ML042960023

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Exhibit CY-5-Panel 1 - Panel Attachment 4: Health Physics Department, Technical Support Document, HP Number BCY-HP-0125, Rev. 0: Dose Estimate for an Ingested Particle (12/05/02)
ML042960023
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 02/07/2003
From:
Connecticut Yankee Atomic Power Co, Ropes & Gray
To:
Atomic Safety and Licensing Board Panel
References
-RFPFR, 50-213-LTP, ASLBP 01-787-02-OLA, FOIA/PA-2004-0153
Download: ML042960023 (19)


Text

PRE-FILED, PRE-NUMBERED EXHIBIT COVER SHEET l

Exhibit CY PANEL1-.

For Reporters' Use Only United States of America Nuclear Regulatory Commission before the Atomic Safety and Licensing Board In the Matter of Docket No. 50-213-LTP CONNECTICUT YANKEE AToNSC POWER COMSPA-NYN c

ASLBP No. 01-787-02-OLA (Haddaxn Neck Plant)

PANEL ATrACHMENT 4: "HEALTH PHYSICS DEPARTMENT, TECHNICAL SUPPORT DOCUMENT, HP NUMBER: BCY-HP-0125 REV. 0: DOSE ESTIMATE FOR AN INGESTED PARTICLE" (12/05/02).

Submitted by:

R. K. Gad II Martin J. Newhouse Ropes & Gray One International Place Boston, MA 02110 Counsel to CY Dated: February 7, 2003.

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BCY-HP-0125 Revision 0 Page I of 18 UNCONTROLLED COPY BECHTEL HEALTH PHYSICS TECHNICAL SUPPORT DOCUMENT DOCUMENT No.

24265-000-G65-GEHH-P0125-000 Connecticut Yankee Decommissioning Health Physics Department Technical Support Document HP Number: BCY-BHP-0125 Revsion#: 0

Subject:

Dose Estimate for an Ingested Particle Date: 12105/02

'1114" /,//,. /,J Date:

Date:

Date:

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BCY-HP-0125 Revision 0 Page 2 of 18 PURPOSE To provide a dose estimate from the ingestion of a 1 j+/-Ci particle.

DISCUSSION Assumptions and Basis This assessment was performed using the following assumptions:

1. The particle is insoluble and therefore does not enter the blood stream but rather passes through the gastrointestinal (GI) tract, similar to a bolus of material.
2. The ingestion pathway is the only pathway considered since a hot particle is likely to exceed 10 micron activity median aerodynamic diameter (AMAD).
3. The only progeny nuclide included in this assessment is Y-90 (Sr-90 progeny) because its half life is short enough to result in secular equilibrium. The remaining nuclides half lives are too long to reach secular equilibrium.

The number of disintegrations for each segment of the GI tract for each nuclide in the License Termination Plan (LTP) in Table 2-12, Radionuclides Potentially Present at HNP, was determined by using INDOS0. Even though the particle is expected to be eliminated within 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> (based upon the sum of the mean residence times for each of the organs along the GI tract), the total number of disintegrations calculated over 50 years was used for conservatism. The input parameters used are illustrated in Table 1. The number of disintegrations for each segment of the GI tract is listed in Table 2 for a 1 Bq activity of each radionuclide. Note that the number of disintegrations for each segment of the GI tract for each nuclide is essentially the same. The reason for this is that the half-lives of the radionuclides in the LTP are long compared to the passage time through the GI tract. Therefore, the number of disintegrations is determined primarily by the clearance fine assumed, as stated previously, for conservatism the total number of disintegrations over 50 years was used. A copy of the INDOS runs for the shortest half-life nuclide and longest half-life nuclide in the LTP is included as Attachment 1.

BCY-H.PI1-5 Revision 0 Page 3 of 18 Table 1. INDOS Input Parameters and Values Parameter Value Comment fl 0

Zero value assumes particle is insoluble Intake Pathway Ingestion Only considered pathway Exposure Condition Acute Appropriate for particle ingestion.

Systemic NOS requires at least one systemic Compartments compartment.

Compartment half life was deliberately set low, since this assessment only Systemic Half Life 2.OOE-06 Days evaluates the dose to the GI tract.

Therefore, this parameter does not effect the dose to the GI tract Since the particle is considered to be Fraction of Systemic 0

representative of a bolus (i.e., insoluble),

Excreted through urine the particle will travel through the GI and be eliminated through feces.

Since the particle is considered to be Fraction of Systemic 1

representative of a bolus (i.e., insoluble),

Excreted through feces the particle will travel through the GI and be eliminated through feces.

Time post intake days INDOS calculates the number of (T) disintegrations post intake between time, T1 and T2. Setting T1 to 0 and T2 to 1.75 days gives the total of Time post intake days disintegrations that occur while the (1p).75 particle passes through the body.

However, the fifty year value was used in this assessment for the estimate of CEDE.

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BCY-HP-0125 Revision 0 Page 4 of 18 Table 2. Number of Disintegrations for each Segment of the GI Tract for an Intake Activity of 1 Bq.

T1 T2 DIstint.

  1. Dlstint.

Post Post Upper #1Distint.

Lower Half-LIfe Intake Intake Intake # DlstInt. Large Small Large # Distint.

