BYRON 2019-0035, Submittal of 2018 Annual Radioactive Effluent Release Report

Submittal of 2018 Annual Radioactive Effluent Release Report

ML19108A010
Person / Time
Site:	Byron
Issue date:	04/18/2019
From:	Kanavos M Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BYRON 2019-0035
Download: ML19108A010 (289)

Text

S

. Byron Generating Station 4450 North German Church Road j-zz Exe[onGeneration April 18, 2019 LTR: BYRON2OY9-0035 100FR5O.36a File 1.10.0101 (YD.101) 2.12.1522(20.111)

United States Nuclear Regulatory Commission AITN: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455

Subject:

2018 Annual Radioactive Effluent Release Report Enclosed is the Annual Radioactive Effluent Release Report for Byron Station. This report is being submiffed in accordance with 10 CFR 50.36 a(2), Technical specifications on effluents from nuclear power reactors, and includes a summary of radiological liquid and gaseous effluents and solid waste released from the site from January 2018 through December 2018.

We are enclosing Revision 14 of the Byron Station Offsite Dose Calculation Manual (ODCM),

the ODCM Change Determination and the ODCM Change Log in accordance with ODCM Section 5.4.1.

If you have any questions regarding this information, please contact Mr. Jon Cunzeman, Regulatory Assurance Manager, at (81 5) 406-2800.

Respectfully, Mark E. Kanavos Site Vice President Byron Nuclear Generating Station M EKIJG/ZC/rm Enclosures cc: Darrell J. Roberts, Regional Administrator NRC Region III

Byron Station ODCM Revision 14 Change Summary Matrix Administrative Changes Determination A Technical Changes (Figure 2-1 Simplified HVAC & Gaseous Effluent Flow Diagram) Determination B Technical Changes (Bypass of U2 SJAE offgas filter unit) Determination C Technical Changes (New Dosimeter Location) Determination D Technical Changes (Duplicate Environmental Dosimeter Additions) Determination E Item (old) Rev. (new) Rev. Determi Description of Change No. page No. page No. nation Identifier 1 . 61 of 1 88 61 of 1 88 B

• Changed containment mini-purge flow from 4,000 to Figure 2-1 Figure 2-1 3,000 cfm.

• Changed Post-LOCA purge flow from 440 to 400 cfm

• Changed Aux Bldg Access Areas flow from 125,400 to 125,460 cfm.

• Changed Aux Bldg Non-Access flow from 1 25,400 to 125,460 cfm.

• Changed Aux Bldg Plenum flows from 135,900 to 135,980 cfm.

• Changed Sample Rooms & Laboratories from 13,000 to 14,430 cfm.

2. 61 of 1 88 61 of 1 88 A Added Flows listed in cfm to Figure 2-1 description Figure 2-1 Figure 2-1

3. 62 of 188 62 of 188 B

• Removed Ui & U2 Condenser Hogging Pump flows Figure 2-1 Figure 2-1 during startup (2,500 cfm).

• Removed Ui & U2 Gland Steam Condenser Normal flow (1 ,432 cfm).

• Added Solid Radwaste flow (8,630 cfm).

• Removed Drumming Station flow (3,100 cfm).

• Removed F (Refueling Operation) from legend key and from Unit 1 &2 Condenser Hogging Pump flow paths.

• Removed N (Normal Operation) from legend key and from Unit 1 &2 Condenser Hogging Pump flow paths.

4. 62 of 1 88 62 of 1 88 A Added Flows listed in cfm to Figure 2-1 description Figure 2-1 Figure 2-1

5. 62 of 1 88 62 of 1 88 C

• Removed Offgas Filter Unit as a result of Figure 2-1 Figure 2-1 Engineering CaIc BYRY6-012 and EC 402668.

• Removed NOTE 3 (Filter unit operates only when high radiation is detected in offgas system effluent discharge).

Page 1 of 2

Byron Station ODCM Revision 14 Change Summary Matrix Administrative Changes Determination A Technical Changes (Figure 2-1 Simplified HVAC & Gaseous Effluent Flow Diagram) Determination B Technical Changes (Bypass of U2 SJAE offgas filter unit) Determination C Technical Changes (New Dosimeter Location) Determination D Technical Changes (Duplicate Environmental Dosimeter Additions) Determination E

6. 1 71 of 1 88 1 71 of 1 88 D Added Two dosimeters at each location to Direct Radiation Table 6-1 Table 6-1 exposure pathway description.

7. 1 73 of 1 88 1 73 of 1 88 E

• Removed Two from the Indicators-Other Direct Table 6-1 Table 6-1 Radiation Sampling Location description of Two at each airborne location listed in Section 1 :

• Changed Direct Radiation Indicators-Other nomenclature from BY-XX-X to BY-XX.

8. 173 of 188 173 of 188 A

• Rearranged listed order of Indicators-Other sampling Table 6-1 Table 6-1 locations to numerical.

9. 1 74 of 1 88 1 74 of 1 88 E

• Changed Direct Radiation Control nomenclature Table 6-1 Table 6-1 from BY-08-X to BY-08 1 0. 1 74 of 1 88 1 74 of 1 88 A

• Rearranged listed order of Indicators-Other sampling Table 6-1 Table 6-1 locations to numerical.

11 . 1 74 of 1 88 1 74 of 1 88 E

• Removed Two from the Control Direct Radiation Table 6-1 Table 6-1 Sampling Location description of Two at each airborne location listed in Section 1 :

1 2. 1 74 of 1 88 1 74 of 1 88 A

• Added QuarterlV to Control and Special Interest Table 6-1 Table 6-1 Sampling or Collection Frequency column.

• Added Gamma Dose Quarterly to Type of Frequency and Analysis column.

1 3. 1 88 of 1 88 1 88 of 1 88 D

• Changed BY-31 4-2 dosimeter location latitude from Table 6-2 Table 6-2 42.07601 to 42.0761 8, longitude from -89.28764 to -

89.28806, distance from 0.43 to 0.48 km, distance from 0.27 to 0.29 mi, direction from 289 to 290 degrees.

Page 2 of 2

Byron Station ODCM Revision 14 Change Determination CYAA1 704100 Station:.. Byron ODCM Revision No: 14 Determination Identifier: A Administrative Changes .

I .

Does the ODCM change maintain the level of radioactsve effluent control required by xYes No IOCFR%O 1301?

Explain:

This ODCM change will maintain the radioactive effluent control required by IOCFR2O.1301, Dose Limits for Individual Members of the Public, which is to ensure total effective dose equivalent to individual members of the public from licensed operation does not exceed O.lrem.

Determination A changes are administrative in nature. The changes include adding units to a flow diagram description, rearranging the order of listed air sample locations to numerical, and adding direct radiation sampling frequencies and type of analysis that had been previously missing from a table.

None of these administrative changes affect the radioactive effluent control required by IOCFR2O.1301?

2.

Does the ODCMchange maintain the level of radioactive effluent control required by _x_s No 1 OCFR2O.1 302?

Explain:

This ODCM change will maintain the level of control required in IOCFR2O. The requirement of IOCFR2O.1 302 is to provide surveys of radiation levels in unrestricted and controlled areas and radioactive materials in effluents released to unrestricted and controlled areas to demonstrate compliance with the dose limits for individual members of the public in 1 OCFR2O.1301.

Determination A changes are administrative in nature. The changes include adding units to a flow diagram description, rearranging the order of listed air sample locations to numerical, and adding direct radiation sampling frequencies and type of analysis that had been previously missing from a table.

None of these administrative changes affect the radioactive effluent control required by I OCFR2O. I 302.

Page 1 of 19

Byron Station ODCM Revision 14 Change Determination CYAA-1 7O31OO Station: Byron ,

ODCM Revision No: 14 Determination Idenllfier, AØrnin strative Changes a Does the ODCM change maintain the level of radioactive effluent control required by _>es _No 4OCFRI9Q and IOCFR72104?

Explain:

This ODCM change will not reduce the control required by 4OCFRI9O. The controls required by 4OCFRI9O and 10CFR72104 include limiting the annual dose equivalent of any member of the public to less than 2% mrem whole body, 75 mrem thyroid, and 25 mrem to any organ as the result of activities from the uranium fuel cycle, including direct radiation from lSFSl.

Determination A changes are administrative in nature. The changes include adding units to a flow diagram description, rearranging the order of listed air sample locations to numerical, and adding direct radiation sampling frequencies and type of analysis that had been previously missing from a table.

None of these changes affect the ability to maintain radioactive effluent and direct radiation controls required by 4OCFR1 g and 10CFR%%.104.

4, Does the 013CM change maintain the level of radioactive effluent control required by _xjes 1 OCFR5O.36a?

Explain:

This ODCM change does not affect the level of control previously established in the ODCM required by I OCFR5O36a. The basic requirement of IOCFR%O36a is to keep releases and the resultant dose to the public as low as reasonably achievable (ALARA). This ODCM change will not reduce the stations ability to keep releases of radioactive materials to unrestricted areas as low as reasonably achievable, as required by 10CFR%Q.36a.

Determination A changes are administrative in nature. The changes include adding units to a flow diagram description, rearranging the order of listed air sample locations to numerical, and adding direct radiation sampling frequencies and type of analysis that had been previously missing from a table.

None of these administrative changes affect the radioactive effluent control required by I OCFR5O,36a.

5. Does the ODCM change marntatn the level of radioactive effluent control reqwred by

. , xYes No 1 OCFR5O Appendix I?

Explain:

IOCFRSO Appendix I states that liquid effluents from each reactor each year shall not expose any individual to more than 3 mrem to the total body or 10 mrem to any critical organ. Gaseous releases of particulates and iodines with halflives >8 days shall not expose any individual organ to more than I 5 mremlyear. Noble gases shall not expose any individual total body to more than 500 mrem/year, skin to more than 3000 mrem/year, gamma dose to I 0 mradlyear, and beta dose to 20 mrad/year.

Determination A changes are administrative in nature. The changes include adding units to a flow diagram description, rearranging the order of listed air sample locations to numerical, and adding direct radiation sampling frequencies and type of analysis that had been previously missing from a table.

None of these administrative changes affect the radioactive effluent control required by IOCFPSO Annendix I.

6. Does the ODCM change maintain the accuracy or reliability of effluent, dose, or setpoint x_Ves calculations?

.g pl&n . .

Page 2 of 19

Byron Station ODCM Revision 14 Change Determination CYAA-I 704100 Station:yrn .

ODCM Revision No: 4 Determination dentitierAAdministrative çjag The accuracy and reliability of effluent, dose, and setpoint calculations will not be affected by this ODCM change. Effluent and setpoint calculations will continue to be performed using the established ODCM methodology.

Determination A changes are administrative in nature. The changes include adding units to a flow diagram description, rearranging the order of listed air sample locations to numerical, and adding direct radiation sampling frequencies and type of analysis that had been previously missing from a table.

None of these administrative changes affect the accuracy or reliability of effluent, dose, or tpqtgculations.s. .

7. . .

Does the ODCM change maintain the accuracy of radioactive effluent control required by

. . . xYes No the SAR?

Explain:

This ODCM change will maintain the accuracy of the radioactive effluent control required by the Byron/Braidwood UFSAR. The B/B UFSAR Table I 1 5-6, RadiologIcal Analysis Summary of Gaseous Effluent Samples, includes typical sampling frequency, type of analysis, sensitivity, and purpose for effluent radiation monitors. No UFSAR described effluent samples or monitors are affected by this change.

Determination A changes are administrative in nature. The changes include adding units to a flow diagram description, rearranging the order of listed air sample locations to numerical, and adding direct radiation sampling frequencies and type of analysis that had been previously missing from a table.

None of these administrative changes affect the accuracy of radioactive effluent control requiredbytheSAR. .

Page 3 of 19

Byron Station ODCM Revision 14 Change Determination CYAA1 704100 Station:Byron ..

ODCM Revision No: 1% .. Determination Identifier: B fjgqre 2i S implifiedHVAC & GasePiisfffluent EJw Piagram I Does the ODCM change maintain the level of radioactive effluent control required by

. . , xYes No I OCFR2O.1301?

Explain:

This ODCM change will maintain the radioactive effluent control required by 10CFR%O1301, Dose Limits for Individual Members of the Public, which is to ensure total effective dose equivalent to individual members of the public from licensed operation does not exceed 0.1 rem.

Changes are being made to the flow diagram solely for the purpose of aligning the flow parameters with those listed in the UFSAR and will not affect the way doses are calculated.

Current procedural requirements use flow rates that are either consistent with or conservative with respect to the flow rates listed in the UFSAR.

This ODCM change does not affect any radioactive effluent control required by I OCFR2O.1301.

2. Does the ODCM change maintain the level of radioactive effluent control required by .yJes No 1 OCFR2O. 1302?

Explain:

This ODCM change will maintain the level of control required in 10CFR2O. The requirement of IOCFR2O.1302 is to provide surveys of radiation levels in unrestricted and controlled areas and radioactive materials in effluents released to unrestricted and controlled areas to demonstrate compliance with the dose limits for individual members of the public in 10CFR2O.1301, Changes are being made to a flow diagram solely for the purpose of aligning the flow parameters with those listed in the UFSAR and will not affect the way doses are calculated.

Current procedural requirements use flow rates that are either consistent with or conservative with respect to the flow rates listed in the UFSAR. Surveys of radiation levels are unaffected by this change.

The change to ODCM Figure 2-1 does not affect any radioactive effluent controls required

. .= . ..- - -

3, Does the ODCM change maintain the level of radioactive effluent control required by ..xJes _No 40CFR190 and 10CFR7%.104?

Explain:

This ODCM change will not reduce the control required by 4OCFR1 go. The controls required by 4OCFRI9O and IOCFR72104 include limiting the annual dose equivalent of any member of the public to less than 25 mrem whole body, 75 mrem thyroid, and 2% mrem to any organ as the result of activities from the uranium fuel cycle, including direct radiation from ISFSI.

Changes are being made to a flow diagram solely for the purpose of aligning the flow parameters with those listed in the UFSAR and will not affect the way doses are calculated.

Current procedural requirements use flow rates that are either consistent with or conservative with respect to the flow rates listed in the UFSAR. Since no flow rates are being changed within effluent procedures, resultant doses will be unaffected by this change.

This ODCM revision does not affect radioactive effluent or direct radiation controls and therefore maintains the level of radioactive effluent control required by 4OCFRI9O and 10CFR 72.104.

4, xYes No Does the QDCM change maintain the level of radioactive effluent control required by 1 OCFR5O,36a?

Expkn: . , -

Page4of 19

Byron Station ODCM Revision 14 Change Determination CY4A1 704100 Station:yron ..

ODCM Revision No: 14 _Determination Identifier: B Figure 2-1 Simplified HVAC & Gaseous Effiqent Flow.

p The basic requirement of 10CFR5O36a is to keep releases and the resultant dose to the public as low as reasonably achievable (ALARA).

Changes are being made to a flow diagram solely for the purpose of aligning the flow parameters with those listed in the UFSAR and will not affect the way doses are calculated.

Current procedural requirements use flow rates that are either consistent with or conservative with respect to the flow rates listed in the UFSAR. Since no flow rates are being changed within effluent procedures, resultant doses will be unaffected by this change.

This ODCM revision does not reduce the stations ability to keep releases of radioactive materials to unrestricted areas as low as reasonably achievable, and therefore does not

._.Mfc.c t!lflval.Pf.contr.ol pjyoslestabhshedintheOPCMrecuJred by 1 OCFR5cL36a Page 5 of 19

Byron Station 00CM Revision 14 Change Determination CYAA1 704100 Station:yrqn . .. .

ODCM Revision No: 14 . . . . Determination Identifier: B Figure 2-1 SimpilfieçAC & cja,soous fflqpt Flow p iagmci.

.i(Jes No S Does the ODCM change maintain the level of radioactive effluent control required by 10CFRSO Appendix I?

Explain:

I OCFR5O Appendix I states that liquid effluents from each reactor each year shall not expose any individual to more than 3 mrem to the total body or 1 0 mrem to any critical organ. Gaseous releases of particulates and iodines with half-lives >8 days shall not expose any individual organ to more than 1 5 mrem/year. Noble gases shall not expose any individual total body to more than 500 mrem/year, skin to more than 3000 mremfyear, gamma dose to 10 mrad/year, and beta dose to 20 mrad/year.

Changes are being made to a tlow diagram solely for the purpose of aligning the flow parameters with those listed in the UFSAR and will not affect the way doses are calculated.

Current procedural requirements use flow rates that are either consistent with or conservative with respect to the flow rates listed in the UFSAR. Since no flow rates are being changed within effluent procedures, resultant doses will be unaffected by this change.

This ODCM revision does not affect the amount of liquid and gaseous effluent releases required to maintain the level of radioactive effluent control required by I OCFR%O Appendix

- xYes No

% Does the ODCM change matntatn the accuracy or relrabihty of effluent, dose, or setpomt calculations?

Explain:

Changes are being made to a flow diagram solely for the purpose of aligning the flow parameters with those listed in the UFSAR and will not affect the way doses are calculated.

Current procedural requirements use flow rates that are either consistent with or conservative with respect to the flow rates listed in the UFSAR. Since no flow rates are being changed within effluent procedures, resultant doses and rad monitor setpoint calculations will be unaffected by this change.

The accuracy and reliability of effluent, dose, and setpoint calculations will not be affected bythisODCM change. ,. . ..= . . . . ..... .. ... .. ...

. , ,  ? xYes No 7, Does the ODCM change mamtwn the accuracy of radioacbve effluent control reqwred by

• the SAR?

Explain:

This QDCM change will maintain the accuracy of the radioactive effluent control required by the Byron/Braidwood UFSAR. The B/B UFSAR Section 1 1.2 describes liquid radwaste management systems and concentrations and doses expected from liquid releases. The B/B UFSAR Section 1 1 .5 describes process and effluent radiological monitoring and sampling systems.

Changes are being made to a flow diagram solely for the purpose of aligning the flow parameters with those listed in the UFSAR and will not affect the way doses are calculated. Current procedural requirements use flow rates that are either consistent with or conservative with respect to the flow rates listed in the UFSAR. Since no flow rates are being changed within effluent procedures, the accuracy of radioactive effluent control will be unaffected by this change.

The revision to ODCM Figure 21 does not affect the ability to maintain the accuracy of radioactiveeffluentcontrolreqijired by the SAR. . . .

Page 6 of 19

Byron Station ODCM Revision 14 Change Determination CY-AAI 704100 Station: Byron -

ODCM Revision No: 14Determination Identifier:Q Bypass of U? SJAE offoas filter unit I .

Does the QDCM change mamtain the level of radtoactive effluent control required by

, xYes No I OCFR2O. 1301?

Explain:

This ODCM change will maintain the radioactive effluent control required by IOCFR2O.1301 Dose Limits for Individual Members of the Public, which is to ensure total effective dose equivalent to individual members of the public from licensed operation does not exceed 0. 1 rem.

EC 402668 removed the existing actuator from %0G03% and installed a block to restrain the valve in the open position. 20G036 is the Unit 2 Off Gas (OG) system vent stack isolation valve. Originally, the system was designed to route flow through the charcoal filter unit OOGOIS upon sensing radiation in the steam jet air ejector (SJAE) exhaust. However, the filter unit isolated early on in plant operation due to problems with wetting the charcoal.

That left the flow path through 20G035 as the only vent path for the exhaust of the vacuum hogging pumps and SJAEs. As such, %0G035 represented a significant single point vulnerability (SPV) in that it would cause a loss of condenser vacuum potentially leading to a reduction in reactor power if it were to spuriously close. Removal of the actuator and installation of a block ensured that the valve remains in the open position at all times, but the ability to filter radioiodines in the event of a high rad alarm has been eliminated.

The Off Gas (OG) system provides a means to remove noncondensabte gases from the condenser and vent them to atmosphere. Valve 20G035 was originally intended to isolate the normal vent stack flow path so that flow would be routed through the charcoal filter unit OOGO1 S in the event that radiation was detected in the OG flow stream. This modification deletes the isolation function of 20G035, causing OG flow to be routed through the unfiltered vent stack at all times. Since the UFSAR and TRM assumed a I Ox reduction of I-131 and 1-133 concentrations as a result of the filtration, new dose calculations were performed and evaluated in accordance with Section 5.4.1 of the ODCM, Licensee.initiated major changes to the Radwaste Treatment Systems (liquid and gaseous), and approved under Engineering Calc BYRI 6-01 2. The evaluation concluded that any unfiltered release through the vent stack will remain within the limits established in IOCFR5O Appendix I, 10CFR2O Appendix B, and 4OCFRI9O and the permanent bypassing of the OGFU does not result in a significant increase in radioactive materials or dose to the general public. ODCM Figure 2-1 is being updated to reflect the removal of the filtration capability of the offgas filter unit. Since no changes are being made to the way dose calculations are being performed, the resultant doses are unchanged, and the radioactive effluent control required by 10CFR2O.13O1 is maintained.

2.

Does the ODCM change maintain the level of radioactive effluent control required by xYes No I OCFR2O. 1302?

Explain:

This ODCM change will maintain the level of control required in IOCFR2O. The requirement of 1 OCFR2O.1302 is to provide surveys of radiation levels in unrestricted and controlled areas and radioactive materials in effluents released to unrestricted and controlled areas to demonstrate compliance with the dose limits for individual members of the public in IOCFR2O.13O1.

BC 402668 removed the existing actuator from 20GO35 and installed a block to restrain the valve in the open position. 20G035 is the Unit 2 Off Gas (OG) system vent stack isolation valve. Originally, the system was designed to route flow through the charcoal filter unit 00GW S upon sensing radiation in the steam jet air ejector (SJAE) exhaust. However, the filter unit isolated early on in plant operation due to problems with wetting the charcoal.

That left the flow path through 20G035 as the only vent path for the exhaust of the vacuum

___!12fl0F gpP mps and SJAEs. Assuch,20G035 pnted a significant sigppint Page7of 19

Byron Station 00CM Revision 14 Change Determination CYAA-1 7O31 00 Station:Byron * - -.-- - -...

ODCM Revision No: 14 *. . . Determination WentIfier:QJypss of Q?.NAE ffgas filter unit vulnerability (SPV) in that it would cause a loss of condenser vacuum potentially leading to a reduction in reactor power if it were to spuriously close. Removal of the actuator and installation of a block ensured that the valve remains in the open position at all times? but the ability to filter radioiodines in the event of a high rad alarm has been eliminated.

The Off Gas (OG) system provides a means to remove noncondensable gases from the condenser and vent them to atmosphere. Valve 20G0%5 was originally intended to isolate the normal vent stack flow path so that flow would be routed through the charcoal filter unit OOGO1 S in the event that radiation was detected in the OG flow stream. This modification deletes the isolation function of 20G035, causing OG flow to be routed through the unfiltered vent stack at all times. Since the UFSAR and TRM assumed a I Ox reduction of l I 31 and 1-1 33 concentrations as a result of the filtration? new dose calculations were performed and evaluated in accordance with Section 5.4,1 of the ODCM, Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous)? and approved under Engineering Calc BVRI6-O12. The evaluation concluded that any unfiltered release through the vent stack will remain within the limits established in IOCFR5O Appendix I, 1 OCFR2O Appendix B, and 4OCFR 1 90 and the permanent bypassing of the OGFU does not result in a significant increase in radioactive materials or dose to the general public. ODCM Figure 2-1 is being updated to reflect the removal of the filtration capability of the offgas filter unit. Since no changes are being made to the way dose calculations are being performed, the resultant doses are unchanged, and this change does not affect the ability to provide surveys of radiations levels and maintains the level of control of radioactive materials reouired by 10CFR2O.

Page 8 of 19

Byron Station 00CM Revision 14 Change Determination CYAA-1 704100 Station:yjpn

• ODCM Revision No: 14 .

Determination ldentifieçC Bypass of U2

3. Does the ODCM change maintam the level of radioactive effluent control required by

, . . . . xYes No 4OCFR190 and IOCFR72 104?

Explain:

This ODCM change will not reduce the control required by 4OCFRI9O. The controls required by 4OCFR19O and 10CFR72.104 include limiting the annual dose equivalent of any member of lhe public to less than 25 mrem whole body, 75 mrem thyroid, and 25 mrem to any organ as the result of activities from the uranium fuel cycle, including direction radiation from ISFSI.

EC 402668 removed the existing actuator from 20G03% and installed a block to restrain the valve in the open position. 20G035 is the Unit 2 Off Gas (OG) system vent stack isolation valve. Originally, the system was designed to route flow through the charcoal filter unit OOGO1 S upon sensing radiation in the steam jet air ejector (SJAE) exhaust. However, the filter unit isolated early on in plant operation due to problems with wetting the charcoal.

That left the flow path through 201303% as the only vent path for the exhaust of the vacuum hogging pumps and SJAEs. As such, 2OG035 represented a significant single point vulnerability (SPV) in that it would cause a loss of condenser vacuum potentially leading to a reduction in reactor power if it were to spuriously close. Removal of the actuator and installation of a block ensured that the valve remains in the open position at all times, but the ability to filter radioiodines in the event of a high rad alarm has been eliminated.

The Off Gas (OG) system provides a means to remove non-condensable gases from the condenser and vent them to atmosphere. Valve 200035 was originally intended to isolate the normal vent stack flow path so that flow would be routed through the charcoal filter unit OOGO1S in the eventthat radiation was detected in the 00 flow stream. This modification deletes the isolation function of 20G035, causing OG flow to be routed through the unfiltered vent stack at all times. Since the UFSAR and TRM assumed a I Ox reduction of I-131 and 1-133 concentrations as a result of the filtration, new dose calculations were performed and evaluated in accordance with Section 5.4.1 of the ODCM, Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous), and approved under Engineering CaIc BYRI6-012. The evaluation concluded that any unfiltered release through the vent stack will remain within the limits established in IOCFR5O Appendix I, IOCFR%O Appendix B, and 4OCFR19O and the permanent bypassing of the OGFU does not result in a significant increase in radioactive materials or dose to the general public. ODCM Figure 2-1 is being updated to reflect the removal of the filtration capability of the offgas filter unit. Since no changes are being made to the way dose calculations are being performed, the resultant doses are unchanged, and this change does not affect the ability to maintain the radioactive effluent or direct radiation controls required by 4OCFRI 90 and tOCFR 72.104.

4. Does the ODCM change maintain the level of radioactive effluent control required by

. . . xYes No 1 OCFR5O.36a?

Explain:

This ODCM change does not affect the level of control previously established in the ODCM required by IOCFR5O.36a. The basic requirement of IOCFR%O,36a is to keep releases and the resultant dose to the public as low as reasonably achievable (ALARA). This ODCM change will not reduce the stations ability to keep releases of radioactive materials to unrestricted areas as low as reasonably achievable, as required by I OCFR5O.36a.

EC 402668 removed the existing actuator from 20G035 and installed a block to restrain the valve in the open position. 20G035 is the Unit 2 Off Gas (OG) system vent stack isolation valve. Originally, the system was designed to route flow through the charcoal filter unit OOGOI S upon sensing radiation in the steam jet air ejector (SJAE) exhaust. However, the filter unit isolated early on in plant operation due to problems with wetting the charcoal.

That leftthe f!o pTh through ?QO35 as the onl path forthe exhaust ofthe vacuum Page 9 of 19

Byron Station ODCM Revision 14 Change Determination CY4A1 70-3100 Station: Byron . .

ODCM Revision No: 14 .

Determination ldentifier:Qjypassof U2 SJEpfgjIter unit hogging pumps and SJAEs. As such, 20G035 represented a significant single point vulnerability (SPV) in that it would cause a loss of condenser vacuum potentially leading to a reduction in reactor power if it were to spuriously close. Removal of the actuator and installation of a block ensured that the valve remains in the open position at all times, but the ability to filter radioiodines in the event of a high rad alarm has been eliminated.

The Off Gas (OG) system provides a means to remove noncondensable gases from the condenser and vent them to atmosphere. Valve 20G035 was originally intended to isolate the normal vent stack flow path so that flow would be routed through the charcoal filter unit OOGOI S in the event that radiation was detected in the OG flow stream. This modification deletes the isolation function of 20G035, causing OG flow to be routed through the unfiltered vent stack at all times. Since the UFSAR and TRM assumed a 1 Ox reduction of I-I 31 and I-I 33 concentrations as a result of the filtration, new dose calculations were performed and evaluated in accordance with Section 5.4.1 of the ODCM, Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous), and approved under Engineering CaIc BYRI6-012. The evaluation concluded that any unfiltered release through the vent stack will remain within the limits established in IOCFR5O Appendix I, 1 OCFR2O Appendix B, and 4OCFRI 90 and the permanent bypassing of the OGFU does not result in a significant increase in radioactive materials or dose to the general publicS ODCM Figure 2-1 is being updated to reflect the removal of the filtration capability of the offgas filter unit. Since no changes are being made to the way dose calculations are being performed, the resultant doses are unchanged, and this change does not affect the ability to maintain releases of radioactivity to the unrestricted area ALARA.

Page lOoiI9

Byron Station ODCM Revision 14 Change Determination CYAA1 704100 Station:yqn --- . - .- - - - --$-

QDCM Revision No: 14 Determination dentifierjD Bypass of 2 SJAE offqas filter unit 5,

Does the ODCM change marntain the level of radioactive effluent control requwed by

. . xYes No I OCFR5O Appendix I?

Explain:

10CFR5O Appendix I slates that liquid effluents from each reactor each year shall not expose any individual to more than 3 mrem to the total body or 1 0 mrem to any critical organ. Gaseous releases of particulates and iodines with half-lives >8 days shall not expose any individual organ to more than 1 5 mrem/year. Noble gases shall not expose any individual total body to more than 500 mrem/year, skin to more than 3000 mrem/year, gamma dose to 10 mrad!year, and beta dose to 20 mrad/year.

EC 402668 removed the existing actuator from 20G035 and installed a block to restrain the valve in the open position. 20G035 is the Unit 2 Off Gas (OG) system vent stack isolation valve. Originally, the system was designed to route flow through the charcoal filter unit OOGO1 S upon sensing radiation in the steam jet air ejector (SJAE) exhaust. However, the filter unit isolated early on in plant operation due to problems with wetting the charcoal.

That left the flow path through 20G03% as the only vent path for the exhaust of the vacuum hogging pumps and SJAEs. As such, 20G035 represented a significant single point vulnerability (SPV) in that it would cause a loss of condenser vacuum potentially leading to a reduction in reactor power if it were to spuriously close. Removal of the actuator and installation of a block ensured that the valve remains in the open position at all times, but the ability to filter radioiodines in the event of a high rad alarm has been eliminated.

The Off Gas (OG) system provides a means to remove non-condensable gases from the condenser and vent them to atmosphere. Valve 20G035 was originally intended to isolate the normal vent stack flow path so that flow would be routed through the charcoal filter unit OOGOI S in the event that radiation was detected in the OG flow stream. This modification deletes the isolation function of 20G035, causing OG flow to be routed through the unfiltered vent stack at all times, Since the UFSAR and TRM assumed a I Ox reduction of I-I 31 and 1-1 33 concentrations as a result of the filtration, new dose calculations were performed and evaluated in accordance with Section 5.4.1 of the ODCM, Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous), and approved under Engineering Calc BYR1G-O12. The evaluation concluded that any unfiltered release through the vent stack will remain within the limits established in 10CFR%O Appendix I, 10CFR2O Appendix B, and 4OCFRIOO and the permanent bypassing of the OGFU does not result in a significant increase in radioactive materials or dose to the general public. ODCM Figure 2-1 is being updated to reflect the removal of the filtration capability of the offgas filter unit. Since no changes are being made to the way dose calculations are being performed, the resultant doses are unchanged and this change does not affect the ability to meet Appendix I requirements.

6. .

Does the ODCM change maintain the accuracy or reliabihty of effluent, dose, or setpo!nt

. ., . xYes No calculations?

Explain:

The accuracy and reliability of effluent and dose calculations will not be reduced. They will be unaffected or increased as a result of these changes. Setpoint calculations will not be affected.

EC 402668 removed the existing actuator from 20G035 and installed a block to restrain the valve in the open position. 20G035 is the Unit 2 Off Gas (00) system vent stack isolation valve. Originally, the system was designed to route flow through the charcoal filter unit OOGOI S upon sensing radiation in the steam jet air ejector (SJAE) exhaust. However, the filter unit isolated early on in plant operation due to problems with wetting the charcoal.

