ML17285A262
| ML17285A262 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 11/30/1988 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17285A259 | List: |
| References | |
| PROC-881130-01, NUDOCS 8902230548 | |
| Download: ML17285A262 (98) | |
Text
CONTROLLED COP YNovember 1988 WNP-2 OFFSITE DOSE CALCULATION MANUAL (ODCN)
The following instructional information and checklist is furnished to help you insert Amendment No. 6 into the Washington Public Power Supply System Plant No. 2 ODCN.
Discard the old sheets and insert the new sheets as listed below. Keep these instructions to serve as a record of changes.'f you have questions concerning insertion of this amendment, or if you are missing any pages, please contact Bernice Kasko/Linda Wilson (509) 377-2369.
DISCARD INSERT'EW OLD PAGE PAGE List of Effective Pages (LEP LEP-5) List of Effective Pages (LEP-1 LEP-5) 1V 1V 2 2 6 6 through through 8 8 15 15 17 17 18 18 26 26 27 27 29 29 through through
. 32 32 32a 32b 34 34 through through 37 37 44 44 47 47 48 48 50 50 52 52 53 53 55 55 through through 57 57 61 61 through through 67 67 71 71 86 86 88 88 90a 90b 106 890223054S S90215 106 PDR ADOCK 05000397 R PDC
CGNTRGLLEG CQPY 0
AMENDMENT NO. 6, November 1988 CONTROLLED COPY WNP-2 OFFSITE DOSE CALCULATION MANUAL (ODCM)
List of Effective Pages
~Pa e Amendment 1V CHAPTER 1 CHAPTER 2 2' 6 3
3 5 3 6 6 7 6 8 6 9 0 10 3 11 3 12 3 12a 3 12b 5 13 0 14 0 15 6 16 3 17 6 18 6 LEP-1
CGNTIRGLLEG CQPY ANENONENT NO. 6 November 1988 CONTFIIGLILFG CGPY
~Pa e Amendment 19 19a 20 21 22 3 23 3 24 2 25 2 26 6 27 6 28 5 28a 5 29 6 30 6 31 6 32 6 32a 6 32b 6 CHAPTER 3 33 0 34 6 35 6 36 6 37 6 38 3 39 3 40 3 41 3 42 3 43 3 44 6 45 3 LEP-2
CGMTIRQLLEG COPY ANENONENT NO. 6 November 1988 CGNYIRGLLED COPY
~Pa e Amendment 46 47 48 49 50 51 52 53 6 54 3' 54a 55 6 56 6 57 6 58 0 59 3 60 3 61 6 62 6 63 6 63a 6 64 6 65 6 66 6 67 6
,68 3 69 3 70 3 71 6 72 3 73 0 74 0 75 0 76 0 77 0 LEP-3
CGNTBGLLEG CQPY ANENONENT NO. 6 November 1988 CGN'II'FIICILLED CGP Y Pa<ac Amendment 78 79 80 81 82 83 84 85 86 87 88 89 90 90a 90b CHAPTER 4 91 91a CHAPTER 5 92 93 94 95 96 97 98 99 100 101 102 103 LEP-4
CGN7RGLLEG CQPY AMENONENT NO. 6 November 1988 Pa(ac Amendment 104 105 3 106 107 108 0 109 0 110 3 1,1 1 3 LEP-5
CGNTRGLLEG CGPY AMENDMENT NO. 6 November 1988 CONTROLLED COPY Tab 1 e Ti tl e ~Pe e Input Parameters Needed for Calculating Dose to the Maximum Individual from WNP-2 Gaseous Effluent"...... 71 3-10 Reactor Building Stack X/Q and D/Q Values .......... -73
.3-11 Turbine Building X/Q and D/Q Values . . . . . . . . . . . . . 77 3-12 Radwaste Building X/Q and D/Q Values . . . . . . . . . . . . . 81 3-13 Characteristics of WNP-2 Gaseous Effluent Release Points . . . 85 3-14 References for Values Listed in Table 3-9 . . . . . . . . . . 86 3-15 Design Base Percent Noble Gas (30-Minute Decay) . . . . . . . 87 3-16 Annual Doses at Special Locations Within WNP-2 Site Boundary.
Source: WNP-2 Gaseous Effluent .- . . . . . . . . . . . . . . 88 3-17 Annual WNP-2 Site Boundary .....................
Air Dose at Special Locations Within 89 Section 5.0 5-1 Radiological Environmental Monitoring Program Plan . ~ ~ ~ ~ e 98 5-2 WNP-2 REHP Locations . . . . . . . . . . . . . . . . . . . . . 102 5-3 Environmental Radiological Monitoring Program Annual Summary . 108 Reporting Levels for Nonroutine Operating Reports . . . . . . 109 LIST OF FIGURES
~Fi ure Title Pa<ac 2-1 Simplified Block Diagram of Liquid Waste System 32a 2-2 Simplified Block Diagram of Solid Radwaste System 32b 3-1 Site Boundary for Radioactive Gaseous and Liquid Effluents 90 3-2 Simplified Block Diagram of Gaseous Waste System . 90a 3-3 Simplified Block Diagram of Off-Gas Treatment System . 90b 5-1 Radiological Environmental Monitoring Sample Locations Inside of 10-Mile Radius . 106 5-2 Radi ol ogi ca 1 Environmental Outside of 10-Mile Radius Moni toring Samp1 e Loca ti ons 107 iv
CGNTBOLLEQ COPY AHENDHENT NO. 6 November 1988 CGNTIRGLLEG CQPY 2.0 LI UID EFFLUENT DOSE CALCULATION 2.1 Introduction Liquid radwaste released from NNP-2 will meet 10 CFR 20 limits at the point of discharge to the Columbia River. This design objective will be kept at all times. Actual discharges of liquid radwaste effluents will only occur on a Batch Basis, and the average concentration at the point of discharge will be only a small percentage of the allowed limits. A simplified block diagram of the liquid waste management system and effluent pathways is contained in Figure 2-1. Solid radioactive wastes are disposed of by way of an approved disposal site. A simplified block diagram of the solid radwaste system is described in Figure 2-2.
The cumulative quarterly dose contributions due to radioactive liquid efflu-ents released to the unrestricted areas will be determined once every 31 days using the LADTAP II computer code. The maximum exposed individual is assumed to be an adult whose .exposure pathways include potable water and fish consump-tion. The choice of an adult as the maximum exposed individual is based on the highest fish and water consumption rates shown by that age group and the fact that most of the dose from the liquid effluent comes from these two pathways.
The dose contributions will be calculated for all radionuclides identified in the released effluent. The calculations are based on guidelines provided by Nureg-0133 and the LADTAP II computer code.
The methods for calculating the doses are discussed in Section 2.4 of this manual.
2.2 Radwaste Li uid Effluent Radiation Honitorin S stem This monitoring subsystem measures the radioactivity in the liquid effluent prior to its entering the cooling tower blowdown line.
CGMTRGLLEG CQPV 0
p
AMENONENT NO. 6 November 1988 CGNTIRGLLED COPY unrestricted area would be calculated according to Equation (3) and Equa-tion (4). To show compliance with 10 CFR 20, the two equations must again hold.
2.4 10 CFR 50 A endix I Release Rate Limits Technical Specification 4.11.1.2 requires that the cumulative dose contribu-tions be determined in accordance with the OOCN at least once per 31 days.
Technical Specification 3.11.1.2 specifies that the dose to a member of the public from radioactive material in liquid effluents released to the unre-stricted area shall be limited to:
< 1.5 mrem/Calendar quarter - Total Body and
< 5.0 mrem/Calendar l}uarter Any Organ.
The cumulative dose for the calendar year shall be limited to:
< 3 mrem Total Body and
< 10 mrem Any Organ.
The dose contribution will be calculated for all radionuclides identified in the liquid effluent released to the unrestricted area, using the following equation:
m D< =g(A,. get Ci F ) (5) i g,=l where:
The cumulative dose commitment to the total body or organ,~, from liquid effluents for the total time period in mrem.
g 4tR L=l
CGNTRGLLEG COPY AMENDMENT NO. 6 November 1988 CONTROLILEG COP'%I" The length of the ath time period over which C.45 and Fg are averaged for all liquid releases, in hours.
The number of releases for the time period under consideration.
The average concentration of radionuclide, i, in undiluted liquid e'ffluent during time periodAta from any liquid release, in pCi/ml.
The site-related ingestion dose commitment factor to the total body or any organ ~ for each identified principle gamma and beta emitter listed in Table 2-2, in mrem/hr per >Ci/ml.
The near field average dilution factor for C-1X during any liquid waste release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times 500.
Li uid Radioactive Waste Flow fw Discharge Structure Exit Flow x 500 ft x 500
CGNTROLLEQ CQPY AMENDMENT NO. 6 November 1988 CGNYIRGLLEG CQPY The term A, the ingestion dose factors for the total body and critical organs, are tabulated in Table 2-2." It embodies the dose factor, fish bioac-cumulation factor, pathway usage factor, and the dilution factor for the plant diffuser pipe to the Richland potable water intake. The following equation was used to calculate the ingestion dose factors:
U
= + (7)
Ai> Ko(D UP BPi)DP w
where:
The composite dose parameter For total body or criti-cal organ of an adult for nuclide i (in mrem/hr per p,Ci/ml) .
K A conversion factor:
1.14E+05 = (10 6 pCi/pCi) x (10 3 ml/liter) :
8760 hr/yr.
Uw 730 liter/yr which is the annual water consumption by the maximum adult (Table E-4 of Regulatory Guide 1.109, Revision 1).
Bioaccumulation factor for radionuclide i in fish (pCi/Kg per pci/liter) (Table A-1 of Regulatory Guide 1.109, Revision 1 and NUREG/CR-4013).
Dp ~ Adult ingestion dose conversion factor for nuclide i
- Total body or critical organ (mrem/pCi) (Table E-11 of Regulatory Guide 1.109, Revision 1 and NUREG/CR-4013).
'w Dilution factor from near Field area to the Richland potable water intake - 100.
Adult fish consumption, 21 kg/yr (Table E-5 of Regulatory Guide 1.109, Revision 1).
CGNTROLLEG CQPV V IV
ANENDNENT NO. 6 November 1988 CGNTIRGLLED CGPY d ~ The deposition rate of nuclide i, in pCi/m per hour.