Nucllde (days) pathway jqffs (days( Stomach IntestIne Intestine Intestine GI Total Aa-1 O8m.64E+04 Ingestion 0

182503.60E+03 4.68E+O4I.44E+04 8.64E+041.51E+05 Am-241 1.58E+05 Ingestion 0

182503.60E+03 4.68E+04.4412+04.64E+041.51E+05 C-124

.09E+06 Ingestion 0

18250 3.60E+0 4.68E+O 1.44E+04 8.64E+04 1.51E+05 Co-243 1.04E+04 Ingestion 0

182503.60E+03 4.88E+04 1.44E+04 8.64E+04 1.51 E+05 Co-13 1.92E+03 Ingestion 0

18250 3.60E+03.68E+04 i.44E+04 8.64E+04 1.51 E+05 Cs-134 7.53E+02 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E+0A 8.63E+04 1.51 E+05 Cs-i 37 1.1 0OE+04 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E0 8.64E+D4 1.51 E+05 Eu-1 52 3.21E+03 Ingestion 0

18250 3.60E+03 4.682+04 1.44E+04 8.64E+04 1.51 E+05 Eu-1 54 21 E+03 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+05 Eu-1 55 1.81E+03 Ingestion 0

18250.60E+03.682+04 1.44E+04 8.64E+04 1.51 2+05 Fe-55 4.8E+02 Ingestion 0

18250 3.60E+03 6sE+04 1.44E+04 8.64E+04 1.51E+05 H-3

.492+03 Ingestion 0

18250 3.60E+03.68E+04 1.44E+04 8.64E+04 1.51 E+.5 Mn-54 3.12E+02 Ingestion 0

18250 3.BOE+03.67E+04 1.44E+04 8.61 E+04 1.51 E+0I5 Nb-94 7.30E+06 Inqgestfon 0

18250.BOE+03.68E+04 1.44E+04 8.64E+04 1.51 E+05 NI-63 3.65E+04 Ingestion 0

18250 3.60E+03.68E+04 1.44E+04 8.64E+04 1.51 E+05 Pu-238 320E+04 Ingestion 0

18250.60E2+3 4.8E+0 1.44E+04.64E+04 1.1 E+05 Pu-239 8.80E+06 Ingestion 0

18250 a60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+05 Pu-241 S.26E+03 Ingestlon 0

18250 60+03 4.68E+04 1 A4E+04.64E+04 1.51 E+05 Sr-90 1.04E+0 Ingeston 0

18250.60E+03 4.68E+041.44E+04 8.64E+04 1.51E+05 Tc-99 7.772+07 Ingeston 0

18250 3.60E+03 1.GE+04 1.44E+04 8.64E+04 1.51 E+05 Organ Dose The Specific Effective Energy (SEE) terms were used from ICRP-30 (Reference 1) to determine the dose to other target organs from the disintegrations in the GI tract. Attachments 2 through 5 list the specific absorbed dose factors (Mev per gram per Becquerel) for each organ and each nuclide in the LTP for the small intestine (SI), upper large intestine (Il), lower large intestine (LL1), and stomach, respectively. Table 3 lists the sum of the specific absorbed dose factors (Mev per gram per Becquerel) for each of the GI tract components, which is converted to dose equivalent factor (rem per bequerel) by multiplying by the conversion factor provided in ICRP 30 of 1.6E-10 Sievert (Sv) per MeV per gram and 100 to convert Sv to rem.

It should be noted that the SEE Values in ICRP 30 assume instantaneous uniform mixing of the radionuclide within the compartment (organ).

This actually overestimates the dose, since this evaluation is for a discrete particle (i.e., uniform mixing will not occur) and uniform irradiation of the compartment (organ) will not occur.

This represents a significant overestimate of dose for alpha emitting nuclides since most of the alpha energy is absorbed in the GI tract content. This is evident in Table 3 since the alpha transuranics illustrate a substantially higher dose than other beta/gamma

BCY.HP-0125 Revision 0 Page 5 of 18 emitting nuclides.

However, no adjustments are made in this assessment to account for these conservative assumptions.

Table 3. Absorbed Dose and Dose Equivalent Factors for LUP nuclides Dose Absorbed Dose Equlvalen Factor Factor Nucilde (Maovgramlbg) (Remibq)

Ag-1o8m 2.39E+01 3.82E-07 An-241 o.0OE+00 O.OOE+OO C-14 O.OOE+00 0.OOE+00 Cm-243 O.OE+00 0.00E+00 Co-6O 1.18E+01 1.88E-07 Cs-134 O.OOE+00 0.00E+00 Cs-137 O.OOE+0 O.OOE+00 Eu-162 8.30E+00 1.33E-07 Eu-154 124E+01 1.99E-07 Eu-155 1.94E+00 3.11 E-08 Fe-55 1.1 8E-01 1.88E-09 H-3 O.OOE+00 O.OOE+00 Mne-4 a58E+OO 5.75E.08 Nb-94 7.92E+00 1.2E-07 NM63 4.61 E-01 7.39E-09 Pu-238 2.83E+01 4.53E-07 Pu-239 2.61 E+O1 4.19E-07 PU-241 9.84E-02 1.58E-09 Sr.90 2.90E+01 4.65E-07 Tc-99 3.21 E+00 5.14E-08 Total 1.57E+0a 2.52E-06 I

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Determination of Nucide Scaling Nuclide scaling was performed using the same conservative waste stream mixture used in calculating annual doses from contaminated embedded piping as described in the LTP (reference 2). The sample was a composite of Dry Activated Waste (DAW) in the WDB from 2000. This sample was shipped off site and analyzed by Duke Engineering and Services Environmental Laboratory (DES). The analysis results are provided in Attachment 6. A summary of the results for the nuclides in the LTP is provided in Table 4. The activity results were used to scale the dose in order to determine the dose relative to the worst case expected radionuclide mix. A nuclide fracdon was determined by dividing each individual nuclide activity by the total activity in the sample. If the nuclide activity did not exceed the Minimum Detectable Activity (MDA) of the sample, than the reported MDA was used as the activity amnount.