That left the flow path through 20G035 as the only vent path forthe exhaust of the vacuum Page 1 1 of 19

Byron Station ODCM Revision 14 Change Determination CY4AI 70-3100 Station:Byrpn .:

ODCM Revision No: 14 Determination Identifier: Cfygssof U2 SJAE ottgas filtexjjnjt hogging pumps and SJAEs. As such, 2013035 represented a significant single point vulnerability (SPV) in that it would cause a loss of condenser vacuum potentially leading to a reduction in reactor power if it were to spuriously close. Removal of the actuator and installation of a block ensured that the valve remains in the open position at all times, but the ability to filter radioiodines in the event of a high rad alarm has been eliminated.

The Off Gas (OG) system provides a means to remove non-condensable gases from the condenser and vent them to atmosphere. Valve 20G035 was originally intended to isolate the normal vent stack flow path so that flow would be routed through the charcoal filter unit OOGOI S in the event that radiation was detected in the OG flow stream. This modification deletes the isolation function of 20G035, causing OG flow to be routed through the unfiltered vent stack at all times. Since the UFSAR and fiRM assumed a lox reduction of l I 31 and I-I 33 concentrations as a result of the filtration, new dose calculations were performed and evaluated in accordance with Section 5.4.1 of the ODCM, Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous), and approved under Engineering CaIc BYRI6-012. The evaluation concluded that any unfiltered release through the vent stack will remain within the limits established in IOCFR5O Appendix I, 1 OCFR2O Appendix B, and 4OCFR I 90 and the permanent bypassing of the QGFU does not result in a significant increase in radioactive materials or dose to the general public. ODCM Figure 2-1 is being updated to reflect the removal of the filtration capability of the offgas filter unit. Since no changes are being made to the way dose calculations are being performed, the resultant doses are unchanged, and this change does not reduce the aççu raqy en t dpso .prpjgint calculation 5.

Page 12 of 19

Byron Station ODCM Revision 14 Change Determination CWAA-1 7O31 00 Station: Byron .

ODCM Revision No: 14 Determination Identifier:,Q Bypassof U2 SJAE offoas filter fl

7. Does the ODCM change maintain the accuracy of radioactive effluent control required by No the SAR?

Explain:

This ODCM change will maintain the accuracy of the radioactive effluent control required by the Byron/Braidwood UFSAR. The B/B UFSAR Section 1 1 .2 describes liquid radwasle management systems and concentrations and doses expected from liquid releases. Since the ODCM changes do not result in any appreciable changes in effluent concentrations and doses, the accuracy of radioactive effluent control required by the SAP is not affected.

EC 402667 removed the existing actuator from %0G035 and installed a block to restrain the valve in the open position. 20G035 is the Unit 2 Off Gas (OG) system vent stack isolation valve. Originally, the system was designed to route flow through the charcoal filter unit OOGO1 S upon sensing radiation in the steam jet air ejector (SJAE) exhaust. However, the filter unit isolated early on in plant operation due to problems with wetting the charcoal.

That left the flow path through 2OG035 as the only vent path for the exhaust of the vacuum hogging pumps and SJAEs. As such, %OG035 represented a significant single point vulnerability (SPV) in that it would cause a loss of condenser vacuum potentially leading to a reduction in reactor power if it were to spuriously close. Removal of the actuator and installation of a block ensured that the valve remains in the open position at all times, but the ability to filter radioiodines in the event of a high rad alarm has been eliminated.

The Off Gas (OG) system provides a means to remove noncondensable gases from the condenser and vent them to atmosphere. Valve 2OG035 was originally intended to isolate the normal vent stack flow path so that flow would be routed through the charcoal filter unit OOGOI S in the event that radiation was detected in the OG flow stream. This modification deletes the isolation function of 2OG03%, causing OG flow to be routed through the unfiltered vent stack at all times. Since the UFSAP and TRM assumed a I Ox reduction of I-1 31 and 1-1 33 concentrations as a result of the filtration, new dose calculations were performed and evaluated in accordance with Section 5.4.1 of the ODCM, Licensee-initiated major changes to the Padwaste Treatment Systems (liquid and gaseous), and approved under Engineering CaIc BYRI 6-01 2. The evaluation concluded that any unfiltered release through the vent stack will remain within the limits established in IOCFR5O Appendix 1, IOCFR2O Appendix B, and 4OCFRI9O and the permanent bypassing of the OGFU does not result in a significant increase in radioactive materials or dose to the general public. ODCM Figure 2-1 is being updated to reflect the removal of the filtration capability of the offgas filter unit. Since no changes are being made to the way dose calculations are being performed, the resultant doses are unchanged, and this change does not affect the

accuracy ofradioacfive effluent control required by the SAR.

Page l3of 19

Byron Station 00CM Revision 14 Change Determination CYAA1 704100 Station:yrog CDCM Revision No: 14 .

Determination Identifier:, QrN w.Dosimeter Location

_x_s _No I Does the ODCM change maintain the level of radioactive effluent control required by 1 OCFR2O 1301?

Explain:

This ODCM change will maintain the radioactive effluent control required by IOCFR2O.1301 Dose Limits for Individual Members of the Public, which is to ensure total effective dose equivalent to individual members of the public from licensed operation does not exceed 0.1 rem.

BY-314-2 dosimeter was relocated approximately 20 feet from a dead tree to a light pole.

The dosimeter remains in the same meteorological sector and the ODCM revision updates the GPS coordinates and distance to the plant.

The relocation of the dosimeter does not affect plant effluents, therefore the radioactive effluentcontrol required by 10CFR2O,1301 is maintained.

xjes

2. Does the ODCM change maintain the level of radioactive effluent control required by 1 OCFR%0.1 302?

Explain:

This ODCM change will maintain the level of control required in I OCFR2O. The requirement of 1 OCFR2O. 1302 is to provide surveys of radiation levels in unrestricted and controlled areas and radioactive materials in effluents released to unrestricted and controlled areas to demonstrate compliance with the dose limits for individual members of the public in IOCFR2O.1301.t BY414-2 dosimeter was relocated approximately 20 feet from a dead tree to a light pole.

The dosimeter remains in the same meteorological sector and the ODCM revision updates the GPS coordinates and distance to the plant.

The dosimeter relocation does not affect the ability to provide surveys of radiations levels PP ptrol of radioactive matehals required yi0C FR ?Q ... .

xes ....fio 3 Does the ODCM change maintain the level of radioactive effluent control required by 4OCFRI9O and IOCFR72104?

Explain:

This ODCM change will not reduce the control required by 4OCFR1gO. The controls required by 4OCFRI9O and IOCFR72.104 include limiting the annual dose equivalent of any member of the public to less than 25 mrem whole body, 75 mrem thyroid, and 2% mrem to any organ as the result of activities from the uranium fuel cycle, including direction radiation from SF01.

8Y414-2 dosimeter was relocated approximately 20 feetfrom a dead tree to a light pole.

The dosimeter remains in the same meteorological sector and the ODCM revision updates the GPO coordinates and distance to the plant.

The dosimeter relocation will not change the resultant doses, therefore this change does not affect the ability to maintain the radioactive effluent or direct radiation controls required by 4OCFR19O and 10CFR 72.104.

_x_Yes

4. Does the ODCM change maintain the level of radioactive effluent control required by 1 OCFR5O.36a?

Explain:

This QDCM change does not affect the level of control previously established in the ODCM required by 10CFRSO.36a. The basic requirement of IOCFR%0.36a is to keep releases and theresultantdosetothe public asJow asreasonalyachievable (ALARA). This CDCM ,

Page l4of 19

Byron Station ODCM Revision 14 Change Determination CYAA1 704100 Station:jyrpn . . . .

ODCM Revision No: ..

Determination Identifier: D New Dosjrnoer Location change will not reduce the stations ability to keep releases of radioactive materials to unrestricted areas as low as reasonably achievable, as required by IOCFR%O36a.

BY-314-2 dosimeter was relocated approximately 20 feet from a dead tree to a light pole.

The dosimeter remains in the same meteorological sector and the ODCM revision updates the GPS coordinates and distance to the plant.

The relocation of the dosimeter does not affect plant effluents, therefore it does not affect the abilIty tomahita tire çgo t.dioactivity to the unrestrictedare ALA %A

. xYes No

5. Does the ODCM change maintain the level of radtoacttve effluent control requtred by IOCFR5O Appendix I?

Explain:

1 OCFR%O Appendix I states that liquid effluents from each reactor each year shall not expose any individual to more than 3 mrem to the total body or I 0 mrem to any critical organ. Gaseous releases of particulates and iodines with half-lives >8 days shall not expose any individual organ to more than I 5 mrem/year. Noble gases shall not expose any individual total body to more than 500 mrem/year, skin to more than 3000 mrem/year, gamma dose to 10 mrad/year, and beta dose to 20 mrad/year.

BY-31 4-2 dosimeter was relocated approximately 20 feet from a dead tree to a tight pole.

The dosimeter remains in the same meteorological sector and the ODCM revision updates the GPS coordinates and distance to the plant.

The dosimeter relocation will not change the resultant doses, therefore this change does not affectthe abilitytomeetAppend x I requ rem ents. .

6.

Does the ODCM change mamtain the accuracy or reliabthty of effluent, dose, or setpont

.. xYes Nol calculations?

Explain:

The accuracy and reliability of effluent and dose calculations will not be reduced. They will be unaffected or increased as a result of these changes. Setpoint calculations will not be affected.

BY-314-2 dosimeter was relocated approximately 20 feet from a dead tree to a light pole.

The dosimeter remains in the same meteorological sector and the ODCM revision updates the GPS coordinates and distance to the plant.

The dosimeter relocation does not affect plant effluents or rad monitor setpoints, therefore this change does not reduce the accuracy or reliability of effluent, dose, or setpoint calculations.

7.

Does the ODCM change maintatn the accuracy of radioactive effluent control required by. xYes No the SAR?

Explain:

BY-31 4-2 dosimeter was relocated approximately 20 feet from a dead tree to a light pole.

The dosimeter remains in the same meteorological sector and the ODCM revision updates the GPS coordinates and distance to the plant.

The dosimeter relocation does not affect plant effluents, therefore the the accuracy of

_ja activ Pzc.!t pmqontrol required by the SAR is maintahied. I_____

Page 15 of 19

Byron Station ODCM Revision 14 Change Determination CY-AA-1 704100 Station: Byro n . . . . .

ODCM Revision No: 14 .

...Determination Identifier: E DupIicaçpv momenta I Dosimeter AdJiJop

. . . xVes No I . Does the ODCM change maintain the level of radioactive effluent control requwed by IOCFR2O.1301?

Explain:

This ODCM change will maintain the radioactive effluent control required by IOCFR2O1301 Dose Limits for Individual Members of the Public, which is to ensure total effective dose equivalent to individual members of the public from licensed operation does not exceed 01 rem.

New procedure CY-AA-170-1001, Environmental Dosimetry Performance Specifications, Testing, and Data Analysis, requires duplicate dosimeters at each location. While duplicate dosimeters currently exist within each meteorological sector, each physical location contained only one dosimeter, so duplicate dosimeters were added to each location beginning in the I Quarter of 201 8. The dosimeter nomenclature for air sample locations and Table 6-1 descriptions are being changed to indicate there are two dosimeters present at each location.

Since the addition of duplicate dosimeters does not affect plant effluents, the radioactive effluent control required by IOCFR%0.1301 is maintained.

2. Does the QDCM change maintain the level of radioactive effluent control required by IOCFR2O. 130%?

Explain:

This ODCM change will maintain the level of control required in I OCFR%0. The requirement of 1 OCFR%0. I 30% is to provide surveys of radiation levels in unrestricted and controlled areas and radioactive materials in effluents released to unrestricted and controlled areas to demonstrate compliance with the dose limits for individual members of the public in IOCFR%01301.

New procedure CY-AA-1 70-1 001 Environmental Dosimetry Performance Specifications, Testing, and Data Analysis, requires duplicate dosimeters at each location. While duplicate dosimeters currently exist within each meteorological sector, each physical location contained only one dosimeter, so duplicate dosimeters were added to each location beginning in the 1 st Quarter of 201 8. The dosimeter nomenclature for air sample locations and Table 6-1 descriptions are being changed to indicate there are two dosimeters present at each location.

The addition of duplicate dosimeters does not affect the ability to provide surveys of radiations levels and therefore maintains the level of control of radioactive materials

. . . _xYes No

3. Does the ODCM change maintain the level of radtoactive effluent control required by 4OCFR19O and 10CFR%2.104?

Explain:

This ODCM change will not reduce the control required by 40CFR190, The controls required by 4OCFRI9O and IOCFR72.1 04 include limiting the annual dose equivalent of any member of the public to less than %5 mrem whole body, 75 mrem thyroid, and 25 mrem to any organ as the result of activities from the uranium fuel cycle, including direction radiation from SF51.

New procedure CY-AA-170.i001, Environmental Dosimetry Performance Specifications, Testing, and Data Analysis, requires duplicate dosimeters at each location. While duplicate dosimeters currently exist within each meteorological sector, each physical location contained only one dosimeter, so duplicate dosimeters were added to each location

.P&gJnoIngjnjPc rI2ti.s! %01 8. The osirneter nomenclature for air sample locations Page l6of 19

Byron Station ODCM Revision 14 Change Determination CY-AA-1 7O31 00 Station:Jyrn -..

QDCM Revision No: I 4 Determination Identifier: E DupUcate Environmental Dosimeter Additions F and Table 6-1 descriptions are being changed to indicate there are two dosimeters present ] I I at each location.

I I The addition of duplicate dosimeters does not affect plant effluents or measured radiation I dose and therefore will not affect the ability to maintain the radioactive effluent or direct I

L____radiatncgreuiyedbj%9f19O andlOCFR7?104. . ..

Page 17o1 19

Byron Station ODCM Revision 14 Change Determination CY-AA-1 70-3100 Station:Byçn . . ....

ODCM Revision No: 1.4 .

Determination Identifier: E Duplicate pyirpnmcntal Dosimeter Add Wons

. xYes No 4, . .

Does the ODCM change maintain the level of radioactive effluent control required by 1 OCFRSO36a?

Explain:

This ODCM change does not affect the level of control previously established in the ODCM required by IOCFR5O.36a. The basic requirement of 10CFR%O36a is to keep releases and the resultant dose to the public as low as reasonably achievable (ALARA). This ODCM change will not reduce the stations ability to keep releases of radioactive materials to unrestricted areas as low as reasonably achievable, as required by IOCFR5O36a.

New procedure CY-AA-1%O-1001 Environmental Dosimetry Performance Specifications, Testing, and Data Analysis, requires duplicate dosimeters at each location. While duplicate dosimeters currently exist within each meteorological sector, each physical location contained only one dosimeter, so duplicate dosimeters were added to each location beginning in the I Quarter of 201 8. The dosimeter nomenclature for air sample locations and Table 6-1 descriptions are being changed to indicate there are two dosimeters present at each location.

The addition of duplicate dosimeters does not affect plant effluents, therefore the ability to maintain releases of radioactW ty to the unrestricted area ALA kis maintained.

. . . xYes No

5. Does the ODCM change maintain the level of radioactive effluent control requred by 10CFRSO Appendix I?

Explain:

IOCFR5O Appendix I states that liquid effluents from each reactor each year shall not expose any individual to more than 3 mrem to the total body or 10 mrem to any critical organ. Gaseous releases of particulates and iodines with halflives >8 days shall not expose any individual organ to more than I 5 mrem/year. Noble gases shall not expose any individual total body to more than 500 mrem/year, skin to more than 3000 mrem/year, gamma dose to I 0 mrad/year, and beta dose to 20 mrad/year.

New procedure CYAA1 70-1 001 Environmental Dosimetry Performance Specifications, Testing, and Data Analysis, requires duplicate dosimeters at each location, While duplicate dosimeters currently exist within each meteorological sector, each physical location contained only one dosimeter, so duplicate dosimeters were added to each location beginning in the 1 Quarter of 201 8. The dosimeter nomenclature for air sample locations and Table 6-1 descriptions are being changed to indicate there are two dosimeters present at each location.

The addition of duplicate dosimeters does not affect measured radiation doses, therefore this change does not affect the ability to meet Appendix I requirements, .

. . xYes No

6. Does the ODCM change maintain the accuracy or reliability of effluent, dose, or setpont calculations?

Explain:

The accuracy and reliability of effluent and dose calculations will not be reduced. They will be unaffected or increased as a result of these changes, Setpoint calculations will not be affected.

New procedure C&AA-170.iOO1 Environmental Dosimetry Performance Specifications, Testing, and Data Analysis, requires duplicate dosimeters at each location. While duplicate dosimeters currently exist within each meteorological sector, each physical location contained only one dosimeter, so duplicate dosimeters were added to each location beginning in the Quarter of 201 8. The dosimeter nomenclature for air sample locations and Table &1 descriptions are being changed to indicate there are two dosimeters present at each location.

Page lSof 19

Byron Station ODCM Revision 14 Change Determination CYAA.1 704100 Stitinn: Rurnn QDCM Revision No: 14 Determination Identifier: E Duplicate Environmental Dosimeter Additions The addition of duplicate dosimeters does not impact plant effluents, doses, or radiation monitor setpoints, therefore this change does not reduce the accuracy or reliability of effluent. dose. or setooint calculations.

7. Does the ODCM change maintain the accuracy of radioactive effluent control required by es No the SAR?

Explain:

New procedure CY-AA-1701 001 Environmental Dosimetry Performance Specificalions, Testing, and Data Analysis, requires duplicate dosimeters at each location. While duplicate dosimeters currently exist within each meteorological sector, each physical location contained only one dosimeter, so duplicate dosimeters were added to each location beginning in the Quarter of 2018. The dosimeter nomenclature for air sample locations and Table 6-1 descriptions are being changed to indicate there are Iwo dosimeters present at each location.

The addition of duplicate dosimeters does not i pact plant effluents, therefore this change 00es not ?ff!ct the accuracy ofLadioactive e nt control re . .-

Prepared by:.. flat Reviewed by: /QdUJ( eL:t Date:

Page l9of 19

BYRON NUCLEAR POWER STATION ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT (ARERR) 2018 Page 1 of 79

BYRON NUCLEAR POWER STATION UNIT 1/2 DOCKET NUMBER STN-50-454/455 RADIOACTIVE EFFLUENT RELEASE REPORT January 201 8 December2018 Supplemental Information 1 . Regulatory Limits

a. Fission and activation products:

Tech Spec Whole Body = 500 mrem/year Skin = 3000 mrem/year 1 OCFR5O Gamma = 5 mrad/quarter; 1 0 mrad/year Beta = 10 mrad/quarter; 20 mrad/year

b. Iodine: (summed with particulate, see below)

c. Particulates with half-lives > 8 days:

Tech Spec Organ = 1500 mrem/year 10CFR5O Organ = 7.5 mrem/quarter; 15 mrem/year

d. Liquid Effluents:

1 OCFR5O Whole Body = 1 .5 mrem/quarter; 3 mrem/year Organ = 5 mrem/quarter; 10 mrem/year

2. Maximum Permissible Concentration

a. Fission and Activation Products: 1 OCFR2O Appendix B Table 2

b. Iodine: 10CFR2O Appendix B Table 2

c. Particulates: 1 OCFR2O Appendix B Table 2

d. Liquid Effluents: 1 0 X 1 OCFR2O Appendix B Table 2

3. Average Energy: This item is not applicable. The ODCM limits the dose equivalent rates due to the release of noble gases to less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin.

4. Measurements and Approximations of Total Radioactivity

a. Fission and activation products: Prior to release, the isotopic content is determined. Released activity is calculated using volume of release, which is determined by the change in tank level, containment pressure, or containment purge fan flow rates.

b. Particulate and iodine sampling media for the plant vent stacks are continuously collected and analyzed weekly. Tritium and noble gas analysis for the plant vent stacks are obtained and analyzed weekly.

c. Liquid effluents: Isotopic analysis is performed on each batch liquid release tank prior to its release. Total release activity is calculated using volume of release. Total tritium activity Page 2 of 79

released is calculated from the highest of a monthly circulating water blowdown composite activity or a sum of the effluent input composite activities.

d All positive results (i.e. higher than the lower limit of detection (LLD)) are reported in units of uCi/cc or uCi/mi unless otherwise noted. All LLD values and the associated LLD requirements are listed in Attachment A.

5. Batch Releases:

a. Liquid:

1 . Number of batch releases = 78

2. Total time period for batch releases = 1 5,71 9 minutes

3. Maximum time period for a batch release = 720 minutes

4. Average time period for a batch release = 202 minutes

5. Minimum time period for a batch release = 49 minutes

6. Average Rock River stream flow during periods of release of effluent into a flowing stream = 368 m3/sec, based on information from the U.S. Geological Survey Byron Gauging Station.

b. Gaseous:

1 . Number of batch releases = 405

2. Total time period for batch releases = 46,407 minutes

3. Maximum time period for a batch release = 2,1 1 6 minutes

4. Average time period for batch releases = 1 1 5 minutes

5. Minimum time period for a batch release = 22 minutes

6. Abnormal Releases:

a. Liquid - None

b. GaseousNone

7. There was one revision to the Offsite Dose Calculation Manual (ODCM), which was implemented in February 2018 under Revision 14. The revision included administrative changes, an update to the HVAC & Gaseous Effluent flow diagram to align with flow rates listed in the Updated Final Safety Analysis Report (UFSAR), bypass of the U2 Steam Jet Air Ejector (SJAE) filtration unit, an environmental dosimeter relocation, and addition of duplicate environmental dosimeters.

Based on a thorough review of the UFSAR, some flows listed in Figure 2-1 were either inconsistent, incorrect, or not found in the UFSAR. Therefore, Figure 2-1 is was updated for the purpose of aligning the flow parameters with those listed in the UFSAR. The update to the figure did not affect the way doses are calculated. Most of the flow rates listed in Figure 2-1 are not used in effluent calculations.

Current procedural requirements either use flow rates that are consistent with or conservative with respect to the flow rates listed in the UFSAR. Therefore, the changes to Figure 2-1 had no impact on plant effluents, radioactive controls, or dose calculations.

The ability to route U2 SJAE offgas through a filter unit on a high radiation alarm was removed under EC 402668. Since the UFSAR and TRM credited a lOx removal of 1-131 and 1-133, Engineering Caic BYRY6-012 was perlormed in order to demonstrate compliance with offsite dose limits without the benefit of filtration. The new dose calculations were perlormed and evaluated in accordance with Section 5.4.1 of the ODCM, Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous). AT 4014039-05 was created to include the Engineering CaIc in the submittal of the 2017 Annual Radiological Effluent Release Report (ARERR) in accordance with ODCM Section 5.4.1 The Engineering CaIc was performed, reviewed, and approved prior to issuing the Engineering Page 3 of 79

Change. The Engineering Change included revision of the applicable UFSAR and TRM sections. The filter unit bypass increases the potential thyroid dose to a member of the public, however, the projected doses remain at a fraction of the 1 OCFR5O Appendix I dose limits, therefore the change is considered insignificant. The offgas filtration is not credited in the ODCM. Therefore, the only required change to the ODCM was to Figure 2-1 to reflect the U2 SJAE offgas filtration bypass. The bypass of the Ui Steam Jet Air Ejector (SJAE) offgas filter unit was previously addressed in ODCM Revision i 3.

Environmental dosimeter BY-31 4-2 was relocated approximately 20 feet from a dead tree to a light pole. Table 6-2 was updated to reflect the new GPS location and distance to the plant for the relocated dosimeter. The relocated dosimeter remains in the same meteorological sector and the relocation does not impact the ability to maintain the direct radiation measurement requirements of TRM Section 3.12.

New procedure CY-AA-1 70-i 001 Environmental Dosimetry Performance Specifications, Testing, and Data Analysis, requires duplicate environmental dosimeters at each location. While duplicate dosimeters currently existed within each meteorological sector, each physical location contained only one dosimeter, so duplicate dosimeters were added during the 1st Quarter 20i8 environmental dosimeter exchange. Table 6-i descriptions were changed to indicate there are two dosimeters present at each location. The addition of environmental dosimeters and the change in descriptions do not impactthe ability to maintain the direct radiation measurement requirements of TRM Section 3.i2.

8. Errata Data There was no errata data to report for 2018.

9. 2018 Radiological Groundwater Protection Program (RGPP) Results Summary:

In 2018, fifteen (15) Radiological Groundwater Protection Program (RGPP) monitoring wells were sampled in total. Groundwater samples were obtained in February, May, August, and October and analyzed for tritium. In addition, a study of gamma, gross beta, and gross alpha radioisotopes was per[ormed in accordance with Nuclear Energy Institute (NEI) 07-07, Groundwater Protection Initiative, for the samples obtained in May. None of the June samples showed concentrations of radionuclides above what is considered background levels. Three wells contained levels of tritium above the lower limit of detection (LLD) of 200 pCi/L. They were: AR-4 (283 pCi/L in February, 372 pCi/L in May, 336 pCi/L in August, 340 pCi/L in October) and AR-i i (646 pCi/L in February, 675 pCi/L in May, 653 pCi/L in August, 685 pCi/L in October) and AR-f (278 pCi/L in February, 301 pCi/L in May, 237 pCi/L in August, 233 pCi/L in October. Wells AR-4 and AR-i 1 are near the Circulating Water Blowdown piping, where historical leakage through vacuum breakers was known to have occurred. Tritium in Well AR-f, located on-site just west of plant structures, has been measured in this well slightly above detection limits on an intermittent basis since the well was first drilled in 2006. The tritium present in this well is at or below tritium levels that have been historically measured in rainwater as a result of precipitation recapture from permitted gaseous releases and is not believed to be the result of new leak(s). In August 20i 4, a break in the well piping was discovered about six feet below the surtace that could have served as the entry point for tritium in the recapture water. Should the water in these aquifers migrate to off-site wells used for drinking, the off-site dose consequence from tritium present in any of these three wells would be negligible. There are no existing or new leaks evident at the site and all groundwater well sample results are well below the drinking water standard of 20,000 pCi/L tritium.

In December 20i8, two new wells, AR-i2 and AR-i3, were installed near well AR-f. These wells were added to provide additional monitoring capabilities in the area directly west of plant structures and will be added to the routine quarterly sampling schedule in 20i 9.

Page 4 of 79

SUMMARY

Calculations based on gaseous and liquid effluents and meteorological data indicate that public dose due to radioactive material attributable to Byron Station during the period did not exceed any regulatory or Offsite Dose Calculation Manual (ODCM) limits.

The Total Effective Dose Equivalent (TEDE) due to licensed activities at Byron Station calculated for the maximum exposed individual for the period is 2.65E-O1 mrem. The annual limit on TEDE is 100 mrem.

The assessment of radiation doses to the public is performed in accordance with the ODCM. The results ofthese analyses confirm thatthe station is operating in compliance with 100FR5O Appendix I, 10CFR2O and 40CFR190.

There were no additional operational controls implemented in 201 8 that affected radiological effluents.

There were no measurements which exceeded the reporting levels, including any that would not have been attributable to station effluents.

The results of the current radiological environmental monitoring program are approximately the same as those found during the pre-operational studies conducted at Byron Station.

RELEASES Gaseous Effluents to the Atmosphere A total of 1 .41 E+00 curies of fission and activation gases were released with a maximum average quarterly release rate of 1.1OE-01 jiCi/sec.

A total of 6.32E-7 curies of I-i 31 were released during the year with a maximum average quarterly release rate of 6.92E-08 pCi/sec.

A total of 0.OOE+00 curies were released as airborne particulate matter with a maximum average quarterly release rate of 0.OOE+00 pCi/sec.

A total of 9.01 E+00 curies of other (C-i 4) radioisotopes were released with a maximum average quarterly release rate of 3.09E-Oi pCi/sec.

A total of 5.87E+Oi curies of tritium were released with a maximum average quarterly release rate of 2.80E+00 pCi/sec.

Gross alpha-emitting radionuclides were below detectable limits.

Liquids Released to Rock River A total of 3.OOE+i 0 liters of radioactive liquid wastes containing 2.04E-02 curies of fission and activation products were discharged with a maximum quarterly average concentration of 9.51 E-i 0 pCi/mi.

A total of 2.82E+03 curies of tritium were discharged with a maximum quarterly average concentration of i .75E-04 uCi/mi.

A total of 7.32E-04 curies of dissolved and entrained gases were discharged with a maximum quarterly average concentration of 9.i4E-ii uCi/mi.

Page 5 of 79

Gross alpha-emitting radionuclides were below detectable limits.

DOSE TO HUMAN GASEOUS EFFLUENT PATHWAYS Noble Gas Gamma Dose Rates Offsite Gamma air and whole body dose rates for the period were calculated based on measured release rates, isotopic composition of the noble gases, and average meteorological data. The maximum gamma air dose was 5.81 E-05 mrad based on measured effluents and average meteorological data, and 9.70E-06 mrad based on measured effluents and concurrent meteorological data.

Noble Gas Beta Air and Skin Dose Rates The range of beta particles in air is relatively small (on the order of a few meters or less).

Consequently, plumes of gaseous effluents may be considered semi-infinite for the purpose of calculating the dose from beta radiation incident on the skin. However, the actual dose to sensitive skin tissues is difficult to calculate due to the effect of the beta particle energies, thickness of inert skin, and clothing covering sensitive tissues. For purposes of this report the skin is taken to have a thickness of 7.0 mg/cm2 and an occupancy factor of 1 .0 is used. The maximum skin dose was 2.70E-05 mrem based on measured effluents and average meteorological data, and 1 .31 E-05 mrem based on measured effluents and concu rrent meteorological data.

The maximum offsite beta air dose for the year based on measured effluents and average meteorological data was 2.29E-05 mrad, and 1 .57E-05 mrad based on measured effluents and concurrent meteorological data.

Radioactive Iodine & Particulate The human thyroid exhibits a significant capacity to concentrate ingested or inhaled iodine. I-i 31 released during routine operation of the station may be made available to man resulting in dose to the thyroid. C-i 4 is also included in this category. C-i 4 exhibits a capacity to concentrate in bone. C-i 4 is released in gaseous form and is absorbed into vegetation through photosynthesis. The principal pathways of interest for C-i 4 are the consumption of vegetation by humans and milk from which animals have ingested C-i4 through the consumption of vegetation. With the requirementto begin reporting C-i4 dose in 2Oii and the addition of C-i4 to plant effluents, human dose in this category is primarily driven by the release of C-i4 from the plant.

The hypothetical dose to the maximum exposed individual living near the station via ingestion of milk and vegetation was calculated. The source of milk and vegetation was assumed to be at the nearest site boundary with the cows pastured and vegetation grown from May through October. The maximum organ dose from radioactive iodine and particulate (including C-i4) to any organ was 7.33E-Oi mrem (child/bone) based on measured effluents and average meteorological data, and 6.45E-Oi mrem (child/bone) based on measured effluents and concurrent meteorological data. The maximum dose from radioactive iodine and particulate (including C-i 4) to the whole body was 1 .50E-Oi mrem (child) based on measured effluents and average meteorological data, and 1 .32E-Oi mrem (child) based on measured effluents and concurrent meteorological data.

Page 6 of 79

Gaseous Total Dose The maximum total dose from gaseous releases to any organ was 7.33E-O1 mrem (child/bone) based on measured effluents and average meteorological data, and 6.45E-O1 mrem (child/bone) based on measured effluents and concurrent meteorological data. The maximum total dose from gaseous releases to the whole body was 1 50E-O1 mrem (child) based on measured effluents and average meteorological data, and 1 .32E-O1 mrem (child) based on measured effluents and concurrent meteorological data.

LIQUID EFFLUENT PATHWAYS The principal pathways through the aquatic environment for potential doses to man from liquid waste are ingestion of potable water and eating aquatic foods. Liquid dose was calculated based on the ingestion of potable water and sport fish. It should be noted, however, there are currently no communities within 1 0 km downstream of the plant using the Rock River for drinking water. NRC-developed equations are used to calculate the doses to the whole body, bone, liver, thyroid, kidney, lung, lower GI tract, and skin. Specific parameters for use in the equations are given in the Exelon Offsite Dose Calculation Manual (QDCM).

