ML022070141

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Offsite Dose Calculation Manual for Calvert Cliffs Nuclear Power Plant, Enclosure (2), Section 5.0, Pages 159 - 325
ML022070141
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/17/2002
From: Tonacci M
Constellation Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML022070141 (167)


Text

Offsite Dose Calculation Manual Page 159 of 325 Revision 5 ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN GASEOUS EFFLUENTS

1. Introduction a) 10 CFR 20.1301 specifies dose rate limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 20.1301.

c) These radiological effluent controls are described below.

2. Radiological Effluen-t CGontroIso a) The annual skin dose rate, due to noble gases in gaseous waste discharged to UNRESTRICTED AREAS, shall be less than 3000 mr/yr (per Control 3.11.2.1).

b) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

3. Surveillance Requirement a) The annual skin dose rate at the SITE BOUNDARY, due to noblejgases in all gaseous effluents discharged from the site, shall be determined in accordance with equation 11G (per Control 4.11.2.1.1).

b) The results of the radioactive gaseous waste sampling and analysis program (required by Control 4.11.2.1.2, and implemented by various CCNPP CHEMISTRY SECTION procedures) are used to calculate the annual skin dose rate due to noble gases in gaseous effluents.

C) The plant group(s) responsible for performing the required surveillances are identified below.

4. Responsible Plant Organization(s) a) The CHEMISTRY SECTION is responsible for calculating the annual skin dose rate due to noble gases in gaseous effluents.

b) The CCNPP CHEMISTRY SECTION calculates the annual skin dose rate whenever the appropriate initiating conditions are present.

c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each release of a WGDT.

b) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each vent of a containment building.

Offsite Dose Calculation Manual Page 160 of 325 Revision 5 c) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each PURGE of a containment building.

d) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated at least weekly1 for CONTINUOUS discharges from plant vent stacks.

e) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each discharge of combustion products resulting from the burning of contaminated oil.

-f-The-annual-skin-dose-rate-due-to-noble-gases-in-all-gaseous-effluents discharged from the site is calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE.

g) Whenever the correct initiating conditions are present, the annual skin dose rates shall be calculated as described below.

6. Calculation Methodology a) The annual skin dose rate, at the SITE BOUNDARY, due to noble gases in all gaseous effluents discharged simultaneously from the site to UNRESTRICTED AREAS shall be calculated in accordance with equation 11G.2 ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN ALL SIMULTANEOUS GAS RELEASES, r D50 = -Dsr Eq. 11G DO0 = the annual skin dose rate at the SITE BOUNDARY due to noble gases in all simultaneous discharges of gaseous radwaste from the site ("Unit 0")

Dsr = the annual skin dose rate at the SITE BOUNDARY due to noble gases in release, r Sum for all releases, r, which are discharged simultaneously.

An example of a SIMULTANEOUS RELEASE would include the release of noble gas radionuclides from the Unit 1 plant vent stack while also discharging noble gases from the Unit 2 plant vent stack.

An example of a SIMULTANEOUS RELEASE would include the release of noble gas radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay tank.

The frequency is controlled by the implementing procedureand is based on plant conditions.

Under no conditions shall the frequency be less than once per month (Control 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9).

Offsite Dose Calculation Manual Page 161 of 325 Revision 5 Calculate the values of Dsr for each SIMULTANEOUS RELEASE as shown below.

b) At CCNPP, two methods exist for calculating Dsr (i.e., annual total skin dose rate at the SITE BOUNDARY due to noble gases contained in a gaseous radwaste release, r, discharged from the site).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

c) Rigorous Method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the annual skin dose rate due to noble gases in gaseous release, r, discharged from the site to UNRESTRICTED AREAS shall be calculated in accordance with equation 12G.

ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES INGAS RELEASE, r (RIGOROUS METHOD)

D., = (X/Q) {[L, +(1.1) (MI) ] (Q,,) } Eq. 12G'

Where, x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered "long-term" releases 2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases)

(UFSAR, 2.3.6.3)

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3)

Equation 12G has been derived from NUREG-0133, 5.2.1, and Regulatory Guide 1.109 (Appendix B, Equation B-9 and Section C.2.f).

2 NUREG-0133, 3.3

Offsite Dose Calculation Manual Page 162 of 325 Revision 5 Li = the skin dose factor due to beta emissions for each identified noble gas radionuclide, i (mrem/yr per microcurie/cubic meter)

The beta skin dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-I.

The beta skin dose factors for various noble gas radionuclides are tabulated in Attachment 10.

M, =the air dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

The-gamma-air-dose-factors-have-been-obtained-from-Regulatory-Guide-l.109, Appendix B, Table B-I.

The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10.

1.1 = The conversion constant, 1.1 mrem/mrad, represents the skin dose (1.1 mrem) equivalent to air dose (1.0 mrad), and is used to convert air dose to skin dose.

Oir = the release rate of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/second).

This value shall be calculated in accordance with equation 9G.

INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Qir = (A0) (Fr}(G') Eq.(9c Air = the specific activity of noble gas radionuclide, i, in (simultaneous) release, r (microcudes/cubic centimeter)

Fr = the discharge flow rate for (simultaneous) release, r (cubic meters per second)

If the discharge flow rate is unknown (e.g., the release has not been conducted), the "Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual skin dose rate.

Whenever possible, the actual discharge flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G.

Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures.

c = a conversion constant (1 E6 cubic centimeters per cubic meter) d) Simplified method

Offsite Dose Calculation Manual Page 163 of 325 Revision 5 (1) If a computer system and the appropriate software are NOT available, the annual skin dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED AREAS may be calculated in accordance with equation 13G.

ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED METHOD)

Dsr = [(xIQ)/(Ks)][Lavg+(I"I)(Mavg)]*Qir Eq.13G'

_Where, x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered "long-term" releases 2 , and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases)

(UFSAR, 2.3.6.3)

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3)

Ksf = a constant, actually a safety factor, which is the ratio of the CCNPP annual skin dose rate limit to the annual skin dose rate limit of Control 3.11.2.1, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the annual skin dose rate is always less than or equal to the annual skin dose rate limit of Control 3.11.2.1.

A safety factor of 1.00 will yield an annual skin dose rate which corresponds to the annual skin dose rate limit of Control 3.11.2.1.

A safety factor of 0.500 will yield an annual skin dose rate which corresponds to one half the annual skin dose rate limit of Control 3.11.2.1.

It is recommended that a safety factor of 1.0 be used for calculating the annual skin dose rate, however, other values--not to exceed 1.00--may be used as directed by the General Supervisor Chemistry.

Equation 13G has been derived from NUREG-0133, 5.2.1, and Regulatory Guide 1.109 (Appendix B, Equation 8-9 and Section C.2.).

2 NUREG-01 33, 3.3

Offsite Dose Calculation Manual Page 164 of 325 Revision 5 The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.1 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 13G to account for any potential nonconservatism-associated-with-applying-the-empirically-denived-skin-beta-dese factor, Lavg, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a skin beta dose factor greater than Lavg are present in a gaseous release.

Lavg = the empirically derived, site specific, average, skin dose factor due to beta emissions from TYPICAL GASEOUS EFFLUENTS (mrem/yr per microcurie/cubic meter)

A site-specific, average, beta skin dose factor for TYPICAL GASEOUS EFFLUENTS has been calculated from historical data.

The calculation of this site-specific, average, beta skin dose factor is presented on Attachment 11.

Refer to the table on Attachment 11 for the current value for the empirically derived, site specific, average beta skin dose factor.

Mavg = the empirically derived, site specific, average, air dose factor due to gamma emissions from TYPICAL GASEOUS EFFLUENTS (mrad/yr per microcurie/cubic meter)

A site-specific, average, gamma air dose factor for TYPICAL GASEOUS EFFLUENTS has been calculated from historical data.

The calculation of this site-specific, average, gamma air dose factor is presented on Attachment 11.

Refer to the table on Attachment 11 for the current value for the empirically derived, site specific, average gamma air dose factor.

1.1 = The conversion constant, 1.1 mrem/mrad, represents the skin dose (1.1 mrem) equivalent to air dose (1.0 mrad), and is used to convert air dose to skin dose.

Qir = the release rate of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/second)

This value shall be calculated in accordance with equation 9G.

Offsite Dose Calculation Manual Page 165 of 325 Revision 5 INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Qir = (Air) (F,) (c') Eq. 9G Air = the specific activity of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/cubic centimeter)

Fr = the discharge flow rate for (simultaneous) release, r (cubic meters per second)

If the discharge flow rate is unknown (e.g., the release has not been conducted), the "Maximum-Discharge-F-low-Rate!Llisted-on-Attachments-7-or-8-may-be-used-to calculate the annual skin dose rate.

Whenever possible, the actual discharge flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G.

Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures.

c = a conversion constant (1E6 cubic centimeters per cubic meter) e) Radiation monitoring system algorithms (1) The plant vent stack radiation monitoring systems display values which are proportional to the annual skin dose rate due to noble gases emanating from the plant vent stacks.

(2) The values displayed by the plant vent stack radiation monitoring systems are not used for the purpose of effluent accountability per se, but the values displayed can provide a gross approximation of annual skin dose rate (see Control 3.3.3.9).

(3) The Westinghouse Main Vent Stack Noble Gas Monitor, 1/2-RE 5415, is an analog system and does not employ instrument algorithm to determine noble release rates.

(a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RI-5415.

(b) These calculations are described elsewhere in the ODCM.

(See equation 4G in the section "Calculating the Fixed Setpoint for 112-RI-5415.")

(4) The Sorrento WRNGM, 1/2-RE-5416, is a digital radiation monitoring system which employs an instrument algorithm to determine noble release rates (microcuries per second).

Offsite Dose Calculation Manual Page 166 of 325 Revision 5 (a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RIC-5415.

(b) These calculations are described elsewhere in the ODCM.

(See equation 1G in the section "Calculating the Fixed High-High Alarm Setpoint for 1/2-RIC-5415.")

(5) The instrument algorithms and the (data base) values accessed by the instrument algorithms are controlled by EN-I-100.

f) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective ACTIONs are initiated as described below.

7. Corrective actions C4 a) CHEMISTRY SECTION surveillance procedures shall contain/and or reference administrative and/or Control limits for annual skin dose rate for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.1 for actions to be taken in the event the calculated annual skin dose rate exceeds 3000 mr/yr.

ANNUAL ORGAN DOSE RATES DUE TO IODINES AND PARTICULATES IN GASEOUS EFFLUENTS

1. Introduction a) 10 CFR 20.1301 specifies dose rate limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls were originally established to implement the requirements of 10 CFR 20.1301. The 10 CFR 50 Appendix I, Design Objectives for ALARA Radioactive Effluents, upon which these calculations are based, are more restrictive than the public dose limits of 10 CFR 20.1301.

c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The annual organ dose rates, due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS, shall be less than 1500 mr/yr (per Control 3.11.2.1).

b) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

Offsite Dose Calculation Manual Page 167 of 325 Revision 5

3. Surveillance Requirements a) The CHEMISTRY SECTION's sampling and analysis procedure(s) shall describe the CCNPP radioactive gaseous waste sampling and analysis program (required by Control 4.11.2.1.2).

b) The results of the radioactive gaseous waste sampling and analysis program are used to calculate the annual organ dose rates due to iodines and particulates in gaseous effluents.

c) The plant group(s) responsible for performing the required surveillances are identified below.

4. Responsible Plant Organization(s) a) The CHEMISTRY SECTION is responsible for calculating the annual organ dose rates due to iodines and particulates in gaseous effluents.

b) The CHEMISTRY SECTION calculates the annual organ dose rates whenever the appropriate initiating conditions are present.

c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The annual organ dose rate-for each organ and at the SITE BOUNDARY-due to iodines and particulates in gaseous effluents is calculated at least weekly" for CONTINUOUS discharges from plant vent stacks.

b) The annual organ dose rate--for each organ and at the SITE BOUNDARY--due to iodines and particulates in gaseous effluents is calculated for each discharge of combustion products resulting from the burning of contaminated oil.

c) The annual organ dose rate-for each organ and at the SITE BOUNDARY--due to iodines and particulates in gaseous effluents is calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE 2.

d) Whenever the correct initiating conditions are present, the annual organ dose rates shall be calculated as described below.

The frequency is controlled by the implementing procedure and is based on plant conditions. J Under no conditions shall the frequency be less than once per month (Control 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

See the definition of ABNORMAL/UNANTICIPATED GAS RELEASE in the DEFINITIONS section of the ODCM.

Offsite Dose Calculation Manual Page 168 of 325 Revision 5

6. Calculation Methodology a) The annual organ dose rate, at the SITE BOUNDARY, due to iodine and particulate radionuclides in gaseous effluents released to UNRESTRICTED AREAS shall be calculated in accordance with equation 14G.1 ANNUAL ORGAN, o, DOSE RATE DUE TO IODINES AND PARTICULATES INALL SIMULTANEOUS GASEOUS RELEASES, r FROM THE SITE, 0 Do" D. Eq. 14G]

D00 = the site-boundary annual organ dose rate due to iodine and particulate radionuclides in all gaseous effluents discharged simultaneously from the site ("Unit 0")

Dot = the site-boundary annual organ dose rate due to iodine and particulate radionuclides in release, r Sum for all releases, r, which are discharged simultaneously.

An example of a SIMULTANEOUS RELEASE would include the release of iodines and particulate radionuclides from the Unit 1 plant vent stack while also discharging iodines and particulate radionuclides from the Unit 2 plant vent stack.

An example of a SIMULTANEOUS RELEASE would include the release of iodine and particulate radionuclides from the Unit I plant vent stack while also discharging a waste gas decay tank.

Calculate the values of Dor for each SIMULTANEOUS RELEASE as shown below.

b) At CCNPP, two methods exist for calculating Dor (i.e., the annual organ dose rates due to iodine and particulate radionuclides in gaseous effluents released to UNRESTRICTED AREAS).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

The alarm and fixed setpoints ... shall be determined and adjusted in accordance with the I=

methodology and parameters of the ODCM. (Control 3.3.3.9).

Offsite Dose Calculation Manual Page 169 of 325 Revision 5 C) Rigorous Method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the annual organ dose rates due to iodines and particulates in gaseous effluents released to an UNRESTRICTED AREA shall be calculated in accordance with equation 15G.

ANNUAL ORGAN, o, DOSE RATE DUE TO IODINES AND PARTICULATES IN GASEOUS RELEASE, r (RIGOROUS METHOD)

Dor (XIQ) Z(P )(Qir) Eq. 15G(1

Where, x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2,2E-6 seconds per cubic meter)

All releases are considered "long-term" releases 2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (UFSAR, 2.3.6.3).

P! the maximum organ inhalation pathway dose parameter for iodine and particulate radionuclides, i, for the most restrictive (i.e., child) age group (mrem/year per microcude/cubic meter)

The inhalation pathway dose parameters have been obtained in accordance with NUREG-0133, 5.2.1.1.

The pathway dose factor specified in NUREG-0133, 5.2.1 .b, specifies calculating the exposure to the "INFANT" age group, where the exposure is due to a combination of three separate pathways.

1) inhalation,
2) ground plane, and
3) food.

Equation 15G has been derived from NUREG-0133, 5.2.1.

2 NUREG-0133, 3.3

Offsite Dose Calculation Manual Page 170 of 325 Revision 5 The latest NRC guidance has deleted the requirement to include the ground plane and food dose contributions when calculating maximum organ doses, therefore no pathway dose factors are calculated for the ground plane or food pathways.

The latest NRC guidance has changed the critical receptor age group from "infant" to "child."

The child, inhalation pathway dose parameters for various radionuclides, sorted by critical organ, are tabulated in Attachment 12.

It should be noted that the dose parameters, Pi, (listed in Attachment 12) calculated in accordance with NUREG-0133, section 5.2.1.1 and the latest NRC guidance are numerically equal to the "Inhalation Pathway Factors," !S, calculated in accordance with NUREG-01 33, section 5.3.1.1. As a result the ODCM does not contain two separate tables for values of Pi and K1.

Qir the release rate of iodine or particulate radionuclide, i, in (simultaneous) gaseous release, r (microcudes/second).

Calculate the values of Qjr for each SIMULTANEOUS RELEASE in accordance with equation 9G.

INSTANTANEOUS RELEASE RATE OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r .

Qir = (Air) (Fr)(C)

(:Eq. G I Air = the specific activity of iodine or particulate radionuclide, i, in (simultaneous) release, r (microcuries/cubic centimeter)

Fr = the discharge flow rate for (simultaneous) release, r (cubic meters per second)

If the discharge flow rate is unknown (e.g., the release has not been conducted), the "Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual organ dose rate.

c-4 Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures.

c' = a conversion constant (1 E6 cubic centimeters per cubic meter) d) simplified method (1) If a computer system and the appropriate software are NOT available, the annual organ dose rate due to iodines and particulates in gaseous effluents discharged from the site to UNRESTRICTED AREAS may be calculated in accordance with equation 16G.

Offsite Dose Calculation Manual Page 171 of 325 Revision 5 ANNUAL ORGAN, o, DOSE RATE DUE TO IODINES AND PARTICULATES IN GASEOUS RELEASE, r (SIMPLIFIED METHOD)

Do, = IKs) (YJQ) (Prrx) **Qr Eq. 16G' Where, Ksf = a constant, actually a safety factor, which is the ratio of the CCNPP organ dose rate limit to the organ dose rate limit of Control 3.11.2.1, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the organ dose rate is always less than or equal to the organ dose rate limit of Control 3.11.2.1.

A safety factor of 1.00 will yield an organ dose rate which corresponds to the organ dose rate limit of Control 3.11.2.1.

A safety factor of 0.500 will yield an organ dose which corresponds to one-half the organ dose rate limit of Control 3.11.2.1.

It is recommended that a safety factor of 1.0 be used for calculating the organ dose rate, however, other values-not to exceed 1.00--may be used as directed by the General Supervisor Chemistry.

The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.1 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 16G to account for any potential nonconservatism associated with applying the dose parameter, Pmax, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a dose parameter greater than Pmax are present in a gaseous release.

x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered "long-term" releases 2 , and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases)

(UFSAR, 2.3.6.3).

Equation 16G has been derived from NUREG-0133, 5.2.1.

2 NUREG-0133, 3.3

Offsite Dose Calculation Manual Page 172 of 325 Revision 5 The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3).

Pmax = the most restrictive dose parameter which would be reasonably anticipated for the inhalation pathway, child age group, thyroid organ, and 1-131 radionuclide (mrem/year per microcurie/cubic meter)

The inhalation pathway dose parameters have been obtained in accordance with NUREG-0133, 5.2.1.1.

The pathway dose factor specified in NUREG-01 33, 5.2.1 .b, specifies calculating the exposure to the "INFANT" age group, where the exposure is due to a combination of three separate pathways.

1) inhalation,
2) ground plane, and
3) food.

The latest NRC guidance has deleted the requirement to include the ground plane and food dose contributions when calculating maximum organ doses, therefore no pathway dose factors are calculated for the ground plane or food pathways. _

The latest NRC guidance has changed the critical receptor age group from "infant" to "child."

The child, inhalation pathway dose parameters for various radionuclides, sorted by critical organ, are tabulated in Attachment 12.

It should be noted that the dose parameters, Pi, (listed in Attachment 12) calculated in accordance with NUREG-01 33, section 5.2.1.1 and the latest NRC guidance are numerically equal to the "Inhalation Pathway Factors," K 1 , calculated in accordance with NUREG-0133, section 5.3.1.1. As a result the ODCM does not contain two separate tables for values of Pi and i1.

Qir = the release rate of iodine or particulate radionuclide, i, in (simultaneous) gaseous release, r (microcuries/second).

Calculate the values of Qir for each SIMULTANEOUS RELEASE in accordance with equation 9G.

Offsite Dose Calculation Manual Page 173 of 325 Revision 5 INSTANTANEOUS RELEASE RATE OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r Qr - (Air) (Fr) (c') Eq.9 G9 Air = the specific activity of iodine or particulate radionuclide, i, in (simultaneous) release, r (microcuries/cubic centimeter)

Fr = the discharge flow rate for (simultaneous) release, r (cubic meters per second)

If the discharge flow rate is unknown (e.g., the release has not been conducted), the "Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual organ dose rate.

Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures.

c' = a conversion constant (1E6 cubic centimeters per cubic meter) e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are initiated as described below.

7. Corrective actions a) CHEMISTRY SECTION surveillance procedures shall contain/and/or reference administrative and/or Control limits for annual organ dose rates for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.1 for actions to be taken in the event the calculated annual organ dose rate to any organ exceeds 1500 mr/yr.

CUMULATIVE GAMMA AIR DOSES DUE TO NOBLE GASES INGASEOUS EFFLUENTS

1. Introduction a) Appendix I to 10 CFR 50 specifies cumulative gamma air dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix I.

c) These radiological effluent controls are described below.

Offsite Dose Calculation Manual Page 174 of 325 Revision 5

2. Radiological Effluent Controls a) The cumulative gamma air dose, due to noble gases in gaseous effluents released to UNRESTRICTED AREAS, shall be less than 10 mrads in any calendar quarter, and shall be less than 20 mrads in any calendar year (per Control 3.11.2.2) b) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
3. Surveillance Requirement(s) a) The cumulative gamma air doses, for the current calendar month, -the calendar quarter, and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 60 days (Control 4.11.2.2).

b) The plant group(s) responsible for performing the required surveillance(s) are identified below.

4. Responsible Plant Organizations a) The CHEMISTRY SECTION is responsible for calculating the cumulative gamma air doses for the current calendar quarter and the current caleindar year.

b) The CHEMISTRY SECTION calculates the cumulative gamma air doses whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The cumulative gamma air doses due to noble gases in gaseous effluents shall be determined at least once per 60 days (Control 4.11.2.2).

b) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each release of a WGDT.

c) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each vent of a containment building. I

  • d) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each PURGE of a containment building.

e) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated at least weekly1 for CONTINUOUS discharges from plant vent stacks. !1 The frequency is controlled by the implementing procedure, and is based on plant conditions. __

Under no conditions shall the frequency be less than once per month (Control 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

Offsite Dose Calculation Manual Page 175 of 325 Revision 5 f) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each discharge of combustion products resulting from the burning of contaminated oil.

g) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE'.

h) Whenever the correct initiating conditions are present, the cumulative gamma air doses shall be calculated as described below.

6. Calculation Methodology a) The cumulative gamma air dose at the SITE BOUNDARY (e.g., for the current calendar month, current calendar quarter, current calendar year, or previous 92 days) due to noble gases in gaseous effluents shall be calculated using the following equation 2 :

The criteria used to define ABNORMAL AND UNANTICIPATED GAS RELEASES may be found in theafarm The implementing and fixed procedures.

2 setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9).

Offsite Dose Calculation Manual Page 176 of 325 Revision 5 CUMULATIVE GAMMA, g, AIR DOSE FOR ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t Dgt = *Dgr Eq. 17G

Where, Dgt = the cumulative gamma air dose (mrad) at the SITE BOUNDARY due to noble gas radionuclides contained in all gaseous radwaste discharged from the site during the time interval, t Dgr = the cumulative gamma air dose (mrad) at the SITE BOUNDARY due to noble gas radionuclides contained in gaseous radwaste release, r, discharged from the site during the time interval of interest Calculate the values of Dgr for each gaseous release as described below.

b) At CCNPP, two methods exist for calculating Dgr (i.e., the gamma air dose at the SITE BOUNDARY due to noble gas radionuclides contained in a gaseous radwaste release, r, discharged from the site during a specified time interval).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

c) rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS shall be calculated in accordance with equation 18G.

Offsite Dose Calculation Manual Page 177 of 325 Revision 5 GAMMA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS EQUATION)

, = (3.17E-8)(xQ/) [(M, Q')Eq18G 1

Where, 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

x/Q the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered "long-term" releases 2 , and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases)

(UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3).

M, = the air dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

The gamma air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-I.

The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10.

Q'ir = the total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries).

At CCNPP, all releases are considered long term releases.

Calculate the values of Qir for each release in accordance with equation 19G.

Equation 18G has been derived from NUREG-0133, 5.3.1..

2 NUREG-0133, 3.3

Offsite Dose Calculation Manual Page 178 of 325 Revision 5 TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE 1INGASEOUS RELEASE r Qir = (Ai-) (F,) (wr(e) Eq. 19G Air = the specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcudes/cubic centimeter)

Fr = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second)

Ifthe discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the "Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Whenever possible, the actual discharge flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 19G.

Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures.

tir = the duration of the gaseous radwaste release (seconds) "

c' = a conversion constant, I E6 cubic centimeters per cubic meter, which represents the number of cubic centimeters per cubic meter.

(3) In the event a computer system is unavailable, a simplified equation may be used to calculate the gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS.

(4) The simplified method is presented below.

d) simplified method (1) Ifa computer system and appropriate software are NOT available to perform the rigorous gamma air dose calculation described in the previous section, the gamma air dose, due to noble gas radionuclides, in any single release of waste gases discharged to UNRESTRICTED AREAS may be calculated in accordance with equation 20G.

Offsite Dose Calculation Manual Page 179 of 325 Revision 5 GAMMA AIR DOSE DUE TO NOBLE GASES INGAS RELEASE, r (SIMPLIFIED EQUATION)

Der [ (3.17E) (xQ) (M.vg) / K IYQ' Eq.20G' 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered "long-term" releases 2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases)

(UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3).

Mavg = the empirically derived, site specific, average gamma air dose factor for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

A site-specific, average, gamma air dose factor has been calculated from historical data.

The calculation of this site-specific, average, gamma air dose factor is presented on Attachment 11 (use section 3.4.5 of the old ODCM.)

Ksf = a constant, actually a safety factor, which is the ratio of the CCNPP gamma air dose limit to the gamma air dose limit of Control 3.11.2.2, (unitfess)

The safety factor chosen shall be less than or equal to 1.00. This ensures the gamma air dose is always less than or equal to the gamma air dose limit of Control 3.11.2.2.

A safety factor of 1.00 will yield an gamma air dose which corresponds to the gamma air dose limit of Control 3.11.2.2.

A safety factor of 0.500 will yield an gamma air dose which corresponds to one-half the gamma air dose limit of Control 3.11.2.2.

It is recommended that a safety factor of 1.0 be used for calculating the gamma air dose, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry.

Equation 20G has been derived from NUREG-01 33, 5.3.1.

2 NUREG-0133, 3.3

Offsite Dose Calculation Manual Page 180 of 325 Revision 5 The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.2 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 20G to account for any potential nonconservatism associated with applying the empirically derived gamma air dose factor, Mavg, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a gamma air dose factor greater than Mavg are present in a gaseous release.

Q'ir = the total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries)

At CCNPP, all releases are considered long term releases.

Calculate the values of Qir for each release in accordance with equation 19G.

TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE i INGASEOUS RELEASE r Q0, = (A,)(Fr)(tr)(C') Eq. 19G Air = the specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter).

Fr = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second).

If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the "Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures.

tit = the duration of the gaseous radwaste release (seconds).

c' = a conversion constant, I E6 cubic centimeters per cubic meter, which represents the number of cubic centimeters per cubic meter.

Offsite Dose Calculation Manual Page 181 of 325 Revision 5 e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are initiated as described below.

7. Corrective actions C=,

a) CHEMISTRY SECTION surveillance procedures shall contain/and or I reference administrative and/or Control limits for quarterly and yearly gamma air doses for gaseous effluents and shall specify corrective actions to be Initiated when these limits are exceeded.

b) Refer to Control 3.11.2.2 for actions to be taken in the event the calculated cumulative gamma air doses exceed 10 mrads per calendar quarter or 20 mrads per calendar year.

CUMULATIVE BETA AIR DOSES DUE TO NOBLE GASES IN GASEOUS EFFLUENTS

1. Introduction a) AppendixlI to 10 CFR 50 specifies cumulative beta air dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix I.

c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The cumulative beta air dose, due to noble gases in gaseous effluents released to UNRESTRICTED AREAS, shall be less than 20 mrads in any calendar quarter, and shall be less than 40 mrads in any calendar year (per Control 3.11.2.2) b) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
3. Surveillance Requirement(s) a) The cumulative beta air doses, for the current calendar quarter and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 60 days (Control 4.11.2.2).

b.) The plant group(s) responsible for performing the required surveillance(s) are identified below.

4. Responsible Plant Organizations a) The CHEMISTRY SECTION is responsible for calculating the cumulative beta air doses for the current calendar quarter and the current calendar year.

Offsite Dose Calculation Manual Page 182 of 325 Revision 5 b) The CHEMISTRY SECTION calculates the cumulative beta air doses whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The cumulative beta air doses due to noble gases in gaseous effluents shall be determined at least once per 60 days (Control 4.11.2.2).

b) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each release of a WGDT.

c) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each vent of a containment building. I '

d) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each PURGE of a containment building.

e) The cumulative beta air doses due to noble gases in gaseous effluents are calculated at least weekly' for CONTINUOUS discharges from plant vent stacks.

f) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each discharge of combustion products resulting from the burning of contaminated oil.

g) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each ABNORMAL ANDIOR UNANTICIPATED RADIOACTIVE GAS RELEASE 2.

h) Whenever the correct initiating conditions are present, the cumulative beta air doses shall be calculated as described below.

6. Calculation Methodology a) The cumulative beta air doses (e.g., for the current calendar month, current calendar quarter, current calendar year, or previous 92 days) due to noble gases in gaseous effluents shall be calculated in accordance with equation 21G.

The frequency is controlled by the implementing procedure, and is based on plant conditions.

Under no conditions shall the frequency be less than once per month (Controls 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

The criteria used to define ABNORMAL AND UNANTICIPATED GAS RELEASES may be found in CP-612 or CP-604.

Offsite Dose Calculation Manual Page 183 of 325 Revision 5 CUMULATIVE BETA AIR DOSE FOR ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t DDt Dg, Eq. 21G

Where, Dat = the cumulative beta air dose (mrad) at the SITE BOUNDARY due to noble gas radionuclides contained in all gaseous radwaste discharged from the site during the time interval, t Dar = the beta air dose (mrad) due to noble gas radionuclides contained in gaseous radwaste release, r, discharged from the site during the time interval of interest Calculate the values of Dar for each gaseous release as described below.

b) At CCNPP, two methods exist for calculating Dar (the beta air dose at the SITE BOUNDARY due to noble gas radionuclides contained in a gaseous radwaste release, r, discharged from the site).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

c) Rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the cumulative beta air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS shall be calculated in accordance with equation 22G.

Offsite Dose Calculation Manual Page 184 of 325 Revision 5 BETA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS EQUATION)

Ds, = (3.17E-8) (xQ) [(NI) (Q'rr)] Eq. 22G1 Where, Dr, = the beta air dose due to noble gas radionuclides contained in gaseous radwaste release, r, discharged from the site during the time interval of interest 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered "long-term" releases 2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases)

(UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters-for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3).

Ni = the air dose factor due to beta emissions for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

The beta air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

The beta air dose factors for various noble gas radionuclides are tabulated in Attachment 10 (Attachment 1 of old ODCM).

Q' = the total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries).

At CCNPPTlII releases are considered long term releases.

Calculate the values of Qir for each release in accordance with equation 19G.

1 Equation 22G has been derived from NUREG-0133, 5.3.1.

2 NUREG-0133, 3.3

Offsite Dose Calculation Manual Page 185 of 325 Revision 5 TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Q'i, (Air) (F,) (tr)(C') Eq. 19G AVr = the specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter).

Fr = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second).

If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the "Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures.

tir = the duration of the gaseous radwaste release (seconds).

c! = a conversion constant, I E6 cubic centimeters per cubic meter.

(3) In the event a computer system is unavailable, a simplified equation may be used to calculate the gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS (4) The simplified method is presented below.

d) Simplified method (1) If a computer system and the appropriate software are NOT available to perform the rigorous beta air dose calculation described in the previous section, the beta air dose resulting from a single release of waste gases discharged to UNRESTRICTED AREAS may be calculated in accordance with equation 23G.

Offsite Dose Calculation Manual Page 186 of 325 Revision 5 BETA AIR DOSE DUE TO NOBLE GASES INGAS RELEASE, r (SIMPLIFIED EQUATION)

Dgr [(3.17E-8) (xQ) (Nan) / Ksf d-Q Eq. 23G' 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

x/Q the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered "long-term" releases2 , and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases)

(UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3).

Navg= the empirically derived, site specific, average beta air dose factor for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

A site-specific, average, beta air dose factor has been calculated from historical data.

The calculation of this site-specific, average, beta air dose factor is presented on Attachment 11.

Ksf = a constant, actually a safety factor, which is the ratio of the CCNPP beta air dose limit to the beta air dose limit of Control 3.11.2.2, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the beta air dose is always less than or equal to the beta air dose limit of Control 3.11.2.2.

A safety factor of 1.00 will yield an organ dose which corresponds to the beta air doWsei t-of Control 3.11.2.2.

A safety factor of 0.500 will yield an beta air dose which corresponds to one-half the beta air dose limit of Control 3.11.2.2.

It is recommended that a safety factor of 1.0 be used for calculating the beta air dose, however, other values-not to exceed 1.00--may be used as directed by the General Supervisor Chemistry.

Equation 23G has been derived from NUREG-0133, 5.3.1.

2 NUREG-0133, 3.3

Offsite Dose Calculation Manual Page 187 of 325 Revision 5 The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.2 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 23G to account for any potential nonconservatism associated with applying the empirically derived beta air dose factor, Navg, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a beta air dose factor greater than Navg are present in a gaseous release.

Q'ir = the total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries)

At CCNPP, all releases are considered long term releases.

Calculate the values of Qir for each release in accordance with equation 19G.

TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r di, ((A4,)( F,) (ti..) ( c) Eq. 19G Air = the specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter)

Fr = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second)

If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the "Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average actiiy for nuclide i.

Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures.

tir = the duration of the gaseous radwaste release (seconds).

cý = a conversion constant, 1E6 cubic centimeters per cubic meter.

e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are initiated as described below.

Offsite Dose Calculation Manual Page 188 of 325 Revision 5

7. Corrective actions a) CHEMISTRY SECTION surveillance procedures shall contain/and or I '

reference administrative and/or Control limits for quarterly and yearly beta air doses for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.2 for actions to be taken in the event the calculated cumulative beta air doses exceed 20 mrads per calendar quarter or 40 mrads per calendar year.

CUMULATIVE ORGAN DOSES DUE TO IODINES AND PARTICULATES INGASEOUS EFFLUENTS

1. Introduction a) Appendix I to 10 CFR 50 specifies cumulative organ dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix I.

c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The cumulative organ dose due to iodines and particulates in gaseous effluents released to UNRESTRICTED AREAS shall be less than 15 mrems per calendar quarter, and shall be less than 30 mrems per calendar year (per Control 3.11.2.3).

b) The cumulative organ dose due to iodines and particulates in gaseous, contaminated oil combustion products released to UNRESTRICTED AREAS shall be less than 0.015 mrems per quarter, and shall be less than 0.030 mrems per year (per Control 3.11.2.3).

c) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

3. Surveillance Requirements a) The cumulative organ doses (due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS), for the current calendar month, the current calendar quarter, and the current calendar year, shall be determined at least once every 60 days in accordance with the ODCM (per Control 4.11.2.3).

b) The plant group(s) responsible for performing the required surveillances are identified below.

Offsite Dose Calculation Manual Page 189 of 325 Revision 5

4. Responsible Plant Organizations a) The CHEMISTRY SECTION is responsible for implementing the surveillances required by Control 4.11.2.3.

b) The CCNPP CHEMISTRY SECTION calculates the cumulative organ doses whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The cumulative organ dose-for each organ-shall be determined at least once per 60 days (Control 4.11.2.2).

b) The cumulative organ dose-for each organ--due to iodines and particulates in gaseous effluents shall be calculated at least weekly1 for CONTINUOUS discharges from plant vent stacks. jo c) The cumulative organ dose-for each organ--due to lodines and particulates in gaseous effluents shall be calculated for each discharge of combustion products resulting from the burning of contaminated oil.

d) The cumulative organ dose--for each organ--due to iodines and particulates in gaseous effluents-shall be calculated for each ABNORMAL ANDIOR UNANTICIPATED RADIOACTIVE GAS RELEASE.

e) Whenever the correct initiating conditions are present, the annual cumulative organ doses shall be calculated as described below.

6. Calculation Methodology a) The cumulative organ doses (for the calendar month, calendar quarter, previous 92 days, and calendar year) due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS shall be calculated in accordance with equation 24G.

The frequency is controlled by the implementing procedure, and is based on plant conditions. I Under no conditions shall the frequency be less than once per month (Controls 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

Offsite Dose Calculation Manual Page 190 of 325 Revision 5 CUMULATIVE DOSE TO ORGAN, o, FROM ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t D0t = ZDor Eq. 24G

Where, Dot = the cumulative dose (mrad) to organ, o, at the SITE BOUNDARY, due to iodine and particulate radionuclides contained in gaseous waste discharged from the site during the time interval, t Dor = the dose (mrad) to organ, o, at the SITE BOUNDARY due to iodine and particulate radionuclides in gaseous release, r, discharged from the site during the time interval of interest Calculate the values of Dor for each gaseous release as described below.

b) At CCNPP, two methods exist for calculating Dor (the organ doses due to iodines and particulates resulting from any single release of radioactive gases to an UNRESTRICTED AREA).

(1) The rigorous method shall be used IF a-computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

c) Rigorous method (1) Application of the following equation may prove too rigorous for routine use unless a computer system and the appropriate software are available.

(2) If a computer system and the appropriate software are available, the organ doses due to lodines and particulates contained in any single release of radioactive gases to UNRESTRICTED AREAS shall be calculated in accordance with equation 25G.

Offsite Dose Calculation Manual Page 191 of 325 Revision 5 DOSE TO ORGAN, o, DUE TO IODINES AND PARTICULATES INGAS RELEASE, r (RIGOROUS EQUATION)

Dor = (3.17E-8) (Wv) I (RIpo) (Q',) Eq. 25G1 '

Where, Dor = the dose (mrem) to organ, o, at the SITE BOUNDARY due to iodine and particulate radionuclides in gaseous release, r, discharged from the site dudng the time interval of interest 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

Wv = the dispersion parameter for estimating the dose to an individual at the controlling location for long term releases, and may assume one of two values as described below Wv is x/Q for the inhalation pathway (2.2E-6 sec/cubic meter)

WV is D/Q for the food and ground plane pathways (meters-2 )

D/Q = the dispersion parameter at the controlling location for long term releases (meters-2) 2 The value for DIQ has been determined to be 8.63E-1 0 m-2.

The grass-cow-milk pathway is the controlling pathway. 3 The controlling sector is the south-southwest sector.

The controlling location is at a distance of 4800 meters.3 Ripo = the dose factor for each identified iodine or particul e radionuclide, i, exposure pathway, p, receptor age group, a, and organ, o (m mrem/year per microcuries/second or mrem/year per microcuries/cubic meter) dose factors have been derived for the following pathways

1) inhalation - see Attachment 12
2) ground plane - see Attachment 12
3) grass-cow-milk - see Attachment 12
4) grass-cow-meat - see Attachment 12
5) vegetation - see Attachment 12 1 Equation 25G has been derived from NUREG-0133, 5.3.1.

2 See CP-607, Revision 2 section 3.4.3.

3 See the "Land Use Survey", 1990.

Offsite Dose Calculation Manual Page 192 of 325 Revision 5 The inhalation pathway dose factors were obtained using the formula from NUREG 0133, 5.3.1.1.

