ML033080271

From kanterella
Jump to navigation Jump to search
Exhibit 4 (Cy Exhibit 5-PANEL 1) - Recd 03/10/03: Panel Attachment 4 - Health Physics Department Technical Support Document - Dose Estimates for an Ingested Particle
ML033080271
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
(DPR-061)
Issue date: 02/07/2003
From: Gad R, Newhouse M
Ropes & Gray
To:
Atomic Safety and Licensing Board Panel
Byrdsong A T
References
-RFPFR, 50-213-LTP, 50-213-OLA, ASLBP 01-787-02-OLA, Haddam Neck-4 (CY-5-Panel 1), RAS 6968
Download: ML033080271 (20)
v • d • e


Text

(9 i6F 5O-P13-OL4 A PRE-FILED, PRE-NUMBERED EXHIBIT COVER SHEET Exhibit CY PANEL1-.

FKAhiAit 4

'1ec'c 3/Ie6/ca

'CLEAR REGULo;ZnRY COMMl'D'

~ei.C_ 4--OfiWExhfi No.I -

In the mno Of

,Stgcaif l/

IDENTISE StaL RECEIVED REJECTED WITHDRAWN Witness For Reporters' Use Only United States of America Nuclear Regulatory Commission before the Atomic Safety and Licensing Board In the Matter of CONNECTICUT YANKEE ATOMIC POWER COMPA-NY (Haddam Neck Plant)

Docket No. 50-213-LTP ASLBP No. 01-787-02-OLA 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).

Submitted by:

R. K. Gad III Martin J. Newhouse Ropes & Gray One International Place Boston, MA 02110 Counsel to CY.

Dated: February 7,'2003.

-1 emp laQ -1 e Sc V - 6 a-9 SEC V A

DOCKETED U SNRC 2003 OCT 31 AM 9: 54 O F t11; R

TfRARY RiLLf ~:,-..J~) AND AOJUWClAVIONS STAFF F

BCY-HP-0125 Revision 0 Page 1 of 18 UNCONTROLLED COPY BECHTEL HEALTH PHYSICS TECHNICAL SUPPORT DOCUMENT DOCUMENT No.

24265-000-G65-GEIH-P0125-000 Connecticut Yankee Decommissioning Health Physics Department Technical Support Document HIPNumber: BCY-HP-0125 Revision #: 0

Subject:

Dose Estimate for an Ingested Particle Date: 12/05/02 Performed By:

Reviewed By:.

Date:

Date:

/V/0S/° Date: A2 //a).

Approved By:

K>

BCY-HP-0125 Revision 0 Page 2 of 18 PURPOSE To provide a dose estimate from the ingestion of a 1,uCi 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 (ITP) in Table 2-12, Radionuclides Potentially Present at HNP, was determined by using 1NDOSO. 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 LIP are long compared to the passage time through the GI tract. Therefore, the number of disintegrations is determined primarily by the clearance time 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-HP-0125 Revision 0 Page 3 of 18 Table 1. INDOS Input Parameters and Values Parameter Value Conunent fl 0

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

Systemic INDOS requires at least one systemic Compartments compartment.

Compartment half life was deliberately set low, since this assessment only Systemic Half Life 2.QOE-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 TI to 0 and T2 to 1.75 days gives the total of Time post intake days disintegrations that occur while the (7V).75 particle passes through the body.

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

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 I Bq.

T1 T2

  1. Distint.
  1. DIstint.

Post Post Upper MDistint.

Lower Half-LIfe Intake Intake Intake # Dlstint. Large Small Large t1 Dlstint.

Nuclide (days) pathway (days) (days) Stomach Intestine Intestine Intestine GI Total Aq-108m 4.64E+04 Ingostion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E05 Am-241 1.58E+05 Ingestion 0

18250 3.602+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+05 C-1 4 2.09E+06 Ingestion 0

18250 3.60E+03 4.68E+04 t.44E+04 8.64E+04 1.51 E+05 Cm-243 1.04E+04 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+05 Co-60 1.92E+03 Inqestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+051 Cs-134 7.53E+02 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.63E+04 1.51 E+05 Cs-1 37 1.10E+04 Ingestion 0

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

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+05 Eu-1 54 321 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 3.60E+03.68E+04 1.44E+04 8.64E+04 1.51 E+05 Fe-55 9.86E+02 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+05 H-3 4.49E+03 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+05 Mn-54 3.12E+02 Ingestion 0

