IA-87-742, Final Response to FOIA Request for Records.App C Documents Encl & Available in PDR
| ML20236U730 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 11/30/1987 |
| From: | Grimsley D NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| To: | Graber L NUS CORP. |
| References | |
| FOIA-87-742 NUDOCS 8712030328 | |
| Download: ML20236U730 (2) | |
Text
{{#Wiki_filter:I f* **w%,, 1 F0IA-87-742 ets m u rwt f. s 3 RESPONSE TO FREEDOM OF 6 I "*" IX l '*'" S-INFORMATION ACT (FOIA) REQUEST NOV 3 01esi Docm hwata son ..e., s tout $7te Mr. Lyle Graber PART l.-RECORDS RELEASED OR 8eOT LOCAttD t$ e checked bossel No agency recorth mApoct to the roovest howe been located. No adspoorwl agency recon $s mepect to tie roguest have been located A 0ency records oAgect to the romaest that ero onentmed m Appendia sie eboody eveisNe for pubhc repection and copveng m the NRC Pm Documere Room, 1717 H Street, N W., Weehogion, DC Aemey recones subsect to the roovest ewi are identmed in Appendts C es timme mods eveasme for putsc rupeemon are copytne h h NRC Pubec Documeg X Room,1717 H Seest, N W., WesNngton, DC, si e fehler under ins FOtA nutreer and resumeser rieme. The namproprtnery weremon of the propomells) het you egreed to accept in a teiephone h _ . _ . meth a member of my staff is now bomg made eveastdo for putse supacton and coytng et tu NRC Putte Document Room 1717 H Street, N W , Weehmgton. DC. e a tender under the FOIA number and wer nome. E.ncioned is ineormaton on how you may obtem access to end the charges for ccoving reopes peaced e the NRC Put$c Document Room,1717 H $treet, N W., Weehogen, DC. Agency recon $s mApoct to the reS#est are enctooed. Any appEcstdo charge for copses of 9e umrds pqmded and payment procedures se noted e the commeme escean Records mabpect to he request hM been referred to another Federal egencyiies) for rowee ed drect respones to you. In wtow of NRC's response to fins reesest, no further scilon le bemg teken on appeal loest dead l PART II.A-INPORMAT104 WITNMELD Paced PUSUC OtSCLOSURE Cermin >formeeen h the reoussied records a being wehead from pubac dociosure pure ==t ne ve toA emenwiiore descreied b and er es reasono ented m Pen s, sec. sore S. C, and D. Any reseened partlore of the documems for wNch on#v part of the reces e tones adinhand are bemo made evenetdo for pubec % mid cap,eng a vie NRC Putdc Document Room.1717 H $treet, N W., WesNngton. DC. in a folder unds fu FOlA number and requester home. Commann l f l l 8712030328 871130 PDR FOIA GRADER 87-742 PDR DentCTOR. 80N os 5 ANDREC0e06 WL AW4h
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NEC FOT,M 404 ite si rs a, l
Re: FOIA-87-742 APPENDIX C
- 1. Enclosure to letter from Iowa Electric dated 8/25/87 transmitting the Semi-Annual Effluent Release Report - PDR Accession No. 8708280278.
(203pages)
4NUS COAPORAT10N !*.LTi&"%# 01&798 Weed . CD-LIS-87-757 . October 28, 1987 l Director I Division of Rules and Records MM OF INFORMA7XW g REQUEST
$i $n, D.C. 20555 "d 7"7h2. f
Dear Sir:
O 'd] 'd) l This is a Freedom of Information Act, request for the following document to be placed in the Public Document Roue: .
- 1. Enclosures to letter from Commonwealth Edison Company (Byron' Unit 1) to llRC dated August 7,1987 regarding inservice inspection performed 2/17/87through5/14/87(Accessionllo. 8708180212).
2. Enclosures to letter from Southern California. Edison transmitting LER86-015 dated 1/12/87(Accessionllo. 8701200203). 3. Enclosures to letter from the llRC to Southern California Edison (San Onofre Units 2 and 3) regarding responses to IE Bulletin 85-03 dated 6/30/87 (Accession llo. 8707070243). 4. Enclosure to letter from Iowa Electr.ic dated 8/25/87 transmitting the Semiannual Effluent Release Report (Accession 11o. 8708280278). If clarification for is needed, please call me at (813) 796-2264. Thank you your assistance. Sincerely. ! Lyle Graber Licensing Engineer . Licensing Information Service l LG/sw i
SEMI-ANNUAL REPORT RADIOACTIVE EFFLUENT RELEASES January 1, 1987 through June 30, 1987 I i O
)
)
~((
': 9 4 $ 6 ? 8 p 3 Y l8 p )
b
l SEMIANNUAL RADIOACTIVE MATERIAL RELEASE REPORT 1987 LIQUID EFFLUENTS
- l l
Nuclides Released Unit 1st Quarter 2nd Quarter strontium-99 Ci 0.00 E 0.00 E strontium-90 Ci 0 00 E 0 00 E cesium-134 Ci 0 00 E 0 00 E cesium-137 Ci 0.00 E 0.00 E iodine-131 Ci 0 00 E 0 40 E cobalt-58 Ci 0.00 E 0.00 E j cobalt-60 Ci 0.00 E 0.00 E f iron-55 Ci 0.00 E 0.00 E l iron-59 Ci 0.00 E 0.00 E zinc-65 Ci 0.00 E 0.00 E manganese-54 Ci 0.00 E 0.00 E chromium-51 Ci 0.00 E 0.00 E zirconium-niobium-95 Ci 0.00 E 0.00 E
.. molybdentin-99 Ci 0.00 E 0.00 E technetium-99m Ci 0.00 E 0,00 E b crium-l anth anum-140 Ci 0.00 E 0.00 E cerium-141 Ci 0.00 E 0.00 E l Other Ci 0.00 E 0.00 E Ci . E , E Ci . E . E Ci . E , E Ci . E , E Total for period Ci 0.00 E 0.00 E xenon-133 Ci 0.00 E 0.00 E xenon-135 Ci 0.00 E 0.00 E
- No liquid release January 1 - June 30,1987.
7
. 1 SEM8 ANNUAL RA010ACTZVE MAJER8AL RELEASE REPORT 1987 GASEOUS EFFLUENTS, Unit 1st Quarter 2nd Quarter
- Nuclides Released l
- 1. Fission gases Ci 0.0 EO 0.0 EO krypton-85 Ci 0.0 EO . 0 .0 EO krypton-85m Ci 0.0 EO 0 .0 EO krypton-87' Ci 0.0 EO 0 .0 EO krypton-88 Ci 3.3 E-1 0.0 EO xenon-133 Ci 2.2 E1 0 .0 EO xenon-135 Ci 1. 8 EO 0.0 EO xenon-135m xenon-138 Ci 1.1 E1 0.0 EO l
Ci 1. 2 E-1 0.0 EO Nitrogen-13 Ci 47 EO 28 E0 Tri tium , Total for period Ci 4. 0 E1 2.8 E0
- 2. Iodines l iodine-131 Ci 16 E-3 1.5 E -3 iodine-133 C1 1.3 E-3 0.0 EO
~ iodine-135 Ci 1. 5 E-5 0.0 EO Total for period Ci 2.9 E-3 1.5 E -3
- 3. Particulate strontium-89 Ci 5.9 E-6 l 7. 4 E -7 strontium-90 Ci 1.1 E-7 l 2.0 E -7 cesium-134 Ci a0 E O l 0. 0 E0 cesium-137 Ci G0 EO i 0. 0 EO barium-l anth anum-140 Ci aO EO l 0. 0 EO ,
Otners Ci G0 EO l 00 EO Ci 1. 4 E -2 ' O. 0 EO Chromium-51 Manganese-54 Ci 2, 5 E-3 4. 8 E -3 Cobalt-58 Ci 9.1 .E-4' 6.0 .E-4 Cobal t-60 C1 1.0 E-2 7.6 E-3 Total for period Ci 2.7 E-2 1.3 E-2
- Plant in refuel shutdown March - June,1987.
FIRST QUARTER 1987 January 1, 1987 to March 31.-1987 IDENTITY OF PRINCIPAL NUCLIDES Dewatered Resin Dry Active Waste, Hot Trash Nuclide Class A Stable (C1) Dewatered Resin, Absorbed Wet Trash Class A, Unstable (Cf) Co-60 21.36 2.252E1 Cs-137 1.149 1.683E-1 H-3 1.98E-2 1.308E-2 Ni-63 5.762E-1 6.561E-1 Sr-90 2.18E-3 9.944E-3 C-14 5.916E-2 3.712E-3 Pu-241 4.83E-3 3.46E-2 Tc-99 4.23E-4 8.007E-3 I-129 7.31E-4 5.270E-3 TRus 2.058E-4 2.48E-5 Np-237 N/A 6.72E-7 Pu-238 N/A 6.590E-4 Pu-239 N/A 2.094E-4 Am-241 N/A 7.816E-5 Cm-243 N/A 1.238E-4 Cm-242 5.33E-5 2.800E-4 Mn-54 6.854 3.352 Cr-51 1.391 2.120 In-65 3.159E-1 4.724E-1
. Co-58 1.526 3.558E-1 Fe-59 2.574E-1 1.56E-2 Cs-134 N/A 5.6E-3 Ni-59 4.487E-2 1.383E-1 Sr-89 6.895E-2 2.944E-2 Pu-242 N/A 1.167E-4 Fe-55 1.453E1 3.895 Nb-94 3.99E-4 4.745E-5 l
1 SECOND QUARTER 1987 April 1, 1987 to June 30, 1987 IDENTITY OF PRINCIPAL NUCLIDES Dewatered Resin Dry Active Waste, Hot Trash Nuclide Class A, Stable (C1) Dewatered Resin, Absorbed Wet Trash Class A, Unstable (C1) Co-60 1.621El 5.287 Cs-137 2.813E-1 9.5498E-2 H-3 9.9E-3 6.54E-3 ] Ni-63 4.381E-1 6.503E-1 Sr-90 5.39E-4 2.36E-2 C-14 2.958E-2 3.401E-2 Pu-241 1.17E-3 8.567E-2 Tc-99 1.03E-4 2.136E-2 1-129 1.76E-4 1.390E-2
~
TRus 5.14E-5 1.235E-5 Pu-242 N/A 3.146E-4 Pu-238 N/A 1.76019E-3 Pu-239 N/A 5.301E-4 Am-241 N/A 1.925E-4 _ Cm-243 N/A 3.309E-4 Cm-242 1.29E-5 6.951E-4 Mn-54 1.335El 3.431E-1 Cr-51 1.12E-1 8.8316E-2 ,
. Zn-65 4.298E-1 6.933E-2 I Co-58 2.872 8.509E-2 Fe-59 3.317E-1 N/A Cs-134 N/A 3.02E-3 La-140 4.39E-3 N/A I
Ni-59 3.41E-2 3.155E-1 Sr-89 1.684E-2 2.972E-2 Fe-55 11.03 9.3268 Nb-94 9.8E-5 2.363E-5
t S U M M A'R Y January 1 June 30,1987 ! BARNWELL, SC RICHLAND, WA TOTAL SOLIDIFIED RESIN ;
- No. of Shipments 0 0 0
- 0 0 0 Volume (ft3) 0
- Activity (Ci) 0 0 ,
l , DEWATERED RESIN (RADLOK 100)
- No. of Shipments 9 0 .9
- 1467. 0 1467 i Volume (ft8) .
0' 93.33
- Activity (Ci) 93.33 l DEWATERED RESIN (HN-100)
- No. of Shipment 6 'O. 6
- 1062 0 1062 Volume (ft8)
- Activity (Ci) 3.119 .0 3.119 DRY ACTIVE WASTE
No. of Shipments 0 9 9 Compactible Volume (ft )
8 0 5336 5336
** Activity (Ci) 0 11.968- 11.968
- Non-Compactible Volume (ft8) 0 -1380 1380 ~
** Activity (C1) 0 1.8257 1.8257 ABSORBED WET TRASH
- No. of Shipments 0 0 0 ,
- 0 2592 2592 -!
Volume (ft8) 6.285 i
- Activity (C1) 0 6.285 ABSORBED LIQUIDS
- No. of Shipments 0 0- 0 ;
l
- 0 0 0 l Volume (ft8)
- Activity (Ci) 0 0 -0 HOT TRASH.
- 0
- 1 No. of Shipments 1
- 3 0 202.5 202.5 Volume (ft ) 27.11 Activity (Ci) 0 27.11.
. j 1
SUMMARY
January 1 - June 30, 1987 BARNWELL, SC RICHLAND. MA TOTAL i
- TOTAL
- No. of Shipments 15 10 25. .j 2529 9510.5 12039.5 Volume (ft) 8 4
- Activity (Ci) 96.449 47.1887 143.6377 )
J
\ l
'
- Absorbed Wet Trash and Hot Trash shipped with Dry Activity Waste Shipments l
l l l i l M i i a 1 i I
SUMMARY
OF CHANGES TO THE OFFSITE DOSE ASSESSMENT MANUAL During the period of January 1, 1987, through June 30, 1987, the offsite Dose Assessment Manual has been revised in six (6) areas.
- The changes are as follows:
- 1. The reference meteorological conditions are from the annual 1986 data. This replaces the previously used composite from 1971, 1974, and 1975. See page 1 - last footnote.
- 2. The Figure 3-1, " Gaseous Radioactive Waste Flow Diagram",
was updated to include the newly constructed LLRPSF (Low Level Radwaste Processing and Storage Facility). See page 42.
- 3. The Table 3-1, " Atmospheric Gaseous Release Points at the Duane Arnold Energy Center", was updated to include the LLRPSF. See page 45.
- 4. The environmental sample station 72 was changed from milk to groundwater. The farmer sold his milk cows. See page 64. l l
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- 5. The page numbers on pages A-41 and A-42 were switched to their proper order.
- 6. The Table A.4-3 was completed by the addition of page A-43, which includes the nuclides of interest from I-135 through Np-239 for " Vegetation Pathway Factors". Previously, this page was omitted. See page A-43.
1
i i OFFSITE DOSE ASSESSMENT MAN h
- for GASEOUS AND LIQUID EFFLUENTS Duane Arnold Energy Center Iowa Electric Light and Power Company 1
Approved by: ! Rabiation Pro e
}M s a ervisor 6!27/(7
' Date Reviewed by:
A s
~/ 7 Reviewed by: "I Ff l P1 ant Aterident '( D(te Issue Date: July 8, 1987
-8 ? pa# 4+JF-(44W Rev 3 06/p7
1 0FFSITE DOSE ASSESSMENT MANUAL FOR GASEOUS AND LIQUID EFFLUENTS 1.0 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 ! 1 2.0 Liquid Effluent ........................2 2.1 Radioactivity in Liquid Waste . . . . . . . . . . . . . . . . 2 2.2 o Aqueous C'ncentration . . . . . . . . . . . . . . . . . . . . 2 2.3 Method of Establishing Alarm Setpoints . .,. . . . . . . . . 3 2.3.1 Setpoint for a Batch Release . . . . . . . . . . . . . 4 2.3.2 Setpoint for a Continuous Release ..........6 2.4 Radioactivity Concentration in Water at the Unrestricted Area Boundary .................8 2.5 Accumulated Personal Maximum Dose . . . . . . . . . . .' . . . .9 2.6 Projected Personal Maximum Dose . . . . . . . . . . . . . . . 12 1 3.0 G aseous Ef fl uent . . . . . . . . . . . . . . . . . . . . . . . . . 13 3.1 Introduction ........................13 3.2 Radioactivity in Gaseous Effluent . . . . . . . . . . . . . . 13 3.3 Main Condenser Offgas Monitor Alara Setpoint . . . . . . . . 15 3.4 Effluent Noble Gas Monitor Alarm Setpoint . . . . . . . . . . 16 { 3.5 Dese Equivalent Rate Offsite '
.22 l 3.5.1 Noble Gas ...... . . . . . .'. . . . . . . . . 22 l
j 3.5.1.1 Tot al Bo dy Do s e . . . . . . . . . . . . . . . 23 3.5.1.2 Skin Dose . . . . . . . . . . . . . . . . . . 24 3.5.2 Iodine, Tritium, and Particulate ..........25 ; 3.5.2.1 Organ Dose Rate . . . . . . . . . . . . . . . 25 l 3.6 Noble Gas Gamma Radiation Dose Accumulated in Air . . . . . . 28 i 3.6.1 Alternate Method of Evaluating Compliance with Gamma Air Dose Limits . . . . . . . . 30 3.7 Noble Gas Beta Radiation Dose Accumulated in Air . . . . . . 32 > 3.8 Dose Due to Iodine and Particulate in Gaseous . Effluents . . . . . . . . . . . . . . . . . . . . . . 33 3.8.1 Alternate Method of Evaluating Doses Due ' to Iodine and Particulate in Gaseous Effluents . . . 37 3.9 Dese to a Person from Noble Gases . . . . . . . . . . . . . . 38 3.9.1 Gamma Dose to Total Body . . . . . . . . . . . . . . . 39 3.9.2 Do s e t o Sk i n . . . . . . . . . . . . . . . . . . . . . 4 0 Rev. 3 i 6/07
4.0 Dose Comitment from Releases over Extended Time . . . . . . . . . . . 50 4.1 Dose Assessment for 10 CFR Part 50, Appendix I . . . . . . . . . 50 4.2 Dose Assessment for 40 CFR Part 190 . . . . . . . . . . . . . . 52 5.0 Radiological Environmental knitoring Program Sampling Station Locations Appendices. . . . . . . . . . . . . . . . . 55 Appendix A: Airborne Pathway Site-Specific Dose Transfer Factors. . . . . . . A-1 Appendix B: Technical Bases for' Effective Dose Factors . ... . . . . . . . . B-1
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Appendix C: Water Pathway Site-Specific Dose Transfer Factors . . . . . . . . C-1 a
. 1 1
i ii Rev. 3 ; 6/87 ; i I
l ! 0FFSITE DOSE ASSESSENT MANUAL FOR GASEOUS AND LIQUID EFFLUENTS I
1.0 INTRODUCTION
8 This Manual describes acceptable methods of calculating radioactivity
- concentrations in the environment and the potentially resultant personal J doses
- offsite** that are associated with LWR liquid and gaseous effluents. The radioactivity concentrations and dose estimates are used j to demonstrate compliance with Environmental Technical Specifications !
required by 10 CFR 50.36. The methodology stated in this Manual is acceptable for use in demonstrating operational compliance with 10 CFR 20.106,10 CFR 50 Appendix I, and 40 CFR 190. Only the dose attributable to the Duane Arnold Energy Center is considered in demonstrating compliance with 40 CFR 190 since no other nuclear facility exists within 50 miles of the Center. 1 Calculations are made monthly to assess the potential air doses offsite and to a nearby resident in order to guide the management of station effluents. The receptor is described such that the dose to any resident near the Station is unlikely-to be underestimated. Calculations made to assess the radioactive noble gas dose to air are based on the
- location offsite that could be occupied by a person where the maxima air dose is expected. For these monthly accumulated dose calculations, j atmospheric dispersion and deposition of gaseous effluents is based on reference meteorological conditions.*** More conservative conditions (i.e., location and/or exposure pathways expected to yield higher computed doses) than appropriate for the maximally exposed person may be assmed in the dose estimated.
- Dose is consonly used to mean personal dose equivalent commitment. ,
** Offsite means outside of the boundary of property owned, leased, or controlled by IELP on which CAEC is sited, i.e., outside the exclusion-area. The DAEC site boundary is identified in UFSAR Figure 1.2-1.
*** Reference meteorological conditions re based on previous calendar years data.
Rev. 3 6/87
Calculations of dose.consitted from radioactive releases over extended time (3'and 12 months);are also made for the purpose of verifying compliance with regulatory limits on offsite dose. For these ' calculations the' receptor is selected on the basis of the combination of applicable exposure pathways identified in'the land use census and the maximian ground level X/Q at a residence, or on the basis of more j conservative conditions such that the dose to any resident near the { Station is unlikely to be underestimated. i l l 2.0 LIQUID EFFLUENT 2.1 Radioactivity In Liquid Waste The concentration of radionuclides in liquid waste is determined by sampling and analysis in accord with surveillance requirement i 4.14.2, Table 4.14-2 of the Technical Specifications. When a radionuclides concentration is below the LLD for the analysis, it is not reported as being present in At sample. l 2.2 Aqueous Concentration Radioactive material in liquid' effluent is diluted successively by water flowing in the discharge canal and in the River. The diluted concentration of radionuclides i in a receiving stream is estimated
~
with the equation Cg j = Cj F 1 F2 where Cj = concentration of radionuclides i in liquid radwaste released (uci/ml) Cg j = concentration of radionuclides i in the receiving ' stream (uci/ml) F, = release rate of liquid radwaste (al/sec)* F2 = dilution flow of receiving stream of water (ml/sec)*
. *F,, F2 and Fe may have any convenient units of flow (i.e., volume / time) provided the units of all are identical.
I Rev. 3 6/87
For the purpose of calculating the radioactivity concentration in water at the restricted area boundary (section 2.4), the fion in the discharge canal, eF , is assigned to F2 , The water flow in the discharge canal may include the liquid waste effluent flow, the liquid radwaste dilution water flow, the cooling tower blandown flow and other streams such as RHR and emergency service water discharged via the dilution structure and discharge canal. In the River immediately beyond the discharge canal and the restricted area boundary, the effective dilution is F2=Fc*M where Fc = discharge canal flow , M = factor of additional mixing in the River A near field mixing ratio from the canal into the near field of the River, M = 5, is assigned when estimating maxima potential , individual doses involving exposure by eating fish or from consming irrigated foods. In the event water is drawn from the River
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downstream of the Station for drinking water or another esposure
~
pathway, F2 represents the portion of the River flow into which the liquid effluent from the. Station is effectively mixed. 2.3 Method of Establishing Alare Setpoints
~
Liquid waste effluent monitors are connected to alarms which provide automatic indication when 10 CFR Part 20 Appendix E, Table 2, Column 2 concentrations are being exceeded offsite. With prompt action to reduce radioactive releases following an alars, the liquid release limit of 10 CFR Part 20.106 and the limits provided by 10 CFR Part 50 Appendix I, Section IV should not be exceeded after the alars. The alarm setpoint for the liquid effluent radiation monitor is derived from the concentration limit provided in 10 CFR Part 20 Appendix B Table 2 Colum 2 applied at the restricted area boundary - Rev. 3
-3 6/87
where the discharge-canal flows into the river. The alam setpoint does not consider dilution, dispersion, or dec,ay of radioactive material beyond the site boundary. That is, the alarm setpoint is 1 based on a concentration limit at the end of the discharge canal. ; The radiation monitoring and isolation points are located in each 4 line. through w:tich radioactive waste effluent is eventually l discharged into the discharge canal. ; i The alam setpoint for* effluent monitors on batch releases is based l on maiwoments, according to Table 4.14-2 of the Technical Specifi-cations. . For liquids released in continuous aqueous discharge which are normally radioactively clean, the setpoint is based on the
' effective MPC for the most likely contaminating source, i.e., the primary coolant water. A measured spectrum from the primary coolant water is used to detemine the efft.ctive MPC based on MPC fractions !
according to 10 CFR 20 Appendix B. Alternately, the afarm setpoint may be based upon gross 8-y activity analysis of the liquid waste
. provided the unrestricted area MPC for unidentified emitters, j 1 x 100 pCi/m1, is observed in acceed with Specification 4.14.2.
2.3.1 Setpa[rit for a Datch Release ( A sample of each batch of liquid radwaste is analyzed for 1-131 and oths principal gamst snitters, or for total activity concentration prior to release. The ratio, FMPCb ' of the activity concentratica in the tank to the unrestricted area PFC (10 CFR Part 20, Appendix 8. Table 2 Coltann 2) 1's calculated with the equation - FMPCb "(E ) ! 1 i s where FMPC3 = fraction of unrestricted area MPC in hatch derived from activity measured prior to release. < C bi = concentration of radionuclides 1 (including I-131 and principal gamma emitters) in batch sa:nple taken prior to release (vC1/ml) L i 1. i 4 Rev. 3 ! 6/87 l -
In the. event total or gross 6-y analysis alone is used to determine the radioactivity in a batch prior to release, the fraction of the unrestricted area MPC in the batch is just i
. Cy l
FWCb" ' 1 x 10-7 where Cb = the total or gross 8-y activity measured in the batch senple (pC1/ml) 1x10-7 = the unrestricted area FC for unidentified radionuclides (vC1/ml) j Whether radioiodine and primary ganma emitters are identified prior to a batch release or not, the liquid radwaste effluent line radiation monitor alarm setpoint is determined with the I equation F A S2 S= ( - x g + 8kg ) FMPC b F)3 where S
= radiation monitor alarm setpoint (cpm)
A
= counting rate (cpm /ml) or activity concentration (uci/ml) of saple in ,
laboratory analysis. A equals { Cbi If ""
' isotopic analysis was performed or C if a b l gross activity analysis was performed.
g
= ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration is a given batch of liquid (cpm per cpm /ml or epm per pCi/ml)
Bkg = monitoring instrunent background. (cpm) Rev. 3 6/87 1 .
F
$t a flow in the batch release line (gal /ain).o. Value not greater than the discharge line flow alarm maxima setpoint.
FS2 = minimus flow in the discharge canal
'(gal / min).* Value not less than the discharge canal flow alarm minimum setpoint.
Note that A/FMPCb represents the counting rate of a
, solution having the same radionuclides distribution as the sample and having the maximum permissible concentration of . that mixture.
l 2.3.2 Setpoint for a Continuous Release. Continuous aqueous discharges are sampled and analyzed according to the schedule in Table 4.14-2. The ratio, FWC g , of the activity concentration in each of the continuous release streams to' the unrestricted area WC is calculated with the equations l Ci FMPCc"U1 WC ) j where FMPC c = fraction of unrestricted area WC in I continuous release based upon activity measured in primary coolant sample (s) ; Cj e = concentration of radionuclides i in i sample (s) (vCi/ml) ' In the event the total or gross 6-7 analysis alone is used to determine the radioactivity, the fraction of the unrestricted area MPC in the continuous release is FMPC = C c c 1 x 10-/
*Any suitable but identical units of flow (volume / time)
Rev. 3 6/87
where Cg a the total or gross s-y activity measured .{ in the continuous release sample (uCi/ml) The alarm setpoint. of the radiation monitor on a continuous radioactive discharge line is determined with the equation A s2 S= x x g + Skg_ FMPC g F,g where A = activity concentration (uCi/ml) or counting rate (cpm /ml) in laboratory of monthly reactor primary coolant sample. F sA
= Flow in the liquid discharge line (ml/sec).* Value not greater than discharge line flow alars maximum setpoint.
Fs2 = flow in the discharge canal (al/sec).* Value not less than discharge canal flow alarm ministan setpoint. g = ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch of liqu'id (cpm per cpm /mi or cpm per uCi/ml) The radioactivity concentration in continuous aqueous effluent is usually so low that measurement of a representative radionuclides in a sample of the water is uncertain. Thus, the
~
ratio A/FWC c, which represents the WC of a given spectrum of radionuclides, is usually derived from reactor primary , coolant analysis (es). Alternatively, it may be determined j from analyses of the continuous effluent itself. . l l In the event the concentration of radioactive material in the sample from the continuous release is below seasurable levels (i.e., less than the lower limit of detection), the value of 1
*Any suitable but identical units of flow (voltane/ time). ]
-7 Rev. 3 !
6/87 .
. . 1 where FFC o fraction of the unrestricted area caxi;um pemissible l concentration of a mixture of r. radionuclides in water ;
(unitiess) 1 TE-TB = increment of time between beginning and ending period of interest during which the concentration is averaged (min) C = concentration of radionuclides i in sample k ik representing a radioactive liquid effluent ' release into an unrestricted area (uti/ml) i Fi k = release rate of radwaste liquid represented by sample k and in which Cik w.s measured (gal / min)* I F2k = flow into unrestricted area of aqueous stream into which radioactive release represented by sample k is diluted, i.e., the discharge canal flow during the rel' ease represented by sample k (gal / min)* Atk = duration of radioactive release represented by sample k which occurs within time boundaries TB and l TE (min). MPCi = unrestricted area maximum permissible concentration of radionuclides i per 10 CFR Pa'rt 20 Appendix B, . Table 2, column 2 (uC1/ml) . MPCj = 2 x 10-" uCi/m1 'for radioactive noble gases in water. Reference NUREG-0133. 2.5 Accumulated Personal Maximum Dose Technical Specification 4.14.3 requires an essessment to be perfomed at least once every 31 days in any quarter in which radioactive effluent is discharged which determines whether the dose or dose commitment to a person offsite due to radioactive material released in liquid effluent calculated on a cumulative basis exceeds Specification 3.14.3. The requirement is s,atisfied by computing the
*Any suitable but identical units of flow (volume / time).
Rev. 3 6/87
accumulated dose commitment to the most exposed organ and to the totall body of a hypothetical person exposed by eating fish or consming irrigated st.*aderries and drinking water taken from the l river offsite downstream of the discharge canal. The accmulated dose connitment is computed at least once every 31 days but may be computed as analyses become availabie. The computation is made in the following way. l AD ank
=3.785x10-syA sanic ik Atk Fik 5 )
. D an =[AD ank k
1 where AD = the dose commitment (mram) to organ n of ank age group a due to the isotopes identified in analysis k, where the analyses are thDse required by Table 4.14-2 of the Technical Specifications. Thus the contribution to the dose from gamma emitters become available on a batch basis for batch releases and on a weekly basis for continuous releases. Similarly the contributions from H-3 is available on a monthly basis and the contributions from Fe-55, Sr-89, and Sr-90 become available on a. quarterly basis. D = the dose commitment during the quarter-to-date to an organ n, including total body, of the maximally exposed person in age group a (erem). A = transfer factor relating a unit release of eani radionuclides 1 (C1) in a unit stream flow (gal / min) to dose commitment to organ n, or total bodg of .ag)viaexposed person environmental in age pathway e. grow . a(C n j C = the concentration of radionuclides i in the ik undiluted liquid waste represented by sample k to be discharged (uCi/ml) i i l Rev. 3 6/87
~
1
Atk a duration of radioactive release represented by sample k which occurs within time boundaries TB and TE and during which concentration Cik and flows Fik and F2g exist. (min.) 3.785 x 10-3 = conversion constant (3785 ml/ gal x 10-8 C1/uC1) Pathway-to-dose transfer factors, Aeani, for use in calculating the dose commitment arising from radioactive material released in aqueous effluents are tabulated in Appendix C. Appropriate tables representing applicable environmental pathways of exposure and most exposed age group (s) are selected and used in calculating the dose comhiitment. .The pathway (s) and/or ege group (s) ' selected may vary by i season. For instance, fishing near the DAEC _is non-existent during-the winter; thus, a dose evaluation of the fish pathway is not required for aqueous effluent discharged during the winter months of January, February, or March. .
, For the purpose of calculating the dose to a Monber of the Public who is potentially exposed by eating fish taken from the river offsite near the discharge canal, F2 = SFe. The age group ;
potentially the most exposed via eating fish is expected to be the adult. F2 = 5Fe is also used for the irrigated food pathway when appropriate. The age group potentially the most exposed via drinking water taken from the Cedar River is expected to be the infant. As long as water
' is known not to be taken from the Cedar River within 3 miles downstream of the DAEC, for drinking water, as verified by the annual land use survey, the potential dose to a Member of the Public via drinking water will be assessed on the basis of water assuned to be taken from the river three miles downstream. At that location, F2 is conservatively assumed to be F2 = 10Fe. Variables F1 , F2 .
and Fe are defined in section 2.2. > l l Rev. 3 6/87
\
2.6 Projected Maximum Dese to a Person Offsite The dose comitment to a person offsite due to radion::ive material i released in liquid effluent may be projected by calculating the extrapolated total body and most exposed organ dose essaitments to a [ hypothetical person exposed via the same pathways evaluated in' section 2.5. The potential dose commitments to organs and to the I
'totEl body are computed separately. * : .'
The dose commitment to a maximally exposed hypothetical person will be projected by calculating the doses acctssulated during the most j recent three months (according to the method described in - ) I section 2.5) and by assaing the result represents the projected { doses during the current quarter. - j
. :. e -
)
. l l Alternatively, th,e quarterly dose comitment may be projected by j using the equation: -
. :.s P an
= 92 D an ~
X - where P an a projected dose commitment (aram) to organ s Cl) (including total body) of' age group a for the curr<ent j quarter ! l l 92 = nisnber of dafs in a quarter l . , X = number of days to date in current quarter D an = dose commitment to organ n, including total body, of l the maximally exposed person in age group a based on available aqueous effluent measurements dring the
' quarter to date (mrm). ,
9
,1 ! -
o b3
. 6/B7-
l
)
3.0 GASEOUS EFFLUENT l l 3.1 Introduction The Station discharges gaseous effluent through a stack and discharges ventilation air from the reactor and radwaste building through the reactor building vents. Ventilation air from the Turbine Building is discharged through the Turbine Building vent and through the Reactor Building vent. These gaseous effluent streams, l radioactivity monitoring points, and effluent discharge points are shown schematically in Figure 3-1. Gaseous release point locations { and elevations at the Station are described in Table 3-1. Baseous discharges from the stack are treated as an elevated release while
, j discharges via the building vents are assurned to be ground-level,
)
bui1 ding wake, or split wake releases. 3.2 Radioactivity in Gaseous Effluent 1 For the purpose of estimating offsite radionuclides concentrations i and radiation doses, measured radionuclides concentrations in gaseous 1 effluent and in ventilation air exhausted from the Station are I relied upon. 1 The gross radioactivity of noble gases discharged is measured by the radioactive noble gas effluent monitors according to Technical Specification Tables 3.15-1 and 4-15-2. Radionuclides other than noble gases 'in gaseous effluents are measured by sampling and analyses in accordance with Table 4.15-2. Each radionuclides
, measured in an effluent may be assumed to be discharged uniformly during the sampling period. When a radioactivity concentration is below the LLD for the analysis, it is not reported as being present in the sample.
The quantity of radioactive noble gas discharged via the offgas stack or a vent during an interval of time is determined by integrating the release rate measurement of each effluent' noble gas
' 13-
- Rev. 3 6/87
monittr. An hourly. intceval_ is normally used fer dose rate-assessments and a daily or longer interval is used for dose assessments. .If AQj represents the gross activity of noble gas discharged via the offgas stack or L vent and gi represents the ' fraction of radionuclides i in the distribution of radioactive gases in that effluent stream, then the quantity of radionuclides 1 released in the gaseous effluent stream during counting interval j is estimated by the relation: AQgg*AQ3*gg The distribution of radioactive noble gases in gaseous effluent ~ streams is determined by gama spectrum analysis of gaseous effluent samples in accordance with Technical Specification Table 4.15-2. Results of one or more previous analyses may be averaged to obtain a representative spectrum. In the event a representative distribution is not available or is unobtainable from sanple(s) of an effluent
, stream taken during the current quarter, it will be derived from past measurements, e.g., earlier sample results or sami-annual radioactive . material release reports. Alternatively, a noble gas spectrisn for a given effluent stream in Table 3-2 herein, may be ,
assisted. . An airborne discharge of radionuclides other than noble gases may be represented by multiple samples with each sample providing a measure ! of the concentration of specific radionuclides, Cg, in gaseous l effluent discharged at flow, Fa, during a time increment At. Thus, each release is quaatified according to the relation: , N ik F g Atj ik = f C ] where Q ik = the quantity of radionuclides i released in.a given effluent stream based on analysis k (C1) Rev. 3 >
~14'
. 6/87 l r
1 l Cik a c!ncentration of radionuclides i in gaseous effluent
)
identified by analysis k (pC1/ml or Ci/m3 ) Faj = effluent stream discharge rate during the increment Atj (m 3/sec)
. 1 atj = time increment during which radionuclides i at concentration Cik is being discharged (sec) i The analysis index k may_ represent either a grab sample, integrated sample, or a composite sample required by the effluent sampling and )
analysis progran specified in Technical Specification Table 4.15-2. ) l 3.3 Main Condenser Offgas Retreatment Monitor Alann Setpoint ! A noble gas activity monitor is provided to measure gross gama activity in gases from the main condenser air ejector. The retreatment monitor includes an alarm that is set to report when j the gama radiation level in gas discharged by the main condenser air ejector indicates the gross radioactivity discharge rate, after
~
30 minutes delay and decay, exceeds 1 C1/sec. The alann setpoint is detemined with the relation 2120 g S= + Bkg F { f je 'Ai t where S = inain condenser air ejector noble gas monitor alarm , setpoint (cpm) or (mR/hr) 2120 = [1.0 E6 vCi/sec / (1 ft 3 / 28317 cm3 )] x 60 sec/ min F = air ejector discharge rate (ft /3 min) i
)
1 Rev. 3 6/87 u_____________ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
g a noble gas monitor calibration or counting rate- l response for gunma rediation ,, ! cpm mR/hr ! uCi/m3 uCi/cm8 - 8 fj = fraction of noble gas gross activity due to noble gas radionuclides 1 in a representative spectra of noble gases at the main condenser i offgas detector l Ag = radioactive decay constant of noble gas nuclide , 1 (min-1) l t = 30 min; decay time in delay line 3.4 Effluent Noble Gas Monitor Alam Setpoint Specification 3.15.2 provides limits on dose. equivalent rates ^ l associated with airborne radioactive materials concentrations in the unrestricted area due to airborne effluents from the Station. Instroentation is provided to monitor gamma radiation in the airborne effluents according to Technical Specification Table.- 3.15-1. Each effluent noble gas monitor includes an alarm that can be set to activate when the dose rate offsite or the noble gas concentration at ground level of.fsite is. expected (calculated) to l exceed a specified level. Compliance with the limits on dose rate from noble gases is demonstrated by setting each gaseous effluent t monitor alarm setpoint so that an alarm will occur at or before either dose rate limit or the MPC* for noble gases is reached. If an alars occurs with the setpoint at the limit, compliance with Specification 3.15.2.1 is assessed as described in section 3.5. ' On the basis of effluent noble gases from the DAEC during recent years, the ganma dose rate to a person's body is expected to be a I
*MPC means the 10 CFR Part 20, Appendix B, Table 2, colon 1 limit for radioactive noble gases.
Rev. 3 6/87 l
larger fraction of the liait, 500 crem/yr, than is the beta plus gamma dose rate to skin is to its limit, 3000 mrem /yr. In which case, a gaseous effluent monitor setpoint may be derived on the basis of the gamma dose rate to 'a person's body alone such.that an , alam is set to occur at or before the total body dose rate offsite exceeds 500 mren/yr. 1 I A noble gas monitor may be set to activate an alarm at a lower setting than the derived setpoint corresponding to the dose rate j limit (or correspond 1 rag concentration limit). In the event an alam
, occurs at the lower setting, the monitor record is compared with the derived setpoint. If the derived setpoint is exceeded, compliance .
with Specification 3.15.2.1 is assessed as described in section 3.5. Each radioactive noble gas effluent monitor setpoint is derived l either on the basis of total body dose equivalent rate in the ! unrestricted area offsite or on the basis of the 10 CFR Part 20., l Appendix B, Table 2, column 1 limit for radioactive noble gases. ' l l For the purpose of deriving a setpoint, the distribution of
~
radioactive noble gases in an effAuent stream is determined as described in section 3.2. -
- l Setroint Based on Dose Rate !
The alarm setpoint of a radioactive noble gas effluent monitor may be calculated on the basis of whole body dose equivalent rate offsite, 500 mrem /yr. A setpoint of a monitor of an elevated release, e.g., from the stack, may be calculated with the equation: {C g
+ Bkg S='1.06f[I i C$ x DFs 8
-17 Rev. 3 6/87 '
9
The setpoint of a monitor of a ground-level or building release, e.g., from the turbine building vent or 3 reactor building vents may be calculvel with the equation {C g h i S = 1.06 + Bkg fX,1C$ x DF Q where S = the alann setpoint (cpe) or (mR/hr) h = monitor response to activity concentration of effluent being monitored, com _ or mR/hr ("uC1/cm* } (pC1/cm) a C4 = relative concentration of noble gas radionuclides i in 4 effluent at the point of monitoring (pCi/cm3) X/Q = atmospheric dispersion from point of ground-level or building wake release to the location of potential . exposure (sec/m3) i DFs = factor converting elevated release rate of i radionuclides i to total body dose equivalent rate mr at the location of potential exposure [yr =amuC1) sec DFV = factor converting ground-level of split-wake release i of radionuclides i to the total body dose equivalent rate at the location of potential exposure mr j [yr amuCi) m3 f = flow of gaseous effluent stream, i.e., flow past the monitor (ft /3 min) ! i Bkg = monitoring instrument background (cpm) or (nR/hr) Rev. 3 6/87 i
1.06 = 500 " *" x 60 sec , 35.3 fts x 1S yr min' m3 108 cm 3 Each monitoring channel has a unique response,.h, which is determined by the instraent calibration. The concentration of each noble gas radionuclides, Cg, in a gaseous effluent is determined as discussed earlier in this section. Since the dose rate limits for airborne effluents apply everywhere offsite, alam setpoints are determined and compliance is assessed at the site boundary where the minime atmospheric dispersion (maxim m x/Q) occurs. The - atmospheric dispersion factor and the dose conversion factor DF{ depend on local. conditions. The value of x/Q adopted in a setpoint calculation will be based either on prevailing' meteorological conditions or on reference meteorological conditions at the DAEC. The minime atmospheric dispersion offsite from a ground-level or building wake release derived from reference meteorological conditions is at the site boundary 1260 meters NNW of the Station where: j X
= 4.3 x 10-6,sec/m3 (0) vent The dose conversion factors, DF{, used in setpoint calculations ,
for gaseous effluent monitors are in Table 3-4. In the event DFf is derived on the basis of prevailing meteorology, it will be calculated in accordance with Regulatory Guide 1.109, Appendix B. i Setpoint Based on Concentration The alarm setpoint of an effluent noble gas monitor may be calculated r7 the basis of the 10 CFR Part 20, Appendix B, Table II, Column 1 concentration limit for radioactive noble gases, corresponding to the expectation of the concentration reaching the limit at ground level offsite.
)
Rev. 3 6/87 j
The gross activity concentration of noble gas corresponding to the 10 CFR Part 20 Appendix B Table 2 Colunn 1 li31t is calculated frra - the distribution with the equation , C
.j l MPC =1 { Cg + {i WC 4
where MPC = gross activity concentration of noble gas mixture corresponding to 10 CFR 20 Appendix B Table 2 Column 1 limit (uC1/cm3 ). ) I Cg a relative concentration of noble gas radionuclides i in
~
gaseous release (pC1/cm3 ). MPCg = 10 CFR Part 20 Appendix 8 Table 2 Colunn 1 value. l
)
Note that this is simply the aggregate of the concentrations of radionuclides i in a sample divided by the fraction of WC l constituted by radionuclides i in the same sample. For the purpose of deriving an effluent monitor setpoint, the relative concentration, i.e., the distribution or. spectrum, of radioactive noble gases in an effluent is determined as described ir. l section 3.2. l Alternatively, the total activity concentration of the noble gases may be used with the MPC value of Kr-88 (2 x 10-s pCi/cm3) for the purpose of conservatively determining an activity. concentration of l noble gases that will be less than the 10 C'FR 20 Appendix 8 Table 2. Colunn 1 limit. If this approach is used, the value of MPC is simply 2 x 10-8 uCi/cm3 . l l i Rev. 3 6/87 O
The alars setpoint fcr the effluent noble gas monitor is then calculated with the equation . 3, MPC x h
, gg 4.7 x 10-" x F x X Q
where 5 = alam counting rate setpoint (cpe) or (mR/hr) h = effluent noble gas monitor counting rate response or calibration mR/hr for noble gas cpm (pC1/an)8 (uC1/cm) 3
, gauna radiation ,
F = discharge rate of gaseous effluent (ft /3 min) X/Q = minimun atmospheric dispersion from release point to unrestricted area (uci/m3 per uCi/sec) 4.7 x 10-4 = conversion constant 1m3 1 min ( x ) 35.31 ft3 60 sec MPC = maximum permissible concentration for the j effluent nob 1'e gas mixture as detemined above i 1 Bkg = monitoring instrument background (cpm) or (mR/hr) The value of X/Q adopted in a setpoint calculation wi11 be bcsed either on prevailing meteorological conditions or on reference ~ meteorological conditions. Minimum atmospheric dispersion offsite derived from reference meteorological conditions at the site boundary 1260 meters NNW of the Station are: l X X > (-) = 2.8 x 10- / sec/m3 (-) = 4.3 x 10- 6 sec/m3 Q stack Q vent-
' ' ' ~
Rev. 3
, 6/87
. . j 3.5 Dose Equivalent Rate Offsite Spe.ification 3.15.2 provides limits on dose equivalent rates I associated with airborne radioactive materials concentrations in the i unrestricted area due to airborne affluents from the Station.
