ML20217M677

Annual Effluent Release Rept for 970101-1231, for Wolf Creek Generating Station

ML20217M677
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1997
From:	Warren C WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
WO-98-0037, WO-98-37, NUDOCS 9805050080
Download: ML20217M677 (261)

Text

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l W$LF CREEK NUCLF.AR OPERATING CORPORATION Clay C. Warren Chief Operating Omcer April 30, 1998 WO 96-0037 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station F1-137 Washington, D. C. 20555

Subject:

Docket No. 50-482: Annual Radioactive Effluent Release Report Gentlemen:

This letter transmits the enclosed Wolf Creek Generating Station (WCGS)

Annual Radioactive Effluent Release Report. This report covers the period from January 1, 1997, through December 31, 1997. This report is being submitted pursuant to section 6. 9. '1. 7 of the WCGS unit No. 1, Technical Specifications.

If you should have any questions regarding thic submittal, please contact'me at (316) 364-8831, extension 4485, or Mr. Michael J. Angus at extension 4077 Ver truly yours, Cla C. Warren

! CCR/rir

.~,

Enclosure ,; , ; v V s V

j. cc: W. D. Johnson (NRC), w/a \

l E. W. Mershcoff (NRC), w/a \k j J. F. Ringwald (NRC), w/a K. M. Thomas (NRC), w/a 9805050080 971231 4

PDR ADOCK 05000482 f R PDR P.O. Box 411/ Burhngton, KS 66839 / Phone: (316) 364 8831 j An Equal Opportunity Employer M/F/HCNET

Enclosure to WM 98-0037 :

Page1of29 2-Wolf Creek Nuclear Operating Corporation .

' Wolf Creek Generating Statibn Docket No: 50-482 -

Facility Operating License No: NPF-42

- Annual Radioactive Emuent Release Report -

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Report No. 21 1

Reporting Period: January 1,1997 - December 31,1997 L ~j l

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Enclosure to WO 98-0037 Page 2 of 29 Table of Contents Pag.e Executive Summary 3 Section I 4 Liquid Radioactive Effluents .4 Dose Summary 8 Airborne Radioactive Efiluents 10 Gaseous Effluents 12 Dose Summary 14 Section II 16 Offsilelio'se Calculation 'Manu'al' Limits 16 Maximum Permissible Concentrations 16 Average Energy 17 Measurements and Approximations of Total Reactivity 17 Batch Releases 19 Continuous Releases 19 Doses to a Member of the Public from Activities inside the Site Boundary 19 Percentage Eftluent Concentration Limit 20 Solid Waste Shipments 21 Irradiated Fuel Shipments 22 Section III 24 Meteorological Data 25 Validation and Resultant Changes to Historical Meteorological Data 29 Section IV 30 Unplanned or Abnormal Releases 30 Offsite Dose Calculation Manual 30 Major Changes to Liquid, Gaseous, or Solid Radioactive Waste Systems 30 Land Use Census 30 Radioactive Shipments 30 Inoperability of Airborne Efiluent Monitoring Instrumentation 32 Storage Tanks 30 Attachment I Reprint of 1990 and 1991 Data and Revalidated Meterological Data For 1992 through 1996 Attachment II Offsite Dose Calculation Manual i

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Enclosure to WO 98-0037 Page 3 of 29 EXECUTIVE

SUMMARY

This Annual Radioactive Effluent Release Report documents the quantities ofliquid and gaseous effluents and solid waste released by the Wolf Creek Generating Station (WCGS) from January 1,1997, through

! December 31,1997. The format and content of this report is in accordance with Regulatory Guide 1.21, Revision 1.

Section I of this report provides a summary of the quantities of radioactive liquid and gaseous effluents for this reporting period. An elevated release pathway does not exist at WCGS, therefore, all airborne releases l are considered to be ground level releases. The concurrent meteorological condition gaseous pathway dose determination is met by the WCGS Offsite Dose Calculation Manual (ODCM) methodology of assigning l all gaseous pathways to a hypothetical individual residing at the highest annual X/Q and D/Q location.

l This results in a conservative estimate of dose to a member of the public rather than determining each pathway dose for each release condition. A conservative error of thirty percent has been estimated in the effluent data.

l Sections 11,111, and IV provide, additional information required by Regulatory G side 1.21, Revision 1, and ODCM Section 7.2.

Section II includes supplemental information on ODCM limits, average energies of radionuclides, and total radioactivities for liquid and gaseous effluents; maximum permissible concentrations (MPCs);

continuous and batch releases; calculated doses; and solid waste disposal.

Section III documents WCGS meteorological data for wind speed, wind direction, and atmospheric stability. In addition past problems with the validation and verification of meteorological data are explained.

Section IV provides additional information concerning changes to the ODCM manual, planned and unplanned releases, changes to radwaste treatment systems, land use census, monitoring instruments, l radwaste shipments, and storage tanks quantities.

" Attachment 1" provides 1990 through 1996 meteorological data. See Section til for a d t died explanation.

The 1992 through 1996 data has been revalidated and re-verified using a new computer program. The 1990 and 1991 data has been previously vahdated and reported in the 1991 and 1992 annual reports; however, because of a commitment to include 1990 through 1996 data in this 1998 annual report, the 1990 and 1991 data is also included in Attachment 1.

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" Attachment 11" provides an updated Offsite Dose Calculation Manual. I l

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Enclosure to WO 9s-0037 Page 4 of 29 Section I REPORT OF RADIOACrlVE EFFLUENTS (1997): LIQUID Type of Efiluent Unit Quarter 2 Quarter 1 A. Fission and Activation Products l

1. Total Release (not including tritium, gases, alpha) Ci 2.745E-02 3.976E-02

2. Average Diluted Concentration During Period uCi/ml 1.717E-09 8.533 E-10

3. Percent of Applicable Limit (1)  % 0.55 0.80 B. Tritium

1. Total Release Ci 2.129E+02 7.318E+02

2. Average Diluted Concentration During Period uCi/ml 1.332E-05 1.570E-05

3. Percent of Applicabic Limit (MPC) ' (2)  %

' 4.439E-'01 ' 5.235 E-61 '

~

(ECL)  % 1.3 1.6 C. Dissolved and Entrained Gases

1. Total Release Ci 2.334E-04 8.973E-02

2. Average Diluted Concentration During Period uCi/mi 1.460E-11 1.926E-09

3. Percent of Applicable Limit (3)  % 7.300E-06 9.628E-04 D. Gross Alpha Radioactivity

1. Total Release Ci 6.344E-06 2.850E-05 E. Volume of Waste Release (prior to dilution) Liters 3.939E+07 3.59?E+07 F. Volume of Dilution Water Used Liters 1.594E+ 10 4.656E+10 The applicable limit for the Wolf Creek Generating Station is 5 Curies per year.

, (Reference 10 CFR 50, Appendix 1," Guides On Design ^jectives For Light Water 1

-Cooled Nuclear Power Reactors", paragraph A.2). The value printed here is derived by dividing the total release Curies by 5 Curies and then multiplying the result by 100.

2 This value is derived by the following formula:

(Average Diluted Concentration)(100)

% of Applicable L.irni.t =

(ECL, Appendix B, Table 210CFR20)

This value is derived by the following formula:

(Average Diluted Concentration)(PS)

% of Applicable Lirr.it =  ;

(2E -4 from ODCM Section 2,1)  !

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l Enclosure to WO 98-0037 Page 5 of 29 '

l REPORT OF RADIOACTIVE EFFLUENTS (1997): LIQUID l

l Type of Effluent Unit Quarter 3 Quarter 4 l A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) Ci . 4.897E-02 6.457E-02

2. Average Diluted Concentration During Period uCi/mi 2.037E-09 3.918E-09 j 3. Percent of Applicable Limit (1)  % 0.98 1.3  ;

l B. Tritium

'l. Total Release Ci 2.769E+02 1.290E+02

2. Average Diluted Concentration During Period uCi/mi 1.152E-05 7.828E-06

3. Percent of Applicable Limit (MPC) (2)  % 3.840E-01 2.609E-01 (ECL). .% 1? 0.8 C. Dissolved and Entrained Gases

1. Total Release Ci 1.499E-02 2.665E-02

2. Average Diluted Concentration During Period uCi/ml 6.235E-10 1.617E-09

3. Percent of Applicable Limit (3)  % 3.118E-04 8.087E-04 D. Gross Alpha Radioactivity I. Total Release Ci 2.490E-05 1.461E-05 l E. Volume of Waste Release (prior to dilution) Liters 3.085E+07 3.277E+07 l

F. Volume of Dilution Water Used Liters 2.401 E+10 1.644E+10

1. The applicable limit for the Wolf Creek Generating Station is 5 Curies per year.

(Reference 10 CFR 50, Appendix I, " Guides On Design Objectives For Light-Water

-Cooled Nuclear Power Reactors", paragraph A.2). The value printed here is derived by dividing the total release Curies by 5 Curies and then multiplying the result by 100.

2. This value is derived by the following formula:

. . (Average Diluted Concentration)(100)

% of Applicable Limit =

(ECL, Appendix B, Table 210CFR20)

3. This value is derived by the following formula:

(Average Diluted Concentration) (100)

% of Applicable Limit =

(2E -4 from ODCM Section 2.1) i-

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Enclosure to WO 98-0037 -

P:gs 6 of29 ]

LIQUID EFFLUENTS NUCLIDE Continuous Mode Batch Mode l RELEASED Unit Quaner 1 Quaner 2 Quarter 1 Quarter 2 i H-3 Ci 4.79E-01 4.35E-01 2.12E+02 7.31 E+02 Cr-51 Ci n/a n/a n/a n/a Mn-54 Ci <l .95 E-02 <l .75E-02 2.84E-05 9.69E-04 Fe Ci <3.91 E-02 <3.50E-02 1.87E-02 1.35E-02 Fe-59

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Ci. <l .95E-02 <l.75E-02 <l .46E-04 <5.14E-04 i Co-57 Ci n/a 'n/a n/a 6.79E-05 l Co-58 Ci <l.95E-02 <l .75E-02 2.73E-04 1.46E-03 i Co-60 Ci <l .95 E-02 <l .75E-02 4.49E-03 1.5 I E-02 Zn-65 Ci <l .95 E-02 <l .75 E-02 <l .46E-04 <5.14 E-04 Sr-89 Ci <l .95 E-03 <l .75 E-03 <l.46E-05 <5.14 E-05 )

Sr-90 Ci <l .95E-03 <l .75 E-03 <l .46E-05 <5.14e-05 i Hf-181 Ci n/a n/a n/a n/a i Nb-95 Ci n/a n/a n/a 2.89E-04.

Zr-95 Ci n/a n/a n/a 5.78E-05 Mo-99 Ci <l .95E-02 <l .75E-02 <l .46E-04 <5.14 E-04 Ag-110m Ci n/a n/a 2.01E-06 n/a Sn-113 Ci n/a n/a 2.96E-05 1.38E-04 Sn-117m Ci n/a n/a n/a 1.26E-06 Sb-125 Ci n/a n/a 3.10E-03 5.53E-03 1-131 Ci <3.91 E-J2 <3.50E-02 <2.93 E-04 <l .03 E-03 Cs-134 Ci <l .95 E-02 <l .75 E-02 3.30E-04 1.22E-03 Cs-137 Ci <! .95 E-02 <l .75 E-02 4.53 E-04 1.34E Ce-141 Ci <l .95 E-02 <l .75E-02 <l .46E-04 <5.14E-04 Ce-144 Ci <l.95E-02 ~ <l .75E-02 <l .46E-04 4.41E-05 Gross Alpha Ci <3.91 E-03 <3.50E-03 6.34E-06 2.85E-05 Ar-41 Ci <3.91 E-01 <3.50E-01 <2.93 E-03 <l .03 E-02 Kr-85m Ci <3.91 E-01 <3.50E-01 <2.93 E-03 2.38E-06 Kr-85 Ci <3.91 E-01 <3.50E-01 <2.93 E-03 6.25E-03 Kr-87 Ci <3.91 E-01 <3.50E-01 <2.93 E-03 <l .03 E-02 Kr-88 Ci <3.91 E-01 <3.50E-01 <2.93 E-03 <l .03 E-02 Xe-131m Ci <3.91 E-01 <3.50E-01 <2.93 E-03 4.01E-05 Xe-133m Ci <3.91 E-01 <3.50E-01 <2.93 E-03 1.58E-04 Xe-133 Ci <3.91 E-01 <3.50E-01 2.33E-04 8.32E-02 Xe-135m Ci <3.91 E-01 <3.50E-01 <2.93 E-03 <l .03 E-02

' Xe-135 Ci <3.91 E-01 <3.50E-01 <2.93 E-03 4.31 E-05 Tc-99m Ci n/a n/a n/a n/a Ru-103 Ci n/a n/a n/a n/a Ru-106 Ci n/a n/a n/a n/a Sb-124 Ci n/a n/a n/a n/a Sb-126 Ci n/a n/a n/a 1.38E-06 Te-132 Ci n/a n/a n/a n/a 1-132 Ci n/a n/a n/a n/a Ba-140 Ci n/a n/a n/a n/a La-140 Ci n/a n/a n/a n/a Np-239 Ci n/a n/a n/a .n/a NOTE Less than values are calculated using the Lower Limit of detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The less than values are not included in the summation for the total release values.

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i Enclosure to WO 98-0037 Page 7 of 29 i

LIQUID EFFLUENTS I NUCLIDE Continuous Mode Batch Mode RELEASED l Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 i

11-3 Ci 2.90E-01 2.56E-01 2.77E+02 1.29E402 Cr-5 I . Ci n/a. n/a 8.53E-05 7.13E-03 Mn 54 Ci <l.50E-02 <l .60E-02 6.59E-04 5.69E-04 Fe-55 Ci <3.00E-02 <3.20E-02 1.20E-02 5.31E-03 Fe-59 Ci- <l .50E-02 <l .60E-02 <4.07E-04 3.84E-04 Co-57 Ci n/a n/a 1.18E-05 4.80E-05 l Co-58 Ci <l .50E-02 1.12E-04 4.54E-04 2.47E-02 l

Co-60 Ci <l.50E-02 <l .60E-02 1.13E-02 2.83E-03 Zn-65 Ci <l .50E-02 <l .60E-02 <4.07E-04 - <3.79E-04 Sr-89 Ci <l.50E-03 <l .60E-03 <4.07E-05 <3.79E-05 Sr-90 Ci <l .50E-03 <l .60E-03 <4.07E-05 <3.79E-05 Sr-92 Ci n/a n/a n/a n/a Nb-95 : Ci n/a n/a ~ '4.39E-05 1.' LEE-03 Zr-95 Ci n/a n/a n/a 8.58E-04 j Mo-99 Ci <l .50E-02 <l .60E-02 <4.07E-04 <3.79E-04 Tc-99M Ci n/a n/a n/a 1.05E-05 Ru-103 Ci n/a n/a n/a 2.71 E-06 l - Ag 110m Ci n/a n/a 8.43E-06 n/a Sn-l l3 Ci n/a n/a 3.39E-05 2.82E-05 Sn-ll7m Ci n/a n/a n/a 1.15 E-04 Sb-124 Ci n/a n/a n/a 1.19E-03 Sb-125 Ci n/a n/a 2.16e-02 1.81 E-02 Sb-126 Ci n/a n/a n/a 4.86E-06 1 131 Ci <3.00E-02 <3.20E-02 1.47E-06 <7.59E-04 j

'l132 Ci n/a n/a n/a 6.83E-05 i Te-132 Ci n/a n/a n/a 9.27E-06

' Cs-134 Ci <l .50E-02 .1.07E-04 1.35E-03 6.83E-04 Cs-137 Ci < l .50E-02 <l .60E-02 1.41E-03 6.86E-04 l Ce-141 Ci <l .50E-02 <l .60E-02 <4.07E-04 <3.79E-04 Ce 144 Ci <l .50E-02 < l .60E-02 6.57E-06 <3 79E-04 I Gross Alpha Ci <3.00E-03 <3.20E-03 2.49E-05 1.46E-05 l Ar-41 Ci <3.00E-01 <3.20E-01 <8.14 E-03 <7.59E-03 Kr-85m Ci <3.00E-01 <3.20E-01 8.44 E-06 6.73 E-05 Kr-85 Ci <3.00E-01 <3.20E-01 <8.14 E-03 <7.59E-03 Kr-87 Ci <3.00E-01 <3.20E-01 <8.14E-03 <7.59E-03 l

Kr 88 Ci <3.00E-01 <3.20E-01 <8.14 E-03 <7.59E-03 Xe-131m Ci <3.00E-01 <3.20E-01 <8.14 E-03 <7.59E-03 Xe-133m Ci <3.00E-01 <3.20E-01 1.2 ] E-04 6.34E-04

' Xe 133 Ci <3.00E-01 <3.20E-01 1.48E-02 1.70E-02 Xe 135m Ci <3.00E-01 <3.20E-01 8.14E-03 <7.59E-03 l Xe 135 Ci <3.00E-01 <3.20E-01 1.06E-04 <8.93 E-03 l Na-24 Ci n/a n/a n/a 1.32E-06 NOTE Less than values are calculated using the Lower Limit of detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The less than values are not included in the summation for the total release values.

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1 Enclosure to WO 98-0037 Page 8 of 29 -

LIQUlD CUMULATIVE DOSE

SUMMARY

(1997)

TABLE 1 QUARTER 1 OF 1997 ODCM CALCULATED ODCMI LIMIT .  % OF LIMIT _'

DOSE-TOTAL DOSE (mrem) FOR BONE 3.50E-03 5.00E+00 7.01E-02 TOTAL DOSE (mrem) FOR LIVER 4.43E-02 5.00E+00 8.86E-01 TOTAL DOSE (mrem) FOR TOTAL 4.27E-02 1.50E+00 2.85E+00 BODY TOTAL DOSE (mrem) FOR TIIYROID 3.84E-02 5.00E+00 ~ 7.68E-01 TOTAL DOSE (mrem) FOR KIDNEY 4.03E 5.00E+00 8.06E-01 TOTAL DOSE (mrem) FOR LUNG 3.91E-02 5.00E+00 7.82E-01 TOTAL DOSE (mrem) FOR GI-LLI 3.91E-02 5.00E+00 7.82E-01 QUARTER 2 OF 1997

' TOTAL DOSE (mrem) FOR BONE 7.68E-03 5.00E+00 1.54E-01 TOTAL DOSE (mrem) FOR LIVER 7.80E-02 5.00E+00 1.56E+00 TOTAL DOSE (mrem) FOR TOTAL 7.46E-02 l'50E400

. . 4.97E+00

' BODY TOTAL DOSE (mrem) FOR TilYROID 6.45E-02 5.00E+00 1.29E+00 TOTAL DOSE (mrem) FOR KIDNEY 6.89E-02 5.00E+00 .1.38E+00 TOTAL DOSE (mrem) FOR LUNG 6.60E-02 5.00E+00 1.32E+00 TOTAL DOSE (mrem) FOR GI-LLI 6.96E-02 5.00E+00 1.39E+00 QUARTER 3 OF 1997 TOTAL DOSE (mrem) FOR BONE 7.93E-03 5.00E+00 1.59E-01 TOTAL DOSE (mrem) FOR LIVER 4.15E 5.00E+00 ' 8.29E-01 TOTAL DOSE (mrem) FOR TOTAL 3.79E-02 1.50E+00 2.53E+00 BODY TOTAL DOSE (mrem) FOR THYROID 2.73 E-02 5.00E+00 5.46E-01 TOTAL DOSE (mrem) FOR KIDNEY 3.19E-02 5.00E+00 6.39E-01 TOTAL DOSE (mrem) FOR LUNG 2.89E-02 5.00E+00 5.77E TOTAL DOSE (mrem) FOR GI-LLI 2.92E-02 5.00E+00 5.85E-01 QUARTER 4 OF 1997 TOTAL DOSE (mrem) FOR BONE 1.00E-02 5.00E+00 2.01E-01 TOTAL DOSE (mrem) FOR LIVER 9.53E-02 5.00E+00 1.91E+00 TOTAL DOSE (mrem) FOR TOTAL 9.1IE-02 1.50E+00 6.08E+00 BODY TOTAL DOSE (mrem) FOR THYROID 7.77E-02 5.00E+00- 1.55E+00 TOTAL DOSE (mrem) r'OR KIDNEY 8.34E-02 5.00E+00 1.67E+00 TOTAL DOSE (mrem) FOR LUNG 7.96E-02 5.00E+00 1.59E+00 TOTAL DOSE (mrem) FOR GI-LLI L75E-01 5.00E+00 3.51E+00 TOTALS FOR 1997 TOTAL DOSE (mrem) FOR BONE 2.91 E-02 1.00E+01 2.91E-01 TOTAL DOSE (mrem) FOR LIVER 2.59E-01 1.00E+01 2.59E+00 -

TOTAL DOSE (mrem) FOR TOTAL 2.46E-01 3.00E+00 8.21E+00 BODY TOTAL DOSE (mrem) FOR TilYROID 2.08E-01 1.00E+01 2.08E+00 TOTAL DOSE (mrem) FOR KIDNEY 2.24E-01 1.00E+01 2.24E+00 TOTAL DOSE (mrem) FOR LUNG 2.14E-01 1.00E+01 2.14E+00

. TOTAL DOSE (mrem) FOR GI-LLI 3.13 E-01 1.00E+01 3.13E+00

1. Based on ODCM Section 2.2 which restricts dose to the whole body to less than or equal to 1.5 mrem per quarter an 3.0 mrem per year. Dose restrictic 1 of any organ is less than or equal to 5 mrem per quarter and 10 mrem per year.

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l l Enclosure to WO 98-0037 l Page 9 of 29 LIQUID CUMULATIVE DOSE

SUMMARY

(1997) j TABLE 2 A. Fission and Activation Quarter ! Quarter 2 Quarter 3 Quarter 4 Total Products (not including 113, gases, alpha) l 1. Total Release -(Ci) 2.75 E-02 3.98E-02 4.90E-02 6.46E-02 1.81 E ! 2. Maximum Organ Dose (mrem) 6.25E-03 1,34E-02 1.42E-02 9.77E-02 1.06E-01

3. Organ Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

4. Percent of Limit 1.25E-01 2.69E-01 2.84E-01 1.95E+00 1.06E+00 l

l B. Tritium

1. Total Release -(Ci) 2.13E+02- 7.32E+02 2.77E+02 1.29E+02 1.35E+03

2. Maximum Organ Dose (mrem) 3.80E-02 6.45 E-02 2.73E-02 7.76E-02 2.07E-01

3. Organ Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 -  !

L 4. Percent of Limit ' 7.60E-01 1.29E+00 5.45E 1.55E+00 2.07E+00 This table is included to show the correlation between Curies released and the associated caIculated maximum organ dose. Wolf Creek ODCM methodology is used to calculate the maximum organ dose which assumes that an individual drinks the water and cats the fish from the discharge point. ODCM Section 2.2 organ dose limits are used.

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Enclosure to WO 98-0037 Page 10 of 29 REPORT OF RADIOACTIVE EFFLUENTS (1997): AIRBORNE Unit Quarter ! Quarter 2 A. Fission and Activation Gases

1. Total Release - Ci 1.295E-01 4.519E-01

2. Average Release Rate for Period uCi/sec 1.665E-02 5.748E-02

3. Percent of ODCM Limit (1)  % l .08E-03 7.82E-04 B. lodines

1. Total lodine-13 i Ci 0.000E+00 2.951 E-06

2. Average Release Rate for Period uCi/sec 0.000E+00 3.754E-07

3. Percent of Applicable Limit (2)  % 0.000E400 2.95E-04 C. Particulates

1. Particulates with IIalf-lives > 8 days Ci 0.000E+00 0.000E+00

2. Average Release Rate for Period uCi/sec 0.000E+00 0.000E+00

3. Percent of ODCM Limit (3)  % 0.000E+00 0.000E+00

4. Gross Alpha Radioactivity Ci 6.179E-08 0.000E+00 D. Tritium

' Total Release Ci 1.254E+0i 2.580E+01 Average Release Rate for Period uCi/sec 1.613 E+00 3.281 E+00 Percent of ODCM Limit (4)  % 1.19E-01 2.44E-01

1. The percent of ODCM limit for fission and activation gases is calculated using the following methodology:

% of ODCM Limit = (Qtrly Total Beta Airdose)(100) or (Qtrly Total Gamma Aridose)(100) 10 mrad 5 mrad i

The largest value calculated between Gamma and Beta airdose is listed as the % of ODCM Limit.

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2. The percent of ODCM limit for iodine is calculated using the following methodology: i

% of ODCM Limit = (Total Curies ofIodine-131)(100) 1 Curie

3. The percent of ODCM limit for particulates is calculated using the following methodology:

. . (Highest Organ Dose Due to Particulates)(100)

% of ODCM Limit =

7.5 mrem l

NOTE l This type of methodology is used since the Wolf Creek ODCM ties release limits to doses rather than Curie release rates.

4. The percent of ODCM limit for tritium is calculated using the following methodology:

. . (Highest Organ Dose Due to H -3)(100)

% of 0DCMLimit =

7.5 mrem

i Enclosure to WO 98-0037 Page 11 of 29 1

REPORT OF RADIOACTIVE EFFLUENTS (1997): AIRBORNE Unit Quarter 3 Quarter 4 i A. Fission and Activation Gases

1. Total Release Ci 1.22E+01 1.44 E+00 i

- 2 Average Rd:ase Rate for Period uCi/sec 1.532E+00 1.809E-01

3. Percent of ODCM Limit (1)  % 3.42E-02 6.04E-03 B. lodines L Totallodine 131 Ci 2.27E-07 1.91 E-10

2. Average Release Rate for Period uCi/sec 2.856E-08 2.404E-I l i

3. Percent of Applicable Limit (2)  % 2.27E-05 1.91E-08 C. Particulates L Particulates with Half lives > 8 days Ci 0.00E+00 1.27E-08

2. Average Release Rate for Period uCi/sec 0.00E+00 1.603E-09

3. Percent of ODCM Limit (3)  % 0.00E+00 1.44 E-07

4. Gross Alpha Radioactivity Ci 6.179E-08 0.00E+00 D. Tritium l Total Release Ci 1.83E+01 2.83E+01 Average Release Rate for Period uCi/sec '2.307E40

~ ' l 3.558E+00 '

Percent of ODCM Limit (4)  % 1.76E-01 2.62E-01

1. The percent of ODCM limit for fission and activation gases is calculated using the following methodology:

% ofODCM Limit = (Qttly Total Beta Airdose)(100) or (Qtrly Total Gamma Aridose)(100) 10 mrad 5 mrad The largest value calculated between Gamma and Beta airdose is listed as the % of ODCM Limit.

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2. The percent of ODCM limit for iodine is calculated using the following methodology:

% ofODCM Limit = (Total Curies ofIodine-131)(100) 1 Curie

3. The percent of ODCM limit for particulates is calculated using the following methodology:

. . (Highest Organ Dose Due to Particulates)(100)

% of ODCM Limit =

7.5 mrem NOTE  !

This type of methodology is used since the Wolf Creek ODCM ties release limits to doses rather than Curie release rates.

4. The percent of ODCM limit for tritium is calculated using the following methodology:

. . (Highest Organ Dose Due to II-3)(100)

% of 0DCMLimit =

7.5 mrem I

i

Enclosure to WO 98-0037 I Page 12 of 29 i

GASEOUS EFFLUENTS NUCLIDES RELEASED Continuous Mode Batch Mode Unit Quarter 1 Quarter 2 Quarter ! Quarter 2 l 1. Fission and Activation Gases Ar-41 Ci n/a n/a 7.68E-02 2.90E-01 Kr-85 Ci n/a n/a n/a n/a Kr-85m Ci n/a n/a n/a 2.67E-05 Kr-87 Ci - <2.03E+01 <2.34E+01 <8.19E-04 <3.90E-02 .

Kr-88 Ci <l .51 E+01 < l.75E+01 <6.llE-04 <2.91 E-02 Xe-131m Ci n/a n/a n/a n/a Xe 133 Ci <6.10E+00 1.13E-01 8.76E-03 4.90E-02 Xe 133m Ci <2.89E+01 <3.34E+01 <l.17E-03 <5.56E-02 Xe 135 Ci <3.94E+00 <4.56E+00 5.58E-05 <7.58E-03 Xe-138 Ci <3.17E+02 <3.67E+02 <l .28E-02 <6.10E-01 Total Ci 4.39E-02 1.13E-01 8.56E-02 3.39E-01

2. Italogens (Gaseous) 1-131 Ci <!.88E 2.95E-06

'<7.39E' 09

'<3.' ele'07 1-133 Ci <l .88E-02 <2.17E-02 <7.59E-07 <3.61 E-05 Total Ci 0.00E+00 2.95E-06 0.00E+00 0.00E+00

3. Particulates and Tritium 11-3 Ci 1.22E+01 2.26E+01 2.95E-01 3.25E+00 Mn-54 Ci <l .88E-03 <2.17E-03 <7.59E-08 <3.61 E-06 Fe-59 Ci <2.27E-03 <2.17E-03 <7.59E-08 <3.61 E-06 Co-57 Ci n/a n/a n/a n/a Co-58 Ci <l .88E-03 <2.17E-03 <7.59E-08 <3.61 E-06 Co-60 Ci <l .88E-03 <2.17E-03 <7.59E-08 <3 F E-06 Zn-65 Ci <l .88E-03 <2.17E-03 <7.59E-08 <3.t. 6-06 Mo-99 Ci <l .88E-03 <2.17E-03 <7.59E-08 <3.61 E-06 Cs-134 Ci <l .88E-03 <2.17E-03 <7.59E-08 <3.61 E-06 Cs-137 Ci <l .88 E-03 <2.17E-03 <7.59E-08 <3.61 E-06 Ce-141 Ci <l .88E-03 <2.17E-03 <7.59E-08 <3.61 E-06 Ce-144 Ci <l .88 E-03 <2.17E-03 <7.59E-08 <3.61 E-06 St-89 Ci <l .88E-03 <2.17E-03 <7.59E-08 <3.61 E-06 Sr-90 Ci <l .88 E-03 <2.17E-03 <7.59E-08 <3.61 E-06 Gross Alpha Ci 6.18E-08 <2.17E-03 <7.59E-08 <3.61 E-06 Total. Ci 1.22E+01 2.26E+01 2.95E-01 3.25E+00 Less than values for Noble Cases are calculated using the lower limit of detection (LLD) values obtained at Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates the ODCM LLD values are used.

i Enclosure to WO 98-0037 Page _13 of 29 GASEOUS EFFLUENTS l

NUCL! DES RELEASED Continuous Mode Batch Mode j Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 -

l' 1. Fission and Activation Gases j ' Ar-41 Ci n/a n/a 2.6] E+00 4.19E-01 {

Kr-85 Ci n/a n/a 9.2SE400 n/a-Kr-85m Ci n/a j

n/a n/a 'n/a  ;

Kr-87 Ci <2.42E+01 <2.44 E+01 <2.78E-01 <2.84E+00 Kr-88 Ci <l .81 E+01 <l .82E+0! <2.08E-01 <2.12E+00 Xe 131m Ci n/a n/a n/a n/a {

! Xe-133 Ci 7.80E-02 7.96E-01 2.40E-01 1.79E-01 1 I

Xe-133m ' Ci <3.45E+01 <3.48E+01 - <3.97E <4.06E+00 Xc-135 Ci- <4.71 E+00 4.32 E-02 5.97E-04 <5.53 E-01 Xe-138 Ci <3.79E+02 <4.74 E+00 <4.35E+00 <4.45E+01 -

Total Ci 7.80E-02 8.39E-01 1.21E+01 5.99E-01

2. IIalogens (Gaseous) i 1-131 Ci 2.27E-07 <2.24E-04 <2.57E 06 1.91E-10

. 1-133 Ci <2.24E 02 <2.26E-02 <2.57E-04 <2:63E-03 Total Ci 2.27E-07 0.00E+00 0.00E+00 1.91E-10

3. Particulates and Tritium 11-3 Ci 1.28E+01 2.02E+01 5.57E+00 8.l lE+00 Cr 51 Ci n/a n/a n/a 3.14E-09 Mn-54 Ci <2.24 E-03 <2.79E-03 <2.57E-05 2.07E 10 Fe-59 Ci <2.24E-03 <2.79E-03 <2.57E-05 <2.63E-04 Co-58 Ci <2.24 E-03 <2.79E-03 <2.57E-05 8.46E-09 Co-60 Ci <2.24 E-03 <2.79E-03 <2.57E-05 3.77E-10 l Zn-65 Ci <2.24 E-03 <2.79E-03 <2.57E-05 <2.63E-04 l Zr-95 Ci n/a n/a n/a 2.31E-10 L Nb-95 Ci n/a n/a n/a 3.24E-10 Mo-99 Ci <2.24 E-03 <2.79E-03 <2.57E-05 <2.63 E-04 Cs-134 Ci <2.24 E-03 <2.79E-03 <2.57E-05 <2.63 E-04 Cs-137 Ci <2.24 E-03 <2.79E-03 <2.57E-05 <2.63 E-04

! Ce-141 . Ci <2.24 E-03 <2.79E-03 <2.578-05 <2.63E-04 l ' Ce-144 Ci <2.24E-03 <2.79E-03 <2.57E 05 <2.63 E-04 Sr-89 Ci <2.24E-03 <2.79E-03 <2.57E-05 <2.63 E-04 Sr-90 Ci <2.24E-03 <2.79E-03 <2.57E-05 <2.63 E-04 Grcss Alpha Ci <2.24 E-03 <2.79E-03 <2.57E-05 <2.63 E-04 Total. Ci 1.28E+01 2.02E+01 5.57E+00 8. l l E+00 l

Less than values for Noble Gsses are calculated using the lower limit of detection (LLD) values obtained at Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates the ODCM LLD values are used.

l l j

1 Enclosure to WO 98-0037 Page 14 of 29 G ASEOUS CUMULATIVE DOSE

SUMMARY

(1997)

Table 1

- QUARTER I OF 1997 . ODCM CALCULATED . ODCMI LIMIT  % OF LIMIT i . DOSE l TOTAL DOSE (mrem) FOR BONE 0.00E+00 7.50E+00

!^

~ 0.00E+00 .

TOTAL DOSE (mrem) FOR LIVER 8.87E -03 7.50E+00 1.18E-01

TOTAL DOSE (mrem) FOR TOTAL 8.87E-03 ~ 7.50E+00 1.18E-01 BODY TOTAL DOSE (mrem) FOR THYROID 8.87E-03 7.50E+00 1.18E-01 l- TOTAL DOSE (mrem) FOR KIDNEY 8.87E-03 7.50E+00 1.18E-01 L TOTAL DOSE (mrem) FOR LUNG ' 8.87E-03 7.50E+00 ' l .18E-01 j TOTAL DOSE (mrem) FOR GI-LLI 8.87E 7.50E+00 1.18E-01 :

- QUARTER 2 OF 1997

. TOTAL DOSE (mrem) FOR BONE 5.14E-06 7.50E+00 - 6.85E-05 TOTAL DOSE (mrem) FOR LIVER 1.82E-02 ' 7.50E+00 2.43 E ' TOTAL DOSE (mrem) FOR TOTAL 1.82E-02 7.50E+00 2.43 E-01 BODY'

,, TOTAL DOSE (mrem) FOR TH.YROID 1.99E-02 7,50E+00 2.66E TOTAL DOSE (mrem) FOR KIDNEY 1.82E-02 7.50E+00 2.43E-01 TOTAL DOSE (mrem) FOR LUNG l .82E-02 7.50E+00 2.43E-01 l TOTAL DOSE (mrem) FOR GI-LLI 1.82E-02 . 7.50E+00 2.43E-01 l

) QUARTER 3 OF 1997 TOTAL DOSE (mrem) FOR BONE ~ 3.95E-07 7.50E+00 5.27E-06 '

TOTAL DOSE (mrem) FOR LIVER I.30E-02 7.50E+00 1.73E-01 '

' TOTAL DOSE (mrem) FOR TOTAL 1.30E-02 7.50E+00 1.73E-01 BODY

' TOTAL DOSE (mrem) FOR THYROID 1.31E-02 7.50E+00 1.75E-01 ' ,

TOTAL DOSE (mrem) FOR KIDNEY 1.30E-02 7.50E+00 1.73E-01 'j TOTAL DOSE (mrem) FOR LUNG 1.30E-02 7.50E+00 1.73E-01 TOTAL DOSE (mrem) FOR GI-LLI 1.30E-02 7.50E+00 1.73E-01 QUARTER 4 OF 1997  !

i- TOTAL DOSE (mrem) FOR BONE . . 7.02E-09 7.50E+00 9.37E-08 TOTAL DOSE (mrem) FOR LIVER - 2.00E-02 7.50E+00 2.67E-01 TOTAL DOSE (mrem) FOR TOTAL 2.00E-02 -7.50E+00 2.67E-01 i BODY  !

l TOTAL DOSE (mrem) FOR THYROID 2.00E-02 7.50E+00 2.67E-01 '

TOTAL DOSE (mrem)FOR KlDNEY 2.00E-02 7.50E+00 2.67E-01 '

TOTAL DOSE (mrem) FOR LUNG 2.00E-02 7.50E+00 - 2.67E-01 TOTAL DOSE (mrem) FOR GI-LLI 2.00E-02 7.50E+00 2 '

TOTALS FOR 1997 TOTAL DOSE (mrem) FOR BONE 5.54E-06 1.50E+01 3.69E-05 TOTAL DOSE (mrem) FOR LIVER 2.87E-02 1.50E+01 4.00E-01 TOTAL DOSE (mrem) FOR TOTAL 2.86E-02 1.50E+01 4.00E-01 BODY i TOTAL DOSE (mrem) FOR TilYROID 8.01E-01 1.50E+01 4.13E-01 l TOTAL DOSE (mrem) FOR KIDNEY 2.88E-02 1.50E+01 4.01E-01 l TOTAL DOSE (mrem) FOR LUNG 2.85E-02 1.50E+01 4.00E-01 TOTAL DOSE (mrem) FOR GI-LLI 2.85E-02 1.50E+01 4.00E-01

1. Based on Wolf Creek ODCM Section 3.2.2 which restricts dose during any calendar quarter to less than or equal to 7.5 mrem to any organ and during any calendar year to less than or equal to 15 mrem to any organ.  ;

l.

Enclosure to WO 98-0037 l Page 15 of 29 GASEOUS CUMULATIVE DOSE

SUMMARY

(1997)

-TABLE 2 Nuclides Released Quarter 1 Quarter 2 Quarter 3 Total Quarter 4

-A. Fission and Activation Gases 1'

l 1. Total Release -(Ci) 1.29E-01 4.52E-01 1.22E+01 1.44 E+00 1.42E+01

2. Total Gamma Airdose(mrad) 5.38E-05 1.92E-04 1.71E-03 3.02E-04 2.23 E-03

3. Gamma Airdose Limit (mrad) 5.00E+00 5.00E+00 5.00E+00 5.00E+00' l.00E+01 -

4. Percent of Gamma Airdose Limit 1.08E-03 3.84E-03 3.42E-02 6.04E-03 2.26E-02

5. Total Beta Airdose(mrad) 2.42E-05 7.82E-05 1.88E-03 1.75E-04 2.16E-03 ,

6. Beta Airdose Limit (mrad) 1.00E401 1.00E+01 1.00E+01 1.00E+01 2.00E+01

7. Percent of Beta Airdose Limit (mrad) 2.42E-04 7.82E-04 1.88E-02 1.75E-03 1.08E-02 l

i B. Particulates

1. Total Particulates (Ci) 0.00E+00 0.00E+00 0.00E+00 1.27E-08 1.27E-08

2. Maximum Organ Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 1.03E-08 1.08E-08

3. Organ. Dose Limit (mrem) .7.50E+00 7.50E+00. 7.50F.+00 7.50E+00

. 1.50E+01

4. Percent of Limit 0.00E+00 0.00E+00 0.00E+00 1.44 E-07 7.18E-08 C. Tritium

1. Total Release (Ci) 1.25E+01 2.58E+01 1.83E+01 2.83 E+01 8.50E+01

2. Maximum Organ Dose (mrem) 8.94E-03 1.83 E-02 1.32E-02 1.97E-02 6.01E-02

3. Organ Dose Limit (mrem)' 7.50E+00 - 7.50E+00 7.50E+ 00 7.50E+00 1.50E+01

4. Percent of Limit 1.19E-01 2.44E-01 1.76E-01 2.62E-01 4.00E-01 l

l D. lodine

1. Total l-131,1-133 (Ci) 0.00E+00 2.95E-06 2.27E-07 1.9 l E-10 3.18E 2. Maximum Organ Dose (mrem) 0.00E+00 1.83 E-03 0.00E+00 1.10E-07 1.83E-03

3. Organ Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 ' 7.50E+00 - 1.50E+0!

'4. Percent of Limit 0.00E+00 2.44E-02 0.00E+00 1.47E-06 122E-02 I'

This table is included to show the correlation between Curies released and the associated calculated l_ maximum organ dose. The maximum organ dose is calculated using Wolf Creek ODCM methodology which assumes that an individual actually resides at the release point. ODCM Section 3.2.2 organ dose limits are used.

I' 1

i Enclosure to WO 98-0037 Page 16 of 29 Section II Supplemental lnformation

1. Offsite Dose Calculation Manual Limits A. For liquid waste emuents A.1 'Ihe concentration of radioactive material released in liquid emuents to l UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20.

Appendix B, Table 11, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10" microCuries/ml total activity.

I A.2 The dose or dose commitment to MEMBER OF THE PUBLIC from radioactive -

materials in liquid emuents released, from each unit, to UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to ! css than or equal to 5 mrems to any orgiin and.'

b. During any calendar year to less than or equal to 3 mrems, to the whole body and to less than or equal to 10 mrems to any organ. i B. For gaseous waste effluents B.1 The dose rate due to radioactive material released in gaseous emuents from the site to area at and beyond the SITE BOUNDARY shall be limited to the following:

a. - For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and l

b. For Iodine 131, lodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

B.2 The air dose due to noble gases released in gaseous emuents, from each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

B.3 The dose from Iodine-131, lodine-133, tritium, and a radionuclide in particulate form with half-lives greater than 8 days in gaseous emuents released to area at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 rnrems to any organ, and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

2. Maximum Permissible Concentrations (MPC's)

Water - covered in Section I.A.

Air - covered in Section 1.B.

\

Enclosure to WO 98-0037 Page 17 of 29 l- 3. Average Energy Average energy of fission and activation gaseous effluents is not applicable. See ODCM Section 3.1.2 for the methodology used in determining the release rate limits from noble gas releases.

4. Measurements and Approximations of Total Radioactivity

~

A. Liquid Effluents I

Liquid Release

]

Sampling Method of Analysis Type of Activity l Type Frequency . Analysis j 1

i

\

l

1. Batch Waste i P

Release Tank Each Batch P.H.A. PrincipalGamma Emitters

]

P Each Batch P.H.A. 1-131 j a. Waste Monitor Tank P P.H.A. Dissolved and Entrained One Batch /M Gases (Gamma Emitters) 1

b. Secondary Liquid P L.S. H3 1 Waste Monitor Each Batch S.A.C. Gross Alpha Tanks P O.S.L. Sr-89, Sr-90

2. Continuous Daily P.H.A. Principal Gamma Emitters Releases Grab Sample P.H.A. 1-131

a. Steam Generator M Dissolved and entrained Blowdown Grab Sample P.H.A. Gases (Gamma Emitters)

b. Turbine Building Daily L.S. H-3 Sump / Waste Water Grab Sample Treatment S.A.C. Gross Alpha

c. Lime Sludge Pond Daily O.S.L. Sr-89, Sr-90 Grab Sample O.S.L. Fe-55 P = prior to each batch S.A.C. = scintillation alpha counter M = monthly O.S.L. = performed by an offsite laboratory L. S. = Liquid scintillation detector P.H.A. = gamma spectrum pulse height analysis using a High Purity Germanium detector

Enclosure ts WO 98-0037.

Page 18 of 29 B. Gaseous Waste Emuents Gaseous, Release Sampling Frequency Method of Analysis Type of Activity Type' Analysis P _P.ll.A. Principal Gamma Emitters Waste Gas Decay Tank Each Tank Grab Sample Containment Purge or P P.11.A. Principal Gamma Emitters Vent Each Purge Grab Sample ~

Gas Bubbler and L.S. 113 (oxide)

Unit Vent M- P.11.A. Principal Gamma Emitters Grab Sample -

Gas Bubbier and L.S. 11-3 (oxide) -

Ra$aste Buil'ding M P.fl.A Principal Gamma Emitters Vent Grab Sample For Unit Vent and Continuous P.ll.A. 1-13]

Radwaste Building Vent release types 1133 Continuous P.ll.A. Principal Gamma Emitters .

Particulate Sample Continuous S.A.C. Gross Alpha

. Composite Particulate Sample' Continuous O.S.L. Sr-89, Sr-90 Composite Particulate Sample P = prior to each batch S.A.C. = scintillation alpha counter M = monthly O.S.L. =_ performed by an offsite laboratory L.S. = Liquid scintillation detector P.ll.A. = r -~ . spectrum pulse height analysis using a liigh Purity Germanium detector

Enclosure to WO 98-0037..

' Page 19 of 29 )

I l

'5. Baich Releases A batch release is the discontinuous release of gaseous or liquid effluents which takes place over a finite period of time usually hours or days.

There were 74 gaseous batch releases during the reporting period. The longest gaseous batch release lasted 10.082 minutes, while the shortest lasted 15 minutes. The average release lasted 1288 minutes with a total gaseous batch release time of 95,342 minutes.

There were 143 liquid batch releases during the reporting period. The longest liquid batch release -

lasted 397 minutes, while the shortest lasted 46 minutes. The average release lasted 160 minutes -

with a total liquid batch release time of 22,912 minutes.

6. - Continuous Releases A continuous release is a release of gaseous or liquid effluent which is essentially, uninterrupted for extended periods during normal operation of the facility.

- There were four release pathways designated as continuous releases during this reporting period:

Steam Generator B' lowdown, Turbine Building sump,' Waste Water Treatment, and Lime Sludge Pond. There were two gas release pathways designated as continuous releases: Unit Vent and Radwaste Building Vent.

7. Doses to a Member of the Public from Activities Inside the Site Boundary Four activities by members of the public were considered in this evaluation:. personnel making .

deliveries to the plant, workers at the Construction Administration Building located outside of the ,

restricted area, the use of the access road south of the Radwaste building, and personnel using the '

lake during times when fishing was allowed. The dose calculated for the maximum exposed

individual for these four activities was as follows:

Plant Deliveries 1.60E-02 mrem Construction Administration Workers 4.56E-03 mrem Access Road Users 2.69E-03 mrem

. Lake Use 4.49E-03 mrem t

The plant delivery calculations were based on deliveries 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per week for 50 weeks per year.

The Construction Administration Building occupancy was based on nonnal working hours of 2000 peryear. The usage factor for the access road South of the Radwaste Building was 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> per year. The dose to fishermen on the lake was based upon 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> a day for 28 days, based on the maximum number of days any one fisherman was on the lake).

Pathways used in the calculation were gaseous inhalation, submersion, and ground plane. All calculations were performed in accordance with the methodology and parameters in the ODCM.-

8, AdditionalInformation -

On October 19,1997, at 15:30, an unplanned gaseous release occurred from the Containment Building. _Using data from containment atmosphere samples obtained prior to the release, and using pressure drop data .over the release period, a release volume of.16,676 cubic feet was calculated. This resulted in the calculated value of 6.18E-05 Curies for the release. Containment atmosphere monitor filters were analyzed for particulate, iodine and beta emitters (Sr-89 and Sr.

90). The quantities released are included in the Report of Radioactive Efiluents (1997):

Airborne.

l

Enclosure to WO 98 0037 Page 20 of 29 -

[-

Emuent Concentration Limits j Nuclides - Curies Average Diluted 10 CFR20 ECL  % of ECL Concentration

[ (mci /ml) .

l 1I-3 = 1.35E+03 1.31E-05 1.00E-03 1.31E+00 l Cr-51 7.22 E-03 . 7.00E-11 5.00E-04 1.40E-05 1

Mn-54 2.22E-03 2.15E Il 3.00E-05 7.18E-05 l Fe-55 4.95E 02 4.80E 10 1.00E-04 4.80E-04 1

Fe-59 3.84E-04 3.72E-12 1.00E-05 3.72E-05 l Co-57 1.28E-04 1.24E-12 6.00E-05 2.07E-06 i Co-58 2.70E-02 . 2.62E-10 2.00E-05 _ l .31 E-03

! Co-60 3.37E-02 3.27E.10 3.00E-06 1.09E-02 l- Sr-89 5.43E-04 ' 5.27E-12 8.00E-06 6.59E-05

Sr-90 1.46E-05 1.42E-13 5.00E-07 2.83E-05

( Zr-95 9.16E-04 , 8.88E-12 2.00E-05 4.44 F,05 l Nb-95 1.47E'-03 1.43E-11 3.00E-05 4.75E-05 i 'u-103 2.71E 06 2.63E-14 3.00E-05 8.76E-08 Ag-110M ' l.04E-05 1.01E-03 6.00E-06 1.68E-06 Sn-ll3 2.30E-04 2.23 E-12 3.00E-05 7.44E-06 Sn-117M 1.16E-04 1.13E-12 3.00E-05 3.75E-06 Sb-124 1.19E-03 1.95E-11 7.00E-06 1.65E-04 Sb-125 4.83E 02 4.68E 10 3.00E-05 1.56E-03 Sb-126 6.24E-06 6.05E-14 7.00E-06 8.64E-07 1131 1.47E-06 1.43E 14 1.00E-06 1.43E-06

, Cs-134 3.69E-03 3.58E-11 9.00E 07 3.98E-03

Cs 137 3.89E-03 3.77E-11 1.00E-06 3.77E-03 Ce-144 5.07E-05 4.92E-13 3.00E-06 1.64E-05 Kr-85 6.25E-03 6.06E-11 2.00E 04 3.03E-05 Kr-85M 7.81E-05 7.57E-13 2.00E-04 3.79E-07 Xe-131M 4.01 E-05 3.89E-13 2.00E-04 1.94E-07 Xe-133 1.15E-01 1.12E-09 2.00E-04 5.58E-04 l Xe-133M 9.13 E-04 8.86E 12 2.00E 04 4.43E-06

.Xe-135 9.08E-03 8.81E-I l 2.00E-04 4.40E-05

, Tc-99m 1.05E-05 1.02E-13 1.00E-03 ' l .02E-08 l' Te-132 9.27E-06 8.99E-14 9.00E-06 9.99E-07 l132 6.83 E-05 6.62E-13 7.00E-06 9.46E-06 Na-24 1.32E-06 1.28E-14 5.00E-05 2.56E-08 l

l l

l l

4 i

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Enclosure to WO 98-0037 Page 21 of 29 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1998) I SOLID WASTE SHIPMENTS {

l A.

SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) {

i

1. Type of waste Unit 1. Year Est. Total l Period Error %

a. Spent resins, filter sludges, m3* 6.266E+01 evaporator bottoms, etc. Ci 7.007E+02 2.50E+0 l  ;

l j b. Dry compressible waste, m3* - 1.5534E+02"'

contaminated equip. etc. Ci f

7.10E-01 2.50E+01 I

. c. trradiated components, m3 * - 0.00E+00 '

control rods, etc. Ci 0.00E+00 0.00E+00 l d. Other m3* 0.00E+00 Ci 0.00E+00 0.00E+00 l *m3 = cubic meters " This is the volume sent offsite for volume reduction, prior to disposal.

2. Estimate of major nuclide composition (by type of waste).

a. Spent resin, filter sludges, evaporator bottoms, etc.

Nuclide Percent Name Abundance Curies Ni-63 8.0 '5.629E+01 Fe-55 9.0 6.334E+01 Cs 137 33 2.299E+02

! Cs-134 40 2.811E+02

! Co-60 4.0 2.908E+01 Mn-54 1.0 8.78E+00 Co-58 .9 6.97E+00 Be-7 2.0 1.68E+01

b. Dry compressible waste, contaminated equipment, etc.

Nuclide Percent Name Abundance Curies Co-58 3 2.00E-02 Fe-55 19 1.38E-01 Co-60 4.7 3.35E-02 Ni-63 5 3.66E-02 Cs-137 26 1.855E-01 C-14 0.5 3.9E-04 <

Cs-134 30 2.148E-01 Mn 54 1.6 1.14E-02 Be-7 9.6 6.86E-02 p

Enclosure to WO 98 0037 Page 22 of 29 c.- Irradiated components, control rods, etc.

none

d. ' Other '

none

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3 Truck CNSI Barnwell, SC 3 Truck SEG/Tennesee

'4 Truck HAKEffennesee i Truck CNSI Defense '

, ,, Cons'olidation Facility S.C.

4. Class of Solid Waste

a. Class A, Class B, Class C- Corresponding to 2a

b. Class A - corresponding to 2b

- c. Not applicable

d. Not applicable

5. Type of container

a. LSA (Strong, tight), Type A, Type B - corresponding to 2a

b. ' LSA (Strong, tight)- corresponding to 2b

c. Not applicable

d. Not applicable

6. Solidification Agent

a. Not applicable

b. Not applicable

c. Not applicable

d. Not applicable -

B. IRRADIATED FUEL SillPMENTS (Disposition)

There were no irradiated fuel shipments during this period.

\

- Enclosure to WO 98 0037 .

Page 23 of 29 Section III:

HOURS AT EACH WIND SPEED AND DIRECTION

- All gaseous releases at the WCGS are ground level releases. The meteorological data supplied in these tables covers the period from January 1,1997, through December 31,1997, and indicates the number of .

hours at each wind speed and direction for each stability class.

1 l

l

Enclosure to WO 98-0037 Page 24 of 29 i HOURS AT EACH WIND SPEED AND DIRECTION j PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 1997 STABILITY CLASS: A I ELEVATION: 10 METERS WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 1 17 13 3 3 37 NNE O 6 6 3 0 0 15 NE O 4 12 0 0 0 16 ,

ENE 1 7 15 1 0 'O 24 E O 3 7 j

4 0 0 14 )

ESE O 2 7 2 0 0 11 j SE O 3 6 1 0 0 10  !

SSE 1 0 41 17 1 0 68 1 S 0 7 43 43 4 0 97 l SSW 0 2 10 13 0 0 25 l SW 0 1 8 5 0 0 14 l WSW 0 3 3 0 0 0 6 i W 0 6 10 2 0 0 13 l WNW 0 1 2 2 5 5 15 {

NW 0 1 1 2 5 3 12  !