18250 3.60E+03 4.67E+04 1.44E+04 8.61 E+04 1.51 E+05 Nb-94 7.30E+06 Ingestion 0

18250 3.60E+034.68E+04 1.44E+04 8.64E+04 1.51E+05 NI-63 3.65E+04 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+05 Pu-238 3.20E+04 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51E+05 Pu-239 8.80E+06 Inqestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 11.51 E+05 Pu-241 5.26E+03 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+05 Sr-90 1.04E+04 Ingestion 0

18250 3.60E+03 4.68E+04 1.442+04 8.64E+04 1.51 E+05 Tc-99 7.77E+07 Ingestion 0

18250 3.60E+03 4.68E+04 1.44E+04 8.64E+04 1.51 E+05 K- /

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 (MIL),

lower large intestine (LU), 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 Revisimn 0 Page 5 of I8 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 LTP nuclides Dose bsorbed Dose Equivalent Factor Factor Nuclide (Mevlgranbq) (Renmbq)

Ag-_08m 2.39E+01 3.82E-07 Am-241 O.OOE+OO O.OOE+O0 C-14 O.OOE+OO O.OOE+OO Cm-243 O.OO+OO O.OOE+OO Co-60 1.18E+01 1.88E-07 Cs-134 O.OOE+0O O.OOE+00 Cs-137 O.OOE+O0 O.OOE+00 Eu-152 8.30E+00 1.33E-07 Eu-154 1.24E+01 1.99E-07 Eu-155 1.94E+00 3.11E-08 Fe-55 1.1BE-01 1.88E-09 H-3 O.OOE+00 O.OOE+O0 Mn-54 3.58E+0O 5.75E-08 Nb-94 7.92E+00 1.27E-07 NI-63 4.61 E-01 7.39E-09 Pu-238 2.83E+01 4.53E-07 Pu-239 2.61 E+01 4.1 9E-07 Pu-241 9.84E-02 1.58E-09 Sr-90 2.90E+01 4.65E-07 Tc-99 3.21 E+OO 5.14E-08 Total 1.57E+02 2.52E-06 Detennination of Niclide 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 fraction 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 amount.

The sample 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 DAWV from WD1B in 2000 Activity Nucdide Decayed Decay Corrected Nucide uCa e

Coent Fratio Activity Nuclide Fraction (u~llampl)

Coment Fration (UM/sample)

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 2.1 IE-03 Fe-55 7.30E-04 Reported MDA 1.33E-02 4.57E-04 9.01E-03 Co-60 1.52E-03 2.76E-02 1.20E-03 2.36E-02 Ni-63 3.45E-03 6.27E-02 3.41E-03 6.72E-02 Sr-90 2.09E-03 3.80E-02 2.O0E-03 3.94E-02 Nb-94 4.60E-04 Reported MDA 8.36E-03 4.60E-04 9.07E-03 Tc-99 6.10E-03 Reported MDA 1.IIE-O1 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 0.OOE+00 N/A NIA Eu-154 Not Provided 20.OOEoo N/A N/A Eu-155 Not Provided O.OOE00 N/A N/A Cs-134 1.67E-03 3.04E-02 9.03E-04 1.78E-02 Cs-137 1.17E-02 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-O1 Am-241 3.05E-04 5.54E-03 3.04E-04 6.OOE-03 Cm-243 8.10E-05 1.47E-03 7.75E-05 1.53E-03 Total 5.50E-02 l.OOE+00 5.07E-02 l.OOE+00 Calculated Scaled Dose Table 5 lists the scaled dose using the rem per Becquerel values from Table 3 and the nuclide 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 [uCi. Therefore, for a nominal activity of I pLCi, the estimated dose would be 1.74 mrem. For a Co-60 particle with an activity of 1 pCi, the estimated dose would be 6.96 mTem.

BCY-HP-0125 Revision 0 Page7 of 18 Tablc 5. Scaled Dose Based Upon WDB Composite Sample.

Scaled Scaled Total Total Nuclide Total Total Nuclide (MevlgranVbq) (Rng) Fraction (Renlbq) (mReln/Ci Ag-108m 2.39E+01 3.82E-07 1.03E-02 3.94E-09 1.46E-01 Am-241 O.OOE+00 0.OOE+00 6.00E-03 O.OOE+O0 0.00E+00 C-14 O.OOE+00 0.00E+O0 3.55E-02 O.OOE+00 O.OOE+00 Cm-243 O.OOE+00 O.OOE+00 1.53E-03 O.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 0.00E+00 1.78E-02 0.OOE+00 O.OOE+00 Cs-137 O.OOE+00 O.OOE+00 2.21E-01 O.OOE+00 O.OOE+00 Eu-152 8.30E+00 1.33E-07 0

