Determination of Max Permissible Concentrations in Water for Xe-133 & Xe-135 for Mar 1975.Prepared for Met EdML19210A605 |
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Three Mile Island |
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Issue date: |
03/31/1975 |
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From: |
PORTER CONSULTANTS, INC. |
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Shared Package |
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ML19210A602 |
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References |
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GQL-1389, PGC-TR-108, NUDOCS 7910300642 |
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Category:NON-RECURRING TECHNICAL REPORT (ENVIRONMENTAL)
MONTHYEARML20245F1141988-12-31031 December 1988 Ecological Study of Susquehanna River Near Tmi,Annual Rept for 1988 ML20151D0831987-12-31031 December 1987 Radiation Monitoring Sys for Nuclear Power Plants (W/Special Ref to TMI Nuclear Power Station) ML20094G1571984-07-30030 July 1984 PRA of Offsite Releases Initiated by Toxic Chemical Release, Final Rept ML20235N2021979-04-15015 April 1979 Preliminary Estimates of Population Dose & Health Effects ML20197E4661978-04-30030 April 1978 Natl Environ Studies Project:De Minimus Concentrations of Radionuclides in Solid Wastes ML19249F1231977-03-31031 March 1977 Spent Fuel Pool Mod Environ Impact Evaluation. ML19210B0191977-01-31031 January 1977 Rept of Water Quality & Heavy Metals Analysis for 760224-1102 & 760406-1019 to TMI-1, Jan 1977 ML19290A4011976-01-31031 January 1976 Rept of Water Quality & Heavy Metals Analysis for Apr-Oct 1975 & Jan-Dec 1975, Prepared for Met Ed ML19210A6051975-03-31031 March 1975 Determination of Max Permissible Concentrations in Water for Xe-133 & Xe-135 for Mar 1975.Prepared for Met Ed 1988-12-31
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W/900222 Ltr ML20059G1151989-12-31031 December 1989 TMI-1 Effluent & Offsite Dose Rept for Jul-Dec 1989 ML20247F7781989-08-31031 August 1989 Programmatic Environmental Impact Statement Related to Decontamination and Disposal of Radioactive Wastes Resulting from March 28, 1979 Accident Three Mile Island Nuclear Station, Unit 2.Final Supplement Dealing with ML20247A4021989-08-31031 August 1989 Environ Assessment & Finding of No Significant Impact Re 870225 Application for Amend to License DPR-23,revising App a Tech Specs by Deleting Prohibition on Disposal of Accident Generated Water ML20246J2511989-06-30030 June 1989 TMI-2 Quarterly Dose Assessment Rept for Second Quarter 1989 ML20246J2631989-06-30030 June 1989 TMI-2 Semiannual Radioactive Effluent Release Rept for First & Second Quarters 1989 ML20246M7821989-06-30030 June 1989 Effluent & Waste Disposal Semiannual Rept for Jan-June 1989 ML20247R7151989-03-31031 March 1989 Effluent & Offsite Dose Rept for Jan-Mar 1989 ML20235L8791988-12-31031 December 1988 10CFR20.407 Personnel Exposure, Annual Rept ML20235W8161988-12-31031 December 1988 Second Half 1988 Semiannual Effluent & Release Rept for TMI-1 ML20235L8761988-12-31031 December 1988 Number of Personnel & Man Rems by Work & Job Function, Annual Rept ML20235M4941988-12-31031 December 1988 Personnel Exposure Rept - 1988 ML20245F1141988-12-31031 December 1988 Ecological Study of Susquehanna River Near Tmi,Annual Rept for 1988 ML20235U3171988-12-31031 December 1988 TMI-2 Quarterly Radioactive Effluent Release Rept for Oct- Dec 1988 ML20245F0681988-12-31031 December 1988 1988 Annual Environ Operating Rept,Part a: Nonradiological ML20245H8551988-12-31031 December 1988 TMI-1 Annual Rept for 1988,including CY88 Tabulation of Personnel Exposure,Aircraft Movement Data from Harrisburg Intl Airport,Leak Reduction Program Test Info & Pressurizer PORV & Pressurizer Safety Valve Challenges ML20155J0191988-10-19019 October 1988 Environ Assessment & Finding of No Significant Impact Re Exemption from 10CFR50.54(w)(5)(i) Re Schedular Requirements of Property Insurance Rule,Effective 881004 ML20205G8601988-09-30030 September 1988 TMI Aquatic Study,Monthly