ML13317A039
| ML13317A039 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/12/1979 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13317A038 | List: |
| References | |
| NUDOCS 7909240251 | |
| Download: ML13317A039 (44) | |
Text
OFFSITE DOSE CALCULATION MANUAL SAN ONOFRE NUCLEAR GENERATING STATION UNITI 7 9O9'4
'j
TABLE OF CONTENTS 1.0 Effluent Monitor Setpoints 2.0 Liquid Effluents Concentration 3.0 Gaseous Effluents Dose Rates 4.0 Liquid Effluent Dose Calculation 5.0 Gaseous Effluent Dose Calculation 6.0 Projected Doses 7.0 Operability of Equipment 8.0 Sample Lcations (g)
1.0 Effluent Monitor Setpoints 1.1 Liquid Effluent Monitor Setpoint 1.1.1 Radwaste System Liquid Effluent Monitor (R-1218)
The trip/alarm setting for the liquid effluent radiation monitor is based on dilution flow, liquid effluent flow and the
.isotopic composition of the liquid discharge.
This monitor is described in Section 5.7 of San Onofre Unit 1, Final Safety Analysis.
For a liquid monitor tank release, the alarm trip setting is determined by the following methodology
- 1. Assume the total tank sample activity is due to the isotope with the highest concentration.
- 2. Determine the corresponding detector response using the calibration curve for the effluent monitor.
- 3. The alarm setpoint is set at two times the cpm value corresponding to the activity level plus the background.
For a liquid holdup tank release, the alarm/trip setting is set at 2 x 104 cpm above background.
1.1.2 Steam Generator Blowdown Liquid Sample Monitor (R-1216)
The trip/alarm setting for the steam generator blowdown monitor is set at twice the background reading.
This monitor is described in Section 5-7 of the San Onofre Unit 1, Final Safety Analysis.
1.2 Gaseous Effluent Monitor Setpoint The setting on the Plant Stack Monitor (R-1214), the Stack Gas Activity Monitor (R-1219), the Stack Iodine Activity Monitor (R-1220),
and the Stack Particulate Monitor (R-1221), is based on the gaseous effluent flow rate and the meterological dispersion factor.
The following methodology is used for the alarm setting.
- 1. The concentration at the detector is determined by using:
MPC (1-1)
(X/Q) (flow rate) 4.72x104 min-m sec-ft 3 where:
C = the concentration at the detector in juCi/cc MPC = the 10CFR Part 20 concentration for the limiting radionuclide in MCi/cc flow rate = the plant vent flow rate in cfm (X/Q) = the annual average atmosphere dispersion in sec/mi3 min M3 L.72 x 10-
= 60 sec 35.31 ft
- 2. The alarm setting is determined by using the calibration curve for the effluent monitor.
The alarm setpoint is the cpm value corres ponding to the activity level.
2.0 Liquid Effluent-Concentration The methodology used to assure that the concentration of radioactive material released to unrestricted areas is less than the concentrations specified in 10CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases is the following:
- 1. The activity, Ai, associated with each photopeak in the Y-spectrum is calculated from (net counts)i (2-1)
Ai (pCi/cc)=
(factor, dpm/pCi)i(counting time, min.) (volume, cc)
- 2. From the analysis and the MPC values for each detected radionuclide, i, a maximum release rate, Rj, is determined using:
Ri (MPCiA (flow rate)
(2-2) where:
Ri = the flow at the radiation rbnitor for radionuclide, i, in gpm flow rate = the dilution water flow in gpm MPC
= the effluent concentration limit implementing 10CFR Part 20 for radionuclide, i, in pCi/ml
- 3. The individual isotopic release rates are combining using R1 1(2-3)
R1 + R2 + R3 +
where:
R = the total flow rate at the radiation monitor in gpm R1, R2, R3...
the individual isotopic flow rate at the radiation monitor 0
0 3.0 Gaseous Effluents Dose Rate The methodology used to determine the dose rate above background to an individual in an unrestricted area is calculated by using the following expressions.
3.1 For noble gases:
DTB = YK (X/Q)
Q(3-1)
(3-1 Ds =
2 [(L +l1.1M ) (X/Q) Qg]
(3-2) where:
Ki the total body dose factor due to gamma emissions for each identified noble gas radonuclide, in mrem/yr per uCi/m 3 from Table 3-1 Li
=
the skin dose factor due to the beta emissions for each identified noble gas radionuclide in mrem/yr per 4Ci/mr3 from Table 3-1 Mi
=
the air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per /Ci/m 3 from Table 3-1.
(Unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.)
Qi
=the release rate of radionuclide, i, in gaseous effluents in pCi/sec
= 6.1E-5 sec/m.
The highest calculated annual average relative (X/Q) concentration for any area at or beyond the unrestricted area boundary.
DTB
= total body dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, in mrem/yr Ds
= skin dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, in mrem/yr 3.2 For all radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than eight days:
Do
=
Y Pik Wk ]i (3-3) i k
where:
Do=
organ dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, in mrem/yr Qi=
the release rate of radionuclide, i, in gaseous effluents in pCi/sec Pik the dose parameter for radionuclide, i, for-pathway, k, from Table 3-2 for the inhalation pathway in.mrem/yr per ACi/m3 and for the food and ground plane pathway in m2-mrem/yr per gCi/sec.
The dose factors are based on the critical individual organ and most restrictive age group.
k
=the highest calculated annual average dispersion parameter for estimating the dose to an individual at or beyond the unrestricted area boundary for pathway, k.
=
6.1E-5 sec/m 3 for the inhalation pathway.