The sarnple was analyzed on December 6, 2000. Therefore the nuclides were decay corrected to

BCY-HP.0125 Revision 0 Page 6 of 18 determine the scaling fraction. Europium-152, Euriopium-154, and Europium-155 were not listed in the Part 61 analysis provided by DES.

Table 4. Part 61 Results of Composite Sample of DAW from WDB In 2000 Decayed Ncde Acivite Nucdide Activity Decay Corrected Nule uCtivityle Fraction (uCi/sample) Nuclide Fraction H-3 1.50E-03 Reported MDA 2.73E-02 1.35E-03 2.67E-02 C-14 1.80E-03 Reported MDA 3.27E-02 1.80E-03 3.55E-02 Mn-54 4.70E-04 Reported MDA 8.54E-03 1.07E}04 2.11E-03 Fe-55 7.30E-04 Reported A 1.33E-02 4.57E-04 9.01E-03 Co-60 1.52E-03 2.76E-02 1.20E-03 236E-02 Ni-63 3.45E.03 6.27E-02 3.41E-03 6.72E-02 Sr-90 2.09E-03 3.80E-02 2.0OE-03 3.94E-02 Nb-94 4.60E-04 Reported MDA 836E-03 4.60E-04 9.07E-03 Tc-99 6.10E-03 Reported MDA 1.1 1E-01 6.10E-03 1.20E-01 Ag-108m 5.30E-04 Reported MDA 9.63E-03 5.25E-04 1.03E-02 Eu-152 Not Provided O.OOE+00 N/A N/A Eu-154Not Provided O.OOE+00 NIA N/A Eu-155 NotProvided O.OOE+00 N/A N/A Cs-134 1.67E-03 3.04E-02 9.03E-04 1.78E-02 Cs-137 1.17E2 2.12E-01 1.12E-02 2.21E-01 Pu-238 9.89E-04 1.80E-02 9.75E-04 1.92E-02 Pu-239 3-53E-04 6.42E-03 3.53E-04 6.96E-03 Pu-241 2.13E-02 3.87E-01 1.95E-02 3.85E-01 Am-241 3.05E-04 5.54E-03 3.04E-04 6.OOE-03 Cm-243 8.IOE-05 1.47E-03 7.75E-05 153E-03 Total 5.50E-02 1.OOE+00 5.07E-02 1.OOE+00 Calculated Scaled Dose Table 5 lists the scaled dose using the rem per Becquerel values from Table 3 and the nuctide scaling fractions in Table 4. The total dose equivalent per unit intake for the scaled dose is 4.69E-08 rem per bq or 1.74 mrem per puCi. Therefore, for a nominal activity of I gCi, the estimated dose would be 1.74 mrem. For a Co-60 particle with an activity of 1 RCi, the estimated dose would be 6.96 mrem.

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I BCY-HP-0125 Revision 0 Page 7 of IS Table 5. Scaled Dose Based Upon WDB Composite Sample.

Scaled Scaled Total Total NuclIde Total Total Nucilde (Movlgramnbg) (Remibq) Fraction (Renlbq) [mRqem/Ci Agk 08m 2.39E+01 3.82E-07 1.03E.02 3.94E-09 1.46E-01 AP-241 O.00E+00 O.OOE+00 6.OOE-03 O.oOE+00 O.0E0+00 C-14 0.00E+00 0.00E+00 3.55E-02 O.OE+00 0.00E+00 Cm-243 O.OOE+00 0.D0Es00 1.53E-03 0.OOE+00 O.OOE+00 Co-60 1.18E+01 1.88E-07 2.36E-02 4.45E-09 1.65E-01 Cs-134 O.OOE+00 O.OOE+00 1.78E-02 0.DOE+00 O.0E0+00 Cs-137 O.OOE+00 0.0012+00 2.21E-01 O.OOE+00 0.OOE+00 Eu-152 8.30E+00 1.33E-07 0

O.OOE+00 0.00E+00 Eu-i 54 1.24E+01 1.99E-07 0

O.OOE+00 O.00E+00 Eu-1 55 1.94E+00 3.11 E-08 0

0.OOE+00 O.OOE+00 Fe-55 1.18E-01 1.88E-09 9.01 E-03 1.70E-11 6.29E-04 H-3 O.OOE+00 O.OOE+00 2.67E-02 O.OOE+00 O.OOE+00 Mn-64 3.58E+00 5.75E-08 2.11 E-03 1.21 E-10 4.48E-03 Nb-94 7.92E+00 1.27E-07 9.07E-03 1.1SE-09 426E-02 tNl-63 4.81E-01 7.39E-09 6.72E-02 4.97E-10 1.84E-02 Pu-238 2.83E+01 4.3E-07 1.92E-02 8.70E-09 3.22E-01 Pu-239 2.61 E+01 4.19E-07 6.96E-03 2.922-09 1.08E201 Pu-241 9.84E-02 1.5E-09 3.85E-01 6.07E-10 2.25E-02 Sr-so 2.90E+01 4.65E-07 3.94E-02 1.83E-08 6.77E-01 Tc-99 3.21 E+00 5.14E-08 1.20E-01 6.17E-09 228E-01 Total 1.57E+02 2.52E-06 1.00E+00 4.69E208 1.74E200 Conclusion At a nominal activity of 1,uCi, composed of a conservative radionuclide mix, an ingested particle would result in a conservative estimated dose of 1.7 mnrern. For ingestion of a 1 giCi Co-60 particle, the CEDE is conservatively estimated as 6.96 mnrem.