O.OOE+00 O.OOE+00 Eu-154 1.24E+01 1.99E-07 0

O.OOE+00 O.OOE+00 Eu-155 1.94E+00 3.11 E-08 0

O.OOE+00 O.OOE+00 Fe-55 1.18E-01 1.88E-09 9.o1E-03 1.70E-11 6.29E-04 H-3 0.002+00 O.OOE+O0 2.67E-02 O.OOE+00 _O.OE+00 Mn-54 3.58E+00 5.75E-08 2.11 E-03 1.21 E-10 4.48E-03 Nb-94 7.92E+00 1.272-07 9.07E-03 1.15E-09 4.26E-02 NI-63 4.61E-01 7.39E-09 6.72E-02 4.97E-10 1.84E202 Pu-238 2.83E+01 4.53E-07 1.92E-02 8.70E-09 3.22E-01 Pu-239 2.61 E+01 4.19E-07 6.96E-03 2.92E-09 1.08E-01 Pu-241 9.84E-02 1.58E-09 3.85E-01 6.07E-10 2.25E-02 Sr-90 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 16.17E-09 2.28E-01 Total 1.57E+02 2.52E-06 I 1.OOE+00 4.69E-08 1.74E+00 Conclusion At a nominal activity of 1 PCi, composed of a conservative radionuclide mix, an ingested particle would result in a conservative estimated dose of 1.7 mrem. For ingestion of a 1 uCi Co-60 particle, the CEDE is conservatively estimated as 6.96 mrem.

BCY-HP.0125 Revision 0 Page 8 of 18 K>

ATTACHMENTS

1. INDOS 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.

BCY-HP-0125 Revision 0 Attachment I 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

                                • I**** 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 Bq

'BCY-HP-0125 Revision 0 Page 10 of 18 PAGE 2 A_,*************** 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

  • BCY-HP-0125 Revision 0 Attachment I Page 11 of 18 PAGE 3 NUCLEAR TRANSFORMATIONS IN BODY RESULTING FROM A 1.0 Bq INGESTION INTAKE OF Shortest NUMBER OF TRANSFORMATIONS IN COMPARTMENTS FROM O.OOOE+000 DAYS O.OOOE+000 DAYS TO TO COMPARTMENT FIFTY YEARS 2.OOOE+000 DAYS.

RATIO SYSTEMIC COMPARTMENT 1 O.OOOE+OO0 O.OOOE+000 TOTAL SYSTEMIC O.OOOE+000 0.OOOE+O0O STOMACH 3.600E+003 3.600E+003 1.OOOE+000 SMALL INTESTINE 1.439E+004 1.439E+004 1.000E+000 UPPER LARGE INTESTINE 4.672E+004 4.491E+004 9.612E-O01 LOWER LARGE INTESTINE 8.607E+004 5.829E+004 6.773E-001 TOTAL GI TRACT 1.508E+005 1.212E+005 8.038E-OO1 NASAL PASSAGE o.OOOE-000 0.OOOE+000 LUNGS O.OOOE+000 O.OOOE+000 S

  • BCY-HP-0125 Revision 0 Page 12 of 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 = 1.0D0
                                          • PARAMETERS FOR SYSTEMIC MODEL **********************

COMPARTMENT COEFFICIENT BIOLOGICAL HALF-LIFE (DAYS) 1 1.000E+000 2.200E-006 INTAKE ***********************************

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

BCY-HP-0125 Revision 0 Attachment I Page 13 of 18 PAGE 2 A********~*******

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 LILI 6.931E-001 1%

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.OOOE+000 DAYS O.OOOE+000 DAYS TO TO COMPARTMENT FIFTY YEARS 2.OOOE+000 DAYS RATIO SYSTEMIC COMPARTMENT 1 0.000E+000 0.000E+000 TOTAL SYSTEMIC 0.000E+000 0.000E+000 STOMACH 3.600E+003 3.600E+003 1.000E+000 SMALL INTESTINE.