The flow rate of the liquid effluent, in ft /sec.
The fraction of the year crops are irrigated, dimensionless.
iA The stable. element transfer coefficient that relates the daily intake rate by an animal to the concen-tration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal pro-duct) per pCi/day.
The mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food), dimensionless.
The effective "surface density" for soil, in kg (dry soil)/m 2 (Table E-15, Regulatory Guide 1.109, Revision 1).
QAw The consumption rate of contaminated water by an animal, in liters/day.
QF The consumption rate of contaminated feed or forage by an animal, in kg/day (wet weight).
Q; The release rate of nuclide i, in Ci/yr.
The fraction of deposited activity retained on, crops, dimensionless (Table E-15, Regulatory Guide l.'109, Revision 1).
15
CGNYRGLLEG CQPY ANENONENT NO. 6 CONTIROLLED Cop'r November 1988 The shoreline width factor, dimensionless (Table A-2, Regulatory Guide 1.109, Revision 1).
Y The agricultural productivity (yield), in kg (wet weight) /m (Table E-15, Regulatory Guide 1.109, Revision 1).
XE; The effective removal rate constant for radionuclide i from crops, in hr,-1 where XE. = x. + x W' El 1 1
is the radioactive decay constant, and A, w
is the removal rate constant for physical loss by weathering (Regulatory Guide 1.109, Revision 1, Table 8-15).
The radioactive decay constant of nuclide i, in hr 1100 The factor to convert from (Ci/yr)/(ft /sec) to pCi/1 i ter.
110,000 The factor to convert From (Ci/yr)/(ft /sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.
These equations yield the dose rates to various organs of individuals from the exposure pathways mentioned above.
2.7.2 Plant Parameters WNP-2 is a river shoreline site with a variable efFluent discharge'low rate 0 to 7500 gpm. The population center nearest WNP-2 is the city of Richland, where drinking water withdrawal takes place. The applicable dilution factor is 50,000, using average river flow. The time required for released liquids 17
CGNTRGLLEG COPY (5
to
AMENDMENT NO. 6 November 1988 CONTIRGLLED CGPY leased liquids to reach Richland, approximately 12 miles downstream, is esti-mated at 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Richland is the "realistic case" location, and doses cal-culated for the Richland location are typically applicable to the population as a whole. Individual and population doses based on Richland parameters are calculated for all exposure pathways.
Only the population downstream of the WNP-2 site is affected by the liquid effluents released. There is no significant commercial fish harvest in the 50-mile radius region around MNP-2. Sportfish harvest is estimated at 14,000 kg/year.
for irrigated foods exposure pathways, it can be assumed that production with-in the 50-mile radius region around MNP-2 is sufficient to satisfy consumption requirements.
Other relevant parameters relating to the irrigated foods pathways are d fined as follows:
d
~ood Tvae (liter/m /mo) (kg/m ) (Days)
Vegetation 150 5.0 70 Leafy Vegetation 200 1.5 70 Feed for Milk Cows 200 1.3 30 Feed for Beef Cattle 160 2.0 130 Source terms are measured based on sampled effluent.
Table 2-3 summarizes the LADTAP II input parameters. Documentation and/or calculations of these parameters are discussed in detail in R P.I. 2.3, and ~
Rad. Prog. ca 1 cul at i on Log 88-3.
18
CONTROLLED CQPV AMENDMENT NO. 6 November 1988 CGNTFtGLLEG "CQP"f
Table 2-1 FISH BIOACCUHULATION FACTORS (BF.)
AND ADULT INGESTION DOSE CONVERSION FACTORS (DFi)
.Dose Conversion Factor (DF,.)
Fish Bioaccumulation Total GI Nuclide Factor (BF,.) Body Bone Thyroid Liver Tract (pCi/kg per . (mRem per pCi Ingested) pCi/1 i ter) 9.0E-01 6.0E-OB (3) 6.0E-OB 6.0E-OB 6.0E-OB Na-24 1.0E+02 1.7E-06 1.7E-06 1.7E-06 1.7E-06 1.7E-06 P-32 1.0E+05 7.5E-06 . 1.9E-04 (3) 1.2E-05 2.2E-05 Cr-51 2.0E+02 2.7E-09 (3) 1.6E-09 (3) 6.7E-07 Mn-54 4.0E+02 8.7E-07 (3) (3) 4.6E-06 1.4E-05 Nn-56 4.0E+02 2.0E-OB (3) (3) 1.2E-07 3.7E-06 Fe-55 1.0E+02 4.4E-07 2.8E-06 (3) 1.9E-06 1.1E-06 Fe-59 1.0E+02 3.9E-06 4.3E-06 (3) 1.0E-05 3.4E-05 Co-58 5.0E+01 1.7E-06 (3) (3) 7.5E-07 1.5E-05 Co-60 5.0E+01 4 'E-06 (3) (3) 2.1E-06 4.0E-05 Ni-65 1.0E>02 3.1E-OB 5.3E-07 (3) 6. 9E-08 1. IE-06 Cu-64 5.0E+01 3.9E-OB (3) (3) 8.3E-OB 7.1E-06 Zn-65 2.0E+03 7.0E-06 4.8E-06 (3) 1.5E-05 9.7E-06 Zn-69m 2.0E+03 3.7E-OB 1.7E-07 (3) 4.1E-07 2.5E-05 As-76 1.0E+02 4.8E-06 (3) (3) (3) 4.4E-05 Br-82 4.2E+02 2.3E-06 (3) (3) (3) 2.6E-06 Br-83 4.2E+02 4.0E-OB (3) (3) (3) 5.8E-OB Br-84 4.2E+02 5.2E-OB (3) (3) (3) 4.1E-13 Rb-89 2.0E+03 2.8E-OB (3) (3) 4.0E-OB 2.3E-21 Sr-89 3.0E+01 B.BE-06 3.1E-04 (3) (3) 4.9E-05 Sr-90 3.0E+Ol 1.8E-04 8.7E-03 (3) (3) 2.2E-04 26
CONTROLLED COPY AMENDMfNT NO. 6 November 1988 CGNTBGLLEG COPY Table 2-1 (contd.)
Dose Conversion Factor (DF,.)
Fish Bioaccumulation Total GI Nuclide Factor (BF.) Body Bone Thyroid Liver Tract (pCi/kg per (mRem per pCi Ingested) pCi/1 i ter)
Sr-91 3.0E+01 2.3E-07 5.7E-06 (3) (3) 2.7E-05 Sr-92 3.0E+01 9.3E-OB 2.2E-06 (3) (3) 4.3E-05 Y-90 2.5E+Ol 2.6E-10 9.7E-09 (3) (3) 1.0E-04 Y-91m 2.5E+01 3.5E-12 9.1E-ll (3) (3) 2.7E-10 Y-91 2.5E+Ol 3.8E-09 1.4E-07 (3) (3) 7,8E-05
- 2. 56.01 2.5E-11 8.5E-10 (3) 1.5E-05
'-92 (3)
Y-93 2.5E+01 7.4E-1'1 2.7E-09 (3) (3) 8.5E-05 Zr-95 3.3E+00 6.6E-09 3.1E-08 (3) 9.8E-09 3.1E-05 Nb-95 3.0f>04 1.9E-09 6.2E-09 (3) 3.5E-09 2.1E-05 lr-97 3.3E+00 1.6E-10 1.7E-09 (3) 3.4E-10 1.1E-04 Nb-97 3.0E+04 4.8E-12 5'.2E-11 (3) 1.3E-11 4.9E.-OB Mo-99 1.Of+01 8.2E-07 (3) (3) 4.3E-06 1.0E-05 Tc-99m 1.5E+Ol 8.9E-09 2.5E-10 (3) 7.0E-10 4.1E-07 Tc-101 1.5E+01 3.6E-09 2.5E-10 (3) 3.7E-10 1.1E-21 Ru-103 1.0E+01 8.0E-OB 1.9E-07 (3) (3) 2.2E-05 RU-105 1. Of+01 6.1E-09 1.5E-08 (3) (3) 9.4E-06 Rh-105 1.0E+Ol 5.8E-OB 1.2E-07 (3) 8.9E-OB 1.4E-05 Ru-106 1.0E+Ol 3.5E-07 2.8E-06 (3) (3) 1.8E-04 Ag-110m 2.3E+00 8.8E-OB 1.6E-07 (3) 1.5E-07 6.0E-05 Sb-124 1.0E+00 1.1E-06 2.8E-06 6.8E-09 5.3E-OB B.OE-05 Sb-125 1.Of+00 4.3E-07 1.8E-06 1.8E-09 2.0E-OB 2.'OE-05 Sb-126 1.0E+00 4.2E-07 1.2E-06 7.0E.09 2.3E-OB 9.4E-05 Sb-127 1.Of+00, 9.9E-08 2.6E-07 3.1E-09 5.7E-09 5.9E-05 Te-127 4.0E+02 2.4E-08 1.1E-07 8.2E-OB 4.0E-OB 8.7E-06 Te-129m 4.0E+02 1.8E-06 1.2E-05 4.0E-06 4.3E-06 5'.BE-05 Te-129 4.0E+02 7.7E-09 3.1E-OB 2.4E-08 1.2E-OB 2.4E-OB 27
CONTROLLED COPY AHENOHENT NO. 6 November 1988 CONTIROLLED 2-2 COP'II'able INGESTION OOSE FACTORS (A..) FOR TOTAL BOOY AND CRITICAL ORGAN (in mrem/hr per Ci/ml)
Liquid Effluent Total Gi Nuclide ~Bod Bone ~Th roid Liver Tract H-3 1.8E-01 1.8E-01 1.8E-01 1,8E-01 Na-24 4.1E+02 4.1E+02 4.1E+02 4.1E+02 4.1E+02 P-32 1.BE+06 4.6E+07 2.9E+06 5.3E>06 Cr-51 1.3E+00 7.7E-01 3.2E~02 Hn-54 8.3E+02 4.4E+03 1.3E+04 Hn-56 1.9E+01 1.6E+02 3.6E+03 Fe-55 1.1E+02 6.7E+02 4.6E+02 2.6E+02 Fe-59 9.4E+02 1.0E+03 2.4E+03 8.2E+03 Co-58 2,1E+02 9.0E+01 1.BE+03 Co-60 5.7E+02 2.5E+02 4.BE+03 Ni-65 7.5E+00 1.3E+02 1.7E+01 4.1E+02 Cu-64 4.7E+00 1.0E+Ol 8.6E+02 Zn-65 3.4E+04 2.3E+04 7.2E+04 4.7E+04 Zn-69m 1.BE+02 8.1E+02 2.0E+03 1.2E+05 As-76 1.2E+03 1.1E+04 Br-82 2.3E+03 2.6E+03 Br-83 4.0E+01 5.BE+01 Br-84 5.2E+01 4.1E-04 Rb-89 1.3E+02 1.9E+02 1.1E-11 Sr-89 6.4E+02 2.3E+04 3.6E+03 Sr-90 1.3E+04 6.3E+05 1.6E+04 Sr-91 1.7E+01 4.1E+02 2.0E+03 Sr-92 6.BE+00 1.6E+02 3elE~03 29
CONTROLLED COPY AMENDMENT NO. 6 November 1988 CONTROLLED Table 2-2 COPY (contd.)