Compliance is assessed on the basis of measurements specified in Table 4.15-2. 3.5.1 Noble Gas l Limits on radioactive noble gas in the unrestricted area are provided in Specification 3.15.2.1. Each radioactive noble gas effluent monitor is set to alars when, or below when, the noble gas in airborne effluent from a monitored stack or vent is expected to cause either' dose rate limit in Specification 3.15.2.1 to be exceeded. In the event an airbonne effluent release from the Station exceeds the derived setpoint (limit) for an effluent noble gas monitor (except when caused by the performance of a Surveillance Test Procedure), an assessment l of compliance is performed as described herein. , 1 i The quantity of radioactive noble gas released in an' I increment of . time is measured by the radioactive noble. gas effluent monitors and the distribution of radioactive noble gases in a gaseous effluent strean is determined as described in section 3.2 herein. Compliance with Specification 3.15.2.1 may be assessed by calculating the dose equivalent rate as described hereafter I and by comparing it with the limiting dose rate in. the Specification. 1 l l
^
Rev. 3 6/87 i
~
3.5.1.1 Total Body Dose Rate The total body dose equivalent rate due to noble gas ! gama radiation is calculated with the equation:
'i by = 3.156 x 10/ [ ( t xPy{}s+y((j(ti x x PYT)v l 4 Q where Dy = noble gar gauna dose rate to total body l (mram/hr) i Q gj/t = quantity of noble gas radionuclides i
{ discharged (uC1) during time increment t i (hr) PTS = factor converting unit noble gas nuclide I 1 stack release to total body dose at ground level received from the overhead mran plune ((uC1 yr)/sec) . l
. 1 Py} = factor converting time integrated, ground level concentration of noble gas , :
nuclide i to total body dose from gamma mram-radia. tion ((uCi yr)/m 8 ) ' 3.156 x 10/ j l Specification 3.15.2.1 total body dose rate is evaluated by calculating the noble gas gesna dose equivalent rate offsite at 1260 meters NNW of the . Station, which location is identified in Figure 3-2. At that location the referenced atmospheric dispersion factor to be used in the calculation is ( )y = '4.3 x 10-6 5,cf,3 I Rev. 3 6/87,
Alternatively, averaged met orological dispersion data coincident with the period of release may be used to evaluate the dose rate. The noble gas plane l gamma-to-total body dose f actor, Py{, is calculated from plume data. The noble gas semi-infinite cloud gamma-to-total body dose factor, Py{, is derived from Regulatory Guide 1.109. Table B-1. Values of Py{ and Py} applicable at 1260 meters NW of the Station are in Table 3-4 j 3.5.1 2 Skin Dose Rate The skin dose equivalent rate due to radioactive noble gas is calculated with the equation
=
\
l fg . I 3.156 x 10 / 11 SSi(E t ix1)s+y((j Q SS(E it ix1)v Q I where Dg = noble gas beta dose rate to skin (mrem /hr) a-Qg/t = quahtity of noble gas radionuclides 1 (uC1) dischargad during time increment t(hr) l 58g = factor converting time integrated j ground level concentration of noble gas to skin dose from beta radiation aren m' l 9C1 yr 1 3.156 x 10 / = conversion (yr/sec) Compliance with Specification 3.15.2.1 dose rate to skin is evaluated by calculating the noble gas beta l - dose equivalent rate offsite at a location 1260 i Rev. 3 6/87
meters NNW of the Station, which is also identified in Figure 3-2. At that location, the reference atmospheric dispersion factors to be u' sed in the calculations are: (f) = 4.3 x 10-6sec/m3 and(f)=2.8x10-7 sec/m3 Alternatively, averaged meteorological dispersion data coincident with the period of release may be - used to evaluate the dose rate. The semi-infinite noble gas cloud-to-skin dose equivalent factors are in Table 3-4. They are also derived from Regulatory Guide 1.109. Table B-1. 3.5.2 Iodine, Tritium, and Particulate Specification 3.15.2.2 provides a limit on iodine-131, iodine-133. H-3, and on radioactive particulate having 8 day or longer half-lives in air in the unrestricted area around the Station. In the event airbcrne effluent from the Station causes a radioactive noble gas effluent monitor to alars (except when alarm is due' to the performance of a Surveil-lance Test Procedure) or if the, assessment required by l Specification 4.15.4.2 shows Specification 3.15.4 to have been exceeded, an assessment of compliance with Specification 3.15.2.2 will be performed using a method described in this section. 3.5.2.1 Organ Dose Ratel Compliance with Specification 3.15.2.2 is assessed by calculating the dose rate 1 to the most exposed
'For inhaled or ingested radioactive material, the consequent " dose" means the committed dose equivalent. The " dose rate" is the connitted dose' equivalent per unit of time of exposure to the radioactive material in the environment.
( - p
-gq=j -ep '~h My[- m i s.* I Rev. 3 6/87 I h b,k ! y -
organ of an assumed adult cember of the public inhaling airborne I-131, I-133, H-3, and inhaling radioactive partict.lates having half-lives of 8 days or longer at the location in the unrestricted area having the maximum potential concentration of the effluents (i.e...the location at which reference meteorological data indicates minimtsa atmospheric dispersion from the Station (max X/Q). The organ dose rate is calculated with the following equatio,ns: i For an offgas stack discharge: 5 ans
= 6 IIQ iks i k TA (4) ani Q s For a vent discharge:
b any = h [lQ $k ikv TA ani (fi) y Combining separate release points gives D =D +[D any - an ans y Rev. 3
. 6/87
there D = the dcse equivalent rate. to organ n
"" of a person in age group a due to
. radionuclides discharged in airborne eff'uents during time interval T8 to TE (ares /hr)
= dose equivalent rate from a b
ans stack discharge (mram/hr) i b = dose equivalent rate from a-any vent discharge (mram/hr)
= quantity of radionuclides i released Qiks,Q ikv in a given effluent stream based on analysis k (uC1) during discharge time )
increment TB to TE (hr) of interest TA = factor converting airborne
""i concentration of radionuclides i to dose commitment to organ n of a person in age group a where exposure is directly to airborne material aram
((pCi sec)/m3 ) atmospheric dispersion from stack and (fi)s, (fi)v = vent, respectively, to ground level 3 location of . interest (sec/m3 ) Radionuclides other than noble gases in airborne effluent are measured and quantified as described in section 3.2. Nomally, radioactive material
, measured in effluent is assuned to be discharged ~
unifomly over the period represented by the sample. The averaging time of the measured releases used to , evaluate compliance will not exceed 92 days for Sr-89 and Sr-90 and will not exceed 31 days for the other radionuclides. Rev. 3
-27 6/87
The Caxirta offsite exposure potential is e'xpected
, to occur at 1260 meters NNW of the Station where the reference atmospheric dispersion, to be used in the calculation is (f) = 4.3 x 10-6sec/m3 and
= 2.8 x 10-7 sec/m3 (f)
Currently, compliance with Specification 3.15.2.2 is evaluated by calculating an adult inhalation dose rate at 1260 meters NNW of the Station. The dose - transfer factors, TAani, used in the computa-tion are tabulated in Appendix A.
~
3.6 Noble Gas Ganna Radiation Dose Accumulated in Air Technical Specification 3.15.3 requires that the offsite air dose during any calendar quarter not exceed 5'arad and the annual air dose not exceed 10 mrad from noble gas genma radiation. Specification 4.15.3.1 requires a monthly calculational assessment to verify that the cumulative air dose due to gauna radiation from radioactive noble gas released in gaseous effluents during the _ quarter and year do not exceed Specification 3.15.3.
,The distribution of radioactive noble gases in gaseous releases and the quantity of. radioactive noble gas discharged during an interval of time are detemined as described in section 3.2 herein.
The gama radiation dose to air offsite as a consequence of noble gas discharge from DAEC is calculated with the ! i S x AY ) + 1 Ay
- f f (Mj
- 9 Oy 1 (@)x.g4 x f) l where D y = noble gas gamma dose to air due to effluent from stack l and vent (mrad) i Rev. 3 l 6/87 !
J
AQj o total Eeasured radioactivity release-via stack or vent measured by noble gas efflu;nt monitor during counting interval j (uC1) , gg = the fraction of radioactive gas in a given effluent stream attributable to noble gas radionuclides 1.
'AYs = factor converting unit release of noble gas radionuclides
. i from the stack to air dose at ground-level received from gamma radiation from the overhead plume (mrad /uCi)
AY{ = factor converting time integrated, ground-level concentration of noble gas to air dose from gamma mrad . radiation .[(uCi sec)/m ) 3 (X/Q)y = atmospheric dispersion factor for a vent (ground-level
, or building wake) discharge (sec/m3 )
l Specification 4.15.3.1 is satisfied by calculating the noble gas gamma radiation dose to air at the offsite location identified in Figure 3-2. At that location,1260 meters NNW of the Station, the reference
- atmospheric dispersion factor to be used is 1
(1) =.4.3 x 10-6 secfas . .., Qv S Values of AY and AY{ appropriate for use at that location, assining reference meteorological conditions,. are listed in Table 3-3.
- Reference atmospheric conditions are stamarized and discussed in "Duane Arnold Energy Center, Evaluation of Liquid and Gaseous Effluent Releases in Accordance with 10 CFR.50 Appendix I," submitted to NRC June 3,1976, i Reference atmospheric dispersion factors tabulated therein, also appear in Appendix B herein.
' i Rev. 3 6/87 J
..__m___m._.________
3.6.1 Alternate Method of Evaluating Compliance with Gama Air Dose
. Limits Alternatively,'the gamma radiation dose to air offsite may bc calculated with the equation U
*h f(Nj
- ATseff)s*hff(Nj*f*ATveff)v where Ay 5 'II = an effective dose conversion factor based on the typical radionuclides distribution in stack releases converting unit release of radioactive noble gases from the stack to air dose at ground level at a specific location (mrad /uti).
Ay = an effective dose conversion factor based on
If the typical radioactive ' distribution in a vent releases converting a time integrated, i ground level concentration of noble gases to l mrad .
air dose from gamma radiation (_(uCisec/m)j 3 l O.8 = a f actor of conservatism which compensates for variability in radionuclides distribution q The derivation and basis of the effective gauna air dose conversion factor are provided in Appendix B. Values of the
. effective factors- are tabulated in Table 3-3. By inserting j the appropriate values for Dy (5 mrad / quarter y-air dose) i and for Ayseff(1.6 x 10-12 mrad /uti) or AYveff (6.4 x 10-5 mrad /(uCi sec/m8 )) into the equation above and solving for either ( 43 )s 0" INj)v, respectively, release quantities of noble gases from either the stack or vent corresponding to the technical specification limit of 5 i mrad / quarter (total for all release points) may be j determined. At the location,1260 meters NNW of the station, Rev. 3 l 6/87
F j 1 (which is the controlling location based on reference _ meteorology) the release limits are individually i Release Quarterly Limit Annual Limit l Point (C1) (C1) ! Stack 2.5 x 105 5.0 x 105 Vent 1.25 x 104 2.5 x 10 i The following equations may be used to assess both the stack' i and vent discharges for compliance with the quarterly release limits on noble gas gesna dose to air.. , p7 l 1(Mj)g 17. (Mj)y . j +v; <1 u 250,000 12,500 ' or, on a monthly rate basis (although not a requirement) n
, o 1 (Mj)s +vj11 (M j)y I' 3 11 250,000 12,500 3 f
The equations which may be used to as'sess both the stack and 1
,, vent discharges for compliance with the e.fmual air dose limits from noble gas are: '
^
j1(M j)s +vjE 1 INj )v < 1 , 500,000 25,000 or, on a monthly rate basis (although not a requirement) 1 (4 3)g 1 [ (M j)y j +vj dl 500,000 25,000 12 l FOR IN:CRVA"QN Rev. ~ 3 f'\,j [ } [
~ ~ ,e 6/87
As long as these relations are satisfied fCr both stack and vent releases of noble gases, no' additional calculations are needed to verify compliance with the genma-air,tiose limits of Technical Specification 315.3. Calculs; ions of beta air doses per Section 3.6 may be cuitted as discussed in Appendix B. '
;f 3.7 Noble Gas Beta Radiation Dose Accumulated in Air -
Technical Specification 3.15.3 requires that the offsite air dose during any calendar quarter not exceed 10 mrad from noble gas beta radiation and not exceed 20 mrad during any calendar year. Specification 4.15.3.1 requires a monthly assessment to vqrify that i the etnulative air dose due to beta radiation from radioactive noble l gas released gaseous effluents not exceed, either limit of Specification 3.15.3. s z. I The radioactive noble gas distribution and activity tischarged are detemined as described in { 3.6 herein. The beta radiation dose to air offsite as a consequence of noble gas released from the Station is calculated with the eqcMion: g A i jIi ,
- f f A81 (N9 j 1 )v dere 'D6 = noble gas beta dose to air due to stack and psnt ,
releases (mrad) ABj = f actor converting time-integrated, ground-level concentration of noble gas radionuclides i to air do!& ' from beta radiation [ pCi-sec mrad-m3) ,
? .
Rev. 3 6/87 ,
w C L -
' (X/Q),
' o atmosphe lh dispersion factor for. a discharge via the stack (scic/m3 ) , ,
(X/Q)y _= atmospheric dispersion lf actor for a vent (ground level or building wake) discharge (sec/m3). Specification 4.15.3.1 is saticfied by calculating the noble gas l
~
beta radiation dose to air at i.f e location identified on Figure 3-2. At that location, 1260 meters NNW of the reactor, the reference atmospheric dispersion factors to be used are , i
~
(f)5 2.8 x 10-I ' s -
.(f) = 4 c3f x 10-5 3
Beta radiation-to-air' dose conversion factors, A89 , for noble gas radionuclides are-lideed in Table 3-3. i 3.8 Dose Due to Iodine and Particulate in Gaseous Effluents _* j Technf al Specificadon 3.15.4 requires that I 131,1-133, H-3, and ! radioactive material in particulate f6rs having half-lives greater thaE8) days in gaseous effluents releasert to the area offsite cause no more than 7.5 mram to any orgN ofa' member of'the public during
~
a calendar quarter and no more than 15 mrsa during any calendar year. Specification 4.15.4 requires an assessment at least once ! every month to verify that the etnulative dose conuitment does not- ; exceed either limit of Specification 3'.15.4. < x, Airborne releases are discharged either via the offgas stack as an i elevated release or via building vents and treated as a ground-n .
'4 1
*The dose to any organ of a, pers,on arising from rdfoactive iodine-131-iodine-133, tritium, and radioactive materir,1 in, particulate fore having -
half-lives greater than 8 days.- Noble gases n:t considered. j ; > t i e A I
. f' ,
b
~33 -
- Rev. 3 -
,L---_-__-_----_-2 6/87 .
1- J.
- l level, building take, cr split. wake release. Radionuclides sentioned above in airborne effluents that are measured by the ,
sampling and analysis schedule in Technical Specification Table 4.15-2 are included in the release ters used to caleclate doses. Section 3.2 describes the quantification of these radionuclides i other than noble gases.
~ A person may be exposed ddrectly to an airborne concentration of radioactive material discharged in effluent and indirectly via pathways involving deposition of radioactive material onto the ground. Dose estimates account for the separate exposure pathways.
The dose commitment to a person offsite associated with a gaseous release Qik, of radioactive material other than noble gas is calculated.with the appropriate one(s) of the following equations for a stack release: . anske iks i anie( )s+{TGanie( i
)s]
for a vent release: D =Q [lTAanie( )v+ 1 TGanie( )v3 anvke ivk $ $ q J where D = the dose connitment (aram) to organ n of a person in I
-. anske age group a via exposure pathway e due to radionuclides identified in analysis k of a stack release where the analysis is required by Technical Specification Table 4.15-2. ~
D = the dose connitment via pathway e from a vent release i anvke (,7,,) ! l i i l Rev. 3 6/87
TA = f actor converting airborne concentration of anie radionuclides i to dose commitment.to organ n of a person in any group a where exposure is directly to airborne material via exposure pathway e. mram ((Cisec)/m3) l TG = factor converting ground deposition of radionuclides i .
""I' to dose commitment to organ n of a person in age group ,a_ where exposure is directly or. indirectly to radioactive material that has been deposited on the ground via exposure pathway e.
(EER.) C1/m2 Q = quantity of radionuclides i released in a given ik effluent strean based on analysis k (C1)
,D ,D = relative deposition factor, i.e., factor converting Qs Ov airborne effluent discharge from stack or vent respectively, to a real- deposition on land (m I).
The analysis index k may represent either an analysis of a grab sample, a weekly composite analysis, a monthly composite analysis, j or a quarterly composite analysis. . Since tritium in water vapor is absorbed directly by vegetation, the tritiun concentration in growing, vegetation is proportional to the ' airborne concentration rather than to relative deposition as in the case of particulate. Thus the dose connitment from airborne tritium via vegetation (fruit and vegetables), air-grass-cow-milk, or air-grass-cow-meat pathways is calculated with the appropriate one(s) of the equations: for a stack release D TA
=(f)s ik llQ iks anse anie for a vent release D TA anve =(f)v ik llQ ikv anie I
u!hk- \ . Rev. 3 6/87
The dose connitment accoulated by a person offsite is. computed at leact every 30 days to sat lsfy Specification 4.15.4.2 but any be celculated as analytical results of effluent measurements, perfonned as specified in Table 4.15-2 in the Technical Specification, become avail able. The cose accmulated as a' result of stack discharge is computed with D =1D ans , anse and the dose accmulated as a result of vent discharge is computed with , D any
=1D anye Doses committed during the same time period due to discharges from the stack and vents are additive, thus
. D an
=D ans
+10 any y
where D = the dose comitment accoulated during the quarter to
"" date as a result of, all measured radioactive gaseous discharges except. noble gases to any organ n, including total body, of a person offsite in age group 1
.a_(mrem). !
When the dose to a person from iodine and particulate discharged in gaseous effluents is calculated as requir'ed by Specification 4.15.4, l appropriate environmental pathways (from among those for which dose
. transfer factors are provided in Appendix A) wil1 be. evaluated. The dose calculated is to a receptor at the location identified in i j
l Rev. 3 6/87 e
-._._____________m-________._mm
i 1 l 1 1 Figure 3-2 where reference atmospheric dispersion and deposition f actors are: '
= 3.1 x 10-I sec/m3 = 7.2 x 10-8 m-2
= 3.9 x 10-6 sec/m3 = 1.3 x 10- s m-2 i
Food pathways are evaluated with reference meteorology applicable at i the location of food production. Seasonal appropriateness of
, pathways is considered. , .
1 The air-grass (fresh or stored)-cow-milk-man pathway is evaluated where a cow is located, 2650m WNW of DAEC, and where reference meteorological data are (h),=2.1x10-8 m-2 ( )y = 4.28 x 10-8 m-2 3.8.1 Alternate Method of Evaluating Doses Due to Iodine and Particulate in Gaseous Effluents a Alternatively, the dose c'omitment to a maximally exposed, _ hypothetical individual may be calculated by the equation 1 D = - x 1 (Q x TG x D/Q) inf-thy 0.8 4, i inf-thy-I-131 s 1 ,
= - x 1 (Q x TG x D/Q) 0.8 $
i inf-thy-I-131 v where D = the dose commitment acasnulated inf-thy during the quarter to date to a ' hypothetical infant's thyroid as a result of the releases of I-131 (mrem) Rev. 3 6/87
Q4 a the measured quantity of'I-131 3 released in a given effluent strean, stack or vent (C1) -
)
. TG inf-thy-I-131
= the dose transfer factor for the infant thyroid from the cow-milk pathway for I-131 measured 'in the 1 effluentstream[Ci/mmram)2 1 . = a factor of conservation which 0.8 accounts for the dose contribution )
for releases of particulate- j radioactive material other than I-131 -) i i When the maximun organ dose is evaluated by using the ) equation above, analyses of other organ doses via 'other pathways are not needed to demonstrate compliance within the 4 dose limits of Technical Specification 3.15.4. The rationale for only evaluating the dose contribution of I-131 is derived from an evaluation of the radioactive , material releases and the environmental pathways. The air-grass-cow-milk-man pathway is by far the controlling pathway-and the. infant's thyroid is the limiting organ. This pathway typically contributes greater than 90% of the total calculated dose to the infant's thyroid and I-131 contributes ~ essentially all of the dose (45%). Therefore, it is possible to demonstrate compliance with the dose limits of Technical Specification 3.15.4 by the conservative j calculational method presented above. 3.9 Dose to a Person from Noble Gases , Technical Specification 4.16.1 requires the calculation of the dose or dose commitment to a person offsite exposed to 17, consecutive
-38 -Rev. 3
. 6/87
months cf radioactive liquid and gaseous effluents from the Station. One component of personal dose is total body irradiation by gamme . rays from noble gases. a nother is irradiation of skin by beta and ganna radiation from . noble gases. The methods of calculating these doses are presented in sections 3.9.1 and 3.9.2. The amount of radioactive noble gas dischaked is determined in the manner described in section 3.2. 3.9.1 Gamma Dose to Total Bod _y The gauna radiation dose to the whole body of a menber of the public as a consequence of noble gas released from the Station. is calculated with the equation: 0 = 0.7 7 (Q4 x Py 8 ),+0.71 (Qg xfxPy{), where Dy = noble gas gamma dose to total body (mram) Qg = quantity of noble gas nuclide i released via l stack or vent (uC1) Py} = factor conve'rting unit noble gas nuclide i stack release to total body dose at ground level received from the overhead pita (mram/uC1) Py{ = factor converting time integrated, ground level concentration of noble gas nuclide i to total body dose from gamma radiation mram ((uC1. sec)/m ) 3 j l
, 0.7 = reduction in dose due to shielding by housing When the total body dose due to gamma radiation from noble gas is computed as required by Technical Specification ;
4.16.1, the nearby resident exposed to maiimal ground-level Rev. 3 6/87 i
noble gas concentrations (eaxine X/Q) is selectec cs the ' receptor. Alternatively, the total body dose to a maximally exposed,' hypothetical ind'vidual may be calculatec at location 1260 meters NW of the reactor, in which case values of the 1
, dose f actors, particularly Py}, in Table 3-5 are employed, i
Noble gas pipe gamma-to-total body dose factors, PT{, j are calculated in accordance with Regulatory Guide 1.109, I Appendix B. hoble gas semi-infinite cloud gamma-to-total body dose f actors, Py{ are listed in Table 3-5 herein, and finite p1tme gauna-to-total body dose factors, Pr}, for the location 1260 meters NNW are listed in Table 3-5. l 3.9.2 Dose to Skin i The beta radiation dose to the skin of a msnber of the public due' to beta radiation from noble gas released from the Station may be calculated with the equation DS"138(0
- i i )s + 11381(0* i
)
$ yj V where Da = noble as dose to skin (mrem)
S81 = factor converting time integrated ground level concentration of noble gas to skin dose from ! beta radiation ;
, mram
[pCi m ) m8 Semi-infinite cloud noble gas beta-to-skin dose factors, S81, ; appear in Table 3-5. The total dose to the skin from noble gases is approximate 1,y equal to the beta radiation dose to the skin plus the grAsna radiation dose to the total body.
' Rev. 3 6/87
When the skin dose due to noble gas beta' radiation is computed as required by Sp. edification 4.16.1, the receptor selected is the nearby resident exposed to maximal ground-level concentrations (maximun.X/Q). Alternatively, the skin ' dose to a postulated receptor (resident) at 1260 meters NNW l of the reactor may be calculated. 4 l ==w O I 1 e e 1 a Rev'. 3 6/87
-"------------------_a,__ _ _ , , , , , _ , , , _ _ _
Figure 3-1 Gasoous Radioactive Haste Flow Diagram
~~
as at l0FFCAS SYSTEM ! 8 anun !
'" r 2 PREP;i.ve gi. Tan i G.1.,
an .llllllk!r
===== - -
i v =. n 7-,-
- 1.e,n entas.vTre l :
[ asconelsesa as MINUTE - -. y I
, t i
j "m8u' PIP 1No j
=
i l TeescPa t.Ta sleeWTE es0LDuP P1PIsle
! j gSecTSYSTEM L % ,.,.,. ,,,,, q, e
g je' ~"" 5 l -
- c =
V' f : i h '
-e- 1, acte ennenrTRIC
=_:..# ;
i
, e e A
- OFFCRS STACK I I
REACTOR BLDC _ VENTS
- aIncten eLps agy :es py
_fifEL PL ) ) ) I IV-SP-19C -
~
- 22 _ ;Fn
) ) )
g-
!V-SP-190 -
,,- . = -
\
2 i,-.-it. TORUS aseecFM
, 1V-SP-!SC
-. ig as na e
;i ,,, m mT 2ANTAftflARTED amena
-f . -
- == _ aansecPM l l g- , . P- y
$_ n .
-81A/t/c LPPER T W I M !W=EPat 3 78 800P Tues1N. -_
__=" P rM 1V-SP-atA/8/C egenuet WUIL91 ass _ Tune 1NE OLDS esaneern POTENTIALY IV*IP"I8" I 200tThMIMRTED r ) MIM EEEET NEntgiuggessegun
*** U 1V-EP-190
8"u" - -
l TO ROOF STACK y /\ M 88 PT 99999CFM Rev. 3 6/87
Figure 3-1 Continued R1 Main Condenser SJAE Offgas Post-treatment Noble Gas Activity Monitor R2 Main Condenser SJAE Offgas Hydrogen Monitor R3 Offgas Stack Radiation Monitoring System R4 Reactor Building Exhaust Vent Monitoring System j
.)
R5 Turbine Building Exhaust Vent Monitoring System
, ]
R6 Main Condenser SJAE Offgas Retreatment Noble Gas Activity Monitor R7 LLRPSF Exhaust Vent Monitoring System e
\
Rev. 3 6/87
$/sC/&:%
- y s, d** f % '
- X J' \ / ~ / f*/ ~ Jw
- **L. e i.4 f.?:h_PI(p..}I%-:('"*@ff5: <~-1,.b W? .'.
h
~
, hl.'i .l ]
m (
.f.'5 z.. .
g.k bv& g 6 N %s gVy, < . e -J QR-H M % LC'* 3L 94 (A =~ :.-i! L. . NW - [ W s;e i
]
[u W ", u
-- 5 , \ g/' l
'( p/*.4try:j/..(
.t
$~'j r , h1, .
- e. . .&
u,wa4 4 W. 1 i
. ( ; ,' *.Q. -.q .
Ky EA ) c v\T D's r7 4 A.: s : / o
! i "-
/ y .
% ::y .
%.t -f $f@f % 'E [
P' ; '"#- ygi
.V g_l $= hJw ?l
.. V ! \j'D h
\
zg- y vi. ; :.,9
, e.. . e . .: . . .
n h- ! i l/ h. e +'l % w{ % :a W< (/ ,/ m !
~ l l
ie llg' i i'
; . .R c.. r f'( . ..Jw.,,= -[f~-a % ,
. y,
^] \.)
j i i i i i
. .e 4 .
~ ya CE t i, .2 d l /
! [,I . * (
ib : k/. ' f / i
.1 Figure 3-2 ,
y, I 2 Offsite Locations at which Radiological Doses are Calculated ~. . . ('; . 7*** 4 '}-y* ', b
; A Noble gas gamma and beta doses to air,1260 m NNW , y 5
1 B Milk cow, 2650 m WNW -
"T i i C Aquatic pathways, in River , _ , ,
.S.
.-1 i ,,, .
O Most exposed residence, 1610 m NNW E *[*.
/ . . _ _ d 'd/
/ , n *s W \ / \ # R'r2 0'a,I % osea ]# 'l l W $. :-i . '
Rev. 3 J 6/87' ; l
Table 3-1 .
)
I Atmospheric Gaseous Release Points 1 at the Duane Arrold Energy Center I P arameter Release Point Offcas Stack Reactor Side. Vent Turbine 81do. Vent Radweste 81dg. Vent I
. Release Height 328 ft 156 ft 90 ft ,
65 ft Release Mode elevated wake-split wake-split wake-split Effluent Source Waste Gas System Reactor 81d. Upper Turbine Bid. LLRPSF Standby Gas Radwaste Bld. Building Treatment System and , 1 Lower Turbine Storage l Building Facility l O s e= l l O 9 9 1 Rev. 3 6/87 j n.
l Table 3-2 ! Computed Releases of Radioactive Noble Gases in Gaseous i Effluent from Duane Arnold Energy Center I l Stack Release Plant Vents Release Nuclide (Ci/yr[a fractionb (C1/yrla fractionb l 4 Kr-83m 4.90E+01 2.53E-03 0 0 Kr-85m 2.34E+03 1.21E-01 7.40E+01 1.98E-02 Kr-85 ! 1.40E+02 7.23E-03 0 0 K'-87 1. 56E+02 8.06E-03 1.36E+02 , 3.64E-02 : Kr-88 1.65E+03 8.52E-02 2.36E+02 6.32E-02 !
' Kr-89 6.40E+02 3.31E-02 0 0 Xe-131m 4.80E+01 2.48E-03 0 0 Xe-133m -
3.50E+01 1.81E-03 0 - 0 l Xe-133 1.24E+04 6.41E-01 3.92E+02 1.05E-01 i Xe-135m 1.80E+01 9.30E-04 7.42E+02 1.99E-01 Xe-135 5.10E+02 2.63E-02 7.34E+02 1.99E-01 - Xe-137 7.80E+02 4.03E-02 0 0 Xe-138 5.90E+02 3.05E-02 1.41E+03 3.78E-01 i 19356 1.0 3733. 1.0 a Releases computed by 8WR-GALE for DAEC Base Case gaseous radwaste treatment. Computed releases are included only to show.the basis of the radionuclides distribution, b This is the calculated distribution of radionuclides in gasecus effluents in each release pathway. To estimate radionuclides concentrations in a sanple in which only the total activity concentration has been measured, multiply the total activity concentration by the fraction of respective radionuclides listed above. Rev. 3 6/87
i Table 3-3 ! Transfer Factors for Maximum Offsite Air Dose Based on Reference Meteorology ~ Air Dose Transfer Factors I a,b Ay} Ay{ A84 mrad mrad GRCRA) Radionuclides uCi (Cisec/m)' p 3 [Cisec/m8) u 1 Kr-83m 4.3E-14 6.1E-7 9.1E-6 Kr-85m 6.0E-12 3.9E-5 6.2E-5 i Kr-85 8.4E-14 5.4E 6.2E-5 Kr-87 2.3E-11 2.0E-4 3.3E-4 Kr-88 6.4E-11 4.8E-4 9.3E-5 Kr-89 3.0E-11 5.5E-4 3.4E-4 Kr-90 --- 5.2E-4 2.5E-4 Xe-131m 1.8E-12 4.9E-6 3.5E-5 Xe-133m 1.4E-12 1.0E-5 4.7E-5 Xe-133 1.5E-12 1.1E-5 3.3E-5 Xe-135m 1.1E-11 1.1E-4 2.3E-5 1 Xe-135 9.5E-12 6.1E-5 7.8E-5 Xe-137 2.6E-12 <~ 4.8E-5 4.0E-4 Xe-138 3.6E-11 2.9E-4 1.5E-4 l Ar-41 4.4E-11 2.9E-4 1.0E-4 l a Based on reference meteorology at DAEC
. b Receptor located 1260 meters NNW of Station i
* )
e 0 0
. Rev. 3 .;
-47 6/87 i
Table 3-4 .
~
~
Transfer Factors for Dose Equivalent Rate to A Person Offsite Due to Ra'dioactive noble Gases l Dose Transfer Factors I a,b ; PY{ Py} j
-or- -or-DF{ DF{ ,
58j mram eram eram i Radionuclides (uC1 yr)/sec (vCi yr)/m3 (uC1 yr)/m3 I Kr-83m 6.27E-9 7.56E-2 0 Kr-85m 1.81E-4 1.17E+3- 1.46E+3 I Kr-85 2.51E-6 1.61E+1 1.34E+3 Kr-87 6.97E-4 5.92E+3 9.73E+3 Kr-88 1.91E-3 1.47E+4 2.37E+3 - Kr-89 9.14E-4 1.66E+4 1.01E+4 l Kr-90 --- 1.56E+4 7.29E+3 Xe-131m 4.83E-5 ' 9.15E+1 4.76E+2 Xe-133m 3.61E-5 2.51E+2 - 9.94E+2 l Xe-133 4. 09E-5 2.94E+2 3.06E+2 Xe-135m 3.39E-4 3.12E+3 7.11E+2 Xe-135 2.84E-4 1.81E+3 1.86E+3 Xe-137 7.90E-5 1.42E+3 1.22E+4 Xe-138 1.08E-3 8.83E+3 4.13E+3 - Ar-41 1.32E-3 8.84E+3 2.69E+3
~
a Receptor located 1260 meters NNW of Station b Based on reference meteorology at DAEC l Rev. 3 6/87
Table 3-5 Transfer Factors for Maximum Dose to A Person Offsite Oue to Radioactive Noble Gases Dose Transfer Factors a,b PY{ PY} S8j gg mre arm Radionuclides uC1 uti sec/m3 uCi sec/m3 Kr-83m 1.99E-16 2.4E-9 --- Kr-85m 5.75E-12 3.7E-5 4.6E-5 Kr-85 7.97E-14 5.1E-7 4.2E-5 Kr-87 2.21E-11 1.9E-4 3.1E-4 Kr-88 6.07E-11 4.7E-4 7.5E-5 Kr-89 2.90E-11 5.3E-4 3.2E-4 . Kr-90 --- 4.9E-4 2.3E-4 Xe-131m 1.53E-12 2.9E-6 1.5E-5 Xe-133m 1.15E-12 8.0E-6 3.1E-5 Xe-133 1.29E-12 9.3E-6 9.7E-6 Xe-135m 1.07E-11 9.9E-5 2.3E-5 Xe-135 9.01E-12 5.7E-5 5.9E-5 Xe-137 2.50E-12 4.5E-5 3.9E-4 Xe-138 3.42E-11 . 2.8E-4 1.3E-4 Ar-41 4.17E-11 2.8E-4 8.5E-5 a Receptor located 1260 meters NNW of Station .
. b Based on reference meteorology at DAEC l
' ,i y
~
j 6i .
4.0 DOSE COP 911 TENT FROM RELEASE OVER EXTENDED TIME 4.1 Dose Assessment for 10 CFR Part 50 Appendix I Technical Specifications 4:14.3, 4.15.3, and 4.15.4 require quarterly and annual assessments to demonstrate compliance with Appendix I dose limits. The assessment includes the following calculations of dose as described by equations for:
- 1. total body and maximally exposed organ doses due to liquid-effluent via drinking water and eating fish from.the River and from consuning food irrigated with river water as in l 2.5.
- 2. total body and maximally exposed organ doses due to gaseous l
effluents
- other than noble gases as in j 3.8.
- 3. doses to air offsite due to noble gas y as in 3.6 and due to noble gas 8 as in j 3.7.
The dose calculations are based on liquid and gaseous effluents from the Station during each calendar guarter and for a calendar year, detemined in accord with Technical Specification Tables 4.14-2 and 4.15-2. l Environmental concentrations depend on dispersion and dilution of l the effluent. For aqueous effluents over extended time, the aquatic
. concentration is estimated according to section 2.2. Atmospheric dispersion and deposition factors'used to estimate the dose ;
commitment due to gaseous effluents are ordinarily derived from ! reference meteorological data. Otherwise, quarterly averaged or
- Radioactive iodine-131, iodine-133, tritium, and radioactive material in particulate form having half-lives greater than 8 days. .
Rev. 3 6/87
annual averaged. meteorological conditions concurrent'with the gaseous release being evaluated will be used to.estiaate atmospheric dispersion and deposition. The receptor of the dose is described such that the dose to any resident near the Station is unlikely'to be underestimated. That is, the receptor. is selected on the basis of the combination of applicable pathways of exposure to gaseous effluent identified in the annual land use census.and maximum ground level X/Q at the residence. Conditions (i.e., location,' X/Q, and/or pathways) more conservative (i.e, expec.ted to yield higher calculated doses) than appropriate for the maximally exposed individual may be assmed in the dose assessment. Seasonal appropriateness of exposure pathways may be considered. Exposure by eating fresh vegetation or drinking milk from cows or goats fed fresh forage is an inappropriate assumption during'the first or fourth calendar quarter; rether consumption of stored , vegetation and ' stored forage is assmed during those. quarters. ' Otherwise, during the second and third calendar quarters, exposure by eating fresh vegetation and/or drinking milk from cows or goats fed fresh forage is assmed where those pathways exist. Similarly, the liquid effluent-river-fish-man pathway is not assumed during the
. winter quarter.
Factors converting stack-released noble gas to gama radiation dose from the overhead plume are calculated on the basis of reference meteorological data for the receptor location. Other-environmental pathway-to-dose transfer factors used in the dose calculations are
- provided in Appendix A.
i O $ Rev. 3 6/87
4.2 ' Dese Assessment for 40 CFR Part 19j The regulation governing the maxima allowable dose or dose consnitment to a member of the public from all urania fuel cycle sources of radiation and radioactive material in the environment is stated in 40 CFR Part 190. It requires that the dose or dose commitment to a menber of the public from all sources not exceed 25 mean/yr to any organ or 75 mram/yr to the thyroid. Technical Specification 4.16.1 requires calculation of the dose at least once every year to assess compliance with tie regulation. More frequent calculations may be performed if higher than normal releases tre experienced (twice the design objective rates in a single quarter). Fuel cycle sources or nuclear power reactors other than the Station itself do not measurably or significantly increase the, radioactivity concentration in the vicinity of the Station; therefore, only radiation and radioactivity in the environment attributable to the Station.itself are considered in the assessment of compliance with 40 CFR Part 190. *
~
Contributions to the dose due to liquid and gaseous effluent are calculated as described by the equations for:
- 1. total body and maximally exposed organ doses due to liquid effluent via drinking water, consming irrigated food and from )
eating fish fra the River as in $ 2.5 i
- 2. total body dose due to noble gas y as in 6 3.9.1 I
- 3. skin dose due to noble gas 8 as in j 3.9.2 i 9
Rev. 3 6/87
4 total body and aaxinally expostd organ doses due to gaseous effluents
- other than noble gases as in $ 3.8.
The doses are calculated on the basis of liquid and gaseous effluents from the Station during 12 consecutive months, determined in accord with Technical Specification Tables 4.14-2 and,4.15-2. , For the purpose of the Annual Radiological Environmental Report, doses are based upon release during' a calendar year. Aqueous radioactive material concentrations are estimated according to 5 2.2 on the basis of annual averaged stream flow. Annual ' averaged meteorological conditions concurrent with gaseous releases being evaluated are used to estimate atmospheric dispersion, deposition, and elevated pine gesna exposure. The receptor of the dose is described such that the dose to .any ! resident near the Station is not likely to be underestimated, although conditions more conservative than appropriate for the maximally exposed person may be assmed in the dose assessment. ; Ordinarily, the receptor is selected on the basis of the applicable combination of existing pathways of exposure to gaseous effluent identified in the annual land use census and the maximm ground l level X/Q at the residence. < 1 When assessing compliance with 40 CFR 190, Radiological Environmental Monitoring Program results may be used to indicate
. actual radioactivity levels in the environment attributable to the DAEC. These measured levels may be used to supp1 ment the
. evaluation of doses to members of the public for assessing . i compliance with 40 CFR 190.
- Radioactive iodine-131, iodine-133, tritis, and radioactive material in particulate form' having half-lives greater than 8 days.
Rev. 3 6/87
Factors converting stack-released noble gas to gesna radiation dose - from the overhead pitsne 'are calculated on the basis of annual averaged meteorological data for the receptor location. Other , environmental pathway-to-dose transfer factors are listed in Appendices A, 3 and C. l I i l i
\
f Rev. 3 6/87
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PR0' GRAM SAMPLING STATION LOCATIONS Sampling station locations identified in Table 5-1 correspond to the minimum required neber of radiological environmental monitoring program sampling stations in Technical Specifications Table 3.16-1. Environmental monitoring locations are shown on Figures 3-3 and 3-4. IELP may conduct additional' environmental monitoring exclusive of the requirements of Specifications 3.16.2 and 6.11.1.e. , 9 e up g> l l e
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8 . Radiological Environmental - Ip,gu-- 7 'l Monitoring Program $amplin near * / the' Duane Arnold Energy Ce ter
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' Radiological Environmental g
Monitoring Progran Sampling Stations Outside 0.5 miles Rev. 3 6/87
Table 5-1 REQUIRED Et:VIRONMENTAL SAMPLE STATIONS Station Nunber ' Station Location and Sanple Type 1 Location: Cedar Rapids,11 miles (135*) SE Type : TLD Control Airborne Particulate Control 2 - Location:. Marion,' 11 miles (125*) ESE Type : TLD Control Airborne Particulate and Iodine Control 3 Location: Hiawatha, 7 miles (130*) SE Type : TLD Control Airborne Particulate a 4 Not'used 5 Location: Palo, 3 miles (200*). SSW Type : TLD Control Airborne Particulate and Iodine 6 Location,: Center Point, 7 miles (0*) N Type : TLD Control Airborne Particulate 7 Location: She11sburg, 6 miles (255*) W' Type : TLD Control Airborne Particulate and Iodine 8 , Location: Urbana,10 miles (345*) NW Type : TLD Control Airborne Particulate and Iodine 9 Not used Rev. 3 6/87 ,
s Table 5-1 (Continued) . ; j I REQUIRED ENVIRONME::TAL SAMPLE STATIONS s_ 7 F , s Station _, Number Station Location and Sample Type
, f .
c. 10- Location: Atkins, 9 miles (210*) SSW Type : TLD Control jj Airborne Particulate "e h 11 Location: Toddv111e, 4 miles (90*) E Type : TLD Control - Airborne Particulate and Iodine' , l 4 e 12 Not used l
, c- --
13 Location: Alburnett, 9 miles (70*) ENE 7
- TLD Control Type -
Airborne Particulate Control I i 14 Not ussd 15 Location: On-site North, b.5 miles (305*) NW Type :. TLD Control Airborne Particulate and Iodine tv l{ 16 Location: On-site South, 0.5 miles (190') SSE Type : TLD Control Airborne Particulate - Vegetation I < 17 N0t used 3
; 9 18 . Location: On-site, 0.5 miles NNE' Type : TLD 19 Location: On-site, 0.5 miles NE Type : TLD Rev. 3
' 6/87 4 ,;
T q Tole 5-1 (Continued) ." .t r REQUIRED ENVIRONMENTAL SAMTLE STATIONS 4
. ~' ,7 -
Station l Number Station Location and Sample Type
, . L.
20 Location: On-site, 0.5 miles ENE l' Type : TLD .;
/
- t. ,
F1 f. Location: On-site, 0.5 miles ENE Type : TLD ' 22 Location: On-site, 0.5 miles E Type : TLD 23 Location: On-site, 0.5 miles ESE , l Type : TLD 24 . Not used g y; 25 Not used <- (, 26 Not used s
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27 Not used ' t
. .i 23 Location: Da-site, 0.5 miles WS'A >
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Type : TLD
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31 Location: On-site.ot.5 miles NW , f' ' Type. : TLD , e r
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'i Rev. 3 '
, 6/87 60 q -
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Table 5-i (Continued) f(. REQUIRED ENVIRONMENTAL SAMPLE STA110NS ' r Station 5. Number Statio,1 eocation and Sample Type J
- n. 32 ' Location: On-site, 0.5 miles HNW - -
s < Type : TLD ,
,s ,
33 ' Location: 3 miles'N N Type : TLD 1, 34 Location: 3 miles NNE
^
Type : Ti.D 35 Location: ~3 miles NE Type :' lid
'N 36 Location: 3 miles ENE 5
Type : TLD ,
)
37- Locaticp: 3 miles E Type TLD , k 38 Location: 3 miics ESE Type : TLD , 39 Location: 3 miles SE I Type : TLD 40 Location: ' 3 miles SSE Type : TLD 41 Location: 3 miles S Type : TLD i i 42 Not used I
)
Rev. 3 l 6/87 : i l \
\ Table 5-1 (Continued) REQUIRED ENVIRONMENTAL SAMPLE STATIONS ! Station Number Station Location and Sample Type 43 Location: 1 mile SSW Type : TLD l . 44 Location: 1 mile WSW , Type : TLD 45 Location: 1 mile W i Type : TLD 46 Location: 1 mile WNW i Type : TLD 47 Location: 1 mile WNW Type : TLD 48 Location: ,1 mile NW , Type : TLD 49 Location: Lewis Access, upstream of DAEC 4 miles NNW Type : Fi.sh Control Surf ace Water Control . I 50 Location: Plant Intake Type : Sediment Surf ace Water 1 51 Location: Plant Discharge Type : Sediment Surface Water 52 Not used , Rev. 3
. 6/87 .
i Tab e1' 5-1 (Continued) ' 1 REQUIRED ENVIRONMENTAL SAMPLE STATIONE i Station Number Station Location 'and Sample Type 53 Location: Treated Municipal Water j Type : Ground Water 54 Location: Inlet to Municipal Water Treatment System Type : Ground Water -
]
1 l 55 Location: On-site Well Type : Ground Water . 56 Not used l 57 Location: Farm, 1 mile WSW Type : Ground Water , Vegetation
~
58 Location:' Farm, 1 mile'WSW-SW Type : Ground Water Vegetation 59 Not used 60 Not used 61 Location: Cedar River about one-half mile downstream ) from DAEC discharge Type : Fish , , 62 Not used 63 Location: Farm, 1.5 miles WNW Type : Milk Vegetation Rev. 3 63- 6/87
Table 5-1 (Continued) , REQUIRED ENVIRONMENTAL' SAMPLE STATIONS Station Number Station Location and Sample Type 64 Not used 65 Not used 66 Not used ; 67 Not used j 68 Not used 69 Not used 70 Not used 71 Not used 1
)
72 Location: Farm, 2 miles SSW Type : Ground Water l Vegetation . 73 Not used 74 Not used 75 Not used 76 Not used l
. 77 Not^used 78 Not used 79 Not used .
1 80 Not used
. 81 Not used l
I 82 Location: On-site, 0.5 miles SE Type : TLD 83 Location: On-site, 0.5 miles SSE Type : TLD 84 Location: On-site, 0.5 miles 5 ; Type' : TLD 85 Location: On-site, 0.5 miles SSW , I' Type : TLD Rev. 3 64- 6/87 l _. - _ _ - - l
Table 5-1 (Continued) REQUIRED ENVIRONMENTAL SAMPLE STATIONS Station N e er . Station Location and Sanple Type 86 Location: On-site, 0.5 miles SW Type : TLD ; 87 Not used I 88 Not used . 89 Not used 90 Not used 91 Location: On-site, 0.5 mil'es N Type : TLD 92 . Not used 93 Location: Farm 2.8 miles NNE ,
)
Type : Vegetation ' Milk - i 94 Location: Farm, 2.7 miles N ; Type : Vegetation Milk 95 Not used I 96 Location: Farm, 8 miles SSW Type : Milk 97 Not used l 98 Not used - 99 Location: Pleasant Creek Lake, 2.5 miles WNW Type : Surface Water Rev. 3 6/87
TC11e5-l'(Continued) i REQUIRED' ENVIRONMENTAL SAMPLE STATIONS Station ; Number Station Location and Sample Type i 100 Not used 101 Location: Farm, 4 miles E Type : Milk I l 102 Not used 103 Not used I 104 Not used ' 105 Location: Farm. 21.3 miles SSW Type : Milk Control J Vegetation Control 106 Location: Farm, 4.5 miles SE ! Type : Milk Vegetation ) 1
]
s l 4 1 I 1 Rev. 3 6/87
APPENDIX A AIRBORNE PATHWAY SITE-SPECIFIC DOSE TRANSFER FACTORS Environmental pathway transfer f actors, usage f actors, and dose comitment
' f actors appropriate for each exposure pathway, age, and organ are combined into integrated environmental concentration-to-dose f actors for each radionuclides. This appendix includes tables of values of the transfer factors calculated in accord with equations and values recommended in Regulatory Guide 1.109, Revision 1. The transfer f actors have been tabulated for individual pathways. If a single, composite transfer factor is desired, it can be obtained by sinming the factors for appropriate pathways for a given organ and age group of interest.