The location is the unrestricted area in the NW sector.
2.3E-7 m-2 for the food and ground plane pathways.
The location is the unrestricted area in the NNW s.ector.
TABLE 3-1 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose Radio-Factor Ki Factor Li Factor Mi Factor Ni nuclide (mrem/yr per uCi/m3 ) (mrem/yr per uCi/m 3 ) (mrad/yr per uCi/m3 ) (mrad/yr per 4Ci/m3 )'
Ka-83m 7.56 E-2*
1.93 E+2 2.88 E+2 Kr-85m 1.17 E+3 1.46 E+3 1.23 E+3 1.97 E+3 Kr-85 1.61 E+1 1.34 E+3 1.72 E+1 1.95 E+3 Kr-87 5.92 E+3 9.73 E+3 6.17 E+3 1.03 E+4 Kr-88 1.47 E+4 2.37 E+3 1.52 E+4 2.93 E+3 Kr-89 1.66 E+4 1.01 E+4 1.73 E+4 1.06 E+4 Kr-90 1.56 E+4 7.27 E+3 1.63 E+4 7.83 E+3 Xe-131m 9.15 E+1 4.76 E+2 1.56 E+2 1.11 E+3 Xe-133m 2.51 E+2 9.94 E+2 3.27 E+2 1.48 E+3 Xe-133 2.94 E+2 3.06 E+2 3.53 E+2 1.05 E+3 Xe-135m 3.12 E43 7.11 E+2 3.36 E+3 7.39 E-2 Xe-135 1.81 E+3 1.86 E+3 1.92 E+3 2.46 E+3 Xe-1 3 7 1.42 1.22 E+4 1.51 E+3 1.27 E+4 Xe-138 8.83 E+3 4.13 E+3 9.21 E+3 4.75 E+3 Ar-41 8.84 E+3 2.69 E+3 9.30 E+3 3.28 E+3 7.56 x 10 -2 = 7.56 E-2 TABLE 3-2 DOSE PARAMETER Pik Inhalation Pathwa Food and Ground Pathway Radionuclide (mrem/yr per /,Ci/mi)
(m2 /mrem/yr per uCi/sec)
H -
3 6.5 E+2 2.4 E+3 P -
32 2.0 E+6 1.5 E+11 Mn-54 2.5 E+4 1.1 E+9 Fe-59 2.4 E+4 7.0 E+8 Co-58 1.1 E+4 5.7 E+8 Co-60 3.2 E+4 4.6 E+9 Zn-65 6.3 E+4 1.7 E+10 Rb-86 1.9 E+5 1.6 E+10 Sr-89 4.0 E+5 1.0 E+10 Sr-90 4.1 E+7 9.5 E+10 Y -
91 7.0 E+4 1.9 E+9 Zr-95 2.2 E+4 3.5 E+8 Nb-95 1.3 E+4 3.6 E+8 Ru-103 1.6 E+4 3.4 E+10 Ru-106 1.6 E+5 4.4 E+11 Ag-.110m 3.3 E+4 1.5 E+10 Cd-115m 7.0 E+4 4.3 E+7 Sn-123 2.9 E+5 3.4 E+9 Sn-126 1.2 E+6 1.1 E+9 Sb-124 5.9 E+4 1.1 E+9 Sb-125 1.5 E+4 1.1 E+9 Te-127m 3.8 E+4 7.4 E+10 Te-129m 3.2 E+4 1.3 E+9 Cs-134 7.0 E+5 5.3 E+10 Cs-136 1.3 E+5 5.4 E+9 Cs-137 6.1 E+5 4.7 E+10 Ba-5.6 E+4 2.4 E+8 Ce-141 2.2 E+4 8.7 E+7 Ce-144 1.5 E+5 6.5 E+8 I -131 1.5 E+7 1.1 E+12 I -133 3.6 E+6 9.6 E+9 Unidentified*
4.1 E+7 9.5 E+10
- If Sr-90 analysis is performed use P for Ru-106 for unidentified components.
If Sr-90 and Ru-106 analyses are performed use Pi given in 1-131 for unidentified components.
If Sr-90, Ru-106 and 1-131 analyses are performed, use Pi given in P-32 for unidentified components.
- 4. 0 Liquid Effluent Dose Calculation The dose commitment to an individual from radioactive materials in-liquid effluents released to unrestricted areas are calculated using the following expression.
DT = 2 [Ai, I( tl Cil F1) i 1
where:
AiT
=
the site related adult ingestion dose commitment factor to the total body or any organ,
, for each identified principal gamma and beta emitter, i, from Table 4-1 in mrem/hr per PCi/ml.
Cil
= the average concentration of radionuclide, i, in the undiluted liquid effluent during time period,At 1 in uCi/ml.
D 7
=
the dose commitment to the total body or an organ, r from the liquid effluents for the time period, A tl*
in mrem.
Fl
=
the near field average dilution factor for Cil during the time period,-Atl.
This factor is the ratio of the maximum undiluted liquid waste flow during time period,dtl, to the average flow from the site discharge structure to unrestricted receiving waters or (1)1
maximum liquid radioactive waste flow discharge structure exit flow At
=
the length of the lth time period over which Cil and F1 are averaged for all liquid releases, in hours.