NNW 0 3 12 27 9 0 51 I TOTAL 2 58 200 135 27 11 433 j PERIOD OF CALM (HOURS): 0 ,

I PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 1997 STABILITY CLASS: B t ELEVATION: 10 METERS WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL j

N O 1 8 12 1 0 22 NNE O 4 18 8 0 0 30 NE O 9 7 0 0 0 16 ENE O 16 16 0 0 0 32 E O 5 9 1 0 0 15 ESE O 2 5 3 0 0 10 i SE O 2 8 1 0 0 11 l SSE 1 16 29 7 0 0 53 S 0 17 36 11 1 1 66 SSW 0 6 23 15 1 0 45 SW 0 5 6 5 0 0 16 l WSW 1 8 3 2 0 0 14 W l 0 9 10 8 0 1 28 WNW 1 4 10 2 4 1 22 NW 1 3 5 16 2 0 27 NNW 1 2 12 18 2 0 35 TOTAL 5 109 205 109 11 3 442 PERIOD OF CALM (HOURS): 1 1

Enclosure to WO 98-0037 Page 25 of 29 HOUES AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 1997 STABILITY CLASS: C ELEVATION: 10 METERS WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 2 9 13 1 1 27 NNE O 8 27 6 0 0 41 NE 1 9 12 0 0 0 22 ENE O 9 11 0 0 0 20 E O 7 5 1 0 0 13 ESE 3 10 9 2 0 0 24 SE O 13 11 4 C 0 28 SSE 2 16 20 6 1 0 45 S 3 19 30 15 7 0 74 SSW l 5 19 13 1 0 39

.SW , .1 4. 8 _. 0 0- 19-WSW 1 9 4 0 0 0 14 W 0 4 9 2 0 0 15 WNW 1 4 3 5 3 2 18 NW 1 4 12 35 16 4 72 NNW 0 8 12 22 1 0 43 TOTAL 15 131 201 126 30 7 510 PERIOD OF CALM (HOURS): 0 1

PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 1997 i STABILITY CLASS: D l ELEVATION: 10 METERS j WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l

____________.______________________________________ j N 1 15 62 106 22 0 206 j NNE 5 44 108 39 12 1 209 J NE 12 116 64 2 0 0 194  ?

ENE 10 64 91 13 0 0 178  !

E 13 46 42 14 2 0 117  !

ESE 10 51 24 13 1 0 99 SE 7 47 62 16 0 0 132 ,

SSE 4 46 116 63 17 0 24r  !

S 4 52 150 137 29 4 3 j SSW 8 31 82 57 18 8 204 .

SW 8 31 20 12 2 0 73 '

WSW 8 21 10 6 1 0 46 W 3 23 36 '4 6 5 87 WNW 3 16 61 32 9 2 123 NW 4 26 88 94 42 16 270 NNW 1 43 134 '43 44 5 370 TOTAL 101 672 1150 761 205 41 2930 l PERIOD OF CALM (HOURS): 0 1

Enclosure to WO 98-0037 Page 26 of 29 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 1997 STABILITY CLASS: E ELEVATION: 10 METERS WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 17 32 24 5 1 80 NNE 3 61 36 16 2 5 123 NE 19 78 7 1 0 0 105 ENE 15 57 33 3 0 0 108 E 9 48 15 8 1 0 81 ESE 9 81 23 6 1 0 120 SE 12 100 84 20 5 0 221 SSE 7 87 192 75 16 6 383 S 4 57 241 148 35 2 487 SSW 7 54 105 61 19 8 254 SW 8 50 33 7 1 0 99 WSW 5 31 25 7 0 0 70 W 3 19 16 5 1 0 44 WNW 5 19 16 7 0 0 47 NW 7 43 23 1 0 0 74 NNW 5 53 54 6 1 0 119 TOTAL 119 857 935 395 87 22 2415 PERIOD OF CALM (HOURS): O PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1957 STABILITY CLASS: F ELEVATION: 10 METERS WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 18 6 0 0 0 25 NNE 4 47 11 0 0 0 62 NE 26 29 0 0 0 0 55 ENE 10 55 8 0 0 0 73 E 15 54 22 0 0 0 91 ESE 11 82 12 1 0 0 106 SE 11 89 8 0 0 0 108 SSE 3 42 48 10 0 0 103 S 5 26 48 15 3 0 97 SSW 6 21 13 5 3 0 50 SW 7 25 3 0 1 0 36 WSW 10 13 3 0 0 0 26 W 6 10 1 0 0 0 17 WNW 5 12 1 0 0 0 18 NW 7 32 8 0 0 0 47 NNW 8 37 17 0 0 0 62 TOTAL 137 592 209 31 7 0 976 PERIOD OF CALM (HOURS): 1 l

l

i Enclosure to WO 98-0037 Page 27 of 29 HOURS AT EACH WIND SPEED AND DIRECTION l

\

FERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 1997 i STABILITY CLASS: G I ELEVATIm1: 10 METERS l i

WIND 8 DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l N 1 15 1 0 0 0 17 NNE 8 47 9 0 0 0 64 NE 18 10 0 0 0 0 28 ENE 8 26 1 0 0 0 35 E 2 24 5 0 0 0 31 ESE 4 43 0 0 0 0 47 SE 1 22 1 0 0 0 24 SSE O 11 11 0 0 0 22 l S 3 12 20 0 0 0 35 SSW 3 3 1 0 0 0 7 SW 1 4 0 0 0 0 5 WSW 2 2 1 0 0 0 5 W 2 0 0 0 0 0 2 i WNW 4 1 0 0 0 0 5  !

NW 3 11 0 0 0 0 14 NNW 3 19 4 0 0 0 26

]

j TOTAL 63 250 54 0 0 0 367 '

PERIOD OF CALM (HOURS): 1 f

I PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1997 STABILITY CLASS: ALL -

ELEVATION: 10 METERS WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 69 135 168 32 5 414 NNE 20 217 215 72 14 6 544 NE 76 255 102 3 0 0 436 ENE 44 234 175 17 0 0 470 E 39 187 105 28 3 0 362 ESE 37 271 80 27 2 0 417 SE 31 276 180 42 5 0 534 SSE 18 226 457 178 35 6 920 S 19 190 560 369 79 7 1232 SSW 27 122 253 164 42 16 624 SW 25 120 78 31 4 0 258 WSW 27 89 49 15 1 0 181 W 14 71 82 31 7 6 211 WNW 19 57 93 48 21 10 248 NW 23 120 137 148 65 23 516 NNW 18 165 245 216 57 5 706 TOTAL 442 2669 2954 1557 367 84 8073 PERIOD OF CALM (HOURS): 3 HOURS OF MISSING DATA: 684

l i

Enclosure to WO 98-0037 Page 28 of 29 i

l Validation and Changes to Historical Meteorological Data In Wolf Creek Nuclear Operating Corporation (WCNOC) letter WM 98-0022, issued March 27, 1998, WCNOC committed to complete the test ing of the meteorological data screening criteria; to complete the devel3pment of a computer program to validate the meteorological tower ins t rumenta t. ion data; and to validate the meteorological tower instrumentation data for 1997 by using the tested criteria and computer program.

WCNOC also committed to provide validation of meteorological tower instrumentation data for the years 1990 through 1996, and to include this validated data in the 1997 Annual Radioactive Effluent Release Report. A similar commitment was previously documented in the 1996 Annual Radioactive Effluent Release Report.

The question of proper validation was originally identified as part of I investigations associated with a concern identified in Inspection {

Follow-Up Item 9617-01. WCNOC has determined that the data for tb7 year l 1990 was fully and correctly validated in 1991, using the computer data j validation program available at that time. This data was included in 4 Semi-Annual Radioactive Effluent Release Report #12, issued March 1, i 1991, and no re-validation is necessary. This 1990 data will also be  !

included ir. Attachment I of the 1997 Annual Radioactive Effluent Release l Report in compliance with our commitment.

The meteorological data for the early part of year 1991 was validated by using the same computer validation program as was used for the 1990 data, and a review of each instrument's hourly strip chart points for I the remainder of the year. The data validated in this manner was {

included in Semi-Annual Radioactive Effluent Release Report #14, issued '

February 28, 1992, and is considered valid and correct. This data will  ;

also be included in Attachment I of the 1997 Annual Radioactive Effluent '

Release Report, in compliance with our commitment.

The data for years 1992 through 1996 has been validated using the new l meteorological data computer validation program, and this data has also been included in Attachment I of the 1997 Annual Radioactive Effluent Release Report.

The completed new meteorological data computer validation program, validated data, and controlling program discussed above were reviewed by Dr. J. Blair Nicholas during NRC Inspection 98-11, from March 16 through March 20, 1998. This data validation concern was subsequently closed in Inspection Report 98-11;

Enclosure to WO 98-0037 Page 29 of 29 Section IV Additional information

1. Unplanned or Abnormal Releases On October 19,1997, at 15:30, an unplanned gaseous release occurred from the Containment Building. See Section 11, Page 19, item 8, of this report for details.

2. Offsite Dose Calculation Manual (ODCM)

The Offsite Dose Calculation Manual is documented as Wolf Creek Nuclear Operating i Corporation Administrative Procedure AP 078-003, "Offsite Dose Calculation Manual". The l

current revision, Revision 1, issued January 19,1998, is included with this report as " Attachment l II" I t

3. Major Changes to Radwaste Treatment Systems There were no major changes made to the Radioactive Waste Processing Systems in 1997 that were not previously reported in the 1996 or earlier Annual Radioactive Efnuent Release Reports.

Ilowever, on October 29,1997, during Refuel Outage 9. a skid mounted filtration system was installed as a temporary modification (TMO 97-14-ilB) to more effectively filter particulates from the Waste Holdup Tank. This filtration skid is located in the south-east comer of the Radwaste Building, at elevation 2013' 6". The modification is still in-service and functioning at the time of this Annual Radioactive Efuuent Report.

4. Land Use Census

- There were no new locations for dose calculation identified during this report period. l S. Radioactive Shipments There were eleven shipments of radioactive waste during this report period. The shipments went by truck to Barnwell, South Carolina.

6. Inoperability of Effluent Monitoring Instrumentation There were no events that involved inoperable liquid or gaseous ef0uent monitoring instrumentation not being corrected within the time specified in former Technical Specification 3.3.3. I 1.

7. Storage Tanks There were no events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.!!.l.4 or 3.11.2.6. (Note: Technical Specification 3.11.1.4, " Liquid Efnuents--Liquid 11oldup Tanks", and Technical Specification 3.11.2.6, " Gas Storage Tanks",

were relocated to the Wolf Creek Generating Station USAR on October 2,1995. Technical Specification requirements for the program are now covered by Section 6.8.5.a," Explosive Gas and Storage Tank Radioactivity Monitoring Program) i

ATTACHMENT I This Attachment I contains revalidated meteorological monitoring data for 1990 through 1996. An explanation of the revalidation process is found on page 28 of this Annual Radioactive Effluent Release Report # 21.

4

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 1 of 37 ATTACHMENT I HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1992 STABILITY CLASS: A ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 0 11 1 0 12 NNE O 1 3 1 0 0 5 NE O 4 1 0 0 0 5 ENE O 0 0 0 0 0 0 E O O 0 0 0 0 0

.ESE O O O 1 0 0 1 SE 0 0 0 3 0 0 3 SSE O O 2 4 0 0 6 S 0 0 6 26 3 0 35 SSW 0 0 0 1 0 0 1 SW 0 0 1 2 0 0 3 WSW 0 0 0 0 0 0 0 W 0 0 0 2 0 0 2 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 2 5 10 6 1 24 TOTAL 0 7 18 61 10 1 97 PERIOD OF CALM (HOURS): 0 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1992 STABILITY CLASS: B ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 O 5 11 4 0 20 NNE O 2 2 4 1 0 9 NE O 0 0 0 0 0 0 ENE O 0 3 0 0 0 3 E O O O 2 0 0 2 ESE 0 1 4 2 0 0 7 SE O 0 0 2 0 0 2 SSE O O 3 10 1 0 14 S 0 0 17 19 3 0 39 SSW 0 1 5 3 0 0 9 SW 0 0 3 2 0 0 5 WSW 0 0 2 2 2 0 6 W 0 1 2 6 0 1 10 WNW 0 0 0 1 0 0 1 NW 0 2 0 1 0 0 3 NNW 0 1 2 13 7 0 23 TOTAL 0 8 48 78 18 1 153 PERIOD OF CALM (HOURS): 0 f

i i

i Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 2 of 37 HOURS AT EACH WIND SPEED AND DIRECTION l

PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1992 STABILITY CLASS: C ELEVATION: 10 METERS '

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 2 8 19 1 1 31 NNE O 7 6 16 2 0 31 NE 0 2 4 0 0 0 6 ENE O 1 8 0 0 0 9 E 1 0 l

4 1 0 0 6 l ESE O O O 3 0 0 3 '

SE O 2 10 4 0 0 16 SSE O 2 17 11 1 0 31 S 0 3 29 27 7 1 67 SSW 1 2 13 9 0 0 25 SW 1 1 9 3 1 0 15 WSW 3 7 9 3 1 0 23 W 0 3 5 1 0 0 9 WF 0 0 0 2 1 2 5 NW 0 4 2 5 1 0 12 NNW 0 1 4 15 4 2 26 TOTAL 6 37 128 119 19 6 315 PERIOD OF CALM (HOURS): 0 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1992 STABILITY CLASS: D ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 20 47 79 24 7 178 NNE 6 53 75 49 l' 9 209 NE 2 51 29 3 0 0 85 ENE 2 41 69 9 0 0 121 E 4 28 55 13 0 0 100 ESE 2 37 61 7 0 0 107 SE 3 33 71 18 0 0 125 SSE 8 79 91 67 16 0 261 S 8 53 111 141 58 3 374 SSW 11 30 85 72 23 1 222 SW 7 27 21 9 0 0 64 WSW 6 27 27 14 5 2 81 W 4 39 39 21 6 11 120 WNW 2 33 52 54 24 4 169 NW 2 27 86 83 32 2 232 NNW 0 34 111 68 25 2 240 TOTAL 68 612 1030 707 230 41 2688 PERIOD OF CALM (HOURS): 2 l

f I

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 3 of 37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1992 STABILITY CLASS: E ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 22 48 40 12 0 124 NNE 5 35 61 27 5 0 133 NE 22 74 30 11 0 0 137 ENE 10 61 46 7 0 1 125 E 16 54 53 19 1 0 143 ESE 11 76 88 13 0 0 188 SE 13 74 138 44 2 0 271 SSE 5 63 186 139 23 0 416 S 7 71 217 223 62 3 583 SSW 5 65 94 46 13 2 225 SW 9 45 45 7 0 0 106 '

WSW 3 31 33 13 2 0 82 l W 7 19 31 11 0 2 70 WNW 4 29 38 6 0 2 79 l NW 2 35 68 13 3 0 121 i NNW 6 50 89 26 4 0 175 TOTAL 127 804 1265 645 127 }

10 2978

)

1 PERIOD OF CALM (HOURS): 5 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1992 STABILITY CLASS: F ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 21 21 4 1 0 48 NNE 6 35 28 3 0 0 72 NE 26 36 9 0 0 0 71 ENE 14 41 8 0 0 0 63 E 7 49 12 0 0 0 68 ESE 7 61 30 2 1 0 10]

SE 6 79 29 1 1 0 116 SSE 2 53 48 3 0 0 106 S 5 38 63 15 1 0 122 SSW 8 17 15 10 0 0 50 SW 4 15 6 0 0 0 25 WSW 11 17 8 1 0 0 37 W 3 14 4 0 0 0 21 WNW 3 9 5 1 0 0 18 NW 7 37 8 0 0 0 52 NNW 3 38 23 1 0 0 65 TOTAL 113 560 317 41 4 0 1035 PERIOD OF CALM (HOURS): 6

r Attachment I to WCGS Annual Radioactive Effluent Report # 21 f Page 4 of 37 l l

l l

1 HOURS AT EACH WIND SPEED AND DIRECTION I l

i PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1992 STABILITY CLASS: G ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL

-_-_-__----_--------__-------__----_--__-_--__----- )

N 0 9 5 1 0 0 15 I NNE 6 34 14 0 0 0 54 NE 15 37 2 0 0 0 54 l ENE 4 25 0 0. 0 0 29 E 4 26 4 0 0 0 34 ESE 1 45 4 0 0 0 50 SE 3 36 2 0 0 0 41 SSE 6 33 10 0 0 0 49 S 5 8 12 1 0 0 26 SSW 4 2 1 1 0 0 8 SW 0 3 0 0 0 0 3 l WSW 1 3 1 0 0 0 5 W 0 1 0 0 0 0 3 WNW 1 5 0 0 0 0 6 NW 4 15 2 0 0 0 21 NNW 1 16 6 0 0 0 23 TOTAL 55 298 63 3 0 0 419 PERIOD OF CALM (HOURS): 4 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1992 STABILITY CLASS: ALL ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N

• 74 134 165 43 8 428 NNE 23 167 189 10J 25 9 513 NE 65 204 75 14 0 0 358 ENE 30 169 134 16 0 1 350 E 32 157 128 35 1 C 353 ESE 21 220 187 28 1 0 457 SE 25 224 250 72 3 0 574 SSE 21 230 357 234 41 0 883 S 25 173 455 452 134 7 1246 SSW 29 117 213 142 36 3 540 SW 21 91 85 23 1 0 221 WSW 24 85 80 33 10 2 234 I W 14 77 81 41 6 14 233 WNW 10 76 95 64 25 8 278 NW 15 120 166 102 36 2 441 NNW 10 142 240 133 46 5 576 l TOTAL 369 2326 2869 1654 408 59 7685 '

I PERIOD OF CALM (HOURS): 17 HOURS OF MISSING DATA: 1082

s Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 5 of 37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1993 STABILITY CLASS: A ELEVATION: 10 METERS '

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 2 3 0 0 5 NNE 1 1 5 0 0 0 7 i NE 1 0 2 0 0 0 3 ENE 1 0 0 0 0 0 1 E O O O O O O O l ESE 1 1 0 0 0 0 2 s SE O 2 1 1 0 0 4 SSE O 1 18 9 3 0 31 S 0 1 19 35 7 0 62 SSW 0 1 6 14 5 0 26 SW 0 2 7 0 0 0 9 WSW 1 0 2 1 0 0 4 W 0 1 2 4 0 0 7 WNW 0 1 0 0 0 0 1 l NW 0 0 2 4 0 0 6 NNW 0 0 0 19 11 1 31 TOTAL 5 11 66 90 26 1 199 )

PERIOD OF CALM (HOURS): O PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1993 I STABILITY CLASS: B ELEVATION: 10 METERS

]

(

1 DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 1 l

N 1 0 0 7 1 0 9  ;

NNE O 5 7 0 0 0 12 i NE O 3 1 1 0 0 5 i ENE O 1 0 0 0 0 1 j E O O 1 0 0 0 1 ESE O O 1 0 0 0 1 SE O O 6 2 0 0 8 s SSE 0 1 8 6 1 0 16 S 0 11 j

2 12 8 0 33 '

SSW 0 3 14 16 1 0 34 SW 0 6 3 1 0 0 10 l

q WSW 0 2 5 9 0 0 16 I W 0 5 5 8 1 0 19 l WNW 0 0 2 1 2 0 5 NW 0 2 1 10 1 0 14 l NNW 3 3 7 7 9 1 28 i TOTAL 2 33 72 80 24 1 212 l PERIOD OF CALM (HOURS): 0 I

Attachment I to WCGS Annual Radicactive Effluent Report # 21 Page 6 of 37 l

l HOURS AT EAC.$ WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1993 STABILITY CLASS: C ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 3 1 4 2' O 10 NNE O 7 12 9 3 0 31 NE 2 7 7 1 0 0 17 ENE O 3 3 0 0 0 6 E O 2 3 0 0 0 5

' ESE O 1 2 1 0 0 4 SE O 2 8 4 1 0 15 SSE O 2 10 5 0 0 17 S 0 8 18 10 3 0 39 SSW 0 3 11 16 4 0 34 SW 1 5 8 6 0 0 20 WSW 2 6 4 1 1 0 14 W 1 3 13 3 0 0 20 WNW 0 6 4 3 0 0 13 NW 3 4 4 17 4 0 32 NNW 0 2 15 16 3 0 36 TOTAL 9 64 123 96 21 0 313 PERIOD OF CALM (HOURS): 0 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1993 STABILITY CLASS: D ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 12 36 53 20 2 123 NNE 9 41 74 48 13 0 185 NE 12 70 64 7 0 0 153 ENE 14 58 71 25 0 1 169 E 9 37 46 23 1 0 116 ESE 7 26 37 9 0 0 79 SE 8 22 53 18 1 0 102 SSE 8 57 96 45 5 0 211 S 7 36 95 126 38 1 303 SSW 3 20 80 62 11 3 179 SW 7 24 36 16 3 0 86 WSW 2 26 39 9 2 0 78 W 6 24 41 15 3 1 90 WNW 4 36 43 32 18 4 137 NW 3 21 94 91 35 6 250 NNW 1 33 101 105 52 5 297 TOTAL 100 543 1006 684 202 23 2558 PERIOD OF CALM (HOURS): 2

Attachment'I to WCGS Annual Radioactive Effluent Report # 21 l Page 7 of 37 '

HOURS AT EACH WIND SPEED AND DIRECTION 4 PERIOD OF RECORD: JANUARY 1 THROUGH DrCEMBER 31 1993 i STABILITY CLASS: E '

ELEVATION: 10 METERS I l

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAI N 1 19 46 40 14 0 120 NNE 7 45 55 24 6 0 137 NE 33 66 28 3 0 0 130 ENE 27 70 42 18 0 0 157 E 14 51 44 9 0 0 118 ESE 12 67 56 18 2 0 155 SE 11 79 108 30 1 0 229 SSE 8 80 226 134 30 0 478 S 10 89 247 222 77 13 658 SSW 9 73 132 75 19 6 314 UV 8 46 39 9 1 0 103 WSW 9 33 23 9 1 0 75 W 2 37 26 3 4 1 73 WNW 5 31 37 10 1 0 84 NW 5 35 58 30 3 0 131 NNW 10 59 89 76 11 0 245 TOTAL 171 880 1256 710 170 20 3207 PERIOD OF CALM (HOUFF): 4 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1993 STABILITY CLASS: F ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 25 17 0 0 0 44 NNE 8 29 9 2 0 1 49 NE 19 19 5  : 0 0 44 ENE 24 20 8 0 0 0 52 E 3 43 26 4 0 0 76 ESE 10 67 18 1 0 0 96 SE 8 55 17 2 0 0 82 SSE 4 49 47 6 1 0 107 S 2 40 42 20 5 1 110 SSW 6 33 31 12 0 0 82 SW 4 36 6 1 0 0 47 WSW 5 16 0 0 0 0 21 W 1 9 1 0 0 0 11 WNW 5 21 4 3 0 0 33 NW 3 42 22 0 0 0 67 NNW 4 43 22 1 1 0 71 TOTAL 108 547 275 53 7 2 992 PERIOD OF CALM (HOURS): 5

i Attachment I to WCGS Annual Radioactive Effluent Report # 21 }

Page 8 of 37 1 I

i 1

HOURS AT EACH WIND SPEED AND DIRECTION  ;

l PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1993 [

STABILITY CLASS: G )

ELEVATION: 10 METERS (

l 1

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 19 0 0 0 0 20 NNE 1 46 13 0 0 0 60 NE 12 16 0

{

1 1 0 30  ;

ENE 4 23 7 0 0 0 34 l E 6 28 12 0 0 0 46 l ESE 6 51 2 0 0 0 59 t SE 6 38 0 SSE 22 5

5 0 0 0 49 )

4 0 0 31 i S 1 8 14 3 0 0 26 i SSW 0 4 3 0 0 0 7  !

SW 2 4 1 0 0 0 7 WSW 0 3 0 0 0 0 3 l,

W 1 2 2 0 0 0 5 l WNW 2 4 0 0 0 0 6 l NW 3 17 4 0 0 0 24 NNW 1 16 10 1 0 0 28 i TOTAL 50 301 79 4 1 0 435 l 1

PERIOD OF CALM (HOURS): 2 '

PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1993 STABILITY CLASS: ALL ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 78 102 107 37 2 331 NNE 26 174 175 83 22 1 481 NE 79 181 108 13 1 0 382 ENE 70 175 131 43 0 1 420 E 32 161 132 36 1 0 .362 ESE 36 213 116 29 2 0 396 SE 33 198 198 57 3 0 489 SSE 24 212 410 205 40 0 891 S 20 184 446 428 138 15 1231 SSW 18 137 277 195 40 9 676 SW 22 123 100 33 4 0 282 WSW 19 86 73 29 4 0 211 W 11 81 90 33 8 2 225 WNW 16 99 90 49 21 4 279

NW 17 121 185 152 43 6 524 NNW 17 156 244 225 87 7 736

} TOTAL 445 2379 2877 1717 451 47 7916 PERIOD OF CALM (HOURS): 13 HOURS OF MISSING DATA: 831

Attachment I to WOGS Annual Radioactive Effluent Report # 21 Page 9 of 37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1994 STABILITY CLASS: A ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O 3 19 23 2 0 47 NNE 1 10 21 3 2 0 37 NE 1 20 18 0 0 0 39 ENE O 13 17 0 0 0 30 E 1 5 16 5 0 0 27 ESE 1 4 16 6 0 0 27 SE O 11 33 12 0 0 56 SSE O 14 74 61 2 0 151 S 0 12 46 87 21 2 168 SSW 0 9 13 25 7 0 54 SW 0 6 4 12 1 0 23 WSW 0 6 8 7 1 0 22 W 0 1 21 5 2 6 35 WNW 0 0 3 5 4 1 13 NW 0 1 8 14 8 1 32 NNW 0 4 30 46 10 0 90 TOTAL 4 119 347 311 60 10 851 PERIOD OF CALM (HOURS): 0 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1994 STABILITY CLASS: B ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 4 7 11 0 0 22 NNE O 12 16 10 0 38 NE O 17 17 0 0 0 34 ENE 1 6 16 1 0 0 24 E 1 5 12 3 0 0 21 ESE 2 6 10 5 0 0 23 SE 1 7 23 3 0 0 34 SSE' 2 12 40 12 3 1 70 S 1 14 28 15 8 6 72 SSW 0 4 7 14 5 1 31 SW 1 9 13 2 1 0 26 WSW 0 7 5 2 1 0 15 W 0 11 10 3 2 2 28 WNW 1 2 11 14 5 0 33 NW 0 5 16 29 15 0 65 NNW 0 5 44 23 5 1 78 j TOTAL 10 126 275 147 45 11 614 PERIOD OF CALM (HOURS): 0 i

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 10 of 37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1994 STABILITY CLASS: C ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 7 12 17 3 0 39 NNE O 20 33 18 1 0 72 NE 2 34 21 0 0 0 57 ENE 1 18 13 0 0 0 32 E O 5 11 1 0 0 17 ESE O 9 26 2 0 0 37 SE 1 11 25 9 2 0 48 SSE 1 21 31 14 2 0 69 S 2 15 27 20 12 11 87 Son 3 ,7 16 16 4 4 50 SW 3 11 13 0 0 0 27 WSW 2 9 8 2 0 0 21 w 1 9 15 10 4 0 39 WNW 0 7 13 8 0 0 28 NW 2 5 16 33 6 0 62 NNW 0 7 34 34 10 0 85 TOTAL 18 195 314 184 44 15 770 PERIOD OF CALM (HOURS): 1 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1994 STABILITY CLASS: D ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 16 65 61 18 2 164 NNE 7 40 118 52 9 1 227 NE 5 95 57 7 0 0 164 ENE 7 42 60 26 6 0 141 E O 40 53 12 5 1 111 ESE 7 42 65 30 3 0 147 SE 12 55 76 32 1 0 176 SSE 7 66 116 158 30 5 382 S 10 40 145 165 58 7 425 SSW 5 31 47 59 11 3 156 SW 7 36 26 12 3 0 84 WEW 2 26 30 17 11 0 86 W 1 21 25 18 6 0 71 WNW 3 18 47 10 4 0 82 NW 1 31 55 35 9 0 131 NNW 1 44 99 78 23 2 247 TOTAL 77 643 1084 772 197 21 2794 PERIOD OF CALM (HOURS): 4

)

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 11 of 37 l

HOURS AT EACH WIND SPEED AND DIRECTION I

PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1994 l STABILITY CLASS: E ELEVATION: 10 METERS i

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 20 35 5 4 0 66  ;

NNE 2 34 34 17 0 0 87  !

NE 14 32 6 2 0 0 54 i ENE 10 40 14 3 2 0 69 l E 6 62 39 3 0 0 110 {

ESE 7 65 24 3 0 0 99 7 SE 3 80 76 17 0 0 176 SSE 9 67 167 64 11 5 323 S 3 44 115 127 44 9 342 SSW 7 47 31 26 1 0 112 i SW 3 39 14 4 0 0 60 WSW 3 18 12 7 0 0 40 W 5 l

31 14 1 0 0 51 l WNW 5 19 15 1 0 0 40 NW 2 40 32 3 0 0 77 i NNW 2 34 32 7 0 0 75 i TOTAL 83 672 660 290 62 14 1781 l i

PERIOD OF CALM (HOURS): 3 1

PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1994 I STABILITY CLASS: F j

ELEVATION: 10 METERS l

l DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL li

---

I N 1 14 8 0 0 0 23  !

NNE 6 46 6 2 0 0 60 i NE 16 25 0 0 0 0 41 l ENE 12 42 3 1 0 0 58 i E 3 76 26 0 0 0 105 ESE 4 94 19 0 0 0 117 {

SE 6 112 20 0 0 0 138 SSE 2 30 26 9 0 0 67 l)

S S 28 30 11 3 0 77 SSW 3 10 6 3 0 0 22 SW 3 13 2 0 0 0 18 WSW 0 15 1 0 0 0 16 W 0 10 0 0 0 0 10 WNW 4 10 0 0 0 0 14 NW 7 21 7 1 0 0 36 NNW 1 31 16 0 0 0 48 TOTAL 73 577 170 27 3 0 850 PERIOD OF CALM (HOURS): 10

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 12 of 37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER ?1 1994 STABILITY CLASS: G ELEVATION: 10 METERS e

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 21 5 0 0 3 26 NNE 3 37 16 1 0 0 57 NE 14 17 0 0 0 0 31 ENE 2 41 5 0 0 0 48 l E 1 63 10 0 0 0 74 ESE 5 64 2 0 0 0 71 SE 1 45 0 0 0 0 46 SSE 0 13 11 0 0 0 24 S 4 8 12 1 0 0 25 SSW 1 8 0 0 0 0 9 SW 1 6 0 0 0 0 7 WSW 1 6 1 0 0 0 8 W 0 5 0 0 0 0 5 WNW 1 5 0 0 0 0 6 NW 3 19 0 3 0 0 25 NNW 1 34 0 0 0 0 35 TOTAL 38 392 62 5 0 0 497 PERIOD OF CALM (HOURS): 7 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1994 STABILITY CLASS: ALL ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 85 151 117 27 2 387 NNE 19 199 244 103 12 1 578 NE 52 240 119 9 0 0 420 ENE 33 202 128 31 8 0 402 E 12 '256 167 24 5 1 465 ESE 26 284 162 46 3 0 521 SE 24 321 253 73 3 0 674 SSE 21 223 465 318 48 11 1086 S 25 161 403 426 146 35 1196 SSW 19 116 120 143 28 8 434 SW 18 120 72 30 5 0 245 WSW 8 87 65 35 13 0 208 W 7 88 85 37 14 8 239 WNW 14 61 89 38 13 1 216 NW 15 122 134 118 38 1 428 NNW 5 159 255 188 48 3 658 TOTAL 303 2724 2912 1736 411 71 8157 PERIOD OF CALM (HOURS): 25 HOURS OF MISSING DATA: 578 r

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 13 of 37 s

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY ' THROUGH DECEMBER 31 1995 STABILITY CLASS: A ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O 16 49 17 0 82 NNE 1 17 26 17 0 0 61 NE 1 29 2 0 0 0 32 ENE 1 18 18 3 0 0 40 E 1 13 15 6 0 0 35 ESE 1 11 15 3 0 0 30 SE 1 20 21 13 5 0 60 SSE 1 14 78 40 7 0 140 S 0 22 77 83 15 0 197 SSW 0 13 21 28 9 4 75 SW 1 12 7 6 5 0 31 WSW 2 12 1 4 5 0 24 W 0 9 8 8 3 1 29 WNW 0 12 14 12 10 3 51 NW 0 14 14 30 20 0 78 NNW 1 12 26 36 33 3 111 TOTAL 11 228 359 338 129 11 1076 PERIOD OF CALM (HOURS): O PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1995 STABILITY CLASS: B ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL

--_------__---_--___-__--e.----_-___----------------

N 0 3 9 16 3 0 31 NNE O 3 13 1 1 0 18 NE O 13 1 0 0 0 14 ENE 1 13 5 2 0 0 21 i E O 5 6 1 0 0 12 I ESE O 2 4 2 0 0 8 SE O 3 6 3 2 0 14 SSE 1 14 33 7 3 0 58 S 0 15 29 33 7 0 84 SSW 0 5 20 16 1 1 43 3

SW 1 3 2 2 0 1 9 WSW 0 8 0 4 2 3 17 W 1 9 9 6 4 6 35 WNW C 8 5 6 5 4 28 NW 1 12 16 13 9 1 52 NNW 0 4 20 16 8 1 49 TOTAL 5 120 178 128 45 17 493 PERIOD OF CALM (HOURS): 0

)

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 14 of 37 I

i l

HOURS AT EACH WIND SPEED AND DIRECTION '

PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1995 STABILITY CLASS: C ELEVATION: 10 METERS l

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 3 16 13 3 0 36 NNE O 3 18 2 0 0 23 l NE O 17 6 0 0 0 23 )

ENE O 7 3 0 0 0 10 E O 10 5 7 0 0 22 ESE O 5 8 0 0 0 13 SE O 10 6 3 1 0 20 SSE 0 10 20 12 6 0 48 ;

S 0 10 21 19 12 2 64 '

SSW 0 6 14 18 6 1 45 SW 0 3 6 1 0 1 11 ,

WSW 0 2 4 4 1 2 13 I W 4 7 3 6 4 2 26 WNW 0 6 5 4 5 1 21 NW 0 7 26 13 5 0 51 NNW 1 6 22 11 8 0 48 TOTAL 6 112 183 113 51 9 474 PERIOD OF CALM (HOURS): O PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1995 STABILITY CLASS: D ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL

_____-----------_--~--_---_---__---__---__---_---__

N 1 13 59 62 17 1 153 NNE 7 35 70 38 4 0 154 NE 6 32 25 2 0 0 65 ENE 5 30 31 12 0 0 78 E 7 35 47 14 0 0 103 ESE 7 34 47 14 0 0 102 SE 5 24 51 19 4 0 103 SSE 2 37 58 73 11 2 183 S 6 39 101 85 25 9 265 SSW 4 31 29 48 9 1 122 SW 3 19 15 11 2 1 51 WSW 6 14 19 18 17 2 76 W 1 13 31 14 17 3 79 WNW 4 8 46 55 8 3 124 NW 4 27 100 42 16 5 194 NNW 9 46 86 78 21 2 242 TOTAL 77 437 815 585 151 29 2094 t

PERIOD OF CALM (HOURS): 8

[

t 1

t

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 15 of 37 i

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1995 STABILITY CLASS: E ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 22 34 19 1 0 78 NNE 6 29 32 1 1 0 69 NE 22 31 4 0 0 0 57 ENE 6 29 14 1 1 0 51 E 5 41 40 1 0 0 87 ESE 4 59 36 1 1 0 101 SE 1 74 85 20 1 0 181 SSE 6 71 195 157 38 7 474 S 8 48 237 108 32 11 444 SSW 3 50 46 39 8 1 147 SW 6 47 15 3 0 0 71 WSW 2 26 26 8 1 0 63 W 6 34 27 1 0 0 68 WNW 0 33 42 3 0 0 78 NW 1 61 33 6 2 0 103 NNW 5 53 40 12 2 0 112 TOTAL 83 708 906 380 88 19 2184 PERIOD OF CALM (HOURS): 14 PERIOD OF RECORC- JANUARY l THROUGH DECEMBER 31 1995 STABILITY CLASS: F ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 11 15 2 0 0 29 NNE 7 47 31 0 0 0 85 NE 19 33 5 0 0 0 57 ENE 4 66 3 0 0 0 73 E 4 60 15 0 0 0 79 ESE 6 120 12 0 0 0 138 SE 4 114 29 1 0 0 148 SSE 1 55 68 8 0 0 132 S 3 21 35 12 0 0 71 SSW 4 8 10 0 0 0 22 SW 4 25 7 0 0 0 36 WSW 8 16 3 0 0 0 27 W 4 3 1 0 0 0 8 WNW 4 7 6 1 0 0 18 NW 3 39 15 8 0 0 65 NNW 5 41 29 2 0 0 77 TOTAL 81 666 284 34 0 0 1065 PERIOD OF CALM (HOURS): 2

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 16 of 37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1995 STABILITY CLASS: G ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 9 7 0 0 0 16 NNE 2 48 9 0 0 0 59 NE 19 24 1 0 0 0 44 ENE 14 51 2 0 0 0 67 E 8 54 2 0 0 0 64 ESE 1 68 3 0 0 0 72 SE 4 45 5 0 0 0 54 SSE 1 8 7 1 0 0 17 S 6 6 3 1 0 0 16 SSW 1 2 1 0 0 0 4 SW 2 5 0 0 0 0 7 WSW 2 1 0 0 0 0 3 W 1 2 0 0 0 0 3 WNW 2 1 1 1 0 0 5 NW 3 19 3 1 0 0 26 NNW 2 25 10 2 0 0 39 TOTAL 68 368 54 6 0 0 496 PERIOD OF CALM (HOURS): 3 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1995 l STABILITY CLASS: ALL ELEVATION: 10 METERS l

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 61 156 161 41 1 425 NNE 23 182 199 59 6 0 469 NE 67 179 44 2 0 0 292 ENE 31 214 76 18 1 0 340 E 25 218 130 29 0 0 402 ESE 19 299 125 20 1 0 464 SE 15 290 203 59 13 0 580 SSE 12 209 459 298 65 9 1052 S 23 161 503 341 91 22 1141 SSW 12 115 141 149 33 8 458 SW 17 114 52 23 7 3 216 WSW 20 79 53 38 26 7 223 W 17 77 79 35 28 12 248 WNW 10 75 119 82 28 11 325 NW 12 179 207 113 52 6 569 NNW 23 187 233 157 72 6 678 TOTAL 331 2639 2779 1584 464 85 7882 PERIOD OF CALM (HOURS): 27 HOURS OF MISSING DATA: 851

Attachment I to WCGS Annual Radioactive Effluent Report # 21 l Page 17 of 37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1996 STABILITY CLASS: A ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O 1 11 11 3 0 26 l

NNE O 11 10 3 0 0 24 NE O 5 3 1 0 0 9 ENE O 5 3 6 0 0 14 E O 2 13 1 0 0 16 ESE O 3 6 1 0 0 10 SE O 1 2 6 0 0 9 l SSE 0 3 17 8 3 0 31 S 0 7 12 36 5 0 60 SSW 1 5 3 14 4 0 27 SW 0 5 5 4 0 0 14 I WSW 0 5 2 1 0 2 10 W 0 7 20 4 6 3 40 WNW 1 5 10 6 9 2 33 NW 0 6 7 23 31 0 67 NNW 0 1 12 17 21 4 55 TOTAL 2 72 136 142 82 11 445 <

l PERIOD OF CALM (HOURS); 3 l PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1996 STABILITY CLASS: B l ELEVATION: 10 METERS l DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 6 5 2 0 13 NNE O 8 3 3 0 0 14 j NE O 3 4 0 0 0 7 i ENE O 4 5 0 0 0 9 E 1 2 7 3 0 0 13 ESE O 2 7 3 0 0 12 SE O 6 8 1 0 0 15 JSE 1 7 10 7 0 0 25 S 1 11 16 21 3 0 52 SSW 0 3 4 6 6 1 20 SW 0 0 3 1 0 0 4 WSW 0 6 4 1 0 1 12 W 1 6 10 2 0 0 19 WNW 0 7 4 6 2 3 22 l

NW 0 2 10 12 16 9 49 NNW 1 2 3 9 2 4 21 TOTAL 5 69 104 80 31 18 307 PERIOD OF CALM (HOURS): 4 l

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 18 of 37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1996 STABILITY CLASS: C ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 1 8 12 3 0 24 NNE O 5 7 2 0 0 14 NE O 11 1 0 0 0 12 ENE O 4 3 2 0 0 9 E O 5 8 1 0 0 14 ESE O 3 4 1 0 0 8 SE 1 9 5 6 0 0 21 SSE O 11 11 3 1 0 26 S 0 8 10 12 4 1 35 SSW 1 4 6 12 0 6 29 SW 4 4 2 3 0 0 13 WSW 0 4 1 2 2 0 9 W 2 7 4 1 0 1 15 WNW 2 5 1 6 4 1 19 NW 1 5 5 37 14 11 73 NNW 0 2 5 8 5 1 21 TOTAL 11 88 81 108 33 21 342 PERIOD OF CALM (HOURS): 2 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1996 STABILITY CLASS: D ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 21 45 114 21 0 201 NNE 2 34 72 58 0 0 166 NE 6 54 30 1 0 0 91 ENE 2 66 47 12 0 0 127 E 5 46 78 16 3 0 148 ESE 4 42 66 16 1 1 130 SE 3 34 47 34 0 0 118 SSE 6 43 70 60 16 5 200 S 8 41 71 128 51 9 308 SSW 7 27 35 41 22 10 142 SW 5 19 6 4 2 4 40 WSW 5 13 14 6 4 0 42 W 1 19 13 5 4 1 43 WNW 2 10 50 61 14 1 138 NW 3 19 62 91 26 2 203 NNW 2 26 55 121 38 0 242 TOTAL 61 514 761 768 202 33 2339 PERIOD OF CALM (HOURS): 19

i Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 19 of 37 l

l l

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY l THROUGH DECEMBER 31 1996 STABILITY CLASS: E ELEVATION: 10 METERS I DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 21 56 17 4 0 100 NNE 8 39 53 18 3 0 121 l NE 18 48 21 3 0 0 90 l ENE 14 84 39 7 5 0 149 E 12 73 50 6 2 0 143 ESE 7 85 77 15 1 0 185 SE 14 77 80 22 1 0 194 SSE 11 82 176 147 50 5 471 S 8 65 185 225 103 13 599 SSW 8 55 60 41 11 3 178 SW 12 54 17 5 2 1 91 WSW 8 33 21 5 1 1 69 W 10 30 33 6 0 1 80 WNW 2 29 44 11 0 0 86 NW 7 33 41 18 0 0 99 i NNW 3 37 65 12 1 0 118 TOTAL 144 845 1018 558 184 24 2773 PERIOD OF CALM (HOURS): 20 I

PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1996 STABILITY CLASS: F ELEVATION: 10 METERS  :

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 8 6 1 0 0 16 NNE 8 41 5 0 0 0 54  !

NE 31 23 2 0 0 0 56 ENE 18 41 2 0 0 0 61 l E 6 65 19 1 0 0 91 4 ESE 6 95 13 0 0 0 114 SE 8 64 16 1 0 0 89  :

SSE 6 48 42 23 9 0 128 S 7 37 31 30 17 1 123 I SSW 5 19 2 3 1 0 30 j SW 5 29 3 0 0 0 37 WSW 3 18 1 1 0 0 23 W 4 5 0 0 0 0 9  !

WNW 3 8 1 0 0 0 12 NW l

2 22 10 1 0 0 35  !

j NNW 10 33 12 0 0 0 55 I TOTAL 123 556 165 61 27 1 933 l i

PERIOD OF CALM (HOURS): 27 ,

j i

l

l I

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 20 of 37 l

l HOURS AT EACH WIND SPEED AND DIRECTION {

PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1996 STABILITY CLASS: G ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 1

N 3 13 1 0 0 0 17 NNE 2 39 1 0 0 0 42 NE 22 23 0 0 0 0 45 ENE 3 55 6 0 0 0 64 E 7 66 8 0 0 0 81 ESE 6 48 1 0 0 0 55 SE 3 27 1 0 0 0 31 SSE 2 16 10 0 0 0 28 S 2 11 14 3 0 0 30 SSW 2 4 2 1 0 0 9 SW 1 6 0 0 0 0 7 WSW 2 1 0 0 0 0 3 W 3 10 0 0 0 0 13 WNW 1 2 0 0 0 0 3 NW 2 5 1 0 0 0 8 NNW 2 13 3 0 0 0 18 TOTAL 63 339 48 4 0 0 454 PERIOD OF CALM (HOURS): 11 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1996 STABILITY CLASS: ALL ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 6 65 133 160 33 0 397 NNE 20 177 151 84 3 0 435 NE 77 167 61 5 0 0 310 ENE 37 259 105 27 5 0 433 E 31 259 183 28 5 0 506 ESE 23 278 174 36 2 1 514 SE 29 218 159 70 1 0 477 SSE 26 210 336 248 79 10 909 S 26 180 339 455 183 24 1207 SSW 24 117 112 118 44 20 435 SW 27 117 36 17 4 5 206 WSW 18 80 43 16 7 4 168 W 21 84 80 18 10 6 219 WNW 11 66 110 90 29 7 313 NW 15 92 136 182 87 22 534 NNW 18 114 155 167 67 9 530 TOTAL 409 2483 2313 1721 559 108 7593 PERIOD OF CALM (HOURS): 86 HOURS OF MISSING DATA: 1105

(~ )

Attachment I to WCGS rnnual Radioactive Effluent Report # 21 Page 21 of 37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1997 STABILITY CLASS: A '

ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 1 17 13 3 3 37 NNE O 6 6 3 0 0 15 NE 0 4 12 0 0 0 16 l ENE 1 7 15 1 0 0 24 E O 3 7 4 0 0 14 ESE O 2 7 2 0 0 11 SE O 3 6 1 0 0 10 SSE 1 8 41 17 1 0 68 S 0 7 43 43 4 0 97 SSW 0 2 10 13 0 0 25 SW 0 1 8 5 0 0 14 WSW 0 3 3 0 0 0 6 W 0 6 10 2 0 0 18 WNW 0 1 2 2 5 5 15 NW 0 1 1 2 5 3 12 NNW 0 3 12 27 9 0 51 TOTAL 2 58 200 135 27 11 433 PERIOD OF CALM (HOURS): 0 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBEF 31 1997 STABILITY CLASS: B ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 1 8 12 1 0 22 i NNE O 4 18 8 0 0 30 NE O 9 7 0 0 0 16

! ENE O 16 16 0 0 0 32 E O 5 9 1 0 0 15 ESE O 2 5 3 0 0 10 SE O 2 8 1 0 0 11 SSE 1 16 29 7 0 0 53 S 0 17 36 11 1 1 66 SSW 0 6 23 15 1 0 45 SW 0 5 6 5 0 0 16 WSW 1 8 3 2 0 0 14 W 0 9 10 8 0 1 28 WNW 1 4 10 2 4 1 22 NW 1 3 3 16 2 0 27 NNW 1 2 12 18 2 0 35 TOTAL 5 109 205 109 11 3 442 PERIOD OF CALM (HOURS): 1

{

t

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 22 of 37 HOURS AT EACH WIND SPEED AND DIRECTION j I

l PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1997 STABILITY CLASS: C ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 2 9 13 1 1 27 NNE O 8 27 6 0 0 41 NE 1 9 12 0 0 0 22 ENE O 9 11 0 0 0 20 E O 7 5 1 0 0 13 ESE 3 10 9 2 0 0 24 SE O 13 11 4 0 0 28 SSE 2 16 20 6 1 0 45 S 3 19 30 15 7 0 74 SSW 1 5 19 13 1 0 39 SW 1 4 8 2 0 0 15 WSW 1 9 4 0 0 0 14 W 0 4 9 2 0 0 15 WNW 1 4 3 5 3 2 18 i NW 1 4 12 35 16 4 72 )

NNW 0 8 12 22 1 0 43 l TOTAL 15 131 201 126 30 7 510 )

l PERIOD OF CALM (HOURS): 0 I PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1997 3 STABILITY CLASS: D }

ELEVATION: 10 METERS j e

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL i

___________________________________________________ j N 1 15 62 106 22 0 206 4 NNE 5 44 108 39 12 1 209 i NE 12 116 64 2 0 0 194 1 ENE 10 64 91 13 0 0 178 E 13 46 42 14 2 0 117 ESE 10 51 24 13 1 0 99 SE 7 47 62 .' 6

. 0 0 132  !

SSE 4 46 116 63 17 0 246 l S 4 52 150 137 29 4 376 '

SSW 8 31 82 57 18 8 204 l SW 8 31 20 12 2 0 73  !

WSW 8 21 10 6 1 0 46 W 3 23 36 14 6 5 87 WNW 3 16 61 32 9 2 123 NW 4 26 88 94 42 16 270 NNW 1 43 134 143 44 5 370 TOTAL 101 672 1150 761 205 41 2930 PERIOD OF CALM (HOURS): 0

)

l Attachment I to WCGS Annual Radioactive Effluent Report # 21 l Page 23 of 37 i

I l

HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1997 l

STABILITY CLASS: E ELEVATION: 10 METERS l

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 17 32 24 5 1 80 NNE 3 61 36 16 2 5 123 l NE 19 78 7 1 0 0 105 ENE 15 57 33 3 0 0 108 E 9 48 15 8 1 0 81 ESE 9 81 23 6 1 0 120 SE 12 100 84 20 5 0 221 l SSE 7 87 192 75 16 6 383

! S 4 57 241 148 35 2 487 SSW 7 54 105 61 19 8 254 SW 8 50 33 7 1 0 99 WSW 5 33 25 7 0 0 70 W 3 19 16 5 1 0 44 l

WNW 5 19 16 7 0 0 47 NW 7 43 23 1 0 0 74

' NNW 5 53 54 6 1 0 119 TOTAL 119 857 935 395 87 22 2415 PERIOD OF CALM (HOURS): 0 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1997 STABILITY CLASS: F ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l N 1 18 6 0 0 0 25 NNE 4 47 11 0 0 0 62 NE 26 29 0 0 0 0 55 ENE 10 55 8 0 0 0 73 E 15 54 22 0 0 0 91 ESE 11 82 12 1 0 0 106 SE 11 89 8 0 0 0 108 SSE 3 42 48 10 0 0 103 S 5 26 48 15 3 0 97 SSW 8 21 13 5 3 0 50 l SW 7 25 3 0 1 0 36

WSW 10 13 3 0 0 0 26 W 6 10 1 0 0 0 17 WNW 5 12 1 0 0 0 18 NW 7 32 8 0 0 0 47 NNW 8 37 17 0 0 0 62 TOTAL 137 592 209 31 7 0 976 PERIOD OF CALM (HOURS); 1 l

l l

l

Attachment I to WCGS Annual Radioactive Effluent Report # 21 Page 24 of 37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1997 STABILITY CLASS: G ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 15 1 0 0 0 17 NNE 8 47 9 0 0 0 64 NE 18 10 0 0 0 0 28 ENE 8 26 1 0 0 0 35 E 2 24 5 0 0 0 31 ESE 4 43 0 0 0 0 47 SE 1 22 1 0 0 0 24 SSE O 11 11 0 0 0 22 S 3 12 20 0 0 0 35 SSW 3 3 1 0 0 0 7 SW 1 4 0 0 0 0 5 WSW 2 2 1 0 0 0 5 W 2 0 0 0 0 0 2 WNW 4 1 0 0 0 0 5 NW 3 11 0 0 0 0 14 NNW 3 19 4 0 0 0 26 TOTAL 63 250 54 0 0 0 367 PERIOD OF CALM (HOURS): 1 PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 1997 STABILITY CLASS: ALL ELEVATION: 10 METERS DIRECTION 1-3 4-7 8-12 13-18 2 1-24 >24 TOTAL N 5 69 135 168 32 5 414 NNE 20 217 215 72 14 6 544 NE 76 255 102 3 0 0 436 ENE 44 234 175 17 0 0 470 E 39 187 105 28 3 0 362 ESE 37 271 80 27 2 0 417 SE 31 276 180 42 5 0 534 SSE 18 226 457 178 35 6 920 S 19 190 568 369 79 7 1232 SSW 27 122 253 164 42 16 624 SW 25 120 78 31 4 0 258 WSW 27 89 49 15 1 0 181 W 14 71 82 31 7 6 211 WNW 19 57 93 48 21 10 248 NW 23 120 137 148 65 23 516 NNW 18 165 245 216 57 5 706 TOTAL 442 2669 2954 1557 367 84 8073 PERIOD OF CALM (HOURS):3 HOURS OF MISSING DATA: 684

e Enclosure to NO 91-0071

, Pag 3 19 cf 26 Attachment I to WCGS Annual Radio-active Effluent Report # 21 Page 25 of 37 summ frint 22I IEGt5 M ERCE WDC SPEED JWD Dumm'frw All gasecus releases at the Wolf Creek Generating Statias are ground level releases. 'Ihm 1,1990, frun January insteoroleMrm1 n t-i-$. *data r=14M and 31,1990, in these tables indicate cover the the WM number of hours at each wind speed and diefe= for each stability class.