The ground plane dose factors were obtained using the formula from NUREG-0133, 5.3.1.2.

The grass-cow-milk pathway dose factors were obtained using the formula from NUREG-01 33, 5.3.1.3.

The grass-cow-meat pathway dose factors were obtained using the formula from NUREG-01 33, 5.3.1.4.

The vegetation pathway dose factors were obtained using the formula from NUREG 0133, 5.3.1.5.

Q'ir = the total (time averaged) activity of iodine or particulate radionuclide, i, in gaseous release, r, discharged during the specified time interval (microcuries)

At CCNPP, all releases are considered long term releases.

Calculate the values of Qir for each release in accordance with equation 19G.

TOTAL (TIME AVERAGED) ACTIVITY OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r iQr = (Air) (F,) (tr) (C') Eq. 19G Air = the specific activity of iodine and particulate radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter)

Fr = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second)

If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the "Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures.

tir = the duration of the gaseous radwaste release (seconds) cl = a conversion constant, 1E6 cubic centimeters per cubic meter (3) In the event a computer system and the appropriate software are unavailable, a simplified equation may be used to calculate the organ doses due to individual gaseous releases.

(4) The simplified method is presented below.

Offsite Dose Calculation Manual Page 193 of 325 Revision 5 d) simplified method (1) If a computer system and appropriate software are NOT available to perform the rigorous organ dose calculations described in the previous section, the organ doses due to iodines and particulates in a single release of radioactive gases discharged to an UNRESTRICTED AREA may be calculated in accordance with equation 26G.

DOSE TO ORGAN, o, FROM IODINES AND PARTICULATES IN GAS RELEASE, r (SIMPLIFIED EQUATION)

Dmaxor = [(3.17E-8)(Wv)(R. 31 )/KfJ] (Q'ir) Eq. 26G' Dmaxor = the maximum dose to any organ, o, due to iodines and particulates contained in any single release, r, of radioactive gases to an UNRESTRICTED AREA 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

D/Q = the dispersion parameter at the controlling location for long term releases (meters-2 )

The value for D/Q has been determined to be 8.63E-1 0 m-2. 2 The grass-cow-milk pathway is the controlling pathway. 3 The controlling sector is the south-southwest sector.

The controlling location is at a distance of 4800 meters.3 R1.13 1 = the infant, thyroid, dose factor for 1-131 via the grass-cow-milk pathway (m2 mrem/year per microcuries/second)

This value is 1.05E12 and it is listed on Attachment 12.

Ksf = a constant, actually a safety factor, which is the ratio of the CCNPP organ dose limit to the organ dose limit of Control 3.11.2.3, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the organ dose is always less than or equal to the organ dose limit of Control 3.11.2.3.

A safety factor of 1.00 will yield an organ dose which corresponds to the organ dose limit of Control 3.11.2.3.

A safety factor of 0.500 will yield an organ dose which corresponds to one-half the organ dose limit of Control 3.11.2.3.

26G has been derived from NUREG-01 33, 5.3.1.

2 See CP-607, Revision 2 section 3.4.3.

3 See the "Land Use Survey", 1990.

Offsite Dose Calculation Manual Page 194 of 325 Revision 5 It is recommended that a safety factor of 1.0 be used for calculating the organ dose, however, other values--not to exceed 1.00-may be used as directed by the General Supervisor Chemistry.

The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.3 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 26G to account for any potential nonconservatism associated with applying the infant, thyroid, grass-cow-milk dose factor, R1.131 , to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a pathway dose factor greater than R1.131 are present in a gaseous release.

air = the total (time averaged) activity of iodine or particulate radionuclide, i, in gaseous release, r (microcuries)

At CCNPP, all releases are considered long term releases.

This value shall be calculated in accordance with equation 19G.

TOTAL (TIME AVERAGED) ACTIVITY OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r Q'i, = (Ar)(Fr) tM) (c') Eq. 19G]

Air = the specific activity of iodine and particulate radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter)

Fr = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second) if the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the "Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures.

tir = the duration of the gaseous radwaste release (seconds) co = a conversion constant, 1E6 cubic centimeters per cubic meter

Offsite Dose Calculation Manual Page 195 of 325 Revision 5 e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are initiated as described below.

7. Corrective actions a) CHEMISTRY SECTION surveillance procedures shall contain/and or I =

reference administrative and/or Control limits for cumulative organ dose for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.3 for actions to be taken in the event the calculated cumulative gamma air doses exceed any of the radiological effluent controls listed above.

LIMITS FOR THE GASEOUS RADWASTE PROCESSING SYSTEM

1. Introduction a) 10 CFR 50.36a requires licensees to maintain and use the equipment installed in the gaseous waste processing system for the purpose of controlling effluents to the environment.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR-50.36a.

c) These radiological effluent controls are described below.

2. Radiological effluent controls a) The GASEOUS RADWASTE PROCESSING SYSTEM and the VENTILATION EXHAUST PROCESSING SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the gaseous effluent air dose, to areas at and beyond the SITE BOUNDARY, exceeds 1.20 mrads gamma radiation in a 92 day period (per Control 3.11.2.4).

b) The GASEOUS RADWASTE PROCESSING SYSTEM and the VENTILATION EXHAUST PROCESSING SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge M when the gaseous effluent air dose, to areas at and beyond the SITE BOUNDARY, exceeds 2.4 mrads beta radiation in a 92 day period (per Control 3.11.2.4)..

c) The VENTILATION EXHAUST PROCESSING SYSTEM shall be used to reduce the quantity of radioactive materials in gaseous waste prior to their discharge when the calculated doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY exceeds 1.80 mrem to any organ in a 92 day period (per Control 3.11.2.4).

d) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

Offsite Dose Calculation Manual Page 196 of 325 Revision 5

3. Surveillance Requirement(s) a) The cumulative gamma air dose, for the previous 92 days, due to noble gases in gaseous effluents, shall be determined at least once every 60 days (Control 4.11.2.2).

b) The plant group(s) responsible for performing the required surveillance(s) are identified below.

4. Responsible Plant Organizations a) The CHEMISTRY SECTION is responsible for calculating the cumulative gamma air doses for the current calendar month, the previous 92 days, the current calendar quarter, and the current calendar year.

b) The cumulative gamma air dose for the previous 92 days is calculated whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.

5. Initiating conditions a) For a listing of initiating conditions associated with calculating gamma air doses, see "Initiating Conditions" in the section of the ODCM titled, "Cumulative Gamma Air Doses Due To Noble Gases In Gaseous Effluents."

b) For a listing of initiating conditions associated with calculating beta air doses, see "Initiating Conditions" in the section of the ODCM titled, "Cumulative Beta Air Doses Due To Noble Gases In Gaseous Effluents."

c) For a listing of initiating conditions associated with calculating cumulative organ doses, see "Initiating Conditions" in the section of the ODCM titled, "Cumulative Organ Doses Due To lodines And Particulates In Gaseous Effluents."

6. Calculation methodology a) Calculate the previous 92-day cumulative gamma air dose as described in the section "Cumulative Gamma Air Doses Due To Noble Gases In Gaseous Effluents."

b) Calculate the previous 92-day cumulative beta air dose as described in the section "Cumulative Beta Air Doses Due To Noble Gases In Gaseous Effluents."

c) Calculate the previous 92-day cumulative organ dose as described in the section "Cumulative Organ Doses Due To lodines And Particulates In Gaseous Effluents."

Offsite Dose Calculation Manual Page 197 of 325 Revision 5

7. Corrective actions a) CHEMISTRY SECTION surveillance procedures shall contain/and or reference administrative and/or Control limits for 92-day cumulative gamma, beta, or organ doses for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.4 for actions to be taken in the event the calculated 92-day cumulative gamma air, beta air, or organ doses exceed any of the radiological effluent controls listed above.

LIMITS ON TOTAL ANNUAL DOSE - GASES, LIQUIDS, AND URANIUM FUEL CYCLE SOURCES

1. Introduction a) 40 CFR 190 specifies annual dose limits for radionuclides released to the environment.

b) Radiological effluent controls have been established to implement the requirements of 40 CFR 190.

c) These radiological effluent controls are described below.

2. Radiological effluent controls a) The total body dose from exposure to the combination of liquid releases, gas releases, and uranium fuel cycle sources shall be less than 25 mrem for the current calendar year (per Control 3.11.4).

b) The organ dose (for the maximum exposed organ, not including the thyroid) from exposure to the combination of liquid releases, gas releases, and uranium fuel cycle sources shall be less than 25 mrem for the current calendar year (per Control 3.11.4).

c) The thyroid dose from exposure to the combination of liquid releases, gas releases, and uranium fuel cycle sources shall be less than 75 mrem for the current calendar year (per Control 3.11.4).

d) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.

3. Surveillance Requirements a) The cumulative gamma air doses, for current calendar month, the current calendar quarter, and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 60 days (Control 4.11.2.2).

b) The cumulative organ doses (due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS), for the current calendar month, the current calendar quarter, and the current calendar year, shall be determined at least once every 60 days in accordance with the ODCM (per Control 4.11.2.3).

Offsite Dose Calculation Manual Page 198 of 325 Revision 5 C) Cumulative total body dose to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS-for the current calendar month, the calendar quarter, and the current calendar year--shall be calculated at least once per 60 days (per Control 4.11.1.2).

d) Cumulative organ doses to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS--for the current calendar month, the current calendar quarter, and the current calendar year--shall be calculated at least once per 60 days (per Control 4.11.1.2).

e) The direct radiation dose to MEMBERS OF THE PUBLIC exposed to uranium fuel cycle sources (i.e., reactor units and outside storage tanks) shall be determined IF THE APPROPRIATE INITIATING CONDITIONS ARE PRESENT.

4. Responsible Plant Organization(s) a) The CHEMISTRY SECTION is responsible for implementing the effluent surveillances required by Control 4.11.4.1.

b) The CHEMISTRY SECTION is responsible for ensuring implementation of the direct radiation surveillances required by Control 4.11.4.2.

c) IT SHOULD BE NOTED THAT NO SURVEILLANCES NEED BE PERFORMED UNILESS THE APPROPRIATE INITIATING CONDITIONS ARE PRESENT.

d) These initiating conditions are contained In the following section.

5. Initiating conditions a) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated doses from liquid effluents exceed any of the following (per Control 4.11.4.2):

(1) Six (6) mrem per quarter to the total body (2) Twelve (12) mrem per calendar year to the total body (3) Twenty (20) mrem per quarter to any organ (4) Forty (40) mrem per calendar year to any organ b) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated air doses from noble gasses in gaseous effluents exceed any of the following (per Control 4.11.4.2):

(1) Twenty (20) mrad gamma per quarter (2) Forty (40) mrad gamma per calendar year (3) Forty (40) mrad beta per quarter

Offsite Dose Calculation Manual Page 199 of 325 Revision 5 (4) Eighty (80) mrad beta per calendar year c) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated organ doses from iodines and particulates in gaseous effluents exceed any of the following (per Control 4.11.4.2):

(1) Thirty (30) mrem per quarter to any organ (2) Sixty (60) mrem per calendar year to any organ d) Whenever the correct initiating conditions are present, the total doses from liquid releases, gas releases, and uranium fuel cycle sources (for the calendar year) shall be calculated as shown below.

6. Calculation methodology a) The total body dose and the organ doses from liquid releases, gas releases, and uranium fuel cycle sources (for the calendar year) shall be calculated in accordance with equation 1T and 2T respectively.

TOTAL, TOTAL BODY DOSE FROM LIQUID RELEASES, GAS RELEASES, AND URANIUM FUEL CYCLE SOURCES Dtbal = DToL + Dgt + Dtank Eq. IT TOTAL ORGAN DOSES FROM LIQUID RELEASES, GAS RELEASES, AND URANIUM FUEL CYCLE SOURCES Doasi = DToL + Dot + Dta.k Eq.2T Dtball = the dose (mrem) to total body resulting from the combination of all gas releases, all liquid releases, and all uranium fuel cycle sources.

= the dose (mrem) to organ, o, resulting from the combination of all gas releases, all liquid releases, and all uranium fuel cycle sources.

Separate values shall be calculated for each of the organs listed below:

1. bone
2. liver
3. thyroid
4. kidney
5. lung
6. GI tract

Offsite Dose Calculation Manual Page 200 of 325 Revision 5 DTOL = the cumulative dose (mrem) to organ, o, for all liquid releases discharged in a given time interval Calculate this value as specified by equation 8L.

Dgt = the site-boundary cumulative gamma air dose (mrad) due to noble gas radionuclides contained in all gaseous radwaste discharged from the site during the time interval, t Calculate this value as specified by equation 17G, except substitute K, for M1 (see Attachment 10).

Dot = the site-boundary cumulative organ dose (mrem) resulting from the release of iodine and particulate radionuclides in gaseous releases from the site Calculate this value as specified by equation 24G.

Drank = the calendar-year cumulative dose (mrem) to the maximum exposed MEMBER OF THE PUBLIC due to direct radiation from the reactor units and outside storage tanks This value shall be based on the results of direct radiation measurements from TLDs or continuous dose rate instruments placed near the SITE BOUNDARY (e.g., from radiological environmental monitoring sites DRI-DR9 described on Attachment 13 and shown on Attachment 18).

The CHEMISTRY SECTION, and the Radiation Safety Section are responsible for determining this value.

b) Compare the calculated values to the radiological effluent controls (listed in this section), and if any of the radiological effluent controls have been exceeded, perform the appropriate corrective actions listed below.

7. Corrective actions a) CHEMISTRY SECTION surveillance procedures shall contain/and or reference administrative and/or Control limits for total dose for liquid releases, gaseous releases, and uranium fuel cycle sources and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.4 for actions to be taken in the event the total dose exceeds any of the radiological effluent controls listed above.

c) If any of the radiological effluent controls have been exceeded, refer to 40 CFR 302, Appendix B, and verify the quantities of radioactive materials released are less than the values specified. [375B]

Offsite Dose Calculation Manual Page 201 of 32:5 Revision 5 SPECIAL EXCEPTIONS AND ASSUMPTIONS FOR CALCULATION OF DOSES AND DOSE RATES

1. CamD Conov a) Locatic (1) Camp Conoy is located within the SITE BOUNDARY.

(2) Camp Conoy is located in the SE sector.

(3) Camp Conoy is approximately 3000 feet from the plant.

b) Occupancy (1) Camp Conoy is frequently visited by MEMBERS OF THE PUBLIC.

(2) Maximum occupancy for MEMBERS OF THE PUBLIC at Camp Conoy is restricted to approximately 3380 hours0.0391 days <br />0.939 hours <br />0.00559 weeks <br />0.00129 months <br /> per year.

C) Meteorology (1) The highest historical annual average x/Q for Camp Conoy is 2.40E-6 seconds per cubic meter.'

d) Dose calculation assumptions (1) Based on sections (b) and (c) above, any actual exposure to a MEMBER OF THE PUBLIC at Camp Conoy will be less than the calculated exposure for a MEMBER OF THE PUBLIC at the SITE BOUNDARY.'

(2) No special considerations are required for addressing potential exposure at Camp Conoy.

2. Visitor's Center a) Location (1) The Visitor's Center is located within the SITE BOUNDARY.

(2) The Visitor's Center is located in the WNW sector.

(3) The Visitor's Center is approximately 1000 feet from the plant.

b) Occupancy (1) The Visitor's Center is frequently visited by MEMBERS OF THE PUBLIC.

1 See CP-607, Revision 2 page 24.

Offsite Dose Calculation Manual Page 202 of 325 Revision 5 (2) Maximum occupancy for MEMBERS OF THE PUBLIC at The Visitor's Center is restricted to daylight hours.

c) Meteorology (1) The highest historical annual average x/Q for the Visitor's Center is 8.68E-6 seconds per cubic meter.'

(2) The wind frequency for the WNW sector, based on 1983 meteorological data, is four percent (4%).'

d) Dose calculation assumptions (1) "Using a conservative basis of 10% wind frequency, and individual visiting the center for 330 hour0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />s/year during the periods of worst case meteorological conditions would be most highly exposed."1 (2) The dose calculated for the controlling SITE BOUNDARY is more conservative by a factor of 7.1 (3) Based on sections (b) and (c) above, any actual exposure to a MEMBER OF THE PUBLIC at The Visitor's Center will be less than the calculated exposure for a MEMBER OF THE PUBLIC at the SITE BOUNDARY.

(4) No special considerations are required for addressing potential exposure at The Visitor's Center.

I See CP-607, Revision 2 page 24.

Offsite Dose Calculation Manual Page 203 of 325 Revision 5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM1

1. Introduction a) 10 CFR 50, Appendix I, Section IV.B.2 requires licensees to establish an environmental surveillance and monitoring program for the purpose of evaluating the relationship between quantities of radioactive material released in effluents and resultant radiation doses to individuals.

b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix 1,Section IV.B.2.

c) These radiological environmental controls are described below.

2. Controls on the Radiological Environmental Monitoring Program (REMP) a) The REMP shall consist of environmental sample locations, analysis parameters, analysis frequencies, detection limits, and ACTION levels all of which conform to the requirements of Control 3.12.1. (See Attachment 13, 14,15, 16, and 17).

b) The REMP shall maintain a map showing sample locations near the SITE BOUNDARY in accordance with Control 3.12.1. (See Attachment 18).

C) The REMP shall maintain a map showing sample locations within a 8 km.

radius of the plant in accordance with Technical Specification 6.6.2 (Improved Technical Specification 5.6.2). (See Attachment 19).

3. Surveillance Requirements a) Surveillances for direct radiation (1) Direct radiation dosimetry shall be collected from locations DR1 DR23 listed on Attachment 13.

(2) In the event any of the monitoring stations, DR1-DR23, described on Attachment 13 become unavailable, establish new monitoring stations (with new dosimetry) as described below:

(a) In lieu of any location DR1-DR9 described on Attachment 13, establish a new monitoring station in the same meteorological sector in the general area of the SITE BOUNDARY.

(b) In lieu of any location DR10-DR18 described on Attachment 13, establish a new monitoring station in the This portion of the environmental monitoring program is designed to monitor the environment surrounding the CCNPP. A separate environmental monitoring program designed to monitor the environment surrounding the Independent Spent Fuel Storage Installation is described elsewhere in the ODCM.

Offsite Dose Calculation Manual Page 204 of 325 Revision 5 same meteorological sector in the 6-8 km range from the site.

(c) In lieu of any location DR19-DR23 described on Attachment 13, establish a new monitoring station in either a special interest area (e.g., population center, nearby residence, school) or a control station whichever is applicable.

(3) In the event any dosimetry at an existing monitoring location DRI DR23 becomes unavailable, place new dosimetry at the monitoring station.

(4) Analyze the dosimeters at the frequencies and for the parameters identified on Attachment 14.

(5) The sampling locations(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM after October 31 of the year in which the land use census was conducted in accordance with Control 3.12.2.b.

b) Surveillances for airborne activity (1) Radioiodine and particulate samples shall be collected from locations Al1-A5 listed on Attachment 13.

(2) In the event any of the monitoring stations, AI-A5, described on Attachment 13 become unavailable, establish new monitoring station(s) (fitted with new radioiodine and particulate samplers) as described below:

(a) In lieu of any location Al1-A3 described on Attachment 13, establish a new monitoring station in the general area of the SITE BOUNDARY, such that the three monitoring stations are located in the meteorological sectors with the three highest calculated annual average ground level D/Q.

(b) In lieu location A4 described on Attachment 13, establish a new monitoring station near a community having the highest calculated annual average ground level D/Q.

(c) In lieu of location A5 described on Attachment 13 establish a new "control" location 15 to 30 kilometers from the plant in the least prevalent wind direction.

(3) In the event any radioiodine cartridge or particulate filter becomes unavailable from an existing monitoring location A1-A5 described on Attachment 13, place new radioiodine cartridge or particulate filter in the air sampler at the monitoring station.

(4) Analyze the samples at the frequencies and for the parameters identified on Attachment 15.

Offsite Dose Calculation Manual Page 205 of 325 Revision 5 (5) The sampling locations(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM after October 31 of the year in which the land use census was conducted in accordance with Control 3.12.2.b.

c) Surveillances of waterborne activity (1) Water and sediment samples shall be collected from the locations Wal, Wa2, and Wbl listed on Attachment 13.

(2) In the event any of the samples at Wal, Wa2, or Wbl are unavailable, collect substitute samples as described below:

(a) In lieu of a liquid sample at Wal, collect a substitute sample of surface water from the intake area.

(b) In lieu of a liquid sample at Wa2, collect a substitute sample of surface water from the discharge area.

(c) In lieu of sample at Wbl, collect a substitute sample of sediment from a downstream shoreline with existing or potential recreational value.

(3) Analyze the samples at the frequencies and for the parameters identified on Attachment 16.

(4) The sampling locations(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM after October 31 of the year in which the land use census was conducted in accordance with Control 3.12.2.b.

d) Surveillances for ingestible activity (1) Fish/invertebrate, milk, and food product samples shall be collected from the locations lal thru la6 and Ibl thru Ib9 listed on Attachment 13.

(2) In the event any of the samples at lal thru la6 or IbI thru Ib9 are unavailable, collect substitute samples as described below:

(a) In lieu of samples at lal thru la3, collect substitute three commercially and/or recreationally important species (two fish species and one invertebrate species) from the vicinity of the plant discharge area.

(b) In lieu of samples at la4 thru la6, collect three commercially and/or recreationally important species (two fish species and one invertebrate species) from an area not influenced by plant discharges.

Offsite Dose Calculation Manual Page 206 of 325 Revision 5 (c) In lieu of samples at IbI thru Ib6, collect three kinds of broad leaf vegetation grown near the SITE BOUNDARY at two different locations of highest average ground level D/Q 1 .

(d) In lieu of samples at Ib7 thru Ib9, collect one sample each of the similar broad leaf vegetation grown 15-30 km distant in the least prevalent wind direction.

(3) Analyze the samples at the frequencies and for the parameters identified on Attachment 17.

(4) The sampling locations(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from the Radiological Environmental Monitoring Program after October 31 of the year in which the land use census was conducted in accordance with Control 3.12.2.b.

4. Responsible Company Organizations a) The CHEMISTRY SECTION, CCNPPI is responsible for ensuring I
  • performance of the surveillances listed above.
5. Initiating conditiouis a) Collect samples in accordance with the frequencies specified on Attachments 14, 15, 16, and 17.

b) Analyze samples in accordance with the frequencies specified on Attachments 15, 16, and 17.

c) Calculate the potential annual doses in accordance with the methodology outlined below if any of the following conditions are true:

(1) any of the above surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 15, 16, 17 (per Control Table 3.12-2)

(2) any radionuclides other than those in Attachments 15, 16, and 17 are detected, and the radionuclides are the result of plant effluents.

d) The REMP Manager is responsible for notifying the General Supervisor-Chemistry, CCNPP, if any of the following conditions are true:

(1) any of the above surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 15, 16 17 (per Control Table 3.12-2)

With fresh leafy vegetable samples unavailable from one or more of the sample locations listed on Attachment 13, perform corrective actions specified by Control 3.12.1.c.

Offsite Dose Calculation Manual Page 207 of 325 Revision 5 (2) any radionuclides other than those in Attachments 15, 16, and 17 are detected, and the radionuclides are the result of plant effluents, and the potential annual doses due to the radionuclides are greater than the calendar year limits of Controls 3.11.1.2, 3.11.2.2, and 3.11.2.3.

6. Calculation methodology a) Ifthe correct initiating conditions, as described above, are present, calculate potential annual doses for the pathway of interest in accordance with the methodologies contained in ODCM, or b) if methodologies other than those listed in the ODCM are used to calculate potential annual doses, such methodologies shall be documented in the AREOR in accordance with Control 3.12.1.b.
7. Corrective ACTIONs a) If a sample is unobtainable due to sampling equipment malfunction, then attempt to restore equipment to operable status before the end of the next sampling period, and document in the AREOR (per Control 4.12.1, Table 3.12-1, notation "a").

b) If the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM is not being conducted Tn accordance with Attachments 13, 14, 15, 16, or 17 document deviations in the AREOR (per Control 3.12.1.a).

c) With fresh leafy vegetable samples unavailable from one or more of the sample locations listed on Attachment 13, establish a new monitoring location and document applicable information in the AREOR (per Control 3.12.1.c).

d) When the analysis result for any parameter exceeds the ACTION Level listed on Attachments 15, 16, or 17, submit a Special Report to the NRC (per Control 3.12.1.b).

e) When radionuclides other than those listed on Attachments 15, 16, and 17 are detected; and if those radionuclides are the result of plant effluents; and if the potential annual doses due to the radionuclides are greater than the calendar year limits of Controls 3.11.1.2, 3.11.2.2, and 3.11.2.3; submit a Special Report in accordance with Control 3.12.1 .b.

Offsite Dose Calculation Manual Page 208 of 325 Revision 5 LAND USE CENSUS

1. Introduction a) 10 CFR 50, Appendix I, Section IV.B.3 requires licensees to identify changes in the use of UNRESTRICTED AREAS In order to permit modifications in monitoring programs.

b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix 1,Section IV.B.3.

c) These radiological environmental controls are described below.

2. Controls on the Land Use Census a) Identify the location of the nearest milk animal, within a distance of 8 km of the plant site, in each of the 9 meteorological sectors (per Control 3.12.2).

b) Identify the location of the nearest residence, within a distance of 8 km of the plant site, in each of the 9 meteorological sectors (per Control 3.12.2).

c) Identify the location of the nearest garden, within a distance of 8 km of the plant site, in each of the 9 meteorological sectors; or if the garden census was not conducted, obtain samples of three different kinds of broad leaf vegetation from the SITE BOUNDARY in two different meteorological sectors which have the highest predicted SITE BOUNDARY D/Q (per Control 3.12.2).

3. Surveillance Requirement(s) a) Perform a land use census that will provide the best results. Example methods may include, but are not limited to, the following:

(1) door-to-door surveys (2) aerial views (3) consult local agricultural authorities b) Document the results of the land use census in the Annual Radiological Environmental Operating Report in accordance with Technical Specification 6.6.2 (Improved Technical Specification 5.6.2).

c) Perform an Independent Technical Review of the land use census data.

4. Responsible Company Organizations C1.4 a) The Chemistry Section, CCNPPI, is responsible for ensuring the I '

performance of the surveillances listed above.

Offsite Dose Calculation Manual Page 209 of 325 Revision 5

5. Initiating conditions a) Conduct the land use census during the growing season, and conduct the land use census at least once per 12 months.
6. Calculation methodology a) Calculate doses for the pathways of interest in accordance with the methodologies contained in Regulatory Guide 1.109, or b) if methodologies other than those listed in Regulatory Guide 1.109 are used to calculate doses, such methodologies should be documented in the Annual Radiological Environmental Operating Report.
7. Corrective actions a) The results of the land use census shall be used to determine the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM's sample locations identified on Attachment 13.

b) If the land use census has identified a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, perform the following activities.

(1) Document the new location(s) in the next Annual Radiological Environmental Operating Report in accordance with Technical Specification 6.6.2 (Improved Technical Specification 5.6.2), and (2) revise the figures and tables in the ODCM to reflect the new location(s).

c) If the land use census has identified a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) which is 20%

greater than the equivalent location identified on Attachment 13, perform the following activities.

(1) Add the new location(s) to the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM within 30 days, (2) document the new location(s) in the next Annual Radiological Environmental Operating Report in accordance with Technical Specification 6.6.2 (Improved Technical Specification 5.6.2), and (3) revise the figures and tables in the ODCM to reflect the new location(s).

INTERLABORATORY COMPARISON PROGRAM I. Introduction a) 10 CFR 50, Appendix I, Section IV.B.2 requires licensees to establish an environmental surveillance and monitoring program for the purpose of evaluating the relationship between quantities of radioactive material released in effluents and resultant radiation doses to individuals.

Offsite Dose Calculation Manual Page 210 of 325 Revision 5 b) Radiological environmental controls have been established to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

c) These radiological environmental controls are described below.

2. Controls on the Interlaboratory Comparison Program a) Analyze INTERLABORATORY COMPARISON PROGRAM samples supplied by either the Commission or a Commission approved laboratory for all parameters listed on Attachments 15, 16, and/or 17, as applicable' (per Control 3.12.3).
3. Surveillance Requirement(s) a) A summary of the results obtained as part of the Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.6.2 (Improved Technical Specification 5.6.2).

b) This section of the ODCM shall describe the Interlaboratory Comparison Program.

4. RWsponsible Company Organizations a) The CHEMISTRY SECTION, CCNPPI, is responsible for ensuring I '

performance of the surveillances listed above.

5. Initiating conditions a) Analyze INTERLABORATORY COMPARISON PROGRAM samples whenever they are supplied by either the Commission or a Commission approved laboratory.
6. Calculation methodology a) Analysis methods and calculational methodologies used to satisfy the above surveillances shall be documented in approved procedures.
7. Corrective actions a) Ifanalyses are not performed as required, document actions taken to prevent reoccurrence in the Annual Radiological Environmental Operating Report (AREOR) pursuant to Technical Specification 6.6.2 (Improved Technical Specification 5.6.2).

Since no Commission approved laboratory supplies TLDs as part of a comparison program, no TLDs are analyzed as part of the INTERLABORATORY COMPARISON PROGRAM.

Offsite Dose Calculation Manual Page 211 of 325 Revision 5 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT I- Introduction a) 10 CFR 50, Appendix I, Section IV.B.2 requires licensees to provide data on measurable levels of radiation and radioactive materials in the environment.

b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix I, Section IV.B.2.

c) These radiological environmental controls are described below.

2. Controls on the Annual Radiological Environmental Operating Report (AREOR) a) The AREOR shall include a summary description of the radiological environmental monitoring program (REMP).

b) The AREOR shall include a summary description of the Independent Spent Fuel Storage Installation Monitoring Program (ISFSIMP).

c) The AREOR shall include a table similar to Attachment 13 which states the distance and direction from the central point between the two containment buildings to each of the REMP sample points. _

d) The AREOR shall include a table similar to Attachment 20 which states the distance and direction from the central point of the ISFSI to each of the ISFSIMP sample points.

e) The AREOR shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period.

f) The AREOR shall include a comparison between the annual REMP results and the Radiological Environmental Operating Report preoperational studies.

g) The AREOR shall include a comparison between the annual ISFSIMP results and Radiological Environmental Operating Report pre-fuel-load studies.

h) The AREOR shall include a comparison with operational controls as appropriate.

i) The AREOR shall include a comparison with the previous environmental surveillance reports.

j) The AREOR shall include an assessment of the observed impacts of plant operation on the environment.

k) The AREOR shall include an assessment of the observed impacts of ISFSI operation on the environment.

Offsite Dose Calculation Manual Page 212 of 325 Revision 5 I) The AREOR shall include the results of the land use censuses required by Control 3.12.2.

m) The AREOR shall include the results of analysis of all radiological environmental samples taken during the period pursuant to the locations specified on Attachments 13 and 20.

n) The AREOR shall include the results of all environmental radiation measurements taken during the period pursuant to the locations specified on Attachments 13 and 20.

o) The AREOR shall include summarized and tabulated results--in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979-of analysis of all radiological environmental samples taken during the period pursuant to the locations specified on Attachments 13 and 20.

p) The AREOR shall include summarized and tabulated results--in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979-of all environmental radiation measurements taken during the period pursuant to the locations specified on Attachments 13 and 20.

q) The AREOR shall include an explanation for missing results, if some individual results (as described in the above paragraph) are not available for inclusion with the report.

r) The AREOR shall include any data which was missing from previous reports.

s) The AREOR shall include at least two legible mapslcovering all REMP sampling locations keyed to a table giving distances and directions from the central point between the two containment buildings.

t) The AREOR shall include at least one legible map covering all ISFSIMP sampling locations keyed to a table giving distances and directions from the central point of the ISFSI.

u) The AREOR shall include results of the licensee participation in the INTERLABORATORY COMPARISON PROGRAM required by Control 3.12.3.

v) The AREOR shall include a discussion of all deviations from the sampling schedules listed on Attachments 14, 15, 16, and 17, and specify the reason(s) for the deviations, and the plan for preventing recurrence.

w) The AREOR shall include a discussion of all analyses in which the LLD listed on Attachments 15, 16, and 17 (and required by Control Table 4.12-1) was not achievable.

One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

Offsite Dose Calculation Manual Page 213 of 325 Revision 5 X) The AREOR shall include the identification of the cause of unavailability of samples (if any), and describe the locations used for replacement samples.

y) The AREOR shall include any permanent changes in the sample locations in the monitoring program.

z) The AREOR shall include revised figure(s) (e.g., like Attachments 18 and

19) and tables (e.g., like Attachment 13) for the ODCM which reflect any new REMP sample location(s).

aa) The AREOR shall include revised figure(s) (e.g., like Attachments 21 and

22) and table(s) (e.g., like Attachment 20) for the ODCM which reflect any new ISFSIMP sample location(s).

bb) The AREOR shall receive an independent review for technical content prior to submittal to the NRC.

cc) The AREOR shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result.

dd) Material provided in the AREOR shall be consistent with the objectives outlined in the ODCM and 10 CFR 50, Appendix 1,Section IV.3.2, IV.3.3 and NV.C.

3. Surveillance Requirement(s) a) Write the Annual Radiological Environmental Operating Report covering the previous calendar year's operation of the reactor units.
4. Responsible Company Organizations a) The Chemistry Section, CCNPPI, is responsible for ensuring the performance of the surveillances listed above'.
5. Initiating conditions a) Submit the Routine AREOR (covering operation of the reactor units for the previous calendar year) of each year in accordance with Technical Specifications 6.6.2 (Improved Technical Specification 5.6.2).
6. Calculation methodology a) Calculational methodologies used to satisfy the above surveillances should be documented in approved procedures, or should be included in the AREOR.

I A separate company may be contracted to complete the Routine AREOR.

Offsite Dose Calculation Manual Page 214 of 325 Revision 5

7. Corrective actions a) If analyses are not performed as required, document actions taken to prevent reoccurrence in the AREOR pursuant to Technical Specification 6.6.2 (Improved Technical Specification 5.6.2).

INDEPENDENT SPENT FUEL STORAGE INSTALLATION MONITORING PROGRAM

1. Introduction a) The Technical Specifications for the Independent Spent Fuel Storage Installation1 (ISFSI), licensed under 10 CFR 72, require that monitoring for the ISFSI be added to the existing environmental monitoring program for CCNPP.

b) CCNPP has committed to additional monitoring for the ISFSI. 2 c) Radiological environmental controls have been established to implement the requirements and commitments described above.

d) These radiological environmental controls are described below.

2. Controls on the ISFSI Monitoring Program a) Environmental rnonitoring sites, as described in Attachment 20, shall be established to monitor the air, vegetation, and soil as well as direct radiation in the ISFSI environs.

b) Analysis parameters, analysis frequencies, detection limits, and ACTION levels shall conform to the applicable requirements of Controls 3.12.1.

(See attachment 14, 15, 16, and 17) c) Map(s) shall be maintained and shall show the locations of the environmental monitoring sites with respect to plant facilities. (See attachment 21 and 22).

3. Surveillance Requirements a) Surveillances for direct radiation (1) Direct radiation dosimetry shall be collected from locations SFDR1-SFDR16, DR7, and DR30 listed in Attachment 20.

The Technical Specifications For Calvert Cliffs Independent Spent Fuel Storage Installation is Appendix "A"to Materials License SNM-2505.

See the letter titled "Response to NRC's Comments to Environmental Issues Regarding BGE's License Application for Calvert Cliffs Independent Spent Fuel Storage Installation (ISFSI)" from Mr. R. E. Denton (BGE) to Director, Office of Nuclear Material Safety and Safeguards (NRC),

dated November 1, 1990.

Environmental monitoring sites and monitoring parameters specifically excluded from the ISFSIMP include airborne radioiodines, radioiodines in food products, surface water, and fish and invertebrates. Additionally, soil samples shall be collected in lieu of shoreline sediment. The sampling frequency for vegetation and soil shall be quarterly.

Offsite Dose Calculation Manual Page 215 of 325 Revision 5 (2) In the event any dosimetry at an existing monitoring location SFDRI-SFDR16, DR7, or DR30 becomes unavailable, place new dosimetry at the monitoring station.

(3) Analyze the dosimeters at the frequencies and for the parameters identified on Attachment 14.

b) Surveillances for airborne particulate activity (1) Air particulate samples shall be collected from locations Al and SFAI-SFA4 listed on Attachment 20.

(2) In the event any particulate filter becomes unavailable from an existing monitoring location Al or SFAI-SFA4 described on Attachment 20, place a new particulate filter in the air sampler at the monitoring station.

(3) Analyze the samples at the frequencies and for the parameters identified under "Particulate Filters" on Attachment 15.

c) Surveillances for deposition on vegetation (1) The vegetation samples SFbI -SFb5 shall be collected from the locations listed on Attachment 20.

(2) In the event any of the sampling sites SFbl-SFb5 described on Attachment 20 become unavailable, establish new sampling sites as described below:

(a) In lieu of sample SFbI, collect vegetation grown in the NW sector of the ISFSI.

(b) In lieu of sample SFb2, collect vegetation grown in the general vicinity of the CCNPP Visitor's Center.

(c) In lieu of sample SFb3, collect vegetation grown in the North North West sector of the ISFSI.

(d) In lieu of sample SFb4, collect vegetation grown in the South sector of the ISFSI.

(e) In lieu of sample SFb5, collect vegetation grown in the Southeast sector of the ISFSl.

(3) Analyze the samples quarterly for the non-iodine parameters identified under "Food Products" on Attachment 17.

d) Surveillances for soil activity (1) The soil samples SFSI-SFS5 shall be collected from the locations listed on Attachment 20.

Offsite Dose Calculation Manual Page 216 of 325 Revision 5 (2) In the event any of the sampling sites SFS1-SFS5 described on Attachment 20 become unavailable, establish new sampling sites as described below:

(a) In lieu of sample SFS1, collect soil in the NW sector of the ISFSI.

(b) In lieu of sample SFS2, collect soil in the general vicinity of the CCNPP Visitor's Center.

(c) In lieu of sample SFS3, collect soil in the North North West sector of the ISFSI.

(d) In lieu of sample SFS4, collect soil in the South sector of the ISFSI.

(e) In lieu of sample SFS5, collect soil in the Southeast sector of the ISFSI.

(3) Analyze the samples quarterly for the parameters identified under "Shoreline Sediment Sample" on Attachment 16.

4. Responsible Company Organizations a) The CHEMISTRY SECTION, CCNPPI, is responsible for ensuring the performance of the surveillances listed above.
5. Initiating conditions a) Collect samples in accordance with the frequencies specified on Attachments 14, 15, 16, and 17. Soil and vegetation samples shall be collected quarterly.

b) Analyze samples in accordance with the frequencies specified on Attachments 14, 15, 16, and 17. Soil and vegetation samples shall be analyzed quarterly.

c) Calculate the potential annual doses in accordance with the methodology outlined elsewhere in this section if any of the following conditions are true:

(1) any of the above surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 14, 15, 16, and 17, as appropriate. (per Control Table 3.12-2), or (2) any radionuclides other than those listed on Attachments 14, 15, 16, and 17 are detected, and the radionuclides are the result of plant effluents or radionuclide deposition from the ISFSJ, and the potential annual doses due to the radionuclides are greater than the limits listed in Control 3.12.1 .b.