TABLE 4-1 DOSE COMMITMENT FACTORS, Ai, (mrem/hr per uCi/ml)
Radio-Total GI Nuclid Body Bone Liver Thyroid Kidney Lung LLI H -
3 2.8 E-1 2.8 E-1 2.8 E-1 2.8 E-1 2.8 E-1 2.8 E-1 P -
32 6.46 E+5 1.67 E+7 1.04 E+6 1.88 E+6 CR-51 5.6 E-1 3.3 E-1 1.2 E-1 7.4 E-1 1.40 E+2 Mn-54 1.35 E+3 7.08 E+3 2.11 E+3 2.17 E+4 Fe-55 8.24 E+3 5.12 E+4 3.53 E+4 1.97 E+4 2.03 E+4 Fe-59 7.27 E+4 8.07 E+4 1.90 E+5 5.30 E+4 6.23 E+5 Co-58 1.35 E+3 6.04 E+2 1.22 E+4 Co-60 3.83 E+3 1.74 E+3 3.26 E+4 Zn-65 2.32 E+5 1.61 E+5 5.13 E+5 3.43 E+5 3.23 E+5 Rb-86 3.02 E+2 6.48 E+2 1.28 E+2 Sr-89 1.43 E+2 4.99 E+3 8.00 E+2 Sr-90 3.01 E+4 1.23 E+5 3.55 E+3 Y -
91 2.38 8.90 E+1 4.90 E+4 Zr-95 3.47 1.60 E+1 5.12 8.03 1.62 E+4 Zr-97 3.14 E-2 8.8 E-1 1.8 E+1 2.7 E-1 5.51 E+4 Nb-95 1.34 E+2 4.48 E+2 2.49 E+2 2.46 E+2 1.51 E+6 Mo-99 2.44 E+1 1.28 E+2 2.90 E+2 2.97 E+2 Ru-103 4.61 E+1 1.07 E+2 4.08 E+2 1.25 E+4 Ru-106 2.01 E+2 1.59 E+3 3.07 E+3 1.03 E+5 Ag-110m 8.61 E+2 1.57 E+3 1.45 E+3 2.85 E+3 5.91 E+5 Sb-124 1.10 E+2 2.77 E+2 5.23 6.7 E-1 7.85 E+3 Sb-125 4.42 E+1 2.20 E+2 2.37 2.0 E-1 2.30 E+4 1.94 E+3 Te-125m 2.91 E+1 2.17 E*2 7.87 E+1 6.54 E+1 8.84 E+2 8.68 E+2 Te-127m 6.69 E+1 5.49 E+2 1.96 E+2 1.40 E+2 2.23 E+3 1.84 E+3 Te-i29m 1.40 L+2 9.33 E+2 3.48 E+2 3.20 E+2 3.89 E+3 4.67 E+3 Te-131m 5.72 E+1 1.40 E+2 6.88 E+1 1.09 E+2 6.95 E+2 6.81 E+3 Te-132 1.24 E+2 2.40 E+2 1.32 E+2 1.46 E+2 1.27 E+3 6.25 E+3 I -131 1.79 E+2 2.18 E+2 3.12 E+2 1.02 E+5 5.36 E+2 8.24 E+1 1 -133 3.95 E+1 7.46 E+1 1.30 E+2 1.91 E+4 2.26 E+2 1.17 E+2 Cs-134 1.33 E+4 6.84 E+3 1.63 E+4 5.27 E+3 1.75 E+3 2.85 E+2 Cs-136 2.04 E+3 7.16 E+2 2.83 E+3 1.57 E+3 2.16 E+2 3.21 E+2 Cs-137 7.85 E+3 8.77 E+3 1.20 E+4 4.07 E+3 1.35 E+3 2.32 E+2 Ba-140 1.08 E+2 1.65 E+3 2.07 7.0 E-1 1.18 3.39 E+3 La-140 2.1 E-1 1.58 8.0 E-1 5.84 E+2 Ce-141 2.6 E-1 3.43 2.32 1.08 8.86 E+3 Ce-143 4.94 E-2 6.0 E-1 4.47 E-2 2.0 E-1 1.67 E+4 Ce-144 9.59 1.99 E+2 7.47 E+1 4.43 E+1 6.04 E+4 ND-239 1.92 E-3 3.53 E-2 3.47 E-3 1.08 E-2 7.13 E+2 5.0 Gaseous Effluent Dose Calculation 5.1 Dose from Noble Gases in Gaseous Effluent The air dose in unrestricted areas due to noble gases released in gaseous effluents is calculated using the following expressions:
5.1.1 For historical meteorology:
Dy
=
3.17 x 10-8 I Mi [(x/Q)
Qi]
D
=
3.17 x 10-8 1 Ni [(X/Q)
Qi]
1 where:
Dy
= the total gamma air dose from gaseous effluents, in mrad D
= the total beta air dose from gaseous effluents, in mrad Mi
=
the air dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per 4Ci/m3 from Table 3-1 Ni
= the air dose factor due to beta emissions for each identified noble gas radionuclide, i, in mrad/yr per LCi/m 3 from Table 3-1.
(X/Q) =
6.1E-5 sec/m 3.
The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary.
=
the amount of noble gas radionuclide, i, released in gaseous effluents.
5.1.2 For meteorology concurrent with release:
Dy0 =
1.14x104 Mi E ( tj (X/Q)j o Qij)]
(5-3) i j
(5-4)
D 0 =
- 1. 1 4x10 IN.
[Y ( t. (X/Q)
Q )]
9 1
3 jo ij where:
DyO = the total gamma air dose from gaseous effluents in sector 9, in mrad.
