 3 22EMO 2.90E900 1 77Et00 0 00E-04 5.esEMO 0.005-0&
1 215903 C0&&SM 0.004-01 9 00EM2 2 47EM1 0.00E-01 7.20Et02 0.00C=0&
3.825t04 84=&24 4.78E+e&
S.50E-01 1 89E+03 0.00E-01 0.00E-01 3.70EM&
4 35EM3 7E-132 2 45E903 1 50E903 1 49EM3 1 75Et03 1.53EM4 0.00E-01 7.50E+04 4-134 2.10E+02 3.0&Et02 1.72EM2 9.05E904 5 15E.t02 0 00E-01 7 93EM1 1-132 1.03E+01 2.74EM1 9 40EMG 9 40Et02 4.37EM&..
0.00E-01 5.15EMO
&=1U
.,7.17Et04 1 25E+02 3.80Et01 1 83Et04 2 18Et02 0 00E-04 1.12E+02 1;&J4 5.35Et00 1.45E+01 5 20Et00 2.52EM2 2.3&Et04 0.00E-08 5 27E-02 1-135 2.24Et01 5.GeEt01 2.&eE908 3.865t03.. 9.39Et01 0.00E 01 4.42E901 CS-134 2.YvEt03 7.1& EMS 5 815905 0 00E-01 2.30EM5 7.44Et04 1.24Et04 CS-134 3.13E+04 1.23Et03 8.84EM4 0.00E-41 4.87EM4 9.41E+03 1.40Et04 CS-137 3.03Et03 5.23Et03 3.43Et05..
0.00E=01..
-1 78E+05 5.9&Ct04.. 1 0&EM4 CS-13W 2.4LCt02 5.23C+02 2 59E902 0 00E-01 3.85EM2 3 00Et01 2 23C-03 C3-139 1 44Et02 2.40E+02 4 80Et01 0 00E-01 1.92EM2 0 00E-01 0.00E=01 84-1JV 2.35Et00 1.47E 4.87E-02.. 0 00E-01.....&,545-03 9.4es-04
. 4.&egM0 94-140 4.Y&Et02 e.1eE-04 3 225901 0.00E-01 2.10E-01 3.53E-01 1.0&Et03 LA-140 1 04E-01 9.38E 02 2 48E-02 0.00E-01 0.00E-01 0.00E-01 4.09Et03 CC-444 1.LYC=0&
1.0GC-04 4.22E-02 0.00C=0&...
5.00C-02 0.00E-01 4 1&Et02 CE-14J 2.00E-02 2.07Et03 2.295-03 0.00E-01 9.13E=43 0.00E-01 7 75Et02
. ~..
CE-144 8.29CM0 3.47EMO 4.45E-01 0 00E-04 2.0eEMO 0.00E-01 280EM3 PR-144 2.24E-03
'9.34E-04 3.44C-04 0.00E-01...
5.25E*04
- 0 00E-01 3.22E-10 W-187 2.Y7Et02 2.4WEM2 9 49Et04 0 00E-01 0 00E-01 0 00E-01 S.14EM4
~
~
~
U-235 1 5&Et04 0 00E-04 9.42Et02 0."00E-01 3.43E403' O.00E'01 3 5&Et03 *
'~
~
U-238 1.49Et04 0.00E-01 0.02Et02 0 00E-01 3 39Et03 0.00E-01 3 22Ct03 NP=239 4.5WE*02 4 54E-03 2 49C-03 0.00E-01 1.41E-02 0.00C-01 9 25Et02 XE-133, 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0 00E-41 XE133M 0.00E-01 0 00E-01 0.00C-01 0 00C-01 0.00E-01 0.00E-01 0.00E-41 XE-135 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 KASSM 0.00C-05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0 00E-01 CO-57 0.00E*0&
0 00E-0&
0.00E-01 0 00E=0&
0.00E-41 0 00E-01 0.00C-01 SM-113 0.00E-01 0 00E-01 0.00E-41 0.00E-01 0.00E-01 0 00E-01 0 00E-01 St=&25 0.00E-01 0 00E-01 0.00E-01 0 00E-01 0.00E-01 0.00E-01 0.00E-41 P-30 1.39Et04 a.44EM4 5.37Et04 0.c0E-01 0 00E-01 0.00E-01 1.5eEt05 I
DAVIS-BESSE, UNIT 1 B-6 1
TABLE 4 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES Nuclide y-8ody**(K) 8-Skin **(L) y-Air *(M) 6-air *(N)
Kr-85m.
1.17E+03***
1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 T.r-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 t
Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1,92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 f
Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 l
- mrad-m vC1-yr 3
- mrem-m pCi-yr 3
- 1.97E+03 = 1.97 x 10 DAVIS-BESSE, UNIT 1 E-7
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DAVIS-BESSE, UNIT 1 B-8 e
r
4 E
TABLE 5 (CONT) 4 5
i#m PATHWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PARI 20 M
AGE 3 ADULT PATHWAY 1 INHALATIOtt g
N
!!O ISOTOPE W.
BODY THYROID BONE LIVER KIDNEY LONG GI-LLI SKIN CRITICAL 36 ND-95 4.200Et03 0.000E-01 1.400Et04 7.016Ef03 7.736Ef03 5.04UEfv
. 40Et05 4.209Et03 LUNG 37 ND-97 2.040E-02 0.000E-01 2.224E-01 5.624E-02 6.544E-02 2.400Ef03 2.416Et02 0.000E-01 LUNG 30 60-99 2.296El01 0.000E-01 0.000E-01 1.200E+02 2.912E402 9.120Ef04 2.4000605 0.000E-01 G1-LLI 39 TC-99H 3.704E-02 0.020E-01 1.032E-03 2.912C-03 4.416E-02 7.640El02 4.160Et03 0.000E-01 GI-tLI 40 TC-101 5.904E-04 0.000E-01 4.176E-05 6.016E-05 1.000E-03 3.992Et02 1.0 GOC-11 0.000E-01 LONG 41 RU-103 6.504E602 0.OOOE-01 1.520Et03 0.000E-01 5.032E103 5.040EtO5 1.104E405 0.000E-01 LUHG i
42 RU-105 3.112C-01 0.000E-01 7.904E-01 0.000L'-01 1.016Ef00 1.096E104 4.016E604 0.000E-01 GI-LLI 43 l<ti-104 U.720Et03 0.000E-01 6.912E104 0.000E-01 1.336Ef05 9.360E404 9.120Et05 0.000E-01 Lut4G 44 AG-110M 5.944Et03 0.000E-01 1.000EIO4 1.000E404 1.960Et04 1.632Et06 3.024Et05 0.000E-01 LUNG 45 ED-115M 4.360E103 0.000E-01 0.000E-01 1.968E105 1.504E105 1.408El06 3.040Et05 0.000E-01 LUHG 46 SD-124 1.240Et04 7.552E401 3.120E104 5.000Elo2 0.00CE-01 2.400Et06 4.044EIO5 0.000E-01 LilHG g
s 47 TE-125H 4.672E 602 1.010E t03 3.416E t03 1.504Et03 1.240El04 3.136E405 7.044Et04 0.000E-01 LUtl0 8
")
40 1L-127H 1.540Et03 3.200E603 1.264Ef04 5.760E403 4.576Et04 9.600Et05 1.496E105 0.000E-01 LUNG 49 TE-127 3.096E-01 1.056E100 1.400Et00 6.424E-01 5.096Et00 6.512El03 5.736Ef04 0.000E-01 GI-LLI 50 TE-129H 1.501Et03 3.440C103 9.760E603 4.672EiO3 3.656Et04 1.160Et06 3.032El05 0.000E-01 LUNG 51 TE-129 1.240E-02 3.096E-02 4.976E-02 2.392E-02 1.072E-01 1.936Et03 1.56CEt02 0.000E-01 LUNG 52 TE-131H 2.904Ef01 5.501E401 6.992Et01 4.360Et01 3.000Et02 1.456EIO5 5.560El05 0.000E-01 GI-LLI 53 TE-131 3.592E-03 9.360E-03 1.112E-02 5.952E-03 4.360E-02 1.392E103 1.040E101 0.000E-01 LUNG t
54 TE-132 1.616EiO2 1.096E102 2.600El02 2.152Et02 1.45fEt03 2.000EtOS 5.096E105 0.000E-01 GI-LLI b5 I-130 5.200C103 1.136Et06 4.576E103 1.344EiO4 2.00CE404 0.000E-01 7.600El03 0.000E-01 THYR 01D 56 I-131
'2.040Et04 1.192E107 2.520E104 3.574El04 6.1200604 0.000E-01 6.200E103 0.000E-01 TilYROID a
57 I-132 1.140E103 1.144E105 1.160El03 3.256E103 5.104E103 0.000E-01 4.064E602 0.000E-01 TilVROID 50 I-133 4.520El03 2.152Et06 0.640Et03 1.400Et04 2.504Et04 0.000E-01 8.800E103 0.000E-01 TilYRDID 59 I-134 6.152Et02 2.904Ef04 6.440Et02 1.720Et03 2.752El03 0.000E-01 1.008Et00 0.000E-01 THYROID t
60 I-135 2.560Et03 4.400El05 2.600Et03 6.904Et03 1.112E104 0.000E-01 5.240El03 0.000E-01 TilYRUID of CS-134 7.200E105 0.000E-01 3.720Et05 0.400El05 2.072E105 9.760El04 1.010Et04 0.000E-01 LIVER 62 CS-136 1.101El05 0.000E-01 3.904E104 1.464El05 0.560Et04 1.200E104 1.169E104 0.000E-01 LIVER
+
63 CS-137 4.200E105 0.000E-01 4.704El05 6.200E405 2.224E105 7.5200604 0.400E103 0.000E-01 L1VER 64 CS-130 3.240E102 0.0'00E-01 3.312E102 6.200E102 4.000EIO2 4.056EiO1 1.064E-03 0.000E-01 LIVER 65 CS-139 1.112E102 0.000E-01 2.040Ef02 2.904Et02 2.440E102 2.2/2EiO! 0.000E-01 0.000E-01 LIVER s
66 DA-139 2.736E-02 0.000E-01 9.360E-01 6.656E-04 6.224E-04 3.760E103 8.960E102 0.000E-01 Lut!G 67 DA-140 2.540El03 0.000E-01 3.904E104 4.904Et01 1.672Ef01 1.272E106 2.184El05 0.000E-01 LONG 60 DA-141 3.360E-03 0.000E-01 1.000E-01 7.520E-05 7.000E-05 1.936Et03 1.160E-07 0.000E-01 LUHG t
69 DA-142 1.656E-03 0.000E-01 2.632C-02 2.704E-05 2.200E-05 1.192EiO3 1.560E-16 0.000E-01 LONG 70 LA-140 4.504Et01 0.000E-01 3.440Ef02 1.736Ef02 0.000E-01 1.360Ef05 4.504Etob 0.000E-01 GI-LLI J