Offsite Dose Calculation Manual Page 217 of 325 Revision 5 d) The Chemistry Section, CCNPPI, is responsible for notifying the General I ¢ Supervisor--Chemistry, CCNPP, if any of the following conditions are true:

(1) any of the above surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 14, 15, 16, and 17, as appropriate (per Control Table 3.12-2), or (2) any radionuclides other than those in Attachments 14, 15, 16, and 17 are detected, and the radionuclides are the result of plant effluents or radionuclide deposition from the ISFSI, and the pote-intialannuýf~al d-o-ses due to the radionuclides are greater than the limits listed in Control 3.12.1.b.

6. Calculation methodology a) If any (of the above) surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 14, 15, 16, or 17 (per Control Table 3.12-2), calculate potential annual doses for the pathway of interest, in accordance with the methodologies contained in Regulatory Guide 1.109.

b) If methodologies other than those listed in Regulatory Guide 1.109 are used to calculate potential annual doses, such methodologies shall be documented in accordance with Control 3.12.1.b.

7. Corrective actions a) If a sample is unobtainable due to sampling equipment malfunction, then attempt to restore equipment to operable status before the end of the next sampling period, and document in the AREOR.

b) If the ISFSIMP Is not being conducted in accordance with the "Surveillance Requirements" listed elsewhere in this section, document deviations in'the AREOR.

c) When the analysis result for any parameter exceeds the ACTION Level listed on Attachments 15, 16, or 17, as appropriate, submit a Special Report to the NRC (per Control 3.12.1 .b).

d) When radionuclides other than those listed on Attachments 15, 16, and 17 are detected, and when those radionuclides are the result of plant effluents or radionuclide deposition from the ISFSI, submit a Special Report if required by and in accordance with Control 3.12.1 .b.

Offsite Dose Calculation Manual Page 218 of 325 Revision 5 RADIOACTIVE EFFLUENT RELEASE REPORT INTRODUCTION

1. Technical Specification 6.6.3 (improved Technical Specification 5.6.3) requires submittal of a written report to the NRC every 12 months.
2. The report is described below.

RESPONSIBILITIES

1. The General Supervisor Chemistry is responsible for the timely and accurate completion of the report.

REPORT CONTENTS

1. The Radioactive Effluent Release Report (RERR) covering the operation of the unit shall be submitted every 12 months in accordance with 10 CFR 50.36a.
2. The RERR shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. The material provided shall be consistent with the objectives outlined in the ODCM and in conformance to 10CFR50.36a and 10CFR50, Appendix I, section IV.B.1.

Principle Gamma Emitters from Batch Waste Releases and Turbine Building Sump shall be analyzed and included in this report pursuant to Table Notation c of Control Table 4.11-1, "Radioactive Liquid Waste Sampling and Analysis Program." In addition, Principal Gamma Emitters from the Waste Gas Storage Tank, Containment Purge and Vent, and the Main Vent shall be analyzed and included in this report pursuant to Table Notation b of Controls Table 4.11-2, "Radioactive Gaseous Waste Sampling and Analysis Program." Additional information which may be required in the report is contained in Controls 3.3.3.9.b, 3.3.3.10.b and Technical Specification 6.6.3 (Improved Technical Specification 5.6.3).

3. The RERR shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or In the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.1 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. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

Inlieu of submission with the Radioactive Effluent Release Report, this summary of required meteorological data may be retained on site in a file that shall be provided to the NRC upon request.

Offsite Dose Calculation Manual Page 219 of 325 Revision 5

4. The RERR 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 CFR Part 190, Environmental Radiation Protection Standards for with 40 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, and NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants."
5. The RERR shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report.period:__
a. Container volume,
b. Total curie quantity (specify whether determined by measurement or estimate),
c. Principal radionuclides (specify whether determined by measurement or estimate),
d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),
e. Solidifi-,ation agent or absorbent (e.g., cement).
6. The RERR shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
7. The RERR shall include any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM) and a listing of new locations for dose calculations identified by the annual land use census pursuant to Control 3.12.2.
8. The RERR shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP)'- The report shall contain:
a. A description of the equipment, components and processes involved.
b. Documentation of the fact that the change, including the safety analysis, was reviewed and found acceptable by the POSRC.

REPORT SUBMITTAL

1. Prior to submittal a Independent Technical Review will be performed.
2. The RERR will be submitted every 12 months in accordance with 10 CFR 50.36a and 50.4.

Licensee initiated changes to the PCP shall become effective upon review by the POSRC and approval of the Plant General Manager.

Offsite Dose Calculation Manual Page 220 of 325 Revision 5 ADMINISTRATION OF THE ODCM INTRODUCTION

1. Procedures covering the ODCM and the implementation of the ODCM shall be implemented.
2. Administrative controls have been established to implement controls on the ODCM.
3. These administrative controls are described below.

CONTROLS ON THE ODCM

1. The format, organization, content, and administration of the ODCM are controlled by CH-1-103.
2. Methodologies identified in the ODCM are implemented by various CCNNPI i

organizations in accordance with approved procedures. (See the "RESPONSIBILITIES" section of CH-1 -103 for a list of those Sections of CCNNPI responsible for approving and maintaining procedures which implement the requirements of the ODCM.)

f, "

3. The main vent stack flow-rates shall be verified in accordance with the surveillances described in the following section, "Surveillance Requirements".
4. Licensee initiated changes to the ODCM:

a) Shall be documented and records of reviews performed shall be retained.

This documentation shall contain (1) Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s);

(2) A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and 10 CFR Part 50, Appendix I, and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculations; b) Shall become effective upon review by the onsite review function and approval of the plant manager; and c) Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. 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 indicate the date (i.e., month and year) the change was implemented.

Offsite Dose Calculation Manual Page 221 of 325 Revision 5 SURVEILLANCE REQUIREMENTS

1. Complete audits and PERIODIC REVIEWS of the ODCM in accordance with CH-1-103.
2. Determine main vent stack flow rates for both units as described below.

a) The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (L 25%).

b) The Test and Equipment Unit shall be responsible for performing this test.

c) The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates.

d) IF the main vent stack flow rate for either unit, as determined in accordance with approved Test and Equipment procedure(s), changes +

10% from the values referenced in Attachment 7 of the ODCM, a technical evaluation shall be initiated to determine if the ODCM should be revised.

RESPONSIBLE COMPANY ORGANIZATIONS I. CH-1-1 03 identifies the responsibilities of various personnel and company organizations which administer and implement the ODCM. This section of the ODCM identifies company organizations which are assigned responsibility for implementing the surveillances described above.

2. The Test Equipment Unit is responsible for ensuring the main vent stack flow rate test procedure (e.g., TE-001 or equivalent) is completed in accordance with the surveillances listed above.
3. The Test Equipment Unit is responsible for forwarding main vent stack flow rate test results to the General Supervisor - Chemistry.
4. The RETS Program Manager, CCNPPI CHEMISTRY SECTION, is responsible for evaluating main vent flow rate test results (e.g., TE-001 or equivalent results)

I and for performing the technical evaluation described in the above surveillances.

INITIATING CONDITIONS

1. Main vent stack flow rates shall be determined at least once per 6 months L.

25%), or more often if required by Controls.

2. Complete PERIODIC REVIEWS of the ODCM as specified in CH-i -103.

Offsite Dose Calculation Manual Page 222 of 325 Revision 5 CALCULATION METHODOLOGIES

1. Calculational methodologies used to satisfy the above surveillances should be documented in approved procedures.
2. Documents which serve as a basis for calculation methodologies used in the ODCM should be maintained in an accessible location.

(1) Supporting documents may be incorporated into the ODCM (e.g., as Attachments).

(2) Supporting documents may be maintained in a "procedure history file".

(3) Supporting documents may be identified in the "references" section of the ODCM.

CORRECTIVE ACTIONS

1. IF main vent stack flow rates, as determined in accordance with appropriate Test Equipment procedure(s), change + 10% from the values referenced in Attachment 7 of the ODCM, a technical evaluation shall be initiated to determine if the ODCM should be revised.

BASES

1. [B527], NRC Inspection Report INSR 91-30/30

Offsite Dose Calculation Manual Page 223 of 325 Revision 5 EXECUTIVE

SUMMARY

OF CHANGES REV. CHANGE DESCRIPTION 5 0 Replaced "Treatment" with "Processing". Editorial change to make terminology consistent with UFSAR (pages 2, 10, 31, 38, 141, 142, 149, 195, 322)

Removed "Dominant" and "Less Dominant" from nuclide mix calculation (pages 3, 7, 8, 9, 62, 72, 73, 83, 115, 132, 147, 226, 233). New setpoints will assume 10 CFR 20 MPCs regardless of fractional abundance in mix.

In addition, terminology is added to allow use of a more conservative isotopic mix to be used for setpoint determinations.

Removed references to Technical Specifications in Definitions section.

ODCM is Technical Specification-related document. All requirements of definitions are Technical Specification-related and must be met (pages 6 through 10)

Replaced "trip setpoint" with "fixed setpoint". Clarification of terminology (pages 2, 4, 8, 20, 25, 57 through 60, 63 through 70, 72 through 81, 84 through 86, 112, 113, 115, 116 through 118, 122, 124, 128 through 131, 133 through 135, 137, 140, 143 through 146, 148 through 151, 168, 175, 230). Clarification of terminology. Also added statements for clarification to 3.3.3.9 and 3.3.3.10 (pages 16 and 21)

Reworded specifications for radiation monitor setpoints to more accurately reflect controlling mechanism via alarm function (pages 16 and 21)

Added requirement for tritium sampler to Table 3.3-12 to be consistent with requirements of Table 4.11-2 (page 17)

Deleted statement from footnote (e) of Table 4.11-2 which had stated that the requirement did not apply under certain circumstances. That statement applied only to footnote (c) (page 35)

Editorial corrections (pages 28, 34, 40, 50)

Revised text and attachments to eliminate outfall 002. Plant modification has redirected this liquid effluent via outfall 001. Combined Attachments 2 and 3 (pages 54-56, 226, 228-231)

Added flexibility in minimum circulating pump requirements. If calculations show existing radiation monitor setpoint is conservative, the setpoint need not be changed (pages 61, 71 and 82)

Changed the safety factor for steam generator blowdown radiation monitor

Offsite Dose Calculation Manual Page 224 of 325 Revision 5 REV. CHANGE DESCRIPTION adjustable setpoints from 1.50 to 2.50 (pages 75 and 86). This safety factor is designed to account for random variations in radiation monitor background. Operating experience shows that a factor of 2.50 will avoid random alarms that lead to unnecessary valve manipulations by Operations.

Deleted Battery Room Exhaust. Plant modification eliminated this discharge point (pages 104, 108)

Deleted references to CP-612. This was an implementing procedure, which was cancelled and replaced. (pages 153, 161, 175, 182)

Update Executive Summary of Changes (pages 223,224)

Added Sewage Treatment Plant as a source of liquid radioactive waste in Attachment 2 (page 229)

Added Auxiliary Building Drains as a source of liquid radioactive waste in Attachment 2 (page 229)

Revised footnote regarding steam generator blowdown releases to reflect operating practice (page 230)

Revised Unit 2 Main Vent and Unit 2 Containment Purge flow rate values on Attachment 7 to reflect plant historical data (page 237)

Changed Attachment 7 to indicate that purge releases are continuous (page 237)

Added new footnote for detail in Attachment 8 (page 238)

Updated descriptions of TLD locations around ISFSI to Attachment 20 (page 319)

Offsite Dose Calculation Manual Page 225 of 325 Revision 5 PART 6.0: ATTACHMENTS Part 1.0: purpose and applicability/scope ............................................................................................. 4 Purpose ..................................................................

Applicability/scope ............................................................ 4 Part 2.0: Definitions and references ............................................... 6 DEFINITIONS .............................................................. 6 Refe ren ce s References" 11 Dvelop.ent Reen ..................................................... 11 Performance References .................... .*...................................13 PArt 3.0/4.00: CONTROLS and surveillance requirements ............................................................... 14 Monitoring Instrumentation ...................................................................................................... 16 Radioactive Gaseous Effluent .......................................................... 16 Radioactive Liquid Effluent . ............ 216...............................

RADIOACTIVE EFFLUENTS .......................................................... 2 LIQUID EFFLUENTS: .... .26 26................................

Concentration 26..........................

Dose ....................................................................... 26 Liquid Radwaste Processing System... . ... ...................................... 30 GASEOUS EFFLUENTS:..................................32 Dose Rate ..................................................... 32 Dose - Noble Gases 32...............................

Dose - Iodine-1 31 &Radionuclides inParticulate Form....................... 37 Gaseous Radwaste Processing System .................................................. 38

_ TO TAL DOSE ..................................................................................... ............................................................................... 39 RADIOLOGICAL ENVIRONMENTAL MONITORING:-..40 PROGRAM ..................................................................... 40 LAND USE CENSUS.................................5 INTERLABORATORY COMPARISON PROGRAM ................................................................................................................. 53 Part 5.0 : calculational m ethodologies ...................................................................................................... 54 Radioactive Liquid Effluents..........................................................

Release Pathways [B5271 ................................................................................................................................. 54 Types of Liquid Releases ........................................................................ ............................. 5 Processing Equipment .............................................................. 56 Liquid Effluent Radiation Monitor Alarm and FIXED Setpoints ........................................................................................... 57 Limits On Radlonuclide Concentrations In Liquid Effluents ......................................... 87 Umits On Cumulative Total Body Doses And Cumulative Organ Doses For Liquid Effluents ................................................. 93 Umits For The Liquid Waste Processing System ......................................................................................................... .. 100 Radioactive ReleaseRees Gaseous Effluents Pathways [1327 .............................................................................................................................. 103 ahas [B527]............................................................................................. 103; Types of Gaseous Releases .......................................................... 108 Processing Equipment........... ...................................... 4.......... 108 Gaseous Effluent Radiation Monitors And Setpoints .......................................................... 109 Annual Total Body Dose Rate Due To Noble Gases In Gaseous Effluents ......................................... ........... 151 Annual Skin Dose Rate Due To Noble Gases In Gaseous Effluents...................15 Annual Organ Dose Rates Due To lodines And Particulates In Gaseous Effluents ............................................... 166 Cumulative Gamma Air Doses Due To Noble Gases In Gaseous Effluents..............................173 Cumulative Beta Air Doses Due To Noble Gases In Gaseous Effluents ..................................... . .181 Cum ulative Orga n Do ses Du e To lodines And Part ic ulate s In Gaseo us Effl ue nts. . ........................ ....................I..................1 88 Umits For The Gaseous RADWaste Processing System ............................................................................................... 195 Limits On Total Annual Dose - Gases, Liquids, and Uranium Fuel Cycle Sources ......................... 197 Special Exceptions and Assumptions For Calculation of Doses and Dose Rates .................................................................. 201 Radiological Environmental Monitoring Program .............................................................................................. .. 203 Radiological Environmental Monitoring Program..............................................203 Land Use Census ....................... 208 Interlaboratory Comparison Program ............ ........................................ 209 Annual Radiological Environmental Operating REPORT .................................................................................................... 211 independent Spent Fuel Storage Installation Monitoring Program ......................................................................................... 214 RADIOACTIVE EFFLUENT RELEASE REPORT ..................................................................  :............................... 218 Introduction 218

............................................ 218

Offsite Dose Calculation Manual Revision 5 Page 226 of 325 Report Contents...........................................................218 Report Submittal ................................................................. 219 Administration Of The ODCM ............. 219.................................

Introduction .............................................................. 220 Controls On The ODCM ....................................................... 220 Surveillance Requirements ..................................................... 221 Responsible Company Organizations ............................. ................... 221 Initiating Cnditos........... 221 Calculation Methodologies ................................... *.............222 Corrective actions ............................ ............................. 222 Bases Of.. . . . . . .................................................................................. 222 Executive Summary Of Changes................................................. 223 "Part 6.0 : ATT achments ......... ....... ....... ................ ..... ...................................................... 225 Attachment I Final Grading And Drainage Plan .................................................................................................... 227 Attachment 2 Sources of Liquid Radioactive W aste .............................................................................................. 228 Attachment 2 Sources of Liquid Radioactive Waste.....................................

Attachment 3 ............................................................. 231

............................................... 231 (This page intentionally left blank.)

232 Attachment 4 Block Diagram of Liquid Radioactive Waste Systems .............................................................

Attachment 5 RADIONUCLIDEs in Typical Radwaste Discharges .................................................................... 233 Attachment 6 Liquid Effluent Dose Factors ........................................... 234 Liquid Effluent Dose Factors ............................................................................................... 236 Attachment 7 General Information Related to Gaseous Releases via the Main Vents .......................................... 237 Attachment 8 General Information Related to Gaseous Releases via Pathways other than the Main Vents ........ 238 Attachment 9 Block Diagram of Gaseous Radioactive Waste Systems ......................................239 Attachment 10 Noble Gas Do69 Factors ........................................... ..240 Attachment 11 Empirical Derivation Of Site-Specific Dose Factors ......................... ... 241 Attachment 12 Gaseous Effluent Pathway Dose Factors ................................................ .......... 246 Attachment 13 Environmental Monitoring Sites for REMP ............................................. ............ 312 Attachment Attachment 14 Radiological

'15 Radiological Environmental Monitoring Program Surveillances Environmental Monitoring Program Surveillances for Direct Radiation ............. 313 Attachment 16 Radiological Environmental Monitoring Program Surveillances for Airborne Activity .............. 314 Attachment 17 Radiological Environmental Monitoring Program Surveillances for Waterborne Activity ............... 315 Attachment 18 Map of Environmental Monitoring Sites for REMP (5 Km for Ingestible Activity ............ 316 Attachment 19 Map of Environmental Monitoring Sites for REMP (10 MileRadius).................... 317 Radius)........................................ 318 Attachment 20 Environmental Monitoring Sites for ISFSI ................................................................................. 319 Attachment 21 Map of Environmental Monitoring Sites for ISFSI.............................................320 Attachment 22 Map of Environmental Monitoring Sites for ISFSI (ENLARGED) .............................................. 321 Attachment 23 Effluent Radiation Monitors ........................................... 322 Attachment 24 List of Effective Pages .............................................. 3232

Offsite Dose Calcuration Manual Page 227 of 325 Revision 5 Attachment 1 Final Grading And Drainage Plan A reference diagram which depicts the grading for and the drainage from the Calvert Cliffs Nuclear Power Plant can be found in the following reference:

Final Grading And Drainage Plan Calvert Cliffs Nuclear Power Plant Units I and 2, BGE Document ID Number: 61517SHOOOI BGE Document ID Number: 61514SH0002 The above referenced grading and drainage plan is intended for reference only. This drawing may not reflect the changes and modifications since March 1975.

Offsite Dose Calculation Manual Revision 5 Page 228 of 325 Attachment 2 Sources of Liquid Radioactive Waste Waste Stream Radiation Type of Max. Discharge Maximum Volume Notes Monitor Release Flow Rate gal/min liters/rmin gal liters Rx. Coolant Wst. Mon. Tk. 0-RE-2201 Batch 120 454 9000013 3.407E513 Rx. Coolant Wst. Rec. Tk. 0-RE-2201 Batch 120 454 9000013 3.407E5 13 Misc. Wst. Mon. Tk. O-RE-2201 Batch 120 454 400013 1514013 Misc. Wst. Rec. Tk. 0-RE-2201 Batch 120 454 400013 1514013 Aux. Boiler Steam Drum All releases are via Auxiliary Browdown Tank Aux. Blowdown Tk. Unmonitored Continuous 20012 757 N/A N/A Waste Neut. Tk. 11 Unmonitored Batch 10001 37901 45988 1.74E5 Waste Neut. Tk. 12 Unmonitored Batch 10001 37901 47749 1.80E5 Stm. Gen. Blowdown Tk. 1/2-RE-401414 Continuous/ 2252 8522 23503 88953 Batch 11 Component Cooling Water4 Unmonitored Continuous variable 5 variable 5 440906 1.669E5 Condenser Hotwells Unmonitored Batch 10 45007 170007 1.05E5 3.97E5 Salt Water System Unmonitored Continuous 15500 58670 N/A N/A Condensate Storage Tank Unmonitored Batch Variable 8 Variable 8 3.5E5 9 1.3126 9 Demin. Water Storage Tank Unmonitored Batch Variable 8 Variable 8 3.5E5 9 1.3E6 9 Precoat Sump Unmonitored Continuous 50 94R6 in.n.3 'aonnA3

Offsite Dose Calculation Manual Page 229 of 325 Revision 5 Attachment 2 Sources of Liquid Radioactive Waste Waste Stream Radiation Type of Max. Discharge Maximum Volume Notes Monitor Release Flow Rate Gal/min liters/min gal liters Aux. Building Roof Drains 1 9 Unmonitored Continuous Variable Variable N/A N/A Sewage Treatment Plant Unmonitored Continuous 185 700 N/A N/A Turbine Bldg. Sump No. 11 Unmonitored Continuous 470 889 1950 7381 Turbine Bldg. Sump No. 12 Unmonitored Continuous 470 889 2415 9141 Turbine Bldg. Sump No. 21 Unmonitored Continuous 4170 889 2490 9425 Turbine Bldg. Sump No. 22 Unmonitored Continuous 470 889 2182 8259 Diesel Oil Interceptor Sump Unmonitored Continuous 100 378.5 5790 21920 Yard Oil Interceptor Unmonitored Continuous variable 15 variable1 5 N/A N/A Refueling Water Tank Unmonitored Batch/Cont. 17 varlable' 5 variable 15 4.2E5 1.6E6 Condensate Storage Tank Unmonitored Batch/Cont. 17 variable 15 variable' 5 3.5E5 16 1.3E616 Service Water System 1/2-RE-1595 Continuous variable 15 variable 15 31418 1.189E5 Plant Heating System 18 Unmonitored Continuous variable 15 variablels N/A N/A

Offsite Dose Calculation Manual Revision 5 Page 230 of 325 Attachment 2 Sources of Liquid Radioactive Waste

1. This flow rate is only an approximation. The motive force is gravity
2. This is the maximum flow rate. The actual flow rate will be considerably
3. This is the maximum volume of the tank for a BATCH RELEASE. Ifthe less.

release is a CONTINUOUS RELEASE, the volume discharged would be calculated from the discharge flow rate and duration of the release.

4. There is no direct path by which radioactive liquid from the CCW System could enter outfall 001. Liquid from the CCW System may leak into either the Salt Water System (which drains to outfall 001) or the Liquid
5. Radioactive liquid is not normally released from the CCW system. Flow Waste Processing System (via Aux. Bldg. Drains).

rate to outfall 001 may occur via Salt Water System. For this pathway, the flow rate will vary (e.g., depending on size of leak). See Safety Analysis No. 2, FCR 82-1053, Supplement 1.

6. System volume is 5894 cubic feet. Conversion constant is 0.13368 cubic
7. The flow rate shown here is the flow rate for one condensate pump. Verify feet per gallon.

the number on condensate pumps in service, and modify this flow rate accordingly.

8. Flow rate should be calculated on a case-by-case basis.
9. Volume obtained from "Plant Data Book", BGE CCNPP Units I and 2, Bechtel Power Corporation, Volume 1, Job
10. May be a CONTINUOUS RELEASE if contaminated sealing steam is operated 6750.
11. Although steam generator releases may be either CONTINUOUS RELEASEs during the release.

or BATCH RELEASEs. Verify type of release to be conducted prior to discharge.

12. This is the maximum rated discharge for two pumps in operation.
13. The volume specified is the design basis volume from Table 11-1 of the
14. The steam generator blowdown effluent radiation monitor, 1/2-RE-4095, UFSAR.

may be equivalent to the 1/2-RE-4014 (see part 5, Liquid Effluent Radiation Monitor Alarm and Fixed Setpoints,para. 2)

15. Maximum discharge flow rate shall be determined on a case-by-case
16. Volume obtained from "Plant Data Book", BGE CCNPP Units 1 and 2,basis.
17. Bechtel Power Corporation, Volume 1, Job 6750.

Releases via this pathway would be considered a BATCH RELEASE if a catastrophic tank failure occurred. In the event of a small leak, the release may be considered a CONTINUOUS RELEASE. The release

18. mode should be determined on a case-by-case basis.

The plant heating system is a closed system and is not normally released to released to the environment via the turbine building sumps. In some cases, the environment. In the event of a leak, the effluent may be depending on the location of the leak, the effluent would be collected in the auxiliary building sump and subsequently released through the liquid radioactive waste processing system. The effluent pathway should be determined on a case-by-case basis.

19. Plant drawings Indicate that these drains discharge to outfalls 003 and 004.

Offsite Dose Calculation Manual Page 231 of 325 Revision 5 Attachment 3 (This page intentionally left blank.)

c14

Offsite Dose Calculation Manual Revision 5 Page 232 of 325 Attachment 4 Block Diagram of Liquid Radioactive Waste Systems Reactor Coolant Waste MIscellaneous Waste

Offsite Dose Calculation Manual Page 233 of 325 Revision 5 Attachment 5 RADIONUCLIDEs in Typical Radwaste Discharges The term fi - a fraction which represents the relative activity contribution of nuclide i to the average total effluent activity - is used in several equations in the ODCM (e.g., equations 2G, 5G, 3L, and 4L). This attachment provides guidance for calculating the values of fi.

1. Select the calendar quarters which contain at least one "typical" liquid (or gas) release (see definition of TYPICAL RADWASTE RELEASE).
2. For each of the calendar quarters selected above, obtain a listing of the nuclides, nuclide activities, and
a. release (end) dates.

This data may be obtained from the Radioactive Effluent Release Report(s) for the time periods of interest, or

b. This data may be obtained from a computer-based effluent management system (if available).
c. The values of nuclide activities and release end times may be close approximations of the true values.
3. Sum the quarterly activities (curies) for each individual radionuclide.

I E°q. I RZ-1

  • E . IR
4. Sum the quarterly activities for all radionuclides, i.

AT = A A* Eq. 2R

5. Calculate the fraction of the total activity attributable to each radionuclide (i.e.,

the relative activity of nuclide i).

f, = Ar lAT Eq. 3R

Offsite Dose Calculation Manual Page 234 of 325 Revision 5 Attachment 6 Liquid Effluent Dose Factors (mrem/hr per uCi/ml)

Nuclide Bone Liver "Tbody Thyroid Kidney Lung Gitract H-3 0.OOOE+00 2.820E-01 2.820E-01 2.820E-01 2.820E-01 2.820E-01 2.820E-01 BE-7 2.700E+01 1.100E+01 6.500E+01 1.300E+00 1.600E+01 3.100E+00 2.700E+02 C-14 1.450E+04 2.900E+03 2.900E+03 2.900E+03 2.900E+03 2.900E+03 2.900E+03 NA-24 4.570E-01 4.570E-01 4.570E-01 4.570E-01 4.570E-01 4.570E-01 4.570E-01 P-32 4.690E+06 2.910E+05 1.810E+05 0.000E+00 0.000E00 0.000E+00 5.270E+05 CR-51 0.000E+00 0.000E+00 5.580E+00 3.340E+00 1.230E+00 7.400E+00 1.400E+03 MN-54 0.OOOE+00 7.060E+03 1.35E+03 o.0o0E+00 2.100E+03 o.0ooE+00 2.160E+04 MN-56 0.000E+00 1.780E+02 3.150E+01 0.000E+00 2.260E+02 0.000E+00 5.670E+03 FE-55 5.110E+04 3.530E+04 8.230E+03 0.000E+00 0.000E+00 1.970E+04 2.030E+04 FE-59 8.060E+04 1.900E+05 7.270E+04 0.000E+00 0.000E+00 5.300E+04 6.320E+05 CO-57 0.000E+00 1.420E+02 2.360E+02 0.000E+00 0.000E+00 0.000E+00 3.590E+03 CO-58 0.000E+00 6.030E+02 1.350E+03 O.O00E+00 0.000E+00 0.000E+00 1.220E+04 CO-60 0.000E+00 1.730E+03 3.820E+03 0.000E+00 0.000E+00 0.000E+00 3.250E+04 NI-63 4.960E+04 3.440E+03 1.670E+03 0.000E+00 0.000E+00 0.000E+00 7.180E+02 NI-65 2.020E+02 2.620E+01 1.200E+01 0.000E+00 0.000E+00 o.oooE+00 6.650E+02 CU-64 0.OOOE+00 2.140E+02 1.010E+02 0.000E+00 5.400E+02 0.000E+00 1.830E+04 ZN-65 1.610E+05 5.130E+05 2.320E+05 0.000E+00 3.430E+05 0.000E+00 3.230E+05 ZN-69 3.430E+02 6.560E+02 4.560E+01 0.000E+00 4.260E+02 0.000E+00 9.850E+01 BR-82 0.000E+00 0.000E+00 4.070E+00 0.000E+00 0.000E+00 0.000E+00 4.670E+00 BR-83 0.000E+00 0.000E+00 7.250E-02 0.000E+00 0.000E÷00 0.000E+00 1.040E-01 BR-84 0.000E+00 0.000E+00 9.390E-02 0.000E+00 0.000E+00 0.000E+00 7.370E-07 BR-85 0.OOOE+00 0.OOOE+00 3.860E-03 O.O00E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 6.240E+02 2.910E+02 0.000E+00 0.000E+00 0.000E+00 1.230E+02 RB-88 0.000E+00 "1.790E+00 9.490E-01 0.000E+00 0.000E+00 0.000E+00 O.O00E+00 RB-89 0.000E+00 1.190E+00 8.340E-01 0.000E+00 0.000E+00 0.000E+00 O.000E+00 SR-89 4.990E+03 0.000E+00 1.430E+02 0.000E+00 0.000E+00 0.000E+00 8.000E+02 SR-90 1.230E+05 0.000E+00 3.010E+04 0.000E+00 0.000E+00 0.000E+00 3.550E+03 SR-91 9.1 80E+01 0.000E+00 3.710E+00 0.000E+00 0.000E+00 0.000E+00 4.370E+02 SR-92 3.480E+01 0.000E+00 1.510E+00 0.000E+00 0.000E+00 0.000E+00 6.900E+02 Y-90 6.060E+00 0.000E+00 1.630E-01 0.000E+00 0.000E+00 0.000E+00 6.420E+04 Y-91M 5.730E-02 0.000E+00 2.220E.03 0.000E+00 O.O00E+00 0.000E+00 1.680E-01 Y-91 8.880E+01 0.000E+00 2.370E+00 0.000E+00 O.O00E+00 0.000E+00 4.890E+04 Y-92 5.320E-01 0.000E+00 1.560E-02 0.000+E00 0.000E+00 0.000E+00 9.320E+03 Y-93 1.690E+00 0.000E+00 4.660E-02 0.000E+00 0.000E+00 0.000E+00 5.350E+04 ZR-95 1.590E+01 5.110E+00 3.460E+00 0.000E+00 8.020E+00 0.000E+00 1.620E+04 ZR-97 8.810E-01 1.780E-01 8.130E-02 0.000E+00 2.680E-01 0.000E+00 5.51 0E+04 NB-95 4.470E+02 2.490E+02 1.340E+02 0.000E+00 2.460E+02 0.000E+00 1.510E+06 NB-97 3.750E+00 9.490E-01 3.460E-01 0.000E+00 1.110E+00 0.000E+00 3.500E+03

Offsite Dose Calculation Manual Revision 5 Page 235 of 325 Attachment 6 Liquid Effluent Dose Factors (mrem/hr per uCVmI)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract MO-99 0.000E+00 1.280E+02 2.430E+01 0.OOOE+00 2.890E+02 0.000E+00 2.960E+02 TC-99M 1.300E-02 3.660E-02 4.660E-01 0.OOOE+00 5.560E-01 1.790E-02 2.170E+01 TC-101 1.330E-02 1.920E-02 1.880E-01 0.000E+00 3.460E-01 9.810E-03 0.OOOE+00 RU-103 1.070E+02 0.000E+00 4.600E+01 0.000E+00 4.070E+02 0.000E+00 1.250E+04 RU-105 8.890E+00 O.OOOE+00 3.510E+00 0.000E+00 1.150E+02 0.000E+00 5.440E+03 RU-106 1.590E+03 0.000E+00 2.010E+02 0.000E+00 3.060E+03 0.0002+00 1.030E+05 RH-103M 0..:000+00 0.000E+00 0.0060+00 0.0002+00 0..000+00 0.00oE2+0 O.o0E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.0002+00 CD-109 2.IOOE+05 4.000E+06 1.600E+06 1.500E+05 2.200E+07 1.8002+05 2.500E+06 AG-I1OM 1.560E+03 1.450E+03 8.600E+02 0.000E+00 2.850E+03 0.000E+00 5.910E+05 SN-113 6.700E+03 1.200E+03 2.100E+04 6.200E+02 1.600E+03 7.300E+02 2.2002+05 SB-122 5.300E+01 5.520E+01 6.690E+02 8.780E+00 2.610E+01 1.140E+01 6.580E+03 SB-124 2.770E+02 5.230E+00 1.100E+02 6.710E-01 0.000E+00 2.150E+02 7.860E+03 SB-125 1.770E+02 1.980E+00 4.210E+01 1.800E-01 0.000E+00 1.360E+02 1.950E+03 TE-125M 2.170E+02 7.860E+01 2.910E+01 6.520E+01 8.820E+02 0.000E+00 8.660E+02 TE-127M 5.480E+02 1.960E+02 6.680E+01 1.400E+02 2.230E+03 0.000E+00 1.840E+03 TE-127 8.900E+00 3.200E+00 1.930E+00 6.600E+00 3.630E+01 0.000E+00 7.030E+02 TE-129M 9.310E+02 3.470E+02 1.470E+02 3.200E+02 3.890E+03 0.000E+00 4.690E+03 TE-129 2.540E+00 9.550E-01 6.190E-01 1.950E+00 1.070E+01 0.000E+00 1.920E+00 TE-131M 1AOOE+02 6.850E+01 5.710E+01 1.080E+02 6.940E+02 0.000E+00 6.800E+03 TE-131 1.590E+00 6.660E-01 5.030E-01 1.310E+00 6.990E+00 0.000E+00 2.260E-01 TE-132 2.040E+02 1.320E+02 1.240E+02 1.460E+02 1.270E+03 0.000E+00 6.240E+03 1-130 3.960E+01 1.170E+02 4.610E+01 9.910E+03 1.820E+02 0.000E+00 1.010E+02 1-131 2.180E+02 3.120E+02 1.790E+02 1.020E+05 5.350E+02 0.000E+00 8.230E+01 1-132 1.060E+01 2.850E+01 9.960E+00 9.960E+02 4.540E+01 0.000E+00 5.350E+00 1-133 7.450E+01 1.300E+02 3.950E+01 1.900E+04 2.260E+02 0.OOOE+00 1.160E+02 1-134 5.560E+00 1.510E+01 5.400E+00 2.620E+02 2.400E+01 0.000E+00 1.320E-02 1-135 2.320E+01 6.080E+01 2-240E+01 4.010E+03 9.750E+01 0,000E+00 6.870E+01 CS-134 6.840E+03 1.630E+04 1.330E+04 0.000E+00 5.270E+03 1.750E+03 2.850E+02 C0-136 7.160E+02 2.830E+03 2.040E+03 0.000E+00 1.570E+03 2.160E+02 3.210E+02 CS-137 8.770E+03 1.200E+04 7.850E+03 0.000E+00 4.070E+03 1.350E+03 2.320E+02 GS-138 6.070E+00 1.200E+01 5.940E+00 0.000E+00 8.810E+00 8.700E-01 5.120E-05 BA-139 7.850E+00 5.590E-03 2.300E-01 0.000E+00 5.230E-03 3.170E-03 1.390E+01 BA-140 1.640E+03 2.060E+00 1.080E+02 0.000E+00 7.020E-01 1.180E+00 3.380E+03 BA-141 3.810E+00 2.880E-03 1.290E-01 0.000E+00 2.680E-03 1.630E-03 1.800E-09

Offsite Dose Calculation Manual Revision 5 Page 236 of 325 Attachment 6 Liquid Effluent Dose Factors (mrem/hr per uCi/ml)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract BA-142 1.720E+00 1.770E-03 1.080E-01 0.000E+00 1.500E-03 1.000E-03 0.000E+00 LA-140 1.570E+00 7.940E-01 2.100E-01 0.000E+00 0.000E+00 0.000E+00 5.830E+04 CE-139 1.000E+02 4.800E+01 3.700E+02 6.200E-01 3.400E+01 4.800E+00 3.200E+03 LA-142 8.060E-02 3.670E-02 9.130E-03 0.0004E00 0.000E+00 0.000E+00 2.680E+02 CE-141 3.430E+00 2.320E+00 2.630E-01 0.000E+00 1.080E+00 O.000E+00 8.860E+03 CE-143 .6.040E-01 4.460E+02 4.940E-02 O.000+00 1.970E-01 0.000E+60 1.670E+04 CE-144 1.790E+02 7.470E+01 9.590E+00 0.000E+00 4.430E+01 0.000E+00 6.040E+04 PR-143 5.790E+00 2.320E+00 2.870E-01 0.0002+00 1.340E+00 0.0002+00 2.540E+04 PR-144 1.900E-02 7.870E-03 9.640E-04 O.O00E+00 4.440E-03 O.OOOE+00 2.730E-09 NDI-147 3.960E+00 4.580E+00 2.740E-01 0.000E+00 2.680E+00 0.000E+00 2.200E+04 EU-154 3.870E,02 4.760E+01 3.390E+01 0.000E+00 2.280E+02 0.000E+00 3.450E+04 EU-155 5.420E+01 7.68E+00 4.960E+00 0.000E+00 3.550E+01 0.000E+00 6.050E+03 W-187 9.160E+00 7.660E+00 2.680E+00 0.000E+00 0.0002+00 0.000E+00 2.510E+03 NP-239 3.530E-02 3.470E-03 1.910E-03 0.000E+00 1.080E-02 0.000E+00 7.110E+02 HG-203 1.400E+05 0.000E+00 1.600E+05 0.0002+00 - 1.600E+06 1.000E+05 3.200E+05

Offsite Dose Calculation Manual Page 237 of 325 Revision 5 Attachment 7 General Information Related to Gaseous Releases via the Main Vents Waste Stream Radiation Type of Nominal Discharge Maximum Discharge Note Monitor release Flow Rate Flow Rate m' / sec SCFM m7/sec SCFM Waste Gas System (WGDT) 0-RE-2191' Batch N/A N/A 2.36E-2 50 Cntmt. Vent (via H2 Purge) 1/2-RE-5415 2 Batch 3 2.36E-2 50 2.93E-1 620 Unit I Cntmt. Purge (100%) I -RE-54154 Continuous' N/A N/A 22.46 47,3878 Unit 2 Cntmt. Purge (100%) 2-RE-5415 7 Continuous N/A N/A 20.98 44,3208 Unit 1 Main Vent Release 4 Continuous 56.39 1 19339 62.010 13127310 1-RE-5415 Unit 2 Main Vent Release 2-RE-541 5 7 Continuous 45.7 9 96745 9 50.2°10 106420 10 11 Since the WGDT Is released to the plant vent stack, 112-RE-5415 and 1/2-RE-5416 may also be used to monitor releases from a WGDT.

2 The WRGM, 1/2-RE-5416, may also monitor these releases.

3 A containment vent is considered a 'batch" release (even though inleakage of radioactive gases into the containment atmosphere 4 may occur during the time the vent is in progress).

The WRGM, 1-RE-5416, may also monitor these releases.