The maximum dose from liquid releases to any organ was 1 .92E-O1 mrem (adult/gilli). The maximum dose from liquid releases to the whole body was 1 .38E-O1 mrem (adult).

GASEOUS + LIQUID TOTAL DOSE The maximum total dose to any organ via both gaseous and liquid effluents is 8.19E-O1 mrem (child/bone). The maximum dose to the whole body via both gaseous and liquid effluents is 2.67E-O1 mrem (child).

Dose Limits to Members of the Public Byron Station did not exceed any of the dose limits as shown below based on concurrent or historical meteorological data.

. The limits on dose or dose commitment to a member of the public due to radioactive materials in liquid effluents from each reactor is 1 .5 mrem to the whole body or 5 mrem to any organ during any calendar quarter and 3 mrem to the whole body or 1 0 mrem to any organ during a calendar year.

. The limits on air dose due to noble gases released in gaseous effluents to a member of the public from each reactor is 5 mrad for gamma radiation or 1 0 mrad for beta radiation during any calendar quarter and 1 0 mrad for gamma radiation or 20 mrad for beta radiation during a calendar year.

. The limits on dose to a member of the public due to radioactive iodine & particulate with half-lives greater than eight days in gaseous effluents released from each reactor is 7.5 mrem to any organ during any calendar quarter and 1 5 mrem to any organ during a calendar year.

. The annual 1 OCFR2O limit on Total Effective Dose Equivalent to individual members of the public is 100 mrem.

. The 4OCFR1 90 limits on individual members of the public is 25 mrem to the whole body, 25 mrem to any organ (except thyroid), and 75 mrem to the thyroid.

Page 7 of 79

SITE METEOROLOGY Detailed records of the site meteorological measurements taken during each calendar quarter of the year are maintained by the meteorological vendor, retained on site, and are available upon request.

The data are presented as cumulative joint frequency distributions of the wind direction for the 250 level and wind speed class by atmospheric stability class determined from the temperature difference between the 250 and 30 levels. Data recovery for all measurements on the meteorological tower was 99.8% during 2018.

Page 8 of 79

SOLID RADIOACTIVE WASTE FOR BURIAL 1 ST QUARTER 2018 DATE DISPOSITION OF MATERIAL MODE OF DESTINATION VOLUME (m3) CURIES*

Shipment# (DESCRIPTION, CLASS, TYPE AND TRANSPORT! PER PER Description SOLIDIFYING AGENT) CARRIER SHIPMENT SHIPMENT 2/13/18 UN3321, RADIOACTIVE MATERIAL, LOW SPECIFIC Highway RWS18-001 ACTIVITY (LSA-II), 7, 20 METAL BOX(2), CLASS A, Hittman Transport Bear Creek 6 26E÷O1 42E-o1 DAW/Trash NONE EXCLUSIVE-USE Oak Ridge, TN 2/14/18 UN3321, RADIOACTIVE MATERIAL, LOW SPECIFIC Highway RWS18-002 ACTIVITY (LSA-II), 7, 20 METAL BOX(1), CLASS A, Hittman Transport Bear Creek 75E+O1 5 99E-o1 DAW/Filters NONE EXCLUSIVE-USE Oak Ridge, TN

• Number of Quarterly Totals 2 8.01 E+O1 7.41 E-O1 Shipments:

• Calculated using measured ratios CUBIC M CURIES Page 9 of 79

6LJ° 01 S3IUflD LIN DIflO

suewd!q OI7O*9 Q+66 9 SIO1 AieirnnO o ieqwn UISOJ pO xj_ SM]pUV Sfl-AISfl7OX NON SSV7O Joov+/-u o+o OO+LEC SS!Ie!3dS jodsui UW4!H imvoi S3GI7DflNOIGVH- OH L OV)13Vd lo]uoD BS AMq6! (fl) dA1 7VIH1VV AI1DVOIGVH 96Nfl ANON U!SOH peed xJ_ SMOJpUV Sfl-AISfl7QX LOO-9L -is jodsuEJ UeW!H ssv1o ()oo vii i+/-voi sai7onNoiavu OI7V OO+3LEC SSiIei3edS AMq6! -

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()ooviu 73+/-VSOH SacIlonNolavU O+3669 OO+VS SSiI!3Od5 9OO9LUS AMq6I -

QU G1dOX 1ISSId L OV)DVd Io]uoo G1SM (n)S aia 7ViH+/-vv AI+/-DVOIGVH 96Nfl NON S U!SOU PS xJ_ SMOJPUV Sfl-AISfl7DX SUO!flIOS AJUO!SiA SSv7O iooviu 7+/-VSOH SaI7DflNOIGvU IOO-9L-HS O+69L OO+9OS SSiI!3ad5 AMq6I -

OH G+/-dOX 311551d L DV)1DVd IoJuo3 8SM (n)S 3dA+/- 7VIH1VV 3ALLDVOICVH 96Nfl Sfl-AISfl13X3 NON V SSV1O (iSvo a+/-aox u!seU poS i_n OA!IQ OO+9Lt OO+36 Jodsua uwT!H 371551d L (ii-vsi) ,uIAI+/-OV OIdIO3dS SOO-S SMU SUO!lflIOS AbJOU AMq! MOl 7VIUIVN 3AIIQVOIGVU CENfl S It HIHHVD 1NNdIHS +/-NNdIHS (+/-Nov ONIAdIGI7OS GNV uoid!Josea

/+/-HOdSNVHI #1uewdq Hd Hd (sw) NOLLVNI1SG adA! SSV7D NOI1dIHOSG) dOGOV

£IHflD VNfl7OA 7VIH1WJ dO NOIIISOdSIG 9 I.O H1HVflO GN 7VIHfl HOd ISVM AI1DVOGV)d GI7OS

SOLID RADIOACTIVE WASTE FOR BURIAL 3RD QUARTER 2018 DATE DISPOSITION OF MATERIAL MODE OF VOLUME (m3) CURIES* PER Shipment # (DESCRIPTION, CLASS, TYPE AND TRANSPORT! DESTINATION PER SHIPMENT Description SOLIDIFYING AGENT) CARRIER SHIPMENT 9/6/18 UN3321 RADIOACTIVE MATERIAL, LOW

, Highway RWS18-011 Bear Creek SPECIFIC ACTIVITY (LSA-II), 7, 20 METAL Hittman Transport 6.27E+01 4.89E-02 Bead Oak Ridge, TN BOX(2), CLASS A, NONE EXCLUSIVE-USE Resin/DAW Number of Quarterly Totals 1 Shipments: 6.27E+01 4.89E-02 Calculated using measured ratios CUBICM CURIES Page 11 of 79

4TH QUARTER 2018 SOLID RADIOACTIVE WASTE FOR BURIAL DISPOSITION OF MATERIAL MODE OF VOLUME(m3) CURIES*

DATE Shipment# (DESCRIPTION, CLASS, TYPE TRANSPORT! DESTINATION PER PER Description AND SOLIDIFYING AGENT) CARRIER SHIPMENT SHIPMENT 1 1/5/1 8 UN3321 RADIOACTIVE MATERIAL, LOW Highway Beat Cteek 1.83E-O1 RWS18-012 SPECIFIC ACTIVITY (LSA-II), 7, 20 METAL Hittman Ttanspott 6.44E+O1 Oak Ridge, TN DAW/Trash BOX(2), CLASS A, NONE EXCLUSIVE-USE 11/29/18 Highway UN3321, RADIOACTIVE MATERIAL, LOW Enetgy Solutions RWS18-013 Hittman Ttansport 453E+00 6.25E+00 SPECIFIC ACTIVITY (LSA-II), 7, 20 METAL Clive, UT Bead CASK(1), CLASS A, NONE EXCLUSIVE-USE Resin/Chatcoal 11/30/18 UN3321, RADIOACTIVE MATERIAL, LOW Highway Beat Cteek 5.78E-02 RWS18-014 SPECIFIC ACTIVITY (LSA-II), 7, 20 METAL Hittman Ttanspott 6.44E+01 Oak Ridge, TN DAW/Ttash BOX(2), CLASS A, NONE EXCLUSIVE-USE Number of 6A9E+OO Quarterly Totals 3 1 .33E+02 Shipments:

Calculated using measured ratios CUBIC M CURIES Page 12 of 79

SOLID RADIOACTIVE WASTE FOR BURIAL Estimated Solid Waste Compotion 2018 Res,s, Filters,Eiap Bottoms Resins, Filters, Ep Bottoms Dry Acth.e Waste 2018 2018 2018 Volume (m3) 9.15E+OO Volume (m3) 160E+O1 Volume (m3) 3.32E+02 Class A Class B Class A Nuclide  % Abund Curies uCi/mi Nuclide  % Abund Curies uCi/mI Nuclide  % Abund Curies uCi/mI H-3 28.09 322E+OO 3.52E-O1 H-3 1.16 5.78E+OO 3.61E-O1 H-3 14.18 8.48E-02 2.55E-04 Be-7 001 1.30E-03 1.42E-04 C-14 0.11 5.39E-O1 3.37E-02 Cr-51 0.35 2.09E-03 630E-06 C-14 2.53 290E-O1 3.17E-02 Mn-54 3.75 1.87E+O1 1.17E+OO Mn-54 0.60 3.60E-03 1.08E-05 Cr-51 0.51 5.80E-02 6.34E-03 Fe-55 1728 8.62E+O1 5.39E+OO Fe-55 29.86 179E-O1 5.39E-04 Mn-54 0.71 816E-02 8.92E-03 Co-57 0.35 1.73E+OO 1.08E-O1 Co-57 0.11 6.67E-04 2.O1E-06 Fe-55 257 2.95E-O1 3.22E-02 Co-58 3.36 1 68E+O1 1 05E+OO Co-58 1.89 1.13E-02 3.40E-05 Fe-59 0.03 3.30E-03 361 E-04 Co-60 27.69 1.38E+02 8.63E+OO Co-60 26.69 1 .60E-O1 4.82E-04 Co-57 0.16 1.80E-02 197E-03 Ni-59 0.57 2.86E+OO 1.79E-O1 Ni-63 2394 1.43E-O1 4.31E-04 Co-58 6.38 7.32E-O1 8.OOE-02 Ni-63 43.12 2.15E+02 1.34E+O1 Zr-95 0.12 7.40E-04 2.23E-06 Co-60 17.87 2.05E+OO 2.24E-O1 Zn-65 0.62 3.12E+OO 1.95E-O1 Nb-95 0.24 143E-03 4.31E-06 Ni-59 0.27 3.08E-02 3.37E-03 Sr-89 0.00 1.81E-03 1.13E-04 Sb-125 1.55 9.27E-03 279E-05 Ni-63 23.85 2.73E÷OO 2.98E-O1 Sr-90 0.01 5.55E-02 3.47E-03 Cs-137 0.26 153E-03 4.61E-06 Zn-65 0.12 1.39E-02 1.52E-03 Nb-95 0.01 359E-02 224E-03 Ce-144 0.04 217E-04 654E-07 Zn-69m 0.00 2.22E-46 2.43E-47 Tc-99 0.02 9.03E-02 5.64E-03 Pu-238 0.00 2.1OE-05 6.33E-08 Sr-90 0.00 5.18E-04 5.66E-05 Sb-125 1.18 5.90E+OO 3.69E-O1 Pu-239 0.00 8.82E-06 2.66E-08 Zr-95 0.40 4.56E-02 498E-03 Cs-137 0.74 3.70E+OO 2.31E-O1 Pu-241 0.17 1.02E-03 307E-06 Nb-95 0.66 760E-02 8.31E-03 Ce-144 0.01 4.05E-02 2.53E-03 Am-241 0.00 2.89E-05 8.70E-08 Tc-99 000 2.54E-04 2.78E-05 Pu-238 0.00 5.1OE-04 3.19E-05 Pu-241 0.02 8.48E-04 2.55E-06 Ag-ibm 0.06 6.43E-03 7.03E-04 Pu-241 0.00 2.43E-02 1.52E-03 Am-241 0.00 2.35E-05 7.08E-08 Sn-113 006 6.79E-03 7.42E-04 Am-241 0.00 239E-04 1.49E-05 Sb-124 0.00 509E-04 5.56E-05 Cm-242 000 9.86E-06 6.16E-07 Other Waste Sb-125 13.01 1.49E+OO 1.63E-O1 Cm-244 0.00 4.05E-04 2.53E-05 2018 Te-123m 0.00 3.97E-04 4.34E-05 Volume (m3) 1 .79E÷O1 1-131 0.00 2.65E-08 2.90E-09 Irradiated Components Class A Cs-134 0.68 7.84E-02 8.57E-03 2018 Cs-137 1.34 1.54E-O1 1.68E-02 Volume (m3) O.OOE+OO  % Abund Curies uCi/mi Ce-144 0.21 245E-02 2.68E-03 Class N/A H-3 3.02 1.11E-04 Pu-238 0.00 7.34E-07 8.02E-08 No Shipments Cr-51 0.68 2.48E-05 Pu-239 0.00 3.08E-07 3.37E-08 Mn-54 0.81 297E-05 Pu-241 0.45 5.Y1E-02 5.58E-03 Fe-55 34.29 1.26E-03 Am-241 0.01 1.04E-03 1.14E-04 Co-57 0.15 5.67E-06 Cm-242 0.00 2.O1E-04 2.20E-05 Co-58 3.57 131E-04 Cm-244 0.01 9.43E-04 103E-04 Co-60 29.35 1.08E-03 Ni-63 25.15 9.21E-04 Zr-95 0.24 8.67E-06 Nb-95 0.45 1.65E-05 Sb-125 1.78 6.51E-05 Cs-137 0.27 9.88E-06 Ce-144 0.05 1.82E-06 Pu-238 0.00 1.35E-07 Pu-239 0.00 5.66E-08 Pu-241 0.18 6.67E-06 Am-241 0.01 1.86E-OZ Page 13 of 79

Estimated Solid Waste Composition 2018 Sum of All Categories Sum of All Categories Total Combined 2018 2018 2018 Volume(m3) 3.59E+02 Vokime (m3) 1 60E÷0i Volume (m3) 5.11E+02 Class A Class B Class A&B uclide  % Abund Curies uCi/mI Nuclide  % Abund Curies uCi/mI Nuclide  % Abund Cuhes uCi/mI

-3 27.39 3.30E+00 9.19E-03 H-3 1.16 5.78E+00 3.61E-0i H-3 1.78 9.09E+00 i.78E-02 e-7 0.01 1.30E-03 3.62E-06 C-14 0.11 5.39E-0i 3.37E-02 Ee-7 0.00 i30E-03 2.54E-06 C-14 2.40 2.90E-01 8.08E-04 Mn-54 3.75 i.87E+0i i.17E+00 C-14 0.16 8.29E-0i i.62E-03 Cr-51 0.50 6.O1E-02 167E-04 Fe-55 1T2 8.62E+Oi 5.39E+00 Cr-Si 0.01 6.O1E-02 i18E-04 Mn-54 0.71 8.52E-02 2.37E-04 Co-57 i3 i.73E+00 i.08E-0i Mn-54 3.68 i88E+0 3.68E-02 Fe-55 3.93 4.75E-01 1 .32E-03 Co-58 3 i.68E÷0i i.05E+00 Fe-SS 16.97 8.66E+0 i.69E-0i Fe-59 0.03 3.30E-03 919E-06 Co-60 2T6 i.38E+02 8.63E+00 Fe-59 0.00 330E-0 6.46E-06 Co-57 015 1.86E-02 5.18E-05 1-59 L57 286E+00 i.79E-0i Co-57 0.34 1 .75E+0 3.42E-03 Co-58 6.16 7.43E-01 207E- Ni-63  : 2.15E+0 i.34E+0i Co-58 43 1 .75E+0i 3.42E-02 Co-60 18.31 2.21E+00 6.16E- Zn-65 i6 312E+ i.95E-0i Co-60 27.47 i.40E+0 2.74E-0i Ni-59 0.26 3.08E-02 858E- r-89 0 i.81E- i13E-04 Ni-59 0.57 2.89E+0 S.66E-03 Ni-63 23.85 2.88E+00 8.02E- r-90 flO 5.55E- 3.47E-03 Ni-63 42.66 2.18E+0 4.27E-0i Zn-65 0.11 1.39E-02 3.87E- b-95 cLOl 3.59E- 2.24E-03 Zn-65 0.61 3.13E+0 6.13E-03 Zn-69m . 0 222E-46 6.18E-49 Tc-99 002 9.03E-0 5.64E-03 Zn-69m 0 2.22E-4 4.34E-49 Sr-90 . 5.18E-04 1.44E- 6 b-i25 118 5.90E÷ 3.69E-0i Sr-89 i.81E-0 3.54E-06 Zr-95 . 4.64E-02 1.29E-04 Cs-137 074 3.70E+ 231E-0i Sr-90 co S.60E-0 i.1OE-04 Nb-95 . 7.75E-02 216E- 4 Ce-144 0.01 4.05E- 253E-03 Zr-95 i0 4.64E-0 9.08E-0S Tc-99 . 0 254E-04 LOBE- 7 Pu-238 000 5.1OE- 3.19E-05 Nb-95 i0 i.13E-0 2.21 E-04 Ag-ibm . 6.43E-03 1.79E- 5 Pu-241 0.00 2.43E-02 i.52E-03 Tc-99 0.0 9.OSE-0 i.77E-04 n-113 . 6.79E-03 1.89E- Am-241 0.00 2.39E- i.49E-05 Ag-ibm flO 6.43E-03 i.26E-0S b-124 . 5.09E-04 142E- Cm-242 0.00 9.86E- 6.16E-07 Sn-113 flO 6.79E-03 i.33E-0S b-125 12.44 1.50E÷00 418E- Cm-244 000 405E- 2.53E-05 Sb-124 0 S.09E-04 9.96E-07 Te-123m . 0 397E-04 tilE- Sb-125 1.45 7.40E+00 i.45E-02 131 000 265E-08 7.38E-ii Te-123m 0.00 3.97E-04 7.77E-07 Cs-134 784E-02 2.18E-04 -131 0.00 2.65E-0 S.19E-il Cs-137 1. i55E-0i 4.32E-04 Cs-134 0.02 7.84E-0 i.53E-04 Ce-144 . 2.47E-02 6.88E- Cs-137 0.75 3.85E+0 7.53E-03 Pu-238 0.00 2.18E-05 6.07E- Ce-144 0.0 6.52E-0 i.28E-04 Pu-239 0.00 9.19E-06 2.56E-08 Pu-238 0.00 S.32E-0 1 .04E-06 Pu-241 0.43 5.21E-02 i.45E-04 Pu-239 0.00 9.i9E-0 i.80E-08 Am-241 0.01 i.07E-03 2.98E-06 Pu-241 0.01 7.64E-0 i.SOE-04 Cm-242 0.00 2.O1E-04 5.60E-07 Am-241 0.00 i.31E-0 2.56E-06 Cm-244 0.01 9.43E-04 2.63E-06 Cm-242 0.00 2.11E-0 4.13E-07 Cm-244 0.00 1 .35E-03 2.64E-06 Page 14 of 79

Process Control Program (PCP) for Radioactive Wastes There were no changes to RW-AA-100, Process Control Program (PCP) for Radioactive Waste, in 2018.

There was a change made to the Steam Generator Blowdown liquid effluent flow path in 20 1 8 under Engineering Change (EC) 624333. See Miscellaneous Information Section I for more details.

Page 15 of 79

Error Analysis The following is an estimate of the errors associated with effluent monitoring and analysis. The estimate is calculated using the square root of the sum of the squares methodology.

1 . Gaseous Effluents Qme=3.33%

RM=N/A ECe=5%

Stdcse/Smplcse=5%

qme=N/A Total error = 7.8%

2. Liquid Effluents Qme=3.33%

RM=N/A ECe=N/A Stdcse/Smplcse=5%

qme=2.22%

Total error = 6.4%

3. Waste Resin Qme=1 0.0%

RM=N/A ECe=5%

Stdcse/Smplcse=5%

qme=1 .0%

Total error = 12.3%

4. DAW, Mechanical Filters, and Contaminated Metal Qme=10.0%

RM=N/A ECe=N/A Stdcse/Smplcse=5%

qme=N/A Instrument calibration error = 10%

Totalerror= 11.2%

Qme = the process quantity measurement error associated with the release point (e.g. flow, level measurements)

RM = error associated with the radiation monitor used in quantifying releases through the release point ECe = error associated with the collection efficiency of the sample media Stdcse = one-sigma counting error associated with the counting instrument of interest Smplcse = one-sigma counting error associated with a sample of a given geometry that is used for the release point of interest qme = sample quantity measurement error associated with the sample of interest Page 16 of 79

Miscellaneous Information A. As required by Technical Specification 5.6.2, meteorological and environmental impact information is reported in the 2018 Annual Radiological Environmental Operating Report (AREOR) or is retained on file to be provided upon request.

B. No limits were exceeded during the 2018 reporting period in liquid hold up tanks or waste gas decay tanks as stated in Technical Specification 5.5.12.

C. There were no irradiated fuel shipments during the 2018 reporting period. An Independent Spent Fuel Storage Installation (ISFSI) campaign began in 2010 when used fuel was removed from the Spent Fuel Pool (SFP), placed into six (6) casks, each containing 32 fuel bundles, and transferred to an outdoor storage pad. No additional casks were placed on the pad in 201 1 In 201 2, eight (8) additional casks were placed on the pad for a total of fourteen (14) casks. No additional casks were placed on the pad in 2013 or 2014. In 2015, six (6) additional casks were placed on the pad for a total oftwenty (20) casks. In 201 6, six (6) additional casks were placed on the pad. No additional casks were placed on the pad in 2017. In 2018, five (5) additional casks were placed on the pad for a total of thirty-one (31).

Prior to the first SF51 campaign, additional dosimeters were placed at the site boundary nearest to the storage pad (in between the pad and the nearest resident) for the purpose of measuring any potential offsite dose to the public from the storage pad. Since the dosimeters were placed, data from the dosimeters, when compared to the existing environmental dosimeters in the surrounding area, have shown no statistical difference. As a result, there is currently no offsite dose contribution from the ISFSI facility or any other on-site storage facility, including the Dry Active Waste (DAW) Building and the Old Steam Generator (OSG) Storage Building, as evidenced by dosimetry data that is indistinguishable from the existing environmental dosimeters.

D. There were no effluent releases or offsite dose calculations that exceeded technical specification or TRM limits during the 2018 reporting period. There were no REMP sample results that exceeded TRM or analytical result investigation levels.

E. There were no elevated releases during the 2018 reporting period. All planned gaseous releases are considered mixed mode releases and were discharged by way of the plant vent stacks.

F. There were no gaseous or liquid effluent monitors that exceeded their respective inoperability time limits in 201 8 as stated in TRM TLCO 3.1 1 .b.

G. There were no unplanned gaseous or liquid releases to unrestricted areas during the 2018 reporting period.

H. All Rock River flow measurements during liquid effluent discharges were obtained from the U.S.

Geological Survey Byron Gauging Station for the Rock River with the following exceptions. Due to icing conditions near the Byron gauging stations on 2/7/1 8 and 2/1 5/1 8, flow was obtained from the Dixon flow gauge, located approximately 32 miles downstream of the Byron flow gauge.

In 2018, a change was made to the Steam Generator Blowdown (SGBD) effluentflow path for both units under Engineering Change (EC) 624333. This EC installed piping to allow SGBD water at a total flow rate up to 1 00 gpm to bypass the SGBD demineralizers and be routed directly to the CP trench in order to extend the life of the SGBD demineralizers, allow overall reduction in SGBD flow, and recover thermal output. The EC increases the amount of water being discharged, which normally contains tritium. However, the amount of tritium present in secondary process water when discharged is negligible compared to the amount of tritium being discharged via liquid release tanks. Therefore, this modification has no impact to effluent release concentrations or offsite dose calculations.

Page 17 of 79

I Attached are offsite dose calculation reports for January through December of 2018.

Page 18 of 79

The following are the maximum annual calculated cumulative offsite doses resulting from Byron airborne releases in 2018 based on concurrent meteorological data:

Unit 1:

Dose Maximum Value Sector Affected gamma air (1) 2.59 xl 06 mrad South-Southeast beta air (2) 6.95 xl 0-6 mrad South-Southeast whole body (3) 6.33 xl 02 mrem South-Southeast skin (4) 4.12 x106 mrem South-Southeast organ (5) (child-bone) 3.13 x101 mrem South-Southeast Unit 1 Compliance Status 10 CFR 50 Appendix I Yearly Objective  % of Appendix I gammaair 10.0 mrad 0.00 betaair 20.0 mrad 0.00 whole body 5.0 mrem 1.27 skin 15.0 mrem 0.00 organ 15.0 mrem 2.09 Unit 2:

Sector Dose Maximum Value Affected gamma air (1) 7.11 x106 m rad South-Southeast beta air (2) 8.78 x106 mrad South-Southeast whole body (3) 6.90 x102 mrem South-Southeast skin (4) 9.00 x106 m rem South-Southeast organ (5) (child-bone) 3.32 x101 mrem South-Southeast Unit 2 Compliance Status 10 CFR 50 Appendix I Yearly Objective  % of Appendix I gamma air 10.0 mrad 0.00 betaair 20.0 mrad 0.00 wholebody 5.0 mrem 1.38 skin 15.0 mrem 0.00 organ 15.0 mrem 2.21 (1)

Gamma Air Dose GASPAR II, NUREG-0597 (2)

Beta Air Dose GASPAR II, NUREG-0597 (3)

Whole Body Dose GASPAR II, NUREG-0597 (4)

Skin Dose GASPAR II, NUREG-0597 (5)

Inhalation and Food Pathways Dose GASPAR II, NUREG-0597 Data recovery: 99.8%

Page 19 of 79

CL JO OZ d LO-389 89 SSOJE LO-3OO 8O-9VL qdI SSOJ 9O-OO*9 LO-3L9 eD LO-300*9 8O-6OV U78O 8O-3L99 OtE7 LO-39V* OV89 9O-3OO* LO- 9E8X LO-OO9 8O-396 LESD 9O-OO 8O-69 LO-OO9 8O-EV9 VE%SD 9O-3OO* LO-96 9O-3OO* 8O-9 9O-68E EELI 80-3 c E;I -oo 9Vt9 2qd, ssoi 9o-E;8t7 9O-3OO* 8O-V8* EIi V3OO V386 9o-oo. LO-3L6 W9)( V3OO V68V V8D 9o-o.v 9qs EV8L Ol1 9O-VVL W981 V3L6 OV9 LO-O[ gq vo-oo 9O-3O LO-OV vs voo EVO99 LeSD 8O-3L9 WE8+/- tO-3OO LO-BE6 8O-69V qs V3*E 8O-39E wO6V W3OO EV3teL VSD LO-3009 8O-38O* 66°VJ VO-OO 9O-O9 W9)(

8O-39L9 96]Z tO-300 LO-30Le 8O-3V6E 96N OVOO EVE98 80-3899 6JS 90-3098 9O-OO9 60-39V8 O6JS VOO EV3699 8O-3OO9 8O-3LE 68JS H.-OO EV6 660VJ go-oo. 8O-309*8 88>1 VOO 9-6 O6-S go-oo. 80-3969 L2)1 L-OO VV3L8 69JS 9O-3OO* 8O-3V99 W99])j vo-oo. LO-3L69 89J>1 8O-399 99J9 170-300* LO-3L1V LO-3009 8O-O6 99UZ LO-9V W99J>j LO-6L1 E9!N VLOL 8JS Lo-oo.9 80-3698 0900 W3OO VO9 99UZ LO-OO9 80-3806 698d 9V36V9 E9!N LO-3009 8O-W9 8900 [-OO 0900 80-EE* L900 V00 V0V 69ed 90-00 L0-30L 998d V300 EVE09 890Q L0-009 80-t7E*V t79UN V00 Vl0L V9UL/N L0-EL 9J0 VLE9 80-LE VEN L0-L69 VJV 90-300* 90-L9 EH L0-00 90-99V (oI!on) au P!flb!7 (Iw/!on) au eP!PflN (°°I!on) au snoese (oo/!on) au ep!pn peJnbaj P!flbIl pai!nbeH snoase (SOil) uoioeiec 0 S1!Wfl i8M07 80 JodeH eseieu U8flU1 !D0O!PH 80 V 1U8WDUV

EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS - BATCH MODE Unit 1 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 63 67 77 56 263 Total release time minutes 4.94E+03 6.47E+03 1.68E+04 5.41E+03 3.36E÷04 Maximum release time minutes 1.87E+02 1.04E+03 2.12E+03 3.07E+02 2.12E+03 Average release time minutes 7.84E+O1 9.65E+O1 2.18E+02 9.66E+O1 1.28E+02 Minimum release time minutes 2.90E+O1 2.20E+O1 5.OOE+O1 5.40E+O1 2.20E+O1 Note: Waste Gas Decay Tank releases are included with Unit 1 data EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS - BATCH MODE Unit 2 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 36 35 32 39 142 Total release time minutes 3.21E+03 2.68E+03 2.S1E+03 4.41E+03 1.28E+04 Maximum release time minutes 1.09E+02 1.71E+02 1.11E+02 2.11E+02 2.11E+02 Average release time minutes 8.93E+O1 7.65E+O1 7.84E+O1 1.13E+02 9.02E+O1 Minimum release time minutes 5.20E+O1 5.70E+O1 5.90E+O1 5.40E+O1 5.20E+O1 EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS - BATCH MODE Unit 1 & Unit 2 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 9 18 37 14 78 Total release time minutes 8.45E+02 7.09E+03 6.28E+03 1.50E+03 1.57E+04 Maximum release time minutes 2.25E+02 7.20E+02 4.66E+02 1.94E+02 7.20E+02 Average release time minutes 9.39E+Ol 3.94E+02 1.70E+02 l.07E+02 2.02E+02 Minimum release time minutes 5.20E+Ol 9.20E+Ol 5.20E+Ol 4.90E+O1 4.90E+O1 Average dilution flow gpm O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Note: Liquid Releases are divided evenly between units Page 21 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 1 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci 8.04E-02 1.23E-O1 4.30E-O1 3.04E-02 6.64E-Ol

2. Avg. Release Rate uCi/sec l.03E-02 1.56E-02 5.41E-02 3.82E-03 2.llE-02 Iodine- 131

1. Total Release Ci 5.38E-07 9.42E-O8 (1) (1) 6.32E-07

2. Avg. Release Rate uCi/sec 6.92E-08 1.20E-08 (1) (1) 2.OOE-O8 Particulates Half Life >= 8 days

1. Total Release Ci (1) (1) (1) (1) (1)

2. Avg. Release Rate uCi/sec (1) (1) (1) (1) (1)

Others

1. Total Release Ci l.l8E+OO l.1OE+OO 9.62E-O1 1.l2E+OO 4.37E+OO

2. Avg. Release Rate uCi/sec l.52E-O1 1.40E-Ol l.2lE-Ol 1.4lE-O1 l.38E-Ol Tr I t ium

1. Total Release Ci 3.51E+OO S.22E+OO 3.2lE+OO l.22E+OO l.32E+Ol

2. Avg. Release Rate uCi/sec 4.SlE-O1 6.64E-Ol 4.04E-O1 1.54E-O1 4.17E-O1 Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) (1)

2. Avg. Release Rate uCi/sec (1) (1) (1) (1) (1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 22 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1C GASEOUS EFFLUENTS - MIXED MODE - CONTINUOUS RELEASES Unit 1 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 7.94E-02 1.21E-O1 3.98E-O1 3.OOE-02 6.28E-O1 Totals for Period. . . Ci 7.94E-02 l.2lE-Ol 3.98E-Ol 3.OOE-02 6.28E-Ol lodines 1-131 Ci 5.38E-07 9.42E-08 (1) (1) 6.32E-07 Totals for Period. . . Ci 5.38E-07 9.42E-08 (1) (1) 6.32E-07 Particulates Half Life >= 8 days

• • No Nuclide Activities ** (1) (1) (1)

(1) (1)

Others C-14 Ci l.18E+OO l.1OE+OO 9.62E-Ol l.l2E+OO 4.37E+OO Totals for Period. . . Ci l.18E+OO l.1OE+OO 9.62E-Ol l.l2E+OO 4.37E+OO Tr i t ium H-3 Ci 3.45E+OO 5.l7E+OO 2.92E+OO l.22E+OO l.28E+Ol Totals for Period. . . Ci 3.45E+OO 5.l7E+OO 2.92E+OO l.22E+OO l.28E+Ol Gross Alpha Radioactivity