Total G1 Nuclide ~Bod Bone ~Th roid Liver Tract Y-90 1.6E-02 5.9E-01 6.1E+03 Y-91m 2.1E-04 5.5E-03 1.6E-02 Y-91 2.3E-01 8.5E+00 4.7E+03 Y-92 1.5E-03 5.2E-02 9.1E+02 Y-93 4.5E-03 1.6E-01 5.2E+03 Zr-95 5.3E-02 2.5E-01 7.9E-02 2.5E+02 Nb-95 1.4E+02 4.5E+02 2.5E+02 1.5E+06 Zr-97 1.3E-03 1.4E-02 2.7E-03 8.BE+02 Nb-97 3.5E-01 3.7E+00 9.3E-01 3.5E+03 Mo-99 2.0E+01 1.1E+02 2.5E+02 Tc-99m 3.3E-Ol 9.2E-03 2.6E-02 1.5E+01 Tc-101 1.3E-01 9.2E-03 1.4E-02 4.0E-14 Ru-103 2.0E+00 4.7E+00 5.5E+02 Ru-105 1.5E-01 3.7E-01 2.3E+02 Rh-105 1.4E+00 3.0E+00 2.2E+00 3.5E+02 Ru-106 8.7E+00 6.9E+Ol 4.5E+03 Ag-110m 5.6E-01 1.0E-OO 9.5E-01 3.BE+02 Sb-124 3.6E+00 9.0E+00 2.2E-02 1.7E-01 2.6E+02 Sb-125 1.4E+00 5.BE+00 5.8E-03 6.5E-02 6.5E+Ol Sb-126 ).4E+00 3.9f+00 2.3E-02 7.4E-02 3.0E+02 Sb-127 3.2E-Ol 8.4E-Ol 1.0E-02 1.8E-02 1.9fw02 Te-127 2.3E+Ol 1.1E+02 7.9E+01 3.BE+01 8.3E+03 Te-129m 1.7E+03 1.2E+04 3.BE+03 4.1E+03 5.6E+04 Te-129 7.4E+00 3.0E+Ol 2.3E+01 1.2E+01 2.3E+Ol Te-131m 6.BE+02 1.6E+03 1.3E+03 8.2E+02 8.1E+04 Te-131 5.9E+00 1.9E+Ol 1.5E+01 7.9E+00 2.7E+00 Te-132 1.4E+03 2.4E+03 1.7E+03 1.5E+03 7.4E-04 I-131 1.3E+02 1.5E+02 7.4E+04 2.2E+02 5.9E+Ol
'I-1 32 7.0E+00 7.4E+00 7.0E+02 2.0E+01 '.7E+00 I-133 2.BE+01 5.1E+Ol 1.3E+04 9.2E+Ol 8.1E+01 I-134 3.7E+00 4,0E+00 1.BE+02 1.1E+01 9.2E-03 I-135 1.6E+01 1.6E+Ol 2.BE+03 4.4E+01 4.BE+01 30
CONTROLLEG COPY AMENDMENT NO. 6 November 1988 CONTRQLLED COPY Table 2-2 (contd.)
Total Gi Nuclide ~Bod Bone ~Th roid Liver Tract Cs-134 5.BE+05 3.0E+05 7.2E+05 1.3E+04 Cs-136 9.1E+04 3.1E+04 1.3E+05 1.4E+04 Cs-137 3.4E+05 3.BE+05 5.3E+05 1.0E+04 Cs-138 2.6E+02 2.6E+02 5.3E+02 2.3E-03 Ba-139 2.9E-02 1.0E-OO 7.2E-04 1.BE+00 Ba-140 1.4E+01 2.1E+02 2.7E-Ol 4.4E+02 La-140 2.0E-02 1.5E-01 7.9E-02 5.6E+03 La-141 9.7E-04 1.9E-02 6.0E-03 7.3E+02 La-142 9.1E-04 7.9E-03 3.5E-03 2.6E+Ol Ce-141 2.3E-03 3.0E-02 2.0E-02 7.7Ew01 Ce-143 4.5E-04 5.5E-03 3.9E+00 1.5E+02 Ce-144 8.4E-02 1.6E+00 6.5E-Ol 5.5E+02 Pr-143 2.8E-02 5.6E-01 2.3E-01 2.4E+03 Nd-147 2.7E-02 3.8E-01 4.4E-01 2.1E>03 Hf-179m 4.2E+01 3.6E+02 Hf-181 3.BE+01 3.6E+02 W-185 4.0E+01 1.2E+03 4.0E+02 4.6E+04 W-187 8.6E+Ol 2.9E+02 2.5E+02 8.1E+04 Np-239 1.6E-03 3.0E-02 3.0E-03 6.0E+02
- No Ingestion Dose Factor (DF;) is listed in NUREG/CR-4013. (Total body dose factor value will be used as an approximation.)
31
CGNTRGLLEG CGPY AMENDMENT NO. 6 November 1988 CGNTBGLLEG COPY TABLE 2-3 INPUT PARAMETERS USED TO CALCULATE MAXIMUM INDIVIDUAL DOSE FROM LI UID EFFLUENTS River Dilution: 50,000 River Transit Time: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Usage Factors: Adult = 730 1/yr Teenager = 510 1/yr Child = 510 1/yr Infant = 330 1/yr Boatin and A uatic Food River Dilution: 2,000 Transit Time: 2 hours Usage Factors: (Aquatic Food) Adult = 21 kg/yr Teenager = 16 kg/yr Child = 6.9 kg/yr Infant = 0 (Boating) Adult = 100 hr/yr Teenager = 100 hr/yr Child = 85 hr/yr Infant = 0 Recreation River Dilution: 20,000 Shoreline Width Factor: 0.2 Usage Factors: Shoreline Activities: Adult = 90 hr/yr Teenager = 500 hr/yr Child = 105 hr/yr Infant = 0 Swimming: Adult = 18 hr/yr Teenager = 100 hr/yr Child = 21 hr/yr Irri ated Foodstuffs River Dilution: 50,000 River Transit Time: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Leafy Ve etabl es Food Delivery Time: 14 days 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 20 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Usage Factors:
Adul t 520 kg/yr 310 1/yr 110 kg/yr 64 kg/yr Teenager 630 kg/yr 400 1/yr 65 kg/yr 42 kg/yr Child 520 kg/yr 330 1/yr 41 kg/yr 26 kg/yr Monthly Irrigation Rate: 180 1/m~ 200 1/m2 160 1/m2 200 1/m2 Annual Yield: 5.0 kg/m 1.3 1/m2 2.0 kg/m2 1.5 kg/m2 Annual Growing Period: 70 days 30 days 130 days 70 days Annual 50-Mile Production: 3.5E+09 kg 2.BE+08 L 2.3E+07 kg 1.9E+06 kg 32
CGNTROLLEQ COPY AMENDMENT NO. 6 November 1988 t
CONTIROLLED COPY SUMPS COOLING TQVER VASTE VASTE BLOVDOVN LINE RADWASTE BLDG SURGE TURBINE BLDG SAMPLE AND TANKS DRYWELL COLLECTOR (TVQ)
TANKS FLOOR DRAIN ~ FLOOR COLLECTOR DRAIN MISC WASTE TANK SAMPLE TANK REACTOR BLDG DISTILLATE TANKS (TWO)
DETERGENT DRAIN TANKS FILTERS 8 DENINERAL-,
IZERS
<SOLID WASTE)
CHEMICAL WASTE TANKS SHOP DECON CONDENSATE CHEM PUMPS STORAGE DECON DRAIN PLANT TANKS REACTOR BLDG USE (TVQ)
TURBINE BLDG COLUMBIA RIVER SIMPLIFIED BLOCK DIAGRAM OF LIQUID VASTE SYSTEM FIGURE 2-1 32a
CGNTROLLEQ CQPY d
AMENDMENT NO. 6 November 1988 CGNTFtGLLE0 CGPV DEMINERALIZERS Condensate RHCU Phase Dewatering Disposal EDR/FDR Separator Liners Site Radwaste Bead Dry Active Compactor. Disposal Haste Site SIMPLIFIED BLOCK DIAGRAM OF SOLID RADHASTE SYSTEM Figure 2-2 32b
CONTROLLED CGPY
'p
AMENDMENT NO. 6 November 1988 All other locations listQQgggQ}$3+1QQpQQLPI~~2 activities and are controlled by the Supply System. Figure 3-2 provides a simplified block diagram of the gaseous radwaste system for the reactor, turbine and radwaste buildings. figure 3-3 provides a simplified block diagram for the Off-Gas Treatment System.
Air doses and doses to individuals at these locations were calculated based on the NRC GALE code design base mixture, location specific estimated occupancy, and X/Qs from XOQOOQ. (Note: Oesert Sigmas .were used in calculating X/Q and D/Q values, and are listed in Table 3-10 to 3-12). These doses are listed in Tables 3-16 and 3-17 along with the doses to the maximum exposed individual.
The most likel ex osed member of the ublic is considered to be residing in Taylor Flats (4.2 miles ESE of WNP-2). This is the closest residential area with the high- est X/Q and 0/Q values.
3.2 Gaseous Effluent Radiation Monitorin S stem 3.2.1 Main Plant Release Point The Main Plant Release is instrument monitored for gaseous radioactivity prior to discharge to the environment via the main plant vent release point.