6 A purge is considered to be a CONTINUOUS RELEASE due to potential introduction of radioactive gases to the containment 6

atmosphere during containment maintenance activities. I This is the purge flow rate as determined by approved test procedure (i.e., TE-006) inApril 1998.

7 C"i The WRGM, 2-RE-5416, may also monitor these releases.

a This Is the purge flow rate as determined by approved test procedure (i.e.. TE-006) In March 2001.

9 This is the mean main vent stack flow rate as determined by approved test procedure (i.e., TE-001 from 8/1990-3/1996 for Unit 1 and TE-001 from 8/1990-3/2000 for Unit 2).

10 This is the maximum vent stack flow rate which is equal to 110% of the Nominal Discharge Flow rate.

Offsite Dose Calculation Manual Page 238 of 325 Revision 5 Attachment 8 General Information Related to Gaseous Releases via Pathways other than the Main Vents Waste Streams Radiation Monitor Type of Release Nominal Discharge Notes Flow Rate Flow Rate Aux. Boiler Deaerator Unmonitored See Footnote1 See Footnotez Stm. Gen. Atm. Stm. Dumps 2 Unmonitored See Footnote 1 See Footnote Plant Nitrogen System Unmonitored See Footnote 1 2 See Footnote Turbine Bldg. Vent. Exh 3 1 2 Emergency Air Lock Unmonitored Unmonitored See Footnote See Footnote 1 See Footnote See Footnote 2

I Plant Compressed Air Unmonitored See Footnote 1 2 See Footnote Main Steam Line Penetrations Unmonitored See Footnote 1 2 See Footnote Steam Driven Auxiliary Feed Pumps Unmonitored See Footnote1 2 See Footnote Containment Equipment Hatch Unmonitored 1 2 See Footnote See Footnote Since radioactive gaseous waste is not normally vented via this pathway, the determination of release type (i.e., continuous or batch) will be evaluated on a case-by-case basis. 3-J 2 Since radioactive gaseous waste is not normally vented via this pathway, the determination of discharge flow rate will be evaluated on a 3 case-by-case basis.

Includes sources such as Gland Seal Exhaust.

Offsite Dose Calculation Manual Page 239 of 325 Revision 5 Attachment 9 Block Diagram of Gaseous Radioactive Waste Systems

Offsite Dose Calculation Manual Revision 5 Page 240 of 325 Attachment 10 Noble Gas Dose Factors Nuclide GAMMA BODY DOSE BETA SKIN DOSE GAMMA AIR DOSE BETA AIR DOSE K1 L, M1 Nj (mrem/yr)/(pCVm3) (mrem/yry(pCi/m3) (mradlyr)I(pCim3) (mrad/yr)/(pCifm3)

Ar-41 8.84E1+03 2.69E+03 Kr-85 9.30E+03 3.28E+03 1.61 E+01 1.34E+03 Kr-85m 1.72E+01 1.95E+03 1.17E+03 1.46E+03 Kr-87 1.23E+03 1.97E+03 5.92E+03 9.73E+03 6.17E+03 Kr-88 1.47E+04 1.03E+04 2.37E+03 1.52E+04 2.93E+03 Xe-131m 9.15E+01 4.76E+02 Xe-133 1.56E+02 1.11E+03

. 2.94E+02 3.06E+02 1.3'53E+02 Xe-133m 2.51 E+02 .1.05E03 9.94E+02 3.27E+02 1.48E+03 Xe-135 1.81 E+03 1.86E+03 Xe-135m 1.92E+03 2.46E+03 3.12E+03 7.11E+02 Xe-1 38 3.36E+03 7.39E+02 8.83E+03 4.13E+03 9.21 E+03 4.75E+03

Offsite Dose Calculation Manual Page 241 of 325 Revision 5 Attachment 11 Empirical Derivation Of Site-Specific Dose Factors The total body dose, the skin dose, and the air doses--resulting from gamma and beta emitting radionuclides in discharges of gaseous radwaste--are normally calculated using nuclide specific factors. However, these same doses may be estimated using empirically derived, site specific, dose dose factors as shown below.

TOTAL-BODY, GAMMA-DOSE FACTOR A site-specific, total-body, gamma-dose factor has been derived from historical data in accordance with the following equation.

Kav9 = (K)(f,) Eq.IF K,-g = the empirically derived, site-specific, total-body, gamma-dose factor due to all noble gases released during a specified time period Values of Kavg have been calculated using gaseous radwaste discharge data collected over several years.

The results of the calculations appear in the Table on page 5 of this attachment.

K[ - = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrem/yr per microcude/cubic meter)

The total-body dose factors for gamma rays from noble gas radionuclides were obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

The total-body dose factors for various noble gas radionuclides are tabulated in Attachment 10.

ft = a fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value has been calculated for all gaseous radwaste discharges for the years 1986, 1987, and 1988 in accordance with equation 3R on Attachment 5.

Offsite Dose Calculation Manual Page 242 of 325 Revision 5 Attachment 11 Empirical Derivation of Site-Specific Dose Factors SKIN, BETA-DOSE FACTOR A site-specific, skin, beta-dose factor has been derived from historical data in accordance with the following equation.

Lavi = (L,) (f,) Eq. 2F L=* the empirically derived, site-specific, skin, beta-dose factor due to all noble gases released during a specified time period Values of Lavg have been calculated using gaseous radwaste discharge data collected over several years.

The results of the calculations appear in the Table on page 5 of this attachment.

L1 = the skin dose factor due to beta emissions for each identified noble gas radionuclide, i (mrem/yr per microcurie/cubic meter)

The beta skin dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-I.

The beta skin dose factors for various noble gas radionuclides are tabulated in Attachment 10.

= a fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value has been calculated for all gaseous radwaste discharges for the years 1986, 1987, and 1988 in accordance with equation 3R on Attachment 5.

Offsite Dose Calculation Manual Page 243 of 325 Revision 5 Attachment 11 Empirical Derivation of Site-Specific Dose Factors GAMMA-AIR-DOSE FACTOR A site-specific, gamma-air-dose factor has been derived from historical data in accordance with the following equation.

Mawg = (Mi) (f) Eq.3F M =m the empirically derived, site-specific, gamma-air-dose factor due to all noble gases released during a specified time period Values of Mavg have been calculated using gaseous radwaste discharge data collected over several years.

The results of the calculations appear in the Table on page 5 of this attachment.

Mi =the air dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

The gamma air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-i.

The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10.

= a fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value has been calculated for all gaseous radwaste discharges for the years 1986, 1987, and 1988 in accordance with equation 3R on Attachment 5.

Offsite Dose Calculation Manual Page 244 of 325 Revision 5 Attachment 11 Empirical Derivation of Site-Specific Dose Factors BETA-AIR-DOSE FACTOR A site-specific, beta-air-dose factor has been derived from historical data in accordance with the following equation.

Ne9 = (NI) (fl) Eq.4F Nan = the empirically derived, site-specific, beta-air-dose factor due to all noble gases released during a specified time period Values of Navg have been calculated using gaseous radwaste discharge data collected over several years.

The results of the calculations appear in the Table on page 5 of this attachment.

N. = the air dose factor due to beta emissions for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

The beta air dose factors have been obtained from Regulatory Guide 1.109, Appendix B,_Table B-1.

The beta air dose factors for various noble gas radionuclides are tabulated in Attachment 10 (Attachment 1 of old ODCM).

f = a fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value has been calculated for all gaseous radwaste discharges 1986, 1987, and 1988 in accordance with equation 3R on for the years Attachment 5.

Offsite Dose Calculation Manual Page 245 of 325 Revision 5 Attachment 11 Empirical Derivation of Site-Specific Dose Factors SITE-SPECIFIC, AVERAGE DOSE FACTORS Year Kavg Lavg Mavg Navg 1986 330 790 390 1100 1987 340 810 400 1100 1988 390 960 450 1200 Average 350 850 410 1100 Maximum % difference 11% 13% 10% 9%

As can be seen from the above table, the percent difference between the yearly dose factors and the 3 year average dose factors range from 9% to 13%. This variability is minor considering other areas of uncertainty inherent in the environmental dose calculation models.

It should be noted that the empirically-derived, site-specific, average dose factors listed in the above table shall only rarely be used. In those rare instances where empirically-derived, site-specific, average dose factors are used, the results shall be carefully evaluated by qualified members of the facility staff to ensure the estimated doses are only a small fraction of the Control limits. Additionally, the doses shall be recalculated using the RIGOROUS METHODS prior to submitting the Radioactive Effluent Release Report.

Offsite Dose Calculation Manual Page 246 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS ADULT (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract H-3 0.000E+00 3.250E+02 3.2502+02 3.250E+02 3.250E+02 3.250E+02 3.250E+02 C-I 4 3.330E+05 6.660E+04 6.660E+04 6.660E+04 6.660E+04 6.660E+04 6.660E+04 NA-24 1.840E-03 1.840E-03 1.840E-03 1.840E-03 1.840E-03 1.840E-03 1.840E-03 P-32 4.650E÷09 2.890E+08 1.800E+08 0.000E+00 0.000E+00 0.000E+00 5.230E+08 CR-51 0.000E+00 0.000E+00 7.070E+03 4.220E+03 1.560E+03 9.380E+03 1.780E+06 MN-54 0.000E+00 9.150E+06 1.750E+06 0.000E+00 2.720E+06 0.000E+00 2.800E+07 MN-56 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-55 2.930E+08 2.020E+08 4.720E+07 0.00DE+00 0.000E+00 1.130E+08 1.160E+08 FE-59 2.670E+08 6.270E+08 2.400E+08 0.000E+00 0.000E+00 1.750E+08 2.090E+09 CO-57 0.000E+00 5.640E+06 9.370E+06 0.000E+00 0.000E+00 0.000E+00 1.430E+08 CO-58 0.000E+00 1.830E+07 4.100E+07 0.000E+00 0.000E+00 0.000E+00 3.700E+08 CO-60 0.000E+00 7.520E+07 1.660E+08 0.000E+00 0.000E+00 0.000E+00 1.410E+09 NI-63 1.890E+10 1.310E+09 6.330E+08 0.000E+00 0.000E+00 0.OOOE+00 2.730E+08 NI-65 0.000E+00 0.000E+0D 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CU-64 0.000E+00 2.950E-07 1.390E-07 0.000E+00 7.450E-07 0.000E+00 2.520E-05 ZN-65 3.560E+08 1.130E+09 5.120E+08 0.000E+00 7.570E+08 0.000E+00 7.130E÷08 ZN-69 0.000E+00 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 RB-85 0.000E+00 4.870E+08 2.270E+08 0.000E+00 0.000E+00 0.000E+00 9.600E+07 RB-88 0.000E+00 0.000E+00 0.002E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 3.010E+08 0.000E+00 8.650E+06 0.000E+00 0.OOOE+00 0.000E+00 4.840E+07 SR-90 1.240E+10 0.000E+00 3.050E+09 0.000E+00 0.000E+00 0.000E+00 3.590E+08 SR-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.380E-09 SR-92 O.O00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-90 1.070E+02 0.000E+00 2.860E+00 0.000E+00 0.000E+00 0.000E+00 1.130E+06 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.130E+06 0.000+E00 3.030E+04 0.000E+00 0.000E+00 0.000E+00 6.240E+08 Y-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-93 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.080E-07

Offsite Dose Calculation Manual Page 247 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS ADULT (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gltract ZR-95 1.880E+06 6.040E+05 4.090E+05 0.000E00 9.480E+05 0.000E+00 1.91 OE+09 ZR-97 1.830E-05 3.690E-06 1.690E-06 0.000E+00 5.580E-06 0.OOOE+00 1.140E+00 NB-95 2.290E+06 1.280E+06 6.860E+05 0.000E+00 1.260E+06 0.OOOE+00 7.750E+09 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.o000E+00 1.090E+05 2.070E+04 0.000E+00 2.460E+05 0.000E+00 2.520E+05 TC-99M 0.000E+00 0.000E+00 0.000E+00 0.OOOE+0O O.OOOE+00 0.000E+00 0.000E+00 TC-101 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.060E+08 0.000E+00 4.550E+07 0.000E+00 4.030E+08 0.000E+00 1.230E+10 RU-1 05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-106 2.800E÷09 0.000E+00 3.540E+08 0.000E+00 5.400E+09 0.000E+00 1.810E+11 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 AG-1 10M 6.690E+06 6.190E+06 3.670E+06 0.000E+00 1.220E+07 0.000E+00 2.520E+09 SB-122 5.580E+03 5.820E+03 7.050E+04 9.250E+02 2.750E+03 1.200E+03 6.930E+05 SB-124 1.980E+09 3.740E+07 7.850E+08 4.800E+06 0.000E+00 1.540E+09 5.620E+10 SB-125 1.910E+09 2.130E+07 4.540E+08 1.940E+06 0.000E+00 1.470E+09 2.100E+10 TE-125M 3.590E+08 1.300E+08 4.810E+07 1.080E+08 1.460E+09 0.000E+00 1.430E+09 TE-127M 1.120E+09 3.990E+08 1.360E+08 2.850E+08 4.530E+09 O.O00E+00 3.740E+09 TE-127 0.000E+00 O.O00+00 0.000E.00 0.000E+00 1.090E-09 0.000E+00 2.100E-08 TE-129M 1.140E+09 4.270E+08 1.81 0E+08 3.930E+08 4.770E+09 O.O00E+00 5.760E+09 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 4.510E+02 2.210E+02 1.840E+02 3.500E+02 2.240E+03 O.O00E+00 2.190E+04 TE-131 0.000E+00 O.000+00 0O.000+00 0O.000+00 0.000E+00 O.000+00 0O.000+00 TE-132 1.400E+06 9.070E+05 8.510E+05 1.000E+06 8.730E+06 O.O00E+00 4.290E+07 1-130 2.350E-06 6.940E-06 2.740E-06 5.880E-04 1.080E-05 O.O00E+00 5.980E-06 1-131 1.080E+07 1.540E+07 8.830E+06 5.050E+09 2.640E+07 O.O00E+00 4.070E+06 1-132 0.000E+00 O0O.00+00 0O.000+00 0.000E+00 0.000E+00 O.O00+00 0O.000+00 1-133 4.300E-01 7.470E-01 2.280E-01 1.100E+02 1.300E+00 0.000E+00 6.720E-01 1-134 0.000E+00 0.000E+00 O.O00+00 0O.000+00 0O.000+00 0.000E+00 O.O00E+00 1-135 0.000E+00 O.000+00 0.0002+00 O.000+00 0O.000+00 0.000E+00 0.000E+00 CS-134 6.570E+08 1.560E+09 1.280E+09 O.O00E+00 5.060E+08 1.680E+08 2.740E+07 CS-1 36 1.180E+07 4.670E+07 3.360E+07 O.O00E+00 2.600E+07 3.560E+06 5.300E+06 CS-137 8.720E+08 1.190E+09 7.810E+08 O.O00E+00 4.050E+08 1.350E+08 2.310E+07 CS-138 O.O00+00 0.000E+00 O.O00+00 0.000E+00 O.O00+00 O.O002E+0 0.000E+00

Offsite Dose Calculation Manual Page 248 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS ADULT (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract BA-139 0.000E+00 .E0.000+00 0.O00E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 2.880E+07 3.610E+04 1.890E+06 0.000E+00 1.230E+04 2.070E+04 5.920E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 3.600E-02 1.810E-02 4.790E-03 0.OOOE+00 0.000E+00 0.000E+00 1.330E+03 LA-142 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CE-141 1.400E+04 9.480E+03 1.080E+03 0.OOOE.00 4.400E+03 0.000E+00 3.620E+07 CE-143 2.090E-02 1.550E+01 1.710E-03 0.000E+00 6.800E-03 0.000E+00 5.780E+02 CE-144 1.460E+06 6.090E+05 7.830E+04 0.000E+00 3.610E+05 0.000E+00 4.930E+08 PR-143 2.130E+04 8.540E+03 1.060E+03 0.000E+00 4.930E+03 0.0002+00 9.330E+07 PR-144 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 7.080E+03 8.180E+03 4.900E+02 0.000E+00 4.780E+03 0.000E+00 3.930E+07 EU-154 8.030E+06 9.870E+08 7.020E+05 0.OOOE+00 4.720E+06 0.OOOE+00 -- 7.150E+08 EU-155 1.110E+06 1.580E+05 1.020E+05 0.000E+00 7.300E+05 0.000E+00 1.240E+08 W-187 2.160E-02 1.810E-02 6.320E-03 0.000E+00 0.000E+00 0.000E+00 5.920E+00 NP-239 2.560E-01 2.510E-02 1.390E-02 0.OOOE+00 7.840E-02 0.000E+00 5.150E+03

Offsite Dose Calculation Manual Page 249 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS TEEN (m2*mrem/yr per uCVsec)

Nuclide Bone Liver "body Thyroid Kidney Lung Gitract H-3 0.OOOE+00 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 C-14 2.810E+05 5.620E+04 5.620E+04 5.620E+04 5.620E+04 5.620E+04 5.620E+04 NA-24 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 P-32. 3.93D0E+/-09 . 2.-4402+O08 -.---- 1.520E+08 ...- -..0000E+00 -. O..000E+00--0:00OE+00.... 3:300E+08. . .

CR-51 0.000E+00 0.000E+00 5.650E+03 3.140E+03 1.240E+03 8.070:+03 9.500E+05 MN-54 0.0002+00 6.980E+06 1.380E+06 0.000E+00 2.080E+06 0.000E+00 1.430E+07 MN-56 0.0002+00 0.0002+00 0.000E+00 0.0002+00 0.0000+00 0.0000+00 0.OOOE+00 FE-55 2.380E+08 1.690E+08 3.930E+07 0.000E+00 0.OOOE+00 1.070E+08 7.300E+07 FE-59 2.130E+08 4.980E+08 1.920E+08 0.0002+00 0.000E+00 1.570E+08 1.180E+09 CO-57 0.000E+00 4.530E+06 7.590E+06 0.000E+00 0.000E+00 0.000E+00 8.450E+07 CO-58 0.000E+00 1.410E+07 3.250E+07 0.000+E00 0.000E+00 0.000E+00 1.940E+08 CO-60 0.000E+00 5.830E+07 1.310E+08 0.000E+00 0.000E+00 0.000E+00 7.600E+08 NI-63 _1.520E+10 1.070E+09 5.150E+08 0.000E+00 0.000E*00 0.000E+00 1.710E+08 NI-65 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 CU-64 0.000E+00 2.410E-07 1.130E-07 0.000E+00 6,1002-07 0.000E+00 1.870E-05 ZN-65 2.500E208 8.690E+08 4.050E+08 0.000E+00 5.560E208 0.000E+00 3.680E+08 ZN-69 0.0004E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.OOOE+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 BR-85 0.000E+00 0.000E+00 O.OOOE+00 0.000E+00 0.000E+00 0.000+E00 0.0002+00 RB-86 0.000E+00 4.060E+08 1.910E+08 0.000E+00 0.000E+00 0.000E+00 6.010E+07 RB-88 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 RB-89 0.000E+00 0.000+E00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 2.540E+08 0.000+E00 7.290E+06 0.000E+00 0.000E+00 0.000E+00 3.030E+07 SR-90 8.050E+09 0.000E+00 1.990E+09 0.000E+00 0.000E+00 0.0002+00 2.260E+08 SR-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.100E-09 SR-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.O00E+00 Y-90 8.980E+01 0.000E+00 2.420E+00 0.000E+00 0.000E+00 0.0002E00 7.400E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.0002+00 0.000E+00 Y-91 9.560E+05 0.000E+00 2.560E+04 0.000E+00 0.000E+00 0,000E+00 3.920E+08 Y-92 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.000E+00 Y-93 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.690E-07

Offsite Dose Calculation Manual Page 250 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS TEEN (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract ZR-95 1.510E+06 4.760E+05 3.270E+05 0.000E+00 6.990E+05 0.000E+00 1.100E+09 ZR-97 1.530E-05 3.020E-06 1.390E-06 0.000E÷00 4.580E-06 0.000E+00 8.180E-01 NB-95 1.790E+06 9.940E+05 5.470E+05 0.0002E00 9.640E+05 0.000E+00 4.250E+09 NB-97 0.000E+00 _0 O0002E+00 --0.0000E_00_ -0.000E+00-- .000E+00-- -- 0000E+00---0-.000E+0o..

wU-%ra u.UUU=-i-ul 8.980-.+04 1.710E+04 0.OOOE+00 2.060E+05 0.000E+00 1.610E+05 TC-99M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 0.000E+00 TC-101 0.000.E00 0.000E+00 0.000E+00 0.000E+00 O.000E÷00 0.000E+00 0.000E+00 RU-1 03 8.600E+07 0.000E+00 3.680E+07 0.000E+00 3.030E+08 0.000E+00 7.180E+09 RU-105 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 0.000E+00 RU-106 2.360E+09 0.000E+00 2.970E+08 0.000E+00 4.550E+09 0.000E+00 1.130E+11 RH-1 03M 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E÷00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 5.060E+06 4.790E+06 2.910E+06 0.000E+00 9.140E+06 0.000E+00 1.350E+09 SB-122 3.300E+03 3.440E+03 4.170E+04 5.460E+02 1.620E+03 7.080E+02 4.100E+05 SB-124 1.620E+09 2.980E+07 6.310E+08 3.670E+06 0.000E+00 1.41 0E+09 3.260E+10 SB-125 1.560E+09 1.710E+07 3.660E+08 1.490E+06 0.000E+00 1.370E+09 1.220E+10 TE-125M 3.030E+08 1.090E+08 4.050E+07 8.470E+07 0.000E+00 0.OOOE+00 8.940E+08 TE-127M 9.410E+08 3.340E+08 1.120E+08 2.240E+08 3.820E+09 0.000E+00 2.350E+09 TE-127 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 1.750E-08 TE-129M 9.580E+08 3.560E+08 i.520E+08 3.090E+08 4.01 0E+09 0.000E+00 3.600E+09 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 O.000E+00 O.000E+00 TE-131 M 3.760E+02 1.800E+02 1.500E+02 2.710E+02 1.880E+03 0.000E+00 1.450E+04 TE-131 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 1.150E+06 7.260E+05 6.840E+05 7.660E+05 6.970E+06 O.O00E+00 2.300E+07 1-130 1.890E-06 5.480E-06 2.190E-06 4.470E-04 8.440E-06 0.000E+00 4.210E-06 1-131 8.950E+06 1.250E+07 6.730E+06 3.660E+09 2.160E+07 0.000E+00 2.480E+06 1-132 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1-133 3.590E-01 6.100E-01 1.860E-01 8.510E+01 1.070E+00 0.OOOE+00 4.610E-01 1-134 0.000E+00 0.0OOE+00 0.000+E00 O.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1-135 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 5.230E+08 1.230E+09 5.710E+08 0.000E+00 3.910E+08 1.490E+08 1.530E+07 CS-136 9.220E+06 3.630E+07 2.440E+07 0.000E+00 1.970E+07 3.110E+06 2.920E+06 CS-137 7.240E+08 9.630E+08 3.360E+08 0.000E+00 3.280E+08 1.270E+08 1.370E+07 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00

Offsite Dose Calculation Manual Page 251 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS TEEN (m2*mremlyr per uCVsec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 0.000E+O0 O.000E+00 BA-140 2.380E+07 2.910E+04 1.530E+06 0.000E+00 9.880E+03 1.960E+04 3.670E+07 BA-141 O.OOOE+00 0.000E+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 BA-142 0.00_E+00 0. E+ -0.000E0......0.000E+00 --.0.000E+00 .0.000E+00 0000E+00 -..

LA-140 2.960E-02 1.450E-02 3.870E-03 0.OOOE+00 0.000E+00 0.000E+00 8.350E+02 LA-142 0.000E+00 0.OOOE+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 CE-141 1.180E+04 7.860E+03 9.030E+02 0.000E+00 3.700E+03 0.000E+00 2.250E+07 CE-143 1.760E-02 1.280E+01 1.430E-03 0.000E+00 5.740E-03 0.000E+00 3.850E+02 CE-144- 1.230E+06 5.080E+05 6.600E+04 0.000E+00 3.040E+05 0.000E+00 3.090E+08 PR-143 1.790E+04 7.150E+03 8.920E+02 0.000+E00 4.160E+03 0.000E+00 5.900E+07 PR-144 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 ND-147 6.240E+03 6.790E+03 4.060E+02 0.000E+00 3.980E+03 0.000E+00 2.450E+07 EU-154 _ 6.090E+06 7.870E+05 5.540E+05 0.OOOE+00 3.520E+06 0.000E+00 4.160E+08 EU-155 1.330E+06 1.290E+05 7.970E+04 0.000E+00 5.030E+05 0.000E+00 7.380E+08 W-187 1.810E-02 1.480E-02 5.170E-03 0.OOOE+00 0.000E+00 0.000E+00 3.990E+00 NP-239 2.230E-01 2.110E-02 1.170E-02 0.000E+00 6.6102E-02 0.000E+00 3.390E1+03

Offsite Dose Calculation Manual Page 252 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS CHILD (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver "Tbody Thyroid Kidney Lung Gltract H-3 0.000E+00 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 C-14 5.290E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 NA-24 2.340E-03 2.340E-03 2.340E-03 2.340E-03 2.340E-03 2.340E-03 2.340E-03

---P-32 ... _7.410E+09 .3.470E+08 -2.860*+08- -0.000E+00 -0.000E+00 -0;000+E00 -2;050E+08 CR-51 0.000E+00 0.000E+00 8.810E+03 4.890E+03 1.340E+03 8.930E+03 4.670E+05 MN-54 0.000E+00 7.990E+06 2.130E+06 0.000E+00 2.240*406 0.000E+00 6.700E+06 MN-56 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-55 4.570E+08 2.420E+08 7.510E+07 0.000E+00 0.000E+00 1.370E+08 4.490E+07 FE-59 3.780E+08 6.120E+08 3.050E+08 0.000E+00 0.000E+00 1.770E+08 6.370E+08 CO-57 0.000E+00 5.920E+06 1.200E+07 0.000E+00 0.000E+00 0.000E+00 4.850E+07 CO-58 0.000E+00 1.650E+07 5.040E+07 0.000E+00 0.000E+00 0.000E+00 9.600E+07 CO-60 0.OOOE+00 6.930E+07 2.040E+08 0.000E+00 0.000E+00 0.000E+00 3.840E+08 NI-63 2.910E+10 1.560E+09 9.910E+08 0.000E+00 0.000E+00 0.0002+00 1.050E+08 NI-65 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CU-64 0.000E+00 3.240E-07 1.960E-07 0.000E+00 7.820E-07 0.000E+00 1.520E-05 ZN-65 3.750E+08 1.OOOE+09 6.220E+08 0.000E+00 6.300E+08 0.000E+00 1.760E+08 ZN-69 0.000E+00 0.OOOE+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 O.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.760E+08 3.540E+08 0.000E+00 0.000E+00 0.000E+00 3.710E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 4.820E+08 0.000E+00 1.380E+07 0.000E+00 0.000E+00 0.000E+00 1.860E+07 SR-90 1.040E+10 0.000E+00 2.640E+09 0.000E+00 0.000E+00 0.000E+00 1.400E+08 SR-91 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.000E+00 1.01 0E-09 SR-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-90 1.700E+02 0.000E+00 4.550E+00 0.000E+00 0.000E+00 0,000E+00 4.840E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.810E+06 0.000E+00 4.830E+04 0.000E+00 O.O00E+00 0.000E+00 2.410E+08 Y-92 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-93 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.550E-07

Offsite Dose Calculation Manual Page 253 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS CHILD (m2*mrem/yr per uCVsec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract ZR-95 2.680E+06 5.890E+05 5.240E+05 0.000E+00 8.430E+05 0.000E+00 6.140E+08 ZR-97 2.840E-05 4.100E-06 2.420E-06 0.000E+00 5.890E-06 0.OOOE+00 6.210E-01 NB-95 3.090E+06 1.200E+06 8.610E+05 0.000E+00 1.130E+06 0.000E+00 2.230E+09

...... N.B-97. o0.0oo E+t000. O.OOOE+00a- -.. 000E+00 .- -..0.000E+00- -0;000E+00 o0.000E+00 .... 0.000E+00 MO-99 0.000E+00 1.250E+05 3.090E+04 0.000E+00 2.670E+05 0.000E+00 1.030E+05 TC-99M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.560E+08 0.0004E00 5.980E+07 0.000E+00 3.920E+08 0.000E+00 4.020E+09 RU-105 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-106 4.440E+09 0.000E+00 5.540E+08 0.000E+00 5.990E+09 0.000E+00 6.900E+10 RH-103M 0.000E+00 0.000E+00 0.000+E00 0.000+E00 0.000E+00 O.OOOE+00 0.000E+00 RH-106 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-11OM 8.400E+06 5.670E+06 4.530E+06 0.000E+00 1.060E+07 0.000E+00 6.750E+08 SB-122 2.080E+03 2.170E+03 2.630E+04 3.450E+02 1.020E+03 4.460E+02 2.580E+05 SB-124 2.930E+09 3.800E+07 1.030E+09 6.460E+06 0.000E+00 1.620E+09 1,830E+10 SB-125 2.850E+09 2.190E+07 5.960E+08 2.640E+06 0.OOOE+00 1.590E+09 6.800E+09 TE-125M 5.690E+08 1.540E+08 7.590E+07 1.600E+08 0.000E+00 0.000E+00 5.490E+08 TE-127M 1.770E+09 4.780E+08 2.110E+08 4.240E+08 5.060E+09 0.O00E+00 11.440E+09 TE-127 0.000E+00 O.000E+00 0.000E+00 O.000E+00 1.210E-09 0.000E+00 1.660E-08 TE-129M 1.810E+09 5.040E+08 2.800E+08 5.820E+08 5.300E+09 0,000E+00 2.200E+09 TE-129 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 TE-131M 7.OOOE+02 2.420E+02 2.580E+02 4.980E+02 2.340E+03 0.000E+00 9.820E+03 TE-131 0.000E+00 0.000+E00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.090E+06 9.270E+05 1.120E+06 1.350E+06 8.600E+06 0.OOOE+00 9.330E+06 1-130 3,390E-06 6.850E-06 3.530E-06 7.540E-04 1.020E-05 0.000E+00 3.200E-06 1-131 1.660E+07 1.670E+07 9.490E+06 5.520E+09 2.740E+07 0.000E+00 1.490E+06 1-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 1-133 6.680E-01 8.260E-01 3.120E-01 1.530E+02 1.380E+00 0.000E+00 3.330E-01 1-134 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1-135 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 9.220E+08 1.510E+09 3.190E+08 0.OOOE+00 4.690E+08 1.680E+08 8.150E+06 CS-136 1.590E+07 4.370E+07 2-830E+07 0.000E+00 2.330E+07 3.470E+06 1.540E+06 CS-137 1.330E+09 1.280E+09 1.880E+08 0.000E+00 4.160E+08 1.500E+08 7.990E+06 CS-138 0.OOOE+00 0.000E+00 O.O00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

Offsite Dose Calculation Manual Page 254 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS CHILD (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gltract BA-139 O.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 O.OOOE+00 0.000E+00 BA-140 4.390E+07 3.850E+04 2.560E+06 0.000E+00 1.250E+04 2.290E+04 2.220E+07 BA-141 0.000E+00 O.OOOE+00 0.000E+00 0.OOOE+00 0.000+E00 0.000E+00 0.OOOE+00

..BA142...- O00.OOOE+00 0+E00 0.0 -- 000E2+0O ...... 00.000E+00

.... 0,0E400 0..0E00+0-0 . -0.0-0E: ..

LA-140 5.410E-02 1.890E-02 6.380E-03 0.000E+00 0.OOOE+00 0.000E+00 5.270E+02 LA-142 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.O0OE+00 CE-141 2.220E+04 1.110E+04 1.640E+03 0.000E+00 4.840E+03 0.000E+00 1.380E+07 CE-143 3,300E-02 1.790E+01 2.590E-03 0.000E+00 7.5102-03 0.000E+00 2.620E+02 CE-144 2.320E+06 7.260E+05 1.240E+05 0.000E+00 4.020E+05 0.000E+00 1.890E+08 PR-143 3.390E+04 1.020E+04 1.680E+03 0.000E+00 5.510E+03 0.000E+00 3.660E+07 PR-144 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 ND-147 1.170E+04 9.480E+03 7.340E+02 0.000E+00 5.200E+03 0.000E+00 1.500E+07 EU-154 1.120E+07 1.010E+06 9.190E+05 0.000E+00 4.420E+06 0.000E+00 2.340E+08 EU-155 2.330E+06 1.680E+05 1.310E+05 0.000E+00 6.280E+05 0.000E+00 4.200E+08 W-187 3.360E-02 1.990E-02 8,920E-03 0.000E+00 0.000E+00 0.000E+00 2.790E+00 NP-239 4.200E-01 3.020E-02 2.120E-02 0.000E+00 8.730E-02 0.000E+00 2.230E+03

Offsite Dose Calculation Manual Page 255 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS INFANT (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gltract THIS PATHWAY IS NOT APPLICABLE TABLE INTENTIONALLY LEFT BLANK

Offsite Dose Calculation Manual Page 256 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS ADULT (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver "body Thyroid Kidney Lung GItract H-3 0.000E+00 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 C-14 8.970E+05 1.790E+05 1.790E+05 1.790E+05 1.790E+05 1.790E+05 1.790E+05 NA-24 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 P-32 I .400E+09 ..... 8.730E.+07 ---- 5.420E+07. 0.000E-+0.... 0-.00E+00... -.O000E+00 -- 1.580E+08............

CR-51 0.000E+00 0.000E+00 4.660E+04 2.790E+04 1.030E+04 6.190E+04 1.170E+07 MN-54 0.000E+00 3.110E+08 5.940E+07 0.000E+00 9.270E+07 0.000E+00 9.540E+08 MN-56 0.000E+00 1.610E+01 2.850E+00 0.0002E00 2.040E+01 0.000E+00 5.130E+02 FE-55 2.090E+08 1.450E+08 3.370E+07 0.000E+00 0.OOOE+00 8.060E+07 8.290E+07 FE-59 1.270E+08 2.990E+08 1.140E+08 0.000E+00 0.000E+00 8.350E+07 9.960E+08 CO-57 0.OOOE+00 1.170E+07. 1.950E+07 0.000E+00 0.OOOE+00 0.000E+00 2.970E+08 CO-58 0.000E+00 3.090E+07 6.920E+07 0.000E+00 0.0002+00 0.000E+00 6.260E+08 CO-60 0.000E+00 1.670E+08 3.690E+08 0.OOOE+00 0.000E+00 0.000E+00 3.140E+09 NI-63 1.040E+10 7.210E+08 3.490E+08 0.0002+00 _ 0.000E+00 0.000E+00 1.500E+08 NI-65 6.150E+01 7.990E+00 3.650E+00 0.0002+00 0.000E+00 0.000E+00 2.030E+02 CU-64 0.000E+00 9.270E+03 4.350E+03 0.000E+00 2.340E+04 0.000E+00 7.900E+05 ZN-65 3.170E+08 1.010E+09 4.560E+08 0.000E+00 6.750E+08 0.000E+00 6.360E+08 ZN-69 8.750E-06 1.670E-05 1.160E-06 0.000E+00 1.090E-05 0.000E+00 2.510E-06 BR-82 0.000E+00 0.000E+00 1.510E+06 0.000E+00 0.000E+00 0.000E+00 1.730E+06 BR-83 0.000E+00 0.000E+00 3.210E+00 0.000E+00 0.000E+00 0.000E+00 4.630E+00 BR-84 0.000E+00 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.0002+00 0.OOOE+00 0.000E+00 RB-86 0.000E+00 2.190E+08 1.020E+08 0.000E+00 0.000E+00 0.000E+00 4.320E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 SR-89 9.960E+09 0.000E+00 2.860E+08 0.000E+00 0.000E+00 0.000E+00 1.600E+09 SR-90 6.050E+11I 0.000E+00 1.480E+11 0.000E+00 0.000E+00 0.000E+00 1.750E+10 SR-91 3.200E+05 0.000E+00 1.290E+04 0.000E+00 0.000E+00 0.000E+00 1.520E+06 SR-92 4.270E+02 0.000E+00 1.850E+01 0.000E+00 0.000E+00 0.000E+00 8.460E+03 Y-90 1.330E+04 0.000E+00 3.560E+02 0.000E+00 0.000+E00 0.000E+00 1.410E+08 Y-91M 5.830E-09 0.000E+00 0.000E+00 0.0002+00 0.000+E00 0.000E+00 1.710E-08 Y-91 5.130E+06 0.000E+00 1.370E+05 0.000E+00 0.000E+00 0.000+E00 2.820E+09 Y-92 9.010E-01 0.000E+00 2.630E-02 0.000E+00 0.000E+00 0.000E+00 1.580E+04 Y-93 1.740E+02 0.000E+00 4.800E+00 0.OOOE+00 0.000E+00 0.000E+00 5.520E+06

Offsite Dose Calculation Manual Page 257 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS ADULT (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract ZR-95 1.190E+06 3.810E+05 2.580E+05 0.000E+00 5.970E+05 0.0002+00 1.210E+09 ZR-97 3.330E+02 6.730E+01 3.080E+01 0.000E+00 1.020E+02 0.000E+00 2.080E+07 NB-95 1.420E+05 7.910E+04 4.250E+04 0.000E+00 7.810E+04 0.000E+00 4.800E+08 NB-97 2.900E-06 7.340E-07 2.680E-07 0.000E+00 8.560E-07 0.000E+00 2.710E-03 MO-99 0.000E+00 6.250E+06 1.190E+06 0.000E+00 1.410E+07 O.000E+00 1.450E+07 TC-99M 3.060E+00 8.660E+00 1.100E+02 0.000E+00 1.320E+02 4.240E+00 5.120E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 4.800E+06 0.000E+00 2.070E+06 0.000E+00 1.830E+07 O.OOOE+00 5.610E+08 RU-105 5.390E+01 0.000E+00 2.130E+01 O.OOOE+00 6.960E+02 O.000E+00 3.300E+04 RU-106 1.930E+08 O.OOOE+00 2.440E+07 0.0002E00 3.720E+08 0.000E+00 1.250E+10 RH-103M O.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000O+00 RH-106 0.000E+00 0,000E+00 0.000E+00 O.O00E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 1.060E+07 9.760E+06 5.800E+06 O.O00E+00 1.920E+07 - O.O00E+00 3.980E+09 SB-122 7.500E+05 7.820E+05 9.470E+06 1.240E+05 3.690E+05 1.610E+05 9.320E+07 SB-124 1.040E+08 1.960E+06 4.110E+07 2.520E+05 0.000+E00 8.080E+07 2.950E+09 SB-125 1.350E+08 1.520E+06 3.250E+07 1.390E+05 0.000E+00 1.050E+08 1.500E+09 TE-125M 9.660E+07 3.500E+07 1.290E+07 2.900E+07 3.930E+08 0.000E+00 3.860E+08 TE-127M 3,490E+08 1.250E+08 4.260E+07 8.920E+07 1.420E+09 0.000E+00 1.170E+09 TE-127 5.760E+03 2.070E+03 1.250E+03 4.270E+03 2.350E+04 0.000E+00 4.540E+05 TE-129M 2.550E+08 9.500E+07 4.030E+07 8.750E+07 1.060E+09 0.000E+00 1.280E+09 TE-129 6.650E-04 2.500E-04 1.620E-04 5.10OE-04 2.790E-03 O.O00E+00 5.020E-04 TE-131M 9.120E+05 4.460E+05 3.720E+05 7.060E+05 4.520E+06 0.000E+00 4.430E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 4.290E+06 2-770E+06 2.600E+06 3.060E+06 2.670E+07 O.002E+00 1.310E+08 1-130 3.960E+05 1.170E+06 4.610E+05 9.900E+07 1.820E+06 0.000E+00 1.010E+08 1-131 8.090E+07 1.160E+08 6.630E+07 3.790E+10 1.980E+08 0.000E+00 3.050E+07 1-132 5.740E+01 1.540E+02 5.380E+01 5.380E+03 2.450E+02 0.000E+00 2.890E+01 1-133 2.120E+06 3.690E+06 1.120E+06 5.420E+08 6.440E+06 0.000E+00 3.310E+06 1-134 1.060E-04 2.880E-04 1.030E-04 5.000E-03 4.590E-04 0.000E+00 2.510E-07 1-135 4.080E+04 1.070E+05 3.940E+04 7.040E+06 1.710E+05 0.000E+00 1.210E+05 CS-134 4.660E+09 1.110E+10 9.070E+09 O.O00E+00 3.590E+09 1.190E+09 1.940E+08 CS-136 4,200E+07 1.660E+08 1.190E+08 0.0002+00 9.240E+07 1.270E+07 1.890E+07 CS-137 6.360E+09 8.700E+09 5.700E+09 O.O00E+00 2.950E+09 9.810E+08 1.680E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