• • No Nuclide Activities ** (1) (1) (1) (1)

(1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 S

Page 23 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1C GASEOUS EFFLUENTS - MIXED MODE - BATCH RELEASES Unit 1 REPORT FOR 2018 Units QTR 1 QTR2 QTR3 QTR 4 YEAR Fission and Activation Gases AR-4l Ci (1) (1) 2 .64E-03 9 .48e-06 2 . 65E-03 KR-85M Ci (1) (1) 3 36E-05

. 3 56E-07

. 3 .40E-05 KR-88 Ci (1) (1) 1. OlE-OS (1) 1 . O1E-05 XE-l3lM Ci (1) (1) 5 53E-O5

. 7 15E-06

. 6 .25E-05 XE-133 Ci 9.SOE-04 2 .22E-03 2 53E-02

. 3 70E-04

. 2 . 88E-02 XE-133M Ci (1) (1) 4 02E-04

. 2 60E-06

. 4 . OSE-04 XE-135 Ci (1) (1) 3 76E-03

. 7 37E-06

. 3 . 77E-03 Totals for Period. . . Ci 9 50E-04

. 2 .22E-03 3 .22E-02 3 . 97E-04 3 . 58E-02 lodines

• • No Nuclide Activities (1) (1) (1) (1) (1)

Particulates Half Life >= 8 days

• • No Nuclide Activities (1) (1) (1) (1) (1)

Others

• • No Nuclide Activities (1) (1) (1) (1) (1)

Tr i t ium H-3 Ci 5.60E-02 5.66E-02 2.94E-Ol l.58E-03 4.09E-Ol Totals for Period. . . Ci 5.60E-02 5.66E-02 2.94E-Ol l.58E-03 4.09E-Ol Gross Alpha Radioactivity

• • No Nuclide Activities ** (1) (1) (1) (1) (1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRY Section 3.11 Page 24 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 2 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci 8.04E-02 1.26E-O1 4.41E-Ol 9.33E-02 7.41E-O1

2. Avg. Release Rate uCi/sec l.03E-02 l.60E-02 5.55E-02 l.17E-02 2.35E-02 Iodine-131

1. Total Release Ci (1) (1) (1) (1) (1)

2. Avg. Release Rate uCi/sec (1) (1) (1) (1) (1)

Particulates Half Life >= 8 days

1. Total Release Ci (1) (1) (1) (1) (1)

2. Avg. Release Rate uCi/sec (1) (1) (1) (1) (1)

Others

1. Total Release Ci l.22E+OO l.12E+OO l.17E+OO l.12E+OO 4.64E+OO

2. Avg. Release Rate uCi/sec l.57E-Ol l.43E-Ol l.47E-Ol l.41E-Ol l.47E-Ol Tr I t lum

1. Total Release Ci 8.60E+OO l.68E+Ol l.28E+Ol 7.37E+OO 4.55E+Ol

2. Avg. Release Rate uCi/sec l.11E+OO 2.14E+OO l.61E+OO 9.27E-Ol l.44E+OO Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) (1)

2. Avg. Release Rate uCi/sec (1) (1) (1) (1) (1)

(2) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 25 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1C GASEOUS EFFLUENTS - MIXED MODE - CONTINUOUS RELEASES Unit 2 REPORT FOR 201$ Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 7.94E-02 1.21E-01 3.98E-01 3.OOE-02 6.28E-01 Totals for Period. . . Ci 7.94E-02 1.21E-01 3.98E-01 3.OOE-02 6.28E-01 Iodines

• • No Nuclide Activities (1) (1) (1) (1) (1)

Particulates Half Life >= 8 days

• • No Nuclide Activities ** (1) (1) (1) (1) (1)

Others C-14 Ci 1.22E+00 1.12E+00 1.17E+00 1.12E+00 4.64E+00 Totals for Period. . . Ci l.22E+00 1.12E+00 1.17E+00 1.12E+00 4.64E+00 Tr I t ium 1-1-3 Ci $.52E+00 1.67E+01 l.27E+0l 7.24E+00 4.51E+0l Totals for Period. . . Ci 8.52E+00 1.67E+0l l.27E+0l 7.24E+00 4.51E+01 Gross Alpha Radioactivity

• • No Nuclide Activities ** (1) (1) (1) (1) (1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 26 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1C GASEOUS EFFLUENTS - MIXED MODE - BATCH RELEASES Unit 2 REPORT FOR 201$ Units QTR 1 QTR2 QTR3 QTR 4 YEAR Fission and Activation Gases AR-4l Ci (1) (1) 7.17E-03 4.54E-02 5.26E-02 KR-85M Ci (1) (1) 3.37E-05 3.55E-07 3.41E-05 KR-$8 Ci (1) (1) l.02E-05 (1) l.02E-05 XE-l3lM Ci (1) (1) 5.57E-05 7.l5E-06 6.29E-05 XE-l33M Ci (1) (1) 4.02E-04 2.59E-06 4.OSE-04 XE-l33 Ci 9.54E-04 4.29E-03 3.12E-02 l.78E-02 5.42E-02 XE-l35 Ci (1) (1) 3.77E-03 6.73E-05 3.84E-03 Totals for Period. . . Ci 9.54E-04 4.29E-03 4.26E-02 6.33E-02 l.llE-0l lodines

• • No Nuclide Activities ** (1) (1) (1) (1) (1)

Particulates Half Life >= 8 days

• • No Nuclide Activities ** (1) (1) (1) (1) (1)

Others

• • No Nuclide Activities ** (1) (1) (1) (1) (1)

Tr i t ium H-3 Ci 7.80E-02 9.36E-02 9.77E-02 1.23E-0l 3.92E-0l Totals for Period. . . Ci 7.80E-02 9.36E-02 9.77E-02 1.23E-0l 3.92E-Ol Gross Alpha Radioactivity

• • No Nuclide Activities (1) (1) (1) (1) (1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 27 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit 1 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

1. Total Release Ci 1.85E-03 2.33E-03 2.43E-03 3.60E-03 1.02E-02

2. Avg. Diluted Conc. uCi/mi 5.OSE-1O 6.09E-1O 6.61E-1O 9.S1E-1O 6.82E-1O Tr I t ium

1. Total Release Ci 7.89E+O1 6.73E+02 5.65E+02 9.67E+O1 1.41E+03

2. Avg. Diluted Conc. uCi/mi 2.15E-05 1.75E-04 1.54E-04 2.56E-05 9.44E-O5 Dissolved and Entrained Gases

1. Total Release Ci (1) 2.97E-05 3.36E-04 (1) 3.66E-04

2. Avg. Diluted Conc. uCi/ml (1) 7.74E-l2 9.14E-ll (1) 2.44E-11 Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) (1)

Volume of liquid waste liters 3.67E+09 3.83E÷09 3.67E+09 3.78E+09 1.SOE÷lO (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 28 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A - Release Tank LIQUID EFFLUENTS - SUMMATION BY RELEASE POINT Unit 1 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

1. Total Release Ci l.85E-03 2.33E-03 2.43E-03 3.60E-03 l.02E-02

2. Avg. Diluted Conc. uCi/ml 5.06E-06 3.07E-06 1.60E-06 6.l7E-06 3.16E-06 Tr I t lum

1. Total Release Ci 6.64E+Ol 5.69E+02 5.l2E+02 8.93E+Ol 1.24E+03

2. Avg. Diluted Conc. uC+/-/ml l.SlE-Ol 7.49E-Ol 3.37E-Ol l.53E-Ol 3.83E-Ol Dissolved and Entrained Gases

1. Total Release Ci (1) 2.97E-O5 3.36E-04 (1) 3.66E-04

2. Avg. Diluted Conc. uCi/ml (1) 3.90E-08 2.2lE-07 (1) l.13E-07 Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) (1)

Volume of liquid waste liters 3.67E+05 7.60E+05 l.52E+06 5.82E+05 3.23E+06 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRY Section 3.11 Page 29 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A - Circulating Water Blowdown LIQUID EFFLUENTS - SUMMATION BY RELEASE POINT Unit 1 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

1. Total Release Ci (1) (1) (1) (1) (1)

2. Avg. Diluted Conc. uCi/mi (1) (1) (1) (1) (1)

Tr i t ium

1. Total Release Ci 1.24E+O1 1.04E+02 5.26E+O1 7.41E+OO 1.76E+02

2. Avg. Diluted Conc. uCi/mi 3.3$E-06 2.70E-05 1.43E-05 1.96E-06 1.18E-05 Dissolved and Entrained Gases

1. Total Release Ci (1) (1) (1) (1) (1)

2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) (1)

Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) (1)

Volume of liquid waste liters 3.67E+09 3.83E+09 3.67E+09 3.78E+09 l.50E+lO (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 30 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 23 LIQUID EFFLUENTS - CONTINUOUS MODE Unit 1 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products No Nuclide Activities Ci (1) (1) (1) (1) (1)

Totals for Period Ci (1) (1) (1) (1) (1)

Tn t lum H-3 Ci 1.24E+O1 1.04E+02 5.26E+O1 7.41E+OO 1.76E+02 Totals for Period. . . Ci 1.24E+O1 1.04E+02 5.26E+O1 7.41E+OO 1.76E+02 Dissolved and Entrained Gases No Nuclide Activities Ci (1) (1) (1) (1) (1)

Totals for Period Ci (1) (1) (1) (1) (1)

Gross Alpha Radioactivity No Nuclide Activities Ci (1) (1) (1) (1) (1)

Totals for Period Ci (1) (1) (1) (1) (1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 31 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 23 LIQUID EFFLUENTS - BATCH MODE Unit 1 REPORT FOR 2018 Units QTR 1 QTR2 QTR3 QTR 4 YEAR Fission and Activation Products AG-llOM Ci (1) (1) 4.5lE-06 (1) 4.51E-06 CO-57 Ci 7.59E-06 l.42E-05 l.36E-06 7.85E-06 3.1OE-05 CO-58 Ci l.09E-03 l.07E-03 6.72E-04 9.OOE-04 3.74E-03 CO-CO Ci l.79E-04 4.43E-04 l.02E-03 5.7lE-04 2.2lE-03 CR-Sl Ci (1) (1) 5.87E-04 l.27E-04 7.l3E-04 CS-l36 Ci (1) 2.08E-OC (1) (1) 2.08E-OC FE-59 Ci (1) (1) l.79E-05 3.52E-OC 2.l4E-05 MN-54 Ci 2.llE-OC (1) 2.33E-O5 5.90E-OC 3.l3E-OS N3-95 Ci (1) (1) 4.03E-05 8.SSE-OC 4.89E-05 NI-63 Ci 5.72E-04 7.83E-04 (1) l.93E-03 3.28E-03 S3-124 Ci (1) (1) 8.49E-07 (1) 8.49E-07 S3-l25 Ci (1) l.96E-05 3.92E-05 4.53E-O5 l.04E-04 TE-l23M Ci (1) (1) C.02E-OC (1) C.02E-OC ZR-95 Ci (1) (1) l.63E-05 (1) l.63E-05 Totals for Period. . . Ci l.85E-03 2.33E-03 2.43E-03 3.COE-03 l.02E-02 Tn t ium H-3 Ci 6.64E+Ol 5.69E+02 5.l2E+02 8.93E+Ol l.24E+03 Totals for Period... Ci 6 64E+01

. 5.69E+02 5.12E+02 8.93E+01 l.24E+03 Dissolved and Entrained Gases XE-133 Ci (1) 2 . 97E-05 3 . 36E-04 (1) 3 .66E-04 Totals for Period. . . Ci (1) 2 . 97E-05 3 36E-04

. (1) 3 . 66E-04 Gross Alpha Radioactivity No Nuclide Activities Ci (1) (1) (1) (1) (1)

Totals for Period Ci (1) (1) (1) (1) (1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 32 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit 2 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

1. Total Release Ci 1.85E-03 2.33E-03 2.43E-03 3.60E-03 1.02E-02

2. Avg. Diluted Conc. uCi/mi 5.05E-1O 6.09E-1O 6.61E-1O 9.51E-1O 6.82E-1O Tn t ium

1. Total Release Ci 7.89E+O1 6.73E+02 5.65E+02 9.67E+O1 1.41E+03

2. Avg. Diluted Conc. uCi/mi 2.1SE-05 1.75E-04 1.54E-04 2.56E-05 9.44E-05 Dissolved and Entrained Gases

1. Total Release Ci (1) 2.97E-05 3.36E-04 (1) 3.66E-04

2. Avg. Diluted Conc. uCi/ml (1) 7.74E-12 9.l4E-ll (1) 2.44E-ll Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) (1)

Volume of liquid waste liters 3.67E+09 3.83E+09 3.67E+09 3.78E+09 l.50E+lO (2) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 33 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A - Release Tank LIQUID EFFLUENTS - SUMMATION BY RELEASE POINT Unit 2 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

1. Total Release Ci l.85E-03 2.33E-03 2.43E-03 3.EOE-03 l.02E-02

2. Avg. Diluted Conc. uCi/ml 5.06E-06 3.07E-06 l.60E-06 6.l7E-06 3.16E-06 Tr I t ium

1. Total Release Ci 6.64E+Ol 5.69E+02 5.l2E+02 8.93E+Ol l.24E+03

2. Avg. Diluted Conc. uCi/mi l.81E-Ol 7.49E-Ol 3.37E-Ol l.53E-O1 3.23E-Ol Dissolved and Entrained Gases

1. Total Release Ci (1) 2.97E-05 3.36E-04 (1) 3.66E-04

2. Avg. Diluted Conc. uCi/mi (1) 3.90E-08 2.2lE-07 (1) l.l3E-07 Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) (1)

Volume of liquid waste liters 3.67E+05 7.60E+O5 l.52E+OC 5.82E+05 3.23E+06 (2) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 34 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A - Circulating Water Blowdown LIQUID EFFLUENTS - SUMMATION BY RELEASE POINT Unit 2 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

1. Total Release Ci (1) (1) (1) (1) (1)

2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) (1)

Tr I t ium

1. Total Release Ci l.24E+Ol l.04E+02 S.26E+Ol 7.4lE+OO l.76E+02

2. Avg. Diluted Conc. uCi/ml 3.38E-O6 2.70E-05 l.43E-O5 l.96E-06 l.l8E-05 Dissolved and Entrained Gases

1. Total Release Ci (1) (1) (1) (1) (1)

2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) (1)

Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) (1)

Volume of liquid waste liters 3.67E+09 3.83E+09 3.67E+09 3.78E+09 l.50E+lO (2) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 35 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 23 LIQUID EFFLUENTS - CONTINUOUS MODE Unit 2 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products No Nuclide Activities Ci (1) (1) (1) (1) (1)

Totals for Period Ci (1) (1) (1) (1) (1)

Tr i t ium H-3 Ci 1.24E+O1 1.04E÷02 5.26E÷O1 7.41E+OO 1.76E+02 Totals for Period. . . Ci 1.24E+O1 1.04E+02 5.26E+O1 7.41E+OO 1.76E+02 Dissolved and Entrained Gases No Nuclide Activities Ci (1) (1) (1) (1) (1)

Totals for Period Ci (1) (1) (1) (1) (1)

Gross Alpha Radioactivity No Nuclide Activities Ci (1) (1) (1) (1) (1)

Totals for Period Ci (1) (1) (1) (1) (1)

(2) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 36 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 23 LIQUID EFFLUENTS - BATCH MODE Unit 2 REPORT FOR 2018 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG 1 1 OM

- Ci (1) (1) 4.5lE-06 (1) 4 . 51E-06 CO-57 Ci 7.59E-06 1 .42E-05 1 36E-06

. 7. 85E-O6 3 . 1OE-05 CO-58 Ci 1. 09E-03 1 07E-03

. 6.72E-04 9. OOE-04 3 . 74E-03 CO-CO Ci 1 79E-04

. 4 .43E-04 1 02E-03

. 5 . 7lE-04 2 . 2lE-03 CR-51 Ci (1) (1) 5. 87E-04 1 . 27E-04 7 . 13E-04 CS- 136 Ci (1) 2 08E-06

. (1) (1) 2 . 08E-06 FE-S 9 Ci (1) (1) 1. 79E-O5 3 . 52E-O6 2 . 14E-O5 MN -4 Ci 2 llE-06

. (1) 2 .33E-05 5 . 90E-06 3 . 13E-O5 NB -9 Ci (1) (1) 4 03E-O5

. 8 . 55E-06 4 . 89E-05 NI-63 Ci 5 72E-04

. 7 83E-04

. (1) 1 . 93E-03 3 .28E-03 53-124 Ci (1) (1) 8 .49E-07 (1) 8 .49E-07 53- 125 Ci (1) 1 96E-O5

. 3 92E-05

. 4 .53E-05 1 . 04E-04 TE-123M Ci (1) (1) 6 02E-06

. (1) 6 02E-O6 ZR-95 Ci (1) (1) 1. 63E-05 (1) 1 63E-05 Totals for Period... Ci 1. 85E-03 2 .33E-03 2 43E-03

. 3 . 60E-03 1 02E-02 Tr i t ium H-3 Ci 6 64E+O1

. S 69E+02

. 5 . 12E+02 8 . 93E+Ol 1 24E+03 Totals for Period... Ci 6 64E+O1

. 5 69E+02

. S l2E+02

. 8 . 93E+Ol 1 24E+03 Dissolved and Entrained Gases XE-133 Ci (1) 2 . 97E-05 3 . 36E-04 (1) 3 . 66E-04 Totals for Period. . . Ci (1) 2 . 97E-05 3 . 36E-04 (1) 3 . 66E-04 Gross Alpha Radioactivity No Nuclide Activities Ci (1) (1) (1) (1) (1)

Totals for Period Ci (1) (1) (1) (1) (1)

(2) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 37 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) =========== QUARTER 1 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 4.96E-02 3.69E-02 3.30E-02 3.30E-02 3.30E-02 4.17E-02 0.OOE+00 3.56E-02 TEEN 5.14E-02 2.88E-02 2.48E-02 2.48E-02 2.48E-02 3.08E-02 0.OOE+00 2.74E-02 CHILD 6.77E-02 3.16E-02 2.76E-02 2.76E-02 2.76E-02 2.97E-02 0.OOE+00 3.09E-02 INFANT 3.79E-04 1.23E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 0.OOE+00 1.23E-02

S I TE DO S E L I M I T ANALYS I S == ======

========== QUARTER 1 =====

Age Dose Limit Max % of Quarter - Limit Group Organ (mrem) (mrem) Limit Qtr 1 - Admin. Any Organ CHILD BONE 6.77E-02 3.75E+00 l.8lE+00 Qtr 1 - Admin. Total Body ADULT TBODY 3.56E-02 l.l3E+00 3.l6E+00 Qtr 1 - T.Spc. Any Organ CHILD BONE 6.77E-02 5.OOE+00 1.35E+00 Critical Pathway: Fresh Water Fish - Sport (FF5?)

Major Contributors (0% or greater to total)

Nuclide Percentage NI-63 1.OOE+02 Qtr 1 - T.Spc. Total Body ADULT TBODY 3.56E-02 l.SOE+00 2.37E+00 Critical Pathway: Fresh Water Fish - Sport (FF5?)

Major Contributors (0% or greater to total)

Nuclide Percentage H-3 9 . 28E+0l MN -54 1 . 38E-02 CO-58 1 . 72E+00 CO-CO 7 . 94E-Ol NI-C3 4 . 68E+00 Page 38 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) ============ QUARTER 2 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 8.04E-03 3.42E-02 3.35E-02 3.35E-02 3.35E-02 3.50E-02 0.OOE+00 3.40E-02 TEEN 8.33E-03 2.59E-02 2.S1E-02 2.52E-02 2.51E-02 2.62E-02 0.OOE+00 2.56E-02 CHILD 1.1OE-02 2.88E-02 2.80E-02 2.81E-02 2.80E-02 2.84E-02 0.OOE+00 2.86E-02 INFANT 6.12E-05 1.25E-02 1.25E-02 1.25E-02 1.25E-02 1.25E-02 0.OOE+00 1.25E-02

S I TE DO S E L I M I T ANALYS I S =========== ================= QUARTER 2 ========

Age Dose Limit Max % of Quarter - Limit Group Organ (mrem) (mrem) Limit Qtr 2 - Admin. Any Organ ADULT GILLI 3 SOE-02

. 3 75E+00

. 9.33E-0l Qtr 2 - Admin. Total Body ADULT TBODY 3 .40E-02 1 l3E+00

. 3 02E+00 Qtr 2 - T.Spc. Any Organ ADULT GILLI 3 . SOE-02 5 OOE+00

. 6 99E-0l Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors (0% or greater to total)

Nuclide Percentage H-3 9 58E+O1 CO-S 8 1 83E+OO CO-CO 2 O1E+OO NI-63 3 .31E-Ol 53-125 1. l7E-03 CS- 136 2 .72E-02 Qtr 2 - T.Spc. Total Body ADULT TBODY 3.40E-02 1.50E+OO 2.27E÷OO Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors (0% or greater to total)

Nuclide Percentage H-3 9 86E+Ol CO-S 8 2 08E-Ol CO-CO 2 .43E-Ol NI-63 7. 9lE-Ol 53-125 2 60E-05 CS-136 1 77E-O1 Page 39 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) ============ QUARTER 3 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 1.45E-05 3.63E-02 3.61E-02 3.61E-02 3.61E-02 6.26E-02 0 . OOE+OO 3 64E-02 TEEN 1.48E-05 2.73E-02 2.71E-02 2.71E-02 2.71E-02 4.58E-02 0 . OOE+OO 2 74E-02 CHILD 1.78E-05 3.03E-02 3.02E-02 3.02E-02 3.02E-02 3.69E-02 0 . OOE+OO 3 05E-02 INFANT 1.57E-07 1.34E-02 1.34E-02 1.34E-02 1.34E-02 1.34E-02 0 . OOE+OO l.34E-02

S I TE DO S E L I M I T ANALYS I S ========== =================== QUARTER 3 ========

Age Dose Limit Max % of Quarter - Limit Group Organ (mrem) (mrem) Limit Qtr 3 - Admin. Any Organ ADULT GILLI 6.26E-02 3.75E+00 1.67E+00 Qtr 3 - Admin. Total Body ADULT TBODY 3.64E-02 1.13E+00 3.23E+00 Qtr 3 - T.Spc. Any Organ ADULT GILLI 6.26E-02 5.OOE+00 1.25E+00 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors (0% or greater to total)

Nuclide Percentage H-3 5.76E+01 CR-51 1.18E-Ol MN-54 1.96E-01 FE-59 9.18E-02 CO-58 7.67E-01 CO-CO 3.1OE+OO ZR-95 2.76E-03 NB-95 3.81E+Ol AG-11OM 1.08E-03 SB-124 1.37E-04 SB-125 l.SCE-03 Qtr 3 - T.Spc. Total Body ADULT TBODY 3.C4E-02 1.50E+OO 2.43E+OO Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors (0% or greater to total)

Nuclide Percentage H-3 9 92E+Ol CR-5l 8 09E-04 MN S 4

- 2 lOE-02 FE-59 1. 82E-02 qo-ss l.4CE-Ol CO-CO C.27E-Ol ZR-95 1. O1E-OC Page 40 of 79

4OCFR19O URANIUN FUEL CYCLE DOSE REPORT Nuclide Percentage NE-95 5.82E-03 AG-11OM 2.71E-06 S3-124 3.29E-06 S3-125 5.82E-05 Page 41 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) ============ QUARTER 4 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 9.56E-02 3.24E-02 2.54E-02 2.54E-02 2.54E-02 5.45E-02 0 . OOE+00 2 94E-02 TEEN 9.91E-02 2.65E-02 1.90E-02 1.91E-02 1.90E-02 3 96E-02 . 0 . OOE+00 2 .32E-02 CFIILD 1.31E-01 2.85E-02 2.12E-02 2.12E-02 2.12E-02 2 86E-02 . 0 . OOE+00 2 .65E-02 INFANT 7.31E-04 9.45E-03 9.40E-03 9.40E-03 9.40E-03 9.41E-03 0 . OOE+00 9.44E-03

S I TE DO S E L I M I T ANALYS I S ============================ QUARTER 4 ========

Age Dose Limit Max % of Quarter - Limit Group Organ (mrem) tmrem) Limit Qtr 4 - Admin. Any Organ CHILD BONE 1.31E-01 3.75E+00 3.48E+00 Qtr 4 - Admin. Total Body ADULT TBODY 2.94E-02 1.13E+00 2.61E+00 Qtr 4 - T.Spc. Any Organ CHILD BONE 1.31E-01 5.OOE+00 2.61E+00 Critical Pathway: Fresh Water Fish - Sport tFFSP)

Major Contributors (0% or greater to total)

Nuclide Percentage FE-59 5.60E-03 NI-63 1.OOE+02 NB-95 5.52E-03 SB-125 5.40E-04 Qtr 4 - T.Spc. Total Body ADULT TBODY 2.94E-02 1.50E+00 1.96E+00 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors (0% or greater to total)

Nuclide Percentage H-3 8.63E+01 CR-51 8.72E-04 MN-54 2.66E-02 FE-59 1.78E-02 CO-58 9.78E-01 CO-60 1.75E+00 NI-63 1.09E÷01 NB-95 6.17E-03 SB-125 3.36E-04 Page 42 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) ============ ANNUAL 2018 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 6.23E-02 1.40E-01 1.35E-01 1.35E-01 1.35E-01 1.92E-01 0.OOE+00 1 . 38E-Ol TEEN 6.46E-02 1.06E-01 1.O1E-01 1.O1E-01 1.O1E-01 1.41E-01 0.OOE+00 1. OSE-Ol CHILD 8.51E-02 1.18E-01 1.13E-01 1.13E-01 1.13E-01 1.27E-01 0.OOE+00 1 . l7E-Ol INFANT 4.76E-04 5.OOE-02 5.OOE-02 5.OOE-02 5.OOE-02 5.OOE-02 0.OOE+00 5 . OOE-02

=== SITE DOSE LIMIT ANALYSIS ============================= ANNUAL 2018 Age Dose Limit Max % of Annual - Limit Group Organ (mrem) (mrem) Limit 2018 - Admin. Any Organ ADULT GILLI 1.92E-01 7.50E+00 2 55E+OO 2018 - Admin. Total Body ADULT TBODY 1.38E-01 2.25E+00 6 l4E+OO 2018 - T.Spc. Any Organ ADULT GILLI l.92E-Ol l.OOE+Ol l.92E+OO Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors (0% or greater to total)

Nuclide Percentage H-3 7 . 03E+O1 CR-51 7 . 26E-02 MN -54 1 . 33E-O1 FE-S 9 5 .56E-02 CO-S 8 2 . 16E+OO CO-CO 3 .40E+OO NI-63 4 . 70E-O1 ZR-95 1 .39E-03 NB -9S 2 . 34E+O1 AG 1 1 OM

- 5 . 47E-04 SB- 124 6 . 93E-05 SB- 125 2 . 1OE-03 CS- 136 9 . 21E-03 2018 - T.Spc. Total Body ADULT TBODY l.38E-Ol 3.OOE+OO 4.60E+OO Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors (0% or greater to total)

Nuclide Percentage H-3 9.75E+O1 CR-5l 4 OOE-04 MN -4 1. l5E-02 FE-S 9 8 86E-03 CO-58 3 .31E-Ol Page 43 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT Nuclide Percentage CO-CO 5.53E-O1 NI-63 1.51E+OO ZR-95 4.13E-07 NB-95 2.87E-03 AG-11OM 1.1OE-OC S3-124 1.34E-OC SB-125 C.29E-05 CS-136 8.09E-02 Page 44 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Un+/-tl&2 Report for: 2018 Unit Range - From: 1 To: 2

I &P DOS E L IMI T ANALYS I S ======== =

============ QUARTER 1 =======

Age Dose Limit Max of Quarter - Limit Group Organ (mrem) (mrem) Limit Qtr 1 - Admin. Any Organ CHILD BONE 1.96E-01 5.63E+00 3.49E+00 Qtr 1 - Admin. Total Body CHILD TBODY 3.99E-02 5.25E÷00 7.COE-01 Qtr 1 - T.Spc. Any Organ CHILD BONE 1.96E-01 7.50E+00 2.62E+00 Receptor: S Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway: Vegetation Major Contributors (0% or greater to total)

Nuclide Percentage H-3 0.OOE+00 C-14 l.OOE+02 1-131 4.86E-05 Qtr 1 - T.Spc. Total Body CHILD TEODY 3.99E-02 7.SOE+00 5.32E-0l Receptor: S Composite Crit. Receptor - IP Distance: 800 (meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)

Nuclide Percentage H-3 l.71E+00 C-l4 9.83E+01 1-131 l.38E-04 Page 45 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2

NG DO S E L I M I T ANALYS I S =============== =========== ===== QUARTER 1 ========

Dose Limit Max % of Quarter - Limit (mrad) (mrad) Limit Qtr 1 - Admin. Gamma 3.29E-06 3.75E+00 8.78E-05 Qtr 1 - Admin. Beta 2.41E-06 7.50E+00 3.21E-05 Qtr 1 - T.Spc. Gamma 3.29E-06 5.OOE+00 6.58E-05 Receptor: 4 Composite Crit. Receptor - NG Distance: 800 (meters) Compass Point: SSE Nuclide Percentage XE-133 1.OOE+02 Qtr 1 - T.Spc. Beta 2.41E-06 1.OOE+01 2.41E-05 Receptor: 4 Composite Crit. Receptor - NG Distance: 800(meters) Compass Point: SSE Nuclide Percentage XE-133 1.OOE+02 Page 46 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 201$

Unit Range - From: 1 To: 2

I &P DO S E L TM I T ANALYS I S ========================== ==== QUARTER 2 ========

Age Dose Limit Max % of Quarter - Limit Group Organ (mrem) (mrem) Limit Qtr 2 - Admin. Any Organ CHILD BONE 1 8lE-0l

. 5.63E+00 3.22E+00 Qtr 2 - Admin. Total Body CHILD TBODY 3 75E-02

. 5.25E+00 7.14E-01 Qtr 2 - T.Spc. Any Organ CHILD BONE l.SlE-Ol 7.50E+00 2.42E+00 Receptor: 5 Composite Crit. Receptor - IP Distance: 800 (meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)

Nuclide Percentage H-3 0.OOE+00 C-l4 1.OOE+02 1-131 9.20E-06 Qtr 2 - T.Spc. Total Body CHILD TBODY 3.75E-02 7.50E+00 5.OOE-Ol Receptor: 5 Composite Crit. Receptor - TP Distance: 800 (meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)

Nuclide Percentage H-3 3.32E+00 C-14 9.67E+Ol 1-131 2.57E-05 Page 47 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2

NG DO S E L I M I T ANALYS I S == ============================= QUARTER 2 ========

Dose Limit Max % of Quarter - Limit (mrad) (mrad) Limit Qtr 2 - Admin. Gamma S.09E-06 3.75E+00 1.36E-04 Qtr 2 - Admin. Beta 3.72E-06 7.50E+00 4.96E-05 Qtr 2 - T.Spc. Gamma 5.09E-06 S.OOE+00 1.02E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 800 (meters) Compass Point: SSE Nuclide Percentage XE-133 1.OOE+02 Qtr 2 - T.Spc. Beta 3.72E-06 1.OOE+01 3.72E-05 Receptor: 4 Composite Crit. Receptor - NG Distance: 800 (meters) Compass Point: SSE Nuclide Percentage XE-133 1.OOE+02 Page 48 of 79

40CFR190 URANIUM FUEL CYCLEDOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2

I &P DO S E L I M I T ANALYS I S ============================== QUARTER 3 ========

Age Dose Limit Max % of Quarter - Limit Group Organ (mrem) (mrem) Limit Qtr 3 - Admin. Any Organ CHILD BONE 1.73E-01 5.63E+00 3.08E+00 Qtr 3 - Admin. Total Body CHILD TEODY 3.56E-02 5.25E+00 6.78E-01 Qtr 3 - T. Spc . Any Organ CHILD BONE 1 73E-01

. 7 50E+00

. 2 . 31E+00 Receptor: S Composite Crit. Receptor - IP Distance: 800 (meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)