1.440E+004 1.440E+004 1.OOOE+000 UPPER LARGE INTESTINE 4.680E+004 4.498E+004 9.610E-001 LOWER LARGE INTESTINE 8.640E+004 5.844E+004 6.763E-001 TOTAL GI TRACT 1.512E+005 1.214E+005 8.030E-001 NASAL PASSAGE O.OOOEE+000 O.OOOE+000 LUNGS 0.OOOE+000 0.OOOE+000

(

7 IBCY-}IP-0125 Revislon 0 (

Attaclunent 2 Page 15 of 18. Mev/g for Target Organs from Disintegrations in the Small Intestine MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per MoV per MeV per MeV per MeV per MeV per MeV per g/bj glbq glbq g/bq g

gb 9q

/

g/bg qgbg glb g

g/bg g/bq glbq glbq g

g/br g/bg g/bg Bone Nuclid Adrenas Surf Breast Gonads Kidneys Liver LLI Wall Lungs Pancreas R Marrow Sl Wall Spleen ST Wall Thymus Thyroid UU wall Uterus Ag-108m 5.94E-03 O.OOE400 1.88E-02 1.86E-01 1.49E-02 8.74E-03 3.32E-02 3.14E-03 9.61E.03 2.45E-02 8.38E-01 0.ooE400 0.ooE+00 0.OOE+00 o.00o2+00 1.14E-01 O.OOE+o0 Am-241 N/A 1

N/A N/A N/A N/A NUA N/A N/A N/A N/A NIA N/A N/A N/A N/A N/A N/A C-14 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A m-243 NWA N/A N/A N/A NIA NWA N/A N/A N/A N/

A N/A NA N/A N/A N/A N/A Co-60 8.21E-00 0.OOE+00 2.59E-02 2.56E-01 0.oOE+00 1.30E-02 458E-02 4.84E-03 o.0E+00 3.28E-02 3.02E-01 o.ooE+o0 O.OOE+o0 1.21E-03 O.OOE+00 1.47E-01 5.53E-02 Cs-134 N/A NA N/A N/A N/A N/A N/A N/A NIA N/A N/A N/A NIA N/A N/A N/A N/A Cs-137 NUA N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Eu-152 3.82E03 1.38E-43 1.27E-02 130-E01 1.04E-02 6.05E-03 2.25E-02 2.25E-03 6.22E-03 1.73E-02 2.51E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0 7.60E-02 o.00E+00 Eu-15414.15E-03 1.43E-0310.OOE40o M.OE-01 0.002+00 I6.48E-03 2.42E-02 2.42E-03 0.00E400 1.73E-02 4.23E-01 0.OOE.+00 O.002+0 0.O)OE+oa 0.002400I 7.88E-02

.ODOE+00 Eu-155 0.OOE402O 1.602-04 0.00200 1.08E-02 O.OOE00 3.72E4)4 1.73E-03 6.91E-05 O.OOE400 2.25E-03 O.00E+00 000+0 O.OOE2 000.002E4400 O.OE0200 5.88E-03 O.0E2400 Fe-55 1.90E-14 O.04E+00 1.51E-06 5.04E-05 O.OE+00 8.65E-08 2.42E-05 7.78E-18 0.00E400 1.57E-06 5.18E-03 1.81E-10 0.00E+00 o.OOE+00 o.ooE+00 3.89E-04 o.OOE+00 H-3 N/A N/A N/A N/A N/A N/A NUA NIA N/A NWA N/A N/A N/A N/A N/A N/A N/A Mn-54 2.85E-03 9.50E-04 99r-03 9.72E-02 7.60E-03 4.41E-03 1.C42E02 1.68E-03 4.84E-03 1.1862-02 7.68E-02 0.0oE+00 O.0OE+00 3.72E-04 o.00E+00 5.36E-02 1.99E-02 Nb-94 0.02E+00 0.OOE 0

o4.ooE400 9.00E-03 O.OOE+00 O.02E+00 3.02E-02 3.11E-03 O.OOE+00 2.25E-02 320E-01 O.OOE400 0.OOE+00 O.OOE+00 O..E2400 1.04E-01 O.ooE+00 Ni-63 o.0E4

.O0E04O o.ooE+oo00 0.00WEoo 0.00E+00 0.00E+oo 0.00E+00 O.OOE+00 o.0E+00

.00400 1.81OE-02 0.0024s O

.OOE +00 0.00W2+00 O.0E0400 O.OOE400 O.OOE400 Pu-238 o.o0E+00 D.COE400 o.00E400 O.OOE+OO O.OOE+00 0.002400 0.002+00 0.0024 0 0.00240 O.004E+ 0 O.OOE+00 O.W0E400 O.00DE+O O.002400 0.002400 0.00240 Q.o00+0 Pu-239 o.ooE400 0.OOE4CO o.0wE+oo400 0.WE+OO o.