DpO = the total beta air dose from gaseous effluents in sector 0, in mrad Mi
= the air dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per uCi/m3 from Table 3-1 Ni
= the air dose factor due to beta emissions for each identified noble gas radionuclide, i, in mrad/yr per p Ci/m 3 from Table 3-1 tj
=
the length of the jth time period over which (X/Q) jo and Qij are averaged for gaseous releases in hours j/
=
the atmospheric dispersion factor for time period At1 at exclusion boundary location in sector a determined by concurrent meteorology, in sec/m3 ij =the average release rate of radionuclide, i, in gaseous effluents during time period, Atj, inMCi/sec 5.2 Dose from Radioiodines, Radioactive Material in Particulate Form, and Radionuclides other than Noble Cases in Gaseous Effluents The dose to an individual from radioiodines, radioactive materials in particulate form and all radionuclides other than noble gases with half lives greater than eight days in gaseous effluents released to unrestricted areas is calculated using the following expressions:
5.2.1 For historical meteorology:
Do
=
3.17x10-8 v [(
RRik Wk) i (5-5) i k
where:
Do=
the total dose from gaseous effluents to an indivi dual, in mrem Q
=
the amount of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases with half lives greater than eight days, i, released in gaseous effluents.
SRik Wk the sum for all pathways k for radionuclide, i, of k
the Ri, W'product in mrem/yr per tCi/sec.
The Rik Wk value for each radionuclide, i, is given in k
Table 5-1.
The value given is the maximum v Rik Wk k
for all locations and is based on the most restrictive age -groups.
Rik
=
the dose factor for each identified radionuclide, i, for pathway k (for the inhalation pathway in mrem/yr per MCi/m 3 and for the food and ground plane pathways in m2 -
mrem/yr per ACi/sec) at the controlling location.
The dose factor is based on the maximum dose to the most restrictive age group. The Rik's for each controlling location are. given in Tables 5-2 thru 5-10.
Wk
=
the annual average dispersion parameter for estimating the dose to an individual at the controlling location for pathway k.
=
(X/Q) for the inhalation pathway in sec/m 3.
The (x/Q) for each controlling location are given in Tables 5-2 thru 5-10.
=
(D/Q) for the food and ground plane pathways in m-2 The (D/Q) for each controlling location are given in Tables 5-2 thru 5-10.
5.2.2 For meteorology concurrent with releases.
o = 1.14x10 4
[
At
(
RikO WjkO) Qij (5-6) i j k
where:
Do
=
the total dose from gaseous effluents to an indivi dual in sector G is mrem Atj
=
the length of the jth time period over which WjkO and Qij are averaged for gaseous releases in hours Qjj
=
the average release rate of radionuclide, i, in gaseous effluents during time period Atj in MCi/sec Rike = the dose' factor for each identified radionuclide, i, for pathway k for sector & (for the inhalation pathway in mrem/yr per uCi/m 3 and for the food and ground plane pathways in m2 - mrem/yr per uCi/sec) at the controlling location.
The dose factor is based on the maximum dose to the most restrictive age group. A listing of Rik for the controlling locations in each landward sector is given in Tables 5-2.thru 5-10. The sector e is determined by the concurrent meteorology.
Wjk6
=
the dispersion parameters for time period At for each pathway k for calculating the dose to an indivi dual at the controlling location in sector 9 using concurrent meteorological conditions.
(X/Q) for the inhalation pathway in sec/m3
=
(D/Q) for the food and ground plane pathways in m-2 TABLE 5-1 CONTROLLING LOCATION FACTORS Rik Wk Radionuclide mrem/yr per uCi/sec H -
3 9.18 E-3 Cr-51 1.47 E-1 Mn-54 2.04 E+1 Fe-59 1.09 E+1 Co-58 8.91 Co-60 2.21 E+2 Zn-65 3.10 E+1 Sr-89 3.09 E+2 Sr-90 1.25 E+4 Zr-95 1.35 E+1 Sb-124 3.24 E+1 I -131 5.75 E+2 I -133 1.40 E+1 Cs-134 2.92 E+2 Cs-136 3.65 Cs-137 3.01 E+2 Ba-140 2.95 Ce-141 5.07 TA 2
DOSE PARAMETER Ri for WNW Sector San Onofre Nearest Milk Location Beach Residence Pathway Distance 0.40 Miles 2.8 Miles 4.5 Miles X/Q 1.1 E-5 1.6 E-7 6.11 E-8 D/Q 2.5 E-8 3.4 E-10 1.18 E-10 Inhalation Food & Ground Inhalation Food & Ground Inhalation Food & Ground Pathway Pathway Pathway Pathway Pathway Pathway Radionuclide inrem/yr m2-mrem/yr marem/yr n2 -mren/yr mrem/yr m2-nrem/yr tCi/mj