Progress Rept for Sept 1988 ML20195J8971988-09-30030 September 1988 TMI-2 Effluent & Offsite Dose Rept for Jul-Sept 1988 ML20155G7911988-09-30030 September 1988 TMI Aquatic Study,Monthly Progress Rept for Sept 1988 ML20235Q7271988-09-30030 September 1988 Corrected Quarterly Dose Assessment Rept for Third Quarter 1988,consisting of Corrected Summary of Liquid & Gaseous Effluents ML20207J4791988-09-20020 September 1988 Environ Assessment & Finding of No Significant Impact Re Exemption from Requirements of 10CFR55 ML20151Y7521988-08-23023 August 1988 Environ Assessment & Finding of No Significant Impact Re Util 871228 Request for Exemption from 10CFR55.59 to Eliminate Requirement That Operator Requalification Program Cover Plant Protection Sys & ESFs ML20151Z5951988-07-31031 July 1988 TMI Aquatic Study Monthly Progress Rept for Jul 1988 ML20153D7351988-06-30030 June 1988 Effluent & Offsite Dose Rept for Apr-June 1988 1999-07-15
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
[Table view] |
Text
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' ~- i PGC Report - -
. 1 A DETERMINATION OF THE MFC.,'S .-
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FOR '34XE & 1"XE It! WATER s . $
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March 1975 .
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I. Introduction
- Xenon-133 and Xenon-135 are radio-noble gases which can be found in power reactor liquid effluents. It is the purpose of this report to detemine the Maximum Pemissible Concentration in Water (MPC y )' of these radionuclides for the general population.
II. Xenon In The Water Environment A. Maximum Specific Activities Attainable in Water The maximum specific activities of Xenon-133 and Xenon-135 attainable in the water environment are functions of solubility and intrinsic specific activi-ties. The concentration of Xenon in water can be detemined by Henry's Law.
This law states that the solubility of a gas in a liquid is directly propor-tional to the pressure of the gas above the liquid at equilibrium. Mathema--
t':: ally Henry's Law may be expressed as, C = kP ,
1.
where C is the weight of gas in the liquid, P is the atmospheric partial ^
pressure, and k is Henry's constant for a given gas and a given temperature.
At 0 C and 1 atmosphere partial pressure,242 ml of Xenon will be soluble -
in 1 liter of water (1). And, by extrapolation it can be shown that I lit er of water at 10 C can absorb approximately 210 ml of Xenon at 1 atmosphere pressure. Since the density of Xenon is 5.85 mg/ml (2) Henry's constant at -
10* C for Xenon is 1.23 g/1-ata. The mole fraction of Xenon in the atmos-phere is 8 x 10-a(3); therefore,substitutin3 into equation 1, C = (1.23g/1-atm)(8 x 10-3 atm) = 9.8 x 10-89/1 2.
it is fcund that I liter of water can absorb up to 9.8 x 10-8 g/l of Xenon a- 10 C. .
i The intrinsic specific activities of Xeno1-133 and Xenon-135 are 1.85 x 105
~
Ci/g and 2.55 x 105 C1/g, respectively. As such each liter of water can ab-sorb a maximum of either 1.8 x 10-2 Ci of Xenon-133 or 0.25.Ci of Xenon-135. .
These values are equivalent to 18 uCi/mi of Xenon-133 or 250 pCi/mi of Xenon ,
-135. '
III. Detemination of MPC, .
The calculation of an adult MpCyequal to 5000 mrem / year for the drinking -
water pathway is based on the following equation (4):
1.3x10-6 mRA D .
MPC" 3. .
f,(i - e-l t)o I E F gj (RBE)jng .
Each tem in this equation is discussed below.
1492 (07 1
m-
~ m is the mass in grams of the critical organ. It has been shown that Xenon is concentrated in the body fat approximately ten to twenty times above the level in the blood stream (5). Thus the body fat is considered to be the critical organ; its mass is 10,000' g(4).
R- R is the permissible dose rate to the organ in rems / week. Since the body fat is the critical crgan, and since it is distributed through the whole body, R is taken as 0.1.
Ao -lo is the effe:tive decay constant, it is a combination of the physicai and biological decay constants. In order to calculate lo the bie'agi- -
cal half life (T ) bmust be determined. .