O.OOE 00240O O.0+00 O.OOE+w O.OOE+00 O.OOE400 Q.OOE400 O.oOE+00 o.OOE+00 O.W2E+00 o.w2E400 O.W2E+00 o.00E+00 Pu-241 o.00+o00

.0OE400 O.WE+00 0.o4E+00 O..E040O o.oE0+00 O.0oE+00 O.OOE200 o.0oE400

.0oE400 0.002+00 O.OOE+00 O.oOE+00 O.OOE2+00 O.OOE400 O.OoE+00 O.OOE+00 Sr-9O 0.0000 0.OOE40200 0 O.OOE400 0.00o 0

0.00400 O.OE400 O.OOE+00 O.OOE400 O.0OE40O O.OOE400 0.00o2400 0.002400 O.OOE+00 o.OOE+00 0.00E+00 0.00E400 Tc-99 0.00E+00 0.OOE400 0.00E+00 0.OOE400 0.002400 O.OOE+00 O.OOE400 O.OOE+00 O.OE400 0.OOE+00 O.OOE2+0 O.0OE+00 0.00E+00 0.

OOE+00 O.OOE+00 0.0o0+00 O.OOE+00

'Values Not Provided in ICRP 30 II II II II iIII

(

(

  • BCY-ITP-0l25 Revislom 0 (

Attachmentl 3 Page 16 of 18 Attacbment 3. Mev/g for Target Organs from Disintegratlons in the Upper Large Intestine MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per leY per MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per glbq gnbo a/bq g/bq Ib gllbg_

plbg glbp albg glbg glbq

_9bbq g bq gibq g.bq glbq g/bg glbq Bone ucide Adrenals Surf Breast Gonads Kldneys Liver LU Walt L

Pancreas R Marrow Si Wall Spleen ST Wall Thynius Thyroid ULI wall Uterus Ag-108m 1.67E-02 O.0OE400 5.82E-02 7.45E-ol 4.26E-02 397;-02

.832-2 1.13E-02 2.84E-02 6.B1E-02 2.56E-01

.0.00E+00 0.002iE O.0OE+00 0.00E+00 4.72E400 o.00E+00 Am-241 NWA' NA N/A N/A NWA I/A N/A N/A N/A N/A NWA N/A N/A NWA NIA N/A NWA C-14 N/A NIA N/A N/A N/A W/A NWA N/A NA NIA NWA N/A N/A N/A N/A N/A N/A m-24 N/AA NIA N/A N/A N/A N/A NA NA N/A N/A NA N/A WA NA NA N/A WNA CO-GO 2.67E-02 0.OOE00 8.42E-02 6.08E-01 O.OOE+00 5.61E-02 6.74E-02 1.97E-02 0.00E+00 8.98E-02 3.37E-01 0.OOE+00 0.00E+00 4.21E-03 o.oOE+00 1.542400 1.09E-01 Cs-134 wA WA NWA NWA NIA N/A N/A N/A N/A N/A N/A N/A NWA N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A N/A N/A N/A N/A NIA N/A NIA N/A N/A N/A N/A N/A N/A Eu-152 1.21E-02 3.93E-03 3.93E-02 3.74E- 013.09E-02 Z67E-02 3.372-02 8.42-03 2.192-02 4.77E-02 1.71E-01 0.ooE-oo 0.00E400 0.004E40 O.OOE+00 1.35E+00 0.002EOO EU-154 1.35E-02 4.21E-03 0.OOE+00 3.86Eo01 lO.OE+0 2.81E-02 3.659-02 9.55E-03 0.00E+00 4.88E-02 1.80E-01

.00E4+

0.OOE+o00 0.002Eo O.OOE2400 Z36E+00 O.OOE00 Eu-155.OOE+OO 4.77E-04 O.OOE+00 3.51E-02 O.OOE400 1.74E-03 2.33E-03 Z86E-04 0.00E+00 6.18E-03 0.00E+00 O.OOE+,00

.OOE+00

.OOE400 0.00E+00 4.492-01 o.ooE200 Fe-55 1.63E-14 O.OOE+00 5.26E-07 2.34E-04 O.OOE400 4.49E-07 7.02E-08 2.25E-17 O.OOE+00 3.93E-08 1.54E-05 1.63E-10 0.00+00

.00E+0 o0.00o2o+00 2.78E-02 o.ooE+00 H-3 N/A NVA N/A NWA N/A N/A N/A N/A N/A N/A N/A NIA N/A N/A WA N/A NWA Mn-54 9.25E-03 2-66E-03 2.87E-2 Z92E-01 2.19E-02 1.942-02 2.S5E-02 6.17E-03 1.54E-02 3.14E-02 1.23E-01 0.00E+00 0.00E400 1.32E-03 0.002EOO 3.65E-01 3.65E-02 Nb-94 o.0oo0o E.0E2400 0.00E+0a 3939E02 0.0E2400 o.OOE040 4.77E-02 1.12E-02 0.00E+00 6.18E-02 233E-01 O.OOE+00