)Ci/sec
/Ci/m3 MCi/sec 7PCi/m3
[Ci/sec 11-3 7.6 E+l 0
5.1 E+3 0
2.4 E+3 0
Cr-51 2.0 E+2 2.8 E+5 3.3 E+3 1.6 E+7 0
7.5 E+6 Mn-54 4.6 E+3 8.2 E+7 7.7 E+4 2.3 E+9 0
3.1 E+7 Fe-59 1.1 E+4 1.6 E+7 1.9 E+5 1.2 E+9 0
3.4 E+8 Co-58 6.3 E+3 2.3 E+7 1.1 E+5 9.9 E+8 0
9.1 E+7 Co-60 1.7 E+4 1.3 E+9 2.8 E+5 2.5 E+10 0
2.9 E+8 Zn-65 7.9 E+3 4.4 E+7 1.3 E+5 3.5 E+9 0
1.7 E+10 Sr-89 3.6 E+4 1.3 E+3 6.0 E+5 3.5.E+10 0
1.1 E+10 Sr-90 6.4 E+6 0
1.1 E+8 1.4 E+12 0
1.0 E+ll Zr-95 8.9 E+3 1.5 E+7 1.5 E+5 1.5 E+9 0
1.0 E+6 Sb-124 2.4 E+4 3.6 E+7 4.1 E+5 3.6 E+9 0
7.8 E+8 1-131 9.6 E+5 1.0 E+6 1.6 E+7 4.8 E+10 0
1.0 E+12 1-133 2.3 E+5 1.5 E+5 3.8 E+6 8.1 E+8 0
9.6 E+9 Cs-134 6.7 E+4 4.1 E+8 1.1 E+6 3.3 E+10 0
5.4 E+10.
Cs-136 1.1 E+4 8.9 E+6 1.9 E+5 3.8 E+8 0
5.5 E+9 Cs-137 5.0 E+4 6.1 E+8 8.5 Et5 3.4 E+10 0
4.9 E+9 Ba-140 1.4 E+4 1.2 E+6 2.3 E+5 3.0 E+8 0
2.3 E+8 Ce-141 7.5 E+3 8.1 E+5 1.3 E+5 5.5 E+8 0
1.5 E+7
- 1 TABLE 5-3 DOSE PARAMETER Ri for NW Sector Lcation Vegtable Meat Pathway Family Milk Cattle Housin.'
Pathway Distance 2.2 Miles 4.0 Miles 1.8 Miles 4.5 Miles
/q
- 3.
E-7 5.9 E-7 8.5 E-8 1.3 E-9 3.4 E-10 2.2 E-9 2.6 E-10 Inhalation Food & Ground Inhalation Focd & Ground Inhalation Food & Ground Inhalation Food & Cround Pathway Pa~thway Pathway Pathwav Pathway Pathway Pathway Pahy Radionuclide mrea/yr M2-mrem/yr mre/yr 2-way Pahy PathayPeha Pathway
- y.
m-mcem/yr mrem/yr m-- mrem/yr mrem/yr m2-mrem/yr ACi/sec CCi/sec j, Ci/rn PCi/sec
.*jCilma ytCi/sec F-3 2.9 E+3 0
3.8 r+2 0
5.1 E+3 0
2.4 E+3 0
Cr-I 8.3 E+2 1.3 E+7 1.7 E+2 1.3 E+6 3.3 E+3 1.6 E+7 0
7.5 E+6 Y-n-54 1.9 E+4 1.3 E+9 3.9 E+3 9.2 E-+7 7.7 E+4 2.3 E+9 0
3.1 E+7 Fc-59 4.7 E+4 1.0 E+~9 9.4 E+3 1.8 E+9 1.9 E+5 1.2 S+9 0
3.4 E+8 Co-53 2.7 E-t4 7.0 E+8 5.3 E+3 3.3 "
+8 1.1 E+5 9.9 E+8 0
9.1 E+7 Co-60 7.1. E+4 8.6 Ei9 1.4 E+4 2.2 E5+9 2.8 E+5 2.5 E+10 02.E8 Zoi-65 3.3 E+4 2.9 E+9 6.7 E+3 1.1 E+9 1.3 E+5 3.5 E+9 0