Table A.1 Inhalation Pathway Factor (Tg) Table A.2 Grass-Cow-Milk Pathway Factor (T6 ) Ttble A.3 Grass-Cow-Meat Pathway Factor (Tg) Table A.4 Vegetation Pathway Factor (Tg ) Table,A.5 Grass-Goat-Milk Pathway Factor (Tg ) 4 e Rev. 3 - A ,1 6/87
TABLE A.2-2 COW GRASg*mram-MILK m / PATHWAY FACTOR TEEN]vrperuCi/sec TgFACTORS) NUCLIOE BONE LIVER T B00Y THYROID KIDNEY LUNG GI-LLI H-3 0.00E-01 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 C-14 4.86E 08 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 Na-24 4.26E 06 4.26E 06 4.26E 06 4.26E 06 4.26E 06 4.26E 06 4.26E 06 3.15E 10 1.95E 09 1.22E 09 0.00E-01 0.00E-01 0.00E-01 2.65E 09 P-32 Cr-51 0.00E-01 0.00E-01 4.99E 04 2.77E 04 1.09E 04 7.13E 04 8.39E 06 Mn-54 0.00E-01 1.40E 07 2.78E 06 0.00E-01 4.18E 06 0.00E-01 2.87E 07 9 Mn-56 0.00E-01 7.37E-03 1.31E-03 0.00E'-01 9.33E-03 0.00E-01 4.85E-01 Fe-SS 4.45E 07 3.16E 07 7.36E 06 0.00E-01 0.00E-01 2.00E 07 1.37E 07 Fe-59 5.18E 07 1.21E 08 4.67E 07 0.00E-01 0.00E-01 3.81E 07 2.86E'08 1 Co-58 0.00E-01 7.94E 06 1.83E 07 0.00E-01 0.00E-01 0.00E-01 1.09E 08 Co-60 0.00E-01 2.78E 07 6.26E 07 0.00E-01 0.00E-01 0.00E-01 3.62E 08 Ni-63 1.18E 10 8.35E 08 4.01E 08 0.00E-01 0.00E-01 0.00E-01 1.33E 08 Ni-65 8.48E-01 1.08E-01 4.94E-02 0.00E-01 0.00E-01 0.00E-01 5.88E 00 Cu-64 0.00E-01 4.25E 04 2.00E 04 0.00E-01 1.08E 05 0.00E-01 3.30E 06 Zn-65 2.11E 09 7.31E 09 3.41E 09 0.00E-01 4.68E 09 0.00E-01 3.10E 09 In-69 9.62E-12 1.83E-11 1.28E-12 0.00E-01 1.20E-11 0.00E-01 3.38E-11 Br-83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ~ Br-84 Br-85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01
'Rb-86 0.00E-01 4.73E 09 2.22E 09 0.00E-01 0.00E-01 0.00E-01 7.00E 08 i
. Rb-88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01
. 1 Rb-89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ] '
Sr-89 2.67E 09 0.00E-01 7.66E 07 0.00E-01 0.00E-01 0.00E-01 3.19E 08 Sr-90 6.61E 10 0.00E-01 1.63E 10 0.00E-01 0.00E-01 0.00E-01 1.86E 09 l Sr-91 5.27E 04 0.00E-01 2.10E 03 0.00E-01 0.00E-01 0.00E-00 2.39E 05 Sr-92 8.96E-01 0.00E-01 3.82E-02 0.00E-01 0.00E-01 0.00E-00 2.28E C'_ Y-90 1.30E 02 0.00E-01 3.50E 00 0.00E-01 0.00E-01 0.00E-00 1.07E 06 Rev. 3 i A-2 6/87
TABLE A.5-1 , GRASS-GOAT-MILK PATHWAY FACTOR m2 . mrem /yr per uCi/see ADULT (TG FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H-3 1.56E+03 1.56E+03 1.56E+03 1.56EE03 1.56E+03 1.56E+03 1.56E+03 i C-14 2.63E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07- ! P-32 2.05E+10 1.27E+09 7.91E+08 0.00E+00 0.00E+00 0.00E+00 2.30E+09 Mn- 54* 0.00E+00 7.53E+05 0.00E+00 0.00E+00 2.25E+05 0.00E+00 2.31E+06 Fe-59 3.86E+05 9.07E+05 '3.48E+05 0.00E+00 0.00E+00 2.53E+05 3.02E+06 Co-58* 0.00E+00 4.47E+07 9.99E+05 0.00E+00 0.00E+00 0.00E+00 9.04E+06 Co-60* 0.00E+00 1.46E+04 3.21E+06 0.00E+00 0.00E+00 0.00E+00 2.47E+07 Zn-65* 1.40E+08 4.44E+08 2.01E+08 0.00E+00 2.97F+08 0.00E+00 2.80E+08 Sr-89 3.05E+09 0.00E+00 8.74E+07 0.00E+00 0.00E+00 0.00E+00 4.89E+08 Sr-90 9.83E+10 0.00E+00 2.41E+10 0.00E+00 0.00E+00 0.00E+00 2.89E+09 Zr-95* 1.98E+03 1.08E+03 4.32E+02 0.00E+00 1.09E+03 0.00E+00 6.49E+06
. Nb-95* 8' 35E+03 4.63E+03 1.82E+03 0.00E+00 4.60E+03 0.00E+00 2.81E+07 Ru-103* 1.02E+02 0.00E+00 4.41E+01 0.00E+00 3.91E+02 0.00E+00 1.19E+04 Ru-106* 1.85E+03 0.00E+00 2.34E+03 0.00E+00 3.56E+03 0.00E+00 1.20E+05 Ag-110M* 5.48E+06 5.07E+06 3.00E+06 0.00E+00 9.99E+06 0.00E+00 2.07E+09
~~
Sb-124* 2.47E+06 4.66E+04 9.77E+05 5.99E+03 'O.00E+00 1.90E+06 6.99E+07 I-131 3.55E+08 5.08E+08 2.91E+08 1.67E+11 8.72E+08 0.00E+00 1.34E+08 I-133 4.65E+06 8.09E+06 2.47E+06 1.19E+09 1.41E+07 0.00E+00 7.27E+06 Cs-134 1.70E+10 4.04E+10 3.30E+10 0.00E+00 1.31E+10 4.34E+09 7.06E+08
- Cs-136 7.07E+08 3.11E+09 2.24E+09 0.00E+00 1.73E+09 2.37E+08 3.53E+08 Cs-137 2.21E+10 3.03E+10 1.98E+10 0.00E+00 1.03E+10 3.42E+09 5.86E+08 Ba-140* 3.12E+06 3.91E+03 0.00E+00 1.33E+03 2.24E+03 6.58E+06 2.05E+05 Ce-141* 2.96E+03 2.00E+03 0.00E+00 9.23E+02 0.00E+00 3.15E+01 2.27E+02 Ce-144* 1.91E+05 7.97E+04 0.00E+00 4.73E+04 0.00E+00 6.43E+07 1.97E+04 er Rev. 3 A-3 6/87
TABLE A.5-2
. GRASS-GOAT-MILK PATHWAY FACTOR' .
2 r per uC1/sec ' m .orem/y(T TEEN ,
, G FACTORS) . NUCLIOE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H-3 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 i P-32 3.78E+10 2.34E+09 1.46E+09 0.00E+00 0.00E+00 0.00E+00 3.17E+09 j Mn-54* 0.00E+00 9.73E+05 1.86E+05 0.00E+00 2.89E+05 0.00E+00 2.98E+06 ,
Fe-59 6.74E+05 1.57E+06 6.07E+05 0.00E+00 0.00E+00 4.96E+05 3.72E+06 Co-58* 0.00E+00 7.65E+05 1.75E+06 0.00E+00 0.00E+00 0.00E+00 1.03E+07 Co-60* 0.00E+00 2.43E+06 5.54E+06 0.00E+00 0.00E+00 0.00E+00 2.91E+07-Zn-65* 1.81E+08 5.73E+08 2.60E+08 0.00E+00 3.84E+08 0.00E+00 3.62E+08 Sr-89 5.61E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+08 i Sr-90 1.39E+11 0.00E+00 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+09 Zr-95* 2.58E+04 1.55E+04 8.73E+03 0.00E+00 1.22E+04 0.00E+00 6.30E+07 Nb-95 7.18E+03 4.32E+03 2.44E+03 0.00E+00 3.40E+03 0.00E+00 1.77E+07 Ru-103* 1.23E+02 0.00E+00 5.51E+01 0.00E+00 3.69E+02 0.00E+00 9.61E+03 Ru-106* 1.14E+04 0.00E+00 1.43E+03 0.00E+00 1.52E+04 0.00E+00 5.17E+05 - Ag-110M* 2.23E+07 2.07E+07 1.23E+07 0.00E+00 4.06E+07 0.00E+00 8.44E+09 Sb-124* 4.03E+06 7.62E+04 1.59E+06 9.77E+03 0.00E+00 3.13E+06 1.14E+08 I-131 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.55E+09 0.00E+00 1.79E+08 ;
. 1-133 8.49E+06 1.44E+07 4.39E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07 l Cs-134 2.94E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10. 8.14E+09. 8.62E+08 Cs-136 1.34E+09 5.27E+09 3.54E+09 0.00E+00 2.87E+09 4.52E+08 4.24E+08 i Cs-137 4.02E+10 5.34E+10 3.03E+10 0.00E+00 1.82E+10 7.06E+09 7.92E+08 l
Ce-141* 5.20E+03 3.47E+03 3.94E+02 0.00E+00 1.20E+03 0.00E+00 9.32E+06 A-4 6 _________.____________m_____.___.______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ _ _ _ _ . - _ _ _ _ _ . _ - _ . _____________..._____._._..m._-_.____._.-.________m_b
TABLE A.5-3 GRASS-GOAT-MILK PATHWAY FACTOR , m2 . mrem /yr per~uC1/sec ; CHILD (Tg FACTORS) NUCLIDE BONE -LIVER T BODY ' THYROID KIDNEY LUNG GI-LLI H-3 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 C-14 1.19E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2. 39E+08 P-32 9.31E+10 4.36E+09 3.59E+09 0.00E+00 0.00E+00 0.00E+00 2.57E+09 i Mn-54* 0.00E+00 8.03E+05 3.04E+05 0.00E+00 2.39E+05 0.00E+00 2.46E+06 Fe-59 1.56E+06 2.61E+06 1.26E+06 0.00E+00 ,0.00E+00 7.33E+05 2.36E+06 Co-58* .0.00E+00 .1.18E+06 3.56E+06 0.00E+00 0.00E+00 0.00E+00 6.99E+06- )! Co-60* 0.00E+00 3.75E+06 1.12E+07 0.00E+00 0.00E+00 0.00E+00 2.07E+07 2n-65* 1.49E+08 4.73E+08, 2.14E+07 0.00E+00 3.18E+08 0.00E+00 7.33E+05 Sr-89 1.39E+10 0.00E+00 3.97E+08 0.00E+00 0.00E+00 0.00E+00 5.38E+08 Sr-90 2.35E+11 0.00E+00 5.95E+10 0.00E+00 0.00E+00 0.00E+00 3.16E+09 Zr-95* 6.62E+03 2.77E+03 2.04E+03 0.00E+00 1.16E+03 0.00E+00 4.76E+06 Nb-95* 2.78E+04 1.18E+04 8.69E+03 0.00E+00 4.88E+03 0.00E+00 2.05E+07 Ru-103* 3.97E+02 0.00E+00 1.61E+02 0.00E+00 4.16E+02 0.00E+00 1.05E+04 i Ru-106* 8.51E+03 0.00E+00 1.06E+03 0.00E+00 3.81E+03 0.00E+00 1.32E+05 Ag-110M* 5.83E+06- 5.42E+06 3.21E+06 0.00E+00 1.06E+05 0.00E+00 2.21E+09 Sb-124* 2.63E+06 4.98E+04 1.04E+06 6.36E+03 0.00E+00 2.'04E+06 7.43E+07 ! I-131 1.56E+09 1.57E+09 8.94E+08 5.20E+11 2.55E+09 0.00E+00 1.40E+08 I-133 2.06E+07 2.55E+07 9.65E+06 4.74E+09 4.25E+07 0.00E+00 1.03E+07 Cs-134 6.38E+10 1.11E+11 2.35E+10 0.00E+00 3.54E+10 1.24E+10 6.01E+08 Cs-136 3.02E+09 8.31E+09 5.38E+09 0.00E+00 4.43E+09 6.60E+08 2.92E+08 Cs-137 9.67E+10 9.26E+10 1.37E+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 8a-140* 1.35E+07 1.18E+04 7.94E42 0.00E+00 1.42E+03 6.93E+03 8.79E+05 Ce-141* 1.26E+04 6.33E+03 9.42E+02 0.00E+00 9.99E+02 0.00E+00 7.94E+06 Ce-144* 8.88E+05 2.78E+05 4.73E+04 0.00E+00 5.04E+04 0.00E+00 7.25E+07 Rev. 3 A-5 6/87
TABLE A.5-4 GRASS-60AT-MILK PATHWAY FACTOR m2 .mram/yr per uCi/sec , INFANT (TG FACTORS) NUCLIDE BONE LIVER T BODY THYROIO KIDNEY LUNG GI-LLI , H-3 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 ! C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 P-32 1.92E+11 1.13E+10 7.44E+09 0.00E+00 0.00E+00 0.00E+00 2.60E+09 Mn-54* 0.00E+00 8.03E+05 1.53E+05 0.00E+00 2.39E+05 0.00E+00 2.46E+06 Fe-59 2.92E+06 5.09E+06 2.01E+06 'O.00E+00 0.00E+00 1.51E+06 2.43E+06 Co-58* 0.00E+00 2.41E+06 5.89E+06 0.00E+00 0.00E+00 0.00E+00 6.24E+06 Co-60* 0.00E+00 7.37E+09 1.92E+07 0.00E+00 0.00E+00 0.00E+00 1.86E+07 Zn-65* 1.49E+08 4.73E+08 2.14E+08 0.00E+00 3.18E+08 0.00E+00 2.98E+08 '
, Sr-89 2. 26E+10 0.00E+00 7.58E+08 0.00E+00 0.00E+00 0.00E+00 5.43E+08 l
Sr-90 2.48E+11 -- 6.50E+10 -- -- -- 3.19E+09 Zr-95* 1.32E+04 5.83E+03 3.47E+03 0.00E+00 1.16E+03 0.00E+00 4.60E+06
. Nb-95* 5.54E+04 2.49E+04 1.47E+04 0.00E+00 4.83E+03 De00E+00 1.99E+07 ,
Ru-103* 8.28E+02 0.00E+00 2.85E+02 0.00E+00 4.16E+02 0.00E+00 1.03E+04 Ru-106* 1.81E+04 0.00E+00 2.23E+02. 0.00E+00 3.81E+03 0.00E+00 1.41E+05 Ag-110M* 5.83E+06, 5.42E+06 3.21E+06 0.00E+00 1.06E+07 0.00E+00 2.21E+09 Sb-124* 2.63E+06 4.98E+04 1.04E+06 6.36E+03 0.00E+00 2.04E+06 7.43E+07 I-131 3.27E+09 .3.85E+09 1.69E+09 1.26E+12 4.49E+09 0.00E+00 1.37E+08 I-133 4.36E+07 6.34E+07 1.86E+07 1.15E+10 7.46E+07. 0.00E+00 1.07E+07 Cs-134 1.09E+11 2.04E+11 2.06E+10 0.00E+00 5.25E+10 2.15E+10 5.54E+08
. Cs-136 5.91E+09 1.74E+10 6.48E+09 0.00E+00 6.92E+09 1.42E+09 2.64E+08 Cs-137 1.54E+11 1.81E+11 1.28E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 '
. l Ba-140* 2.84E+07 2.86E+04 1.45E+06 0.00E+00 1.42E+03 1.75E+04 9.23E+05 Ce-141* 2.69E+04 1.65E+04 1.93E+03 0.00E+00 9.89E+02 0.00E+00 8.00E+06 Ce-144* 1.86E+06 7.37E+05 1.05E+05 0.00E+00 5.04E+04 0.00E+00 7.69E+07 Rev. 3 A-6 , 6/87
1 TABLE A.1-2 IWALATION PATHWAY FAQTOR
- aram/yr per uC1/m3 .
TEEN (Tg FACTORS) NUCLIDE DONE LIVER T BODY TfDmOID KIDNEY IIRC GI-LLI
~
I-135 3.70E 03 9.44E 03 3.49E 03 6.21E 05 1.49E 04 0.00E-01 6.95E 03 Co-134 5.02E 05 1.13E 06 5.49E 05 0.00E-01 3.75E 05 1.46E 05 9.76E 03 Cs-136 5.15E 04 1.94E 05 - 1.37E 05 0.00E-01 1.10E 05 1.78E 04 1.09E 04 Cs-137 6.70E' 05 8.48E 05 3.llE 05 ,0.00E-01 3.04E 05 1.21E 05 8.48E 03 Ce-138 4.66E 02 8.56E 02 . 4.46E 02. 0.00E 6.62E 02 7.87E 01 2.70E-01 Be-139 1.34E 00 9.44E-04 3.90E-02 0.00E-01 8.88E-04 6.46E 03 6.45E 03 Be-140 5.47E 04 6.70E 01 3.52E 03 0.00E-01 2.28E 01 2.03E 06 2.29E 05 Be-141 1.42E-01 1.06E-04 4.74 E-03 0.00E-01 9.84E-05 3.29E 03 7.46E-04 Be-142 3.70 E-02 3.70E-05 2.27 E-03 0.00E-01 3.14 E-05 1.91E 03 4.79E-10 La-140 4.79E 02 2.36E 02 6.26E 01 0.00E-01 0.00E-01 2.14E 05 4.87E 05 Le-142 9.60 E-01 4.25E-01 1.06E-01 0.00E-01 0.00E-01 1.02E 04 1.20E 04 i Cel41 2.84E 04 1.90E 04 2.17E 03 0.00E-01 8.88E 03 6.14E 05 1.26E 05 i
~
Ce-143 2.66E 02 1.94E 02 2.16E 01 0.00E-01 8.64E 01 1.30E 05 2.55E 05 Ce-144 4.89E 06 2.02E 06 2.62E 05 0.00E-01 1.21E 06 1.34E 07 8.64E 05 Pr-143 1.34E 04 5.31E 03 6.62E 02 0.00E-01 3.09E 03 4.83E 05 2.14E 05
=
l Pr-144 4.30E-02 1.76E-02 2.18E-03 0.00E-01 1.01E-02 1.75E 03 2.35E-04 _ !t5-147 7.86E 01 8.56E 03 5.13E 02 0.00E-01 5.02E 03 3.72E 05 1.82E 05 W-187 1.20T,!i 9.76E 00 3.43E 00 0.00E-01 0.00E-01 4.74E 04 1.77E 05 Np-239 3.38E 02 3.19E 01 1.77E 01 0.00E-01 1.00E 02 6.49E 04 1.32E 05 i l t e 4
* ^~ 7 Rev. 3 6/87
TABLE A.1-3 . D84ALATION PATHWAY FACTOR mramlyr per uC1/m3 CHILD (T GFACTORS) , NGCLIDE B3NE LIVER T 82N , 'HfYRDID KIDNEY WNG GI-LLI H-3 0.00E41 1.12E 03 1.12E 03 1.12E 03 .l.12E 03 1.12E 03 1.12E 03-C-14 3.59E 04 6.73E 03 6.73E 03 6.73E 03 6.73E 03 6.73E 03 6.73E 03 Na-24 1.61E 04 1.61E 04 1.61E 04 1.61E 04 1.61E 04 1.61E 04 1.61E 04 i l P-32 2.60E 06 1.14E 05 9.88E 04 0.00E-01 0.00E-01 0.00E-01 4.22E 04 Cr-51 0.00E-01 0.00E-01 1.54E 02 0.00E41 2.43E 01 1.70E 04 1.08E 03 Mn-54 0.00E41 4.29E 04 9.51E 03 0.00E-01 1.00E 04 1.58E 06 2.29E 04
~
Mn-56 0.00E-01 1.66E 00 3.12E-01 0.00E-01 1.67E 00 - 1.31E 04 1.23E 05 Fe-55 4.74 E 04 2.52E 04 7.77E 03 0.00E-01 0.00E-01 1.11E 05 2.87E 03 Fe59 2.07E 04 3.34E 04 1.67E 04 0.00E-01 0.00E-01 1.27E 06 7.07E 04, Co-58 0.00E41 1.77E 03 3.16E 03 0.005-01 0.00E-01 1.11E 06 3.44E 04 Co-60 0.00E-01 1.31E 04 2.26E 04 0.00E 0.00E-01 7.07E 06 9.62E 04 J Ni-63 8.21E Of 4.63E 04 2.80E 04 0.00E-01 0.00E-01 2.75E 05 6.33E 03 - Ni-65 2.99E 00 2.96 E-01 1.64 E-01' O.00E-01 0.00E-01 8.18E 03 8.40E 04 l Co-64 0.00E41 1.99E 00 1.07E 00 0.0E-01 6.03E 00 9.58E 03 3.67E 04 Zn-65 4.26E 04 1.13E 05 7.03E 04 0.00E-01 7.14E 04 9.95E 05 1.63E 04 Zrt-69 6.70 E42 9.66E-02 8.92E-03 0.00E-01 5.85E-02 1.42E 03 1.02E 04 Br-83 0.00 E-01 0.00E-01 4.74E 02 0.00E-01 0.00E-01 0.00E-01 3.70E-15 Br.e4 0.00 E-01 0.00E-01 5.48E 02 0.00E-01 0.00 E-01 0.00E-01 3.70E-15 Br-85 0.00 E-01 0.00E-01 2.53E 01 0.00E-01 0.00E-01 0.00E-01 3.70E-15
~
Rb-86 0.00E41 1.98E 05 1.14E 05 0.00E-01 0.00E-01 0.00E-01 7.99E 03 Rb-88 0.00 E-01 5.62E 02 3.66E 02 0.00E-01 0.00E-01 0.00E-01 1.72E 01 Rb-89 0.00 E-01 3.45E 02 2.90E 02 0.00E-01 0.00E-01 0.00E-01 1.89E 00 Sr-89 5.99E 05 0.00E-01 1.72E 04 0.00E-01 0.00E-01 2.16E 06 1.67E 05 Sr-90 1.01E 08 0.00E-01 6.44E 06 0.00E-01 0.00E-01 'l.48E 07 3.43E 05 Sr-91 1.21E 02 0.00E-01 4.95E 00 0.00E-01 0.00E-01 5.33E 04 1.74E 05 Sr-92 1.31E 01 0.00E-01 5.25E-01 0.00E-01 0.00E-Cl 2.40E 04 2.42E 05 ) Y-90 4.llE 03 0.00E-01 1.llE 02 0.00E-01 0.00E-01 2.62E 05 2.68E 05 l l i A-8 Rev. 3 6/87
TABLE A.1-3 IEIALATION PAT)(WAY FAGTOR orem/yr per uC1/m3- i Oi!LD(TfFACTORS) WCLIDE 90NE
- LTVER T BODY THYROID, KlDNEY IDG GI-ILI i Y-91M 5.07E-01 0.00E-01 1.845-02 0.00E-01 0.00541 2.81E 03 1.72E'03 Y-91 9.14E 05 0.00E-01 2.44E 04 0.00E-01 0.00E41 2.63E 06 1.84E 05 )
Y-92 2.04E 01 0.00E-01 5.81541 0.00E-01 0.005-01 2.39E 04 2.39E 05 1 l 1 Y-93 1.86E 02 0.00E-01 5.11E 00 0.00E-01 0.00E-01 7.44E 04 3.89E 05 Er-95 1.90E 05 4.18E 04 3.70E 04 0.005-01 5.96E 04 2.23E 06 6.11E 04 Er-97 1.88E 02 2.72E 01 1.60E 01 0.00E-01 3.88E 01 1.13E 05 3.51E 05 Nt> 95 2.35E 04 9.18E 03 6.55E 03 0.00E41 8.62E 03 6.14E 05 3.70E 04
.Mo-99 0.00 E-01 1.72E 02 4.25E 01 0.005-01 3.92E 02 1.35E 05 1.27E 05 To-99M 1.78 E-03 3.48E-03 '5.77E-02 0.00E-01 5.07E-02 9.51E 02 4.81E 03 To-101 8.10E45 8.51E-05 1.08E-03 0.00E-01 1.45E-03 5.85E 02 1.63E 01 Ru-103 2.79E 03 0.00E-01 1.07E 03 0.00E 7.03E 03 6,62E 05 4.48E 04
. Ru-105 1.53E 00 0.00E-01 5.55E-01 0.00E-01 1.34E 00 1.59E 04 9.95E 04 Ru-106 1.36E 05 0.00E-01 1.69E 04 0.00E-01 1.84E 05 1.43E 07 4.29E 05 A9-110M 1.69E 04 1.14E 04 9.14E 03 0.00E-01 2.12E 04 5.48E 06 1.00E 05 Te125M 6.73E 03 2.33E 03 9.14E 02 1.92E 03 0.00E41 4.77E 05- 3.38E 04
~
Te-127M 2.49E 04 8.55E 03 3.02E 03 6.07E 03 6.36E 04 1.48E 06 7.14E 04 Te-127 2.77E 00 9.51E-01 6.10E-01 1.96E 00 7.07E 00 1.00E 04- 5.62E 04 . Te-129M 1.92E 04 6.85E 03 3.04E 03 6.33E 03 5.03E 04 1.76E 06 1.82E 05 Te-129 9.77 E-02 3.5bE-02 2.38E-02 7.14E-02 : 2.57E-01 2.93E 03 2.55E 04 ;
. Te-131M 1.34 E 02 5.92E 01 5.07E 01 9.77E 01 4.00E 02 2.06E 05 3.08E 05 Te-131 2~17 E-02 8.44K-03 6.59E-03~ 1.70E-02 5.88E-02 2.05E 03 1.33E 03 i
Te-132 4.81E 02 2.72E 02 2.63E 02 3.17E 02 1.77E 03 3.77E 05 1.38E 05 l I-130 8.18E 03 1.64E 04 8.44E 03 1.85E 06 2.45E 04 0.00E-01 5.11E 03 I-131 4.81E 04 4.81E 04 2.73E 04 1.62E 07 7.88E 04 0.00E-01 2.84E 03 I-132 2.12E 03 4.07E 03 l'.88E 03 1.94E 05 6.25E 03 0.00E-01 3.20E 03 I-133 1.66E 04 2.03E 04 7.70E 03 ~ 3.85E 06 3.38E 04 0.00E-01 5.48E 03 I-134 1.17E 03 2.16E 03 9.95E 02 5.07E 04 3.30E 03 0.00E-01 9.55E 02
. A-9 Rev. 3 6/87-
TA8LE A.1 3 IE ALATION PATHWAY FACTOR mram/yr per uC1/m3 . DiILD.(T ' gFACTORS) NDC2JDE BCNE LIVER T B3R TItY101D KIDNEf LUNG GI-ILI-I-135 4.92E 03 8.73E 03 4.14E 03- 7.92E 05 1.34E 04 0.00E-01 4.44E 03 I Cs-134 6.51E 05 1.01E 06 2.25E 05 0.00E-01 3.30E 05 1.21E 05 3.85E 03 I co-136 6.51E 04 1.71E 05 1.16E 05 0.00E-01 9.55E 04 1.45E 04 4.18E 03 - Cs-137 9.07E 05 8.25E 05 A.28E 05 0.00E-01 2.82E 05 1.04E 05 3.62E 03-Cs-138 6.33E 02 8.40E 02 5.55E 02 0.005-01 6.22E 02 6.81E Ol' 2.70E 02 Ba-139 1.84E 00 9.84 5-04 5.36E-02 0.005-01 8.625-04 5.77E 03 5.77E 04 Be-140 7.40E 04 6.48E 01 4.33E 03 0.00E-01 2.llt 01 1.74E 06 1.02E 05 l Be-141 1.96E41 1.09E-04 6.36E-03 0.00E-01 9.475-05 2.92E 03 2.75E 02 l Be-142 4.99 E-02 3.60E-05 2.79E-03 0.00E-01 2.915-05 1.64E 03 2.74E 00 Le-140 6.44E 02 2.25E 02 7.5EE 01 0.00E-01 0.00E-01 1.83E 05 2.26E 05' La-142 1.29E 00 4.11E-01 1.295-01 0.00E-01 0.00D 01 8.70E 03 7.59E 04 4 Co-141 3.92E 04 1.95E 04 2.90E 03 0.005-01 8.55E 03 5.44E 05 5.66E 04. 1 Co-143 3.66E 02 1.99E 02 2.87E 01 0.00E-01 8.36E 01 -1.15E 05 1.27E 05 Ce-144 6.77E 06 2.12E 06 3.61E 05 0.00E-01 1.17E 06 1.20E 07 3.89E 05 i Pr-143 1.85E 04 5.55E 03 9.14E 02 0.00E-01 3.00E 03 4.33E 05 9.73E 04 ) Pr-144 5.96 E-02 1.85E-02 3.00E-0'3 0.00E-01 9.77E-03 1.57E 03 1.97E 02 1 l Nd-147 1.08E 04 8.73E 03 6.81E 02 0.005-01 4.81E 03 3.28E 05 8.21E 04 l W-187 1.63E 01 9.66E 00 4.33E 00 0.00E-01 0.00E41 4.11E 04 9.10E 04 NP-239 4.66E 02 3.34E 01 2.35E 01 0.00E-01 9.73E 01 5.81E 04 , 6,40E 04- 1
'i O
i A-10 Rev. 3
, 6/87
~
TABLE A.1-4' j IIMALATION PATWAY FAGTOR ~ I aren/yr per uC1/m3 l INFANT (Tg FAC M S) NUCLIDE BONE LIVER T BODY TifYROID KIDNEY IDC GI-LLI
'l H-3 0.00E-01 6.47E 02 6.47E 02 6.47E 02 6.47E 02 6.47E 02 6.47E 02 i C-14 2.65E 04 5.31E 03 5.31E 03 5.31E 03 5.31E 03 5.31E 03 5.31E 03 l Na-24 1.06E 04 1.06E 04 1.06E 04 1.06E 04 1.06E 04 1.06E 04 1.06E 04, P-32 2.03E 06 1.12E 05 7.74E 04 0.00E-01 0.00E-01 0.00E-01 1.61E 04 Cr-51 0.00E-01 0.00E4 1 8.95E 01 5.75E 01 1.32E 01 1.28E 04 3.57E 02 Ph-54 0.00E-01 2.53E 04 4.98E 03 0.00E-01 4.98E 03' l.00E 06 7.06E 03 Pb-56 0.00E-01 1.54E 00 2.21E-01 0.00E-01 1.10E 00 1.25E 04 7.17E 04 Fe-55 1.97E 04 1.17E 04 3.33E 03 0.00E-01 0.00E-01 8.69E 04 1.09E 03 Fe-59 1.36E 04 2.35E 04 9.48E 03 0.00E-01 0.00E-01 1.02E 06 2.48E 04 00-58 0.00E-01 1.22E 03 1.82E 03 0.00E-01 0.00E-01 7.77E 05 1.11E 04 Co-60 0.00E-01 8.02E 03 1.18E 04 0.00E41 0.00E-01 4.51E 06 3.19E 04 Ni-63 3.39E 05 2.04E 04 1.16E 04 0.005-01 0.00E-01 , 2.096 05 2.42E 03 Ni-65 2.39E 00 2.84E-01 1.23E-01 0.00E-01 0.00E-01 8.12E 03 5.01E 04 Cu-64 0.00E-01 1.8BE 00 7.74E-01 0.00E-01 3.98E 00 9.30E 03 1.50E 04 Zn-65 1.93E 04 6.26E 04 3.llE 04 0.00E-01 3.25E 04 6.47E 05 5.14E 04 Zn-69 5.39E-02 9'.67E-02 7.l'8E-03 0.00E-01 4.02E-02 1.47E 03 1.32E 04
_. Br-83 0.00E-01 0.00E-01 3.81E 02 0.00E-01 0.00E-01 0.00E-01 1.40E-15 l Br-84 0.00E-01 0.00E-01 4.00E 02 0.00E-01 0.00E-01 0.00E-01 1.40E-15 l Br-85 0.00E-01 0.00E-01 2.04E 01 0.00E-01 0.00E-01 0.00E-01 1.40E-15 l Rb-86 0.00E-01 1.90E 05 8.82E 04 0.00E-01 0.00E-01. 0.00E-01 3.04E 03 Rb-88 0.00E-01 5.57E 02 2.87E 02 0.00E-01 0.00E-01 0.00E-01 3.39E 02
'l Rb-89 0.00E-01 3.21E 02 2.06E 02 0.00E-01 0.00E-01 0.00E-01 6.82E 01 ,
Sr-89 3.98E 05 0.00E-01 1.14E 04 0.00E-01 0.00E-Ol 2.03E 06 6.40E 04 i Sr-90 4.09E 07 0.00E-01 2.59E 06 0.00E-01 0.00E-01 1.12E 07 1.31E 05 Sr-91 9.56E 01 0.00E-01 3.46E 00 0.00E-01' O.00E-01 5.26E 04 7.34E 04 Sr-92 1.05E 01 0.00E-01 3.91E-01 0.00E-01 0.00E-01 2.38E 04 1.40E 05 Y-90 3.29E 03 0.00E-01 8.82E 01 0.00E-01 0.00E-01 2.69E 05 1.04E 05
.A-11 .
Rev. 3 5/87
TABLE A.1-4 IttiALATION PATHWAY FACTOR mrem /yr per uC1/ # INFANT (T GFACTORS) T BODY 'DPIROID KIDNEY IDNG GI-ILI NOCLIDE BCNE LIVER _, Y-91M 4.07E-01 0.00E-01 1.39E-02 0.00E-01 0.00E-01 2.79E 03 2.35E 03 Y-91 5.88E 05 0.00E-01 1.57E 04 0.00-E01 0.00E-01 2.45E 06 7.03E 04 Y-92 1.64E 01 0.00E-01 4.61E-01 0.00E-01 0.00E-01 2.45E 04 1.27E 05 Y-93 1.50E 02 0.00E-01 4.07E 00 0.00E-01 0.00E-01 7.64E 04 1.67E 05 Zr-95 1.15E 05 2.79E 04 2.03E 04 0.00E-01 3.11E 04 1.75E 06 2.17E 04 Zr-97 1.50E 02 2.56E 01 1.17E 01 0.00E-01 2.59E 01 1.10E 05 - 1.40E 05
~
Nb-95 1.57E 04 6.43E 03 3.78E 03 0.00E-01 4.72E 03 4.79E 05 1.27E 04
* % 99
. 0.00E-01 1.65E 02 3.23E 01 0.00E-01 2.65E 02 1.35E 05 4.87E 04
.Te-99M 1.40E-04 2.88E-03 3.72E-02 0.00E-01 3.11E-02 8.11E 02 2.03E 03 6.51E-05 8.23E-65 8.12E-04 0.00E-41 9.79E-04 5.84E 02 8.44E 02 Tc-101 2.02E 03 0.00E-01 6.79E 02 0.00E-01 4.24E 03 5.52E 05 1.61E 04 Ra-103 4.84E 04
. Ru-105 1.22E 00 0.00E-01 4.10E-01 0.00E-01 8.99E-01 1.57E 04
\
Ru-106 8.68E 04 0.00E-01 1.09E 04 0.00E-01 1.07E 05 1.16E 07 1.64E 05 I Ag-110M 9.98E 03 7.22E 03 5.00E 03 0.00E-01 1.09E 04 3.67E 06 3.30E 84
'te-125M 4.76E 03 1.99E 03 6.58E 02 1.62E 03 0.00E-01 4.47E 05 1.29E 04 ,
Te-127M 1.67E 04 6.90E 03 2.07E 03 4.87E 03 3.75E 04 1.31E 06 2.73E 04
~
Te-127 2.23E 00 9.53E-01 4.89E-01 1.85E 00 4.86E 00 1.03E 04 2.44E 04 1.41E 04 6.09E 03 2.23E 03 5.47E 03 3.18E 04 1.68E 06 6.90E 04
, Te-129M Te-129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.00E 03 2.63E'04
'IW-131M 1.07E 02 5.50E 01 3.63E 01 8.93E 01 2.65E 02 1.99E 05 1.19E 05 1.74E-02 8.22E-03 5.00E-03 1.58E-02 3.99E-02 2.06E 03 8.22E 03
'!*-131 3.72E 02 2.37E 02 1.76E 02 2.79E 02 1.03E 03 3.40E 05 4.41E 04 Te-132 6.36E 03 1.39E 04 5.57E 03 1.60E 06 1.53E 04 0.00E-01 1.99E 03 I-130 .
1.06E 03 I-131 3.79E 04 4.44E 04 1.96E 04 1.48E 07 5.18E 04 0.00E-01 I-132 1.69E 03 3.54E 03 1.26E 03 1.69E 05 3.95E 03 0.00E-01 1.90E 03 I-133 1.32E 04 1.92E 04 5.60E 03 s3.56E 06 2.24E 04 0.00E-01 2.16E 03 I-134 9.21E 02 1.88E 03 6.65E 02 4'.45E 04 2.09E 03 0.00E-01 1.29E 03 A-12 Rev. 3 6/87
TABLE A.1-4 IltiALATkONPATHWAYFAGTOR O L - pren/yr r uCt/W INFANT (T FACTORS) 1 10CLIDE IDIE LIVER T EGN THY 1CID KIINEY IUNG GI-ILI I-135 3.86E 03 7.60E 03 2.77E 03 6.96E 05 8.47E 03 0.00E-01 1.83E 03 Co-134 3.96E 05 7.03E 05 7.45E 04 0.005-01 1.90E 05 7.97E 04 1.33E 03 Ca-136 4.83E 04 1.35E 05 5.29E 04 0.005-01 5.64E 04 1.18E 04 1.43E 03 Ca-137 5.49E 05 6.12E 05 4.55E 04 0.00E-01 1.72E 05 7.13E 04 1.33E 03 l Co-138 5.05E 01 7.81E 02 3.98E 02 0.005-01 4.10E 02 6.54E 01 8.76E 02 Be-139 1.48E 00 9.845-04 4.30 H 2 0.005-01 5.92E-04 5.95E 03 5.10E 04 Be-140 5.60E 04 5.60E 01 2.90E 03 0.00E-01 1.34E 01 1.60E 06 3.84E 04 Be-141 1.575-01 '1.08H4 4.97 H 3 0.005-01 6.50E-05 2.97E 03 4.75E 03 , sa-142 3.98H2 3.305-05 1.96E-03 0.00 H 1 1.90E-05 1.55E 03 6.93E 02 Ie140 5.05E 02 2.00E 02 5.15E 01 0.00 H 1 0.00 H 1 '1.685 05 8.48E 04 La-142 1.03E 00 3.775-01 9.045 0.005-01 0.00E-01 8.22E 03 5.95E 04 O Ce-141 2.77E 04 1.67E 04 '1.99E 03 0.005-01 5.25E 03 5.17E 05 2.16E 04 Co-143 2.93E 02 1.93E 02 2.21E 01 0.00 H 1 5.64E 01 1.16E 05 4.97E 04 Co-144 3.19E 06 1.21E 06 1.76E 05 0.00E-01 5.38E 05 9.84E 06 1.48E 05 Pr-143 1.40E 04 5.24E 03 6.99E 02 0.00E-01 1.97E 03 4.33E 05 3.72E 04 Pe-144 4.79E-02 1.855-02 2.41543 0.00E-01 6.725-03 1.61E 03 4.28E 03 145-147 7.94E 03 8.13E 03 5.00E 02 0.00E-01 3.15E 03 3.22E 05 3.12E 04 W187 1.30E 01 9.02E 00 3.12E 00 0.00 H 1 0.00E-41 3.96E 05 3.56E 04 Np-239 3.71E 02 3.32E 01 1.88E 01 0.00E-01 6.62E 01 5.95E 04 2.49E 04 D L. . . . - A-13 Rev. 3 6/87 88
TABLE A.2-1 GRASS-COW-MILK PATHWAY FACTOR f .m2. mrem /yr per uCi/see ADULT (TfFACTORS) l NtXLIDE IENE LIVER T 83W 'HfY1CID KIINEY IDG GI-ILI H-3 0.00E-01 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 C-14 2.63E 08 5.27E 07 5.27E 07 5.27E 07 5.27E 07 5.27E 07 5.27E 07 Na-24 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 4 P-32 1.71E 10 1.06E 09 6.60E 08 0.00E-01 0.00E-01 0. 00E-01 1.92E 09 l Cr-51 0.00E-01 0.00E-01 2.86E 04 0.00E-01 6.30E 03 3.79E 04 7.19E 06 i Mm-54 0.00E-01 8.41E 06 1.61E 06 0.00E-01 0.005-01 0.00E-01 2.58E 07 Ph-56 0.00E-01 4.16E-03 7.38E-04 0.00E-01 5.28E-03 0.00E-01 1.33E-01 Fe-55 2.51E 07 1.73E 07 4.04E 06 0.00E-01 0.00E-01 9.67E 06 9.95E 06 Fe-59 2.97E 07 6.98E 07 2.68E 07 ,0.00E-01 0.00E-01 1.95E 07 2.33E 08 00-58 0.00E-01 4.71E 06 1.06E 07 0.00E-01 0.00E-Ol 0.00E-01 9.56E 07 C0-60 0.00E-01 1.64E 07 3.62E 07 0.00E-01 0.00E-01 0.00E-01 3.08E 08 Ni-63 6.73E 00, 4.71E 08 2.26E 08 0.00E-01 0.00E-01 0.00E-01 9.73E 07 O Ni-65 4.63E-01 6.02E-02 2.75E-02 0.00E-01 0.00E-01 0.00E-01 1.53E 00 Co-64 0.00E-01 2.39E 04 . 1.12E 04 0.00E-01 6.02E 04 0.00E-01 2.03E 06 2n-65 1.37E 09 4.37E 09 1.97E 09 0.00E-01, 2.92E 09 0.00E-01 2.75E 09 l 2n-69 5.22E-12 9.99E-12 6.95E-13 0.00E-01 6.49E-12 0.00E-01 1.50E-12 Be-83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Be-84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 B*-85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Ro-86 0.00E-01 2.59E 09 1.21E 09 0.00E-01 0.00E-01 0.00E-01 5.12E 08 Rt>-88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-89 0.00E-01 0.00E-01 b.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 St-89 1.45E 09 0.00E-01 4.16E 07 0.00E-01 D.00E-01 0.00E-01 2.33E 08 Sr-90' 4.68E 10 0.00E-01 1.15E 10 0.00E-01 0.00E-01 0.00E-01 1.35E 09 Sr-91 2.87E 04 0.00E-01 1.16E 03 0.00E-01 0.00E-01 0.00E-01 1.37E 05 Sr-92 4.90E-01 0.00E-01 2.12E-02 0.00E-01 0.00E-01 '0.00E-01 9.70E 00 Y-90 7.07E 01 0.00E-01 1.90E 00 0.00E-01 0.00E-01 0.00E-01 7.50E 05 ( A-14 Rev. 3 6/87 E
TABLE A.2-1 . GRASS-COW-MILK. PATHWAY FACTOR l-3 m2.aren/yr per uC1/sec ADULT (TG FACTORS) NDCLIDE BONE LTVER T IKI2Y '!NYROID KIDNEY , __, IDNG GI-LLI Y-91M 6.035-20 0.00E-01 2.34F21 0.005-01 0.005-01 0.005-01 1.775-19 Y-91 8.59E 03 0.000-01 2.30E 02 0.00>01 0.00F01- 0.00601 4.73E 06 Y-92 5.59845 0.00E-01 1.63E-06, 0.005-01 0.005-01 0.005-01 9.79E-01 Y-93 2.33E-01 0.00E-01 6.44h03 0.005-01 0.005-01 0.005-01 7.39E 03 Er-95 9 44E 02 3.03E 02 2.05E 02 0.005-01 4.75E 02 0.005-01 9.59E 05 3ra 97 4.33h01 8.75E-05 4.00E-02 0.005-01 1.32>01 0.005-01 2.71E 04 lb-95 8.26E 04' 4.59E 04. 2.47E 04 0.00E-01 4.54E 04 0.00E-01 2.79E 08 ft>-99 0.00E-01 2.48E 07 4.71E 06 0.00E-01 5*.61E 07 0.00E41 5.74E 07
'!b-99M 3.33E 00 9.40E 00 1.20E 02 0.00F01 1.43E 02 4.60E 00 5.56E 03 To-101 0.00E41 0.00E-01 0.00E-01 0.00E-01 0.00E 0.00E-01 0.00E-01 Ru-103 1.02E 03 0.00E-01 4.38E 02 0.00E41 3.A8E 03 0.005-01 1.19E 05 Ru-105 8.58E44 0.00E-01 3.39E-04 0.00E-01 1.11E-02 0.005-01 5.25E-01 Ru-106 2.04E 04 0.00E-01 2.58E 03 0.00E-01 3.94E 04 0.00601 1.32E 06 G4 Aq-110M 5.82E 07 5.39E 07 3.20E 07 0.00E-01 1.06E 08 0.005-01 2.20E 10 Te-125M 1.63E 07 5.90E 06 2.18E 06 4.90E 06 6.63E 07 0.00>01 6.50E 07 Te-127M 4.58E 07 1.64E 07 5.58E 06 1.17E 07 1.86E 08 0.005-01 1.54E 08 I Te-127 6.54E 02 2.35E 02 1.41E 02 4.84E 02 2.66E 03 0.00E-01 5.16E 04 l
~
Te-129M 6.02E 07 2.25E 07 9.53E 06 2.07E 07 2.51E 08 0.00E-01 3.03E 08
. Te-129 2.845-10 1.07E-10 6.29E-11 2.18E-10 1.19E49 0.005-01 2.14E-10 ,
Te-131M 3.61E 05 1.77E 05 1.47E 05 2.80E 05 1.79E 06 0.~005-01 1.73E 07 Te-131 3.67 E-33 1.53E-33 1.16 F33 3.015-33 1.61 632 0.005-01 0.00E-01 Te-132 2.40E 06 1.55E 06 1.46E 06 1.72E 06 . 1.50E 07 0.00>01 7.35E 07 I-130 4.20E 05 1.24E 06 4.89E 05 1.05E 08 1.94E 06 0.00E-01 1.07E 06' I-131 2.96E 08 4.24E 08 2.43E 08 1.39E 11 7.26E 08 0.005-01 1.12E 08 4
.I-132 1.65E41 4.41E-01 1.54 E-01 1.54E 01 7.02E-01 0.00E41 8.28E-02 I-133 3.87E 06 6.73E 06 2.05E 06 9.90E 08 1.18E 07 0.00E-01 6.05E 06 -
I-134 2.03 E-12 5.52E-12 1.98E-12 9.57E-11 8.78 E-12 0.00E-01 4.81E-15 A-15
- Rev. 3
. 6/87
TABl.E A.2-1 i GRASS-COW-MILK PATHWAY FACTOR m2.mram/yr per uCl/sec {, ADULT (Tg FACTORS) PUC2JDE BCNE LIVER T ICDY '!!r/ROID KIDNEY IDG GI-ILI I-D5 1.29E 04 3.37E 04 1.24E 04 2.22E 06 5.40E 04 0.00E-01 3.80E 04 Cs-134 5.65E 09 1.35E 10 1.10E 10 0.00 >01 4.35E 09 1.45E 09 2.35E 08 Co-D6 2.61E 08 1.03E 09 7.42E 08 0.00E-01 5.73E 08 7.86E 07 1.17E 08 l Cs-D7 7.38E 09 1.01E 10 6.61E 09 0.00E-41 3.43E 0'9 1.14E 09 1.95E OS i Cs-138 9.16E-24 1.81E-23 8.97E-24 0.00E-01 1.33E-23 1.31E-24 7.72E-29
.Ba-139 4.56 E-08 3.25E-11 1.34 E-09 0.00E-01 3.04E-11 1.84E-11 8.09E-08 Be-140 2.69E 07 3.38E 04 1.76E 06 0.00E-01 1.15E 04 1.93E 04 5.54E 07 Be-141 0.00E41 0.00E-01 0.00E-01 0 00E-01 0.00E-01 0.00E-01 0.00E-01 pe-142 0.00E-01 0.00E-01 0.00E-01 0.00E-41 0.00F01 0.00E-01 0.00E-01 Im-140 4.52E 00 2.28E 00 6.025-01 0.005-01 0.00E-01 0.00E-01 I.67E 05 La-142 9.39 5-12 4.276 12 1.06E-12 0.00&Ol- 0.005-01 0.00E-01 3.12E-08 4.84E 03 3.28E 03 Ce-141 3.72E 02 0.00E-01 1.52E 03 0.00E-01 1.25E 07 Ce-143 4.16E 01 3.07E 04 3.40E 00 0.505-01 1.35E 01 0.00E-01 4 1.15E 06 Ce-144 3.58E 05 1.50E 05 1.92E 04 0.00E-01 8.87E 04 0.00E-01 1.21E 08 . _ _ Pr-143 1.58E 02 6.33E 01 7.83E 00 0.00E-01 3.66E 01 0.00E-01 6.92E 05 Pr-144 0.00E41 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 N6-147 9.46E 01 1.09E 02 6.55E 00 0.00E-01 6.40E 01 0.00E-01 5.25E 05 W-lS7 6.56E 03 5.49E 03 1.92E 03 0.00E-01 0.00E-01 0.00E-01 1.80E 06 Np-239 3.67E 00 3.61E-01 1.99 E-01 0.00E-01 1.D E 00 0.00E-01 7.41E 04 WIP A-16 Rev. 3 6/87
' TABLE A02-2 l GRASS-COW-MILK PATHWAY FACTOR m2c.mram/yr' per uCl/sec TEEN (Tg FACTORS)
NUCLIDE BONE LIVER T BCEE 'DfYBOID KIDNEY 11NG GI-ILI H-3 0.00E-01 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 C-14 4.86E 08 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 Na-24 4.26E 06 4.26E 06 4.26E 06 4.26E 06 , 4.26E 06 4.26E 06 4.26E 06 P-32 3.15E 10 1.95E 09 1.22E 09 0.005-01 0.00E-01 0.00E-01 2.65E 09 Cr-51 0.00E-01 0.00E-01 4.99E 04 2.77E 04 1.09E 04 7.13E 04 8.39E 06
> 54 0.00E-01 1.40E 07 2.78E 06 0.00Fr01 4.18E 06 0.00E-01 2.87E 07 i
Mv-56 0.00E-01 7.37E-03 1.31E-03 0.00E-01 9.33E-03 0.00E-01 4.85E-01 ) FW-55 4.45E 07 3.16E 07 7.36E 06 0.00E-01 0.00E-01 2.00'E 07 1.37E 07 I I Fe-59 5.18E 07 1.21E 08 4.67E 07 0.00E-01 0.00E-01 3.81E 07 2.86E 08 Co-58 0.00E41 7.94E 06 1.83E 07 0.00E-01 0.00E-01 0.00E-01 1.09E 08 00-60 0.00E-01 2.78E 07 6.26E 07 0.00E-01 0.00E-01 0.00E-01 3.62E 08 Ni-63 1.18E 10 8.35E 08 4.01E 08 0.00E-01 0.00E-01 0.00E-01 L33E 08 Ni-65 8.48E-01 1.08E-01 4.94E-02 0.00E-01 0.00E-01 0.00E-01 5.88E 00 1 Co-64 0.00E-01 4.25E 04 2.00E 04 0.00E-01 1.08E 05 0.00E-01 3.30E 06 ; Zn-45 2.llE 09 7.31E 09 3.41E 09 0.00E-01 4.68E 09 0.00E-01 3.10E 09 j Zn-69 9.62E-12 l'.83E-ll 1.28E-12 0.00E-01 1.20E-ll 0.00E-01 3.38E-11 , Br-83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 !