Tb =0.693mC/ 4,
/ Ifw i
where, '
m = cass of critical organ = 10,000 g I i
C = average tissue concentration = 1.1 x 10-s g/kg based on equation 1 with k equal to 0.68 g/1-atm at 37.8a C and .
j:
a concentration factor of 20 ..
I = average daily ingestion rate = 2.3 x 10-7 g based on a water plus fluid uptake of 2200 cc/ day and 300 cc/ day .
of water of oxidation produced in the body, therefore -3 J
intake is 2.21(9.8 x 10-a g/l) + 0.31(0.68 g/l-atm)(8 -
x 10-8 atm) f y= 0.95 based on a fraction from GI tract to blood of 1.0 f.
p and a concentration factor of 20 in the body fat ,
h t' .
'b (XS)" 0.693(10,000)(1.1x10-9) /
/(2.3x10-7)(0.95) = 35 days 5.
., f.;.
U.
E eff Tb+T p 6.
i.' . .
3 2, T3ff(133Xe) = = 4.53 days 7. ,
t . ' .-
q T
eff(13sXe) =( f( g) = 0.38 days
- 8. -
f
- '. N, 0.693 -
i Ao" T
eff -
9' o
.l g(133Xe) = 0.693/4.58 = 0.151/d 10. !
V 1 r' 1492 108 !
2 -
- 0.693 (13sxe}= 0.38 " 1*
t_ - t is the time which in this case is 365 days 133Xe ,f reference IEjfj(RBE)ingand - effective energy for organ o 0.090 for 135Xe (4) drinking are, y
Referring back to equation 3 the adult MPC 's for .
12.
(1.3x10-6 )(10,000)(0.1'l(0. t st l = 7.7x10-2u ci/ml 13 Xe MPCv (0.95)(1-e-(0.143)(365))(0.0027) 13.
(1.3x10-6)(10,000)(0.1)(1.821 2.8x10-2pCi/ml 13sxe HPC u (0.95)(1-e-(1.82)(365))(0.090) i and are not repre-The MPCy's calculated above are for the adult l populat tion must be onIn orde sentative of MPCv's for the general population. the for the general population the age discribution of the popu a considered.
However, it would be impractical toatadd to arrive gen- this v
!!PC . calculationalThescheme.10 MPCy 's for 133XeCFR 20, the und 13sXe adult MPCy's ar are then:
eral population MPCy's.
= 8 x 10-3 pCi/mi 133XeMPCy pCi/mi 13sXegp q = 3 x 10-3 P
4 1492 1D9 s ,
IV. Conclusions MPCy
's were calcusated for 133Xe and 13sXe in water. The critical organ was the body fat. The MPC y val es found were lower than the solubility of Xenon in water. Ft.rther analysis has shown that drinking water is the critical dose pathway. Apper. dix A of this report reviews other dose pathways.
I i
9 h
k 1
492 110 J N
E 4
i References Lange, N.A. Handbook of Chemistry _,. Ninth Edition. Handbook Publi-1.
shers, Inc. Sandusky, Ohio. 1956. .
Eshback, 0.W. Handbook of Engineering Fundamentals. John Wiley &
2.
Sons, Inc. New York, 1952.
- 3. Gray,D.E.(Ed.) American Institute of Physics Handbook. McGraw-Hill Book Company, Inc. New Yort. 1957. ..
~
- 4. Recomr.endations of the International Commission on Radiological Pre-te::fon. ICRP Publication 2. Report of Committee New II on Permissible York. 1959.
Dose for Internal Radiation. Pergamon Press.
- 5. Itaghissi, A.A. Personal Communication.
O s
a D
e 6
5
~
Appendix A I. Introduction .
In this appendix general population MPC.,,'s are calculated for dose pathways other than drinking for Xenon in water. These pathways are swiming and shine at the shoreline. Adult dose conversion factors are also calculated '
for these pathways as well as the drinking water pathway. General popula-
- tion MPC.,'s and adult dose conversion factors were chosen to agree with 10 CFR 20 and ALAP philosophy respectively. 1 II. Swimino Pathway _
The calculation of an MPCy equal to 5000 mres/ year for the swiming path-way is based on the following assumptions- l
- 1. The maximum individual swims 107 hours0.00124 days <br />0.0297 hours <br />1.76918e-4 weeks <br />4.07135e-5 months <br /> per year (1)
- 2. The critical organ is the whole body
- 3. Adult dose conversion factcr. (DCF)are(1):
5.7 x 10-8 mrem /hr/pCi/l for 133Xe 4.5 x 10-7 mrem /hr/pCi/l for 135Xe ,
The equation for calculating an MPC. s based en a dose conversion factor is, p
MFC..(uCi/ml) = (5000 mrem / year)(10-3 Ci/ml/pCi/1)
/ (D /, CF)(t) 1; ;
l Therefore the adult MPC.,'s are, .