SEABILITY CIASS: A E R ATICN: GIOGC WDC SPEED (MPH) wne DIRECTICN 1-3 4-7 8-12 13-18 19-24 ~ >24 'IUZhL N 0 2 4 4 0 0 10

!sta 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE O O 0 0 0 0 0 E 0 0 0 0 0 0 0 EBE O O 0 0 0 0 0 SE 1 0 0 0 0 0 1 SEE 1 2 -0 0 0 0 3 S 0 7 6 1 0 0 14 Ssw 0 6 11 6 0 0 23 SN 0 0 6 1 0 0 7 MIR 1 4 0 0 0 0 5 W 0 1 1 0 0 0 2 MM 0 1 0 3 1 1 6 NW 1 6 4 2 6 0 19

!alR 0 4 2 2 0 0 8 TorhL 4 33 34 19 7 1 98  ;

Periods of Calm (Itmrs): 0

._~_

94 mte tw we,e,

Enclosure to NO 91 0071 Attachment I to WCGS Annual Radio-

, Page 20 of 26 active Effluent Report # 21 Page 26 of 37 SUBII2TY CIASS: B ELEVATIN: GEX2O WIND SPEID (MPH) wne ,

DIRECITCN 1-3 4-7 8-12 13-18 19-24 >24 TothL N 0 0 4 3 3 0 10 lect 0 0 0 0 1 0 1 M 0 0 0 0 0 0 0 BE- 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 I SSE O 0 0 1 6 0 1 l

5 0 1 6 4 0 0 11 SSW 0 1 4 6 0 0 11 W 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 W 0 0 0 0 0 1 1 met 0 0 0 0 0 0 0 ist 2 0 0 0 0 0 2 lest 0 0 2 4 0 0 6 1DrnL 2 2 16 18 4 1 43 i pr4eria of Calm (Itms): 0 SSBILITY CIASS: C EIRATICN: 200tO WItc SPEED (MPH) wnO DIRECTICN 1-3 4-7 8-12 13-18 19-24 >24 TOIAL N 1 0 4 10 1 0 16 test 0 0 0 2 1 0 3 NE 0 0 0 0 0 0 0 Dat 0 0 0 0 0 0 'O E 0 0 0 0 1 0 1 IlsE 0 0 0 0- 0 0 0 SE 0 0 _0 0 0 0 0 SSE 1 0 0 0 0 0 1 S 0 1 12 2 0 0 15 SSW 0 0 3 3 0 0 6 SW 0 0 0 0 0 0 0 NSW 0 0 0 0 1 0 1 W 0 0 0 1 0 0 1 105t 0 0 0 0 2 0 2 let 3 1 0 0 1 0 5 tatt 0- 0 6 5 2 0 13 TIE 5 2 25 23 9 0 64 scirns of Calm (Iturs): 0

Enclosure to N0 91 0071 Pago 21 cf 26 Attachment I to WCGS Annual Radio-active Effluent Report # 21 Page 27 of 37 SDBILITY CLASS: D ELEVATICN GRDutC WIND SPEED (MPH)

Wne DIRECTICH 1-3 4-7 8-12 13-18 19-24 >24 TorhL N- .

24 8 40 36 '10 1 119 NNE' 24 8 61 32 -8 0 133 NE 4 35 57 28 0 0 124 ENE 15 21 17 6 0 0 59 E 1 20 28 17 2 0 68 ESE 3 19 29 19 3 0 73 SE 4- 26 54 6 2 0 92 SSE 1 38 57 41 2 0 139 s 2 35 102 126 29 2 296 SSW 4 21 76 85 29 6 221 SW 2 24 25 10 1 0 62 WSW 1 17 25 11 2 0 56 W 4 23 35 23 5 1 91 m 12 13 26 40 24 0 115 NW 14 14 30 53 24 5 140 Itat 19 18 54- 37 19 7 154 TorhL 134 340 716 570 160 22 1942 Periods of Calm (Itaxrs): O SnBILITY CLASS: E ELEVATICN: GROUND WIND SPEED (MPH) unc DIREcrICN 1-3 4-7 8-12 13-18 19-24 >24 TOIAL j N 11 36 112 154 34 1 348 lets 30 37 93 69 35 9 273 NE 13 59 70 18 2 0 162 ENE 12 45 50 10 0 0 117 E 5 40 54 18 1 0 118 26 171  :

ESE 9 78 48 9 1 SE 9 72 96 45 5 0 227 SSE 6 96 236 127 27 2 494 S 5 63 255 467 194 34 IM5 SSW 8 50 161 221 57 17 ble SW 7 58 41 12 2 0 120 NSW 8 35 46 14 2 0 105 W 7 30 50 14 1 1 103 Met 6 19 38 12 0 0 75 l#f 5 47 72 44 15 16 199 It#f 61 44 98 85 32 8 328 TUIAL 202 809 1520 1336 416 89 4372 Periods of Calm (Hours): 1

,' Enclosure to NO 91-0071 Palo 22 cf 26 1.ttachment I to WCGS Annual Radio-active Effluent Peport # 21 Page 28 of 37 STMlILITY CIASS: F ELEVATIN: GOUtB WIND SPE!!D (MPH)

WIND DIRECTIm 1-3 4-7 8-12 13-18 19-24 >24 '10IAL N. 7 50 30 1 1 0 89 lent 6 44 18 3 0 0 71 NE 12 39 6 1 1 0 59 DIE 11 33- 8 4 0 0 56 E 12 38 16 0 0 0 '66 ESE 11 57 25 5 1 0 99 SE 8 88 33 1 1 0 131 SSE 7' 81 145 12 1 0, 246 S 7 31 174 108 22 0 342 SSN 7 27 94 25 4 1 158 SW 2 41 9 0 0 0 52 ilSW 7 33 19 0 0 0 59 W 7 12 10 1 0 0 30 met 6 11 3 0 0 0 .20 19f 9 22 23 1 0 0 55 leaf 24 23 17 3 0 0 67 TOIRL 143 630 630 163 31 1 1600 Periods of Calm (Hours): 0 STABILITY CLASS: G ELEVATI N : G OOND i WIND SPEED (MPH)

WIND DIRECTIm 1-3 4-7 8-12 13-18 19-24 >24 '1UIAL N 5 27 9 0 0 0 41 NNE 9 28 9 0 0 0 46 NE 3 27 1 0 0 0 31 2 12 0 0 0 0 14 ENE E 1 27 4 0 0- 0 32 ESE 4 34 4 0 0 0 42 SE 1 79 0 0 0 0 80 SSE 5 66 27 0 0 0 98 S 1 20 30 0 0 0 51 SSN 1 9 3 0 0 0 13 SW 0 16 3 0 0 0 19 NSW 0 4 1 0 0 0- 5 W 1 2 0 0 0 0 3 mei 1 4 0 0 0 0 5 1#i - 5 25 2 0 0- 0 32 Itti 9 27 12 0 0 0 48

'IDIAL 48 407 105 0 0 0 560 Periods of Calm (Hours): 0

1 Enclosure to NO 91-0071

, P:go 23 ef 26 Attachment I to WCGS Annual Radio-active Effluent Report # 21 Page 29 of 37 SMBILITY CIASS: All ELEVATICN GR00tc WIIC SPEED (MPH) wzuD DIRECTICN 1-3 4-7 8-12 13-18 19-24 >24 TOIhL N 48 123 203 208 49 2 633 NNE- 69 117 181 106 45 9 527 NE 32 160 134 47 3 0 376 ENE 40 111 75 20 0 0 246 E 19 125 102 35 4 0 285 ESE 27 188 106 50 13 1 385 SE 23 265 183 52 8 0 531 SSE 21 283 465 181 30 2 982 S 15 158 -585 708 245 36 1747 SSN 20 114 352 346 90 24 946 SW 11 139 84 23 3 0 260 NeR 17 93 91 25 5 0 231 W 19 68 96 39 6 3 231 wNw 25 48 67 55 27 1 223 NN 39 115 131 100 46 21 452 tem 113 116 191 136 53 15 624 TOBL 538 2223 3046 2131 627 114 8679 Periods of Calm (Iburs): 1 Hours of Missing Datas 80 Se 7_*- that m=14= the wind speed ard directicn data for 21f Creek Generating Statica does not report hours unless there are three 15=4=**

intervals of good data per hour. S e 80 missing hours of data are due to this critaria. In most cases there is at least one good 15=i=*= interval for each hour. His data is availabla ensite for zuview at elf Creek Generating Staticn.

- . .._.... ...... _ .a ._. ._.

Attachment I to WCGS Annual Radio-active Effluent Report # 21 Enclosure to NO 92 0067 Page 30 of 37 Page 21 of 34 SECTION III BOURS AT EACE WIND SPEED AND DIRECTION j

All gaseous releases at the Wolf Creek Generating Station are ground level releases. The meteorological data supplied in these tables cover the period from January 1, 1991, through December 31. 1991, and indicate the number of hours at each wind speed and direction for each stability class.

1 ELEVATION: 10 METERS STABILITY CLASS: A WIND SPEED (MPH) i VIND >24 TOTAL 13 47 8 12 13 18 19 24 DIRECTION 0 0 0 0 0 0

..........0 N 0 0 0 O 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE O O 0 0 O O O E 0 0 0 O O 0 0 ESE 0 0 0 0 0 0 0 SE 1 0 5 O 1 3 0

.SSE 0 0 10 5 2 0 17 S 4 0 25 0 0 7 14 i SSW ~

0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 1 1 0 0 2.

W 0 0 2 0 0 1 1 WNW 0 0 0 0 0 0 0 l NW 0 0 0 0 0 0 0 NNW 0 0 0 0....

O O O VARIABLE l

7 0 51 l

0 1 22 21 TOTAL 0

Periods of Calm (Hours):

Attachment I to WCGS Annual Radio.

Enciesure to NO 92 0067 active Effluent Report # 21 Page 22 of 34 Page 31 of 37' STABILITY CLASS: B ELEVATION: 10 METERS WIND SPEED (MPH)

WIND DIRECTION- 1 3~ 47 8 12 13 18 19 24 >24 TOTAL 0 2 5 7 1 0 15 N

0 l' 1 3 0 0 5 NNE O O O 0 0 0 0 NE ENE O O O O 0 0' 0 0 0 0 0 0 0 0 E

0 1 2 0 0 0 3 ESE 0 3 1 0 0 0 4

-SE SSE O 7 8 10 0 0 25 1 ...................__.........................___..........__............

l S

• 0 0 61 43 14 2 120 SSW 1 2 39 39 10 1 92 SW 0- 1 7 2 0 0 10 l

WSW 0 0 4 8 0 0 12 l

0 0 5 1 0 0 6 I W WNW 0 0 1 9 5 1 16 0 0 1 1 2 4 8 NW 0 0 5 10 1 2 18 NNW 0 0 0 0 0 0 0 VARIABLE 1 17 140 133 33 10 334 TOTAL' Periods of Calm (Hours):' 0 l

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Attachment I to WCGS Annual Radio-active Effluent Report # 21 Encicsure to NO 92 0067 Page 32 of 37 i Page 23 of 34 i

STABILITY CLASS: C ELEVATION: 10 METERS l

WIND SPEED (MPH) l

, WIND l DIRECTION 13 4-7 8 12 13 18 19 24 >24 TOTAL i

.................__................_______...__.............__........ . l l

N 0 0 1 1 0 0 '2 0 1- 2 1 0 0 4 NNE-NE O 0 0 0 0 0 0 ENE O 0 2 0 0 0 2-E 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE SE 0 2 1 0 0 0 3 SSE O 1 4 0 0 0 5 S 0 2 13 11 2 1 29 SSW 0 0 5 2 2 0 9 ,

SW 0 0 2 3 0 0 5  !

l WSW 0 0 0 0 1 0 1 W 0 0 0 1 1 0 2 I WNW 0 0 1 5 l' 1 8 NW- 0 0 2 1 0 2 5 0 0 5 3 0 0 8  ;

!$ NNW '

O 0 0 0 0 0 VARIABLE O 0 6 38 28 7 4 83 TOTAL Periods of Calm (Hours): 0 e

4 i

Attachment I to WCGS Annual Radio-Enclosure to NO 92-_0067- active Effluent Report # 21 Page 33 of 37 Page 24 of 34 STABILITY CLASS: D ELEVATION: 10 METERS WIND SPEED (MPH)

I WIND DIRECTION 13 47 8 12 -13 18 19 24 >24 TOTAL N 3 29 67 40 3 1 143 NNE' 1 29 40 14 3 1 88 I NE 1 25 13 7 0 0 46 ENE 1 8 12 3 1 0 25 E 1 9 31 7 0 0 48 ESE 4 13 37 4 0 0 58 SE 1 15 33 2 1 0 '52 SSE 0 21 89 20 1 2 133 S 1 32 287 124 40 4 488 SSW 3 26 98 37 9 0 173 SW 2 8 23 7 4 0 44 WSW 4 11 17 6 5 1 45 W 6 21 23 9 11 0 70 WNW 0 16 34 44 7 1 102 NW 1 6 26 29 6- 3 71 NNW 0 17 35 46 17 0 115 0 0 0 0 0 0 0 VARIABLE TOTAL 29 287 865 399 108 13 1701 Periods of Calm (Hours): 3 l

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Attachment I to WCGS Annual Radio-Encicsure to NO 92 0067 active Effluent Report # 21 Page 25 of 34 Page 34 of 37 I

i STABILITY CLASS: E ELEVATION: 10 METERS WIND SPEED (MPH) l

WIND

! DIRECTION 13 4-7 8-12 13 18 19 24 >24 TOTAL i

25 182 83 2 1 0 293 N

29 94 47 3 0 0 173 NNE 45 84 12 0 0 0 141 NE 22 68 26 0 0 0 116 ENE 14 104 59 2 1 0 180-E 16 140 43 2 0 0 201 ESE 23 100 57 2 0 0 182 SE 27 205 164 39 6 4 445 SSE 19 313 339 76 15 4 766 S

9 164 138 6 1 0 318 SSW 9 70 23 4 0 0 106 SW 18 58 24 3 0 0 103 WSW 12 65 38 1 0 1 117 W

13 52 50 11 0 1 127 WNW 4 76 75 10 4 0 169 NW 22 150 90 11 0 0 273 ,

NNW 0 0 0 0 0 0 VARIABLE 0 10 3710 TOTAL 307 1925 1268 172 28 Periods of Calm (Hours): 119 i

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I Attachment I to WCGS Annual Radio-Enclosure to NO 92 0067 active Effluent Report # 21 l '

Page 26-of'34 Page 35 of 37 )

STABILITY CLASS: F ELEVATION: 10 METERS WIND SPEED (MPH)- f l WIND DIRECTION 1 47 8 12 -13 18 19 24 >24 TOTAL

__........____...........................__....__..__.._____.....__..... l N 40 70 9 0 1 0 120 NNE 35 48 2- 0 0 0 85 NE 34 19- 1 0 0 0 54 ENE 40 42- 7 0 0 0 89 E 34 65 11 0 0 0 110 l ESE 31 48 3 0 1 0 83 SE 20 50 4 0 0 0 74-SSE 55 100 24 2 0 0 181 S- 48 124 36 1 0 0 209 10 0 0 0 90 l SSW 21 59 SW 24 17 3 0 0 0 44 I WSW 28 23 3 1 0 0 55 l W 41 29 0 0 0 0 70

'WNW 24 12 4 1 0 0 41 l NW 18 33 7 0 0 0 58' NNW 38 45 17 0 .0 0 100 VARIABLE 0 0 0 0 0 0 0 l TOTAL 531 784 141 5 2 0 1463 ]

I Periods of Calm (Hours): 18 l

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i Attachment'I to WCGS Annual Radio-Enclosure to NO 92 0067_ active Effluent Report 4 21 Page 36 of 37

, Page 27 of 34 STABILITY CLASS: G ELEVATION: 10 METERS

, WIND SPEED (MPH)

WIND D1RECTION 13 4-7 8 12 13 18 19 24 >24 TOTAL 22 27 3 0 0 1 53 N

22 21 1 0 0 0 44

'NNE

~NE 14 7 1 0 0 0 22 ENE 2 22- 4 0 '0 0 28 E 13 27 3 0 0 0 43 ESE 6 13 2 0 0 0 21 SE 15 15 1 0 0 0 31 SSE 44 32 1 0 0 0 77 S 41 28 1 0 0 0 70 SSW 9 17 1 0 0 0 27 SW 10 3 0 0 0 0 13 3 1 0 0 0 0 4 WSW-W 11 8 0 0 0 0 19 WNW 14 5 0 0 0 0 19 NW 12 4 0 0 0 0 16 NNW 25 13 3 0 0 0 41 O 0 0 0 0 0 VARIABLE O TOTAL 263 243 21 0 0 1 528 Periods of Calm (Hours): 9 l

m

Encicsure to NO 92 0067 Attachment I to WCGS Annual Radio-Page 28 of 34 active Effluent Report # 21 Page 37 of 37 I

STABILITY CLASS: All ELEVATION: 10 METERS WIND SPEED (MPH)

WIND-DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL

90. 310 .168 50 6 2 626 N'

87 194 93 21 3 1 399 NNE 94 135 27 7 0 0 263 NE ENE 65 140 51 3 1 0 260 E 62 205 104 9 1 0 381 ESE 57 215 87 6 1 0 366 SE 59 185 97 4 1 0 346 126 367 293 71 8 6 871 SSE S 109 499 747 260 73 11 1699 SSW 43 268 298 98 26 1 734 SW 45 99 58 16 4 0 222 WSW 53 94 48 18 6 1 220 W 70 123 67 13 12 1 286 WNW 51 85 91 71 13 4 315 35 119 111 41 12 9 327 NW 85 225 155 70 18 2 555

, NNW 0 0 0 0 0 0 0

(.. VARIABLE 1131 3263 -2495 758 185 38 7870 TOTAL Periods of Calm (Hours): 149 Hours of Missing Data 741 A plant computer changeout occurred in April 1991. The meteorological data could not be retrieved through the new syste.m. The data being presented has been obtained through strip charts from Apr.t December. The high number of missing hours has been attributed to the malfunctioning of the strip chart recorders.

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ATTACHMENT II The Wolf Creek Generating Station (WCGS) Offsite Dose Calculation Manual (ODCM), Revision 1, is included as Attachment II to this submittal of the WCGS Annual Radioactive Effluent Release Report # 21. The ODCM is separately controlled as a WCGS administrative procedure but is - 4 submitted annually with the .WCGS Annual Radioactive Effluent Release i Report, as required.

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ATTACHMENT II 1

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I The Wolf Creek Generating-Station (WCGS) Offsite Dose Calculation Manual (ODCM), Revision 1, is included as Attachment II to this submittal of the WCGS Annual Radioactive Effluent Release Report # 21. The ODCM is separately controlled as a WCGS administrative procedure but is  ;

i submitted annually with the WCGS Annual Radioactive Effluent Release

Report, as required.

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W8LF CREEK' NUCLEAR OPERATING CORPORATION AP 07B-003 OFFSITE DOSE CALCULATION MANUAL r

Responsible Manager Superintendent Chemistry Revision Number 1 Use Category Reference Administrative Controls Procedure Yes Infrequently Performed Procedure No Program Number 07B DCl2 01/19/98

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 1 of 188 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE 2 2.0 SCCPE 2

3.0 REFERENCES

AND COMMITMENTS 2 4.0 DEFINITIONS 2 5.0 RESPONSIBILITIES 2 6.0 PROCEDURE 3 6.1 Revisiori Of The ODCM 3 6.2 ODCM Submittal To NRC 3 7.0 RECORDS 3 8.0 FORMS 4 ATTACHMENT A OFFSITE DOSE CALCULATION MANUAL 5

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Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 j Reference Use Page 2 of 188 1.0 PURPOSE 1.1 This procedure contains the Offsite Dose Calculation Manual (ODCM) and the requirements for revision and submittal to the NRC.

2.0 SCOPE 2.1 Technical Specification 6.14 shall be fully iriplemented by this procedure.

3.O REFERENCES 4AND COMMITMENTS 3.1 References 3.1.1 Technical Specification 6.14 l I

3.1.2 AP 15C-001, PROCEDURE WRITERS GUIDE l 3.1.3 AP 15C-004, PREPARATION, REVIEW, AND APPROVAL OF DOCUMENTS l 3.1.4 Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFRPartS0, Appendix I 3.1.5 NUREG 0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants 3.2 Commitments 3.2.1 None 4.0' DEFINITIONS 4.1 None 5.0 RESPONSIBILITIES 5.1 The Superintendent chemistry is responsible for the ODCM.

I

i Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 3 of 188 1

6.0 PROCEDURE 6.1 Revision Of The ODCM 6.1.1 All revisions to the ODCM are to be submitted through the Superintendent Chemistry via a document revision request (APF 15C-004-01).

6.1.2 The Superintendent Chemistry shall ensure the Document Revision Request (APF 15C-004-01) package includes the following:

1. A copy of the revised pages including revision bars l

and the date (e.g., month / year) in the right column.

2. Sufficient information to support the change together with the appropriate analyses or l evaluations justifying the change (s) and l

3. A determination that the change will maintain the level of Radioactive Effluent Control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36A, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculations.

6.1.3 The ODCM revision shall become effective after review and acceptance by the PSRC and the approval of the Plant Manager as documented on the Document Revision Request (APF 15C-004-01).

6.2 ODCM Submittal To NRC 6.2.1 Changes to the ODCM shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM ,

was made. I i

1. Each change shall be identified by markings in the margin of the affected pages, clearly indicating  ;

the area of the page that was changed, and shall i indicate the date (e.g., month / year) the change was i implemented.

l 7.0 RECORDS j 7.1 The following is a lifetime QA Record:

7.1.1 AP 07B-003, OFFSITE DOSE CALCULATION MANUAL

1 Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 i Reference Use Page 4 of 188 i

l 8.0 FORMS i I

8.1 None j l

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Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 5 of 188 ATTACHMENT A (Page 1 of 184) j OFFSITE DOSE CALCULATION MANUAL l

Wolf Creek Generating Station j

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l Offsite Dose Calculation Manual l 1

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Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 6 of 188 ATTACHMENT A (Page 2 of 184)

OFFSITE DOSE CALCULATION MANUAL' TABLE OF CONTENTS Page

1.0 INTRODUCTION

10 2.0 LIQUID EFFLUENTS 11 2.1 CONCENTRATION - COMPLIANCE WITH 10 CFR 20 11 2.2 DOSE - COMPLIANCE WITH 10 CFR 50 APPENDIX I 16 '

2.3 PROJECTED DOSE 18 2.4 INSTRUMENTATION 19 ,

j 3.0 GASEOUS EFFLUENTS 37 3.1 DOSE RATE - COMPLIANCE WITH 10 CFR 20 38 3.2 DOSE - COMPLIANCE WITH 10 CFR 50 APPENDIX I 45 3.3 PROJECTED DOSE 55  ;

3.4 INSTRUMENTATION 57 4.0 TOTAL DOSE 72 4.1 REMEDIAL ACTION 72 l 4.2 SURVEILLANCE REQUIREMENTS 73 I 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 73 5.1 MONITORING PROGRAM 73 5.2 LAND USE CENSUS 74 5.3 INTERLABORATORY COMPARISON PROGRAM 74 5.4 REPORTING REQUIREMENTS 75 6.0 BASES 92 7.0 REPORTS 102 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING 102 REPORT 7.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 103 APPENDIX A: DOSE CONVERSION FACTOR TABLES 106 APPENDIX B: METEOROLOGICAL MODEL 182 m

l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 i Reference Use Page 7 of 188 ATTACHMENT A (Page 3 of 184)

OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES I Table Page 2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 12 2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMFNTATION 21 l 2-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 24 SURVEILLANCE REQUIREMENTS 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 41 3-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 58 1

3-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 60 SURVEILLANCE REQUIREMENTS 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 76 5-2 SAMPLING LOCATION NUMBERS, DISTANCES (MILES) AND 82 DIRECTIONS i 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE 83 ANALYSIS 5-4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN 86 ENVIRONMENTAL SAMPLES A.1-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF 107 SITE SPECIFIC DATA A.1-2 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 108 A.2-1 INHALATION DOSE FACTORS FOR ADULTS 109 A.2-2 INHALATION DOSE FACTORS FOR TEENAGERS 111 A.2-3 INHALATION DOSE FACTORS FOR CHILD 113 A.2-4 INHALATION DOSE FACTORS FOR INFANT 115 A.2-5 EXTERNAL DOSE FACTOR FOR STANDING ON CONTAMINATED 117 GROUND A.3-1 INGESTION DOSE FACTOR FOR ADULTS 119 c

Revision: 1 OFFSITE DOSE CALCULATION MANUAL RP 07B-003 )

Reference Use Page 8 of 188 i

ATTACHMENT A (Page 4 of 184)

J OFFSITE DOSE CALCULATION MANUAL '

LIST OF TABLES Table Page A.3-2 INGESTION DOSE FACTOR FOR TEENAGERS 122 I 1

A.3-3 INGESTION DOSE FACTOR FOR CHILD 125 I A.3-4 INGESTION DOSE EACTOR FOR INEANT 128 A.3-5 STABLE ELEMENT TRANSFER DATA 131 A.4-1 SITE RELATED INGESTION DOSE COMMITMENT FOR ADULT 132 A.4-2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR FOR 135 i TEENAGER I A.4-3 SITE RELATED INGESTION DOSE COMMITMENT FACTOR FOR CHILD 138 A.4-4 SITE RELATED INGESTION DOSE COMMITMENT FACTOR FOR 141 IN EANT l

A.5-1 INHALATION DOSE PARAMETER FOR THE CHILD 144 A.5-2 INHALATION PATHWAY FACTOR FOR ADULT (RI FACTOR) 145 A.5-3 INHALATION PATHWAY FACTOR FOR TEENAGER (RI FACTOR) 147 A.5-4 INHALATION PATHWAY FACTOR FOR CHILD (RI FACTOR) 149 l A.5-5 INHALATION PATHWAY EACTOR FOR INFANT (RI FACTOR) 151 A.5-6 GRASS-COW-MILK PATHWAY FACTOR ADULT (RI FACTOR) OF SITE 153 SPECIFIC DATA A.5-7 GRASS-COW-MILK PATHWAY FACTOR TEEN (RI FACTOR) 155 A.5-8 GRASS-COW-MILK PATHWAY FACTOR CHILD (RI FACTOR) 157 A.5-9 GRASS-COW-MILK PATHWAY FACTOR INEANT (RI EACTOR) 159 A.5-10 GRASS-COW-MEAT PATHWAY FACTOR ADULT (RI FACTOR) 161 A.5-11 GRASS-COW-MEAT PATHWAY FACTOR TEEN (RI EACTOR) 163 A.5-12 GRASS-COW-MEAT PATHWAY FACTOR INFANT (RI FACTOR) 165

i Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l

Reference Use Page 9 of 188 ATTACHMENT A (Page 5 of 184)

OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES Table Page A.5-13 VEGETATION PATHWAY FACTOR ADULT (RI FACTOR) 167

A.5-14 VEGETATION PATHWAY FACTOR TEEN (RI FACTOR) 169 A.5-15 VEGETATION PATHWAY FACTOR CHILD (RI FACTOR) 171 A.5-16 GROUND PLANE PATHWAY FACTOR (RI FACTOR) 173 A.5-17 GRASS-GOAT-MILK PATHWAY FACTOR ADULT (RI FACTOR) 174 A.5-18 GRASS-GOAT-MILK PATHWAY FACTOR TEEN (RI FACTOR) 176 A.5-19 GRASS-GOAT-MILK PATHWAY FACTOR CHILD (RI FACTOR) 179 A.5-20 GRASS-GOAT-MILK PATHWAY FACTOR INFANT (RI FACTOR) 181 LIST OF FIGURES l Figure Page I

2.1 BOUNDARY FOR LIQUID EFFLUENTS 36 3.1 BOUNDARY FOR GASEOUS EFFLUENTS 71 5.1 AIRBORNE PATHWAY SAMPLING LOCATIONS 87 5.2 DIRECT RADIATION PATHWAY SAMPLING LOCATIONS 88 5.3 WATERBORNE PATHWAY SAMPLING LOCATIONS 89 5.4 INGESTION PATHWAY SAMPLING LOCATIONS 90 5.5 DISTANT SAMPLING LOCATIONS 91 B-1 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 186 l B-2 PLUME TRAVEL DISTANCE VERSUS FRACTION REMAINING IN 187 PLUME B-3 PLUME TRAVEL DISTANCE VERSUS RELATIVE DEPOSITION RATE 188 i

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Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 '

Reference Use Page 10 of 188 )

l ATTACHMENT A  !

(Page 6 of 184)

OFFSITE DOSE CALCULATION MANUAL 1.0 Introduction The Offsite Dose Calculation Manual describes the Radioactive Effluent Controls Program. The implementation of this program ensures compliance with the requirements of 10 CFR 50.36, 10 CFR 20.106, 10 CFR 50 Appendix I and 40 CFR 190.

On January 1, 1994, 10CFR20.1001-20.2402 shall be implemented.

Wolf Creek will continue to maintain the existing level of effluent control (10CFR20.106) to comply with the new  ;

requirements. This method of compliance has been determined by )

the NRC to be ALARA.

The ODCM describes the methodology and parameters used in the I calculation of offsite doses due to radioactive liquid and gaseous effluents. The ODCM contents for calculation of dose l are based on " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants (NUREG-0133) ," and  ;

Regulatory Guide 1.109, Revision 1.

l Dose calculations are performed for the limiting age group i.e., i Adult age group for the liquid pathway, and the Child age group for gaseous effluent organ doses.

The ODCM provides the limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination. Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified interval.

The ODCM provides the Radiological Environmental Monitoring Program. The program consists of monitoring stations and sampling programs designed to confirm the dose estimates made under normal or accident conditions, and conform to NRC requirements in 10 CFR Part 50.

The ODCM provides descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-002 Reference Use Page 11 of 188 l'

ATTACHMENT A

(Page 7 of 184) i L

OFFSITE DOSE CALCULATION MANUAL  !

2.0 Liquid Effluenta l-l 2.1 , concentration - compliance With 10 CFR 20 The concmentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 2.1) shall be limited to the concentration specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained ,

noble gases, the concentration shall be limited to 2x 10" l microcurie /mL total activity.

2.1.1 Remedial Action With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, irmediately restore the concentration to within the above limits.

2.1.2 Surveillance nequirements To show compliance with this requirement, concentrations of l l

actual liquid effluents will be determined by performing Isotopic Analyses. Radioactive liquid wastes shall be sampled i

and analyzed according to the sampling and analysis program of Table 2-1.

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OITSITE DOSE CALCULATION MANUAL TABLE 2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLE PRINCIPAL I-131 DISSOLVED / GROSS ALPHA Sr-89, Fe-55

( TYPE FREQUENCY GAMMA ENTRAINED AND H-3 Sr-90 EMITTERS GASES (GAMMA)

1. Batch Tanks Q (2) Composite (4)

a. THB07A&B P P(3) P M M Q Composite (4) Composite (4)

LLD (1) SE-7 IE-6 IE-5 1E-7 for SE-8 IE-6 Alpha 1E-5 for H-3

b. THF04AEB P P(3) P M M Q Q Composite (4) Composite (4 ) Composite (4)

LLD (1) SE-7 l1E-6 I

IE-5 1E-7 for SE-8 1E-6 Alpha 1E-5 for H-3

2. Continuous Releases (5)

a. Steam Daily (6) W(3) W M M 0 0 Generator Composite (4) Composite (( Composite (4) Composite (4) Composite (4)

Blowdown LLD(1) SE-7 IE- 3 IE-5 1E-7 for SE-8 IE-6 Alpha IE-5 for H-3

b. Turbine Daily (6) W(3) W M M Q Q Building Sump Composite (4) Composite (4) Composite (4) Composite (4) Composite (4)

LLD(1) 5E-7 1E-6 IE-5 1E-7 for SE-8 IE-6 Alpha IE-5 for H-3

c. Waste Water Daily (6) W(3) W M M Q Q Treatment Composite (4) Composite (4) Composite (4) Composite (4 ) Composite (4)

LLD(1) SE-7 1E-6 IE-5 IE-7 for SE-8 1E-6 Alpha 1E-5 for H-3 LLD = (pCi/mL) 1/9F f

)

5

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OFFSITE DOSE CALCULATION MANUAL TABLE'2-1 (Continued)

TAM ' NOTATIONS (1) The'LLD is' defined, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

-probability of falsely concluding'that a blank observation represents a'"real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66 s

E x V x 2.22 x 10' x Y x Decay

-Where:

LLD =' the "a. priori" lower limit of detection (microcuries-pe'r unit mass or' volume), ,

~ I sb = the standard deviation of the background  ;

counting rate or of the counting rate of a blank sample  ;

as appropriate, (counts per minute) , ss - & LT Where: B = background sum (' counts)

LT = live time (minutes), 1 E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 106= the number of disintegrations per minute per I microcurie, Y = the fractional radiochemical yield, when applicable, Decay = decay factor (s), There are three decay factors that may.be appropriate for use depending on the nature of the sample and the half life of the nuclide. Any combination of the three may be used. The factors are as follows:

A) This decay factor corrects for decay from the time of p sampling to the start of the analysis, e AAts, where:

Ata = decay time = acquisition start time - sample time

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TABLE NOTATIONS A = In2/ half-life l l

B) This decay factor corrects for decay during the analysis.

"7 1-e 2 x RT A= In2/ half-life RT = real time of counting ,

C) This decay _ factor corrects for decay during sampling.

1 - e '""

2Atd 1

A = In2/ half-life td = deposition time = sample time - deposition start time NOTE All times used in decay calculations should be in the same units.

Typical values of E, V, Y, t 3, td should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in plant procedures to assure representative sampling.

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OFFSITE DOSE CALCULATION MANUAL TABLE 2-1 (Continued) l TABLE NOTATIONS (3) The principal gamma emitters for which the LLD specification applies l include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. This list does not l mean that only these nuclides are to be considered. Other gamma peaks I that are identifiable, together with those of the above nuclides, I shall also be analyzed and reported in the semiannual Radioactive Effluent Release Report in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, Jun3 1974.

(4) A composite sample is one in which the quantity of liquid sampled is i proportional to the quantity of liquid waste discharged and in which l the method of sampling employed results in a specimen that is l representative of the liquids released. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite samples to be representative of the effluent release.

l (5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) Samples shall be taken at the initiation of effluent flow and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter while the release is occurring. To be representative of the liquid effluent, the sample volume shall be proportioned to the effluent stream discharge volume. The ratio of sample volume to effluent discharge volume shall be maintained constant for all samples taken for the composite sample.

FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days M At least once per 31 days.

O At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not applicable.

P Completed prior to each release.

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OFFSITE DOSE CALCULATION MANUAL.

2.2 Dose - Compliance With 10 CFR 50 Appendix I The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each l unit, to UNRESTRICTED AREAS (see Figure 2.1) shall be limited: I i

a. During any calendar quarter to less than or' equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3-mrems to the whole body and to less than or equal to 10 mrems to any organ.

2.2.1 Remedial Action With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, l prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause (s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent' releases will be in compliance with the above limits.

This Special Report shall also include the results of radiological analyses of the drinking water source, and the radiological impact on finished drinking water supplies with-regard to the requirements of 40 CFR Part 141, Clean Drinking Water Act. This requirement of (1.) and (2.) are applicable only if drinking water supply is taken from the receiving body within 3 miles of the plant discharge.

2.2.2 Surveillance Requirements Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined using the following methodology at least once per 31 days.

l / 3 m

D7 =E i Ad,t.A t oCitFt >

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-Where, DT= thel cumulative dose commitment to the total body:

or any organ, T, from the liquid effluent for the total time period f A tt ,in mrem L-l At t = the length'of the Lth time period over which Cit and Ft are averaged for all liquid releases, in hours.

C i n = the average concentration of radionuclide, 'i', in undiluted liquid effluent flow during time period At t, in Ci/mL.

Et =-the near field average dilution. factor for Cit during any liquid effluent release where:

f F' = (F)K Where:

f= Liquid Radioactive Waste Flow F= Discharge Structure Exit Flow, the sum of the release and dilution flow.

K= Applicable factor; the site dependent value for the mixing effect of the discharge structure. This value is conservatively assumed to be 1 (one) for this section.

A 17 = The site related ingestion dose commitment factor to the total body or any organ, 'T', for each identified principal gamma and beta emitter, mrem /hr per Ci/mL. See Tables A.4-1 through A.4-4.

The limiting age group for liquid dose calculations is the Adult age group.

Air = 1.14E5 (U, / Dw+Up x BF)DF, i

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OFFSITE DOSE CALCULATION MANUAL Where, DW = Dilution factor from the near field area to the potable water intake for water consumption, for Wolf Creek-Generating Station this factor is 1 (one).

BFi= Bioaccumulation factor ~for radionuclide 'i', in fish, pCi/Kg per pCi/1, from Table A.1-1 from Regulatory Guide 1.109 (Rev. 1).

DFi= Adult dose Conversion factor for radionuclide,

'i', in mrem /pCi, from Table A.3-1 through A.3-4, from Regulatory Guide 1.109 (Rev. '1).

Uw = Adult water consumption,(730 1/yr.from Reg. Guide 1.109)

Up = Adult fish consumption,(21 kg/yr.from Reg. Guide 1.109) 1.14E5 = Units conversion factor = # X 8 8760 hr / yr The dose calculations are based on the. actual isotopic analysis of the radioactive liquid effluents, the radioactive liquid effluent flow, and the dilution ~ flow.

2.3 Projected Dose The Liquid Radwaste Treatment System shall be OPERABLE.and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 2.1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period.

2.3.1 Remedial Action With' radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

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a. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the. reason for the inoperability, i l

b. Action (s) taken to restore the inoperable equipment to j OPERABLE status, and 1 l

'l

c. Summary description of action (s) taken to prevent a recurrence.

2.3.2 Surveillance Requirements 2.3.2.1 Doses due to liquid releases from each init to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance'with the following .ethodology when Liquid-Radwaste Treatment Systems are not being fully utilized.

Dn -

x 31

_T_

1 Where, -l l

D31 = Projected 31 day dose A = Cumulative dose for previous three months T = Number of days that the cumulative dose occurred in A above 2.3.2.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting the requirements of Sections 2.1 and 2.2.

2.4 Instrumentation The radioactive liquid effluent monitoring instrumentation channels shown in~ Table 2-2 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Section 2.1 are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined.and adjusted in accordance with the methodology and parameters described in Section 2.4.4.

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OFFSITE DOSE CALCULATION MANUAL 2.4.1 Remedial Action 2.4.1.1 With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip'Setpoint less conservative than required by the above, immediately suspend the release of radioactive liquid effluents monitored by the.affected channel, or declare the channel inoperable.

2.4.1.2 With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2-2. Restore the inoperable instrumentation to OPERABLE statusEwithin the' time specified in the ACTION, or explain in the next Annual Radioactive Effluent Release Report, why this inoperability was.not corrected within the time specified.

2.4.2 Surveillance Requirements Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 2-3.

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( OFFSITE DOSE CALCULATION MANUAL .,

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(- TABLE 2-2 l RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

! INSTRUMENT MINIMUM ACTION

CHANNELS OPERABLE

1. Radioactivity Monitors Providing Alarm and l Automatic Termination of Release

[ a. Liquid Radwaste Discharge Monitor-(HB-RE-18) 1 31

'b. Steam Generator Blowdown Discharge Monitor 1 32 (BM-RE-52)

c. Turbine Building Drain Monitor (LE-RE-59) 1 32

d. Secondary' Liquid Waste System Monitor (HF-RE-45) 1 33 Wastewater Treatment System Influent Monitor 1 32 I e.

(HF-RE-95)

2. Flow Rate Measurement Devices l

a. Liquid Radwaste Discharge Line j i

1) Waste Monitor Tank A Discharge Line 1 34 I

2) Waste Monitor Tank B Discharge Line 1 34 )

b. Steam Generator Blowdown Discharge Line 1 34

c. Secondary Liquid Waste System Discharge Line 1 34

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ATTACHMENT A' (Page 18 of 184) l OFFSITE DOSE CALCULATION MANUAL TABLE 2-2 (Continued)

ACTION STATEMENTS Action 31 - With the number of channels OPERABLE less than required by the

Minimum Channels OPERABLE requirement, effluent releases via this pathway may_ continue for up to 14 days.providedLthat prior ~to initiating a release

a. At least two independent samples are analyzed in'accordance L with Section 2.1.2,-and i

i. b. At least two technically. qualified members of the facility ll staff-independently. verify the release rate calculations and l discharge'line valving.

l Otherwise,. suspend release of radioactive effluents via this pathway.

Action'32 - With the number of channels. OPERABLE less than required by the-Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for.up to 30 days provided grab samples are

! analyzed for principle gamma emitters and I-131 at a lower limit of

. detection as specified in Table 2-1.

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the_ specific activity of the

secondary coolant is greater than 0.01 microcurie / gram DOSE.

[ EQUIVALENT I-131, or p b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the

'~

secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.

Action 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this l pathway may continue for up to 30 days provided that prior to initiating a release:

l <

l a. At least.two independent samples are analyzed in accordance with Section 2.1.2, and

b. At least two technically qualified members of the facility i staff independently verify the release rate calculations and l' dischargeLline valving.

f Otherwise, suspend release of radioactive effluents via this pathway.

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ACTION STATEMENTS.

Action 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE. requirement, efflue'nt releases.via this pathway may continue for up to 30 days provided the flow rate is estimated at least once~per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance curves generated in place may be used to estimate flow.

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TABLE 2-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION  :

SURVEILLANCE REQUIREMENTS l INSTRUMENT CHANNEL SOURCE CHANNEL ANALOG f CHECK CHECK CALIBRATION CHANNEL i OPERATIONAL i TEST )

1. Radioactivity Monitors providing alarm and automatic termination of release

a. Liquid Radwaste Discharge Monitor D P R(2) Q(1)

(HB-RE-18)

b. Steam Generator Blowdown Dis- D M R(2) Q(1) charge Monitor (BM-RE-52)

I

c. Turbine Building Drain Monitor D M R(2) Q(1) l (LE-RE-59) l l

d. Secondary Liquid Waste System D P R(2) Q(1) l Monitor (HF-RE-45) i

e. Wastewater Treatment System D M R(2) O(1)

Influent Monitor (HF-RE-95)

2. Flow Rate Measurement Devices j

a. Liquid Radwaste Discharge Line D(3) N.A. R N.A.

b. Steam Generator Blowdown Dis- D(3) N.A. R N.A.

charge Line

c. Secondary Liquid Waste System D(3) N.A. R N.A.

Discharge Line l

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OFFSITE DOSE CALCULATION MANUAL TABLE 2-3 (Continued)

TABLE NOTATIONS (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur as appropriate if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm / Trip Setpoint (isolation and alarm), or '

b. Circuit failure (alarm only), or

c. Instrument indicates a downscale failure (alarm only), or

d. Instrument controls not set in operate mode (alarm only).

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range or energy, measurement range, and establish monitor response to a solid calibration source. For subsequent CHANNEL CALIBRATION, NIST traceable standard (gas, liquid, or solid) may be used; or a gas, liquid, or solid source that has been calibrated by relating it to equipment that was previously (within 30 days) calibrated by the same l geometry and type of source standard traceable to NIST.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

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2.4.3 Liquid Monitor calibration Methodology {

l The five monitors associated with liquid releases are listed ,

below: i I

l Monitor ID Description I 0-BM-RE-52 Steam Generator Blowdown Discharge Monitor 0-LE-RE-59 Turbine Building Drain Monitor 1 0-HF-RE-45 Secondary Liquid Waste System Monitor -f

'0-HB-RE-18 Liquid Radwaste Discharge Monitor j 0-HF-RE-95 Wastewater Treatment System Influent Monitor '

l J

(

' Liquid effluent streams 'are monitored by an NaI(Tl) Detector.

The' detector operates in a gross counting mode and is gamma sensitive.

L Calibration of the liquid monitors shall be performed using three' standard solutions of Cs-137. The solutions shall cover the appropriate range of the detector and have1 concentrations of approximately 5 x 10-7 Ci/cc, 1 x 10-5 pCi/cc,.and 1 x 10-3 Ci/cc. The solutions shall be presented to the detector and i

! _the meter-reading in counts per minute shall be recorded.

A -)

determination of linearity shall be produced using the counts I

! per minute vs. concentration data..

I 2.4.4 Liquid Effluent Monitor Setpoints.

The Alarm / Trip Setpoints for the Liquid Effluent Radiation

! Monitors are based on instantaneous concentration limits of 10 l

CFR 20, Appendix B, Table II, Column 2 applied at the boundary of the restricted area. Specifically, the High Alarm Setpoint will correspond to the 10 CFR Part 20 limits at the Boundary of j

!- the restricted area; the Alert Alarm Setpoint is set one order

! of magnitude below the High Alarm / Trip Setpoint. Since the high q i

l alarm / trip initiates isolation of the.particular system and L

termination of the release, this setpoint represents assurance L that the instantaneous liquid release limit of 10 CFR Part 20 is l .not exceeded. Auditable records shall be maintained indicating the actual setpoints used at all times.

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The calculated Alarm and Trip Action Setpoints for the Liquid Effluent Line Monitors must satisfy the following equation:

l cf i F+f-1 l

Where:

, C = The liquid effluent concentration limit-(MPC) l implementing Section 2.1 in'pci/mL.

l c = The Setpoint, in pCi/mL, of the Radioactivity L Monitor measuring the radioactivity concentration in

the effluent.line prior'to dilution and subsequent l release; the Setpoint, which is inversely proportional to the Volumetric Flow of the' effluent line and l directly proportional to the Volumetric Flow of the  !

dilution stream plus the effluent stream, represents a value, which if exceeded would result in concentrations i exceeding the limits of 10 CFR 20 in the restricted ]

l area. j 1

f = The Pump Flow Rate as measured at the Radiation 1 Monitor Location, in Volume per Unit Time, but in the l same units as F, below.

) ,

F = The Dilution Water Flow Rate as measured prior.to the release point, in Volume per Unit Time.

Thus, the exprassion for determining the cetpoint on the Liquid

Radwaste "itluent Line Monitor becomes:

l i

c$ C(F+ f) (pCi/ ml) '

. f 2.4.4.1 Continuous Liquid Effluent Monitors l

The three monitors associated with continuous liquid releases are listed below:

Monitor ID Description 0-BM-RE-52 Stm Generator Blowdown Discharge Monitor 0-LE-RE-59 Turbine Building Drain Monitor 0-HF-RE-95 Waste Water Treatment System Influent Monitor .

i i

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The Steam Generator Blowdown Discharge Effluent Monitor  !

continuously monitors the Blowdown Discharge Pump l Outlet to detect excess radioactivity due to System l Demineralizer breakthrough or abnormal Primary to l Secondary leakage. The Blowdown Discharge Monitor's  !

High Alarm Setpoint initiates CLOSURE of the Blowdown l Isolation Valves and the Blowdown Discharge Valve. I Similarly, the High Radiation Alarm on the Turbine {

Building Drain Monitor and Waste Water Treatment j Monitor initiates CLOSURE of the Drain Line Isolation i Valves to prevent the release of radioactive effluents.

Monitor setpoints will be conservatively based on I-131, the most restrictive isotope expected to be i present. This is particularly appropriate for the l Turbine Building Drain Line Monitor since the most probable source is the Secondary Steam System which is expected to have negligible activity unless there is a  ;

significant Primary to Secondary leak. Due to changing  :

activities, it will not be possible to select a j radionuclide distribution on which to base the monitor i setpoint. Additionally, maximum effluent flows and l minimum dilution flows will normally be assumed. j The High Alarm / Trip Setpoint will be set to correspond to the I-131 MPC limit at the boundary of the j restricted area from 10 CFR Part 20, Appendix B, Table j II, Column 2. The alert alarm is set one order of magnitude below the High Alarm / Trip Setpoint for ,

release points that have dilution and to the High Alarm value for those without dilution. This High Alarm / Trip l Setpoint assures the limits of Section 2.1 are not exceeded at the boundary of the restricted area.

In the event that an alarm is TRIPPED, an evaluation of the system will be made by taking an actual isotopic and flow analysis of the discharge.

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OFFSITE DOSE CALCULATION MANUAL' The above continuous liquid effluents are not radioactive effluents until activity has been detected by the Liquid Effluent Monitor, a Tritium analysis of the Secondary. system,.or a. gross Beta analysis of the Secondary system. At that time an analysis of the-effluent will be made to verify activity in the system effluent. During periods of time when the above liquid effluents are not radioactive the High Alarm / Trip Setpoint may be set to 1.5 times the background count rate.

2.4.4.1.1 Steam Generator Blowdown Discharge Monitor SETPOINT(pCi/ ml) = MPCs ui x '"

B where, MPC I -in = Maximum Permissible Concentration of '-131,  ;

3.0 E-7 pCi/mL.

Fm = Dilution flow rate. I FB = Blowdown flow rate. )

l The setpoint calculation is based on the minimum dilution flow l rate, the maximum possible blowdown flow rate, and, due to l changing conditions, I-131 which is the most restrictive isotope  :]

expected to be present. )

i On the event that an alarm is reached, the setpoint will be j reevaluated using the actual dilution flow rate, the actual i

' blowdown flow rate, and the actual isotopic analysis as outlined I in Section 2.4.4.2. This evaluation will be used to ensure the limit of Section 2.1 was not exceeded. The setpoint will still be based on the MPC of I-131 due to the changing conditions of activity and I-131 being the most restrictive isotope.

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OFFSITE DOSE CALCULATION MANUAL 2.4.4.1.2 Turbine Building Drain Monitor And Waste Water Treatment System Influent Monitor

+ 7 SETPOINT(pCi/ ml) = MPC yn x '"

T MPC 1 in = 3.0 E-7 pCi/mL.

Fm = Dilution flow rate ]

Fe = Ef fluent flow rate ,

l The setpoint is based on.the minimum dilution flow rate, the l' maximum possible effluent flow rate, and the most restrictive isotope expected to be present, I-131.

On the event that an alarm is reached, the-release will be evaluated to see if the limit of Section 2.1 was exceeded by using the actual Dilution Flow Rate, the actual Effluent Flow l Rate, and the actual isotopic analysis as outlined in Section j 2.4.4.2. The setpoint will still be based on the MPC of I-131 l due.to the changing conditions of activity and I-131 being the

]

most restrictive isotope. .

2.4.4.2 Batch Radioactive Liquid Eff].uent Monitor The two monitors associated with liquid batch releases are I listed below:

Monitor ID Description 0-HF-RE-45 Secondary Liquid Waste System Monitor 0-HB-RE-18 Liquid Radwaste Discharge Monitor The setpoint is a function of dilution flow rate, tank flow rate, and isotopic composition. A laboratory isotopic analysis is made of each batch prior to discharge. Based on the isotopic analysis and existing flow condition, the setpoint will be calculated and set on the appropriate monitor to ensure the concentration limits of 10 CFR 20, Appendix B, Table II, Column 2 is not exceeded.

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ATTACHMENT A (Page 27 of 184)

OFFSITE DOSE CALCULATION MANUAL The setpoints are determined using the following methodology:

(

l 1) Determine concentrations of radioactivity of the batch being considered for release.

The' isotopic concentration of the batch is the sum of-

[ the concentrations for the isotopes present as D determined from the analysis required in Table-2-1.

h

[Ci = [C +g C, + C, + C i + Cr i- g-l L Where:

, ci = The concentration of nuclide i as determined.by.

L the analysis of the waste sample. I Cg -=

The sum of the concentrations Cg of each measured gamma emitting nuclide observed by gamma-ray. )

spectroscopy of the waste sample. I I

L *Ca = The measured concentration Ca of alpha emitting nuclides observed by gross alpha analysis of the monthly composite sample.  ;

• C 3 = The measured concentrations of Sr-89 and Sr-90

'in liquid waste as determined by analysis of the quarterly composite sample.

• Ct= The measured concentration of H-3 in liquid waste as determined by analysis of the monthly composite.

l L *Cf= The measured concentration of Fe-55 in liquid l waste as determined byfanalysis of the quarterly j l- composite.

• Values for these concentrations will be based on previous composite sample analysis'as required.by Table L 2-1.

L

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ATTACHMENT A (Page 28 of 184)

OFFSITE DOSE CALCULATION MANUAL

2) The measured radionuclide concentrations are used to calculate a dilution factor, F, d whidi is the ratio of total dilution flow rate to tank flow rate required to assure that the limiting concentrations of Section 2.1 I

are met at the' point of discharge. This is referred to as the required dilution factor and is determined according to:

r ,, 8 F, =

s Z'MPCp H x F' Where:

Ci= Measured concentrations of C g, C, a C, s Ct and C f, as defined in Step 1. Terms Ca, C, 3 Ct and C f, will be ,

I included in the calculation as appropriate.

MPCi = MPC g, MPC a, MPCs, MPCt and MPCf, are limiting concentrations of the appropriate radionuclide from 10 <

CFR 20, Appendix B, Table II, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04, Ci/mL total activity.

Fs '= The safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurement default value is 0.5.

3) For the case Fd<1, the waste tank effluent concentration meets the limits of 10 CFR 20 without dilution and the effluent may be released at any desired flow rate. For the case Fd > 1, a modified dilution factor, Fd n, must be determined so that available dilution flow may be apportioned among simultaneous discharge pathways. 1 Fu = F /a F, Where Fa is the allocation factor which will modify the required dilution factor so that simultaneous liquid releases may be made without exceeding 10 CFR 20 limits. l l

l 1

l l

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OFFSITE DOSE CALCULATION MANUAL The most straight-forward determination of allocation factor is:

F, = 1/ n Where:

n = The number of liquid discharge pathways for which Ed > 1 and which is planned for simultaneous release.

However, this value for Fa may be unnecessarily restrictive in that all release pathways are apportioned the same fraction of the available dilution stream, regardless of the relative concentrations of each of the sources.

Since the radionuclide concentration of the two continuous scurces is expected to be less than that of the batch release source, it is acceptable to allocate smaller portions of the dilution stream to the continuous releases and a larger portion to the batch releases.

Therefore, Fa is defined as a flexible quantity with a default value of 1/n. Prior to initiating simultaneous release, a check will be made to assure that the sum of the allocation factors assigned to pathways for the simultaneous release is < 1.

4) The calculated maximum permissible waste tank effluent flow rate, Fmax, is based on the modified dilution factor, Fdn, and the effective dilution flow rate, Feff.

The cooling lake into which the effluent is discharged is also the source of the dilution stream. It is therefore necessary to take into account the recirculation of previously emitted radionuclides should they be detected by sample analysis of the cooling lake water. This is accomplished by defining an effective dilution flow rate as:

a

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OFFSITE DOSE CALCULATION MANUAL Where:

Fm = The expected minimum dilution water flow rate. ,

l LCi = Measured concentration of nuclide i in the

! cooling lake water sample.

MPCi = Limiting concentration of radionuclide i from 10CFR20, Appendix B, Table II, Column 2.

For the purpose of setpoint calculations the expected minimum dilution flow rate is assigned a value based upon the type and number of pumps RUNNING into the circulating water piping.