~~
Br-84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 4 0.00E41 0.00E-01 Br-85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Bb-86 0.00E41 4.73E 09 2.22E 09 0.00E 01 0.00E-01 0.00E-01 7.00E 08 Rb-88 0.,00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 Rb-89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-89 2.67E 09 0.00E-01 7.66E 07 0.00E-01 0.00E-01 0.00E-01 3.19E 08 Sr-90 6.61E 10 0. 00E.-01 1.63E 10 0.00E-01 0.00E-01 0.00E-01 1.86E 09 Sr-91 5.27E 04 0.00E-01 2.10E 03 0.00E-01 0.00E-01 0.00E-00 2.39E 05 Sr-92 8.96E-01 0.00E-01 3.82E-02 0.00E-01 0.00E-01 0.00E-00 2.28E 01 Y-90 1.30E 02 0.00E-01 3.50E 00 0.00E-01 0.00E-01 0.00E-00 1.07E 06 i A-17 Rev. 3
, 6/87
TABLE A.2-2 l GRASS-COW-MILK PATHWAY FACTOR-m2.aram/yr nr uCl/sec TEEN (TG ACTORS) NUCLIDE BCNE LIVER T BODY 'Dft1CID ' KIDNEY IDG _ GI-LLI
~
Y-91M 1.llE-19 0.00 F01 4.22F21 0.00E-01 0.00F01 0.00E-01 5.22E-18 1.58E 04 0.00E-01 4.24E 02 0.00541 0.005-01 0.00E-01 6 48E 06 Y-91 1.03 E-04 0.00E-01 2.99E-06 0.00E-01 0.00 F01 0.00 F01 2.83E 00 Y-92 4.30E-01 0.00E-01' 1.18E-02 0.005-01 0.005-01 0.00E-01 1.31E 04 Y-9'3 1.65E 03 5.21E 02 3.58E 02 0.005-01 7.65E 02 0.00E-01 1.20E 06 Er-95 7.89E41 1.56E-01 7.19E-02 0.00E-01 2.375-01 0.00E-01 4.23E 04 Er-97 , Nb-95 l'.41E 05 7.81E 04 4.30E 04 0.00E-01 7.57E 04 0.00E-01 3.34E 08 Mo-99 0.00E-01 4.47E 07 8.53E 06 0.00E-01 1.02E 08 0.00E-01 8.01E 07 Tc-99M 5.77E 00 1.61E 01 2.08E 02 0.00E-01 2.40E 02 8.93E 00 1.06E 04 l Te-101 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1 Ru-103 1.81E 03 0.00E-01 7.74E 02 0.00E-01 6.38E 03 0.00E-01 1.51E 05 ) Ru-105 1.57E-03 0.00E-01 6.08E-04 0.00E-01 1.98E-02 0.00E-01 1.27E 00 4.73E 03 0.00E-01 7.23E 04 0.00E-01 -1.80E 06 ! Ru-106 3.75E 04 0.00E-01 Ag-110M 9.63E 07 9.llE 07 5.54E 07 0.00E-01 1.74E 08 0.00E-01 2.56E 10 Te-125M 3.00E 07 1.08E 07 4.02E 06 8.39E 06 0.00E-01 0.00E-01 8.86E 07 Te-127M 8.44E 07 2.99E 07 1.00E 07 2.01E 07 3.42E 08 0.00E-01 2.10E 08 Te-127 1.21E 03 4.29E 02 2.61E 02 8.36E 02 4.91E 03 0.00E-01 9.35E 04 Te-129M 1.10E 08 4.09E 07 1.74E 07 3.55E 07 4.61E 08 0.00E-01 4.13E 08 Te-129 5.23E-10 1.95E-10 1.27E-10 3.74E-ld 2.20E-09 0.00E-01 2.86E-09 Te-131M 6.57E 05 3.15E 05 2.63E 05 4.74E 05 3.29E 06 0.00E-01 2.53E 07 Te-131 6.70E-33 2.76E-33 2.09E-33 5.16E-33 2.93E-32 0.00E-01 5.50E-34 Te-132 4.29E 06 2.72E 06 2.56E 06 2.87E 06 2.61E 07' O.00E-01 8.61E 07 I-130 7.39E 05 2.14E 06 8.54E 05 1.74E 08 3.26E 06 - 0.00E-01 1.64E 06 I-131 5.37E 08 7.52E 08 4.04E 08 2.20E 11 1.30E 09 0.00E-01 1.49E 08 ) I-132 2.92E-01 7.65E-01 2.74 E-01 2.58E 01 1.20E 00 0.00E-01 3.33E-01 ; I-133 7.07E 06 1.20E 07 3.66E 06 1.67E 09 2.10E 07 0.00E-01 9.0RE 06 I-134 3.61E-12 9.58E-12 3.44E-12 1.6DE-10 1.51E-11 0.00E-01 1.26E-13 e A-I8 Rev. 3 6/87 l
TABLE A.2-2 GRASS-COW-MILK PAINWAY FACTOR m2.mram/yr per uC1/see hs TEEN (T g! FACTORS) . NUCLIDE BWE LIVER T BODY TETICID KIDNEY LONG GI-LLI
~
I-135 2.28E 04 5.88E 04 2.18E 04 3.78E 06 9.28E 04 0.00bO1 6.51E 04 Cs-134 9.82E 09 2.31E 10 l'07E
. 10 0.00E 41 7.34E 09 2.80E 09 2.87E 08 Cs-136 4.44E 08 1.75E 09 1.17E 09 0.00601 9.52E 08 1.50E 08 1.41E 08 Cs-137 1.34E 10 1.78E 10 6.20E 09 0.00E-01 6.06E 09 2.35E 09 2.53E 08 Cs-138 1.66E-23 3.19E-23 1.60E-23 0.005-01 2.36 523 2.74E-24 1.45E-26 ,
Ba-139 8.445-08 5.945-11 2.465-09 0.005-01 5.605-11 4.09E-11 7.535-07 Ba-140 4.85E 07 5.95E 04 3.13E 06 0.005-01 2.02E'04 4.00E 04 7.48E 07 i Ba-141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.QDE-01 0.00E-01 ! Ba-142 0.00E-01 0.00E-01 0.005-01 0.005-01 0.00>01 0.00E-01 0.00E-01 l La-140 8.12E 00 3.99E 00 1.06E 00 0.00E-01 0.00541 0.005-01 2.29E 05 !' La-142 1.695-11 7.525-12 1.87E-12 0.00E-01 0.00>01 0.00E41 2.29E-07 O Co-141 8.88E 03 5.93E 03-6.81E 02 0.005-01 2.79E 03 -0.00E-01 1.70E 07 l Ce-143 7.64E 01 - 5.56E 04 ' 6.21E 00 0.00E-01 2.49E 01 0.00E-01 1.67E 06 Co-144 6.58E 05 2.72E 05 3.54E 04 0.00E-01 1.63E 05 0.00E-01 1.66E 08 1 Pr-143 2.90E 02 1.16E 02 1.44E 01 0.005-01 6.73E 01 0.00F01 9.55E 05 Pr-144 0.00E41 0'.00E-01 0.00E-01 0.005-01 0.005-01 0.00E-01 0.00E-01 l
'N6-147 1.82E 02 1.98E 02 1.19E 01 0.00E-01 1.16E 02 0.00E-01 7.15E 05 W-187 1.20E 04 9.78E 03 3.43E 03 0.00>01 0.005-01 0.00E-01 2.65E 06 Np-239 7.01E 00 6.61E-01 3.67E-01 0.00E-01 2.07E 00 0.00E-01 1.06E 05 A-19' Rev. 3 6/87
TABLE A.2-3 GRASS-COW-MILK PATHWAY FACTOR m2.mram/yr per uC1/sec CHILD (Tg FACTORS) NOCI.TDE BONE LIVER T BCDY TWtlOID KIDNEY WNG CI-LI.I H-3 0.00 E-01 1.57E 03, 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 C-14 1.19E 09 2.39E OS 2.39E 08 2.39E 08 2.39E 08 2.39E 08- 2.39E 08 Na-24 8.86E 06 8.86E'06 8.86E 06 8.86E 06 8.86E 06 8.86E 06 8.86E 06 , p-32 7.77E 10 3.64E 09 3.00E 09 0.00E-01 0.00 H 1 0.00E-01 2.15E 09 Cr-51 0.0E-01 0.00E-41 1.02E 05 5.65E 04 1.54E 04 1.03E 05 5.40E 06 Mrt-54 0.00 E-Cl 2.10E 07 5.59E 06 0.00E-01 5.885 06 0.005-01 1.76E 07 19t-56 0.00 E-01 1.29E-02 2.90E-03 0.00E-01 1.56E-02 0.00E-01 1.86E 00 . Fe-55 1.12E 08 5.93 E07 1.84E 07 0.00E-01 0.00E-01 3.35E 07 1.10E 07 Fe-59 1.20E 08 1.94E 08 9.69E 07 0.00E-01 0.00E-01 5.64E 07 2.02E 08 Co-58 0.00E-01 1.21E 07 3.71E 07 0.00E-01 0.005-01 0.00E-01 7.07E 67 CMO 0.00 E-41 4.32E 07 1.27E 08 0.00E-01 0.005-01 0.00E-01 2.39E 08 Ni-63 2.96E 10 1.59E 09 ' 1.01E 09 0.00E-01 0.00E-01 0.00E-01 1.07E 08 Ni-65 2.07E 00 1.95E-01 1.14E-01 0.00E-01 0.005-01 0.00E-01 2.39E 01 Cu-64 0-00 E-01 7.47E 04 4.51E 04 0.00E-01 1.81E 05 0.00E-01 3.51E 06 t 2rt-65 4.13E 09 1.10E 10 6.85E 09 0.00E-01 6.94E 09 0.00E-01 1.93E 09
~
Ert-69 2.36 E-11 3.42E-11 3.16E-12 0.00E-01 2.07E-11 0.00E-01 2.15E-09 Br-83 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Br-84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00 E-01 0.00E-01 0.00E-01 Br-85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-86 0.00E-01 8.77E 09 5.39E 09 0.00E-01 0.00E-01. 0.00E-01 5.64E 08 Rb-88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-89 6.62E 09 0.00E-01 1.89E 08 0.00E-01 0.00E-01 0.00E-01 2.56E 08 Sr-90 1.12E 11 0.00E-01 2.83E 10 0.00E-01 0.00E-01 0.00E-01 1.50E 09 Sr-91 1.29E 05 0.00E-01 4.88E 03 0.00E-01 0.00E-01 0.00E-01 2.85E 05 Sr-92 2.19E 00 0.00E-01 8.78E-02 0.00E-01 0.00E-01 0.00E-01 4.15E 01 ; Y-90 3.22E 02 0.00E-01 8.61E 00 0.00E-01 0.00E-01 0.00E 9.15E 05 i A-20 Rev. 3 6/87
TABLE A.2-3 : p GRASS-COW-MILK PATHWAY FACTOR
- m2.mram/yr per uC1/sec i CHILD (Tg FACTORS)' ;
. 3 NUCLIDE BONE LIVER T BODY , THYROID ' KIDNEY IUNG GI-LLI Y-91M 2.705-19 0.00E-01 9.82E-21 0.008H01 0.005-01 0.005-01 5.295-16 Y-91 3.90E 04 0.00E-01 1.04E 01 l0.003-01 0.005-01 0.00E-01 5.20E 06 Y-92 2.54E-04 0.00E-01 7.265-06 0.005-01, 0.005-01 0.00E-01 7.33E 00
, Y-93 1.06E 00 0.00E-01 2.90E-02 0.005-01 0.00E-01 0.005-01 1.57E 04 Er-95 3.83E 03 8.43E 02 7.50E 02 0.00E-01 1.21E 03 0.005-01 8.7S5 05 Er-97 1.92E 00 2.77E-01 1.64E-01 0.005-01 3.98E-01 0.005-01 4.20E 04 Nt>-95 3.18E 05 1.24E 05 8.85E 04 0.005-01 1.16E 05 0.005-01 2.29E 08 I Mc>-99 0.00E-01 8.14': 07 2.01E 07' O.00E-01 1.74E 08 0.00E-41 6.73E 07 Tb-99M 1.32E 0,1 2.59E 01 4.30E 02 0.005-01 3.77E 02 '1.32E 01 1.48E 04 Tc-101 0.00E-01 0.00E-01 0.00E-01. 0.00E-Cl 0.00E*01 0.00E-01 0.00E-01 l Ru-103 4.28E 03 0.00E-01 1.65E 03 0.00E-01' 1.08E'04 0.00E-01 1.11E 05 m-105 3.83E-03 0.00E-01 1.39E-03 0.00E-01 3.36E-A2 0.00E-01 2.50E 00 7 Ru-106 9.24E 04 0.00E-01~ 1.15E 04 0.00E-01 1.25E 05' O.00E-01 -1.,44E 06 I Ag-110M 2.09E 08 1.41E 08 1.13E 08 0.00E-01 2.63E 08 0.00E -01 1.68E 10 ! Te-125M 7.38E 07 2.00E 07 9.84E 06 2,.07E 07 0.00E-01 0.00E-01 7.12E 07 1 Te-127M 2.08E 08 5.60E 07 2.47E 07 4.97E 07 5.93E 08 0.00E-01 1.68E 08 Te-127 2.98E 03 8.03E 02 6.39E 02 2.06E 03 8.47E 03 0.00E-01 1.16E 05 Te-129M 2.71E 08 7.58E 07 2.54E,07 8.75E 07 7.97E 08 0.00E-01 3.31E 08
- l
. l
. L
. Te-129 1.29E-09 3.60E-10 3.06E-10 9.21E-10 3.7&E49 0.00E-01 8.03E-08 )
Te-131M 1.60E 06 5.53E 05 5.89E 05 1.14E 06 5.36E 06 ' O.00E-01 2.24E 07 Te-131 1.64E,-32 '5.01E-33 4.89E-33 1.26E-32 4.975-32 3.00E-01 8.64E-32 4 h-132 1.02E 07 4.54E 06 5.48E 06 6.61E 06 4.21E 07 < 0.00E-01 4.57E 07 I-130 1.73E 06 3.49E 06 1.60E 06 3.85E 08 5.22E 06 't.00E-01 1.63E 06 I-131 1.30E 09 1.31E 09 7.45E 08 4.33E 11 2.15E 09 0.00E-01 1.17E 08 I-132 6.91E-01 1.27E 00 5.84E-01 5.89E 01- 1.94E 00 0.00E-01 1.49E 00 I-133 1.72E 07 2.12E 07 8,04E 06 3.95E 09 3.54E 07 0.00E-01~ 8.56E 06 I-134 8.55E-12 1.59E-11 7.31E-12 3.65E-10 2.43E-11 0.00E-01 1.05E-11 e ; A-21 '
.Rev 3 6/87
.---.----_.x-.---.---_wm, -__ _ _ _ _ _
e , . . . . - - . . . . -
;.. --;,r -
, t
- y j
' [' GRASS-COW-MILK PATHWAY FACTOR' V 2.nrem/yr per uCi/sec .
)
CHILD (Tg FACTORS) i l n ; t o , y
,, 4 NUCLIDE BCC LIVER ' T BODY MID KIDNEY IING GI-LLI
' I-135 5.413 C1 9.73E 04 4.60E 04 8.62E,06 1.49E 05 0.00E-01 7.41E 04 Cs-134 2.27E 10 3.72E 10 7.84E 09 0.00E-01 1.15E 10 4.13E 09 2.00E 08 Ca-136 1.00E 09 2.76E 09 1.78E 09 0.00E-01 1.47E 09 2.19E 08 9.69E 07 *
)
Cs-l'37 3.22E 10 3.09E 10 4.55E 09 0.00E41 '1 01E 10
. 3.62E 09 1.93E 08 Cs-138 4.03E-23 5.60E-23 3.55E-23 0.00L'-01 3.94E-23 4.24E-24 2.58E-23 Ba-137 4 2.07E-07 1.11E-10 6.01E-09 0.00E-01 9,67E-11 6.51E-11 1.20E-05
. . Y-l Sa-140 1;17E 08 1.03E 05 6.84E 06 0.00E-01 3/?4'I 04 6.12E 04 5.94E 07 l l Ba-141 ,/0.00E-01 0.00E-01 0.00E-01 0.00E-01 - 0.00E-01 0.00E-01 0.00E-01 !
Ba-142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 La-140 1.94E 01 6.80E 00[ 2.29E 00 0.00E-01 0.00E-01 % 00E-01 1.89E 05 i La-142 4.09E-11 1.30E 4.08E-12 0.00E-01 0.00T-01 c.00E-01 2.58E-06. Ce-141 2.198 04 1.Q9% 04 1.62E 03 0.00E-01 4.78E 03 0.00E-01 1.36E 07 o
' i
~
Ce-143 1.88E 02 1.02E 05 1.47E 01 0.00E-01 4.27E 01 0.00E-01 1.49E 06 .' Ce-144 .1.62E 06 5.09E 05 8.66E 04 ' l.00E- 01 2.82E 05 0.00E-01 1.33E 08 Pr-143 7.18E G2 2.16E 02 3.56E 01 0.00E-01 1.17E 02 0.00E-01 7.75E 05
? ?
Pr-144 0.00E-01 0.50E-01 0.002-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01
. Nd-147 4.47E 02 '3.62E 02. 2.8cE 01 0.00E-01 1.99E 02 0.00E-01 5.73E 05 W-187 . 2.91E 04 1.72E 04 7.73E D3 0.00E-01 0.00E-01 0.00E-01 2.42E 06 Np-239 1.72E 01 1.24E 00 8.70E-01 0.00E-01 3.58E 03 0.00E-01 9.16E 04
,. k' -
t : l.- P I s 4 3 t (- 5
, A-22 - J
< s ,
Rev. 3 6/87 l l
TABLE A.2-4 GRASS-COW-MILK PATHMAY FACTOR , m2.c. rem /,yn per uC1/sec , I INFANT (Tg FACT.0R~,) l 17JCLIDS BCNE LIVER T BODY TUCD.' KIDNEY LtRG GI-LLI j H-3 0.00E-01 2.38E 03 2.38E 03 2.38f,03 2.38E 03 2.83E 03 2.83E 03 C-14l 2.34E 09 5.00E 08 5.00E 08 5.00E 00 5.00E 08 5.00E 08 5.00E 08 i Na-24 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 j l i P-32 1.60E 11 9.42E 09 6.21E 09 0.00E-01 0.00E-01 0.00E-01 2.17E 09 cr-51 0.00 E-01 0.0.0E-01 1.GlE 05 1.05E 05 2.30E 04 2.05E 05 4.70E 06
.9n-54 0.00E-01 3 JOE 07 8.841 06 0.00E-01 8.64E 06 0.00E-01 1.43E,07 Mn-56 0.00E-01 3.15E-02
- 5.43E-03 0.00E-01 2.71E-02 0.00E-01 2.86E 00 Fe-55 1.35E 06 8.72E 07 2.33E 07 0.00E-01 0.00E-01 4.26E 07 1.llE 07 ,
Fe-59 2.24t 08 3.92E 08 1.54E 08 0.00E-01 0.00E-01 1.16E 08 1.87E 08 Co-58 0.00 E-01 2.43E 07 6.05E 07 0.00E-01 0.00E-01 0.00E-01 6.04E 07
' Co-60 0.00 E-41 S.82E 07 2.08E 03 0.00E-01 0.00E-01 0.00E-01 2.10E 08 Ni-63 3.49E 10 2.16E 09 1.?lE 09 0.00E-01 0.00E-01 0.00E-01 1.07E 08 1
Ni-65 4.39E 00 4.97E 01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 3.78E 01 Cu-64 0.00E 01 1.86E 05 8.60E 04 0.00E-01 3.14E 05 0.00E-01 3.81E 06 Zn-65 5.55E 09 1.90E 10 8.78E 09 0.00E-01 9.23E 09 0.00E-01 1.61E 10 Zn-69 5.04 E-11 9.07E-ll 6.75 E-12 0.00E-01 3.77 E-11 0.00E-01 7.40E-09
. .Br-93 0.00 E-01 0.00E- 01 0.00E-01 0.00E-01 0.00 E-01 0.00E-01 0.00E-01 3r-34 0.00E41 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Br-95 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-86 0.00 E-01 2.23E 10 1.10E 10 0.00E-01 0.00E-01 0.00E-01 5.70.E 08
- Pl>-88 0.00 E-Ol 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-89 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-89 1.26 E 10 0.00E-01 3.61E 08 0.00E-01 0.00E-01 0.00E 2.59E 08 Sr-90 1.22E 11 0.00E-01 3.10E 10 0.00E-01 0.00E-01 0.00E-01 1.52E 09 Sr-91 2.69E 05 0.00E-01 9.75E 2 0.00E-01 0.00E-01 0.00E-01 3.19E 05 Sr-92 4.66E 00 0.00E-01 1.73 E-01 0.'J0E-01 0.00E-01 0.00E-01 5.02E 01 '
Y-90 6.80E 02 0.00E-01 1.82E 01 0.00E-01 0.00E-01 0.00E-01 9.39E 05 k TN3 Rev. 3 6/87
=q mou A.e-4 GRASS-COW-MILK PATHWAY FACTOR i
, m2.mram/yr per uC1/sec j INFANT (Tg FACTORS) jpLCLIDE BONE IJVER T BODY 'DfYICID KID @f _ IRC GI-ILI Y-91M 5.72E-19 0.00E-01 1.95E-20 0.00E-01 0.00E-01 0.00E-01 1.91E-15 Y-91 ,7.33E 04 0.00E-01 1.95E 03 0'.00El-0 0.00E-01 0.00E-01 5.25E 06 Y-92 5.39E-04 0.00E-01 1.51E-05 0.00E-01 0.00E-01 0.00E-01 1.03E 01 Y-93 2.25E 00 0.00E-01 6.13E-02 0.00E-01 0.00E-01' O.00E-01 1.78E 04 2r-95 6.81E 03 1.66E 03 1.18E 03 0.005-01 1.79E.03 0.00E-01 8.26E 05 2r-97 4.06E 00 6.98E-01 3.19E-01 0.005-01 7.03E-01 0.00E-01 4.45E 04 W95 5.94E 05 2.45E 05 1.41E 05 0.00E-01 1.75E 05 0.00'E-01 2.06E 08 i Mo-99 0.00E41 2.08E 08 4.06E 07 0.00E-01 3.llE 08 0.00E-01 6.85E 07 Te-99M 2.75E 01 5.68E 01 7.31E 02 0.00E-01 6.11E 02 2.97E 01 1.65E 04 i
To-101 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Ru-103 8.67E 03 0.00E-01 2.90E 03 0.00E-01 1.80E 04 0.00E-01 1.05E 05 3 Ru-105 8.07 E-03 0.00E-01 2.72E-03 0.00E-01 5.93 E42 0.00E-01 3.21E 00 Ru-106 1.90E 05 0.00E-01 2.38E 04 0.00E-01 2.25E 05 0.00E-01 1.44E 06 ; Ag-110M 3.86E OC 2.82E 08 1.86E 08 0.0.0E-01 4.03E 08 0.00E-01 1.46E 10 l Te-125M 1.51E 08 5.04E 07 2.04E 07 5.07E 07 0.00E-01 0.00E-01 7.18E 07 ~ Te-127M 4.21E 08 1.40E 08 5.10E 07 1.22E 08 1.04E 09 0.00E-01 1.70E 08 Te-127 6.32E 03 2.12E 03 1.36E 03 5.15E 03 1.54E 04 ' O.00E-01 1.33E 05 Te-129M 5.57E 08 1.91E 08 8.58E 07 2.14E 08 1.39E 09 0.00e-01 3.33E 08 1
. Te-129 2.74 E-09 9.43E-10 6.39E-10 2.29E 09 6.81E-09 0.00E-01 2.19E-07 1 Te-131M 3.38E 06 1.36E 06 ' l.12E 06 2.76E 06 9.36E 06 0.00E-01 2.29E 07 Te-131 3.49 E-32 1.29E-32 9.7BE-33 3.115-32 8.915-32 0.00E-01 1.41E-30 Te-132 2.11E 07 1.05E 07 9.75E 06 1.54E 07 6.53E 07 0.00E-01 3.87E 07 I-130 3.55E 06 7.81E 06 3.14E 06 8.76E 08 8.58E 06 0.00E-01 1.68E 06 3 I-131 2.72E 09 3.21E 09 1.41E 09 1.05E 12 3.74E 09 0.00E-01 1.14E 08 1
I-132 1.43E 00 2.91E 00 1.04E 00 1.37E 02 3.25E 00 0.00E-01 2.36E 00 I-133 3.63E 07 5.2BE 07 1.55E 07 9.61E 09 6.21E 07 0.00E-01 8.94E 06 I-134 1.77E-11 3.63E-ll 1.29E-11 8.47E-10 4.06 E-11 0.00E-01 3.76E-11 , l e A.24 4
. Rev. 3
. 6/87
TABLE A.2-4 , GRASS COW-MILK PATHWAY FACTOR 4 mrem /yr per uCl/sec i INFANT (ThFACTORS) l NUCLIDE BONE LIVER T B0tTt 'DIYICID KIDNEY WNG GI-LLI I-135 l'.12E 05 2.24E 05 8.15E 04 2.00E 07 2.49E 05 0.00E-01 3.09E 04 Cs-134 3.65E 10 6.80E 10 6.87E 09 0.00E-01 1.75E 10 6.21E 09 1.85E OR Cs-136 1.96 E 09 5.76E 09 2.15E 09 0.00E-01 2.30E 09 4.70E 08 S.75E 07 Cs-137 5.15E 10 6.02E 10 4.27E 09 0.00E-01 1.62E 10 6.55E 09 1.88E 08 Cs-138 8.50E-23 1.38E-22 6.70 E-23 0.00E-01 6.8SE-23 1.08E-23 2.21E-22 Ba-139 4.41E-07 2.93E-10 1.28E-08 0.00E-01 1.76 E-10 1.77E-10 2.80E-05 Ba-140 2.41E 08 2.41E 05 1.24E 07 0.00E-01 5.72E 04 1.4BE 05 5.92E 07 Be-141 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0100E-01 0.00E-01 Ba-142 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 La-140 4.06E 01 1.60E 01 4.12E 00 0.00E-01 0.00E-01 0.00E-01 1.88E '05 La-142 8.59 E-ll 3.15E-11 7.55E-12 0.00E-01 0.00E-01 0.00E-01 5.36E-06 Ce-141 4.34 E 04 2.64E 04 3.11E 03 0.00E-01 8.16E 03 0.00E-01 1.37E 07 Ce-143 3.97E 02 2.63E"03 3.00E 01 0'.00E-01 7.67E 01 0.00E-01 1.54E T6 Ce-144 2.33E 06 9.52E 05 1.30E 05 0.00E-01 3.85E 05 0.00E-01 1.33E 08 Pr-143 1.49E 03 5.56E 02 7.36E 01 0.00E-01 2.07E 02 0.00E-01 7.R4E 05 Pr-144 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 N -147 8.86E 02 9.10E 02 5.57E 01 0.00E-01 3.51E 02 0.00E-01 5.77E 05 W-187 6.12E 04 4.26E 04 ,1.47E 04 0.lbd-01 0.00E-01 0.00E-01 2.50E 06 Np-239 3.65E 01 3.26E 00 1.84E 00 0.00E-01 'l.50E 00 0.00E-01 9.43E 04 l A-25 Rev. 3 6/87
- e. _ - - _ _ _ . - . _- - - _ _ . _ . - - _ __ _ _ _ - _ - _ _ . - - _ - _ - _ _ _ _ _ . - _ _ . _ - _ _ _ _ . _ _ _ _ . _ _ _ _ - - - _ - _ _ _ _ _ . _ - _ . - _ _ - _ .--____.--_______3
TABLE A.3-1 GRASS-COW-MEAT PATHWAY FACTOR m2. mrem /yr per uCt/see ADULT (Tg FACTORS) NUeT.mE BONE LIVER T BODY THYlOID KIDNEY WNG GI-LLI
.H-3 0.00E-01 3.25E 02 1.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 C-14 2.41E 08 4.83E 07 4.83E 07 4.83E 07 4.83E 07 4.83E 07 4.83E 07 Na-24 1.36E-03 1.36E-03 1.36E-03 1.36E-03 1.36E-03 1.36E-03 1.36E-03 P-32 4.65E 09 2.89E 08 1.80E 08 0.00E-01 0.00E-01 0.00E-01 5.23E 08 Cr-51 0.00E-01 0.00E-01 7.05E 03 4.21E 03 1.55E 03 9.35E 03 1.77E 06 m-54 0.00E-01 9.18E 06 1.75E 06 0.00E-01 2.73E 06 0.00E-01 2.81E 07 Mn-56 0.00E-01 0.0CE-01 0.00E-01 0.00E 0.00E-01 0.00E-01 0.00E-01 Fe-55 2.93E 08 2.02E 08 4.72E 07 0.00E-01 0.00E-01 1.13E 08 1.16E 08 Fe-59 2.65E 08 6.24E 08 2.39E 08 0.00E-01 0.00E-01 1.74E 08 2.00E 09 l C&58 0.00E-01 1.82: 07 4.09E 07 .0.00E-01 0.00E-01 0.00E-01 3.70E 08 Co-60 0.00E-01 7.52: 07 1.66E 08 0.00E-01 0.00E-01 0.00E-01 1.41E 09 Ni-63 1.89E 10 1.32E 09 6.33E 08 0.00E-01 0.00E-01 0.00E-08 2.73E 08
. Ni-65 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E Ou-64 0.00E-01 2.73E-07 1.2SE-07 0.00E-01 6.89E-07 0.00E-01 2.33E-05 Zn-65 3.56E 08 1.13E 09 5.12E 08 0.00E-01 7.57E 08 0.00E-01 7.13E 08 1
In-69 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Br-83 0.00E-01 0.0CE-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Br-84 0.00E-01 0.0CI-01 3.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Br-85 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rt>-96 0.00 E-01 4.87E 08 2.27E 08 0.00E-01 0.005-01 0.00E-01 9.61E 07 Rb-88 0.00 E-01 0.00,E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E Rb-89 0.00E 41 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-89 3.02E 08 0.00E-01 9.66E 06 0.00E-01 0.00 E 0.00E-01 4.84E 07 Sr-90 1.24E 10 0.00E-01 3.05E 09 0.00E-01 0.00E-01 0.00E-01 3.59E 08 Sr-91 1.43 E-10 0.00E-01 5.73 E-12 0.00E-01 0.00E-01 0.00E-01 6.76E-10 l Sr-92 0.00 E-01 0.00E-01 0.00 E-01 0.00E-01' O.00E-01 0.00E-01 0.00E-01 Y-90 1.07E 02 0.00E-01 2.86E 00 0.00E-01 0.00E-01 0.00E-01 1.13E 06 0 l
, Rev. 3 6/87.
TABLE A.3-l' GRASS-COW-MEAT PATHWAY FACTOR m2,mram/yr per uCi/sec ADULT (T[ FACTORS) NUCLIDE BONE LlVER T BODY THYRDID KIDNEY IDNG GI-LLI Y-91M 0.00E41 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E Y-91 1.13E 06 0.00E-01 3.03E 04 0.00E-01 0.00E-01 0.00E-01 6.23E 08 Y-92 , 0.00E41 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y-93 6.59 E-12 0.00E-01 1.82E-13 0.00E-01 0.00E-01 0.00E-01 2.09E-07 2r-95 1.87E 06 6.01E 05 4.07E 05 0.00E-01' 9.43E 05 0.00E-01 1.90E 09 Zr-97 2.08E-05 4.19E-06 1.92E-06 0.00E-01 6.335-06 0.00E-01 1.30E 00 Nb-95 2.30E 06 1.28E 06 6.88E 05 0.00E-01 1.26E 06 0.00E-01 7.76E 09 Mc>-99 0.00 E41 9.99E 04 1.90E 04 0.00E-01 2.26E 05 0.00E-01 2.32E 05 To-99M 4.50E-21 1.2.E-20 7 1.62E-19 0.00E41 1.93E-19 6.23E-21 7.53E-18 Tc-101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 h-103 1.05E 08 0.00E-01 4.53E 07 0.00E-01 4.01E 08 0.00E-01 1.23E 10 Ra-lC5 5.87E-28 0.00E-01 2.32E '28 0.00E-01 7.58E-27 0.00E-01 3.59E-25
.%-106 2.80E 09 0.00E-01 3.54E 08 0.00E-01 '5.40E 09 0.00E-01 1.81E 11 Ag-110M 6.68t 06 6.18E 06 3.67E 06 0.00E-01 1.22E 07 0.00E-01 2.52E 09-Te-125M 3.59E 08 1.30E 08 4.81E 07 1.08E 08 1.46E 09 0.00E-01 1.43E 09
~ Te-127M 1.12E 09 3.99E 08 1.36E 08 2.85E 08 4.53E 09 0.00E-01 3.74E 09 Te-127 2.14E-10 7.68E-11 4.63E-11 1.58E-10 8.71E-10 0.00E-01 1.69E-08 Te-129M 1.13E 09 4.23E 08 1.80E 08 3.90E 08 4.73E 09 0.00E-01 5.71E 09 Te-129 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E41 0.00E-01 0.00E-01 Te-131M 4.52E 02 2.21E 02 1.84E 02 3.50E 02 2.24E 03 0.00E-01 2.20E 04 Te-131 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Te-132 1.42E 06 9.19E 05 8.63E 05 1.01E 06 8.85E 06 0.00E-01 4.35E 07-I-130 2.12E-06 6.26E-06 2.47E-06 5.30E-04 9.76E-06 0.00E-01 5.39E-06: I-131 1.07E 07 1.54E 07 8.81E 06 5.04E 09 2.64E 07 0.00E-01 4.06E 06' I-132 0.00E-01 0.0'0E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I-133 3.67E-01 6.38E-01 1.94E-01 9.37E 01 1.llE 00 0.00E-01 '5.73E-01 I-134 0.00E-01 0.00E-61 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 h27 Rev. 3 6/87
TABLE A.3-1 GRASS-COW-MEAT PATHWAY FACTOR m2 mrem /yr per uCi/sec ADULT (Tg FACTORS) - 9 NUCLIDE BONE LIVER T !!Ot71 THYRDID- KIINEY URG GI-LLI I-135 4.47 E-17 1.17E-16 4.32E-17 7.73E-15 1.88E-16 0.00E-01 1.32E-16 Cs-134 6.58E 08 1.56E 09 1.2SE 09 0.00E-01 5.06E 08 1.68E 08 2.74E 07 Cs-136 1.18E 07 4.66E 07 , 3.35E 07 0.00E-01 2.59E 07 3.55E 06 5.24E 06 Cs-137 8.72E 08 1.19E 09 7.81E 08 0.00E-01' 4.05E 08 1.35E 08 2.31E 07 Cs-138 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E41 0.00E-01 Ba-139 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sa-140 2.87E 07 3.61E 04 1.6BE 06 0.00E-01 1.23E 04 2.07E 04 5.92E 07 3a-141 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Ba-142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00 E-01 0.00E-01 0.00E-01 La-140 3.76 E-02 1.89E-02 5.00E-03 0.00E-01 0.00E-01 0.00E-01 1.39E'03 La-142 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ' 0.00E-01 0.00E-01 Ce-141 1.40E 04 9.50E 03 1.08E 03 0.00E-01 4.41E 03 0.00E-01 3.63E 07 Ce-143 2.01E-02 1.49E 01 1.65E-03 0.00E-01 6.55 E-03 0.00E-01 5.56E 02
~
l
.. Ce-144 1.46E 06 6~.09E C5 9.83E 04 0.00E-01 3.61E 05 0.00E-01 '4.93E 08 i Pr-143 2.10E 04 8.41E 03 1.04E 03 0.00E-01 4.86E 03 0.00E-01 9.19E 07 Pr-144 ' O .00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3
.Nd-147 7.17 E 03 8.29E 03 4.96E 02 0.00E-01 4.84E 03 0.00E-01 3.98E 07 !