b
4 g
TABLE 5 (CONT) un 1
PATHWAY DOSE PARANETER FACTORS FOR INPLENENTING 10 CFR PART 20 a
tn AGE 1 ADULT PATHWAY 1 INHALATION g
NO ISOTOPE W. BODY THYROID DONE LIVER KIDNEY LUNO GI-LLI SKIN CRITICAL 71 LA-142 7.720L-02 0.000E-01 6.832E-01 3.104E-01 0.000E-01 6.320Et03 2.112EiO3 7.720E-02 LUNG 72 EE-141 1.5200603 0.000E-01 1.992Ef04 1.352Ef04 6.264Et03 3.616Cf05 1.200Et05 0.000E-01 LUNG 73 CE-143 1.52CEt01 0.000E-01 1.064EiO2 1.376Ef02 6.000Et01 7.974Et04 2.264El05 0.000E-01 OI-LLI 74 EE-144 1.040Et05 0.000E-01 3.432Et06 1.432Et06 0.480El05 7.776Et06 8.160Et05 0.000E-01 LUNG 75 PR-143 4.640E+02 0.000E-01 9.360E103 3.752F103 2.160El03 2.000Ef05 2.000Et05 0.000E-01 LUMG 76 PR-144 1.520E-03 0.000E-01 3.000E-02 1.240E-02 7.048E-03 1.016Et03 2.152E-00 0.000E-01 LUHG 77 ND-147 3.64HE602 0.000E-01 5.272El03 6.096E103 3.560Et03 2.200Et05 1.720Et05 0.000E-01 LUNG 70 W-105 5.440Et01 0.000E-01 1.560Et03 5.176EiO2 0.000E-01 4.456E605 0.560E104 0.000E-01 LUHG 7Y W-107 2.400El00 0.000E-01 U.400Et00 7.000Et00 0.000E-01 2.904Ct04 1.552EtOS 0.000E-01 GI-LLI i
110 U-235 4.0*56Ef06 0.000E-01 8.000Et07 0.000E-01 1.072Ef07 3.920Ct00 3.072Et05 0.000E-01 LUHG y
til U-230 4.536Ef06 0.000E-01 7.464Et07 0.000E-01 1.744Ef07 3.664Et08 8.240EtOS 0.000E-01 LUNG
>d 02 NP-23V 1.240Et01 0.000E-01 2.296Et02 2.256Ef01 7.000Et01 3.760Ef04 1.192E105 0.000E-01 GI-LLI O
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TABLE 5 (CONT)
T N
PATHWAY DOSE PARANETER FACTORS FOR IMPLEMENTING 10 CFR PART 20 l2 tn AGE 1 TEEN l' ATilWAY 1 INHALATION NO ISOTOPE W.
DODY THfROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL r
71 LA-142 1.056E-01 0.000E-01 9.600E-01 4.248E-01 0.000E-01 1.016Et04 1.200Et04 1.056E-01 GI-LLI 72 CE-141 2.160E103 0.000E-01 2.840Ef04 1.896Ef04 0.800E603 6.126Et05 1.264E105 0.000E-01 LONG
(
73 CE-143 2.160E101 0.000E-01 2.654Et02 1.936Et02 8.640Ef01 1.304Et05 2.552Et05 0.000E-01 GI-LLI 74 EC-144 2.624EtO5 0.000E-01 4.080Et06 2.024Ef06 1.200Et06 1.336Et07 0.640Et05 0.000C-01 LUHG i
75 PR-143 4.424Elo2 0.000E-01 1.336E604 5.312Et03 3.000E003 4.032Et05 2.136E605 0.000E-01 LUHG
(
76 Pk-144 2.176E-03 0.000E-01 4.296E-02 1.760E-02 1.000E-02 1.752EiO3 2.352E-04 0.000E-01 LUNG 77 ND-147 5.120Et02 0.000E-01 7.864E603 0.560EiO3 5.024Et03 3.720Et05 1.024Et05 0.000E-01 LUNG 78 W-105 5.440Ct01 0.000E-01 1.560E403 5.176Et02 0.000E-01 4.454E105 0.560Et01 0.000E-01 LUNG
(
79 W-107 3.432EiOO 0.000E-01 1.200Et01 v.760E400 0.000E-01 4.736Et04 1.7602405 0.000E-01 GI-LLI 80 U-235' 4.056E406 0.000E-01 8.000Et07 0.000E-01 1.072E407 3.920Et08 3.072Et05 0.000E-01 LUNG Y
01 U-230 4.536Et06 0.000E-01 7.664E607 0.000E-01 1.744Et07 3.664Et00 0.240EiOS 0.000E-01 LUNG
[j 02 HP-239 1.760E601 0.000E-01 3.384Et02 3.192Et01 1.000E602 6.488Ef04 1.320E+05 0.000E-01 GI-LLI 4.
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DAVIS-BESSE, UNIT 1 B-14 1
0
ts TABLE 5 (CONT)
>c:
un sy PATituoY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 20 u) u)
AGE 1 CHILD PATHuAY 1 INHALATION
(
NO 150TOFE W.
LODY THYROID BONE LIVER KIDHEY LUNG GI-LLI SKIN CRITICAL 4
36 ND-95 6.549E603 0.000E-01 2.350Et04 9.176E103 0.621Et03 6.142E105 3.700Ef04 6.549Et03 LONG 37 HD-97 9.472C-03 0.000E-01 1.029E-01 2.601E-02 3.027E-02 1.110Et03 1.117Et02 0.000E-01 LUNG 30 MO-99 4.255E401 0.000E-01 0.000E-01 1.724E+02 3.Y22Ct02 1.354E405 1.265Et05 0.000E-01 LUNG t
39 1C-99N 5.772E-02 0.000E-01 1.780E-03 3.402E-03 5.069E-02 9.509EiO2 4.010Et03 0.000E-01 G I-Ll_ I 40 TC-101 1.077E-03 0.000E-01 0.103E-05 0.510E-05 1.450E-03 5.044E102 1.632Et01 0.000E-01 LUNG 41 RU-103 1.073Et03 0.000E-01 2.060Et03 0.000E-01 7.030E103 6.623E105 4.477Et04 0.000E-01 LUNG 6
42 nu-105 5.550L-01 0.000E-01 1.520EtOO O.000E-01 1.343Et00 1.591Et04 9.953E401 0.000E-01 GI-tLI 43 RU -106 1.6V1Et04 0.000E-01 1.362E105 0.000E-01 1.039Et05 1.432Et07 4.2920605 0.000E-01 LUNG 44 AG-110N 9.13YEt03 0.000E-01 1.607Et04 1.140Etoi 2.124E104 5.476E404 1.003E105 0.000E-01 LUNG 45 C18-115N 2.942Ef03 0.000E-01 0.000E-01 9.102Et04 7.326E104 6.512Et05 1.776Lt05 0.000E-01 LUNG 08 46 SD-124 5.735Et03 3.493Et01 1.443Ct04 2.723EiO2 0.000E-01 1.147Et06 1.000Et05 0.000E-01 LUHG b
47 1E-125H Y.139Ct02 1.92iE403 6.734Et03 2.327Et03 0.000E-01 4.773E905 3.37CE104 0.000E-01 LUHG 4
u qu IE-12/N 3.027Et03 6.060Et03 2.406Et04 0.547Et03 6.364EiO4 1.400E106 7.141Et04 0.000E-01 LilHO 49 TE-127 6.105E-01 1.961Et00 2.771EtOO 9.50VE-01 7.067E100 1.003Et04 5.621E404 0.000E-01 GI-LLI 50 TE-129M 3.011Et03 6.327Et03 1.920El04 6.045E403 5.032El04 1.761Et06 1.017El0S 0.000E-01 LUNG 51 IE-129 2.303C- 02 7.141E-02 9.760E-02 3. 4V7E-02 2.560E-01 2.934E t 03 2.549E 604 0.000E-01 GI-1LI G2 TE-131H 5.069Et01 v.7600601 1.343EiO2 5.920El01 3.996Et02 2.057E105 3.07uEt05 0.000E-01 GI-LLI 53 TE-131 6.506E-03 1.6?DE-02 2.172E-02 U.436E-03 5.003E-02 2.054El03 1.332Et03 0.000E-01 LilHG 51 1E-132 2.631Et02 3.175EIO2 4.010E102 2.723E602 1.772E103 3.771E605 1.376El05 0.000E-01 LtiHG 55 I-130 0.436Et03 1.016Et06 0.177Et03 1.63?Et04 2.446El04 0.000E-01 5.106El03 0.000E-01 THYNOID 56 I-131 2.727E104 1.621E107 4.010E404 4.010Et04 7.001E404 0.000E-01 2.042E403 0.000E-01 TilYkulD 57 I-132 1.076E603 1.935Ei35 2.116Et03 4.070E403 6.253EiO3 0.000E-01 3.201ElG3 0.009E-01 TitVROID 50 1-133 7.6V6Et03 3.010El06 1.650E104 2.031Et04 3.37CEt04 0.000E-01 5.476Et03 0.000E-01 THYkO11:
59 1-134 9.953Et02 5.06YE104 1.173E103 2.161Et03 3.300Et03 0.000E-01 9.546El02 0.000E-01 TitYkOID 60 1-135 4.141Et03 7.Y18Et05 4.921Et03 0.732E103 1.339Et04 0.000E-01 4.410EIO3 0.000E-01 TilYROID 61 CS-134 2.216E605 0.000E-01 6.512EtO5 1.014Et06 3.304El05 1.210Et05 3.040E603 0.000E-01 LIVER 62 CS -136 1.162Et05 0.000E-01 6.512El04 1.709E405 9.546Et04 1.454Et04 4.101Et03 0.000E-01 LIVER s
63 CS-137 1.284El05 0.000E-01 9.065E405 0.251Et05 2.023EiO5 1.040Et05 3.619Et03 0.000E-01 LONE 64 CS-130 5.550Et02 0.000E-01 6.327E602 0.399EIO2 6.216Et02 6.000Et0! 2.697Ct02 0.000E-01 L1"LR 65 CS-139 5.113El01 0.000E-01 9.472Et01 1.343C402 1.129Ef02 1.051Et01 0.000E-01 0.000E-01 LIVER s
66 DA-137 5.365E-02 0.000E-01 1.II13E t 00 9.012E-04 0.621E-04 5.7720103 5.772E t 04 0.000E-01 GI-LLI 67 bA-140 4.32 vet 03 0.000E-01 7.400El04 6.475El01 2.113El01 1.743Ct06 1.010LiOS 0.000E-01 LUNG 60 DA-141 6.364E-03 0.000E-01 1.957E-01 1.092E-04 9.472E-05 2.919Et03 2.753EiO2 0.000E-01 LUNG i