Having established the values of Fdn and Feff, the calculated maximum permissible waste tank flow rate is given by F F'"

f,,,, 5 *" ,+ f, for f,((Feff I<o,, f a,,

Where f p if the expected effluent flow rate; normally the rated capacity of the effluent pump. Thus the pump

{

flow rate is set at or below fmax. Even though the 4 I

value of f max may be larger than the actual effluent l pump capacity, f, p it does represent the upper limit to the effluent flow rate, whereby the requirement 'of 10CFR20 may still be met. If Fd $ 1, the effluent pump flow rate may be assigned any value since the waste  ;

tank effluent concentration meets the limits of 10CFR20 l without dilution and the release may be made without  ;

regard to the setpoints for other release pathways.

For those discharge pathways selected to be secured during the release under consideration, the pump flow ,

rate should be set at as low a value as practicable to "

detect any inadvertent release.

A setpoint for the dilution stream flow rate is not ,

applicable since the minimum flow rate is  !

administratively set.

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t l ATTACHMENT A (Page 31 of 184) l OFFSITE DOSE CALCULATION MANUAL l

5) The liquid radiation monitor setpoint may now be determined based on the values of E,C, i 1 and fmax-The monitor response is primarily to gamma radiation, therefore, the actual setpoint is based on E g , C g. The calculated monitor setpoint concentration is determined l as follows: l c = A [C g( Ci / ml) l i l Where:

A= Adjustment factor which will allow the setpoint to be established in a practical manner for convenience and to prevent spurious alarms.

A=

f

! r l If A > 1, calculated c and determine the maximum value for the actual monitor setpoint (pCi/mL).

If A < 1, no release may be made.

If Fd<1, no further dilution is required and the release may be made without regard to available dilution or to other releases made simultaneously. However, it is necessary to establish a monitor setpoint which will provide alarm should the release concentration inadvertently exceed 10CFR20 limits. This l can be accomplished by establishing the adjustment factor as follows:

A = 1/ Fo l

L i

I r

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ATTACHMENT-A (Page 32 of 184)

! OFFSITE-DOSE CALCULATION MANUAL

FIGURE 2.1 ,

BOUNDARY FOR LIQUID EFFLUENTS I l )

l l-  !

'I l

l.

s L ( ,--

) _

5 p

i.

i ---

i W y. w= ir= r'--X4 ,

N ..

.... - , X -, 4 i

( w.n s-m

~

, nJ ~~\

_ l

~~'- ,.

} L $.K:: 'yB \ l o l l- ,

\.

L --.

3 ----

W

'l =

n\

l  :. s.

A  : -.---c. :

j t 7 - -.

- ~

..% w

9) wot/ CRET.K CEN(.81ATWC STATION

! V & UNIT MQ, I

\

sim 2.1

! ,y <- t . .... < < < i m

=e/ <=tte to e s ac l- (\ > ; \ -

L v _w

.D*u

. . . .._ . _ _ a .--

25 t

I

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OFFSITE DOSE CALCULATION MANUAL 3.0 Gaseous Effluents Gaseous effluent releases from the Unit Vent and Radwaste Building Vent are monitored continuously. .The Unit Vent is the release point for the Fuel / Auxiliary Building, access control area, containment purge, and condenser air discharge. The Radwaste Building Vent is the release point for Waste Gas Decay Tanks and the Radwaste Building Ventilation System.

Waste Gas Decay Tank releases and Containment Building releases are treated as batch releases. Waste Gas Decay Tank releases are monitored by the Radwaste Building Exhaust Monitor.

Containment Building releases (purges) are monitored by the Containment Purge System monitors and the Plant Unit Vent Monitor.

Monitor identifications are as follows:

Monitor ID Release Point Description 0-GT-RE-21 A and B Unit Vent (Fuel / Auxiliary Building, access control area, containment purge, condenser air discharge) 0-GH-RE-10 A and B Radwaste Building vent (Radwaste Building, waste gas decay tank discharge. Acts to isolate Waste Gas Decay Tank discharge) 0-GT-RE-22 & 23 Containment Purge System Monitor (e. cts to isolate the purge; is not an effluent monitor)  !

t 0-GT-RE-31 & 32 Containment Atmosphere Monitor (acts to isolate purge; not an effluent monitor)  :

The setpoint for monitors may be determined either based on total body dose or skin dose rate. The dose rate limits are for i dose rates at the unrestricted area boundary. The monitor l setpoint is the lesser of the total body dose rate or skin dose rate. .

l I

I i

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OFFSITE DOSE. CALCULATION MANUAL l

3.1- Dose Rate - Compliance With 10 CFR 20

'The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the. SITE BOUNDARY (see Figure 3.1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and

b. For Iodine-131 and 133, for tritium, and'for all.

radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 I mrems/yr to any organ.

3.1.1 Remedial Action With the dose rate (s) exceeding the above limits, immediately restore the release to within the above limit (s).

3.1.2 Surveillance Requirems..ts The dose rate to radionuclides in gaseous effluents shall be determined to be within the above limits in accordance with the methodology described _below by obtaining representative samples and performing analyses in accordance with the sampling and analysis program'specified in Table 3-1.

l Based on the methodology of NUREG-0133; 1

l a. Release rate limit for nobles gases:

K i (X / Q) Q, < 500 mrem / yr for the total body, and l

(L, + 1.1 M )(X i / Q) Q, < 3000 mrem / yr for the skin l

Where:

l Ki = Total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m 3, from Table A.1-2.

I

I i

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(X/Q) = 2.2E-06 sec/m3, the highest calculated annual average relative concentration at the restricted area boundary in the north sector.

Qi = Release rate of radionuclide i from vent, in pCi/sec.

Li =

Skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3, from Table A.1-2.

Mi = Air dose factor due to ganna emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 from Table A.1-2.

1.1 = Conversion constant of air dose to skin dose,

b. Release rate limit for all radionuclides and radioactive materials in particulate form and  !

radionuclides other than noble gases:

[(P,)IN x (X / Q)x Qi) < 1500 mrem / yr to any organ, i

Where:  ;

Qi = The release rate of radionuclides, i, in gaseous effluent from all vent releases, in pCi/se.c. 1 P(i)IN = The dose parameter for radionuclides other than nobles gases for the inhalation pathway, in mrem /yr per Ci/m 3. See Table A.5-1.

(X/g) = 2.2E-06 sec/m3 (the highest annual average).

The highest calculated annual average relative I concentration for estimating the dose to any l individual at the unrestricted area boundary in the N sector.

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ATTACHMENT A iPage 36 of 184)

OFFSITE DOSE CALCULATION MANUAL All radionuclides are assumed to be released in e3emental form.

The limit is applicable to the location (unrestricted area l boundary or beyond), characterized by the value cf X/Q which l results in the maximum total body or skin dose ,cmmitment. The factors K i, L,i and Mi relate the radionuclide airborne concentrations to various dose rates assuming a semi-infinite cloud. These facters are taken from Table B-1 of the Regulatory

, Guide 1.109 and multiplied by 106 to convert pCi-1 to pCi-1 and listed in Table A.1-2.

The following equation for P(i)IN was taken from NUREG 0133:

P(i)IN (Inhalation);

l P, = K' (BR) DF A (mrem i / yr per pCi / m )

Where:

K' = a constant of unit conversion, 106 pCi/ Ci.

BR = the breathing rate of the child age group in m3/yr DFAi = the maximum organ inhalation dose factor ter the child age group for the i th radionuclide, in mrem /pCi. The total body is considered as an organ in the selection of DFAi.

The age group considered is the child group. The child's breathing rate is taken as 3700 m 3 /yr from Table E-5 of l Regulatory Guide 1.109. The inhalation dose factors for the child, DFAi are presented in Table E-9 of Regulatory Guide 1.109, in units of mrem /pCi.

Resolutions of the units yield:

1 Pi (Inhalation) = 3.7 X 109 DFAi The Pi value for tritium is:

l Pi (Inhalation) = 3.7 x 109 DFAi l

I l

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ATTACHMENT A (Page 37 of 184)

OFFSITE DOSE CALCULATION MANUAL TABLE 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Sample Principal H-3 I-131/ Gross Sr-89, Type Frequency Gamma (Oxide) I-133 Alpha Sr-90 Emitters l

l

1. linit Vent Gas M M(3) (2) M(4) l LLD(1) lE-4 lE-6 )

Particulate Continuous (6) W(7) M Q Composite LLD(1) lE-ll ( 2 ) 1E-11 lE-11 Charcoal continuous (6) W(7)

LLD(1) lE-12/

lE-10

2. Radwaste Building Vent ,

Gas M M(2) M i LLD(1) 1E-4 lE-6 Particulate Continuous t 6) W(7) (2) M Q (Composite)

LLD(1) 1E-11 lE-11 1E-11 Charcoal Continuous ( 6) W(7)

LLD(1) 1E-12/

1E-10

3. Containment M Purge or Vent Gas P(3) P(3) (2)

LLD(1) lE-4 lE-6 l

4. Waste Gas Decay Tanks Gas P P(2)

LLD(1) lE-4 LLD = (pCi/ml) 1/9C

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-1 (Continued) 2 TABLE NOTATIONS (1) The LLD is defined, as the smallest concentration ,f radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 s b LLD =

E x V x (2.22E + 6) x Y x Decay Where:

LLD = the "a priori" lower limit of detection (microCuries per unit mass or volume),

= the standard deviation of the background counting sb rate or of the counting rate of a blank sample as appropriate, (counts per minute), s o - VB / LT Where: B = background sum (counts)

LT = live time (minutes),

E =

the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22E+6 = the number of disintegrations per minute per microcurie, 1/98 Y =

the fractional radiochemical yield, when applicable, Decay = decay factor (s), There are three decay factors that may be appropriate for use depending on the nature of the sample and the half life of the nuclide. Any combination of the three may be used. The factors are as follows:

A) This decay factor corrects for decay from the time of sampling to the start of the analysis, e -Aat s, where:

Ats = decay time = acquisition start time - sample time

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l ATTACHME!!T A (Page 39 of 184)

OFFSITE DOSE CALCULATION MANUAL TABLE 3-1 (Continued) l TABLE NOTATIONS A = In2/ half-life B) This decay factor corrects for decay during the analysis.

l.

1 - e '*

2 x RT A =

In2/ half-life RT = real time of counting C) This decay factor corrects for decay during sampling.

1 - e **

AAtd A = In2/ half-life Atd = deposition time = sample time - deposition start time NOTE A11 times used in decay calculations should be in the same units.

Typical values of E, V, Y, t 3, td should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the i fact) limit representing the capability of a measurement system and not as ao

'a_ posteriori (after the fact) limit for a particular measurement.

l-l

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OFFSITE DOSE CALCULATION MANUAL I TABLE 3-1 (Continued)

TABLE NOTATIONS

l. (2) The principal gamma emitters'for which the'LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133,'Xe-133m, Xe-135, and Xe-138 in noble gas releases and.Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137,-Ce-141 and Co-144 in iodine L and particulate releases. This list does not mean that only these.

nuclides are to be considered. 'Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the' semiannual Radioactive Effluent Release Report in the format outlined in Regulatory Guide 1.21,~ Appendix B, i

Revision 1, June 1974. 2/98 i '.

(3) ' Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.

(4) Tritium grab samples shall be taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.

(6) The ratio of the sample flow rate to the sampled stream flow rate l shall be known for the time period covered by each dose or dose rate calculation made in accordance with Sections 3.1, 3.2 and'3.3.

(7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. For unit vent, sampling shall also be performed at least

( once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change. exceeding 15% of RATED THERMAL POWER within a 1-hour peri ~od, and analysca shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10. This.

requirement to sample once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> does not apply if analysis shows that both the DOSE EQUIVALENT I-131 concentration in the reactor l coolant and the unit vent noble gas monitor activity have not increased more than a factor of 3. 2/98 i

l l

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OFFSITE DOSE CALCULATION MANUAL 3.2 Dose - Compliance With 10 CFR 50 Appendix I 3.2.1 Noble Gases-

, The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

3.2.1.1 Remedial Action With the calculated air dose from radioactive noble gases in i gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a special report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent release: will be in compliance with the above limits.

3.2.1.2 Surveillance Requirements Cumulative dose contributions for the current calendar quarter and calendar year for noble gases shall be determined in accordance with the following methodology at least once per 31 days. The dose calculations for the actual releases of radioactive noble gases in gaseous effluent will be consistent with the methodology provided in Reg. Guide 1.109, Rev. 1. The following dose calculations will be performed:

a. During any calendar quarter; For gamma radiation; D = 3.17E -8 Mi fX/ G)x Qis 5 mrad.

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OFFSITE DOSE CALCULATION MANUAL For beta radiation:

D = 3.17E-8 [N; X/Q)x Qi s 10 mrad.

i-i

b. During any calendar year:

For gamma radiation; D = 3.17E -8 [ M i (X / Q) x Qis 10 mrad.

i=1 For beta radiation:

D = 3.17E - 8 N, s 20 mrad.

(X / Q) x Qi Where:

3.17 E-8 = The inverse of the number of seconds in a )

year.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per i pCi/m3 from Table A.1-2 (Reg. Guide 1.109, Table B-1, Col. 4).

Ni = The air dose factor due to beta emissions for l each identified noble gas radionuclide, in mrad / year per Ci/m3 from Table A.1-2 (Reg. Guide 1.109, Table )

B-1, Column 2). {

= 2.2E-06 sec/m3, the highest calculated annual (X/Q) average relative concentration at the restricted area boundary in the north sector.

Qi = The release of noble gas radionuclides, 'i', in gaseous effluents, in Ci. Releases shall be cumulative t

over the calendar quarter or year as appropriate.

An average monthly air dose schedule should be setup to ensure section 3.2.1 is not exceeded. The average monthly air dose should be as follows:

I i

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OFFSITE DOSE CALCULATION MANUAL ,

1

a. For gamma radiation $ 1.6 mrad /mo.

! For beta radiation < 3.3 mrad /mo.

l .

)

If the monthly average air doses for: .(a) is exceeded, it should be noted that if the release is continued at the same (or l higher) frequencies or activities the quarterly limit of Section )

3.2.1.A will be exceeded. l I

b. For gamma radiation 5 0.8 mrad /mo.

j For beta radiation $ 1.6 mrad /mo.

l If the monthly average air doses for: (b) is exceeded, it should i be noted that if the release is continued at the same (or l higher) frequencies or activities the annual limit of Section 3.2.1.B will be exceeded.

If any of the above monthly average air doses are exceeded, j evaluation of the causes of the high. air dose should be j j

performed and steps should be taken to: reduce the activity.or frequency (e.g. delay the release' of a Waste Gas Decay Tank) of the release.

3'.2.2 Radioiodines, Particulates and Other Radionuclides The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from cach' unit, to areas at and beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 l

mrems to any organ; and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

9

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3.2.2.2 Surveillance Requirements Cumulative dose contributions for the current calendar quarter l and current calendar year for Iodine-131~and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 .

days shall be determined in accordance with the following I methodology at least once per 31 days. To show compliance, the ;

dose calculations for the actual releases of the. subject materials are consistent with the methodology provided in Regulation Guide 1.109, Revision 1. The following dose calculations will be performed:

a. D (mrem) = 3.17E-8 R i (WQi) s 7.5 mrem

b. D (mrem) ' 3.17E-8 R i (WQi) $ 15 mrem Where:

3.17 E-8 = The inverse of the number of seconds in a year.

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ATTACHMENT A (Page 45 of 184)

OFFSITE DOSE CALCULATION MANUAL Qi = The release of radiciodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, 'i', in pCi.

Releases shall be cumulative over the calendar quarter or year as appropriate. The Qi value shall be j determined as the product of the flow rate through the release point and grab samples of the effluent analyzed in accordance with Table 3-1.

W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location.

t W = (X/Q), 2.2 x 10-6 sec/m3 for the inhalation  !

pathway.  !

I W = (D/Q), 1.8 E-8 m-2, for the food and ground plane pathways.  ;

Ri = The dose factor for each identified radionuclide, 'i', in mrem /yr per pCi/m3 See Table  !

A.5-2 through Table A.5-20.

Where:

i Inhalation Pathway Factor, RI i [X/Q]

R'i [X / Q) = K' (BR),(DFA ),i (mrem / yr per pCi / m')  ;

Where:

K' = a constant of unit conversion, 10 6 pCi/pCi.

(BR) a = The breathing rate of the receptor of age group (a), in m3/yr.

The breathing rates (BR)a for the various age groups are tabulated below, as given in Regulatory Guide 1.109, Table E-5.

AGE GROUP (a) BREATHING RATE (m3 /yr) l Infant 1400 Child 3700 Teen 8000 Adult 8000

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OFFSITE DOSE CALCULATION MANUAL (DFAi )a = The maximum organ inhalation dose factor for the receptor of age group (a) for the i th radionuclide, in mrem /pCi. The body is considered as an organ in the selection of (DFA i)a. See Tables A.2-1, A.2-2, A.2-3, & A.2-4. From Regulatory Guide 1.109, Tables E-7,E-8, E-9 and E-10.

Ground Plane Pathway' Factor, RGi[D/Q]

2 R i (D / Q) = K'K" (SF) DFG, (1-eT)/2, m x mrem / yr per /Ci/ sec)

Where:

K' = A constant of unit conversion, 106 pCi/ Ci. l K" = A constant of unit conversion, 8760 hr/ year.

Ai = The decay constant for the i th radionuclide, sec-1 t = The exposure time, 4.73 E8 sec (15 years).

DFGi= The ground plane dose conversion factor for the i th radionuclide (mrem /hr per pCi/m )2 . See Table A.2-5. (Regulatory Guide 1.109, Table E-6).

SF = The shielding factor (dimensionless), 0.7 (Reg.

Guide 1.109) l l

Grass-Cow-Milk Pathway Factor, RC 1[p/g) l d 2

' ' [D / Q) = K' i F,(r)(DFL),('/Y,fe i i'ffm mrem /yrper/Ci/ sec)

Where:

K' = A constant of unit conversion, 106 pCi/ Ci.

Op = The cow's consumption rate, in Kg/ day (wet weight), 50 kg/ day. (Reg. Guide 1.109, Table E-3).

Ua

= The receptor's milk consumption rate for age (a , in liters /yr. (Reg. Guide 1.109, Table E-5).

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Infant = 330 1/yr Child = 330 1/yr Teen = 400 1/yr Adult = 310 1/yr l

Yp = The agricultural productivity b unit area of pasture feed grass, in kg/m2, 0.7 kg/m . (Reg. Guide- j 1.109, Table E-15) '

Fm =

The stable element transfer coefficients, in days / liter, see Table A.3-5. (Reg. Guide 1.109, Table E-1) r = Fraction of deposited activity retained on cow's j feed grass, r=1 for radiciodine and r= 0.2 for {

particulates. (Reg. Guide 1.109, Table E-15)

(DFL1 )a = The maximum organ ingestion dose factor for the i th radionuclide for the receptor in age group

'a', in mrem /pCi. See Tables A.3-1, A.3-2, A.3-3, and l A.3-4. (Reg. Guide 1.109, Table E-11, E-12, E-13, and E-14) 11 = The decay constant for the i th radionuclide, in sec-1

= The decay constant- for removal of activity on Aw leaf and plant surfaces by weathering, 5.73 E-7 sec-1 J (corresponding to a 14 day half-life). j NOTE The fraction of the year that the cow is on pasture and the fraction of the cow feed that is pasture grass is assumed to be 1.0, which is the most restrictive case.

l tf

= The transport time from pasture to cow, to milk, to receptor, in sec, 1.73 E5 sec (2 days). (Reg. Guide l 1.109, Table E-15).

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l Grass-Goat-Milk Pathway Factor, Re 1[D/Q)

I C ' d 2 R i[D / Q) '= K' F,(r)(DFL,),('/Y,fe i'f)(m mrem /yrper/Ci/sec)

Where:

Op = The goat's consumption rate, in Kg/ day (wet  !

weight), 6 Kg/ day. (Reg. Guide 1.109, Table E-3). l tf = The transport time from pasture to goat, to milk, to receptor, in sec, 1.73 E5 sec (2 days). (Reg.

Guide 1.109, Table E-15).

all other terms are defined under the Grass-Cow-Milk-Pathway Factor. .

l NOTE The fraction of the year that the goat is on pasture and the fraction of the goat feed that is pasture grass is assumed to be 1.0, which is the most restrictive case.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RC i is based on (X/g),

C 2 R i[X/Q) = K'K" ' F,Q,U,,(DFL ),(0.75 i (0.5/ H))(mrem /yr per/Ci/m )

Where:

K"' = a constant of unit conversion, 103 gm/Kg.

H = Absolute humidity of the atmosphere, 8 gm/.n 3 (Reg. Guide 1.109).

0.75 = The fraction of total feed that is water.

(NUREG 0133) l 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG 0133)

{

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Where-I Ff = The stable element transfer coefficients, in I days /kg, Table A.3-5. (Reg. Guide 1.109, Table'E-1).

Uap = The receptor's meat consumption rate for age (a), in kg/yr. (Reg. Guide 1.109, Table E-5).

Infant = 0 child = 41 Teen = 65 Adult = 110 l l

I tf

= The transport time from pasture to receptor, in sec., 1.73 E6 (20 days) (Reg. Guide 1,109, Table E-15).

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the RM i is based on (X/Q):

M R i[X/Q) = K'K" ' FrQ,U,,(DFL,),[0.75 (0.5/ H))(mrem / yr per Ci/ m')

Where:

All terms defined above.

Vegetation Pathway Factor, RV i[D/Q]

Man is considered to consume two types of vegetation (fresh and stored) that differs only in the time period between harvest and consumption, therefore:

V ' S 2 R i (D / Q)- K' (DFLi ), (U'.)(fo)(ci'L)+(U .)(f,{c-'i'b) (m x mrem / yr per pCi / see)

Where:

K' = A constant of unit conversion, 106 pCi/pCi.

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L Ua= The consumption, rate of fresh leafy vegetation l by.the receptor in age group (a), in kg/yr. (Reg. Guide 1.109, Table E-5).

l-Infant. = 0 kg/yr.

Child = 26 kg/yr Teen = 42 kg/yr

.=.64 Adult kg/yr I~

S Ua =

The' consumption rate of stored vegetation by the receptor in age group (a), Kg/yr. -(Reg. Guide 1.109, Table E-5).

Infant = 0 kg/yr Child = 520 kg/yr .

l Teen = 630 kg/yr l Adult = 520 kg/yr l'

fL = The fraction of the annual intake of fresh, leafy vegetation grown locally. (default = 1.0) (Reg. Guide'

1.109).

I fg = The fraction of the annual intake of stored vegetation grown locally (default = 0.76) (Reg. Guide

1.109).

l.

I tL =- .The average time between harvest of leafy vegetation and its consumption, in seconds, 8.6 E4 sec (1 day). (Reg.. Guide 1.109).

L th = The average time between harvest of stored L vegetation and its consumption, in seconds, 5.18 E6 sec ,

i; (60 days) (Reg. Guide 1.109, Table E-15). 1 5

Yy = The vegetation area density, 2.0 kg/m 2. (Reg.

Guide 1.109, Table E-15).

All other factors previously defined.

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(, Grass-Cow-Meat Pathway Factor,-RMi[p/g]

l 4 l

2 R"'(D / Q) .= K' Fr(r) (DFLi ),('/Y,)(ci'f)(m mrem / yr per mci / see)

Where:

Ff = The stable element transfer coefficients, in days /kg, Table A.3-5. (Reg. Guide 1.109, Table'E-1).

Uap = The receptor's meat consumption rate for age (a), in kg/yr. (Reg. Guide 1.109, Table E-5).

Infant = 0 Child = 41 Teen = 65

i. Adult = 110 a

tf

= The transport time from pasture.to receptor, -fr sec., 1.73 E6 (20 days) (Reg. Guide 1,109, Table E-15).

The concentration of tritium in meat'is based on its airborne concentration rather than the deposition. Therefore, the RM i is based on (X/Q):

s R"i(X/Q) = K'K" '. FrQrU.p(DFL;),{0.75 (0.5/H))(mrem /yr perpCi/m )

Where:

All terms defined above.

Vegetation ~ Pathway Fact'or, RV i[D/Q]  ;

Man is considered to consume two types of vegetation (fresh and stored) that differs only in the time period between harvest and consumption, therefore:

V ' 8 2 R i (D / Q)= K' (DFLi ), (U'.)f t)(e-di 'L) +(U .)(fde-'i'h) (m x mrem / yr per pCi / sec)

Where:

K' = A constant of unit conversion, 106 -pCi/ Ci.

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OFFSITE DOSE CALCULATION MANUAL UL a =

The consumption rate of fresh leafy vegetation by the receptor in age group (a), in kg/yr. (Reg. Guide 1.109, Table E-5).

Infant = 0 kt/yr Child = 26 ,sg/yr Teen = 4T kg/yr Adult = 64 kg/yr S

Ua =

The consumption rate of stored vegetation by the receptor in age group (a), Kg/yr. (Reg. Guide 1.109, Table E-5).

Infant = 0 kg/yr Child = 520 kg/yr Teen = 630 kg/yr Adult = 520 kg/yr fL = The fraction of the annual intake of_ fresh leafy vegetation grown locally. (default = 1.0) (Reg. Guide 1.109).

fg = The fraction of the annual intake of stored vegetation grown locally (default = 0.76) (Reg. Guide 1.109).

tt = The average time between harvest of leafy vegetation and its consumption, in seconds, 8.6 E4 sec (1 day). (Reg. Guide 1.109).

th = The average time between harvest of stored-vegetation and its consumption, in seconds, 5.18 E6 sec (60 days) (Reg. Guide 1.109, Table E-15).

Yy = The vegetation area density, 2.0 kg/m 2. (Reg.  ;

Guide 1.109, Table E-15). l l

All other factors previously defined.

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OFFSITE DOSE CALCULATION MANUAL The concentration of tritium in vegetation is based on the ,

I airborne concentration rather than the deposition. Therefore, the RV i is based on (X/Q):

V 8 R p / % = K'K" ' (U'.ft + U .fdDFL,),{0.75 (0.5/ H))(mrem / yr per /fi/ m')

Where:

All terms defined previously. All values indicated are default values from Reg. Guide 1.109, Rev. 1.

An average ;nonthly dose schedule should be setup to ensure Section 3.2.2 is not exceeded. The average monthly dose due to radiciodines, particulates, and other radionuclides which are included in this section should be as follows: ,

1

a. < 2.5 mrem /mo.

If the monthly average dose for (a) is exceeded, it should be l noted that if the release is continued at the same (or higher) 1 frequencies or activities the quarterly limit of Section 3.2.2.a will be exceeded.

b. < 1.25 mrem /mo.

If the monthly average dose for (b) is exceeded, it should be noted that if the release is continued at the same (or higher) frequencies or activities the yearly limit of Section 3.2.2.b will be exceeded.

If any of the above monthly doses are exceeded, evaluation of the causes should be performed and steps taken to reduce the activity or frequency of the release.

3.3 Projected Dose The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions cf i these systems shall be used to reduce releases of radioactivity l when the projected doses in 31 days due to gaseous effluent l releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 3-1) would exceed:

a. 0.2 mrad to air from gamma radiation, or 1

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b. 0.4 mrad to air from, beta radiation, . or

c. 0.3 mrem to any organ'of a MEMBER O.F THE PUBLIC.

l 3.3.1 Remedial Action

! I With' radioactive gaseous waste being discharged without I treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical 1 Specification 6.9.2, a special report that includes the  !

following information: )

> Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence.

3.3.2 Surveillance Requirements 3.3.2.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the following methodology when Gaseous Radwaste Treatment Systems are not being fully utilized.

Du - x 31 Where:

D31 = Projected 31 day dose A = Cumulative dose for previous three months

-T = Number of days that the cumulative dose occurred in A above 3.3.2.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered. OPERABLE by meeting Section 3.1 and 3.2 limits.

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OFFSITE DOSE CALCULATION MANUAL 13 . 4 Instrumentation l

i i The radioactive gaseous effluent monitoring instrumentation j channels shown in Table 3-2 shall be OPERABLE with their I Alarm / Trip Setpoints set to ensure that the limits of Section l 3.1 are not exceeded. The Alarm / Trip setpoints of these j channels-meeting Section 3.1 shall be determined and adjusted in accordance with the methodology and parameters of Section 3.4.4 below.  !

3.4.1 Remedial Action

a. With a radioactive gaseous effluent monitoring I instrumentation channel Ala ' Trip Setpoint less conservative than required by the above specification, l immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare l

the channel inoperable.

L b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the ACTION shown in Table 3-2. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Annual Radioactive Effluent Release Report, why this inoperability was not corrected within the time specified.

3.4.2 surveillance Requirements Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 3-3.

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ATTACHMENT A l (Page 54 of 184) l OFFSITE DOSE CALCULATION MANUAL TABLE 3-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM APPLICABILITY ACTION CHANNELS OPERABLE

1. Unit Vent System

a. Noble Gas Activity 1

• 40 Monitor - Providing i Alarm (GT-RE-21B) l

b. Iodine Sampler (GT-RE-21A) 1

• 43

c. Particulate Sampler (GT-RE-21A) 1

• 43 Flow Rate *

d. N.A. 45

e. Sampler Flow Rate 1

• 39 Monitor

2. Containment Purge System

a. Noble Gas Activity Monitor - 41 Providing Alarm and Automatic 1

• Termination of Release (GT-RE-22, GT-RE-33)

b. Flow Rate N.A.

• 45

3. Radwaste Building Vent System

a. Noble Gas Activity Monitor - 38,40 Providing Alarm and Automatic

• 1 Termination of Release (GH-RE-10B)

b. Iodine Sampler (GH-RE-10A) 1 43

c. Particulate Sampler (GH-RE-10A) 1 43

d. Flow Rate N.A.

• 45

e. Sampler Flow Rate Monitor 1 39

• At all times.

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TABLE 3-2 (Continued)

TABLE NOTATIONS ACTION STATEMENTS ACTION 38 - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are l analyzed, and j

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 39 - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 40 - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 41 - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

ACTION 43 - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sample equipment as required in Table 3-1.

ACTION 45 - Flow rate for this system shall be based on fan status and operating curves or actual measurements.

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TABLE 3-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE

! REQUIREMENTS INSTRUMENT CHANNEL SOURCE CHANNEL ANALOG MODES FOR CHECK CHECK CALIBRATION CHANNEL WHICH OPERATIONAL SURVEILLANCE TEST IS REQUIRED

1. Unit Vent System

a. Noble Gas Activity Monitor- D M R(3) Q(2)

• Providing Alarm (GT-RE-21)

b. Iodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A. *

d. Flow Rate N.A. N.A. R(4) N.A. *

e. Sampler Flow Rate Monitor D N.A. R

• Q

2. Containment Purge System

a. Noble Gas Activity Monitor- D P R(3) Q (1)

• Providing Alarm and Auto-matic Termination of Re-lease (GT-RE-22, GT-RE-33)

b. Iodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A. *

d. Flow Rate N.A. N.A. R(4) N.A. *

e. Sampler Flow Rate Monitor D N.A. R N.A. *

3. Radwaste Building Vent System D, P M,P R(3) *

a. Noble Gas Activity Monitor- O(1)

Providing Alarm and Auto-matic Termination of Release (GH-RE-10)

b. Iodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A. *

d. Flow Rate N.A. N.A. R(4) N.A.

• I

e. Sampler Flow Rate Monitor D N.A. R N.A.

• I e *At all times.

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TABLE NOTATIONS 1

l (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation as appropriate occur if any of the following conditions exists:

I l

a. Instrument indicates measured levels above the Alarm / Trip Setpoint (isolation and alarm), or l

b. Circuit failure (alarm only), or I l

l

c. Instrument indicates a downscale failure (alarm only) or

d. Instrument controls not set in operate mode (alarm only).

(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate'that control room alarm annunciation occurs if any one or combination of the following conditions exists: ]

a. Instrument indicates meaoured levels above the alarm setpoint 1

b. Circuit failure i

c. Instrument indicates a downscale failure {

d. Instrument controls not set in operate mode.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy, measurement range, and establish monitor response to a solid calibration source. For subsequent CHANNEL CALIBRATION, NIST traceable standard (gas, liquid or solid) may be used; or a gas, liquid, or solid source that has been calibrated by relating it to equipment that was previously (within 30 days) calibrated by the same geometry and type of source traceable to NIST.

(4) If flow rate is determined by exhaust fan status and fan performance curves, the following surveillance operations shall be performed at least once per 18 months:

a. The specific vent flows by direct measurement, or

b. The differential pressure across the exhaust fan and vent flow established by the fan's " flow- P" curve, or

c. The fan motor horsepower measured and vent flow established by the fan's " flow-horsepower" curve.

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OFFSITE DOSE CALCULATION MANUAL 3.4.3 Airborne Radiation Monitor Calibration Methodology The following monitors are' associated with gaseous releases Monitor ID Monitor Description Monitor Type o-GT-RE-21A Plant Unit Vent Particulate, Iodine O-GH-RE-10A Radwaste Building Effluent Particulate, Iodine o-GT-RE-21B, Plant Unit Vent Wide Range Gas 0-GH-RE-10B Radwaste Building Effluent Wide Range Gas O-GT-RE-22 & 33 Conta!iunent Purge Exhaust Particulate, Iodine, Gas O-GT-RE-31 & 32 Containment Atmosphere Particulate, Iodine, Gas 3.4.3.1 Particulate Detector I Beta particulate is monitored by a 50 mm diameter by 0.25 mm thick plastic scintillator optically coupled to a 50 mm diameter photomultiplier tube. This detector shall be calibrated over its range of energy and rate capabilities.

For energy range calibration four sources shall be used. Each source consists of a filter paper impregnated with a beta emitting radionuclide. The radionuclides used should be Tc-99,-

Cs-137, Cl-36, and Rh-106. Each source shall be positioned in the filter paper retaining ring and counted separately. The count rates for each radionuclide source shall be recorded and the data plotted on a graph of cpm /pCi versus average beta energy. This curve represents the detectors response characteristics over the range of beta energies observed. The efficiency for setpoint calculations shall be based on the efficiency of the detector for Cs-137.

The detector shall be calibrated for its rate capabilities using a filter paper impregnated with standard activities of Cs-137.

Increasing amounts of a standard Cs-137 solution shall be impregnated on a filter paper. The counts per minute for each Cs-137 standard shall be recorded. A determination of linearity shall be' produced using the counts per minute vs. concentration data. At least three sources covering approximately 4, H, and k of full scale shall be checked.

3.4.3.2 Iodine Detector Iodine gas is monitored by absorbing the gas on a charcoal filter element. The charcoal filter is viewed by an NaI(Tl) integral line gamma scintillator assembly.

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! gaseous iodine, barium sources shall be used for calibration.

The photo peaks of interest are as follows:

a. Ba-133: 356 kev gamma is 0.69 efficient / disintegration

b. I-131: 364 kev gamma is 0.82 efficient / disintegration Therefore, each iodine disintegration will produce 0.82/0.69 x barium disintegrations. Assuming that the detector efficiency for 356 kev is the same as for the 364 kev, the sensitivity for I-131 equals 1.19 x Ba-133 (counts / min) pCi. The standard sources shall be constructed by impregnating a standard Ba-133 solution into the charcoal filter element. The geometry shall simulate the iodine retention on the first surface of the charcoal. Sources shall be prepared to cover approximately k, H and h of full scale. The barium counts per minute for each standard shall be adjusted to iodine counts per minute as described above. A determination of linearity shall be produced using the corrected counts per minute vs. concentration data.

3.4.3.3 Gas Detector The gas detectors associated with monitors 0-GT-RE-22 & 33, 0-GT-RE-31 & 32 and the low-range detectors of monitors j 0-GT-RE-21B and 0-GH-RE-10B are a plastic scintillator identical to the particulate detector. The mid-range and high-range detectors of monitors 0-GT-RE-21B and 0-GH-RE-10B are cadmium telluride, solid state sensors.

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OFFSITE DOSE CALCULATION MANUAL Sources for all gas detectors shall be produced by evacuating the sample chamber with a vacuum pump. The sample chamber then shall be backfilled to the desired pressure with a source of standard Xe-133. The source is then counted and the counts per minute recorded. A determination of linearity shall be produced using the counts per minute vs. concentration data. Sources shall be prepared to cover approximately 4, H and k of full scale for the detectors associated with monitors 0-GT-RE-22 and 33, 0-GT-RE-31 and 32 and the low-range detectors of monitors 0-GT-RE-21B and 0-GH-RE-10B. Sources shall be prepared for the mid/high range detector to cover two points on the mid-range scale. For ALARA purposes, response for the high-range scale shall be extrapolated using the data from the mid-range calibration.

3.4.4 Airborne Monitor Setpoints 3.4.4.1 Total Body Dose Rate Setpoint Calculations ,

The limit of the total body dose rate is 500 r. rem /yr at the unrestricted area boundary. The monitor alarm / trip setpoint based on total body dose will be calculated as follows:

S. s (SF x AF) x D. x R, Where:

Stb = The monitors alarm / trip setpoint based on the total body dose rate. (pCi/cc)

NOTE If the monitor setpoint units needed are (pci/sec), multiply

( Ci/cc) calculated setpoint by the waste gas stream flow rate (cc/sec).

Dtb = Limit of 500 mrem /yr total body, conservatively interpreted as a continuous release over a one year period.

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! SF = Normally will be set to 0.85. This number is chosen since the gaseous monitors are set using Xe-133 energy level. -Xe-133 comprises 85% of total noble l gaseous. activity expected. (See USAR Table 11.1-1). 3 If necessary the 0.85 can be further modified to compensate for statistical fluctuations and errors of-l_ measurement.

AF = Allocation factor for each release so that.

L simultaneous releases can be made_without exceeding the L limit. Normally AF is calculated as follows:

l RF

AF TF Where

RF = Release flow rate of the release point under consideration.

TF = Total flow rate of all release points including I release under consideration. j l

Rt= monitor response,per mrem /yr to the total body, I determined according to:

R =, 3 s

(x/Q)EKQi i

i s

Where:

c'= The monitor response to the gaseous effluent noble 7 gas ( Ci/cc) corresponding to grab sample radionuclide concentrations.

(X/QJ = The highest calculated annual average atmospheric dispersion (sec/m3) at the restricted area boundary.

Ki= The total body dose factor due to gamma emissions from isotope i (mrem /yr per pCi/m3) from Table A.1-2.

a.

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OFFSITE DOSE CALCULATION MANUAL Qi = Rate of release of noble gas radionuclide i

( Ci/sec) (concentration of radionuclide i x release flow rate) 3.4.4.2 Skin,gose Rate Calculation The limit of the skin dose rate is 3000 mrem /yr at the restricted area boundary. The monitor alarm / trip setpoint is  !

calculated as follows:

1 S, s (SF r AF) x D, x R, Where: j i

Ss= The monitors alarm / trip setpoint based on the I skin dose rate. (pCi/cc)

~

NOTE l

l If the monitor setpoint units needad are (pCi/sec) , multiply the pCi/cc), calculated setpoint by the waste gas stream flow rate (cc/sec).

D3 = Limit of 3000 mrem /yr to the skin of the oody, censervatively interpreted as a continuous release over a one year period.

Rs= Monitor response per mrem /yr to the skin of the body.

R,=, 3

<(X / Q)i Z(L i + 1.lMi ) Q, Where:

Li= Skin dose factor due to beta emissions from isotope 1 (mrem /yr per Ci/m3) from Table A.1-2.

1.1 = Conversion factor to mrem skin dose per mrad air dose.

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l ATTACHMENT A l (Page 63 of 184)

. OFFSITE DOSE CALCULATION MANDAL l

Mi= Air dose factor due to gamma emissions from isotope 1 (mrad /yr per Ci/m3 ) from Table A.1-2. j The factors SF, AF, c, (X/g)andQiareasdefinedinSection 3.4.4.1.

The results of equations from Sections 3.4.4.1 and 3.4.4.2 are compared to determine the smaller setpoint. The actual monitor setpoint is the lower of the two values.

A pre-release isotopic analysis is performed for batch releases from Waste Gas Decay Tanks and Containment Building purges to determine the identity and quantity of the principal radionuclides. The appropriate alarm / trip setpoint (s) are l adjusted accordingly to ensure that the limits of 3.1 are not exceeded.

3.4.4.3 Alert Alarm Setpoint Calculations l l l The' Noble Gas Alert Alarm for the Plant Unit Vent (0-GT-RE-21)  ;

and Radwaste Building Exhaust Monitor (0-GH-RE-10), is set to l alert operators to that average concentration which if  !

maintained for a full year would result in the 10 CFR 50, Appendix I Annual Dose Guidelines being reached. Section 3.2.1 limits the annual dose due to noble gases to $ 10 mrads for

gamma radiation and $_20 mrads for beta radiation. Section 3.2.2 limits the annual dose to a MEMBER OF THE PUBLIC from l Iodine-131, Iodine-133, tritium and all radionuclides _in particulate form with half-lives greater than 8 days in gaseous effluents to $ 15 mrem to any organ. These two sections contain the annual dose limits due to gaseous releases found in 10 CFR 50, Appendix I.

3.4.4.3.1 Noble Gas Alert Alarm Setpoint Calculation The alert alarm setpoint is the lesser of l S, 5 (SF x AF) x Dy x Ry l Sp$ (SF x AF) x Dp x Rp Where:

Sy = Monitor setpoint based on gamma radiation.  !

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. ATTACHMENT A (Page.64 of 184)

OFFSITE DOSE CALCULATION' TNUAL D, = Limit of 10 mrad /yr conservatively interpreted as a continuous release over a one year period.

F( = ' Monitor response per mrad /yr determined according to:

R7 =

7, .

3 s(X/Q)i E Mi xs Qi Where:

Mi = Gamma air dose factor (mrad /yr per Ci/m3),

See Table A.1-2, 1

S, = Monitor setpoint based on beta radiation.

l D, = Limit of 20 mrad /yr conservatively interpreted as {

a continuous release over a one year peric>.i.

R, = Monitor response per mrad /yr determined according to:

Rp=, , .

t (X/Q)EN i i xQi s

Where:

Ni = Beta air dose factor (mrad /yr per Ci/m3),

See Table A.1-2.

A semi-fixed alert alarm setpoint for the Plant Unit Vent ,

Monitor (0-GT-RE-21) and Radwaste Building Vent Monitor  :

(0-GH-RE-10) is calculated using the following:

i e >

, (10 mrad / yr)(.85)(AF)

Setpomt(pCi/cc) = , ,

i

(((X/Q)[P i x Mi x Q /s Where:

Pi = Fractional value of isotope expected, C i /C T'

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OFFSITE DOSE CALCULATION MANUAL Where:

l Ci = Concentration in Ci/cc of isotope.

CT.

= Total Gaseous Activity from USAR Table 11.1-1 l AF = Either unit vent flow'or Radwaste Building vent L flow civided by the combined flow of the unit vent and l Radwaste Building vent.

t

=

j Q Vent flow rate in cc/sec.

Isotopes used and Pi values are as follows:

l l

ISOTOPE Pi Kr-85M .018 Kr-87 .010 l

l Kr-88 .033 l

I Xe-133M .017 l Xe-133 .851 l Xe-135 .051 I

Should this semi-fixed alert alarm cause a continuous alarm condition, then actual setpoints will be calculated.

3.4.4.4 Particulate And Iodine Alarm Setpoints l Setpoints for the gaseous effluent particulate and iodine channels are set using Cs-137 MPC for particulates and I-131 MPC e for_ iodines. The following is the calculation used:

l Setpomt(pCi/cc) = (MPC i

)(AF)(SF)

(Q)(X/Q)

Where:

MPCi = 5 x 10- Ci/cc for Cs-137

= 1 x 10-1 pCi/cc for I-131 l

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(

l ATTACHMENT A (Page 66 of 184)

'OFFSITE DOSE CALCULATION MANUAL AF = as defined previously SF = .0625 for I-131 *

= .9375 for Cs-137

• L

• derived from ratio of isotope activity (either I-131 l or Cs-137) to sum of activity of Cs-137 and I-131 found I in USAR Table 11.1-1 for reactor coolant.

0 = Vent flow in M 3 /sec This vill pr ovide the hi alarm setpoint. The alert alarm setpc1*.e ~. 10% of the hi alarm setpoint.

i

{

I

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! OFFSITE DOSE CALCULATION MANUAL FIGURE 3.1 BOUNDARY FOR GASEOUS EFFLUENTS l

r .. l t --

/

I

! 3 5 j asos e.o

'I"eE".'s". "n"'er'e'IEE[

m'k

! [- .M \rt X .

yW vj --s_ s,

. _ _ - ~

M' c

\ ,

Y *'"

, .se o00 m, ._.

. T Ig N *0EHEELI

_,. 1 7 ...

Y - ""

WOLFCR K EN ATING STAfl0N C

Figure 3.1 tovtulary For Geseevs Effluents suLP tunes tenume Last A )%\ - oo.

u w muta no e A..

^ " _ _ _ * *--

LD L L M tf8EOP == 3pttent

{ n=.r l WOLF CREEK - UNIT 1 .....

s

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I i ATTACHMENT A.

.(Page 68 of 184) 4

OFFSITE DOSE CALCULATION MANUAL l l

1 4 '. 0 Total Dose The~ annual (Calendar year) dose or dose commitment tx): any_ MEMBER ,

OF THE PUBLIC. due to releases ~ of radioactivity and '13) . radiation I from' uranium fuel' cycle sources shall-be limited to less-than or equal to 25 mrems tolthe whole body or any organ, except the thyroid, which shall be limited to less than or equal to-75 mrems.

! 4 .1. Renedial Action-With~the calculated doses from.the release of radioactive materials'in-liquid or. gaseous effluents exceeding twice the'

-limits of Section 2.2a, 2.2b, 3.2.la,_ 3.2.lb, 3.2.2a and 3.2.2b-calculation.should be made including direct radiation

~ contributions from the. units and from outside storage tanks to:

determine.whether theJabove111mits of Section 4.0 above'has been exceeded. If'such is the case,' prepare and submit to the

. Commission within 30 days, pursuant to Technical' Specification j 6.9.2, a special report that defines the~ corrective action to'be taken to reduce subsequent. releases to' prevent recurrence'of exceeding the above limits. This special report, as defined in 4 10 CFR 20.405c, shall. include an analysis.that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the' release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the special report shall include a

. request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal'of the report is considered a timely request, and a variance is granted until staff action on the request is complete. 1/98 q

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OFFSITE DOSE CALCULATION MANUAL 4.2 Surveillance Requirements 4.2.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with the methodology of Sections 2.2 and 3.2 at least once per 31 days when the release of. radioactive materials in liquid or gaseous effluents exceed twice the limits of Section 2.2a, 2.2b, 3.2.la, 3.2.lb, 3 2.2a and 3.2.2b. Otherwise, no further evaluation is required.

4.2.2 Cumulative dose contribution from direct radiation from the reactor unit and from Radwaste storage tanks shall be determined utilizing the results of routine plane perimeter surveys, TLD data or a combination of both, when necessary. This requirement is applicable only under conditions set forth in the remedial action above.

5.0 Radiological Environmental Monitoring Program This section describes the Radiological Environmental Monitoring Program specified in Section 6.8.4.f of the Wolf Creek Technical Specifications. 1/98 5.1 Monitoring Program Table 5-1 provides a schedule which describes the pathways, specific locations, sample collection frequencies, and analyses l to be performed to implement the Radiological Environmental l Monitoring Program. I Figures 5.1 through 5.5 contain maps depicting sampling locations in relation to the WCGS site. Table 5-2 lists distances and directions to these locations from the WCGS site.

Table 5-3 lists required detection capabilities for the analyses performed.

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! ATTACHMENT A I l (Page 70 of 184) l OFFSITE DOSE CALCULATION MANUAL ,

l 5.2 Land Use Census l

l A Land Use Census shall be conducted annually during the growing l season to identify the nearest (1) milk animal, (2) residence, i and (3) garden of greater than 500 square feet producing L broadleaf vegetation

• in each of the 16 meteorological sections l within five miles of the WCGS site. Methods shall be used ir.  !

conducting the census that provide the best results, such as door-to-door surveys, telephone surveys, consulting the_U.S.D.A.  ;

office in Burlington, inspection of aerial photographs of the

area, or reviewing leasing records for area farms and ,

l residences. 5/96  !

, If a location (s) is identified which yields a calculated dose.or l dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained,  ;

the new location (s) shall be added to the~ Radiological Environmental Monitoring Program within 30 days as described in Table 5-1, Note (1). The indicator sampling location (s) having L the lowest calculated dose or dose commitment may then be l deleted from the monitoring program. The revision to Table 5-1 L and the corresponding Figure (s) as a result of such substitutions shall be documented in accordance with Section-6.14 of the Wolf Creek Technical Specifications.

I The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report described in Section 7.1.

5.3 Interlaboratory Comparison Program The analysis laboratory contracted to analyze samples from the Radiological Environmental Monitoring Program participates in l

the EPA Laboratory Intercomparison Program or similar program.

l

• Broad leaf vegetation sampling of available vegetation may be

. performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5-1, Part 4.c. shall be followed, including analysis of control samples.

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OFFSITE DOSE CALCULATION MANUAL A summary of intercomparison results shall be included in the Annual Radiological Environmental Operating Report described in Section 7.1.

5.4 Reporting Requirements-5.4.1 Annual Radiological Environmental Operating Report l

To meet the requirements of Wolf Creek Technical Specification

6. 9.1. 6, the Annual Radiological Environmental Operating Report covering the previous year of operation shall be submitted to the NRC by May 1 of each year. The content of this report is described in Section 7.1.

5.4.2 Special Reports A special report shall be prepared and submitted to the NRC within 30 days if levels of radioactivity as a result of plant effluents detected in an environmental medium at a specified location exceed the reporting levels of Table 5-4 when averaged over any calendar quarter. The special report shall identify L the cause (s) for exceeding the limit (s) and define the j corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

• to a member of the public is less than the calendar year limits of Wolf Creek Technical '

Specification 6.8.4.e. When one or more of the radionuclides in Table 5-4 is detected in the sampling medium, this report shall be submitted if:

Concentration (1) + Concentration (2) +. 21.0 Reporting Level (1) Reporting Level (2)

When radionuclides other than those in Table 5-4 are detected )

and are the result of plant effluents, this report shall be l submitted if the potential annual dose

• to a member of the public from all radionuclides is equal to or greater than the calendar year limits of Technical Specification 6.8.4.e.

• The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report. 5/96 l

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OFFSITE DOSE CALCULATION MANUAL TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING' PROGRAM Exposure Pathway / Number of Samples and Sample Collection ' Type and Frequency Sample Type Sample Locations (1) Frequency . of Analysis

1. AIRBORNE FIGURES 5.1 & 5.5 Radiciodine and Samples from five locations Continuous sampler . Analyze radioiodine Particulates operation with canister weekly for sample collection I-131 weekly, or more fre-quently if required' by dust loading Samples from locations near the site boundary-in three sectors having the highest calculated annual average D/Q (Locations 2, 3& 37 on Figure 5.1);

Sample from the vicinity of Analyze particulate a community having the falter weekly for highest calculated annual gross beta activity average D/Q (Location 32 on (2); perform quar-Figure 5.1, New Strawn); terly gamma isotopic analysis (3)compo-site (by location).

Sample from a control location 10-20 miles dis-tant in a low D/O sector (Location 40 on Figure 5.5). (11)

2. DIRECT FIGURES 5.2 AND'5.5 RADIATION (4) 40 routine monitoring sta- Quarterly . Gamma dose quarterly tions rith two or more dosimeters measuring-dose continuously, placed as follows:

An inner ring of stations,

.one in each meteorological sector 0-3 mile range from the site (Locations 1,7-9, 11-13, 18, 26, 27, 29-31, 37, 38 & 47 on Figure.5.2). 7/97 l

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ATTACHMENT A (Page 73 of 184)

OFFSITE DOSE CALCULATION MANUAL TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway / Number of Samples and Sample Collection Type and Frequency of Sample Type Sample Locations (1) Frequency Analysis DIRECT RADIATION An outer ring of stations, (4) (CONTINUED) one in each meteorological sector in the 3 to 5 mile range from the site (Loca-tions 4-6, 15-17, 19-25, and 33-36 on Figure 5.2).

Five sectors (A,D,D,G & L]

contain an addit'onal sta-tion (Locations 2,3.10, 14 and 28)

The balance of the stations to be placed in special interest areas such as population centers (Loca-tions 23 and 32), nearby residences (many locations are near a residence),

schools (Location 23), and in one or two areas to serve as control stations 10-20 miles distant from the site (Locations 39 and 40 on Figure 5.5) (11) 6/97

3. WATERBORNE FIGURE 5.3 Surface One sample upstream (5) Monthly grab sample Monthly gamma iso-(Location MUSH on Figure topic analysis (3) 5.3) and one sample down- and composite for stream (Location DC on tritium analysis Figure 5.3) quarterly.

Ground Samples from one or two Quarterly grab Quarterly gamma sources only if likely to sample isotopic analysis (3) be affected and tritium analysis.

6/97 Indicator samples at loca-tions hydrologically down-gradient of the site (Loca-tions C-10, C-49 and D-65 on Figure 5.3); control sample at a location hydro-logically upgradient of tne site (Location B-12 on Figure 5.3) (6) l l

f' l

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OFFSITE DOSE CALCULATION MANUAL l TABLE 5 (Continued) l- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l l

l Exposure Pathway / Number of Samples and Sample Collection Type and Frequency

! Sample Type. Sample Locations'(1) Frequency of Analysis

l 3. WATERBORNE Sample of municipal water Monthly' composite Monthly gamma iso-i (CONT.) supply at'an indicator (7) topic analysis (3)

(. Drinking location downstream of the and gross _ beta site (Location LW-40 on analysis of compo-Figure 5.5); control sample site sample, from location upstream of Quarterly tritium the site (Location BW-15 on analysis of Figure 5.3) composites (8).

! Shoreline Sediment- One sample from the vic- Semiannually Semiannual gamma

[ inity of Wolf Creek Cooling isotopic analysis (3)

Lake discharge cove (Loca-tion DC on Figure 5.3);

control sample from John Redmond Reservoir.

4. INGESTION FIGURES 5.4 AND 5.5 l Milk Samples from milking Semimonthly April to Gamma isotopic animals at three indicator November; monthly analysis (3) and I-

! locations within 5 miles of December-March (9) 131-analysis of each the site having the highest sample. 7/97

. dose potential (currently there are no locations pro-ducing milk for human con-sumption within 5 miles of the site);one sample from a control location greater than 10 miles from the site if indicator locations are I sampled. (11) 6/97

, Fish Indicator samples of 1 to 3 Semiannually Gamma isotopic l'- recreationally important analysis (3) on l species from Wolf Creek edible portions Cooling Lake (several samp-

. ling areas indicated in l Figure 5.4); control sam-ples of similar species from John Redmond Reservoir

!- Spillway (indicated on l Figure 5.4).