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BCY-HP.0125 Revision 0 Page 8 of 18 AlTTACHMENTS

1. ENDOS runs for the shortest and longest half-life nuclides listed in the LTP.
2. Mev/g for Target Organs from Disintegrations in the Small Intestine.
3. Mev/g for Target Organs from Disintegrations in the Upper Large Intestine.
4. Mev/g for Target Organs from Disintegrations in the Lower Large Intestine.
5. Mev/g for Target Organs from Disintegrations in the Stomach.
6. Part 61 Analysis of Waste Disposal Building Composite in 2000.

REFERENCES

1. Internal Commission on Radiological Protection, 1977-1982, Annals of the ICRP, Limits for Intakes of Radionuclides by Workers, ICRP Publication 30.
2. Connecticut Yankee License Termination Plan. August 2002, Revision 1. pages 5-22 to 5-24.

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BCY-HP-0125 Revision 0 Page 9 of 18 19-DEC-02 RADIATION SAFETY & CONTROL SERVICES, INC.

Shortest Half Life NUMBER OF DISINTEGRATION TABLE RADIONUCLIDE ******************************

Shortest PHYSICAL HALF-LIFE - 3.120E+002 DAYS RESPIRATORY AND GI TRACT MODELS *********************

ACUTE INGESTION INTAKE STANDARD ICRP 30. GI TRACT MODEL USED FRACTION OF INTAKE DEPOSITED IN STOMACH = 1.000 PARAMETERS FOR SYSTEMIC MODEL ***********f**********

COMPARTMENT COEFFICIENT BIOLOGICAL HALF-LIFE (DAYS) 1 1.OOOE+000 2.200E-006 INTAKE ************************************

NUMBER OF DISINTEGRATIONS IN REFERENCE MAN CALCULATED WITH INTAKE OF 1.0 Bq i

'BCYHIP-0125 Revision 0 Page 10 of 18 PAGE 2 PARAMETERS FOR LUNG AND GI TRACT. MODELS

  • GI TRACT PARAMETERS GI TRACT REMOVAL HALF-TIME REGION (DAYS)

S 2.888E-002 Si 1.155E-001 ULI 3.755E-001 LLI 6.931E-001

i.

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- L I :~I BCY-HP.0125 Revision 0 Pagellof 18 1

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PAGE 3 NUCLEAR TRANSFORMATIONS IN BODY RESULTING FROM A 1.0 Bq INGESTION INTAKE OF Shortest NUMBER OF TRANSFORMATIONS IN COMPARTMENTS FROM 0.OOOE+O0O DAYS O.OOOE+000 DAYS TO TO FIFTY YEARS 2.OOOE+000 DAYS COMPARTMENT RATIO SYSTEMIC COMPARTMENT 1 TOTAL SYSTEMIC STOMACH SMALL INTESTINE UPPER LARGE INTESTINE LOWER LARGE INTESTINE TOTAL GI TRACT NASAL PASSAGE LUNGS 0.OOOB+OOO O.OOOE+000 3.600E+003 1.439E+004 4.672E+004 B.607E+004 1.508E+005 O.OOOE+000 O.OOOE+000 O.OOOE+000 O.OOOE+OOO 3.600E+003 1.439E+004 4.491E+004 5.829E+004 1.212E+005 O.OOOB+OOO O.OOOEiOOO 1.OOOE+000 1.OOOE+000 9.612E-001 6.773E-001 8.038E-001

BCY-HP-0125 RevIslon 0 Page12of 18 19-DEC-02 RADIATION SAFETY & CONTROL SERVICES, INC.

Longest Half Life NUMBER OF DISINTEGRATION TABLE RADIONUCLIDE ******************************

Longest PHYSICAL HALF-LIFE 7.770E+007 DAYS

                                          • RESPIRATORY AND GI TRACT MODELS
  • ACUTE INGESTION INTAKE STANDARD ICRP 30 GI TRACT MODEL USED FRACTION OF INTAKE DEPOSITED IN STOMACH = 1.000 PARAMETERS FOR SYSTEMIC MODEL **********************

COMPARTMENT COEFFICIENT BIOLOGICAL HALF-LIFE (DAYS) 1 1.OOOE+000 2.200E-006 INTAKE ***********************************

NUMBER OF DISINTEGRATIONS IN REFERENCE MAN CALCULATED WITH INTAKE OF 1.0 Pq I

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BCY-HP-0125 Revision 0 Attachment I Page 13 of 18 PAGE 2 1*7 FPARAMETERS FOR LUNG AND GI TRACT MODELS tiVr*********t GI TRACT PARAMETERS GI TRACT REMOVAL HALF-TIME REGION (DAYS)

S 2.888E-002 SI 1.155E-OO1l UI.I 3.75SE-OO1 LLI 6.931E-001 I_

BCY-HP.0125 Revision 0 Page 14 of 18 PAGE 3

-NUCLEAR TRANSFORMATIONS IN BODY RESULTING FROM A 1.0 Bq INGESTION INTAKE OF Longest NUMBER OF TRANSFORMATIONS IN COMPARTMENTS FROM O.000E+000 DAYS O.OOOE+000 DAYS TO TO FIFTY YEARS 2.000E+O00 DAYS COMPARTMENT RATIO SYSTEMIC COMPARTMENT 1 TOTAL SYSTEMIC STOMACH SMALL INTESTINE UPPER LARGE INTESTINE LOWER LARGE INTESTINE TOTAL GI TRACT NASAL PASSAGE LUNGS 0.000E+000 O.OOOE+000 3.600E+003 1.440E+004 4.680E+004 8.640E+004 1.S12E+005 o.OOOE+000 0.000E+000 O.OOOE+000 0.00OE+000 3.600E+003 1.440E+004 4.498E+004 5.844E+004 1.214E+005 0.000E+000 0.OOOE+000 1.000E+000 1.000E+000 9.610E-001 6..763E-001 B.030E-001