(~
132x*M?C y
= (5000)(10-3)!(5.7x10-a)(100)=0.88pCi/mi ,
. 2. .
I'#X0 (4.5x10-7)(100) = 0.11 pCi/ml 3.
MPCy ,
and the general population MPC y 's are,
= 0.1 pCi/ml 4.
133XeMPC
= 0.01 pCi/ml 5.
135XeMPC v III. Direct Radiation At The Shoreline Xenon is a noble gas and will not absorb in the ~ sediments; therefore the ex-posure is limited to the shine dose from the dissolved gas. The following
+
A-1
F assumptions are made,
- 1. The problem is defined as primary ionization above an infinite disc where buildup due to scatter and absorption cancel each other out
- 2. At a point above the center of the disc the dose is equal to the 2r air imersion dose minus a correction factor, F (2)
- 3. Then at a point above one edge of this infinite disc the dose is the 2x irmersion dose minus a correction factor, that is, (2x imersion dose)(1-F) 6. ?(;.
Dshine =
where, ..
F = e-Vo - vo[Euo ) 7.
and, ,
- i o
dt 8.
Ev a
=fe-vt t
therefore by integration, ,
g pt o 9t22 vjt 3 ,,,
vDtn Eu = log t + + + 9. s 0 11 2 2! 3 3! n n!
apply limits with, .
p o(133Xe)=0.2cm/g 2 (3) 10.
5 11.
and 9 0 (135Xe) = 0.12 cm2 /g (3) then, 12.
Euo(1334e) = 0.19 and Eva (13sXe) = 0.12 13..
and from equation 7, F (133Xe) = e-o.2 - 0.2(0.19) = 0.78 14.
and F (13sXe) = e-o.12 - 0.12(0.12)~= 0.87 15.
Therefore from equation 6 and utilizing the 2n ir=ersion DCF's in reference 1 the dose conversion facto,rs a' re, DCF(133Xe)= (2.8x10-8 mrem /hr/pCi/1)(0.22)=3.1x10-9 mrem /hr/pCi/l 16.
~
DCF(13sXe)=b(2.2x10-7 mrem /hr/pCi/1)(0.;3)=1.4x10-emrem/hr/pCi/l 17. ,
And the adult P.PC/s for 5000. mrem / year are, in a fashion analagous to equa- ,
tion 1, t
32 1492 113
133XeMPC y
" (5000)(10-9)
, / /(3.1x10-9)(365)(24) = 0.18pCi/ml 18. ,
135Xe MPCy
"( }(
p (1.4x10-8)(365)(24) = 4.1x10-2 Ci/ml 19.
And the general population MPC y 's are, 133Xe = 0.02 pCi/ml 20. h, ,
MPC y 135Xegp q = 4 x 10-3 uCi/ml 21.
These MPC y 's are overly conservative in that they assume an individual would stand at the shoreline all year, which is unrealistic. The dose rate drop.s off very rapidly with distance from the shoreline.
IV. Deterniination of Dose Conversion Factorr (DCF's) ,
A. Drinking Water Pathway '
The OCF's are determined by rearranging equation 1 to, nr.e
~
, (5000 mrem / year)(10-9 uCi/ml/cCi/1) 22*
(MFCw pCi/ml)(hours / year) and substituting the appropriate values. The DCF's are,
" ^*0CF * (5000)(10-9)!(7.7x10-2)(365)(24)v 7.4x10-9 mrem /hr/pCi/l 23.
13sz
- 2.8x10-2)(365)(24)= 2.0x10-8 mrem /hr/pCi/l 24.
GCF B. Swimino Pathway The DCF's are given in reference 1. They are, based on whole body dose, 133Xe = 5.7 x 10-8 mrem /hr/pCi/l 25. -
g7 13sXeDCF = 4.5 x 10-7 mrem /hr/pCi/l 26.