-m Offsite Dose Calculation Manual Page 258 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS ADULT (m2*mrem/yr per uCi/sec)

Nuclide Bone Uver Tbody Thyroid Kidney Lung Gitract BA-139 2.950E-02 2.100E-05 8.640E-04 0.000E+00 1.960E-05 1.190E-05 5.230E-02 BA-140 1.290E+08 1.620E+05 8.430E+06 0.000E+00 5.490E+04 9.250E+04 2.650E+08 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E200 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA.140 1.970E+03 9.920E+02 2.620E+02 0.000E+00 O.000E+00 0.OOOE+00 7.280E+07 LA-142 1.400E.04 6.350E-05 1.580E-05 0.000E+00 0.000E+00 0.000+E00 4.640E-01 CE-141 1.960E+05 1.330E+05 1.510E+04 0.000E+00 6.170E+04 0.000E+00 5.080E+08 CE-143 1.000E+03 7.420E+05 8.210E+01 0.000E+00 3.260E+02 0.000E+00 2.770E+07 CE-144 3.290E+07 1.380E+07 1.770E+06 0.000E+00 8.160E+06 0.000E+00 1.110E+10 PR-143 6.340E+04 2.540E+04 3.140E+03 0.000E+00 1.470E+04 0.000E+00 2.780E+08 PR-144 0.000E+00 0.000E+00 O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 3.340E+04 3.860E+04 2.310E+03 0.000E+00 2.250E+04 0.000E+00 1.850E+08 EU-154 4.850E+07 5.970E+06 4.250E+06 0.000E+00 2-860E+07 0.000E+00 4.320E+09 EU-155 6.710E+06 9.510E+05 6.140E+05 0.000E+00 4.390E+06 0.000E+00 7.490E+08 W-187 3.820E+04 3.190E+04 1.120E+04 0.000E+00 0.000E+00 0.000E+00 1.050E+07 NP-239 1.420E+03 1.400E+02 7.720E+01 0.000E+00 4.370E+02 0.000E+00 2.870E+07

Offsite Dose Calculation Manual Page 259 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS TEEN (m2*mremfyr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.OOOE+00 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 C-14 1.450E+06 2.910E+05 2.910E+05 2.910E+05 2.910E+05 2.910E+05 2.910E+05 NA-24 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 P-32 1.610E+09 9.960E+07 6.230E+07 0.000E+00 O.O00E+00 O.O00E+00 1.350E+08 CR-51 0.OOOE+00 0.000E+00 6.200E+04 3.440E+04 1.360E+04 8.850E+04 1.040E+07 MN-54 0.000E+00 4.520E+08 8.970E+07 O.O00E+00 1.350E+08 O.000E+00 9.270E+08 MN-56 0.000E+00 1.450E+01 2.580E+00 0.000E+00 1.830E+01 0.000E+00 9.540E+02 FE-55 3.250E+08 2.310E+08 5.380E+07 0.000E+00 0.000E+00 1.460E+08 9.980E+07 FE-59 1.810E+08 4.220E+08 1.630E+08 0.000E+00 0.000E+00 1.330E+08 9.980E+08 CO-57 0.000E+00 1.790E+07 3.000E+07 0.000E+00 0.000E+00 0.000E+00 3.340E+08 CO-58 O.OOOE+00 4.380E+07 1.010E+08 0.0002+00 0.000E+00 0.000E+00 6.040E+08 CO-60 0.000E+00 2.490E+08 5.600E+08 0.000E+00 0.000E+00 0.000E+00 3.240E+09 NI-63 1.610E+10 1.130E+09 5.450Et08 0.0002+00 0.000E+00 0.000E+00 1.810E+08 NI-65 5.730E+01 7.320E+00 3.330E+00 0.000E+00 0.000E+00 0.000E+00 3.970E+02 CU-64 O.O00E+00 8.400E+03 3.950E+03 0.000E+00 2.120E+04 0.000E+00 6.510E+05 ZN-65 4.240E+08 1.470E+09 6.860E+08 0.000E+00 9.410E+08 0.000E+00 6.230E+08 ZN-69 8.190E-06 1.560E-05 1.090E-06 0.000E+00 1.020E-05 0.000E+00 2.880E-05 BR-82 O.000E+00 O.O00E+00 1.330E+06 0.000E+00 0.000E+00 0.000E+00 0.0002+00 BR-83 0.000E+00 0.000E+00 3.010E+00 0.OOOE+00 0.000E+00 0.0002+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.O00E+00 BR-85 0.000E+00 0.000E÷00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 RB-86 0.000E+00 2.730E+08 1.280E+08 0.000E+00 0.000E+00 0.000E+00 4.050E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 OO00E+00 0.000E+00 O.O00E+00 O.O00E+00 O.O00E+00 O.O00E+00 0.0002+00 SR-89 1.510E+10 O.O00E+00 4.330E+08 O.O00E+00 O.O00E+00 O.O00E+00 1.800E+09 SR-90 7.510E+11 O.O00E+00 1.850E+11 0.0002+00 0.000E+00 O.O002E+0 2.110E+10 SR-91 2.990E+05 O.O00E+00 1.190E+04 0.000E+00 O.O00E+00 0.000E+00 1.360E+06 SR-92 3.970E+02 0.0002+00 1.690E+01 O.O00E+00 O.00E2+00 O.O00E+00 1.010E+04 Y-90 1.240E+04 O.O00E+00 3.340E+02 O.OOOE+00 O.O00E+00 O.O00E+00 1.020E+08 Y-91M 5.430E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.560E-07 Y-91 7.870E+06 O.O00E+00 2.110E+05 0.O00E+00 0.000E+00 0.000E+00 3.230E+09 Y-92 8.470E-01 O.O00E+00 2.450E-02 0.000E+00 O.O00E+00 0.000E+00 2.320E+04 Y-93 1.630E+02 O.O00E+00 4.470E+00 O.O00E+00 0.000E+00 0.000E+00 4.980E+06

Offsite Dose Calculation Manual Page 260 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS TEEN (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gltract ZR-95 1.740E+06 5.490E+05 3.780E+05 0.000E+00 8.070E+05 0.000E+00 1.270E+09 ZR-97 3.090E+02 6.110E+01 2.810E+01 0.000E+00 9.260E+01 0.000E+00 1.650E+07 NB-95 1.920E+05 1.060E+05 5.860E+04 0.000E+00 1.030E+05 0.000E+00 4.550E+08 NB-97 2-690E-06 6.670E-07 2.440E-07 0.000E+00 7.800E-07 0.000E+00 1.590E-02 MO-99 0.000E+00 5.740E+06 1.090E+06 0.000E+00 1.310E+07 0.000E+00 1.030E+07 TC-99M 2.700E+00 7.540E+00 9.770E+01 0.000E+00 1.120E+02 4.190E+00 4.950E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 6.870E+06 0.000E+00 2.940E+06 0.OOOE+00 2.420E+07 0.000E+00 5.740E+08 RU-105 5.000E+01 0.OOOE+00 1.940E+01 0.OOOE+00 6.310E+02 0.000E+00 4.040E+04 RU-106 3.090E+08 0.000E+00 3.900E+07 0.000E+00 5.970E+08 0.000E+00 1.480E+10 RH-103M 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-1i OM 1.520E+07 1.440E+07 8.740E+06 0.000E+00 2.740E+07 _0.000E+00 4.040E+09 SB-122 4.920E+05 5.130E+05 6.220E+06 8.150E+04 2.420E+05 1.060E+05 6.120E+07 SB-124 1.550E+08 2.850E+06 6.030E+07 3.510E+05 0.000E+00 1.350E+08 3.110E+09 SB-125 2.140E+08 2.340E+06 5.000E+07 2.040E+05 O.000E+00 1.880E+08 1.6602+09 TE-1 25M 1.480E+08 5.340E+07 1.980E+07 4.140E+07 0.000E+00 0.000E+00 4.370E+08 TE-127M 5.510E+08 1.960E+08 6.560E+07 1.310E+08 2.240E+09 0.000E+00 1.370E+09 TE-127 5.430E+03 1.920E+03 1.170E+03 3.740E+03 2.200E+04 0.000E+00 4.190E+05 TE-129M 3.670E+08 1.360E+08 5.810E+07 1.180E+08 1.540E+09 0.000E+00 1.380E+09 TE-129 6.220E-04 2.320E-04 1.510E-04 4.450E-04 2.610E-03 0.000E+00 3.400E-03 TE-131M 8.440E+05 4.050E+05 3.380E+05 6.090E+05 4.220E+06 0.OOOE+00 3.250E+07 TE-131 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 TE-132 3.900E+06 2.470E+06 2.320E+06 2.600E+06 2.370E+07 0.000E+00 7.820E+07 1-130 3.540E+05 1.020E+06 4.090E+05 8.350E+07 1.580E+06 0.000E+00 7.870E+05 1-131 7.700E+07 1.080E+08 5.790E+07 3.140E+10 1.850E+08 0.000E+00 2.130E+07 1-132 5.180E+01 1.360E+02 4.870E+01 4.570E+03 2.140E+02 0.000E+00 5.910E+01 1-133 1.970E+06 3.340E+06 1.020E+06 4.660E+08 5.860E+06 0.000E+00 2.530E+06 1-134 9.590E-05 2.540E-04 9.130E-05 4.240E-03 4.010E-04 0.000E+00 3.350E-08 1-135 3.680E+04 9.480E+04 3.520E+04 6.100E+06 1.500E+05 0.000E+00 1.050E+05 CS-134 7.090E+09 1.670E+10 7.740E+09 0.000E+00 5.300E+09 2.020E+09 2.080E+08 CS-136 4.290E+07 1.690E+08 1.130E+08 0.000E+00 9.190E+07 1.450E+07 1.360E+07 CS-137 1.010E+10 1.350E+1 0 4.690E+09 0.000E÷00 4.590E+09 1.780E+09 1.920E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

Offsite Dose Calculation Manual Page 261 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS TEEN (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver "Tbody Thyroid Kidney Lung Gitract BA-139 2.770E-02 1.950E-05 8.080E-04 0.000E+00 1.840E-05 1.340E-05 2.470E-01 BA-140 1.380E+08 1.690E+05 8.910E+06 0.000E+00 5.750E+04 1.140E+05 2.130E+08 BA-141 0.000E+00 0.O00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 OO000E+00 0.000E+00 LA-140 1.800E+03 8.840E+02 2.350E+02 0.000E+00 O.000E+00 0.000E+00 5.080E+07 LA-142 1.280E-04 5.690E-05 1.420E-05 0.000E+00 0.000E+00 0.000E+00 1.730E+00 CE-141 2.820E+05 1.8802+05 2.160E+04 0.000E+00 8.860E+04 0.0002+00 5.380E+08 CE-143 9.370E+02 6.820E+05 7.620E+01 O.000E+0 3.060E+02 0.000E+00 2.050E+07 CE-144 5.270E+07 2.180E+07 2.830E+06 0.000E+00 1.300E+07 0.000E+00 1.330E+10 PR-143 7.120E+04 2.840E+04 3.550E+03 0.000E+00 1.650E+04 0.000E+00 2.340E+08 PR-144 0.000E+00 O.O00E+00 O.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 ND-147 3.630E+04 3.940E+04 2.360E+03 0.000E+00 2.320E+04 0.OOOE+00 1.420E+08 EU-154 7.060E+07 9.120E+06 _ 6.430E+06 0.000E+00 4.080E+07 0,000E+00 4.820E+09 EU-155 1.540E+07 1.480E+06 9.1902+05 0.000E+00 5.800E+06 0.000E+00 8.510E+09 W-187 3.5505+04 2.900E+04 1.020E+04 0.000E+00 O.000+E00 0.0002+00 7.840E+06 NP-239 1.380E+03 1.300E+02 7.240E+01 0.000+E00 4.090E+02 0.000E+00 2.100E+07

Offsite Dose Calculation Manual Page 262 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS CHILD (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Ghtract H-3 0.OOOE+00 4.010E+03 4.010E+03 4.010E+03 4.010E+03 4.010E+03 4.010E+03 C-14 3.500E+06 7.010E+05 7.010E+05 7.010E+05 7.010E+05 7.010E+05 7.010E+05 NA-24 3.830E+05 3.830E+05 3.830E+05 3.830E+05 3.830E+05 3.830E+05 3.830E+05 P-32 3.370E+09 1.580E+08 1.300E+08 0.0004E00 0.000E+00 0o.000E+00 9.300E+07 CR-51 0.000E+00 0.000E÷00 1.180E+05 6.540E+04 1.790E+04 1.190E+05 6.250E+06 MN-54 0.000E+00 6.610E+08 1.760E+08 0.000E+00 1.850E+08 0.000E+00 5.550E+08 MN-56 0.000E+00 1.900E+01 4.280E+00 0.000E+00 2.290E+01 0.000]+00 2.750E+03 FE-55 8.000E+08 4.240E+08 1.310+E08 0.000E+00 0.000E+00 2.400E+08 7.860E+07 FE-59 4.010E÷08 6.490E+08 3.230E+08 0.000+E00 0.000E+00 1.880E+08 6.760E+08 CO-57 0.000E+00 2.990E+07 6.040E+07 0.000E+00 0.000E+00 0.000E+00 2.450E+08 CO-58 0.000E+00 6.470E+07 1.980E+08 0.000E+00 0.000E+00 0.000E+00 3.770E+08 CO-60 0.000E+00 3.780E+08 1.120E+09 0.OOOE+00 0.000E+00 0.000E+00 2.100E+09 NI-63 3.950E+10 2.110E+09 1.340E+09 _ 0.000E+00 0.000E+00 0.000E+00 1.420E+08 NI-65 1.050E+02 9.890E+00 5.770E+00 0.000E+00 0.000E+00 0.000E+00 1.210E+03 CU-64 0.000E+00 1.110E÷04 6.690E+03 0.000E+00 2.6802+04 0.000E+00 5.200E+05 ZN-65 8.120E+08 2.160E+09 1.350E+09 0.000E+00 1.360E+09 0.000E+00 3.800E+08 ZN-69 1.510E-05 2.180E-05 2.020E-05 0.OOOE+00 1.320E-05 0.000E+00 1.380E-03 BR-82 0.000E+00 0.OOOE+00 2.040E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000+E00 0.000E+00 5.550E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.000+E00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.520E+08 2.780E+08 0.000E+00 0.000E+00 0.000E+00 2.910E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 SR-89 3.590E+10 0.000E+00 1.030E+09 0.000E+00 0.0002+00 0.000E+00 1.390E+09 SR-90 1.240E+12 0.000E+00 3.150E+11 0.000E+00 0.000E+00 0.000E+00 1.670E+10 SR-91 5.500E+05 0.000E+00 2.080E+04 0.000E+00 0.OOOE+00 0.000E+00 1.210E+06 SR-92 7.280E+02 0.000E+00 2.920E+01 0.000E+00 0.000E+00 0.000E+00 1.380E+04 Y-90 2.300E+04 0.000+E00 6.170E+02 0.000E+00 0.000E+00 0.000E+00 6.560E+07 Y-91M 9.940E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.950E-05 Y-91 1.870E+07 0.000E+00 5.010E+05 0.000E+00 0.000E+00 0.0002+00 2.490E+09 Y-92 1.560E+00 0.000E+00 4.460E-02 0.000E+00 0.000E+00 0.000E+00 4.510E+04 Y-93 3.010E+02 0.000E+00 8.250E+00 0.000+E00 0.000E+00 0.000E+00 4.480E+06

Offsite Dose Calculation Manual Page 263 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS CHILD (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract ZR-95 3.900E+06 8.580E+05 7.640E+05 0.000E+00 1.230E+06 0.000E+00 8.950E+08 ZR-97 5.640E+02 8.150E+01 4.810E+01 0.000E+00 1.170E+02 0.000E+00 1.230E+07 NB-95 4.100E+05 1.590E+05 1.140E+05 0.000E+00 1.500E+05 0.000E+00 2.950E+08 NB-97 4.900E-06 8.850E-07 4.130E-07 0.000E+00 9.820E-07 0.000E+00 2.730E-01 MO-99 0.OOOE+00 7.830E+06 1.940E+06 0.000E+00 1.670E+07 0.000E+00 6.480E+06 TC-99M 4.650E+00 9.120E+00 1.510E+02 0.000E+00 1.330E+02 4.6302+00 5.190E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 RU-103 1.550E+07 0.000E+00 5.940E+06 0.000E+00 3.890E+07 0.OOOE+00 3.990E208 RU-1 05 9.170E+01 0.000E+00 3.330E+01 0.000E+00 8.060E+02 0.000E+00 5.980E+04 RU-106 7.450E+08 0.000E+00 9.300E+07 0.000E+00 1.010E+09 0.000E+00 1.160E+10 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 RH-106 0,000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 3.220E+07 2.170E+07 1.740E+07 0.000E+00 4,050E+07 0.000E+00 2.580E+09 SB-122 3.050E+05 3.180E+05 3.850E+06 5.050E+04 1.500E+05 6.540E+04 3.790E+07 SB-124 3.520E+08 4.570E+06 1.230E+08 7.780E+05 O.000E+00 1.960E+08 2.200E+09 SB-125 4.990E+08 3.850E+06 1.050E+08 4.620E+05 0.000E+00 2.780E+08 1.190E+09 TE-125M 3.510E+08 9.500E+07 4.670E+07 9.840E+07 0.000E+00 0.000E+00 3.380E+08 TE-127M 1.320E+09 3.560E+08 1.570E+08 3.160E+08 3.770E+09 0.000E÷00 1.070E+09 TE-127 1.000E+04 2.700E+03 2.150E+03 6.930E+03 2.850E+04 0.000E+00 3.910E+05 TE-129M 8.540E+08 2.390E+08 1.330E+08 2.750E+08 2.510E+09 0.OOOE+00 1.040E+09 TE-129 1.150E-03 3.220E-04 2.740E-04 8.220E-04 3.370E-03 0.000E+00 7.170E-02 TE-131M 1.540E+06 5.330E+05 5.680E+05 1.1002+06 5.160E+06 0.000E+00 2.160E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 TE-1 32 6.980E+06 3.090E+06 3.730E+06 4.500E+06 2.870E+07 0.000E+00 3.110E+07 1-130 6.210E+05 1.260E+06 6.470E+05 1.380E+08 1.880E+06 0.000E+00 5.870E+05 1-131 1.430E+08 1.440E+08 8.180E+07 4.760E+10 2.360E+08 0.000E+00 1.280E+07 1-132 9.200E+01 1.690E+02 7.770E+01 7.840E+03 2.590E+02 0.000E+00 1.990E+02 1-133 3.590E+06 4.440E+06 1.680E+06 8.250E+08 7.400E+06 0.000E+00 1.790E+06 1-134 1.700E-04 3.160E-04 1.460E-04 7.280E-03 4.840E-04 0.000E+00 2.100E-04 1-135 6.540E+04 1.180E+05 5.570E+04 1.040E+07 1.810E+05 0.000E+00 8.980E+04 CS-134 1.600E+10 2.630E+10 5.540E+09 0.000E+00 8.140E+09 2.920E+09 1.420E+08 CS-136 8.060E+07 2.220E+08 1.430E+08 0.000+E00 1.180E+08 1,760E+07 7.790E+06 CS-137 2.390E+10 2.290E+10 3.380E+09 0.000E÷00 7.460E+09 2.680E+09 1.430E+08 CS-138 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00

-m Offsite Dose Calculation Manual Page 264 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS CHILD (m2*mremlyr per uC!/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract BA-139 5.110E-02 2.730E-05 1.480E-03 0.000E+00 2.380E-05 1.610E-05 2.950E+00 BA-140 2.770E+08 2.430E+05 1.620E+07 0.000E+00 7.900E+04 1.450E+05 1.400E+08 BA-141 0.000E+00 0.000E÷00 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 0.000E+00 BA-142 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 3.230E+03 1.130E+03 3.810E+02 0.000E+00 0.000E+00 0.000E+00 3.150E+07 LA-142 2.320E-04 7.400E-05 2.320E-05 0.000E+00 0.000E+00 0.000E+00 1.470E+01 CE-141 6.350E+05 3.260E+05 4.840E+04 0.000E+00 1,430E+05 0.000E+00 4.070E+08 CE-143 1.730E+03 9.360E+05 1.360E+02 0.000E+00 3.930E+02 0.000E+00 1.370E+07 CE-144 1.270E+08 3.980E+07 6.780E+06 0.000E+00 2.210E+07 0.000E+00 1.040E+10 PR-143 1.480E+05 4.460E+04 7.370E+03 0.000E+00 2.410E+04 0.000E+00 1.600E+08 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 7.160E+04 5.800E+04 4.490E+03 0.000E+00 3.180E+04 0.000E+00 9.180E+07 EU-154 1.660E+08 1.500E+07 1.370E+07 0.0002E00 6.570E+07 0.000E+00 3.480E+09 EU-155 3.440E+07 2.480E+06 1.940E+06 0.000E+00 9.280E+06 0.000E+00 6.200E+09 W-187 6.470E+04 3.830E+04 1.720E+04 0.000E+00 0.000E+00 0.000E+00 5.380E+06 NP-239 2.550E+03 1.830E+02 1.290E+02 0.000E+00 5.300E+02 0.000E+00 1.360E+07

Offsite Dose Calculation Manual Page 265 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS INFANT (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gttract THIS PATHWAY IS NOT APPLICABLE TABLE INTENTIONALLY LEFT BLANK

Offsite Dose Calculation Manual Page 266 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS ADULT (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract THIS PATHWAY IS NOT APPLICABLE TABLE INTENTIONALLY LEFT BLANK

Offsite Dose Calculation Manual Page 267 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS TEEN (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gttract H-3 0.000E+00 0.000E+00 0.OOOE+00 O.OOOE+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 O.000E+00 0.000E+00 0.OOOE+0O 0.000E+00 0.000E+00 0.000E+00 NA-24 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 MN-54 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 MN-56 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 FE-55 0.000E4-00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 CO-58 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 CO-60 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 NI-63 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970Et05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 - 2.970E+05 CU-64 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 ZN-65 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 BR-83 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 0.0002E00 0.OOOE+00 0.000E+00 RB-86 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 RB-88 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 RB-89 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.190E+06 2.1901+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 Y-90 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 Y-91M 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 Y-91 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 "Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 Y-93 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 ZR-95 2.480E208 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 ZR-97 2.940E+08 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 NB-95 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08

Offsite Dose Calculation Manual Page 268 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS TEEN (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract MO-99 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 TC-99M 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 RU-103 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 RU-106 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.O00E+00 0.000E+00 0.0002+00 0.OOOE+00 0.000E+00 AG-110M 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E209 3.470E+09 3.470E+09 SB-122 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 TE-127M 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 TE-1 27 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000+E03 3.000E+03 TE-129M 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 TE-129 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 TE-131"M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 TE-131 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 TE-132 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 1-130 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 1-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1-132 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1-133 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 1-134 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 1-135 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 CS-134 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 CS-136 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 CS-137 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 BA-141 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4A90E+04

Offsite Dose Calculation Manual Page 269 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS TEEN (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract LA-140 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 LA-142 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 CE-141 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 CE-143 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 ND-147 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 EU-154 2.700E+10 2.700E+10 2.700E+10 2.700E+10 2.700E+10 2.700E+10 2.700E+10 EU-155 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 W-187 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06

Offsite Dose Calculation Manual Page 270 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS CHILD (m2*m rem/yr per uCVsec)

Nuelide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 0.OO0E+00 0.000E+00 0.000E+00 0.002E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 P-32 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.580E+06 4.680E+06 MN-54 1.340E+09 1.340E+09 1.340E+09 1.340E=+09 1.340E+09 1.340E+09 1.340E+09 MN-56 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 FE-55 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 FE-59 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 CO-58 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 CO-60 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05- 2.970E+05 2.970E+05 CU-64 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 ZN-65 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 ZN-69 0.OOOE+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.980E+06 8.980E+06 8.980E+06 8.980E÷06 8.980E+06 8.980E+06 8.980E+06 RB-88 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 RB-89 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E÷00 0.000E+00 0.OOOE+00 0.000E+00 SR-91 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 Y-90 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 Y-91M 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 Y-91 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 Y-93 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 ZR-95 2,480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 ZR-97 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 NB-95 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08

Offsite Dose Calculation Manual Page 271 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS CHILD (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung GItract MO-99 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 TC-99M 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 RU-103 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 RU-105 6.360E+05 6,360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 RU-106 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 RH- 103M 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 AG-110M 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 SB-122 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.5502+06 1.550E+06 TE-127M 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 TE-127 3.000E+03 3.OOOE+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 _ 3.000E+03 TE-129M 2.000E+07 2.0002+07 2.0002+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 TE-129 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 TE-131 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 TE-132 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 1-130 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 1-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1-132 1.240E+06 1.240E+06 1,240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1-133 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 1-134 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 1-135 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 CS-134 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750*+09 CS-136 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 CS-137 1.040E+1 0 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 BA-141 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 LA-140 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 LA-142 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05

Offsite Dose Calculation Manual Page 272 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS CHILD (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Thbdy Thyroid Kidney Lung Gitract CE-141 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 CE-143 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.9502+07 6.950E+07 PR-143 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 ND-147 8A00E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 EU-154 2.700E+10 2.700E+10 2.700E+10 2.700E+10 2.7002+10 2.700E+10 2.700E+10 EU-1 55 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 W-187 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06

Offsite Dose Calculation Manual Page 273 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS INFANT (m2*mremlyr per uCil/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gltract H-3 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.21 0E+07 1.210E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 MN-54 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 MN-56 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 FE-59 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 CO-58 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 CO-60 2.160E+10 2.160E+10 2.160E+10 2.180E+10 2.160E+10 2.160E+10 2.160E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 CU-64 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 ZN-65 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7o450E+08 7.450E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.0002+00 RB-86 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 RB-88 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E404 3.290E+04 3.290E+04 RB-89 1.210E+05 1.210E+05 1.21 OE+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 SR-90 0.000E+00 O.O00E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 SR-91 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 Y-90 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 Y-91M 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.0102+05 1.010E+05 1.010E+05 Y-91 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 Y-93 1.850E+05 1.850E+05 1.850E+05 1.850E÷05 1.850E+05 1.850E+05 1.850E+05 ZR-95 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 ZR-97 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06

Offsite Dose Calculation Manual Page 274 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS INFANT (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver "Tbody Thyroid Kidney Lung Gitract NB-95 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 MO-99 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 TC-99M 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 RU-103 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 RU-106 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 SB-122 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 TE-127M 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 TE-127 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000-+03 3.000E+03 TE-129M 2.OOOE+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000+E07 2.000E+07 TE-1 29 2.600E+04 2.600E+04 2,600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 TE-131 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 TE-132 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 1-130 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 1-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1-132 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1-133 2.470E+06 2.470E+06 2.470E+05 2.470E+06 2.470E+06 2.470E+06 2.470E+06 1-134 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 1-135 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+08 2.560E+06 2.560E+06 CS-134 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 CS-136 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 CS-137 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 CS-1 38 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.5901+05 BA-1 39 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 BA-141 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04

Offsite Dose Calculation Manual Page 275 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS INFANT (m2*mremfyr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract LA-140 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 LA-142 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 CE-141 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1,360E+07 1.360E+07 1.360E+07 CE-143 2.320E+06 2.320E+06 2.320E+06 2.3202+06 2.320E+06 2.320E+06 2.320E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.OOOE+00 0.0002+00 0.0001+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 ND-147 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 EU-154 2.700E+10 2.700E+10 2.700E+10 2.700E+10 2.700E+10 2.700E+10 2.700E+10 EU-1 55 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 W-187 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06

Offsite Dose Calculation Manual Page 276 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS ADULT (mrem/yr per uCi/m 3)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 C-14 1.820E+04 3.410E+03 3.410E+03 3.410E+03 3.410E+03 3.410E+03 3.410E+03 NA-24 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 P-32 1.320E+06 7.710E+04 5.010E+04 0.000E+00 0.000E+00 0.000+E00 8.640E+04 CR-51 0.OOOE+00 0.000E+00 1.000E+02 5.950E+01 2.280E+01 1.440E+04 3.320E+03 MN-54 0.000E+00 3.960E+04 6.300E+03 0.000E+00 9.840E+03 1.400E+06 7.740E+04 MN-56 0.000E+00 1.240E+00 1.830E-01 0.000E+00 1.300E+00 9.440E+03 2.020E+04 FE-55 2.460E+04 1.700E+04 3.940E+03 0.0002+00 0.000E+00 7.210E+04 6.030E+03 FE-59 1.180E+04 2.780E+04 1.060E+04 0.000E+00 0.OOOE+00 1.020E+06 1.880E+05 CO-57 0.000E+00 6.920E+02 6.710E+02 0.000E+00 0.000E+00 3.700E+05 3.140E+04 CO-58 0.000E+00 1.580E+03 2.070E+03 0,000E+00 0.000E+00 9.280E+05 1.060E+05 CO-60 0.000E+00 1.150E+04 1.480E+04 0.000E+00 0.000E+00 5.970E+06 2.850E+05 NI-63 4.320E+05 3.140E+04 1.450E+04 0.000E+00 0.000E+00 1.780E+05 1.340E+04 NI-65 1.540E+00 2.100E-01 9.120E-02 0.000E+00 0.000E+00 5.600E+03 1.230E+04 CU-64 0.000E+00 1.460E+00 6.150E-01 0.000E+00 4.620E+00 6.780E+03 4.900E+04 ZN-65 3.240E+04 1.030E+05 4.660E+04 0.000E+00 6.900E+04 8.640E+05 5.340E+04 ZN-69 3.380E-02 6.510E-02 4.520E-03 0.000E+00 4.220E-02 9.200E+02 1.630E+01 BR-82 0.000E+00 0.000E+00 1.350E+04 0.000E+00 0.000E+00 0.000E+00 1.040E+04 BR-83 0.000E+00 0.000E+00 2.410E+02 0.000E+00 0.000E+00 0.OOOE+00 2.320E+02 BR-84 0.000E+00 0.000E+00 3.130E+02 0.0002+00 0.000E+00 0.000E+00 1.640E-03 BR-85 0.000E+00 0.000E+00 1.280E+01 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 RB-86 0.000E+00 1.350E+05 5.900E+04 0.000E+00 0.000E+00 0.000E+00 1.660E+04 RB-88 0.000E+00 3.870E+02 1.930E+02 0.0002+00 0.000E+00 0.000E+00 3.340E-09 RB-89 0.000E+00 2.560E+02 1.700E+02 0.000E+00 0.000-+00 0.000E+00 0.000E+00 SR-89 3.040E+05 0.OOOE+00 8.720E+03 0.000E+00 0.000E+00 1.400E+06 3.500E+05 SR-90 9.920E+07 0.000E+00 6.100E+06 0.000E+00 0.000E+00 9.600E+06 7.220E+05 SR-91 6.190E+01 0.000E+00 2.500E+00 0.000E+00 0.000E+00 3.650E+04 1.910E+05 SR-92 6.740E+00 0.000E+00 2.910E-01 0.000E+00 0.000E+00 1.650E+04 4.300E+04 Y-90 2.090E+03 0.000E+00 5.610E+01 0.000E+00 0.000E+00 1.700E+05 5.060E+05 Y-91M 2.61 0E-01 0.000E+00 1.020E-02 0.000E+00 0.000E+00 1.920E+03 1.330E+00 Y-91 4.620E+05 0.000E+00 1.240E+04 0.000E+00 0.000E+00 1.700E+06 3.850E+05 Y-92 1.030E+01 0.000E+00 3.020E-01 0.000E+00 0.000E+00 1.570E+04 7.350E+04 Y-93 9.440E+01 0.000E+00 2.610E+00 0.000E+00 0.000E+00 4.850E+04 4.220E+05

Offsite Dose Calculation Manual Page 277 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS ADULT (mrem/yr per uCilm 3)

Nucilde Bone Liver Thody Thyroid Kidney Lung GItract ZR-95 1.070E+05 3.440E+04 2.330E+04 0.000E+00 5.420E+04 1.770E+06 1.500E+05 ZR-97 9.680E+01 1.960E+01 9.040E+00 0.000E+00 2.970E+01 7.870E+04 5.230E+05 NB-95 1.410E+04 7.820E+03 4.210E+03 0.000E+00 7.740E+03 5.050E+05 1.040E+05 NB-97 2.220E-01 5.620E-02 2.050E-02 0.000E+00 6.540E-02 2.400E+03 2.420E+02 MO-99 0.000E+00 1.210E+02 2.300E+01 0.000E+00 2.910E+02 9.120E+04 2.480E+05 TC-99M 1,030E-03 2.910E-03 3.700E-02 0.000E+00 4.420E-02 7.640E+02 4.160E+03 TC-101 4.180E-05 6.020E-05 5.900E-04 0.000E+00 1.080E-03 3.990E+02 0.000E+00 RU-103 1.530E+03 0.000E+00 6.580E+02 0.000E+00 5.830E+03 5.050E+05 1.100E+05 RU-105 7.900E-01 0.000E+00 3.110E-01 0.000E+00 1.020E+00 1.100E+04 4,820E+04 RU-106 6.910E+04 0.000E+00 8.720E+03 O.O00E+00 1.340E+05 9.360E+06 9.120E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 O.O00E+00 0.000E+00 0.000E+00 0.000E+00 RH-1 06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.O00E+00 O.O00E+00 AG-110M 1.080E+04 1.000E+04 5.940E+03 0.000E+00 1.970E+04 4.630E+06 3.020E+05 SB-122 3.100E+03 4.110E+03 4.110E+04 1.070E+03 1.550E+03 1.670E+05 2.020E+05 SB-124 3.120E+04 5.890E+02 1.240E+04 7.550E+01 0.000E+00 2.480E+06 4.060E+05 SB-125 5.340E+04 5.950E+02 1.260E+04 5.400E+01 0.000E+00 1.740E+06 1.010E+05 TE-125M 3.420E+03 1.580E+03 4.670E+02 1.050E+03 1.240E+04 3.140E+05 7.060E+04 TE-127M 1.260E+04 5.770E+03 1.570E+03 3.290E+03 4.580E+04 9.600E+05 1.500E+05 TE-127 1.400E+00 6.420E-01 3.100E-01 1.060E+00 5.100E+00 6.510E+03 5.740E+04 TE-129M 9.760E+03 4.670E+03 1.580E+03 3.440E+03 3.660E+04 1.160E+06 3,830E+05 TE-129 4.980E-02 2.390E-02 1.240E-02 3.900E-02 1.870E-01 1.940E+03 1.570E+02 TE-131 M 6.990E+01 4.360E+01 2.900E+01 5.500E+01 3.090E+02 1460E+05 5.560E+05 TE-131 1.110E-02 5.950E-03 3.590E-03 9.360E-03 4.370E-02 1.390E+03 1.840E+01 TE-132 2.600E+02 2.150E+02 1.620E+02 1.900E+02 1.460E+03 2.880E+05 5.100E+05 1-130 4.580E+03 1.340E+04 5.280E+03 1.140E+06 2.090E+04 7.690E+03 0.000E+00 1-131 2.520E+04 3.580E+04 2.050E+04 1.190E+07 6.130E+04 0.000E+00 6.280E+03 1-132 1.160E+03 3.260E+03 1.160E+03 1.140E+05 5.180E+03 0.000E+00 4.060E+02 1-133 8.640E+03 1.480E+04 4.520E+03 2.150E+06 2.580E+04 0.000E+00 8.880E+03 1-134 6.440E+02 1.730E+03 6.150E+02 2.980E+04 2750E+03 0.000E+00 1.010E+00 1-135 2.680E+03 6.980E+03 2.570E+03 4.480E+05 1.110E+04 0.000E+00 5.250E+03 CS-1 34 3.730E+05 8.480E+05 7.280E+05 0.000E+00 2.870E+05 9.760E+04 1.040E+04 CS-136 3.900E+04 1.460E+05 1.100E+05 0.000E+00 8.560E+04 1.200E+04 1.170E+04 GS-137 4.780E+05 6.210E+05 4.280E+05 0.000E+00 2.220E+05 7.520E+04 8.400E+03 CS-138 3.31 0E+02 6.210E+02 3.240E+02 0.000E+00 4.800E+02 4.860E+01 1.860E-03

Offsite Dose Calculation Manual Page 278 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS ADULT (mrem/yr per uCims3)

Nucilde Bone Liver Thody Thyroid Kidney Lung Gitract BA-139 9.360E-01 6.660E-04 2.740E-02 0.000E+00 6.220E-04 3.760E+03 8.960E+02 BA-140 3.900E+04 4.900E+01 2.570E+03 0.000E+00 1.670E+01 1.270E+06 2.180E+05 BA-141 1.000E-01 7.530E-05 3.30E2-03 0.000E+00 7.OOOE-05 1.940E+03 1.160E-07 BA-142 2.630E-02 2.700E-05 1.660E-03 0.0002+00 2.290E-05 1.190E+03 0.000E+00 LA-140 3.440E+02 1.740E+02 4.580E+01 0.000E+00 0.000E+00 1.360E+05 4.580E+05 LA-142 6.830E-01 3.100E-01 7.720E-02 0.000E+00 0.000E+00 6.330E+03 2.110E+03 CE-141 1.990E+04 1.350E+04 1.530E+03 0.000E+00 6.260E+03 3.620E+05 1.200E+05 CE-143 1.860E+02 1.380E+02 1.530E+01 0.000E+00 6.080E+01 7.980E+04 2.260E+05 CE-144 3.430E+06 1.430E+06 1.840E+05 0.000E+00 8.480E+05 7.780E+06 8.160E+05 PR-143 9.360E+03 3.750E+03 4.640E+02 0.000E+00 2.160E+03 2.810E+05 2.000E+05 PR-144 3.010E-02 1.250E-02 1.530E-03 0.000E+00 7.050E-03 1.020E+03 2.150E-08 ND-147 5.270E+03 6.100E+03 3.650E+02 0.000E+00 3.560E+03 2.2102+05 1.730E+05 EU-154 5.920E+06 7.280E+05 5.180E+05 0.000E+00 3.490E_+06 4.670E+06 2.720E+05 EU-155 8.080E+05 1.140E+05 7.370E+04 0.000E+00 5.270E+05 7.570E+05 4.760E+04 W-187 8.480E+00 7.080E+00 2.480E+00 0.000E+00 0.000E+00 2.900E+04 1.550E+05 NP-239 2.300E+02 2.260E+01 1.240E+01 O.000E+00 7.000E+01 3.760E+04 1.190E+05