Nuclide Percentage H-3 0.OOE+00 C-14 100E+02 Qtr 3 - T.Spc. Total Body CHILD TBODY 3.56E-02 7.50E+00 4.75E-01 Receptor: S Composite Crit. Receptor - IP Distance: 800 (meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)

Nuclide Percentage H-3 2.54E+00 C-l4 9.75E+Ol Page 49 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2

=== NG DO S B L I M I T ANALYS I S === =========== ====== ========== QUARTER 3 Dose Limit Max % of Quarter - Limit (mrad) (mrad) Limit Qtr 3 - Admin. Gamma 2.36E-05 3 75E+00

. 6 30E-04 Qtr 3 - Admin. Beta 1.35E-05 7 50E+00

. 1 80E-04 Qtr 3 - T.Spc. Gamma 2 36E-05

. S OOE+00

. 4 . 72E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 800(meters) Compass Point: SSE Nuclide Percentage AR-41 2.24E+01 KR-85M 2.03E-02 XE-135 3.55E+00 XE-133M 6.46E-02 KR-88 7.59E-02 XE-131M 4.27E-03 XE-133 7.39E+01 Qtr 3 - T.Spc. Beta 1.35E-05 1.OOE+01 1.35E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 800(meters) Compass Point: SSE Nuclide Percentage AR-41 3.40E+00 KR-85M 1.40E-02 XE-135 1.96E+00 XE-133M 1.26E-01 KR-88 6.29E-03 XE-131M 1.31E-02 XE-133 9.45E+01 Page 50 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2

I &P DO S E L I M I T ANALYS I S ============================== QUARTER 4 ==== == ==

Age Dose Limit Max % of Quarter - Limit Group Organ (mrem) (mrem) Limit Qtr 4 - Admin. Any Organ CHILD BONE 1.83E-01 5.63E+00 3.24E+00 Qtr 4 - Admin. Total Body CHILD TEODY 3.70E-02 5.25E+00 7.04E-01 Qtr 4 - T.Spc. Any Organ CHILD BONE 1.83E-01 7.50E+00 2.43E+00 Receptor: 5 Composite Crit. Receptor - IP Distance: 800(meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)

Nuclide Percentage H-3 0.OOE+00 C-14 l.OOE+02 Qtr 4 - T.Spc. Total Body CHILD TBODY 3.70E-02 7.SOE+00 4.93E-0l Receptor: 5 Composite Crit. Receptor - IP Distance: 800(meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)

Nuclide Percentage H-3 l.31E+00 C-14 9.87E+Ol Page 51 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2

NG DO S E L I M I T ANALYS I S ======= ========== ======== ==== QUARTER 4 == =======

Dose Limit Max % of Quarter - Limit (mrad) (mrad) Limit Qtr 4 - Admin. Gamma 2.61E-05 3.75E+00 6.96E-04 Qtr 4 - Admin. Beta 3.30E-06 7.50E+00 4.39E-05 Qtr 4 - T.Spc. Gamma 2 . 61E-05 5 OOE+00

. 5 22E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 800 (meters) Compass Point: SSE Nuclide Percentage AR -41 9 . 38E+01 KR- 8 SM 1 . 94E-04 XE- 135 3 . 19E-02 XE- 13 3M 3 . 77E-04 XE- 13 1M 4 . 96E-04 XE- 133 6 . 14E+00 Qtr 4 - T.Spc. Beta 3.30E-06 1.OOE+01 3.30E-05 Receptor: 4 Composite Crit. Receptor - NG Distance: 800(meters) Compass Point: SSE Nuclide Percentage AR -41 6 . 44E+01 KR- 8 SM 6 . 06E-04 XE- 135 7 . 94E-02 XE-133M 3 . 32E-03 XE-131M 6 . 86E-03 XE- 133 3 . SSE+01 Page 52 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS ============================== ANNUAL 2018 Age Dose Limit Max % of Annual - Limit Group Organ (mrem) (mrem) Limit 2018 - Admin. Any Organ CHILD BONE 7.33E-01 1.13E+01 6 52E+00 2018 - Admin. Total Body CHILD TBODY 1.50E-01 1.05E+01 1 43E+00 2018 - T.Spc. Any Organ CHILD BONE 7.33E-0l l.50E÷Ol 4.89E+00 Receptor: 5 Composite Crit. Receptor - IP Distance: 800(meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)

Nuclide Percentage H-3 0.OOE+00 C-14 l.OOE+02 1-131 l.53E-05 2018 - T.Spc. Total Body CHILD TBODY l.50E-Ol l.SOE+Ol l.OOE+00 Receptor: 5 Composite Crit. Receptor - IP Distance: 800(meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)

Nuclide Percentage H-3 2.2lE+00 C-l4 9.78E+Ol 1-131 4.30E-05 Page 53 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS =============================== ANNUAL 2018 Dose Limit Max % of Annual - Limit (mrad) (mrad) Limit 2018 - Admin. Gamma 5.81E-05 7.SOE+00 7.75E-04 2018 - Admin. Beta 2.29E-05 1.SOE+01 1.53E-04 2018 - T.Spc. Gamma 5.81E-05 1.OOE÷01 5.81E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 800(meters) Compass Point: SSE Nuclide Percentage AR -41 5 . 13E+01 KR-85M 8 .36E-03 XE- 135 1 . 46E+00 XE-133M 2 . 64E-02 KR -88 3 . 08E-02 XE-131M 1 . 96E-03 XE -133 4 . 72E+01 2018 - T.Spc. Beta 2.29E-05 2.OOE+01 1.15E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 800(meters) Compass Point: SSE Nuclide Percentage AR -41 1 . 13E+01 KR 8 SM

- 8 .34E-03 XE- 135 1 . 16E+00 XE- 13 3M 7 .45E-02 KR -88 3 . 70E-03 XE-131M 8 . 68E-03 XE-133 8 . 75E+01 Page 54 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT Unit 1 & 2 Report for: 2018 Unit Range - From: 1 To: 2

MAX I MUM DO S E ANALYS I S ================ ================ ANNUAL 2 0 1 8 ======

Age Dose Dose Type Group Organ (mrem)

Any Organ CHILD BONE 8.19E-01 Liquid Receptor: 0 Liquid Receptor Gaseous Receptor: 5 Composite Crit. Receptor - IP Distance: 800(meters) Compass Point: SSE Liquid Dose: 8.S1E-02  % of Total: l.04E+0l Critical Pathway: Fresh Water Fish - Sport tFFSP)

Maj or Contributors (0% or greater to total)

Nuclide Percentage H-3 0 . OOE+OO CR-5l 0 . OOE+OO MN -54 0 . OOE+OO FE-59 2 . OOE-02 CO-58 0 . OOE+0O CO-CO 0 . OOE+OO NI-63 9 . 99E+O1 ZR-95 4 . 28E-O6 NB -95 1 . 85E-02 AG- ilOM 4 . lSE-06 53-124 9 . 22E-O6 53-125 7 . 29E-04 CS- 136 5 . 48E-02 Gaseous Dose: 7.33E-Ol  % of Total: 8.95E+Ol Critical Pathway: Vegetation (VEG)

Maj or Contributors (0% or greater to total)

Nuclide Percentage H-3 0 OOE+OO C-14 1 OOE+02 1-131 1 53E-05 Page 55 of 79

4OCFR19O URANIUM FUEL CYCLE DOSE REPORT Unit 1 & 2

MAX I MUM DO S E ANALYS I S ========== ============= ======== ANNUAL 2 0 1 8 ======

Age Dose Dose Type Group Organ (mrem)

Total Body CHILD T3ODY 2.67E-01 Liquid Receptor: 0 Liquid Receptor Gaseous Receptor: S Composite Crit. Receptor - IP Distance: 800(meters) Compass Point: SSE Liquid Dose: 1.173-01  % of Total: 4.38E+Ol Critical Pathway: Fresh Water Fish - Sport (FFSP)

Maj or Contributors (0% or greater to total)

Nuclide Percentage 11-3 9 63E+O1 CR-51 S 20E-04 MN -54 1.463-02 FE-S 9 1 17E-02 CO-S 8 4.273-01 CO-CO 7 1SE-Ol NI-63 2 47E+OO ZR-95 6 103-07 NB 9S

- 3 75E-03 AG-11OM l.63E-06 53-124 2 .35E-06 53- 125 1. 11E-04 CS- 136 7 1OE-02 Gaseous Dose: 1.SOE-O1  % of Total: S.62E+Ol Critical Pathway: Vegetation (VEG)

Maj or Contributors (0% or greater to total)

Nuclide Percentage 3-3 2 2 13+00 C-14 9 78E+O1 1-131 4 30E-OS Page 56 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY tThHT (Composite Critical Receptor - Limited Analysis)

Release ID  : 1 All Gas Release Types Period Start Date. . . : 01/01/2018 00:00 Period End Date 01/01/2019 00:00 Period Duration (mm)  : 5.256E+05 Coefficient Type  : Historical Unit  : 1

== RELEAS E DATA = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =

Total Release Duration (minutes) 5.794E+0S Total Release Volume (cf) 6.068E+l0 Average Release Flowrate (cfm) 1.047E÷05 Average Period Flowrate (cfm) l.154E÷05

NUCL I BE DATA ============================= =================== =

=

Average EC Nuclide uCi uC i / cc Ratio EC AR -41 2 . 64E+03 l.54E-12 1 54E-04

. 1. OOE-08 KR 8 SM

- 3 . 40E+Ol 1 98E-l4

. 1. 98E-07 1 . OOE-07 KR -82 1 . 02E+0l 5 91E-l5

. 6 .57E-07 9. OOE-09 XE-l3lM 6 . 29E+0l 3 66E-l4

. 1 $3E-08

. 2 . OOE-06 XE-l33M 4 . 04E+02 2 35E-l3

. 3 92E-07

. 6 . OOE-07 XE- 133 6 . 57E+05 3 82E-lO

. 7 65E-04

. 5. OOE-07 XE- 135 3 . 77E+03 2 .20E-l2 3 l4E-05

. 7. OOE-08 F &AG 6 . 64E+05 3 . 86E-lO 9 SlE-04 1-131 6 32E-Ol

. 3 . 68E-l6 1 84E-06

. 2 . OOE-lO Iodine 6.32E-01 3 . 68E-16 1 84E-06 C-14 4 37E+06

. 2 54E-09

. 8 .47E-0l 3 . OOE-09 Other 4 37E+06

. 2 .54E-09 8 .47E-Ol H-3 1 32E+07

. 7 66E-09

. 7 66E-02

. 1 OOE-07 H-3 1 32E+07

. 7 66E-09

. 7 66E-02 Total 1 . 82E+07 1 06E-08

. 9.24E-0l Page 57 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID 2 1 All Gas Release Types Period Start Date 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mm)  : 5.256E+05 Coefficient Type  : Historical Unit  : 1

== MAXIMUM I&P DOSE F OR PER I OD = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =

Limit Organ Age Dose Limit Limit Percent Type Type Group Organ (mrem) Period (mrem) of Limit Admin Any Organ CHILD BONE 3.56E-0l 31-day 2.25E-01 l.58E+02 Quarter 5.63E+00 6.32E+00 Annual 1.l3E+0l 3.16E+00 T.Spec Any Organ CHILD BONE 3.56E-Ol 31-day 3.OOE-0l l.l9E+02 Quarter 7.50E+00 4.74E+00 Annual l.50E+Ol 2.37E+00 Receptor  : 5 Composite Crit. Receptor - IP Distance (meters)  : 0.0 Compass Point . 0.0 Critical Pathway  : 2 Vegetation (VEG)

Major Contributors  : 0.0  % or greater to total Nuclide Percentage H-3 0 OOE+00 C-14 1 OOE+02 1-131 3 .l5E-05 Page 58 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID  : 1 All Gas Release Types Period Start Date. . . : 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mm)  : 5.256E+05 Coefficient Type  : Historical Unit  : 1

=== PERIOD ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem)

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB AGPD 1 . 30E-09 1 30E-09

. 1 30E-09

. 1 . 30E-09 1 . 30E-09 1 30E-09

. 0 . OOE+00 l.30E-09 AINHL 1 . 13E-03 3 .47E-04 3 .47E-04 3 .47E-04 3 .47E-04 3 47E-04

. 0 . OOE+00 3 .47E-04 AVEG 5 . 58E-02 1 14E-02

. 1 14E-02

. 1 . 14E-02 1 . 14E-02 1. 14E-02 0 . OOE+00 1. 14E-02 ACMEAT 2 . 07E-02 4 18E-03

. 4 18E-03

. 4 . l8E-03 4 . l8E-03 4 18E-03

. 0 . OOE+00 4 18E-03 ACMILK 2 . 26E-02 4 60E-03

. 4 61E-03

. 4 . 60E-03 4 . 60E-03 4. 60E-03 0 . OOE+00 4 60E-03 TGPD 1 . 30E-09 1. 30E-09 1 30E-09

. 1 .30E-09 1 . 30E-09 1 30E-09

. 0 . OOE+00 l.30E-09 TINHL 1 . 62E-03 4 39E-04

. 4 39E-04

. 4 . 39E-04 4 . 39E-04 4 39E-04

. 0 . OOE+00 4 .39E-04 TVEG 9 . 02E-02 1 84E-02

. 1. 24E-02 1 . 84E-02 1 . 84E-02 1. 84E-02 0 . OOE+00 1. 84E-02 TCMEAT 1 . 75E-02 3 52E-03

. 3 52E-03

. 3 .52E-03 3 .52E-03 3 52E-03

. 0 . OOE+00 3 52E-03 TCMILK 4 . 17E-02 8 .45E-03 8 .46E-03 8 .45E-03 8 .45E-03 8 .45E-03 0 . OOE+00 8 .45E-03 CGPD 1 . 30E-09 1 30E-09

. 1 30E-09

. 1 . 30E-09 1 . 30E-09 1. 30E-09 0 . OOE+00 1. 30E-09 C INHL 2 . 23E-03 5 39E-04

. 5 39E-04

. 5 . 39E-04 5 . 39E-04 S 39E-04

. 0 . OOE+00 5 .39E-04 CVEG 2 . 12E-0l 4 .41E-02 4 4lE-02

. 4 . 41E-02 4 . 41E-02 4 .41E-02 0 . OOE+00 4 41E-02 CCMEAT 3 . 29E-02 6 62E-03

. 6 62E-03

. 6 . 62E-03 6 . 62E-03 6 62E-03

. 0 . OOE+00 6 62E-03 CCMILK 1 . 03E-0l 2 06E-02

. 2 07E-02

. 2 . 06E-02 2 . 06E-02 2 06E-02

. 0 . OOE+00 2 06E-02 IGPD 1 . 30E-09 1 30E-09

. 1 30E-09

. 1 . 30E-09 1 . 30E-09 1 30E-09

. 0 . OOE+00 1. 30E-09 IINHL 1 . 65E-03 4 OOE-04

. 4 OOE-04

. 4 . OOE-04 4 . OOE-04 4 OOE-04

. 0 . OOE+00 4 OOE-04 ICMILK 2 . OlE-Ol 4 31E-02

. 4 .32E-02 4 . 3lE-02 4 . 31E-02 4 3lE-02

. 0 . OOE+00 4 31E-02 TOTALS ADULT l.OOE-0l 2.OSE-02 2 05E-02

. 2.OSE-02 2.OSE-02 2.05E-02 0.OOE+00 2 05E-02 TEEN l.51E-Ol 3.08E-02 3 08E-02

. 3.08E-02 3.08E-02 3.08E-02 0.OOE+00 3 0$E-02 CHILD 3.56E-0l 7.l9E-02 7 l9E-02

. 7.19E-02 7.l9E-02 7.19E-02 0.OOE+00 7 l9E-02 INFANT 2.03E-0l 4.35E-02 4 36E-02

. 4.35E-02 4.35E-02 4.35E-02 0.OOE+00 4 35E-02

AGE GROUP I PATHWAY DE S CR I PT I ONS ========================================

Abbreviation Age Group Pathway AGPD ADULT Ground Plane Deposition (GPD)

AINHL ADULT Inhalation (INHL)

AVEG ADULT Vegetation (VEG)

ACMEAT ADULT Grs/Cow/Meat (CMEAT)

ACMILK ADULT Grs/Cow/Milk (CMILK)

TGPD TEEN Ground Plane Deposition (GPD)

TINHL TEEN Inhalation (INHL)

TVEG TEEN Vegetation (VEG)

TCMEAT TEEN Grs/Cow/Meat (CMEAT)

TCMILK TEEN Grs/Cow/Milk (CMILK)

CGPD CHILD Ground Plane Deposition (GPD)

CINHL CHILD Inhalation (INHL)

Page 59 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID  : 1 All Gas Release Types Period Start Date. . . : 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mm)  : 5.256E+05 Coefficient Type  : Historical Unit  : 1

= = AGE GROUP I PATHWAY BE S CR I PT I ONS =========================== ======= ======

Abbreviation Age Group Pathway CVEG CHILD Vegetation (VEG)

CCMEAT CHILD Grs/Cow/Meat (CMEAT)

CCMILK CHILD Grs/Cow/Milk (CMILK)

IGPD INFANT Ground Plane Deposition (GPD)

IINHL INFANT Inhalation (INHL)

ICMILK INFANT Grs/Cow/Milk (CMILK)

Page 60 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID . 1 All Gas Release Types Period Start Date. . . : 01/01/2018 00:00 Period End Date 01/01/2019 00:00 Period Duration (mm) : 5.256E+05 Coefficient Type  : Historical Unit . 1

MAX I MUM NG DO S E FOR PER I 00 ========================= =

======

Limit Dose Limit Limit Percent Type Dose Type (mrad) Period (mrad) of Limit Admin Gamma l.53E-05 3 1 day

- 1 SOE-Ol

. 1 . 02E-02 Quarter 3 75E+00

. 4 . 08E-04 Annual 7 SOE+00

. 2 . 04E-04 Admin Beta l.OlE-05 31-day 3.OOE-Ol 3 .37E-03 Quarter 7.50E+00 1 35E-04 Annual l.50E+01 6 73E-05 T.Spec Gamma 1 53E-05

. 31-day 2.OOE-Ol 7 . 66E-03 Quarter 5.OOE+00 3 . 06E-04 Annual l.OOE+01 1 . 53E-04 Receptor  : 4 Composite Crit. Receptor - NG Distance (meters)  : 0.0 Compass Point  : 0.0 Major Contributors  : 0.0  % or greater to total Nuclide Percentage AR -41 9 32E+00 KR- 8 SM l.58E-02 KR -88 5 85E-02 XE-l3lM 3 71E-03 XE-133M 5 OlE-02 XE -133 8 78E+Ol XE- 135 2 74E+00 T.Spec Beta 1.O1E-05 31-day 4.OOE-01 2 . 52E-03 Quarter l.OOE+01 1 . O1E-04 Annual 2.OOE+Ol 5 . 05E-05 Receptor  : 4 Composite Crit. Receptor - NG Distance (meters)  : 0.0 Compass Point  : 0.0 Major Contributors  : 0.0 6 or greater to total Nuclide Percentage AR -41 1 22E+00 KR 8 SM

- 9.46E-03 Page 61 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID  : 1 All Gas Release Types Period Start Date. . . : 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mm)  : 5.256E+05 Coefficient Type  : Historical Unit  : 1 Major Contributors  : 0.0  % or greater to total Nuclide Percentage KR-88 4.20E-03 XE-l3lM 9.85E-03 XE-133M 8.45E-02 XE-l33 9.74E+Ol XE-135 l.3lE+00 Page 62 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID .  : 1 All Gas Release Types Period Start Date. . . : 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mm)  : 5.256E+05 Coefficient Type  : Historical Unit  : 2

RE LEAS E DATA = = = = = = = = = = = = = = = = = = = = = = = = = = =============================== ==

Total Release Duration (minutes) 5.637E+05 Total Release Volume (cf) 8.l96E+lO Average Release Flowrate (cfm) l.454E+05 Average Period Flowrate (ctm) l.559E+05

NUCL I IDE DATA ==== ======================================================= =

Average EC Nucl ide uCi uCi/cc Ratio EC AR -41 5 26E+04

. 2 . 26E-ll 2 .26E-03 1 . OOE-08 KR- 8 SM 3 40E+Ol

. 1 .47E-14 l.47E-07 1 . OOE-07 KR -88 1 02E+01

. 4 . 38E-lS 4 86E-07

. 9. OOE-09 XE-l3lM 6 29E+Ol

. 2 . 7lE-14 1 35E-08

. 2 . OOE-06 XE- 13 3M 4 04E+02

. 1 . 74E-l3 2 90E-07

. 6 . OOE-07 XE- 133 6 82E+05

. 2 . 94E-lO 5 88E-04

. 5 . OOE-07 XE- 135 3 83E+03

. 1 . 65E-12 2 .36E-05 7 . OOE-08 F &AG 7 39E+05

. 3 . 18E-10 2 . 88E-03 C-14 4.64E+06 2.OOE-09 6.66E-0l 3.OOE-09 Other 4.64E+06 2.OOE-09 6.66E-Ol H-3 4.55E+07 l.96E-08 l.96E-Ol l.OOE-07 H-3 4.55E+07 l.96E-08 l.96E-0l Total 5 . 09E+07 2 . 19E-08 8 65E-0l Page 63 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID  : 1 All Gas Release Types Period Start Date 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mm)  : 5.256E+05 Coefficient Type . Historical Unit  : 2

== MAX I MUM I &P DO S E FOR PER I OD = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =

Limit Organ Age Dose Limit Limit Percent Type Type Group Organ (mrem) Period (mrem) of Limit Admin Any Organ CHILD BONE 3.78E-0l 31-day 2.25E-0l 1 68E+02 Quarter 5.63E+00 6 72E+00 Annual l.13E+0l 3 36E+00 T.Spec Any Organ CHILD BONE 3.78E-0l 31-day 3.OOE-0l 1 26E+02 Quarter 7.SOE+00 5 04E+00 Annual l.50E+0l 2 52E+00 Receptor  : 5 Composite Crit. Receptor - IP Distance (meters)  : 0.0 Compass Point . 0.0 Critical Pathway  : 2 Vegetation (VEG)

Major Contributors  : 0.0  % or greater to total Nuclide Percentage H-3 0 OOE+00 C-l4 1 .OOE+02 Page 64 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID  : 1 All Gas Release Types Period Start Date. . . : 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mm)  : 5.256E+05 Coefficient Type  : Historical Unit  : 2

=== PERIOD ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem)

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB AINHL l.20E-03 6.92E-04 6.92E-04 6.92E-04 6.92E-04 6.92E-04 0.OOE+00 6.92E-04 AVEG 5.93E-02 l.27E-02 l.27E-02 l.27E-02 l.27E-02 l.27E-02 0.OOE+00 l.27E-02 ACMEAT 2.20E-02 4.52E-03 4.52E-03 4.52E-03 4.52E-03 4.52E-03 0.OOE+00 4.52E-03 ACMILK 2.40E-02 5.08E-03 5.O8E-03 5.08E-03 5.08E-03 5.08E-03 0.OOE+00 5.08E-03 TINHL l.72E-03 7.92E-04 7.92E-04 7.92E-04 7.92E-04 7.92E-04 0.OOE+00 7.92E-04 TVEG 9.58E-02 2.02E-02 2.02E-02 2.02E-02 2.02E-02 2.02E-02 0.OOE+00 2.02E-02 TCMEAT l.86E-02 3.79E-03 3.79E-03 3.79E-03 3.79E-03 3.79E-03 0.OOE+00 3.79E-03 TCMILK 4.43E-02 9.23E-03 9.23E-03 9.23E-03 9.23E-03 9.23E-03 0.OOE+00 9.23E-03 CINHL 2.37E-03 8.60E-04 8.60E-04 8.60E-04 8.60E-04 8.60E-04 0.OOE+00 8.60E-04 CVEG 2.31E-0l 4.78E-02 4.78E-02 4.78E-02 4.78E-02 4.78E-02 0.OOE+00 4.78E-02 CCMEAT 3.SOE-02 7.09E-03 7.09E-03 7.09E-03 7.09E-03 7.09E-03 0.OOE+00 7.09E-03 CCMILK l.09E-0l 2.23E-02 2.23E-02 2.23E-02 2.23E-02 2.23E-02 0.OOE+00 2.23E-02 IINHL l.75E-03 5.90E-04 5.90E-04 5.90E-04 5.90E-04 S.90E-04 0.OOE+00 5.90E-04 ICMILK 2.14E-0l 4.64E-02 4.64E-02 4.64E-02 4.64E-02 4.64E-02 0.OOE+00 4.64E-02 TOTALS ADULT l.07E-0l 2.30E-02 2.30E-02 2.30E-02 2.30E-02 2.30E-02 0.OOE+00 2.30E-02 TEEN l.60E-0l 3.40E-02 3.40E-02 3.40E-02 3.40E-02 3.40E-02 0.OOE+00 3.40E-02 CHILD 3.78E-0l 7.81E-02 7.8lE-02 7.81E-02 7.SlE-02 7.81E-02 0.OOE+00 7.$lE-02 INFANT 2.15E-0l 4.70E-02 4.70E-02 4.70E-02 4.70E-02 4.70E-02 0.OOE+00 4.70E-02

= = = AGE GROUP

/ PATHWAY IDE S CR I PT I ONS ====================================== === ==

Abbreviat ion Age Group Pathway AINHL ADULT Inhalation (INHL)

AVEG ADULT Vegetation (VEG)

ACMEAT ADULT Grs I Cow/Meat ( CMEAT)

ACMILK ADULT Grs/Cow/Milk (CMILK)

T INHL TEEN Inhalation (INHL)

TVEG TEEN Vegetation (VEG)

TCMEAT TEEN Grs/Cow/Meat (CMEAT)

TCMILK TEEN Grs/Cow/Milk (CMILK)

CINHL CHILD Inhalation (INHL)

CVEG CHILD Vegetation (VEG)

CCMEAT CHILD Grs/Cow/Meat (CMEAT)

CCMI LK CHILD Grs/Cow/Milk (CMILK)

IINHL INFANT Inhalation (INHL)

ICMILK INFANT Grs/Cow/Milk (CMILK)

Page 65 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID  : 1 All Gas Release Types Period Start Date. . . : 01/01/2018 00:00 Period End Date 01/01/2019 00:00 Period Duration (mm)  : 5.256E+05 Coefficient Type  : Historical Unit  : 2

== MAX I MUM NG DO S E FOR PER I OD ============================== =================

Limit Dose Limit Limit Percent Type Dose Type (mrad) Period (mrad) of Limit Admin Gamma 4 28E-05

. 31-day 1 50E-Ol

. 2 85E-02 Quarter 3 75E+00

. 1. l4E-03 Annual 7 50E+00

. 5 .70E-04 Admin Beta l.28E-05 31-day 3.OOE-Ol 4 .27E-03 Quarter 7.50E+00 1. 7lE-04 Annual l.50E+Ol 8 54E-05 T.Spec Gamma 4 .28E-0S 31-day 2 OOE-01

. 2 14E-02 Quarter 5 OOE+00

. 8 .55E-04 Annual 1 OOE+01

. 4 28E-04 Receptor  : 4 Composite Crit. Receptor - NG Distance (meters)  : 0.0 Compass Point  : 0.0 Major Contributors  : 0.0  % or greater to total Nuclide Percentage AR -41 6 63E+01 KR-85M 5 68E-03 KR -88 2 09E-02 XE-131M l.33E-03 XE- 13 3M 1.79E-02 XE- 133 3 27E+01 XE- 135 9 98E-01 T.Spec Beta 1 28E-05

. 31-day 4 OOE-01

. 3 .20E-03 Quarter 1 OOE+01

. 1 28E-04 Annual 2 OOE+01

. 6 .41E-05 Receptor 4 Composite Crit. Receptor - NG Distance (meters)  : 0.0 Compass Point . 0.0 Major Contributors . 0.0  % or greater to total Nuclide Percentage AR -41 1 92E+01 KR- 8 SM 7 .46E-03 Page 66 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID . 1 All Gas Release Types Period Start Date. . . . : 01/01/2018 00:00 Period End Date 01/01/2019 00:00 Period Duration (mm) : 5.256E+05 Coefficient Type . Historical Unit  : 2 Major Contributors  : 0.0  % or greater to total Nuclide Percentage KR-88 3.31E-03 XE-131M 7.76E-03 XE-133M 6.66E-02 XE-133 7.97E+0l XE-135 l.05E+00 Page 67 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID . . 1 All Liquid Releases Period Start Date  : 01/01/2018 00:00 Period End Date . 01/01/2019 00:00 Period Duration (mins) : 5.256E+05 Unit . 1

= = MULT I PLE RELEAS E P0 I NT ME S SAGE = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =

Undiluted and Diluted Flowrate(s) and Concentration(s) cannot be combined.