BCY-HP-0125 Revlslon 0 Page 15 of 18. Mevlg for Target Organs from Disintegrations In the Small Intestine I1 MeV per UleV per MeV per MeV per leV per MeV per 11eV per MUV per M4eV per MeV per MeV per NoV pu M.

eV per MeV per UeV per MeV per

,q,,

l b g

Bone VW a

b S1/__

g l bq bq gIbq Q/bj g/bq g bq g / bq g / bq g / bq g I bg q

Lbq g/ bq Bone Nuclid Adrenals Surf Btust Gonads Kidneys Uver LU Wall Lunns Pancreas R Marrow St Wall S

STWa S

IVnmus lhyroid UU wall Uterus Ag-108m 5.94E-03o0.ooEo 1.88E-02 1.868-01 1.49E-02 8.74E433 332E-02 3.14E-03 9.61E-03 2.45E-02 8.38E-01 0.00E+00 0.OOE+00 O.OOE+00 O.OOE+00 1.14E-01 0.00E400 Ar-241 N/A1 NrA NrA NWA N/A N/A N/A NWA NWA NWA NtA NWA NWA NrA NWA NIA N/A C-4 NJA WA WNA N/A N/A N/A N/A WA N/A NWA NIA NrA NWA NWA WA W/A WA Cn-24_ NA N/A NWA NA N/WA N/A NIA NWA NA WA NA NWA NWA WA WNA N/A NWA Co-60 8.21E-03 O.ooE+00 25E-02 2.56E-01 0.00E+00 1.0E-02 4ME-02 4.84E-03 O.00E+00 3.28E-02 3.02E-01 0.002E00 O.00E400 1.21E-03 o.00E+00 1.47E-01 5.53E-02 Cs-134 N/A NWA NWA N/A NA N/A N/A N/A N/A N/A NWA NWA NWA NWA W/A N/A N/A Cs-137 N/A NA WA WA WA WA WA N/A WA NA N/A N/A WAA WNA NIA NJA N/A Eu-162 3.89-E03 1.382-03 127E-02 1.30E-01 1.04E-02

.0sE5-03 22sE-02 2.25E-03 6.22E203 1.73E-02 2.61E-01 041+00 O.OOE400 0.002+00 0.00E+0017.50E-02 O.OOE+O00 Eu154 4.15E-03 1.43Eo03 o.00E40 1.40oE41 0.OOE+00 848E-03 2.42E-02 2.42E-03 0.001240 1.73E-02 4.23E-01 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+WO 7.I2E-02 o.ooE+00 EuI-155 o.002 1.62-04 0.002+00 1.0812-02 0.002+00 372E-404 1.73E-03 6.91 E.05 0.OOE-100 2.26E-03 0.00r=i00 0.002+00 0.00r24

-00 000400 0.00E400 5.88E-03 0.00E4001 Fe-55 i.goE-14 0.002400 1.61E-06 5.042-05 0.00E400 8.8652-08 2.4212-05 7.78E-18 0.OOE-400 1.67E-08 5.18E-03 1.8112-10 0.002+00 0.00E400 '3.OOE-.00 3.89E204 0.002400 3

N/A NWA N/A NWA N/A N/A N/A N/A NWA NWA N/A N/A N/A N/A NWA N/A N/A Mn-54 2E5-3 9.502-04 2SE-03 9.72E-02 7.60E-03 4.41E403 1 84E-02 1.68E803 4.84E-03 1.1 8E-02 7.69E-02 0.00E+00 0.00E+00 3.72E-04 O.OOE+00 5.36E-02 1.99E-02 Nb-94 ooEoc

.+oo OE40 0.001400 9.002-03 O.OOE+OO o.OOE20 3.02E-02 3.11 E-03 o.OEa00 22s2-0 320E-01 0.00E+0 0.00E+00 0.00E+00 0.00E+00 1.04E-01 0.002+00 NI63

.00E+00 0.00E+0o 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00.E*00 0.00E+00 0.000E+0 1.81E-02 0.00o2o+00 0.00WE+00

.ooE+00 OOE400 0.002E00 Q.OOE+00 PU-238.E400 O.OOE+W o.wE+oo

.002+00

.400 0.002o.o+E+00 O.OOE+00 OOOE400 O.OOE+00 O.OE+00O 0.00 0 0.E+00 0.00E+00 0.00E+00 O.0E2400 0.002+00 0.002+00 Pu-239 O.oE OO.E4o 0.00.+00 0.00W+OO O.0OE+00 0.000E+00 o.0E+00 O.OOE+00 0.OOE+00 0.002400.OOE00W+00 O.OCE+00 0.02 O00+00

.OOE0 0 0.00240

.OOE+0E Pu-241.0024WE00.C 00 0.00.E+DO 0.00E+

O.0E0400 I 0.00240 o.020.0 0.00E400 O.OoE 4

W 0

.004E40 Qo 0.004E+00 O.OE+00 O.OOE+00 0.00E+00 0.002400,0.00E+00 Sr-9

.ooE+oo0.00o+00 0.00o+OW 0.00 0.W00.000.0 0200 O.OOE+0 0.0CI+00 O.OOE+

0.OOE40

.oOE400 0.00E+00 0.00E+4W 0.00E+00 o.o0E04 Q.OOE+00 0.ooE4+0 Tc-99 00.00 00 0.00E00 a.00240 0.00400 0.004W 0.00400 I0G.00E0 0.002+00 0.002400 0.00E+00 0.00Not 0nIR 3

'Values Not Pro vidled in ICRP 30.