Offsite Dose Calculation Manual Page 279 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS TEEN (mrem/yr per uCiim 3)

Nuclide Bone Liver "Thody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.2702E03 1.270E+03 1.270E+03 1.270E+03 1.270E+03 1.270E+03 C-14 2.600E+04 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 NA-24 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 P-32 1.890E+06 1.100E+05 7.160E+04 O.000E+00 0.000E+00 0.000E+00 9.280E+04 CR-51 0.000E+00 0.000E+00 1.350E+02 7.500E+01 3.070E+01 2.100E+04 3.000E+03 MN-54 0.000E+00 5.110E+04 8.400E+03 0.000E+00 1.270E+04 1.980E+06 6.680E+04 MN-56 0.000E+00 1.700E+00 2.520E-01 O.O00E+00 1.790E+00 1.520E+04 5.740E+04 FE-55 3.340E+04 2.380E+04 5.540E+03 0.000E+00 0.000E+00 1.240E+05 6.390E+03 FE-59 1.590E+04 3.700E+04 1.430E+04 0.000E+00 0.000E+00 1.530E+06 1.780E+05 CO-57 0.000E+00 6.920E+02 9.200E+02 0.000E+00 0.000E+00 5.860E+05 3.140E+04 CO-58 0.000E+00 2.070E+03 2.780E+03 O.000E+00 O.O00E+00 1.340E+06 9.520E+04 CO-60 0.000E+00 1.510E+04 1.980E+04 0.000E+00 0.000E+00 8.720E+06 2.590E+05 NI-63 5.800E+05 4.340E+04 1.980E+04 0.000E+00 0.000E+00 3.070E+-05 1.420E+04 NI-65 2.180E+00 2.930E-01 1.270E-01 0.000E+00 0.000E+00 9.360E+03 3.670E+04 CU-64 0.000E+00 2.030E+00 8.480E-01 0.000E+00 6.410E+00 1.110E+04 6.140E+04 ZN-65 3.860E+04 1.340E+05 6.240E+04 0.000E+00 8.640E+04 1.240E+06 4.660E+04 ZN-69 4.830E-02 9.200E-02 6.460E-03 0.000E+00 6.020E-02 1.580E+03 2.850E+02 BR-82 0.000E+00 0.OOOE+00 1.820E+04 0.000E+00 0.000E+00 0.000E+00 0.000+E00 BR-83 0.000E+00 0.000E+00 3.440E+02 0.000E+00 0.000E+00 0.000E+00 OO00E+D0 BR-84 0,000E+00 0.000E+00 4.330E+02 O.000E+00 0.000E+00 O.O00E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 1.830E+01 O.OOOE+00 O,O00E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.900E+05 8.400E+04 0.000E+00 0.000E+00 0.000E+00 1.770E+04 RB-88 0.000E+00 5.460E+02 2.720E+02 0.000E+00 0.000E+00 0.000E+00 2.920E-05 RB-89 0.000E+00 3&520E+02 2.330E+02 0.000E+00 0.000E+00 0.000E+00 3.380E-07 SR-89 4.340E+05 0.000E+00 1.250E+04 0.000E+00 0.000E+00 2.420E+06 3.710E+05 SR-90 1.080E+08 0.000E+00 6.680E+06 0.000E+00 O.000E+00 1.650E+07 7.650E+05 SR-91 8.800E+01 0.000OE+00 3.510E+00 0.000E+00 0.000E+00 6.070E+04 2.590E+05 SR-92 9.520E+00 0.OOOE+00 4.060E-01 0.000E+00 0.000E+00 2.740E+04 1.190E+05 Y-90 2.980E+03 0.000E+00 8.000E+01 0.000E+00 0.000E+00 2.930E+05 5.590E+05 Y-91M 3.700E-01 0.000E+00 1.420E-02 0.000E+00 0.000E+00 3.200E+03 3.020E+01 Y-91 6.610E+05 0.000E+00 1.770E+04 0.000E+00 0.000E+00 2.940E+06 4.090E+05 Y-92 1.470E+01 0.000E+00 4.290E-01 0.000E+00 0.000E+00 2.680E+04 1.650E+05 Y-93 1.350E+02 0.0OE+00 3.720E+00 0.OOOE+00 0.000E+00 8.320E+04 5.790E+05

Offsite Dose Calculation Manual Page 280 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS TEEN (mrem/yr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract ZR-95 1.460E+05 4.580E+04 3.150E+04 0.000E+00 6.740E+04 2.690E+06 1.490E+05 ZR-97 1.380E+02 2.720E+01 1.260E+01 O.O00E+00 4.120E+01 1.300E+05 6.300E+05 NB-95 1.860E+04 1.030E+04 5.660E+03 O.O00E+00 1.000E+04 7.510E+05 9.680E+04 NB-97 3.140E-01 7.780E-02 2.840E-02 O.O00E+00 9.1202-02 3.930E+03 2.170E+03 MO-99 0.000E+00 1.690E+02 3.220E+01 O.O00E+00 4.110E+02 1.540E+05 2.690E+05 TC-99M 1.380E-03 3.860E-03 4.990E-02 0.000E+00 5.760E-02 1.150E+03 S.130E+03 TC-101 5.920E-05 8.400E-05 8.240E-04 0.000E+00 1.520E-03 6.670E+02 8.720E-07 RU-103 2.100E+03 0.000E+00 8.960E+02 O.O00E+00 7.430E+03 7.830E+05 1.090E+05 RU-105 1.120E+00 O.O00E+00 4.340E-01 0.000+E00 1.410E+00 1.820E+04 9.040E+04 RU-106 9.840E+04 0.000E+00 1.240E+04 0.000E+00 1.900E+05 1.610E+07 9.600E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 AG-110M 1.380E+04 1.310E+04 7.990E+03 0.000E+00 2.500E+04 6.750E+06 2.730E+05 SB-122 3.100E+03 4.110E+03 4.10OE+04 1.070E+03 1.550E+03 1.670E+05 2.020E+05 SB-124 4.300E+04 7.940E+02 1.680E+04 9.760E+01 0.000E+00 3.850E+06 3.980E+05 SB-125 7.380E+04 8.080E+02 1.720E+04 7.040E+01 0.000E+00 2.740E+06 9.920E+04 TE-125M 4.880E+03 2.240E+03 6.6702+02 1.400E+03 0.000E+00 5.360E+05 7.500E+04 TE-127M 1.800E+04 8.160E+03 2.180E+03 4.380E+03 6.540E+04 1.660E+06 1.590E+05 TE-127 2.010E+00 9.120E-01 4.420E-01 1.420E+00 7.280E+00 1.120E+04 8.080E+04 TE-129M 1.390E+04 6.580E+03 2.250E+03 4.580E+03 5.10E+04 1.980E+06 4.050E+05 TE-129 7.100E-02 3.380E-02 1.760E-02 5.180E-02 2.660E-01 3.300E+03 1.620E+03 TE-131M 9.840E+01 6.010E+01 4.020E+01 7.250E+01 4.390E+02 2.380E+05 6.210E+05 TE-131 1.580E-02 8.320E-03 5.040E-03 1.240E-02 6.180E-02 2.340E+03 1.510E+01 TE-132 3.600E+02 2.900E+02 2.190E+02 2.460E+02 1.950E+03 4.490E+05 4.630E+05 1-130 6.240E+03 1.790E+04 7.170E+03 1.490E+06 2.750E+04 0.000E+00 9.120E+03 1-131 3.540E+04 4.910E+04 2.640E+04 1.460E+07 8.400E+04 0.OOOE+00 6.490E+03 1-132 1.590E+03 4.380E+03 1.580E+03 1.510E+05 6.920E+03 0.OOOE+00 1.270E+03 1-133 1.220E+04 2.050E+04 6.220E+03 2.920E+06 3.590E+04 0.000E+00 1.030E+04 1-134 8.880E+02 2.320E+03 8.400E+02 3.950E+04 3.660E+03 0.000E+00 2.040E+01 1-135 3.700E+03 9.440E+03 3.490E+03 6.210E+05 1.490E+04 0.000E+00 6.950E+03 CS-134 5.020E+05 1.130E+06 5.490E+05 0.000E+00 3.750E+05 1.460E+05 9.760E+03 CS-136 5.150E+04 1.940E+05 1.370E+05 0.000E+00 1.100E+05 1.780E+04 1.090E+04 CS-137 6.700E+05 8.480E+05 3.110E+05 0.000E+00 3.040E+05 1.210E+05 8.480E+03 CS-138 4.660E+02 8.560E+02 4.460E+02 0.000E+00 6.620E+02 7.870E+01 2.700E-01

Offsite Dose Calculation Manual Page 281 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS TEEN (mrem/yr per uCim 3 )

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract BA-139 1.340E+00 9.440E-04 3.900E-02 0.000E+00 8.880E-04 6.460E+03 6.450E+03 BA-140 5.470E+04 6.700E+01 3.520E+03 0.000E+00 2.280E+01 2.030E+06 2.290E+05 BA-141 1.420E-01 1.060E-04 4.740E-03 0.000E+00 9.840E-05 3.290E+03 7.460E-04 BA-142 3.7002-02 3.700E-05 2.270E-03 0.000E÷00 3.140E-05 1.910E+03 O.OOOE+00 LA-140 4.790E+02 2.360E+02 6.260E+01 0.000+E00 0.OOOE+00 2.140E+05 4.870E+05 LA-142 9.600E-01 4.250E-01 1.060E-01 0.000E+00 0.000E+00 1.020E+04 1.200E+04 CE-141 2.840E+04 1.900E+04 2.170E+03 0.000E+00 8.880E+03 6.140E+05 1.260E+05 CE-143 2.660E+02 1.940E202 2.160E+01 0.000E+00 8.640E+01 1.300E+05 2.550E+05 CE-144 4.890E+-6 2.020E+06 2.620E+05 0.000+E00 1.210E+06 1.340E+07 8.640E+05 PR-143 1.340E+04 5.310E+03 6.620E+02 0.000E+00 3.090E+03 4.830E+05 2.140E+05 PR-144 4.300E-02 1.760E-02 2.180E-03 0.OOOE+00 1.010E-02 1.750E+03 2,350E-04 ND-147 7.860E+03 8.560E+03 5.130E+02 0.000E+00 5.020E+03 3.720E+05 1.820E+05 EU-154 7.540E+06 9.840E+05 6.880E+05 O.000E+00 4.350E+06 7.300E+06 2.670E+05 EU-155 1.600E+06 1.570E+05 9.680E+04 0.000E+00 6.120E+05 1.210E+07 4.780E+05 W-187 1.200E+01 9.760E+00 3.430E+00 0.000E+00 0.000E+00 4.740E+04 1.770E+05 NP-239 3.380E+02 3.190E+01 1.770E+01 0.000E+00 1.000E+02 6.490E+04 1.320E+05

Offsite Dose Calculation Manual Page 282 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS CHILD (mrem/yr per uCi/m 3)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 C-14 3.590E+04 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 NA-24 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 P-32 2.600E+06 1.140E+05 9.880E+04 0.OOOE+00 0.000E+00 0.000E+00 4.220E+04 CR-51 0.000E+00 0.000E+00 1.540E+02 8.550E+01 2.430E+01 1.700E+04 1.080E+03 MN-54 0.000E+00 4.290E+04 9.510E+03 0.000E+00 1.000E+04 1.580E+06 2.290E+04 MN-56 0.000E+00 1.660E+00 3.120E-01 0.000E+00 1.670E÷00 1.310E+04 1.230E+05 FE-55 4.740E+04 2.520E+04 7.770E+03 0.0002+00 0.000E+00 1.110E+05 2.870E+03 FE-59 2.070E+04 3.340E+04 1.670E+04 0.000E+00 0.000E+00 1.270E+06 7.070E+04 CO-57 0.000E+00 9.030E+02 1.070E+03 0.000E+00 0.0002+00 5.070E+05 1.320E+04 CO-58 0.000E+00 1.770E+03 3.1602+03 0.000E+00 0.000E+00 1.110E+06 3.440E+04 CO-60 0.000E+00 1.310E+04 2.260E+04 0.0002+00 0.000E+00 7.070E+06 9.620E+04 NI-63_ 8.21 0E+05 4.630E+04 2.800E+04 0.000E+00 - 0.000E+00 2.750E+05 6.330E+03 NI-65 2.990E+00 2.960E-01 1.640E-01 0.000E+00 0.000E+00 8.180E+03 8.400E+04 CU-64 0.000E+00 1.990E+00 1.070E+00 0.000E+00 6.030E+00 9.580E+03 .3.670E+04 ZN-65 4.260E+04 1.130E+05 7.030E+04 0.000E+00 7.140E+04 9.950E+05 1.630E+04 ZN-69 6.700E-02 9.660E-02 8.920E-03 0.000E+00 5.850E-02 1.420E+03 9.510E+03 BR-82 0.OOOE+00 0.000E+00 2.090E+04 0.000E+00 0.000E+00 0.000+E00 0.OOOE+00 BR-83 0.000E+00 0.OOOE+00 4.740E+02 0.000E+00 0.OOOE+00 0.0002+00 0.000E+00 BR-84 0.000E+00 0.000E+00 5.480E+02 0.000E+00 0.000E+00 0.000E+00 0.0002+00 BR-85 0.000E+00 0.000E+00 2.530E+01 0.000E+00 0.000E+00 0.0002+00 0.000E+00 RB-86 0.OOOE+00 1.980E+05 1.140E+05 0.000E+00 0.0002+00 0.000E+00 7.990E+03 RB-88 0.OOOE+00 5.620E+02 3.660E+02 0.000E+00 0.000E+00 0.000E+00 1.720E+01 RB-89 0.000E+00 3.450E+02 2.900E+02 0.000E+00 0.000E+00 0,000E+00 1.890E+00 SR-89 5.990E+05 0.000E+00 1.720E+04 0.000E+00 0.000E+00 2.160E+06 1.670E+05 SR-90 1.010E+08 0.OOOE+00 6.440E+06 O.000E+00 0.000E+00 1.480E+07 3.430E+05 SR-91 1.210E+02 0.000E+00 4.590E+00 0.000E+00 0.000E+00 5.330E+04 1.740E+05 SR-92 1.310E+01 0.000E+00 5.250E-01 0.000E+00 0.000E+00 2.400E+04 2.420E+05 Y-90 4.110E+03 0.OOOE+00 1.110E+02 0.000E+00 0.000E+00 2.620E+05 2.680E+05 Y-91M 5.070E-01 0.000E+00 1.840E-02 0.000E+00 0.000E+00 2.810E+03 1.720E+03 Y-91 9.140E+05 0.000E+00 2.440E+04 0.000E+00 0.000E+00 2.630E+06 1.840E+05 Y-92 2.040E+01 0.000E+00 5.810E-01 0.000E+00 0.000E+00 2.390E+04 2.390E+05 Y-93 1.860E+02 0.000E+00 5.110E+00 0.000+E00 0.000E+00 7.440E+04 3.890E+05 ZR-95 1.900E+05 4.180E+04 3.700E+04 0.000E+00 5.960E+04 2.230E+06 6.110E+04

Offsite Dose Calculation Manual Page 283 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS CHILD (mrem/yr per uCVm 3)

Nuclide Bone Uver Thody Thyroid Kidney Lung Gitract ZR-97 1.880E+02 2.720E+01 1.600E+01 0.000E+00 3.890E+01 1.130E+05 3.510E+05 NB-95 2.350E+04 9.180E+03 6.550E+03 0.000E+00 8.620E+03 6.140E+05 3.700E+04 NB-97 4.290E-01 7.700E-02 3.600E-02 0.000E+00 8.550E-02 3.420E+03 2.780E+04 MO-99 0.000E+00 1.720E+02 4.260E+01 0.000E+00 3.920E+02 1.350E+05 1.270E+05 TC-99M 1.780E-03 3.480E-03 5.770E-02 0.000E+00 5.070E-02 9.510E+02 4.810E+03 TC-101 8.100E-05 8.510E-05 1.080E-03 0.000E+00 1.450E-03 5.850E+02 1.630E+01 RU-103 2.790E+03 0.000E+00 1.070E+03 0.000E+00 7.030E+03 6.620E+05 4.480E+04 RU-105 1.530E+00 0.000E+00 5.550E-01 0.0002+00 1.340E+00 1.590E+04 9.950E+04 RU-106 1.360E+05 0.000E+00 1.690E+04 0.000E+00 1.840E+05 1.430E+07 4.290E+05 RH-103M 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000+E00 0.000E+00 0.000+E00 0.000E+00 0.OOE+00 0.OOOE+00 AG-11OM 1.690E+04 1.140E+04 9.140E+03 0.000E+00 2.120E+04 5.480E+06 1.000E+05 SB-122 1.440E+03 1.980E+03 1.900E+04 4.960E+02 7.180E+02 - 7.730E+04 9.360E+04 SB-124 5.740E+04 7.400E+02 2.000E+04 1.260E+02 0.000E+00 3.240E+06 1.640E+05 SB-125 9.840E+04 7.590E+02 2.070E+04 9.100E+01 0.000E+00 2.320E+06 4.030E+04 TE-125M 6.730E+03 2.330E+03 9.140E+02 1.920E+03 0.000E+00 4.770E+05 3.380E+04 TE-127M 2.490E+04 8.550E+03 3.020E+03 6.070E+03 6.360E+04 1.480E+06 7,140E+04 TE-127 2.770E+00 9.510E-01 6.110E-01 1.960E+00 7.070E+00 1.000E+04 5.620E+04 TE-129M 1.920E+04 6.850E+03 3.040E+03 6.330E+03 5.030E+04 1.760E+06 1.820E+05 TE-129 9.770E-02 3.500E-02 2.380E-02 7.140E-02 2.570E-01 2.930E+03 2.550E+04 TE-131M 1.340E+02 5.920E+01 5.070E+01 9.770E+01 4.000E+02 2.060E+05 3.080E+05 TE-131 2.170E-02 8.440E-03 6.590E-03 1.700E-02 5.880E-02 2.050E+03 1.330E+03 TE-132 4.8102+02 2.720E+02 2.630E+02 3.170E+02 1.840E+03 3.770E+05 1.380E+05 1-130 8.180E+03 1.640E+04 8.440E+03 1.850E+06 2.450E+04 0.000E+00 5.110E+03 1-131 4.810E+04 4.810E+04 2.730E+04 1.620E+07 7.880E+04 0.0002E00 2.840E+03 1-132 2.120E+03 4.070E+03 1.880E+03 1.940E+05 6.250E+03 0.0002E00 3.200E+03 1-133 1.660E+04 2.030E+04 7.700E+03 3.850E+06 3.380E+04 0.000E+00 5.480E+03 1-134 1.170E+03 2.160E+03 9.950E+02 5.0702+04 3.300E+03 0.000E+00 9.550E+02 1-135 4.920E+03 8.730E+03 4.140E+03 7.920E+05 1.340E+04 0.000+E00 4.440E+03 CS-134 6.510E+05 1.010E+06 2.250E+05 0.000E+00 3.300E+05 1.210E+05 3.850E+03 CS-136 6.510E+04 1.710E+05 1.160E+05 0.000E+00 9.550E+04 1.450E+04 4.180E+03 CS-137 9.070E+05 8.250E+05 1.280E+05 0.000E+00 2.820E+05 1.040E+05 3.620E+03 CS-138 6.330E+02 8.400E+02 5.550E+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02

Offsite Dose Calculation Manual Revision 5 Offste MaualPaaeDse alcuatin 284 of 325 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS CHILD (mrem/yr per uCi'm 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Getract BA-139 1.840E+00 9.840E-04 5.370E-02 0.000E+00 8.620E-04 5.770E+03 5.770E+04 BA-140 7.400E+04 6.480E+01 4.330E+03 0.000E+00 2.110E+01 1.740E+06 1.020E+05 BA-141 1.960E-01 1.090E-04 6.360E-03 0.000E+00 9.470E-05 2.920E+03 2.750E+02 BA-142 5.OOOE-02 3.600E-05 2.790E-03 0.000E+00 2,910E-05 1.640E+03 2.740E+00 LA-140 6.440E+02 2.250E+02 7.550E+01 0.000E+00 0.000E+00 1.830E+05 2.260E+05 LA-142 1.300E+00 4.110E-01 1.290E-01 0.000E+00 0,000E+00 8.700E+03 7.590E+04 CE-141 3.920E+04 1.950E+04 2.900E+03 0.OOOE+00 8.550E+03 5.440E+05 5.6602+04 CE-143 3.660E+02 1.990E+02 2.870E+01 0.000E+00 8.360E+01 1.150E+05 1.270E+05 CE-144 6.770E+06 2.120E+06 3.610E+05 0.000=+00 1.170E+06 1.200E+07 3.890E+05 PR-143 1.850E+04 5.550E+03 9.140E+02 0.000E+00 3.000E+03 4.330E+05 9.730E+04 PR-144 5.960E-02 1.850E-02 3.000E-03 0.000E+00 9.770E-03 1.570E+03 1.970E+02 ND-147 1.080E+04 8.730E+03 6.810E+02 0.000E+00 4.810E+03 3.280E+05 8.210E+04 EU-154 1.010E+07 9.210E+05 8.400E+05 0.000E+00 4.030E+06 6.140E+06 - 1.100E+05 EU-155 2.070E+06 1.500E+05 1.180E+05 0.000E+00 5.590E+05 1.030E+06 1.990E+05 W-187 1.630E+01 9.660E+00 4.330E+00 0.000E+00 0.000E+00 4.110E+04 9.100E+04 NP-239 4.700E+02 3.340E+01 2.350E+01 0.000E+00 9.730E+01 5.810E+04 6.400E+04

Offsite Dose Calculation Manual Page 285 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS INFANT (mrem/yr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 6.470E+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 C-14 2.650E+04 5.310E+03 5.310E+03 5.310E+03 5.310E+03 5.310E+03 5.310E+03 NA-24 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 P-32 2.030E+06 1.120E+05 7.740E+04 0.000E+00 0.000E+00 0.000E+00 1.610E+04 CR-51 0.000E+00 0.000E+00 8.950E+01 5.750E+01 1.320E+01 1.280E+04 3.570E+02 MN-54 O.000E+00 2.530E+04 4.980E+03 0.000E+00 4.980E+03 1.000E+06 7.060E+03 MN-56 O.000E+00 1.540E+00 2.210E-01 0.000E+00 1.100E+00 1.250E+04 7.170E+04 FE-55 1.970E+04 1.170E+04 3.330E+03 0.000E+00 0.000E+00 8.690E+04 1.090E+03 FE-59 1.360E+04 2.350E+04 9.480E+03 0.000E+00 0.000+E00 1.020E+06 2.480E+04 CO-57 0.000E+00 6.510E+02 6.410E+02 0.000E+00 0.000E+00 3.790E+05 4.860E+03 CO-58 0.000E+00 1.220E+03 1.820E+03 0.000E+00 0.000E+00 7.770E+05 1.110E+04 CO-60 0.000E+00 8.020E+03 1.180E+04 O.000E+00 0.000E+00 4.510E+06 3.190E+04 NI-63 3.390E+05 2.040E+04 1.160E+0D4 0.000E+00 0.000E+00 2.090E+05 2.420E+03 NI-65 2.390E+00 2-8402-01 1.230E-01 0.0002+00 0.000E+00 8.120E+03 5.010E+04 CU-64 0.000E+00 1.880E+00 7.740E-01 0.000E+00 3.980E+00 9.300E+03 1.500E+04 ZN-65 1.930E+04 6.260E+04 3.110E+04 0.0002+00 3.250E+04 6.470E+05 5.140E+04 ZN-69 5.390E-02 9.670E-02 7.180E-03 0.000E+00 4.020E-02 1.470E+03 1.320E+04 BR-82 0.OOOE+00 0.000E+00 1.330E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 3.810E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 4.000E+02 0.000E+00 0.000E+00 0.000E+00 0.000.E00 BR-85 0.000E+00 0.000E+00 2.040E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.900E+05 8.820E+04 0.000E+00 0.000E+00 0.OOOE+00 3.040E+03 RB-88 0.OOOE+00 5.570E+02 2.870E+02 0.000+E00 0.000E+00 0.000E+00 3.390E+02 RB-89 0.000E+00 3.210E+02 2.060E+02 0.000E+00 0.000E+00 0.000E+00 6.820E+01 SR-89 3.980E+05 0.000E+00 1.140E+04 0.000E+00 0.000E+00 2.030E+06 6.400E+04 SR-90 4.090E+07 0.000E+00 2.590E+06 0.000E+00 0.000E+00 1.120E+07 1.310E+05 SR-91 9.560E+01 0.000E+00 3.460E+00 0.000E+00 0.000E+00 5.260E+04 7.340E+04 SR-92 1.050E+01 0.OOOE+00 3.910E-01 0.0002+00 0.000E+00 2.380E+04 1.400E+05 Y-90 3.290E+03 0.000E+00 8.820E+01 0.OOOE+00 O.000E+00 2.690E+05 1.040E+05 Y-91 M 4.070E-01 0.000E+00 1.390E-02 0.000E+00 0.000E+00 2.790E+03 2.350E+03 Y-91 5.880E+05 0.OOOE+00 1.570E+04 0.000E+00 0.000E+00 2.450E+06 7.030E+04 Y-92 1.640E+01 0.000E+00 4.610E-01 0.000E+00 0.000+E00 2.450E+04 1.270E+05 Y-93 1.500E+02 0.000E+00 4.070E+00 0.000E+00 0.000E+00 7.640E+04 1.670E+05

Offsite Dose Calculation Manual Page 286 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS INFANT 3 (mrem/yr per uCi/m )

Nuclide Bone Liver "Thody Thyroid Kidney Lung Gitract ZR-95 1.150E+05 2.790E+04 2.030E+04 0.000E+00 3.110E+04 1.750E+06 2.170E+04 ZR-97 1.500E+02 2.560E+01 1.170E+01 0.000E+00 2.590E+01 1.100E+05 1.400E+05 NB-95 1.570E+04 6.430E+03 3.780E+03 0.000E+00 4.720E+03 4.790E+05 1.270E+04 NB-97 3.420E-01 7.290E-02 2.630E-02 0.000E+00 5.700E-02 3.320E+03 2.690E+04 MO-99 0.000E+00 1.650E+02 3.230E+01 0.000E+00 2.650E+02 1.350E+05 4.870E+04 TC-99M 1.400E-03 2.880E-03 3.720E-02 O.000E+00 3.110E-02 8.110E+02 2.030E+03 TC-101 6.510E-05 8.230E-05 8.120E-04 0.000E+00 9.790E-04 5.840E+02 8.440E+02 RU-103 2,020E+03 O.000E+00 6.790E+02 0.000E+00 4.240E+03 5.520E+05 1.610E+04 RU- 105 1.220E+00 0.000E+00 4.100E-01 O.000E+00 8.990E-01 1.570E+04 4.840E+04 RU-106 8.680E+04 O.OOOE+00 1.090E+04 0.000E+00 1.070E+05 1.160E+07 1.640E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 9.980E+03 7.220E+03 5.000E+03 0.Q00E+00 1.090E+04 3.670E+06 3.300E+04 SB-122 5.430E+02 7.200E+02 7.200E+03 1.880E+02 2.720E+02 2.930E+04 3.540E+04 SB-124 3.790E+04 5.560E+02 1.200E+04 1.010E+02 0.000E+00 2.650E+06 5.910E+04 SB-125 5.170E+04 4.770E+02 1.090E+04 6.230E+01 0.000E+00 1.640E+06 1.470E+04 TE-125M 4.760E+03 1.990E+03 6.580E+02 1.620E+03 0.000E+00 4.470E+05 1.2g0E+04 TE-127M 1.670E+04 6.900E+03 2.070E+03 4.870E+03 3.750E+04 1.310E+06 2.730E+04 TE-127 2.230E+00 9.530E-01 4.890E-01 1.850E+00 4.860E+00 1.030E+04 2.440E+04 TE-129M 1.410E+04 6.090E+03 2.230E+03 5.470E+03 3.180E+04 1.680E+06 6.900E+04 TE-129 7.880E-02 3.470E-02 1.880E-02 6.750E-02 1.750E-01 3.000E+03 2.630E+04 TE-131M 1.070E+02 5.500E+01 3.630E+01 8.930E+01 2.650E+02 1.990E+05 1.190E+05 TE-131 1.740E-02 8.220E-03 5.000E-03 1.580E-02 3.990E-02 2.060E+03 8.220E+03 TE-132 3.720E+02 2.370E+02 1.760E+02 2.790E+02 1.030E+03 3.400E+05 4.410E+04 1-130 6.360E+03 1.390E+04 5.570E+03 1.600E+06 1.530E+04 0.000E+00 1.990E+03 1-131 3.790E+04 4.440E+04 1.960E+04 1.480E+07 5.180E+04 0.000E+00 1.060E+03 1-132 1.690E+03 3.540E+03 1.260E+03 1.690E+05 3.950E+03 0.000E+00 1.900E+03 1-133 1.320E+04 1.920E+04 5.600E+03 3.560E+06 2.240E+04 0.000E+00 2.160E+03 1-134 9.210E+02 1.880E+03 6.650E+02 4.450E+04 2.090E+03 0.000E+00 1.290E+03 1-135 3.860E+03 7.600E+03 2.770E+03 6.960E+05 8.470E+03 0.000E+00 1.830E+03 CS-134 3.960E+05 7.030E+05 7.4502+04 0.000E+00 1.900E+05 7.970E+04 1.330E+03 CS-136 4.830E+04 1.350E+05 5.290E+04 0.000E+00 5.640E+04 1.180E+04 1.430E+03 CS-137 5.490E+05 6.120E+05 4.550E+04 0.OOOE+00 1.720E+05 7.130E+04 1.330E+03 CS-138 5.050E+02 7.81 0E+02 3.980E+02 0.000E+00 4.100E+02 6.540E+01 8.760E+02

Offsite Dose Calculation Manual Page 287 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS INFANT (mremlyr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 1.480E+00 9.840E-04 4.300E-02 0.000E+00 5.920E-04 5.950E+03 5.100E+04 BA-140 5.600E+04 5.600E+01 2.900E+03 0.000E+00 1.340E+01 1.600E+06 3.840E+04 BA-141 1.570E-01 1.080E-04 4.970E-03 0.0002+00 6.500E-05 2.970E+03 4.750E+03 BA-142 3.980E-02 3.300E-05 1.960E-03 0.000E+00 1.900E-05 1.550E+03 6.930E+02 LA-140 5.050E+02 2.000E+02 5.150E+01 0.000E+00 0.000E+00 1.680E+05 8.480E+04 LA-142 1.030E+00 3.770E-01 9.040E-02 0.000E+00 0.000E+00 8.220E+03 5.950E+04 CE-141 2.770E+04 1.670E+04 1.990E+03 0.000E+00 5.250E+03 5.170E+05 2.160E+04 CE-143 2.930E+02 1.930E+02 2.210E+01 0.0002+00 5.640E+01 1.160E+05 4.970E+04 CE-144 3.190E+06 1.210E+06 1.760E+05 0.000E+00 5.380E+05 9.840E+06 1.480E+05 PR-143 1.400E+04 5.240E+03 6.990E+02 0.000E+00 1.970E+03 4.330E+05 3.720E+04 PR-14 4.790E-02 1.850E-02 2.41 OE-03 0.000E+00 6.720E-03 1.610E+03 4.280E+03 ND-147 7.940E+03 8.130E+03 5.000E+02 0.000E+00 3.150E+03 3.220E+05 3.120E+04 EU-154 4.140E+06 4.840E+05 3.430E+05 0.0002+00 1.540E+06 4.270E+06 3.980E+04 EU-155 8.360E+05 8.010E+04 4.840E+04 0.000E+00 2.210E+05 7.280E+05 7.270E+04 W-187 1.300E+01 9.020E+00 3.120E+00 0.000E+00 0.000E+00 3.960E+04 3.560E+04 NP-239 3.710E+02 3.320E+01 1.880E+01 0.000E+00 6.620E+01 5.950E+04 2.490E+04

Offsite Dose Calculation Manual Page 288 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS ADULT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Uver "Thody Thyroid Kidney Lung Gltract H-3 O.O00E+00 7.630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 C-14 3.630E+05 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 NA-24 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 P-32 1.710E+10 1.060E+09 6.600E+08 0.000E+00 0.000E+00 0.000E+00 1.920E+09 CR-51 0.000E+00 0.000E+00 2.860E+04 1.710E+04 6.300E+03 3.800+E.04 7.200E+06 MN-54 0.000E+00 8.400E+06 1.600E+06 0.000E+00 2.500E+06 0.000E+00 2.570E+07 MN-56 0.000E+00 4.230E-03 7.510E-04 0.000E+00 5.380E-03 0.000E+00 1.350E-01 FE-55 2.510E+07 1.730E+07 4.040E+06 0.000E+00 0.000E+00 9.670E+06 9.950E+06 FE-59 2.980E+07 7.000E+07 2.680E+07 0.000E+00 0.000E+00 1.950E+07 2.330E+08 CO-57 0.000E+00 1.280E+06 2.130E+06 0.000E+00 0.000E+00 0.000E+00 3.250E+07 CO-58 0.000E+00 4.720E+06 1.060E+07 0.000E+00 0.000E+00 0.000E+00 9.570E+07 CO-60 0.000E+00 1.640E+07 3.620E+07 0.000E+00 0.000E+00 0.000E+00 3.080E+08 NI-63 6.730E+09 4.660E+08 2.260E+08 0.000E+00 0.000E+00 0.000E+00_ 9.730E+07 NI-65 3.700E-01 4.810E-02 2.190E-02 0.OOOE+00 0.000E+00 0.000E+00 1.220E+00 CU-64 0.000E+00 2.410E+04 1.130E+04 0.000E+00 6.080E+04 0.000E+00 2.050E+06 ZN-65 1.370E+09 4.360E+09 1.970E+09 0.000E+00 2.920E+09 0.000E+00 2.750E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0,000E+00 0.000E+00 0.OOOE+00 O.O00E+00 0.000+E00 0.000E+00 BR-83 0.OOOE+00 0.OOOE+00 0.000E+00 0.000+E00 O.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E÷00 O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.OOOE+00 2.590E+09 1.210E+09 0.000E+00 0.000E+00 0.000E+00 5.110E+08 RB-88 O.O00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.O000E00 0.000E+00 SR-89 1.450E+09 0.000E+00 4.160E+07 0.000E+00 0.000E+00 0.000E+00 2.330E+08 SR-90 4.680E+10 0.000E+00 1.150E+10 0.000E+00 0.000E+00 0.000E+00 1.350E+09 SR-91 3.130E+04 0.000E+00 1.270E+03 0.000E+00 0.000E+00 0.000+E00 1.490E+05 SR-92 4.890E-01 0.000E+00 2.110E-02 0.000E+00 0.000E+00 0.000E+00 9.680E+00

Offsite Dose Calculation Manual Page 289 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS ADULT (M 2 *mrem/yr per uCVsec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gltract Y-90 7.070E+01 0.OOOE+00 1.900E+00 0.000E+00 0.000E+00 0.000E+00 7.500E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 8.600E+03 0.OOOE+00 2.300E+02 0.OOOE+00 0.000E+00 0.000E+00 4.730E+06 Y-92 5.420E-05 0.OOOE+00 1.580E-06 0.000E+00 0.000+E00 0.000E+00 9.490E-01 Y-93 2.330E-01 0.000E+00 6.430E-03 0.OOOE+00 0.000E+00 0.000E+00 7.390E+03 ZR-95 9.460E+02 3.030E+02 2.050E+02 0.000E+00 4.760E+02 0.000E+00 9.620E+05 ZR-97 4.260E-01 8.590E-02 3.930E-02 0.000E+00 1.3002-01 0.000E+00 2.660E+04 NB-95 8.250E+04 4.590E+04 2.470E+04 0.0002+00 4.540E+04 0.000E+00 2.790E+08 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.470E-09 MO-99 0.000E+00 2.520E+07 4.800E+06 O.O00E+00 5.720E+07 0.000E+00 5.850E+07 TC-99M 3.250E+00 9.1902+00 1.170E+02 0.000E+00 1.400E+02 4.500E+00 5.440E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 O.O00E+00 0.000E+00 0.000E+00 O.000E+00 RU-103 1.020E+03 O.000E+00 4.390E+02 0.000E+00 3.890E+03 0.000E+00 M190E+05 RU-105 8.570E-04 0.000E+00 3.380E-04 0.000+E00 1.110E-02 0.000E+00 5.24012-01 RU-106 2.040E+04 0,000E+00 2.580E+03 0.000E+00 3.940E+04 0.000E+00 1.320E+06 RH-103M 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 0.000E+00 RH-106 0.000E+00 0.OOOE+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 5.830E+07 5.390E+07 3.200E+07 0.000E+00 1.060E+08 0.000E+00 2.200E+10 SB-122 6.010E+05 6.270E+05 7.590E+06 9.960E+04 2.960E+05 1.290E+05 7.470E+07 SB-124 8.580E+08 1.620E+07 3.400E+08 2.080E+06 0.000E+00 6,680E+08 2.440E+10 S8-125 6.810E+08 7.610E+06 1.6202+08 6.930E+05 0.000+E00 5.250E+08 7.500E+09 TE-125M 1.630E+07 5.900E+06 2.180E+06 4.900E+06 6.630E+07 0.000+E00 6.500E+07 TE-127M 4.580E+07 1.640E+07 5.580E+06 1.170E+07 1.860E+08 0.000E+00 1.540E+08 TE-127 6.720E+02 2.410E+02 1.450E+02 4.980E+02 2.740E+03 0.000E+00 5.300E+04 TE-129M 6.040E+07 2.250E+07 9,570E+06 2.080E+07 2.520E+08 0.000E+00 3.040E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 TE-131M 3.610E+05 1.770E+05 1.470E+05 2.800E+05 1.790E+06 0.000E+00 1.750E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.390E+06 1.550E+06 1.450E+06 1.710E+06 1.490E+07 0.000E+00 7.320E+07 1-130 4.260E+05 1.260E+06 4.960E+05 1.070E+08 1.960E+06 0.000+E00 1.080E+06 1-131 2.960E+08 4.240E+08 2.430E+08 1.390E+11 7.270E+08 0.000E+00 1.120E+08 1-132 1.640E-01 4.370E-01 1.530E-01 1.530E+01 6.970E-01 0.000E+00 8.2202-02 1-133 3.970E+06 6.900E+06 2.100E+06 1.010E+09 1.200E+07 0.000E+00 6.200E+06