2.9 E+10 Sr-89 1.5 E+5 3.5 Ei-10 3.0 E+4
- 4. 1E8 6.0 E+5 3.5 E+10 0
1.1 E+10 Sr-90 2.7 E+7 1.4 E+12 5.4 q6
.1.0 E+10 1.1 E+8 1.4 E+12 0
1.0 E+,12 Zrc-95 3.8 E+4 1.3 E+9 7.5 E 1-3 1.6 E+9 1.5 E+5 1.5 E+9 0
1.0 E+6 Sb-124 1.0 E 5 3.2 E+9 2.0 F+4 5.0 E+8 4.1 E+5 3.6 E+9 0
7.8 E+8 1-131 4.1 E+6 4.8 E-10 8.1 E+5 54
+/-91.6 E+7 4.8 E+10 0
1.0 E+-12 1-133 9.6 E+/-5 8.1 E+8 1.9 E+5
].. 55 3.8 E+6 8.1 E+8 0
9.6 E+9 Cs-134 2.8 E+5 2.7 E+10 5.6 E+4 1.6 E+9 1.1 E+6 3.3 E+10 0
5.4 E+10 Cs-136 4.8 E+4 2.6 E+8 9.7 E+3 5.3 E +7 1.9 5+5 3.8 E+8 0
5.5 5+9 Cs-137 2.1 E+5 2.7 E+10 4.2 E+4
- 1. 6 5-'-9 8.5 5+5 3.4 E+10 0
4.9 E+9 Ba-1410 5.7 E+4 2.8 E+8 1.1 E+4 5.8 E:+7 2.3 E+5 3.0. 5+8 0
2.3 E+8 Ce-14]
3.2 E+4 5.4 5+8 6.3 E+3 3,3 E+7 1.3 E+5 5.5 E+8 0
1.5 ET7 S.
TABLE 5-4 DOSE PARAMETER Ri for NNW Sector Vegetable Mobile Milk Meat Pathway Location Garden Homes Pathway (Cattle)
Distance 2.2 Miles 1.18 Milea 4.5 Miles 4.5 Miles X/Q 4.1 E-7 1.8 E-6 9.0 E-8 9.0 E-8 D/Q 1.9 F-9 8.8 E-9 3.7 E-10 3.7 E-10 Inhalation Food & Ground Inhalation Food & Ground Inhalation Food & Ground Inhalation Food & Ground Pathway Pathway Pathway P-thway Pathway Pathway Pathway Pathway Radionuclide mren/yr m2 -mrem/yr mrem/yr M2 -mrem/yr mrem/yr m2 -mrem/yr mrem/yr m2 -mrem/yr ILCi/mj -
PCi/scc pCi/m3 IACi/sec JACi/m iCi/sec uACilmj PCilsec H-3 2.9 E+3 0
5.1 E+3 0
2.4 E+3 0
3.8 E+2 0
Cr-51 8.3 E+2 1.3 E+7 3.3 E+3 1.6 E+7 0
7.5 E+6 1.7 E+2 1.8 E+6 Mn-54 1.9 E+4 1.3 E+9 7.7 E+4 2.3 E+9 0
3.1 E+7 3.9 E+3 9.2 E+7 4.7 E+4 1.0 Et9 1.9 E+5 1.2 E+9 0
3.4 E+8 9.4 E+3 1.8 E+9 Co-58 2.7 E+4 7.0 E+8 1.1 E+5 9.9 E+8 0
9.1 E+7 5.3 E+3 3.3 E+8 Co-60 7.1 E+4 8.6 E9 2.8 E+5 2.5 E+10 0
2.9 E+8 1.4 E+4 2.2 E+9 Zn-65 3.3 E+4 2.9 E+9 1.3 E+5 3.5 E+9 0
1.7 E+10 6.7 E+3 1.1 E+9 Sr-89 1.5 E+5 3.5 E+10 6.0 E+5 3.5 E+10 0
1.1 E+10 3.0 E+4 4.1 E+8 Sr-90 2.7 E+7 1.4 E+12 1.1 E+8 1.4 E+12 0
1.0 E+11 5.4 E+6 1.0 E+10.
Zr--95 3.8 E+4 1.3 E+9 1.5 E+5 1.5 E+9 0
1.0 E+6 7.5 E+3 1.6 E+9 Sb-124 1.0 E+5 3.2 E+9 4.1 E+5 3.6 E+9 0
7.8 E+8 2.0 E+4 5.0 E+8 1-131 4.1 E+6 4.8 E+10 1.6 E+7 4.8 E+10 0
1.0 E+12 8.1 E+5 5.4 E+9 1-133 9.6 E+5 8.1 E+8 3.8 E+6 8.1 E+8 0
9.6 E+9 1.9 E+5 1.2 E+5 Cs-134 2.8 E+5 2.7 E+10 1.1. E+6 3.3 2+10 0
5.4 Z+10 5.6 E+4 1.6 E+9 Cs-L36 4.8 E+4 2.6 E+8 1.9 E+5 3.8 E+8 0
5.5 E+9 9.7 E+3 5.3 E+7 Cs-137 2.1 E+5 2.7 Z+10 8.5 E+5 3.4 E+10 0
4.9 E+9 4.2 E+4 1.6 E+9 Ba-140 5.7 E+4 2.8 E+8 2.3 E+5 3.0 E+8 0
2.3 E+8 1.1 E+4 5.8 E+7 Ce-141 3.2 E+4 5.4 E+8 1.3 E+5 5.5 E+8 0
1.5 E+7 6.3 E+3 3.3 E+7 TABLE 9 DOSE PARAMETER R-for N Sector Milk Location Pathway Distance 4.5 Miles X/Q 6.9 E-8 D/Q 3.5 E-10 Inhalation Food & Ground Pathway Pathway Radionuclide mrem/yr m2-mrem/yr pCi/mj YCi/sec H-3 2.4 E+3 0
Cr-51 0
7.5 E+6 Mn-54 0
3.1 E+7 Fe-59 0
3.4 E+8 Co-58 0
9.1 E+7 Co-60 0
2.9 E+8 Zn-65 0
1.7 E+10 Sr-89 0
1.1 E+10 Sr-90 0
1.0 E+11 Zr-95 0
1.0 E+6 Sb-124 0
7.8 E+8 1-131 0
1.0 E+12 1-133 0
9.6 E+9 Cs-134 0
5.4 E+10 Cs-136 0
5.5 E+9
.Cs-137 0
4.9 E+9 Ba-140 0
2.3 E+8 Ce-141 0
1.5 E+7 TABLE Ai DOSE PARAMETER Ri for NE Sector Milk Location Pathway Distance 4.5 Miles x/Q 4.5 E-8 D/Q 2.9 E-10 Inhalation Food & Cround Pathway Pathway Radionuclide nrem/yr m2 -mrem/yr Ci/m3 YCi/sec 11-3 2.4 E+3 0
Cr-51 0
7.5 E+6 Mn-54 0
3.1 E+7 Fe-59 0
3.4 E+8 Co-58 0
9.1 E+7 Co-60 0
2.9 E+8 Zn-65 0
1.7 E+10 Sr-89 0
1.1 E+10 Sr-90 0
1.0 E+11 Zr-95 0
1.0 E+6 Sb-124 0
7.8 E+8 1-131 0
1.0 E+12 1-133 0
9.6 E+9 Cs-134 0