BCY-P-0125 Reision 0 Page 16 of 18. Mevlg for Target Organs from Disintegrations In the Upper Large Intestine MeV per MeV per MeV per MeY per MeV per MeV per MeV per UleV per leV per MeV per MeY per MeV per MeV per MeV per l4eV per MeV per MeV per gIbq albq 9 gL jgbq I g/bq ubq g/bq 91bq _ glbg glbq gqibq jbqg 91q glbq g/bq g/b

-g/bq Bone Nuclid Adrenali Surf Bremast Gonads Kke" Lihvr LU Wall Lungs Pancreas R Marrow Sl Wall sawn ST Wall rhymus Thyroid ULI wall Uterus Ag-108m 1.s7Eg02

.OE4Woo 5.82E-02 7.452-01 4.26E5-02 97-02

.83E-02 1.13E202 2.84E42 8.81E-02 25E-01 a

.OOE+0.0040

.O0+00 0.0W02 4.72+00 E.00400 241 wA1 NtA WIA NtA NA IA WA WA

/AA A

I A

WA WA N/A NIA WA WA C-14 N/A NIA IA NWA NWA NWA N/A N/A WA NWA WA NA N/A N/A N/A NWA N/A Cm-24 N/A N/A MA NA NIA NA WA WA NA NWA WA WA N/A A

N/A NWA-WNA CO-60 67E-02 0.004W0 8.42E-02 6.08E-01 O.00E+O 5.61E-02 6.74E-02 197E-02 D.OOE+00 8.98E-02 3.37E-01 O.OOE+O O..E+00 4.21E-03 o.OOE+00 1.S4E400 1.092-01 CS-134 N/A WA WA WA NA WA N/A N/A WA N/A N/A N/A WA N/A NWA N/A N/A Cs-137 N/A N1A WA NIA NIA N/A WA N/A

/A WA WA NA WA N/A N/A NWA NWA Eu-152 1.21E-02 932-03 o3E-02 374E-01 3.09E-02 z6E-02 3.37E-02 &42E-03 2.194-02 4.77E-02 I.71E-01 O.oo00+ 0oo5o+o

.00oE400 0.OOE4O 1.35E200 0.00E+00 Eu;154 1.2-02 21E-03

.OOE40 3.86E-01 O.OOE400 Z81E-02 3 9.55E-03 Q.00E+00 4.88E-02 1.BOE-01

.00E400 OOE240

].00E40 0.OOE+00 2.3100 0.00E+00 Eu.-155 0.00400

.77 4 0 O.OOE+

3I1E-02 0.00QE40 1.74E-03 Z33E-03 Z8E-04 0.00+00 B.18E-03 Q.OOE+40O.00E+00 0.004+00 Q.WOOE0 0.00+00 4.49E-01 O.OOE00 Fe-55 1.83E-14

.00E+

522E-07 2.34E-04

.0E400 4.49E-07 7.02E4-25E-17 OOE40D 3.93E-06 1.54E -05 1.6E-10 0.001+40 0.002E00 0.00o+00 2.78E-02 O.OOE400 H-3 NIA VA WAA NA NTA-NIA N/A NWA NWA tVA N/A WA N/A N/A NIA WA NWA Mn-54

.2sE-03 82-E03 2.87E-02 2.92E401 2.19-02 1.94E-02 2.50-02 6.17E-03 I.542402 3.14E.02 1 23E-01

.002E00 0.00240 1.322-03 O.DOE+OO 9.65E-01 3.65E-02 Nb-94 O.WE400

.oOE4 Q.OOE+00 3.39E02 O.WE4+O

.00E+00

.T7E402 1.12E-02

.00+OO 5.18E-02 233E-01

.OOE+0

.00E+O O.0E+40 0.00E400 1.71E+00 0.00E+00 NI-3

.0WE+OO Q00E2400

.00+00

.00 O.OOE+

OO Q.00Eo00 E002OO

.00400.0 00

.00 4E+00

.00EW0 0020 0E+W0

+0

.00*00.00E+00 0.002+00 1.09E-01 0.002E+

PU-238 O.WoE+W 1.97E-

.E+00O2O 11 E07 o.00o2+00

.05E-0 37205 1.011E-07 J.O0+O0

.14E-05

.00 E00

.002.00

.002400

.0OE400 O.0E+00 7.

40 0.00E+00 Pu-239.00E+00 1.02E-06 0.002400 8.0727 0.00E+0 372E06 1.43E-05 37E-07 O00O+00 1.57E-05

.00+0 Q

+O 0005+0 0.0E40 0.00.+00

.46E+00 0.00E+00 Pu-241 DoE+0 oo.00O+00

.E+020 O.00E+00

.00E+00

.0E2+0

.00E+0W 0.OOE40O

.002400 0.00E+00 O002+O0

.0E0400

.002+00

.00+00 0.00E+00

.002+00 0.00E+0o Sr-9O o.002+o 1.172-09 0.0020 O.002E+00 o.00E+00

.000 552-0 2.41 E-14 i.002+0 1.97E-08 E.00+00 0.00E+00 0 00

.002400 0.OOE+00 7.132E+0 0.002+00 Tc-99 6..0400 O.OO200 4OOE+O0 ODOE+W

.oo+00

.002400 6.0025+00

.002.0.0E+00 O.OOE+0 E.00400 0.00E+00 0002400

.002+500 O.O0+00 8.42E-01 o.oo0+o0

'Values Not Provided in ICRP 30 I

I i

BCY-BP-0125 Revision 0 Page 17 of 18. Mev/g for Target Organs from Disintegrations in the Lower Large Intestine MeY pcr MeV per MeV per MeY per MeV per MeV per MeV per MeY per MeY per MeV per MeV per MeV per MeV per MaY per MeV per MeV per MeV per g~bg -

gIbg g I bg gb / bq jjbq 91bq g.b.