== RELEAS E DATA = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =

Total Release Duration (minutes) 5.4l3E+05 Total Undiluted Volume Released (gallons) NA Average Undiluted Flowrate (gpm) NA Total Dilution Volume (gallons) NA Average Dilution Flowrate (gpm) NA

NUCL I IDE DATA ===== =======================================================

Nuclide uCi CO-57 3.1OE+Ol 53-124 8.49E-Ol 53-125 l.04E+02 TE-l23M 6.02E+00 CR-Sl 7.l3E+02 MN-54 3.l3E+Ol FE-59 2.l4E+0l CO-58 3.74E+03 CO-CO 2.21E+03 ZR-95 l.63E+Ol NB-95 4.89E+Ol AG-llOM 4.5lE+OO CS-l36 2.O$E+OO Gamma C.93E+03 XE-l33 3.66E+02 D&EG 3.CCE+02 H-3 l.4lE+09 NI-63 1.36E+03 Beta l.4lE+09 Total l.4lE+09 Page 68 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID  : 1 All Liquid Releases Period Start Date  : 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mins)  : 5.256E+05 Unit  : 1 Receptor  : 0 Liquid Receptor

=== PERMIT ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem)

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB APWtr 4.46E-05 l.88E-02 l.88E-02 l.88E-02 l.88E-02 l.89E-02 0.OOE+00 l.88E-02 AFWFSp l.28E-02 4.98E-02 4.85E-02 4.86E-02 4.85E-02 7.66E-02 0.OOE+00 4.96E-02 TPWtr 4.24E-05 l.33E-02 l.33E-02 l.33E-02 l.33E-02 l.33E-02 0.OOE+00 l.33E-02 TFWFSp l.33E-02 3.86E-02 3.73E-02 3.73E-02 3.73E-02 5.71E-02 0.OOE+00 3.84E-02 CPWtr l.29E-04 2.55E-02 2.54E-02 2.54E-02 2.54E-02 2.55E-02 0.OOE+00 2.55E-02 CFWFSp l.75E-02 3.21E-02 3.09E-02 3.09E-02 3.09E-02 3.79E-02 0.OOE+00 3.22E-02 IPWtr 9.84E-05 2.50E-02 2.SOE-02 2.50E-02 2.50E-02 2.50E-02 0.OOE+00 2.50E-02 TOTALS -

ADULT 1.29E-02 6.86E-02 6.73E-02 6.74E-02 6 74E-02 9.55E-02

. 0 . OOE+OO 6 85E-02 TEEN 1.34E-02 5.19E-02 5.05E-02 5.06E-02 5 OSE-02 7 03E-02

. . 0 . OOE+OO 5.17E-02 CHILD 1.76E-02 5.76E-02 5.63E-02 5.64E-02 5. 63E-02 6 .34E-02 0 . OOE+OO 5 .76E-02 INFANT 9.84E-05 2.50E-02 2.50E-02 2.50E-02 2 .50E-02 2 SOE-02

. 0 . OOE+OO 2 50E-02

= = AGE GROUP I PATHWAY DE S CR I PT I ONS ==========================================

Abbreviation Age Group Pathway APWtr ADULT Potable Water (PWtr)

AFWFSp ADULT Fresh Water Fish - Sport (FFSP)

TPWtr TEEN Potable Water (PWtr)

TFWFSp TEEN Fresh Water Fish - Sport (FFSP)

CPWtr CHILD Potable Water (PWtr)

CFWFSp CHILD Fresh Water Fish - Sport (FFSP)

IPWtr INFANT Potable Water (PWtr)

Page 69 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID . 1 All Liquid Releases Period Start Date  : 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mins)  : 5.256E+05 Unit  : 1 Receptor  : 0 Liquid Receptor

=== PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 1:1-3 0.OOE+00 6.73E-02 6.73E-02 6.73E02 6.73E-02 6.73E02 0.OOE+00 6.73E02 CR-51 0.OOE+00 0.OOE+00 1.65E-07 6.09E-08 3.67E-07 6.95E-05 0.OOE+00 2.76E-07 MN-54 0.OOE+00 4.16E-05 0.OOE+00 1.24E-05 0.OOE+00 1.28E-04 0.OOE+00 7.95E-06 FE-59 6.79E-06 1.60E-05 0.OOE+00 0.OOE+00 4.46E-06 5.32E-05 0.OOE+00 6.12E-06 CO-58 0.OOE+00 1.02E-04 0.OOE+00 0.OOE+00 0.OOE+00 2.07E-03 0.OOE+00 2.29E-04 CO-60 0.OOE+00 l.73E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.26E-03 0.OOE+00 3.82E-04 NI-63 1.29E-02 8.91E-04 0.OOE+00 0.OOE+00 0.OOE+00 l.86E-04 0.OOE+00 4.31E-04 ZR-95 1.31E-09 4.21E-10 0.OOE+00 6.6lE-10 0.OOE+00 l.33E-06 0.OOE+00 2.85E-10 NB-95 6.63E-06 3.69E-06 0.OOE+00 3.64E-06 0.OOE+00 2.24E-02 0.OOE+00 1.98E-06 AG-ibM 1.39E-09 l.28E-09 0.OOE+00 2.53E-09 0.OOE+00 5.24E-07 0.OOE+00 7.63E-lO SB-124 2.33E-09 4.41E-11 1.46E-08 0.OOE+00 1.82E-09 6.64E-08 0.OOE+00 9.25E-lO SB-125 1.83E-07 2.04E-09 1.86E-10 0.OOE+00 l.41E-07 2.O1E-06 0.OOE+00 4.35E-08 CS-136 1.97E-05 7.77E-05 0.OOE+00 4.32E-05 5.92E-06 8.82E-06 0.OOE+00 5.59E-05 TEEN H-3 0.OOE+00 5.05E-02 5.05E-02 5.05E-02 5.05E-02 5.OSE-02 0.OOE+00 5.OSE-02 CR-51 0.OOE+00 0.OOE+00 1.58E-07 6.24E-08 4.07E-07 4.79E-05 0.OOE+00 2.85E-07 MN-54 0.OOE+00 4.lOE-05 0.OOE+00 l.22E-05 0.OOE+00 8.40E-05 0.OOE+00 8.12E-06 FE-59 7.OOE-06 1.63E-05 0.OOE+00 0.OOE+00 5.1SE-06 3.86E-05 0.OOE+00 6.30E-06 cO-58 0.OOE+00 1.O1E-04 0.OOE+00 0.OOE+00 0.OOE+00 l.40E-03 0.OOE+00 2.33E-04 CO-GO 0.OOE+00 1.73E-04 0.OOE+00 0.OOE+00 0.OOE+00 2.26E-03 0.OOE+00 3.90E-04 NI-63 1.33E-02 9.41E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.50E-04 0.OOE+00 4.52E-04 ZR-95 1.35E-09 4.24E-10 0.OOE+00 6.24E-10 0.OOE+00 9.80E-07 0.OOE+00 2.92E-lO NB-95 6.68E-06 3.70E-06 0.OOE+00 3.59E-06 0.OOE+00 l.58E-02 0.OOE+00 2.04E-06 AG-ibM 1.34E-09 l.27E-09 0.OOE+00 2.42E-09 0.OOE÷00 3.56E-07 0.OOE+00 7.72E-lO SB-124 2.40E-09 4.42E-11 5.45E-12 0.OOE+00 2.1OE-09 4.86E-08 0.OOE+00 9.39E-10 SB-125 1.89E-07 2.06E-09 1.80E-10 0.OOE+00 l.66E-07 1.47E-06 0.OOE+00 4.42E-08 CS-136 1.98E-05 7.78E-05 0.OOE+00 4.24E-05 6.68E-06 6.26E-06 0.OOE+00 5.23E-05 CHILD 1-1-3 0. OOE+00 5 63E-02 5 63E-02

. . 5. 63E-02 5. 63E-02 5. 63E-02 0 OOE+00

. 5.63E-02 CR-51 0.OOE+00 0.OOE+00 1.69E-07 4.62E-08 3.O8E-07 l.61E-05 0.OOE+00 3.04E-07 MN-54 0.OOE+00 3.2lE-05 0.OOE+00 8.99E-06 0.OOE+00 2.69E-05 0.OOE+00 8.54E-06 FE-59 2.52E-06 l.3$E-05 0.OOE÷00 0.OOE÷00 3.99E-06 l.43E-05 0.OOE+00 6.86E-06 CO-58 0.OOE+00 8.16E-05 0.OOE+00 0.OOE+00 0.OOE+00 4.76E-04 0.OOE+00 2.50E-04 CO-co 0.OOE+00 1.42E-04 0.OOE+00 0.OOE+00 0.OOE+00 7.85E-04 0.OOE+00 4.18E-04 NI-63 1.75E-02 9.39E-04 0.OOE+00 0.OOE+00 0.OOE+00 6.33E-05 0.OOE+00 5.97E-04 ZR-95 1.82E-09 4.O1E-10 0.OOE+00 5.74E-10 0.OOE+00 4.l8E-07 0.OOE+00 3.57E-10 NB-95 7.88E-06 3.07E-06 0.OOE+00 2.88E-06 0.OOE+00 5.67E-03 0.OOE+00 2.19E-06 Page 70 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID . 1 All Liquid Releases Period Start Date . 01/01/2018 00:00 Period End Date 01/01/2019 00:00 Period Duration (mins): 5 256E+05

=== PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB AG-llOM l.76E-09 l.19E-09 0.OOE+00 2.22E-09 0.OOE+00 l.42E-07 0.OOE+00 9.53E-lO SB-l24 3.92E-09 5.08E-ll 8.67E-l2 0.OOE+00 2.l8E-09 2.45E-08 0.OOE+00 l.37E-09 SB-125 3.1OE-07 2.39E-09 2.87E-l0 0.OOE+00 l.73E-07 7.41E-07 0.OOE+00 6.49E-08 CS-136 2.33E-05 6.4lE-05 0.OOE+00 3.42E-05 S.09E-06 2.25E-06 0.OOE+00 4.l5E-05 INFANT H-3 0.OOE+00 2.SOE-02 2.50E-02 2.50E-02 2.SOE-02 2.50E-02 0.OOE+00 2.50E-02 CR-5l 0.OOE+00 0.OOE+00 7.SOE-lO l.64E-l0 l.46E-09 3.35E-08 0.OOE+00 l.l5E-09 MN-54 0.OOE+00 7.l2E-08 0.OOE+00 l.S8E-08 0.OOE+00 2.61E-08 0.OOE+00 l.6lE-08 FE-59 7.55E-08 l.32E-07 0.OOE+00 0.OOE+00 3.90E-08 6.30E-08 0.OOE+00 5.l9E-08 cO-58 0.OOE+00 l.54E-06 0.OOE+00 0.OOE+00 0.OOE+00 3.83E-06 0.OOE+00 3.84E-06 CO-co 0.OOE+00 2.73E-06 0.OOE+00 0.OOE+00 0.OOE+00 6.50E-06 0.OOE+00 6.45E-06 NI-63 9.82E-05 6.07E-06 0.OOE+00 0.OOE+00 0.OOE+00 3.02E-07 0.OOE+00 3.4lE-06 ZR-95 3.83E-lO 9.34E-ll 0.OOE+00 l.OlE-l0 0.OOE+00 4.65E-08 0.OOE+00 6.62E-ll NB-95 2.34E-l0 9.66E-ll 0.OOE+00 6.92E-ll 0.OOE+00 8.l5E-08 0.OOE+00 5.58E-ll AG-llOM 5.l3E-l0 3.74E-lO 0.OOE+00 5.36E-l0 0.OOE+00 l.94E-08 0.OOE+00 2.48E-lO SB-124 2.08E-09 3.07E-ll 5.52E-12 0.OOE+00 l.30E-09 6.42E-09 0.OOE+00 6.45E-lO SB-l25 l.46E-07 l.42E-09 l.83E-lO 0.OOE+00 8.47E-08 l.95E-07 0.OOE+00 3.OlE-08 CS-l36 l.09E-08 3.20E-08 0.OOE+00 l.28E-08 2.61E-09 4.87E-l0 0.OOE+00 l.20E-08 Page 71 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID  : 1 All Liquid Releases Period Start Date . 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mins)  : 5.256E+05 Unit 2 1 Receptor  : 0 Liquid Receptor

=== MAXIMUM DOSE FOR PERIOD Limit Organ Age Dose Limit Limit Percent Type Type Group Organ (mrem) Period (mrem) of Limit Admin Any Organ ADULT GILLI 9 SSE-02

. 31-day 1 SOE-O1

. 6 37E+Ol Quarter 3 75E+OO

. 2 SSE+OO Annual 7 SOE+OO

. 1 27E+OO Admin Tot Body ADULT TBODY 6.85E-02 3 1 day

- 4 SOE-02

. 1 52E+02 Quarter 1 l3E+OO

. 6 09E+OO Annual 2 25E+OO

. 3 04E+OO T.Spec Any Organ ADULT GILLI 9.SSE-02 31-day 2 OOE-Ol

. 4 77E+Ol Quarter S OOE+OO

. 1 91E+OO Annual 1 OOE+Ol

. 9 SSE-O1 Critical Pathway . : 1 Fresh Water Fish - Sport (FFSP)

Major Contributors .  : 0.0 % or greater to total Nuclide Percentage SB- 125 2. 1OE-03 SB- 124 6. 95E-OS H-3 7 OSE+O1 CR-S 1 7 28E-02 MN -4 l.34E-Ol FE-59 S.57E-02 CO-SB 2 l6E+OO CO-CO 3 41E+OO NI-63 1. 95E-O1 ZR-95 1 40E-03 NB 9S

- 2 34E+Ol AG 1 1 OM

- S 49E-04 CS- 13 6 9.24E-03 T.Spec Tot Body ADULT TBODY 6 . 85E-02 31-day 6 OOE-02

. 1 l4E+02 Quarter 1 SOE+0O

. 4 56E+OO Annual 3 OOE+0O

. 2 28E+OO Critical Pathway  : 1 Fresh Water Fish - Sport (FFSP)

Major Contributors  : 0.0 % or greater to total Nuclide Percentage Page 72 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID  : 1 All Liquid Releases Period Start Date  : 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mins)  : 5.256E+05 Major Contributors  : 0.0 % or greater to total Nuclide Percentage 53-125 6.35E-05 SB-l24 l.35E-06 H-3 9.84E+Ol CR-51 4.04E-04 MN-54 l.16E-02 FE-59 8.94E-03 CO-58 3.34E-Ol CO-co 5.58E-Ol NI-63 6.30E-Ol ZR-95 4.l6E-07 NB-95 2.90E-03 AG-11OM l.llE-06 CS-l36 8.l7E-02 Page 73 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID  : 1 All Liquid Releases Period Start Date 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mins)  : 5.256E+05 Unit  : 2

= = MULT I PLE RELEAS E P0 I NT ME S SAGE = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =

Undiluted and Diluted Flowrate(s) and Concentration(s) cannot be combined.

== RELEAS E DATA = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =

Total Release Duration (minutes) 5.4l3E+05 Total Undiluted Volume Released (gallons) NA Average Undiluted Flowrate (gpm) NA Total Dilution Volume (gallons) NA Average Dilution Flowrate (9pm) NA

===

Nuclide uCi CO-57 3.lOE+Ol 53-124 8.49E-01 53-125 l.04E+02 TE-123M 6.02E+00 CR-5l 7.l3E+02 MN-54 3.l3E+0l FE-59 2.14E+Ol CO-58 3.74E+03 CO-60 2.2lE+03 ZR-95 l.63E+0l NB-95 4.89E+Ol AG-llOM 4.5lE+00 CS-l36 2.08E+00 Gamma 6.93E+03 XE-l33 3.66E+02 D&EG 3.66E+02 H-3 l.4lE+09 NI-63 l.36E+03 Beta l.4lE+09 Total l.41E+09 Page 74 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT)

Release ID  : 1 All Liquid Releases Period Start Date  : 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mins)  : 5.256E+05 Unit  : 2 Receptor  : 0 Liquid Receptor

=== PERMIT ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem)

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB APWtr 4.46E-05 l.88E-02 l.88E-02 l.88E-02 l.88E-02 l.89E-02 0.OOE+00 l.88E-02 AFWFSp l.28E-02 4.98E-02 4.85E-02 4.86E-02 4.85E-02 7.66E-02 0.OOE+00 4.96E-02 TPWtr 4.24E-05 l.33E-02 l.33E-02 l.33E-02 l.33E-02 l.33E-02 0.OOE+00 l.33E-02 TFWFSp l.33E-02 3.86E-02 3.73E-02 3.73E-02 3.73E-02 5.71E-02 0.OOE+00 3.84E-02 CPWtr l.29E-04 2.55E-02 2.54E-02 2.54E-02 2.54E-02 2.55E-02 0.OOE+00 2.SSE-02 CFWFSp l.75E-02 3.2lE-02 3.09E-02 3.09E-02 3.09E-02 3.79E-02 0.OOE+00 3.22E-02 IPWtr 9.84E-05 2.50E-02 2.SOE-02 2.50E-02 2.50E-02 2.SOE-02 0.OOE+00 2.50E-02 TOTALS ADULT 1.29E-02 6.86E-02 6.73E-02 6.74E-02 C.74E-02 9.55E-02 O.OOE+OO 6.85E-02 TEEN 1.34E-02 5.19E-02 5.05E-02 5.06E-02 5.05E-02 7.03E-02 O.OOE+OO 5.17E-02 CMILD 1.76E-02 5.76E-02 5.63E-02 5.64E-02 5.63E-02 6.34E-02 O.OOE+OO 5.76E-02 INFANT 9.84E-O5 2.50E-02 2.50E-02 2.EOE-02 2.50E-02 2.SOE-02 O.OOE+OO 2.SOE-02

AGE GROUP I PATHWAY IDE S CR I PT I ONS ========================================

Abbreviation Age Group Pathway APWtr ADULT Potable Water (PWtr)

AFWF$p ADULT Fresh Water Fish - Sport (FFSP)

TPWtr TEEN Potable Water (PWtr)

TFWF$p TEEN Fresh Water Fish - Sport (FFSP)

CPWtr CHILD Potable Water (PWtr)

CFWFSp CHILD Fresh Water Fish - Sport (FFSP)

IPWtr INFANT Potable Water (PWtr)

Page 75 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID  : 1 All Liquid Releases Period Start Date  : 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mins)  : 5.256E+05 Unit  : 2 Receptor  : 0 Liquid Receptor

=== PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT H-3 0.OOE+00 6.73E-02 6.73E-02 6.73E-02 6.73E-02 6.73E-02 0.OOE+00 6.73E-02 CR-5l 0.OOE+00 0.OOE+00 l.65E-07 6.09E-08 3.67E-07 6.95E-05 0.OOE+00 2.76E-07 MN-54 0.OOE+00 4.16E-05 0.OOE+00 1.24E-05 0.OOE+00 l.28E-04 0.OOE+00 7.95E-06 FE-59 6.79E-06 l.60E-05 0.OOE+00 0.OOE+00 4.46E-06 5.32E-05 0.OOE+00 6.l2E-06 CO-58 0.OOE+00 l.02E-04 0.OOE+00 0.OOE+00 0.OOE+00 2.07E-03 0.OOE+00 2.29E-04 CO-co 0.OOE+00 l.73E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.26E-03 0.OOE+00 3.82E-04 NI-63 l.29E-02 8.9lE-04 0.OOE+00 0.OOE+00 0.OOE+00 l.86E-04 0.OOE+00 4.3lE-04 ZR-95 l.31E-09 4.21E-lO 0.OOE+00 6.61E-lO 0.OOE+00 l.33E-06 0.OOE+00 2.85E-l0 NB-95 6.63E-06 3.69E-06 0.OOE+00 3.64E-06 0.OOE+00 2.24E-02 0.OOE+00 l.98E-06 AG-llOM l.39E-09 l.28E-09 0.OOE+00 2.53E-09 0.OOE+00 5.24E-07 0.OOE+00 7.63E-lO SB-124 2.33E-09 4.4lE-ll l.46E-08 0.OOE+00 l.82E-09 6.64E-08 0.OOE+00 9.25E-lO SB-l25 l.83E-07 2.04E-09 l.86E-l0 0.OOE+00 l.41E-07 2.OlE-06 0.OOE+00 4.35E-08 CS-l36 l.97E-05 7.77E-05 0.OOE+00 4.32E-05 5.92E-06 8.$2E-06 0.OOE+00 5.59E-05 TEEN H-3 0.OOE+00 5.05E-02 5.05E-02 5.OSE-02 5.05E-02 5.05E-02 0.OOE+00 5.OSE-02 CR-5l 0.OOE+00 0.OOE+00 l.58E-07 6.24E-08 4.07E-07 4.79E-05 0.OOE+00 2.8SE-07 MN-54 0.OOE+00 4.lOE-05 0.OOE+00 l.22E-05 0.OOE+00 8.40E-05 0.OOE+00 $.l2E-06 FE-59 7.OOE-06 l.63E-05 0.OOE+00 0.OOE+00 5.15E-06 3.86E-05 0.OOE+00 6.30E-06 CO-58 0.OOE+00 l.OlE-04 0.OOE+00 0.OOE+00 0.OOE+00 l.40E-03 0.OOE+00 2.33E-04 CO-co 0.OOE+00 l.73E-04 0.OOE+00 0.OOE÷00 0.OOE+00 2.26E-03 0.OOE+00 3.90E-04 NI-63 l.33E-02 9.4lE-04 0.OOE+00 0.OOE+00 0.OOE+00 l.SOE-04 0.OOE+00 4.52E-04 ZR-95 l.35E-09 4.24E-lO 0.OOE+00 6.24E-l0 0.OOE+00 9.80E-07 0.OOE+00 2.92E-lO NB-95 6.68E-06 3.70E-06 0.OOE+00 3.59E-06 0.OOE+00 l.58E-02 0.OOE+00 2.04E-06 AG-llOM l.34E-09 l.27E-09 0.OOE+00 2.42E-09 0.OOE+00 3.56E-07 0.OOE+00 7.72E-lO SB-l24 2.40E-09 4.42E-ll 5.45E-12 0.OOE÷00 2.lOE-09 4.$6E-08 0.OOE+00 9.39E-lO SB-l25 l.89E-07 2.06E-09 l.80E-l0 0.OOE+00 l.66E-07 1.47E-06 0.OOE+00 4.42E-08 CS-136 l.98E-05 7.78E-05 0.OOE+00 4.24E-05 6.68E-06 6.26E-06 0.OOE+00 S.23E-05 CHILD H-3 0.OOE+00 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 0.OOE+00 5.63E-02 CR-5l 0.OOE+00 0.OOE+00 l.69E-07 4.62E-08 3.08E-07 l.6lE-05 0.OOE+00 3.04E-07 MN-54 0.OOE+00 3.2lE-05 0.OOE+00 8.99E-06 0.OOE+00 2.69E-05 0.OOE+00 8.54E-06 FE-59 8.52E-06 l.38E-05 0.OOE+00 0.OOE+00 3.99E-06 l.43E-05 0.OOE+00 6.86E-06 CO-58 0.OOE+00 8.l6E-05 0.OOE+00 0.OOE+00 0.OOE+00 4.76E-04 0.OOE+00 2.SOE-04 CO-CO O.OOE÷OO 1.42E-04 O.OOE÷OO O.OOE+OO O.OOE+OO 7.$5E-04 O.OOE+OO 4.18E-04 NI-63 l.75E-02 9.39E-04 O.OOE+OO O.OOE+OO O.OOE+OO C.33E-05 O.OOE+OO 5.97E-04 ZR-95 1.82E-09 4.OlE-lO O.OOE+OO 5.74E-lO O.OOE+OO 4.18E-07 O.OOE+OO 3.57E-lO NB-95 7.88E-OC 3.07E-OC O.OOE+OO 2.2$E-06 0.OOE+OO 5.67E-03 O.OOE+OO 2.19E-06 Page 76 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID . . 1 All Liquid Releases Period Start Date .  : 01/01/2018 00:00 Period End Date . 01/01/2019 00:00 Period Duration (mins) : 5.256E+05

=== PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB AG-llOM l.76E-09 l.l9E-09 0.OOE+00 2.22E-09 0.OOE+00 l.42E-07 0.OOE+00 9.53E-lO SB-l24 3.92E-09 5.O8E-ll 8.67E-l2 0.OOE+00 2.l8E-09 2.45E-08 0.OOE+00 l.37E-09 SB-125 3.1OE-07 2.39E-09 2.87E-lO 0.OOE÷00 l.73E-07 7.4lE-07 0.OOE+00 6.49E-08 CS-136 2.33E-05 6.4lE-05 0.OOE+00 3.42E-05 5.09E-06 2.25E-06 0.OOE+00 4.l5E-05 INFANT H-3 0.OOE+00 2.50E-02 2.50E-02 2.50E-02 2.50E-02 2.50E-02 0.OOE+00 2.SOE-02 CR-51 0.OOE+00 0.OOE+00 7.50E-l0 l.64E-l0 l.46E-09 3.35E-02 0.OOE+00 l.l5E-09 MN-54 0.OOE+00 7.l2E-08 0.OOE+00 l.58E-08 0.OOE+00 2.6lE-08 0.OOE+00 l.61E-08 FE-59 7.55E-08 l.32E-07 0.OOE+00 0.OOE+00 3.90E-08 6.30E-08 0.OOE+00 5.l9E-08 CO-58 0.OOE+00 l.54E-06 0.OOE+00 0.OOE+00 0.OOE+00 3.83E-06 0.OOE+00 3.84E-06 CO-co 0.OOE+00 2.73E-06 0.OOE+00 0.OOE+00 0.OOE+00 6.50E-06 0.OOE+00 6.45E-06 NI-63 9.82E-05 6.07E-06 0.OOE+00 0.OOE+00 0.OOE+00 3.02E-07 0.OOE+00 3.4lE-06 ZR-95 3.83E-lO 9.34E-ll 0.OOE+00 l.O1E-l0 0.OOE+00 4.65E-08 0.OOE+00 6.62E-ll NB-95 2.34E-lO 9.66E-ll 0.OOE÷00 6.92E-ll 0.OOE+00 8.lSE-08 0.OOE+00 5.58E-ll AG-liOM 5.13E-l0 3.74E-lO 0.OOE+00 5.36E-lO 0.OOE+00 l.94E-08 0.OOE+00 2.48E-lO SB-124 2.08E-09 3.07E-ll 5.52E-l2 0.OOE+00 l.30E-09 6.42E-09 0.OOE+00 6.45E-l0 SB-125 l.46E-07 l.42E-09 l.83E-l0 0.OOE+00 8.47E-08 l.95E-07 0.OOE+00 3.O1E-08 CS-136 l.09E-08 3.20E-08 0.OOE+00 l.28E-08 2.6lE-09 4.87E-lO 0.OOE+00 l.20E-08 Page 77 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID . . 1 All Liquid Releases Period Start Date .  : 01/01/2018 00:00 Period End Date . . 01/01/2019 00:00 Period Duration (mins)  : 5.256E+05 Unit  : 2 Receptor  : 0 Liquid Receptor

= MAX I MUM DO S E FOR PER I OlD ======================== =========================

Limit Organ Age Dose Limit Limit Percent Type Type Group Organ (mrem) Period (mrem) of Limit Admin Any Organ ADULT GILLI 9.55E-02 31-day 1.50E-0l 6.37E+0l Quarter 3.75E+00 2.55E+00 Annual 7.50E+00 l.27E+00 Admin Tot Body ADULT TBODY 6 . 85E-02 31-day 4 SOE-02

. 1 52E+02 Quarter 1 13E+00

. 6 09E+00 Annual 2 25E+00

. 3 04E+00 T.Spec Any Organ ADULT GILLI 9 55E-02

. 3 1 day

- 2 OOE-01

. 4 77E+01 Quarter 5 OOE+00

. 1 91E+00 Annual 1 OOE+0l

. 9.55E-01 Critical Pathway  : 1 Fresh Water Fish - Sport (FFSP)

Major Contributors . 0.0 % or greater to total Nuclide Percentage SB- 125 2 . 1OE-03 SB- 124 6 . 95E-05 H-3 7 . 05E+01 CR-5l 7 . 28E-02 MN -54 1 . 34E-0l FE-59 5 . 57E-02 CO-58 2 . l6E+00 CO-EQ 3 .4lE+00 NI-63 1 . 95E-01 ZR-95 1 . 40E-03 NB -95 2 . 34E+01 AG- 11OM 5 .49E-04 CS- 136 9 . 24E-03 T.Spec Tot Body ADULT TBODY 6.85E-02 31-day 6 OOE-02

. 1 l4E+02 Quarter 1 50E+00

. 4 56E+00 Annual 3 OOE+00

. 2 28E+00 Critical Pathway . 1 Fresh Water Fish - Sport (FFSP)

Major Contributors  : 0.0 % or greater to total Nuclide Percentage Page 78 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) -

Release ID  : 1 All Liquid Releases Period Start Date 01/01/2018 00:00 Period End Date  : 01/01/2019 00:00 Period Duration (mins) : 5.256E÷05 Major Contributors  : 0.0 % or greater to total Nuclide Percentage SB-l25 6.35E-05 SB-l24 l.35E-06 1-1-3 9.84E+0l CR-51 4.04E-04 MN-54 l.l6E-02 FE-59 8.94E-03 CO-58 3.34E-0l CO-co 5.58E-Ol NI-63 6.30E-Ol ZR-95 4.l6E-07 NB-95 2.90E-03 AG-llOM l.llE-06 CS-l36 8.l7E-02 Page 79 of 79

CY-BY-17O-301 Exeton Generation Revision 14 February 2018 Page 1 of 188 Level 3 Information Use OFFSITE DOSE CALCULATION MANUAL FOR BYRON STATION UNITS I AND 2 ODCM TABLE OF CONTENTS PART I - RADIOLOGICAL EFFLUENTS I .0 DEFINITIONS pp. 6-9 3.1 1 RADIOLOGICAL EFFLUENTS AND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM p. 12 3.13 METEOROLOGICAL MONITORING PROGRAM p. 12 4.0 BASES pp. 13-20 5.0 ADMINISTRATIVE REQUIREMENTS pp. 21-25 PART 2-ODCM I .0 INTRODUCTION ODCM GENERAL INFORMATION

- pp. 26-42 1.1 StructureoftheODCM p.26 1.2 Regulations pp.27-32 I .2.1 Code of Federal Regulations pp. 27-30 I .2.2 Radiological Effluent Technical Standards p. 30 I .2.3 Offsite Dose Calculation Manual p. 31 1.2.4 Overlapping Requirements p. 31 I .2.5 Dose Receiver Methodology p. 32 I .3 Offsite Dose Calculation Parameters p. 36 1.4 References pp.36-42 2.0 INSTRUMENTATION AND SYSTEMS pp. 47-56 2.1 Liquid Effluent System Description p. 47 2.1 .1 Release Tanks p. 47 2.1.2 Turbine Building Fire and Oil Sump p. 47 2.1.3 Condensate Polisher Sump p. 47 2.2 Liquid Effluent Radiation Monitors pp. 47-48 2.2.1 Liquid Radwaste Effluent Monitor p. 47 2.2.2 Station Blowdown Monitor p. 48 2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service Water (SX) Outlet Line Monitor p. 48 2.2.4 Turbine Building Fire and Oil Sump Monitor p. 48 2.2.5 Condensate Polisher Sump Monitor p. 48 2.2.6 Component Cooling Water Monitors p. 48

CY-BY-i 70-301 Revision 14 I Page 2 of 188 2.3 Liquid Radiation Effluent Monitors Alarm and Trip Setpoints pp. 48-52 2.3.1 Station Blowdown Monitor p. 49 2.3.2 Liquid Radwaste Effluent Monitor pp 50-51 2.3.3 Other Liquid Effluent Monitors p. 52 2.3.4 Conversion Factors p. 52 2.3.5 Allocation of Effluent from Common Release Points p. 52 2.3.6 Solidification of Wastes/Process Control Program p. 52 2.4 Gaseous Effluent System Description pp. 52-53 2.4.1 Waste Gas Holdup System p. 52 2.4.2 Ventilation Exhaust Treatment System p. 53 2.5 Gaseous Effluent Radiation Monitors pp. 53-54 2.5.1 Auxiliary Building Vent Effluent Monitors p. 53 2.5.2 Containment Purge Effluent Monitors p. 53 2.5.3 Waste Gas Decay Tank Monitors p. 54 2.5.4 Gland Steam and Condenser Air Ejector Monitors p. 54 2.5.5 Radwaste Building Ventilation Monitor p. 54 2.6 Gaseous Effluent Monitor Alarm and Trip Setpoints pp. 54-56 2.6.1 Auxiliary Building Vent Effluent Monitors p. 54 2.6.2 Containment Purge Effluent Monitors p. 55 2.6.3 Waste Gas Decay Tank Effluent Monitors p. 55 2.6.4 Gaseous Effluent Release Limits pp. 55-56 2.6.5 Release Mixture p. 56 2.6.6 Conversion Factors p. 56 2.6.7 HVAC Dilution Flow Rates p. 56 2.6.8 Allocation of Effluents from Common Release Points . . . . p. 56 2.6.9 Dose Projections for Batch Releases p. 56 3.0 LIQUID EFFLUENTS pp. 65-73 3.1 Liquid Effluent Releases General Information pp. 65-66 3.2 Liquid Effluent Concentrations pp. 66-67 3.3 Liquid Effluent Dose Calculation Requirements p. 68 3.4 Dose Methodology pp. 69-72 3.5 Site Specific Dose Factors and Bioaccumulation Factors pp.

. 72-73 4.0 GASEOUS EFFLUENTS pp.91-113 4.1 Gaseous Effluents General Information pp. 91-92 4.2 Gaseous Effluents Dose and Dose Rate Calculation Requirements pp.92-113 4.2.1 Instantaneous Dose Rates pp. 92-96 4.2.2 Time Averaged Dose from Noble Gas pp. 96-1 00 4.2.3 Time Averaged Dose from Non-Noble Gas Radionuclides pp. 101-113 5.0 TOTAL DOSE pp. 163-168

CY-BY-1 70-301 Revision 14 I Page 3 of 188 5.1 Total Dose Calculation Requirements pp. 163-1 64 5.1 .1 Total Effective Dose Equivalent Limits, 10CFR2O and 40CFR190 p. 163 5.1.2 ISFSI p. 164 5.1 .3 Total Dose Calculation Methodology p. 164 5.2 Onsite Radwaste and Rad Material Storage Facilities pp.