Particulates and iodine activity are accumulated in filters which will be changed and analyzed as per Technical Specification 4.11.2.1.2 and Table 4.11.2. The effluent is supplied from: i the gland seal exhauster, mechanical vacuum pumps, treated off gas, standby gas treatment, and exhaust air from the entire reactor building's ventilation.
Two 100-percent capacity vanaxial fans supply 98,000 CFM ventilation air. One is normally operating, the other is in standby. The radiation monitors are located on'he ventilation exhaust plenum.
Effluent monitoring consists of a low range beta scintillator, an intermediate range beta scintillator and two ion chamber LOCA monitors. The beta scintillators are mounted in thick lead shielded chambers. The low range beta scintillator has an approximate response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133 and a meter range of 10-10 cpm. The intermediate 34
CONTROLLED COPY If,
AMENDMENT NO. 6 November 1988 range has a response frdgclgT+~L'PgoeQOPF/nival ant, and reads in panel meter units (PMU) with a meter range of 10 -10 PMU.
The readouts and recorder are located in the main control room panel BD-RAD-24. Power is provided from 125 VDC divisional buses. This monitor has no control Function but annunciates in the main control room. The alarm will e
initiate proper action as defined in the WNP-2 Plant Procedures.
3.2.2 Radwaste Buildin Ventilation Exhaust Monitor The radwaste building ventilation exhaust monitoring system monitors the radio-activity in the exhaust air prior to discharge. Radioactivity can originate from: radwaste tank vents, laboratory hoods, and various cubicles housing liquid process treatment equipment and systems.
The radwaste building exhaust system has three 50 percent capacity exhaust filter units of 42,000 cfm capacity. Each exhaust unit has a medium-efficiency prefilter, a high efficiency particulate air filter (HEPA) and two centrifugal fans. Total exhaust flow will vary as the combined exhaust unit maintains a radwaste building differential pressure of -0.25 inches H20 to the environment.
Particulate and iodine air sample filters are changed weekly for laboratory analysis. After the particulate and iodine filters, the air sample streams are combined in a manifold prior to being monitored by a beta scintillator.
The beta scintillators, on the 487'evel are mounted in lead shielded chambers. The low range beta scintillator has an approximate response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133 and a meter range of 10-10 cpm. The intermediate range has a response from 10 10 3 pCi/cc 6
Xe -133 equivalent, and reads in panel meter units (PMU) with a meter range of 0 5 10 -10 PMU. The readouts and recorder are located in the main control room panel BO-RAO-24. Power is provided from 125 VDC divisional buses. This monitor has no control functions but annunciates in the main control room.
The alarm will initiate proper action as defined in the WNP-2 plant procedures.
35
CONTRGLLEG CGPY 0
t
AMENDMENT NO. 6 November 1988 3.2.3 Turbine Buildin IIVKb Exhale o QP This monitoring system detects fission and the activation products from the turbine building air which may be present due to leaks from the turbine and other primary components in the building.
The turbine building main exhaust system consists of four roof-mounted centri-fugal fans which draw air from a central exhaust plenum. Three fans operate continuously, with one in,.standby to provide a flow of 260,000 cfm.
A representative sample is extracted from the exhaust vent and passed through a particulate and charcoal Filter. The air sample then passes to a beta scintillator.
The beta scinti llators are mounted in lead shielded chambers. The low range beta scintillator has an approximate response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133 and a meter range of 10-10 cpm. The intermediate
-2 3 range has a response from 10 10 qCi/cc Xe -133 equivalent, and reads in panel meter units (PHU) with a meter range of 10 - 10 PHU. The monitors are on the 525'evel of the radwaste building and the readouts and the recorder are located in the main control room panel BD-RAD-24. Power is provided from the 125 VDC divisional buses. This monitor has no control functions but annunciates in the main control room. The alarm will initiate proper action as defined in the INP-2 plant procedures.
3.3 10 CFR 20 Release Rate Limits Limits for release of airborne effluents to the unrestricted area are stated in Technical Specification 3.11.2.1. The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
'a)
"The dose rate limit for noble gases shall be <500 mrem/yr to the total body and <3000 mrem/yr to the skin.
(b) "The dose rate limit for all radioiodines and For all radio-active materials in particulate form and radionuclides other than noble gases with halF-lives greater than eight days shall be <1500 mrem/yr to any organ."
36
CONTRGLLEQ CQPY AMENDMENT NO. 6 November 1988 3.3.1 Noble Gases CONTROLLED COPY In order to comply with Technical Specification 3.11.2.1, the Following equa-tions must hold:
Nhole body:
g Ki [(X/Q) Q. + (X/Q) m im g Q.
ig )
< 500 mrem/yr ('I) 1 Skin p [(Li + 1.1N,.)((X/Q) Q. + (X/Q) I), )] S 3000mrem/yr (2) 3.3.2 Radioiodines and Particulates Part "b" of Technical Specification 3.11.2.1 requires that the release rate limit for all radioiodines and radioactive materials in particulate Form and radionuclides other than noble gases must meet the following relationship:
Any organ:
QP.i W H
(}. +
im M g. 1 <1500 mrem/yr igJ (3) g The terms used in equations 1 through 3 are defined as follows:
K. = The total body dose Factor due to gamma emissions for each identified noble gas radionuclide i (mrem/yr per t Ci/m ).
L = The skin dose factor due to beta emissions for each iden-tified noble gas radionuclide i (mrem/yr per vCi/m ).
CONTROLLEG COPY AHENOMENT NO. 6 November 1988 qim CTQNv~egoLrglpD Qogllg gas radionuclides in gaseous ef fluents, i, for short-term releases (equal to or less than 500 hr/yr) from the main plant release point, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.
lg The average release of noble gas radionuclides in gaseous effluents, i, for short-term releases (equal to or less than 500 hr/yr) from Radwaste and Turbine Building, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.
oim The average release of noble gas radionuclides in gaseous releases, i, for long-term releases (greater than 500 hr/yr) from the main plant release point, in pCi. Release shall be cumulative over the I
calendar quarter or year, as appropriate.
0;g The average release of noble gas radionuclides in gaseous effluents, i, for long-term releases'greater than 500 hr/yr) from Radwaste and Turbine Building, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.
3.17 x 10
-8 = The inverse of the number of seconds in a year.
3.4.2 Radioiodines Tritium and Particulates Technical S ecification
~3. 11 . 2.3 The following equation calculates the dose to an individual from radioiodines, tritium radioactive material in particulate form, and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to the unrestricted areas:
CONTROLLEG COPY AHENDMENT NO. 6 November 1988 3.4.2.1 Rose Parameter r Ki A iRe i RQQpV The R. values used in equations 12 and 13 of this section are calculated separately for each of the following potential exposure pathways: ~
Inhalation Ground plane contamination Grass-cow/goat-milk pathway Grass-cow-meat pathway Vegetation pathway Monthly dose assessments for WNP-2 gaseous effluent will be done for all age groups.
Calculation of R.
1 (Inhalation Pathway Factor)
I (Inhalation) I R. = K (SR) (DFA.) (mrem/yr per qCi/m3 ) (14) where:
RI The inhalation pathway factor (mrem/yr per pCi/m 3 ).
1 A constant of unit conversion, 10 pCi/pCi.
(BR) The breathing rate of the receptor of age group (a) in meter 3 /yr. ( Infant = 1400, child = 3,700, teen = 8,000, adult = 8,000. From P.32 NUREG-0133).
47
CONTROLLED COPY AMENDMENT NO. 6 November 1988 (OFA.) The QQÃeTVprl-4IIaQtQPPosY factor for receptor of age group (a) for the ith radionuclide (mrem/pCi). The total body is considered as an organ in the selection of (OFA.)a. (OFAi)a values are listed in Tables E-7 through E-10 of Regulatory Guide 1.109 manual, Revision 1 and NUREG/CR-4013. Values of R. are listed in 1
Table 3-,5.
G Calculation of R. (Ground Plane Pathway Factor)
G A 8 R.(Ground Plane) = K K (SF)(DFG-) (1-e )/A (m x mrem/yr per vCi/sec) (15) where:
G R. = Ground plane pathway factor (m x mrem/yr per uCi/sec).
A =
K A conversion constant of (10 pCi/uCi) .
8 K = A conversion constant (8760
'I hr/yr).
The decay constant for the ith radionuclide (sec ).
t = Exposure time, 6.31 x 10 sec (20 years).
DFG. The ground plane dose conversion factor for the ith radio-nuclide, as listed in Table E-6 of Regulatory Guide 1.109, Revision 1 and NUREG/CR-4013 (mrem/hr per pCi/m ).
SF = Shielding Factor (dimensionless) 0.7 if building is present, as suggested in Table E-15 of Regulatory Guide 1.109, Revision 1.
CGNTIRGLLEG COPY AMENDMENT NO. 6 November 1988 (DFLi) The+gbggggn'f~iQQP+factor for the ith radio-nuclide for the receptor in age group (a), in mrem/pCi (Tables E-11 to E-14 of Regulatory Guide 1.109, Revision 1 and NUREG/CR-4013).
The decay constant for the ith radionuclide, in sec The decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10 sec (cor-responding to a 14-day half;life).
The transport time from pasture to animal, to milk, to receptor, in sec.
The transport time from pasture, to harvest, to animal, to milk, to receptor, in sec.
Fraction of the year that the cow/goat is on pasture (dimensionless).
's Fraction of the cow/goat feed that is pasture grass while the cow is on pasture (dimensionless).
NOTE: For radioiodines, multiply R. value by 0.5 to obtain the amount of elemental iodihe present.
The input parameters used for calculating R.
1 are listed in Table 3-6 and the M
R,. values are tabulated in Table 3-7.
For Tritium:
C In calculating RT, pertaining to tritium in milk, the airborne concentration rather than the deposition will be used:
C RT (Grass-Cow/Goat-Milk Factor) =
K K F Q U (DFL.) 0.75(0.5/H) (mrem/y"r per >Ci/m ) (17) 50
CONTROLLEI3 COPY
AHENOHENT NO. 6 November 1988 tf = The tranQQgC)"rg~~aQugp'gceptor, in sec.
h The transport time from crop field to receptor, in sec.