6V DA-142 2.7VOC-03 0.000E-01 4.995E-02 3.600E-05 2.Y12E-05 1.643Et03 2.742E400 0.000E-01 LilHG 70 LA-140 7.540El01 0.000E-01 6.430E602 2.250Et02 0.000E-01 1.020Ef05 2.257E105 0.000E-01 GI-LL1
)
es TABLE 5 (CONT) k a
m PAfflWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 20 g
AGE 1 CilILD g
PATHWAY 1 INHALATION H
r fl0 ISOTOF E W. DODY THYROID BONE LIVER KIDNEY LUNG-GI-LLI SKIN CRITICAL 11 LA-142 1.291E-01 0.000E-01 1.295Ef00 4.107E-01 0.000E-01 8.695Et03 7.505E604 1.291E-01 GI-LLI 72 CE-141 2.097Et03 0.000E-01 3.922Et04 1.954Ef04 8.547Ef03 5.439Et05 5.661Et04 0.000E-01 LUNG 73 CE-143 2.075Et01 0.000E-01 3.659Et02 1.987E402 8.362Et01 1.154Et05 1.273Et05.0.000E-01 GI-LLI 74 CE-144 3.615Et05 0.000E-01 6.771E106 2.116El06 1.173Et06 1.195Et07 3.835EtOS 0.000E-01 LUHG 75 lR-143 9.139Et02 0.000E-01 1.046E104 5.550Et03 3.001Et03 4.32?Et05 9.731E104 0.000E-01 LuslG 76 PR-144 2.997E-03 0.000E-01 5.957E-02 1.846E-02 9.760E-03 1.565E603 1.968Et02 0.000E-01 LilNG 77 tid-147 6.000Et02 0.000E-01 1.000E404 0.732Ef03 4.810Et03 3.282Et05 0.214Et04 0.000E-01 LilHG 70 W-10S 2.500E t01 0.000E-01 7.215E102 2.471Et 02 0.000E-01 2.061E105 3.955 0 004 0.000E-01 LLittG D8 79 W-107 4.329Ef00 0.000E-01 1.432C101 9.457Et00 0.000C-01 4.107Et04 9.102Et04 0.000E-01 GI-LLI
[.
80 U 235 2.216Ct06 0.000E-01 3.700Et07 0.000E-01 0.65CEf06 1.013E400 1.711Et05 0.000E-01 LUNG Os 01 U-230.
2.OVDEt06 0.000E-01 3.545Et07 0.000E-01 8.066Et06 1.695Et08 3.011Et05 0.000E-01 LUNG 02 HP-239 2.350Et01 0.000E-01 4.662Et02 3.345Et01 9.731E401 5.009Et04 6.4010404 0.000E-01 GI-LLI
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TABLE 5
(CONT)
T
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w!"
PATHWAY DOSE FARANETER FACTORS FOR INPLEMENTING 10 CFR PART 20 h
H AGE 1 INFANT PATHWAY 1 IllHALATION w
tl0 ISOTOPE W. DODY TilVROID BONE LIVER KIDNEY LUNO GI-LLI SKIN CRITICAL 71 LA-142 9.044C-02 0.000E-01 1.030E100 3.766E-01 0.000E-01 8.218Et03 5.950EiO4 9.044E-02 GI-LLI 72 CE-141 1.900El03 0.000E-01 2.772El04 1.666Et04 5.250E803 5.166Et05 2.156Et04 0.OOOE-01 LuttG
/3 EC-143 2.212EiO1 0.000E-01 2.926E102 1.932EiO2 5.642E101 1.142E105 4.970Et04 0.000E-01 LUHG 74 EC-144 1.764Et05 0.000E-01 3.192E406 1.211E406 5.374Et05 9.042El04 1.401E405 0.000E-01 Lut4G 75 F R-143 6.906Et02 0.000E-01 1.400E104 5.235Cf03 1.974EIO3 4.324E105 3.72iEl04 0.000E-01 LUHG 76 PR-144 2.400E-03 0.000E-01 4.700E-02 1.840E-02 4.720E-03 1.610Et03 4.281Cl03 0.000E-01 GI-LLI 77 HD-147 4.9?dE602 0.000E-01 7.93 set 03 8.134Et03 3.150E403 3.220Et05 3.122E104 0.OOOE-01 LUrfG 70 W-105 9.534Et00 0.000E-01 2.730E602 9.059El01 0.000E-01 7.7YdEt04 1.47UEt04 0.000E-01 LutlG 79 u-107 3.122Cl00 0.000E-01 1.296Et01 9.016Et00 0.000L-01 3.962Et04 3.b56E104 0.000E-01 LutlG
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00 U-235 U.490Et05 0.OOOE-01 1.400El07 0.000E-01 3.276El06 6.060EtO7 6.774Et04 0.000E-01 LUNG U1 U-238 7.930El05 0.000E-01 1.341Et07 0.000E-01 3.052E-106 6.412E607 1.412E105 0.000E-01 LUHG d2 tlP-239 1.074Et01 0.000E-01 3.710Et02 3.310E401 6.422E101 5.9500604 2.472El04 0.000E-01 LUHG W
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H us
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PATUWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 50 81 AGE 1 TEEN f
PAlllWAY 1 ItHIALATION H
-tKI ISOTorE W. 00DY TilYROID BONE LIVER KIDNEY LUNG GI-LLI SKIti CRITICAL
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w 71 LA-142 1.056E-01 0.000E-01 9.600E-01 4.240E-01 0.000E-01 1.016Et04 1.200El04 1.056E-01 GI-LLI 72 CE-141 2.160Et03 0.000E-01 2.040E604 1.0?6Et04 8.000E603 6.136Et05 1.264E105 0.000E-01 LUNG
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73 CE-143 2.160Et01 0.000E-01 2.656Et02 1.936Et02 8 610Et01 1.304Et05 2.552Et05 0.000E-01 GI-LLI 74 CE-144 2.624Et05 0.000E-01 4.080Et06 2.024E104 1.200Et06 1.336E107 0.640E605 0.000E-01 LUNG 75 lR-143 6.624Et02 0.000E-01 1.336Et04 5.312Et03 3.000Et03.4.032El05 2.136E105 0.000E-01 LUNG ls 76 PH-144 2.176E-03 0.000E-01 4.296E-02 1.760E-02 1.000E-02 1.752El03 2.352E-04 0.000E-01 LUNG-77 t!D-147 5.120Et02 0.000E-01 7.064E103 8.540Et03 5.024E103 3.720EtOS 1.024El05 0.000E-01 LutlG 70 W-105 5.44dEiO1 0.000E-01 1.560Et03 5.176EiO2 0.000E-01 4.456Et05 0.560Et04 0.000E-01 LUNO-()
79 IJ-107 '
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01 t1-230 4.536Et06.0.000E-01 7.664EtO7 0.000E-Of 1.714Et07 3.664E600 0.240t;t05 0.000E-01 LUNG l'
y 02 NP-239 1.768Et01 0.000E-01 3.304Et02 3.192Et01 1.000Ef02 6.408Et04 3.320E105 0.000E-01 GI-LLI
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M PATHWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 50 m
FI ACE : ALL PATHuAY ! GROUND PLANE sH tia ISOTOPE W. BODY TilYROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL M
36 NB-95 1.366Et00 1.366Et00 1.366Et00 1.366Et00 1.366Et00 1.366Et00 1.366Et00 1.407El00 SKIN 37 ND-97 1.797E405 1.797E605 1.797Et05 1.797Et05 1.797EtOS 1.797Et05 1.797Et05 2.10?Ef05 SNIN 30 M0-99 3.990E106 3.V90Ct06 3.990E604 3.990Et06 3.990Et06 3.990Et06 3.990Et06 4.620El06 SNIN 39 TC-99M 1.015E t05 1.0 45E t 05 1.0 45E t 05 1.8 45E105 1.045E tOS 1.045E l 05 1.015Ef 05 2.115E105 SKIN 40 TC-101 2.03-)E104 2.034EIO4 2.034E104 2.034Et04 2.034Et04 2.034Et04 2.034E104 2.260Et04 SNIN 41 RU-103 1.093EiOD 1.093E100 1.093Et00 1.093EiOD 1.093Et00 1.093Et00 1.093E400 1.275EIOD CNIN
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42 RU-105 6.373EiO5 6.373EtOS 6.373E105 6.373EtO5 6.373Ct05 6.373Et05 6.373Et05 7.223Et05 CNIN 43 RU-104 4.239Et00 4.239E100 4.239Et00 4.23YEt00 4.23YEl00 4.239E400 4.23VE800 5.006El00 SKIN 44 A0-110M 3.440E109 3.440Et09 3.460EiO9 3.460Et09 3.460E109 3.460E609 3.460Et09 4.037E109 SAIN t
45 CD-115M 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 46 SD-124 5.994E100 5.994E100 5.994El00 5.9940400 5.994Et00 5.994Et00 5.99tEt00 6.V14CtO8 CK1H D3 47 TE-125M 1.555Et06 1.555Et06 1.555Ef01,1.555Et06 1.555C106 1.5550106 1.555Lt06 2.133Et06 SKIH n
40 TE-127M V.16* jet 04 9.165C104 9.165E104 9.165E104 9.145ElO4 v.145Eloi 9.145E104 1.003E105 LKIN u
49 TE-127 2.991Et03 2.9Y1E103 2.991Et03 2.991Et03 2.991Et03 2.991Et03 2.VVIC103 3.290E103 SKIH SO 'IE-129H 1.967Et07 1.V67Ef07 1.967E107 1.967EIO7 1.V67Et07 1.967Et07 1.967E107 2.300Eio7 CKIH i
51 lE-127 2.63YEtoi 2.63?El04 2.43YEt01 2.63YEloi 2.639Et04 2.63YEt01 2.6390601 3.122Et04 SKIH 52 'IE-131H 0.023El04 0.023Et06 0.023Et06 0.023El06 0.023Et06 0.023Et06 0.02SE106 9.456ElO6 Chill 53 IC-131 2.Y26El04 2.V26Et04 2.926Et04 2.926Et04 2.926E!O4 2.926El04 2.926Et04 3.150C107 CKIll 5.