Offsite Dose Calculation Manual Page 290 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS ADULT (M 2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gltract 1-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.OOOE+00 1-135 1.390E+04 3.630E+04 1.340E+04 2.400E+06 5.830E+04 0.000E+00 4.100E+04 CS-134 5.650E+09 1.340E+10 1.100E+10 0.000E+00 4.350E+09 1.440E+09 2.350E+08 CS-136 2.61 OE+08 1.030E+09 7.420E+08 0.000E+00 5.740E+08 7.870E+07 1.170E+08 CS-137 7.380E+09 1.010E+10 6.610E+09 0.000E+00 3.430E+09 1.140E+09 1.950E+08 CS-138 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 BA-139 4.700E-08 0.000E+00 1.380E-09 0.000E+00 0.000E+00 0.000E+00 8.340E-08 BA-140 2.690E+07 3.380E+04 1.760E+06 0.000+E00 1.150E+04 1.930E+04 5.540E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 OO.0E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 LA-140 4.490E+00 2.260E+00 5.970E-01 0.000E+00 0.000E+00 0.000E+00 1.660E+05 LA-142 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E-08 CE-141 4.840E+03 3.270E+03 3.710+E02 0.000E+00 1.520E+03 0.000E+00 1.250E+07 CE-143 4.190E+01 3.090E+04 3.420E+00 0.000E+00 1.360E+01 0.000E+00 1.160E+06 CE-144 3.580E+05 1.500E+05 1.920E+04 0.000E+00 8.870E+04 0.000E+00 1.210E+08 PR-143 1.590E+02 6.370E+01 7.880E+00 0.000E+00 3.680E+01 0.000E+00 6.960E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 9.420E+01 1.090E+02 6.520E+00 0.000E+00 6.370E+01 0.000E+00 5.230E205 EU-154 2.370E+04 2.910E+03 2.070E+03 0.000E+00 1.390E+04 0.000E+00 2.110E+06 EU-155 3.300E+03 4.680E+02 3.020E+02 0.000E+00 2.160E+03 0.000E+00 3.680E+05 W-187 6.560E+03 5.480E+03 1.920E+03 0.000E+00 0.000E+00 0.000E+00 1.800E+06 NP-239 3.660E+00 3.600E-01 1.980E-01 0.000E+00 1.120E+00 0.000E+00 7.390E+04

Offsite Dose Calculation Manual Page 291 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS TEEN (M2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.OOOE+00 9.940E+02 9.940E+02 9.940E+02 9.940E+02 9.940E+02 9.940E+02 C-14 6.700E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 NA-24 4.440E+06 4.440E+06 4.440E+06 4.440E÷06 4.440E÷06 4.440E+06 4.440E+06 P-32 3.150E+10 1.950E+09 1.220E+09 0.000E+00 0.000+E00 0.000E+00 2.650E+09 CR-51 0.000E+00 0.000E+00 5.000E+04 2.780E+04 1.100E+04 7.130E+04 8.400E+06 MN-54 0.000E+00 1.400E+07 2.780E+06 0.000E+00 4.170E+06 0.000E+00 2.870E+07 MN-56 0.000E+00 7.510E-03 1.330E-03 0.000E÷00 9.500E-03 0.OOOE+00 4,940E-01 FE-55 4.450E+07 3.160E+07 7.360E+06 0.0002+00 0.000E+00 2.000E+07 1.370E+07 FE-59 5.200E+07 1.210E+08 4.680E+07 0.000E+00 0.000E+00 3.820E+07 2.870E+08 CO-57 0.000E+00 2.250E+06 3.760E+06 0.000E+00 0.000E+00 0.0002E00 4.190E+07 CO-58 0.000E+00 7.950E+06 1.830E+07 0.000E+00 0.000E+00 0.000E+00 1.100E+08 CO-60 0.000E+00 2.780E+07 6.260E+07 0.000E+00 0.000E+00 0.000E÷00 3.620E+08 NI-63 1.180E+10 8,350E+08 4.010E+08 0.000E+00 0.000E+00 0.0002+00 1.330E+08 NI-65 6.780E-01 8.660E-02 3.940E-02 0.000E+00 0.000E+00 0.000E+00 4.700E+00 CU-64 0.OOOE+00 4.290E+04 2.020E+04 0.000E+00 1.090E+05 0.000E+00 3.330E+06 ZN-65 2.110E+09 7.310E+09 3.410E+09 0.000+E00 4.680E+09 0.0002+00 3.100E+09 ZN-69 O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 0.000E+00 0.000+E00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002E00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000+E00 0.OOOE+00 0.000E+00 0.000E+00 0.0002+00 BR-85 0.000E+00 0.0002E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.730E+09 2.220E+09 0.000E+00 0.000E+00 0.000E+00 7.000+E08 RB-88 0.000E+00 0.000+E00 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 0.000E+00 0.000E+00 SR-89 2.670E+09 0.000E+00 7.660E+07 0.000+E00 0.000+E00 0.000E+00 3.180E+08 SR-90 6.610E+10 0.000E+00 1.630E+10 0.000E+00 0.000E+00 0.000E+00 1.860E+09 SR-91 5.750E+04 0.000E+00 2.290E+03 0.000E+00 0.000+E00 0.000E+00 2.610E+05 SR-92 8.950E-01 0.000E+00 3.810E-02 0.000E+00 0.000+E00 0.OOOE+00 2.280E+01 Y-90 1.300E+02 0.000E+00 3.500E+00 0.000E+00 0.000E+00 0.000E+00 1.070E+06 Y-91M 0.000E+00 0.00OE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.580E+04 0.000E+00 4.240E+02 0.000E+00 0.000E+00 0.000+E00 6.480E+06 Y-92 1.000E-04 0.000E+00 2.900E-06 0.OOOE+00 0.000E+00 0.000+E00 2.750E+00 Y-93 4.300E-01 0.000E+00 1.180E-02 0.000E+00 0.000E+00 0.000E+00 1.310E+04

Offsite Dose Calculation Manual Page 292 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS TEEN (M2 *mrem/yr per uCi/sec)

Nuclide Bone Liver "Thody Thyroid Kidney Lung Gltract ZR-95 1.650E+03 5.220E+02 3.590E+02 0.000E+00 7.670E+02 0.000E+00 1.200E+06 ZR-97 7.750E-01 1.530E-01 7.060E-02 0.000E+00 2.320E-01 0.000E+00 4.150E+04 NB-95 1.410E+05 7.800E+04 4.300E+04 0.000E+00 7.570E+04 0.000E+00 3.340E208 NB-97 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 6.340E-08 MO-99 0.000E+00 4.560E+07 8.690E+06 0.000E+00 1.040E+08 0.000E+00 8.160E+07 TC-99M 5.640E+00 1.570E+01 2.040E+02 0.000E+00 2.340E+02 8.730E+00 1.030E+04 TC-101 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000+E00 0.000E+00 RU-103 1.810E+03 0.000E+00 7.750E+02 0.000E+00 6.400E+03 0.000+E00 1.520E+05 RU-105 1.570E-03 0.000E+00 6.080E-04 0.0002+00 1.970E-02 0.0002+00 1.260E+00 RU-106 3.750E+04 0.000E+00 4.730E+03 0.000E+00 7.230E+04 0.000E+00 1.800E+06 RH-103M 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 O.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 AG-110M 9.630E+07 9.110E+07 5.540E+07 0.OOOE+00 1.740E+/-08 0.000E+00 2.560E+10 SB-122 7.760E+05 8.090E+05 9.800E+06 1.290E+05 3.820E+05 1.660E+05 9.640E+07 SB-124 1.530E+09 2.820E+07 5.970E+08 3.470E+06 0.0002E00 1.340E+09 3.080E+10 SB-125 1.220E+09 1.330E+07 2.850E+08 1.160E+06 0.000E+00 1.070E+09 9.480E+09 TE-125M 3.000E+07 1.080E+07 4.020E+06 8.390E+06 0.000E+00 0.0002+00 8.860E+07 TE-127M 8.440E+07 2.990E+07 1.000E+07 2.010E+07 3.420E+08 0.000E+00 2.100E+08 T.-127 1.240E+03 4.410E+02 2.680E+02 8.590E+02 5.040E+03 0.000E+00 9.610E+04 TE-129M 1.110E+08 4.1002+07 1.750E+07 3.570E+07 4.620E+08 0.000E+00 4.150E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.670E-09 0.000E+00 2.180E.09 TE-131M 6.570E+05 3.150E+05 2.630E+05 4.740E+05 3.290E+06 0.000E+00 2.530E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 TE-132 4.280E+06 2.710E+06 2.550E+06 2.860E+06 2.600E+07 0.000E+00 8.580E+07 1-130 7.490E+05 2.170E+06 8.660E+05 1.770E+08 3.340E+06 0.000E+00 1.670E+06 1-131 5.380E+08 7.530E+08 4.040E+08 2.200E+11 1.300E+09 0.002E+00 1.490E+08 1-132 2.900E-01 7.590E-01 2.720E-01 2.560E+01 1.200E+00 0.000E+00 3.310E-01 1-133 7.240E+06 1.230E+07 3.750E+06 1.720E+09 2.150E+07 0.0002E00 9.300E+06 1-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.0002+00 1-135 2.470E+04 6.350E+04 2.350E+04 4.080E+06 1.000E+05 0.000E+00 7.030E+04 CS-134 9.810E+09 2.310E+10 1.070E+10 0.000E+00 7.340E+09 2.800E+09 2.870E+08 CS-136 4.450E+08 1.750E+09 1.180E+09 0.000E+00 9.530E+08 1.500E+08 1.410E+08 CS-137 1.340E+10 1.780E+10 6.200E+09 0.000E+00 6.060E+09 2.350E+09 2.530E+08 CS-1 38 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

Offsite Dose Calculation Manual Page 293 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS TEEN (M2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract BA-139 8.690E-08 0.000E+00 2.530E-09 0.000E+00 0.000E+00 0.000E+00 7.750E-07 BA-140 4.850E+07 5.950E+04 3.130E+06 0.000E+00 2.020E+04 4.000E+04 7.490E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 BA-142 0.000E+00 0.OOOE+00 0.000E+00 0.0002E00 0.000E+00 0.000E+00 0.000E+00 LA-1 40 8.060E+00 3.960E+00 1.050E+00 0.000E+00 0.000E+00 0.0O0E+00 2.270E+05 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.230E-07 CE-141 8.870E+03 5.920E+03 6.810E+02 0.000E+00 2.790E+03 0.000E+00 1.690E+07 CE-143 7.690E+01 5.600E+04 6.250E+00 0.000E+00 2.510E+01 0.000E+00 1.680E+06 CE-144 6.580E+05 2.720E+05 3.540E+04 0.000E+00 "1.630E+05 0.000E+00 1.660E+08 PR-143 2.920E+02 1.A70E+02 1.450E+01 0.000E+00 6.770E+01 0.000E+00 9.610E+05 PR-144 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.810E+02 1.970E+02 1.180E+01 0.000E+00 1.160E+02 0.000E+00 7.110E+05 EU-154 3.920E+04 5:060E+03 3.570E+03 0.000E+00 2.260E+04 0.000E+00 2.670E+06 EU-155 8.600E+03 8.310E+02 5.140E+02 0.000E+00 3.250E+03 0.000E+00 4.760E+06 W-187 i.200E+04 9.780E+03 3.430E+03 O.000E+00 0.000E+00 0.000E+00 2.650E+06 NP-239 6.990E+00 6.590E-01 3.660E-01 0.000E+00 2.070E+00 0.000E+00 1.060E+05

Offsite Dose Calculation Manual Page 294 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS CHILD (in2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 C-14 1.650E+06 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 NA-24 9.230E+06 9.230E+06 9.230E+06 9.230E+06 9.230E+06 9.230E+06 9.230E+06 P-32 7.770E+10 3.640E+09 3.000E+09 0.000E+00 0.000E+00 0.000E+00 2.150E+09 CR-51 0.000E+00 0.000E+00 1.020E+05 5.660E+04 1.550E+04 1.030E+05 5.410E+06 MN-54 0.000E+00 2.090E+07 5.580E+06 0.000E+00 5.870E+06 0.000E+00 1.760E+07 MN-56 0.000E+00 1.310E-02 2.950E-03 0.000E+00 1.580E-02 0.000E+00 1.900E+00 FE-55 1.120E+08 5.930E+07 1.840E+07 0.000E+00 0.000E+00 3.350E+07 1.100E+07 FE-59 1.200E+08 1.950E+08 9.710E+07 0.000E+00 0.000E+00 5.650E+07 2.030E+08 CO-57 0.OOOE+00 3.840E+06 7.770E+06 0.000E+00 0.000E+00 0.000E+00 3.140E+07 CO-58 0.000E+00 1.210E+07 3.720E+07 0.000E+00 0.000E+00 0.000E+00 7.080E+07 CO-60 0.000E+00 4.320E+07 1.270E+08 0.000E+00 0.000E+00 0.000E+00 2.390E+08 NI-63 2.960E+10 1.590E+09 1.010E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+08 NI-65 1.660E÷00 1.560E-01 9.110E-02 0.000E+00 0.000E+00 0.000E+00 1.910E+01 CU-64 0.000E+00 7.550E+04 4.560E+04 0.000E+00 1.820E+05 0.000E+00 3.540E+06 ZN-65 4.130E+09 1.100E+10 6,850E+09 0.000E+00 6.940E+09 0.000E+00 1.930E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.140E-09 BR-82 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000+E00 O.OOOE+00 0.000E+00 O.O00E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 O.0O0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000+E00 8.770E+09 5,390E+09 0.000E+00 0.000E+00 0.000E+00 5.640E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 RB-89 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 6.620E+09 0.000E+00 1.890E+08 0.000E+00 0.000E+00 0.000E+00 2.560E+08 SR-90 1.120E+11 O.O00E+00 2.830E+10 0.000+E00 0.000E+00 0.000E+00 1.510E+09 SR-91 1.410E+05 0.000E+00 5.330E+03 0.000E+00 0.000E+00 0.O00E+00 3.120E+05 SR-92 2.190E+00 0.000E+00 8.760E-02 0.000E+00 O.000E+00 0.000E+00 4.140E+01 Y-90 3.220E+02 0.000E+00 8.610E+00 0.000E+00 0.000E+00 0.000E+00 9.150E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 0.000E+00 Y-91 3.910E+04 0.000E+00 1.040E+03 0.000E+00 0.000E+00 0.000E+00 5.210E+06 Y-92 2.460E-04 0.000E+00 7.030E-06 0.000E+00 0.000E+00 0.000E+00 7.100E+00 Y-93 1.060E+00 0.000E+00 2.900E-02 0.000E+00 0.000E+00 0.000E+00 1.570E+04

Offsite Dose Calculation Manual Page 295 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS CHILD (M2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gltract ZR-95 3.840E+03 8.450E+02 7.520E+02 0.000E+00 1.210E+03 0.000E+00 8.810E+05 ZR-97 1.890E+00 2.720E-01 1.610E-01 0.000E+00 3.9102-01 0.000E+00 4.130E+04 NB-95 3.180E+05 1.240E+05 8.840E+04 0.000E+00 1.160E+05 0.000E+00 2.290E+08 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.450E-06 MO-99 0.000E+00 8.290E+07 2.050E+07 0.000E+00 1.770E+08 0.000E+00 6.860E+07 TC-99M 1.290E+01 2.540E+01 4.200E+02 O.000E+00 3.680E+02 1.290E+01 1.440E+04 TC-101 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 O.000E+00 RU-103 4.290E+03 0.OOOE+00 1.650E+03 0.000E+00 1.080E+04 0.000E+00 1.110E+05 RU-105 3.820E-03 0.000E+00 1.390E-03 O.0OOE+00 3.360E-02 0.000E+00 2.490E+00 RU-106 9.240E+04 0.000E+00 1.150E+04 0.000E+00 1.250E+05 0.000E+00 1.440E+06 RH-103M O.0OOE+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.0002E00 0.000E+00 RH-106 0.000E+00 O.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 2.090E+08 1.410E+08 1.130E+08 - 0.000E+00 2.630E+08 0.OOOE÷00 1.680E+10 SB-122 4.140E+06 4.320E+06 5.230E+07 6.870E+05 2.040E+06 8.890E+05 5.150E+08 SB-124 3.620E+09 4.700E+07 1.270E+09 7.990E+06 0.000E+00 2.010E+09 2.260E+10 SB-125 2.900E+09 2.240E207 6.080E+08 2.690E+06 0.000E+00 1.620E+09 6.930E+09 TE-125M 7.380E+07 2.000E+07 9.840E+06 2.070E+07 0.000E+00 0.000E+00 7.120E+07 TE-127M 2.080E+08 5.600E+07 2.470E+07 4.970E+07 5.930E+08 0.0002E00 1.680E+08 TE-127 3.060E+03 8.250E+02 6.560E+02 2.120E+03 8.710E+03 0.000E+00 1.200E+05 TE-129M 2.720E+08 7.610E+07 4.230E+07 8.780E+07 8.000E+08 0.000E+00 3.320E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.870E-09 0.000E+00 6.120E-08 TE-131M 1.600E+06 5.530E+05 5.890E+05 1.140E+06 5.350E+06 0.000E+00 2.240E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 0.0002+00 O.000E+00 0.000E+00 TE-132 1.020E+07 4.520E+06 5.460E+06 6.580E+06 4.200E+07 0.000E+00 4.550E+07 1-130 1.750E+06 3.540E+06 1.820E+06 3.900E+08 5.290E+06 0.000E+00 1.660E+06 1-131 1.300E+09 1.310E+09 7.460E+08 4.340E+11 2.150E+09 0.000E÷00 1.170E+08 1-132 6.860E-01 1.260E+00 5.800E-01 5.850E+01 1.930E+00 0.000E+00 1.480E+00 1-133 1.760E+07 2.180E+07 8.230E+06 4.040E+09 3.630E+07 0.OOOE+00 8.770E+06 1-134 0.0002+00 0.O00E+00 0.000E+00 0.000E+00 O.OOOE+00 0.000E+00 0.000E+00 1-135 5.840E+04 1.050E+05 4.970E+04 9.300E+06 1.610E+05 0.000E+00 8.000E+04 CS-134 2.260E+10 3.710E+10 7.830E+09 0.000E+00 1.150E+10 4.130E+09 2.000E+08 CS-136 1.000E+09 2.760E+09 1.790E+09 0.000E+00 1.470E+09 2.190E+08 9.700E+07 CS-137 3.220E+10 3.090E+10 4.550E+09 0.000E+00 1.010E+10 3.620E+09 1.930E+08 CS-1 38 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00

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Nuclide Bone Liver Thody Thyroid Kidney Lung Gltract BA-139 2.140E-07 0.000E+00 6.190E-09 0.000E+00 0.000E+00 0.000E+00 1.230E-05 BA-140 1.170E+08 1.030E+05 6.840E+06 0.000+E00 3.340E+04 6.120E+04 5.940E+07 BA-1 41 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 O.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 0.000+E00 O.OOOE+00 LA-140 1.930E+01 6.740E+00 2.270E+00 0.000E+00 0.000E+00 0.000E+00 1.880E+05 LA-142 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 2.510E-06 CE-141 2.190E+04 1.090E+04 1.620E+03 0.000E+00 4.780E+03 0.000E+00 1.360E+07 CE-143 1.890E+02 1.020E+05 1.480E+01 0.000E+00 4.290E+01 0.OOOE+00 1.500E+06 CE-144 1.620E+06 5.090E+05 8.660E+04 0.000E+00 2.820E+05 0.000E+00 1.330E+08 PR-143 7.230E+02 2.170E+02 3.590E+01 0.000E+00 1.170E+02 0.OOOE+00 7.800E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 O.O00E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 4.450E+02 3.600E+02 2.790E+01 0.000E+00 1.980E+02 0.000E+00 5.710E+05 EU-154 9.420E+04 8.470E+03 7.7405+03 0.000E+00 _3.720E+04 0.000E+00 1.970E+06 EU-155 1.970E+04 1.420E+03 1.110E+03 0.000E+00 5.300E+03 0.000E+00 3.540E+06 W-187 2.910E+04 1.720E+04 7.730E+03 0.000E+00 0.000E+00 0.OOOE+00 2.420E+06 NP-239 1.720E+01 1.230E+00 8.680E-01 0.000E+00 3.570E+00 0.000E+00 9.140E+04

Offsite Dose Calculation Manual Page 297 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS INFANT (m 2 *mrem/yr per uCi/sec)

Nuclide Bone Liver "rbody Thyroid Kidney Lung Gitract H-3 0.0002+00 2.380E+03 2.380E203 2.380E+03 2.380E+03 2.380E+03 2.380E+03 C-14 3.230E+06 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 NA-24 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 P-32 1.600E+11 9.420E+09 6.210E+09 0.000E+00 0.000E+00 0.0002+00 2.170E+09 CR-51 0.000E+00 0.000E+00 1.610E+05 1.050E+05 2.300E+04 2.050E+05 4.710E+06 MN-54 0.O00E+00 3.890E+07 8.830E+06 0.000E+00 8.630E+06 0.000E+00 1.430E+07 MN-56 0.000E+00 3.210E-02 5.530E-03 0.000E+00 2.760E-02 0.000E+00 2.910E+00 FE-55 1.350E+08 8.720E+07 2.330E+07 0.0002+00 0.000E+00 4.270E+07 1.110E+07 FE-59 2.250E+08 3.930E+08 1.550E+08 0.000E+00 0.000+E00 1.160E+08 1.880E+08 CO-57 0.OOOE+00 8.950E+06 1.460E+07 0.000E+00 0.000E+00 0.000E+00 3.050E+07 CO-58 0.000E+00 2.430E+07 6.060E+07 0.000E+00 0.000E+00 0.000E+00 6.050E+07 CO-60 0.000E+00 8.810E+07 2.080E+08 0.000E+00 0.000E+00 0.000+E00 2.100E+08 NI-63 3.490E+10 2.160E+09 1.210E+09 0.000E+00 0.000E+00 -0.000E+00 1.070E+08 NI-65 3.510E+00 3.970E-01 1.810E-01 0.000E+00 0.000E+00 0.000E+00 3.020E+01 CU-64 0.000E+00 1.880E+05 8.690E+04 0.000E+00 3.170E+05 0.000E+00 3.850E+06 ZN-65 5.550E+09 1.9002+10 8.780E+09 0.000E+00 9.230E+09 0.000E+00 1.610E+10 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.360E-09 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 BR-83 0.000E+00 O.O00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 0.000E+00 RB-86 O.OOOE+00 2.220E+10 1.100E+10 0.000E+00 0.000E+00 0.OOOE+00 5.690E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.O00E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 1.260E+10 0.000E+00 3.610E+08 0.000E+00 0.000E+00 0.000+E00 2.590E+08 SR-90 1.220E+11 0.000E+00 3.100E+10 0.000E+00 0.000E+00 0.000E+00 1.520E+09 SR-91 2.940E+05 0.000E+00 1.060E+04 0.000E+00 0.000E+00 0.000E+00 3.480E+05 SR-92 4.650E+00 0.000E+00 1.730E-01 0.000E+00 0.000E+00 0.000E+00 5.010E+01 Y-90 6.800E+02 0.000+E00 1.820E+01 0.000E+00 0.000E+00 0.000E+00 9.390E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 7.330E+04 0.000E+00 1.950E+03 0.000E+00 0.000E+00 0.000E+00 5.260E+06 Y-92 5.220E-04 0.000E+00 1.470E-05 0.000E+00 0.000E+00 0.000E+00 9.970E+00 Y-93 2.250E+00 0.000E+00 6.130E-02 0.000E+00 0.000E+00 0.000E+00 1.780E+04

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Nuciide Bone Liver Thody Thyroid Kidney Lung Gltract ZR-95 6.830E+03 1,660E+03 1.180E+03 0.000E+00 1.790E+03 0.000E+00 8.280E+05 ZR-97 3.990E+00 6.850E-01 3.130E-01 0.000E+00 6.910E-01 0.0002+00 4.370E+04 NB-95 5.930E+05 2.440E+05 1.410E+05 0.000E+00 1.750E+05 0.0002+00 2.060E+08 NB-97 0.0002+00 0.OOOE+00 0.000.E00 0.000E+00 0.000E+00 0.000E+00 3.700E-06 MO-99 0.000E+00 2.120E+08 4.130E+07 0.000E+00 3.170E+08 0.0002+00 6.980E+07 TC-99M 2.690E+01 5.550E+01 7.150E+02 0.000E+00 5.970E+02 2.900E+01 1.610E+04 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.00012+00 0.000E+00 RU-103 8.690E+03 0.000E+00 2.91 OE+03 0.000E+00 1.810E+04 0.0002+00 1.060E+05 RU-105 8.060E-03 0.000E+00 2.710E-03 0.000E+00 5.920E-02 0.000E+00 3.210E+00 RU-1 06 1 .9002+05 0.000E+00 2.380E+04 0.000E+00 2.250E+05 0.000E+00 1.440E+06 RH-103M 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 RH-106 0.000E+00 0.000E+00 O.000E+00 0.0002+00 0.000E100 0.0002+00 0.000E+00 AG-110M 3.860E+08 2.820E+08 1.860E+08 0.000E+00 4.030E+08 0.000E+_00 1.460E+10 SB-122 6.400E+05 6.670E+05 8.080E+06 1.060E+05 3.150E+05 1.370E+05 7.950E+07 SB-124 6.980E+09 1.030E+08 2.160E+09 1.850E+07 0.000E+00 4.370E+09 2.150E+10 SB-125 4.980E+09 4.820E+07 1.020E+09 6.240E+06 0.000E+00 3.130E+09 6.640E+09 TE-125M 1.510E+08 5.040E+07 2.040E+07 5.070E+07 0.000E+00 0.000E+00 7.180E+07 TE-127M 4.210E+08 1.400E+08 5.100E+07 1.220E+08 1.040E+09 0.000E+00 1.700E+08 TE-127 6.500E+03 2.180E+03 1.400E+03 5.290E+03 1.590E+04 0.000E+00 1.360E+05 TE-129M 5.590E+08 1.920E+08 8.620E+07 2.150E+08 1.400E+09 0.000E+00 3.340E+08 TE-129 2.080E-09 O.O00E+00 0.0002+00 1.750E-09 5.180E-09 0.000E+00 1.660E-07 TE-131M 3.380E+06 1.360E+06 1.120E+06 2.760E+06 9.350E+06 0.0002+00 2.290E÷07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.100E+07 1.040E+07 9.720E+06 1.540E+07 6.510E+07 0.000E+00 3.850E+07 1-130 3.600E+06 7.920E+06 3.180E+06 8.880E+08 8.700E+06 0.000E+00 1.700E+06 1-131 2.720E+09 3.210E+09 1.410E+09 1.050E+12 3.750E+09 0.000E+00 1.150E+08 1-132 1.420E+00 2.890E+00 1.030E+00 1.350E+02 3.220E+00 0.000E+00 2.340E400 1-133 3.720E+07 5.410E+07 1.580E+07 9.840E+09 6.360E+07 0.000E+00 9.160E+06 1-134 0.000E+00 0.OOOE+00 0.000E+00 1.010E-09 0.000E+00 0.000E+00 0.000E+00 1-135 1.21 OE+05 2.410E+05 8.800E+04 2.160E+07 2.690E+05 0.0002+00 8.740E+04 CS-1 34 3.650E+10 6.800E+1 0 6.870E+09 0.000E+00 1.750E+10 7.180E+09 1.850E+08 CS-136 1.960E+09 5.770E+09 2.150E+09 0.000E+00 2.300E+09 4.700E+08 8.760E+07 CS-137 5.150E+10 6.020E+10 4.270E+09 0.O00E+00 1.620E+10 6.550E+09 1.880E+08 CS-1 38 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.OOOE+00

Offsite Dose Calculation Manual Page 299 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS INFANT (M 2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gltract BA- 139 4.550E-07 0.OOOE+00 1.320E-08 O.OOOE+00 0.000E+00 O.O00E+00 2.880E-05 BA-140 2.410E+08 2.410E+05 1,240E+07 OO.000E+0 5.730E+04 1.480E+05 5.920E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 OO00E+00 0.000E+00 OO00E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 LA-140 4.030E+01 1.590E+01 4.090E+00 0.000E+00 0.000E+00 O.000E+00 1.870E+05 LA-142 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 0.000=+00 O.O00E+00 5.210E-06 CE-141 4.330E+04 2.640E+04 3.11 OE+03 0.000E+00 8.150E+03 0.000E+00 1.370E+07 CE-1 43 4.000E+02 2.650E+05 3.020E+01 0.000E+00 7.720E+01 OO.000E+0 1.550E+06 CE-144 2.330E+06 9.520E+05 1.300E+05 O.O00E+00 3&850E+05 0.000E+00 1.330E+08 PR-143 1.490E+03 5.590E+02 7.410E+01 0.000E+00 2.080E+02 O.000E+00 7.890E+05 PR-144 0.000E+00 0.000E+00 0,000E+00 0,000E+00 0.000E+00 0.O00E+00 0.000E+00 ND-147 8.820E+02 9.060E+02 5.550E+01 0.000E+00 3.490E+02 0.000E+00 5.740E+05 EU-154 1.080E+05 1.500E+04 9.0_0E+03 0.000E+00 4.070E+04 OO.00÷+00 1.880E+06 EU-1 55 2.210E+04 2.550E+03 1.320E+03 0.000E+00 5.710E+03 0.000E+00 3.410E+06 W-187 6.120E+04 4.260E+04 1.470E+04 O.O00E+00 0.000E+00 OO00E+00 2.500E+06 NP-239 3.640E+01 3.250E+00 1.840E+00 0.000E+00 6.490E+00 OO.00E+00 9.400E+04

Offsite Dose Calculation Manual Page 300 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS ADULT (M2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.O00E+00 1.560E+03 1.560E+03 1.560E+03 1.560E+03 1.560E+03 1.550E+03 C-14 3.630E+05 7.260E+04 7,260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 NA-24 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 P-32 2.050E+10 1.270E+09 7.930E+08 0.000E+00 0.000E+00 O.000E+00 2.310E+09 CR-51 0.000E+00 O.O00E+00 3.430E+03 2.050E+03 7.560E+02 4.560E+03 8.640E+05 MN-54 0.000E+00 1.010E+06 1.920E+05 0.000E+00 3.000E+05 0.000E+00 3.090E+06 MN-56 0.000E+00 5.080E-04 9.010E-05 0.000E+00 6.450E-04 O.O00E+00 1.620E.02 FE-55 3.260E+05 2.250E+05 5.260E+04 O.O00E+00 0.0002+00 1.260E+05 1.290E+05 FE-59 3.870E+05 9.090E+05 3.490E+05 O.O00E+00 O.002E+00 2.540E+405 3.030E+06 CO-57 0.0002+00 1.540E+05 2.550E+05 0.000E+00 0.000E+00 0.O00E+00 3.900E+06 CO-58 0.000E+00 5.660E+05 1.270E+06 O.O00E+00 0.000E+00 O.000E+00 1.1 50E+07 CO-60 O.O00E+00 1.970E+06 4.3402+06 0.000E+00 0.000E+00 0.000E+00 3.700E+07 NI-63 8.070E+08 5.600E+07 2.710E+07 0.0Q0E+00 0.000E+00 0.000E+00 1.170E+07 NI-65 4.440E-02 5.770E-03 2.630E-03 0.000E+00 0.000E+00 OO00E+00 1.460E-01 CU-64 0.000E+00 2.690E+03 1.260E+03 0.OOOE+00 6.770E+03 0.000E+00 2.290E+05 ZN-65 1.6502+08 5.240E+08 2.370E+08 O.O00E+00 3.500E+08 OO002+00 3.300E+08 ZN-69 O.O00E+00 O.000E+00 0.000E+00 O.O00E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 O.O00E+00 O.002E+00 3.900E+06 0.000E+00 O.O00E+00 0.000E+00 4.470E+06 BR-83 O.O00E+00 0.000E+00 1.240E-02 O.O00E+00 0.000E+00 OO.00E+00 1.790E-02 BR-84 0.000E+00 O.O00E+00 O.O00E+00 0.000E+00 0.000E+00 O.O00E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 O.O00E+00 0.000E+00 O.002E+00 0.000E+00 O.00E-+00 RB-86 0.000E+00 3.110E+08 1.450E+08 O.OOOE+00 O.000E+00 0.000E+00 6.140E+07 RB-88 0,000E+00 O.002E+00 O.000E+O0 0.000E+00 0.000E+00 O.000E+00 0.OOOE+00 RB-89 0.000E+00 O.OOOE+00 O.000E+00 O.O00E+00 0.0001+00 O.O00E+00 O.000E+00 SR-89 3.050E+09 0.000E+00 8.740E+07 O.000E+00 0.000E+00 O.O00E+00 4.890E+08 SR-90 9.830E+10 0.000E+00 2.410E+10 0.OOOE+00 0.000E+00 0.000E+00 2.840E+09 SR-91 6.580E+04 O.O00E+00 2.660E+03 0.000E+00 0.000E+00 0.000E+00 3.130E+05 SR-92 1.030E+00 0.0002+00 4.440E-02 0.000E+00 0.000E+00 0.000E+00 2.030E+01 Y-90 8.480E+00 O.000E+00 2.280E-01 O.O00E+00 0.000E+00 OO.0E+00 8.990E+04 Y-91M 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 O.O00E+00 O.000E+00 Y-91 1.030E+03 0.000E+00 2.760E+01 0.000E+00 O.O00E+00 OO00E+00 5.680E+05 Y-92 6.51 0E-06 O.O00E+00 1.900E-07 0.000E+00 O.O00E+00 0.000E+00 1.140E-01 Y-93 2.800E-02 0.000E+00 7.720E-04 0.000E+00 O.O00E+00 O.000E+00 8.870E+02 ZR-95 1.140E+02 3.640E+01 2.470E+01 O.O00E+00 5.710E+01 0.000E+00 1.150E+05

Offsite Dose Calculation Manual Page 301 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS AD ULT (M2 *mrem/yr per uCi/sec)

Nucilde Bone Liver Thody Thyroid Kidney Lung Gitract ZR-97 5.110E-02 1.030E-02 4.710E-03 0.000E+00 1.560E-02 0.000E+00 3.190E+03 NB-95 9.900E+03 5.510E+03 2.960E+03 0.000E+00 5.440E+03 0.000E+00 3.340E+07 NB-97 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 MO-99 0.OOOE+00 3.030E+06 5.760E+05 0.000E+00 6.860E+06 0.000E+00 7.020E+06 TC-99M 3.900E-01 1.100E+00 1.400E+01 0.000E+00 1.670E+01 5.400E-01 6.520E+02 TC-101 0.000E+00 0.OOOE+00 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.OOOE+00 RU-103 1.220E+02 0.000E+00 5.270E+01 0.000E+00 4.670E+02 0.000E+00 1.430E+04 RU-105 1.030E-04 0.000E+00 4.060E-05 0.000E+00 1.330E-03 0.000E+00 6.290E-02 RU-106 2.450E+03 0.000E+00 3.100E+02 0.000E+00 4.730E+03 0.000E+00 1.580E+05 RH-103M 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000+E00 AG-1 10M 6.990E+06 6.470E+06 3.840E+06 0,000E+00 1.270E+07 0.000E+00 2.640E+09 SB-122_ 7.210E+04 7.520E+04 9.110E+05 1.200E+04 -3.550E+04 1.550E+04 8.960E+06 SB-124 3.090E+06 5.840E+04 1.220E+06 7.490E+03 0.000E+00 2.410E+06 8.770E+07 SB-125 2.450E+06 2.740E+04 5.840E+05 2.490E203 0.000E+00 1.890E+06 2.700E+07 TE-125M 1.950E+06 7.080E+05 2.620E+05 5.88.0+05 7.950E+06 0.0O0E+00 7.810E+06 TE-127M 5.490E+06 1.960E+06 6.690E+05 1.400E+06 2.230E+07 0.000E+00 1.840E+07 TE-127 8.060E+01 2.890E+01 1.740E+01 5.970E+01 3.280E+02 0.000+E00 6.360E+03 TE-129M 7.250E+06 2.710E+06 1.150E+06 2.490E+06 3.030E+07 0.000+E00 3.650E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002E00 0.000E+00 TE-131M 4.330E+04 2.120E+04 1.770E+04 3.360E+04 2.150E+05 0.000E+00 2.100E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E400 0.000E+00 0.0002+00 TE-132 2.870E+05 1.860E+05 1.740E+05 2.050E+05 1.790E+06 0.000E+00 8.790E+06 1-130 5.110E+05 1.510E+06 5.950E+05 1.280E+08 2.350E+06 0.000E+00 1.300E+06 1-131 3.560E+08 5.090E+08 2.920E+08 1.670E+11 8.720E+08 0.000E+00 1.340E+08 1-132 1.960E-01 5.250E-01 1.840E-01 1.840E+01 8.360E-01 0.000E+00 9.860E-.02 1-133 4.760E+06 8.280E+06 2.520E+06 1.220E+09 1.440E+07 0.000+E00 7.440E+06 1-134 0.000E+00 0.000E+00 0.000E+00 0.000+E00 0.0002+00 0.000E+00 0.000E+00 1-135 1.670E204 4.360E+04 1.610E+04 2.880E+06 6.990E+04 0.000+E00 4.920E+04 CS-134 1.700E+10 4.030E+10 3.300E+10 0.0002+00 1.310E+10 4.330E+09 7.060E+08 CS-136 7.840E+08 3.090E+09 2.230E+09 0.000E+00 1.720E+09 2.360E+08 3.520E+08 CS-137 2.210E+10 3.030E+10 1.980E+10 0.000E+00 1.030E+10 3.420E+09 5.860E+08 CS-1 38 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

Offsite Dose Calculation Manual Page 302 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS ADULT (M2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract BA-139 5.640E-09 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 1.000E-08 BA-140 3.230E+06 4.050E+03 2.11 OE+05 0.000E+00 1.380E+03 2.320E+03 6.650E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 5,380E.01 2.710E-01 1.990E+04 0.000E+00 0.000E+00 0.000E+00 1.990E+04 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.640E-09 CE-141 5.81 OE+02 3.930E+02 4.450E+01 0.000+E00 1.820E+02 0.OOOE+00 1.500E+06 CE-143 5.020E+00 3.710E+03 4.110E-01 0.000E+00 1.630E+00 0.000E+00 1.390E+05 CE-144 4.290E+04 1.790E+04 2.300E+03 0.000E+00 1.060E+04 0.000E+00 1.450E+07 PR-143 1.910E+01 7.650E+00 9.450E-01 0.O00E+00 4.410E+00 0.000E+00 8.350E+04 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 ND-147 1.130E+01 1.310E+01 7.820E-01 0.000E+00 7.640E+00 0.000E+00 6.270E+04 EU-154 2.840E+03 3.490E+02 2.480E+02 0.000E+00 1.670E+03 -0.000E+00 2.530E+05 EU-155 3.950E+02 5.610E+01 3.620E+01 0.000E+00 2.590E+02 0.000E+00 4.410E+04 W-187 7.870E+02 6.580E+02 2.300E+02 0.000E÷00 0.000E+00 0.000E+00 2.1 60E+05 NP-239 4.390E-01 4.320E-02 2.380E-02 0.000E+00 1.350E-01 0.000E+00 8.860E+03

Offsite Dose Calculation Manual Page 303 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS TEEN 2