W-lS7 2.17 E-02 1.81E-02 6.33E-03 0.00E-01 0.00E-01 0.00E-01 5.93E 00 Np-239 2.59 E-01 2.55E-02 1.40E-02 0.00E-01 7.94E-02 ' O.00E-01 5.22E 03' A-28 Rev. 3 6/87 -__ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ . _ _ . _ _ . _ - - _ . _ _ _ _ . _ - _ _ _ __ __ . . . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ ..__J
TABLE A.3-2 GRASS-COW-MEAT PATHWAY FACTOR m2 .orem/yr per uCi/see TEEN (TG FACTORS) NUCLIDE BONE LIVER T BODY -
'DIYRDID KIDNEY WNG GI-LLI H-3 0.00E-01 1.94E 02 1.94E 02 1.94E 02 1.94E 02 1.94E 02 1.94E 02 C-14 2.04E 08 4.08E 07 4.08E 07 4.08E 07 4.08E 07 4.08E 07 4.08E 07 Na-24 1.09E-03 1.09E-03 1.09E-03 1.09E-03 1.09E-03 1.09E-03 1.09E-03 P-32 3.93E 09 2.44E 08 1.52E 08 0.00E 0.00E-01 0.00E-01 3.30E 08 Cr-51 0.00E-01 0.00E-01 5.64E 03 3.13E 03 1.24E 03 8.05E 03 9.47E 05 Mn-54 0.00E-01 7.00E 06 1.39E 06 0.00E-01 2.09E 06 0.00E-01 1.44E 07 Mn-56 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01~ 0.00E-01 Fe-55 2.38E 08 1.69E 08 3.93E 07 0.00E-01 0.00E-01 1.07E 08 7.30E 07 Fe-59 2.12E 08 4.95E 08 1.91E 08 0.00E-01 0.00E-01 1.56E 08 1.17E 09 Co-58 0.00E-01 1.41E 07 3.24E 07 0.00E-01 0.00E-01 0.00E-01 1.94E 08 Co-60 0.00E-01 5.83E 07 1.31E 08 0.00E-01 0.00E-Ol' O.00E-01 7.60E 08 Ni-63 1.52E 10 1.07E 09 5.15E 08 0.00E-01 .0.00E-01 0.00E-01 1.71E 08 Ni-65 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Cu-64 0.00E-01 2.23E-07 1.05E-07 0.00E-01 5.64E-07 0.00E 1.73E-05 Zn-65 2.50E 08 8.69E 08 4.05E 08 0.00E-01 5.56E 08 0.00E-01' 3.68E 08 ~
Zn-69 0.00E-01 0 00E-01
. 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3r-83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Br-84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 . Br-85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-86 0.00E-01 4.07E 08 1.91E 08 0.00E-01 0.00E-01 0.00E-01 6.02E 07 Ro-88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-89 ' O.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-07 Sr-69 2.55E 08 0.00E-01 7.29E 06 0.00E-01 0.00E-01 0.00E-01 3.03E 07 Sr-90 8.05E 09 0.00E-01 1.99E 09 0.00E-01 0.00E 0.00E-01 2.26E 08 Sr-91 1.19E-10 0.00E-01 4.75E-12 0.00E-01 0.00E-01 0.00E-01 5.41E-10 Sr-92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E 0.00E-01 0.00E-01 Y-90 8.98E 01 0.00E-01 2.42E 00 0.00E-01 0.00E-01 0.00E-01 7.41E 05 A-29 Rev. 3 A/R7
GRASS-COW-MEAT PATHWAY FACTOR 1 12.orem/yr per.uC1/sec I TEEN (Tg FACTORS) 1:UCLIDE BONE LIVER T BODY 'IHY1CID KIDNEY WNG ,GI-LLI Y-91M 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y-91 9.54E 05 0.00E-01 2.56E 04 0.00E-01 0.00E-01 0.00E-01. 3.91E 08 , Y-92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l Y193 5.56E-12 0.00E-01 1.53E-13 0.00E-01 0.00E-01 0.00E-01 1.70E-07 Zr-95 1.50E 06 4.73E 05 3.26E 05 0.00E-01 6.96E 05 0.00E-01 1.09E 09 2r-97 1.73E-05 3.42E-06 1.58E-06 0.00E-01 5.19E-06 0.00E-01 9.27E-01 Nb-95 1.80E 06 9.96E 05 5.48E 05 0.00E-01 9.66E'05 0.00E-01 4.26E 09 Mo-99 0.00E-01 8.26E 04 1.58E 04 0.00E-01 1.89E 05 0.00E-01 1.48E 05 Tc-99M 3.58E-21 9.97E 1.29E-19 0.00E-01 1.49E-19 5.54E-21 6.55E-18 i 1 l Tc-101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 { l . Ru-103 8.56E 07 0.00E-01 3.66E 07 0.00E-01 3.02E 08 0.00E-01 7.15E 09 F.u-105 4.91E-28 0.00E-01 1.91E-28 0.00E-01 6.91E-27 0.00E-01 3.96E-25 I Ra-106 2.36E 09 0.00E-01 2.97E 08 0.00E-01 4.55E 09 0.00E-01 1.13E 11 Ag-110M 5.06E 06 4.79E 06 2.91E 06 0.00E-01 9.13E 06 0.00E-01 1.35E 09 Te-126M 3.03E 08 1.09E 08 4.05E 07 G.47E 07 0.00E-01 0.00E-01 8.94E 08
~ Te-127M 9.42E 08 3.34E 08 1.12E 08 2.24E 08 3.82E 09 0.00E-01 2.35E 09 Te-127 1.81E-10 6.43E-11 3.91E-11 1.25E-10 7.35E 0.00E-01 1.40E-08 Te-129M 9.50E 08 3.53E 08 1.50E 08 3.07E 08 3.97E 09 0.00E-01 3.57E 09
. Te-129 0.00E-01 0.00E'01
- 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Te-131M 3.77E 02 1.81E 02 1.51E 02 2.72E 02 1.88E 03 0.00E-01 1.45E 04 Te-131 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Te-132 1.16E 06 7.36E 05 6.93E 05 7.76E 05 7.06E 06 0.00E-01 2.33E 07 I-130 1.71E-06 4.94E-06 1.97E-06 4.03E-04 7.61E-06 0.00E-01' 3.80E-06 I-131 8.93E 06 1.25E 07 6.72E 06 3.65E 09 2.15E 07 0.00E-01 2.47E 06 I-132 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I-133 3.07E-01 5.20E-01 1.59E-01 7.26E 01 9.12E-01 0.00E-01 3.93E-01 1-134 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rev. 3 A-30 6/87
. , . . , . . . , - 1
. i GRASS-COW-MEAT PATHWAY FACTOR m2 .mram/yr per uCUsec TEEN (Tg FACTORS)
NUCLIDE BCNE LIVER T BCDY TKYROID KIDNEY 11RG GI-LLI I-135 3.64E-17 9.37E-17 3.47E-17 6.03E-15 1.48E-16 0.00E-01 1.04E-16 Cs-134 5.23E 08 1.23E 09 5.71E 08 0.00E-01 3.91E 00 1.49E 08 1.53E 07 Cs-136 9.20E 06 3.62E 07 2.43E 07 0.00E-01 1.97E 07 3.11E 06 2.91E 06 Cs-137 7.24E 08 9.63E 08 3.36E 08 0.00E-01 3.28E 08 1.27E 08 1.37E 07. Cs-138 0.00E-01 D.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Ba-139- 0.00E-01 0.00E-01 0.00E-01 D.00E-01 0.00E-01 0.00E-01 0.00E-01 Ba-140 2.38E 07 2.91E 04 1.53E 06 0.00E-01 9.88E 03 1.96E 04 3.67E 07 Ba-141 - 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Ba-142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 IA-140 3.09E-02 1.52E-02 4.04E-03 0.00E-01 0.00E-01 0.00E-01 8.72E 02 La-142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Ce-141 1.18E 04 7.88E 03 9.05E 02 0.00E-01 3.71E 03 0.00E-01 2.2SE 07 Ce-143 1.69E-02 'l.23E 01 1.38E-03 0.00E-01 5.53E-03 0.00E-01 3.70E 02 Ce-144 1.23E 06 5.08E 05 6.60E 04 0.00E-Q1 3.04E 05 0.00E-01 3.09E 08 Pr-143 1.77E 04 7.05E 03 8.78E 02 0.00E-01 4.10E 03 0.00E-01 5.81E 07 Pr-144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Nd-147 6.32E 03 6.87E 03 , 4.llE 02 0.00E-01 4.03E 03 0.00E-01 2.48E 07 W-187 1.81E-02 1.4BE-02 5.18E-03 0.00E-01 0.00E-01 0.00E-01 4.00E 00 Np-239 2.26E-01 2.13E-02 1.19E-02 0.00E-01 6.70E-07 0.00E-01 3.43E 03 i d Rev. 3 A-31 , , 6/87
GRASS-COW-MEAT PATHWAY FACTOR . m2.crem/yr per uCi/sec CHILD (Tg FACTORS) NUCLIDE BCNE IJVER T BODY 'IWlROID KIDNEY WNG GI-LLI
. l H-3 0.00E-01 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 C-14 3.83E 08 7.67E 07 7.67E 07 7.67E 07 7.67E 07 7.67E 07 7.67E 07 Na-24 1.73E-03 1.73E-03 1.73E-03 1.73E-03 1.73E-03 1.73E-03 1.73E-03 P-32 7.41E 09 3.47E 08 2.86E 08 0.00E-01 0.00E-01 0.00E-01 2.05E 08 Cr-51 0.00E-01 0.00E-01 8.79E 03 4.88E 03 1.33E 03 8.91E 03 4.66E 05 Mn-54 0.00E-01 8.01E 06 2.13E 06 0.00E-01 2.25E 06 0.00E-01 6.72E 06 3
Mn-56 1.19E-10 0.00E-01 4.75E-12 0.00E-01 0.00E-01 0.00E-01 5.41E-10' Fe-55 4.57E 08 ' 2.42E 08 ~ 7.50E 07 0.00E-01 0.00E-01 1.37E 08- 4.49E 07 Fe-59 3.76E 08 6.09E 08 3.03E 08 0.00E-01 0.00E-01 1.76E 08 6.34E 08 Co-58 0.00E-01 1.64E 07 5.03E 07 0.00E-01 0.00E-01 0.00E-01 9.58E 07 , Co-60 0.00E-01 6.93E 07 2.04E 08 0.00E-01 0.00E-01 0.00E-01 3.84E 08 l Ni-63 2.91E 10 1.56E 09 9.91E 08 0.00E-01 0.00E-01 0.00E-01 1.05E 08 ) Ni-65' O.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Cu-64 0.00E-01 3.00E-07 1.81E-07 0.00E-01 7.24E-07 0.00E-01 1.41E-05 I In-65 3.75E 08 1.00E 09 6.22E 08 0.00E-01 6.30E 08 0.00E-01 1.76E 08 Zn-69 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01
. Br-83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 - 0.00E-01 0.00E-01 Br-84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 B'-85 r 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- Rb-86 0.00E-01 5.77E 08 3.55E 08 0.00E-01 0.00E-01 0.00E-01 3.71E 07 ,
Rb-88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ! I i l Rb-89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 St-89 4.82E 08 0.00E-01 1.38E 07 0.00E-01 0.00E-01 0.00E-01 1.87E 07 Sr-90 1.04E 10 0.00E-01 2.64E 09 0.00E-D1 0.00E-01 0.00E-01 1.40E 08 Sr-91 2.24E-10 0.00E-01 8.45E-12 0.00E-01 0.00E-01 0.00E-01 4.94E-10 Sr-92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y-90 1.70E 02 0.00E-01 4.55E 00 0.00E-01 0.00E-01 0.00E-01 4.84E 05 A-32 Rev. 3 6/87
- 4 s
__ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ . _ _ _ _ _ . . . _ _ .___._._.___._____._.__________m__ - _ _ _ . _ - _ _ _ _ . _ _ _
GRASS-COW-MEAT PATHWAi~ FACTOR , m2.mram/yr per uCl/sec CHILD (TG FACTORS) NOCLIDE ' BCNE LIVER T BODY 'nflRDID KIDNCl WNG GI-LLI Y-91M 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y-91 1.80E 06 0.00E-01 '4.82E 02 0.00E-01 0.00E-01 0.00E-01 2.40E 08 1 Y-92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ! l
- 1 Y-93 1.04E-11 0.00E-01 2.87E-13 0.00E-01 0.00E-01 0.00E-01 1.56E-07 Zr-95 2.66E 06 5.86E 05 5.21E 05 0.005-01 8.38E 05 0.00E-01 6.11E 08 3r-97' 3.22E-05 '4.65E-06 2.74E-06 0.00E-01 6.68E-06 0.00E-01 7.05E-01 Nb-95 3.10E 06 1.21E 06 8.63E 05 0.00E-01 1.13E 06 0.00E-01 2.23E 09 i
M:HP9 0.00E-01 1.15E 05 2.84E 04 0.00E-01 2.45E 05 0.00E-01 9.51E 04 i
~ To-99M 6.27E-21 1.23E-20 2.04E-19 0.00E-01 1.79E-19 6.24E-21 7.00E-3,8 To-101 0.00E-01 0.00E-01 ' O.00E-01 0.00E-01 0.00 E-01 0.00E-01 0.00E-01 Ru-103 1.55E 08 0.00E-01 5.95E 07 0.00E-01 3.90E 08 0.00E-01 4.00E 09 Ru-105 9.16 E-28 0.00E-01 3.32E-28 0.00E-01 8.05 E-27 0.00E-01 5.98E-25 Ru-106 4.44E 09 0.00E-01 5.54E 08 0.00E-01 5.99E 09 0.00E-01 6.90E 10 Ag-110M 8.34E 06 5.67E 06 4.53E 06 0.00E-01 1.06E 07 0.00E-01 6.74E 08 Te-125M 5.69E 08 1.54E 08 7.59E 07 1.60E 08 0.00E-01 0.00E-01 5.49E 08 Te -127M 1.77E 09 4.78E 08 2.11E 08 4.24E 08 5.06E 09 0.00E-01 1.44E 09 Te-127 3.415-10 9.20E-11 7.32E-11 2.36E-10 9.71E-10 0.00E-01 1.33E-08 Te-129M 1.79E 09 5.00E 08 1.68E 08 5.77E 08 ' 5.26E 09 0.00E-01 2.18E 09 Te 129 0.00 E-01 0.00E-01 0.00E-01 ' O.00E-01 0.00 E-01 0.00E-01 0.00E-01 Te-131M 7.01E 02 2.43E 02 2.58E 02 4.99E 02 2.35E 03 0.00E-01 9.84E 03 0.00E41 0.00E-01 Te-131 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Te-132 2.12E 06 9.39E 05 1.13E 06 1.37E 06 8.72E 06 0.00E-01 9.46E 06 I-130 3.05E-06 6.17E-06 3.18E-06 6.80E-04 9.22E-06 0.00E-01 2.89E-06 I-131 1.66E 07 1.67E 07 9.47E 06 5.51E 09 2.74E 07 0.00E-01 1.48E 06
.I-132 0.00E41 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1-133 5.70 E-01 7.04E-01 2.66E-01 1.31E 02 1.17E 00 0.00E-01 2.84E-01 I-134 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 !
t i 1
. A-33 i Rev. 3 '
6/87 i l j
in m n.s a i GRASS-COW-MEAT PATHWAY FACTOR
.m2. mrem /yr per uCi/sec j CHILD (Tg FACTORS) ,
4 NUCLIDE BONE LIVER T BCDY 'IHYROID KIDNEY WNG GI-ILI I-135 6.59E-17 1.19E-16 5.61E-17 1.05E-14 1.82E-16 0.00E-01 9.04E-17 Cs-134 9.22E 08 1.51E 09 3.19E 08 0.00E-01 4.69E 08 1.68E 08 8.16E 06 Cs-136 1.59E 07 4.36E 07 2.82E 07 0.00E-01 2.32E 07 3.46E 06 1.53E 06 i
. I Cs-137 1.33E 09 1.28E 09 1.88E 08 0.00E-01 4.16E 08 1.50E 08 7.99E 06 I Cs-138 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Ba-139 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Ba-140 4.39E 07 3.84E 04 2.56E 06 0.00E-01 1.25E 04 2.29E 04 ~1.22E 07 Ba-141 0.00E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Ba-142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01
. La-1'40 5.66E-02 1.98E-02 6.66E-03 0.00E-01 0.00E-01 0.00E-01 5.51E-02 i La-142 0.00E-01 0.00E-01
- 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Ce-141 2.22E 04 1.11E 04 1.64E 03 0.00E-01 4.86E 03 0.00E-01 1.38E 07 Ce-143 3.18E-02 1.72E 01 2.50E-03 0.00E-01 7.23E-03 0.00E-01 2.52E 02 Ce-144 2.32E 06 7.26E 05 1.24E 05 0.00E-01 4.02E 05 0.00Er01 1.89E 08 j Pr-143 3.34E 04 1.00E 04 1.66E 03 0.00E-01 5.43E 03 0.00E-01 3.60E 07 Pr-144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Nd-147 1.19E 04 9.60E 03 7.43E 02- 0.00E-01 5.27E 03 0.00E-01 1.52E 07 W-187 3.36E-02 1.99E-02 S.94E-03 0.00E-01 0.00E-01 0.00E-01 2.80E 00 I
Np-239 4.26E-01 3.06E-02 2.15E-02 0.00E-01 8.84E-02 0.00E-01 2.26E-03 A-34 ' Rev. 3
. 6/87
i VEGETATION PATHWAY FACTOR ! mLmrem/yr per uCi/sec ( ADULT (TG FACTORS) NUCLIDE BONE LIVER T BODY 'IWYICID KIDNEY . WNG GI-f1I H-3 0.00E-01 2.26E 03. 2.26E 03 2.26E 03 2.26E 03 2.26E 03 2.26E 03 C-14 2.38E 08 . 4.55E 07 4.55E 07' 4.55E 07 4.55E 07 4.55E 07 4.55E 07 Na-24 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 P-32 1.40E 09 8.73E 07 5.42E 07 0.00E-01 0.00E-01 0.00E-01 1.58E 08 Cr-51 0.00E-01 0.00E-01 4.64E 04 2.78E 04 1.02E 04 6.16E 04 1.17E 07 Mn 0.00 E-01 3.13E 08 5.97E 07 0.00E-01 9.31E 07 0.00E-01 9.58E 08 Mn-56 0.00 E-01 1.59E 01. 2.32E .00 0.00E-01 2.02E 01 0.00E-01 5.08E 02 Fe-55 2.09E 08 1.45E 08 3.37E 07 0.00E-01 0.00E-01 8.06E 07 8.29E C7 Fe-59 1.26 E. 08 2.96E 08 1.14E 08 0.00E-01 0.00E-01 8.28E 07 9.83E 08 1
'Co-58 0.00 E-41 3.07E 07 ' 6.89E 07 0.00E-01 0.00E-01 0.00E-01 6.23E 08 l Co-60 0.00E-Ol 1.67E 08 3.69E 08 0.00E-01 0.00E-01 0.00E-01 3.14E 09 '
Ni-63 1.04E 10 7.2SE 08 3.49E 08 0.00E-01 0.00 E-01. 0.00E-01 1.50E 08 Ni-65 6.93E 01 9.01E 00 4.11E 00 0.00E-01 0.00 E-01 0.00E-01 2.28E 02 Cu-64 0.00 E- 01 9.21E 03, 4.32E 03 0.00E-01 2.32E 04 0.00E-01 7.85E 05 Zn-65 3.17E 08 1.01E 09 4.56E 08 0.00E-01 6.75E 08 0.00E-01 6.36E 08 Zn-69 8.77 E-06 1.68E-05 1.17E-06 0.00E 1.09 E-05 0.00E-01 2.52E-06 Br-83 0.00 E-01 0.00E-01 3.11E 00 0.00E-01 0.00E-01 0.00E-01 4 48E 00 Br-84 0.00E-01 0.00E-01 2.49 E-ll 0.00E-01 0.00 E-01 0.00E-01 1.96E-16 Br-85 0.00 E-Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-86 0.00 E-01 2.19E 08 1.02E 08 0.00E-01 0.00E-01 0.00E-01 4.33E 07 Rb-88 0.00 E-01 3.47E-22 1.84 E-22 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-89 0.00E-01 1.41E-26 9.8BE-27 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-89 9.97E 09 0.00E-01 2.86E 08 0.00E-01 0.00E-01 0.00E-01 1.60E 09 Sr-90 6.05E 11 0.00E-01 1.48E 11 0.00E-Cl 0.00E-01 0.00E-01 1.75E 10 Sr-91 3.03E 05 0.00E-01 1.22E 04 0.00E-01 0.00E-01 0.00E-01 1.44E 06 Sr-92 4.27 E 02 0.00E-01 1.85E 01 0.00E-01 0.00E-01 0.00E-01 S.46E 03 Y-90 1.33E 04 0.00E-01 3.56E 02 0.00E-01 0.00E-01 0.00E-01 1.41E 08 A-35 Rev. 3 6/87
1
' I VEG[TATION PATHWAY FACTOR mGmram/yr per uC1/sec I ADULT (T g FACTORS) ,
NUCLIDE BONE LIVER T BODY 'I1NROID KIDNEY IUNG GI-LLI
~
Y-91M 5.24 E-49 0.00E-01 2.03E-10 0.00E-01 0.00E-01 0.00E-01 1.54 >08 Y-91 5.llE 06 0.00E-01 1.37E 05 0.00E-01 ' O.00E-01 0.00E-01 2.81E 09 l Y-92 9.16 E-01 0.00E-01 2.68E-02 0.00>01 0.00E-0.1 0.00E-m 1.60t; 04 ) Y-93 1.74E 02 0.00E-01 4.81E 00 0.005-01 0.00E-01 0.00E-01 5.52E 06 . Er-95 ' 1.18E 06 3.77E 05 2.55E 05 0.00E-01 SM2E 05 0.00E-01 1.20E 09 tr-97 L37E 02 6.81E 01 3.11E 01 u.00E-01 1.03E 02 0.00E-01 2.11E 07 l Nb-95 1.43E 05 7.93E 04 4.26E 04 0.00E-01 7.84E 04 0.00E-01 4.81E 08 Mo-99 0.00 E-01 6.15E 06 1.17E 06 0.005-01 1.39E 07 0.00E-01 1.43E 07 To-99M 3.10E 00 8.77E 00 1.12E 02 0.00E-01 'l.33E 02 4.30E 00 5.19E 03 Tc-101 3.34 E-31 1.20E-30 1.18E-29 0.00E-01 2.16E-29 6.14E-31 0.00E-01 Ru-103 4.76E 06 0.00E-01 2.05E 06 0.00E-01 1.82E 07 0.00E-01 5.56E 08 Ru-105 5.39E 01 0.00E-01 2.13E 01 0.00E-41 6.97E 02 0.00E-01 3.30E 04 Ru-106 1.93E 08 0.00E-01 2.44E 07 0.00E-01 3.72E 08 0.00E-01 1.25E 10 Ag-110M 1.05E 07 9.75E 06 5.79E 06 0.00E-01 1.92E 07 0.00E-01 3.98E 09 Te-125M 9.66E 07 3.50E 07 1.29E 07 2,.90E 07 3.93E 08 0.00E-01.. 3.86E 08
-- Te-127M 3.49E 08 1.25E 08 4.26E 07 8.93E 07 1.42E 09 0.00E-01 1.17E 09 Te-127 5.66E 03 2.03E 03 1.23E 03 4.20E 03 2.31E 04 0.00E-01 4.47E 05 Te-129M 2.51E 08 9.38E 07 3.98E 07 8.63E 07 1.05E 09 0.00E-01 1.27E 09 Te-129 7.65 E-04 2.87E-04 1.86 E-04 5.87E-04 3.225-03 0.00E-01 5.77E-04 i ~
Te-131M 9.12E 05 4.46E 05 3.72E 05 7.07E 05 '4.52E 06 0.00E-01 4.43E 07 1 Te-131 1.51E-15 6.32E-16 4.78E-16 1.24E-15 6.635-15 0.00E-01 2.14E-16 Te-132 4.30E 06 2.78E 06 2.61E 06 3.07E 06 2.68E 07 0.00E-01 1.32E 08 I-130 3.95E 05 1.16E 06 4.57E 05 9.81E 07 1.81E 06 0.00E-01 9.97E 05 > I-131 8.08E 07 1.16E 08 6.62E 07 3.79E 10 1.98E 08 0.00E-01 3.05E 07 i I-132 5.77E 01 1.54E 02 5.40E 01 5.40E 03 2.46E 02 0.00E-01 2.90E 01 I-133 2.09E 06 3.63E 06 1.11E 06 5.33E 09 6.33E 06 0.00E-01 3.26E 06 I-134 9.69 E-05 2.63E-04 9.42E-05 4.56E-03 4.19E-04 0.00E-01 2.30E-07 iA-36 Rev. 3 6/87
, q VEG{TATION PATHWAY-FACTOR l m4 mrem /yr per uCi/sec i
, ADULT'(TG FACTORS) 10CLIDE BONE LIVER T BCDY VW3CID - KIDtGX LUNG GI-LLI I-135 3.90E 04 1.ch 63 3.77E 04 6.74E 06' l.64E 05 0.00E-01 1.15E 05 Cs-134 4.67E 09 1.llE 10 9.08E 09 0.00E-01 3.59E 09 1.19E 09 1.94E 04 Cs-136 4.20E 07 1.66E 08 1.19E 08 0.00E-01 9.22E 07 1.26E 07 1.88E 07 Cs-137 6.36E 09 8.70E 09 5.70E 09 0.00E-01 2.95E 09 9.81E 08 1.68E 08 Cs-138 3.94 E-11 7'.78E-11 3.86E-ll 0.00E-01 5.72E-ll 5.65E 3.32E ~
Be-139 2.90 E-02 2.07E-05 8.50E-04 0.00E-01 1.93 E-05 1.17E-05 5.15E-02 Ba-140 1.29E 08 1.61E 05 8.42E 06 0.00E-01 5.49E 04 9.25E 04 2.65E 08 Ba-141 ' l .28 E-21 9.64E-25 4.31E-23 0.00E-01 8.965-25 5.475-25 6.01E-31 sa-142 0.00 E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01
.La-140 1.98E 03 9.99E 02 2.64E 02 0.00E-01 0.00E-01 0.00E-01 7.33E 07 l La-142 1.42 E-04 6.44E-05 1.61E-05 0.00E-01 0.00E-01 0.00E-01 4.70E-01 l Ce-141 1.97E 05 1.33E 05 1.51E 04 0.00E-01 ~6.19E 04 0.00E-01 5.10E 08 Ce"143 9.98E 02 7.38E 05 8.17E 01 0.00E-01 3.25E 02 0.00E-01 2.76E 07 4 Co.-144 3.29E 07 1.38E 07 1.77E 06 0.00E-01 8.16E 06 0.00E-01 1.llE 10 l Pr-143 6.26E 04 2.51E 04 3.11E 03 0.00E-01 1.45E 04 0.00E-01 2.74E 08 Pr-144 3.13 E-26 1.30E-26 1.59E-27 'O.00E-01 7.32E-27 0.00 E-O'l 0.00E-01 Nd-147 3.36E 04 3.89E 04 2.32E 03 0.00E-01 2.27E 04 0.00E-01 1.87E 08 W-187 3.82E 04 3.20E 04 1.12E 04 0.00E-01 0.00E-01 0.00E-01 1.05E 07 Np-239 1.43 E 03 1.40E 02 7.74E 01 0.00E-01 4.38E 02 0.00E-01 2.88E 07 4
~
Rev. 3
. 6/87
VEGETATIONPATHWAYFAdTOR
#.mram/yr per uC1/sec TEEN (Tg FACTORS) ,
NUCLIDE BONE LIVER T BODY WlRDID KIDNEY IDN3 GI-LLI H-3 0.00E-01 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03 C-14 3.69E 08 7.38E 07 7.38E 07 7.38E 07 7.38E 07 7.38E 07 7.38E 07 Na-24 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 P-32 1.61E 09 9.96E 07 6.23E 07 0.00E-01 0.00E-01 0.00E-01 1.35E 08 Cc-51 0.00E-61 0.22E 01 S.17E Of 3.43E 04 1:35E 04 a, gig 94 1,04g o7 Mn-34 0.00E-01 4.54E 08 9.01E 07 0.00E-01 1.365 08 0.00E-01 9.32E 08 Mn-56 0.00E-01 1.44E 01 2.55E 00 0.00E-01 1.82E 01 0.00E-01 9.45E 02 Fe-55 3.25E 08 2.31E 08 5.38E 07 0.00E-Ol' O.00E-01 1.46E 08 9.98E 07 Fe-59. 1.79E 08 4.18E 08 1.62E 08 0.00E-01 0.00E-01 1.32E 08 9.90E 08 Co-58 0.00E-01 4.36E 07 1.01E 08 0.00E-01 0.00E-01 0.00E-01 6.01E 08 Co-60 0.00E-01 2.49E 08 5.60E 08 0.00E-Ol 0.00E-01 0.00E-01 3.24E 09 Ni-63 1.61E 10 1.13E 09 5.44E 08 0.00E-01 0.00E-01 0.00E-01 1.81E 08 N1-65 6.45E 01 8 24E 00 3.76E 00 0.00E-01 0.00E-01 0.00E-01 4.47E 02 Ca-64 0.00E-01 8.34E 03 3.92E 03 0.00E-01 2.llE 04 0.00E-01 6.47E 05 En-65 4.24E 08 1.47E 09 6.86E 08' O.00E-01 9.42E 08 0.00E-01 6.23E 08 l _ En-69 3.21E-06 l'.56E 05 1.10E-06 0.00E-01 1.02E-05 0.00E-01 2.88E-05 Br-83 0.00E-01 0.00E-01 2.92E 00 0.00E-01 0.00E-01 0.00E-01 5.08E-17 B -84 0.00E-01 0.00E-01 2.27E-ll 0.00E-01 .0.00E-01 0.00E-01 3.14E-28
. I Br-85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-86 0.00E-01 2.'74E 08 1.29E QB 0.'00E-01 0.00E-01 0.00E-01 4.05E 07 Rb-88 .0.00E-01 3.21E-22 1.71E-22 0.00E-01 0.00E-01 0.00E-01 2.75E-29 i
Ro-89 0.00E-01 1.26E-26 8.94E-27 0.00E-01 0.00E-01 0.00E-01 1.94E-35 Sr-89 1.51E 10 0.00E-01 4.34E 08 0.00E-01 0.00E-01 -0.00E-01 1.80E 09 l Sr-90 7.51E 11 0.00E-01 1.85E 11 0.00E-01 0.00E-01 0.00E-01 2.llE 10 ' dr-91 2.83E 05 0.00E-01 1.13E 04 0.00E-01 0.00E-01 0.00E-01 1.28E 06 Sr-92 3.98E 0'2 0.00E-01 1.70E 01 0.00E-01 0.00E-01 0.00E-01 1.01E 04 Y-90 1.24E 04 0.00E-01 3.34E 02 0.00E-01 0.00E-01 0.00E-01 1.02E 08 A-38 Rev. 3 6/87
VEG[TATION PATHWAY FACTOR
- Mamrem/yr per uCi/sec TEEN (TGFACTORS)
. I NUCLIDE BOtfE LIVER T BODY 'DfYROIO KIDNEY ILNG GI-LLI Y-91M 4.88E-09 0.00E-01 1.87E-10 0.00E-01 0.005-01 0.00E-01 2.30E-07 Y-91 7.84E 06 0.00E-01 2.10E 05 0.00E-31 0.00E-01 0.00E-01
~
3.21E 09 Y-92 8.61E-01 0.00E-01 2.49E-02 0.00E-01 0.00E-01 0.00E-01 2.36E 04 Y-93 1.63E 02 0.00E-01 4.47E 00 0.00E 0.00E-01 0.00E-01 4.99E 06 2r-95 1.72E 05 5.P.:: 05 3.74E 05 0.00E-01 7.99E 05 0.00E-01 1.25E 09 Zr-97 3.12E 02 6.18E 01 2.85E ,01 0.00E-41 9.37E 01 0.00E-01 1.67E 07 - l l Nb-95 1.93E 05 1.07E 05 5.88E 04 0.00E-01 1.04E 05 '0.00E-01 4.57E 08 l Mo-99 0.00E-01 5.65E 06 1.08E 06 0.00E-01 1.29E 07 0.00E-01 1.01E 07 ) Te-99M 2.74E 00 7.64E 00 9.90E 01 0.00E-01 1.14E 02 4.24E 00 5.02E 03 ) l Tc-l'01 7.76E-31 1.10E-30 1.08E-21 0.00E-01 2.00E-29 6.72E-31 0.00E-01 Ru-103 6.81E 06 - 0.00E-01 2.91E 06 0.00E-01 2.40E 07 0.00E-01 5.69E 08
'Ru-105 5.01E 01 '0.00E-01 1.94E 01 0.00E-01 6.322 02 0.00E-01 4.04E 04 Ro-106 3.09E 08 0.00E-01 3.90E 07 0.00E-01 5.97E 08 0.00E-01 1.48E 10 l Ag-110M 1.52E 07 1.43E 07 8.72E 06 0.00E-01 2.74E 07 0.00E-01 4.03E 09 l Te-125M 1.48E 08 5.34E 07 1.98E 07 4.14E 07 0.00E-01 0.00E-01 4.39E 08 l
~ Te-127M 5.52E 08 1.96E 08 6.56E 07 1.31E 08 2.24E 09 0.00E-01 1.37E 09 Te-127 5.34E 03 1.89E 03 1.15E 03 3.68E 03 2.16E 04 0.00E-01 4.12E 05 Te-129M 3.62E 08 1.34E 08 5.73E 07 1.17E 08 1.51E 09 0.00E-01 .i.36E 09 1 . Te-129 7.16E-04 2.67E-04 1.74E-04 5.12E-04 3.01E-03 0.00E-01 3.92E-03 i Te-131M 8.44E 05 4.05E 05 3.38E 05 6.09E 05 4.22E 06 0.00E-01 3.25E 07 1 1.41E-15 45.80E-16 4.40E-16 Te-131 1.08E-15 6.15E-15 0.00E-01' 1.15E-16 - Te-132 3.91E 06 2.4BE 06 - 2.33E 06 2.61E 06 2.37E 07 0.00E-01 7.84E 07 I-130 3.51E 05 1.02E 06 4.05E 05 8.28E 07 1.56E 06 0.00E-01 7.80E 05 I-131 7.69E 07 1.08E 08 5.78E 07 3.14E 10 1.85E 08 0.00E-01 2.13E 07 I-132 5.20E 01 1.36E 02 4.89E 01 4.59E 03 2.14E 02 0.00E-01 5.93E 01 I-133 1.94E 06 3.29E 06 1.00E 06 4.59E 08 5.77E 06 0.00E-01 2.49E 06 I-134 8.76E-05 2.32E-04 8.34E-05 3.87E-03, 3.66E-04 0.00E-01 3.06E-06 A-39 Rev. 3
. 6/87
,1 ABLE A.4-2 VEGETATION PATHWAY FACTOR m4. mrem /yr per uCi/sec TEEN (TqFACTORS)
NUCLIDE BCNE . LIVER T BODY '1WIROID KIDNEY IUNG GI-LLI I-135 3.52E 04 9.07E 04 3.36E 04 5.84E 06 1.43E 05 0.00E-01 1.01E 05 Cs-134 7.10E 09 1.67E 10 7.75E 09 0.00E-01 5.31E 09 2.03E 09 2.06E 08 Cs-136 4.28E 07 1.68E 08 1.13E 08 0.00E-01 9.16E 07 1.44E 07 1.35E 07 1 Cs-137 1.01E 10 1.35E 10 4.69E 09 0.00E-01 4.59E 09 1.78E 09 1.92E 08 i Cs-138 3.64E-11 6.98E-11 3.49E-11 0.00E-01 5.15E-11 6.00E-12 3.17E-14 Ba-139 2.73E-02 1.92E-05 7.96E-04 0.00E-01 1.61E-05 1.32E-05 2.44E-01 i Ba-140 1.38E 08 1.69E 05 it.91E06 0.00E-01 5.74E 04 1.14E'05 2.13E 08 Ba-141 1.19E-21 8.90E-25 3.98E-23 0.00E 8.27E-25 6.10E-25 2.54E-27 Ba-142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 La-140 1.81E 03 8.89E 02 2.37E 02 0.00E-01 0.00E-01 0.00E-01 5.11E 07 . La-142 1.30E-04 5.78E-05 1.44E-05 0.00E-01 0.00E-01 0.00E-01 1.76E'00 f Ce-141 2.83E 05 1.89E 05 2.17E 04 0.00E-01 ,8.90E 04 0.00E-01 5.41E 08 ' Ce-143 9.33E 02 6.79E 05 7.58E 01 0.005-01 3.b4E02 0.00E-01 2.04E 07 I Ce-144 5.27E 07 2.18E 07 2.83E 06 0.00E-01 1.30E 07 0.00E-01 1.33E 10 ~ Pr-143 7.01E 04 2.80E 04 3.49E 03 0.00E-01 1.63E 04 0.00E-01 2.31E 08 Pr-144 2.93E-26 1.20E-26 1.49E-27 0.00E-01 6.88E-27 0.00E-01 3.23E-29 Nd-147 3.66E 04 3.98E 04 2.38E 03 0.00E-01 2.34E 04 0.00E-01 1.44E 08 . W-187 3.56E 04 2.90E 04 1.02E 04 0.00E-01 0.00E-01 0.00E-01 7.84E 06 Np-239 1.39E 02 1.31E 02 7.26E 01 0.00E-01 4.10E 02 0.00E-01 2.10E 07 A-40 Rev. 3 6/87 !
)
inatt. A.4 ,$ VEG[TATIONPATHWAYFACTOR i **mram/yr per uC1/sec QilLD(ThFACTORS) NUCLIDE BCNE LIVER T BODY 'DfY1CID KIDNEY IDNG GI-I.LI H-3 .0.00E-01 4.01E 03 4.01E 03 4.01E 03 4.01E 03 4.01E 03 4.01E 03 C-14 8.89E 08 1.78E 08 1.78E 08 1.78E 08 1.78E 08 1.78E 08 1.78E 08 Na-24 3.73E 05 3.73E 05 3.73E 05 3.73E 05 3.73E 05 '3.73E 05 3.73E 05 P-32 3.73E 09 1.58E 08 1.30E 08 0.00E-01 0.00E-01 0.00E-01 9.30E 07 . Cr-51 0.00E-01 0.00E-01 1.17E 05 6.50E 04 1.78E 04 1.19E 05 6'.21E 06 l ler 54 0.00E-01 6.65E 08 1.77E 08 0.00E-01 1.86E 08 0.00E-01 5.58E 08' l . Ph-56 0.00E-01 1.88E 01 4.24E 00 0.00E-01 2.27E 01 0.00E-01 2.72E 03 Fe-55 8.00E 08 4.24E 08 1.31E 08 'O.00E-01 0.00E-01 2.40E 08- 7.86E 07 Fe -59 3.97E 08 6.43E 08 3.20E 08 0.00E-01 0.00E-01 1.86E 08 6.69E 08 Co-58 0.00E-01 6.44E 07 1.97E 08 0.00E-01 0.00E 0.00E-01 3.76E 08 Co-60 0.00E-01 3.78E 08 1.12E 09 0.00E-01 0.00E-01 0.00E-01 2.10E 09 Ni-63 3.95E 10 2.llE 09 1.34E 09 0.00E-01 0.00E-01 0.00E-01 1.42E 06 Ni-65 1.18E 02 1.llE 01 6.51E 00 0.00E-01 0.00E-01 0.00E-01 1.37E 03 , Cu-64 0.00E-01 1.10E 04 6.65E 03 0.00E-01 2.66E 04 0.00E-01 5.16E 05 Zn-65 8.12E 08 2.16E 09 1.35E 09 0.00E-01 3.80E 08 ] 0.00E-01 1.36E 09 1.51E-05 2.19E-05
. Zn-69 Br-83 0.00E-Cl 0.00E-01 2.02E-06 5.38E 00 0.00E-01 0.00E-01 1.33E-05 0.00E-01 0.00E-01 0.00E-01 1.38E-03 3.14E-17
)
Br-84 0.00E-01 0.00E-01 3.85E-11 0.00E-01 0.00E-01 0.00E-01 1.94E-28 Br-85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- Rb-86 0.00E-01 4.52E 08 2.78E 08 -0.00E-01 0.00E-01 0.00E-01 2.91E 07 Ri> 88 0.00E-01 4.43E-22 3.0BE-22 0.00E-Ol' O.00E-01 0.00E-01 2.17E-23
.1 Rb-89 'O.00E-01 1.67E-26 1.48E-26 0.00E-01 0.00E-01 0.00E-01 1.45E Sr-89 3.60E 10. 0.00E-01 1.03E 09 0.00E-01 0.00E-01 0.00E-01 1.39E 09 Sr-90 1.24E 12 0.00E-01 3.15E 11 0.00E-01 0.00E-01 0.00E-01 1.67E 10 Sr-91 5.21E 05 0.00E-01 1.97E 04 0.00E-01 0.00E-Ol' O.00E-01 1.15E 06 Sr-92 7.29E 02 0.00E-01 2.92E 01 0.00E-01 0.00E-01 0.00E-01 1.38E 04 Y-90 2.30E 04 0.00E-01 6.17E 02 0.00E-01 0.00E-01 0.00E-01 6.56E 07 Rev. 3 A-41 l .
6/87
\
VEG[TATION PATHWAY FACTOR
**mram/yr per UCi/sec CHILD (T gFACTORS)
LIVER T BODY 'DfYROID KIDNEY 11NG GI-tLI NUCLIDE BONE Y-91M 8.95E-09 0.00E-01 3.26E-10 0.00E-01 0.00E-01 0.00E-01 1.75E-05 Y-91 1.86E 07 0.00E-01 4.99E 03 0.00E-01 0.00E-01 0.00E-01 2.48E 09 l Y-92 1.59E 00 0.00E-01 4.54E-02 0.00E-01 0.00E-01 0.005-01 4.58E 04 Y-93 3.01E 02 0.00E-01 8.26E 00 0.00E-01 0.00E-01 0.00E-01 4.48E 06 2r-95 3.86E 06 8.49E 05 7.56E 05 0.00E-01 1.22E 06 0.00E-01 8.85E 08 2r-97 5.70E 02 8.24E 01 4.86E 01 0.00E-01 1.18E 02 0.005-01 1.25E 07 Nb 4.11E 05 1.60E 05 1.14E 05 0.00E-01 1.50E 05 0.00E-01 2.96E 08 et>-99 0.00E-01 7.71E 06 1.91E 06 0.00E-01 1.65E 07 0.00E-01 6.38E 06
'It-99M 4.71E 00 9.24E 00 4.86E 01 0.00E-01 1.34E 02 4.69E 00 5.26E 03 i
Tc-101 1.43E-30 U9E-30 1.89E-29 0.00E-01 2.55E-29 7.90E-31 4.75E-30 Ru-103 1.53E 07 0.00E-01 5.88E 06 0.00E-01 3.85E 07 0.00E-01 3.96E 08 i
~Ru-105 9.17E 01 0.00E-01 3.33E 01 0.00E-01 8.06E 02 0.00E-01 5.99E 04 Ru-106 7.45E 08 0.00E-01 9.30E 07 0.00E-01 1.01E 09 0.00E-01 1.16E 10 Ag-110M 3.21E 07 2.17E 07 1.73E 07 0.00E-01 4.04E 07 0.00E-01 2.58E 09 Te-125M 3.51E 08 9.50E 07 4.67E 07 9.84E 07 0.00E-01 0.00E-01 3.38E 08
-- Te-127M 1.32E 09 3.56E 08 1.57E 08 3.16E 08 3.77E 09 0.00E-01 1.07E 09 Te-127 9.85E 03 2.66E 03 2.llE 03 6.82E 03 2.80E 04 0.00E-01 3.85E 05 i Te-129M 8.41E 08 2.35E 08 7.8BE 07 2.71E 08 2.47E 09 0.00E-01 1.03E 09 '
1 Te-129 1.33E-03 '3.70E-04 3.15E-04 9.46E-04 3.88E-03 0.00E-01 8.25E-02 i Te-131M 1.54E 06 5.33E 05 5.68E 05 1.10E 06 5.16E 06 0.00E-01 2.16E 07 Te-131 2.59E-15 7.90E-16 7.71E-16 1.98E-15 7.84E-15 0.00E-01 1.36E-14 l Te-132 7.00E 06 3.10E 06 3.74E 06 4.51E 06 2.88E 07 0.00E-01 3.12E 07 I-130 6.16E 05 1.24E 06 6.41E 05 1.37E 08 1.86E 06 0.00E-01 5.82E 05 I-131 1.43E 08 1.44E 08 8.17E 07 4.76E 10 2.36E 08 0.00E-01 1.28E 07 4 I-132 9.23E 01 1.70E 02 7.80E 01 7.87E 03 2.60E 02 0.00E-01 2.00E 02 I-133 3.53E 06 4.37E 06 1.65E 06 8.12E 08 7.28E 06 0.00E-01 1.76E 06 I-134 1.56E-04 2.89E-04 1.33E-04 6.65E-03 4.42E-04 0.00E-01 1.92E-04 A-42 Rev. 3 6/87
.-...m.