54 TE-132 4.220Cf06 4.220Et06 4.220E106 4.220El06 4.220Et04 4.220E106 4.220El06 4.Y65El06 CNIH 55 1-130 5.53 vet 06 5.539Et06 5.539Et06 5.539EiO6 5.53YEt06 5.539Et06 5.539E104 6.724El06 CNIH
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b/ I-132 1.230E106 1.230Et06 1.230E406 1.230Et04 1.2300-106 1.230Et06 1.230E106 1.457El04 CKIN 53 1-133 2.453E106 2.153Et06 2.453E106 2.453E106 2.453EtOS 2.453El06 2.453EIOS 2.V03Ct06 Skill 59 I-134 1.160E105 4.160E105 9.460E605 4.460E605 4.4606105 4.460EtOS 4.460Et05 5.296Et05 SKIN t-60 I-135 2.5200606 2.520Et06 2.520Et06 2.5200604 2.5200606 2.520E104 2.520El06 2.940Ef06 SKIN 61 EU-134 6.331E109 6.034E109 6.034E109 6.031Et09 6.034E t0? 6.031EIOV 6.031Et09 7.Y72E10V LKlil 62 CC-136 1.491E600 1.4V1El00 1.491EIOO 1.4VIEl00 1.491El00 1.491C100 1.491Et00 1.690El00 SKItl 63 EG-137 1.030E110 1.030El10 1.030Et10 1.030El10 1.030E110 1.0300110 1.030Et10 1.202Et10 CNIN 61 CS-130 3.597tl05 3.597E105 3.5V7E105 3.5V7Et05 3.597E105 3.597El05 3.597EIO5 4.111E605 skill 65 EG-139 3.115L101 3.115E104 3.115El04 3.115E104 3.115E104 3.115El04 3.115Et04 3.541El04 SKIN s-64 1: A - 139 1.0$ vel 05 1.059Et05 1.059El05 1.05 vet 05 1.059El05 1.05VE105 1.059El05 1.191El05 SKIN 6/ DA-140 2.051E t 07 2.051E107 2.051E 307 2.0510107 2.051E 607 2.051E107 2.051El07 2.343El07 Skill 63 tu-111 4.179Et04 4.1/9Ct04 4.179Ll04'4.179Et04 4.179Et04 4.179Ef04 4.179E101 4.762Et04 skill LV 1:..
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E TABLE 6.
(CONT)
C PATitWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 50 C
M AGE 1 CilILD PATifWAY ! VEGETATION C.
g N
NO ISOTOPE W.
DODY TilYROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL
{'
g I ti-3 4.000E103 4.000E403 0.000E-01 4.000Et03 4.000Et03 4.000E103 4.000Et03 4.000E403 W. DODY 2 C-14 7.008Lf05 7.008Et05 3.504E606 7.000Ef05 7.000Ef05 7.000E105 7.000E405 7.000Et05 BONE 3 NA-24 3.732Et05 3.732Et05 3.732Et05 3.732Et05 3.732E105 3.732EiO5 3.732E105 0.000E-01 W. BODY
(;
4 P-32 1.301Et00 0.000E-01 3.375EtO9 1.579E400 0.000E-01 0.000E-01 9.326Et07 0.000E-01 BONE 5 SC-46 1.239Et05 0.000E-01 2.195E+05.4.302Et05 3.903Et05 0.000E-01 2.075E109 0.000E-01 GI-LLI 4 ER-51 1.175El05 6.522Et04 0.000E-01 0.000E-01 1.702Et04 1.191E+05 6.232E606 0.000E-01 GI-LLI
(>
7 MM-54 1.770EiOO 0.000E-01 0.000E-01 6.646Ef03 1.063E600 0.000E-01 5.57aEt00 0.000E-01 LIVER 0 HN-54 4.100Et00 0.000E-01 0.000E-01 1.016Elot 2.197Ef01 0.000E-01 2.632Et03 0.000E-01 GI-LLI 9 IE-55 1.317Et00 0.000E-01 0.012Et00 4.250E400 0.000E-01 2.404E100 7.073El07 0.000E-01 BONE
()
10 FE-59 3.200E600 0.000E-01 3.970Et00 6.423Ef00 0.000E-01 1.062Et00 6.600Et00 0.000E-01 GI-LLI 11 EO-50 1.907Et00 0.000E-01 0.000E-01 6.490Ef07 0.000E-01 0.000E-01 3.706E100 0.000E-01 GI-LLI g
1 12 CO-60 1.116Et0V 0.000E-01 0.000E-01 3.703Et00 0.000E-01 0.000E-01 2.095E109 0.000E-01 GI-LLI LJ 13 NI-59 1.190El00 0.000E-01 7.102E100 2.443Et0D 0.000E-01 0.000E-01 5.072E107 0.000E-01 B0HE 14 NI-43 1.343El09 0.000E-01 3.949Et10 2.114EiO9 0.000E-01 0.000E-01 1.424Et00 0.000E-01 DOHC 15 N1-65 5.601Et00 0.000E-01 1.019Et02 9.595EiOO 0.000E-01 0.000E-01 1.175E103 0.000E-01 GI-LLI (7
16 CH -64 4.561Et03 0.000E-01 0.000E-01 1.006E104 2.624EIO4 0.000E-01 5.090EIOS 0.000E-01 GI-lLI 17 2H-65 1.344E109 0.000E-01 0.112C-600 2.161Ef09 1.362Et09 0.000E-01 3.795El00 0.000E-01 LIVER 10 ZN-69 1.004E-06 0.000E-01 1.351E-05 1.952E-05 1.104E-05 0.000E-01 1.230E-03 0.000E-01 GI-LLI
()
19 DR-03 5.334El00 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 20 DR-04 3.101E-11 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.OOOE-01 W. DODY 21 L:R -05 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY (3
22 RD-06 2.767Et00 0.000E-01 0.000E-01 4.500Ef00 0.000E-01 0.000E-01 2.095Et07 0.000E-01 LIVER 23 RD-80 1.651E-22 0.000E-01 0.000E-01 2.376E-22 0.000E-01 0.000E-01 1.166E-23 0.000E-01 LIVER 24 RD-09 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 6
25 SR-09 1.02 set 09 0.000C-01 3.590Et10 0.000E-01 0.000E-01 0.000E-01 1.390Et09 0.000E-01 BONE 26 SR-90 3.152Et11 0.000E-01 1.213El12 0.000E-01 0.000E-01 0.000E-01 1.675El10 0.000E-01 DONE 27 LR -91 1.953E 101 0.000E- 01 5.175E t OS 0.000E-01 0.000E-01 0. 000E-01 1.143E106 0.000E-01 GI-LLI LJ 20 ER-92 2.021E101 0.000E-01 7.03DCt02 0.000E-01 0.000E-01 0.000E-01 1.333EIO4 0.000E-01 GI-LLI 29 Y-90 6.177El02 0.000E-01 2.300E604 0.000E-01 0.00CE-01 0.000E-01 6.570Elo7 0.000E-01 GI-LLI 30 Y-91M 3.063E-10 0.000E-01 0.417E-09 0.000E-01 0.000E-01 0.000E-01 1.640E-05 0.000E-01 GI-LLI
()
31 Y-V1 4.9V00005 0.000E-01 1.066L107 0.000E-01 0.000E-01 0.000E-01 2.406El09 0.000E-01 GI-LLI 32 Y-92 4.430E-02 0.000C-01 1.540El00 0.000E-01 0.000E-01 0.000E-01 4.473EiO4 0.000E-01 GI-LLI 33 Y-73 0.164El00 0.000E-01 2.973El02 0.000E-01 0.000E-01 0.000E-01 4.434EIO6 0.000E-01 GI-LLI
's 31 2R is5 7.702Et05 0.000E-01 3.V36Et06 U.452E105 1.230E106 0.000E-01 9.025Et00 0.000E-01 GI-LLI JS 2R-97 4.OJ3Et01 0.000E-01 5.669Et02 0.191E601 1.176El02 0.000E-01 1.241EtO7 0.000E-01 GI-LLI V
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I Table 7 CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS Pathways Age Group Sector N*
NNE*
NE*
ENE*
E*
ESE*
SE*
SSE 7320 Goat / Milk Infant S
1610 Vegetation Child SSW 1000 Vegetation Child SW 990 Vegetation Child WSW 4250 Cow / Milk Infant W
980 Vegetation Child WNW 8047 Cow / Milk Infant NW 2210 Vegetation Child NNW 1250 Vegetation Child i
- These sectors are located over Lake Erie, so no ingestion pathways are present.
DAVIS-BESSE, UNIT 1 B-59
, _ _ - ~ - - - ~, -
Table 8 ATMOSPHERIC DISPERSION PARAMETERS Sector yLq D/Q N*
NNE*
NE*
ENE*
E*
ESE*
SE*
SSE 7320 3.48E-07 2.81E-09 S
1610 4.84E-06 8.22E-08 SSW 1000 1.10E-05 2.52E-07 SW 990 8.13E-06 1.98L-07 WSW 4250 9.99E-07 1.24E-08 W
980 1.20E-05 2.10E-07 WNW 8047 4.1?E-07 2.62E-09 NW 2210 2.98E-06 2.69E-08 NNW 1250 1.09E-05 1.13E-07
- These sectors are located over Lake Erie, so there are no exposure pathways within 5 miles.