NOTE: For radioiodines, multiply R. value by 0.5 to obtain the amount of elemental iodine present.
The input parameters needed for solving equation 18 are listed in Table 3-7.
For Tritium:
In calculating the RT for tritium in meat, the airborne concentration is used rather than the deposition rate. The following equation is used to calculate the RT values for tritium:
H R (Grass-Cow-Heat Pathway) =
T A C K K F g U (OFL.) 0.75(0.5/H) (mrem/yr per pCi/m 3 ) (19)
Where the terms are as defined in equations 16-18, R values for tritium pertaining to the infant age group is zero since there is no meat consumption by this age group.
V Calculation of R, (Vegetation Pathway Factor)
V R.
1 (Vegetation Pathway Factor) =
ULf i L USf ih (20)
Y 1 w aL ag 2
(m x mrem/yr per pCi/sec) 52
COÃTRGLCEQ CGPY AMENDMENT NO. 6 November 1988 where:
I CGNTIRGLLED CGPY K = A constant of unit conversion, 10 pCi/vCi.
L =
U a
The consumption rate of fresh leafy vegetation by the receptor in age group (a), in kg/yr.
S =
U a
The consumption rate of stored vegetation by the receptor in age group (a), in kg/yr.
fL = The fraction of the annual intake of fresh leafy vegetation grown local ly.
fg = The fraction of the annual intake of stored vegetation grown locally.
tL = The average time between harvest of leafy vegetation and its consumption, in seconds.
th = The average time between harvest of stored vegetation and its consumption, in seconds.
Y v
The vegetation area density, in kg/m .
NOTE: For radioiodines, multiply R. value by 0.5 to obtain the amount of elemental iodine present.
All other items are as defined in equations 16-18.
For Tritium:
In calculating the RT for tritium, the concentration of tritium in vegetation is based on airborne concentration rather than the deposition rate. The fol-lowing equation is used to calculate R for tritium:
53
CONTROLLED COPY AMENDMENT NO. 6 November 1988 mrem/yr to the whole boQQi%YBOLkgQ>CIQRVn. The initial setpoints determination is calculated using a conservative radionuclide mix obtained from the WNP-2 GALE code. Once the plant is operating and sufficient measur-able process fission gases are in the effluent, then the actual radionuclide mix will be used to calculate the alarm-setpoint.
3.6.2 Set oint Determination for all Gaseous Release Paths The setpoints for gaseous effluent are based on instantaneous noble gas dose rates. Sampling and analysis of radioiodines and radionuclides in particulate form will be performed in accordance with technical specifications to ensure compliance with 10 CFR 20 and 10 CFR 50 Appendix I limits. The three release points will be partitioned such that their sum does not exceed 100 percent of the limit. Originally, the setpoints will be set at 40 percent for the reactor building, 40 percent for the turbine building and 20 percent for the radwaste building. These percentages could vary at the plant discretion, should the operational conditions warrant such change. However, the combined releases due to variations in the setpoints will not result in doses which exceed the limit stated in technical specifica- tion. Both skin dose and whole body setpoints will be calculated and the lower limit will be used.
3.6.2.1 Set pints Calculations Based on Whole Bod Dose Limits The fraction ( < i) of the total gaseous radioactivity in ea'ch gaseous effluent release path (j) for each noble gas radionuclide i will be determined by using the following equation:
H~ ~
iJ (dimensionless) (22)
NT-where:
H.. = The measured individual concentration of radionuclide i in the 1j gaseous ef fluent release path j ( pCi/cc) .
55
CGNTRGLLEG CGPY AMENDMENT NO. 6 November 1988 MT
= The measurQQg8f g~gtpQoQpp noble gases identified in the gaseous effluent release path j (qCi/cc).
Based on Technical Specification 3.11.2.1, the maximum acceptable release rate of all noble gases in the gaseous effluent 'release path j is calculated by using the following equation:
F 500
= m (p Ci/sec) (23) gT~
x/q. gi = 1 (K,.)( ~, )
where:
9T>
= The maximum acceptable release rate (qCi/sec) of all noble gases in the gaseous effluent release path j (qCi/cc).
Fj = Fraction of total dose allocated to release path j.
500 = Nhole body dose rate limit of 500 mrem/yr as specified in Tech-nical Specification 3.11.2.1a.
X/g. Maximum normalized diffusion coefficient of effluent release path j at the site boundary (sec/m 3 ). Turbine Building and Radwaste Building values are based on average annual ground level values. Main plant vent release values are for mixed mode and may be either short term or average annual value dependent upon type of release.
K. = The total whole body dose factor due to gamma emission from noble gas nuclide i (mrem/yr per wCi/m ) (as listed=- in Table 8-1 of Regulatory Guide 1.109, Revision 1).
56
CONTROLLED COPY AMENDMENT NO. 6 November 1988 As definedQQf(0pg0L2+ED QGpy m = Total number of radionuclides in the gaseous effluent.
j = Different release pathways.
The total maximum acceptable concentration (CT ) of noble gas radionuclides TJ in the gaseous effluent release path j (uCi/cc) will be calculated by using the following equation:
OT ~
CT. = ~R (pCi/cc) (24) where:
CT.
TJ
= The total allowed concentration of all noble gas radionuclides in the gaseous effluent release path j (pCi/cc).
0TJ
= The maximum acceptable release rate (pCi/sec) of all noble gases in the gaseous effluent release path j.
R = The ef fluent release rate (cc/sec) at the point of release.
J To determine the maximum acceptable concentration (C..) of noble gas radio-ij nuclide i in the gaseous effluent for each individual noble gas in the gaseous effluent (uCi/cc), the following equation will be used:
C ~ - =; . CT. (q C i /cc) (25) 57
CONTROLLED COPY AMENDMENT NO. 6 November 1988 CGNTHGLLE0 CGPY Table 3-2 DISTANCES (MILES) TO CONTROLLING LOCATIONS AS MEASURED FROM CENTER OF NNP-2 CONTAINMENT BUILDING*
Location Distance Sector Comments (miles)
Si.te Boundary 1.2 SE Air dose measurement.
Taylor Flats 4.2 ESE The nearest significant residence in the southern direction with vegetable gardens, milk, and meat production.
Ringold 4.0 ENE The nearest significant residence in the northern direction with vegetable gardens, milk, and meat production.
"Selection of location sector is based on the highest annual average X/Q values.
'1
COÃTRGLEEG CGPY 0
Table 3-3 LNP-2 ANNUAL AVERAGE DISPERSION (X/Q)
"e X/Q X/Q X/Q 2.3 Days 8.0 Days No Decay Decay Decay Location Sector Distance Point of Release No De letion No De letion ~0e leted (miles) (sec/m ) (sec/m ) (sec/m ) (m )
Site Boundary SE 1.2 Containment Bldg. 1.8E-06 1.8E-06 1.6E-06 1.0E-08 Turbine Bldg. 1.1E-05 1.1E-05 1.0E-05 8. 3E-08 A
-O Radwaste Bldg. 1.1E-05 1.1E-05 1.0E-05 8.3E-OB K
Taylor Flats ESE 4.2 Containment Bldg. 4.1E-07 4.1E-07 3.8E-07 8.2E-10 O I
I Turbine Bldg. 8.9E-07 8.7E-07 6.8E-07 7. 2E-10 Radwaste Bldg. 8.9E-07 8.7E-07 6.8E-07 7.2E-10 U
O.
Ringold 4.0 Containment Bldg. 2.5E-07 2.5E-07 1.9E-07 3.3E-10 Turbine Bldg. 3.9E-07 3.8E-07 3.0E-07 3.3E-10 Radwaste Bldg. 3.9E-07 3.8E-07 3.0E-07 3.3E-10 BPA"As he 0.5 Containment Bldg. 6.4E-06 6.4E-06 5.8E-06 3.7E-OB Substation Turbine Bldg. 3.0E-05 2.9E-05 2.7E-05 7.8E-OB 0 Pl
(
ED CI O
Radwaste Bldg. 3.0E-05 2.9E-05 2.7E-05 7.8E-OB lD Pl s
CO Q)
O
~
CGRTRGLL,Et3 CQPY AMENDMENT NO. 6 November 1988 Table DOSE RATE PARAMETERS IMPLEMENTATION OF 10 CFR 20 AIRBORNE RELEASES Child Dose Factor* PI 1
DFA. DFGi Inhalation mrem/hr ~mrem/ r 3
Nuclide m~rem/ Ci ~Ci /m ~Ci /m H-3 1.8E-09 1.7E-07 0.0 6.3E+02 Na-24 1.3E-05 4.4E-06 2.9E-OB 1.6E+04 Cr-51 2.9E-07 4.6E-06 2.6E-10 1.7E+04 Hn-54 2.6E-OB 4.3E-04 6.8E-09 1.6E+06 Hn-56 7.5E-05 3.3E-05 1.3E-OB 1.2E+05 Fe-55 8.5E-09 3.0E-05 0.0 1.1E+05 Fe-59 1.8E-07 3.4E-04 9.4E-09 1.3E+06 Co-58 1.1E-07 3.0E-04 8.2E-09 1.1E+06 Co-60 4.2E-09 1.9E-03 2.0E-OB 7.0E+06 Cu-64 1.5E-05 9 'E-06 1.7E-09 3.7E+04 Zn-65 3.3E-OB 2.7E-04 4.6E-09 1.0E+06 Zn-69m 1.4E-05 2.7E-05 3.4E-09 1.0E+05 As-76 7.3E-06 1.9E-05 1.7E-07 7.0E+04 Br-82 5.5E-06 5.7E-06 2.2E-OB 2.1E+04 Sr-89 1.5E-07 5.8E-04 6.5E-13 2.2E+06 Sr-90 7.9E-10 1.0E-02 2.6E-12*" 3.7E+07 Zr-95 1.2E-07 6.0E-04 5.8E-09 2.2E+06 Nb-95 2.3E-07 1.7E-04 6.0E-09 6.3E+05 Zr-97 1.1E-05 9.5E-05 6.4E-09 3.5E+05 Nb-97 1.6E-04 7.5E-06 5.4E-09 2.BE+04 Ho-99 2.9E-06 3.7E-05 2.2E-09 1.4E+05 Tc-99m 3.2E-05 1.3E-06 1.1E-09 4.BE+03 Ru-106 2.2E-OB 3.9E-03 1.8E-09 1.4E+07 Ag-110m 3.2E-OB 1.5E-03 2.1E-08 5:6E+06 Sb-124 '1.3E-07 8.8E-04 1.5E-OB 3.3E+06 Sb-125 7.9E-09 6.3E-04 3.5E-09 2.3E+06 Sb-126 6.5E-07 2.9E-04 1.0E-OB 1.1E+06 Sb-127 2.1E-06 6.2E-05 6.6E-09 2.3E+05 63
CGNTRGLLEG CQPY AMENDMENT NO. 6 November 1988 CONTIROLLED COPY Table 3-4
' DOSE RATE PARAMETERS IMPLEMENTATION OF 10 CFR 20 AIRBORNE RELEASES Child Dose Factor" PI 1
DFA. DFG.