.00E400 O.E2400 O.oEo400 1.71E+00 0.00o+o00 Ni-63 0.00E+4 0.004E+00 o.0E+00 O.OOE+00 0.00E400 0.00E40 0.00E4200 o0.00400 0.00E+4 0.00E00 0.002+0 O

.OOE+0200 0.002400 10.OOE400 0.00E400 1.09E-01 0.002Eoo Pu-238 O.00E400 1.97E-06 o.OOE+00 2.11 E-07 flE+m 00 5.052-06 3.37E-05 1.01E-07 0.00E+o0 3.14E2-O.oOEo00 o.00E400

.OOE400 0.00E+00 0.00E+00 7.02E400 O.OOE400 Pu-239 O.0O0OE+

1.02E-06 o.o0E+o0 a.07E-07

.0oOE400

.37E-06 1.432-05 3.37E-07 O.0OE+00 1.S7E-2-5 O0E400 0.0024E0 L.00E+O 0.00400 0.00400 Q.46E+00 0.0E+00 Pu-241 0.004E 0 0.0o0Eoo O.OE2+00

.0+00 0.00200 400 00 0E+00 0.00E+o0 0.0400 0.0400 0.0 o0 o.ooE+oo 0.0 2400 0.0400 0.ooE+00 0.00 Sr-90 o.00E240 1.17E-9 0.00E400 0.00E+00

.0E0400 O.OOE 00 ZSSE-08 Z412-14 0.002400 1.972-08 0.002400 0.002400 0.00240

.00400 0.00400 7.132400 0.002400 T c-ss o0 o0 4 0 o0.COE oo O.002+OO 0.00E+ 00 0.002400 O.OOE+OO O.002+O fL00E 400 0W E240 0.002+ 00 0.OOE.00 0.002400 0.002400