DAVIS-BESSE, UNIT 1 B-60 r--
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TABLE 9 SAMPLING LOCATIONS, DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 YPe of Location Code
,a T-1 I
Site boundary, 0.6 miles NE of station, near in-take canal.
T-2 I
Site boundary, 0.9 miles E of station.
T-3 I
Site boundary, 1.4 milts ESE of station, near Toussoint River and storm drain.
~
T-4 I
Site boundary, 0.8 miles S of station, near Locust Point and Toussaint River.
T-5 I
Main entrance to site, 0.5 miles W of station.
T-7 I
Sand Beach. 0.9 miles NNW of site.
T-8 1
Earl Moore Farm, 2.7 miles WSW of site.
T-9 C
Oak Harbor, 6.8 miles SSW of site.
T-ll C
Port Clinton, 11.5 miles SE of site.
T-12 C
Toledo, 23.5 miles WNW of site (water samples are taken from an intake located 11 miles NNW of site).
T-17 I
Irv Fick's well onsite, 0.7 miles SW of station.
T-20 C
Carl Gaeth, 12639 W. Toussaint E Road, 4.5 miles WSW of site.
l T-24 C
Sandusky, 24.9 miles SE of site.
T-25 I
Miller Farm 3.7 miles S of site.
i T-27 C
Magee Marsh, 5.3 miles WNW of site.
l T-28 I
Unit 1 treated water supply, onsite.
T-33 I
Lake Erie, within a 5 mile radius of site.
T-35 C
Lake Erie, greater than 10 miles radius of site.
DAVIS-BESSE, UNIT 1 B-61
TABLE $ sr I) yPe Code a
Location T-37 C
Fruit stand, 12.0 miles SW of station (or the farm 10 to 20 miles from the site in the least prevalent wind direction).
T-38 I
Site boundary 0.6 ENE of station near lake.
T-40 I
Site boundary 0.7 miles SE of station near ditch to Toussaint.
T-41 I
Site boundary 0.6 miles SSE of station near ditch to Toussaint.
T-42 I
Site boundary 0.8 miles SSW of station by ECC.
T-43 I
Site boundary 0.5 miles SW of station along Route 2 fence.
T-44 I
Site boundary 0.5 miles WSW of station by railroad tracks.
T-45 I
Site boundary 0.5 miles WNW of station on. access road behind Cooling Tower.
T-46 I
Site boundary 0.5 miles NW of station along access road.
T-47 I
Site boundary 0.5 miles N of station along access road by gate.
T-48 I
Site boundary 0.5 miles NNE of station along access road by lake.
T-50 I
Erie Industrial Park 4.5 miles SE of station by Water Tower.
T-51 I
Daup Farm, 600 Tettau Road, Port Clinton, Ohio 5.5 miles SSE of the station.
T-52 I
Miller Farm 3.7 miles S of site on West Camp Perry Road W.
T-54 1
M. Beier Farm 4.8 miles SW of site on Geneman Road.
T-55 I
Lenke Farms 5 miles W of site on Route 2 I = Indicator location; C = Control locations.
DAVIS-BESSE, UNIT 1 B-62
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5 Table 10 (continued)
In Type and Frequency of Sample Collection h
Environmental Radiation Monitoring Program (Continued) en E
n Location Type Weekly Monthly Quarterly Semi-annually Annually 42 I
TLD l
43 I
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TLD 46 I
TLD 47 I
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48 I
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TLD 51 I
TLD 52 I
TLD 54 I
TLD 55 I
" Composite sample over 1-week period bSemi-monthly when animals are on pasture (May-October), monthly at other times
" Summer months dMonthly when available (July, August, September)
Table 11 Sample Collection Codes Code Description AP Airborne Particulates I
AI Airborne Iodine I
TLD Thermoluminescent Dosimeter M
Milk WW Well Water (Ground Water)
GLV Green Leafy Vegetables SWT Surface Water - Treated i
SWU Surface Water - Untreated i
F Fish BS Bottom Sediments e
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DAVIS-BESSE, UNIT 1 B-65 i
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OFFSITE DOSE CALCULATION MANUAL APPENDIX J JUSTIFICATIONS DAVIS-BESSE, UNIT 1
Safety Evaluation for the Davis-Besse Radiological Effluent Technical Specifications Amendment Ove rview Revisions to the Davis-Besse Appendix A and Appendix B Technical Specifica-tions are proposed which will implement the regulatory requirement of 10 CFR 50, Appendix I on ALARA for radioactive effluents and other NRC regulations and criteria on radioactive material monitoring instrumenta-tion, radioactive material control, and radiological environmental monitoring.
In keeping with NRC guidelines, all radiological requirements are being deleted from Appendix B and placed in Appendix A.
This proposed amendment is a revision to a previously submitted amendment to the NRC dated March 16, 1979 (Serial No. 488).
The major areas that are addressed in the revised submittal are as follows:
Liquid and gaseous effluent monitoring instrumentation--operation and periodic operability checks; i
Liquid and gaseous radioactive material releases--maximum release rates, quarterly does limits and yearly dose limits; Sampling and analysis requirements on batch and continuous radio-active material releases; Operation requirements on the liquid radwaste treatment system; Curie inventory limit on outside temporary liquid storage tanks; Maximum allowable oxygen concentration in the waste gas system; DAVIS-BESSE, UNIT 1 J-1
Requirements to assure all solid waste meets applicable burial site requirements; Radiological environmental monitoring program--minor revisions to reflect current program and current NRC guidelines.
Changes have also been made to Section 6 of Appendix A to reflect the applicable administrative controls needed for the Section 3/4 revisions.
A notable addition to the amendment is the inclusion of a requirement for an Off-site Dose Calculation Manual (ODCM) and a Process Control Program (PCP). The ODCM and PCP are not licensed documents but are referenced in the Technical Specification as presenting acceptable methods for evaluat-ing compliance with applicable Technical Specification requirements. The ODCM provides calculational methods for determining radioactive effluent instrumentation alarm setpoints, and for evaluating releases of radio-active effluents and corresponding doses. The ODCM also includes the sampling locations for the environmental monitoring program. The PCP presents the methods used to verify that waste (dewatered resins) as processed for disposal meets appropriate shipping and burial ground regulations. Changes may be made to these documents without NRC approval; review by the SRB is required.
Safety Evaluation
- l An evaluation of the revised amendment has been performed to assure that the revisions as proposed do not involve an unreviewed safety question as defined in 10 CFR 50.59.
The three criteria of 10 CFR 50.59 for the unreviewed safety question determination are addressed below.
i)
Probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report.
DAVIS-BESSE, UNIT 1 J-2
Except for the addition of the turbine building liquid effluent radiation monitor (for which an FCR has already been initiated), no plant equipment modifications are required by the proposed amendment. Certain procedural requirements will need to be developed but these address routine radio-active material effluents and controls; no accident procedures are involved.
ii) Probability for accident or malfunction of a different type than any evaluated previously in the SAR may be created.
For reasons as stated in response to item (i) above, the proposed amend-ment does not directly or indirectly pose a probability for an accident or malfunction. The amendment will implement the NRC regulations for routine releases and controls of radioactive material. The amendment does not address any engineered safety features of the plant design.
iii) Margin of safety as defined in the basis for any technical specifica-tion is reduced.
The proposed amendment does not reduce the margin of safety. The proposed amendment addresses routine releases and control of radioactive material; except as noted in item (i), no plant modifications are involved. Several operating procedure changes may be needed, but these changes will be only for routine operations and will have no impact on accident probability or consequences.
1 For the reasons discussed above for each of the criteria of to CFR 50.59, it is concluded that the amendment as proposed does not involve an unreviewed safety question.
DAVIS-BESSE, UNIT 1 J-3
Service Water System--Radiological Effluent Monitoring Requirements The service water system is classified as a non-radioactive system, being removed from radioactive systems by two boundaries. Radioactive systems are serviced by the component cooling water system interface; and, the service water system provides cooling to the component cooling water system through closed loop heat exchangers. Therefore, any leaks from radioactive systems into LLu piant water systems would first be identified by the monitoring of the component cooling water system prior to any additional unexpected leakage into the service water system. As a prudent measure, the service water system is monitored in accordance with the NRC guidance of Standard Review Plan, Section 11.5.
However, because this system is a non-radioactive system and is separated from radioactive systems through two closed-loop boundaries, no Technical Specification requirements are needed for routine monitoring and analysis for radio-active effluents.
l DAVIS-BESSE, UNIT 1 J-4
Radioactive Effluent Instrumentation--Automatic Isolation Feature The radioactive effluent monitoring instrumentation at Davis-Besse does not include provisions as called for in the NRC Standard Radiological Effluent Technical Specifications for automatic isolation should any of the following conditions exist: circuit failure, downscale failure, or instrument not set in operate mode. Even though the automatic isolation features do not exist, administrative controls have been established such that should any of these conditions exist the control of radioactive effluents would not be significantly impacted. Essentially all releases of liquid radwaste are controlled as individual batch releases with predetermined allowable release conditions. Thereby the radiation monitor serves mainly as a back-up; primary control is established by the pre-release radiological analyses and evaluations. To assure the availability of the back-up monitoring, the status of the instruments is checked once per shift by the control room operators.
Indicator lights on.the instru-ment panel are checked to verify operability. An indicator would illuminate should a failure occur such as the ones delineated above.
Therefore, in addition to the administrative controls on allowable releases, the verification of instrument operability prior to releases of radioactive effluents and the "once per shift" status check by the control room operators provides adequate assurance of the proper control of the radioactive effluents.
j I
DAVIS-BESSE, UNIT 1 J-5
Technical Bases for Eliminating Curie Inventory Limit for Gaseous Waste Decay Tanks The NRC Standard Technical Specifications include a limit for the amount of radioactivity that can be stored in a single waste gas decay tank.
This curie inventory limit is established to assure that in the event of a tank failure releasing the radioactive content to the environment the resulting total body dose at the site boundary would not exceed 0.5 rem.
For Davis-Besse the inventory limit in the waste gas storage tank has been determined to be approximately 45,000 curies (Xe-133, equivalent).