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OFFSITE DOSE CALCULATION MANUAL TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway / Number of Samples and Sample Collection Type and Frequency Sample Type Sample Locations (1) Frequency of Analysis

4. INGETTION Samples of available Monthly when Gamma isotopic (CONT.) broadleaf vegetation from available (9) analysis (3) on Food Products two indicator locations edible portions.

with highest calculated annual average D/Q (Loca-tions G-1 and F-1 and alternate Location E-1 on Flaure 5.4); sample of similar broadleaf vegeta-  ;

tion from a control loca- i tion greater than 10 miles from the site in a low D/O section (Location S-4 on 2/98 Figure 5.5) . (11)

Food Products Sample of crops irrigated At time of harvest Gamma isotopic wi.h water from the Neosho (10) analysis (3) on River downstream of the edible portions Neosho River-Wolf Creek confluence (locations will vary from year to year, e.g., Location NR-D1 & NR-D2 on rigure 5.5).

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OFFSITE DOSE CALCULATION. MANUAL TABLE 5-1 (Continued)- ')

TABLE NOTATIONS Deviations'are permitted from the required sampling schedule if I (1) j specimens are unobtainable due to hazardous conditions, seasonal j unavailability, malfunction of automatic sampling equipment, and other d legitimate reasons. If specimens are unobtainable due to sampling i equipruent malfunction, every effort shall be made to complete-l corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in.the q Annual Radiological Environmental Operating Report described in j section 7.1.

]

L It_is recognized.that, at times, it may not be possible or practicable to continue to obtain samples of the media'of choice at the most.

desired location or time. In these instances, suitable' specific alternative media and locations may be' chosen for the particular pathway in question and appropriate substitutions made'within 30 days.

l Revisions to this Table and to the' corresponding Figure (s) as a result of such substitutions shall be documented in accordance with Section 6.14 of Wolf Creek' Technical Specifications. This documentation shall provide information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new l location (s) for obtaining samples.

(2) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for Rn-220 and Rn-222 daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, L gamma isotopic analysis shall be performed on the individual samples.

(3) Gamma isotopic analysis means the identification and quantification of g gamma-emitting radionuclides that may be attributable to the effluents l from the facility.

(4) -one or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may used in place of, or in addition to, integrating dosimeters. -For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be  ;

one phosphor; two or more phosphors in a packet are considered as two i or more dosimeters. Film badges shall not be used as dosimeters for l measuring direct radiation. The 40 stations are not an absolute L number. The number of direct radiation monitoring stations may be reduced according to geographical limitations, e.g., some sectors are 1 over water so that the number of dosimeters may be reduced i accordingly. The frequency or analysis or readout for the TLD system l depends upon the characteristics of the specific system used and is selected to obtain optimum dose information with minimal fading. 5/96 l

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OFFSITE DOSE CALCULATION MANUAL TABLE 5-1 (Continued)

TABLE NOTATIONS (5) The " upstream" sample is taken at a distance beyond significant influence of the discharge.

1 (6) Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(7) A composite sample is one in which the quantity (aliquot) of liquid lW sampled is consistent over the sampling period and in which the method of sampling employed results in a specimen that is representative of l the liquid concentrate. In this program, composite sample aliquots shall be collected at time intervals that are very short (e.g., every i two hours) relative to the compositing period (e.g. , monthly) in order to assure obtaining a representative sample. 5/96 l

(8) If the dose calculated for consumption of water (using ODCM l methodology and parameters) exceeds one millirem per year, composite l sampling at the indicator location shall be performed every two weeks {

and I-131 analysis shall be performed on the composite samples. j (9) Milk and broadleaf vegetation samples are often temporarily, but not  !

permanently, unavailable at the scheduled sample collection times.  !

Alternate sampling locations may therefore be listed in the Table and used at these times to provide continued monitoring of these pathways. , '

If samples are considered permanently unavailable at a location, another location will be selected (if available) as described in Note (1).

(10) If harvest occurs more than once a year, sampling shall be performed I during each discrete harvest. If harvest occurs continuously, j sampling shall be monthly. Attention shall be paid to including  !

samples of tuberous and root food products.  !

(11) The purpose of this sample is to obtain background information. If it j is not practical to establish control locations in accordance with the j distance and wind direction criteria, other sites that provide valid j background data may be substituted.

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Number pirection 2 2.7/N 3 3.0/NNE 32 3.2/WNW 37 2.1/NNW 40 >15.0/WNW 6/97 TLD Location Distance / Location Distance / Location Distance / Location Distance /

Number Direction Number Direction Number Direction Number Direction 1 1.4/N 11 1.6/E 21 3.8/S 31 3.0/WNW i 2 2.7/N 12 1.8/ESE 22 4.1/SSW 32 3.2/WNW l 3 3.0/NNE 13 1.5/SE 23 4.5/SW 33 3.7/WNW ]

2.6/SE 4 4.0/NNE 14 24 4.1/WSW 34 4.0/NW S 4.0/NE 15 4.5/ESE 25 3.6/W 35 4.6/NNW 6 4.4/ENE 16 4.2/E 26 2.6/WSW 36 4.2/N 7 1.9/NE 17 3.6/SE 27 2.1/SW 37 2.1/NNW 8 1.6/NNE 18 3.0/SSE 28 2.8/SW 38 1.2/NW l 6/97 j 9 2.0/ENE 19 4.0/SSE 29 2.6/SSW 39 13.0/N i 10 2.4/ENE 20 3.3/S 30 2.2/W 40 >15.0/WNW q 47 .16/S 7/97 Groundwater Drinking Water Surface Water B-12 2.2/NNE BW-15 3.9/SW MUSH 3.6/W C-10 2.8/W LW-40 >10/SSE DC 0.6/WNW C-49 2.9/SW D-65 3.9/S l Milk & Food Products ~

F-1 1.8/ESE G-1 1.6/SE S-4 >15.0/WNW 6/97 E-1 1.8/E 1/98 Fish Shoreline Sediments Irrigated Crops WCCL DC 0.6/WNW NR-D1 9.2/S l JRR 4/W JRR 4/W NR-D2 >10/S '

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OFFSITE DOSE CALCULATION MANUAL ,

TABLE 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (n (2,3)

Lower Limit of Detection (LLD)

AIRBORNE SEDIMENT PARTICULATE FOOD (pCi/kg, WATER OR GAS FISH MILK PRODUCTS dry)

ANALYSIS (pCi/1) (pCi/m )

3 (pCi/kg, wet) (pCi/l) (pCi/kg, wet)

Gross 4 0.01 Beta H-3 2000(4)

Mn-54 15 130 Fe-59 30 260 )

Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 l

)

I-131 1(5) 0.07 1 60 i

Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 l l

Ba-La-140 15 15 l i

l i

l i

'I l

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OFFSITE DOSE CALCULATION MANUAL I l TABLE 5-3 (Continued)

TABLE NOTATIONS l

(1) This list does not mean that only these nuclides are to be considered. l l

Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual l Radiological Environmental Operating Report described in Section'7.1.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13, Revision 1, 1977.

(3) The LLD is defined, as the smallest concentration of radioactive l i

material in a sample that will yield a net count, above system )

background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents l a "real" signal.

For a particular measurement system, which may include radiochemical j separation:

l l

LLD = b E V 2.22 Y exp (-2 At)

Where:

LLD = the "a priori" lower limit of detection (picoCurles per unit mass or volume),

{

Sb

= the standard deviation of the background counting l rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular l radionuclide (s-1), and l l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 85 of 188 ATTACHMENT A (Page 81 of 184)

OFFSITE DOSE CALCULATION MANUAL TABLE 5-3 (Continued)

TABLE NOTATIONS At =

the elapsed time between sample collection, or end of the sample collection period, and time of counting (s).

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (af ter the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological 1 Environmental Operating. Report described in Section 7.1.

(4) LLD for drinking water samples. If no drinking water pathway exists, I a value of 3000 pCi/ liter may be used.

(5) LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

i

Revision:~'l .OFFSITE DOSE CALCULATION MANUAL AP.07B-003 Reference Use Page-86 of 188 ATTACHMENT-A .

-(Page-.82 of 184) 'l OFFSITE DOSE CALCULATION MANUAL' TABLE 5 REPORTING LEVELS FOR RADIOACTIVITY. CONCENTRATIONS.IN ENVIRONMENTAL SAMPLES.

AIRBORNE FOOD WATER PARTICULATE OR FISH MILK' PRODUCTS' ANALYSIS (pCi/1) GAS (pCi/m 3) -(pCi/kg, wet) (pCi/1) (pCi / kg,' wet) .

H-3 '20,000*

Mn-54' 1,000 30,000 l

Fe-59 400' 10,000 Co 1,C00 30,000 Co-60 300 10,000 Zn-65 300 20,000 I

Zr-Nb-95' 400 7I-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 l

Cs-137 50 20 2,000 70 2,000 l l

Ba-La-140 200 '300 l

• For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/1 may be used.

II n

j Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 87 of 188 ATTACHMENT A (Page 83 of 184)

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I l Revision: 1 -OFFSITE DOSE CALCULATION MANUAL AP 07B-003 i

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Revision: 'l OFFSITE DOSE CALCULATION MANUAL AP 07B-003 I. Reference Use Page 89 of 188 I

ATTACHMENT A-(Page 85 of 184)

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1 Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 90 of 188 ATTACHMENT A (Page 86 of 184)

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Revision:,11 OFFSITE DOSE. CALCULATION MANUAL AP 078-003 Reference Use Page 91 of 188 I

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l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 92 of 188 l l ATTACHMENT A (Page 88 of 184) OFFSITE DOSE CALCULATION MANUAL 6.0 Bases l l The bases contained on the succeeding pages summarizes the general requirements of Section 2.0, 3.0, 4.0 and 5.0 of the ! ODCM. l l Section 2.0 Liquid Effluents Section 2.1 Concentration l l This section is provided to ensure that the concentration of l radioactive materials released in liquid waste effluents to j UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II. A design. l objective of Appendix I, 10 CFR Part 50, to a MEMBER OF THE [ PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to'the l population. The concentration limit for dissolved or entrained noble gases are based upon the assumption that Xe-135 is the controlling radioisotope and.its MPC in air (submersion) was i . converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. ! The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits l- of detection (LLDs). Detailed discussion of the LLD, and other !~ detection limits can be found in HASL Procedures Manual, HASL-l 300 (revised annually), Currie, L.A., " Limits for Qualitative l Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques,

          " Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

L I l , l 1 l l l l l 4 l L  !

[- ~

                                                                                 .]

Revision: .1-

                             =OFFSITE DOSE CALCULATION MANUAL        AP 07B-003, Reference ~Use                                                                I Page 93 of 188   i I

ATTACHMENT A (Page 89 of 184) 1 OFFSITE DOSE CALCULATION MANUAL' I l section 2.2 Dose

                                                                                 ]i This-section is provided to implement the. requirements of-          )

Section II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The i remedial action implements the guides set forth in Section II.A ! of Appendix I and provides the required operating flexibility l' and at the same time implement the guides set forth in-Section j IV.A of Appendix I to assure that.the releases of radioactive  ? material in. liquid effluents to UNRESTRICTED AREAS will be kept .

             "as' low as is reasonably achievable." Also, for-fresh. water
                                                                                  ]

sites with drinking water supplies that can be-potentially ) affected by plant operations, there is reasonable assurance that the operation'of the facility will not result in radi'onuclide- f concentrations in the finished drinking water that are11n excess of the requirements of 40 CFR Part 141. .The' dose calculation methodology and parameters th the ODCM !.mplement'the requirements in Section II?.A of Appendix I which specify that conformance with the guides of Appendix I be shown.by. j

            . calculational procedures based on models and data, such that.the
            -actual-exposure-of a MEMBER OF THE PUBLIC through appropriat'e pathways'is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating.the doses due to the actual' release rates of radioactive materials in' liquid i

effluents are consistent with the methodology provided'in-L Regulatory Guide 1.109, " Calculation'of Annual Doses to.' Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating-Compliance with 10 CFR Part 50, Appendix I, " Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April f.- 1977. i 1 l l [ I [ L

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 94 of 188 ATTACHMENT A I

                              .(Page 90 of 184)

OFFSITE DOSE CALCULATION MANUAL Section 2.,3 Liquid Radwaste Treatment System i The OPERABILITY of the Liquid Radwaste Treatment Systems ensures ! that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achieveable." This section implements the I requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section II.D of Appendix I to 10 CFP Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction

of the dose design objective set forth in Section II.A of l Appendix I, 10 CFR Part 50, for liquid effluents.

Section 2.4 Radioactive Liquid Effluent Monitoring Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive i l materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that  ! the alarm / trip will occur prior to exceeding the limits of 10 1 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, l 63, and 64 of Appendix'A to 10 CFR Part 50. l

1

                -                                                          j Revision: 1             OFFSITE DOSE CALCULATION MANUAL        AP 078-003   '

Reference Use Page 95 of 188 ATTACHMENT A (Page 91 of 184) j OFFSITE DOSE CALCULATION MANUAL ) Section 3.0 Gaseous Effluents Section 3.1 Dose Rate This section is provided to ensure that the dose at any time at and beyond the SITE. BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are-the doses associated with the concentrations of 10 CFR Part 20, 4 Appendix B, Table II, Column 1. These. limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a. MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the-limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE , BOUNDARY to less than or equal to 500 mrems/ year to the whole i body or to less than or equal to 3000 mrems/ year to the skin. These release rate limits also restrict, at all times the corresponding thyroid dose rate above background to a child via' { the inhalation pathway to less than or equal to 1500 mrems/ year. The required detection capabilities for radioactive materials in gaseous wasto samples are tabulated in terms of.the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., ." Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem 40~, 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report

      .ARH SA-215 (June 1975).

1 Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 96 of 188 l I ATTACHMENT A (Page 92 of 184) , OFFSITE DOSE CALCULATION MANUAL  ! l Section 3.2.1 Dose - Noble Gases  ! This section is provided to implement the requirements of q Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The  ! remedial action implements the guides set forth in Section II.B of Appendix I and provides the required operating flexibility j and at the same time implement the guides set forth in Section ] IV.A of Appendix I to assure that the releases of radioactive i material in gaseous effluents to UNRESTRICTED AREAS will be kept i "as low as is reasonably achievable." The surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through 1 appropriate pathways is unlikely to be substantially j underestimated. The dose calculation methodology and parameters i established in the ODCM for calculating the doses due to the l actual release rates of radioactive materials in gaseous i effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of-Annual Doses to Man from l i Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are I based upon either the historical average or real time atmospheric conditions. l

I Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 97 of 188 l ATTACHMENT A (Page-93 of 184)' OFFSITE DOSE CALCULATION MANUAL Section 3.2.2 Dose - Iodine-131 and 133, Tritium and Radioactive Material in Particulate Form This section is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The remedial actions are the guides set forth in Section II.C'of Appendix I, and' provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject i materials are consistent with the methodology provided in i Regulatoly Guide 1.109, " Calculational of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon either the historical average or real time conditions. The release rate limits for Iodine-131 and 133, tritium, and radionuclides in particulate form with half lives greater that 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, (4) deposition on the ground with subsequent exposure of man. I l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 3 Reference Use Page 98 of 188 ATTACHMENT A

                            .(Page 94 of 184)

OFFSITE DOSE CALCULATION MANUAL l Section 3.3 Gaseous Radwaste Treatment System' ] The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems I will be available for.use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This section implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design l objectives set forth in_Section II.B and II.C of Appendix I, 10 I CFR Part 50, for gaseous effluents. Section 3.4 Radioactive Gaseous Effluent Monitoritjg Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be adjusted to talues calculated in accordance with the methodology and parameters in the ODCM to , ensure that the alarm / trip will occur prior to exceeding the l limits of 10 CFR Part 20. The OPERABILITY and use of this  ! instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of Section 3.2 shall be such that concentrations as low as 1 x 10-6 pCi/cc are measurable.

I l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l l Reference Use Page 99 of 188 i ' 1 i ! ATTACHMENT A l

                                                                          ~

(Page 95 of 184) OFFSITE DOSE CALCULATION MANUAL i Section 4.0 Total Dose I This section is provided to meet the dose limitations of 40 CFR j Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The section requires the preparation and submittal of a special report whenever the calculated doses due to releases l of radioactivity and the radiation from uranium fuel cycle  ! sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor Units and from outside storage tanks are kept small. The Special Report will describe a course of actior that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special R' port, it may be assumed that the dose commitment to the MEMBEF OF THE PUBLIC from other uranium fuel cycle sources is negligiole, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 a..d 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 1 i

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 100 of 188 i ATTACHMENT A (Page 96 of 184) OFFSITE DOSE CALCULATION MANUAL Section 5.0 Radiological Environmental Monitoring Program Section 5.1 Monitoring Program ) The Radiological Environmental Monitoring Program provides representative measurements of radiation and of radioactive materials in those exposure pathways and-for those radionuclides } that lead to the highest potential radiation exposures of J MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological l Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation j are not higher than expected.on the basis of the effluent measurements and the modeling of the environmental-exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability-of a measurement _ system and not as an a posteriori (after the fact) limit for a particular measurement. Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination-Application to Radiochemistry,' Anal. Chem. 40, l 586-93 (1968), and Hartwell, J.K., " Detection Limits for l l Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). I I i

f Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 101 of 188 ATTACHMENT A (Page 97 of 184) OFFSITE DOSE. CALCULATION MANUAL l l Section 5.2 Land Use Census l This section is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified andEthat modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. Information that will provide the best results, such as door-to-door survey, aerial survey, or consulting with local agricultural authorities, shall be used. This census satisfies the requirements of Section IV.B.3 of-Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assume in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broadleaf vegetation (i.e., similar to lettuce and cabbage),-and (2) a vegetation yield of 2 kg/m 2, Section 5.3 Interlaboratory Comparison Program I The requirement for participation in an approved Interlaboratory I Comparison Program is provided,to ensure that' independent checks l on the precision and accuracy of the measurements of radioactive j material in environmental sample matrices are performed as part l of the quality assurance program for environmental monitoring in 1 order to demonstrate that the results are valid for the purposes i of Section IV.B.2 of Appendix I to 10 CFR Part 50. l

I' ) Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 102 of 188 ATTACHMENT A l (Page 98 of 184) < OFFSITE DOSE CALCULATION MANUAL l i I j 7.0 Reports 7.1 Annual Radiological Environmental Operating Report l i The Annual Radiological Environmental Operating Report shall i L include summaries, interpretations, and an analysis of trends of l the results of the radiological environmental surveillance l activities for the report period, including a comparison with j preoperational studies, with operational controls and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census described in Section 5.2. The Annual Radiological Environmental Operating Report shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in Table 5-1 as well as summarized and tabulated results cf these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The report shall also include the following: a summary description of the Radiological Environmental Monitoring l Program; legible maps covering all sampling locations keyed to a l table giving distances and directions from the centerline of the reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed. as required by Section 5.3; reasons for not conducting the Radiological Environmental Program as required by Section 5.1 with plans for preventing a recurrence and discussion of all deviations from the sampling schedule of Table 5-1; discusaion of environmental sample measurements that exceed the reporting levels of Table 5-4 but are not the result of plant effluents, and discussions of all analyses in which the LLD required by Table 5-3 was not achieved. 5/96 l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL- AP 07B-003 Reference Use Page 103 of 188 ATTACHMENT A (Page 99 of 184) OFFSITE DOSE CALCULATION MANUAL l l 7.2 Annual Radioactive Effluent Release Report The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the Unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting hadioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants," Revision 1, June'1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class , of solid waste (as defined by 10 CFR Part 60), type of container l (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION l agent or absorbent (e.g., cement, urea formaldehyde). The Annual Radioactive Effluent Release Report to be submitted ( before May 1 of each year shall also include an annual summary of hourly meteorological data collected over the previous year. L This annual summary may be either in the form of an hour-by-hour L listing on magnetic tape of wind speed, wind direction, and L atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind Crection, and atmospheric stability.* This same report shall ) include an assessment of the radiation doses due to the _ radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This same report i shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE 3 I PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. Historical average meteorological conditions or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the

       . gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM.

l

l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 I Reference Use Page 104 of 188 l 1 l ATTACHMENT A l (Page 100 of 184) l OFFSITE DOSE CALCULATION MANUAL The Annual Radioactive Effluent Release Report to be submitted before May 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977. The Annual Radioactive Effluent Release Report shall include:

a. A list and description of unplanned releases from the j site to UNRESTRICTED AREAS of radioactive materials in l gaseous and liquid effluents made during the reporting  ;

period.

      *In lieu of submission with the Annual Radioactive Effluent        l Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

b. Any changes made during the reporting period to the ODCM, pursuant to Technical Specification 6.14.

c. Major changes to the Radwaste Treatment Systems for the period in which the evaluation was reviewed and accepted by the PSRC. The discussion of each change shall contain:

1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information;

3) A detailed description of the equipment,  !

components, anc processes involved and the interfaces with other plant systems. l

f Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 105 of 188 l ATTACHMENT A (Page 101 of 184) OFFSITE DOSE CALCULATION MANUAL

4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;

6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

7) An estimate of the exposure to plant operating personnel as a result of the change; and

8) Documentation of the fact that the change was reviewed and found acceptable by the PSRC.  !

d. A listing of new locations for dose calculations identified by the Land Use Census, I

e. A description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of USAR 16.11.1.1 OR 16.11.3.1. 2/98

f. An explanation as to why the inoperability of a liquid l or gaseous effluent monitoring instrumentation was not corrected within the time specified.

g. A description of the events leading to a missed sample required by Table 2-1 or 3-1.

I 1 J l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 106 of 188 ATTACHMENT A (Page 102 of 184) OFFSITE DOSE CALCULATION MANUAL l l l APPENDIX A Dose Conversion Factor Tables l

i l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l Reference Use Page 107 of 188 ATTACHMENT A  ! (Page 103 of 184) I OFFSITE DOSE CALCULATION MANUAL l TABLE A.1-l* BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIED DATA (pCi/kg per pCi/ liter) ELEMENT FRESHWATER FISH H 9.0E-01 C 4.6E 03 Na 1.0E 02 1 P 1.0E 05 Cr 2.0E 02 Mn 4.0E 02 Fe 1.0E 02 Co 5.0E 01 1 l Ni 1.0E 02 Cu 5.0E 01 Zn 2.0E 03 l Br 4.2E 02 l Rb 2.0E 03 Sr 3.0E 01 Y 2.5E 01 Zr 3.3E 00 Nb 3.0E 04 l Mo 1.0E 01 Tc 1.5E 01 Ru 1.0E 01 Rh 1.0E 01 Te 4.0E 02 I 1.5E 01 Cs 2.0E 03 Ba 4.0E 00 La 2.5E 01 Ce 1.0E 00 Pr 2.5E 01 Nd 2.5E 01 W 1.2E 03 Np 1.0E 01

                               **Ag                   2.3E 00
                               **Sb                   1.0E 00

• Taken from Regulatory Guide 1.109 (Rev.1)

         ** Taken from Regulatory Guide 1.109 (Rev.0) l l

l l l _ . . -

1 l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 j Reference Use Page 108 of 188 I l ATTACHMENT A (Page 104 of 184) OFFSITE DOSE CALCULATION MANUAL I TABLE A.1-2 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS

• Radionuclide Total Body Skin Dose Factor Gamma Air Beta Air Dose Factor h Dose Factor Dose Factor ;

Ki (mrem /yr per Mi Ni I (mrem Iyr per Ci/m 3) (mrad /yr per (mrad /yr I 3 3 pCi/m ) pCi/m 3) per pCi/m ) Kr-83M 7.56E-02** --- 1.93E+01 2.88E+02 Kr-85M 1.17E+03 1.46E+03 1.23E+03 1.97E+03 l l Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131M 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133 2.94"ze. 3.06E+02 3.53E+02 1.05E+03 Xe-133M 2.51E+02 9.94E+02 3. 2F 602 1.48E+03 Xe-135M 3.12E+03 7.11E+02 3.36E+03 7.39E+02  ! i Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 l Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 I Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 l

• Based on Regulatory Guide 1.109 (Rev.1)

                                -2
  *

• 7. 5 6E-02 = 7. 5 6 x 10 I

{ I l

I Revisioni 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 1 Reference Use Page 109 of 188 l ATTACHMENT A (Page 105 of 184) ! OFFSITE DOSE CALCULATION MANUAL TABLE A.2-1* INHALATION DOSE FACTORS FOR ADULTS (MREM PER PCI INHALED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C 14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P 32 1.65E-04 9.64E-06 6.26E-06 NO DATA NO DATA NO DATA 1.08E-05 CR 51 NO DATA NO DATA 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN 54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 9.67E-06 MN 56 NO DATA 1.55E-10 2.29E-11 NO DATA 1.63E-10 1.18E-06 2.53E-06 FE 55 3.07E-06 2.12E-06 4.93E-07 NO DATA NO DATA 9.01E-06 7.54E-07 FE 59 1.47E-06 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 58 NO DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1.16E-04 1.33E-05 CO 60 NO DATA 1.44E-06 1.85E-06 NO DATA NO DATA 7.46E-04 3.56E-05 NI 63 5.40E-05 3.93E-06 1.81E-06 NO DATA NO DATA 2.23E-05 1.67E-06 j NI 65 1.92E-10 2.62E-11 1.14E-11 NO DATA NO DATA 7.00E-07 1.54E-06 CU 64 NO DATA 1.83E-10 7.69E-11 NO DATA 5.78E-10 8.48E-07 6.12E-06 ZN 65 4.05E-06 1.29E-05 5.82E-06 NO DATA 8.62E-06 1.08E-04 6.68E-06 ZN 69 4.23E-12 8.14E-12 5.65E-13 NO DATA 5.27E-12 1.15E-07 2.04E-09  ! BR 83 NO DATA NO DATA 3.01E-08 NO DATA NO DATA NO DATA 2.90E-08 i BR 84 NO DATA NO DATA 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 BR 85 NO DATA NO DATA 1.60E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.69E-05 7.37E-06 NO DATA NO DATA NO DATA 2.08E-06 J RB 88 NO DATA 4.84E-08 2.41E-08 NO DATA NO DATA NO DATA 4.18E-19 j RB 89 NO DATA 3.20E-08 2.12E-08 NO DATA NO DATA NO DATA 1.16E-21 SR 89 3.00E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 SR 90 1.24E-02 NO DATA 7.62E-04 NO DATA NO DATA 1.20E-03 9.02E-05 1 SR 91 7.74E-09 NO DATA 3.13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E-10 NO DATA 3.64E-11 NO DATA NO DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 NO DATA 7.01E-09 NO DATA NO DATA 2.12E-05 6.32E-05 Y 91M 3.26E-11 NO DATA 1.27E-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y 91 5.78E-05 NO DATA 1.55E-06 NO DATA NO DATA 2.13E-04 4.81E-05 Y 92 1.29E-09 NO DATA 3.77E-11 NO DATA NO DATA 1.96E-06 9.19E-06 Y 93 1.18E-08 NO DATA 3.26E-10 NO DATA NO DATA 6.06E-06 5.27E-05 ZR 95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E-04 1.8SE-05 ZR 97 1.21E-08 2.45E-09 1.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 NB 95 1.76E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 MO 99 NO DATA 1.51E-08 2.8..-09 NO DATA 3.64E-08 1.14E-05 3.10E-05 TC 99M 1.29E-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07 ! *Taken from Regulatory Guide 1.109 (Rev. 1)

                                                                                                 )

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 110 of 188 ATTACHMENT A (Page 106 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A. 2-1* (cont' d) INHALATION DOSE FACTORS FOR ADULTS (MREM PER PCI INHALED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 5.22E-15 7.52E-15 7.38E-14 NO DATA 1.35E-13 4.99E-08 1.36E-21 RU 103 1.91E-07 NO DATA 8.23E-08 NO DATA 7.29E-07 6.31E-05 1.38E-05 RU 105 9.88E-11 NO DATA 3.89E-11 NO DATA 1.27E-10 1.37E-06 6.02E-06 RU 106 8.64E-06 NO DATA 1.09E-06 NO DATA 1.67E-05 1.17E-03 1.14E-04 l AG 110M 1.35E-06 1.25E-06 7.43E-07 NO DATA 2.46E-06 5.79E-04 3.78E-05 l TE 125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 ' TE 127M 1.58E-06 7.21E-07 1.96E-07 4.11E-01 5.72E-06 1.20E-04 1.87E-05 TE 127 1.75E-10 0.0]E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE 129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 , I TE 129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 l TE 131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 l TE 131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 l l TE 132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I I 130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 NO DATA 9.61E-07 I 131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 I 132 1.45E-07 4.07L-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08E-08 I 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11E-06 I I 134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 NO DATA 1.26E-10 ) i I 135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 NO DATA 6.56E-07  ! CS 134 4.66E-05 1.06E-04 9.10E-05 NO DATA 3.59E-05 1.22E-05 1.30E-06 l CS 136 4.88E-06 1.83E-05 1.38E-05 NO DATA 1.07E-05 1.50E-06 1.46E-06 - CS 137 5.98E-05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1.05E-06 CS 138 4.14E-08 7.76E-08 4.05E-08 NO DATA 6.00E-08 6.07E-09 2.33E-13 - BA 139 1.17E-10 8.32E-14 3.42E-12 NO DATA 7.78E-14 4.70E-07 1.12E-07  ! 1 BA 140 4.88E-06 6.13E-09 3.21E-07 NO DATA 2.09E-09 1.59E-04 2.73E-05 BA 141 1.25E-11 9.41E-15 4.20E-13 NO DATA 8.75E-15 2.42E-07 1.45E-17 4 BA 142 3.29E-12 3.38E-15 2.07E-13 NO DATA 2.86E-15 1.49E-07 1.96E-26 LA 140 4.30E-08 2.17E-08 5.73E-09 NO DATA NO DATA 1.70E-05 5.73E-05 LA 142 8.54E-11 3.88E-11 9.65E-12 NO DATA NO DATA 7.91E-07 2.64E-07  ! CE 141 2.49E-06 1.69E-06 1.91E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05  ; CE 143 2.33E-08 1.72E-08 1.91E-09 NO DATA 7.60E-09 9.97E-06 2.83E-05 CE 144 4.29E-04 1.79E-04 2.30E-05 NO DATA 1.06E-04 9.72E-04 1.02E-04 PR 143 1.17E-06 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51E-05 2.50E-05 PR 144 3.16E-12 1.56E-12 1.91E-13 NO DATA 8.81E-13 1.27E-07 2.69E-18 ND 147 6.59E-07 7.62E-07 4.56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 W 187 1.06E-09 8.85E-10 3.10E-10 NO DATA NO DATA 3.63E-06 1.94E-05 NP 239 2.87E-08 2.82E-09 1.55E-09 NO DATA 8.75E-09 4.70E-06 1.49E-05 l

l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 111 of 188 ATTACHMENT A (Page 107 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.2-2* INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C 14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 NA 24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P 32 2.36E-04 1.37E-05 8.95E-06 NO DATA NO DATA NO DATA 1.16E-05 CR 51 NO DATA NO DATA 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN 54 NO DATA 6.39E-06 1.05E-06 NO DATA 1.59E-06 2.48E-04 8.35E-06 MN 56 NO DATA 2.12E-10 3.15E-11 NO DATA 2.24E-10 1.90E-06 7.18E-06 FE 55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 FE 59 1.99E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 CO 58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 CO 60 NO DATA 1.89E-06 2.48E-06 NO DATA NO DATA 1.09E-03 3.24E-05 NI 63 7.25E-05 5.43E-06 2.47E-06 NO DATA NO DATA 3.84E-05 1.77E-06 NI 65 2.73E-10 3.66E-11 1.59E-11 NO DATA NO DATA 1.17E-06 4.59E-06 CU 64 NO DATA 2.54E-10 1.06E-10 NO DATA 8.01E-10 1.39E-06 7.68E-06 ZN 65 4.82E-06 1. 67 E- O', 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 ZN 69 6.04E-12 1.15E-11 8.07E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 BR 83 NO DATA NO DATA 4.30E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 5.41E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 2.29E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.38E-05 1.05E-05 NO DATA NO DATA NO DATA 2.21E-06 RB 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 RB 89 NO DATA 4.40E-08 2.91E-08 NO DATA NO DATA NO DATA 4.22E-17 SR 89 5.43E-05 NO DATA 1.56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 SR 90 1.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.56E-05 SR 91 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05 SR 92 1.19E-09 NO DATA 5.08E-11 NO DATA NO DATA 3.43E-06 1.49E-05 Y 90 3.73E-07 NO DATA 1.00E-08 NO DATA No DATA 3.66E-05 6.99E-05 Y 91M 4.63E-11 NO DATA 1.77E-12 NO DATA NO DATA 4.00E-07 3.77E-09 Y 91 8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5.11E-05 Y 92 1.84E-09 NO DATA 5.36E-11 NO DATA NO DATA 3.35E-06 2.06E-05 Y 93 1.69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.24E-05 ZR 95 1.82E-05 5.73E-06 3.94E-06 NO DATA 8.42E-06 3.36E-04 1.86E-05 ZR 97 1.72E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05 NB 95 2.32E-06 1.29E-06 7.08E-07 NO DATA 1.25E-06 9.39E-05 1.21E-05 MO 99 HO DATA 2.11E-08 4.03E-09 NO DATA 5.14E-08 1.92E-05 3.36E-05 TC 99M 1.73E-13 4.83E-13 6.24E-12 NO DATA 7.20E-12 1.44E-07 7.66E-07

             *Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference Use Page 112 of 188 ATTACHMENT A (Page 108 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.2-2* (cont' d) INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 RU 103 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 1.3*E-05 RU 105 1.40E-10 NO DATs 5.42E-11 NO DATA 1.76E-10 2.27E-06 1.13E-05 RU 106 1.23E-05 NO DA*A 1.55E-06 NO DATA 2.38E-05 2.01E-03 1.20E-04 AG 110M 1.73E-06 1.64E-06 9.99E-07 NO DATA 3.13E-06 8.44E-04 3.41E-05 TE 125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 NO DATA 6.70E-05 9.38E-06 TE 127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE 127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 TE 129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE 129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE 131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE 131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE 132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I 130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-07 I 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1.59E-07 I 133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.29E-06 I 134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09 I 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 CS 134 6.20E-05 1.41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 CS 136 6.44E-06 2.42E-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 CS 137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51E-05 1.06E-06 CS 138 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.28E-08 9.84E-09 3.38E-11 BA 139 1.67E-10 1.18E-13 4.87E-12 NO DATA 1.11E-13 8.08E-07 0.06E-07 BA 140 6.84E-06 8.38E-09 4.40C-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 BA 141 1.78E-11 1.32E-14 5.93E-13 NO D^.TA '.23E-14 4.11E-07 9.33E-14 BA 142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 LA 140 5.99E-08 2.95E-08 7.82E-09 NO DATA NO DATA 2.68E-05 6.09E-05 LA 142 1.20E-10 5.31E-11 1.32E-11 NO DATA NO DATA 1.27E-06 1.50E-06 CE 141 3.55E-06 2.37E-06 2.71E-07 NO DATA 1.11E-06 7.67E-05 1.58E-05 CE 143 3.32E-08 2.42E-08 2.70E-09 NO DATA 1.08E-08 1.63E-05 3.19E-05 CE 144 6.11E-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04 PR 143 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PR 144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 ND 147 9.83E-07 1.07E-06 6.41E-08 NO DATA 6.28E-07 4.65E-05 2.28E-05 W 187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21E-05 NP 239 4.23E-08 3.99E-09 2.21E-09 NO DATA 1.25E-08 8.11E-06 1.65E-05

l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 j Reference Use Page 113 of 188 ATTACHMENT A (Page 109 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.2-3* INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 ) C 14 9.70E-06 1.02E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 ' NA 24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P 32 7.04E-04 3.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA NO DATA 4.17E-00 2.31E-08 6.57E-09 4.59E-06 2.93E-07 MN 54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06 MN 56 NO DATA 4.48E-10 8.43E-11 NO DATA 4.52E-10 3.55E-06 3.33E-05 FE 55 1.28E-05 6.80E-06 2,10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 FE 59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 CO 58 NO DATA 4.79E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 1.71E-06 NI 65 0.08E-10 7.99E-11 4.44E-11 NO DATA NO DATA 2.21E-06 2.27E-05 CU 64 NO DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 ZN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 ZN 69 1.81E-11 2.61E-11 2.41E-12 NO DATA 1.58E-11 3.84E-07 2.75E-06 BR 83 NO DATA NO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E-24 j RB 86 NO DATA 5.36E-05 3.09E-05 NO DATA NO DATA NO DATA 2.16E-06 ' RB 88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09

- RB     89   NO DATA   9.33E-08    7.83E-08     NO DATA     NO DATA  NO DATA   5.11E-10 SR     89  1.62E-04    NO DATA    4.66E-06     NO DATA     NO DATA  5.03E-04  4.52E-05 SR     90  2.73E-02    NO DATA    1.74E-03     NO DATA     NO DATA' 3.99E-03  9.28E-05 SR     91  3.28E-08    NO DATA    1.24E-09     NO DATA     NO DATA  1.44E-05  4.70E-05 SR     92  3.54E-09    NO DATA    1.42E-10     NO DATA     NO DATA  6.49E-06  6.55E-05     j Y     90  1.11E-06    NO DATA    2.99E-08     NO DATA     NO DATA  7.07E-05  7.24E-05     2 Y    91M  1.37E-10    NO DATA    4.98E-12     NO DATA     NO DATA  7.60E-07  4.64E-07     !

I Y 91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-05 Y 92 5.50E-09 NO DATA 1.57E-10 NO DATA NO DATA 6.46E-06 6.46E-05 Y 93 5.04E-08 NO DATA 1.38E-09 NO DATA NO DATA 2.01E-05 1.05E-04 ZR 95 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.61E-05 6.03E-04 1.65E-05 ZR 97 5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05 NB 95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.00E-05 MO 99 NO DATA 4.66E-08 1.15E-08 NO DATA 1.06E-07 3.66E-05 3.42E-05 TC 99M 4.81E-13 9.41E-13 1.56E-11 NO DATA 1.37E-11 2.57E-07 1.30E-06 j

*Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 1 OFFSITE DOSE CALCULRTION MANUAL AP 07B-003 ) i Reference Use Page 114 of_188 ATTACHMENT A (Page 110 of 184) l OFFSITE DOSE CALCULATION MA11UAL i TABLE A.2-3* (cont' d) INHALATION DOSE FACTORS FOR CHTLD (MREM PER PCI INHALED) ) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.92E-13 1.58E-07 4.41E-09 1 RU 103 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 I RU 105 4.13E-10 NO DATA 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 RU 106 3.68E-05 NO DATA 4.57E-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 AG 110M 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74E-06 1.48E-03 2.71E-05 i TE 125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 TE 127M 6.72E-06 2.31E-06 0.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 l TE 127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 TE 129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 TE 129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 l TE 131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 0.32E-05 4 TE 131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 l l TE 132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 1.72E-05 i 1 130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06  ! I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.68E-07 I 132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07 I 133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 NO DATA 1.48E-06 I 134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 I 135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 NO DATA 1.20E-06 CS 134 1.76E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 i CS 136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 CS 137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 CS 138 1.71E-07 2.27E-07 1.50E-07 NO DATA 1.68E-07 1.84E-08 7.29E-08 BA 139 4.98E-10 2.66E-13 1.45E-11 NO DATA 2.33E-13 1.56E-06 1.56E-05 BA 140 2.00E-05 1.75E-08 1.17E-06 NO DATA 5.71E-09 4.71E-04 2.75E-05 BA 141 5.29E-11 2.95E-14 1.72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 BA 142 1.35E-11 9.73E-15 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 LA 140 1.74E-07 6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 LA 142 3.50E-10 1.11E-10 3.49E-11 NO DATA NO DATA 2.35E-06 2.05E-05 CE 141 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.31E-06 1.47E-04 1.53E-05 CE 143 9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 CE 144 1.83E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E-03 1.05E-04 PR 143 4.99E-06 1.50E-06 2.47E-07 NO DATA 8.11E-07 1.17E-04 2.63E-05 PR 144 1.61E-11 4.99E-12 8.10E-13 NO DATA 2.64E-12 4.23E-07 5.32E-08 ND 147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E-06 8.87E-05 2.22E-05 W 187 4.41E-09 2.61E-09 1.17E-09 NO DATA NO DATA 1.11E-05 2.46E-05 NP 239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1.73E-05 1/98 1 l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 115 of 188 f ATTACHMENT A (Page 111 of 184) , OFFSITE DOSE CALCULATION MANUAL TABLE A.2-4* fI INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED) l l NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI I H 3 NO DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 i NA 24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 j l P 32 1.45E-03 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 CR 51 NO DATA NO DATA 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 l MN 54 NO DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 7.14E-04 5.04E-06 MN 56 NO DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 5.12E-05 FE 55 1.41E-05 8.39E-06 2.38E-06 NO DATA NO DATA 6.21E-05 7.82E-07 FE 59 9.69E-06 1.68E-05 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 1 CO 58 NO DATA 8.71E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 f CO 60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 NI 63 2.42E-04 1.46E-05 0.29E-06 NO DATA NO DATA 1.49E-04 1.73E-06 NI 65 1.71E-09 2.03E-10 0.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 CU 64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05  ! ZN 65 1.38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E-05 ZN 69 3.85E-11 6.91E-11 5.13E-12 NO DATA 2.87E-11 1.05E-06 9.44E-06 J BR 83 NO DATA NO DATA 2.72E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 2.86E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.46E-08 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 RB 88 NO DATA 3.98E-07 2.05E-07 NO DATA NO DATA NO DATA 2.42E-07 j l RB 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 ' SR 89 2.84E-04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91 6.83E-08 NO DATA 2.47E-09 NO DATA NO DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1.70E-05 1.00E-04 Y 90 2.35E-06 NO DATA 6.30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 Y 91M 2.91E-10 NO DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.68E-06 Y 91 4.20E-04 NO DATA 1.12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05 Y 93 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 l ZR 95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 ZR 97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-Of 1.00E-04 NB 95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 MO 99 NO DATA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05 TC 99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06

  *Taken from Regulatory Guide 1.109 (Rev. 1)                                     1/98

I Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l Reference Use Page 116 of 188 ATTACHMENT A (Page 112 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.2-4* (cont' d) INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 4.65E-14 5.88E-14 5.80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07 RU 103 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05 RU 105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E-10 1.12E-05 3.46E-05 RU 106 6.20E-05 NO DATA '?.77E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 AG 110M 7.13E-06 5.16E-06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05 TE 125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06 TE 127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE 127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE 129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE 129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE 131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TE 131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE 132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 I 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 I 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06 I 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 1.54E-06 I 134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E-07 I 135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 NO DATA 1.31E-06 CS 134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 CS 136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS 137 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 CS 138 3.61E-07 5.58E-07 2.84E-07 NO DATA 2.93E-07 4.67E-08 6.26E-07 BA 139 1.06E-09 7.03E-13 3.07E-11 NO DATA 4.23E-13 4.25E-06 3.64E-05 BA 140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 BA 141 1.12E-10 7.70E-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 BA 142 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.11E-06 4.95E-07 LA 140 3.61E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 LA 142 7.36E-10 2.69E-10 6.46E-11 NO DATA NO DATA 5.87E-06 4.25E-05 CE 141 1.98E-05 1.19E-05 1.42E-06 NO DATA 3.75E-06 3.69E-04 1.54E-05 CE 143 2.09E-07 1.38E-07 1.58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE 144 2.20E-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04 PR 143 1.00E-05 3.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05 PR 144 3.42E-11 1.32E-11 1.72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-06 l ND 147 5.67E-06 5.81E-06 3.57E-07 NO DATA 2.25E-06 2.30E-04 2.23E-05 l W 187 9.26E-09 6.44E-09 2.23E-09 NO DATA NO DATA ?.83E-05 2.54E-05 NP 239 2.65E-07 2.37E-08 1.34E-08 HO DATA 4.73E-08 4.25E-05 1.78E-05 l l 1 1 I n l

1 Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 117 of 188 ATTACHMENT A (Page 113 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.2-5* EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /hr per pCi/m') ELEMENT TOTAL BODY SKIN H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-00 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5,50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo 99 1.90E-09 2.20E-09 T 99M 9.60E-10 1.10E-09

                                             .c-101                  2.70E-09               3.00E-09 Ru-103                  3.60E-09               4.20E-09 Ru-105                  4.50E-09               5.10E-09 Ru-106                  1.50E-09               1.80E-09 Ag-110M                  1.80E-08               2.10E-08 Te-125M                  3.50E-11               4.80E-11 Te-127M                  1.10E-12               1.30E-12 Te-127                  1.00E-11               1.10E-11 Te-129M                  7.70E-10               9.00E-10 Te-329                  7.10E-10               8.40E-10
                  *Taken from Regulatory Guide 1.109 (Rev. 1) t l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 a Reference Use Page 118 of 188 ATTACHMENT A (Page 114 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.2-5* (cont' d) EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /hr per pCi/m2) ELEMENT TOTAL BODY SKIN Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2,70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 119 of 188 ATTACHMENT A (Page 115 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.3-1* INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI j H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ( MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.308-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 ] l l NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 l CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 i BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RD 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 ' RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 j I RB 09 NO DATA 4.01E-00 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 l SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05  ! SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 l j SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 l SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07

*Taken from Regulatory Guide 1.109 (Rev. 1)                                            1/98

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 120 of 188 ATTACHMENT A (Page 116 of 184) OFFSITE DOSE CALCOLATION MANUAL TABLE A.3-1* (cont' d) INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED) NUCLIDE BCNE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU 105 1.54E-08 NO DATA 6.00E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 l RU 106 2.75E-06 NO DATA 3.48E-07 MO DATA 5.31E-06 NO DATA 1.78E-04 AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE 125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 8.155-08 4.48E-07 NO DATA 8.68E-06 3 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 l 7.65E-09 2.41E-08 1.32E-07 2.37E-08

                                                                                     )

TE 129 3.14E-08 1.18E-08 NO DATA 4 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 ! TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 1 l TE 132 2.52E-06 1.63E-06 1.53E-06 1.00E-06 1.57E-05 NO DATA 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E 06 j I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 ! I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06  : I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 l I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS 134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS 136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS 137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA 141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA 140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE 143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05

i Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 ! 1 l Reference Use Page 121 of 188 l l ATTACHMENT A > (Page 117 of 184) I OFFSITE DOSE CALCULATION MANUAL TABLE A.3-1* (cont' d) INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 Sb 124** 2.80E-06 5.29E-08 1.11E-06 6.79E-09 NO DATA 2.18E-06 7.95E-05 Sb 125** 1.79E-06 2.00E-08 4.26E-07 1.82E-09 NO DATA 1.38E-06 1.97E-05 Sb 126** 1.15E-06 2.34E-08 4.15E-07 7.04E-09 NO DATA 7.05E-07 9.40E-05 Co 57** NO DATA 1.75E-07 2.91E-07 NO DATA NO DATA NO DATA 4.44E-06

  **Taken from Regulatory Guide 1.109 (Rev. 0)                                              {

l l l l l

I Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l I l Reference Use Page 122 o' ir3 i 1 ATTACHMENT A l (Page 118 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A-3.2 INGESTION DOSU FACTORS FOR TEENAGERS (MREM PER PCI INGESTED) NUCLIDE RONE LIVER T BODY THYROID KIDNEY I.tJNG GI-LLI H 3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C 14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA 24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P 32 2.76E-04 1.71E-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05 I CR 51 NO DATA NO DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 l MN 54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 l 1 MN 56 NO DATA 1.58E-07 2.81E-08 NO DATA 2.00E-07 NO DATA 1.04E-05 I FE 55 3.78E-06 2.68E-06 6.25E-07 NO DATA NO DATA 1.70E-06 1.16E-06 : FE 59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 j i CO 58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 j CO 60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA J.66E-05 NI 63 1.77E-04 1.25E-05 6.000-06 NO DATA NO DATA NO DATA 1.99E-06 NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-06 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 ZN 65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ZN 69 1.47E-08 2.00E-08 1.96E-09 NO DATA 1.83E-08 NO DATA 5.16E-08 BR 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA NO DATA LT E-24 _PR 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.98E-05 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 RB 88 NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA NO DATA 7.30E-15 RB 89 NO DATA 5.50E-08 3.89E-08 NO DATA NO DATA NO DATA 8.43E-17 SR 89 4.40E-04 NO DATA 1.26E-05 NO DATA NO DATA NO DATA 5.24E-05 SR 90 8.30E-03 NO DATA 2.05E-03 NO DATA NO DATA NO DATA 2.33E-04

                                                                                              )

SR 91 0.07E-06 NO DATA 3.21E-07 NO DATA NO DATA NO DATA 3.66E-05 SR 92 3.05E-06 NO DATA 1.30E-07 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-08 NO DATA 3.69E-10 NO DATA NO DATA NO DATA 1.13E-04 Y 91M 1.29E-10 NO DATA 4.93E-12 NO DATA NO DATA NO DATA 6.09E-09 Y 91 2.01E-07 NO DATA 5.39E-09 NO DATA NO DATA NO DATA 8.24E-05 Y 92 1.21E-09 NO DATA 3.50E-11 NO DATA NO DATA NO DATA 3.32E-05 Y 93 3.83E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ZR 95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ZR 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.11E-10 NO DATA 1.27E-04 NB 95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 MO P9 NO DATA 6.03E-06 1 15E-06 NO DATA 1.38E-05 NO DATA 1.08E-05 TC 991 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 6.08E-07

  *Taken from Regulatory Guide 1.109 (Rev. 1)

I t i 3

i Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003  ; I Reference Use Page 123 of 188 ATTACHMENT A (Page 119 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A-3.2 (cont' d) INGESTION DOSE FACTORS FOR TEENAGERS (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 3.60E-10 5.12E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.75E-17 RU 103 2.55E-07 NO DATA 1.09E-07 NO DATA 8.99E-07 NO DATA 2.13E-05 RU 105 2.18E-08 NO DATA 8.46E-09 NO DATA 2.75E-07 NO DATA 1.76E-05 RU 106 3.92E-06 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1.88E-04 AG 110M 2.05E-07 1.94E-07 1.18E-07 NO DATA 3.70E-07 NO DATA 5.45E-05 TE 125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 NO DATA 7 DATA 1.13E-05 TE 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 TE 127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE- 129M 1.63E-05 6.05E-06 2.5SE-06 5.26E-06 6.82E-05 NO DATA 6.12E-05 TE 129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2.45E-07 TE 131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 NO DATA 9.39E-05 TE 131 2.79E-08 1.15E-08 P 72E-09 2.15E-08 1.22E-07 NO DATA 2.29E-09 TE 132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 I 130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 NO DATA 2.29E-06 I 131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 I 132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 NO DATA 3.18E-07 I 133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 NO DATA 2.58E-06 l I 134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 NO DATA 5.10E-09 I 135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 NO DATA 1.74E-06 i CS 134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 { j CS 136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06 CS 137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 CS 138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1=.10E-07 1.28E-08 6.76E-11 l BA 139 1.39E-07 9.78E-11 4.05E-09 NO DATA 9.22E-11 6.74E-11 1.24E-06 l BA 140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 1 BA 141 6.71E-08 5.01E-11 2.24E-09 NO DATA 4.65E-11 3.43E-11 1.43E-13 l NO DATA BA 142 2.99E-08 2.99E-11 1.84E-09 2.53E-11 1.99E-11 9.18E-20

                                                                                          \

LA 140 3.48E-09 1.71E-09 e.55E-10 NO DATA NO DATA NO DATA 9.82E-05 l LA 142 1.79E-10 7.95E-11 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06 CE 141 1.33E-08 8.88E-09 1.02E-09 NO DATA 4.18E-09 NO DATA 2.54E-05 CE 143 2.35E-09 1.71C-06 1.91E-10 NO DATA 7.67E-10 NO DATA 5.14E-05 CE 144 6.96E-07 2.88E-07 3.74E-08 NO DATA 1.72E-07 NO DATA 1.75E-04 PR 143 1.31E-08 5.23E-09 6.52E-10 NO DATA 3.04E-09 NO DATA 4.31E-05 { l PR 144 4.30E-11 1.76E-11 2.18E-12 NO DATA 1.01E-11 NO DATA 4.74E-14 l ND 147 9.38E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 NO DATA 3.68E-05 l W 187 1.46E-07 1.19E-07 4.17E-08 NO DATA NO DATA NO DATA 3.22E-05 I l (

                                                                                          \

1

b i Revision: 1- OFFSITE DOSE CALCULATION MANUAL AP 07B-003-1 Reference Use Page 124 of 188- 1 ATTACHMENT A (Page 120 of.184) OFFSITE. DOSE CALCULATION MANUAL-TABLE A-3.2 (cont' d) INGESTION DOSE FACTORS FOR TEENAGERS (MREM PER PCI INGESTED) 1 NUCLIDE -BONE- LIVER T BODY THYROID KIDNEY LUNG GI-LLI-NP 1 239 .1.76E-09 1.66E-10 9.22E-11 NO DATA- 5.21E-10 NO DATA 2. 67E-O'S , Sb 124** 3.87E-06 7.13E-08 1.51E-06 8.78E-09 NO DATA 3.38E-06 7.'80E-05 l Sb 125** 2.48E-06 ~2.71E-08 5.80E-07 2.37E-09 NO DATA 2.18E-06 1.93E-05 I sb 126** 1.59E-06. 3'.25E-08 5.71E-07 8.99E-09 NO DATA 1.14E-06 9.41E-05 Co 57** NO DATA 2.30E-07 3.99E-07 NO DATA NO DATA- NO DATA 4.44E-06

     **Taken from Regulatory Guide 1.109 (Rev. 0)-

L l: l , i j l I l

1 l l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l { l 1 I Reference Use Page 125 of 188 ) k ATTACFMENT A l I (Page 121 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.3-3 INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI IHOESTED) NUCLIDE BONS LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.86E-05 3.18E-05 NO DATA NO DATA NO DATA 2.28E-05 CR 51 NO DATA NO DATA 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN 54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DATA 4.84E-05 FE 55 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 l CO 58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 { CO 60 NO DATA 5.29E 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 i NI 63 5.38E-04 2.88E-05 1.83E-05 NO DATA NO DATA NO DATA 1.94E-06 I NI 65 2.22E-06 2.09E-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E-05 , ZN 65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 i i ZN 69 4.38E-08 6.33E-08 5.03E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 I BR 83 NO DATA NO DATA 1.71E-07 NO DATA NO DATA NO DATA LT E-24 i BR 84 NO DATA NO DATA 1.98E-07 NO DATA NO DATA NO DATA LT E-24 DR 85 NO DATA NO DATA 9.12E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31E-06 ) RB 88 NO DATA 1.90E-07 1.32E-07 NO DATA NO DATA NO DATA 9.32E-09 ) RB 89 NO DATA 1.17E-07 1.04E-07 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E-03 NO DATA 3.77E-05 NO DATA NO DATA NO DATA 5.11E-05 SR 90 1.70E-02 NO DATA 4.31E-03 NO DATA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 NO DATA 9.06E-07 NO DATA NO DATA NO DATA 5.30E-05 SR 9; 9.03E-06 NO DATA 3.62E-07 NO DATA NO DATA NO LATA 1.71E-04 l Y 90 4.11E-08 MO DATA 1.10E-09 NO DATA NO DATA NO DATA 1.17E-04  : I Y 91M 3.82E-10 NO DATA 1.39E-11 NO DATA NO DATA NO DATA 7.48E-07 Y 91 6.02E-07 NO DATA 1.61E-08 NO DATA NO DATA NO DATA 8.02E-05 Y 92 3.60E-09 NO DATA 1.03E-10 NO DATA NO DATA NO DATA 1.04E-04 , I Y 93 1.14E-08 NO DATA 3.13E-10 NO DATA NO DATA NO DATA 1.70E-04 ZR 95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 UO DATA 2.66E-05 ZR 97 6.99E-09 1.01E-09 5.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04 NB 95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 MO 99 NO DATA 1.33E-05 3.29E-06 NO DATA 2.84E-05 NO DATA 1.10E-05 TC 99M 9.23E-10 1.81E-09 3.00E-08 NO DATA 2.63E-08 9.19E-10 1.03E-06

  *Taken from Regulatory Guide 1.109 (Rev. 1)                                                 l

p l Revision: 1 OFFSITE DOSE CALCULP'" ION MANUAL AP 07B-003 l Reference Use Page 126 of 188 ATTACHMENT A (Page 122 of 184) OFFSITE DOSE CALCULATION MANUAL TABLF. A.3-3 (cont' d) INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 1.07E-09 1.12E-09 1.42E-08 NO DATA 1.91E-08 5.92E-10 3.56E-09 RU 103 7.31E-07 NO DATA 2.81E-07 NO DATA 1.84E-06 NO DATA 1.89E-05 RU 105 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.21E-05 RU 106 1.17E-05 NO DATA 1.46E-06 NO DATA 1.58E-05 NO DATA 1.82E-04 AG 110M 5.39E-07 3.64E-07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TE 125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10E-05 TE 127M 2."9E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 NO DATA 2.34E-05 TE 127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 NO DATA 1.84E-05 TE 129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 TE 129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 NO DATA 8.34E-06 TE 131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 NO DATA 1.01E-04 TE 131 8.30E-08 2.53E 08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 TE 132 1.01E-05 4.17E-06 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05 I 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 I 132 8.00E-07 1.47E-06 6,76E-07 6.82E-05 2.25E-06 NO DATA 1.73E-06 I 133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 NO DATA 2.95E-06 I 134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 NO DATA 5.16E-07 I 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 NO DATA 2.40E-06 CS 134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 CS 136 2.35E-05 6.46E-05 4.18E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 CS 137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 CS 138 2.28E-07 3.17E-07 2.01E-07 NO DATA 2.23E-07 2.40E-08 1.46E-07 BA 139 4.14E-07 2.21E-10 1.20E-08 NO DATA 1.93E-10 1.30E-10 2.39E-05 BA 14C 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 j BA 141 2.00E-07 1.12E-10 6.51E-09 NO DATA 9.69E-11 6.58E-10 1.14E-07 ; BA 142 8.74E-08 6.29E-11 4.88E-09 NO DATA 5.09E-11 3.70E-11 1.14E-09 I LA 140 1.01E-08 3.53E-09 1.1:.L-0 9 NO DATA NO DATA NO DATA 9.84E-05 ! LA 142 5.24E-10 1.67E-10 5.23E-11 NO DATA NO DATA NO DATA 3.31E-05 CE 141 3.97E-08 1.98E-08 2.94E-09 NO DATA 8.68E-09 NO DATA 2.47E-05 j CE 143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1,59E-09 NO DATA 5.55E-05 CE 144 2.08E-06 6.52E-07 1.11E-07 NO DATA 3.61E-07 NO DATA 1.70E-04 PR 143 3.93E-08 1.18E-08 1.95E-09 NO DATA 6.39E-09 NO DATA 4.24E-05 PR 144 1.29E-10 3.99E-11 6.49E-12 NO DATA 2.11E-11 NO DATA 8.59E-08 ND 147 2.79E-08 2.26E-08 1.75E-09 NO DATA 1.24E-08 NO DATA 3.58E-05 W 187 4.29E-07 2.54E-07 1.14E-07 NO DATA NO DATA NO DATA 3.57E-05 , , 1 i i i

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use- Page 127 of 188-ATTACHMENT._A (Page 123 of-184) OFFSITE DOSE CALCULATION MANUAL i TABI2 A.3-3 (cont' d) ! INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED) NUCLIDE ' BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI-NP 239 5.25E-09 3.77E-10 2.65E-10 NO' DATA. 1.09E NO DATA 2.79E-05 Sb 124** 1.11E-05 1.44E-07 3.89E-06 2.45E-08 NO DATA 6.16E-06 6.94E-05

      'Sb  125**  7.16E-06   5.52E-08    1.50E-06   6.63E-09    NO-DATA   3.99E-06  1.71E-05 Sb  126**  4.40E-06   6.73E-08    1.58E-06   2.58E-08    NO DATA   2.10E-06  8.87E-05.