.0024 0 0.002400 6.4 62-01 0.00E400

'Values Not Provided in ICRP 30 i

I I

.I

C BCY-IIP-0125 Revision 0 (

C

~~~~~~~~~~~~Attachment 4

Page 17 of 18. Mev/g for Target Organs from Disintegrations in the Lower Large Intestine MeV per Me')per MeV per Me')per Me')per Me')per MeV per MeV per Me')per MeV per Me') per MeV per Me')per Me')per MeV per Me')per Me'.'per

-glbg.

glbq 9lbg glbg glbg glbg qjbqj glb bg g~ g glbg glbg glbg g*b glbg glbg l

Bone NuiJlde Adrenais Surf Breast Gonads Kdes Uvcr LLi Wall Lungs-Pancreas R Marrow SIWall Spleen ST Walt Thmu Tyrotld UU wail Uterus Ag-108M 1.42E-02 0.OOE2+00 1.2315-01 2.0111S-00 2.4611-02 9.9SE-03 1.37E+01 6.71E-03 2.15E-02 1.89E-O1 2-62E-01 0.00E+00 0.002+00 0.002-400 0.00E4(30 1.21E-01 0.002=+00 Am-241 N/A' W/A N/A W/A W/A NIA N/A N/A N/A N/A N/A Nl/A WA N/A N/A N/A N/A C-1 4 1WA W/A w/A WA

/A N/A

/A N/A N/A N/A

/A N/A N/A N/A N/A NWA N/A Cm-2431 WA N/A N/A N/A WA N/A N/A N/A N/A N/A W/A N/A N/A N/A N/A N/A N/A Co-60 12.07E-02 0.00E+00 1.68E-01 2.81E+00 0.002+00 1.81E-02 3.891E400 1.45E-02 0.0OOE400 2.38E-01 3.572-01 0.0012+00 0.002+00 3.4212-03 0.002+00o 1.7112-01 2.33E-01 Cs-i 341 N/A WA W/A W/A W/A 1A N/A N/A N/A WA N/A NWA N/A N/A N/A W/A N/A Cs-i 371 NWA N/A N/A N/A NWA WA N/A N/A N/A WA W/A WA N/A N/A N/A WA N/A Eu-1 52 9.332-03 1.0912-02 8.29-02 1A42E+00 1.812-02 7.772-03 3.68E+00 5.80E-03 1.40E-02 1.35r=-01 1.762-01i 0.00+00 0.0012+00 0.002+00 0.002+00 8.29E-02 0.002:+00 Eu-154 1.042-02 1.11E-02 0.002+00 1.472+00 0.002+00 8.29E-03 6.74E+i00 6.532-03 0.002+00 I35E-0l 1.872-01 0.002+00 0.00E+00 0.0012+00 0.002+00 8.812-02 0.002*00 Eu-155 0.002=+00 1.40E-03 0.00E*00 1.042=-01 0.002+00 2.252-04 1.30240011.452404 0.002+00 1.87=- 02 0.0012+00 0.0023+00 O.OOE400 0.002+00 0.0012+00 5.70E243 10.002+00 Fe-55 1.042-15 o.002+00 a.B1E-07 8.852-04 0.002+00 1.502-16 8.292-02 12.692-16 0.002+00 1.871248 1.24E-05 7.772-12 0.002+00 0.002+00 0.OOE+00 5.182-0 0.002+001 H-3 N/A N/A N/A N/A N/A N/A N/A N/WA N/A NIA N/A N/A N/A N/A N/A N/A N/A Mn-5417.23E-03 7.232-03 6.072-02 19.902-0?

1.292-02 5.682-03 8.27E-01 4.13E-03 1.08E242 8.682-02 1.2.42-0 0.092+00 0.002+00 1.0312-03 0.0012400 5.652-02 7.7SE.02 Nb-94 o.002!+o0 0.00=+00 0.002,+00 1.962401 0.002+00 I0.002:+00 4.81 2+00 7.671E-03 0.002400 1.662-01 2.382.01 0.002+00 0.002+00 0.002400 0.0024001 1.092-01 0.002+00 Ni-63 0.0012+00 0.002,00 0.00E,00 0.0025+00 0.0012+00 O.002.00 3.262-01 0.002+00 0.002+00 0.002+00 0.002+00 0.0012+00 0.00E+00 0.002-+00 0.002+00 0.002+00 0.002400 Pu-238 0.0012+00 1.402-05 0.002,00 7.9925-06 0.002+00 7.772-08 2.12r=+o1 4.4612-08 0.002+00 2.282-04 0.002+00 0.0025+00 0.002+00 0.002400 0.002+030 2.332.04 0.002+00 Pu-239 0.002+00 6.222-06 0.002+00 1.12E-05 0.002+00 2.90E-07 1.97E4.01 1.762-07 0.0025+00 9.842-05 0.002+00 0.002+00 0.002+00 0.002400 0.002+00 9.332-05 0.002+001 Pu-241 0.00200 3112-08 0.002,0 2.812E-06 0.00E+00 7.2E-09 9.8412-02 4.56E-09 0.002+00 3.94E-07 0.0012+00 0.0012+00 0.0012+00 0.002+00 0.002+00 0.0012+00 0.0012*00 Sr-90 0.002+0 1.012.0s 0.002+00 0.002=+00 0.002+00 0.00+00 2.192+01 1.552-15 0.002+00I 1.662-07 0.002+00 0.002400 0.002+00 0.002400 0.002400[2.122-07 0.00E+00 T-99 0.002+

0 0.002+00 0.002+00 0.002+00 0.002+00 0.0012+00 1.97E+00 0.00E+00 0.00124001 0.002+00 0.002400 0.0012+00 0.002+00 0.0012+00 0.00

+0

.0 2+ 00.0012+00