Inhalation mrem/hr ~mrem/ r Nuclide 3 sec m~rem/ Ci ~Ci /m ~Ci /m Te-127 '2.1E-05 1.5E-05 1.1E-ll 5.6E+04 Te-131m 6.4E-06 8.3E-05 9.9E-09 3.1E+05 I-131 1.0E-06 4.4E-03 3.4E-09 1.6E+07 I-132 8.4E-05 5.2E-05 2.0E-OB '1.9E+05 I-133 9.2E-06 1.0E-03 4.5E-09 3.7E+06 I-135 2.9E-05 2.1E-04 1.4E-OB 7.BE+05 Cs-134 1.1E-08 2.7E-04 1.4E-OB 1.0E+06 Cs-137 7.3E-10 2.5E-04 4.9E-09 9.3E+05 Cs-138 3.6E-04 2.3E-07 2.4E-OB 8.5E+02 Ba-140 6.3E-07 4.7E-04 2.4E-09 1.7E+06 La-140 4.8E-06 6.1E-05 1.7E-08 2.3E+05 Ce-141 2.4E-07 1.5E-04 6.2E-10 5.6E+05 Ce-144 2.8E-OB 3.2E-03 3.7E-10 1.2E+07 Nd-147 7.2E-07 8.9E-05 1.2E-09 3.3E+05 Hf-1 79m 3.7E-02 2.0E-05 NO DATA 7.4E+04 Hf-181 1.8E-07 6.0E-05 1.2E-08 2.2E+05 W-185 1.1E-07 1.9E-04 0.0 7.0E+05
- Maximum Organ
- No data is listed for Sr-90 in Table E-6 of Regulatory Guide 1.109, Revi-sion l. Y-90 valves were used for dose conversion factor Sr-90.
63a
CQNTlRGLLEG, CGPY 0'
AflEHDNENT NO. 6 November 1988 CONTIROLLED 3-5 a
'COP'It'ABLE DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RfLEASES AGE GROUP: ADULT ORGAN OF REFEREN(f: MAXIMUM ORGAN (I), INDIVIDUALPATHWAY DOSE PARAMETfRS FOR RADIONUCLIDES OTHER THAN NOBLE GASES RADIO- INHALATION GROUND PLANE COW-MILK GOAT-MILK ANIMAL-Mf AT VEGETABLE S NUCLIDE (MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (MZ.MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC)
H 3 7.2Et02 O.OE-01 5.8Et02 1.2E+03 2.4E+02 1.6Et03 NA 24 1.0Et04 1.2Et07 1.2E+06 2.2E+05 7.2E-04 1.1Et05 CR 51 1.4E+04 4.7E+06 3.3Et06 5.9E+05 8.2f+05 2.3Et07 MN 54 1.4Et06 1.4E+09 1.4Et07 2.1E+06 1.5E+07 9.4Et08 MN 56 2.0Et04 9.0E+05 6.2E-02 1.1E-02 O.OE-01 2.0E+02 FE 55 7.2Et04 O.OE-01 1.4Et07 2.2Et06 1.6f+08 1.9E+08 FE 59 1.0E+06 2.7E+08 1.1Et08 2.DE+07 9.BE+08 1.5E+09 CO 58 9.3Et05 3.8Et08 4.7Et07 7.6Et06 1.8Et08 B.OEt08 CO 60 6.0Et06 2.3E+10 1.7Et08 2.5Et07 B.OE+08 2.9E+09 CU 64 4.9Et04 6.1Et05 1.0Et06 1.7Et05 1.1E-05 3.3Et05 ZN 65 8.6Et05 7.5E+08 2.7E+09 4.0E+08 7.0Et08 1.3Et09 ZN 69M 1.4EtOS 1.3Et06 1.3Et07 2.4E+06 1.2E-03 1.4Et06 AS 76 1.5E+05 3.8Et06 2.1Et07 3.BE+06 2.9Etol B.OE t06 BR 82 1.4E+04 2.1E+07 1.9Et07 3.4Et06 7.0ft02 7.7E+05 SR 89 1.4Et06 2.2E+04 6.9Et08 2.0E+09 1.4E+08 1.5E+10 SR 90 2.9Et07 6.7Et06 3.4E+10 8.3E+10 8.9ft09 7. 4f+ll ZR 95 1.BE+06 2.5E+08 4.6Et05 7.6E+04 9.2Et08 1.6Et09 NB 95 5.1Et05 1.4E+08 1.3Et08 2.2E+07 3.6E+09 8.4E+08 ZR 97 5.2E+05 3.0E+06 1 ~ 4E+04 2.4E+03 6.4E-01 B.BE+06 NB 97 2.4Et03 1.BE+05 1.6E-09 2.9E-10 O.OE-01 8.1E-04 MO 99 2.5EtOS 4.OE+06 2.9E+07 5.2E+06 1.2E+05 9.3Et06 TC 99M 4.2Et03 1.BEt05 2.8Et03 5.0Et02 3.6E-18 2.2Et03 RU106 9.4Et06 4.2E+08 7.3Et05 1.1E+05 1.0E+11'.4Et09 1.2f+10 AG11OM 4.6Et06 3.5E+09 1.2E+10 1.BE+09 4.4Et09 SB124 2.5Et06 6.0E+08 3.5Et08 5.8Et07 2.7E+08 4.OEt09 58125 1.7Et06 2.4Et09 1.3Et08 1.8Et07 1.2E+08 1.4E+09 SB126 7.7Et05 8.4E+07 2.2Et08 4.DE+07 7.6E+07 1.6Et09 SB127 3,0Et05 1.7Et07 5.2Et07 9.3Et06 1.9E+06 1.2E+08 TE127 5.7E+04 3.0E+03 2.6E+04 4.7E+03 8.4E-09 2.0E+05 TE131M 5.6Et05 B.OE+06 8.9Et06 1.6E+06 1.1Et04 2.0Et07 I 131 1.2E+07 8.6E+06 3.4E+10 6.1E+10 1.2E+09 4.4E+10 I 132 1.1Et05 6.2Et05 3.9E+00 6.9E+00 O.OE-01 l.lft03 I 133 2.2E+06 1. 2f+06 2.5Et08 4.5E+08 2.4Etol 1.1Et08 I 135 4.5Et05 1.3f+06 5.5Et05 9.BE+05 l. 7E-15 1.4Et06 CS134 8.5Et05. 6.9Et09 7.4E+09 2.7Et10 8.6E+08 1.Of+10 CS136 1.5Et05 1.5E+08 5.0Et08 2.2Et09 2.3E+07 4.6Et08 CS137 6.2ft05 1.3E+10 6.0Et09 2.1E+10 7.1E+08 8.6E+09 CS138 6.2E+02 3.6E+05 1.0E-23 4.6E-23 '.OE-OO 3.0E-11 BA140 1.3E+06 2.1E+07 2.7Et07 4.BE+06 2.BE+07 7.3E+08 LA140 4.6E+05 1.9Et07 8.4Et04 1.5E+04 7.0Et02 3.3ft07 CE141 3.6E+05 1.4E+07 5.8Et06 1.0Et06 1.7E+07 9.3Et08 CE144 7.8Et06 7.0E+07 6.4Et07 9.6E+06 2.6E+08 1.1E+10 ND147 2.2E+05 B.SE+06 2.5E+05 4.6E+04 1.9E+07 5.1E+08 HF179M 1.6Et05 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 HF181 4.BE+05 2.1Et08 S.SEt05 9.3E+04 1.2E+10 1.BE+09 W 185 4.5Et05 1.8Et04 2.4ft07 3.9f+06 1.9Et07 8.4ft08 64
CGNTIRGLLEG CGPY P
..a oi I t-f 1
N NO. 6 November 1988 CONTQQPPPP COPY DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RELEASES AGE GROUP: TEEN ORGAN OF REFERENT: MAXIMUM ORGAN R(I), INDIVIDUAL PATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES RADIO- INHALATION GROUND PLANE COW-MILK GOAT-MILK ANIMAL-MEAT. VEGETABLES NUCLIDE (MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC)
H 3 7.3Et02 O.OE-01 7.5Et02 1.5E+03 1.5Et02 1.9Et03 NA 24 1.4Et04 1.2Et07 2.1E+06 3.9E+05 5.8E-04 1.0Et05 CR 51 2.1Et04 4.7Et06 3.9Et06 6.Sf+05 4.4Et05 2.5E+07 MN 54 2.0Et06 1.4E+09 1.6Et07 2.3E+06 7.BE+06 9.6E+08 MN 56 5.7Et04 9.0E+05 2.3E-01 4.1E-02 O.OE-OO 3.7Et02 FE 55 1.2E+05 O.OE-01 2 'E+07 3.8E+06 1.3E+08 3.0E+08 FE 59 1.SEt06 2.7Et08 1.3Et08 2.5E+07 5.5Et08 1.7Et09 CO 58 1.3E+06 3.BE+08 5.3Et07 8.7E+06 9.4E+07 8.3f t08 CO 60 8.7Et06 2.3E+10 2.1Et08 3.Of+07 4.3Et08 3.1Et09 CU 64 6.1Et04 6.1E t05 1.6f t06 2.7E+05 8.0E-06 2.7E+05 ZN 65 1.2Et06 7.5Et08 4.5Et09 6.7Et08 5.4Et08 2.0E+09 ZN 69M 1.7E+05 1 ~ 3E+06 2.1E+07 3.8E+06 9.1E-04 1.1E+06 AS 76 1.5Et05 3.8Et06 2.7E+07 4.9E+06 1.7Et01 5.3E+06 BR 82 1.8ft04 2.1E+07 2.8ft07 5.1E+06 4.9ft02 6.1E+05 SR 89 2.4Et06 2.2Et04 1.3Et09 3.7E+09 1.2Et08 2.4Et10 SR 90 3.3Et07 6.7E+06 5.1E+10 1.3Etll 6.2Et09 1.0E+12 ZR 95 2.7Et06 2.5Et08 5.8Et05 9.5ft04 5.3Et08 1.BE+09 NB 95 7.5Et05 1.4E+08 1.6Et08 2.7Et07 2.0Et09 9.1E+08 ZR 97 6.3Et05 3.0Et06 2.1Et04 3.8Et03 4.6E-01 7.0E+06 NB 97 3.9Et03 1.BE+05 1.9E-08 3.3E-09 O.OE-01 4 'E-03 MO 99 2.7Et05 4.0E+06 5.1Et07 9.2Et06 9.4Et04 1.1E+07 TC 99M 6.1Et03 1.8E+05 5.3Et03 9.5Et02 3.2E-18 2.1E+03 RU106 1.6Et07 4.2Et08 9.9f t05 1.5Et05 6.2Et10 1.5E+10 AG110M 6.8Et06 3.5f+09 1.4E+10 2.1Et09 7.6E+08 4.6E+09 SB124 3.8Et06 6.0Et08 4.5Et08 7.3Et07 1.6Et08 '4.6E+09 SB125 2.7Et06 2.4E+09 1.6f+08 2.3Et07 6.8E+07 1 ~ 6E+09 SB126 1.2Et06 8.4E+07 2.8Et08 5.1Et07 4.5Et07 1.BE+09 SB127 3.2Et05 1.7E+07 6.9Et07 1.2Et07 1.2Et06 1.2E+08 TE127 8.1Et04 3.0Et03 4.8Et04 8.6Et03 7.0E-09 1.8E+05 TE1 31M 6.2E+05 8 'Et06 1.3Et07 2.3E+06 7.4E+03 1.Sf+07 I 131, 1.5Et07 8.6E+06 5.4E+10 9.7Et10 9.0Et08 6.1E+10 I 132 1.5Et05 .