5.4 E+10 Cs-136 0
5.5 E+9 Cs-137 0
4.9 E+9 Ba-140 0
2.3 E+8 Ce-141 0
1.5 E+7 TABLE DOSE PARAMETER Ri for NNE Sector Milk Location Pathway Distance 4.5 Miles X/Q 6.0 E-8 D/Q 3.2 E-10 Inhalation Food & Ground Pathway Pathway Radionuclide mrem/yr m12-mrem/yr YCi/m 3 uCi/sec 11-3 2.4 E+3 0
Cr-51 0
7.5 E+6 Mn-54 0
3.1 E+7 Fe-59 0
3.4 E+8 Co-58 0
9.1 E+7 Co-60 0
2.9 E+8 Zn-65 0
1.7 E+10 Sr-89 0
1.1 E+10 Sr-90 0
1.0 E+ll Zr-95 0
1.0 E+6 Sb-124 0
7.8 E+8 1-131 0
1.0 E+12 1-133 0
9.6 E+9 Cs-134 0
5.4 E+10 Cs-136 0
5.5 E+9 Cs-137 0
4.9 E+9 Ba-140 0
2.3 E+8 Ce-141 0
1.5 E+7 TABLE DOSE PARAMETER R-for ENE Sector Milk Location Pathway Distance 4.5 Miles X/Q 4.8 E-8 D/Q 3.4 E-10 Inhalation Food & Ground Pathway Pathway Radionuclide mrem/yr m2 -mrem/yr IPCi/m3 pCi/sec H-3 2.4 E+3 0
Cr-51 0
7.5 E+6 Mn-54 0
3.1 E+7 Fe-59 0
3.4 E+8 Co-58 0
9.1 E+7 Co-60 0
2.9 E+8 Zn-65 0
1.7 E+10 Sr-89 0
1.1 E+10 Sr-90 0
1.0 E+11 Zr-95 0
1.0 E+6 Sb-124 0
7.8 E+8 1-131 0
1.0 E+12 1-133 0
9.6 E+9 Cs-134 0
5.4 E+10 Cs-13 6 0
5.5 E+9 Cs-137 0
4.9 E+9 Ba-140 0
2.3 E+8 Ce-141 0
1.5 E+7 TABLE DOSE PARkAMETER R-for E Sector Milk Location Pathway Distance 4.5 Miles X/Q 5.8 E-8 D/Q 4.7 E-10 Inhalation Food & Ground Pathway Pathway Radionuclide mrem/yr m1 2 -mrem/yr Ci/m uPCi/sec 11-3 2.4 E+3 0
Cr-51 0
7.5 E+6 Mn-54 0
3.1 E+7 Fe-59 0
3.4 E+8 Co-58 0
9.1 E+7 Co-60 0
2.9 E+8 Zn-65 0
1.7 E+10 Sr-89 0
1.1 E+10 Sr-90 0
1.0 E+l1 Zr-95 0
1.0 E+6 Sb-124 0
7.8 E+8 1-131 0
1.0 E+12 1-133 0
9.6 E+9 Cs-134 0
5.4 E+10 Cs-136 0
5.5 E+9 Cs-137 0
4.9 E+9 Ba-140 0
2.3 E+8 Ce-141 0
1.5 E+7 DOSE PARAMETER Ri for ESE Sector Camp Milk Location Store Pathway Distance 0.89 Miles 4.5 Miles X/Q 2.7 E-6 7.0 E-8 D/Q 2.8 E-8 5.8 E-1.0 Inhalation Food & Ground Inhalation Food & Ground Pathway Pathway Pathway Pathway Radionuclide mrem/yr m2 -mrem/yr mrem/yr m2-mrem/yr MCi/m 3 jCi/sec tLCi/m 3 ktCi/sec 11-3 2.9 E+2 0
2.4 E+3 0
Cr-51 7.6 E+2 1.1 E+6 0
7.5 E+6 Mn-54 1.8 E+4 3.2 E+8 0
3.1 E+7 Fe-59 4.3 E+4 6.2 E+7 0
3.4 E+8 Co-58 2.4 E+4 8.7 E+7 0
9.1 E+7 Co-60 6.5 E+4 4.9 E+9 0
2.9 E+8 Zn-65 3.1 E+4 1.7 E+8 0
1.7 E+10 Sr-89 1.4 E+5 4.9 E+3 0
1.1 E+10 Sr-90 2.5 E+7 0
0 1.0 E+11 Zr-95 3.4 E+4 1.7 E+8 0
1.0 E+6 Sb-124 9.3 E+4 1.4 E+8 0
7.8 E+8 1-131 3.7 E+6 3.9 E+6 0
1.0 E+12 1-133 8.8 E+5 5.6 E+5 0
9.6 E+9 Cs-134 2.6 E+5 1.6 E+9 0
5.4 E+10 Cs-136 4.4 E+4 3.4 E+7 0
5.5 E+9 Cs-137 1.9 E+5 2.3 E+9 0
4.9 E+9 Ba-140 5.2 E+4 4.7 E+6 0
2.3 E+8 Ce-141 2.9 E+4 3.1 E+6 0
1.5 E+7 6.0 Projected Doses 6.1 Liquid Dose Projection The methodology used for projecting a liquid dose is as follows
- 1. Determine the average monthly release for the previous twelve months for each radionuclide.
- 2. Using the average monthly release, project a dose using the methodology of Section 4.0.
6.2 Gaseous Dose Projection The methodology used for projecting a gaseous is as follows.
- 1. Determine the average monthly release for the previous twelve months for each radionuclide.
- 2. Using the average monthly release, project a dose using the methodology of Sections 5.1.1 and 5.2.1.
0 7.0 Operability of Equipment The flow diagrams defining the treatment paths and the components of the radioactive liquid, gaseous and solid waste management systems are shown in Figures 7-1 thru 7-3.
EQA.DA#COOLANT RIA RC W SE A
HM A
IdALV!LA STAOAAGE TAANKA
&CONENSE6Z STEAM IW CLWT FLOO TANKI MEXILIARY W=LPLEOAGLfaN PUILING SY MTO*ST A
DRASTOAN TAANKIT!