C. Direct Radiation At The Shoreline [
These values are as calculated in equations 16 and 17. They are,
, ; 13 3X DCF ~~ * * """
- 1 135Xe0CF = 1.4 x 10-8 mrem /hr/pCi/l 28.
A-3
... ,; ~
. . .;
!. .'ha '
,7 ,. '-s
, V. Suc:ary .;'/j General Population MPCy Values '
based on 5000 mrem / year (uCi/ml) Solubility in Water ..
2
/ \ at 10*C and Drinking Swiming Shoreline 80 nata. Xe ,
133Xe 8 x 10-3 0.1 0.02 18 , ,
i 13sXe 3 x 10-3 0.01 4 x 10-3 250 -
.yj Adult Dose Conversion Factors mrem /hr/oCi/l Drinking Swinaing Shoreline -
133Xe 7.4 x 10-9 5.7 x 10-8 3.1 x 10-9 -
13sXe 2.0 ,: 10-8 4.5 x 10-7 1.4 x 10-8
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1 References t
- 1. U.S.A.E.C. Final Environmental Statement. 'fiumerical Guides For Design Objectives and Limiting Conditions For Operation To Meet The Criterion "As Low As Practicable" For Radioactive Material in Light-Water Cooled fluclear Reactor Effluents. Volume 2. Analytical Itodels and Calcula-tions. WASH-1253. July, 1973.
- 2. Evans, R. The Atomic flucleus. McGraw-Hill Book Company, Inc. flew York. ' -
1955.
- 3. Lapp, R.E. and H.L. Andrews. fluclear Radiation Physics. Prentice-Hall, In:. Englewood Cliffs. 1964.
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Appendix B I. Introduction ,
In this appendix adult dose conversion factors specific to TMINS are calculated for the applicable pathways. Adult dose conversion factors were chosen to agree with the ALAP philosophy. These pathways include the maximum individual drink-ing, the closest realistic drinking individual supplied by a water company, Brunner Island, the individual swirming, and the individual on the shoreline.
All values are in mrea/hr/pCi/l for the effluent concentration.
m -
II. Drinkinc Pathway The licuid outfall at TMINS is submerged and is diluted approximately 1.7 x 104 tices. This dilution factor is based on a maximum pump flow of 30 gpm, a min-imum blowdown flow of 5000 gpm and a river dilution factor of 100. Therefore the concentration of radio-Xenon in the river water (C y ) is v 1.7 x 10 4 '
where CE is the concentration of radio-Xenon in the station effluent.
A. Maxitum Individual The caximum individual drinks 1200 ml of river water per day at the point of discharge. If credit is taken only for dilution and not for physical decay the TMINS site specific dose conversion factors are,
/
1200 133Xe n = (7.4x10-9)(2
( M = 2.4 x 10-13 uCr- 1.7x10g C
13 sX e ,,.
= E(2.0x104)h = 6.4 x 10-13 1.7x104 B. Individuals That Work At Brunner Island The individuals who work at Brunner Island drink 600 ml of water during their work day. The Brunner Island river intake is 4.2 miles below the TlilNS out-fall and as such the travel time is about 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. For calculation of these dose conversion factors crc - for radioactive decay equal to the travel time' is taken. The dose :onver';i; factors are, 9
13 3Xe =C( 4*lW)2 E '
e-blM M = 1.1 x 10-13 DCF 1,7xtwq 1492 17 B-1
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135Xe DCF
= CE (2.0x10-a) 2 0 e~ = 1.6 x 10-13 1.7x104 II. Swi m ing Pathway 133Xe 4= ~4 x 10-12 DCF
=(5.7x10-s)/1.7x10 ,
13sXe = (4.5x10-7) = 2.6 x 10-11 DCF 1.7x104 III. Direct Radiation At The Shoreline 133Xe0CF * (3.1x10-9) 1.7x10g= 1.8 x 10-13 13sXe =(1.4x10-8) = 8*2 x 10-13 OCF 1.7x104 IV. Samole Problem If the effluent at TMINS contained 10-2 pCi/ml (107 pCi/ 1) each of 133Xe.and 135xe the resultant doses to the adult population are as in the table below.
Max Ind Brunner Is Swimming Shoreline Drinking Drinkinc 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> /yr all year 133Xe 2.1x10-2 9.5x10-3 3.4x10-3 1.6x10-2 crem/yr 235Xe 5.6x10-2 1.4x10-2 2.6x10-2 7.2x10-2 mrem /yr 6.= .us - Ar .
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