Co 57** NO DATA 4.93E-07 9.98E-07 NO DATA NO DATA NO DATA 4.04E-06

   **Taken from Regulatory Guide 1.109 (Rev. 0) l l

L l-L i

i i Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 i Reference Use Page 128 of 188 l ATTACHMENT A (Page 124 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.3-4* INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.00E-07 C 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA 24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 ,

                                                                                             }

P 32 1.70E-03 1.00E-04 6.59E-05 NO DATA NO DATA NO DATA 2.30E-05 i CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 l MN 54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 l MN 56 NO DATA 8.18E-07 1.41E-07 NO DATA 7.03E-07 NO DATA 7.43E-05 FE 55 1.39E-05 8.90E-06 2.40E-06 NO DATA NO DATA 4.39E-06 1.14E-06 FE 59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 CO 58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 CO 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 I NI 63 6.34E-04 3.92E-05 2.20E-05 NO DATA NO DATA NO DATA 1.95E-06 NI 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NO DATA NO DATA 4.05E-05 i CU 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-Ob j ZN 65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05

                                                                                              )

ZN 69 9.33E-08 1.68E-07 1.25E-08 NO DATA 6.98E-08 NO DATA 1.37E-05 j BR 83 NO DATA NO DATA 3.63E-07 NO DATA NO DATA NO DATA LT E-24 i BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 _ BR 85 NO DATA NO DATA 1.94E-08 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.70E-04 8.40E-05 NO DATA NO DATA NO DATA 4.35E-06 ) RB 88 NO DATA 4.98E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 I RB 89 NO DATA 2.86E-07 1.97E-07 NO DATA NO DATA NO DATA 9.74E-08 SR 89 2.51E-03 NO DATA 7.20E-05 NO DATA NO DATA NO DATA 5.16E-05 SR 90 1.85E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04 SR 91 5.00E-05 NO DATA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 SR 92 1.92E-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 NO DATA 2.33E-09 NO DATA NO DATA NO DATA 1.20E-04 Y 91M 8.10E-10 NO DATA 2.76E-11 NO DATA NO DATA NO DATA 2.70E-06 Y 91 1.13E-06 NO DATA 3.01E-08 NO DATA NO DATA NO DATA 8.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04 Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA 1.92E-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50E-05 ZR 97 1.48E-08 2.54E-09 1.16E-09 NO DATA 2.56E-09 NO DATA 1.62E-04 NB 95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 MO 99 NO DATA 3.40E-05 6.63E-06 NO DATA 5.08E-05 NO DATA 1.12E-05 TC 99M 1.92E-09 3.96E-09 5.10E-08 NO DATA 4.26E-08 2.07E-09 1.15E-06 ! *Taken from Regulatory Guide 1.109 (Rev. 1) f

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 129 of 188 ATTACHMENT A (Page 125 of 184) l OFFSITE DOSE CALCULATION MANUAL l TABLE A.3-4* (cont' d) INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED) l NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUUG GI-LLI TC 101 2.27E-09 2.06E-09 2.83E-08 NO DATA 3.40E-08 1.56E-09 4.86E-07 RU 103 1.48E-06 NO DATA 4.95E-07 NO DATA 3.08E-06 NO DATA 1.80E-05 RU 105 1.36E-07 NO DATA 4.58E-08 NO DATA 1.00E-06 NO DATA 5.41E-05 RU 106 2.41E-05 NO DATA 3.01E-06 NO DATA 2.85E-05 NO DATA 1.83E-04 AG 110M 9 96E-07 7.27E-07 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE 125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 NO DATA NO DATA 1.11E-05 TE 127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE 127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE 129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE 129 2.84E-07 9.79E-08 6.63E-00 2.38E-07 7.07E-07 NO DATA 2.27E-05 TE 131M' 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 i TE 131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 NO DATA 7.11E-06 TE 132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 NO DATA 3.81E-05 I 130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 NO DATA 2.83E-06 I 131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 I 132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 NO DATA 2.73E-06 I 133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 NO DATA 3.08E I 134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 NO DATA 1.04E-06 I 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 0.07E-06 NO DATA 2.62E-06 CS 134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 CS 136 4.59E-05 1.35E-04 5.04E-05 NO DATA 5.38E-05 1.10E-05 2.05E-06 CS 137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 CS 138 4.81E-07 7.82E-07 3.79E-07 NO DATA 3.90E-07 6.09E-08 1.25E-06 l BA 139 8.81E-07 5.84E-10 2.55E-08 NO DATA 3.51E-10 3.54E-10 5.58E-05 BA 140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 BA 141 4.25E-07 2.91E-10 1.34E-08 NO DATA 1.75E-10 1.77E-10 5.19E-06 BA 142 1.84E-07 1.53E-10 9.06E-09 NO DATA 8.81E-11 9.26E-11 7.59E-07 LA 140 2.11E-08 8.32E-09 2.14E-09 NO DATA NO DATA NO DATA 9.77E-05 ) LA 142 1.10E-09 4.04E-10 9.67E-11 NO DATA NO DATA NO DATA 6.86E-05 CE 141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE 143 1.48E-08 9.82E-06 1.12E-09 NO DATA 2.86E-09 NO DATA 5.73E-05 CE 144 2.98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-04 PR 143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR 144 2.74E-10 1.06E-10 1.38E-11 NO DATA 3.84E-11 NO DATA 4.93E-06 ND 147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 i W 187 9.03E-07 6.28E-07 2.17E-07 NO DATA NO DATA NO DATA 3.69E-05 { 1 i l

l l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 1 1 Reference Use Page 130 of 188 ATTACHMENT A (Page 126 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.3-4* (cont' d) INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI LI NP 239 1.11E-08 9.93E-10 5.61E-10 NO DATA 1.98E-09 NO DATA 2.87E-05 l Sb 124** 2.14E-05 3.15E-07 6.63E-06 5.68E-08 NO DATA 1.34E-05 6.60E-05 Sb 125** 1.23E-05 1.19E-07 2.53E-06 1.54E-08 NO DATA 7.72E-06 1.64E-05 Sb 126** 8.06E-06 1.58E-07 2.91E-06 6.19E-08 NO DATA 5.07E-06 8.35E-06 Co 57** NO DATA 1.15E-06 1.87E-06 NO DATA NO DATA NO DATA 3.92E-06 1 1

  **Taken from Regulatory Guide 1.109 (Rev. 0)                                              l I

l l l I l

~ 1 Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference Use Paga 131 of 188 ATTACHMENT A (Page 127 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.3-5* i STABLE ELEMENT TRANSFET DATA  ! Element B. t F. (Cow) Fr veg7 soil Milk (d/1) Meat (d/kg) l H 4.8E 00 1.0E-02 + 1.20E-02 i C 5.5E 00 1.2E-02 + ' 1E-02

                                                                 .                 I Na                       5.2E-02              4.0E-02     3.0E-02              l P                        1.1E 00              2.5E-02      4.6E-02             j Cr                       2.5E-04              2.2E-03     2.4E-03              l Mn                       2.9E-02              2.5E-04     8.0E-04              I Fe                       6.6E-04             1.2E-03 +     4.0E-02 Co                       9.4E-03              1.0E-03      1.3E-02 Ni                       1.9E-02              6.7E-03      5.3E-02 Cu                       1.2E-01             1.4E-02 +    8.0E-03 7 r.                     4.0E-01              3.9E-02     3.0E-02 Rb                       1.3E-01              3.0E-02      3.1E-02 Sr                       1.7E-02             8.0E-04 +     6.0E-04             i Y                        2.6E-03              1.0E-05     4.6E-03              l Zr                       1.7E-04              5.0E-06      3.4E-02             )

Nb 9.4E-03 2.5E-03 2.8E-01 , Mo 1.2E-01 7.5E-03 8. 0E- 03 l Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E 01 1.0E-02 1.5E-03 Ag 1.5E-01 5.0E-02 1.7E-02 Te 1.3E 00 1.0E-03 7.7E-02 I 2.0E-02 6.0E-03 + 2.9E-03 Cs 1.0E-02 1.2E-02 + 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.5E-03 5.0E 06 2.CE-04 Ce 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03 W 1.8E-02 5.0E-04 1.3E-03 Np 2.5E-03 5.0E-06 2.0E-04

    + F. (Goat) values for milk 'd/l)

Element Milk to/l) H 1.7E-01 C 1.0E-01 P 2.5E-01 Fe 1.3E-04 Cu 1.3E-02 Sr 1.4E-02 I 6.0E-02 Cs 3.0E-01

    *Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07D-003 Reference Use Page 132 of 188 ATTACHMENT A (Page 128 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.4-1 SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML ADULT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 8.96E 00 0.96E 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 4.62E 07 2.87E 06 1.79E 06 0.00E-01 0.00E-01 0.00E-01 5.20E 06 CB 51 0.00E-01 0.00E-01 1.49E 00 8.94E-01 3.29E-01 1.98E 00 3.76E 02 MN 54 0.00E-01 4.76E 03 9.08E 02 0.00E-01 1.42E 03 0.00E-01 1.46E 04 MN 56 0.00E-01 1.20E 02 2.12E 01 0.00E-01 1.52E 02 0.00E-01 3.02E 03 FE 55 8.87E 02 6.13E 02 1.43E 02 0.00E-01 0.00E-01 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 CO 58 0.00E-01 1.51E 02 3.39E 02 0.00E-01 0.00E-01 0.00E-01 3.06E 03 CO 60 0.00E-01 4.34E 02 9.58E 02 0.00E-01 0.00E-01 0.00E-01 0.16E 03 NI 63 4.19E 04 2.94E 03 1.41E 03 0.00E-01 0.00E-01 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 CU 64 0.00E-01 1.69E 01 7.93E 00 0.00E-01 4.26E-01 0.00E-01 1.44E 03 ZH 65 2.36E 04 7.50E 04 3.39E 04 0.00E-01 5.02E 04 0.00E-01 4.73E 04 ZN 69 5.02E 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-01 2.33E 00 0.00E-01 0.00E-01 0.00E-01 1.09E-15 RB 86 0.00E-01 1.03E 05 4.79E 04 0.00E-01 0.00E-01 0.00E-01 2.03E 04 RB 88 0.00E-01 2.95E 02 1.56E 02 0.00E-01 0.00E-01 0.00E-01 4.07E-09 RB 89 0.00E-01 1.95E 02 1.37E 02 0.00E-01 0.00E-01 0.00E-01 1.13E-11 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 0.00E-01 0.00E-01 1.46E 04 Y 91M 1.30E-02 0.00E-01 5.04E-04 0.00E-01 0.00E-01 0.00E-ql 3.02E-02 Y 91 2.02E 01 0.00E-01 5.39E-01 0.00E-01 0.00E-01 0.00E ol 1.11E 04 Y 92 1.21E-01 0.00E-01 3.53E-03 0.00E-01 0.00E-01 0.00E-01 2.12E 03 Y 93 3.83E-01 0.00E-01 1.06E-02 0.00E-01 0.00E-01 0.00E-01 1.22E 04 ZR 95 2.77E 00 0.88E-01 6.01E-01 0.00E-01 1.39E 00 0.00E-01 2.82E 03 ZR 97 1.53E-01 3.09E-02 1.41E-02 0.00E-01 4.67E-02 0.00E-01 9.57E 03 NB 95 4.47E 02 2.49E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 MO 99 0.00E-01 4.62E 02 8.79E 01 0.00E-01 1.05E 03 0.00E-01 1.07E 03 TC 99M 2.94E-02 8.32E-02 1.06E 00 0.00E-01 1.26E 00 4.07E-02 4.92E 01 l l l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 0'7B-003 Reference Use Page 133 of 188 ATTACHMENT A (Page 129 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.4-1 (cont' d) SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML ADULT NUCLIDE BONE LIVER T BODY- THYROID KIDNEY LUNG GI-LLI TC 101 3.03E-02 4.36E-02 4.28E-01 0.00E-01 7.85E-01 2.23E-02 1.31E-13 RU 103 1.98E 01 0.00E-01 8.54E 00 0.00E-01 7.57E 01 0.00E-01 2.31E 03 RU 105 1.65E 00 0.00E-01 6.52E-01 0.00E-01 2.13E 01 0.00E-01 1.01E 03 RU 106 2.95E 02 0.00E-01 3.73E 01 0.00E-01 5.69E 02 0.00E-01 1.91E 04 AG 110M 1.42E 01 1.31E 01 7.80E 00 0.00E-01 2.5BE 01 0.00E-01 5.36E 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 TE 129M 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 2.51E 01 1.37E 02 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 130 9.01E 01 2.66E 02 1.05E 02 2.25E 04 4.15E 02 0.00E-01 2.29E 02

 ,,, 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'

I 135 5.28E 01 1.38E 02 5.10E 01 9.11E 03 2.22E 02 0.00E-01 1.56E 02 CS 134 3.03E 05 7.21E 05 5.89E 05 0.00E-01 2.33E 05 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 BA 140 1.88E 03 2.37E 00 1.23E 02 0.00E-01 8.05E-01 1.35E 00 3.88E 03 BA 141 4.37E 00 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 LA 140 3.58E-01 1.80E-01 4.76E-02 0.00E-01 0.00E-01 0.00E-01 1.32E 04 LA 142 1.83E-02 8.33E-03 2.07E-03 0.00E-01 0.00E-01 0.00E-01 6.00E 01 CE 141 8.01E-01 5.42E-01 6.15E-02 0.00E-01 2.52E-C1 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 FR 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 0.00E-01 4.99E 03 W 187 3.04E 02 2.55E 02 8.90E 01 0.00E-01 0.00E-01 0.00E-01 8.34E 04 1

i i Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 134 of 188 ATTACHMENT A . (Page 130 of 184) l' OFFSITE DOSE CALCULATION MANUAL TABLE A 4-1 (cont' d) SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML ADULT i NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 1.28E-01 1.25E-02 6.91E-03 0.00E-01 3.91E-02 0.00E-01 2.57E 03 Sb 124 2.40E 02 4.53E 00 9.50E 01 5.81E-01 0.00E-01 1.87E 02 6.81E 03 Sb 125 1.53E 02 1.71E 00 3.65E 01 1.56E-01 0.00E-01 1.18E 02 1.69E 03 Sb 126 9.85E 01 2.00E 00 3.55E 01 6.03E-01 0.00E-01 6.04E 01 8.05E 03 Co 57 0.00E-01 3.55E 01 5.90E 01 0.00E-01 0.00E-01 6 00E-01 9.01E 02 1 l l l I l r l 1 l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 135 of 188 ATTACHMENT A (Page 131 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.4-2 SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00 C 14 3.43E 04 6.86E 03 6.86E 03 6.86E 03 6.86E 03 6.86E 03 6.86E 03 NA 24 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 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-01 0.00E-01 1.52E 00 8.46E-00 3.34E-00 2.17E 00 2.56E 02 MN S4 0.00E-01 4.65E 03 9.22E 02 0.00E-01 1.39E 03 0.00E-01 9.53E 03 MN 56 0.00E-01 1.24E 02 2.21E 01 0.00E-01 1.58E 02 0.00E-01 8.19E 03 FE 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 CO 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 0.00E-01 1.72E 01 8.08E 00 0.00E-01 4.35E 01 0.00E-01 1.33E 03 ZH 65 2.13E 04 7.41E 04 3.46E 04 0.00E-01 4.74E 04 0.00E-01 3.14E 04 ZN 69 5.45E 01 1.04E 02 7.26E 00 0.00E-01 6.78E 01 0.00E-01 1.91E 02 BR 83 0.00E-01 0.00E-01 4.73E 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16 BR 84 0.00E-01 0.00E-01 5.95E 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16 BR 85 0.00E-01 0.00E-01 2.51E 00 0.00E-01 0.00E-01 0.00E-01 8.24E-16 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 Y 90 1.42E 00 0.00E-01 3.83E-01 0.00E-01 0.00E-01 0.00E-01 1.17E 04 Y 91M 1.34E-01 0.00E-01 5.11E-03 0.00E-01 0.00E-01 0.00E-01 6.32E-01 Y 91 2.09E 01 0.00E-01 5.59E-00 0.00E-01 0.00E-01 0.00E-01 8.55E 03 j Y 92 1.26E-00 0.00E-01 3.63E-02 0.00E-01 0.00E-01 0.00E-01 3.44E 03 i Y 93 3.97E-00 0.00E-01 1.09E-01 0.00E-01 0.00E-01 0.00E-01 1.21E 04 ZR 95 2.64E 00 8.34E-01 5.74E-00 0.00E-01 1.23E 00 0.00E-01 1.92E 03 ZR 97 1.52E-00 3.01E-02 1.39E-01 0.00E-01 4.56E-01 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 MO 99 0.00E-01 4.61E 02 0.78E 01 0.00E-01 1.05E 03 0.00E-01 8.25E 02 TC 99M 2.84E-01 7.92E-02 1.03E 00 0.00E-01 1.18E 00 4.39E-01 5.20E 01

l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference Use Page 136 of 188 j i i ATTACHMENT A l (Page 132 of 184) I OFFSITE DOSE CALCULATION MANUAL l i l TABLE A.4-2 (cont' d) J SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 3.08E-01 4.38E-02 4.30E-00 0.00E-01 7.92E-00 2.67E-01 7.48E-09 RU 103 1.95E 01 0.00E-01 8.33E 00 0.00E-01 6.87E 01 0.00E-01 1.63E 03 l RU 105 1.67E 00 0.00E-01 6.46E-00 0.00E-01 2.10E 01 0.00E-01 1.34E 03 RU 106 2.99E 02 0.00E-01 3.77E 01 0.00E-01 5.77E 02 0.00E-01 1.44E 04 AG 110M 1.28E 01 1.21E 01 7.36E 00 0.00E-01 2.31E 01 0.00E-01 3.40E 03 TE 125M 3.02E 03 1.09E 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 I TE    127 1.24E 02 4.41E 01    2.68E 01    8.59E 01  5.04E 02 0.00E-01  9.61E 03  l TE   129M 1.28E 04 4.77E 03    2.03E 03    4.14E 03  5.37E 04 0.00E-01  4.82E 04 4

TE 129 3.53E 01 1.32E 01 8.59E 00 2.52E 01 1.40E 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 8.81E 01 2.55E 02 1.02E 02 2.08E 04 3.92E 02 0.00E-01 1.96E 02 1 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 5.11E 02 0.00E-01 2.21E 02 I 134 1.25E 01 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 8.64E 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 CS 136 3.18E 04 1.25E 05 8.41E 04 0.00E-01 6.82E 04 1.07E 04 1.01E 04 CS 137 4.15E 05 5.52E 05 1.92E 05 0.00E-01 1.8BE 05 7.30E 04 7.86E 03 ) CS 138 2.88E 02 5.52E 02 2.76E 02 0.00E-01 4.08E 02 4.74E 01 2.51E-01 i BA 139 9.10E 00 6.40E-03 2.65E-00 0.00E-01 6.03E-02 4.41E-02 8.11E 01 BA 140 1.86E 03 2.28E 00 1.20E 02 0.00E-01 7.72E-00 1.53E 00 2.87E 03 BA 141 4.39E 00 3.28E-03 1.47E-00 0.00E-01 3.04E-02 2.24E-02 9.36E-06 BA 142 1.96E 00 1.96E-03 1.20E-00 0.00E-01 1.66E-02 1.30E-02 6.01E-12 LA 140 3.61E-00 1.77E-01 4.72E-01 0.00E-01 0.00E-01 0.00E-01 1.02E 04 l LA 142 1.86E-01 8.25E-03 2.05E-02 0.00E-01 0.00E-01 0.00E-01 2.51E 02 l CE 141 7.98E-00 5.32E-01 6.12E-01 0.00E-01 2.51E-00 0.00E-01 1.52E 03 j CE 143 1.41E-00 1.03E 02 1.15E-01 0.00E-01 4.60E-01 0.00E-01 3.00E 03 l 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-01 0.00E-01 3.15E-00 0.00E-01 4.47E 03 PR 144 4.46E-02 1.83E-03 2.26E-03 0.00E-01 1.05E-02 0.00E-01 4.92E-06 ND 147 9.73E-00 1.06E 00 6.34E-01 0.00E-01 6.21E-00 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 l t I

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 137 of 188 ATTACHMENT A (Page 133 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.4-2 (cont' d) SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR FER pCI/ML TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 1.34E-00 1.27E-02 7.04E-02 0.00E-01 3.98E-01 0.00E-01 2.04E 03 Sb 124 2.32E 02 4.28E 00 9.05E 01 5.26E-00 0.00E-01 2.03E 02 4.68E 03 Sb 125 1.49E 02 1.63E 00 3.48E 01 1.42E-00 0.00E-01 1.31E 02 1.16E 03 Sb 126 9.53E 01 1.95E 00 3.42E 01 5.39E-00 0.00E-01 6.84E 01 5.64E 03 Co 57 0.00E-01 3.55E 01 5.96E 01 0.00E-01 0.00E-01 0.00E-01 6.63E 02 l I l l t

Ravision: 1. OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 138 of 188 ATTACHMENT A (Page 134 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.4-3 SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pC1/ML CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19E Ol' 1.19E 01 C 14 4.45E 04 8.90E 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03 NA 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 CR 51 0.00E-01 0.00E-01 1.92E 00 1.06E 00 2.91E-00 1.94E 00 1.02E 02 MN 54 0.00E-01 3.99E 03 1.06E 03 0.00E-01 1.12E 03 0.00E-01 3.35E 03 MN 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 CO 58 0.00E-01 1.75E 02 5.37E 02 0.00E-01 0.00E-01 0.00E-01 1.02E 03 CO 60 0.00E-01 5.16E 02 1.52E 03 0.00E-01 0.00E-01 0.00E-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 CU 64 0.0]E-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 ZN 69 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 l 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 RB 88 0.00E-01 3.10E 02 2.15E 02 0.00E-01 0.00E-01 0.00E-01 1.52E 01 RB 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-01 0.00E-01 0.00E-01 0.00E-01 9.10E 03 Y 91M 2.97E-01 0.00E-01 1.08E-02 0.00E-01 0.00E-01 0.00E-01 5.82E 01 Y 91 4.68E 01 0.00E-01 1.25E-01 0.00E-01 0.00E-01 0.00E-01 6.24E 03 Y 92 2.80E-00 0.00E-01 8.01E-02 0.00E-01 0.00E-01 0.00E-01 8.09E 03 Y 93 8.87E-00 0.00E-01 2.44E-01 0.00E-01 0.00E-01 0.00E-01 1.32E 04 ZR 95 7.05E 00 1.55E 00 1.38E 00 0.00E-01 2.22E 00 0.00E-01 1.62E 03 ZR 97 4.25E-00 6.13E-02 3.62E-01 0.00E-01 8.81E-01 0.00E-01 9.29E 03 NB 95 5.32E 02 2.07E 02 1.48E 02 0.00E-01 1.95E 02 0.00E-01 3.83E 05 MO 99 0.00E-01 8.78E 02 2.17E 02 0.00E-01 1.87E 03 0.00E-01 7.26E 02 TC 99M 6.46E-01 1.27E-01 2.10E 00 0.00E-01 1.84E 00 6.43E-01 7.20E 01

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 139 of 188 ATTACHMENT A (Page 135 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.4-3 (cont' d) SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCi/ML CHILD NUCLIDE BONE ___ LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 7.48E-01 7.83E-02 9.93E-00 0.00E-01 1.34E 00 4.14E-01 2.49E-01 RU 103 4.83E 01 0.00E-01 1.85E 01 0.00E-01 1.21E 02 0.00E-01 1.25E 03 RU 105 4.26E 00 0.00E-01 1.54E 00 0.00E-01 3.74E 01 0.00E-01 2.78E 03 RU 106 7.72E 02 0.00E-01 9.64E 01 0.00E-01 1.04E 03 0.00E-01 1.20E 04 AG 110M 3.23E 01 2.18E 01 1.74E 01 0.00E-01 4.06E 01 0.00E-01 2.60E 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 1.00E 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 3.11E 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

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I TE 132 3.77E 03 1.67E 03 2.01E 03 2.43E 03 1.55E 04 0.00E-01 1.68E 04 I I 130 2.04E 02 4.13E 02 2.13E 02 4.55E 04 6.17E 02 0.00E-01 1.93E 02 l I 131 1.20E 03 1.21E 03 6.88E 02 4.00E 05 1.99E 03 0.00E-01 1.08E 02 l l 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 too 1.22E 02 2.20E 02 1.04E 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 CS 136 3.83E 04 1.05E 05 6.82E 04 0.00E-01 5.61E 04 8.37E 03 3.70E 03 i l CS 137 5.33E 05 5.11E 05 7.54E 04 0.00E-01 1.66E 05 5.99E 04 J.20E 03 CS 138 3.72E 02 5.17E 02 3.28E 02 0.00E-01 3.64E 02 3.92E 01 2.38E 02 l BA 139 2.54E 01 1.35E-02 7.35E-00 0.00E-01 1.18E-01 7.97E-02 1.47E 03 BA 140 5.09E 03 4.46E 00 2.97E 02 0.00E-01 1.45E 00 2.66E 00 2.58E 03 BA 141 1.23E 01 6.86E-03 3.99E-00 0.00E-01 5.94E-02 4.03E-01 6.99E 00 BA 142 5.36E 00 3.85E-03 2.99E-00 0.00E-01 3.12E-02 2.27E-02 6.99E-02 LA 140 7.86E-00 2.75E-01 9.26E-01 0.00E-01 0.00E-01 0.00E-01 7.66E 03 LA 142 4.08E-01 1.30E-02 4.07E-02 0.00E-01 0.00E-01 0.00E-01 2.58E 03 CE 141 2.34E 00 1.17E 00 1.73E-00 0.00E-01 5.11E-00 0.00E-01 1.46E 03 i CE 143 4.12E-00 2.23E 02 3.24E-01 0.00E-01 9.37E-01 0.00E-01 3.27E 03 CE 144 1.23E 02 3.84E 01 6.54E 00 0.00E-01 2.13E 01 0.00E-01 1.00E 04 PR 143 3.06E 00 9.18E-01 1.52E-00 0.00E-01 4.97E-00 0.00E-01 3.30E 03 PR 144 1.00E-01 3.10E-03 5.05E-03 0.00E-01 1.64E-02 0.00E-01 6.68E 00 ND 147 2.17E 00 1.76E 00 1.36E-00 0.00E-01 9.65E-00 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 I l l l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 140 of 188 l ATTACHMENT A (Page 136 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A. 4-3 (cont' d) SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pC1/ML CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 3.47E-00 2.49E-02 1.75E-01 0.00E-01 7.19E-01 0.00E-01 1.04E 03 Sb 124 6.54E 02 0.49E 00 2.29E 02 1.44E 00 0.00E-01 3.63E 02 4.09E 03 Sb 125 4.22E 02 3.25E 00 8.84E 01 3.91E-00 0.00E-01 2.35E 02 1.01E 03 Sb 126 2.59E 02 3.97E 00 9.31E 01 1.52E 00 0.00E-01 1.24E 02 5.23E 03 Co 57 0.00E-01 4.81E 01 9.73E 01 0.00E-01 0.00E-01 0.00E-01 3.94E 02

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Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 073-003 Reference Use Page 141 of 188 ATTACHMENT A (Page 137 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.4-4 SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML INFANT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 C 14 8.92E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 NA 24 3.80E 02 3.00E 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 0.00E-01 0.00E-01 0.00E-01 8.65E 02 CR 51 0.00E-01 0.00E-01 5.30E-01 3.46E-01 7.56E-02 6.73E-01 1.55E 01 MN 54 0.00E-01 7.49E 02 1.70E 02 0.00E-01 1.66E 02 0.00E-01 2.75E 02 MN 56 0.00E-01 3.00E 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 0.00E-01 0.00E-01 5.98E 02 9.67E 02 CO 58 0. 061 s ~ 1.35E 02 3.38E 02 0.00E-01 0.00E-01 0.00E-01 3.37E 02 CO 60 0.00E-01 s 16E 02 9.59E 02 0.00E-01 0.00E-01 0.00E-01 9.67E 02 NI 63 2.39E 04 1.=7E 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 CU 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 l ZN 69 3.51E 00 6.32E 00 4.70E-01 0.00E-01 2.63E 00 0.00E-01 5.15E 02 i BR 83 0.00E-01 0.00E-01 1.37E 01 0.00E-01 0.00E-01 0.00E-01 3.76E-17 l BR 84 0.00E-01 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01 3.76E-17 j 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 RB 88 0.00E-01 1.87E 01 1.03E 01 0.00E-01 0.00E-01 0.00E-01 1.82E 01 , RB 09 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 0.09E-03 0.00E-01 0.00E-01 0.00E-03 5.49E 03 Y 93 9.14E-01 0.00E-01 2.49E-02 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 NB 95 1.58E 00 6.51E-01 3.76E-01 0.00E-01 4.66E-01 0.00E-01 5.49E 02 MO 99 0.00E-01 1.28E 03 2.49E 02 0.00E-01 1.91E 03 0.00E-01 4.23E 02 TC 99M 7.22E-02 1.49E-01 1.92E 00 0.00E-01 1.60E 00 7.79E-02 4.33E 01

i L Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 0~7B-003 Reference Use. Page 142 of 188 l ATTACHMENT A (Page 138 of 184) OFFSITE DOSE CALCULATION MANUAL l TABLE A.4-4 (cont' d) ' SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML INFANT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 8.54E-02 1.08E-01 1.06E 00 0.00E-01 1.28E 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 0.00E-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 1.01E 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 I 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 I 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 I 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 9.59E-01 0.00E-01 1.32E-02 1.33E-02 2.10E 03 BA 140 6.43E 03 6.43E 00 3.31E 02 0.00E-01 1.53E 00 3.95E 00 1.58E 03 BA 141 1.60E 01 1.09E-02 5.04E-01 0.00E-01 6.58E-03 6.66E-03 1.95E 02 BA 142 6.92E 00 5.76E-03 3.41E-01 0.00E-01 3.31E-03 3.48E-03 2.86E 01 LA 140 7.94E-01 3.13E-01 8.05E-02 0.00E-01 0.00E-01 0.00E-01 3.68E 03 LA 142 4.14E-02 1.52E-02 3.64E-03 0.00E-01 0.00E-01 0.00E-01 2.5BE 03 CE 141 2.96E 00 1.81E 00 2.13E-01 0.00E-01 5.57E-01 0.00E-01 9.33E 02 CE 143 5.57E-01 3.69E 02 4.21E-02 0.00E-01 1.08E-01 0.00E-01 2.16E 03 CE 144 1.12E 02 4.59E 01 6.28E 00 0.00E-01 1.85E 01 0.00E-01 6.43E 03 PR 143 3.06E 00 1.14E 00 1.52E-01 0.00E-01 4.25E-01 0.00E-01 1.61E 03 PR 144 1.03E-02 3.99E-03 5.19E-04 0.00E-01 1.44E-03 0.00E-01 1.85E 02 ND 147 2.00E 00 2.14E 00 1.31E-01 0.00E-01 8.24E-01 0.00E-01 1.35E 03 l W 187 3.40E 01 2.36E 01 8.16E 00 0.00E-01 0.00E-01 0.00E-01 1.39E 03 I l f

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference Use Page '43 of 188 ATTACHMENT A (Page 139 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.4-4 (cont' d) SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML INFANT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 4.18E-01 3.74E-02 2.11E-02 0.00E-01 7.45E-02 0.00E-01 1.00E 03 Sb 124 8.05E 02 1.19E 01 2.49E 02 2.14E 00 0.00E-01 5.04E 02 2.48E 03 Sb 125 4.63E 02 4.48E 00 9.52E 01 5.79E-00 0.00E-01 2.90E 02 6.17E 02 Sb 126 3.03E 02 5.94E 00 1.09E 02 2.33E 00 0.00E-01 1.91E 02 3.14E 03 Co 57 0.00E-01 4.33E 01 7.03E 01 0.00E-01 0.00E-01 0.00E-01 1.47E 02

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l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 144 of 188 l ATTACHMENT A (Page 140 of 184) { OFFSITE DOSE CALCULATION MANUAL l TABLE A.5-1 INHALATION DOSE PARAMETER FOR THE CHILD, PI MREM /YR per pCi/M' H-3 1.12E 03 RU-103 6.62E 05 I C-14 3.59E 04 RU-105 9.95E 04 NA-24 1.61E 04 RU-106 1.43E 07 P-32 2.60E 06 AG-110M 5.48E 06 CR-51 1.70E 04 TE-125M 4.77E 05 MN-54 1.58E 06 TE-127M 1.48E 06 MN-56 1.23E 05 TE-127 5.62E 04 1 FE-55 1.11E 05 TE-129M 1.76E 06 l FE-59 1.27E 06 TE-129 2.55E 04 ) CO-58 1.11E 06 TE-131M 3.08E 05 CO-60 7.07E 06 TE-131 2.05E 03 NI-63 8.21E 05 TE-132 3.77E 05 NI-65 8.40E 04 I-130 1.85E 06 i CU-64 3.67E 04 I-131 1.62E 07  ; ZN-65 9.95E 05 I-132 1.94E 05 ' ZN-69 1.02E 04 I-133 3.85E 06 BR-83 4.74E 02 I-134 5.07E 04 BR-84 5.48E 02 I-135 7.92E 05 BR-85 2.53E 01 CS-134 1.01E 06 RB-86 1.98E 05 CS-136 1.71E 05 RB-88 5.62E 02 CS-137 9.07E 05 RB-89 3.45E 02 CS-138 8.40E 02 SR-89 2.16E 06 BA-139 5.77E 04 SR-90 1.01E 08 BA-140 1.74E 06 l SR-91 1.74E 05 BA-141 2.92E 03 SR-92 2.42E 05 BA-142 1.64E 03 Y-90 2.68E 05 LA-140 2.26E 05 Y-91M 2.81E 03 LA-142 7.59E 04 Y-92 2.39E 05 CE-141 5.44E 05 Y-93 3.89E 05 CE-143 1.27E 05 ZR-95 2.23E 06 PR-143 4.33E 05 ZR-97 3.51E 05 PR-144 1.57E 03 NB-95 6.14E 05 ND-147 3.28E 05 MO-99 1.35E 05 W-187 9.10E 04 TC-99M 4.81E 03 NP-239 6.40E 04 TC-101 5.85E 02 I

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Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page1k5of188 ATTACHMENT A (Page 141 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-2 INHALATION PATHWAY FACTOR MREM /YR PER pCI/M' ADULT (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E 01 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 C 14 1.82E 04 3.41E 03 3.41E 03 3.41E 03 3.41E 03 3.41E 03 3.41E 03 NA 24 1.02E 04 1.02E 04 1.02E 04 1.02E 04 1.02E 04 1.02E 04 1.02E 04 P 32 1.32E 06 7.71E 04 5.01E 04 0.00E-01 0.00E-01 0.00E-01 8.64E 04 CR 51 0.00E 01 0.00E 01 1.00E 02 5.95E 01 2.28E 01 1.44E 04 3.32E 03 MN 54 0.00E 01 3.96E 04 6.30E 03 0.00E-01 9.84E 03 1.40E 06 7.74E 04 MN 56 0.00E 01 1.24E 00 1.83E-00 0.00E-01 1.30E 00 9.44E 03 2.02E 04 FE 55 2.46E 04 1.70E 04 3.94E 03 0.00E-01 0.00E-01 7.21E 04 6.03E 03 FE 59 1.18E 04 2.78E 04 1.06E 04 0.00E-01 0.00E-01 1.02E 06 1.88E 05 CO 58 0.00E 01 1.58E 03 2.07E 03 0.00E-01 0.00E-01 9.28E 05 1.06E 05 CO 60 0.00E 01 1.15E 04 1.48E 04 0.00E-01 0.00E-01 5.97E 06 2.85E 05 NI 63 4.32E 05 3.14E 04 1.45E 04 0.00E-01 0.00E-01 1.78E 05 1.34E 04 NI 65 1.54E 00 2.10E-01 9.12E-02 0.00E-01 0.00E-01 5.60E 03 1.23E 04 CU 64 0.00E 01 1.46E 00 6.15E-01 0.00E-01 4.62E 00 6.78E 03 4.90E 04 ZN 65 3.24E 04 1.03E 05 4.66E 04 0.00E-01 6.90E 04 8.64E 05 5.34E 04 ZN 69 3.38E-02 6.51E-02 4.52E-03 0.00E-01 4.22E-02 9.20E 02 1.63E 01 BR 83 0.00E-01 0.00E-01 2.41E 02 0.00E-01 0.00E-01 0.00E-01 2.32E 02 BR 84 0.00E-01 0 00E-01 3.13E 02 0.00E-01 0.00E-01 0.00E-01 1.64E-03 BR 85 0.00E-01 0.00E-01 1.28E 01 0.00E-01 0.00E-01 0.00E-01 8.00E-15 RB 86 0.00E-01 1.35E 05 5.90E 04 0.00E-01 0.00E-01 0.00E-01 1.66E 04 RB 88 0.00E-01 3.87E 02 1.93E 02 0.00E-01 0.00E-01 0.00E-01 3.34E-09 RB 09 0.00E-01 2.56E 02 1.70E 02 0.00E-01 0.00E-01 0.00E-01 9.28E-12 SR 89 3.04E 05 0.00E-01 8.72E 03 0.00E-01 0.00E-01 1.40E 06 3.50E 05 SR 90 9.92E 07 0.00E-01 6.10E 06 0.00E-01 0.00E-01 9.60E 06 7.22E 05 SR 91 6.19E 01 0.00E-01 2.50E 00 0.00E-01 0.00E-01 3.65E 04 1.91E 05 SR 92 6.74E 00 0.00E-01 2.91E-01 0.00E-01 0.00E-01 1.65E 04 4.30E 04 Y 90 2.09E 03 0.00E-01 5.61E 01 0.00E-01 0.00E-01 1.70E 05 5.06E 05 Y 91M 2.61E-01 0.00E-01 1.02E-02 0.00E-01 0.00E-01 1.92E 03 1.33E 00 Y 91 4.62E 05 0.00E-01 1.24E 04 0.00E-01 0.00E-01 1.70E 06 3.85E 05 Y 92 1.03E 01 0.00E-01 3.02E-01 0.00E-01 0.00E-01 1.57E 04 7.35E 04 Y 93 9.44E 01 0.00E-01 2.61E 00 0.00E-01 0.00E-01 4.85E 04 4.22E 05 ZR 95 1.07E 05 3.44E 04 2.33E 04 0.00E-01 5.42E 04 1.77E 06 1.50E 05 ZR 97 9.68E 01 1.96E 01 9.04E 00 0.00E-01 2.97E 01 7.87E 04 5.23E 05 NB 95 1.41E 04 7.82E 03 4.21E 03 0.00E-01 7.74E 03 5.05E 05 1.0dE 05 MO 99 0.00E-01 1.21E 02 2.30E 01 0.00E-01 2.91E 02 9.12E 04 2.48E 05 , TC 99M 1.03E-03 2.91E-03 3.70E-02 0.00E-01 4.42E-02 7.64E 02 4.16E 03 I l

Revision: 1 -OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 146 of 188 ATTACHMENT A (Page 142 of 184) l OFFSITE DOSE CALCULATION MANUAL l l TABLE A.5-2 (cont' d) INHALATION PATHWAY FACTOR MREM /YR PER pCI/M 3 ADULT (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 4.18E-05 6.02E-05 5.90E-04 0.00E-01 1.08E-03 3.99E 02 1.09E-11 RU 103 1.53E 03 0.00E-01 6.58E 02 0.00E-01 5.83E 03 5.05E 05 1.10E 05 l RU 105 7.90E-01 0.00E-01 3.11E-01 0.00E-01 1.02E 00 1.10E 04 4.82E 04 RU 106 6.91E 04 0.00E-01 8.72E 03 0.00E-01 1.34E 05 9.36E 06 9.12E 05 AG 110M 1.08E 04 1.00E 04 5.94E 03 0.00E-01 1.97E 04 4.63E 06 3.02E 05 TE 125M 3.42E 03 3.58E 03 4.67E 02 1.05E 03 1.24E 04 3.1/E 05 7.06E 04 TE 127M 1.26E 04 5.77E 03 1.57E 03 3.29E 03 4.58E 04 9.60E 05 1.50E 05 TE 127 1.40E 00 6.42E-01 3.10E-01 1.06E 00 5.10E 00 6.51E 03 5.74E 04 TE 129M 9.76E 03 4.67E 03 1.58E 03 3.44E 03 3.66E 04 1.16E 06 3.83E 05 TE 129 4.98E-02 2.39E-02 1.24E-02 3.90E-02 1.87E-01 1.94E 03 1.57E 02 TE 131M 6.99E 01 4.36E 01 2.90E 01 5.50E 01 3.09E 02 1.46E 05 5.56E 05 TE 131 1.11E-02 5.95E-03 3.59E-03 9.36E-02 4.37E-02 1.39E-03 1.84E 01 TE 132 2.60E 02 2.15E 02 1.62E 02 1.90E 02 1.46E 03 2.88E 05 5.10E 05 I 130 4.58E 03 1.34E 04 5.28E 03 1.14E 06 2.09E 04 0.00E-01 7.69E 05 I 131 2.52E 04 3.58E 04 2.05E 04 1.19E 07 6.13E 04 0.00E-01 6.28E 03 1 I 132 1.16E 03 3.26E 03 1.16E 03 1.14E 05 5.18E 03 0.00E-01 4.06E 02 I 133 8.64E 03 1.48E 04 4.52E 03 2.15E 06 2.58E 04 0.00E-01 8.88E 03 I 134 6.44E 02 1.73E 03 6.15E 02 2.98E 04 2.75E 03 0.00E-01 1.01E 00 I 135 2.68E 03 6.98E 03 2.57E 03 4.48E 05 1.11E 04 0.00E-01 5.25E 03 CS 134 3.73E 05 8.48E 05 7.28E 05 0.00E-01 2.87E 05 9.76E 04 1.04E 04 CS 136 3.90E 04 1.46E 05 1.10E 05 0.00E-01 8.56E 04 1.20E 04 1.17E 04 CS 137 4.78E 05 6.21E 05 4.28E 05 0.00E-01 2.22E 05 7.52E 04 8.40E 03 ! CS 118 3.31E 02 6.21E 02 3.24E 02 0.00E-01 4.80E 02 4.86E 01 1.86E-03 1 BA 139 9.36E-01 6.66E-04 2.74E-02 0.00E-01 6.22E-04 3.76E 03 8.96E 02 BA 140 3.90E 04 4.90E 01 2.57E 03 0.00E-01 1.67E 01 1.27E 06 2.18E 05 BA 141 1.00E-01 7.53E-05 3.36E-03 0.00E-01 7.00E-05 1.94E 03 1.16E-07 BA 142 2.63E-02 2.70E-05 1.66E-03 0.00E-01 2.29E-05 1.19E 03 1.57E-16 LA 140 3.44E 02 1.74E 02 4.58E 01 0.00E-01 0.00E-01 1.36E 05 4.58E 05 LA 142 6.83E-01 3.10E-01 7.72E-02 0.00E-01 0.00E-01 6.33E 03 2.11E 03 CE 141 1.99E 04 1.35E 04 1.53E 03 0.00E-01 6.26E 03 3.62E 05 1.20E 05 CE 143 1.86E 02 1.38E 02 1.53E 01 0.00E-01 6.00E 01 7.98E 04 2.26E 05 i CE 144 3.43E 06 1.43E 06 1.84E 05 0.00E-01 8.48E 05 7.78E 06 8.16E 05 I PR 143 9.36E 03 3.75E 03 4.64E 02 0.00E-01 2.16E 03 2.81E 05 2.00E 05 l 1 0.00E-01 7.05E-03 1.02E 03 2.15E-08 I PR 144 3.10E-02 1.25E-02 1.53E-03 ND 147 5.27E 03 6.10E 03 3.65E 02 0.00E-01 3.56E 03 2.21E 05 1.73E 05 W 187 8.48E 00 7.08E 00 2.48E 00 0.00E-01 0.00E-01 2.90E 04 1.55E 05 NP 239 2.30E 02 2.26E 01 1.24E 01 0.00E-01 7.00E 01 3.76E 04 1.19E 05 ) i I l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 147 of 188

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ATTACHMENT A (Page 143 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-3 INHALATION PATHWAY FACTOR MREM /YR PER pCI/M' TEEN (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIONEY LUNG GI-LLI H 3 0.00E-01 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 C 14 2.60E 04 4.87E 03 4.87E 03 4.87E 03 4.87E 03 4.87E 03 4.97E 03 NA 24 1.38E 04 1.38E 04 1.38E 04 1.38E 04 1.38E 04 1.38E 04 1.38E 04 P 32 1.89E 06 1.10E 05 7.16E 04 0.00E-01 0.00E-01 0.00E-01 9.28E 04 - CR 51 0.00E-01 0.00E-01 1.35E 02 7.50E 01 3.07E 01 2.10E 04 3.00E 03 j MN 54 0.00E-01 5.11E 04 8.40E 03 0.00E-01 1.27E 04 1.98E 06 6.68E 04 i MN 56 0.00E-01 1.70E 00 2.52E-01 0.00E-01 1.79E 00 1.53E 04 5.74E 04 FE 55 3.34E 04 2.38E 04 5.54E 03 0.00E-01 0.00E-01 1.24E 05 6.39E 03 FE 59 1.59E 04 3.70E 04 1.43E 04 0.00E-01 0.00E-01 1.53E 06 1.78E 05 CO 58 0.00E-01 2.07E 03 2.78E 03 0.00E-01 0.00E-01 1.34E 06 9.52E 04 CO 60 0.00E-01 1.51E 04 1.98E 04 0.00E-01 0.00E-01 8.72E 06 2.59E 05 NI 63 5.80E 05 4.34E 04 1.98E 04 0.00E-01 0.00E-01 3.07E 05 1.42E 04 NI 65 2.18E 00 2.93E-01 1.27E-01 0.00E-01 0.00E-01 9.36E 03 3.67E 04 CU 64 0.00E-01 2.03E 00 8.48E-01 0.00E-01 6.41E 00 1.11E 04 6.14E 04 ZN 65 3.86E 04 1.34E 05 6.24E 04 0.00E-01 8.64E 04 1.24E 06 4.66E 04 ZN 69 4.83E-02 9.20E-02 6.46E-03 0.00E-01 6.02E-02 1.58E 03 2.85E 02 BR 83 0.00E-01 0.00E-01 3.44E 02 0.00E-01 0.00E-01 0.00E-01 8.00E-15 BR 84 0.00E-01 0.00E-01 4.33E 02 0.00E-01 0.00E-01 0.00E-01 8.00E-15 BR 85 0.00E-01 0.00E-01 1.83E 01 0.00E-01 0.00E-01 0.00E-01 8.00E-15 RB 86 0.00E-01 1.90E 05 8.40E 04 0.00E-01 0.00E-01 0.00E-01 1.77E 04 RB 88 0.00E-01 5.46E 02 2.72E 02 0.00E-01 0.00E-01 0.00E-01 2.92E-05 RB 89 0.00E-01 3.52E 02 2.33E 02 0.00E-01 0.00E-01 0,00E-01 3.38E-07 SR 89 4.34E 05 0.00E-01 1.25E 04 0.00E-01 0.00E-01 2.42E 06 3.71E 05 SR 90 1.08E 08 0.00E-01 6.68E 06 0.00E-01 0.00E-01 1.65E 07 7.65E 05 SR 91 8.80E 01 0.00E-01 3.51E 00 0.00E-01 0.00E-01 6.07E 04 2.59E 05 SR 92 9.52E 00 0.00E-01 4.06E-01 0.00E-01 0.00E-01 2.74E 04 1.19E 05 Y 90 2.98E 03 0.00E-01 8.00E 01 0.00E-01 0.00E-01 2.93E 05 5.59E 05 Y 91M 3.70E-01 0.00E-01 1.42E-02 0.00E-01 0.00E-01 3.20E 03 3.02E 01 Y 91 6.61E 05 0.00E-01 1.77E 04 0.00E-01 0.00E-01 2.94E 06 4.09E 05 Y 92 1.47E 01 0.00E-01 4.29E-01 0.00E-01 0.00E-01 2.68E 04 1.6SE 05 Y 93 1.35E 02 0 00E-01 3.72E 00 0.00E-01 0.00E-01 8.32E 04 5.79E 05 ZR 95 1.46E 05 4.58E 04 3.15E 04 0.00E-01 6.74E 04 2.69E 06 1.49E 05 ZR 97 1.38E 02 2.72E 01 1.26E 01 0.00E-01 4.12E 01 1.30E 05 6.30E 05 NB 95 1.86E 04 1.03E 04 5.66E 03 0.00E-01 1.00E 04 7.51E 05 9.68E 04 MO 99 0.00E-01 1.69E 02 3.22E 01 0.00E-01 4.11E 02 1.54E 05 2.69E 05 l TC 99M 1.38E-03 3.86E-03 4.99E-02 0.00E-01 5.76E-02 1.15E 03 6.13E 03