(M *mrem/yr per uCilsec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gltract H-3 0.000E+00 2.030E+03 2.030E+03 2.030E+03 2.030E+03 2.030E+03 2.030E+03 C-14 6.700E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 NA-24 5.330E+05 5.330E+05 5.330E+05 5.330E+05 5.330E+05 5.330E+05 5.330E+05 P-32 3.780E+10 2.340E+09 1.470E+09 0.000E+00 0.000E+00 0.000E+00 3.180E+09 CR-51 0.000E+00 0.000E+00 6.000E+03 3.330E+03 1.310E+03 8.560E+03 1.010E+06 MN-54 0.000E+00 1.680E+06 3.330E+05 0-000E+00 5.01 0E+05 0.000E+00 3.440E+06 MN-56 0.000E+00 9.010E-04 1.600E-04 0.000E+00 1.140E-03 0.000E+00 5.930E-02 FE-55 5.790E+05 4.100E+05 9.570E+04 0.0002+00 0.000E+00 2.600E+05 1.780E+05 FE-59 6.750E+05 1.580E+06 6.090E+05 0.000E+00 0.000E+00 4.970E+05 3.730E+06 CO-57 0.000E+00 2.690E+05 4.520E+05 0.000E+00 0.000E+00 0.000E+00 5.030E+06 CO-58 0.000E+00 9.540E+05 2.200E+06 0.0002+00 0.OOOE+00 0.000E+00 1.310E+07 CO-60 0.000E+00 3.340E+06 7.510E+06 0.000E+00 0.000+E00 0.000E+00 4.350E+07 NI-63 1.A20E+09 1.000E+08 4.810E+07 0.000E+00 0.000E+00 0.000E+00 1.-590E+07 NI-65 8.130E-02 1.040E-02 4.730E-03 0.000E+00 0.000E+00 0.000E+00 5.640E-01 CU-64 0.000E+00 4.790E+03 2.250E+03 0.0002+00 1.210E+04 0.0002+00 3.710E+05 ZN-65 2.530E+08 8.780E+08 4.090E+08 0.000E+00 5.620E+08 0.000E+00 3.720E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 6.670E+06 0.000E+00 0.0002E00 0.000E+00 0.000E+00 BR-B3 0.000E+00 0.000E+00 2.290E-02 0.OOOE+00 0.0002+00 0.0002+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.0002+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.670E+08 2.670E+08 0.000E+00 0.000E+00 0.000E+00 8.400E+07 RB-88 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002E00 SR-89 5.620E+09 0.000E+00 1.160E+08 0.000E+00 0.000E+00 0.000E+00 6.690E+08 SR-90 1.390E+11 0.000E+00 3.430E+11 0.000E+00 0.000+E00 0.000E+00 3.900E+09 SR-91 1.210E+05 0.000E+00 4.810E+03 0.000E+00 0.000E+00 0.000E+00 5.480E+05 SR-92 1.880E+00 0.000E+00 8.010E-02 0.000E+00 0.000E+00 0.000E+00 4.790E+01 Y-90 1.560E+01 0.000E+00 4.200E-01 0.000E+00 0.000E+00 0.000E+00 1.290E+05 Y-91M 0.000E+00 0.000E+00 0.0002+00 0.0002+00 0.000E+00 0.OOOE+00 0.OOOE+00 Y-91 1.900E+03 0.000E+00 5.0902+01 0.000E+00 0.000E+00 0.000+E00 7.780E+05 Y-92 1.200E-05 0.000E+00 3.480E-07 0.000E+00 0.000E+00 0.000E+00 3.300E-01 Y-93 5.160E-02 0.000E+00 1.410E-03 0.000E+00 0.000E+00 0.000E+00 1.580E+03

Offsite Dose Calculatron Manual Page 304 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract ZR-95 1.990E+02 6.260E+01 4.310E+01 0.000E+00 9.200E+01 0.000E+00 1.450E+05 ZR-97 9.300E-02 1.840E-02 8.480E-03 0.000E+00 2.790E-02 0.000E+00 4.9.80E+03 NS-95 1.690E+04 9.370E+03 5.160E+03 0.000E+00 9.080E+03 0.000E+00 4.010E+07 NBo97 0.000E+00 0.0002E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.610E-09 MO-99 0.000E+00 5.470E+06 1.040E+06 0.000E+00 1.250E+07 0.000E+00 9.800E+06 TC-99M 6.770E-01 1.890+E00 2.450E+01 0.000E+00 2.810E+01 1.050E+00 1.240E+03 TC-101 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 RU-103 2.180E+02 0.000E+00 9.31 OE+01 0.000E+00 7.670E+02 0.000E+00 1.820E+04 RU-105 1.880E-04 0.000E+00 7.290E-05 0.000E+00 2.370E-03 0.OOOE+00 1.520E-01 RU-106 4.500E+03 0.000E+00 5.670E+02 0.000E+00 8.680E+03 0.000E+00 2.160E+05 RH-103M 0.OOOE+00 0.000E+00 0.000E+O0 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.000E+00 AG-110M 1.160E+07 1.090E+07 6.650E+06 0.000E+00 2.090E+07 0.000E+00 3.070E+09 SB-122 9.310E+04 9.710E+04 1.180E+06 1.540E+04 4.580E+04 2.000E+04 1,160E+07 SB-124 5.510E+06 1.020E+05 2.150E+06 1.250E+04 0.000E+00 4.810E+06 1.110E+08 SB-125 4.380E+06 4.790E+04 1.030E+06 4.190E+03 0.000E+00 3.850E+06 3.410E+07 TE-125M 3.600E+06 1.300E+06 4.820E+05 1.010E+06 0.000E+00 0.000E+00 1.060E+07 TE-127M 1.010E+07 3.590E+06 1.200E+06 2.410E+06 4.100E+07 0.000E+00 2.520E+07 TE-127 1.490E+02 5.290E+01 3.210E+01 1.030E+02 6.050E+02 0.000E+00 1.150E+04 TE-129M 1.330E+07 4.920E+06 2.100E+06 4.280E+06 5.550E+07 0.000E+00 4.980E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 7.890E+04 3.780E+04 3.150E+04 5.690E+04 3.940E+05 0.000E+00 3.030E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E÷00 0.000E+00 TE-132 5.130E+05 3.250E+05 3.050E+05 3.430E+05 3.120E+06 0.000E+00 1.030E+07 1-130 8.990E+05 2.600E+06 1.040E+06 2.120E+08 4.010E+06 0.000E+00 2.000E+06 1-131 6.450E+08 9.030E+08 4.850E+08 2.640E+1 I 1.560E+09 0.000E+00 1.790E+08 1-132 3.480E-01 9.110E-01 3.270E-01 3.070E+01 1.430E+00 0.0002E00 3.970E-01 1-133 8.690E+06 1.470E+07 4.500E+06 2.060E+09 2.590E+07 0.000+E00 1.120E+07 1-134 0.000E+00 0.000E+00 0.O00E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 i-135 2.960E+04 7.620E+04 2.820E+04 4.900E+06 1.200E+05 0.000E+00 8.440E+04 CS-134 2.940E+10 6.930E+10 3,210E+10 0.000E+00 2.200E+10 8.410E+09 8.620E+08 CS-136 1.330E+09 5.2502+09 3.530E+09 0.000+E00 2.860E+09 4.510E+08 4.230E+08 CS-137 4.020E+10 5.340E+10 1.860E+10 0.000E+00 1.820E+10 7.060E+09 7.600E+08 CS-138 0.000E+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

Offsite Dose Calculation Manual Page 305 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS TEEN (M2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract BA-139 1.040E-08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.310E-08 BA-140 5.830E+06 7.140E+03 3.750E+05 0.000E+00 2.420E+03 4.800E+03 8.980E+06 BA-141 0.000E+00 0.OOOE+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 LA-140 9.760E-01 4.750E-01 1.260E-01 0.000E+00 0.000E+00 0.000E+00 2.730E+04 LA-142 1.980E-12 8.780E-13 2.190E-13 0.000E+00 0.000E+00 0.000E+00 2.670E-08 CE-141 1.060E+03 7.110E+02 8.170E+01 0.000E+00 3.350E+02 0.000E+00 2.030E+06 CE-143 9.230E+00 6.720E+03 7.500E-01 0.000E+00 3.010E+00 0.000E+00 2.020E+05 CE-144 7.900E+04 3.270E+04 4.240E+03 0.000E+00 1.950E+04 0.000E+00 1.990E+07 PR-143 3.500E+01 1.400E+01 1.740E+00 0.000E+00 8.130E+00 0.000E+00 1.150E+05 PR-144 0.000E+00 0.OOOE+0Q 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 ND-147 2.180E+01 2.370E+01 1.420E+00 0.OOOE+00 1.390E+01 0.000E+00 8.530E+04 EU-154 4.700E+03 6.070E+02 4.280E+02 0.000E+0_0 2.720E+03 0.000E+00 3.210E+05 EU-155 1.030E+03 9.970E+01 6.170E+01 0.000E+00 3.900=+02 0.000E+00 5.710E+05 W-187 1.440E+03 1.170E+03 4.110E+02 0.OOOE+00 0.000E+00 0.000E+00 3.180E+05 NP-239 8.390E-01 7.910E-02 4.390E-02 0.000E+00 2.480E-01 0.000E+00 1.270E+04

Offsite Dose Calculation Manual Page 306 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS CHILD (i 2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract H-3 0.000E+00 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 C-14 1.650E+06 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 NA-24 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 P-32 9.330E+.10 .. 4.370E÷09 3.600E+09 ..000E+00 ..000E+00 0.000E+00 2.580E+09 CR-51 0.OOOE+00 0.000E+00 1.220E+04 6.790E+03 1.860E+03 1.240E+04 6.490E+05 MN-54 0.000E+00 2.510E+06 6.690E+05 0.000E+00 7.050E+05 0.000E+00 2.1102+06 MN-56 0.000E+00 1.570E-03 3.5502-04 0.000E+00 1.9002-03 0.OOOE+00 2,280E-01 FE-55 1.450E+06 7.700E+05 2.390E+05 0.000E+00 O.000E+00 4.360E+05 1.430E+05 FE-59 1.570E+06 2.530E+06 1.260E+06 0.0002+00 0.000E+00 7.350E+05 2.640E+06 CO-57 0.000E+00 4.600E+05 9.320E+05 0.000E+00 0.000E÷00 0.000E+00 3.770E+06 CO-58 0.000E+00 1.460E+06 4.460E+06 0.000E+00 0.000E-00 0.000E+00 8.500E+06 CO-60 0.000E+00 5.180E+06 1,530E+07 0.000E+00 0.000E+00 0.000E+00 2.870E+07 NI-63 3.560E+09 1.900E+08 1.210E+08 0.000E+00 0.0002E00 0.000E+00 1.280E+07 NI-65 1.990E-01 1.870E-02 1.090E-02 0.000E+00 0.000E+00 0.000E+00 2.290E+00 CU-64 O.000E+00 8.410E+03 5.080E+03 0.000E+00 2.030E+04 0.000E+00 3.950E+05 ZN-65 4.960E+08 1.320E+09 8.220E+08 0.000E+00 8.330E+08 0.000E+00 2.320E+08 ZN-69 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 BR-82 0.000E+00 0.000E+00 1.390E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 5.620E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.002E+00 RB-86 0.000E+00 1.050E+09 6.470E+08 0.000E+00 0.0002+00 0.000E+00 6.770E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000+E00 0.000+E00 0.000E+00 RB-89 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 SR-89 1.390E+10 0.000E+00 3.970E+08 0.000÷+00 0.000E+00 0.OOOE+00 5.380E+08 SR-90 2.350E+11 0.000E+00 5.950E+10 0.000+E00 0.000E+00 0.000+E00 3.190E+09 SR-91 2.970E+05 0.000E+00 1.120E+04 0.000E+00 0.000E+00 0.000E+00 6.550E+05 SR-92 4.590E+10 0.000E+00 1.840E-01 0.000E+00 0.000E+00 0.000E+00 8.690E+01 Y-90 3.860E+01 0.000E+00 1.030E+00 0.0002+00 0.000E+00 0.000E+00 1.100E+05 Y-91M 0.000E+00 0.OOOE+00 0.0002+00 0.000E+00 0.00012+00 0.000E+00 0.000E+00 Y-91 4.690E+03 0.000E+00 1,250E+02 0.0002+00 0.000E+00 0.000E+00 6.250E+05 Y-92 2.950E-05 0.000E+00 8.440E-07 0.000E+00 0.000E+00 0.000E+00 8.520E-01 Y-93 1.270E-01 0.00015+00 3.480E-03 0.0002+00 0.000E+00 0.000E+00 1.890E+03 ZR-95 4.610E+02 1.010E+02 9.030E+01 0.0002+00 1.450E+02 0.000E+00 1.060E+05

Offsite Dose Calculation Manual Page 307 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract ZR-97 2.260E-01 3.270E-02 1.930E-02 0.000E+00 4.690E-02 0.000E+00 4.950E+03 NB-95 3.810E+04 1.480E+04 1.060E+04 0.0002+00 1.390E+04 0.000E+00 2.750E+07 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.740E-07 MO-99 0.000E+00 9.950E+06 2.460E+06 0.000E+00 2.120E+07 0.000E+00 8.230E+06 TC-99M 1.550E+00 3.040E+00 5.040E+01 0.000E+00 4.420E+01 1.550E+00 1.730E+03 TC-101 0.000E+00 0.000E+00 O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 5.150E+02 0.000E+00 1.980E+02 0.000E+00 1.300E+03 0.000E+00 1.330E+04 RU-105 4.590E-04 0.000E+00 1.660E-04 0.0O0E+00 4.030E-03 0.000E+00 2.990E-01 RU-106 1.110E+04 0.000E+00 1.380E+03 0.000E+00 1.500E+04 0.000E+00 1.720E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 RH-106 O.002E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-1 10M 2.510E+07 1.690E+07 1.350E+07 0.000E+00 3.150E+07 0.000E+00 2.010E+09 SB-122 7.680E+04 8.010E+04 9.700E+05 1.270E+04 3.780E+04 1.6-0E+04 9.540E+06 SB-124 1.300E+07 1.690E+05 4.570E+06 2.880E+04 0.000E+00 7.240E+06 B.150E+07 SB-125 I.040E+07 8.050E+04 2.190E+06 9.670E+03 0.000E+00 5.820E+06 2.490E+07 TE-125M 8.850E+06 2.400E+06 1.1 80E+06 2.480E+06 0.000E+00 0.000E+00 8.540E+06 TE-127M 2.500E+07 6.720E+06 2.960E+06 5.970E+06 7.120E+07 0.0002+00 2.020E+07 TE-127 3.670E+02 9.910E+01 7.880E+01 2.540E+02 1.050E+03 0.000E+00 1.440E+04 TE-129M 3.270E+07 9.130E+06 5.080E+05 1.050E+07 9.600E+07 0.000E+00 3.990E+07 TE-129 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.340E-09 TE-131M 1 .920E+05 6.640E+04 7.070E+04 1.370E+05 6.430E+05 0.000E+00 2.690E+06 TE-131 0.000E+00 0.0OE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 TE-132 1.230E+06 5.420E+05 6.550E+05 7.900E+05 5.040E+06 0.000E+00 5.460E+06 1-130 2.100E+06 4.250E+06 2.190E+06 4.680E+08 6.350E+06 0.000E+00 1.990E+06 1-131 1.570E+09 1.570E+09 8.950E+08 5.210E+11 2.580E+09 0.000E+00 1.400E+08 1-132 8.230E-01 1.510E+00 6.960E-01 7.020E+01 2.320E+00 0.000E+00 1.780E+00 1-133 2.110E+07 2.610E+07 9.880E+06 4.850E+09 4.350E+07 O.O00E+00 1.050E+07 1-134 0.000E+00 0.000E+00 0.00OE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1-135 7.000E+04 1.260E+05 5.960E+04 1.120E+07 1.930E+05 0.000E+00 9.600E+04 CS-134 6.790E+10 1.110E+11 2.350E+10 0.000E+00 3.450E+10 1.240E+10 6.010E+08 CS-136 3.01 OE+09 8.280E+09 5.360E+09 0.000E+00 4.410E+09 6.580E+08 2.910E+08 CS-137 9.670E+10 9.260E+10 1.370E+10 0.000E+00 3.020E+10 1.090E+10 5.800E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

Offsite Dose Calculation Manual Page 308 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS CHILD (M 2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gltract BA-139 2.560E-08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.480E-06 BA-140 1.410E+07 1.230E+04 8.210E+05 0.000E+00 4.010E+03 7.340E+03 7.120E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E÷00 0.0002+00 0.000E+00 0.0002+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.0000+00 0.000E+00 0.0002+00 0.0002+00 LA-140 2.310E+00 8.090E-01 2.730E-01 0.000E+00 0.000E+00 0.000E+00 2.260E+04 LA-142 4.770E-12 1.520E-12 4.770E-13 0.000E+00 0.000E+00 0.000E+00 3.020E-07 CE-141 2.620E+03 1.310E+03 1.940E+02 0.000E+00 5.730E+02 0.000E+00 1.630E+06 CE-143 2.270E+01 1.230E+04 1.780E+00 0.000E+00 5.150E+00 0.000E+00 1.800E+05 CE-144 1.950E+05 6.100E+04 1.040E+04 0.000E+00 3.380E+04 0.OOOE+00 1.590E+07 PR-143 8.670E+01 2.600E+01 4.300E+00 0.000E+00 1.410E+01 0.000E+00 9.350E+04 PR-144 0.O00E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 5.340E+01 4.320E+01 3.350E+00 0.000E+00 2.370E+01 0.000E+00 6.850E+04 EU-154 1.130E+04 1.020E+03 _ 9.290E+02 0.000E+00 4.470E+03 0.000E+00 2.360E+05 EU-155 2.360E+03 1.700E+02 1.330E+02 0.000E+00 6.630E+02 0.000E+00 4.250E+05 W-187 3.490E+03 2.070E+03 9.270E+02 0.000E+00 0.000E+00 0.000E+00 2.900E+05 NP-239 2.060E+00 1.480E-01 1.040E-01 0.000E+00 4,280E-01 0.000E+00 1.100E+04

Offsite Dose Calculation Manual Page 309 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS INFANT (M2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.O00E+00 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4,860E+03 C-14 3.230E+06 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 NA-24 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 P-32 1.920E+1 1 1.130E+10 7.450E+09 .0.000E+00 0.000E+00 0.000E+00 2.600E+09 CR-51 0.000E+00 0.000E+00 1.940E+04 1.260E+04 2.760E+03 2.460E+04 5.650E+05 MN-54 0.000E+00 4.670E+06 1.060E+06 0.000E+00 1.040E+06 0.000E+00 1.720E+06 MN-56 0.000E+00 3.850E-03 6.630E-04 0.000E+00 3.310E-03 0.000E+00 3.490E-01 FE-55 1.760E+06 1.130E+06 3.030E+05 0.000E+00 0.000E+00 5.540E+05 1.440E+05 FE-59 2.920E+06 5.110E+06 2.010E+06 0.000E+00 0.000E+00 1.510E+06 2.440E+06 CO-57 0.0002+00 1.070E+06 1.750E+06 0.000E+00 0.000E+00 0.000E+00 3.660E+06 CO-58 0.000E+00 2.910E+06 7.270E+06 0.000E+00 0.000E+00 0.000E+00 7.260E+06 CO-60 0.000E+00 1.060E+07 2.500E+07 0.OOOE+00 0.000E+00 0.OOOE+00 2.520E+07 NI-63 4.190E+09 2.590E+08 1.450E+08 _ 0.000E+00 0.0002+00 0.000E+00 1.290E+07 NI-65 4.210E-01 4.770E-02 2.170E-02 0.000E+00 0.000E+00 0.000E+00 3.630E+00 CU-64 0.000E+00 2.090E+04 9.680E+03 0.000E+00 3.540E+04 0.000E+00 4.290E+05 ZN-65 6.660E+08 2.280E+09 1.050E+09 0.000E+00 1.110E+09 0.000E+00 1.930E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 2.330E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 1.190E-01 0.0002+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000+E00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.00020E0 0.0002+00 0.0000+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.670E+09 1.320E+09 0.000E+00 0.000E+00 0.000E+00 6.830E+07 RB-88 0.000E+00 0.0O0E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 RB-89 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 2.640E+10 0.000E+00 7.580E+08 0.000E+00 0.000E+00 0.000E+00 5.430E+08 SR-90 2.550E+11 0.000E+00 6.500E+10 0.000E+00 0.000E+00 0.000E+00 3.190E+09 SR-91 6.180E+05 0.000E+00 2.240E+04 0.000+E00 0.000E+00 0.000E+00 7.310E+05 SR-92 9.760E+00 0.000E+00 3.620E-01 0.000+E00 0.000E+00 0.000E+00 1.050E+02 Y-90 8.160E201 0.000E+00 2.190E+00 0.0002E00 0.000E+00 0.000E+00 1.130E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 8.800E+03 0.0002E00 2.340E+02 0.000E+00 0.000E+00 0.000E+00 6.310E+05 Y-92 6.270E-05 0.000E+00 1.760E-06 0.0002+00 0.000E+00 0.0002+00 1.200E+10 Y-93 2.700E-01 0.000E+00 7.350E-03 0.000E+00 0.000E+00 0.000E+00 2.130E+03 ZR-95 8.190E+02 2.000E+02 1.420E+02 0.000E+00 2.150E+02 0.000E+00 9.940E+00

Offsite Dose Calculation Manual Page 310 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS INFANT (M2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract ZR-97 4.790E-01 8.220E-02 3.760E-02 0.000E+00 8.290E-02 0.000E+00 5.240E+03 NB-95 7.120E+04 2.930E+04 1.690E+04 0.000E+00 2.100E+04 0.000E+00 2.470E+07 NB-97 6.590E-12 1.410E-12 5.070E-13 O.O00E+00 1.100E-12 0.000E+00 4.440E-07 MO-99 0.000E+00 2.540E+07 4.960E+06 0.000E+00 3.800E+07 0.OOOE+00 8.830E+06 TC-99M 3.230E+00 6.660E+00 8.570E+01 0.000E+00 7.160E+01 3.480E+00 1.930E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 RU-103 1.040E+03 0.000E+00 3.490E+02 0.000E+00 2.170E+03 0.000E+00 1.270E+04 RU-105 9.670E-04 0.000E+00 3.260E-04 0.000E+00 7.110E-03 0.000E+00 3.850E-01 RU-106 2.280E+04 0.000E+00 2.850E+03 0.000E+00 2.700E+04 0.0002+00 1.730E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 RH-1 06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 4.630E+07 3.380E+07 2.240E+07 0.000E+00 4.840E+07 0.000E+00 1.750E+09 SB-122 7.680E+04 8.010E+04 9.700E+05 1.270E+04 3.780E+04 1.650E+04 9.540E+06 SB-124 2.510E+07 3.700E+05 7.790E+06 6.670E+04 0.000E+00 1.570E+07 7.750r=+07 SB-125 1.790E+07 1.740E+05 3.690E+06 2.250E+04 0.000E+00 1.130E+07 2.390E+07 TE-125M 1.810E+07 6.050E+06 2.450E+06 6.090E+06 0.000E+00 0.000E+00 8.620E+06 TE-127M 5.050E+07 1.680E+07 6.120E+06 1.460E+07 1.240E+08 0.000E+00 2.040E+07 TE-127 7.800E+02 2.610E+02 1.680E+02 6.350E+02 1.900E+03 0.000E+00 1.640E+04 TE-129M 6.7102=+07 2.300E+07 1.030E+07 2.580E+07 1.680E+08 0.000E+00 4.010E+07 TE-129 0.000E+00 0.0002+00 0.0000+00 0.0002+00 0.0002+00 0.000E+00 2.000E-08 TE-131M 4.050E+05 1.630E+05 1.350E+05 3.310E+00 1.120E+06 0.000E+00 2.750E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2,520E+06 1.250E+06 1.170E+06 1.840E+06 7.820E+06 0.000E+00 4.620E+06 1-130 4.320E+06 9.510E+06 3.820E+06 1.070E+09 1.040E+07 0.000E+00 2.040E+06 1-131 3.270E+09 3.850E+09 1.690E+09 1.270E+12 4.5002+09 0.000E+00 1.370E+08 1-132 1.710E+00 3.470E+00 1.230E+00 1.630E+02 3.870E+00 0.000E+00 2.810E+00 1-133 4.460E+07 6.490E+07 1.900E+07 1.180E+10 7.630E+07 0.000E+00 1.100E+07 1-134 0.000E+00 0.000E+00 0.0002+00 1.210E-09 0.000E+00 0.0002+00 0.0002+00 1-135 1.460E+05 2.900E+05 1.060E+05 2.600E+07 3.230E+05 0.000E+00 1.050E+05 CS-1:34 1.090E+11 2.040E+11 2.060E+10 0.000E+00 5.250E+10 2.150E+10 5,540E+08 CS-136 5.880E+09 1.730E+10 6.460E+09 0.000E+00 6.900E+09 1.410E+09 2.630E+08 CS-137 1.540E+11 1.810E+11 1.280E+10 0.000E+00 4.850E+10 1.960E+10 5.650E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0,000E+00

Offsite Dose Calculation Manual Page 311 of 325 Revision 5 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS INFANT (M2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Thody Thyroid Kidney Lung Gitract BA-139 5.450E-08 0.000+E00 1.580E-09 0.000E+00 0.OOOE+00 0.000E+00 3.450E-06 BA-140 2.890E+07 2.890E+04 1.490E+06 0.000E+00 6.870E+03 1.780E+04 7.11OE+06 BA-141 0.OOOE+00 0.000E+00 0.0002+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.OOOE+00 0.000E200 0.000E+00 0.000E+00 O.OOOE.00 LA-140 4.840E+00 1.910E+00 4.900E-01 0.000E+00 0.000E+00 0.000E+00 2.240E+04 LA-142 0.000E+00 0.000E÷00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 CE-141 5.200E+03 3.170E+03 3.730E+02 0.000E+00 9.780E+02 0.000E+00 1.640E+06 CE-143 4.800E+01 3.180E+04 3.630E+00 0.000E+00 9.270E+00 0.OOOE+00 1.860E+05 CE-144 2.790E+05 1.140E+05 1.560E+04 0.000E+00 4.620E+04 0.OOOE+00 1.600E+07 PR-143 1.790E+02 6.710E+01 8.890E+00 0.000E+00 2.490E+01 0.000E+00 9.470E+04 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 0.000E+00 0.OOOE+00 ND-147 1.060E+02 1.090E+02 6.660E+00 0.OOOE+00 4.190E+01 0.000E+00 6.890E+04 EU-154 1.300E+04 1.800E+03 1.080E+03 0.000E+00 4.890E+03 0.0002+00

- 2.250E+05 EU-155 2.650E+03 3.060E+02 1.580E+02 0.000E+00 6.850E+02 0.000E+00 4.100E+05 W-187 7.350E+03 5.110E+03 1.770E+03 0.000E+00 0.000E+00 0.000+E00 3.000E+05 NP-239 4.360E+00 3.900E-01 2.210E-01 0.0002+00 7.780E-01 0.000E+00 1.130E+04

Offsite Dose Calculation Manual Page 312 of 325 Revision 5 Attachment 13 Environmental Monitoring Sites for REMP SAMPLE SITE SECTOR 1DISTANCE' DESCRIPTION km mi DRI NW 0.6 0.4 Onsite, Along Cliffs DR2 NW 2.7 1.7 Rt. 765, Auto Dump DR3 2.3 1.4 Rt. 765, Giovanni's Tavern (Knotty Pine)

DR4 WSW 2.0 1.2 Rt. 765, Across from White Sand Drive DR5 SW 2.4 1.5 Rt. 765 at Johns Creek DR6, A4 SSW 2.9 1.8 Rt. 765 at Lusby, Frank's Garage DR7, Al, 1b4, Ib5, Ib6 S 0.7 0.5 Onsite, before entrance to Camp Conoy DR8, A2 SSE 2.5 1.5 Camp Conoy Road at Emergency Siren DR9, A3 SE 2.6 1.6 Bay Breeze Road DRI 0 NW 6.4 4.0 Calvert Beach Rd & Decatur St DR11 WNW 6.6 4.1 Dirt Road off Mackall Rd & Parran Rd DR12 W 6.7 4.2 Bowen Rd & Mackall Rd DR13 WSW 6.1 3.8 Mackall Rd near Wallville DR14 SW 6.4 4.0 Rodney Point DR1 5 SSW 6.2 3.9 Mill Bridge Rd & Turner Rd DRI 6 S 6.5 4.1 Across from Appeal School DR17 SSE 5.9 3.7 Cove Point Rd & Little'Cove Point Rd DR18 SE 7.1 4.5 Cove Point DR19 NW 4.4 2.8 Long Beach DR20 NNW 0.4 0.3 Onsite, near shore DR21, A5, Ib7, Ib8, Ib9 WNW 19.3 12.1 Emergency Operations Facility DR22 S '2.5 7.8 Solomons Island DR23 ENE 2.6 7.9 Taylors Island, Carpenter's Property Wal NNE 0.2 0.1 Intake Area Wa2, tal, la2 N 0.3 0.2 Discharge Area Wb1 ESE 0.6 0.4 Shoreline at Barge Road Ibl, Ib2, Ib3, SSE 2.6 1.6 Garden Plot off Bay Breeze Rd 1a4, ia5 (Area not influence.d by Plant Patuxent River Discharge) la3 E 0.9 0.6 Camp Conoy la6 NNW 0.7 6.7 Kenwood Beach 1 Distance and direction from the central point of the two containment buildings.

Offsite Dose Calculation Manual Page 313 of 325 Revision 5 Attachment 14 Radiological Environmental Monitoring Program Surveillances for Direct Radiation (1) Each sample point shall be monitored using two or more dosimeters OR one instrument for measuring and recording dose rate continuously.

(2) LLD for TLDs used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

Offsite Dose Calculation Manual Page 314 of 325 Revision 5 Attachment 15 Radiological Environmental Monitoring Program Surveillances for Airborne Activity RADIOIODINE CANNISTER PARTICULATE FILTER (1)

PARAMETER UNITS FREQUENCY LLD ACTION LEVEL 5 Gross Beta Activity pCi/mr3 at least weekly (2) 0.01 N/A (3)

Cs-134 pCi/me at least quarterly (4) 0.05 10.0 Cs-137 pCifm 3 at least quarterly (4) 0.06 20.0 (1) All samples consist of continuous sampler operation with sample collection weekly, or more frequently if required by dust loading.

(2) Analyze for gross beta activity 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 radon and thoron daughter decay.

(3) Although there is not an ACTION Level for gross beta activity, ifthis parameter is greater than ten times the yearly mean of the control sample, perform GAMMA ISOTOPIC ANALYSIS on the individual sample.

(4) Perform a GAMMA ISOTOPIC ANALYSIS of a quarterly COMPOSITE SAMPLE. A separate COMPOSITE SAMPLE shall be prepared for each sample location, Al thru A5. Each COMPOSITE SAMPLE shall be a prepared from individual particulate filter samples collected during the applicable calendar quarter and from a single location.

(5) If an ACTION Level is exceeded, check the initiating conditions listed in Radiological Environmental Monitoring Program section 5.c and Radiolog[cal Environmental Monitoring Program section 5.d, and perform the corrective actions specified In Radiological Environmental Monitoring Program section 7.d and/or Radiological Environmental Monitoring Program section 7.e.

Offstte Dose Calculation Manual Page 315 of 325 Revision 5 Attachment 16 Radiological Environmental Monitoring Program Surveillances for Waterbome Activity SURFACE WATER SAMPLE (1)

PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (2)

H-3 pCi/I at least quarterly 2000(') 20,000(4)

Mn-54 pCi/l at least monthly 15 1000 Fe-59 pCi/I at least monthly 30 400 Co-58 pCi/l at least monthly 15 1000 Co-60 pCi/I at least monthly 15 300 Zn-65 pCi/I at least monthly 30 300 Zr-95 I Nb-95 pCi/I at least monthly 15 400 1-131 pCi/I at least monthly l(s) 2 Cs-1 34 pCi/I at least monthly 15 30 Cs-137 pCi/I at least monthly 18 50 Ba-1 40 / La-1 40 pCi/I at least monthly 15 200 SHORELINE SEDIMENT SAMPLE PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (2)

Cs-134 pCi/kg, dry at least semiannually 150 N/A Cs-137 pCi/kg, dry at least semiannually 180 N/A (1) The water sample shall be a composite of individual samples collected over a I month period.

(2) If an ACTION Level is exceeded, check the initiating conditions listed in sections REMP SECTION REMP SECTION 5.d, and perform the corrective actions specified in section REMP SECTION 7.d 5.c and and/or REMP SECTION 7.e.

(3) If a drinking water pathway does not exist, a value of 3000 pCi/I may be used.

(4) If a drinking water pathway does not exist, a value of 30,000 pCi/I may be used.

(5) LLD for drinking water samples. If no drinking water pathway exists, the LLD of the gamma isotopic analysis may be used.

Offsite Dose Calculation Manual Page 316 of 325 Revision 5 Attachment 17 Radiological Environmental Monitoring Program Surveillances for Ingestible Activity FISH AND INVERTEBRATES (1)

PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (5)

Mn-54 pCi/kg, wet (2) 130 30,000 Fe-59 pCi/kg, wet (2) 260 10,000 Co-58 pCi/kg, wet (2) 130 30,000 Co-60 pCi/kg, wet (2) 130 10,000 Zn-65 pCi/kg, wet (2) 260 20,000 Cs-1 34 pCi/kg, wet (2) 130 1000 Cs-1 37 pCi/kg, wet (2) 150 2000 MILK PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (5) 1-131 pCi/I, wet at least monthly (4) 1 3 Cs-1 34 pCi/I, wet at least monthly (4) 15 60 Cs-1 37 pCi/I, wet at least monthly (4) 18 70 Ba-140 / La-140 pCi/i, wet at least monthly (4) 15 300 FOOD P'RODUCTS PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (5) 1-131 pCi/kg, wet at least monthly(3 ) 60 100 Cs-1 34 pCi/kg, wet at least monthlye3 ) 60 1000 Cs-137 pCi/kg, wet at least monthly( 3 ) 80 2000 (1) Edible portions of the fish and invertebrates shall be used for analysis.

(2) The fish and invertebrates shall be sampled at least once per year in season, or semiannually ifthey are not seasonal.

The food products shall be sampled during the growing season.

The milk samples need be collected and analyzed only ifthe milk is commercially available in quantities greater than 310 liters per year (see NUREG-01 33, 5.3.1.1).

(5) if an ACTION Level is exceeded, check the initiating conditions listed in Radiological Environmental Monitoring Program section 5.c and Radiological Environmental Monitoring Program section 5.d, and perform the corrective actions specified in Radiological Environmental Monitoring Program section 7.d and/or Radiological Environmental Monitoring Program section 7.e.

Offsite Dose Calculation Manual Page 317 of 325 Revision 5 Attachment 18 Map of Environmental Monitoring Sites for REMP 5 Km Radius M 'Ar N" .

",n.

.~z . . . .. ."-*-

o,* , ....... " .'.,..:;..,.-,...  :.........

. . . . . . . . . . . . . . . ... '-'-,lluSt.

h. '.i'V-'::

,. ,,.. .- . .. --. -. i,

Offsite Dose Calculation Manual Page 318 of 325 Revision 5 Attachment 19 DM

- ~~CCUPW1WtI mp 7

Offsite Dose Calculation Manual Page 319 of 325 Revision 5 Attachment 20 Environmental Monitoring Sites for ISFSI STATION DESCRIPTION DISTANCE' DIRECTIONI tsetor AIR SAMPLERS A1z On Site Before Entrance to Camp Conoy 0.7 SE SFA1 Meteorological Station 0.4 NW SFA2 CCNPP Visitor's Center 0.7 NNE SFA3 North Northwest of ISFSI 0.1 NNW SFA4 South of ISFSI 0.1 S TLD LOCATIONS SFDR1 Southwest of ISFSI 0.1 SW SFDR2 North of ISFSI 0.1 N SFDR3 North Northeast of ISFSI 0.1 NNE SFDR4 Northeast of ]SFSI <0.1 NE SFDR5 East of ISFSI <0.1 E SFDR6 East Southeast of ISFSI 0.1 ESE SFDR7 CCNPP Visitor's Center 0.7 NNE SFDR8 North Northwest of ISFS1 0.1 NNW SFDR9 South of ISFS1 0.1 S SFDR10 North Northwest of ISFSI 0.1 NNW SFDR11 West Northwest of ISFSI 0.1 WNW SFDR12 West of ISFSI <0.1 W SFDR13 South Southwest of ISFSI <0.1 SSW SFDR14 South Southeast of ISFSI 0.1 SFDR15 SSE East Northeast of ISFSI <0.1 ENE SFDR16 West Southwest of ISFS1 <0.1 2 WSW DR7 On Site Before Entrance to Camp Conoy 0.7 SE DR30 Meteorological Station 0.4 NW VEGETATION SFbl Meteorological Station 0.4 NW SFb2 CCNPP Visitor's Center 0.7 NNE SFb3 North Northwest of ISFSI 0.1 NNW SFb4 South of ISFSI 0.1 S SFb5 On Site Before Entrance to Camp Conoy 0.7 SE SOIL SFS1 Meteorological Station 0.4 NW SFS2 CCNPP Visitor's Center 0.7 NNE SFS3 North Northwest of ISFSI 0.1 NNW SFS4 South of ISFSI 0.1 S SFS5 On Site Before Entrance to Camp Conoy 0.7 SE Distance and direction from the Central Point of the ISFSI.

2 Common to both the REMP and the ISFSIMP.

Offsite Dose Calculation Manual Page 320 of 325 Revision 5 Attachment 21 Map of Environmental Monitoring Sites for ISFSI SN NNW NNE C/'LVERT 1000 Foot

- So,

-- , ¢ NE N

NW ENE WNW W E WSW SW ESE SSE SESE DR SFDR SFA -

-(Plant) Direct Radliaton Spent Fuel Direct Radiation Spent Fuel Air Sampler I

PIC -Pressurized Ion Chamber

Offsite Dose Calculation Manual Page 321 of 325 Revision 5 Attachment 22 Map of Environmental Monitoring Sites for ISFSI (ENLARGED) 9 DR30 PIC3 SFA I NW NE WNW ENE SFDR 15 W

SFDR 5 I SFDR6 WSW ESE SW A1 SsW SE SSE A - MrSanpler S DR - (Plant) Direct Radiation SFDR - Spent Fuel Drfect Radiation SFA - SpenntFudAir Sampler PIC - Presurized Ion Chamber

Offsite Dose Calculation Manual Page 322 of 325 Revision 5 Attachment 23 Effluent Radiation Monitors Description Radiation Radiation Element Indicator Liquid Waste Discharge Radiation Monitor O-RE-2201 O-RI-2201 Steam Generator Blowdown Effluent Radiation Monitor 1-RE-4095 1-RI-4095 Steam Generator Blowdown Effluent Radiation Monitor 2-RE-4095 2-RI-4095 Steam Generator Blowdown Tank Radiation Monitor 1-RE-4014 I-RI-4014 Steam Generator Blowdown Tank Radiation Monitor 2-RE-4014 2-RI-4014 Wide Range Gas Monitor, Low Range 1-RE-5416 1-RIC-5415 Wide Range Gas Monitor, Low Range 2-RE-5416 2-RIC-5415 Westinghouse Plant Vent Stack Monitor I-RE-5415 1-RI-5415 Westinghouse Plant Vent Stack Monitor c-J 2-RE-5415 2-RI-5415 GASEOUS RADWASTE PROCESSING SYSTEM Radiation O-RE-2191 O-RE-2191 Monitor Accident Monitors Not Addressed By The ODCM Wide Range Gas Monitor, Mid Range I-RE-5417 Wide Range Gas Monitor, High Range I-RE-5418 Wide Range Gas Monitor, Mid Range 2-RE-5417 Wide Range Gas Monitor, High Range 2-RE-5418

Offsite Dose Calculation Manual Page 323 of 325 Revision 5 Attachment 24 List of Effective Pages Page No. Change No. Page No Change No. Page No Change No. Page No. Change No.

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