6.2ft05 6.4f t00 '1.2Et01 0.0f-00 9.3E+02 I 133 2.9Et06 1.2E+06 4.2Et08 7.5ft08 1.8Et01 9.6Et07 I 135 6.2E+05 1.3Et06 9.3E+05 1.7Et06 1,3E-15 1.2E+06 CS134 1.1Et06 6.9Et09 1.3E+10 4.6E+10 6.8Et08 1.6EtiO CS136 1.9E+05 1.5E+08 8.4E+08 3.8E+09 1.8Et07 7.0Et08 CS137 S.SEt05 1.3Etl0 1.1E+10 3.8Etlo 5.7Et08 1. 4E+10 CS138 8.6E+02 3.6Et05 1.8E-23 8.1E-23 O.OE-OO 2.7E-11 BA140 2.0Et06 2.1Et07 3.6E+07 6.4ft06 1.8Et07 S.SE+08 LA140 4.9E+05 1.9Et07 1.1E+05 2.1E+04 4.4Et02 2.4E+07 CE141 6.1Et05 1.4Et07 7.9E+06 1.4Et06 1.0Et07 1.1Et09 CE144 1.3Et07 7.0Et07 8.8f+07 1.3f t07 1.6Et08 1.3Et10 ND147 3.7Et05 8.5ft06 3.5E+05 6.2Et04 1.2Et07 6.1E+08 HF1 79M 7.1Et04 O.OE-01 O.OE-01 0.0f-01 O.OE-01 0.0f-01 HF181 4.8EtOS 2.1Et08 7.1E+05 1.2Et05 7.0Et09 2.1Et09 W 185 7.7Et05 1.8Et04 3.3E+07 5.4E+06 1.2E+07 1.0Et09 65
CGNTRGLLEG CGPY At4ENDMENT t<0. 6 November 1988 CONTROLLED COPY TABLE 3-5 c DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RELEASES AGE GROUP: CHILD ORGAN OF
REFERENCE:
MAXIMUM ORGAN R(I), INDIVIDUAL PATHVAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLf GASES RADIO- INHALATION GROUND PLANE COW-MILK GOAT-MILK ANIMAL-MEAT VEGETABLES NUCLIDf (MREM/YR (M2.MREM/YR (M2;MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.NREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC)
H 3 6.4E+02 O.OE-01 1.2Et03 2.4Et03 1.8Et02 2.9E+03 NA 24 1.6Et04 1.2Et07 4.5E+06 B.QEt05 9.2E-04 1 .6Et05 CR 51 1.7E+04 4.7E+06 2.5Et06 4.4Et05 2.2E+05 1.6Et07 MN 54 1.6E+06 1.4E+09 1.1Et07 1.7Et06 4.3E+06 6.9Et08 MN 56 1.2E+OS 9.0E+05 B.BE-.01 1.6E-01 O.OE-OO 1.1Et03 FE 55 1.1E+05 O.OE-01 6.1E+07 9.6Et06 2.5E+08 7.6Et08 FE 59 1.3E+06 2.7E+08 9.5E+07 1.7Et07 3.0Et08 1.2Et09 CO 58 1.1Et06 3.BE+08 3.4E+07 5.6E+06 4.7E+07 5.3Et08 CO 60 7.1E+06 2.3E+10 1.4E+08 2.0E+07 2.2E+08 2.1Et09 CU 64 3.7E+04 6.1Et05 1.7Et06 2.9E+05 6.5E-06 2.2Et05 ZN 65 1.0E+06 7.5E+08 6.BE+09 1.0E+09 6.2E+08 3.0Et09 ZN 69M 1.0E+05 1.3E+06 2.2Et07 4.0Et06 7.2E-04 9.0Et05 AS 76 7.0E+04 3.BE+06 2.2E+07 4.0Et06 1.1E+01 3.3Et06 BR 82 2 'E+04 2.1E+07 5.BE+07 1.0E+07 7.6Et02 9.5Et05 SR 89 2.2E+06 2.2E+04 3.1E+09 9.2E+09 2.3E+08 6.0Et10 SR 90 3.BE+07 6.7Et06 1.0E+11 2.BE+11 9.8Et09 2.1Et12 ZR 95 2.2E+06 2.5E+08 4.2E+05 7.0E+04 3.0ftOB 1.3Et09 NB 95 6.1E+05 1.4E+08 1.1Et08 1.BE+07 1.0E+09 6.2Et08 ZR 97 3.5Et05 3.0E+06 2.1E+04 3.BE+03 3.5E-Oi 5.2Et06 NB 97 2.8Et04 1.Sf+05 4.2E-07 7.6E-OS O.OE-01 8.2E-02 MO 99 1.3E+05 4.0E+06 8.7E+07 1.6E+07 1.2E+05 1.6Et07 TC 99M 4.8Et03 1.BE+05 7.4Et03 1.3E+03 3.4E-18 2.2E+03 RU106 1.4Et07 4.2Et08 7.9E+05, 1.2E+05 3.BE+10 1.2E+10 AG110M 5.5Et06 '3.5E+09 9.4E+09 1.4E+09 3.8Et08 3.0Et09 SB124 3.2Et06 6.0Et08 3.3E+08 5.4E+07 S.BE+07 3.3Et09 SB125 2.3E+06 2.4E+09 1.2E+08 1.7E+07 3.8Et07 1.2Et09 SB126 1.1E+06 8.4E+07 2.2E+08 4.0E+07 2.7Et07 1.4E+09 SB127 2.3Et05 1.7E+07 5.5Et07 1.0Et07 7.2E+05 9.2Et07 TE127 5.Sf+04 3.0Et03 5.9E+04 1.1E+04 6.7E-09 1.7E+05 Tf131M 3.1ft05 S.OEt06 1.1E+07 2.1E+06 5.0E+03 9.9Et06 I 131 1.6E+07 8.BE+06 1.1Etli 1.9E+11 1.4E+09 1.2Etll I 132 1.9Et05 6.2ft05 1.5Et01 2.7E+Oi O.OE-OO 1.6Et03 I 133 3.BE+06 1.2E+06 9.9Et08 1.8Et09 3.3E+01 1.7E+08 I 135 7.9Et05 1.3Et06 2.1Et06 3.8Et06 2.3E-15 2.1E t06 CS134 1.0E+06 6.9E+09 2.0E+10 7.5E+10 8.3f+08 2.6E+10 CS136 1.7E+05 1.5Et08 1.3Et09 6.0Et09 2.1Et07 1.'1Et09 CS137 9.1E+05 1.3E+10 1.9Et10 6.BE+10 7.9E+08 2.5E+10 CS138 8.4E+02 3.6E+05 3.2E-23 1.4E-22 O.OE-OO 3.6f -11 BA140 1.7Et06 2.1E+07 5.6Et07 1.Of+07 2.1E+07 1.4Et09 LA140 '.3Et05 1.9E+07 9.5Et04 1.7Et04 2.BE+02 1.6E+07 CE141 5.4f+05 1.4Et07 6.3Et06 1.1E+06 6.4E+06 9.0EtQB CE144 1.2Et07 7.0Et07 7.0E+07 1.1Et07 1.0Et08 1.1Etl0 ND147 3.3E+OS S.SEt06 2.8Et05 S.OEt04 7.4Et06. 4.8Et08 HF179M 7.4Et04 O.OE-01 O.OE-01 O.OE-01 0.0E-01 O.OE-01 HF181 2.2Et05 2.1E+08 5.9Et05 9.9E+04 4.4E+09 1.BE+09 W 185 6.9E+05 1.8Et04 2.7E+07 4.3E+06 7.3ft06 8.3Et08 66
CONTRGLLEG COPY fg
AMFNDMENT NO. 6 November 1988 CONTIROLLED COPY TABLE 3-5 d DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RELEASES AGf GROUP: INFANT ORGAN OF REFEREN(f: MAXIMUM ORGAN R(I), INDIVIDUAL PATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES RADIO- INHALATION GROUND PLANE COW-MILK GOAT-MILK ANIMAL-MEAT VEGETABLES NUCLIDE (MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR PER UCI/M3), PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC)
H 3 3.7E402 O.OE-01 1.8E+03 3.7E+03 O.OE-01 O.OE-01 NA 24 1.1E004 1.2E+07 7.8f+06 1.4E+06 O.OE-Oi O.OE-01 CR 51 1.3E>04 4.7E+06 2.2E+06 3.BE~05 O.OE-01 O.OE-Ol MN 54 i.'Of~06 1.4E+09 2.1E+07 3.1E+06 O.OE-01 O.OE-01 MN 56 7.2E+04 9.0E+05 1.3E+00 2.4E-01 O.OE-01 O.OE-01 FE 55 8.7E+04 O.OE-01 7.4E+07 1.2E+07 O.OE-01 O.OE-01 FE 59 1.0E+06 2.7E+08 1.8E+08 3.4E+07 O.OE-Oi O.OE-01 CO 58 7.8E+05 3 'E+08 2.9E+07 4.BE+06 O.OE-Oi 0.0f-01 CO 60 4.5E+06 :2.3E+10 1.2E+08 1.7E+07 O.OE-01 O.OE-01 CU 64 1.5E+04 6.1E+05 1.9E+06 3.2E+05 O.OE-01 0.0f-01 ZN 65 6.5E+05 7.5E>08 1.2E+10 1.7E+09 O.OE-01 O.OE-01 ZN 69M 4.1E+04 1.3E+06 2.4E+07 4.3E+06 O.OE-Oi O.OE-Oi AS 76 2.7EI04 3.8E+06 2.2E+07 4.0E+06 O.OE-01 O.OE-01 BR 82 1.3E+04 2.1E+07 9.8E+07 1.8E+07 O.OE-01 Q.OE-01 SR 89 2.0E+06 2.2E+04 6.0E+09 1. 