1 Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l Reference Use Page 148 of 188 l 4 ATTACHMENT A I (Page 144 of 184)  ; OFFSITE DOSE CALCULATION MANUAL

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l TABLE A.5-3 (cont'd) INHALATION PATHWAY FACTOR MREM /YR PER pCI/M 3 TEEN (RI TACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI i TC 101 5.92E-05 8.40E-05 8.24E-04 0.00E-01 1.52E-03 6.67E 02 8.72E-07 i RU 103 2.10E 03 0.00E-01 8.96E 02 0.00E-01 7.43E 03 7.83E 05 1.09E 05 RU 105 1.12E 00 0.00E-01 4.34E-01 0.00E-01 1.41E 00 1.82E 04 9.04E 04 RU 106 9.84E 04 0.00E-01 1.24E 04 0.00E-01 1.90E 05 1.61E 07 9.60E 05 AG 110M 1.38E 04 1.31E 04 7.99E 03 0.00E-01 2.50E 04 6.75E 06 2.73E 05 TE 125M 4.88E 03 2.24E 03 6.74E 02 1.40E 03 0.00E-01 5.36E 05 7.50E 04 TE 127M 1.80E 04 0.16E 03 2.18E 03 4 38E 03 6.54E 04 1.66E 06 1.59E 05 TE 127 2.01E 00 9.12E-01 4.42E-01 1,42E 00 7.28E 00 1.12E 04 8.08E 01 1 TE 129M 1.39E 04 6.58E 03 2.25E 03 4.58E 03 5.19E 04 1.98E 06 4.05E 05 1 TE 129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E 03 1.62E 03 TE 131M 9.84E 01 6.01E 01 4.20E 01 7.25E 01 4.39E 02 2.38E 05 6.21E 05 l TE 131 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E 03 1.51E 01 l TE 132 3.60E 02 2.90E 02 2.19E 02 2.46E 02 1.95E 03 4.49E 05 4.63E 05 I 130 6.24E 03 1.79E 04 7.17E 03 1.49E 06 2.75E 04 0.00E-01 9.12E 03 I 131 3.54E 04 4.91E 04 2.64E 04 1.46E 07 8.40E 04 0.00E-01 6.49E 03 , I 132 1.59E 03 4.38E 03 1.58E 03 1.51E 05 6.92E 03 0.00E-01 1.27E 03 I 133 1.22E 04 2.05E 04 6.22E 03 2.92E 06 3.59E 04 0.00E-01 1.03E 04 I 134 8.88E 02 2.32E 03 8.40E 02 3.95E 04 3.66E 03 0.00E-01 2.04E 01 I 135 3.70E 03 9.44E 03 3.49E 03 6.21E 05 1.49E 04 0.00E-01 6.95E 03 CS 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 13i 6.70E 05 8.48E 05 3.11E 05 0.00E-01 3.04E 05 1.21E 05 8.48E 03 CS 138 4.66E 02 8.56E 02 4.46E 02 0.00E-01 6.62E 02 7.87E 01 2.70E-01 BA 139 1.34E 00 9.44E-04 3.90E-02 0.00E-01 8.88E-04 6.46E 03 6.45E 03 BA 140 5.47E 04 6.70E 01 3.52E 03 0.00E-01 2.28E 01 2.03E 06 2.29E 05 BA 141 1.42E-01 1.06E-04 4.74E-03 0.00E-01 9.84E-05 3.29E 03 7.46E-04 BA 142 3.70E-02 3.70E-05 2.27E-03 0.00E-01 3.14E-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 LA 142 9.60E-01 4.25E-01 1.06E-01 0.00E-01 0.00E-01 1.02E 04 1.20E 04 CE 141 2.84E 04 1.90E 04 2.17E 03 0.00E-01 8.88E 03 6.14E 05 1.26E 05 l CE 143 2.66E 02 1.94E 02 2.168 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 PR 144 4.30E-02 1.76E-02 2.18E-03 0.00E-01 1.01E-02 1.75E 03 2.35E-04 1 ND 147 7.86E 03 8.56E 03 5.13E 02 0.00E-01 5.02E 03 3.72E 05 1.82E 05 I W 187 1.20E 01 9.76E 00 3.43E 00 0.00E-01 0.00E-01 4.74E 04 1.77E 05 l NP 239 18E 02 3.19E 01 1.77E 01 0.00E-01 1.00E 02 6.49E 04 1.32E 05 j i l l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 149 of 188 ATTACHMENT A (Page 145 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-4 INHALATION PATHWAY FACTOR MREM /YR PER pCI/M' CHILD (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LCJG GI-LLI H 3 0.00E-01 1.12E 03 1.12E 03 1.12E 03 1.12E 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 l P 32 2.60E 06 1.14E 05 9.88E 04 0.00E-01 0.00E-01 0.00E-01 4.22E 04 I CR 51 0.00E-01 0.00E-01 1.54E 02 8.55E 01 2.43E 01 1.70E 04 1.08E 03 MN 54 0.00E-01 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 4.74E 04 2.52E 04 7.77E 03 0.00E-01 0.00E-01 1.11E 05 2.87E 03 FE 59 2.07E 04 3.34E 04 1.67E 04 0.00E-01 0.00E-01 1.27E 06 7.07E 04 CO 58 0.00E-01 1.77E 03 3.16E 03 0.00E-01 0.00E-01 1.11E 06 3.44E 04 CO 60 0.00E-01 1.31E 04 2.26E 04 0.00E-01 0.00E-01 7.07E 06 9.62E 04 NI 63 8.21E 05 4.63E 04 2.90E 04 0.00E-01 0.00E-01 2.75E 05 6.33E 03 NI 65 2.99E 00 2.96E-01 1.64E-01 0.00E-01 0.00E-01 8.18E 03 8.40E 04 CU 64 0.00E-01 1.99E 00 1.07E 00 0.00E-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 ZN 69 6.70E-02 9.66E-02 8.92E-03 0.00E-01 5.85E-02 1.42E 03 1.02E 04 BR 83 0.00E-01 0.00E-01 4.74E 02 0.00E-01 0.00E-01 0.00E-01 3.70E-15 BR 84 0.00E-01 0.00E-01 5.48E 02 0.00E-01 0.00E-01 0.00E-01 3.70E-15 BR 85 0.00E-01 0.00E-01 2.53E 01 0.00E-01 0.00E-01 0.00E-01 3.70E-15 RB 86 0.00E-01 1.98E 05 1.14E 05 0.00E-01 0.00E-01 0.00E-01 7.99E 03 RB 88 0.00E-01 5.62E 02 3.66E 02 0.00E-01 0.00E-01 0.00E-01 1.72E 01 RB 89 0.00E-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 1.48E 07 3.43E 05 SR 91 1.21E 02 0.00E-01 4.59E 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-01 2.40E 04 2.42E 05 Y 90 4.11E 03 0.00E-01 1.11E 02 0.00E-01 0.00E-01 2.62E 05 2.68E 05 Y 91M 5.07E-01 0.00E-01 1.84E-02 0.00E-01 0.00F.-01 2.81E 03 1.72E 03 Y 91 9.14E 05 0.00E-01 2.44E 04 0.00E-01 0.00E-01 2.63E 06 1.84E 05 Y 92 2.04E 01 0.00E-01 5.81E-01 0.00E-01 0.00E-01 2.39E 04 2.39E 05 Y 93 1.86E 02 0.00E-01 5.11E 00 0.00E-01 0.00E-01 7.44E 04 3.89E 05 l ZR 95 1.90E 05 4.18E 04 3.70E 04 0.00E-01 5.96E 04 2.23E 06 6.11E 04 i ZR 97 1.88E 02 2.72E 01 1.60E 01 0.00E-01 3.88E 01 1.13E 05 3.51E 05 NB 95 2.35E 04 9.18E 03 6.55E 03 0.00E-01 8.62E 03 6.14E 05 3.70E 04 ] MO 99 0.00E-01 1.72E 02 4.25E 01 0.00E-01 3.92E 02 1.35E 05 1.27E 05 i TC 99M 1.78E-03 3.48E-03 5.77E-02 0.00E-01 5.07E-02 9.51E 02 4.81E 0'4 ) i i i l I

I l 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Revision: 1 Reference Use Page 150 of 188 f ATTACHMENT A , (Page 146 of 184)  ! OFFSITE DOSE CALCULATION MANUAL I TABLE A.5-4 (cont' d) l INHALATION PATHWAY FACTOR MREM /YR PER pCI/M' CHILD (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 8.10E-05 0.51E-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-01 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  ; l RU 106 1.36E 05 0.00E-01 1.69E 04 0.00E-01 1.84E 05 1.43E 07 4.29E 05 AG 110M 1.69E 04 1.14E 04 9.14E 03 0.00E-01 2.12E 04 5.48E 06 1.00E 05 TE 125M 6.73E 03 2.33E 03 9.14E 02 1.92E 03 0.00E-01 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 /.85E 03 3.04E 03 6.33E 03 5.03E 04 1.76E 06 1.82E 05 TE 129 f.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E 03 2.55E 04 TE 131M 1.34E 02 5.92E 01 5.07E 01 9.77E 01 4.00E 02 2.06E 05 3.08E 05 TE 131 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E 03 1. 3 3 E O_'s,, TE 132 4.81E 02 2.72E 02 2.63E 02 3.17E 02 1.77E 03 3.77E 05 1.38E 05 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 94 1.62E 07 7.88E 04 0.00E-01 2.84E 03 I 132 2.12E 03 4.07E 03 1.98E 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 l I 134 1.17E 03 2.16E 03 9.95E 02 5.07E 04 3.30E 03 0.00E-01 9.55E 02 I 135 4.92E 03 0.73E 03 4.14E 03 7.92E 05 1.34E 04 0.00E-01 4.44E 03 CS 134 6.51E 05 1.01E 06 2.25E 05 0.00E-01 3.30E 05 1.21E 05 3.05E 03 CS 136 6.51E 04 1.71E 05 1.16E 05 0.00E-01 9.55E 04 1.45E 04 4.18E 03 CS 137 9.01E 05 8.25E 05 1.28E 05 0.00E-01 2.82E 05 1.04E 05 3.62E 03 CS 138 6.33E 02 8.40E 02 5.55E 02 0.00E-01 6.22E 02 6.81E 01 2.70E 02 BA 139 1.84E 00 9.84E-04 5.36E-02 0.00E-01 8.62E-04 5.77E 03 5.77E 04 BA 140 7.40E 04 6.48E 01 4.33E 03 0.60E 01 2.11E 01 1.74E 06 1.02E 05 BA J'1 1.96E-01 1.09E-04 6.36E-03 0.00t-01 9.47E-05 2.92E 03 2.75E 02 BA 142 4.99E-02 3.60E-05 2.79E-03 0.0vE-01 2.91E-05 1.64E 03 2.74E 00 LA 140 6.44E 02 2.25E 02 7.55E 01 0.00E-01 0.00E-01 1.83E 05 2.26E 05 LA 142 1.29E 00 4.11E-01 1.29E-01 0.00E-01 0.00E-01 8.70E 03 7.59E 04 CE 141 3.92E 04 1.95E 04 2.90E 03 0.00E-01 8.55E 03 5.44E 05 5.66E 04 CE 143 3.66E 02 1.99E 02 2.87E 01 0.00E-01 8.36E 01 1.15E 05 1.27E 05 "E 144 6.77E CG 2.12E 06 3.61E 05 0.00E-01 1.17E 06 1.20E 07 3.89E 05 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 5.96E-02 1.85E-02 3.00E-03 0.00E-01 9.77E-03 1.57E 03 1.97E 02 ND 147 1.08E 04 8.73E 03 6.81E 02 0.00E-01 4.81E 03 3.28E 05 0.21E 04 W 187 1.63E 01 9.66E 00 4.33E 00 0.00E-01 0.00E-01 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 i

Revision: 1 0FFSITE DOSE CALCULATION MANUAL AP 07B-003 3 l j Reference Use Page 151 of 188 i ATTACHMENT A (Page 147 of 184) 0FFSITE DOSE CALCULATION MANUAL TABLE A.5-5 INHALATION PATHWAY FACTOR MREM /YR PER pCI/M' INFANT (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 6.47E 02 6.47E 02 6.47E 02 6.47E 02 6.47E 02 6.47E 02 C 14 2.65E 04 5.31E 03 5.31E 03 5.31E 03 5.31E 03 5.31E 03 5.31E 03 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 0.00E-01 8.95E 01 5.75E 01 1.32E 01 1.28E 04 3.57E 02

  , ' t4
       . 54  0.00E-01 2.53E 04   4.98E 03    0.00E-01   4.98E 03 1.00E 06   7.06E 03 MN      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 CO       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    0.00E-01   0.00E-01 4.51E 06   3.19E 04 NI       63 3.39E 05 2.04E 04   1.16E 04    0.00E-01   0.00E-01 2.09E 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 1.88E 00   7.74E-01    0.00E-01   3.98E 00 9.30E 03   1.50E 04 ZN       65 1.93E 04 6.26E 04   3.11E 04    0.00E-01   3.25E 04 6.47E 05   5.14E 04 ZN      69 5.39E-02 9.67E-02   7.18E-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 BR       84 0.00E-01 0.00E-01   4.00E 02    0.00E-01   0.00E-01 0.00E-01   1.40E-15 BR       85 0.00E-01 0.00E-01   2.04E 01    0.00E-01   0.00E-01 0.00E-01   1.40E-15 RB       86 0.00E-01 1.90E 05   8.82E 04    0.00E-01   0.00E-01 0.00E-01   3.04E 03 I RB       88 0.00E-01 5.57E 02   2.87E 02    0.00E-01   0.00E-01 0.00E-01   3.39E 02 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   0.00F-01 2.03E 06   6.40E 04 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   0.00E-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 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    0.00E-01   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.?.7E 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 MO       99 0.00E-01 1.65E 02   3.23E 01    0.00E-01   2.65E 02 1.35E 05   4.87E 04 TC      99M 1.40E-04 2.88E-03   3.72E-02    0.00E-01   3.11E-02 8.11E 02   2.03E 03

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 152 of 188 l 4 ATTACHMENT A j (Page 148 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-5 (cont' d) l INHALATION PATHWAY FACTOR MREM /YR PER pCI/M' INFANT (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 6.51E-05 8.23E-05 8.12E-04 0.00E-01 9.79E-04 5.84E 02 8.44E 02 RU 103 2.02E 03 0.00E-01 6.79E 02 0.00E-01 4.24E 03 5.52E 05 1.61E 04 ) RU 105 1.22E 00 0.00E-01 4.10E-01 0.00E-01 8.99E-01 1.57E 04 4.84E 04 RU 106 8.68E 04 0.00E-01 1.09E 04 0.00E-01 1.07E 05 1.16E 07 1.64E 05 AG 110M 9.98E 03 7.22E 03 5.00E 03 0.00E-01 1.09E 04 3.67E 06 3.30E 04 , 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 I TE 127 2.23E 00 9.53E-01 4.89E-01 1.85E 00 4.86E 00 1.03E 04 2.44E 04 I TE 129M 1.41E 04 6.09E 03 2.23E 03 5.47E 03 3.18E 04 1.68E 06 6.90E 04 l TE 129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.00E 03 2.63E 04 TE 131M 1.07E 02 5.50E 01 3.63E 01 8.93E 01 2.65E 02 1.99E 05 1.19E 05 TE 131 1.74E-02 8.22E-03 5.00E-03 1.58E-02 3.99E-02 2.06E 03 8.22E 03 TE 132 3.72E 02 2.37E 02 1.76E 02 2.79E 02 1.03E 03 3.40E 05 4.41E 04 I 130 6.36E 03 1.39E 04 5.57E 03 1.60E 06 1.53E 04 0.00E-01 1.99E 03 I 131 3.79E 04 4.44E 04 1.96E 04 1.48E 07 5.18E 04 0.00E-01 1.06E 03 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 3.56E 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 I 135 3.86E 03 7.60E 03 2.77E 03 6.96E 05 8.47E 03 0.00E-01 1.83E 03 CS 134 3.96E 05 7.03E 05 7.45E 04 0.00E-01 1.90E 05 7.97E 04 1.33E 03 CS 136 4.83E 04 1.35E 05 5.29E 04 0.00E-01 5.64E 04 1.18E 04 1.43E 03 CS 137 5.49E 05 6.12E 05 4.55E 04 0.00E-01 1.72E 05 7.13E 04 1.33E 03 CS 138 5.05E 02 7.81E 02 3.98E 02 0.00E-01 4.10E 02 6.54E 01 8.76E 02 BA 139 1.48E 00 9.84E-04 4.30E-02 0.00E-01 5.92E-04 5.95E 03 5.10E 04 BA 140 5.60E 04 5.60E 01 2.90E 03 0.00E-01 1.34E 01 1.60E 06 3.84E 04 BA 141 1.57E-01 1.08E-04 4.97E-03 0.00E-01 6.50E-05 2.97E 03 4.75E 03 BA 142 3.98E-02 3.30E-05 1.96E-03 0.00E-01 1.90E-05 1.55E 03 6.93E 02 LA 140 5.05E 02 2.00E 02 5.15E 01 0.00E-01 0.00E-01 1.68E 05 8.48E 04 LA 142 1.03E 00 3.77E-01 9.04E-02 0.00E-01 0.00E-01 8.22E 03 5.95E 04 CE 141 2.77E 04 1.67E 04 1.99E 03 0.00E-01 5.25E 03 5.17E 05 2.16E 0/ CE 143 2.93E 02 1.93E 02 2.21E 01 0.00E-01 5.64E 01 1.16E 05 4.97E 04 CE 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 PR 144 4.79E-02 1.85E-02 2.41E-03 0.00E-01 6.72E-03 1.61E 03 4.28E 03 ! ND 147 7.94E 03 8.13E 03 5.00E 02 0.00E-01 3.15E 03 3.22E 05 3.12E 04 l W 187 1.30E 01 9.02E 00 3.12E 00 0.00E-01 0.00E-01 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 l

l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 153 of 188 ATTACHMENT A , (Page 149 of 184) i OFFSITE DOSE CALCULATION MANUAL TABLE A.5-6 GRASS-COW-MILK PATHWAY FACTOR M2 MREM /YR PER pCI/SEC ADULT (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 7.63E 02 7.63E 02 7.63E 02 7."1E 02 7.63E 02 7.63E 02 C 14 2.63E 08 5.27E 07 5.27E 07 5.27E 07 5.2*E 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 P 32 1.71E 10 1.06E 09 6.60E 08 0.00E-01 0.00E-01 0.00E-01 1.92E 09 CR 51 0.00E-01 0.00E-01 2.86E 04 0.00E-01 6.30E 03 3.79E 04 7.19E 06 MN 54 0.00E-01 8.41E 06 1.61E 06 0.00E-01 0.00E-01 0.00E-01 2.58E 07 MN 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 l FE 59 2.97E 07 6.98E 07 2.68E 07 0.00E-01 0.00E-01 1.95E 07 2.33E 08 CO 58 0.00E-01 4.71E 06 1.06E 07 0.00E-01 0.00E-01 0.00E-01 9.56E 07 CO 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 09 4.71E 08 2.26E 08 0.00E-01 0.00E-01 0.00E-01 9.73E 07 NI 65 4.63E-01 6.02E-02 2.75E-02 0.00E-01 0.00E-01 0.00E-01 1.53E 00 i CU 64 0.00E-01 2.39E 04 1.12E 04 0.00E-01 6.02E 04 0.00E-01 2.03E 06 ZN 65 1.37E 09 4.37E 09 1.97E 09 0.00E-01 2.92E 09 0.00E-01 2.75E 09 ZN 69 5.22E-12 9.99E-12 6.95E-13 0.00E-01 6.49E-12 0.00E-01 1.50E-12 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 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB C6 0.00E-01 2.59E 09 1.21E 09 0.00E-01 0.00E-01 0.00E-01. 5.12E 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 1.45E 09 0.00E-01 4.16E 07 0.00E-01 0.00E-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 i SR 92 4.90E-01 0.00E-01 2.12E-02 0.00E-01 0.00E-01 0.00E-01 9.70E 00 l Y 90 7.07E 01 0.00E-01 1.90E 00 0.00E-01 0.00E-01 0.00E-01 7.50E 05 Y 91M 6.03E-20 0.00E-01 2.34E-21 0.00E-01 0.00E-01 0.00E-01 1.77E-19 Y 91 8.59E 03 0.00E-01 2.30E 02 0.00E-01 0.00E-01 0.00E-01 4.73E 06 Y 92 5.59E-05 0.00E-01 1.63E-06 0.00E-01 0.00E-01 0.00E-01 9.79E-01 Y 93 2.33E-01 0.00E-01 6.44E-03 0.00E-01 0.00E-01 0.00E-01 7.39E 03 ZR 95 9.44E 02 3.03E 02 2.05E 02 0.00E-01 4.75E 02 0.00E-01 9.59E 05 ZR 97 4.33E-01 8.75E-05 4.00E-02 0.000-01 1.32E-00 0.00E-01 2.71E 04 NB 95 8.26E 04 4.59E 04 2.47E 04 0. 00E- 01 4.54E 04 0.00E-01 2.79E 08 MO 99 0.00E-01 2.40E 07 4.71E 06 0.00E-01 5.61E 07 0.00E-01 5.74E 07 TC 99M 3.33E 00 9.40E 00 1. JOE 02 0.00E 01 1.43E 02 4.60E 00 5.56E 03

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 154 of 188 ATTACHMENT A (Page 150 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-6 (cont' d) i GRASS-COW-MILK FATHWAY FACTOR I M' MREM /YR PER pCI/SEC ADULT (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RU 103 1.02E 03 0.00E-01 4.38E 07 0.00E-01 3.88E 03 0.00E-01 1.19E 05 RU 105 8.58E-04 0.00E-01 3.39E-04 0.00E-01 1.11E-02 0.00E-01 5.25E-01 RU 106 2.04E 04 0.00E-01 2.58E 03 0.00E-01 3.94E 04 0.00E-01 1.32E 06 AG 110M 5.82E 07 5.39E 07 3.20E 07 0.00E-01 1.06E 08 0.00E-01 2.20E 10 TE 125M 1.63E 07 5.90E 06 2.18E 06 4.90E 06 6.63E 07 0.00E-01 6.50E 07 TE 127M 4.58E 07 1.64E 07 5.58E 06 1.17E 07 1.86E 08 0.00E-01 1.54E 08 TE 127 6.54E 02 2.35E 02 1.41E 02 4.84E 02 2.66E 03 0.00E-01 5.16E 04 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 2.84E-10 1.07E-10 6.29E-11 2.18E-10 1.19E-09 0.00E-01 2.14E-10 TE 131M 3.61E 05 1.77E 05 1.47E 05 2.80E 05 1.79E 06 0.00E-01 1.73E 07 TE 131 3.67E-33 1.53E-33 1.16E-33 3.01E-33 1.61E-32 0.00E-01 0.00E-01 TE 132 2.40E 06 1.55E 06 1.46E 06 1.72E 06 1.50E 07 0.00E-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 0.00E-01 1.12E 08 I 132 1.65E-01 4.41E-01 1.54E-01 1.54E 01 7.02E-01 0.00E-01 8.28E-02 i 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 2.03E-12 5.52E-12 1.98E-12 9.57E-11 8.78E-12 0.00E-01 4.81E-15 I 135 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 0.00E-01 4.35E 09 1.45E 09 2.35E 08 CS 136 2.61E 08 1.03E 09 7.42E 08 0.00E-01 5.73E 08 7.86E 07 1.17E 08 CS 137 7.38E 09 1.01E 10 6.61E 09 0.00E-01 3.43E 09 1.14E 09 1.95E 08 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 4.56E-08 3.25E-11 1.34E-09 0.00E-01 3.04E-11 1.84E-11 8. 09E -08 BA 140 2.69E 07 3.38E 04 1.76E 06 0.00E-01 1.15E 04 1.93E 04 5.54E 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 140 4.52E 00 2.28E 00 6.02E-01 0.00E-01 0.00E-01 0.00E-01 1.67E 05 LA 142 9.39E-12 4.273-12 1.06E-12 0.00E-01 0.00E-01 0.00E-01 3.12E-08 CE 141 4.84E 03 3.28E 03 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 0.00E-01 1.35E 01 0.00E-01 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 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ND 147 9.46E 01 1.09E 02 6.55E 00 0.00E-01 6.40E 01 0.00E-01 5.25E 05 W 187 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 1.99E-01 0.00E-01 1.13E 00 0.00E-01 7.41E 04

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 155 of 188 I ATTACHMENT A I (Page 151 of 184) ) OFFSITE DOSE CALCULATION MANUAL l 1

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TABLE A.5-7  ! GRASS-COW-MILK PATHWAY FACTOR 2 M MREM /YR PER pCI/SEC l TEEN (RI FACTORS) ] l NUCLIDE BONE LIVER T BODY THYROID KIDNEY LU. ; 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  ! I P 32 3.15E 10 1.95E 09 1.22E 09 0.00E-01 0.00E-01 0.00E-01 2.65E 09 I 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

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MN 56 0.00E-01 7.37E-03 1.31E-03 0.00E-01 9.33E-03 0.00E-01 4.85E-01 l FE 55 4.45E 07 3.16E 07 7.36E 06 0.00E-01 0.00E-01 2.00E 07 1.37E 07 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 0.00E-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 l ZN 65 2.11E 09 7.31E 09 3.41E 09 0.00E-01 4.68E 09 0.00E-01 3.10E 09 I ZN 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 BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l 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 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 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-01 2.39E 05 SR 92 8.96E-01 0.00E-01 3.82E-02 0.00E-01 0.00E-01 0.00E-01 2.28E 01 l Y 90 1.30E 02 0.00E-01 3.50E 00 0.00E-01 0.00E-01 0.00E-01 1.07E 06 Y 91M 1.llE-19 0.00E-01 4.22E-21 0.00E-01 0.00E-01 0.00E-01 5.22E-18 Y 91 1.58E 04 0.00E-01 4.242 02 0.00E-01 0.00E-01 0.00E-01 6.48E 06 Y 92 1.03E-04 0.00E-01 2.99E-06 0.00E-01 0.00E-01 0.00E-01 2.83E 00 Y 93 4.30E-01 0.00E-01 1.18E-02 0.00E-01 0.00E-01 0.00E-01 1.31E 04 ZR 95 1.65E 03 5.21E 02 3.58E 02 0.00E-01 7.65E 02 0.00E-01 1.20E 06 ZR 97 7.89E-01 1.56E-01 7.19E-02 0.00E-01 2.37E-01 0.00E-01 4.23E 04 NB 95 1.41E 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 G" 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 l I

i Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 156 of 188 i ATTACHMENT A i (Page 152 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-7 (cont' d) GRASS-COW-MILK PATHWAY FACTOR M2 MREM /YR PER pCI/SEC TEEN (RI FACTORS) ] 1 NUCLIDE BONE L'7ER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RU 103 1.81E 03 0.00E-01 7.74E 02 0.00E-01 6.38E 03 0.00E-01 1.51E 05 l RU 105 1.57E-03 0.00E-01 6.08E-04 0.00E-01 1.98E-02 0.00E-01 1.27E 00 I RU 106 3.75E 04 0.00E-01 4.73E 03 0.00E-01 7.23E 04 0.00E-01 1.80E 06 AG 110M 9.63E 07 9.11E 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 i i TE 127M 8.44E 07 2.99E 07 1.00E 07 2.01E 07 3.42E 08 0.00E-01 2.10E 08 l TE 127 1.21E 03 4.29E 02 2.61E 02 8.36E 02 4.91E 03 0.00E-01 9.35E 04 i TE 129M 1.10E 08 4.09E 07 1.74E 07 3.55E 07 4.61E 08 0.00E-01 4.13E 08 l TE 129 5.23E-10 1.95E-10 1.27E-10 3.74E-10 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 I TE 132 4.29E 06 2.72E 06 2.56E 06 2.87E 06 2.61E 07 0.00E-01 8.61E 07 I 130 7.39E 05 2.14E 06 0.54E 05 1.74E 08 3.26E 06 0.00E-01 1.64E 06 i I 131 5.37E 08 7.52E 09 4.04E 08 2.20E 11 1.30L 09 0.00E-01 1.49E 08 l I 132 2.92E-01 7.65E-01 2.74E-01 2.58E 01 1.20E 00 0.00E-01 3.33E-01 ! 7 133 7.07E 06 1.20E 07 3.66E 06 1.67E 09 2.10E 07 0.00E-01 9.08E 06 I 134 3.61E-12 9.58E-12 3.44E-12 1.60E-10 1.51E-11 0.00E-01 1.26E-13 I 135 2.28E 04 5.88E 04 2.18E 04 3.78E 06 9.28E 04 0.00E-01 6.51E 04 CS 134 9.82E 09 2.31E 10 1.07E 10 0.00E-01 7.34E 09 2.80E 09 2.87E 08 ! CS 136 4.44E 08 1.75E 09 1.17E 09 0.00E-01 9.52E 08 1.50E 08 1.41E 08 l l CS 137 1.34E 10 1.78E 10 6.20E 09 0.00E-01 6.06E 09 2.35E 09 2.53E 08 i CS 138 1.66E-23 3.19E-23 1.60E-23 0.00E-01 2.36E-23 2.74E-24 1.45E-26 l BA 139 8.44E-08 5.94E-11 2.46E-09 0.00E-01 5.60E-11 4.09E-11 7.53E-07 BA 140 4.85E 07 5.95E 04 3.13E 06 0.00E-01 2.02E 04 4.00E 04 7.48E 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 I LA 140 8.12E 00 3.99E 00 1.06E 00 0.00E-01 0.00E-01 0.00E-01 2.29E 05 l LA 142 1.69E-11 7.52E-12 1.87E-12 0.00E-01 0.00E-01 0.00E-01 2.29E-07 CE 141 8.88E 03 5.93E 03 6.81E 02 0.00E-01 2.79E 03 0.00E-01 1.70E 07 CE 143 7.64E 01 5.56E 04 6.21E 00 0.00E-01 2.49E 01 0.00E-01 1.67E 06 CE 144 6.58E 05 2.72E 05 3.54E 04 0.00E-01 1.63E 05 0.00E-01 1.66E 08 PR 143 2.90E 02 1.16E 02 1.44E 01 0.00E-01 6.73E 01 0.00E-01 9.55E 05 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 1.82E 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 0.00E-01 0.00E-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

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 157 of 188 ATTACHMENT A (Page 153 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-8 GRASS-COW-MILK PATHWAY EACTOR M2 MREM /YR PER pCI/SEC CHILD (RI EACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-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 08 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 0.00E-01 0.00E-01 2.15E 09 l CR 51 0.00E-01 0.00E-01 1.02E 05 5.65E 04 1.54E 04 1.03E 05 5.40E 06 MN 54 0.00E-01 2.10E 07 5.59E 06 0.00E-01 5.88E 06 0.00E-01 1.76E 07 MN 56 0.00E-01 1.29E-02 2.90E-03 0.00E-01 1.56E-02 0.00E-01 1.86E 00 FE 55 1.12E 08 5.93E 07 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 0,00E-01 0.00E-01 7.07E 07 CO 60 0.00E-01 4.32E 07 1.27E 08 0.00E-01 0.00E-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 0.00E-01 0.00E-01 2.39E 01 CU 64 0.00E-01 7.47E 04 4.51E 04 0.00E-01 1.81E 05 0.00E-01 3.51E 06 ZN 65 4.13E 09 1.10E 10 6.85E 09 0.00E-01 6.94E 09 0.00E-01 1.93E 09 ZN 69 2.36E-11 3.42E-11 3.16E-12 0.00E-01 2.07E-10 0.00E-01 2.15E-09 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 BR 85 0.00E-01 0.00%-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 U.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-01 9.15E 05 Y 91M 2.70E-19 0.00E-01 9.82E-21 0.00E-01 0.00E-01 0.00E-01 5.29E-16 Y 91 3.90E 04 0.005-01 1.04E 03 0.00E-01 0.00E-01 0.00E-01 5.20E 06 _Y 92 2.54E-04 0.00E-01 7.26E-06 0.00E-01 0.00E-01 0.00E-01 7.33E 00 Y 93 1.06E 00 0.00E-01 2.90E-02 0.00E-01 0.00E-01 0.00E-01 1.57E 04 ZR 95 3.83E 03 8.43E 02 7.50E 02 0.00E-01 1.21E 03 0.00E-01 8.79E 05 ZR 47 1.92E 00 2.77E-01 1.64E-01 0.00E-01 3.98E-01 0.00E-01 4.20E 04 NB 95 3.18E 05 1.24E 05 8.85E 04 0.00E-01 1.16E 05 0.00E-01 2.29E 08 MO 99 0.00E-01 8.14E 07 2.01E 07 0.00E-01 1.74E 08 0.00E-01 6.73E 07 TC 99M 1.32E 01 2.59E 01 4.30E 02 0.00E-01 3.77E 02 1.32E 01 1.48E 04

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference Use Page 158 of 188 i ATTACHMENT A (Page 154 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-8 (cont' d) GRASS-COW-MILK PATHWAY FACTOR M2 MREM /YR PER pCI/SEC CHILD (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RU 103 4.28E 03 0.00E-01 1.65E 03 0.00E-01 1.08E 04 0.00E-01 1.11E 05 RU 105 3.83E-03 0.00E-01 1.39E-03 0.00E-01 3.36E-02 0.00E-01 2.50E 00 RU 106 9.24E 04 0.00E-01 1.15E 04 0.00E-01 1.25E 05 0.00E-01 1.44E 06 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 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 n7 4.21E 07 8.75E 07 7.97E 08 0.00E-01 3.31E 08 TE 129 1. 2 9E- 3 9 3.60E-10 3.06E-10 9.21E-10 3.78E-09 0.00E-01 8.03E-08 ( TE 131M 1.60E 06 5.53E 05 5.89E 05 1.14E 06 5.36E 06 0.00E-01 2.24E 07 I TE 131 1.64E-32 5.01E-33 4.89E-33 1.26E-32 4.97E-32 0.00E-01 8.64E-32 I TE 132 1.02E 07 4.54E 06 5.48E 06 f.61E 06 4.21E 07 0.00E-01 4.57E 07 I 130 1.73E 06 3.49E 06 1.80E 06 3.85E 08 5.22E 06 0.00E-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 0.04E 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 I 135 5.41E 04 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 4.33E 09 2.00E 08 CS 136 1.00E 09 2.76E 09 1.78E 09 0.00E-01 1.47E 09 2.19E 08 9.69E 07 CS 137 3.22E 10 3.09E 10 4.55E 09 0.00E-01 1.01E 10 3.62E 09 1.93E 08 CS 138 4.03E-23 5.60E-23 3.55E-23 0.00E-01 3.94E-23 4.24E-24 2.58E-23 BA 139 2.07E-07 1.11E-10 6.01E-09 0.00E-01 9.67E-11 6.51E-11 1.20E-05 BA 140 1.17E 08 1.03E 05 6.84E 06 0.00E-01 3.34E 04 6.12E 04 5.94E 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 140 1.94E 01 6.80E 00 2.29E 00 0.00E-01 0.00E-01 0.00E-01 1.89E 05 LA 142 4.09E-11 1.30E-11 4.08E-12 0.00E-01 0.00E-01 0.00E-01 2.58E-06 CE 141 2.19E 04 1.09E 04 1.62E 03 0.00E-01 4.78E 03 0.00E-01 1.36E 07 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 0.00E-01 2.82E 05 0.00E-01 1.33E 08 PR 143 7.18E 02 2.16E 02 3.56E 01 0.00E-01 1.17E 02 0.00E-01 7.75E 05 PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i ND 147 4.47E 02 3.62E 02 2.80E 01 0.00E-01 1.99E 02 0.00E-01 5.73E 05 i W 187 2.91E 04 1.72E 04 7.73E 03 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 00 0.00E-01 9.16E 04 i

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Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 159 of 188 I l ATTACHMENT A

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1 l (Page 155 of 184) l l OFFSITE DOSE CALCULATION MANUAL i TABLE A.5-9 GRASS-COW-MILK PATHWAY FACTOR M2 MREM /YR PER pCI/SEC ! INFANT (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 2.38E 03 2.38E 03 2.38E 03 2.38E 03 38E 03 2.30E 03 l C 14 2.34E 09 5.00E 08 5.00E 08 5.00E 08 5.00E 08 5.00E 08 5.00E 08 l NA 24 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 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 0.00E-01 0.00E-01 1.61E 05 1.05E 05 2.30E 04 2.05E 05 4.70E 06 MN 54 0.00E-01 3.90E 07 8.84E 06 0.00E-01 8.64E 06 0.00E-01 1.43E 07 l 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 08 8.72E 07 2.33E 07 0.00E-01 0.00E-01 4.26E 07 1.11E 07 FE 59 2.24E 08 3.92E 08 1.54E 08 0.00E-01 0.00E-01 1.16E 08 1.87E 08 < CO 58 0.00E-01 2.43E 07 6.05E 07 0.00E-01 0.00E-01 0.00E-01 6.04E 07 CO 60 0.00E-01 8.82E 07 2.08E 08 0.00E-01 0.00E-01 0.00E-01 2.10E 08 l NI 63 3.49E 10 2.16E 09 1.21E 09 0.00E-01 0.00E-01 0.00E-01 1.07E 08 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 I ZN 65 5.55B 09 1.90E 10 0.78E 09 0.00E-01 9.23E 09 0.00E-01 1.61E 10 ZN 69 5.04E-11 9.07E-11 6.75E-12 0.00E-01 3.77E-11 0.00E-01 7.40E-09 l 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 i i 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 0.00E-01 0.00E-01 0.00E-01 l RB 86 0.00E-01 2.23E 10 1.10E 10 L 00E-01 0.00E-01 0.00E-01 5.70E 08 l 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 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 1.26E 10 0.00E-01 3.61E 08 0.00E-01 0.00E-01 0.00E-01 2.59E 08 j SR 90 1.22E 11 0.00E-01 3.10E 10 0.00E-01 0.00E-01 0.00E-01 1.52E 09 l ! SR 91 2.69E 05 0.00E-01 9.75E 02 0.00E-01 0.00E-01 0.00E-01 3.19E 05 SR 92 4.66E 00 0.00E-01 1.73E-01 0.00E-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 Y 91M 5.72E-19 0.00E-01 1.95E-20 0.00E-01 0.00E-01 0.00E-01 1.91E-15 l Y 91 7.33E 04 0.00E-01 1.95E 03 0.00E-01 0.00E-01 0.00E-01 5.25E 06 l Y 92 5.39E-04 0.00E-01 1.51E-05 0.00E-01 0.00E-01 0.00E-01 1.03E 01 l Y 93 2.25E 00 0.00E-01 6.13E-02 0.00E-01 0.00E-01 0.00E-01 1.78E 04 l l ZR 95 6.81E 03 1.66E 03 1.18E 03 0.00E-01 1.79E 03 0.00E-01 8.26E 05 l ZR 97 4.06E 00 6.98E-01 3.19E-01 0.00E-01 7.03E-01 0.00E-01 4.45E 04 NB 95 5.94E 05 2.45E 05 1.41E 05 0.00E-01 1.75E 05 0.00E-01 2.06E 08 MO 99 0.00E-01 2.08E 08 4.06E 07 0.00E-01 3.11E 08 0.00E-01 6.85E 07 TC 99M 2.75E 01 5.68E 01 7.31E 02 0.00E-01 6.11E 02 2.97E 01 1.65E 04

i Revision: 1 OF 7TTE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 160 of 188 ATTACHMENT A (Page 156 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-9 (cont' d) GRASS-COW-MILK PATHWAY FACTOR l M2 MREM /YR PER CI/SEC INFANT (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI I TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i RU 103 8.67E 03 0.00E-01 2.90E 03 0.00E-01 1.80E 04 0.00E-01 1.05E 05 j RU 105 8.07E-03 0.00E-01 2.72E-02 0.00E-01 5.93E-01 0.00E-01 3.21E 00 l 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 08 2.82E 08 1.86E 08 0.00E-01 4.03E 08 0.00E-01 1.46E 10 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 0.00E-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 TE 129 2.74E-09 9.43E-10 6.39E-09 2.29E-08 6.81E-08 0.00E-01 2.19E-07 TE 131M 3.38E 06 1.36E 06 1.12E 06 2.76E 06 9.36E 06 0.00E-01 2.29E 07 TE 131 3.49E-32 1.29E-32 9.78E-32 3.11F.-31 8.91E-31 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 I 131 2.72E 09 3.21E 09 1.41E 09 1.05E 12 3.74E 09 0.00E-01 1.14E 08 I 132 1.43E 00 ^ 91E 00

                           .          1.04E 00    1.37E 02   3.25E 00 0.00E-01   2.36E 00 I    133 3.63E 07      5.28E 07    1.55E 07    9.61E 09   6.21E 07 0.00E-01   8.94E 06 I    134 1.77E-11      3.63E-11    1.29E-10    8.47E-09   4.06E-10 0.00E-01   3.76E-11 I    135 1.12E ;3      2.24E 05    8.15E 04    2.00E 07   2.49E 05 0.00E-01   8.09E 04 CS    134 3. 6 5r.      6.80. 10    6.07E 09    0.00E-01   1.75E 10 6.21E 09   1.85E 08 CS    136 1. 9 6E 0 9 5.76E 09    2.15E 09    0.00E-01   2.30E 09 4.70E 08   8.75E 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    6.70E-22    0.00E-01   6.89E-22 1.08E-23   2.21E-22 l BA    139 4.41E-07      2.93E-10    1.28E-07    0.00E-01   1.76E-09 1.77E-10   2.80E-05 BA    140 2.41E 08      2.41E 08    1.24E 07    0.00E-01   5.72E 04 1.48E 05   5.92E 07 BA    141 0.0CE-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 4.06E 01 1.60E 01 4.12E 00 0.00E-01 0.00E-01 0.00E-01 1.88E 05 I LA 142 8.59E-11 3.15E-11 7.55E-11 0.00E-01 0.00E-01 0.00E-01 5.36E-06 j CE 241 4.34E 04 2.64E 04 3.11E 03 0.00E-01 0.16E 03 0.00E-01 1.37E 07 i CE 143 3.97E 02 2.63E 05 3.00E 01 0.00E-01 7.f7E 01 0.00E-01 1.54E 06 CE 144 2.33E L6 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 7.84E 05 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 8.86E O2 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 0.00E-01 0.00E-01 0.00E-01 2.50E 06 NP 239 3.65E 01 3.26E 00 1.84E 00 0.00E-01 1.50E 00 0.00E-01 9.43E 04 i l l l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 161 of 188 ATTACHMENT A (Page 157 of 184) OFFSITE DOSE CALCULATION KANUAL TABLE A.5-10 GRASS-COW-MEAT PATHWAY FACT ( P M2 MREM /YR PER pCI/SEC ADULT (RI FACTORS) NtiCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 C 14 2.41E 08 4.83E 07 4.83E07 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 0.00E-01 CR 51 0.00E-01 0.00E-01 7.05E 03 4.21E 03 1.55E 03 9.35E 03 1.77E 06 MN 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 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 FE 55 2.93E 08 2.20E 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 2.08E 09 CO 58 0.00E-01 1.82E 07 4.09E 07 0.00E-01 0.00E-01 0.00E-01 3.70E 08 CO 60 0.00E-01 7.52E 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-01 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-01 CU 64 0.00e-01 2.73E-07 1.28E-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 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 0.005-01 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 4.87E 08 2.27E V8 0.00E-01 0.00E-01 0.00E-01 9.61E 07 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 3.02E 08 0.00E-01 8.66E 06 0.00E-01 0.00E-01 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 1.43E-10 0.00E-01 5.73E-12 0.00E-01 0.00E-01 0.00E-01 6.76E-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 1.07E 02 0.00E-01 2.86E 00 0.00E-01 0.00E-01 0.00E-01 1.13E 06 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 1.13E 06 0.00E-01 3.03E 04 0.00E-01 0.00E-01 0.00E-01 6.23E 08 Y 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E L1 Y 93 6.59E-12 0.00E-01 1.82E-13 0.00E-01 0.00E-01 0.00E-01 2.09E-07 ZR 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 6.33E-06 0.00E-01 1.30E 00 i NB 95 2.30E 06 1.28E 06 6.88E 05 0.00E-01 1.26E 06 0.00E-01 7.76E 09 i MO 99 0.00E-01 9.99E 04 1.90E 04 0.00E-01 2.26E 05 0.00E-01 2.32E 05 1 TC 99M 4.50E-21 1.27E-20 1.62E-10 0.00E-01 1.93E-19 6.23E-21 7.53E-18 I I TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i i

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l Revision: 1 0FFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 162 of 188 i l' ATTACHMENT A (Page 158 of 184) 0FFSITE DOSE CALCULATION MANUAL TABLE A.5-10 (cont'd) l GRASS-COW-MEAT PATHWAY FACTOR 2 M MREM /YR PER pCI/SEC ' ADULT (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI I RU 103 1.05E 08 0.00E-01 4.53E 07 0.00E-01 4.01E 08 0.00E-01 1.23E 10 ] RU 105 5.87E-28 0.00E-01 2.32E-28 0.00E-01 7.58E-27 0.00E-01 3.59E-25 J RU 106 2.80E 09 0.00E-01 3.54E 08 0.00E-01 5.40E 09 0.00E-01 1.81E 11 i AG 110M 6.68E 06 6.18E 06 3.67E 06 0.00E-01 1.22E 07 0.00E-01 2.52E 09 I 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 j TE 129 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-03 0.00E-01 n.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 1 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 3.67E-01 6.38E-01 1.94E-01 9.37E 01 1.11E 00 0.00E-01 5.73E-01 I 134 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1 I 135 4.47E-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 1.28E 09 0.00E-01 5.06E 08 1.68E 08 2.74E 07 CS 136 1.18E 07 4.66E 07 3.353 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 0.00E-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 2.87E 07 3.61E 04 1.88E 06 0.00E-01 1.23E 04 2.07E 04 5.92E 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 140 3.76E-02 1.89E-02 5.00E-03 0.00E-01 0.00E-01 0.00E-01 1.39E 03 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 1.40E 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 6.55E-03 0.00E-01 5.56E 02 CE 144 1.46E 06 6.09E 05 9.83E 04 0.00E-01 3.61E 05 0.00E-01 4.93E 08 l 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 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01  ; ND 147 7.17E 03 8.29E 03 4.96E 02 0.00E-01 4.84E 03 0.00E-01 3.98E 07 l W 187 2.17E-02 1.81E-02 6.33E-03 0.00E-01 0.00E-01 0.00E-01 5.93E 00 1 NP 239 2.59E-01 2.55E-02 1.40E-02 0.00E-01 7.94E-02 0.00E-01 5.22E 03 1 1 l s

Revision: 1 OFFSITE DOSE CALCULATION MANUAL .5P 07B-003 Reference Use 5 age 163of188 ATTACHMENT A (Page 159 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-11 GRASS-COW-MEAT PATHWAY FACTOR Ma MREM /YR PER pCI/SEC TEEN (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG 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 4.00E 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 03 2.44E 08 1.52E 08 0.00E-01 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 1.01E 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-01 0.00E-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-01 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 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 0.06E-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 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 2.55E 08 0.00F-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-01 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-01 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 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 Y 93 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 ZR 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-21 1.29E-19 0.00E-01 1.49E-19 5.54E-21 6.55E-18 I

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I i j Revision: 1 0FFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 164 of 188 j l ! 1 1 ATTACHMENT A (Page 160 of 184) , OFFSITE DOSE CALCULATION MANUAL l l TABLE A.5-11 (cont' d) GRASS-COW-MEAT PATHWAY FACTOR M* MREM /YR PER pCI/SEC TEEN (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RU 103 8.56E 07 0.00E-01 3.66E 07 0.00E-01 3.02E 08 0.00E-01 7.15E 09 RU 105 4.91E-28 0.00E-01 1.91E-28 0.00E-01 6.91E-27 0.00E-01 3.96E-25 RU 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 125M 3.03E 08 1.09E 03 4.05E 07 8.47E 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-09 7.35E-10 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 l l 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 1.08E 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 I 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 l 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 I 134 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l l I 135 3.64E-17 9.37E-17 3.47E-17 6.03E-15 1.48E-16 0.00E-01 1.04E-16 l CS 134 5.23E 08 1.23E 09 5.71E 08 0.00E-01 3.91E 08 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 l 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 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 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 l LA 140 3.09E-02 1.52E-02 4.04E-03 0.00E-01 0.00E-01 0.00E-01 8.72E 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 l CE 141 1.18E 04 7.88E 03 9.05E 02 0.00E-01 3.71E 03 0.00E-01 2.25E 07 CE 143 1.69E-02 1.23E 01 1.38E-03 0.00E-01 5.53E-03 0.00E-01 3.70E 02 CE 144 1.235 06 5.08E 05 6.60E 04 0.00E-01 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 l i PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l ND 147 6.32E 03 6.87E 03 4.11E 02 0.00E-01 4.03E 03 0.00E-01 2.48E 07 W 187 1.81E-02 1.48E-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 l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 165 of 188 ATTACHMENT A (Page 161 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-12 GRASS-CCW-MEAT PATHWAY FACTOR M2 HREM/YR PER pCI/SEC CHILD (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-0~ 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 c MN 56 0.00E-01 1.63E-53 3.67E-54 0.00E-01 1.97E-53 0.00E-01 2.36E-51 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 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 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 3.00E-07 1.81E-07 0.00E-01 7.24E-07 0.00E-01 1.41E-05 ZN 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 J BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1 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 5.77E 08 3.55E 08 0.00E-01 0.00E-01 0.00E-01 3.71E 07 i RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 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-01 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 l Y 90 1.70E 02 0.00E-01 4.55E 00 0.00E-01 0.00E-01 0.00E-01 4.84E 05 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 04 0.00E-01 0.00E-01 0.00E-01 2.40E 08 Y 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 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 0.00E-01 8.38E 05 0.00E-01 6.11E 08 ZR 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 MO 99 0.00E-01 1.15E 05 2.84E 04 0.00E-01 2.45E 05 0.00E-01 9.51E 04 TC 99M 6.27E-21 1.23E-20 2.04E-19 0.00E-01 1.79E-19 6.24E-21 7.00E-18

Revision: 1 OFFSITE DOSE CALCULATION MAPUAL AP 07B-003 Reference Use Page 166 of 188 ATTACHMENT A (Page 162 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-12 (cont' d) GRASS-COW-MEAT PATHWAY FACTOR M8 MREM /YR PER pCI/SEC CHILD (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-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 9.16E-28 0.00E-01 3.32E-28 0.00E-01 8.05E-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 3.41E-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 2.78E 08 5.77E 08 5.26E 09 0.00E-01 2.18E 09 TE 129 9.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-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 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 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 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I 133 5.70E-01 7.04E-01 2.66E-01 1.31E 02 1.17E 00 0.00E-01 2.84E-01 I 134 0.00E-01 0.00E-01 0.00E-Oi 0.00E-01 0.00E-01 0.00E-01 0.00E-01 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 CS 137 1.33E 09 1.28E 09 1.88E 08 0.00E-01 4.16E 08 1.50E 08 7.99E 06 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 2.22E 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 ?42 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 5.66E-02 1.98E-02 6.66E-03 0.00E-01 0.00E-01 0.00E-01 5.51E 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 2.22E 04 1.11E 04 1.64E 03 0.00E-01 4.86E 03 0.00E-01 1.30E 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 0.00E-01 1.89E 08 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 1.992-02 8.94E-03 0.00E-01 0.00E-01 0.00E-01 2.80E 00 NP 239 4.26E-01 3.06E-02 2.15E-02 0.00E-01 8.84E-02 0.00E-01 2.26E 03

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 167 of 188 ATTACHMENT A (Page 163 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-13 VEGETATION PATHWAY FACTOR M3 MREM /YR PER pCI/SEC ADULT (RI FACTORS) , I NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI 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 00 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 i 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 54 0.00E-01 3.13E 08 5.97E 07 0.00E-01 9.31E 07 0.00E-01 9.58E 08 MN 56 0.00E-01 1.59E 01 2.82E 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 07 FE 59 1.26E 08 2.96E 08 1.14E 08 0.00E-01 0.00E-01 8.28E 07 9.83E 08 CO 58 0.00E-01 3.07E 07 6.89E 07 0.00E-01 0.00E-01 0.00E-01 6.23E 08 CO 60 0.00E-01 1.67E 08 3.69E 08 0.00E-01 0.00E-01 0.00E-01 3.14E 09 l NI 63 1.04E 10 7.28E 08 3.49E 08 0.00E-01 0.00E-01 0.00E-01 1.50E 08 l NI 65 6.93E 01 9.01E 00 4.11E 00 0.f?"-01 0.00E-01 0.00E-01 2.28E 02 l CU 64 0.00E-01 9.71E 03 4.32E 03 01 01 2.32E 04 0.00E-01 7.85E 05  ! ZN 65 3.17E 08 1.s1E 09 4.56E OB 0. 0t.t -01 6.75E 08 0.00E-01 6.36E 08 ZN 69 8.77E-06 1.68E-05 1.17E-06 0.00E-01 1.09E-05 0.00E-01 2.52E-06 BR 83 0.00E-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 2.49E-11 0.00E-01 0.00E-01 0.00E-01 1.96E-16 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 2.19E 08 1.02E 08 0.00E-01 0.00E-01 0.00E-01 4.33E 07 RB 88 0.00E-01 3.47E-22 1.84E-22 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 89 0.00E-01 1.41E-26 9.88E-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-01 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 4.27E 02 0.00E-01 1.85E 01 0.00E-01 0.00E-01 0.00E-01 8.46E 03 Y 90 1.33E 04 0.00E-01 3.56E 02 0.00E-01 0.00E-01 0.00E-01 1.41E 08 Y 91M 5.24E-09 0.00E-01 2.03E-10 0.00E-01 0.00E-01 0.00E-01 1,54E-00 Y 91 5.11E 06 0.00E-01 1.37E 05 0.00E-01 0.00E-01 0.00E-01 2.81E 09 Y 92 9.16E-01 0.00E-01 2.68E-02 0.00E-01 0.00E-01 0.00E-01 1.60E 04 Y 93 1.74E 02 0.00E-01 4.81E 00 0.00E-01 0.00E-01 0.00E-01 5.52E 06 ZR 95 1.18E 06 3.77E 05 2.55E 05 0.00E-01 5.92E 05 0.00E-01 1.20E 09 ZR 97 3.37E 02 6.81E 01 3.11E 01 0.00E-01 1.03E 02 0.00E-01 2.11E 07 NB 95 1.43E OL 7.93E 04 4.26E 04 0.00E-01 7.84E 04 0.00E-01 4.81E 08 HO 99 0.00E-01 6.15E 06 1.17E 06 0.00E-01 1.39E 07 0.00E-01 1.43E 07 TC 99M 3.10E 00 8.77E 00 1.12E 02 0.00E-01 1.33E 02 4.30E 00 5.19E 03