An allowable primary coolant radioactivity concentration is established by the Technical Specifications which limit the primary coolant radioactivity concentrations to 100/E with E being the average energy of the radio-activity in Mev. This equation yields an upper primary coolant gross activity limit of about 200 pCi/ml. By applying this activity concentra-tion limit to the total liquid vol'ame of the primary system, a total activity limit can be determined. For Davis-Besse the primary system volume is about 56,000 gallons, which yields a limiting total inventory of approximately 41,000 Ci.
By assuming a typical radionuclide distribution an equivalent Xe-133 inventory can be determined. Table 1 provides the typical radionuclide (noble gases) distribution and the Xe-133 equivalent concentration. The equivalent concentration is determined by multiplying the radionuclide concentration by the ratio of the nuclide total body dose factor to the Xe-133 total body dose factor. Summing all the individual radionuclide equivalent concentrations provides the overall Xe-133 equivalent concentra-tion. For determining concentration in a waste gas decay tank, a conservative assumption of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> decay in degassing the primary system has been used to correct the primary coolant concentrations. The data show that the equivalent concentration (decay corrected) is less than the gross concentration (i.e., 16 pCi/gm total in primary coolant versus 12 pCi/gm equivalent). The resulting Xe-133 equivalent curie inventory for WGDT input is approximately 31,000 Ci.
DAVIS-BESSE, UNIT 1 J-6
i Therefore, even if the total primary system at the maximum Tech Spec allowable concentration was degassed to a single waste gas decay tank, the tank curie inventory would be well below the 45,000 Ci limit. Based on this evaluation, the curie inventory limit on a single waste gas storage tank has not been included as a Technical Specification requirement.
DAVIS-BESSE, UNIT 1 J-7
Table 1 Xe-133 Effective Concentration Prima ry*
Half-life Concentration Reg Guide 1.109 Ratio Xe-133 Coolant
@ 48 hr decay TB Dose Factor TB DF Effective Cone (pCi/GM)
@ 48 hr decay 3
pCi/m (pCi/ml) 7.6x10-8 Kr-83M 2.0-02 1.9 hr 1.2x10-3 4.1 Kr-85M 1.1-01 4.5 hr Kr-85 7.4-02 10.7 yr 7.4x10-2 1.6x10-5 0.06 4.4x10-8 Kr-87 5.8-02 76.3 min 5.2x10-3 20.
Kr-88 1.9-01 2.84 hr 1.5x10-2 52.
1.7x10-2 57.
Kr-89 4.8-03 3.16 min Xe-131M 8.4-02 12 days 7.5x10-2 9.2x10-5 0.32 2.4x10-2 Xe-133M 2.0-01 2.2 days 1.1x10-1 2.5x10-4 0.86 9.5x10-2 Xe-133 1.5+01 5.3 days 1.2x10+1 2.9x10-4 1.0 1.2x10+1 3.1x10-8 11.
Xc-135M 1.3-02 16 min Xe-135 3.3-01 9.1 hr 8.5x10-3 1.8x10-3 6.2 5.3x10-2 1.4x10-3 4.8 X2-137 8.7-03 4 min Xc-138 4.3-02 17 min 8.87 10-3 30 Total 1.6x10+1 1.2x10+1 1.2x10+1
- Adapted.from Davis-Besse Evaluation of Compliance with Appendix I to 10 CFR 50, June 4, 1976.
DAVIS-BESSE, UNIT 1 J-8
Lover Limit of Detection--Decay Correction Factor The equation and definition of the lower limit of detection in the NRC Standard Radiological Effluent Technical Specification include the term
^'which is used to decay correct the analysis.
The LLD is further defined e
as an a priori (before the fact) limit representing the capabilities of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.
Providing a decay correction for an evaluation of the capabilities of a system does not appear appropriate.
It may be appropriate to decay correct certain analyses of specific samples to determine radionuclide concentra-tions at the time of release. Even in this case, such a correction is not appropriate for batch releases. Analyses are performed prior to any release; and, the sample will be decaying at the same rate as the batch from which the sample was taken. For continuous releases, decay correcting analyses of samples obtained over a specified sampling interval must take into account the accumulation of radioactivity in the sampling medium, the decay during the sampling interval and, especially for short lived radionuclides, equilib-rium or quasi-equilibrium conditions that may be achieved.
Short-lived radionuclides will tend to reach an equilibrium value in the sampling medium as a function of source input and half-life. A single decay correction to adjust for sampling interval will provide an unacceptable overestimate. Equilibrium concentrations must be considered if analyses are l
to be indicative of actual release quantities.
Employing exp(-AAt) to adjust for radioactive decay between the en,d of sampling and the time of analysis is straightforward. However, to attempt to use the same term to adjust for decay during the sampling period is not t
proper. As a practical matter, when the half-life of a radionuclide is long relative to the sampling time and the time between sampling and analysis, i.e., minimal decay, the correction term will be near unity..In that event, the correction term is relatively unimportant.
l DAVIS-BESSE, UNIT 1 J-9
At the other extreme, when the half-life of a radionuclide is much shorter than the sampling time or the time between the end of sampling and the analysis, the term exp(-Aat) could be used to adjust for decay between the end of sampling and the analysis. However, it would not be appropriate in that case to use the same term to attempt to adjust for decay during sampling.
The relationship between the radioactivity in a sample at the end of sampling and the activity concentration in the medium being sampled is somewhat more involved. To explain this in the simplest condition, assume the radionuclide concentration is constant in the medium being sampled and that the medium is sampled at a constant rate.
In the instance of water sampling *, the relationship between the activity concentration in the water being sampled and the activity concentration in the water sample at the end of sampling is:
C
=C At (2) 1 2
1 - e'^
where C2 = radionuclide concentration in the water being sampled C2 = radionuclide concentration in the water sample at the end of sampling t = duration of sampling A = radionuclide decay constant when A t >> 1, C : C At t
2 In the separate case of sampling a radionuclide in air by filtering the air and analyzing radioactive material collected on the filter, the radionuclide of interest is concentrated. Absent diluent air in the sample being analyzed, the relation between radioactivity on the sample media and radionuclide concentration in the air being sampled is:
C
=C At (2) t F(1 - e ^')
~
DAVIS-BESSE, UNIT 1 J-10
4 where C1 = radionuclide concentratioa in the air being sampled q = radioactivity on the sample media (assuming 100% collection efficiency)
F = sampler flow rate (volume / time)
A = radionuclide decay constant i
t=
duration of sampling when A t >> 1, C ~ q A/F.
i This merely recognizes that the rate of loss from the filter by radioactive-decay equals the rate of collection onto the filter at equilibrium.
The NRC proposed equation appears to incorporate an adulterated way of encouraging analysis soon after the end of sampling and to encourage efficient sample concentration or radiochemical extraction. Although not rigorous, it combines both objectives in a simple and thus practical way, 1
provided the decay correction is not extrapolated to a time earlier than l
the end of sampling.
J A more nearly rigorous way of determining the activity concentration (or minimum detectable activity) in the medium being sampled is to assess the LLD in the sample at the time of analysis. Then the activity concentration in the medium being sampled can be calculated with the product of exp(-Aat) for decay between the end of sampling and the analysis and one of the equations derived herein for the relation between the medium being sampled and the activity in the sample at the end of sampling.
However, this method is not very practical or necessary considering the types of sampling and analysis at nuclear power plants, the significant radionuclides, and the offsite potential doses. The bulk of the radio-activity is released as batch releases with all sampling and analysis l
performed prior to release. Therefore, no decay corrections are applica-ble.
It is in the sampling and analysis of continuous releases that the accumulation and decay of the radioactive material may need to be considered.
l
- The use of NRC's guidance for decay correction to the mid-point of the I
sampling period can grossly overestimate actual release qualities of short-lived radionuclides, while providing little improvement for the
{
l DAVIS-BESSE, UNIT 1 J-11 l
1.
I i
-,...-n.
-n--
w-,.
-- - - - -, ~ - -,.. - -,
quantification of the longer half-life radionuclides that are the major dose contributors.
Overall, it may be appropriate to decay correct certain analysis to account for radionuclide decay during the sampling period. However, simple decay correction to the mid point of sampling will grossly over-estimate any short-lived radionuclides that may be detected. More consider-ation needs to be given by the NRC to address this problem.
In any case, the use of a decay correction factor in defining a lower limit of detection is inappropriate. The LLD is a measurement of the capability of the measurement system and should not be used to try to establish a regulatory position on sampling and decay correction for quantification of releases.
1 i
DAVIS-BESSE, UNIT 1 J-12 i
Technical Basis for Liquid Radwaste System Operations Technical Specification 3.11.1.3 requires that appropriate subsystems of the liquid radwaste treatment system be routinely used to reduce the radioactive material levels prior to discharge when cumulative doses averaged over 31 days would exceed 0.25 mrem to the total body or 0.833 mrem to any organ.
This specification implements the requirements of 10 CFR 50.36a(s) (1).
The liquid radwaste treatment system should be used to process liquid waste in order to maintain potential doses to members of the public to less than the Appendix I design objective values of 3 mrem /yr, total body and 10 mrem /yr, any organ. Also, additional processing should be conducted to further reduce releases of radioactive material if it is cost-beneficial. This cost-benefit evaluation of the radwaste equipment operation should be based on a cost value of $1,000 per man-rim.
For the Davis-Besse Appendix I evaluation,* the quantities of radioactive material in liquid effluents released annually have been calculated to be:
total iodines 0.104 Ci total others (excluding H-3) 0.123 Ci Total 0.227 Ci
(
- Davis-Basse Nuclear Power Station Unit No. 1, " Evaluation of Compliance with Appendix I to 10 CFR 50," June 4, 1976.
DAVIS-BESSE, UNIT 1 J-13
=
I l
-The population dose commitments resulting from these releases have been calculated to be:
thyroid 0.41 man-rem total body 0.64 man-rem Therefore, population doses are about 4 man-res/Ci of iodines released and about 5 man-rea/Ci of other radionuclides (excluding H-3).
At Davis-Besse, liquid radwaste is processed by demineralization. From Regulatory Guide 1.110, the operating cost of a demineralizer is $75/ft8 3
for resins and $20/ft for disposal or $95, total per fts of resins used.