TABLE k.4-3 VE9ETATION PATlWAY FACTOR j
# mram/yr per uCi/see CHILD (Tg FACTORS) .
NUCLIDE BONE LIVER T B00Y THYROIO KIDNEY LUNG GI-LLI 1-135 5.49E 04 9.87E 04 4.67E 04 8.75E 06 1.51E 05 0.00 7.52E 04 Cs-134 1.60E 10 2.63E 10 5.55E 09 0.00 8.16E 09 2.93E 09 1.42E 08 Cs-136 8.15E 07 2.25E 08 1.45E 08 0.00 1.19E 08 1.78E 07 7.87E 06 Cs-137 2.39E 10 2.29E 10 3. 38E ' 09 0.00 7.46E 09 2.68E 09 1.43E 08 Cs-138 5.73E-11 7.97E-11 5.05E-11 0.00 5.60E-11 6.03E-12 3.67E-11 Ba-139 4. 70E-02 2. 51E-05 1. 36E-03 0.00 2.19E-05 1.48E-05 2.71E 00 Ba-140 2.75E 08 2.41E 05 1.61E 07 0.00 7.86E 04. 1.44E 05 1.40E 08 Ba-141 1.71E-21 9.57E-25 5.56E-23 0.00 8.28E-25 5.62E-24 9.74E-22 Ba-142 0.00 0.00 0.00 0.00 0.00 0.00 0.00 La-140 3.25E 03 1.13E 03 3.83E 02 0.00 0.00 0.00 3.16E 07 La-142 2.10E-04 6.70E-05 2.10E-05 0.00 0.00 0.00- 1.33E 01 Ce-141 6.56E 05 3.27E 05 4.86E 04 0.00 1.43E 05 0.00 4.08E 08 Ce-143 1.71E 03 9.29E 05 1.35E 02 0.00 3.90E 02 0.00 1.36E 07 Ce-144 1.27E 08 3.98E 07 6.78E '07 0.00 3.90E 05 0.00 2.59E 09 Pr-143 2.80E 05 8.40E 04 1.39E 04 0.00 4.55E 04 0.00 3.02E.08 Pr-144 0.00 0.00 0.00 0.00 0.00 0.00- 0.00 Nd-147 7.16E 04 5.80E 04 4.49E 03 0.00 3.1E 04 0.00 9.1E 07 __ W-187 1.59E 07 9.40E 06 4.22E 06 0.00 0.00 0.00 1.32E 09 Np-239 2.52E 03 1.83E 02 5.54E 04 0.00 5.29E-02 0.00 1.35E 07 1 4 A-43 Rev. 3 6/87
TABLE A 5-1 GRASS-GOAT-MILK PATHWAY FACTOR m2 . mrem /yr per uCi/see ADULT (Tg FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H-3 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 C-14 2.63E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E407 5.27E+07 P-32 2.05E+10 1.27E+09 7.91E+08 0.00E+00 0.00E+00 0.00E+00 2.30E+09 Mn-54* 0.00E400 7.53E405 0.00E+00 0.'00E+00 2.25E+05 0.00E+00 2.31E+06 Fe-59 3.86E+05 9.07E+05 3.48E+05 0.00E+00 0.00E+00 2.53E+05 3.02E+06 Co-58* 0.00E+00 4.47E+07 9.99E+05 0.00E+00 0.00E+00 0.00E400 9.04E406 Co-60* 0.00E+00 1.46E+04' 3.21E+06 0.00E+00 0.00E+00 0.00E+00 2.47E+07 Zn-65* 1.40E+08 4.44E+08 2.01E+08 0.00E+00 f.97E+08 0.00E+00 2.80E+08 l l Sr-89 3.05E+09 0.00E400 8.74E+07 0.00E+00 0.00E+00 0.00E+00 4.89E+08 Sr-90 9.83E+10 0.00E+00 2.41E+10 0.00E+00 0.00E+00 0.00E+00 2.89E409 Zr-95* 1.98E+03 1.08E+03 4.32E+02 0.00E+00 1.09E+03 0.00E+00 6.49E+06 Nb-95* 8.35E+03 4.63E+03 1.82E+03 0.0DE+00 4.60E403 0.00E+00 2. ale +07 i Ru-103* 1.02E+02 0.00E+00 4.41E+01 C.00E400 3. 91E+02 0.00E+00 1.19E+04 Ru-106* 1.85E+03 0.00E+00 2.34E+03 0.00E+00 3.56E+03 0.00E+00 1.20E+05 Ag-110M* 5.48E+06 5.07E+06 3.00E+06 0.00E+00 9.99E+06 0.00E+00 2.07E+09 Sb-124* 2. 47'E+06 4.66E+04 9.77E+05 5.99$+03 0.00E+00 1.90E+06 6.99E+07 I-131 3.55E+08 5.08E+08 2.91E+08 1.67E+11 8.72E+08 0.00E+00 1.34E+08 I-133 4.65E+06 8.09E+06 2.47E+06 1.19E+09 1.41E+07 0.00E+00 7.27E+06 Cs-134 1.70E+10 4.04E+10 3.30E+10 0.00E+00 1.31E+10 4.34E+09 7.06E+08 ~ Cs-136 7.07E+08 3.11E+09 2.24E+09 0.00E+00 1.73E+09 2.37E+08 3.53E+08 Cs-137 2.21E+10 3.03E+10 1.98E+10 0.00E+00 1.03E+10 3.42E+09 5.86E408 Ba-140* 3.12E+06 3.91E+03 0.00E+00 1.33E+03 2.24?+03 6.58E+06 2.05E+05 Ce-141* 2.96E+03 2.00E+03 0.00E+00 9.23E+02 0.00E+00 3.15E+01 2.27E+02 Ce-144* 1.91E+05 7.97E+04 0.00E+00 4.73E+04 0.00E+00 6.43E+07 1.97E+04 i A-44 Rev. 3 6/87
TABLE A.5-2 GRASS-GOAT-MILK PATHWAY FACTOR m2 .mren/yr per uCi/sec TEEN (Tg FACTORS) , NUCLIDE BONE LIVER T B00Y THYROID KIDNEY LUNG GI-LLI H-3 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 P-32 3.78E+10 2.34E+09 1.46E+09 0.00E+00 0.00E400 0.00E+00 3.17E+09 I 4 Mn-54* 0.00E+00 9.73E+05 1.86E+05 0.00E+00 2.89E+05 0.00E+00 2.98E+06 Fe-59 '6.74E+05 1.57E+06 6.07E+05 0.00E+00 0 00E+00 4.96E+05 3.72E406 Co-58* 0.00E+00 7.65E+05 1.75E+06 0.00E+00 0.00E+00 0.00E+00 1.03E+07 Co-60* 0.00E+00 -2.43E+06 5.54E+06 0.00E+00 0.00E+00 0.00E+00 2.91E+07 Zn-65* 1.81E+08 5.73E+08 2.60E+08. 0.00E+00 3.84E+08 0.00E+00 3.62E+08 Sr-89 5.61E409 0.00E400 1.61E+08 0.00E+00 0.00E+00 0.00E400 6.69E+08 Sr-90 1.39E+11 0.00E+00 3.43E+10 0.00E400 0.00E+00 0.00E400 3.90E+09 Zr-95* 2.58E+04 1.55E+04 8.73E+03 0.00E+00 1.22E+04 0.00E400 6.30E+07 Nb-95 7.18E+03 4.32E+03 2.44E+03 0.00E+00 3.40E+03 0.00E+00 1.77E+07 Ru-103* 1.23E+02 0.00E+00 5.51E+01 0.00E+00 3.69E402 0.00E400 9.61E+03 Ru-106* 1.14E+04 0.00E+00 1.43E+03 0.00E+00 1.52E+04' O.00E+00 5.17E+05 Ag-110M* 2.23E+07 2.07E+07 1.23E+07 0.00E+00 4.06E+07 0.00E+00 8.44E+09 Sb-124* 4.03E+06 7.62E+04 1 ~. 59E +06 9.77E+03 0.00E+00 3.13E406 1.14E+08 _ I-131 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.55E+09 0.00E+00 1.79E+08 I-133 8.49E+06 1.44E+07 4.39E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07 Cs-134 2. 94E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.14E+09 8.62E+08 Cs-136 1.34E+09 5.27E+09 3.54E+09 0.00E+00 2.87E+09 4.52E+08 4.2.4E408 Cs-137 4.02E+10 5.34E+10 3.03E+10 0.00E+00 1.82E+10 7.06E409 7.92E+08 Ce-141* 5.20E+03 3.47E+03 3.94E+02 0.00E+00 1.20E+03 0.00E+00 9.32E+06 I I A-45 Rev. 3
- 6/87 ~ ~ ~ ~ ~ ' ' - - --__n_ . . _ _ _ , _ _ _ _ _ _ . - _ , _ _ _ _ _
TABLE A.5-3 GRdSS-GOAT-MILK PATHWAY FACTOR m2 . mrem /yr per uCi/sec CHILD (TG FACTORS) NUCLIDE BONE ' LIVER T BODY THYROID KIDNEY LUNG GI-LLI t ~ H -3 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 C-14 1.19E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 P-32 9.31E+10 4.36E+09 3.59E+09 0.00E+00 0.00E+00 0.00E+00 2.57E+09 Mn-54* 0.00E+00 8.03E+05 3.04E+05 0.00E+00 2.39E+05 0.00E+00 2.46E+06 Fe-59 1.56E+06 2.61E+06 1.26E+06 0.00E+00 0.00E+00 7.33E+05 2.36E+06 Co-58* 0.00E+00 1.18E+06,3.56E+06 'O.00E+00 0.00E+00 0.00E+00 6.99E+06 Co-60* 0.00E+00 3.75E+06 1.12E+07 0.00E400 0.00E+00 0.00E+00 2.07E+07 Zn-65* 1.49E+08 4.73E+08 2.14E+07 0.00E+00 3.18E+08 0.00E+00 7.33E+05 Sr-89 1.39E+10 0.00E+00 3.97E+08 0.00E+00 0.00E+00 0.00E+00 5.38E+08 Sr-90 2.35E+11 0.00E+00 5.95E+10 0'.00E+00 0.00E+00 0.00E+00 3.16E+09-Zr-95* 6.62E+03 2.77E+03 2.04E+03 0.00E+00 1.16E+03 0.00E+00 4.76E+06 Nb-95* 2.78E+04 1.18E+04 8.69E+03 0.00E+00 4.88E+03 0.00E400 2.05E+07 Ru-103* 3.97E+02 0.00E+00 1.61E+02 0.00E+00 4.16E+02 0.00E+00 1.05E+04 Ru-106* 8.51E+03 0.00E+00 1.06E+03 0.00E+00 3.81E+03 0.00E+00 1.32E+05 Ag-110M* 5.'JE+06 5.42E+06 3.21E+06 0.00E+00 1.06E+05 0.00E+00 2.21E+09 Sb-124* 2.63E+06 4.98E+04 1.04E+06 6. 36E+03 0.00E+00 2.04E+06 7.43E+07 I-131 1.56E+09 1.57E+09 8.94E+08 5.20E+11 2.55E+09 0.00E +00 1.40E +08 I-133 2.06E+07 2.55E+07 9.65E+06 4.74E+09 4. 25E +07 0.00E+00 1.03E+07 ' Cs-134 6.38E+10 1.11E+11 2.35E+10 0.00E+00 3. 54E+10 1.24E+10 6.01E+08 Cs-136 3.02E+09 8.31E+09 5.38E+09 0.00E+00 4.43E+09 6.60E+08 2.92E+08
. Cs-137 9.67E+10 9.26E+10 1.37E+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 Ba-140* 1.35E+0h 1.18E+04 7.94E+02 0.00E+00 1.42E+03 6.93E+03 8.79E+05 Ce-141* 1.26E+04 6.33E+03 9.42E+02 0.00E+00 9.99E+02 0.00E+00 7.94E+06 Ce-144* 8.88E+05 2.78E+05 4.73E+04 ' O.00E400 5.04E404 0.00E+00 7.25E+07
. A-46 Rev. 3 6/87
TABLE A.5-4
. GRASS-GOAT-MILK PATHWAY FACTOR l m2 . mrem /yr per uCi/sec INFANT (Tg FACTORS) -
NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H-3 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+08 5.00E408 5.00E408 5.00E+08 P.-32 1.92E+11 1.13E+10 7.44E+09 0.00E400 0.00E+00 0.00E+00 2.60E+09 pti-54* 0.00E+00 8.03E+05 1.53E+05 0.00E400 2.39E405 0.00E400 2.46E+06 Fe-59 2.92E+06 5.09E+06 2.01E+06 0.00E+00 0.00E+00 1.51E+06 2.43E+06 Co-58* 0.00E+00 2.41E+06 5.89E406 0.00E400 0.00E+00 0.00E+00 6.24E+06 Co-60* 0.00E+00 7.37E+09 1.92E+07 0.00E+00 0.00E400 0.00E400 1.86E+07 In-65* 1.49E+08 4.73E+08 2.14E+08 0.00E+00 3.18E+08 0.00E+00 2.98E+08 Sr-89 2.26E+10 0.00E+00 7.58E+08 0.00E+00 0.00E+00 0.00E+00 5.43E+08 j ( Sr-90 2.48E+11 -- 6.50E+10 -- -- -- 3.19E+09 i I Ir-95* 1.32E+04 5.83E+03 3.47E+03 0.00E+00 1.16E+03 0.00E+00 4.60E+06 Nb-95* 5.54E+04 2.49E+04 1.47E404 0.00E400 4.83E403 0.00E+00 1. 99E407 Ru-103* 8.28E+02' O.00E+00 2.85E+02 0.00E+00 4.16E+02 0.00E+00 1.03E+04 j Ru-106* 1.81E+04 0.00E+00 2.23E+02 0.00E+00 3.81E+03 0.00E+00 1.41E405 Ag-110M* 5.83E+0E 5.42E406 3.21E+06 0.00E+00 1.06E+07 0.00E+00 2.21E+09 Sb-124* 2.63E+06 4.98E+04 1.04E+06 6.36E+03 0.00E+00 2.04E+06 7.43E+07 I-131 3.27E+09 3.85E+09 1.69E+09 1.26E+12 4.49E+09 0.00E+00 1.37E+08 I-133 4.36E+07 6.34E+07 1.86E+07 1.15E+10 7.46E+07 0.00E+00 1.07E+07 Cs-134 1.09E+11 2.04E+11 2.06E+10 0.00E+00 5.25E+10 2.15E+10 5.54E+08 Cs-136 5.91E+09 1.74E+10 6.48E49 0.00E+00 6.92E+09 1.42E+09 2.64E+08
. Cs-137 1.54E+11 1.81E+11 1.28E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 i
Ba-140* 2.84E+07 2.86E+04 1.45E406 0.00E400 1.42E+03 1.75E+04 9.23E+05 Ce-141* 2.69E+04 1.65E+04 1.93E+03 0.00E+00 9.89E+02 0.00E+00 8.00E+06 Ce-144* 1.86E+06 7.37E+05 1.05E+05 0.00E+00 5.04E+04 0.00E+00 7.69E+07 ; Rev. 3 l A-47 1
APPENDIX B TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclides specific. These effective factors, which are based on the total radioactivity released to approximate the dose in the environment, ie, instead of having to sun the isotopic distribution multiplied by the isotope specific dose factor only a single multiplication times the total quantity of radioactive material released would be needed. This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique. Determination of Effective Dose Factors The effective dose transfer factors are based on past operating data. The radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations. AY =1AY +f s eff 4 i i where Ay = the effective gama-air dose factor due to stack releases of
~
S 'If noble gases (mrad /uC1) Ayj = the gesna-air dose factor due to stack releases of each noble gas radionuclides 1 (mrad /pci) fj = the fraction of noble gas radioactivity constituted by radionuclides i
'l Ay = [ Ay f v eff vi i Rev. 3 B-1 6/87
' k!
where AY = the effective gauna-air dose factor due to vent releases of - veff ] all noble gases [ mrad 3 9C1 sec/m ) Ay = the gamma-air dose f actor due to vent rele'ases of each noble vi gas radionuclides 1 (mrad /uci) [ mrad s) i uCi sec/m A8 =1A6 a f . eff i i J where A6 = the effective beta-air dose factor due to either vent or eff stack releases _of all noble gases [ mrad g uCi sec/m3 AS = the beta air dose factor.due to either vent or stack i - releases of each noble gas radionuclides 1 [ mrad *utis 3 To determine the appropriate effective factors to be used and to evaluate j the degree of variability, the atmospheric radioactive effluents for the past 3 years have been evaluated. Table B-1 presents the radionuclides distribution for stack and vent releases I 1
-- as measured by isotopic analysis of periodic grab samples from the i respective effluent release points. Table B-2 presents the effective dose factors (gsuna-air and beta-air) derived on the basis of the; radionuclides j distribution. 4
{
. l Except for the year 1981, the variability of the effective factors is minor. ,
For 1981, Xe-138 contributes significantly to the derivation of the ; effective factors for stack releases. The Xe-138 contributions for the years l
'I Rev. 3
- B-2 6/87 .
l .
y
. 't ,
1 1979 and lf?O is not,so signifyant. This increase 1,n Xe-138 from 1981 resultiin a larger variabili,ty of the yearly. values from the e.verage than r what i corisidered typical. Therefore, in order to assure adequate .,
^'
l conservatism, the effective d6se factors for stack releases will be based on the radionuclides distribution for the year 1981. Because this is considered an atypical distribution resulting in higher doses, use of the data will (- provide dose, estimates whir.h are conservative. As more data become , avaiiable to further establish a typical radionuclides distribution, the effective [Ae fa$ tors for <stacksrhieases#may be reevaluated. }
)>
t To pjovide vi additional degree { 1f conservatism, a f actor of 0.8 is , introducedg into the dose calcu1Eional process when the effective dose i J h, r . I h transfer factor is used. This added. conservatism provides additional \ assurance that the evaluation of doses by the use of a single efhetive - factor will not significantly underestimate any actual doses in the if I
} environment!
4
.)
1 l 1 L/ By evaluating doses using these effective dose factors, maximum allowable ,- I releases of noble gases for any calendar quarter.may be determined. As .I discussed in Secthn 3.5.1, the maximum allowable rkleases)tsed on the
/
gama-air affectiva dose factor have been determined to be 250,000 C1/ quarter f,ordtack releases and 12,700 L's/ quarter for vent releases. l - t e, f For the beta air effective dose factors, the releases of noble gases l / correspondingtothequarterYylimitof10mradscorrespondsto 307,000 m/ P Ci/ quarter for stack releases and-M,600 Ci/quarth for " vent releases. . l Cowparing $nese values for allowable 6 7elenes with the valuts based on the I gamma-air e"ffective dose factdbs, it is bnstrated that t(e pawn sir 5 I i doses are more restrictive than the beta-air dos 6. In other wurds, the 4 doses calculated by using the gamma-air affectiva dose # actors represent' 6, 1arger fraction of the allowable dose than,doeg t). dose calculated by uy tg O the beta-air effective cose f actors. Therefore, whed using the effectiven i dose f actors for evaluating compliance with the guarterly dose. limits bf
'r_v p at y ,
/>
+
i
) .4 (
J * {( Rev. 3 B-3 6/87 'b > !
>* , _ y
t Technical Specification 3.15.3, only the grana-air dose need'be evalu'ated; compliance with the gamnia-air dose limit. represents a de facto compliance with the beta-air dose 117it. , Reevaluation , The doses due to the gaseous effluents are evaluated by the more detailed ! l calculational methods (i.e., use of nuclide specific dose factors) on a l yearly basis. it that time, a comparison can be made between the simplified method &nd the del 4 fled method to assure the overall reasonableness of this l limited analysis approach. If the comparison 1.ndicates that the radionuclides distribution has changsd' significantly, thereby causing the
~
simplified method to underestimate the doses, the value 'of the effective factors will need to be reexamined to assure the overall acceptability of this approach' However, this reexamination will only be needed if the doses as calculated by the detailed analysis exceed 50% of the design bases doses I (i.e., greater t$an 50% of the 10 mrad gamma air dose or 20 mrad beta air dose). 8
)
d Rev. 3 B-4 - 6/87. - u_._________._._____.____________________________ ___-___m_.__ _ _ __ _ . _ _ . . _ _ _ _ _ _ _ __ _.__________-__________-_______________s
i i Table B-1 i i RADIONUCLIDES DISTRIBUTION OF STACK AND VENT RELEASES i Radionuclides Fraction of Total Releases i Stack Vent i 1979 1980 1931 1979 1980 1981 Kr-85m .11 .05 .09 .02 -- -- Kr-87 .01 -- .02 -- . 01 -- Kr-88 .07 .04 .08 -- -- -- Xe-133 .76 .82 .45 .24 . 24 .14 Xe-135 -
.01 .02 .03 .72 . 50 .59 Xe-135m -- .02 .08 .02 . 22 .21 Xe-138 .02 .06 .25 --
. 03 .05 e
9 wm 1 e j 1 l 1 Rev. 3 I B-5 . 6/87
R Table 8-2 J EFFECTIVE DOSE FAQTORS NOBLE GASES - AIR DOSES i Year Stack Releases Vent Releases Ganma-Air
- Beta-Air Gamma-Air Seta-Air Effective Effective Effective ' Effective Dose Factor Dose Factor Dose Factor Dose Factor Arseff A8 seff Ayy ,ff A8 ,ff mead mead mead l
l (mrad /uC1) (C1.sec/m) u 3 [Cisec/m) p 3 '[ y9C1sec/m) 3 1979 7.0x10 42 5.9x10-5 5.0x10-5 6.5x10- 5 1980 6.7 x10-12 5.3x10- 5 6.7 x10- 5 6.0x10-5 1981 1.6x10-12 9.3x10- 5 6.4x10- 5 6.3 x10- 5 Avg. 9.9x10-12 6.8 x10- 5 6.4 x10- 5 6.3x10- 5 i I l l l l I Rev. 3 8-6 6/87
APPENDIX C { WATER PATHWAY SITE-SPECIFIC DOSE TRANSFER FACTORS (Ag) Table C.1 Fish and Potable Water Conseption Pathway Fact 6r (Ag) Table C.2 Irrigated Food (Strawberry) Conseption Factor-(Aj) I e o eem q l I 4 Rev. 3 ' C-1 6/87
NOTES FOR TABLE C.1 l FISH AND POTABLE WATER CONSUMPTION PATHWAY FACTOR (Aj) ]' mrem /hr per uCi/mi TA j = 1.14E5 (Ug /Dy+Up BFg ) DF g where DW = Dilution factor taken to be 1.0 at DAEC for this formulation ) Ug = Water consumption, in kg/yr Up = Fish consumption in kg/yr , DFg = Dose conversion factor from Tables A.3 A.3-4, Regulatory Guide 1.109 (Rev 1) (mram/pC1)
]
BFj = Bioaccumulation factor in fish pCi/kg per pCi/1 from l Table A.1-1, Regulatory Guide 1.109 (Rev 1)
-- A dilution factor of 5 at DAEC for fish conseption is applied to the ,
)
discharge concentration.. If there is no fish conseption, a dilution factor of 10 is used for potable water dos'e estimates. l l 1 j Rev. 3 C-2 6/87 l
1 NOTES FOR TABLE C.2 i i IRRIGATED FOOD (STRAWBERRY) CONSUMPTION PATHWAY FACTOR (Aj) arem/hr per uCi/ml 84y(1-5 i D) E jth
~
1 TAj = Uap + DFSj [ Tv *Ei F Aj where Uap = Strawberry consumption in (kg/yr) estimated as follows: Adult 23 f Teen 15 Child 11 i Inf ant ' 0 DFS$ = Regulatory Guide 1.109 (Rev 1) dose conversion factors (mram/pCi) and all other parameters are described in Regulatory Guide 1.109 (Rev 1) Table E-15. Table E-1 ) except AE which = 14+A and Ag = decay constaint for the individ,ual isotope in hr-1 me i O i e Rev. 3 C-3 6/87 .
TABLE C.1-1 FISH AND POTABLE WATER CONSUMPTION PATHWAY trem/hr per uCi/ml ADULT (Ag FACTORS) NOCLIDE BCNE LIVER T BODY THYBOID KIDNEY WNG GI-! *.I H-3 0.00E-01 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8.96E 00 C-14 - 3.15E 04 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03 NA-24 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 P-32 4.622 07 2.87E 06 1.79E 06 0.00E-01 0.005-01 0.00E-01 5.20E 06 CR-51 0.00E-01 0.00E-01 1.49E 00 8.945-01' 3.29E-01 1.98E 00 3.76E 02 ftF54 0.00E-01 4.76E 03 9.08E 02 0.005-01 1.42E 03 0.005-01 1.46E 04 fek56 0.00E-01 1.20E 02 2.12E 01 0.00E-01 1.52E 02 0.00E-01 3.82E 03 FS-55 8.87E 02 6.13E 02 1.43E 02* 0.00E-01 0.00E 3.42E 02 3.52E 02 FE-59 1.40E 03 3.29E 03 1.26E 03 0.00E-01 0.00E-01* 9.19E 02 1.10E,04 CD-58 0.00E-01 1.51E 02 3.39E 02 0.00E-01 0.00E-01 0.00E-01 3.06E 03 CIF60 0.00E-01 4.34E 02 9.58E 02 0.00E-01 0.00E-01 0.00E-01 8.16E 03 NI-63 4.19E 04 2.94E 03 1.41E 03 0.00E-01 0.00E 0.00E-01 6.07E 02
~
. NI-65 1.70E 02 2.21E 01 1.01E 01 0.00E-01 0.00E-01 0.00E-01 5.61E 02 CD-64 0.00E-01 1.69E 01 7.93E 00 0.00E-01 4.26E-01 0.00E-01 1.44E 03 IN-65 2.36E 04 7.50E 04 3.39E 04 0.00E-01 5.02E 04 .0.00E-01 4.73E 04 ZN-69 5.025 01 9.60E 01 6.67E 00 0.00E-01 6.24E-01 0.00E-01 1.44E 01
~BR-83 0.00E-01 0.00E-01 4.38E 01 0.00E-01 0.00E-01 0.00E-01 6.30E 01 BR-84 0.00E-01 0.00E-01 5.67E 01 0.00E-01 0.00E-01 0.00E-01 4.45E-04 BR-85 0.00E-01 0.00E-Ol 2.33E 00 0.00E-01 0.00E-01 0.00E-01 1.09E-19 )
RS-86 0.00E-01 1.03E 05 4.79E 04 0.00E-01 0.00E-01 0.00E-01 2.03E 04 1 RS-88 - 0.00E-01 2.95E 02 1.56E 02 0.00E-01 0.00E-01 0.00E-01 4.07E-09 RS-89 0.00E-01 1.95E 02 1.37E 02 0.00E-01 0.00E-Oi- 0.00E-01 1.13E-ll SR-89 4.78E 04 0.00E-01 1.37E 03 0.00E-01 0.00E-01 0.00E-01 7.66E 03 SR-90 1.18E 06 0.00E-01 2.88E 05 0.00E-01 0.00E-01 0.00E-01 3.40E 04 SR-91 8.79E 02 0.00E-01 3.55E 01 0.00E-01 0.00E-01 0.00E-01 4.19E 03 SR-92 3.33E 02. 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01 6.60E 03 y-90 1.38E 00 0.00E-01 3.69E-02 0.00E-01 0.005-01 0.00E-01 3.46E 04 i y-91M 1.30E-02 0.00E-01 5.04E-04 0.00E-01 0.00E-01 0.00E'01
- 3.82E-02 Y-91 ,
2.02E 01 0.00E-01 5.39E-01 0.00E-01 0.00E-01 0.00E-01 1.llE 04 . Y-92 1.21E-01 0.00E-01 3.53E-03 0.00E-01 0.00E-01 0.00E-01 2.12E 03 l l- Rev. 3 l ,
. 6/87
\
TABLE.C.1-1 FISH AND POTABLE WATER CONSUMPTION PATHWAY
.aram/hr per uC1/ml )
ADULT (Ag FACTORS) l i NUCLIDE BCNE LIVER T BODY 'HfYROID KIDNEY IDG GI-LLI Y-93 - 3.83E-01 0.00E-01 1.06E-02 0.00E-01 0.00>01 0.00E-01 1.22E 04 ER-95 2.77E 00 8.88E-01 6.01E-01 0.005-01 1.39E 00 0.005-01 2.82E 03 EA-97 1.53&01 3.095-02 1.41E-02 0.005-01 4.67E-02 0.005-01 9.57E 03 so-95 4.47E 02 2.49E 02 1.34E 02 0.00E-01' 2.46E 02 0.00E-01 1.51E 06 MD-99 0.00E-01 4.62E 02 8.79E 01 0.00E-01 1.05E 03 0.005-01 1.07E 03 tc-99M 2.94E-02 8.325-02 1.06E 00 0.00E-01 1.26E 00 4.07E-02 4.92E 01 I TC-101 3.03E-02 4.365-02 4.28F01 0.00E-01 7.85E-01' 2.235-02 1.31E-13 - 10-103 1.98E 01 0.00E-01 8.54E 00 -0.00E-01 7.57E 01 0.00E-01 2.31E 03 RD-105 1.65E 00 0.005-01 6.525-01 0.00E ,2.13E 01 0.00E-01 1.01E 03 i 1 RD-106 2.95E 02 0.00E-01 3.73E 01 0.00E-01 5.69E 02 0.00E-01 1.91E 04 AG-110M 1.33E 01 1.23E 01 7.32E 00 0.00E-01 2.42E 01 0.00E-01 5.03E 03 TE-125M 2.79E 03 1.01E 03 3.74E 02 8.39E 02 1.13E 04 0.00E-01 1.11E 04 TE-127M 7.05E 03 2.52E 03 8.59E 02 1.80E 03 2.86E 04 0.00E-01 2.36E 04 TE-127 1.14E 02 4.11E 01 2.48E 01 8.48E 01 4.66E 02 0.00E-01 9.03E 03 TE4129M 1.20E 04 4.47E 03 1.89E 03 4.11E 03 5.00E 04 0.00E-01 6.03E 04 TE-129 3.27E 01 1.23E 01 7.96E 00 2.5'1E 01 1.37E 2 0:00E-01 2.47E 01 TE-131M 1.80E 03 8.81E 02 7.34E 02 1.39E 03 8.92E 03 0.00E-01 8.74E 04 TE-131 2.05E 01 8.57E 00 6.47E 00 1.69E 01 8.98E 01 0.00E-01 2.90E 00 TE-132 2.62E 03 1.70E 03 1.59E 03 1.87E 03 1.63E 04 0.00E-01 8.02E 04 I
.I-130 9.01E 01 2.66E 02 1.05E 02 2.25E 04 4.15E 02 0.00E-01 2.29E 02 l
. I.131 4.96E 02 7.09E 02 4.06E 02 2.32E 05 1.22E 03 0.00E-01 1.87E 02 I-132 2.42E 01 6.47E 01 2.26E 01 2.26E 03 1.03E 02 0.00E-01 1.22E 01 I-133 1.69E 02 2.94E 02 8.97E 01 4.32E 04 5.13E 02 0.00E-01 2.64E 02 I-134 1.26E 01 3.43E 01 1.23E 01 5.94E 02 5.46E 01 0.00E-01 2.99E-02 I-135 5.28E 01 1.38E 02 5.10E 01 9.11E 03 2.22E 02 0.00E-01 1.56E 02 C5-134 3.03E 05 7.21E 05 5.89E 05 0.00E-01 2.33E 95 7.75E 04 1.26E 04 cs-136 3.17E 04 1.25E 05 9.01E 04 0.00E-01 6.97E 04 9.55E 03 1.42E 04 cs-137 3.88E 05 5.31E 05 3.48E 05 0.00E-01 1.80E 05 5.99E 04 1.03E 04 CS-138 2.69E 02 5.31E 02 2.63E 02 , 0.00E-01 3.90E 02 3.85E 01 2.27E-03 BA-139 9.00E 00 6.41E-03 2.64E-01 0.00E-01 5.99E-03 3.64E-03 1.60E 01
~
C-5 Rev. 3 6/87-
TABLE C.1 1 FISH AND POTABLE WATER CONSUMPTION PATHWAY crem/hr per uC1/mi-ADULT (A; FACTORS) NUCLICE BCNE LIVER T 907f MINOID KINEY wtC GI-LLI BA-140 1.88E 03 2.37I~00 9 .23E 02 0.00E-01 8.05E-01 1.35E 00- 3.88E 03 BA-141 4.37E CO 3.30E-03 1.48E-01 0.00E-01 3.07E-03 1.87E-03 2.06E-09 BA-142 1.98E 00 2.03E-03 1.24E-01 0.00E-01 1.72E-03 1.15E-03 2.78E-18 IA-140 3.58E-01 1.80E-01 4.76E-02 0.00E-01 0.00E-01 0.00E-01 1.32E 04 IA-142 1.83E-02 8.33E-03 2.07D-03 0.00E-01 0.00E-01 0.00E-01 6.08E 01 CE-141 8.01E-01 5.42E-01 6.15E-02 0.00E-01 2.52E-01 0.00E-01 2.07E 03 CE-143 1.41E-01 1.04E 02 1.16E-02 0.00E-01 4.60E-02 0.00E-01 3.90E 03 CE-144 4.18E 01 1.75E 01 2.24E 00 0.00E-01 1.04E 01 0.00E-01 1.41E 04 PR-143 1.32E 00 5.28E-01 6.52E-02 0.00E-01 3.05E-01 0.00E-01 5.77E 03 PR-144 4.31E-03 1.79E-03 2.19E-04 0.00E'-01 1.01E-03 0.00E-01 6.19E-10 ND-147 9.00E-01 1.04E 00- 6.22E-02 0.00E-01 6.08E-01' O.00E-01 4.99E 03 W-187 3.04E 02 2.55E 02 8.90E 01 0.00E-01 0.0'0E-01 0.00E-01 8.34E 04 NP-239 1.28E-01 1.25E-02 6.91E-03 0.00E-01 3.91E-02 0.00E-01 2.57E 03 40 9 6 9 4 O C-6 Rev. 3 6/87
PROCESS CONTROL PROGRAM FOR DEWATERING WET RADIOACTIVE SOLID WASTE
. PRCP-A Revision 2 February 19, 1987 Duane Arnold Energy Center Iowa Electric Light and Power Company Approved by: () #b
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5 spervisor Date Radwaste 5 Approved by: v f.m,4iL 2-27-97 Date Radiation Protection Supegvisor __ Reviewed by: .
;-E M 3d#7 Chair ~ man, Op Date ' ( '
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Introduction This Process Control Program describes the dewatering of wet radioactive waste solids from liquid systens at the Duane Arnold Energy Center and packaging the waste in a high integrity container (HIC). These Wet wastes are those wastes produced fran the liquid radwaste treatment system. wastes may typically be 5escribed as resins (bead and powdered), filter material, waste ' sludges, and filter precoat media. The wastes included in this progran are specifically those containing nuclides with a radioactive half-life greater than 5 ' The dewatering process years and a concentration in the resin of greater than ICi/m3 removes liquid from the waste in a HIC to meet the criterion in 10 CFR Sections 61.56 (a)(3) and 61.56 (b)(2) for free-standing liquid. Stability is provided by the high integrity container as authorized by Section 61.56 (b)(1). Vendor
' Westinghouse Hittman Nuclear and Development Corporation of Coltsnbia, Maryland, is the vendor of the dewatering and packaging services and of the RADLOK" high integrity containers used at the DAEC. Hittman personnel perfonn the dewatering and packaging operations descMbed herein.
~ Dewatering System Description The Hittman dewatering system employs dewatering equipment to dewater the wet radioactive waste solids in a HIC. The Hittman system consists of an overflow drisn, container level indicators, and interconnecting piping and valves. Figure 1 is a diagram of the dewatering system as it is typically configured. A waste-filled HIC is dewatered in the radwaste building loading bay using dewatering equipment which is located in the radwaste building. The dewatering system uses service air supplied by the DAEC and exhausts air into the DAEC Radwaste' Ventilation Systen. Water removed fran the HIC, during dewatering, is returned to thesDAEC radwaste system and is' treated as liquid rsdwaste.
l 1 2 of 7 02/19/87 - Rev. 2
The Hittman dewatering system is equipped with instruments to provide infomation about the dewatering process. These include mechanical and electrical liquid level Vacus gauges indicate indicators with sensors in the HIC and vacuum receiver tank. Drainable liquid tests are amount of vacuum in the vacuum receiver tank and HIC. performed using a vacuum pump and vacum bottle (VB-1 in Figure 1.) to verify liquid content of the HIC prior to shipment. Operation _ l The radioactive wastes that are dewatered and packaged in a HIC for disposal are ) a normally, but not limited to, wastes from the condensate phase separators, reactor
- water cleanup phase separators, waste sludge tank, spent resin tank, or concentrated waste tank.
i Wastes from any of the above mentioned systems are piped to a waste holding tank which is piped directly to the vendor's equipment. The wastes are transferred to the HIC
.using the vendor's equipment as shown in Figure 1. A conductivity probe near the top of the HIC interior that actuates- an audible alarm and light provides an indication of the waste level during the HIC filling and after dewatering.
After a HIC is filled with waste, dewatering is perfomed by pulling a suction on an underdrain manifold in the HIC until loss of suction occurs. Loss of suction is _. indicated by a decrease in vacutsn in the vacuum receiver tank to 10 inches Hg or less on the vacuum gauge. Pump down by suction on the bottom underdrain manifold is continued for a specified time with the dewatering pump and the vacuun punp. A drainable liquid test is perfomed by allowing the HIC to rest for a stated time, then siphoning from the bottom underdrain manifold for a specified time to remove any liquid that has drained into it. The drainable liquid test is passed if the volume of water removed is less than a volume demonstrated by the vendor to indicate less than 1% l free-standing liquid in the waste for the HIC being tested. I 4, 5} ONLY , ; 3 of 7 ' 02/19/87 . Rev. 2 l
In the event the waste in the HIC does not pass the drainable liquid test, a cycle of caiting a specified time, operating the dewatering and vacuum pumps, waiting a - specified time, and then perfoming a drainable liquid test is repeated until the free-standing liquid criterion is met. Specific times appropriate for the HIC and caste being dewatered have been detennined by the vendor and are stated in the dewatering procedure. Essential Waste Characteristics and Verification The requisite characteristics of the radioactive waste addressed by this Process Control Program are stated in 10 CFR Section 61.56. The wastes subject to the process control plan are fra sources within the DAEC that are well characterized and generally recognized as meeting the essential qualities of Section 61.56 (a), other than (a)(3). By knowing the source and kind of each of the subject wastes, IELP is able to ensure that the qualities of the wastes continue to meet, the requirements of Section 61.56 (a), other than (a)(3), and are compatible with l
'the HIC itself. In addition, the DAEC's chemical control program helps prevent listed substances from being admitted into the waste streams that are deposited into the HIC.
10 CFR Section 61.56 (b) includes provisions for stability of radioactive waste after its disposal . For the wastes covered by this PRCP, Iowa Electric intends to provide
- that stability by placing the waste in a high integrity container that will be stable af ter disposal as authorized in Section 61.56 (b)(1).
Both 10 CFR Sections 61.56 (a)(3) and 61.56 (b)(2) require as little free-standing and
- noncorrosive liquid as is reasonably achievable and no more than 1% of the voltrne of the waste when the waste is in a disposal container designed to ensure stability. Iowa Electric intends to accomplish this be dewatering as described herein and to perform surveillance to assure that it has been done. For a given type of waste, the operating procedure requires the vacuum pump be operated for stated time interval (s). Dewatering is considered complete when the volse of liquid that can be' suctioned fram the HIC during a defined time is no great.er than an amount stated in the operating procedure pertaining to that kind of waste. The conditions stated in the procedure will have been demonstrated by the vendor of the dewatering seWice to achieve less than 1%
free-standing water in the waste. 4 of 7 02/19/87 - Rev. 2
PRCP-A High Integrity Container-Wastes covered by this PRCP will be packaged in RADLOK" high integrity containers. The containers have been certified by the South Carolina Bureau of Radiological Health for the intended use. Each container wilt be visually inspected before use for acceptable condition of:
- 1. Sealing components,
- 2. Exterior surface,
- 3. Dewatering tubes, and j
- 4. Dewatering verification tube.
I After filling and dewatering has been completed,. the fill port opening in the. container is closed in accordance with written procedures. The procedure requires verification- j that the closure gasket is in place and that the threaded fill port lid is tightened to l
' a specified torque value. ]
Quality Assurance - Control of the dewatering and packaging processes is maintained by conducting these operations according to written procedures addressing HIC inspection before filling, dewatering, HIC closure, t.nd cask loading. The vendor verifies and docurnents that key. ) steps have been performed. Iowa Electric maintains assurance that dewatering and packaging is performed as intended by separately verifying and documenting that the key steps were perfomed. - j l l Iowa Electric's quality assurance progran is subject to 10 CFR Part 50, Appendix B, as applied to dewatering and packaging of radioactive waste. 5 of 7 02/19/87 . Rev. 2
Administration The Radiation Protection Department maintains or requires the vendor to maintain procedures which will ensure that all applicable requirements are met prior to shipment , of radioactive waste. Iowa Electric Light and Powr will review applicable vendor's operating procedures before authorizing the vendor to dewater radioactive was'te. Site specific procedures developed by the vendor for the DAEC will be reviewed by the q i Operations Committee. Processing procedures internal to the vendor will be reviewed and approved by the vendor. The Radwaste Group of the Radiation Protection Department j is responsible for ensuring compliance with the PRCP, for vendor oversight, and for l recordkeeping. At least once every 24 months, IELP will audit the radwaste Process Control Progran and operating procedures that implement it (in accordance with Technical Specification 6.5.2.8.j.) Any change to the Process Control Program will be made in, accordance with Technical Specification 6.15, approved by the Plant Superintendent-Nuclear, reviewed by the Operations Comittee, and submitted to the NRC in the next Serni-Annual Radioactive
' Material Release Report after the change is made.
Trainin_g l Before a vendor employee perfonns a dewatering or packaging procedure that is subject _ to this PRCP, they must have received relevant training, and Iowa Electric. must have received documented confirmation of their training along with a statement of their qualifications. References
- 1. DAEC Radwaste Handling Procedures l 2. Westinghouse Hittman Nuclear Incorporated procedure STD-P-03-008, " Transfer and Dewatering Powdered Resin in Hittman RADLOK"-100 or -200 Containers with a Flexible Underdrain Assembly to Less Than 1% Drainable Liquid".
l
- 3. Westinghouse Hittman Nuclear Incorporated procedure STD-P-03-010. " Transfer and Dewatering Bead Resin in Hittman RADLOK'-100 or -200 Containers with Single Layer Underdrain Assembly to Less Than 1% Drainable Liquid".
6 of 7 02/19/87 - Rev. 2
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PROCESS CONTROL PROGRAM FOR LIQUIDS AND WET RADIOACTIVE MATERIAL I
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f PRCP-B ' 1 i Duane Arnold Energy Center i Iowa Electric Light and Power Company Approved by: 0"'/f4 %g / -7 0 -f6 (/ Date RadwasteCyrdinator Approved by: / w /-3l'8b Rabiation Prot ~ection Su ri r Date r- . .;
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chairman Date {Co9ittee Approved by: 2-12 86 Plant Superintendent-Nuclear Date l l I h'M I@[w 6
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1 01/22/86 Rev. 0
INTRODUCTION This Process Control Program (PRCP) describes the solidification, absorption and/or stabilization of liquids and wet waste materials produced at the DAEC. These wastes, regardless of their classification, are processed to assure that the final product is acceptable for transportation and will meet the disposal site license conditions. Liquid wastes consist of contaminated aqueous solutions, oils, neutralized acids, solvents, sludges, antifreeze and other liquids 'all of which may be mixed with one another or in pure form. Wet material wastes may consist of mops, rags, anti-contamination clothing, machine turnings and other material or equipment which may. contain sufficient residual liquid 'to warrant special processing. VENDOR i The DAEC's Radwaste Group normally processes all waste; however, a vendor may be
~
utilized to process large volume quantities of liquids or liquids with special containment characteristics. Shoul'd a contract vendor be utilized to process and package the waste on site in the future a vendor's topical report shall be required. The vendor's topical report will be reviewed to assure that they are compatible with plant requirements. If the vendor has an approved typical report, it shall be l referenced in DAEC's PRCP. If the vendor does not have an approved topical report, the vendor's topical report will be included in the DALC PRCP by reference and submitted to the NRC for review and approval. l l 2 01/22/86 Rev. 0
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1 SYSTEM DESCRIPTION ] The liquids and wet waste materials processing systems are composed of an approved absorption or solidifying agent,17H 55 gallon drums or metal LSA boxes, transfer pumps ) and mixing equipment if required.
~
a Liquids waste which is to be absorbed will require the use of equipment such as a ]) liquid transfer pump and volume measuring containers. In adfiticr., mixing equipment, consisting of a mortar mixing trough and/or a motor driven one yard concrete mixer, is used to assure that the absorbent is well blended with th'e liquid. Absorbed wastes are blended with the absorbent and then transferred to a shipping container. j Liquid waste which is to be s'olidified will also require the use of. a transfer pump and a volume measuring device or container. Liquids are mixed with the solidifying media l l l inside the shipping drum. Aqueous wastes generally do not require the use of mixing ) equipment, however, oils and neutralized acids will require a one-half inch electric motor equipped with a stirring rod. Figure 1 illustrates the various liquid waste
~ package systems typically psed at the DAEC.
OPERATION Liquids to be absorbed are inspected for the quality of the material prior to absorption and sampled to determine the radioactivity. An isotopic analysis is also performed. A 17H 55 gallon shipping dra is prepared by placing a layer of absorbent in the bottom, then two plastic bag liners and layer of absorbent in the bottom of the liner. The shipping dra is then positioned inside the controlled area adjacent to the mortar mixing trough. A measured volume of the liquid, usually twelve to fifteen 3 01/22/86 Rev. O
gallons, is mixed with an absorbent in either the concrete mixer or the mortar mixing trough until a reasonably dry mixture is achieved. The absorbed mixture is then transferred into the bag liner, on top of the abs'orbent layer, and topped off with another layer of absorbent. The layers of dry absorbent on the bottom and top of the absorb'ed liquids assure that the container meets the DOT required absorbent ratio. The dr a lid is lightly secuted and the drum inverted for the 24 hours and then inspected for free standing liquid. Liquid wastes to be solidified are also inspected for quality and sampled for radioactivity. A 17H 55 gallon shipping drum 'is placed inside the controlled area, j l adjacent to the container of contaminated liquid, and the liquid to be solidified is pumped into the new drum. The solidifying media is added and the mixture stirred if necessary. The dra is allowed to stand overnight and inspected 24 hours later for free standing liquid. It is not necessary to invert the solidified drum because the solidified matrix is heavier than the liquid hence any free lig'uid will be forced to the surface. I __ Wet trash and other material which cannot be dried are packaged in a 55 gallon drum or a metal LSA box for shipment. The LSA box is prepared by placing approximately one inch of absorbent and then a plastic liner into the box and then a one inch layer of absorbent in the liner. The wet trash is then placed into the box by layering < l approximately 12" of material and covering with approximately one inch of absorbent until the waste is about two inches from the top of the box. The liner is sealed and i the box lid secured. A free liquid inspection is performed after 24 hours by removal- l of the bottom drain plug in the LSA Box. The 55 gallon dra is prepared by i 4 01/22/86 Rev. 0- _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ . _ _ m _ . _ . . _ . _ _ _ - . _ .
placing approximately four inches of absorbent and then two liners into the dra and then about two inches of absorbent into the liner. The wet trash is placed in the drum by layering approximately six inches of material and covering with about two inches of absorbent until the level is two inches below the top of the dr a. The liners are sealed and the dre lid secured. The dra is stored upside-down for at least 24 hours and then inspected for free standing liquid. Essential Waste Characteristics and Verification The requisite characteristics of the radioactive waste addressed by this Process Control Program are stated in 10 CFR Part 61.56. The wastes subject to the process control program are from sources within the DAEC that are well characterized and generally recognized as meeting the essential qualities of Part 61.56(a), o.ther than (a)(3). By knowing the source and kind of each of the subject wastes, IEi.P is able to ensure that the qualities of the wastes continue to meet the requirements of Part 61.56(a), other than (a)(3), and are compatible with the
~
stabilizing nedia and the container itself. 10 CFR Part 61.56 (b) includes provisions for stability of Class B and C radioactive waste after its disposal. Only Class A waste forms are covered by this PCP hence Part 61.56(b) is not applicable. 10 CFR Parts 61.56 (a)(3) require as little free-standing and noncorrosive liquid as is reasonably achievable, and no more than 1% of the volume. Iowa Electric intends to accomplish this by the processes as described herein and to I perform surveillance to assure that it has been done. For a given type of waste, the Radwaste Handling Procedures require an inspection for free liquids 24 hours after packaging and corrective action as necessary. 5 01/22/86 Rev. O
Ouality Assurance i i Control of the absorption and solidification processes is maintained by conducting ,i these operations according to written. procedures addressing packaging of contaminated liquids and wet or oily ' trash. Procedures also identify requirements for container I control, handling and inspection, handling and closure of metal drtsns, handling and closure of metal LSA boxes, and requirements for transportation of waste to the various authorized disposal site (s). l An extensive quality control audit program with appropriate hold and witness points is included in the Radwaste Handling Procedures. Administration The Radiation Protection Department maintains procedures which will ensure that all applicable requirements are met prior to shipment of radioactive waste. In the event a vendor's service is required, IELP will review applicable vendor's operating procedures before authorizing a vendor to process radioactive waste. The Radwaste Group of the Radiation Protection Department is responsible for ensuring compliance with the PCP, Vendor oversight, and for record keeping. At least once every 24 months, IELP will audit the Radwaste Process Control Program and operating procedures that implement it (in accordance with Technical Specification 6.5.2.8.j.) Any change to the Process Control Program will be made in accordance with l Technical Specification 6.15, approved by the Plant Superintendent-Nuclear, reviewed by l the Operations Committee, and submitted to the NRC in the next Semi ' Annual Radioactive
- Material Release Report after the change is made.
6 01/22/86 {. ( ,. , Rev. 0 .
Training-t Before an'IELP or a vendor employee performs a packaging procedure that is subject to this PRCP, they must .have received. relevant training, and Iowa Electric must have documented confirmation of the training.