FO~TA
~OR D
AUXILAR STE OL.L G =, BDIN G AN STTNA a
A&O*FO4 SNFI I
LAS 0
DRAIN
____TANK__
_TANKS_
50 CLiqui wat-dichrg syst -- ENTT CIECONTA~ffiFigure 7.1WAM
GASES FROM:
SURGE TANK DECAY TANKS A
T 125 FT3 3-125 FT3 SYSTEM
- 1. GASSTRIPPER
- 2. FLASH TANK
- 3. GASEOUS VENTS GASEOUS WASTE SYSTEM REACTOR CONTAINMENT FN AIR A
A TURBINE AREA SEAL.TCONDENSEER I
CONDENSER AIR CONTAINMENT,.AUXILIARY BUILDING AND TURBINE AREA VENTILATION SYSTEM Radioactive gaseous-waste system Figure 7.2
IN C 01"1 C
D*
I DALAS I.NK
~
~
0 tO L0~~I LLE
- TSI CN IIEWSE V--s C--~c,
.503 IMFL~O T
PpTOO CA$,.
DRU T...CCN5-RUMSSI FILTERS~~OLI WASTE1A HANDLING-D-l CS R
Fiur 7.3
.. AL
8.0 Sample Locations The Radiological Environmental Monitoring Sample Locations are identified in Figures 8-1, 8-2 and 8-3.
These sample locations are described in Tables 8-1 and indicate the direction and distance from the center of the building complex of the unit.
Page 1 of 4 TABLE 8-1
.RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS Type of Sample and Distance Sampling Location (Mi)
Direction Airborne City of San Clemente 5.0 NW Camp San Onfore 2.3 NE Huntington Beach Generating Station 37 WNW Unit 1 East Site Boundary 0.1 NNE Soil Samples Camp San Onfore 3.0 NE Old-Route 101 3.0 SE Basilone Road Freeway Offramp 1.6 NW Huntington Beach Generating Station 37 WNW Site Boundary 0.1 NNE Ocean Water Station Discharge Outfall 0.5 SW Newport Beach 30 NW Page 2 of 4 TABLE 8-1 cont.
Type of Sample and Distance Sampling Location (Mi)
Direction Direct Radiation San Clemente City 5.0 NW Camp San Mateo 3.8 N
Camp San Onfore 3.0 NE Camp Horne 4.5 E
Camp Las Pulgas 8.8 ESE Old Route 101 3.0 SE Old Route 101 0.5 ESE Non-Commissioned Officers Beach Club 1.0 NW Basilone Road Freeway Offramp 1.6 NW Bluff 0.5 NW Visitors Center 0.1 NNE South Edge of Switchyard 0.2 SE Site Boundary 0.1 SE Huntington Beach Generating Station 37 WNW Drinking Water Tri-Cities Municipal Water District 8.7 NW Reservoir Local Well 3.5 NW Huntington Beach City
- 37.
WNW
-3 4-
Page 3 of 4 TABLE 8-1 cont.
Type of Sample and -Distance Sampling Location (Mi)
Direction Beach Sand Station Beach 0.5 SE Surfing Beach 1.4 NW San Onfore State Beach 4.1 SE Newport Beach 30 NW Local Crops San Mateo Canyon 2.1 NW Near Oceanside 23 SE Non-Migaratory Marine Animals Station Discharge Outfall 0.6 SW Newport Beach 30 NW Kelp San Mateo Kelp Bed 2.9 WNW Barn Kelp Bed 6.6 SSE San Onofre Kelp Bed 1.6 SSW Newport Beach 30 NW Page 4 of 4 TABLE 8-1 cont.
Type of Sample and Distance Sampling Location (Mi)
Direction Ocean Bottom Sediments East of Station Discharge Outfall 0.5 SW West of Station Discharge Outfall 0.5 SW Newport Beach 30 WNW LEGEND DIRECT RADiATION STATIONS Oan 0 THRu 13)
DRINKING WATER (1)
LOCAL CROPS (102)"
SAN LEM 0\\ JACKRABBITS (1)
,CAM' 0 SoL SAMPLES (,2,3 & 5)
M OPARTICULATE AIR Son Mateo Point PENDLETON SAMPLERS (I THRU 3)
PE \\v4N 3 STATION 2 LOCATED SAN ONOFRE \\SITE D
MI SSE OCEANSIDE 0
5 SCALE IN MILES SAN ONOFRE OCEANSIDE NUCLEAR GENERATING STATION UNIT I FIGURE 8-1 TERRESTRIAL MONITORING FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- Sour, rSAN MATEO KELP BED OUTFALL24 BARN KELP BED D
_0G 6-INTAKE 30 OC6 F
A -
OCEAN WATER SAMPLE B -
BEACH SAND SAMPLES C - OCEAN BOTTOM SEDIMENT SAMPLES E
D - ZONE FOR CRUSTACEA SAMPLING E -
ZONE FOR MOLLUSK SAMPLING NWKL E
F - ZONE FOR FISH a SEAHARE SAMPLING0G G - KELP SAMPLES 4
O 1000- 2000 3000 4000 FEET FIGUREC8A2OGA PHIC MONITORING STATIONS FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING
HJNTINGTON BEACH CONTROL STATION CONTROL STATION NEAR NEWPORT BEACH SAN ONOFRE NUCLEAR GENERATING STATION 10 OCEANSIDE CONTROL STATION 0
0 5
10 20 APPROXIMATE SCALE IN MILES FIGURE 8-3 CONTROL STATIONS FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3 6c