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 168 of 188 ATTACHMENT A (Page 164 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-13 (cont'd) VEGETATION PATHWAY FACTOR M3 MREM /YR PER pCI/SEC ADULT (RI FACTORS) NUCLTDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.34E-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-01 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 7.65E-04 2.87E-04 1.86E-01 5.87E-04 3.22E-03 0.00E-01 5.77E-04 TE 131M 9.12E 05 4.46E 05 3.72E 05 7.07E 05 4.52E 06 0.00E-01 4.43E 07 TE 131 1.51E-15 6.32E-16 4.78E-16 1.24E-15 6.63E-15 0.00E-01 2.14E-16 TE 132 4.30E OC 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 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 08 6.33E 06 0.00E-01 3.26E 06 I 134 9.69E-05 2.63E-04 9.42E-05 4.56E-03 4.19E-04 0.00E-01 2.30E-07 I 135 3.90E 04 1.02E 05 3.77E 04 6.74E 06 1.64E 05 0.00E-01 1.15E 05 CS 134 4.67E 09 1.11E 10 9.08E 09 0.00E-01 3.59E 09 1.19E 09 1.94E 08 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 0.006-01 2.95E 09 9.81E 08 1.68E 08 CS 138 3.94E-11 7.78E-11 3.86E-11 0.00E-01 5.72E-11 5.65E-12 3.32E-16 BA 139 2.90E-02 2.07E-05 8.50E-04 0.00E-01 1.93E-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 1.28E-21 9.64E-25 4.31E-23 0.00E-01 8.96E-25 5.47E-25 6.01E-31 BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l l LA 140 1.98E 03 9.99E 02 2.64E 02 0.00E-01 0.00E-01 0.00E-01 7.33E 07 LA 142 1.42E-04 6.44E-05 1.61E-05 0.00E-01 0.00E-01 0.00E-01 4.70E-01 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 CE 144 3.29E 07 1.38E 07 1.77E 06 0.00E-01 0.16E 06 0.00E-01 1.11E 10 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 3.13E-26 1.30E-26 1.59E-27 0.00E-01 7.32E-27 0.00E-01 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 l W 187 3.82E 04 3.20E 04 1.12E 04 0.00E-01 0.00E-01 0.00E-01 1.05E 07 j NP 239 1.43E 03 1.40E 02 7.74E 01 0.00E-01 4.38E 02 0.00E-01 2.88E 07 l l J l j

E l l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 169 of 188 ATTACHMENT A (Page 165 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-14 VEGETATION PATHWAY FACTOR M2 MREM /YR PER pCI/SEC TEEN (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG 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 ~.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 I P 32 1.61E 09 9.96E 07 6.2SE 07 0.00E-01 0.00E-01 0.00E-01 1.35E 08 I CR 51 0.00E-01 0.00E-01 6.17E 04 3.43E 04 1.35E 04 8.81E 04 1.04E 07 l MN 54 0.00E-01 4.54E 08 9.01E 07 0.00E-01 1.36E 08 0.00E-01 9.32E 08 FD1 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-01 0.00E-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 09 0.00E-01 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 l NI 65 6.45E 01 8.24E 00 3.76E 00 0.00E-01 0.00E-01 0.00E-01 4.47E 02 CU 64 0.00E-01 8.34E 03 3.92E 03 0.00E-01 2.11E 04 0.00E-01 6.47E 05 ZN 65 4.24E 08 1.47E 09 6.86E 08 0.00E-01 9.42E 08 0.00E-01 6.23E 08 ZN 69 8.21E-06 1.56E 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-16 i BR 84 0.00E-01 0.00E-01 2.27E-11 0.00E-01 0.00E-01 0.00E-01 3.14E-28 l l BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l RB 86 0.00E-01 2.74E 08 1.29E 08 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 RB 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 SR 90 7.51E 11 0.00E-01 1.85E 11 0.00E-01 0.00E-01 0.00E-01 2.11E 10 SR 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 02 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 Y 91M 4.88E-09 0.00E-01 1.87E-10 0.00E-01 0.00E-01 0.00E-01 2.30E-07 Y 91 7.84E 06 0.00E-01 2.10E 05 0.00E-01 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 1 I Y 93 1.63E 02 0.00E-01 4.47E 00 0.00E-01 0.00E-01 0.00E-01 4.99E 06 ZR 95 1.72E 06 5.44E 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-01 9.37E 01 0.00E-01 1.67E 07 NB 95 1.93E 05 1.07E 05 5.88E 04 0.00E-01 1.04E 05 0.00E-01 4.57E 08 MO 99 0.00E-01 5.65E 06 1.08E 06 0.00E-01 1.29E 07 0.00E-01 1.01E 07 TC 99M 2.74E 00 7.64E 00 9.90E 01 0.00E-01 1.14E 02 4.24E 00 5.02E 03 l 1^ l 1 l

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 l Reference Use Page 170 of 188 l ATTACHMENT A-(Page 166 of 184) i OFFSITE DOSE CALCULATION MANUAL l l TABLE A.5-14 (cont' d) VEGETATION PATHWAY FACTOR M' MREM /YR PER pCI/SEC TEEN (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 7.76E-31 1.10E-30 1.08E-29 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 6.32E 02 0.00E-01 4.04E 04 RU 106 3.09E 08 0.00E-01 3.90E 07 0.00E-01 5.97E 08 0.00E-01 1.48E 10 AG 110M 1.52E 07 1.43E 07 8.72E 06 0.00E-01 2.74E 07 0.00E-01 4.03E 09 i TE 125M 1.48E 08 5.34E 07 1.98E 07 4.14E 07 0.00E-01 0.00E-01 4.39E 08 I i TE 127M 5.52E 08 1.96E 08 6.56E 07 1.31E 08 2.24E 09 0.00E-01 1.37E 09 l 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 1.36E 09 TE 129 7.16E-04 2.67E-04 1.74E-04 5.12E-04 3.01E-03 0.00E-01 3.92E-03 TE 131M 8.44E 05 4.05E 05 3.38E 05 6.09E 05 4.22E 06 0.00E-01 3.25E 07 TE 131 1.41E-14 5.80E-16 4.40E-16 1.00E-15 6.15E-15 0.00E-01 1.15E-16 TE 132 3.91E 06 2.48E 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 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 2.08E 08 CS 136 4.28E 07 1.68E 08 1.13E 08 0.00E-01 9.16E 07 1.44E 07 1.35E 07 CS 137 1.01E 10 1.35E 10 4.69E 09 0.00E-01 4.59E 09 1.78E 09 1.92E 08 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 1.81E-05 1.32E-05 2.44E-01 BA 140 1.38E 08 1.69E 05 8.91E 06 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-01 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 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 0.00E-01 3.04E 02 0.00E-01 2.04E 07 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 l 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 s

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 171 of 188 ATTACHMENT A (Page 167 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-15 VEGETATION PATHWAY FACTOR M2 MREM /YR PER pCI/SEC CHILD (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI 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 3.37E 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 MN 54 0.00E-01 6.65E 08 1.77E 08 0.00E-01 1.86E 08 0.00E-01 5.58E 08 MN 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 0.00E-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-01 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 2.11E 09 1.34E 09 0.00E-01 0.00E-01 0.00E-01 1.42E 08 NI 65 1.18E 02 1.11E 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 1.36E 09 0.00E-01 3.80E 08 ZN 69 1.51E-05 2.19E-05 2.02E-06 0.00E-01 1.33E-05 0.00E-01 1.38E-03 BR 83 0.00E-01 0.00E-01 5.38E 00 0.00E-01 0.00E-01 0.00E-01 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 00 2.78E 08 0.00E-01 0.00E-01 0.00E-01 2.91E 07 RB 88 0.00E-01 4.43E-22 3.08E-22 0.00E-01 0.00E-01 0.00E-01 2.17E-23 RB 89 0.00E-01 1.67E-26 1.48E-26 0.00E-01 0.00E-01 0.00E-01 1.45E-28 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-01 0.00E-01 1.15E 06 SR 92 7.29E 02 0.00E-01 2.92E 01 0.00E-01 0.00E-01 0.00E-01 1.30E 04 Y 90 2.30E 04 0.00E-01 6.17E 02 0.00E-01 0.00E-01 0.00E-01 6.56E 07 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 Y 92 1.59E 00 0.00E-01 4.54E-02 0.00E-01 0.00E-01 0.00E-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 ZR 95 3.86E 06 8.49E 05 7.56E 05 0.00E-01 1.22E 06 0.00E-01 8.85E 08 ZR 97 5.70E 02 8.24E 01 4.86E 01 0.00E-01 1.18E 02 0.00E-01 1.25E 07 NB 95 4.11E 05 1.60E 05 1.14E 05 0.00E-01 1.50E 05 0.00E-01 2.96E 08 MO 99 0.00E-01 7.71E 06 1.91E 06 0.00E-01 1.65E 07 0.00E-01 6.38E 06 TC 99M 4.71E 00 9.24E 00 1.51E 02 0.00E-01 1.34E 02 4.69E 00 5.26E 03

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 172 of 188 ATTACHMENT A (Page 168 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-15 (cont' d) VEGETATION PATHWAY FACTOR M2 MREM /YR PER pCI/SEC CHILD (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 1.43E-30 1.49E-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 RU 105 9.17E 01 0.00E-01 3.3?E 01 0.00E-01 0.06E 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 '.16E 08 3.77E 09 0.00E-01 1.07E 09 TE 127 9.85E 03 2.66E 03 2.11E 03 6.82E 03 2.80E 04 0.00E-01 3.85E 05 TE 129M 8.41E 08 2.35E 08 1.30E 08 2.71E 08 2.47E 09 0.00E-01 1.03E 09 TE 129 1.33E-03 3.70E-04 3.15E-04 9.46E-04 3.88E-03 0.00E-01 8.25E-02 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 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 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-04 4.42E-04 0.00E-01 1.92E-04 I 135 6.26E 04 1.13E 05 5.33E 04 9.98E 06 1.73E 05 0.00E-01 8.59E 04 CS 134 1.60E 10 2.63E 10 5.55E 09 0.00E-01 8.15E 09 2.93E 09 1.42E 08 CS 136 8.04E 07 2.21E 08 1.43E 08 0.00E-01 1.18E 08 1.76E 07 7.77E 06 CS 137 2.39E 10 2.29E 10 3.38E 09 0.00E-01 7.46E 09 2.68E 09 1.43E 08 CS 138 6.61E-11 9.20E-11 5.83E-11 0.00E-01 6.47E-11 6.96E-12 4.24E-11 BA 139 5.04E-02 2.69E-05 1.46E-03 0.00E-01 2.35E-05 1.58E-05 2.91E 00 BA 140 2.77E 08 2.43E 05 1.62E 07 0.00E-01 7.90E 04 1.45E 05 1.40E 08 BA 141 2.20E-21 1.23E-24 7.16E-23 0.00E-01 1.07E-24 7.24E-24 1.25E-21 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 3,25E 03 1.14E 03 3.83E 02 0.00E-01 0.00E-01 0.00E-01 3.17E 07 LA 142 2.36E-04 7.51E-05 2.35E-05 0.00E-01 0.00E-01 0.00E-01 1.49E 01 CE 141 6.56E 05 3.27E 05 4.86E 04 0.00E-01 1.43E 05 0.00E-01 4.08E 08 CE 143 1.72E 03 9.31E 05 1.35E 02 0.00E-01 3.91E 02 0.00E-01 1.36E 07 CE 144 1.27E 08 3.98E 07 6.78E 06 0.00E-01 2.21E 07 0.00E-01 1.04E 10 PR 143 1.46E 05 4.38E 04 7.23E 03 0.00E-01 2.37E 04 0.00E-01 1.57E 08 PR 144 5.44E-26 1.68E-26 2.74E-27 0.00E-01 8.90E-27 0.00E-01 3.62E-23 ND 147 7.24E 04 5.86E 04 4.54E 03 0.00E-01 3.22E 04 0.00E-01 9.29E 07 W 187 6.47E 04 3.83E 04 1.72E 04 0.00E-01 0.00E-01 0.00E-01 5.38E 07 NP 239 2.56E 03 1.84E 02 1.29E 02 0.00E-01 5.31E 02 0.00E-01 1.36E 07

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 173 of 188 ATTACHMENT A (Page 169 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-16 GROUND PLANE PATHWAY FACTOR M2 MREM /YR PER pCI/SEC (RI FACTOR) H-3 0.00E 00 Y-91M 1.00E 05 CS-134 6.86E 09 C-14 0.00E 00 Y-91 1.07E 06 CS-136 1.49E 08 NA-24 1.19E 07 Y-92 1.80E 05 CS-137 1.03E 10 P-32 0.00E 00 Y-93 1.85E 05 CS-138 3.59E 05 CR-51 4.66E 06 ZR-95 2.45E 08 BA-139 1.06E 05 j MN-54 1.39E 09 ZR-97 2.96E 06 BA-140 2.05E 07  ! MN-56 9.03E 05 NB-95 1.37E 08 BA-141 4.18E 04 FE-55 0.00E 00 MO-99 3.99E 06 BA-142 4.49E 04 FE-59 2.73E 08 TC-99M 1.84E 05 LA-140 1.92E 07 TC-101 2.04E 04  ! CO-58 3.79E 08 RU-103 1.08E 08 LA-142 7.37E 05  ! CO-60 2.15E 10 RU-105 6.36E 05 CE-141 1.37E 07 l NI-63 0.00E 00 RU-106 4.21E 08 CE-143 2.31E 06 l NI-65 3.02E 05 AG-110M 3.44E 09 CE-144 6.96E 07 CU-64 6.07E 05 TE-125M 1.55E 06 PR-143 0.00E 00 ZN-65 7.46E 08 TE-127M 9.17E 04 PR-144 1.83E 03 ZN-69 0.00E 00 TE-127 2.98E 03 ND-147 8.46E 06 BR-83 4.87E 03 TE-129M 1.98E 07 W-187 2.36E 06 BR-84 2.03E 05 TE-129 2.62E 04- NP-239 1.71E 06 BR-85 0.00E 00 TE-131M 8.03E 06 RB-86 8.99E 06 TE-131 2.92E 04 RB-88 3.31E 04 TE-132 4.23E 06 RB-89 1.21E 05 I-130 5.51E 06 SR-89 2.16E 04 I-131 1.72E 07 SR-90 0.00E 00 I-132 1.25E 06 SR-91 2.14E 06 I-133 2.45E 06 SR-92 7.77E 05 I-134 4.47E 05 Y-90 4.49E 03 I-135 2.53E 06 i l

1 AP 07B-003 Revision: 1 OFFSITE DOSE CALCULATION MANUAL Reference Use Page 174 of 188 l l ATTACHMENT A (Page 170 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-17 GRASS-GOAT-MILK PATHAAY FACTOR M2 MREM /YR PER pCI/SEC

ADULT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 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 5.27E 07 5.27E 07 l NA 24 2.93E 05 2.93E 05 2.93E 05 2.93E 05 2.93E 05 2.93E 05 2.93E 05 P 32 2.05E 10 1.27E 09 7.93E 08 0.00E-01 0.00E-01 0.00E-01 2.31E 09 CR 51 0.00E-01 0.00E-01 3.43E 03 2.05E 03 7.55E 02 4.55E 03 8.62E 05 MN 54 0.00E-01 1.01E 06 1.93E 05 0.00E-01 3.00E 05 0.00E-01 3.09E 06 l

MN 56 0.00E-01 4.99E-03 8.85E-04 0.00E-01 6.34E-03 0.00E-01 1.59E-01 l FE 55 3.26E 05 2.25E 05 5.26E 04 0.00E-01 0.00E-01 1.26E 05 1.29E 05 l FE 59 3.66E 05 9.07E 05 3.48E 05 0.00E-01 0.00E-01 2.54E 05 3.02E 06 CO 58 0.00E-01 5.66E 05 1.27E 06 0.00E-01 0.00E-01 0.00E-01 1.15E 07 CO 60 0.00E-01 1.97E 06 4.34E 06 0.00E-01 0.00E-01 0.00E-01 3.70E 07 NI 63 8.07E 08 5.65E 07 2.71E 07 0.00E-01 0.00E-01 0.00E-01 1.17E 07 l NI 65 5.56E-02 7.22E-03 3.30E-03 0.00E-01 0.00E-01 0.00E-01 1.83E-01 l CU 64 0.00E-01 2.66E 03 1.25E 03 0.00E-01 6.70E 03 0.00E-01 2.27E 05 1 ZN 65 1.65E 08 5.24E 08 2.37E 08 0.00E-01 3.50E 08 0.00E-01 3.30E 08 ZN 69 6.27E-13 1.20E-12 8.34E-14 0.00E-01 7.79E-13 0.00E-01 1.80E-13 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 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 3.11E 08 1.45E 08 0.00E-01 0.00E-01 0.00E-01 6.14E 07 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 3.05E 09 0.00E-01 8.75E 07 0.00E-01 0.00E-01 0.00E-01 4.89E 08 SR 90 9.83E 10 0.00E-01 2.41E 10 0.00E-01 0.00E-01 0.00E-01 2.84E 09 SR 91 6.02E 04 0.00E-01 2.43E 03 0.00E-01 0.00E-01 0.00E-01 2.87E 05 SR 92 1.03E 00 0.00E-01 4.45E-01 0.00E-01 0.00E-01 0.00E-01 2.04E 01 Y 90 8.49E 00 0.00E-01 2.28E-00 0.00E-01 0.00E-01 0.00E-01 9.00E 04 Y 91M 7.24E-21 0.00E-01 2.80E-22 0.00E-01 0.00E-01 0.00E-01 2.13E-20 Y 91 1.03E 03 0.00E-01 2.76E 01 0.00E-01 0.00E-01 0.00E-01 5.67E 05 Y 92 6.71E-06 0.00E-01 1.96E-07 0.00E-01 0.00E-01 0.00E-01 1.18E-01 Y 93 2.80E-02 0.00E-01 7.73E-04 0.00E-01 0.00E-01 0.00E-01 0.87E 02 ZR 95 1.13E 02 3.63E 01 2.46E 01 0.00E-01 5.70E 01 0.00E-01 1.15E 05 ZR 97 5.20E-02 1.05E-01 4.80E-03 0.00E-01 1.58E-01 0.00E-01 3.25E 03 NB 95 9.91E 03 5.51E 03 2.96E 03 0.00E-01 5.45E 03 0.00E-01 3.35E 07 MO 99 0.00E-01 2.97E 06 5.65E 05 0.00E-01 6.73E 06 0.00E-01 6.89E 06 TC 99M 3.99E-01 1.13E 00 1.44E 01 0.00E-01 1.71E 01 5.53E-01 6.67E 02 l i

i l Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 1 Reference Use Page 175 of 188 i i ATTACHMENT A (Page 171 of 184) OFFSITE DOSE CALCULATION MANUAL i l TABLE A.5-17 (cont' d) GRASS-GOAT-MILK PATHWAY FACTOR M* MREM /YR PER pCI/SEC ADULT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI 1 TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I RU 103 1.22E 02 0.00E-01 5.26E 01 0.00E-01 4.66E 02 0.00E-01 1.43E 04 ) RU 105 1.03E-04 0.00E-01 4.07E-05 0.00E-01 1.33E-03 0.00E-01 6.30E-02 I RU 106 2.45E 03 0.00E-01 3.10E 02 0.00E-01 4.73E 03 0.00E-01 1.58E 05 AG 110M 6.99E 06 6.46E 06 3.84E 06 0.00E-01 1.27E 07 0.00E-01 2.64E 09 TE 125M 1.95E 06 7.08E 05 2.62E 05 5.88E 05 7.95E 06 0.00E-01 7.81E 06 TE 127M 5.49E 06 1.96E 06 6.70E 05 1.40E 06 2.23E 07 0.00E-01 1.84E 07 TE 127 7.84E 01 2.82E 01 1.70E 01 5.81E 01 3.19E 02 0.00E-01 6.19E 03 TE 129M 7.22E 06 2. . . 26 1.14E 06 2.48E 06 3.02E 07 0.00E-01 3.64E 07 TE 129 3.41E-11 1.28E-11 8.31E-12 2.62E-11 1.43E-10 0.00E-01 2.57E-11 TE 131M 4.33E 04 2.12E 04 1.77E 04 3.36E 04 2.15E 05 0.00E-01 2.10E 06 TE 131 4.40E-34 1.84E-34 1.39E-34 3.62E-34 1.93E-33 0.00E-01 6.23E-35 TE 132 2.88E 05 1.86E 05 1.75E 05 2.06E 05 1.80E 06 0.00E-01 8.82E 06 I 130 5.04E 05 1.49E 06 5.87E 05 1.26E 08 2.32E 06 0.00E-01 1.28E 06 I 131 3.55E 08 5.08E 08 2.91E 08 1.67E 11 8.71E 08 0.00E-01 1.34E 08 I 132 1.90E-00 5.29E-00 1.85E-00 1.85E 01 8.43E-00 0.00E-01 9.94E-01 I 133 4.65E 06 8.08E 06 2.46E 06 1.19E 09 1.41E 07 0.00E-01 7.26E 06 I 134 2.44E-12 6.63E-12 2.37E-12 1.15E-10 1.05E-11 0.00E-01 5.78E-15 I 135 1.54E 04 4.04E 04 1.49E 04 2.66E 06 6.48E 04 0.00E-01 4.56E 04 CS 134 1.70E 10 4.04E 10 3.30E 10 0.00E-01 1.31E 10 4.34E 09 7.06E 08 CS 136 7.83E 08 3.09E 09 2.23E 09 0.00E-01 1.72E 09 2.36E 08 3.51E 08 CS 137 2.21E 10 3.03E 10 1.98E 10 0.00E-01 1.03E 10 3.42E 09 5.86E 08 CS 138 2.75E-23 5.43E-23 2.69E-23 0.00E-01 3.99E-23 3.94E-24 2.32E-28 BA 139 5.48E-09 3.90E-12 1.60E-10 0.00E-01 3.65E-12 2.21E-12 9.71E-09 BA 140 3.23E 06 4.05E 03 2.11E 05 0.00E-01 1.38E 03 2.32E 03 6.64E 06 I BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 4 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 5.43E-01 2.73E-01 7.23E-02 0.00E-01 0.00E-01 0.00E-01 2.01E 04 LA 142 1.13E *1 5.12E-13 1.28E-13 0.00E-01 0.00E-01 0.00E-01 3.74E-09 CE 141 5.81E 02 3.93E 02 4.46E 01 0.00E-01 1.83E 02 0.00E-01 1.50E 06 CE 143 4.99E 00 3.69E 03 4.08E-00 0.00E-01 1.62E 00 0.00E-01 1.38E 05 CE 144 4.29E 04 1.79E 04 2.30E 03 0.00E-01 1.06E 04 0.00E-01 1.45E 07 PR 143 1.90E 01 7.60E 00 9.39E-00 0.00E-01 4.39E 00 0.00E-01 8.30E 04 l 1 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 1.14E 01 1.31E 01 7.85E-01 0.00E-01 7.67E 00 0.00E-01 6.30E 04 W 187 7.87E 02 6.58E 02 2.30E 02 0.00E-O' -0.00E-01 0.00E-01 2.16E 05 NP 239 4.41E-01 4.33E-02 2.39E-02 0.00E-01 1.35E-01 0.00E-01 8.89E 03

i Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 176 of 188 ATTACHMENT A (Page 172 of 184) 1 0FFSITE DOSE CALCULATION MANUAL TABLE A.5-18 GRASS-GOAT-MILK PATHWAY FACTOR M* MREM /YR PER pCI/SEC ) TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 2.03E 03 2.03E 03 2.03E 03 2.03E 03 2.03E 03 2.03E 03 j 4.86E 08 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07

        ^

C 9.72E 07 l NA 24 5.11E 05 5.11E 05 5.11E 05 5.11E 05 5.11E 05 5.11E 05 5.11E 05 l P 32 3.78E 10 2.34E 09 1.47E 09 0.00E-01 0.00E-01 0.00E-01 3.18E 09 CR 51 0.00E-01 0.00E-01 5.99E 03 3.33E 03 1.31E'03 8.55E 03 1.01E 06 l MN 54 0.00E-01 1.68E 06 3.34E 05 0.00E-01 5.02E 05 0.00E-01 3.45E 06 l MN 56 0.00E-01 8.85E-04 1.57E-04 0.00E-01 1.12E-03 0.00E-01 5.82E-02 i FE 55 5.79E 05 4.10E 05 9.57E 04 0.00E-01 0.00E-01 2.60E 05 1.78E 05 FE 59 6.74E 05 1.57E 06 6.07E 05 0.00E-01 0.00E-01 4.96E 05 3.72E 06 l CO 58 0.00E-01 9.52E 05 2.19E 06 0.00E-01 0.00E-01 0.00E-03 1.31E 07 CO 60 0.00E-01 3.34E 06 7.52E 06 0.00E-01 0.00E-01 0.00E-01 4.35E 07 NI 63 1.42E 09 1.00E 08 4.81E 07 0.00E-01 0.00E-01 0.00E-01 1.59E 07 NI 65 1.02E-01 1.30E-02 5.92E-03 0.00E-01 0.00E-01 0.00E-01 7.05E-01 l CU 64 0.00E-01 4.74E 03 2.23E 03 0.00E-01 1.20E 04 0.00E-01 3.67E 05 l ZN 65 2.53E 08 8.78E 08 4.09E 08 0.00E-01 5.62E 08 0.00E-01 3.72E 08_ l ZN 69 1.15E-12 2.20E-12 1.54E-13 0.00E-01 1.44E-12 0.00E-01 4.05E-12 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 l 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 5.67E 08 2.67E 08 0.00E-01 0.00E-01 0.00E-01 8.40E 07 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 0.00E-01 SR 89 5.62E 09 0.00E-01 1.61E 08 0.00E-01 0.00E-01 0.00E-01 6.69E 08 SR 90 1.39E 11 0.00E-01 3.43E 10 0.00E-01 0.00E-01 0.00E-01 3.90E 09 SR 91 1.11E 05 0.00E-01 4.40E 03 0.00E-01 0.00E-01 0.00E-01 5.02E 05 SR 92 1.88E 00 0.00E-01 8.02E-02 0.00E-01 0.00E-01 0.00E-01 4.80E 01 Y 90 1.56E 01 0.00E-01 4.20E-00 0.00E-01 0.00E-01 0.00E-01 1.29E 05 Y 91M 1.33E-20 0.00E-01 5.07E-22 0.00E-01 0.00E-01 0.00E-01 6.26E-19 Y 91 1.90E 03 0.00E-01 5.08E 01 0.00E-01 0.00E-01 0.00E-01 7.77E 05 Y 92 1.21E-05 0.00E-01 3.59E-07 0.00E-01 0.00E-01 0.00E-01 3.40E-01 Y 93 5.16E-02 0.00E-01 1.41E-03 0.00E-01 0.00E-01 0.00E-01 1.58E 03 ZR 95 1.98E 02 6.25E 01 4.309 01 0.00E-01 9.18E 01 0.00E-01 1.44E 05 ZR 97 9.47E-02 1.87E-02 8.63E-03 0.00E-01 2.84E-02 0.00E-01 5.07E 03 NB 95 1.69E 04 9.37E 03 5.16E 03 0.00E-01 9.09E 03 0.00E-01 4.01E 07 MO 99 0.00E-01 5.37E 06 1.02E 06 0.00E-01 1.23E 07 0.00E-01 9.61E 06 TC 99M 6.92E-00 1.93E 00 2.50E 01 0.00E-01 2.88E 01 1.07E 00 1.27E 03 TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference Use Page 177 of 188 l ATTACHMENT A (Page 173 of 184) l OFFSITE DOSE CALCULATION MANUAL l l TABLE A.5-18-(cont'd) GRASS-GOAT-MILK PATHWAY FACTOR , M2 MREM /YR PER pCI/SEC TEEN l NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI RU 103 2.17E 02 0.00E-01 9.28E 01 0.00E-01 7.66E 02 0.00E-01 1.81E 04 RU 105 1.88E-04 0.00E-01 7.30E-05 0.00E-01 2.37E-03 0.00E-01 1.52E-01 RU 106 4.50E 03 0.00E-01 5.67E 02 0.00E-01 8.68E 03 0.00E-01 2.16E 05 AG 110M 1.16E 07 1.09E 07 6.65E 06 0.00E-01 2.08E 07 0.00E-01 3.07E 09 TE 125M 3.60E 06 1.30E 06 4.82E 05 1.01E 06 0.00E-01 0.00E-01 1.06E 07 TE 127M 1.01E 07 3.59E 06 1.20E 06 2.41E 06 4.10E 07 0.00E-01 2.52E 07 TE 127 1.45E 02 5.15E 01 3.13E 01 1.00E 02 5.89E 02 0.00E-01 1.12E 04 TE 129M 1.32E 07 4.90E 06 2.09E 06 4.26E 06 5.53E 07 0.00E-01 4.96E 07

TE 129 6.28E-11 2.34E-11 1.53E-11 4.48E-11 2.63E-10 0.00E-01 3.43E-10 7.89E 04 3.78E 04 3.16E 04 5.69E 04 TE 131M 3.94E 05 0.00E-01 3.04E 06 TE 131 8.04E-34 3.31E-34 2.51E-34 6.19E-34 3.51E-33 0.00E-01 6.60E-35 TE 132 5.15E 05 3.26E 05 3.07E 05 3.44E 05 3.13E 06 0.00E-01 1.03E 07 I 130 8.87E 05 2.57E 06 1.02E 06 2.09E 08 3.95E 06 0.00E-01 1.97E 06 I 131 6.45E 08 9.03E 08 4.85E 08 2.63E 11 1.55E 09 0.00E-01 1.79E J8 I 132 3.51E-01 9.18E-01 3.29E-01 3.09E 01 1.45E 00 0.00E-01 4.00E-01 I 133 8.49E 06 1.44E 07 4.39E 06 2.01E 09 2.52E 07 0.00E-01 1.09E 07 I 134 4.34E-12 1.15E-11 4.13E-12 1.92E-10 1.81E-11 0.00E-01 1.51E-13 I 135 2.74E 04 7.05E 04 2.61E 04 4.54E 06 1.11E 05 0.00E-01 7.82E 04 CS 134 2.94E 10 6.93E 10 3.22E 10 0.00E-01 2.20E 10- 8.41E 09 8.62E 08 CS 136 1.33E 09 5.25E 09 3.52E 09 0.00E-01 2.86E 09 4.50E 08 4.22E 08 CS 137 4.02E 10 5.34E 10 1.86E 10 0.00E-01 1.82E 10 7.06E 09 7.60E 08 CS 138 4.99E-23 9.58E-23 4.79E-23 0.00E-01 7.07E-23 8.23E-24 4.34E-26 BA 139 1.01E-08 7.13E-12 2.95E-10 0.00E-01 6.72E-12 4.91E-12 9.04E-08 i BA 140 5.82E 06 7.14E 03 3.75E 05 0.00E-01 2.42E 03 4.08E 03 8.98E 06 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 9.75E-01 4.79E-01 1.27E-01 0.00E-01 0.00E-01 0.00E-01 2.75E 04 LA 142 2.03E-12 9.03E 13 2.25E-13 0.00E-01 0.00E-01 0.00E-01 2.75E-08 CE 141 1.07E 03 7.12E 02 8.18E 01 0.00E-01 3.35E 02 0.00E-01 2.04E 06 i CE 143 9.17E 00 6.67E 03 7.45E-00 0.00E-01 2.99E 00 0.00E-01 2.01E 05 CE 144 7.90E 04 3.27E 04 4.24E 03 0.00E-01 1.95E 04 0.00E-01 1.99E 07 PR 143 3.48E 01 1.39E 00 1.73E 'O 0.00E-01 8.08E 00 0.00E-01 1.15E 05 l-i 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 2.19E 01 2.38E 01 1.42E 00 0.00E-01 1.40E 01 0.00E-01 8.57E 04 W 187 1.44E 03 1.17E 03 4.11E 02 0.00E-01 0.00E-01 0.00E-01 3.18E 05 HP 239 8.41E-01 7.93E-02 4.41E-02 0.00E-01 2.49E-01 0.00E-01 1.28E 04

( L

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference Use Page 178 of 188 ATTACHMENT A ~ (Page 174 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-19 GRASS-GOAT-MILK PATHWAY EACTOR M8 MREM /YR PER pCI/SEC CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 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 NA 24 1.06E 06 1.06E 06 1.06E 06 1.06E 06 1.06E 06 1.06E 06 1.06E 06 P 32 9.33E 10 4.37E 09 3.60E 09 0.00E-01 0.00E-01 0.00E-01 2.58E 09 CR 51 0.00E-01 0.00E-01 1.22E 04 6.78E 03 1.05E 03 1.24E 04 6.48E 05 MN 54 0.00E-01 2.52E 06 6.70E 05 0.00E-01 7.06E 05 0.00E-01 2.11E 06 MN 56 0.00E-01 1.54E-03 3.48E-04 0.00E-01 1.87E-03 0.00E-01 2.24E-01' FE 55 1.45E 06 7.70E 05 2.39E 05 0.00E-01 0.00E-01 4.36E 05 1.43E 05 FE 59 1.56E 06 2.53E 06 1.26E 06 0.00E-01 0.00E-01 7.33E 05 2.63E 06 CO 58 0.00E-01 1.46E 06 4.45E 06 0.00E-01 0.00E-01 0.00E-01 8.49E 06 l CO 60 0.00E-0) 5.18E 06 1.53E 07 0.00E-01 0.00E-01 0.00E-01 2.87E 07 i NI 63 3.50' 09 1.90E 08 1.21E 08 0.00E-01 0.00E-01 0.00E-01 1.2EE 07 NI 65 2.49E-01 2.34E-02 1.37E-02 0.00E-01 0.00E-01 0.00E-01 2.87E 00 CU 64 0.00E-01 8.23E 03 5.03E 03 0.00E-01 2.01E 04 0.00E-01 3.91E 05 ZN 65 4.96E 08 1.32E 09 8.22E 08 0.00E-01 8.33E 08 0.00E-01 2.32E 08 ZN 69 2.84E-12 4.10E-12 3.79E-13 0.00E-01 2.49E-12 0.00E-01 2.58E-10 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 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 1.05E 09 6.47E 08 0.00E-01 0.00E-01 0.00E-01 6.77E 07 l RB 88 0.00E-01 0.00E U1 0.00E-01 C.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 1.39E 10 0.00E-01 3.97E 08 0.00E-01 0.00E-01 0.00E-01 5.38E 08 j SR 90 2.35E 11 0.00E-01 5.95E 10 0.00E-01 0.00E-01 0.00E-01 3.16E 09 l SR 91 2.71E 05 0.00E-01 1.02E 04 0.00E-01 0.00E-01 0.00E-01 5.99E 05 SR 92 4.60E 00 0.00E-01 1.64E-01 0.00E-01 0.00E-01 0.00E-01 8.71E 01 l Y 90 3.86E 01 0.00E-01 1.03E-00 0.00E-01 0.00E-01 0.00E-01 1.10E 05  ; Y 91M 3.24E-20 0.00E-01 1.18E-21 0.00E-01 0.00E-01 0.00E-01 6.34E-17 Y 91 4.68E 03 0.00E-01 1.25E 00 0.00E-01 0.00E-01 0.00E-01 6.24E 05 Y 92 3.04E-05 0.00E-01 8.71E-07 0.00E-01 0.00E-01 0.00E-01 8.79E-01 Y 93 1.27E-01 0.00E-01 3.48E-03 0.00E-01 0.00E-01 0.00E-01 1.89E 03 ZR 95 4.60E 02 1.01E 02 9.00E 01 0.00E-01 1.45E 02 0.00E-01 1,05E 05 I ZR 97 2.30E-01 3.33E-02 1.96E-02 0.00E-01 4.78C-02 0.00E-01 5.04E 03 NB 95 3.82E 04 1.49E 04 1.06E 04 0.00E-01 1.40E 04 0.00E-01 2.75E 07 MO 99 0.00E-01 9.76E 06 2.42E 06 0.00E-01 2.00E 07 0.00E-01 0.07E 06 TC 99M 1.59E 00 3.11E 00 5.16E 01 0.00E-01 4.52E 01 1.58E 00 1.77E 03 TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 m

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 179 of 188 ATTACHMENT A (Page 175 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A 5-19 (cont' d) i GRASS-GOAT-MILK PATHWAY FACTOR 2 M MREM /YR PER pCI/SEC CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI RU 103 5.14E 02 0.00E-01 1.97E 02 0.00E-01 1.29E 03 0.00E-01 1.33E 04 - RU 105 4.59E-04 0.00E-01 1.67E-04 0.00E-01 4.04E-03 0.00E-01 3.00E-01 l RU 106 1.11E 04 0.00E-01 1.38E 03 0.00E-01 1.50E 04 0.00E-01 1.72E 05 AG 110M 2.51E 07 1.695 07 1.35E 07 0.00E-01 3.15E 07 0.00E-01 2.01E 09 l TE 125M 8.85E 06 2.40E 06 1.18E 06 2.48E 06 0.00E-01 0.00E-01 8.54E 06 ; TE 127M 2.50E 07 6.72E 06 2.96E 06 5.97E 06 7.12E 07 0.00E-01 2.02E 07 TE 127 3.57E 02 9.64E 01 7.67E 01 2.47E 02 1.02E 03 0.00E-01 1.40E 04 TE 129M 3.26E 07 9.09E 06 5.05E 06 1.05E 07 4.56E 07 0.00E-01 3.97E 07 TE 129 1.55E-10 4.32E-11 3.68E-11 1.1E-10 4.53E-10 0.00E-01 9.64E-09 TE 131M 1.92E 05 6.64E 04 7.07E 04 1.37E 05 6.43E 05 0.00E-01 2.69E 06 TE 131 1.97E-33 6.01E-34 5.87E-34 1.51E-33 5.97E-33 0.00E-01 1.04E-32 l TE 132 1.23E 06 5.44E 05 6.58E G5 7.93E 05 5.05E 06 0.00E-01 5.48E 06 I 130 2.07E 06 4.19E 06 2.16E 06 4.62E 08 6.27E 06 0.00E-01 1.96E 06 I 131 1.56E 09 1.57E 09 8.94E 08 5.20E 11 2.58E 09 0.00E-01 1.40E 08 I 132 8.30E-01 1.52E 00 7.01E-01 7.07E 01 2.33E 00 0.00E-01 1.79E 00 I 133 2.06E 07 2.55E 07 9.65E 06 4.74E 09 4.25E 07 0.00E-01 1.03E 07 I 134 1.03E-11 1.91E-11 8.77E-12 4.39E-10 2.92E-11 0.00E-01 1.26E-11 I 135 6.49E 04 1.17E 05 5.52E 04 1.03E 07 1.79E 05 0.00E-01 8.90E 04 CS 134 6.79E 10 1.11E 11 2.35E 10 0.00E-01 3.45E 10 1.24E 10 6.01E 08 i CS 136 3.01E 09 8.27E 09 5.35E 09 0.00E-01 4.40E 09 6.57E 08 2.91E 08 CS 137 9.67E 10 9.26E 10 1.37E 10 0.00E-01 3.02E 10 1.09E 10 5.80E 08 l CS 138 1.21E-22 1.68E-22 1.07E-22 0.00E-01 1.18E-22 1.27E-23 7.74E-23 ' BA 139 2.49E-0E 1.33E-11 7.21E-10 0.00E-01 1.16E-11 7.82E-12 1.44E-06 BA 140 1.41E 07 1.23E 04 8.21E 05 0.00E-01 4.01E 03 7.34E 03 7.12E 06 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 2.33E 00 8.16E-00 2.75E-01 0.00E-01 0.00"-01 0.00E-01 2.27E 04 LA 142 4.91E-12 1.56E-12 4.90E-13 0.00E-01 0.00E-01' O.00E-01 3.10E-07 CE 141 2.63E 03 1.31E 03 1.94E 02 0.00E-01 5.74E 02 0.00E-01 1.63E 06 CE 143 2.25E 01 1.22E 04 1.77E 00 0.00E-01 5.12E 00 0.00E-01 1.79E 05 CE 144 1.95E 05 6.11E 04 1.04E 04 0.00E-01 3.38E 04 0.00E-01 1.59E 07 PR 143 8.62E 01 2.59E 01 4.2BE 00 0.00E-01 1.40E 01 0.00E-01 9.30E 04 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 5.36E 01 4.34E 01 3.36E 00 0.00E-01 2.38E 01 0.00E-01 6.88E 04 W 187 3.49E 03 2.07E 03 9.28E 02 0.00E-01 0.00E-01 0.00E-01 2.90E 05 NP 239 2.07E 00 1.49E-01 1.04E-01 0.00E-01 4.30E-01 0.00E-01 1.10E 04

                                                                                        )

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference Use Page 180 of 188 l ATTACHMENT A (Page 176 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-20 - GRASS-GOAT-MILK PATHWAY FACTOR  : M2 MREM /YR PER pCI/SEC INEAN.  ; 1 NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 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 NA 24 1.85E 06 1.85E 06 1.85E 06 1.85E 06 1.85E 06 1.85E 06 1.85E 06 i l P 32 1.92E 11 1.13E 10 7.45E 09 0.00E-01 0.00E-01 0.00E-01 2.60E 09 1 CR 51 0.00E-01 0.00E-01 1.94E 04 1.26E 04 2.76E 03 2.46E 04 5.64E 05 I MN 54 0.00E-01 4.68E 06 1.06E 06 0.00E-01 1.04E 06 0.00E-01 1.72E 06 ) l MN 56 0.00E-01 3.78E-03 6.51E-04 0.00E-01 3.25E-03 0.00E-01 3.43E-01 FE 55 1.76E 06 1.13E 06 3.03E 06 0.00E-01 0.00E-01 5.54E 05 1.44E 05 FE 59 2.92E 06 5.09E 06 2.01E 06 0.00E-01 0.00E-01 1.51E 06 2.43E 06 l CO 58 0.00E-01 2.91E 06 7.26E 06 0.00E-01 0.00E-01 0.00E-01 7.25E 06 CO 60 0.00E-01 1.06E 07 2.50E 07 0.00E-01 0.00E-01 0.00E-01 2.52E 07 NI 63 4.19E 09 2.59E 08 1.45E 08 0.00E-01 0.00E-01 0.00E-01 1.29E 07 l NI 65 5.27E-01 5.96E-02 2.71E-02 0.00E-01 0.00E-01 0.00E-01 4.54E 00 CU 64 0.00E-01 2.07E 04 9.58E 03 0.00E-01 3.50E 04 0.00E-01 4.25E 05 l ZN 65 6.66E 08 2.28E 09 1.05E 09 0.00E-01 1.11E 09 0.00E-01 1.93E 09 ZN 69 6.04E-12 1.09E-11 8.10E-13 0.00E-01 4.52E-12 0.00E-01 8.87E-10 l 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 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 '0.00E-01 1 RB 86 0.00E-01 2.67E 09 1.32E 09 0.00E-01 0.00E-01 0.00E-01 6.83E 07 ' 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 2.64E 10 0.00E-01 7.58E 08 0.00E-01 0.00E-01 0.00E-01 5.43E 08 SR 90 2.55E 11 0.00E-01 6.50E 10 0.00E-01 0.00E-01 0.00E-01 3.19E 09 ! SR 91 5.65E 05 0.00E-01 2.05E 03 0.00E-01 0.00E-01 0.00E-01 6.69E 05 l SR 92 9.78E 00 0.00E-01 3.63E-01 0.00E-01 0.00E-01 0.00E-01 1.05E 02 Y 90 8.16E 01 0.00E-01 2.19E 00 0.00E-01 0.00E-01 0.00E-01 1.13E 05 Y 91M 6.87E-20 0.00E-01 2.34E-21 0.00E-01 0.00E-01 0.00E-01 2.29E-16 Y 91 8.79E 03 0.00E-01 2.34E 02 0.00E-01 0.00E-01 0.00E-01 6.30E 05 Y 92 6.47E-05 0.00E-01 1.82E-06 0.00E-01 0.00E-01 0.00E-01 1.23E 00 Y 93 2.70E-01 0.00E-01 7.36E-03 0.00E-01 0.00E-01 0.00E-01 2.13E 03 l ZR 95 8.17E 02 1.99E 02 1.41E 02 0.00E-01 2.14E 02 0.00E-01 9.91E 04 l ZR 97 4.88E-01 8.37E-02 3.82E-02 0.00E-01 8.44E-02 0.00E-01 5.34E 03 NB 95 7.12E 04 2.93E 04 1.70E 04 0.00E-01 2.10E 04 0.00E-01 2.48E 07 MO 99 0.00E-01 2.50E 07 4.87E 06 0.00E-01 3.73E 07 0.00E-01 8.22E 06 TC 99M 3.30E 00 6.81E 00 R.77E 01 0.00E-01 7.33E 01 3.56E 00 1.98E 03 I l l

E f Revision: 1 OFFSITE' DOSE CALCULATION MANUAL AP 07B-003 i l Reference Use Page 181 of 188 l l ATTACHMENT A (Page 177 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-20 (cont' d) I l GRASS-GOAT-MILK PATHWAY FACTOR i 2 M MREM /YR PER pCI/SEC l INFANT NUCLIDE BONE LIVER 7' BODY THYROI9 KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RU 103 1.04E 03 0.00E-01 3.48E 02 0.00E-01 2.16E 03 0.00E-01 1.26E 04 RU 105 9.68E-04 0.00E-01 3.26E-04 0.00E-01 7.12E-03 0.00E-01 3.85E-01 RU 106 2.28E 04 0.00E-01 2.85E 03 0.00E-01 2.70E 04 0.00E-01 1.73E 05 AG 110M 4.63E 07 3.38E 07 2.24E 07 0.00E-01 4.83E 07 0.00E-01 1.75E 09 TE 125M 1.81E 07 6.05E 06 2.45E 06 6.09E 06 0.00E-01 0.00E-01 8.62E 06 l TE 127M 5.05E 07 1.68E 07 6.12E 06 1.46E 07 1.24E 08 0.00E-01 2.04E 07 TE 127 7.59E 02 2.54E 02 1.63E 02 6.18E 02 1.85E 03 0.00E-01 1.59E 34 TE 129M 6.69E 07 2.29E 07 1.03E 07 2.57E 07 1.67E 08 0.00E-01 3.99E 07 TE 129 3.28E-10 1.13E-10 7.66E-11 2.75E-10 8.17E-10 0.00E-01 2.62E-08 TE 131M 4.05E 05 1.63E 05 1.35E 05 3.31E 05 1.12E 06 0.00E-01 2.75E 06 TE 131 4.18E-33 1.54E-33 1.17E-33 3.73E-33 1.07E-32 0.00E-01 1.69E-31 l TE 132 2.53E 06 1.25E 06 1.17E 06 1.85E 06 7.84E 06 0.00E-01 4.64E 06 I 130 4.26E 06 9.38E 06 3.76E 06 1.05E 09 1.03E 07 0.00E-01 2.01E 06 I 131 3.26E 09 3.85E 09 1.69E 09 1.26Z 12 4.49E 09 0.00E-01 1.37E 08 I 132 1.72E 00 3.49E 00 1.24E 00 1.64E 02 3.90E 00 0.00E-01 2.83E 00 I 133 4.35E 07 6.34E 07 1.86E 07 1.15E 10 7.45E 07 0.00E-01 1.07E 07 I 134 2.13E-11 4.36E-11 1.55E-11 1.02E-09 4.88E-11 0.00E-01 4.51E-11 I 135 1.35E 05 2.68E 05 9.79E 04 2.41E 07 2.99E 05 0.00E-01 9.71E 04 CS 134 1.09E 11 2.04E 11 2.06E 10 0.00E-01 5.25E 10 1.86E 10 5.54E 08 i CS 136 5.88E 09 1.73E 10 6.45E 09 0.00E-01 6.89E 09 1.41E 09 2.63E 08 j i CS 137 1.54E 11 1.8AE 11 1.28E 10 0.00E-01 4.85E 10 1.96E 10 5.65E 08 ) CS 138 2.55E-22 4.15E-22 2.01E-22 0.00E-01 2.07E-22 3.23E-23 6.63E-22 BA 139 5.30E-08 3.51E-11 1.53E-09 0.00E-01 2.11E-11 2.13E-11 3.35E-06 BA 140 2.89E 07 2.89E 04 1.49E 06 0.00E-01 6.87E 03 1.78E 04 7.11E 06 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 4.88E 00 1.92E 00 4.94E-00 0.00E-01 0.00E-01 0.00E-01 2.26E 04 l j' LA 142 1.03E-11 3.78E-12 9.06E-13 0.00E-01 0.00E-01 0.00E-01 6.43E-07 l CE 141 5.20E 03 3.17E 03 3.74E 02 0.00E-01 9.79E 02 0.00E-01 1.64E 06 L CE 143 4.76E 01 3.16E 04 3.61E 00 0.00E-01 9.21E 00 0.00E-01 1.84E 05 2.79E 05 1.14E 05 1.56E 04 0.00E-01 4.62E 04 0.00E-01 1.60E 07 CE 144 PR 143 1.78E 02 6.67E 01 8.84E 00 0.00E-01 2.48E 01 0.00E-01 9.41E 04 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 1.06E 02 1.09E 02 6.69E 00 0.00E-01 4.21E 01 0.00E-01 6.92E 04 W 187 7.35E 03 5.11E 03 1.77E 03 0.00E-01 0.00E-01 0.00E-01 3.00E 05 NP 239 4.38E 00 3.91E-01 2.21E-01 0. 0_0 E-01 7.80E-01 0.00E-01 1. . . E 0 4

Revision: 1- OFFSITE DOSE CALCULATION MANUAL AP 073-003 Reference Use Page 182 of 188 ATTACHMENT A (Page 178 of 184) OFFSITE DOSE CALCUfATION MANUAL APPENDIX B Meteorological Model l

                                                              ,g     -   -

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 183~of 188 ATTACHMENT A

                                   .(Page 179-of 184)

OFFSITE DOSE CALCULATION MANUAL' APPENDIX B PROPRIETARY'INFORMATION SUPPLIED BY SAI The X/Q's and D/Q's are calculated using the guidance of Reg. Guide 1.111. The constant mean wind direction model, as defined in equation 3 of Reg. Guide-1.111, is used to calculated X/Q. values. 2 2 2.032 Eng exp -h , /2 a 7;(x)

                            -         U (X /<Q )                   _

N x Ui E(x) zj Where:

h. = effective release height (m). (All releases from Wolf Creex Generating Station are considered as ground releases therefore he = 0.).

n13 = hours of valid data for weather conditions in given direction, windspeed class I, and atmospheric , stability class j. N = total house of valid data Ui = midpoint of windspeed class (m/s) x = distance downwind (m) c3(x) z

                            =   vertical plume spread without volumetric correction at distance x and stability class j. See Figure B.l.

E23(x) =. vertical plume spread with columetric correction for release within buildings wake cavity, at i distance x and stability class j. l

                 ' For ground level releases Ez3 (x) is the lesser of             l
                                                   /2 2               2 (o :j (x) + 0.5 D ,f y       or}3o,j(x)

I

Revision: 1: OFFSITE. DOSE CALCULATION MANUAL' AP 07B-003 Reference Usel lPage.184 of.188 ATTACHMENT A (Page 180 of-184) OFFSITE DOSE CALCULATION MANUAL APPENDIX B (CONT'D)

            'Where:

D2 = maximum' adjacent buil' ding' height either up- or-  !

                      ,down-wind from the release point L

2.0321= (2/x)~ ". divided by width, in. radians, of a 22.5 sector (X/Q)o = Average' effluent concentration, X, normalized to source strength, 0, at distance x 'n: sector.D. l For'WCGS the above Meteorological Model will simplify.to the1 g i~ foll'owing equation for X/Q:  ; o i 2.032 Z ng

                              =           "

(X/Q) _ N Ui x Z(x) U The calculation of the relative disposition per unit area, D/0, j is performed using the deposition rate graphs found-infReg. Guide 1.111. .For a 22.5 sector, since the effluent L concentration is assumed uniform across the sector, the relative deposition per unit area is assumed uniform across the sector. The calculation of D/Q is determined from relative deposition by

            .tne following. relationship l                                                                                     i
                              ' Du (x) e DEPLu (X)                                   i D/Q =

(2 x /16) x Where: D13(x) = Relative deposition rate for windspeed class i and stability class j at downwind distance x (1/m). See Figure B.3. (2x/16)x = length of arc across sector at downwind distance x (m). D/Q = relative deposition per unit area (m)

Revision: 1 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 185 of 188 L ATTACHMENT A (Page 181 of 184) OFFSITE DOSE CALCULATION MANUAL l I APPENDIX B (CONT'D) DEPLy (x) = Reduction factor due to plume depletion at distance x l for windspeed i and stability class j. l l l l i I l l l I 1 I i l i i l

     .t Revision: 1                                 OFFSITE DOSE CALCULATION MANURL                                                       AP 07B-003 Reference Use                                                                                                              Page 186 of 188   l l

ATTACHMENT A (Page 182 of 184) 0FFSITE DOSE CALCULATION MANUAL Figure B.1

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1 0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS) Vertical Standard Deviation of Materialin a Plume (Letters denote Pasquilt Stsbility Class) NOTE: THESE ARE STANOARD RELATIONSHIPS AND MAY HAVE TO DE MOOlFIED FOR CERTAIN TYPES OF TERRAIN AN0/OR CLIMATIC CONDITIONS (E.C. VALLEY OESERT Ovf R WATERI. B-4

I l 1 f i Revision: 1 OFFSITE DOSE. CALCULATION MANUAL AP 07B-003 ! Reference Use Page 187 of 188 L t ATTACHMENT A !- (Page 183 of 184) l OFFSITE DOSE CALCULATION MANUAL 1 Figure B.2 o m 8

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