8E+10 O.OE-Ol O.OE-01 SR 90 1.6E+07 6.7E+06 1.2E+11 2.9E+11 Q.OE-Oi O.OE-01 ZR 95 1.8E+06 2.5E+08 4.0E+05 6.5E+04 O.OE-01, O.OE-01 NB 95 4.8E+05 1.4E+08 9.6E+07 1.7E+07 O.OE-01 O.OE-01 ZR 97 1.4E+05 3.0ft06 2.2E+04 4.0E+03 O.OE-01 O.OE-Oi NB 97 2.7E+04 1.8E+05 1.1E-06 1.9E-07 O.OE-01 O.QE-01 tS 99 1.3ft05 4.0E+06 1.6E>08 2.8E+07 O.OE-01 O.OE-01 TC 99M 2.0E+Q3 1.8E+05 8.2E+03 1.5E+03 O.OE-Oi O.QE-Oi RU106 1.2E~07 4.2E+08 8.0E+05 1.2ft05 O.OE-01 O.OE-01 AGiiOM 3.7E+06 3.5E+09 8.2E+09 1.2f+09 O.OE-01 O.QE-01 SB124 2.6E+06 6.0E+08 3.1E+08 5.1E+07 O.OE-01 0.0E-01 SB125 1.6E>06 2.4E+09 1.1E+08 1.6E+07 O.OE-01 O.OE-01 SB126 9.6E+05 8.4E+Q7 2.1E+08 3.7E+07 O.OE-01 O.OE-01 SB127 2.2E+05 1.7E+07 5.5E+Q7 9.9E+06 O.OE-01 O.OE-01 TE127 2.4fi04 3.0E+03 6.8E+04 1.2E+04 O.OE-01 O.OE-01 TE131M 2.0E+05 8.0E+06 1.2E+07 2.1E+06 O.OE-01 O.OE-01 I 131 1.5E+07 8.6E+06 2.6E+11 4.7E+11 O.OE-01 O.OE-01 I 132 1.7E+05 6.2E+05 3.4E+Oi 6.1E+01 O.OE-01 O.OE-01 I 133 3.6E406 1.2E+06 2.4E>09 4.3E+09 O.OE-01 O.OE-01 I 135 7.0E+05 1.3E+06 4.9E+06 8.9E+06 O.QE-01 O.OE-Oi CS134 7.Of<05 6.9E+09 3. 7E+10 1.4E+11 O.OE-01 Q.OE-01 CS136 1.3E405 1.5E+08 2.BE+09 1.2E+10 O.OE-01 O.OE-01 CS137 6.lfi05 1.3E+10 3.6E+10 1. 3E f11 O.OE-01 0.0f-01 CS138 8.8E+02 3.6E+05 1.2E-22 5.6E-22 O.OE-Oi Q.OE-01 BA140 1.6ft06 2.if~07
'1 ~ 9E+07 1.2E+08 2.ifi07 0.0E-01 O.QE-01 LA140 1.7E+05 9.4f+04 1.7E<04 O.OE-01 O.OE-01 CE141 5.2E005 1.4E+07 6.4E+06 1.if~06 O.QE-01 O.OE-01 CE144 9.8f+06 7.0E+07 7.if+07 1.if~07 O.OE-01 O.OE-01 ND147 3.2E+05 8.5E+06 2.BE+05 5.Of~04 O.OE-01 O.OE-01 HF1 79M 2.8E+04 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 HF181 8.4E>04 2.1E+08 5.9E+05 9.9E~04 0.0E-01 O.OE-01 W 185 6.3E+05 1.8E+04 2.7E+07 4.4E~06 O.OE-01 O.OE-01 67
CONTROLLED COPY AMENDMENT NO. 6 CGNTRGLLEG CQPY November 1988 Table 3-9 INPUT, PARAMETERS NEEDED FOR CALCULATING DOSE SUMMARIES TO THE MAXIMUM INDIVIDUAL AND THE POPULATION NITHIN 50 MILES FROM NNP-2 GASEOUS EFFLUENT In ut Parameter Value Reference*
Distance to Maine (miles) 3000 Ref 1 Fraction of year leafy vegetables are grown 0.42 Ref 2 Fraction of year cows are on pasture 0.5 Ref 2 Fraction of crop from garden 0.76 Ref 3 Fraction of daily intake of cows
'erived from pasture while on pasture 1.0 Ref 2 Annual average'relative humidity (5) '3.8 Ref 4 Annual average temperature (Fo) 53.0 Ref 5 Fraction of year goats are on pasture 0.75 Ref 2 Fraction of daily intake of goats derived from pasture while on pasture 1.0 Ref 2 Fraction of year beef cattle are on pasture 0.5 Ref 2 Fraction of daily intake of beef cattle derived from pasture while on pasture 1.0 Ref 2 Population within 50 miles of plant by direction and radii interval in mi 1 es. 252,356 Ref 6 Annual 50-mile milk production
( 1 i ters/yr) 2.8E+08 Refs 7 & 9 Annual 50-mile meat production (kg/yr) 2.3E+07 Refs 7 & 9 Annual 50-mile vegetable production (kg/yr) 3.5E+09 Refs 7 & 9.
Source terms Ref 8 71
CGNTRGILLEG CGPY AMENDMENT NO. 6 November 1988 C0NTR@J.gg COPY REFERENCES FOR VALUES LISTED IN TABLE 3-9 Reference 1 U.S. Hap Reference 2 Site Specific Reference 3 Regulatory Guide 1.109, Revision 1, Table E-15 Reference 4 Section 2.3, WNP-2 FSAR, Table 2.3-1 Reference 5 Section 2.3, WNP-2 FSAR, page 2.3-3 Reference 6 WNP-1 & WNP-2 Emergency Preparedness Plan Table 12.1, Permanent Population Distribution, Rev 5, Feb. 88 Reference 7 1986 50-Hile Land Use Census, WPPSS REHP Reference 8 WNP-2 Effluent Analysis for Applicable Time Period Reference 9 Radiological Programs Calculation Log No. 88-3 Reference 10 WNP-2 XOQDOQ Computer Run 86
CGNTIRGLILEG. CGPV 11 x k
AMENDMENT NO. 6 November 1988 TABLE 3-16 ANNUAL D I I IN WNP-2 SITE BOUNDARY Source: WNP-2 Gaseous Effluent Whole Thyroid Distance Occupancy Body Dose Dose Location Miles hrs/ r mrem/ r mrem/ r BPA Ashe Substation 0.5 N 2080 1.1E+00 1.7E+00 DOE Train 0.5 SE* . 78 6.7E-02 1.0E-01 Wye Burial Site 0.5 WNW 4.1E-03 6 'E-03 f
WNP-1 1.2 ESE 2080 3.8E-02 1.3E-01 WNP-4 1.0 ENE 2080 7.0E-02 1.1E-01 WNP-2 Visitor Center 0.08 ESE 8.6E-02 1.3E-01 Taylor Flats"~ 4.2 ESE 8760 , 3.1E-02 5.2E~OO Site Boundary*"" 1.2 SE 8760 1.1E+00 1,.7E+00
- The sector with the highest X/9 values (within 0-0.5 mile radius) was used.
- Not within site boundary. Closest residental area representative of maximum individual dose from plume, ground, ingestion, and inhalation exposure pathways. Included for comparison.
- Assumed continuously occupied. Actual occupancy is very low. Doses from Inhalation and Ground Exposure pathways. No food crops.
- 88
AMENDMENT NO. 6 November 1988 CONTROLLED COPY Plenum Monitors
~Rx Bld .
Refueling Exhaust To Pump Rooms Plenum Elevated Main Steam Tunnels RM Release Plenum Monitors Turbine Bldg.
Cond. Pump Rm. Exhaust To Turb. Opr. Deck Pl enum Atmosphere Condenser Area RM Radwaste Bld .
Hot Mach. Shop Filter To Chem. Labs Units Atmosphere Demin. Room Radwaste Proc. Area RM Control Room SIMPLIFIED BLOCK DIAGRAM OF GASEOUS WASTE SYSTEM Figure 3-2 9oa
AMENDMENT NO. 6 November 1988 Main Condenser Air Ejector. Off-Gas Condensers Preheaters Hater Off-Gas Off-Gas Separator Condenser Recombiners Gycol Off-Gas Off-Gas Cooler Moisture Pre-Filters Condenser Separators Charcoal Coolers Dr yers Absorbers Post Treatment Monitor, After Filters Elevated Release SIMPLIFIED BLOCK DIAGRAM OF OFF-GAS TREATMENT SYSTEM Figure 3-3 90b
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