. . . 164-165 5.2.1 Process Waste Storage Facilities p. 164 5.2.2 DAW Storage Facilities p. 165 5.2.3 Replaced Steam Generator Storage Facilities p. 165 5.2.4 ISFSI Facilities p. 165 5.3 Methodology p. 165 5.4 Total Dose p. 166 5.5 Compliance to Total Dose Limits pp. 166-1 68 5.5.1 Total Effective Dose Equivalent Limit IOCFR2O Compliance p. 166 5.5.2 Dose to a Member of the Public in the Unrestricted Area p. 166 5.5.3 Dose to a Member of the Public in the Restricted Area p. 167 5.5.4 Total Dose Due to the Uranium Fuel Cycle (4OCFRI9O) pp. 167-168 5.6 When Compliance Assessment is Required p. 168 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM p. 169 LIST OF TABLES PART I RADIOLOGICAL EFFLUENTS Table 1-a Frequency Notations p. 10 Table 1-b Compliance Matrix p. 11 PART 2-ODCM Table 1-1 Regulatory Dose Limit Matrix p. 33 Table 1-2 Dose Assessment Receivers p. 34 Table 1-3 Miscellaneous Dose Assessment Factors: Environmental Parameters p.43 Table 1-4 Stable Element Transfer Data pp 44-45 Table 2-1 Liquid Radioactive Effluent Monitors p. 57 Table 2-2 Gaseous Radioactive Effluent Monitors p. 58 Table 2-3 Assumed Composition of the Byron Station Noble Gas Effluent p.59 Table 2-4 Assumed Composition of the Byron Station Liquid Effluent p.60 Table 3-1 Site Specific Potable Water Dose Factors for Adult Age Group pp 74-75 Table 3-2 Site Specific Potable Water Dose Factors for Teen Age Group pp 76-77

CY-BY-1 70-301 Revision 14 I Page 4 of 188 Table 3-3 Site Specific Potable Water Dose Factors for Child Age Group pp. 78-79 Table 3-4 Site Specific Potable Water Dose Factors for Infant Age Group pp. 80-81 Table 3-5 Site Specific Fish Ingestion Dose Factors for Adult Age Group pp. 82-83 Table 3-6 Site Specific Fish Ingestion Dose Factors for Teen Age Group pp. 84-85 Table 3-7 Site Specific Fish Ingestion Dose Factors for Child Age Group pp. 86-87 Table 3-8 Bioaccumulation Factors (BF1) to be used in the Absence of Site-Specific Data pp. 88-89 Table 4-1 XIQ and DIQ Maxima at or Beyond the Unrestricted AreaBoundary p. 114 Table 4-2 XIQ and DIQ Maxima at or Beyond the Restricted Area Boundary p. 115 Table 4-3 Maximum Offsite Gamma-XIQ p. 116 Table 4-4 XIQ and DIQ at the Nearest Resident Locations within 5 miles p.117 Table 4-5 XIQ and DIQ at the Nearest Cow Milk Locations within 5 miles p. 118 Table 4-6 XIQ and DIQ at the Nearest Cow Meat Locations within 5 miles p.119 Table 4-7 Ground Plane Dose Factors pp. 120-121 Table 4-8 External Dose Factors for Standing on Contaminated Ground pp. 122-1 24 Table 4-9 Adult Inhalation Dose Factors pp. 125-1 26 Table 4-10 Teen Inhalation Dose Factors pp. 127-1 28 Table 4-1 1 Child Inhalation Dose Factors pp. 129-130 Table 4-12 Infant Inhalation Dose Factors pp. 131-1 32 Table 4-1 3 Adult Vegetation Dose Factors pp. 133-134 Table 4-14 Teen Vegetation Dose Factors pp. 135-1 36 Table 4-15 Child Vegetation Dose Factors pp. 137-1 38 Table 4-1 6 Adult Grass-Cow-Milk Dose Factors pp. 139-140 Table 4-17 Teen Grass-Cow-Milk Dose Factors pp. 141 -142 Table 4-18 Child Grass-Cow-Milk Dose Factors pp. 143-144 Table 4-19 Infant Grass-Cow-Milk Dose Factors pp. 145-1 46 Table 4-20 Adult Grass-Goat-Milk Dose Factors pp. 147-148 Table 4-21 Teen Grass-Goat-Milk Dose Factors pp. 149-1 50 Table 4-22 Child Grass-Goat-Milk Dose Factors pp. 151-1 52 Table 4-23 Infant Grass-Goat-Milk Dose Factors pp. 153-1 54 Table 4-24 Adult Grass-Cow-Meat Dose Factors pp. 155-156 Table 4-25 Teen Grass-Cow-Meat Dose Factors pp. 157-158 Table 4-26 Child Grass-Cow-Meat Dose Factors pp. 159-1 60 Table 4-27 Byron Station Characteristics p. 161 Table 4-28 Dose Factors for Noble Gases p. 162

CY-BY-1 70-301 Revision 14 I Page 5 of 188 Table 6-1 Radiological Environmental Monitoring Program pp. 170-178 Table 62 Latitude/Longitude Positions of REMP samples pp. 184-188 LIST OF FIGURES PART I RADIOLOGICAL EFFLUENTS-None PART 2-ODCM Figure 1-1 Radiation Exposure Pathways to Humans p. 35 Figure 1-2 Removed See Figure 6-1 Figure 1-3 Restricted Area Boundary p. 46 Figure 2-1 Simplified HVAC & Gaseous Effluent Flow Diagram pp. 61-62 Figure 2-2 Simplified Liquid Radwaste Processing Diagram p. 63 Figure 2-3 Liquid Release Flow Path p. 64 Figure 6-1 Onsite Air Sampling Locations and Unrestricted Area Boundary p. 179 Figure 6-2 Offsite Air Sampling Locations p. 180 Figure 6-3a Inner Ring & Special Interest Dosimeter Locations p. 181 Figure 6-3b Outer Ring Dosimeter Locations p. 182 Figure 6-4 Ingestion & Waterborne Exposure Pathway Sample Locations p. 182

CY-BY-1 70-301 Revision 14 I Page 6 of 188 Part I - RADIOLOGICAL EFFLUENTS 1 . DEFINITIONS I .1 . ACTIONS shall be that part of a Requirement that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

I .2. CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known inputs. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions. Calibration of instrument channels with Resistance Temperature Detector (RTD) or thermocouple sensors may consist of an in place qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated.

I .3. CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

I .4. CHANNEL OPERATIONAL TEST (COT) shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.

I .5. DOSE EQUIVALENT I-I 31 shall be that concentration of I-I 31 (microcurie/gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes I-I 31 I-I 32, I-I 33, I-I 34, and I-I 35 actually present. The determination ofDOSE EQUIVALENT 1-131 shall be performed using the committed Effective Dose Equivalent (CEDE) dose conversion factors from Table 2.1 of EPA Federal Guidance Report No. 11, 1988, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion.

CY-BY-1 70-301 Revision 14 I Page 7 of 188 I .6. FREQUENCY Table I -a provides the definitions of various frequencies for which surveillances, sampling, etc., are performed unless defined otherwise.

The 25% variance shall not be applied to Operability Action statements. The bases to Surveillance Requirement 3.0.2 provide clarifications to this requirement.

1 .7. IMMEDIATELY When immediately is used as a completion time the Required Action should be pursued without delay and in a controlled manner.

1 .8. MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors and persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

1 .9. MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolttensioning specified in TRM Table TI .1-I with fuel in the reactor vessel.

1.10. OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individuals assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person.

Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.

I .1 1 . A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety functions(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

I .12. PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61 and 71 State regulations, burial ground requirements and other requirements governing the disposal of solid radioactive waste.

CY-BY-1 70-301 Revision 14 Page 8 of 188 1.13. PURGEIPURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

I .14. RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3645MWt.

1.15. RADIOLOGICAL EFFLUENTS (RE) are in accordance with Byron Technical Requirements Manual (TRM) and the Code of Federal Regulations.

1.16. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) are in accordance with Byron Technical Requirements Manual (TRM) and the Code of Federal Regulations.

1.17. SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

1.18. SOLIDIFICATION shall bethe conversion ofwetwastes into a form that meets shipping and burial ground requirements.

I .19. SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

1.20. THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

1 .21 . TLCO-TECHNICAL LIMITING CONDITION FOR OPERATION Limiting Condition for Operation as listed in the TRM.

I .22. TECHNICAL REQUIREMENTS MANUAL (TRM) Chapter 3.1 1 contains the Radiological Effluents (RE). Chapter 3.12 contains the Radiological Environmental Monitoring Program (REMP).

1 .23. UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

CY-BY-1 70-301 Revision 14 1 Page 9 of 188 1 .24. VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

I .25. WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

I .26. Definitions Peculiar to Estimating Dose to Members of the Public using the OFFSITE DOSE CALCULATION MANUAL (ODCM) Computer Program.

A. ACTUAL ACTUAL refers to using known release data to project the dose to members of the public for the previous time period. This data is stored in the database and used to demonstrate compliance with the reporting requirements of the ODCM.

B. PROJECTED PROJECTED refers to using known release data from the previous time period or estimated release data to forecast a future dose to members of the public. This data is not incorporated into the database.

CYBY-1 70-301 Revision 14 I Page 10 of 188 Table 1-a FREQUENCY NOTATIONS*

Notation Frequency S Shiftly

- At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D - Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> w Weekly

- At least once per 7 days B- Biweekly At least once every 14 days M - Monthly At least once per 31 days Q Quarterly

- At least once per 92 days SA Semiannually

- At least once per 184 days A Annually

- At least once per 366 days R - Refuel Cycle At least once per I 8 months S/u Startup

- Prior to each reactor startup NA Not applicable P - Prior Prior to each radioactive release

• Each frequency requirement shall be performed within the specified time interval with the maximum allowable extension not to exceed 25% of the frequency interval. The 25% variance shall not be applied to Operability Action statements. The bases to TSR 3.O.b provide clarifications to this requirement. These frequency notations do not apply to the Radiological Environmental Monitoring Program as described in TRM 3.12.

CY-BY-1 70-301 Revision 14 I Pagell of 188 Table 1-b COMPLIANCE MATRIX

. . ODCM Technical Regulation Dose Component Limit . TRM . .

Equation Specification 10 CFR 50 1. Gamma air dose and beta air dose due to 4-4 3.11 .g 5.5.4.h Appendix I airborne radioactivity in effluent plume. 4-5

a. Total body and skin dose due to airborne 4-6 N/A N/A radioactivity in effluent plume are 4-7 reported only if certain gamma and beta air dose criteria are exceeded.

2. Dose for all organs and all four age groups 4-8 3.1 1 .h 5.5.4.i due to iodines and particulates in effluent plume. All pathways are considered.

3. Dose for all organs and all four age groups 3-3 3.11 .d 5.5.4.d due_to_radioactivity_in_liquid_effluents.

10 CFR 20 1. Total Dose, totaling all external dose 5-2 N/A 5.5.4.c components (direct, ground and plume shine) and internal dose (all pathways, both airborne_and_liquid-borne).

40 CFR 190 1. Total body dose due to direct dose, 5-1 3.11.k 5.5.4.j (now by ground and plume shine from all sources at a reference, station.

also part of 10 CFR 20) 2. Organ doses to an adult due to all 3-3 pathways. 4-8 Technical 1. lnstantaneoustotal body, skin and organ 4-1 3.11.f 5.5.4.g Specifications dose rates to a child due to radioactivity in 4-2 airborne effluents. For the organ dose, only 4-3 inhalation is considered.

2. Instantaneous concentration limits for liquid effluents. 3-1 3.11.c 5.5.4.b Technical I Radioactive Effluent Release Report

. N/A N/A 5.6.3 Specifications IOCFR5O 1. Implement Environmental Monitoring Appendixl Program. N/A 3.12.a N/A Section lV.B.2 IOCFR5O Appendixl 1.LandUseCensus N/A 3.12.b N/A Section IV.B.3 IOCFR5O Appendix I 1. Interlaboratory Comparison Program N/A 3.12.c N/A Section lV.B.2 IOCFR5O Appendix I Section lV.B.2 1. Annual Radiological Environmental Operating N/A N/A 5.6.2 and Technical Report Specifications

CY-BY-1 70-301 Revision 14 I Page 12 of 188 NOTE: 2.0 through 3.10 are not used.

3.11 . Radiological Effluents and Radiological Environmental Monitoring Program NOTE: SEE TRM Chapter 3.1 1 for Radiological Effluents (RE) and TRM Chapter 3.12 for Radiological Environmental Monitoring Program (REMP).

3.13. METEOROLOGICAL MONITORING PROGRAM 3.13.1. METEOROLOGICAL MONITORING I . Meteorological parameters are measured in the vicinity of each nuclear power station in order to provide data for calculating radiation doses due to airborne effluent radioactivity. Some nuclear power stations Technical Specifications state applicable requirements (typically under the subheading, Meteorological Instrumentation in the instru mentation section). Reg ulatory gu idance is g iven in Regulatory Guide I .23 (Reference 5). Wind speed, wind direction and the temperature gradient are measured using instruments at two or more elevations on a meteorological tower at each Exelon Nuclear station. The elevations are chosen to provide meteorological data representative of the elevations of the airborne releases from the station. The Annual Radiological Environmental Operating Report includes a summary of meteorological data collected over the reporting year.

3.13.2. METEOROLOGICAL CONTRACTOR I . The meteorological contractor operates and maintains the meteorological tower instrumentation at each nuclear power station. The contractor collects and analyzes the data and issues periodic reports. The contractor prepares the meteorological data summary required for the Annual Radiological Environmental Operating Report (AREOR).

4. BASES 4.1. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (TRM 3.1 1 .a)

I . The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding 10 times the EFFLUENT CONCENTRATION values specified in Appendix B, Table 2, Column 2 to 10 CFR 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 ofAppendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that if not

CY-BY-1 70-301 Revision 14 I Page 13 of 188 controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.

4.2. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (TRM 3.11.b)

I . The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 ofAppendix A to 10 CFR Part 50.

4.3. CONCENTRATION LIMITS FOR EFFLUENTS (TRM 3.11.c) 1 . This Control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the EFFLUENT CONCENTRATION values specified in Appendix B, Table 2, Column 2 to 10 CFR 20. The Control provides operational flexibility for releasing liquid effluents in concentrations to follow the Section ll.A and ll.C design objectives ofAppendix I to 10 CFR Part 50. This limitation provides reasonable assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section ll.A design objectives ofAppendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the restrictions authorized by 10 CFR Part 20.1301(e). The concentration limit forthe dissolved or entrained noble gases is based upon the assumption that Xe-133 is the controlling radionuclide and its EFFLUENT CONCENTRATION in air (submersion) was converted to an equivalent concentration in water. This control does not affect the requirement to comply with the annual limitations of 10 CFR Part 20.1301 (a).

2. This Control applies to the release of radioactive materials in liquid effluents from all units at the site.

3. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in Currie, L.A.,

Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements, NUREG/CR-4007 (September 1 984), and in the HASL Procedures Manual, HASL-300 (revised annually).

4.4. DOSE FROM LIQUID EFFLUENTS (TRM 3.11.d)

I . This Control is provided to implement the requirements of Sections ll.A, III.A and IV.A ofAppendix I, 10 CFR Part 50. The Control statement implements the guides set forth in Section II.A ofAppendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth

CY-BY-1 70-301 Revision 14 Page 14 of 188 in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept as low as is reasonably achievable. Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part I 41 The dose calculation methodology and parameters in the ODCM implement the requirements in Section llI.A ofAppendix I that conformance with the guides ofAppendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide I .109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the purpose of Evaluating Compliance with I 0 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.113, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977.

2. This Control applies to the release of liquid effluents from each reactor at the site.

For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

CY-BY-J 70-301 Revision 14 I Pagel5ofl88 4.5. LIQUID RADWASTE TREATMENT SYSTEM (TRM 3.1 1 .e)

I . The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable. This Control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 ofAppendix A to 10 CFR Part 50 and the design objective given in Section ll.D ofAppendix I to 10 CFR part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section ll.A ofAppendix I, 10 CFR Part 50, for liquid effluents.

2. This Control applies to the release of liquid effluents from each reactor at the site.

For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

4.6. DOSE RATE FOR GASEOUS EFFLUENT (TRM 3.1 1 .f)

I . This Control provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either at or beyond the SITE BOUNDARY in excess ofthe design objectives ofAppendix I to 10 CFR Part 50. This Control is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and ll.C design objectives ofAppendix I to 10 CFR Part 50. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy ofthat MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for the reduced atmospheric dispersion of gaseous effluents relative to that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1 500 mrem/year. This Control does not affect the requirement to comply with the annual limitations of 1 0 CFR 20.1 301 (a).

2. This Control applies to the release of gaseous effluents from all units at the site.

CY-BY-1 70-301 Revision 14 I Page 16 of 188

3. The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion ofthe LLD and other detection limits can be found in Currie, L.A.,

Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiolog ical Effluent and Environmental Measurements, N UREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revised annually).

4.7. DOSE NOBLE GASES (TRM 3.1 1 .g) 1 . This Control is provided to implement the requirements of Sections ll.B, lll.A and IV.A ofAppendix I, 10 CFR Part 50. The Control statements implement the guides set forth in Section ll.B ofAppendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The Surveillance Requirements implement the requirements in Section lll.A of Appendix I that conformance with the guides ofAppendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

2. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation ofAnnual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision I October 1 977 and Regulatory Guide I .1 1 1 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision I July 1977.

The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

3. This Control applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

CY-BY-1 70-301 Revision 14 I Page 17 of 188 4.8. DOSE IODINE-131, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM (TRM 3.11.h)

I . This Control is provided to implement the requirements of Sections ll.C, lILA and IV.A of Appendix I, I 0 CFR Part 50. The Controls are the guides set forth in Section II.C ofAppendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable. The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section lILA ofAppendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

2. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide I .11 1 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision I July 1 977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for Iodine-I 31 Tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: I) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

3. This Control applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.

CY-BY-1 70-301 Revision 14 Page 18 of 188 4.9. GASEOUS RADWASTE TREATMENT SYSTEM (TRM 3.1 1 .i)

I . The OPERABILITY of the Gaseous Radwaste Treatment System ensures that the system will be available for use whenever gaseous effluents require treatment prior to release of the environment. The requirement that the appropriate portions ofthese systems be used, when specified, provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable. This Control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to I 0 CFR Part 50, and the design objectives given in Section ll.D ofAppendix I to 10 CFR Part 50.

2. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections ILB and ll.C ofAppendix I, 10 CFR Part 50, for gaseous effluents.

3. This Control applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.

4.10. TOTAL DOSE (TRM 3.11.k)

I . This Control is provided to meet the dose limitations of 40 CFR Part I 90 that have been incorporated into 10 CFR Part 20.1301(d). The Control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

2. Forsites containing up to 4 reactors, it is highly unlikelythatthe resultantdose to a MEMBER OF THE PUBLIC will exceed the dose limits of4O CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and ifdirect radiation doses from the reactor units and outside storage tanks, etc., are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part I 90, submittal of the Special Report within 30 days with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part I 90 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.1 1 and 10 CFR Part 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR Part I 90 until NRC staff action is completed.

CY-BY-1 70-301 Revision 14 I Page 19 of 188

3. Demonstration of compliance with the limits of 40 CFR Part I 90 or with the design objectives ofAppendix I to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301.

4.11. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (TRM 3.12)

The Radiological Environmental Monitoring Program required bythis Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.

2. This monitoring program implementsSection IV.B.2 ofAppendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

Isotopes identified in REMP are compared to those identified in the applicable Annual Effluent Report. Program changes may be initiated based on these operational experiences.

3. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD5). The LLDs required by Table T3.12.a-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an posteriori (after the fact) limit for a particular measurement.

4. Detailed discussion of the LLD and other detection limits can be found in Currie, L.A., Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements, N UREG/CR-4007 (September 1 984), and in the HASL Procedures Manual, HASL-300 (revised annually).

CY-BY-1 70-301 Revision 14 Page 20 of 188 4.12. LAND USE CENSUS (TRM 3.12.b)

I . This Control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 ofAppendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden ofthis size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% ofthe garden was used for growing broad Ieafvegetation (i.e.,

similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m2.

4.13. INTERLABORATORY COMPARISON PROGRAM (TRM 3.12.c)

I . The requirement for participation in an approved Interlaboratory Comparison Program is provided 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 in order to demonstrate that the results are reasonably valid for the purposes of Section lV.B.2 of Appendix I to 10 CFR Part 50.

CY-BY-1 70-301 Revision 14 1 Page2l of 188

5. ADMINISTRATIVE REQUIREMENTS 5.1. Annual Radiological Environmental Operating Report*

1 . Routine Annual Radiological Environmental Operating Report covering the operation of the Unit(s) during the previous calendar year shall be submitted prior to May I 5 of each year.

2. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

3. The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in Part 2 Section 6 of the ODCM, as well as summarized and tabulated results ofthese analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1 November 1979.

4. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

5. The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by TLCO 3.12.a, a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule ofTRM Table T3.12.a-1; discussion ofenvironmental sample measurements that exceed the reporting levels ofTRM Table T3.12.a-2 but are not the result of plant effluents, discussion of all analyses in which the LLD required by TRM Table T3.12.a-3 was not achievable; result ofthe Land Use Census required by TRM TLCO 3.12.b; and the results ofthe licensee participation in an lnterlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by TRM TLCO 3.12.c.

CY-BY-1 70-301 Revision 14 I Page 22 of 188

6. The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable 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 ofjoint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

7. The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year.

This report shall also include an assessment of the radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other near-by uranium fuel cycle sources including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM, and in compliance with IOCFR2O and 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

• A single submittal may be made for a multiple unit station.

CY-BY-1 70-301 Revision 14 I Page 23 of 188 5.2. Annual Radioactive Effluent Release Report**

1 . Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous calendar year of operation shall be submitted prior to May I of the following year.

2. The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1 .21 Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1 June 1 974, with data summarized on a quarterly basis following the format of Appendix B thereof.

3. For solid wastes, the format for Table 3 in Appendix B of the report shall be supplemented with three additional categories: class of solid wastes (as defined by I 0 CFR Part 61 ), type of container (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde).

The Annual Radioactive Effluent Release Reports 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.

4. The Annual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PCP as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Part I Section 5.4.

5. The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in TRM TLCO 3.1 I .a or TLCO 3.1 1 .b, respectively; and description of the events leading to liquid holduptanks orgas storagetanks exceeding the limits ofTS 5.5.12.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

CY-BY-J 70-301 Revision 14 I Page 24 of 188 5.3. ODCM 5.3.1 . The ODCM shall be submitted to the Commission following proper approval through station processes.

5.3.2. Licensee-in itiated changes to the ODCM:

I . Shall be documented and records of reviews performed shall be retained as required by UFSAR Chapter 17. This documentation shall contain:

A. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes(s);

and B. A determination that the change will maintain the level of radioactive effluent control required by JO CFR Part 20, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after review and acceptance by the Independent Technical Review and PORC and the approval of the Plant Manager on the date specified by the Independent Technical Review and PORC.

3. Shall be submitted to the Commission in the form of the complete, legible copy of the entire ODCM, or updated pages ifthe Commission retains a controlled copy.

If an entire copy of the QDCM is submitted, it shall be submitted as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. 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 (eg.

month/year) the change was implemented.

CY-BY-1 70-301 Revision 14 1 Page 25 of 188 5.4. Major Changes to Liquid and Gaseous Radwaste Treatment Systems***

5.4.1 . Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):

1 . Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Independent Technical Review and PORC. The discussion of each change shall contain:

A. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; B. Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information; C. A detailed description of the equipment, components, and processes involved and the interlaces with other plant systems.

D. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto; E. An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto; F. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made; G. An estimate of the exposure to plant operating personnel as a result of the change; and H. Documentation of the fact that the change was reviewed and found acceptable by the Independent Technical Review and PORC.

2. Shall become effective upon review and acceptance by the Independent Technical Review and PORC.

• • • Licensees may choose to submit the information called for in this standard as part of the annual FSAR update.

CY-BY-1 70-301 Revision 14 I Page 26 of 188 Part 2 - ODCM I . INTRODUCTION ODCM GENERAL INFORMATION I . The Offsite Dose Calculation Manual (ODCM) presents a discussion of the following:

A. The basic concepts applied in calculating offsite doses from plant effluents.

B. The regulations and requirements forthe ODCM and related prog rams.

C. The methodology and parameters for the offsite dose calculations to assess impact on the environment and compliance with regulations.

2. The methodology detailed in this manual is intended for the calculation of radiation doses during routine (i.e., non-accident) conditions. The calculations are normally performed using a computer program. Manual calculations may be performed in lieu of the computer program.

3. The dose effects of airborne radioactivity releases predominately depend on meteorological conditions (wind speed, wind direction, and atmospheric stability).

For airborne effluents, the dose calculations prescribed in this manual are based on historical average atmospheric conditions. This methodology is appropriate for estimating annual average dose effects and is stipulated in the Bases Section ofthe Radiological Effluents (RE).

1.1. Structure ofthe ODCM 1.1.1. Part I ofthe ODCM is considered to be the Radiological Effluents (RE), and contains the former Radiological Effluent Technical Specifications that have been removed from the Technical Specifications. Part 1 is organized as follows:

1. Definitions

2. Radiological Effluents and Radiological Environmental Monitoring Program

3. Meteorological Monitoring Program

4. Bases

5. Administrative Requirements

CY-BY-J 70-301 Revision 14 I Page 27 of 188 I .1 .2. Part 2 of the ODCM is considered to be the Qffsite Dose Calculation Manual (ODCM), and contains methods, equations, assumptions, and parameters for calculation of radiation doses from plant effluents. Part 2 is organized as follows:

1. Introduction

2. Instrumentation and Systems

3. Liquid Effluents

4. Gaseous Effluents

5. Total Dose

6. Radiological Environmental Monitoring Program I .2. Regulations I . This section serves to illustrate the regulations and requirements that define and are applicable to the ODCM. Any information provided in the ODCM concerning specific regulations are not a substitute for the regulations as found in the Code of Federal Regulations (CFR) or Technical Specifications.

I .2.1 . Code of Federal Regulations 1 . Various sections of the Code of Federal Regulations (CFR) require nuclear power stations to be designed and operated in a manner that limits the radiation exposure to members ofthe public. These sections specify limits on offsite radiation doses and on effluent radioactivity concentrations and they also require releases of radioactivity to be As Low As Reasonably Achievable. These requirements are contained in IOCFR2O, IOCFR5O and 4OCFRI9O. In addition, 4OCFRI4I imposes limits on the concentration of radioactivity in drinking water provided by the operators of public water systems.

A. IOCFR2O, Standards for Protection Against Radiation I . This revision of the ODCM addresses the requirements of IOCFR2O. The IOCFR2O dose limits are summarized in Table 1-1.

CY-BY-1 70-301 Revision 14 I Page 28 of 188 B. Design Criteria (Appendix A of IOCFR5O)

I . Section 50.36 of I OCFR5O requires that an application for an operating license include proposed Technical Specifications. Final Technical Specifications for each station are developed through negotiation between the applicant and the NRC. The Technical Specifications are then issued as a part of the operating license, and the licensee is required to operate the facility in accordance with them.

2. Section 50.34 of IOCFR5O states that an application for a license must state the principal design criteria of the facility. Minimum requirements are contained in Appendix A of IOCFR5O.

C. ALARA Provisions (Appendix I of IOCFR5O)

I . Sections 50.34a and 50.36a of I OCFR5O require that the nuclear plant design and the station RE have provisions to keep levels of radioactive materials in effluents to unrestricted areas As Low As Reasonably Achievable (ALARA). Although IOCFR5O does not impose specific limits on releases, Appendix I of I OCFR5O does provide numerical design objectives and suggested limiting conditions for operation. According to Section I of Appendix I of I OCFR5O, design objectives and limiting conditions for operation, conforming to the guidelines of Appendix I shall be deemed a conclusive showing of compliance with the As Low As Reasonably Achievable requirements of I OCFR5O.34a and 50.36a.

An applicant must use calculations to demonstrate conformance with the design objective dose limits of Appendix I. The calculations are to be based on models and data such that the actual radiation exposure of an individual is unlikely to be substantially underestimated (see IOCFR5O Appendix I, Section lIl.A.1).

The guidelines in Appendix I call for an investigation, corrective action and a report to the NRC whenever the calculated dose due to the radioactivity released in a calendar quarter exceeds one-half of an annual design objective. The guidelines also require a surveillance program to monitor releases, monitor the environment and identify changes in land use.

CY-BY-1 70-301 Revision 14 I Page 29 of 188 D. 4OCFRI9O, Environmental Radiation Protection Standards for Nuclear Power Operations

1. Under an agreement between the NRC and the EPA, the NRC stipulated to its licensees in Generic Letter 79-041 that Compliance with Radiological Effluent Technical Specifications (RETS), NUREG-0472 (Rev.2) for PWRs, implements the LWR provisions to meet 4OCFRI9O.

(See References 49 and 103.)

2. The regulations of4OCFRI9O limit radiation doses received by members of the public as a result of operations that are part of the uranium fuel cycle.

Operations must be conducted in such a manner as to provide reasonable assurance that the annual dose equivalent to any member of the public due to radiation and to planned discharges of radioactive materials does not exceed the following limits:

. 25 mrem to the total body

. 75 mrem to the thyroid

. 25 mrem to any other organ

3. An important difference between the design objectives of IOCFR5O and the limits of4OCFRI9O is that IOCFR5O addresses only doses due to radioactive effluents.

4OCFRI9O limits doses due to effluents and to radiation sources maintained on site. See Section 1 .2.4 for further discussion of the differences between the requirements of IOCFR5O Appendix I and 4OCFRI9O.

E. 40CFR141 National Primary Drinking Water Regulations The following radioactivity limits for community water systems were established in the July, 1 976 Edition of 4OCFRI4I:

. Combined Ra-226 and Ra-228: < 5 pCi/L.

. Gross alpha (particle activity including Ra-226 but excluding radon and uranium): 15 pCi/L.

. The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 mrem/yr.

CY-BY-1 70-301 Revision 14 Page 30 of 188

2. The regulations specify procedures for determining the values of annual average radionuclide concentration that produce an annual dose equivalent of 4 mrem.

Radiochemical analysis methods are also specified. The responsibility for monitoring radioactivity in a community water system falls on the supplier of the water. The Byron Station has requirements related to 4OCFRI4I in the RECS.

F. JOCFR72.104 states that annual dose to any real individual located beyond the controlled area must not exceed the following:

. 25 mrem to the total body

. 75 mrem to the thyroid

. 25 mrem to any other critical organ I . as a result of planned discharges of radioactive material to the environment direct radiation from lSFSl operation, and other radiation from uranium fuel cycle operation (4OCFRI 90). These requirements are consistent with the requirements of 4OCFRI9O.

I .2.2. Radiological Effluent Technical Standards I . The Radiological Effluent Technical Standards (RETS) were formerly a subset of the Technical Specifications. They implement provisions of the Code of Federal Regulations aimed at limiting offsite radiation dose. The NRC published Standard RETS for PWRs (Reference 2) as guidance to assist in the development of technical specifications. These documents have undergone frequent minor revisions to reflect changes in plant design and evolving regulatory concerns. The RETS have been removed from the Technical Specifications and placed in the TRM as the Radiological Effluents (RE) (see Reference 90). The RE are similar but not identical to the guidance of the Standard Radiological Effluent Technical Specifications.

CY-BY-1 70-301 Revision 14 Page3l of 188 1 .2.3. Offsite Dose Calculation Manual 1 . The NRC in Generic Letter 89-01 defines the ODCM as follows (not verbatim)

(see Reference 90):

A. The Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs and (2) descriptions of the Information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

2. Additional requirements for the content of the ODCM are contained throughout the text of the RECS.

I .2.4. Overlapping Requirements In IOCFR2O, IOCFR5O and 4OCFRI9O, there are overlapping requirements regarding offsite radiation dose and dose commitment to the total body. In I OCFR2O. 1 301 the total effective dose equivalent (TEDE) to a member of the public is limited to 100 mrem percalendaryear. In addition, Appendix Ito IOCFR5O establishes design objectives on annual total body dose or dose commitment of 3 mrem per reactor for liquid effluents and 5 mrem per reactor for gaseous effluents (see IOCFR5O Appendix I, Sections ll.A and II.B.2(a)). Finally, 4OCFRI 90 limits annual total body dose or dose commitment to a member of the public to 25 mrem due to all uranium fuel cycle operations.

2. While these dose limits/design objectives appear to overlap, they are different and each is addressed separately by the RE. Calculations are made and reports are generated to demonstrate compliance to all regulations. Refer to Table I -1 and Table 1-2 for additional information regarding instantaneous effluent limits, design objectives and regulatory compliance.

CY-BY-1 70-301 Revision 14 I Page 32 of 188 I .2.5. Dose Receiver Methodology I . Table I -2 lists the location of the dose recipient and occupancy factors, if applicable. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. The dose calculation methodology is consistent with the methodology of Regulatory Guide 1.109 (Reference 6) and NUREG 0133 (Reference 14). Dose is therefore calculated to a maximum individual. The maximum individual is characterized as maximum with regard to food consumption, occupancy and other usage ofthe area in the vicinity ofthe plant site. Such a maximum individual represents reasonable deviation from the average for the population in general. In all physiological and metabolic respects, the maximum individual is assumed to have those characteristics that represent averages for their corresponding age group. Thus, the dose calculated is very conservative compared to the average (or typical) dose recipient who does not go out of the way to maximize radioactivity uptakes and exposure.