References:
- 1. DAEC Radwaste Handling Procedures 4
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t i l l PROCESS CONTROL PROGRAM FOR SOLIDIFICATION OF WET RADIOACTIVE SOLID WASTE PRCP-C Revision 1 February 19, 1987 Duane Arnold Energy Center Iowa Electric Light and Power Company . I l k Approved By: 9A NM 1 li'O i i Date Rapaste Supfrvisor l Approved By: b Radi F ion P e m 6 .d iong5upervisor
- 2. - I L - 9 7 Date r ,T
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Reviewed By: _. 1-3-87 Chaitm ,L perations Commf thee Date 1 3 \ 3-f-[1 l I Approved By: Plant Superintendent - Nuclear Date l 1 of 11 02/19/87 Rev. 1 . 1
1 1 1 Introduction This Process Control Program describes the solidification and packaging of j wet radioactive waste solids from the liquid systems at Duane. Arnold Energy Center in steel liners. Wet wastes are those wastes generally produced from the liquid radwaste treatment system. These wastes are typically described as waste sludges, filter precoat media, both bead and powdered resins, filter material and activated charcoal. The wastes included in this program are specifically those containing nuclides with a radioactive half-life greater than five years and a concentration in the f resin of greater than ICi/m . The solidification proces's meets the stability criterion as stipulated in 10 CFR 61.56 (a) (3) and 61.56 (b) (1), (b) (2). Stability is provided by the process solidification nedia. , Vendor Westinghouse Hittman Nuclear Inc. of Columbia, Maryland, is the vendor of the solidification and packaging services ct Duane Arnold Energy Center DAEC. Westinghouse Hittman personnel perform the transfer, solidification i i' and packaging process described herein. Solidification System Description The Westinghouse Hittman Nuclear Inc. solidification system contains several modular interconnecting components which are described herein. (Figure 1. Solidification Process, Typical Configuration) 2 of 11, 02/19/.87 Rev. 1 ,
Hydraulic Power Unit (Power Pack) ' The Hydraulic' Power Unit consists of an electric motor which requires 480-volt /100 amp service, a hydraulic pump, oil reservo',r, anh control panel all mounted on a roll about stand. The unit also has devices which 1-regulate the oil. temperature within an operating range. , Mixer Head Drive Assembly The Hydraulic Mixer Head Drive assembly delivers power to the mixing blade 1 within the liner used in the incontainer solidification system. The Mixer I. Head Drive Assembly is operated by high pressure bil supplied from the . power pack described above by two high pressure hydraulic hos,es equipped 3 with quick disconnect fittings. The Mixer Head Drive Assembly is 3 controlled from the power pack control panel mounted on the Hydraulic Power Unit. j
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Level Control Panel The Level Control Panel is mounted on a roll about stand and is divided into two subsystems; primary and secondary level control systems. The , primary systen is used to control the desired operating level of resin , j slurry during the waste transfer and dewatering. The secondary level 't
. control system is used to indicated a higher level than the normal 7
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t ., operating level in the liner by sounding an alarm. ,/ L l I I I
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S Cement Feed Sysdi Controb Lanel i. 3 , ? J' ' The, Cement Feed System Control Paneihis mounted on the same roll about ,
, , .. ,u > i stand as the Level Controi Panel. Thedement Feed Penel controls the
's .
0 (Iement hopper, vibreor,Wfexiconldive mor;r 'ah f/ust collector. 1 4 f I j / r; ; i 4 < y
\
Flexicon Dry Camrr. l } t b(;ed 'dstem s' , The Flexicon cement feed systemk:ransports dry cement from the cement This is ' accomplished byV,ihj a 4 hegrtotpeMixer'headDr,1ve,se,embly. screw drive essembly houssiin an ultra'high molecular weight polyethylene % q 9
/- ..
tube. *The motor for this drivif is also mou:ted on the Mixer Head DMye
's 't Assedly. '
.c 1o a 2-DewaterjngPumpSkid i ..\
q , The Westinghouse Hittman Nuclear Iw. standarif Ditatering ' Pump Skid is a ] multipurpose Unit designed to pump McN1 $1.1 slurries, and can be used sq \- s! 4 i i to dewater wet solid wastes. It is prim'trf'1j> . :s intenced to be used in the v processing and packaging of lon.levp? radior.ct%e waste although it can be
.9 sed as a general purpoge pump. The pump is a double diaphragm air driven ?,
L
, ,m g with air supplieb '$c a maxim'um of 100 psi and 40 cfm. It
\bdporates a 'strget supressor, lubricator and regulators. Vacuum, j
>, .i
- diwharge pl/ ssure, and flow gauges monitor operating conditions. The comp 1'ete tssembly is mounted in a conf'iguration so that any leaks are contained on the bottom of the skid. The skid is equipped wMn tidrain plug $d a gasketed bolt on the shipping cover, 7
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C'ement Hopper i The Cement Hopper is a carbon steel bin aith a sloped bottom capable of l holding 65 cubic feet of cement. Mounted on the sloped portion of the hopper are two air powered vibrators which are used to keep the cement fluid. ; l Dust Collector , l I The Dust Collector is used to keep a negative pressure on the Cement Hopper to keep cement' dust to a minimum. .The dust collector contains fabric filters which remove cement dust from the discharged air.- I l Steel Liners. , The incontainer dewatering and solidification system uses specially designed steel liners. The liners are equipped wit.h internal ~ ' mixer assemblies driven by.the Hydraulic Mixer Head Drive assemble. System Operation The Westinghouse Hittman Nuclear Inc. system uses a batch mixing technique where concentrated or wet solid wastes are mixed with dry cement and - .; additives inside the liner. The liner also serves as the burial I container., The final product is a free' standing nonolith meeting all the j burial criteria as- stipulated by the Code of, Federal Regulations 10 CFR l 61.56. Prior to system operation, an appropriate liner is selected depending on the waste type to be processed. The liner is inspected aryd' installed in the process shield. The mixer head and sealing gasket are installed and the final connections of the vent and over flow lines, waste inlet 1.ine, level indicators and alarms are made. The dewatering pump skid connections and dry feed cement system complete the modular connections.
. L 5 of 11 02/19/87 ~
Rev. 1.
- f. ,
. < l
Waste Transfer and Dewatering The waste transfer and dewatering process is initiated from the Level Control Panel by'the " Process Start" button. Switches for the fill / divert valve and dewatering pung are turned to the " auto" position. When this is done the following actions occur: First waste enters through the waste transfer hose from the fill / divert valve to the steel disposable liner. . Waste continues to fill the liner until it reaches the "hi" probe of the level control system. When the waste reaches this point the dewatering pump automatically energizes and the fill divert / valve closes. The clurry is dewatered through the underdrain system in the steel liner until the "lo" probe of the level control system is cleared. The fill / divert valve opens again and the warta rises in the liner until the wasi;e reaches the "hi" probe and the fill / divert valve automatically closes. This series of events continues until the waste is dewatered but does not fall below the level of the "lo" probe. Test Solidification As required by the Radiological Effluent Technical Specifications for
. PWRs and BWRs the PCP is used to verify the solidification of at least one representative sample of at least every tenth batch of waste to be solidified. If any test specimen fails to solidify, processing of the suspect batch is suspended until such time as additional specimens can be obtained. Alternative solidification parameters are then selected and tested in accordance with the Westinghouse Hittman Nuclear Inc. Process Control Program until a test verifies solidification. When this proves satisfactory, solidification is resumed using the alternate solidification parameters. The following criteria define acceptable solidification process and process parameters.
- ) f O Ni_Y 6 of 11 02/19/87 Rev. 1 -
l
- 1. The sample solidification contains no free standing liquid.
- 2. Upon visual inspection it appears the waste would hold its shape if removed from the vessel.
- 3. It resists penetration with a flat metal probe about .125" diameter.
After successful completion of the test solidification the necessary ) amounts of cement. and additive are computed using the test solidification data sheet from the PCP. , i i Essential Waste Characteristics and Verification The requisite characteristics of the radioactive waste addressed by this i Process Control Program are stated in 10 CFR Section 61.56. The waste subject to the process control plan are from sources within the DAEC that ] are well characterized and generally recognized as meeting the essential qualities of Section 61.56 (a). 10 CFR Section 61.56 (b) includes provisinns for stability of radioactive waste after its disposal. For waste covered by this PRCP, Iowa Electric intends to provide the stability by the very process of the waste itself thus meeting stipulation 10 CFR ! 61.56 (b) (1). Both 10 CFR Sections 61.56 (a) (3), and 61.56 (b) (2) < require as little free standing water as possible and no more than 1% by
~
volume. Iowa Electric intends to accomplish this by solidification , described herein and to perform surveillance to assure that it has been done. For a given type of waste the Westinghouse Hittman Nuclear Inc. PCP requires a test solidification with certain parameters to guarantee stability. The conditions stated in the procedure pertaining to that waste type will have been demonstrated by the vendor of the solidification service to achieve less than 1 % free standing water in the waste. l l l 7 of 11 02/19/87 Rev. 1 .
- 1 kncontainer Solidification Liners I
Waste covered by this PRCP will be packaged in incontainer solidification carbon steel liners. The containers have been accepted by the State of South Carolina and Washington for the intended use. Each container will be inspected before-use for the acceptable conditions listed below.- , 1
- 1. Mixer blade and shaft
- 2. Dewatering underdrain
]
- 3. Dewatering hose
]
- 4. Mixer drive alignment pin !
- 5. Operating level probes and pigtail ,
- 6. Exterior surface for gouges or dents After solidification the container is inspected for free standing liquid and hardness of the solidified product. After being found acceptable the container is capped and ready for shipment. .
.1 Quality Assurance Control of the solidification and packaging processes is maintained by conducting these operations according to written procedures addressing - preuse liner inspections, test solidification, transfers, and shipping.
The vendor verifies and documents that key steps have been done. Iowa Electric maintains assurance that solidification and packaging is performed as intended by separately verifying and documenting that the key steps were performed. 1 Iowa Electric's quality assurance program is subject to 10 CFR part 50, j Appendix B, as applied to solidification and packaging of radioactive waste. I 8 of 11 02/19/87 : Rev. 1 . l
' Administration 1
The Radiation Protection Department maintains or requires the vendor to maintain. procedures which will ensure that all applicable requirements are met prior to shipment of radioactive wastes. Iowa Electric Light 'and Power will review applicable vendor's operating procedures before authorizing.the vendor to transfer, package or solidify radioactive waste.
' Site specific procedures developed by the vendor for the DAEC will be reviewed by the Operations Committee. Processing procedures internal to l the vendor will be reviewed and approved by the vendor. The Radwaste Group of the Radiaion Protection Department is responsible for ensuring compliance with the PRCP, for Vendor oversight and recordkeeping.
At least every 24 months, Iowa Electric Light and Power will audit the-radwaste Process Control Program and operating procedures that implement
- it (in 'accordance with Technical Specification 6.5.2.8.j). Any ' change - to the Process Control Program will be made in accordance with Techni, cal-Specification 6.15, approved by the Plant Superintendent - Nuclear, reviewed by the Operations Committee, and- submitted to the NRC in the next Semi-Annual Radioactive Material Release Report after the change is made.
Training. Before the vendor employee performs the solidification or packaging ' process that is subject to this PRCP, they must receive relevant training, and Iowa Electric must have received documented confirmation of their training along with a statement of their qualifications. ; l l 9 of 11 02/19/87 l Rev. 1 . l
References ,
- 1. DAEC Radwaste Handling Procedures ,
- 2. Westinghouse Hittman Nuclear Inc., Procedure STD-P-05-001, PCP for )
Incontainer Solidification of Powdered Resin l
- 3. Westinghouse.Hittman Nuclear Inc., Procedure STD-P-05-004, PCP for Incontainer Solidification of Bead Resin
- 4. Westinghouse Hittman Nuclear Inc., Procedure STD-P-05-011, PCP for ,
Incontsiner Solidification of Granular Activated Carbon
- 5. Westinghouse Hittman Nuclear Inc.. Procedure STD-P-05-040, PCP for Assembly and Operating Procedure for Hydraulic Drive Solidification .
System
- 6. Westinghouse Hittman Nuclear Inc., Technical Specification, TS-12000, Field Assembly and Operating Procedure for Hydraulic Mixer Drive.
Assembly.
- 7. Westinghouse Hittman Nuclear Inc., Technical Specification, TS 13000, Field Assembly and Operating Procedure for Flexicon Cement Feed System. .
- 8. Westinghouse Hittiman Nuclear Inc., Technical Specification, TS 15000, Field Assembly and Operating Procedures for Powdered Resin Transfer and Dewatering System
.- 9. Westinghouse Hittman Nuclear Inc., Technical Specification, TS 18000, Power Distribution and 1.evel Control Module Field Assembly and Operating Procedure
- 10. Westinghouse Hittman Nuclear Inc., Technical Specification, TS 25000, 4 Dewatering Pump Skid Operating Procedure I
l 10 of 11 02/19/87 Rev. 1 . I
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i PROCESS CONTROL PROGRAM FOR DEWATERING ION EXCHANGE RESINS AND FILTER MEDIA (PACIFIC. NUCLEAR SYSTEMS, INC.) PRCP-D Revision 1
. February 19, 1987 Duane Arnold Energy Center Iowa Electric Light and Power Company Approved By: MA -
b 21I' ; Date Radwpste Superv sor QC Approved By: _ ( E v d4 p m -iv 2.- 7 c. dr 7 Radiation Pr l ervisor Date W . Reviewed By: _. o _ _m 3-5-87 t' ,a rm n, 9pera't Committee . Date Approved By: O_
^
*! 3~ T~ 07 Plant 5 superintendent - Nuclear Date R7hS9&bstW $ty 1 of 21 02/19/87 Rev. 1 .
1 1 Introduction l This Process Control Program describes the dewatering of wet radioactive waste solids from liquid systems at the Duane Arnold Energy Center and packaging the waste in suitable' containers for burih1. Wet wastes are those wastes. produced from the liquid radwaste treatment system. These wastes may typically be described as resins (bead and powdered), filter material, waste sludges, and filter precoat media. The wastes included irl this program.are specifically those containing nuclides with a radioactive half-life greater than 5 years and a concentration in the resin of greater than.1Ci/m3 The dewatering process removes liquid from the waste to meet.the criterion in 10 CFR Parts 61.56 (a)(3) and 61.56 (b)(2) for free-standing liquid. Stability is provided by a high integrity container (HIC) as authorized by Part 61.56 (b)(1). Vendor Pacific Nuclear Systems, Inc. through its operating subsidiaries Nuclear
. Packaging, Inc. and NuPac Services, Inc. is a vendor of dewatering and
~
packaging services of the high integrity containers used at the DAEC. Nuclear Packaging, Inc. Topical Report No. TP-02-P-A, Rev.1, has 'been j reviewed by the NRC and accepted for reference by the licensee. The acceptance letter and NRC Safety Evaluation Report are included as Attachment A. e 2 of 21 02/19/87-Rev. 1 ,
Dewatering System Description i The NuPac Dewatering Unit is a portable or permanent in-plant system containing all necessary equipment and controls for rertoving the free water from ion-exchange resins and filter media. It consists of a dewatering fill bead, a piping skid, a blower skid, a water chiller, a control system and the necessary interconnecting hoses and cables. Figure 1 is a diagram of the dewatering system as it is typically configured. The NuPac Dewatering unit is designed to interface with NuPac's line of disposable containers. These containers will be furnished with factory installed internals functionally identical to those used during qualification testing. The internals will be free-standing and self-supporting, without protuberances which might, (in case of polyethylene containers) damage the container. l I The dewatering fillhead serves as the interface between the dewatering 1 l equipment and the disposable container. The lower portion of the fillhead has a set of doors which allow easy access for connecting to, and disconnecting from the container internals, The fillhead seals to the i upper portion of the neck of the container and is held in place by j gravity. l l The upper portion of the dewate' ring fillhead is divided into a piping section and an enclosed electronics section. The piping section is .the connection point for all hoses to and from the fillhead and includes a manual isolation valve for the waste line. This valve prevents any material remaining in the waste hose from spilling during movement of the fillhead to and from the container. l h tl \ VN L. y 3 a l 3 of 21 02/19/87 Rev. 1 , l
The electronics section is enclosed and waterproof. It houses the fillhead' instrumentation and the CCTV' Camera and light. It also serves to interf ace the control system and the container. The piping skid houses the water separator, the dewater pump, the valve manifold and the relative humidity instrument. It is the interface between the dewatering fillhead, the blower skid, the water chiller and the plant. The relative humidity instrument is of the optical chilled mirror type and is used to directly measure the dew point and temperature of the air stream. ine relative humidity monitor is located near the control, panel. The blower skid supplies the correct temperature and quantity of air to f acilitate drying of the resin, and is operated after the bulk of the water has been removed. It is equipped with temperature instrumentation,
~
interlocked such that it will shut down automatically on high temperature. Air is continuously circulated in a loop from the blower to the container and back to the blower again through the water separator. During this process, air is bled off the discharge of the blower as required to maintain a slightly less than atmospheric pressure on the container. The air passes through a HEPA filter prior to entering the plant ventilation system. The water chiller is a weather proof, free-standing unit, used to cool the
. air as it passes through the water separator enroute to the blower. This prevents over heating of the blower as well as serving to condense the water vapor in the air stream, aiding the resin drying process.
The control system consists of a control panel which contains all the necessary controls and interlocks for safe and efficient operation of the system plus a CCTV system used to monitor container operations and a radiation monitor with a detector probe mounted on the waste inlet line. 4 of 21 02/19/87 ! Rev. 1 , J
Operation The radioactive wastes that are dewatered and packaged in a HIC for disposal are termally, but not limited to, wastes from the condensate phase separators, reactor water cleanup phase separators, waste sludge tank, spent resin tank, or concentrated waste tank. Wastes from any of the above mentionded systems are piped to a waste holding tank which is piped directly to the vendor's equipment. The HIC is filled from the plants' transfer system until the solids leve.1 in the container reaches the maximum level. A combination of level' detection instrumentation and a remote TV camera installed in the fillhead give the' operator indication of container levels. An automatic isolation valve will close on a HiHi level alam to prevent overfilling the container. After the liner is filled the pumpable water is removed using the dewatering pump. Specific procedures for processing bead or powdered resin provide operating parameters for the pumpdown cycle. I When all of the pumpable water is removed as indicated by pump suction pressure, the blower and chiller are started to begin the drying cycle.
~~
The blower adds warm dry air to the resin bed and this air strean picks up moisture during transit through the resin bed., The warm moist air then is directed to the entrainment separator tank where refrigeration coils . cause the moisture to condense. This condensate is removed by the dewatering pump. { m*v ,ml:nuamg i 1
%' ' i f 1 i a 4, f \/
%.e J %j *u. 0 5 of 21 Og/j9/g7
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The air entering the entrainment separator tank is periodically monitored for % relative humidity. After the dewatering pump has completed its required pumping time and the 5 relative humidity is below-the predetermined endpoint the liner is considered to be dewatered. Prior to shipment of processed containers the' radwaste group will perfom an independent verification that'the container is dewatered by pulling a vacuum on a tube' installed on the bottom of the HIC. Essential Waste Characteristics and Verification The requisite characteristics of the radioactive waste addressed .by this Process . Control Program are stated in 10 CFR Part 61.56 The wastes subject to the process control plan are from sources within the
. DAEC that are well characterized and generally recognized as meeting the essential ' qualities of Part 61.56 (a), other than (a)(3). By knowing the source and kind of each of the subject wastes, IELP is 'able to ensure that the qualities of the wastes continue to meet the requirements of Part 61.56 (a), other than (a)(3), and are compatible with the HIC itself. In addition, the DAEC's chemical control program helps prevent listed substances from being admitted into the waste streams that are deposited into the HIC. -
Nuclear Packaging's Process Control Procedures are used during the initial
. waste stream characterization to verify that DAEC waste is similar to that waste used during the system qualification and testing program. After s
each waste is characterized the NuPac Process Engineer will determine the ) minimum pumping time for each waste strean and' provide-the endpoint l determination curves for the relative humidity calculation. If any waste stream changes occur which will cause the characterization to be invalid (i.e. change of resin manuf acturer or oil intrusion) the ' aste w stream must be analyzed and the characterization performed again.
. 6 of 21 '
02/19/87 Rev. 1 4
10 CFR Part 61.56 (b) includes provisions for stability of radioactive waste after its ' disposal. For wastes covered by this PCP, Iowa Electric intends to provide the stability by placing the waste in a high integrity container that will be stable after disposal as authorized in Part 61.56 (b)(1). Both 10 CFR Parts 61.56 (a)(3) and 61.56 (b)(2) require as little free-standing and noncorrosive liquid as is reasonably achievable and no more than 1% of the volume of the waste when the waste is in a disposal container designed to ensure stability. Iowa Electric intends to accomplish this by dewatering as described herein and to perform surveillan:e to assure that it has been done. For a given type of. waste, the operating procedure requires the dewatering system be operated for. stated time interval (s). Dewatering is considered complete when the relative humidity of the air stream. leaving the. liner is below a , predetermined valve and the required drying time is completed. The. conditions stated in the procedure have been demonstrated by the Nuclear Packaging Qualification Testing of the dewatering service to achieve less , than 1% free-standing water in the waste. High Integrity Container l \ Wastes covered by this PCP will be packaged in Nuclear Packaging HICs. The containers have been certified by the South Carolina Bureau of Radiological Health for the intended use. C of C number DHEC-PL-012. l F t t 7 of 21- 02/19/87~ Rev. 1
i Each container will be visually inspected before use for acceptable condition of:
- 1. Sealing components, ,
- 2. Exterior surface,
- 3. Internal. filter assemblies, 4 Lifting equipment.
After filling and dewatering has been completed, the fill port opening in the container is closed in accordance with written procedures. The procedure requires verification that the closure gasket is in place and that the threaded fill port lid is tightened to a specified torque value. Quality Assurance Control of the dewatering and packaging processes is maintained by conducting these operations according to written procedures addressing HIC inspection prior to filling, the dewatering process, HIC closure, and cask loading. The vendor verifies and documents 'that key steps have been performed. Iowa Electric maintains assurance that dewatering and packaging is ! performed as intended by separately verifying and documenting that the key steps were performed. Iowa Electric's quality assurance program is subject to 10 CFR Pa'rt 50, Apendix B, as applied to dewatering and packaging of radioactive waste. , 8 of 21 02/19/87 Rev. 1 .
The Radiation Protection Department eaintains or requires the vendor to maintain procedures which will ensure that all applicable requirements are met prior to shipment of radioactive wastes. Iowa Electric Light-and , Power will review applicable. vendor's operating procedures before authorizing the vendor to dewater radioactive waste. Site specific procedures developed by the vendor for the DAEC will be reviewed by the
~
Operations Comittee. Processing procedures internal to the vendor will be reviewed and approved by the vendor. The Radwaste Group of _ the Radiation Protection Department is responsible for. ensuring compliance I with the PRCP, for Vendor oversight and record keeping. At least every 24 months, Iowa Electric Light and Power will audit the radwaste Process Control Program and operating procedures that implement it (in accordance with Technical Specification.6.5.2.8.j.). Any change to the Process Control Program will be made in accordance with Technical Specification 6.15, approved by the Plant Superintendent - Nuclear, reviewed by the Operations Comittee, and submitted'to the NRC in the next
~
Semi-Annual Radioactive Material Release Report after the change is made, j l
, Training Before the vendor employee performs a dewatering or packaging procedure that is subject to this PCP, they must have received relevant training, and Io'wa Electric must have received documented information of their j training along with a statement of their qualifications. ~
i References
- 1. DAEC Radwaste Handling Procedures i
1
- 2. Proprietary Topical Report No. TP-02-P-A, Rev.1, covering Nuclear l
Packaging, Inc. Dewatering System 9 of 21 02/19/87 Rev. 1 4
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- NUPAC DEWATERING SY' STEM TYPICAL CONFIGURATION. ,
FIGURE 1 PAGE 2 0F 3 NUPAC DEWATERING SYSTEM , TYPICAL CONFIGURATION _
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NUPAC DEWATERING SYSTEM TYPICAL CONFIGURATION
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rICutt i race 3 or 3 NUPAC DEWATERING SYSTEM TYPICAL CONFIGURATION
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12 of 21 02/19/87 Rev. 1 ,
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FOR NUPAC DEWATERING SYSTEM l i l l ATTACRMENT "A" PAGE.1 of 9
~
l - NRC AFF10 VAL AND SAFETY EVALUATION F0E NUPAC DEVATERING SYSTEM O unmm erate f*J, . mucum neovuto.av _ e, 388tW88P E' 1888 1 nr. nimere 7. neelsig. > oiene asemw=i . mesleer sec a c as. tas. ! toto see m asstn serwt - SEPis 385 pesent nr. mes,.,.e esens Boer Mr. Ilsele192
' susacri accyranct PW 8tFROClas OF UCINrtas twical, mery fp.ar.s Bt!!3IDE 1. *1RN2SR 7eCIAGINE. INC. EkATERING sTITDI* ~
We have esseleted ear egeries of tne setjeet testel resort seestttes by
,,..- nesteer Paczeging tes. py letter estes Augnet is 19se. tes fine the resort to be estestsele der ro*erencing to Itqnt meter egoctor Itcense eseltsetiene to me estone sesei*tes one easer me Iteitettens seltmoetse in me = sert j ens tne associates tec e,eluetten. unie is enclosse. The evelseeion ee*1aes se tests for secostsace af me reeert. We stil receiro met aselicants er licensees me reference mis toetsel reser* es-elee snetr sum smeros for classify 1ag inste in essereenes.wto 10 CFR Part $1. sectica 41.5(.
We se act totene to rosest ese revise of. the sortset deser9ted is tne resset one es ene secooteele unea tne resort esseert as a refervace to Itconse eselicartene. escoot to assure met the meteMel omsentes is eestissele to one ssecifts plaat tweelves. Our secessoase eseltas.enly to me meters q deseMbes te We reser% fa escorennep ett spesserne esteeltsted in WEG.4390. It is russestes that WeCleer IeC2e(1ag. Iot. suolish estestos forsteps of 1W9: remete preer9eter!' ene asa-omersetery, weeta tarse esatas of reestet of ets le*ter. The acesset ==prions smell taeoreente tant letter ens tne eastenee e eleotten temesa me title esgo ens the sostrect. The acceptes ve=Ttams peelt taeluee se .4 feasignettay accoo*es'. *ntlewing sit resset essattfiestion spl. shnold eer eMter9e er reselettees ehengt.sse**est one eeneloeieme as to tne accernettity of tne essem are tavet'es'.es. ansteer Posseeng. los, ene/or tne eselicente referencing the tedical resort rett to nessetos to revise one ressesnt meir resserttee meise. er tueett Jeetttterten for me -
- eenetamed e**settve senttene111ty of the sosial resort etteous reetstem of meir resseettee seasonaties.
slesents. O ' ' O. Y: = Cecil L f% eses. Chief stoneettietten eos seseist
- Pmsecte trouse 91 states of 1,leenstag
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13 of 21 02/19/87 Rev. 1 i
_ - . ~ ~ . - - - ~ ~ ~ ~ - - FOR NUPAC DEWATERING SYSTEM . i~ I l ATTACHMENT "A" 'PAGE 2 of 9 i NRC APPROVAL AND SAFETT EVALUATION
~
^
FOR NUPAC DEVATERING SYSTEM 25WiE5. SArtTT tvatustten etwier
.P-Josart numer: 7p.42.P. Rev. 1 Resort 7ttles nuclear featsiing DeustaMag 3rstas Originating organisattom: auclear Pastattet. las.. Fesaret Way. WA g,,,,,e 4 notaemlegy and Effluent Trutuant treme. O!!. HRR 1.0 t"M* ION The nuclear Passaging Demetemns trstan (the suPac $rstas) setitzes esmatering eastgment ans s1sposants masta captainers to 4. ster rasteactive spent head and poseeres ruins. and filter prec34ts. The sometaMag pmaass uses an air.4Mwan positive displasumefrt pas to estata a cantiamous suction en a masta entainer a reeve the talk of tres ester. Thes the str blauer rectratates air taresen the assis omstainer ans usue sesorear a factittata
~ erying et tas main, hse processes rueve summaste Itaid from tse mesta contatner to a preestarstand and.petst is assareance wits one aupac process centrol progres ta seat Os free sunstagytesid critaMa sct forts in Sectten 81.54(a)(3)of10CFRPart$1. Vassmas y are prwiese at enca unsts
, entist emnoction ens semifold.. Jbs metai removes free a sesta esaminer is rearnes to me user's.11mid reemasta systan. -
e the 4 of me nuPac tra . 1 n ==cas $. asser .ip s.ct1= ti.. .f m. sta n a.i. riu tuni, t.ei.e me = ui r i.orn.:
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ATTACHMENT A Page 3 of 9 - NRC APPROVAL AND SAFETY EVALUATION-FOR NUPAC DEWATERING SYSTEM I ATTACHMENT."A" l PAGE 3 of 9 NRC AFFROVAL AND SAFETY EVALUATION FOR NUPAC DEWATERINC SYSTEM
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esteempt descreetten. process entroI*irogree, ans esitty nearesas progrus. The dessertag process tmets Not* Pasionettve unete to east reestmements to IN:.8cessa femenical positten. Cf33113. Revisten 2 to SRp Section 11.4 The process is est latensed to eset the maste stne111ty fene er classiftstian remetrements to 10 CM part it. leuclear passaging schott".ed sesartte topical reseMs se IHgh !stegrity Captainers for !stC eveism and soevevel. la these retteus by the le453 staM. the stnc*grel laterrity of the NUPAC apstainers is betag evelsated to ensure long-tern isolatim of lem level restsactive unsta. free tas sett eNetroMt. ' z.s passp The seeip and eserstian of the eUPAC Sretas are esecrthes la estall to me j turaC retcal asem. TP-42.p. Rev. 8 me g.1 and Asprt 8.13H am . June 25,195E reseIsetively. la the rtoff's era,1$,tten of the IIIPAC Srstaa. I the staff emnetderess '
. (1) The seveses entrol e assure suelen emeter,., of set seite reeneste.
(Z) Desip provistens fossreerstes to the nestament and syrtem emely to reasse testage ans anstre: one seester ,,teeses er ,setese;,,e occi , to the esviresumst. - e 15 of 21
$/19{87 y
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ATTACHMENT A Page 4 of 9 NRC APPROVAL AND SAFETY EVALUATION FOR NUPAC DEWATERING SYSTEM- - l 1 I i
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ATTACHMENT "A" PAGE 4 of 9 NRC APPROYAL AND SAFETT ETALUATION FOR NUFAC DEWATERING SYSTEM 3 (u no.ti= - - ,- a mstge.,e.,1....s. moon,n m e syntes. (4) Typical toterfaces ette tas rese1er plant. (I) lieets constner totemel destge. (6) Provisions to sentret estantial asemerwis etecties to deustering ten escriemge rests. (7) Rasiation ymtec en serign *estures. he eUPaC Systen esoststs of a esmetemag mera sustateur, a esustering seas, as off ges vent unit. 4 aortainer level insicster. 4 meste fill heed, a wter _ ~_ . senarecer vita unter atller enit. an alr timer. 4 mlative turietty instrummt, a sentrol semel, aes 1steveemeettog piping and velves. after.*eet* remasta Pres Se eser*8 plant is merged fem a GraC meste
. asetatner, emete-1eg is aante,es ete asoceses mettes e a ears seatstner prwridad by toe amatortag game. The resideal free unter to tie meste sentainer te ressved by restrustarten of shag air perieus bp the air blauer.
vertnes evens ses aussert of tittert are esas =tmia the usate assutaer in ! ete e wrt sun,1gencene a main ses. resis ans filter presset stortils, star f.e,= free me === es.staer is mer.= = me ener.,11.,4 i The esmatertog puso ts seerstes for gte time totervals le essorence wie me W 8C PPWs888 M8tF9IePWgrm. The puestag ttag my penge pyg gjget ge 16 of 21
$19{87
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FOR NUPAC DEWATERING SYSTEM l ATTACRMENT "A" PAGE 5 of 9 Ntc' APPROVAL AND SAFETT EYALUATION FOR NUPAC DEWATERING SYSTEM
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sisteen heart deseMing uten tres of unstes and mese seeminert. After est of me free meter to tse meets emptainer has been'reussed, drying air is emntinuously esientated to a teos from me.atr tiener a tne meste sustainer enceugn tse seene sesoretor es rumsve aar restehaal free unser la me neste entainer. The Nupac $rstes is previses sta tamerence instreewaties i unta is laterleased to ammustiestly shut emme the emetertog process on htga atr temperature ene to potential asetnemtc reaction in demetering to essaange resin. . The unsta container is consteent demeterug what the volume of allectable ttate.and relative hustetty in the recirculating erying sie meet the asemetanes arttaria sescifies in the supaC preemas sentrol program. A
, relative huuHetty instrumspt ans Emmitgr are previesg a mately sat ,
eastinuously sustter tse unsta estateer outlet ate. This lettrement is used ts estan11sa purttive sus seist to the ensatoring preemas. The tesical resort emnerthes WPet 9merts prennes Centrol Programs (pCpt) for emmtergag samt head rests las filter oressem fer ensagertag a moore, mat tne emmeteres unste anstainers east me free stesstog 11sts crieerta set eers to lostian 51.98(a)(3) of 10 Crt port St., The PCps are soreleses basse en me actual test results en erstnasta listi etained frus sometering masts seatstners and from sme nuessenet rens tests en someteres unste, anstainert.
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NRC APPROVAL AND SAFETY EVALUATION' FOR NUPAC DEWATERING SYSTEM ,
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, ATTACHMENT "A" . PAGE 6 of 9 NRC APPROVAL AND SAFETT EVALUATION POR NUPAC DEWATERING SYSTEM 8
f. The stem metmed me W4C emnetaring test preemmerse and is ogsalta.
.P eentled denotertog operating and saintanense presseuru.' and acessumes eMteria deser4hed to the testal repert. The smM finns the NUPAC e acamptease artterta and esmetering test russite seet the free, stanstag itsete artteria to 18.CFR Port 81 ame sac areams Teessial Posteten ETIR 113. Rev. 2 {
a.e more, ore. .m. nnes - W,= ,,,, m ,e _ie. 1 l no atemene or 1tets reemastas are miaases to the enlivenment free the ouPAC emastering eserssies. The esmatered 11esta rammastas are castes to me eser's Itaid reemaste systes ans resta drytag air is ventes to the eser's eM gas ryt*.ae. The WPAC $rrtes is sesignes a pre,est encontralles releasm of roeienettve enterints by sentiering.Itats levels ta me unsta seatstner by a level taoicator, taring sne maste filltag eserse:es. the sporene is reeutres a to sutioned near the entral panel and vtonally esatter the maste trens'er
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presassw'ing the vides sentter ano me resistien smetter prov1ded. Ceres or etter anans to seesta taaevertent spilts 's[everdtous' a will be proviese by
. the user with fieme areine resses a toe user's 1tste reemasta esliestten rFstems. +
e The senteousasse er a matte esmetering sentetser fallere releasing resiomettve starsals to a potsele uster smooly is site esponeant ans will to e,eleistes for inoivtemal lleense asellestians. The stem fines tais nupaC esmatering preessa ano meses assutmer eastge meet ene reestruent of Seatten 20.105 of 10 CPR Part B. Settle W.34e of W CIPhrt N. ans ,Generel Design ' m ,er . m. ., a.m.. r, .. gno @f[NA.bny oNL 18 Of 21 g/}9{87 ,
ATTACHMENT A - Page 7 Of 9- l NRC APPROVAL AND SAFETY EVALUATION FOR NUPAC DEWATERING SYSTEM - l I
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NRC APPROVAL AND S AFETT EVALUATION FOR NUPAC DEVATERING SYSTEM
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The eastp. pmerumrt, fabriastia. testtag and wenties of me supg srutes is assemitened meer prescrites mality'asseresas reestruments metan i sesfera, as 'tne entent prestssante. with me geteeltaes pewtems ta neplatory s ien 1.143 sesty setenes for tastusti, vaste name,seest syftes. Strocures ans C menses tesulted to Lipt Water Cooles a$ clear poner Plants.* The seality assersace progres enfines and sentmis these elements of mee ans mete smeitm' permemen wica anni os suistr of me wac l 3rnes.
- The eastp eef arrangement of me 3l Pat !rttes tennenents are bases en minatatag the esenter restation essesers as law as is reasonaely ace 1ere0IG. The t=1 B I Feeer prWides a 115% of testifft design and escrettag featores untes more teserversted a metmas persental regiatten seensors; All active comaments are lesates se may con he eastly assessed for statenense. ' All pens. salves ans pii tag.een to flamens prtipr to
. fassertient and misteneses.
. The staff ales fines that lEIPaC asecutely tesettfing later* ace i.for.etten a ir- - a .i .en insei. - 1..
N eh sign tatsyrity Centainers. a separece $afety Craluatim Assam will be ; orw iese ne iesent at mlesties. .
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19 Of 21 02/19/87 Rev. 1 *
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FOR- NUPAC DEWATERfNG SYSTEM , i . ,
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i NRC APPROVAL AND SAFETY EVALUATION. f < l TOR NUPAC DEWATERING SYSTEM 1. 4 2.0 CiprCLV5fp
.t b Based en the Nropeing evaluatism, the staff riens tee EMPAC Tapfcal Resort.
TP 4tJ, Rev.1, a te eerseele. 9 h The bases for ser martanse is esi eraclectee test the NUPAC Deusterug l Irrtes is destped ens ces be esersted to wasrence vita merget estaamce of as., , . r ,aw, g. et._. _ _ . ,_ . ,r t_ m, posittens, and Pomment requisttens. ! , . ~ The caentility of me plant resteactive weste tressent systees to meet too reautraents of Assenets ! a la C7t .ert E ele me NuPAC 3rsten te f
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seeratten is site essensent aos will to evaleeses for tastviemal license assitcattens, la assities, see passagtag aos seipping of all processes messes 1 fac!dtag morte classtfiest1em to asseren85 wtg, the asolfentle lections of~ ' ( 10 CFE parts 81 and 71, and'ag CPR Parts 1&L787et11 he deserennes Mr i! fasividual lleense apeltsattama. The esmesamenses of a potential unete T* a
. .g 9'1 ennatner faism retentam reste.ertw mwtais = senante aw :=str I ts sin site ses==ent ans =tfi to enlutes for taetvieul tiennu - 1 pace.s. 1
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The staff concluens Get tee IRIPAC teenal Resort is sedastable for ryerseco is nem 14.= siatt.= ror ityt == r s. a., iiati. 1 feeoWatTW$ mis rWort 4r referWW Md teojam De Pellering v.fe,.c o.: - F b> l 20 of 21 02/19/87 Rev. 1 .; l t i
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i NEO AP PRDWAL AND EAFETT EVALUATION Tolt NCP AC DEWATE11Dr SYSTEM ll ,* r.
. (1) . Any esemptione er err %tions fru me MPAC Tagical tenert, Rey, 1, gated i
. Jane 19tt.
, (Il ' interfaces J atman the plant ens me NUPAC fystae.-
,(3) 1x!.:stien amt arvtagenet growings of the NUPAC $ysta le the plant i
taclissiv, arts er etner means te contate insaver' tent asills aos overfloss; e ' (4) N maste classificat!.z pregvU *.a semenstrate est the salig mesta
' ' prwanct is classit ce is acesrtance wie 10 CFR Part 81, Section 81.38
_l _. , ane NRC traara festical Posittes a Weste C*assifisettee. ( / > ($) ISCPtpt1W f, f 134 NIld USSM P V., i <. *: WSEIM M W ceM. e s (n m estity er me sient rwinets e num trmaant erstes = east t$a twouttw4htts of Agesnetz 1 m CPR part R wtm the IRPAC $frtas la
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- 4 1 (7) The siens enty *seirateen en seastpter essely.
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PROCESS CONTROL PROGRAM FOR'DEKATERING. WET RADIOACTIVE SOLIO WASTE IN CARBON STEEL LINERS l PRCP-E l l REVISION 0 1 Ouane Arnold Energy Center Iowa Electric Light and Power Company Approved by: CrvA NM 1 bt # . t o,19 87 Radwastp Supervipr . Date Approved by: P ;sd- 2 - //- 9 7 Radiation Protectiorl Super sor Date Reviewed by:
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2 f/-87 Chairman, 0pleretiog nwittee ] Date O Approved by: 3'd-87 Plant Superintendent-Nuclear Date, 9 I T
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Introduction This Process Control Program describes the dewatering of wet radioactive waste solids from liquid syst. ems at the Duane Arnold Energy Center and packaging the waste in a carbon steel liner. Wet wastes are those wastes produced fran the liquid radwaste treatment system. These
. wastes may typically be described as resins (bead and powdered), charcoal, filtcr media, waste sludges, and filter precoat media. The wastes included in this progran are specifically those containing nuclides with a radioactive half-life greater than 5 years and a cor<entration in the resin of less than ICi/m3 . The dewatering process . j removes liquid from the waste in a carbon steel liner to meet the criterion'in 10 CFR Sections 61.56 (a)(3) and 61.56 (b)(2) for free-standing liquid.
Vendor Westinghouse Hittman Nuclear and Development Corporation of Colunbia, Maryland, is the , vendor of the dewatering and. packaging services and of the carbon steel liners used at the DAEC. Hittman personnel perfonn the dewatering and packaging operations' descrjbed ' herein. Dewatering System Description The Hittman dewatering system employs dewatering equipment to dewater the wet radioactive waste solids in a carbon steel liner. The Hittman system consists of an l overflow drum, container level indicators, and interconnecting piping and valves. Figure 1 is a diagram of the dewatering system as it, is typically configured. A waste-filled carbon steel liner is dewatered in the radwaste building loading bay using dewatering equipment sich is located in the radwaste building. The dewatering i systen uses service air supplied by the DAEC and exhausts air into the DAEC Radwaste Ventilation System. Water removed from the carbon steel liner, during dewatering, is : returned to the DAEC radwaste systen and is treated as liquid radwaste. 1 02/06/87 Rev. 0 _._____._____.____________m.__-_
The Hittman dewatering systen is equipped with instreents to provide infomation about the denatering process. These include mechanical and electrical liquid level l indicators with sensors in the carbon steel liner and vacuun receiver tank. Vacuun ) gauges indicate snount of vacuum in the vacuum receiver tank and carbon steel liner. Drainable liquid tests are perfonned using a'vacuun punp and vacuun bottle (VB-1 in ) Figure 1.) to verify liquid content of the carbon steel liner prior to shipment. Operation The radioactive wastes that are dewatered and packaged in a carbon steel liner for j disposal are nonnally, but not limited to, wastes from the condensate phase separators, waste sludge tank, spent resin tank, portable domineralizers and filters, or concentrated waste tank. i Wastes from any of the above mentioned systems are piped to a waste holding tank Aich is piped .directly to the vendor's equipment. The wastes are transferred to the carbon steel liner using the vendor's equipment as shown in Figure 1. Conductivity probes near the top of the carbon steel liner interior that actuate an audible alarm and light provide an indication of the waste level during the carbon steel l'iner filling and
. after dewatering.
After a carbon steel liner is filled with ~ waste, dewatering is perfonned by pulling a suction on an underdrain manifold in the carbon steel liner stil loss of suction occurs. Loss of suction is indicated by a decrease in vacuun in the vacuun receiver tank to 10 inches Hg or less on the vacuun gauge. Pump down by suction on the bottom underdrain manifold is continued for a specified time with the dewatering punp and the vacuum punp. ' 1 A drainable liquid test is performed by allowing the carbon steel liner to rest for a-stated time, .then siphoning frm the bottom underdrain manifold for a specified time to remove any liquid that has drained into it. The drainable liquid test is passed if the volune of water renoved is less than a volune demonstrated by the vendor to indicate less than 1% free-standing liquid in the waste for the carbon steel liner being tested . 2 02/06/87 Rev. O l e - - - _ _ - _ - - - . . - - - - . . _ - _ . - _ - _ _ _ . - _ b
PRCP-E In the event the waste in the carbon steel liner does not pass the d: ainable liquid test, a cycle of waiting a specified time, operating the dewatering ami vacuum pumps, waiting a specified time, and then performing a drainable liquid test is repeated until the free-standing liquid criterion is met. Specific times appropriate for the carbon steel liner and waste being dewatered have 'been determined by the vendor and are statec in the dewatering procedure. Essential Waste Characteristics and Verification The requisite characteristics of the radioactive waste addressed by this Process Control Program are stated in 10 CFR Section 61.56. The wastes subject to the process control plan are from sources within the DAEC that are well characterized and generally recognized as meeting the essential qualities of Section 61.56 (a), other than (a)(3). By knowing the source and kind of each of the subject wastes, IELP is able to' ensure that the qualities of the wastes continue to meet the requirements of Section 61.56 (a), other than (a)(3), and are compatible with the carbon steel liner itself. In addition, the DAEC's chemical control program helps prevent listed substances from being admitted into the waste streams that are depositet into the carbon steel liner. __ Both 10 CFR Sections 61.56 (a)(3) and 61.56 (b)(2) require as little free-standing and noncorrosive liquid as is reasonably achievable and no more than 1% of the volse of the waste when the waste is in a disposal container designed to ensure stability. Iow Electric intends to accomplish this by dewatering as described herein and to perform surveillance to assure that it has been done. For a given type of waste, the operatini procedure requires the vacum punp be operated for stated' time interval (s). Dewaterin< is considered complete when the volume of liquid that can be suctioned fran the carbon steel liner during a defined time is no greater than an anount stated in the operating procedure pertaining to that kind of waste. The conditions stated in the procedure will have been demonstrated by the vendor of the dewatering service to achieve less than 15 free-standing water in the waste. 3 02/06/87 Rev. 0 O
Carbon Steel Liner Wastes covered by this PRCP will be packaged in carbon steel liners. g 1 1 Eacti container will be visually inspected before use for acceptable condition of:
- 1. Sealing canponents,
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- 2. Exterior surface,
- 3. Dewatering tubes, and
- 4. Dewatering verification tube.
After filling and dewatering has been completed, the fill port assembly is removed from: the container and the container is closed in accordance with written procedures. The. procedure requires verification that the closure gasket is in place. Quality Assurance Control of the dewatering and packaging processes is maintained by conducting these operations according to written procedures addressing carbon steel liner inspection before filling, dewatering, carbon steel liner closure. and cask loading. The vendor verifies and documents that key steps' have been perfomed. ~ Iowa Electric maintair:s assurance that dewatering and packaging is perfomed as intended by separately verifying and documenting that the key steps were perfomed.