gibq gibq obq g/bq gIbq 91bq Ubg gbib gibq Nucilde Adrenals Surt Breast Gonads Kldnevs Uver LU Wall Lungs Pancreas R Marrow SI Wall Spleen ST Wall Thymus Thyrold UU wall Uterus Aq-108m 11.42E-02 O.OOE+00 1.23E-01 2.o012+0o o 46E-02 9.96E-03 1.37E01

.7103 2.16E-02 1.29E-01 2-62E-01 0.OaE4-0 0.0012400 0.00F2.&

0.00E4ZO J.E-01 0.002+00 241 N/A' N/A NIA NWA NWA N/A NWA NIA N/A NWA N/A N/A NWA NWA NWA N/A N/A C-14 N/A N/A N/A NWA NWA N/A N/A NWA N/A NWA N/A N/A N/A NWA N/A N/A N/A Crn-24 N/A N/A N/A NWA NtA N/A N/A N/A NWA N/A N/A NWA NIA N/A N/A N/A N/A Co-60 2.07-02 G.00E400 1.6841 2.81E+00 0.00E+00 1.8142 389E2+00 1.482-02 0o.+OE00 2.38E-01 3.E701 0.00E+00 0.00E+00 3.42E03 0.00E+00 1.71E-01 2.332-01 Cs-134 NVA NVA NWA N/A N/A N/A N/A WA WNA WNA N/A NWA N/A N/A N/A N/A N/A Cs-137 N/A N/A N/A NVA NA N/A N/A NWA NA NA NA NWA N/A N/A N/A NWA N/A Eu-152 9.33E2-3 1.O9E02 8.2-02 1.422+00 1.812-02 7.77E003 3.SSE+00 &580E3 1AOE4-02 1.5X-01 1.76E-01 O.0E+00 O.WE002-O.OOE+00

&29E-02 Q.OWE+00 Eu-154 1.04E-02 1.11-02 0.OOE+OO 1.47+00 0.4+00

.29E-03 0.74E+Oo 6.63E-03 QOOE+OO 1.35E-0l 1.87o-01 0.00E+00 0.00E+00 0.00QE+00 00000 &81E-02 0.00Q+0 Eu-155 o.oo0+oo 1.40,-03 o.002+00 1.042-1O O.008-toO 2.28E-04 1.30+E00 1.4E-04 0.00E+00 1.87E-02 Q.OOE+00 0.000+00 0.002E+00 0.OE+00 0.00E+00 570-E03

.OOE+00 Fe-55 1.042-15 0.00WE+OO

.81 E-07

.60-04 0.00E+00 1.50E-16 829E-02 2.69E-16 0.00E+00 1.37E-08 124E-05 7.772-12 O.

OOE+00 0.00E+00 0.002-tOO 5.18E-05 0S.0E+00 H-3 NtA WA N/A NWA N/A N/A N/A W/A N/A N/A N/A NA N/A N/A WA N/A N/A Mn-54 7.230-0 7.E2-6.072-02 9.01 129E-02 5.68E-03 8.27E-01 4.13E-03 1.0-02 8.680-2

.24E-01 O.0E400 0.00+00 1.03E-03 0.00 Q

E+

6.68E-02 7.75E-02 Nb-94 o.002+o0o O.OOE+00 0.00+00 18-01

.00+00 0.00E+00 4.810E00 7.670-03 0.00QE+00 1.S6-01 2.201 0.00o00 0.00E+00 0.00+00 0.0020E 1.09E-01 Q.WE-aCO Ni-63 o.0E+a0 0.002+0 0.00E+0 o.0o0200 0.0000 0.WE000 3.26E-01 0.E0+00 0.006+00 0.002+00 O.0WE+W00 0.00+00 0.00E+00 0.00E40 0.0+00W O.OE+0 0.00E+00 Pu-238 o.00E+0o 1.4C-E5 o.ooL+oo 7mE-06 oOOE000 7T.7-2.12+01 4.482 oo0.08 o 2.8-04 O.ooE+00 0.00+00 0.002+00 0.00E+00 0.002400 2.331-04 0.00E+00 Pu-239 O.OOE+OO s.22E-m 0OOE+Wo 1.12E-M 0.00E+00 90E07 1.97E+01 1.76E0 0.004+00 9.ME-05 0.00E+00 0.001+00 0.00E+00 0.00E+00 0.00E400 9.33E-OS 0.00+00 Pu-241 Q.OO+OO 111 E-08

.OOE+00 2.81 E-06 O.OOE+00 7E-0 9.8-02 4.56E49 0.00E+00 3.4-T07 Q0E+0000 0.0+00 O.OOE400 0.002+00 QO 00EE 0.00200 O.OOE+00 Sr.90 0.00E+00 1.01E-0 0.000+0IO.O0E+00 0.00E+00 0.00QO+00 2.1910+01 1.55-15 0.0+0 1

+0 a

+00 000 0.00E0010.000400 21 07 0.OE Tc-99 0.OOE+0O 0.00E+00 0.00EO0 Q0.00+0 0.00E+00 0.00E+001 1.97E+00 I.002+0 W 2+00 0.00 +0 O0 OOE ooEoo.oo0 - 000