Based on a 100 ft8 resin bed with a service life of 200,000 gallons, the cost to process waste is about $0.05 per gallon. To process a 13,000-gallon batch of miscellaneous liquid radwaste would cost about $650. Thereby, the radioactivity concentration below which it is not cost-beneficial to process can be calculated as follows:
s
$650 1 Ci
,lo pCi
,1 man-rem C = 13,000 gal
- 3785 ml/ gal 5 man-rem Ci
$1,000
= 2.6x10-8 pCi/ml Individual doses have been calculated to be:
thyroid 0.034 mrem /0.104 Ci (iodines) total body 0.032 mres/0.123 Ci-(others, excluding H-3)
Conservatively assuming that 100% of the dirty radwaste (2875 gpd) and 20%
1 of the clean radwaste (890 gpd) is discharged to the environment containing all of the radioactive material released, the average gross radioactivity concentration corresponding to the Appendix I individual dose design objectives can be determined as follows:
DAVIS-BESSE, UNIT 1 J-14
O 8
3 mrem, total body = 0.123 Ci
- 3 mrem,
1
,10 pci Ci 0.032 mrem 1.4x108 gal
- 3785
= 2.2 x 10-3 pCi/ml 10 mrem, thyroid = 0.104/Ci
- 10 mrem,
1
,10s Ci p
gal
- 3785 "I Ci 0.034 mrem 1.4x108 gal
= 5.8 x 10-3 pCi/ml The radioactivity concentrations below which it is not cost-beneficial to process (2.6 x 10-3 pCi/ml) are about the same as the limiting concentra-tion corresponding to the Appendix I design objective dose (2.2 x 10-3 pCi/ml). Therefore, it is reasonable to establish the liquid radwaste system operation requirement at a value corresponding to the Appendix I design objective class (i.e., 0.25 mrem /31 days, total body and 0.833 mrem /31 days, any organ).
e l
L DAVIS-BESSE, UNIT 1 J-15
i..
W
' Waste Gas Decay System and Ventilation System--Operability Requirements i
i At Davis-Besse, the operation of the waste gas decay system is essentially continuous, similar to the routine operation of such a. system at other EPWRs. The system consists of a surge tank which receives the waste gases j
from the primary system, dual compressors ~ (one in-service and the other in '
reserve), and three waste gas hold-up tanks (one in-service, one isolated i
for gas decay, and the third in reserve). Once the system is on-line with a waste gas decay tank receiving primary system gases for the surge tank, operation is automatic; no operator actions are required.
i The operating philosophy at Davis-Besse is to essentially operate the j=
waste gas system continuously. Not only'is this philosophy prudent from an ALARA standpoint, but it is also conservative and protective from an operational standpoint. Having to periodically evaluate primary system off-gas activity levels and anticipate unexpected increases in radio-act,1vity would be an unnecessary burden in' determining needed waste gas r
j system operation.
i For the ventilation systems, the operating philosophy is similar to that i
for the waste gas system; operation is continuous. But for the ventila-tion systems, the reasons for continuous operation are even more straight-forward. Areas within the plant must be provided with outside air in
. order to provide an inside environment suitable for continued occupancy.
4 i
Without continuous ventilation system operation, heat, humidity, and airborne radioactive material levels would increase and worker occupancy would be jeopardized.
i As described in the Davis-Besse Appendix I evaluation, the ventilation-systems contain HEPA filters for removal of airborne radioactive particu-late material prior to release to the outside environment. '(As evaluated for Appendix I compliance, only the waste gas vent includes charcoal l
filters for removal of radioiodines) The operation of the systems can essentially be considered a passive operation. No active operational DAVIS-BESSE, UNIT 1 J-16 v.
+. _,,
,_.,_.,,__~..._,,,_.y,,
- m..,
procedures are required for normal system operation for removal of air-borne radioactive material.
Davis-Besse's operating philosophy (and operating procedures) for the waste gas system and ventilation systems is a commitment in itself to the routine continuous operation of the systems. Having to commit to such a requirement (in lieu of a technical specification requirement on operation) without appropriate consideration of system down-time and plant shut-down l
l (where operation may not be needed or feasible) is unacceptable and not in keeping with the principles of ALARA.
Including special technical specifi-cations that would impose additional procedures and periodic surveillance requirements in excess of those already established (which at present assure appropriate operation) is unnecessary and excessive.
l l
l l
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l DAVIS-BESSE, UNIT 1 J-17 i
Radiological Effluent Dose Analysis--
Meteorology for Short Term Releases Except for the waste gas decay tank (WGDT) releases and the containment purges releases, gaseous effluents from the Davis-Besse Station are from ventilation systems and are considered continuous releases. Most of the radioactive material in gaseous effluents is released from the WGDT.
However, because of the essentially random nature of WGDT releases (i.e.,
no prescribed diurnal time, frequency or duration), the dose analysis of these releases is better modeled by the use of annual average meteoro-logical conditions (i.e., 50% meteorology) rather than short term meteoro-logy (i.e., 10% meteorology). Containment purges are so infrequent that special meteorological analyses are not warranted; reasonable evaluations of off-site doses can be provided by the use of annual average meteoro-logical conditions.
DAVIS-BESSE, UNIT 1 J-18
Radiological Environmental Reporting Levels Only the radionuclides listed in Table 3.12-2 of the proposed Radiological Effluent Technical Specifications for Davis-Besse are considered in the reporting requirements for elevated levels of radioactive material in environmental sampling media. The radionuclides listed are those that are dominant in the plant effluents and contribute essentially all of the environmental dose. Other radionuclides will be present in plant effluents, but their contribution to the calculated totsl environmental dose will be minor compared to the contribution of the radionuclides listed in Table 3.12-2.
Even the contents of the NRC's Standard RETS reflect this position; not all pathways include reporting levels for all the radionuclides listed (e.g., no reporting levels are presented for Co-58, Co-60, or Fe-59 for the milk, airborne particulate, or vegetable pathway). This very selective identification of pathway and important radionuclides reflects the very well defined concept of significant radionuclides for each particular pathway.
Based on past experience in monitoring plant effluents and environmental sampling media, it can be stated with confidence that for the routine operation of Davis-Besse the radionuclides listed in Table 3.12-2 with applicable reporting levels by the identified pathways are the only radionuclides that need be considered when evaluating potential doses in the offsite environment. Also, even if reporting levels were included for other radionuclides, the values would be higher than those for the signi-ficant radionuclides and would have a very minor role in determining actual reporting requirements. The reporting levels for the significant i
radionuclides would be reached well before any identified levels of other radionuclides would even be controlling.
i l
DAVIS-BESSE, UNIT I J-19
Technical Basis for Eliminating Curie Inventory Limit of Outside Liquid Tanks At Davis-Besse, outside liquid tanks that potentially contain radioactive material are limited to the borated water storage tanks (2 tanks @ 550,000 gallons) and the primary water storage tank (1 tank, @ 140,000 gallons).
The borated water storage tanks are part of ECCS and are of seismic design. These tanks are designed to withstand extremely adverse environ-mental conditions and for purposes of this evaluation can be considered rupture proof. Also, overflow from the tanks is piped back to radwaste.
For these reasons, it is considered unnecessary to impose curie inventory limits on these tanks.
The primary water storage tank is used for normal make-up and letdown to the primary system. Water contained within the PW storage tank is typically processed primary coolant or clean (non-radioactive) water. Prior to adding primary system water to the PW storage tank, the water is processed by evaporation and demineralization. This processing limits the levels of radioactivity in the tank. Past sampling and analysis of the tank has indicated only detectable levels of tritium, no other radionuclides have been identified. Also, the overflow on the PW storage tank is piped to radwaste. Therefore, due to the processing of any radioactive waste prior to addition to the PW storage tank and the piping of the overflow to radwaste, the probability of any abnormal discharges to the environment that could exceed the concentrations of 10 CFR 20, Appendix B, Table II, Column 2 at the nearest drinking water supply is extremely remote.
Because of the design of the BWST and the design and operating conditions of the PW storage tank, it is considered unnecessary to impose curie inventory limits on these tanks. Having to routinely sample and analyze for radioactivity concentration imposes an undue burden on plant personnel without providing any additional assurance of the public health and safety.
DAVIS-BESSE, UNIT I J-20
Sampling Frequency for I-131: Significance of Power Changes and Increases in Coolant Activity Levels The NRC guidance on effluent monitoring for I-131 (RETS Table 4.11-2, footnote c) calls for increased sampling frequency for I-131 during increases (or decreases) in reactor power level and increases in primary coolant level or noble gas effluent activity level. By system design, releases of radioactive material from plant operation are minor. Trying to identify small increases in I-131 releases that may (or may not) be associated with power changes is unnecessary. To evaluate the potential significance of increases in I-131 releases associated with power changes and the effect that sampling time may have on actual quantification of releases, the following example situation is evaluated.
Consider a power increase (or decrease) on the first day of a seven (7) day sampling period that leads to an increase in I-131 release rate by a factor of 10 for one (1) day. After this one day increase, the release rate returns to the steady-state condition for the remaining 6 days of the sampling period. To evaluate the amount of I-131 on the sampling cartridge as a function of sampling time and concentration, the following equation is used:
q = f F (1,4 t)
C 1
i mAf where:
Q. = quantity of activity on collection medium Cl = air concentration of radionuclide i l
At = decay constant for radionuclide i tl= sample time m = correction factor for collection efficiency Assuming 100% collection efficiency, at the end of the one day increase the totai amount of activity (I-131) on the collection cartridge is determined to-be 9.54 C.F.
(For this example, the steady-state I-131 concentration is designated as C. and the one day increase is 10 C..)
For the remainder of the sampling period with a concentration equal to C, the I-131 activity on the collection cartridgeisequalto4.86CF.
f By decaying the activity on the collection cartridge for the one day increase to the end of the sampling period and adding this quantity to 4.66 C F, the total I-131 activity is determined to be 10.3 C F.
g g
DAVIS-BESSE, UNIT 1 J-21
1 If this value is decay corrected to the mid point of the sampling period in accordance with the guidance of Regulatory Guide 1.21, the I-131 activity which is used to determine the release quantity is equal to 14.0 C.F.