, Iowa Electric's qualdty assurance progrra is subject to 10 CFR Part 50, Appendix B, as applied to dewatering and packaging of, radioactive waste.
9 9 ONLY 4 02/06/87 Rev. 0 f G
PRCP-E l1 8' Administration The Radiation Protection Department maintains or requires the vendor to maintain procedures sich will ensure that all applicable requirements are met prior to shipmen-) of radioactive waste. IELP will review applicable vendor's operating procedures befors' authorizing the vendor to dewater radioactive waste. The Radwaste Group of the Radiation Protection Department is responsible for ensuring compliance with the PRCP, for Vendor oversight, and for recordkeeping. At least once every 24 months, IELP will audit the radwaste Process Control Progran an operating procedures that implement it (in accordance with Technical Specification 6.5.2.8.j.) Any change to the Process Control Program will be made in accordance with Technical Specification 6.15, approved by the Plant Superintendent-Nuclear, reviewed b the Operations Committee, and submitted to the NRC in the next Semi-Annual Radioactive Material- Release Report after the change is made. Training Before a vendor employee performs a dewatering or packaging procedure that is subject to this PRCP, they must have received relevant training, and Iowa Electric must have received documented confirmation of their training along with a statement of their qualifications. 1 References
- 1. DAEC Radwaste Handling Procedures
- 2. Westinghouse Hittman Nuclear Incorporated procedure STD-P-04-002, "PCP for Dewatering Ion Exchange Resin and Activated Charcoal Filter Media to 1/2 Percent Drainable liquid".
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- 3. Westinghouse Hittman Nuclear Incorporated procedure STD-PCP-03-001, " Powdered Resin Transfer and Dewatering Using Steel Containers".
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6 02/06/87
- Rev. 0 9
TABLE C.1-2 FISH AND POTABLE WATER CONSUMPTION PATHWAY tirem/hr per uCi/a1 j TEEN ( Ag FACTORS) NOCLIDE BCNE LIVER T BCDY '1TUCID KIDNEY 'IUNG GI-[LI 0.00E-01 6.34E 00' 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00 5-3 6.86E 03 C-14 3.43E 04 6.86E 03 6.86E 03 6.86E 03' 6.86E 03 6.86E 03 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 j NAr-24 l P-32 5.04E 07 3.12E 06 1.95E 06 0.00E-01 0.00E-01 0.00E-01 4.23E 06 CR-51 0.00E-Ol 0.005-01 1.52E 00 8.46E-01 3.34601 2.17E 00 2.56E 02 pes-54 0.00E-01 4.65E 03 9.22E 02 0.005-01 1.39E 03 - 0.00E.01 9.53E 03 se6-56 0.00E-01 1.24E 02 2.21E 01 0.00E-01 1.58E 02 0.00E-01 8.19E 0; FS-55 9.09E 02 6.45E 02 1.50E 02 0.00E-01 0.00E-01 4.09E 02 2.79E 02 , FE-59 1.41E 03 3.30E 03 1.27E 03 0.00E-01 0.00E-01 1.04E 03 7.79E 03 l l CD-58 0.00E-01 1.45E 02 3.35E 02 0.00E-01 0.00E-01 0.00E-01 2.00E 03 Co-60 0.00E-01 4.20E 02 9.45E 02 0.00E-01 0.00E-01 0.00E-01 5.47E 03 NI-63 4.26E 04 3.01E 03 1.44E 03 0.00E-01 0.00E-01 0.00E-01 4.79E 02 NI-65 1.80E 02 2.30E 01 1.05E 01 0.00E-01 0.00E-01 0.00E-01 1.25E 03 CU-64 'O.00E-01 1.72E 01 8.08E 00 'O .00E-01 4.35E 01 0.00E-01 1.33E 03 ZN-65 2.13E 04 7.41E 04 3.46E 04 0.00E-01 4.74E 04 0.00E-01 3.14E 04 Z1+-69 5.45E 01 1.04E 02 7.26E 00 0.00E-01 6.78E 01 0.00E-01 1.91E 02 i BR-83 0.00E-01 0.00E-01 4.73E 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16 l BR-84 0.00E-01 0.00E-01 5.95E 01 0.00E-01 0.00E-01 0.00E-01 6.24E-16 BR-85 0.00E-01 0.00E-01 2.51E 00 0.00E-01 0.00E-01 0.00E-01 8.24E-16 i RB-86 0.00E-01 1.10E 05 5.19E 04 0.00E-01 0.00E-01 0.00E-01 1.63E 04 RB-88 0.00E-01 3.16E 02 1.68E 02. 0.00E-01 0.00E-01 0.00E-01 2.71E-05 RB-89 0.00E-01 2.04E 02 1.44E 02 0.00E-01 0.00E-01 0.00E-01 3.12E-07 SR-89 4.97E 04 0.00E-01 1.42E 03 0.00E-01 0.00E-01 0.00E-01 5.91E 03 SR-90 9.37E 05 0.00E-01 2.31E 05 0.00E-01 0.00E-01 0.00E-01 2.63E 04 SR-91 9.11E 02 0.00E-01 3.62E 01 0.00E-01 0.00E-01 0.00E-01 4.13E 03 SR-92 3.44E 02 0.00E-01 1.47E 01 0.00E-01 0.00E-01 0.00E-01 8.77E 03 1.42E 00 0.00E-01 3.83E-02 0.00E-01 0.00E-01 0.00E-01 1.17E 04 Y-90 Y-91M 1.34E-02 0.00E-01 5.llE-04 0.00E-01 ' O.00E-01 0.00E-01 6.32E-01 Y-91 2.09E 01 0.00E-01 5.59E-01 0.00E-01 0.00E-01 0.00E-01 8.55E 03 Y-92 1.26E-01 0.00E-01 3.63E-03 0.00E-01 0.00E-01 0.00E-01 3.44E 03 C-7 Rev. 3 6/87
FISH AND POTABLE WATER CONSUMPTION PATHWAY < crem/hr per uCl/c1 l TEEN (AlFACTORS) g NUCLIDE BONE LIVER T BODY 'DfYRDID KIDNEY IDNG GI-LLI l Y-93 3.97E-01 0.00E-01 1.09E-02 0.00E-01 0.00E-01 0.00E-01 1.21E 04 2R-95 2.64E 00 8.34E-01 5.74E-01 0.00E-01 1.23E 00 0.00E-01 1.92E 03 1A-97 , .52E-01 3.01E-02 1 1.39E-02 0.00E 4.56E-02 0.00E-01 8.15E 03 NB-95 4.50E 02 2.50E 02 1.37E 02 0.00E-01 2.42E 02 0.00E-01 1.07E 06 to-99 0.00E-01 4.61E 02 8.78E 01 0.00E-01 1.05E 03 0.00E-01 8.25E 02 TC-99M 2.84E-02 7.92E-02 1.03E 00 0.00E-01 1.18E 00 4.39E-02 5.20E 01 TC-101 3.08E-02 4.38E-02 4.30E-01 0.00E-01 7.92E-01 2.67E-02 7.48E-09 RD-103 1.95E 01 0.00E-01 8.33E 00 0.00E-01 6.87E 01 0.00E-01 1.63E 03 j 20-105 1.67E 00 0.00E-01 6.46E-01 0.00E-01 2.10E 01 0.00E-01 1.34E 03 - RD-106 2.99E 02 f.00E-01 3.77E 01 0.00E-01 5.77E 02 0.00E-01 1.44E 04 AG-110M 1.19E 01 1.13E 01 6.86E 00 0.00E-01 2.15E 01 0.00E-01 3.17E 03 TE-125M 3.02E 03 l'.09E 03 4.03E 02 8.43E 02 0.00E-01 0.00E-01 8.90E 03 -
. TE-127M 7.62E 03 2.70E 03 9.06E 02 1.81E 03 3.09E 04 0.00E-01 1.90E 04 TS-127 1.24E 02 4.41E 01 2.68E 01 8.59E 01 5.04E 02 0.00E-01 9.61E 03 TE-129M 1.28E 04 4.77E 03 2.03E 03 4.14E 03 5.37E 04 0.00E-01 4.82E 04 TE-129 3.53E 01 1.32E 01 8.59E 00 2.52E 01 1.48E 02 0.00E-01 '1.93E 02 TE-131M 1.92E 03 9.22E 02 7.69E 02 1.39E 03 9.61E 03 0.00E-01 7.40E 04 TE-131 2.20E 01 9.06E 00 6.87E 00 1.69E 01 9.61E 01 0.00E-01 1.80E 00 TE-132 2.75E 03 1.74E 03 1.64E 03 1.84E 03 1.67E 04 0.00E-01 5.51E 04 I-130 8.BlE 01 2.55E 02 1.02E 02 2.08E 04 3.92E 02 0.00E-01 1.96E 02 I-131 5.00E 02 7.00E 02 3.76E 02 2.04E 05 1.21E 03 0.00E-01 1.39E 02 I-132 2.39E 01 6.24E 01 2.24E 01 2.10E 03 9.83E 01 0.00E-01 2.72E 01 I-133 1.72E 02 2.92E 02 8.89E 01 4.07E 04 5.llE 02 0.00E-01 2.21E 02 I-134 1.25E O L 3.31E 01 1.19E 01 5.51E 02 5.22E 01 0.00E-01 4.36E-01 I-135 5.22E 01 1.34E 02 4.98E 01 Bo64E 03 2.12E 02 0.00E-01 1.49E 02 CS-134 3.10E 05 7.30E 05 3.39E 05 0.00E-01 2.32E 05 8.86E 04 9.08E 03 i CS-136 3.18E 04 1.25E 05 8.41E 04 0.00E-01 6.82E 04 1.07E 04 1.01E 04 l CS-137 4.15E 05 5.52E 05 1.92E 05 0.00E-01 1.88E 05 7.30E 04 7.86E 03 CS-138 2.88E 02 5.52E 02 2.76E 02 0.006.-01 4.08E 02 4.74E 01 2.51E-01 BA-139 9.10E 00 6.40E-03 2.65E-01 0.00E-01 6.03E-03 4.41E-03 8.llE 01 iC-8 -Rev. 3 6/87 1 .
TABLE C.1-2 FISH .'.ND POTABLE WATER CONSUMPTION PATHWAY FACTOR mram/hr per uC1/ml TEEN (Ag FACTORS) NUCLIDE 80NE LIVER T BODY THYROID KIDNEY LUNG GI-LLI BA-140 1.86E 03 2.28E 00 1.20E 02 0.00E-01 7.72E-01 1.53E 00 2.87E-03 BA-141 4.39E 00 3.28E-03 1.47E-01 0.00E-01 3.04E-03 2.24E-03 9.36E-06 BA-142 1.96E 00 1.96E-03 1.20E-01 0.00E-01 1.66E-03 1.30E-03 6.01E-12 LA-140 3.61E-01 1.77E-01 4.72E-02 0.00E-01 0.00E-01 0.00E-01 1.02E 04 LA-142 1.86E-02 8.25E-03 2.05E-03 0.00E-01 0.00E-01 0.00E-01 2.51E 02' CE-141 7.98E-01 5.32E-01 6.12E-02 0.00E-01 2.51E-01 ,0.00E-01 1.52E 03 CE-143 1.41E-01 1.03E 02 1.15E-02 0.00E-01 4.60E-02 0.00E-01 3.08E 03 CE-144 4.17E 01 1.73E 01 2.24E 00 0.00E-01 1.03E 01 0.00E-01 1.05E 04 PR-143 1.36E 00 5.43E-01 6.76E-02 0.00E-01 3.15E-01 0.00E-01 4.47E 03 ) PR-144 4.46E-03 1.83E-03 2.26E-04 0.00E-01 1.05E-03 0.00E-01 4.92E-06 ) ND-147 9.73E-01 1.06E 00 6.34E-02 0.00E-01 6.21E-01 0.00E-01 3.82E 03 W-187 3.28E 02 2.67E 02 9.37E 01 0.00E-01 0.00E-01 0.00E-01 7.24E 04
)
NP-239 1.34E-01 1.27E-02 7.04E-03 0.00E-01 3.98E-02 0.00E-01 2.04E 03 i O e
~
C-9 , Rev. 3 I
, 6/87
mm .4, FISH AND POTA8LE WATER CON 5tMPTION PATHWAY mram/hr pe'r uC1/ml . CHILD (Ag FACTORS) NUCLIDE BCNE LIVER T BODY- '!HYRDID EIDNEY WNG GI-LLI H-3 0.00E-01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 l'.19E 01 C-14 4.45E 04 8.90E 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03 N&24 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 !
)
P-32 6.49E 07 3.04E 06 2.50E 06 0.00E-01 0.00E-01 0.00E-01 1.79E 06 l CR-51 0.00E-01 0.00E-01 1.92E 00 1.06E 00 2.915-01 1.94E 00 1.02E 02 E 54 0.00E-01 3.99E 03 1.061 03 0.00E-01 1.12E 03 0.00E-01 3.35E 03 W-56 0.00E-01 1.25E 02' 2.81E 01 0.00E-01 1.51E 02 0.00E-01 1.80E 04 FE-55 1.57E 03 8.34E 02 2.59E 02 0.00E-01 0.00E-01 4.72E 02 1.55E 02 FE-59 2.26E 03 3.65E 03 1.82E 03 0.00E-01 0.00E-01 1.06E 03 3.80E 03. CD-58 0.00E-01 3.75E 02 5.37E 02 0.00E-01 0.00E-01 0.00E-01 1.02E 03 CD-60 0.00E-01 5.16E 02 1.52E 03 0.00E-01 0.00E-01 0.005-01 2.86E 03 NI-63 7.36E 04 3.94E 03 2.50E 03 0.00E-01 0.00E-01 0.'00E-01 2.65E 02 NI-65 3.04E 02 2.86E 01 1.67E 01 0.00E-01 0.00E-01 0.00E-01 3.50E 03 CD-64 0.00E-01 2.39E 01 1.44E 01 0.00E-01 5.77E 01 0.00E-01 1.12E 03 ZN-65 2.23E 04 5.95E 04 3.70E 04 0.00E-01 3.75E 04 0.00E-01 1.05E 04 Z.+-6 9 7.15E 01 1.03E 02 9.54E 00 0.00E-01 6.26E 01 0.00E-01 6.51E 03 BR-83 0.00E-01 0.00E-01 6.64E 01 0.00E-01 0.00E-01 0.00E-01 3.89E-16 BR-84 0.00E-01 0.00E-01 7.69E 01 0.00E-01 0.00E-01 0.00E-01 3.89E-16 , BR-85 0.00E-01 0.00E-01 3.54E 00 0.00E-01 0.00E-01 0.00E-01 3.89E-16 RB-86 0.00E-01 1.09E 05 6.72E 04 0.00E-01 0.00E-01 0.00E-01 7.03E 03 RF88 0.00E-01 3.10E 02 2.15E 02 0.00E-01 0.00E-01 0.00Er01 1.52E 01 RS-89 0.00E-01 1.91E 02 1.70E 02 0.00E-01 0.00E-01 0.00E-01 1.66E 00 SR-89 1.08E 05 0.00E-01 3.08E 03 0.00E-01 0.00E-01 0.00E-01 4.18E 03 SR-90 1.39E 06 0.00E-01 3.52E 05 0.00E-01 0.00E-01 0.00E-01 1.87E 04 SR-91 1.96E 03 0.00E-01 7.41E 01 0.00E-01 0.00E-01 0.00E-01 4.33E 03 SR-92 7.38E 02 0.00E-01 2.96E 01 0.00E-01 0.00E-01 0.00E-01 1.40E 04 Y-90 3.20E 00 0.00E-01 8.56E-02 0.00E-01 0.00E-01 0.00E-01 9.10E 03 Y-91M 2.97E-02 0.00E-01 1.08E-03 0.00E-01 0.00E-01 0.00E-01 5.82E 01 Y-91 4.68E 01 0.00E-01 1.25E-02 0.00E-01 0.00E-01 0.00E-01 6.24E 03 Y-92 2.80E-01 0.00E-01 8.01E-03 0.00E-01 0.00E-01 0.00E-01 8.09E 03 t.:10 Rev. 3 6/87 l
TABLE C.1-3 , F.ISH AND POTABLE WATER CONSUMPTION PATHWAY l arem/hr per uCi/ml CHILD (Ag FACTORS) NUCLIDE BCNE LIVER T BGE '!WICID ' KIENEY IUNG GI-Lt.I Y-93 8.87E-01 0.005-01 2.44E-02 0.00E-01 0.005-01 0.00E-01 1.32E 04 1A-95 7.05E 00 1.55E 00 1.38E 00 0.00E-01 2.22E 00 0.005-01 1.62E 03 En-97 4.25E-01 6.135-02 3.62E-02 0.00E-01 8.815-02 0.00E-01 9.29E 03 se-95 5.32E 02 2.07E 02 1.48E 02 0.00E-01 1.95E 02 0.00E-01 3.83E 05 0 99 0.00E-01 8.78E 02 2.17E 02 0.00E-01 1.87E 03 0.005-01 7.26E 02 TC-99M 6.46E-02 1.275-01 2.10E 00 0.00E-01 1.84E 00 6.43E-02 7.20E 01 l
'!C-101 7.48E-02 7.83E-02 9.93E-01 0.00E-01 1.34E 00 4.14E-02 2.49E-01. .
RD-103 .4.83E 01 0.005-01 ~1.85E 01 0.00E-01 1.21E 02 0.00E-01 1.25E 03 RD-105 4.26E 00 0.005-01 1.54E 00 0.00E-01 3.74E 01 0.00E-01 2.78E 03 i 4 RD-106 7.72E 02 0.00E-01 9.64E 01 0.00E-01 1.04E 03 0.00E-01 1.20E 04 AG-110M 3.13E 01 2.12E 01 1.69E 01 0.00E-01 3.94E 01 0.00E-01 2.52E 03 TE-125M 4.25E 03 1.15E 03 5.67E 02 1.19E 03 0.00E-01 0.00E-01 4.10E 03 TE-127M 1.08E 04 2.90E 03 1.28E 03 2.58E 03 3.07E 04 0.00E-01 8.72E 03 TE-127 1.76E 02 4.73E 01 3.77E 01 1.22E 02 5.00E 02 0.00E-01 6.86E 03 TE-129M 1.82E 04 5.07E 03 1.70E 03 5.85E 03 5.33E 04 0.00E-01 2.21E 04 TE-129 5.00E 01 1.39E 01 1.19E 01 3.56E 01. 1.46E 02 0.00E-01 3.llE 03
~
TE-131M 2.68E 03 9.28E 02 9.88E 02 1.91E 03 8.98E 03 0.00E-01 3.77E 04 TE-131 3.09E 01 9.43E 00 9.21E 00 2.37E 01 9.36E 01 0.00E-01 1.63E 02 TE-132 3.77E 03 1.67E 03 2.01E 03 2.43E 03 1.55E 04 0.00E-01 1.68E 04 I-130 2.04E 02 4.13E 02 2.13E 02 4.55E 04 6.17E 02 0.00E-01 1.93E 02 I-el31 1.20E 03 1.21E 03 6.88E 02 4.00E 05 1.99E 03 0.00E-01 1.08E 02 I-132 5.60E 01 1.03E 02 4.73E 01 4.77E 03 1.57E 02 0.00E-01 1.21E 02 I-133 4.14E 02 5.12E 02 1.94E 02 9.51E 04 8.53E 02 0.00E-01 2.06E 02 I-134 2.93E 01 5.44E 01 2.50E 01 1.25E 03 8.32E 01 0.00E-01 3.61E 01 I-135 1.22E 02 2.20E 02 1.t4E 02 1.95E 04 3.38E 02 0.00E-01 1.68E 02 CS-134 3.82E 05 6.26E 05 1.32E 05 0.00E-01 1.94E 05 6.97E 04 3.38E 03 1 CS-136 3.83E 04 1.05E 05 6.82E 04 0.00E-01 5.61E 04 8.37E 03 3.70E 03 l CS-137 5.33E 05 5.11E 05 7.54E 04 0.00E-01 1.66E 05 5.99E 04 3.20E 03 : C5-138 3.72E 02 5.17E 02 3.28E 02 0.00E-01 3.64E 02 3.92E 01 2.38E 02 SA-139 2.54E 01 1.35E-02 7.35E-01 0.00E-01 1.18E-02 7.97E-03 1.47E 03 l C-11 Rev. 3 ; 6/87
TABLE C.1-3 FISH AND POTABLE WATER CONSUMPTION PATWAY FACTOR . j arem/hr per wC1/mi
, CHILD (Aj FACTORS) i NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI 8A-140 5.09E 03 4.46E 00 2.97E 02 0.002-01 1.45E 00 2.66E 00 2.58E 03 BA-141 1.23E 01 6.86E-03 3.99E-01 0.00E-01 5.94E-03 4.03E-02 6.99E 00 BA-142 5.36E 00 3.85E-03 2.99E-01 0.00E-01 3.12E-03 2.27E-03 6.99E-02 .
LA-140 7.86E-01 2.75E-01 9.26E-02 0.00E-01 0.00E-01 0.00E-01 7.66E 03 LA-142 4.08E-02 1.30E-02 4.07E-03 0.00E-01 0.00E-01 0.00E-01 2.58E 03 CE-141 2.34E 00 1.17E 00 1.73E-01 0.00E-01 5.11E-01 0.00E.-01 1.46E 03, CE-143 4.12E-01 2.23E 02 3.24E-02 0.00E-01 9.37E-02 0.00E-01 3.27E 03 CE-144 1.23E 02 3.84E 01 6.54E 00 0.00E-01 2.31E 01 0.00E-01 1.00E 04 PR-143 3.06E 00 9.18E-01 1.52E-01 0.00E-01 4.97E-01 0.00E-01. 3.30E 03 PR-144 1.00E-02 3.10E-03 5.05E-04 0.00E-01 1.64E-03 0.00E-01 6.68E 00 ND-147 2.17E 00 1.76E 00 1.36E-01 0.00E-01 9.65E-01 0.00E-01 2.79E 03 W-187 4.30E 02 2.55E 02 1.14E 02 0.00E-01 0.00E-01 0.00E-01 3.58E 04 NP-239 3.47E-01 2.49E-02 1.75E-02 0.00E-01 7.19E-02 0.00E-01 1.84E 03 9 I l i C-12 Rev. 3 6/S7 ;
~
' TABLE C.1-4 FISH AND POTABLE WATER CONSUMPTION PATSIAY FACTOR artm/h* per UCi/m1 INFAN" (Ag FACTORS)
NUCLIDE 80NE LIVER i E OY THYROID KIDNEY LUNG GI-LLI Y-93 9.14E-01. 0.00E-01 2.4 b 2 0.00E-01 0.00E-01 0.00E-01 7.22E 03 ZR-95 7.75E 00 1.89E 00 1.34E'00 0.00E-01 2.04E 00 0.00E-01 9.41E 02 ZR-97 5.57E-01 9.56E-02 4.36E-02 0.00E-01 9.63E-02 0.00E-01 6.09E 03 l 1 N8-95 1.5E 00 6.51E-01 3.76E-01 0.00E-01 4.66E-01 0.00E-01 5.49E 02 M0-99 0.00E-01 1.28E 03 2.49E 02 0.00E-01 1.91E 03 0.00E-01 4.21E 02 TC-99M 7.22E-02 1.49E-01 1.92E 00 0.00E-01 1.60E 00 7.75E-02 4.33E 01 TC-101 8.54E-02 1.0E-01 1.06E 00 0.00E-01 1.2E 00 5.87E-02 1.83E 01 RU-103 5.57E 01 0.00E-01 1.86E 01 0.00E-01 1.16E 02 0.00E-01 6.77E 02 RU-105 5.12E 00 0. 00E-01 1.72E 00 0400E-01 3.76E 01 0.00E-01 2.04E 03 RU-106 9.07E 02 0.00E-01 1.13E 02 0.00E-01 1.07E 03 0.00E.01 6.88E 03 AG-110M 3.75E 01 2.73E 01 1.81E 01 0.00E-01 3.91E 01 0.00E-01 1.42E 03 TE-125M 8.77E 02 2.93E 02 1.19E 02 2.95E 02 0.00E-01 0.00E-01 4.18E 02 TE-127M 2.20E 03 7.30E 02 2.66E 02 6.36E 02 5.42E 03 0.00E-01 8.88E 02' TE-127 3.76E 01 1.26E 01 8.09E 00 3.06E 01 9.18E 01 0.00E-01 .7.90E 02 TE-129M 3.76E 03 1.29E 03 5.79E 02 1.44E 03 9.41E 03 0.00E 01 2.25E 03 TE-129 1.07E 01 3.68E 00 2.49E 00 8.95E 00 2.66E 01 0.00E-01 8.54E 02 TE-131M 5.72E 02 2.30E 02 1.90E 02 4.66E 02 1.58E 03 0.00E-01 .3.87E 03 TE-131 6.62E 00 2.45E 00 1.86E 00 5.91E 00 1.69E 01 0.00E-01 2.67E 02 TE-132 7.82E 02 3.87E 02 3.62E 02 5.72E 02 2.42E 03 0.00E-01 1.43E 03 1-130 2.26E 02 4.97E 02 1.99E~02 5'57E 04 5.45E 02 0.00E-01 1.06E 02
. I-131 1.35E 03 1.59E 03 7.00E 02 5.23E 05 1.86E 03 0.00E-01 5.68E 01 I-132 6.24E 01 1.27E 02 4.51E 01 5.94E.03 1.41E 02 0.00E-01 1.03E 02 1-133 4.70E 02 6.85E 02 '2.01E 02 1.25E 05 8.05E 02 0.00E-01 1.16E 02 I-134 3.27E 01 6.70E 01 2.38E 01 1.56E 03 7.49E 01 0.00E-01 6.92E 01 1-135 1.37E 02 2.72E 02 9.93E 01 2.44E 04 3.04E 02 0.00E-01 9.86E 01 CS-134 1.42E 04 2.64E 04 2.67E 03 0.00E-01 6.81E 03 2.42E 03 7.19E 01 CS-136 ~1.73E 03 5.08E 03 1.90E 03 0.00E-01 2.02E 03 4.14E 02 7.71E 01 CS-137 1.96E 04 2.30E 04 1.63E 03 0.00E-01 6.17E 03 2.50E 03 7.19E 01 CS-138 1.81E 01 2.94E 01 1.43E 01 0.00E-01 1.47E 01 2.29E 00 4.70E 01 BA-139 3.31E 01 2.20E-02 g
9.59E-01 0.00E-01 1.32E-02 1.33E-02 2.10E 03
~
Rev. 3
- Bioaccumulation f actor assumed to be zero since no data was available. 6/87 C-14
IAtilt C.1-4 FISH AND POTA8LE WATER CONSUMPTION PATHWAY j' crem/hr per uC1/al INFANT (Ag FACTORS) , NOCLIDE BONE LIVER T BODY 71fYROID KIDNEY IUNG GI-ILI
- E-3 . s.40E-01 -ttSE Gi 1.16E G1 1.16E Gi 1.16E-01 1.16E Gi 1.16E Gi C-14 . 8.92E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 1.90E.02 NAr-24 3.80E 02 3.80E 02 3.80E 02 3.80E 02 3.80E 02 3.80E 02 3.80E 02 P-32. 6.40E 04 3.76E 03 2.48E 03 0.00>01 0.00E-01 0.00E-01 8.65E 02 CA-51 0.00E-01 0.005-01 5.30E-01 3.465-01 7.56E-02 6.735-01 1.55E 01 see-54 0.005-01 7.49E 02 1.70E 02 0.005-01 1.66E 02 0.00E-01 2.75E 02 894- 5 6 0.00E-01 3.08E 01 5.30E 00 0.00E-01 2.64E 01 0.00E-01 2.80E 03 FE-55 5.23E 02 3.38E 02 9.03E 01 0.00E-01 0.00E-01 1.65E 02 4.29E 01 FE-59 1.16E 03' 2.02E 03 7.98E 02 0.005-01 0.005-01 5.98E 02 9.67E 02 CD 58 0.00E-01 1.35E 02 3.38E_02 0.00E-01 0.00E-01 0.00E-01 3.37E 02 CD-60 0.00E-01 4.06E 02 9.59E 02 0.00E-01 0.00E-01 0.00E-01 9.67E 02 NI-63 2.39E 04 1.47E 03 8.28E 02 0.00E-01 0.00E-01 0.00E-01 7.34E 01 NI-65 1.77E 02 2.00E 01 9.10E 00 0.00E-01 0.00E-01 , 0.00E-01 1.52E 03 CD-64 0.00E-01 2.29E 01 1.06E 01 0.00E-01 3.87E 01 0.00E-01 4.70E 02 ZN-65 6.92E 02 2.37E 03 1.09E 03 0.00E-01 1.15E 03 0.00E-01 2.01E 03 ZN-69 3.51E 00 6.32E 00 4.70E-01 0.00E-01 ,2.63E 00 0.00E-01 5.15E 02 BR-83 0.00E-01 0.00E-01' l.37E 01 0.00E-01 0.00E-01 0.00E-01 3.76E-17 BR-84 0.00E-01 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01. 3.76E-17 BR-85 0.00E-01 0.00E-01 7.30E-01 0.00E-01 0.00E-01 0.00E-01 3.76E-17 RB-86 0.00E-01 6.40E 03 3.16E 03 0.00E-01 0.00E-01 0.00E-01 1.64E 02 RS-88 0.00E-01 1.87E 01 1.03E 01 0.00E-01 0.00E-01 0.00E-01 1.82E 01 RS 0.00E-01 1.08E 01 7.41E 00 0.00E-01 0.00E-01 0.00E-01 3.66E 00 .
SR-89 9.44E 04 0.00E-01 2.71E 03 0.00E-01 0.00E-01 0.00E-01 1.94E 03 SR-90 6.96E 05 0.00E-01 1.77E 05 0.00E-01 0.00E-01 0.00E-01 8.69E 03 SR-91 1.88E 03 0.00E-01 6.81E 00 0.00E-01 0.00E-01 0.00E-01 2.23E 03 SR-92 7.22E 02 0.00E-01 2.68E 01 0.00E-01 0.00E-01 0.00E-01 7.79E 03 Y-90 3.27E 00 0.00E-01 8.77E-02 0.00E-01 0.00E-01 0.00E-01 4.51E 03 Y-91M 3.05E-02 0.00E-01 1.04E-03 0.00E-01 0.00E-01 0.00E-01 1.02E 02 Y-91 4.25E 01 0.00E-01 1.13E 00 0.00E-01 0.00E-01 0.00E-01 3.05E 03 Y-92 2.88E-01 0.00E-01 8.09E-03 0.00E-01 0.00E-01 0.00E-01 5.49E 03 C-13 Rev. 3
, 6/87
i FISH AND POTABLE WATER CONSUMPTION PATHWAY ' Grem/hr nr uC1/ml-INF. ANT (AjFACTORS) i
-NOCLIDE = ;JVER-- T BODY THYNXD KIDNEY IDG GI-ILI B&l40 6.43E 03 6.43E 00 3.31E 02 0.00F01 1.53E 00 3.95E 00 1.58E 03 l B&l41 1.60E 01 1.09 F02 5.04E-01 0.005-01 6.58F03 6.665-03 1.95E 02 l
, R&l42 6.92E 00 5.76>03 3.415-01 0.005-01 3.31>03 3.48E-03 2.86E 01 IA-140 7.94E-01 3.135-01 8.055-02 0.005-01 0.00>01 0.00601 3.68E 03 IA-142 4.14E-02 1.525-02 3.645-03 0.00E-01 0.005-01 0.005-01 2.58E 03 CE-141 2.96E 00 1.81E 00 2.135-01 0.005-01 5.575-01 0.00E-01 9.33E 02 i CE-143 5.57E-01 3.69E 02 4.21E-02 0.005-01 1.08E-01 0.005-01 2.16E 03 I CE-144 1.12E'02 4.59E 01 6.28E 00 0.00E-01 1.85E 01 0.'00D-01 6.43E 03 )
PR-143 3.06E 00 1.14E 00 1.52E-01 0.005-01 4.25E-01 0.00E-01 1.61E 03 l t PR-144 1.03E-02 3.99 &O3 5.195-04 0.00E-01. 1.44E-03 0.00E-01 1.85E 02 ND-147 2.08E 00 2.14E 00 1.31E-01 0.00E-01 8.24E-01 0.00E-01 1.35E 03 d W-187 3.40E 01 2.36E 01 8.16E 00 0.00E-01 0.00E-01 0.00E-01 1.39E 03 l
,- 1 NP-239 4.18E-01 3.74E-02 2.115-02 0.00E-01 7.45E-02 0.00E-01 1.08E 03 l
aW D 4 6 9 C-15 Rev. 3 6/87 8
1 l TABLE C.2-1 , IRRIGATED F000 (STRAW 8ERRY) PATHWAY
, erem/hr per uC1/ml , j ADULT ( AgFACTORS)
NUCL10E BONE LIVER T BODY THYROIO KIDNEY LUNG GI-LLI H-3 0.00E-00 8.15E-04 8.15E-04 8.15E-05 8.15E-04 8.16E-04 8.16F.-04 C-14 3.57E42 7.14E-03 7.14E-03 7.14E-03 7.14E-03 7.14E-03 7.14E-03 P-32 5.93E-03 3.69E-04 2.29E-04 0.00E-00 0.00E-00 0.00E-00 6.67E-04 Cr-51 0.00E40 0.00E-00 4.29E-07 2.57E-07 9.46E-08 5.70E-07 1.08E-04 Mn-54 0.00E-00 4.04E-03 7.70E-04 0.00E-00 1.20E-03 0.00E-00 1.24E-02 ' Fe-55 2.71E-03 1.88E-03 4.37E-04 0.00E-00 0.00E-00 1.05E-03 1.08E-03 Fe-59 1.40E-03 3.29E-03 1.26E-03 0.00E-00 6.66E-04 9.19E-04 1.10E-02 Co-58 0.00E-00 3.70E-04 8.30E-04 0.00E-00 0.00E-00 0.00E-00 7.50E-03 Co-60 0.00E-00 2.19E-03 4.82E-03 0.00E-00 0.00E-00 0.00E-00 4.11E-02 Ni-63 1.40E-01 9.72E-03 4.70E-03 0.00E-00 0.00E-00 0.00E-00 2.03E-03 Zn-65 3.66E-03 1.36E-02 6.15E-03 0.00E-00 9.11E-03 0.00E-00 8.58E-03 Sr-89 1.14E+01 0.00E-00 3.27E-03 0.00E-00 0.00E-00 0.00E-00 1.84E-02 Sr-90 8.09E+00 0.00E-00 1.98E+00 0.00E-00 0.00E-00 0.00E-00 2.34E-01 Y-90 2.89E-13 0.00E-00 7.76E-15 0.00E-00 0.00E-00 0 00E-00 1.42E-09 Zr-95 1.40E-05 4.48E-06 3.03E-06 0.00E-00 7.02E-06 0.00E-00 1.42E-02 i Nb-95 1.47E-06 8.17E-07 4.39E-07 0.00E-00 8.07E-07 0.00E-00 4.96E-03
~
Mo-99 0.00E-00 3.77E-03 7.17E-04 0.00E-00 8.54E-03 0.00E-00 8.74E-03 Ru-103 5.12E-05 0.00E-00 2.21E-05 0.00E-00 1.95E-04 0.00E-00 5.98E-03 Ru-106 2.51E-03 0.00E-00 3.18E-04 0.00E40 4.85E-03 0.00E-00 1.62E-01 Ag-110M 1.38E-04 1.27E-04 7.56E-05 0.00E-00 2.50E-04 0.00E-00 5.20E-02 Te-132 1.53E-09 9.93E-10 9.32E-10 1.10E-09 9.56E-09 0.00E-00 4.70E-08 ; I-131 4.77E-05 6.82E-05 3.91E-05 2.24E-02 1.17E-04 0.00E-00 1.80E-05 I-133 6.72E-25 1.17E-24 3.57E-25 1.72E-22 2.04E-24 0.00E-00 1.05E-24 Cs-134 6.06E-02 1.44E-01 1.18E-01 0.00E-00 4.76E-02 1.55E-02 2.53E-03 I Cs-137 8.41E-02 1.15E-01 7.53E-02 0.00E 3.90E-02 1.30E-02 2.23E-03 8a-140 4.11E-04 5.16E-07 2.69E-05 0.00E-00 1.75E-07 2.95E-07 8.46E-04 l Ce-141 1.98E-06 '1.34E-06 1.52E-07 0.00E -00 6.21E-07 0.00E-00 5.11E-03 l I Ce-144 4.22E-04 1.76E-04 2.27E-05 0.00E-00 1.05E-04 0.00E-00' 1.43E-01 NP-239 3.94E-15 3.87E-16 2.13E-16 0.00E-00 1.21E-15 0.00E-00 7.94E-11 1 Rev. 3 C-16 , 6/87 ;
IRRIGATED F000 (STRAWBERRY) PATHWAY mram/hr per uC1/ml TEEN (Ag FACTORS) l NUCLIDE 80NE LIVER T BODY THYROIO KIDNEY LUNG GI-LLI 1 H-3 0.00E-00 ' 5.37E-04 5.37E-04 5.37E-04 5.37E-04 5.37E-04 5.37E-04 l C-14 3. 33E -02 6.65E -03 6. 65E-03 6. 65E -03 6. 65E-03 6. 65E-03 6.65E-03 i P-32 5.53E-03 3.43E-04 2.14E-04 0.00E-00 0.00E-00 0.00E-00 4.65E-04 Cr-51 0.00E-00 0.00E-00 3.97E-07 2.10E-07 8.30E-08 5.41E-07 6.37E-05 Mn-54 0.00E-00 3.40E-03 6.74E-04 0.00E-00 1.01E-03 0.00E-00 6.97E-03 ) Fe-55 2.43E-03 1.73E-03 '4.02E-04 0.00E-00 0.00E-00 1.09E-03 7.66E-04 Fe-59 1. 23E-03 2.88E-03 1.11E-03 0.00E-00. 0.00E-00 9.09E-04 6.81E-03 Co-53 0.00E-00 3.15E-04 7.26E-04 0.00E-00 0.00E-00 0.00E-00 2.44E-03 i Co-60 0.00E-00 1.87E-03 4.22E-03 0.00E-00 0.00E-00 0.00E-00 2.44E-03 Ni-63 1.24E-01 8.97E-03 4.22E-03 0.00E-00 0.00E-00 0.00E-00 1.40E-03 Zn-65 3.32E-03 1.15E-02 5.38E-03 0.00E-00 7.38E-03 0.00E-00 4.88E-03 Sr-89 1.06E-01 0.00E-00 3.04E-03 0.00E-00 0.00E-00 0.00E-00 1.27E-02 Sr-90 5.77E+00 0.00E-00 1.43E+00 0.00E-00 0.00E-00 0.00E-00 1.62E-01 ) Y-90 2.69E-13 0.00E-00 7.24E-15 0.00E-00 0.00E-00 0.00E-00 2.22E-09 l Zr-95 1.23E-05 3.89E-06 2.68E+00 0'. 00E -00 5. 72E-06 0.00E-00 8.98E-03 l Nb-95 1.27E-06 7.02E-07 3.86E-07 0. 0'0 E -00 6.80E-07 0.00E-00 3.00E-03 Mo-99 0.00E-00 3.44E-03 6. 56E'-04 0.00E-00 7.87E-03 0.00E-00 6.16E-03 __ Ru-103 4.60E-05 0.00E-00 1.97E-05 0.00E-00 1.62E-04 0.00E-00 3.84E-03 I Ru-106 1. 30E -05 0.00E-00 2. 94E-04 0.00E-00 4. 50E-03 0.00E-00 1.12E-01
. Ag-110M 1.15E-04 1.09E-04 6.62E-05 0.00E-00 2.08E-04 0.00E-00 3.06E-02 Te-132 1.19E-09 8.78E-10 8.26E-10 9.25E-10 8.42E-09 0.00E-00 2.78E-08 I-131 4.37E-05 6.12E-05 3.29E -05 1. 79E-02 1.05E-04 0.00E-00 1.21E-05 I-133 6.21E-25 1.05E-24 .3.21E-25 1.47E-22 1.85E-24 0.00E-00 7.97E-25 Cs-134 5.32E-02 1.25E-01 5.81E-02 0.00E-00 3.98E-02 1.52E-02 1.56E-03 Cs-137 7.70E-02 1.02E-01 3.57E-02 0.00E-00 3. 49E-02 1.36E-02 1.46E-03 Ba-140 3.75E-04 4.59E-07 2.41E-05 0.00E-00 1.56E-07 3.09E-07 5.78E-04 Ce-141 1.83E-06 1.22E-06 1.41E-07 0.00E-00 5.76E-07 0.00E-00 3.50E-04 Ce-144 3.93E-04 1.62E-04 2.11E-05 0.00E-00 9.70E-05 0.00E-00 9.87E-02 NP-239 3.80E-15 3.58E-16 1.99E-16 0.00E-00 1.12E-15 0.00E-00 5.76E-11 Rev. 3 C-17 6/87
_ __.___________m_
. . j l TABLE C.2-3 l IRRIGATED FOOD (STRAW 8ERRY) PATHWAY ,
' arem/hr per uCi/mi CHILD (Ag FACTORS) ,
BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI
. NUCLIOE H -3 0.00E 7.54E-04 7.54E-04 7.54E-04 7.54E-04 7.54E-04 7.54E-04
. C-14 7.27E-02 1.45E-02 1.45E-02 1.45E-02 1.45E-02 1.45E-02 1.45E-02 P-32 1.21E-02 5.67E-04 4.67E-04 0.00E-00 0.00E-00 0.00E-00 3.35E-04 Cr-51 0.00E-00 0.00E-00 6.87E-07 3.81E-07 1.04E-07 6.96E-07 3.64E-05 0.00E-00 4.52E-03 1.20E-03 0.00E-00 1.27E-03 0.00E-00 3.79E-03 Mn-54 Fe-55 5.43E-0,3 2.88E-03 8.92E-04 0.00E-00 0.00E-00 1.63E-03 5.34E-04 Fe-59 0.00E-00 4.12E-03 2.05E-03 0.00E-00 0.00E-00 1.19E-03 4.29E-03 Co-58 0.00E-00 4.28E-04 1.31E-03 0.00E-00 0.00E-00. 0.00E-00 2.49E-03 Co-60 0.00E,-00 2.59E-03 7.63E-03 0.00E-00 0.00E-00 0.00E-00 1.43E-02 Ni-63 1.14E-03 1.49E-02 9.44E-03 0.00E-00 0.00E-00 0.00E-00 1.00E-03 Zn-65 5.97E-03 1.54E-02 9.60E-03 0.00E-00 9.72E-03 0.00E-00 2.71E-03 Sr-89 2.34E-01 0.00E-00 6.67E-03 0.00E-00 0.00E-00 0.00E-00 9.05E-03 4 Sr-90 8.67E+00 0.00E-00 2.20E+00 0.00E-00 0.00E-00 0.00E-00' 1.17E-01 I Y-90 5.92E-13 0.00E-00 1.58E-14 0.00E-00 0.00E-00 0.00E-00 1.68E-09 Zr-95 2.55E-05 0.00E-00 4.98E-06 0.00E-00 8.01E-06 0.00E-00 .5.84E-03 Nb-95 2.54E-06 9.89E-07 7.07E-07 0.00E-00 9.2sE-07 0.00E-00 1.83E-03 Mo-99 0.00E-00 5.56E-03 1.38E-03 0.00E-00 1.19E-02 0.00E-00 4.60E-03 Ru-103 9.67E-05 0.00E-00 3.72E-05 0.00E-00 2.44E-04 0.00E-00 2.50E-03 Ru-106 5.11E-03 0.00E-00 6.37E-04 0.00E-00 6.90E-03 0.00E-00 7.95E-02 Ag-110M 2.22E-04 1.50E-04 1.20E-04 0.00E-00 2.79E-04 0.00E-00 1.78E-02 Te-13.2 2.94E-09 1.30E-09 1.57E-09 1.90E-09 1.21E-08 0.00E-00 1.31E-08 i
1-131 9.43E-05 9.49E-05 5.39E-05 3.14E-02 1.56E-04 0.00E-00 8.44E-06 I-133 1.34E-24 1.66E-24 6.27E-25 3.08E-22 2. 76E-24 0.00E-00 6.68E-25 Cs-134 1.09E-01 1.79E-01 3.78E-02 0.00E-00 5.55E-02 1.99E-02 9.65E-04 Cs-137 1.65E-01 1.58E-01 2.33E-02 0.00E-00 5.14E-02 1.85E-02 9.89E-04 8a-140 8.04E-04 7.04E-07 '4.24E-02 0.00E-00 2.29E-07 4.20E-07 4.07E-04 Ce-141 4.01E-06 2.00E-06 2.97E-07 0.00E-00 8.77E-07 0.00E-00 2.50E-03 Ce-144 8.61E-04 2.70E-03 4.59E-05 0.00E-00 1.49E-04 0.00E-00 7.03E-02 NP-239 8.31E-15 5.96E-16 4.19E-16 0.00E-00 1.72E-15 0.00E-00 4.41E-11
- 5. ,
Rev. 3
. C-18 6/87 l
1 i
)
SUMMARY
OF CHANGES TO THE PROCESS CONTROL PLAN During the period January 1, 1987, thru June 30, 1987, one (1) change was made to the existing PRCP's. PRCP-A, " Process Control Program for Dewatering Wet Radioactive Solid Waste"; PRCP-C, " Process Control Program for Solidification of Wet 1 Radioactive Solid Waste"; and PRCP-D, " Process Control Program j for Dewatering Ion Exchange Resins and Filter Media (Pacific l Nuclear Systems, Inc.)", were revised to clarify IELP review of I vendor procedures. Site specific procedures developed by the 1 vendor for the Duane Arnold Energy Center are reviewed by the Operations Committee. In addition, PRCP-E, " Process Control Program for Dewatering Wet Radioactive Solid Waste in Carbon
~
Steel Liners", was added. Copies are attached. The product waste form conforms to the requirements of 10 CFR Part 61.56. 1 m _ _.___ _ ______ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . _ _ ___ __ _____.__.__.______J}}