'Values Not Provided in ICRP 30 I

I II I

I I

i

(

(

IBCY-HP-0125 Revision 0 6 "S Page 18 of 18 Attachment S. Mev/g for Target Organs from Disintegrations in the Stomach I

II I

MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per MeV per MoV per MeV per MeV per MoV per MeV per MeV per MeV per MeV per g/bg g/bq glbq glbq g/bq g/bq g/ bq gbq gbq g9bg g

glbg glbq g/b g/b

/bq g/bq Nuclidr Adrenals Surne Breast Gonads Kldneys Liver LU Wall Lungs Pancreas R Marrow Si Wall Spleen STWall Thymus Thyroid ULI wall Uterus Ag-108m 2.62E-03 O.OOE+00 4.26E-03 3.82E-03 3.93E-03 2.40E-03 1.55E-03 4.37E-03 2.08E-02 2.53E-03 3.06E-03 0.00E+00 0.00E+00 o.OOE+OO 0.00+00 3.93E-03 0.002400 m-241 N/AW N/A NIA N/A N/A 1I/A N/A N/A NrA N/A NA NA WA WA WA WA N/A C-14 N/A N/A NA N/A N/A I/A N/A N/A WA NWA N/A NWA NWA N1A N/A N/A N/A Cm-243 NIA NA NIA NIA NIA IVA NWA N/A NIA NIA N/A N/A NIA NIA N/A N/A NIA Co-60 o.oOE40 O.0OE+00 O.OOE+0O O.OOE4M 0.001540 0.OOE400

.OOE+OO 0.OOE+00 O.ooE400

.ODOE+0 0.OOEt00 0.OOE+00

.OOE+0O 0.00E400 O.oE+00 O.OOE+00 o.ooE+00 Cs-134 NA NA WA N/A N/A NWA NA N/A NA NA N/A N/A N/A NIA N/A N/A N/A Cs-137 wA N/A NIA N/A N/A NWA N/A N/A NMA NA N/A N/A N/A NWA N/A NIA N/A Eu-152 o.o02+00 O.OOE+00 0.00E+0W o.oo2-Eoo 0.0aE+00 0.002+0 0.0E0+00 0.00E+00 0.00E+0O O.OOE+00 o.OOE+00 O.OOE+00 0.00E+00 O.OOE400 0.002+00 0.0025+00 O.OOE400 Eu-154 a.oo00O 0.002+00 0.OoE+OO O.OOE+OOO.Oo+00 0.00 O.oOE.E00 O.OOE4+00 0.00200 0.00oEo40 O.OOE

+OO o.00200 O.oOE+00 O

O.OOE+00 0.0024 00 O

.OO 0.

OE+00 0.00oE+O Eu-1 55 00o.2+00w O.OOE+00 0.00+00 0.00240 0.00E+00 0.00100 0.002400 0.00400 I0.0OOE-00 0.00o+00 I O.OOE+o00 0.00E+0 O.OOE400 O.OOE+2400 0.00+O0 0.00E+00 0.00+00 Fe-55 Q0.00E+00 0.00E+00 O.OOE+00 0.00+00 O.OoE0+D O.ooE+D00

.OOE40O OO.400 0.00o2+00 0.00E+00 0.OE+o 0.OOE+00 0.0024E0 0.00E240 0.00E+00 0.002+00 O.0WE+o H-3 N/A N/A N/A N/A N/A W/A NIA N/A N/A N/A N A N/A N/A N/A N/A N/A NIA Mn-54 1.VE-03 1.73E-04 zl1 E03 2.97E-03 1.94E-03 1.192-03 7.99s-04 2.16E-03 9.94E-03 1.21E-03 1.53E-03 0.002+0 o.ooE+4D 3.89E-04 0.002400 1.84E-03 5.62E-04 Nb-94 0.002E40 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+000 0.0E+O0 O.OOE+00 0.00E400 0wE+0 o.OOE2400 0.00E+00 O.oOE+00 0.OOE+00 O.OoE400 0.00E+00 0.002+00 O.OOE+00 NI-63 o.OOE+o o

.OOE+OO O.OE+2+0 0O O.00400 0.00o400 0.00+400 0.0024E0 0.00E+00 0.00E+00 0.002E400 o.ooE+00 7.34E-03 0.00E400 0.002E+00 O.OE+0 O.OoE+00 Pu-2380.002+00 0.00o2o00E O

.OOE 0 O

.OOE020 0.002+400 O.OE40D 0.002+00 O.OOE+

0.00E+0 0.00E400 O.OOE400 0.00E400 O.OOE400 O.OE+00 o.ooE+00 0.002E+00 0.00+00 Pu-239 O o

.ooE+oo 0.0.OO0 0.002+00 0.002 E400 O0OOE+OO 0

400 0.00E+00 0.002E00 0.00E+00 O.OOE40 0.002400 0.002+00 O.OOE+00 0.0E0400 0.00E+00 0.002E+00 O.OE+00 Pu-241 o.

02E+

0 o.OOE+00 0.0040E+

0.W0200 O.OOE+OO o.ooE+00 0.002.02 0 0.OOE+00 0.002400 0.ooE400 O.OOE02 0 0.002400 0.WE2oo 0.002+00 Sr-90 0.00W +OC O.OOE+00 o.oE o0 0.

00 0.0012400 0.00E00W Q.WE O.OOE+0 0.002+00 0.00+

0 0.002+

0 0.00

+0 0.00240 0.002400 0.002+

0 0.002400 0.wE+00 0.0 Tc-99 o.oo0 +0i O.0 2+OO o.0 0 E0 00 o.-

-+- -

0.0 2+0 0.00+

00 0.00 +0 0.002400 0.W E+OO 0.002400 0.002400 o.w E+OO 4.322-02 0.002+O 0 s.512E01 0.002+O0 0.002+00

'Values Not Provided in ICRP 30 i

I I

i

Retrieved from "https://kanterella.com/w/index.php?title=ML033080271&oldid=5411694"