1 If a similar analysis is performed for the case of analyzing the collection cartridge at the end of the one day increase and analyzing a new cartridge at the end of 6 days sampling (constituting a 7 day sampling period), the total activity (decay corrected to mid point of sampling periods) is determined to be 16.0 C F.
g By not analyzing the collection cartridge at the end of the one day increase, the total quantity of I-131 is underestimated by 14%. This analysis represents a somewhat worse case situation. The later into the sampling period t!!at the increase occurs, the less the error. If the increase in release rate occurs after the mid point of the 7 day sampling period, the actual release will be overestimated.
Over a period of time involving numerous increases and decreases in effluent level, the rules of probability dictate that the overestimations and underestimations will tend to cancel out, providing an overall closer approximation to actual releases.
2 Both the NRC in plant measurement program and a study by EPRI* have indicated that minor increases in I-131 releases may be associated with reactor power changes and the iodine spiking phenomenon. However, these studies also indicate that overall such increases are minor, not being a significant contributor to the total releases of I-131.
As was concluded by the EPRI study for other PWRs, the main source of I-131 releases at i
Davis-Besse is associated with containment purges.
Regardless of the source, the total I-131 releases are negligible. Since j
initial start-up of Davis-Besse, the annual releases of I-131 have been l
less than 0.06 C and calculated maximum individual doses less than 0.01 g
Even considering a hypothetical 14% increase for sampling periods mrem.
that may include iodine spiking in the primary coolant, the effect on l
- EPRI NP-939, " Sources of Radiciodine at Pressurized Water Reactors".
Science Applications, Inc., November 1978 DAVIS-BESSE, UNIT 1 J-22
total releases and calculated doses is still negligible. The actual increase will be even more insignificant considering the fact that the major source of I-131 at Davis-Besse is from containment purges.
Based on a review of plant operating data and the above analysis of the I-131 release quantification as a function of concentration and sampling time, it is concluded that for Davis-Besse, a sampling frequency based on power changes and increases in primary coolant I-131 concentrations is not justified. Determining the releases (and the insignificant environmental doses of these releases) on a weekly basis is sufficient verification of the negligible impact of plant operation. Trying to " fine tune" these releases is not justified considering the manpower and material costs associated with the additional sampling and analysis.
l l
l l
l i
DAVIS-BESSE, UNIT 1 J-23 r
Condensate Demineralizer Backw:sh Receiving Tank - Radioactivity Control The discharge from the condensate demineralizer backwash receiving tank is controlled on a batch-by-batch basis in lieu of continuous radioactive effluent monitoring. This method of operation has been determined to provide better control over the discharge of the backwash receiving tank, preventing any unanticipated, unevaluated releases of radioactively con-taminated secondary-side clean-up resins to the on-site settling basin.
Prior to discharge, the contents of the backwash receiving tank are sampled and analyzed for radioactivity. As required, radioactively contaminated resins are transferred to radwaste for processing and disposal as radio-active material.
The condensate demineralizer backwash receiving tank discharge line as 4
originally designed included a radiation monitor. However, because.of the nature of the resin-slurry mixture and the accumulation of resin beads in the monitor line, the radiation monitor has failed to provide the reliable indication of radioactivity and control as originally intended. For this reason, it has been determined that the sampling and analysis of each batch prior to discharge is needed to identify and evaluste radioactive con-tamination resulting from minor steam generator tube leaks (or residual radioactive material from previous leaks) that might otherwise go undetected and unevaluated by a gross radiation effluent monitor.
The condensate demineralizer backwash receiving tank discharges to an on-site settling basin. No resia discharges are made directly to the 4
off-site environment. Therefore, even in the event of personnel error resulting in the inadvertent discharge of unacceptably radioactive, contaminated resins to the settling basin, no off-site releases would occur. All resins and radioactive material would be retained on-site within the settling basin. Appropriate follow-up measures could then be initiated to control the radioactive material and prevent'any potential i
for releases to the off-site environment in excess of the regulatory limits.
DAVIS-BESSE, UNIT 1 J-24 4
-~
Controlling the discharge of the condensate demineralizer backwash receiving tank on a batch-by-batch basis provides adequate control over the releases of any radioactive material to the off-site environment from this pathway.
Also, the discharge is to an on-site settling basin, representing an addi-tional passive barrier from release off-site. Even in the unlikely event of personnel error, by discharging to an on-site settling basin and its isolation from the off-site environment, the probability of unwanted, unevaluated releases of radioactive material to the off-site environment is exceedingly remote. Any additional protective measures provided by a continuous radiation monitor (for which operational performance and reliability are unlikely, based on past experience) are not considered needed.
PD 4306B DAVIS-BESSE, UNIT 1 J-25
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THIS IliFORMATION IS CONSIDERED PROPRIETARY AND IS NOT TO BE RELEASED OR COPIED WITHOUT WRITTEN PERMISSION OF CHEM-NUCLEAR SYSTEMS, INC.
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CHECKED DTLE CNSI MOBILE DEMINERALIZATION SYSTEM FOR b
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APPENDIX A PROCESS CONTROL PARAMETERS FOR THE 24-INCH (TALL)
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PRESSURE VESSEL DEMINERALIZATION SYSTEMS 1
l 1.0 SCOPE 1.1 Purpose The purpose of this document is to provide the CNSI operator with process control parameters for the operation of a CNSI Mobile Demineralization System utilizing the 24-Inch (Tall) Pressure Vessels.
1.2 Applicability The instructions c'ontained in this document.Are applicable to the
' operation of demineralization systems ut'ilizing the 24-Inch (Tall) Pressure Vessels.
2.0 REFERENCES
2.1 QA-AD-001, CNSI Quality Assurance Program 2.2 EN-AD-001, CNSI Drawing Control Program p
V 2.3 EN-AD-002, CNSI Design Control Program 3.0 SYSTEM DESCRIPTION 3.1 Process Description The CNSI Mobile Demineralization Systems are designed to process low-level aqueous radwastes.
The systems are composed of a con-trol skid, 24-Inch Pressure Vessels, booster pump (if necessary) and dewatering pumps.
3.1.1 Control Ski [i The control skid provides an. interface between the cus-tomers radwaste system and the demineralization systems vessel. The skid controls flow to and from the vessels.
The flowrate through the demineralization vessels can be adjusted to maximize decontamination of the radwaste l
stream as the chemistry of the stream changes.
The i
normal flowrate should be between 14 and 18 gpm.
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3.1.2 24-Inch Pressure Vessels The 24-inch pressure vessels are 72-3/4" high by 24 inches diameter.
They have a burial volume of 19 cubic feet. The loading logic of the vessels is determined by the chemical characteristics of the radwaste stream being processed and the effluent characteristics required by the customer.
The lof;ic usually employes a filtration vessel followed in series by.one or more cation vessels, followed by one or more anion vessels.
A polishing media is usually employed in the last vessel in the series.
3.1.3
. Booster Pump we A centrifugal pump can be employed as necessary to in-crease the flow through the demineralization system.
3.1.4 Dewatering Pump A positive-displacement dewater pump is used to dewater spent demineralization vessels prior to disposing cf them.
All vessels not being solidified must be de-watered to less than 0.5% of burial volume.
Vessels containing an activity of > 1 Ci/cc of isotopes having a half-life of 5 years or more must be solidified.
4.0 SAMPLING AND ANALYSIS Routina samples are obtained from the influent stream to each vessel and
,the effluent stream from the last vessel in the series.
Dese samples are taken once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of operation as a minimum. Additional sam-pies may be required during periods when the radwaste stream is not chemically constant and when a vessel is nearing depletion.
The routine samples are analyzed for pH and conductivity. These results are recorded on the Chemistry Data Sheets and they. provide the basis for determining when,a demineralization vessel has been depleted.
Daily samples are obtained for isotopic analysis.
The locations of these sample points should be specified by the customer.
As a minimum, these samples should include; influent to the system, effluent from the filter vessel, effluent from the first cation vessel, effluent from the first anion vessel, and the system effluent.
The results of the isotopic analysis should be reported to the CNSI technician in a timely manner.
The isotopic results will be recorded on the chemistry data sheets and they will be used to determine if any adjustments to the flowrate is required to maximize the decontamination of the waste stream.
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5.0 PRESSURE AND TEMPERATURE 5.1 Pressure i
The influent pressure will be monitored daily.
The results will be recorded in the daily operations log.
This data will be used in conjunction with the chemistry and isotopic data to determine j
when the filter vessel should be removed from service.
The sys-1 tem shall be shut down if the pressure of ti1e influent stream
, exceeds 90 psig.
5.2 Temperature The temperature of the influent stream will be monitored daily.
- Abrupt changes in temperature can contribute adversely to the de-ionization pro, cess and possibly damage to resin.
If the tem-perture of the, influent s.tream exceeds 1200 F the deminerali-zation system should be s' hut-down immediately.
If the tempera-ture falls below room temperature (650 F),.. adjustments to the
'flowrate may be required.
6.0 VESSEL REMOVAL CRITERIA 6.1 Anion Vessel (A)
An anion vessel shall be considered to be depleted when the con-ductivity of the effluent stream is within minus 30% of the con-ductivity of the influent. stream.
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Example:
Influent Conductivity = 800 mmohs
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Effluent Conductivity > 560 mmohs
. 6.2 Cation Vessel (C)
A cation vessel shall be considered to be depleted when the pH of
_ the effluent stream is within minus 0.5 pH of the influent stream.
Example:
Influent pH = 4.5
. Effluent pH > 4.0 6.3 Polish Vessel (F)
A polishing vessel shall be considered to be depleted when the effluent ac tivity is not less than the influent activity by a factor of S.
Example:
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A carbon filter shall be cor.sidered to be depleted when the in-fluent pressure has increased 30 psig or when solide are visible i'
in the effluent stream.
6.5 Mechanical Filter (MCF)
A mechanical filter shall be considered to be depleted when the influent pressure has increased to 20 psig or when solids are visible in the effluent stream.
6.6 Activity Criteria 6.~ 6.1 The customer,shall specify the amount of activity, which can be loaded on the resin.
Activites less than 1
- Ci/cc of _ isotopes,.having a -half-life of > 5 years do not require solidification.
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'6.'6. 2 The customer shall specify the acceptance limits for the effluent (processed water) from the-demineralization system.
The flow rate will be adjusted to obtain the specified limits on the average for the effluent from the demineralization system.
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