.00240 0W0

'Values Not Provided in ICRP 30 i

i I

II 0 -

-T--

BCY-JTP-0125 Revision 0 Page 18 or 18. Mev/g for Target Organs from Disintegrations in the Stomach MeV per MeV per l1eV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per NeV per MeV per MeV per MeV per g/bq albq 9/bq gtbq bg p /Ibq

_glbq 9/bq albq a gg Ibbq 9/bq b

bg a

gbq p bg g/q I

Done Nucide AdrenalsB Surf Brast Gonads Kldneys Liver LU Wall Lunags Pancreas arrow Sl Wall Spleen ST Wall Thymus Thyrold UU wall Uterus Ag-108m 2.62E-03 O.OOE+00 4.28E-03 3.82E-03 3.93E-03 2.40E-W M5E-03 4.37E-03 2.08E-02 253E-03 3.061-03 O.OOE+00 O.00E40 0.0017+00 O.OOE+00 3.93E-0 0.0024E0 Arn-241 NWAI NA N/A NWA N/A N/A N/A N/A N/A N/A N/A NWA NWA N/A N/A N/A N/A C-14 N/A NWA NWA NIA N/A

/A N/A NWA N/A WA N/A N/A WA W/A N/A N/A NWA Cm-243 A

NWA NWA NIA WA N/A N/A N/A N/A N/A NA WA NWA N/A N/A NA.-

N/A Co-60 0.00E400

.00E4200 O.OOE,00 0.0OE40 0.0014OOE 0.00E400 0.00E+00 O.OOE+00 0.00E400 0.002+00 O.WEtO4 0.00E4+J0 O.OOE

.0 0.00E+00 0.0025+00 0.00E00 Cs-134 W/A WA NWA WA WA W/A NIA NWA N/A WA NWA N/A N/A N/A N/A NWA N/A Cs-137 NWA N/A WA NIA N/A W/A WA N/A N/A N/A N/A N/A WA N/A N/A WA N/A Eu-152 WE+OO o0ooE0 o oo0E.0 o.ooE000 O.OE+.0 0.00E4.004 00 O.O.040 0.00EW O OOE+OO O.OOE+OO 0.00E240 O.WE+4O O.OOE+0 0 O.WE400

.OOE 00240 0.004-+00 o.00E40 Eu-154 O.OOE+OO o.0+0w 0+00 0.0020E4 O.OOE4+00 0.000 E+4O 0.0E+00

.0024 0.00E40 O

.OO E40W 0.0DE400 0.00E400 0.001400 0.00E+00 0.00WE+00 D.OOE40C Eu-155 01)0o.0 0.0024 oo~o ooE00 0.002+00 MO0DEM 0.0012+00 0.OOE-iO0 0.002+0 0.002+00 000240(

0.002+400

.0.002440 0.0012400 0.OOE-00 0.0015+00 0.0o..o002 001o7oEWo Fe-55 o0.0oE00 O.O0E+00 O.0E40 O.OOE40 0.00E400 O.OOE400 0.002+00 0.00E400O0O.0200 0.00200 0.001+00 0.00240 O

.OO E40 O.W0E400 0.001400 0.00E+00 0.001400 H-3 WA H/A.

WA NWA WA WA N

NA NA WA NA MA NA N/A N/A NA N/A Mn-54 1t7E-03 1.73E-04 Zt11E-03 2.972E03 i.94E-03 1.192-03 7.992-04 2.12-'03 9.4E-03

.21E.03 1ME030 0.004W0 O.OOEW0 3ME.

0.00340WI 1.842-03 5.82E2-Nb-94 0.00W400 0.002400 O.OOE40 0.00E+00 0.00E400 O.OOEOO O.OOE 0E00 0.002400 0.E+

.002+W0 O E

O+

O.OOE+1.00W 0.004 O.W0 0.00E40O 0.00E+00 0.00w+00 0.00E400 NI63 0.00Q4o W

0.00E+00 I00+0oo 0.0E40o0 0OE4W O.O0E4004004 0

.OOE+OO 0.030E+00

.OOE+00 0.00WE4+

0.00E+00 7.342 0.00E+00 0.W0E+00 0.00W+00 0.00E+00 Pu-238 0l.00E+00 0.0W000 0.00E+o0 0.00E400 0 E400 0.00E+00 0.0040 0.00E4+O OOE+oo O.OOE40 0.00E4O 0.0040

0.

0

.OOE+ooo 0.00E400E 0.oo200 0.00EOO Pu-239 o.ooE+O o.ooE.oo ooE+

o O.WE+0 o o0o o2.o O.CO+oo o02E4W O.ooE+W

.0E+00 0.002400 0.WE400 0.002E+0 0.00E+00 0.00240 O..0E+00 O.WE4W00 0.0024 OOO.WE4W Pu-241 O.0WE4+

O.0E4W 0.00E4 O.004O00 0.002400 0.00E40 0.00E+00 0.00E4W O.WE400 O.00E+00 0.OOE+00 0.OOE+4O 0.00E4W 0.00E400 0.0012400 0.00.+00 0.00E+W Sr-90 OOE4W o.o0E+o 0Qw02 O.OOE+o0 0.0024W O

.WO4W I 0.002400 0.001+00 0.00o00 O

.OOE00+00 0.0WE+00 0.00E+00 O..OO4 0.00WE400 0.0E4W

.00.OOE+00 I Tc-99 Q.loE0+0o.WE+OO

.00E+WOO o.00E4w 0.00E400 O.00E4W0 O.0E4+00 O.OOE40 0o.E+00 0.0W0 0.00oE0 o.ooe+oo 4.32-02 o.ooE400 5.61E-01 0.002+o0 0.OOE+00 tValues Not Provided in ICRP 30 i