CY-BY-1 70-301 Revision 14 I Page 33 of 188 Table I - I Regulatory Dose Limit Matrix IRM REGULATION DOSE TYPE DOSE LIMIT(s)

Section Airborne Releases:

(quarterly) (annual)

IOCFR5O App. i Gamma Dose to Air due to Noble Gas 5 mrad 10 mrad 3.1 1.g Radionuclides (per reactor unit)

Beta Dose to Air Due to Noble Gas 10 mrad 20 mrad 3.1 1 .g Radionuclides (per reactor unit)

Organ Dose Due to Specified Non-Noble 7.5 mrem 15 mrem 3.11.h Gas Radionuclides (per reactor unit)

Total Body and Total Body 2.5 mrem 5 mrem N/A Skin Dose (if air dose is exceeded) Skin 7.5 mrem 15 mrem N/A Technical Specifications Total Body Dose Rate Due to Noble Gas 500 mrem/yr 3.1 1 .f Radionuclides (instantaneous limit, per site)

Skin Dose Rate Due to Noble Gas 3,000 mrem/yr 3.11 .f Radionuclides (instantaneous limit, per site)

Organ Dose Rate Due to Specified Non- I 500 mrem/yr 3.1 1 .f Noble Gas Radionuclides (instantaneous limit, per site)

Lig uid Releases:

(quarterly) (annual)

I OCFR5O App. i Whole (Total) Body Dose I .5 mrem 3 mrem 3. 1 1 .d (per reactor unit)

Organ Dose (per reactor unit) 5 mrem 10 mrem 3.1 1 .d Technical Specifications The concentration of radioactivity in liquid Ten times the values effluents released to unrestricted areas listed in IOCFR2O 3.1 1 .c Appendix B; Table 2, Column 2, and note 5 below for Noble Gases Total Doses 1: ODCM PART 2 10 CFR 20.1301 (a)(1) Total Effective Dose Equivalent4 100 mrem/yr 5.5 IOCFR2O.1301 (d) Total Body Dose 25 mrem/yr 5.5 And 4OCFRI9O Thyroid Dose 75 mrem/yr 5.5 Other Organ Dose 25 mrem/yr 5.5 2:

Other Limits 4OCFRI4I Total Body Dose Due to Drinking Water 4 mrem/yr 3.4 From Public Water Systems Organ Dose Due to Drinking Water From 4 mrem/yr 3.4 Public Water Systems I

These doses are calculated considering all sources of radiation and radioactivity in effluents.

2 These limits are not directly applicable to nuclear power stations. They are applicable to the owners or operators of public water systems. However, the Byron RECS requires assessment of compliance with these limits.

3 Notethat IOCFR5O provides design objectives, not limits.

4 Compliance with I OCFR2O.1 301 (a)(1) is demonstrated by compliance with 4OCFRI 90. Note that it may be necessary to address dose from on-site activity by members of the public as well.

5 Kr-85m, Kr-85, Kr-87, Kr-88, Ar-41, Xe-131m, Xe-133m, Xe-133, Xe-135m and Xe-135 allowable concentration is 2E-4 pCi/mI computed from Equation 17 of ICRP Publication 2 adjusted for infinite cloud submersion in water, and R = 0.01 rem/wk, Pw I .0 g/cm3, and PiP = I .0.

CY-BY-1 70-301 Revision 14 I Page 34 of 188 Tablel -2 Dose Assessment Receivers Location; Occupancy if Dose Component or Pathway Different than I 00%

Instantaneous dose rates from Unrestricted area boundary location that airborne radioactivity results in the maximum dose rate Instantaneous concentration limits in Point where liquid effluents enter the liquid effluents unrestricted area Annual average concentration limits for Point where liquid effluents enter the liquid effluents unrestricted area Direct dose from contained sources Receiver spends part of this time in the controlled area and the remainder at his residence or fishing nearby; occupancy factor is considered and is site-specific.

Direct dose from airborne plume Receiver is at the unrestricted area boundary location that results in the maximum dose.

Dose due to radioiodines, tritium and Receiver is at the location in the particulates with half-lives greater than unrestricted area where the combination of 8 days for inhalation, ingestion of existing pathways and receptor age groups vegetation, milk and meat, and ground indicates the highest potential exposures.

plane exposure pathways.

Ingestion dose from drinking water The drinking water pathway is considered as an additive dose component in this assessment only if the public water supply serves the community immediately adjacent to the plant.

Ingestion dose from eating fish The receiver eats fish from the receiving body of water Total Organ Doses Summation of ingestion/inhalation doses Total Dose Summation of above data (Note it may also be necessary to address dose from on-site activity by members of the public.)

Figure 1 -1 illustrates some of the potential radiation exposure pathways to humans due to routine operation of a nuclear power station.

CY-BY-1 70-301 Revision 14 I Page 35 of 188 Figurel -1 Radiation Exposure Pathways to Humans

CY-BY-1 70-301 Revision 14 I Page 36 of 188 1 .3. Offsite Dose Calculation Parameters I . This section contains offsite dose calculation parameter factors, or values not specific only to one of the gas, liquid, or total dose chapters. Additional parameters are provided in the Sections 2, 4 and 5 of the ODCM.

2. IOCFR5O Dose Commitment Factors A. With the exception of H-3, the dose commitment factors for IOCFR5O related calculations are exactly those provided in Regulatory Guide 1.109 (Reference 6). The following table lists the parameters and the corresponding data tables in the RG 1.109:

PATHWAY ADULT TEENAGER CHILD INFANT Inhalation RG 1.109: RG 1.109: RG 1.109: RG 1.109:

Table E-7 Table E-8 Table E-9 Table E-10 Ingestion RG 1.109: RG 1.109: RG 1.109: RG 1.109:

TableE-Il TableE-12 TabIeE-13 Table E-14 B. These tables are contained in Regulatory Guide 1.109 (Reference 6). Each table (E-7 through E-14) provides dose factors for seven organs for each of 73 radionuclides, and Table E-5 lists Miscellaneous Dose Assessment Factors -

Consumption Parameters. For radionuclides not found in these tables, dose factors will be derived from ICRP 2 (Reference 50) or NUREG-0172 (Reference 51). The values for H-3 are taken from NUREG-4013 (Reference 107).

1.4. References

2. U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, NUREG-0472, Rev. 3, Draft, January 1983 (frequently revised).

4. U.S. Nuclear Regulatory Commission, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Regulatory Guide I .21 Revision I June 1974.

5. U.S. Nuclear Regulatory Commission, Meteorological Monitoring Programs for Nuclear Power Plants, Regulatory Guide I .23, Rev. I March 2007.

CY-BY-1 70-301 Revision 14 Page 37 of 188

6. U.S. Nuclear Regulatory Commission, Calculation ofAnnual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part5OAppendix I, Regulatory Guide 1.109, Rev. 1, October 1977.

7. U.S. Nuclear Regulatory Commission, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Regulatory Guide I .111 Rev. 1, July 1977.

8. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors, Regulatory Guide 1.112, Rev. O-R, April 1976; reissued May 1977.

9. U.S. Nuclear Regulatory Commission, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, Regulatory Guide 1 .1 13, Rev. I April 1977.

10. U.S. Nuclear Regulatory Commission, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants, Regulatory Guide 4.1 Rev. I April 1975.

11 . U.S. Nuclear Regulatory Commission, Preparation of Environmental Reports for Nuclear Power Stations, Regulatory Guide 4.2, Rev. 2, July 1976.

12. U.S. Nuclear Regulatory Commission, Environmental Technical Specifications for Nuclear Power Plants, Regulatory Guide 4.8, Rev. 1 December 1 975. (See also the related Radiological Assessment Branch Technical Position, Rev. I, November 1979.)

13. U.S. Nuclear Regulatory Commission, Quality Assurance for Radiological Monitoring Programs (Normal Operations)--Effluent Streams and the Environment, Regulatory Guide 4.15, Rev. 1, February 1979.

14. U.S. Nuclear Regulatory Commission, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, edited by J. S. Boegli et al.

NUREG-0133, October 1978.

I 5. U.S. Nuclear Regulatory Commission, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, J. F. Sagendorfet al. NUREG/CR-2919, PNL-4380, September 1982.

16. U.S. Nuclear Regulatory Commission, Radiological Assessment, edited by J. E.

Till and H. R. Meyer, NUREG/CR-3332, ORNL-5968, September 1983.

17. U.S. Nuclear Regulatory Commission, Standard Review Plan, NUREG-0800, July 1981.

18. U.S. Atomic Energy Commission, Meteorology and Atomic Energy 1968, edited by D. H. Slade, TID-21940, July 1968.

19. U.S. Atomic Energy Commission, Plume Rise, G. A. Briggs, TID-25075, 1969.

CY-BY-J 70-301 Revision 14 I Page 38 of 188

20. U.S. Atomic Energy Commission, The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000, WASH 1209, January 1973.

21 . U.S Atomic Energy Commission, HASL Procedures Manual, Health and Safety Laboratory, HASL-300 (revised annually).

22. U.S. Department of Energy, Models and Parameters for Environmental Radiological Assessments, edited by C. W. Miller, DOE/TIC-I 1468, 1984.

23. U.S. Department of Energy, Atmospheric Science and Power Production, edited byD. Randerson, DOEITIC-27601, 1984.

24. U.S. Environmental Protection Agency, Workbook ofAtmospheric Dispersion Estimates, D. B. Turner, Office of Air Programs Publication No. AP-26, 1970.

25. U.S. Environmental Protection Agency, 4OCFRI9O Environmental Radiation Protection Requirements for Normal Operations ofActivities in the Uranium Fuel Cycle, Final Environmental Statement, EPA 520/4-76-016, November 1, 1976.

26. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle, EPA-520/9-73-003-C, November 1973.

27. American Society of Mechanical Engineers, Recommended Guide for the Prediction ofthe Dispersion ofAirborne Effluents, 1973.

28. Eisenbud, M., Environmental Radioactivity, 3rd Edition, (Academic Press, Orlando, FL, 1987).

29. Glasstone, S., and Jordan, W. H., Nuclear Power and Its Environmental Effects (American Nuclear Society, LaGrange Park, IL, I 980).

30. International Atomic Energy Agency, Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases, Safety Series, No. 57, 1982.

31 . National Council on Radiation Protection and Measurements, Radiological Assessment: Predicting the Transport, Bioaccumulation, and Uptake by Man of Radionuclides Released to the Environment, NCRP Report No. 76, March 15, 1984.

32. American National Standards Institute, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities, ANSI NI 3.1-1 969, February 1 9, 1969.

33. Institute of Electrical and Electronics Engineers, Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N13.I0-1974, September 19, 1974.

CY-BY-1 70-301 Revision 14 I Page 39 of 188

34. American National Standards Institute, Testing and Procedural Specifications for Thermoluminescence Dosimetry (Environmental Applications), ANSI N545-1 975, August20, 1975.

35. American Nuclear Insurers, Effluent Monitoring, ANI/MAELU Engineering Inspection Criteria for Nuclear Liability Insurance, Section 5.1 Rev. 2, October 24, 1986.

36. American Nuclear Insurers, Environmental Monitoring, ANI/MAELU Engineering Inspection Criteria for Nuclear Liability Insurance, Section 5.2, Rev. 1 March 23, 1987.

37. American Nuclear Insurers, Environmental Monitoring Programs, ANI/MAELU Information Bulletin 86-1, June 9, 1986.

38. Cember, H., Introduction to Health Physics, 2nd Edition (Pergamon Press, Elmsford, NY 1983).

41 . U.S. Nuclear Regulatory Commission, Branch Technical Position, Radiological Assessment Branch, Revision 1 November 1979. (This is a branch position on Regulatory Guide 4.8.)

43. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code), NUREG-0017, April 1976.

49. U.S. Nuclear Regulatory Commission, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190),

NUREG-0543, February 1980.

50. International Commission on Radiological Protection, Report of Committee Two on Permissible Dose for Internal Radiation, Recommendations of the International Commission on Radiological Protection, ICRP Publication 2, 1959.

51 . U.S. Nuclear Regulatory Commission, Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, Battelle Pacific Northwest Laboratories, NUREG-0172, 1977.

52. W. C. Ng, Transfer Coefficients for Prediction ofthe Dose to Man via the Forage-Cow-Milk Pathway from Radionuclides Released to the Biosphere, UCRL-51 939.

53. E. C. Eimutis and M. G. Konicek, Derivations of Continuous Functions for the Lateral and Vertical Atmospheric Dispersion Coefficients, Atmospheric Environment 6, 859 (1972).

CY-BY-1 70-301 Revision 14 Page 40 of 188

54. D. C. Kocher, Editor, Nuclear Decay Data for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, ORNL/NUREGITM-102, August 1977.

55. R. L. Heath, Gamma-Ray Spectrum Catalog, Aerojet Nuclear Co., ANCR-1000-2, third or subsequent edition.

56. 5. E. Thompson, Concentration Factors of Chemical Elements in Edible Aquatic Organisms, UCRL-50564, Rev. I I 972.

57. U.S. Nuclear Regulatory Commission, Instruction Concerning Risks from Occupational Radiation Exposure, Regulatory Guide 8.29, July 1981.

58. Dresden Nuclear Power Station, Radioactive Waste and Environmental Monitoring, Annual Report 1987, March 1988.

59. Reserved reference number

70. D. C. Kocher, Radioactivity Decay Data Tables, DOE/TIC-I I 026, 1 981.

71 . J. C. Courtney, A Handbook of Radiation Shielding Data, ANSISD-76114, July 1976.

75. Sargent & Lundy, METWRSUM, S&L Program Number 09.5.187-1.0.

76. Sargent & Lundy, Comments on CECo ODCM and List of S&L Calculations, Internal Office Memorandum, P. N. Derezotes to G. R. Davidson, November 23, 1988.

77. Sargent & Lundy, AZAP, A Computer Program to Calculate Annual Average Offsite Doses from Routine Releases of Radionuclides in Gaseous Effluents and Postaccident XIQ Values, S&L Program Number 09.8.054-1.7.

78. National Oceanic and Atmospheric Administration, A Program for Evaluating Atmospheric Dispersion from a Nuclear Power Station, J. F. Sagendorf, NOAA Technical Memorandum ERL ARL-42, Air Resources Laboratory, Idaho Falls, Idaho, May 1974.

79. G. P. Lahti, R. S. Hubner, and J. C. Golden, Assessment of Gamma-Ray Exposures Due to Finite Plumes, Health Physics 41 31 9 (1981).

80. National Council of Radiation Protection and Measurements, Ionizing Radiation Exposure ofthe Population ofthe United States, NCRP Report No. 93, September 1 I 987.

82. W. R. Van Pelt (Environmental Analysts, Inc.), Letter to J. Golden (ComEd) dated January3, 1972.

84. U.S. Nuclear Regulatory Commission, Draft Generic Environmental Impact Statementon Uranium Milling, NUREG-0511, April 1979.

CY-BY-1 70-301 Revision 14 I Page4l of 188

85. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle, Part I Fuel Supply, EPA-520/9-73-003-B, October 1973.

86. U.S. Nuclear Regulatory Commission, Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors, NUREG-0002, August 1976.

87. U.S. Nuclear Regulatory Commission, Demographic Statistics Pertaining to Nuclear Power Reactor Sites, NUREG-0348, Draft, December 1977.

88. Nuclear News 31, Number 10, Page 69 (August 1988).

89. General Electric Company, Irradiated Fuel Storage at Morris Operation, Operating Experience Report, January 1972 through December 1982, K. J. Eger, NEDO-20969B.

90. U.S. Nuclear Regulatory Commission, Generic Letter 89-01 Guidance For The Implementation of Programmatic Controls For RETS In The Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program, January 1989.

92. NRC Safety Evaluation Report (SER)/Idaho National Engineering Laboratory Technical Evaluation Report (TER) of the Commonwealth Edison Offsite Dose Calculation Manual (ODCM), Revision O.A, December 2, 1 991.

95. U.S. Nuclear Regulatory Commission, Standards for Protection Against Radiation (IOCFR2O).

96. U.S. Nuclear Regulatory Commission, Licensing of Production and Utilization Facilities (IOCFR5O).

97. Federal Register, Vol. 57, No. 169, Monday, August 31 1992, page 39358.

98. Miller, Charles W., Models and Parameters for Environmental Radiological Assessments, U.S. Dept. of Energy, DE8102754, 1984, pages 32, 33, 48, and 49.

99. Kocher, D. C., Dose-Rate Conversion Factors For External Exposure To Photons and Electrons, Health Physics Vol. 45, No. 3 (September), pp. 665-686, 1983.

100. U.S. Department of Health, Education and Welfare Public Health Service, Radiological Health Handbook, January 1970.

CY-BY-1 70-301 Revision 14 Page 42 of 188 I 01 . ODCM Bases and Reference Document, rev.O, November, 1998.

I 03. U.S. Nuclear Regulatory Commission, Generic Letter 79-041 September 17, 1979.

1 04. Federal Register, Vol. 56, No. 98, Tuesday, May 21 I 991 page 23374, column 3.

105. U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, NUREG-1 301 April 1991.

107. U.S. Nuclear Regulatory Commission, LADTAP II Technical Reference and Users Guide, NUREG-4013, April 1986.

108. Holtec Report No. Hl-2146048, Dose Versus Distance from a HI-STORM 1005 Version B Containing the MPC-32 for Byron/Braidwood, Holtec International, 8/14/08.

I 09. Exelon Letter RS-1 I -099, Request For License Amendment Regarding Measurement Uncertainly Recapture (MUR) Power Uprate, June 23, 201 1.

I I 0. Engineering Change (EC) # 405541 Partial Abandonment of the Containment Charcoal Filter Units (Byron Unit 2)

CY-BY-J 70-301 Revision 14 I Page 43 of 188 Tablel -3 Miscellaneous Dose Assessment Factors: Environmental Parameters Parameter Value Comment Equation Basisa fg 0.76 411,412 A fL 1.0 4-11,4-12 A In 1.0 4-13,4-15 A f 1.0 4-13,4-15 A tb 262,800 3Oyears 4-9 C h rs tf 48hrs CowMilkPathway 4-13 A ti 480 hrs Cow Meat Pathway 4-1 5 A th l44Ohrs 6Odaysforproduce 4-11 A th 2l6Ohrs 9Odaysforproduce 4-13,4-15 A tL 24 hrs I day for leafy vegetables 4-1 1 A QF 50 4-13, 4-14, 4-15, B Kg/day 4-16 r 1.0 Forlodines 4-11,4-13,4-15 A r 0.2 For Particulates 4-1 1 4-1 3, 4-1 5

, A Yp 0.7 4-13,4-15 A Kg/rn2 Ys 2.0 4-13,4-15 A Kg/rn2 Yv 2.0 4-11 A Kg/rn2 0.0021 4-11,4-13,4-15 A

-__________ hr-I H 8 gm/rn3 Absolute Atmospheric Humidity 4-12, 4-14, 4-16 D p 1 O Fractional Equilibrium Ratio 4-12a, 4-14a, 4-16a E aBasis key:

A: Reference 6, Table E-15.

B: Reference 6, Table E-3.

C: The parameter tb 5 taken as the midpoint of plant operating life (based upon an assumed 60 year plant operating lifetime).

D: Reference 14, Section 5.3.1.3.

E: Reference 6, Appendix C

CY-BY-1 70-301 Revision 14 I Page 44 of 188 Tablel -4 Stable Element Transfer Data Ff FM(Cow)

Element Meat (U/kg) Milk (U/L) Reference H 1.2E-02 1.OE-02 6 Be I .5E-03 3.2E-03 Footnote I C 3.IE-02 I.2E-02 6 F 2.9E-03 I .4E-02 Footnote 2 Na 3.OE-02 4.OE-02 6 Mg I .5E-03 3.2E-03 Footnote I Al I .5E-02 I .3E-03 Footnote 3 P 4.6E-02 2.5E-02 6 Cl 2.9E-03 I .4E-02 Footnote 2 Ar NA NA NA K I.8E-02 72E-03 16 Ca I .6E-03 I 1 E-02 I6 Sc 2.4E-03 7.5E-06 Footnote 4 Ti 34E-02 5.OE-06 Footnote 5 V 28E-OI I 3E-03 Footnote 6 Cr 2.4E-03 2.2E-03 6 Mn 8.OE-04 2.5E-04 6 Fe 4.OE-02 I .2E-03 6 Co I .3E-02 I OE-03 6 Ni 5.3E-02 6.7E-03 6 Cu 8OE-03 I .4E-02 6 Zn 3.OE-02 3.9E-02 6 Ga I .5E-02 I .3E-03 Footnote 3 Ge 9.IE-04 9.9E-05 Footnote 7 As I .7E-02 5.OE-04 Footnote 8 Se 7.7E-02 I .OE-03 Footnote 9 Br 29E-03 2.2E-02 F1 Footnote 2;FM from Ref. 16 Kr NA NA NA Rb 3.IE-02 3.OE-02 6 Sr 6.OE-04 8.OE-04 6 Y 4.6E-03 I .OE-05 6 Zr 3.4E-02 5.OE-06 6 Nb 2.8E-OI 2.5E-03 6 Mo 8.OE-03 7.5E-03 6 Tc 4.OE-OI 2.5E-02 6 Ru 4.OE-O1 1.OE-06 6 Rh I.5E-03 I.OE-02 6 Pd 5.3E-02 6.7E-03 Footnote 10 Cd 3.OE-02 2.OE-02 Footnote II In I .5E-02 I .3E-03 Footnote 3 Sn 9.IE-04 9.9E-05 Footnote 7 Sb 5.OE-03 2.OE-05 98 Ag I .7E-02 5.OE-02 6 Te 7.7E-02 I .OE-03 6 I 2.9E-03 6.OE-03 6 Xe NA NA NA Cs 4.OE-03 I .2E-02 6 Ba 3.2E-03 4.OE-04 6 La 2.OE-04 5.OE-06 6 Ce I .2E-03 I .OE-04 6 Pr 4.7E-03 5.OE-06 6 Nd 3.3E-03 5.OE-06 6

CY-BY-1 70-301 Revision 14 I Page 45 of 188 Table 1-4 (Contd)

Stable Element Transfer Data Ff FM (Cow)

Element Meat (d/kg) Milk (d/L) Reference Pm 2.9E-04 2.OE-05 16 Sm 2.9E-04 2.OE-05 16 Eu 2.9E-04 2.OE-05 16 Gd 2.9E-04 2.OE-05 16 Dy 2.9E-04 2.OE-05 16 Er 2.9E-04 2.OE-05 16 Tm 2.9E-04 2.OE-05 16 Yb 2.9E-04 2.OE-05 16 Lu 2.9E-04 2OE-05 16 Hf 3.4E-02 5.OE-06 Footnote 5 Ta 28E-O1 I .3E-03 FM Ref.16; Ff -Footnote 6 w I .3E-03 5.OE-04 6 Re 1.OE-O1 1.3E-03 FM Ref.16; Ff-Footnote 12 Os 2.2E-O1 6.OE-04 Footnote 13 Ir 7.3E-03 5.5E-03 Footnote 14 Pt 5.3E-02 6.7E-03 Footnote I 0 Au I .3E-02 3.2E-02 Footnote 15 Hg 3.OE-02 9.ZE-06 FM - Ref.16; Ff -Footnote II TI I .5E-02 I .3E-03 FM Ref. I 6; Ff -Footnote 3 Pb 9.IE-04 9.9E-05 98 Bi I .7E-02 5.OE-04 98 Ra 5.5E-04 5.9E-04 98 Th I .6E-06 5.OE-06 98 U I .6E-06 I .2E-04 98 Np 2.OE-04 5.OE-06 6 Am I .6E-06 2.OE-05 98 Notes:

I NA = It is assumed that noble gases are not deposited on the ground.

2. Elements listed are those considered for IOCFR2O assessment and compliance.

Footnotes:

There are numerous Ff and FM values that were not found in published literature. In these cases, the periodic table was used in conjunction with published values. The periodic table was used based on a general assumption that elements have similar characteristics when in the same column of the periodic table. The values of elements in the same column of the periodic table, excluding atomic numbers 58-71 and 90-103, were averaged then assigned to elements missing values located in the same column of the periodic table. This method was used for all columns where there were missing values except column 3A, where there was no data, hence, the average of column 2B and 4A were used.

I . Values obtained by averaging Reference 6 values of Ca, Sr, Ba and Ra.

2. Ff value obtained by assigning the Reference 6 value for I. FM value obtained by averaging I (Ref. 6) and Br (Ref.16).

3. Ff values obtained by averaging Zn (Ref.6) and Pb (Ref. 98); there were no values for elements in the same column; an average is taken between values of columns 2B and 4A on the periodic table. FM values obtained by using the value for TI from Reference 16.

4. Values obtained by averaging Reference 6 values ofY and La.

5. Values obtained by assigning the Reference 6 value for Zr.

6. Ff values obtained from Ref. 6 value for Nb. FM values obtained by averaging values for Nb (Ref.6) and Ta (Ref. 16).

7. Values obtained from the Reference 6 values for Pb.

8. Values obtained from the Reference 6 values for Bi.

9. Values obtained from the Reference 6 values for Te.

10. Values obtained from the Reference 6 values for Ni.

I1 . Ff values obtained from Ref. 6 values for Zn. FM values obtained by averaging the Reference 6 values for Zn and Hg.

12. Values obtained by averaging Reference 6 values for Mn, Tc, Nd and Reference 98 value for U.

13. Values obtained by averaging Reference 6 values from Fe and Ru.

14. Values obtained by averaging Reference 6 values from Co and Rh.

15. Values obtained by averaging Reference 6 values from Cu and Ag.

CY-BY-1 70-301 Revision 14 I Page 46 of 188 (n Process R:dyjas.te Storage Building (2 DAW Building *(1arehouse #3)

(3) Future DAW & 48 Pack Locations (4) ISFSt Pad Restricted Area Boundiy OFFS[TE DOSE CALCULATiON SYRON STATION

• ae :J *ET F1GURE

jC 51RiCTE AREA

CY-BY-1 70-301 Revision 14 I Page 47 of 188

2. INSTRUMENTATION AND SYSTEMS 2.1 . Liquid Effluents System Description 1 . A simplified liquid release flowpath diagram is provided in Figure 2-3. A simplified liquid radwaste processing diagram is provided in Figure 2-2.

2. The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralizer for the purpose of reducing the total radioactivity prior to release to the environment. The system is described in Chapter 1 1 of the Byron Updated Final Safety Analysis Report.

2.1.1. Release Tanks I . There are two radwaste release tanks (OWXOIT and OWX26T 30,000-gallon capacity each) that receive liquid waste before discharge to the Rock River.

2.1 .2. Turbine Building Fire and Oil Sump 1 . The turbine building fire and oil sump receives water from selected turbine building sumps, the tendon tunnel sumps, and the diesel fuel oil storage sumps, all ofwhich are normally non-radioactive but potentially contaminated. The effluent from this sump is monitored, and if radioactive contamination exceeds a predetermined level pump operation is automatically terminated. The water may then be sent to the liquid radwaste treatment system.

2.1 .3. Condensate Polisher Sump I . The condensate polisher sump receives wastewater from the condensate polisher system, which is normally non-radioactive but potentially contaminated.

The effluent from this sump is monitored and if radioactive contamination exceeds a predetermined level sump discharge is terminated and major condensate polisher inputs to the sump are automatically isolated. The water may then be sent to the liquid radwaste treatment system.

2.2. Liquid Effluent Radiation Monitors Pertinent information on the Liquid Radioactive Effluent Monitors and associated control devices are shown in Table 2-1 ; additional information is provided in the Byron UFSAR Chapter 1 1.

2.2.1. Liquid Radwaste Effluent Monitor 1 . Monitor ORE-PROOI is used to monitor all releases from the release tanks. On high alarm, the monitor automatically initiates closure of valves OWX-353 and OWX-869 to terminate the release.

CY-BYl 70-301 Revision 14 I Page 48 of 188 2.2.2. Station Blowdown Monitor I . Monitor ORE-PROJO continuously monitors the circulating water blowdown. No control device is initiated by this channel.

2.2.3. Reactor Containment Fan Cooler (RCFC) and Essential Service Water (SX)

Outlet Line Monitors.

I . Monitors I RE-PROO2, 2RE-PROO2, I RE-PROO3, and 2RE-PROO3 continuously monitor the RCFC and SX outlet lines. No control device is initiated by these channels.

2.2.4. Turbine Building Fire and Oil Sump Monitor I . Monitor ORE-PROO5 continuously monitors the fire and oil sump discharge. On high alarm the monitor automatically initiates an interlock to trip the discharge pumps, close valve 00D030, and terminate the release.

2.2.5. Condensate Polisher Sump Monitor I . Monitor ORE-PRO4I continuously monitors the condensate polisher sump discharge. On high alarm, the monitor automatically initiates an interlock to trip the discharge pumps and terminate the release.

2.2.6. Component Cooling Water Monitors I . Monitors ORE-PROO9 (common), I RE-PROO9 (Unit I ), and 2RE-PROO9 (Unit 2) continuously monitor the component cooling water heat exchanger outlets. On high alarm ORE-PROO9 initiates closure of both component cooling water surge tank (CCWST) vents, I RE-PROO9 initiates closure of the Unit I CCWST vent, and 2RE-PROO9 initiates closure of the Unit 2 CCWST vent.

2.3. Liquid Radiation Effluent Monitors Alarm and Trip Setpoints I . Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of TRM Section 3.1 1 .a are not exceeded in the unrestricted area.

2. Setpoint calculations normally consist of identified release mixtures, dilution factors, conversion factors (detector sensitivity), maximum release flow rates, and conservatism factors.

CY-BY-1 70-301 Revision 14 I Page 49 of I 88 2.3.1. Station Blowdown Monitor During release, the monitor setpoint is found by solving equation 2-1 P CCW + (7. 50 x CT) x (Frmax/(FCW Frmax)) (2-1)

P Release Setpoint [pCi/mi]

1.50 Factor to account for minor fluctuations in count rate CCW Concentration of activity in the circulating water biowdown at the time of discharge (Background reading) [pCi/mi]

cT Analyzed activity in the release tank (excluding tritium)[pCi/miJ FCW Circulating Water Blowdown Rate [gpm]

Fmax Maximum Release Tank Discharge Flow Rate [gpm]

The flow rate from the radwaste discharge tank I . The release mixture used for the setpoint determination is the radionuclide mix identified in the release tank grab sample isotopic analysis.

CY-BY.1 70-301 Revision 14 1 Page 50 of 188 2.3.2. Liquid Radwaste Effluent Monitor I . During release, the setpoint is established at I .5 times the analyzed tank activity plus the background reading. However, per procedure, the maximum discharge flow rate is limited to a value that will result in less than 50% of 1 O*ECL at the discharge point. (See Section 1) 2.3.2.1 Radwaste Tank Discharge Flow Rate 1 . Prior to each batch release, a grab sample is obtained.

2. The results of the analysis of the waste sample determine the discharge rate of each batch as follows:

Fcnax O.5( f / >(C1 / 10 ECL )) (2-2)

The summation is over radionuclides i.

F Maximum Permitted Discharge Flow Rate [gpm]

The maximum permitted flow rate from the radwaste discharge tank based on radiological limits (not chemistry limits which may be more restrictive)

Circulating Water Blowdown Rate [gpm]

Cl Concentration of Radionuclide i in the Release Tank [pCi/mi]

The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank.

ECL Effluent Concentration Limit [pCi/mi]

The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to IOCFR2O.1001 20.2402.

10 Multiplier 2.3.2.2 Release Mixture I . The release mixture used for the setpoint determination is the radionuciide mix identified in the release tank grab sample isotopic analysis.

CY-BY-1 70-301 Revision 14 I Page5l of 188 2.3.2.3 Liquid Dilution Flow Rates I . Dilution flow rates are obtained from the main control board in the control room.

lfthis information is unavailable, releases may continue for up to 30 days provided the dilution flow rates are estimated every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the release, in accordance with TRM Table T 31 1 a-1.

2.3.2.4 Projected Concentrations for Releases I . After determining Pmax from Equation 2-2, RE compliance is verified using Equations 2-3 and 2-4.

c;1 = cr [Fax / (Fnax + F)] (2-3)

t c / 10

• ECL } 1 (2-4)

The summation is over radionuclides i.

c1 Concentration of Radionuclide i in the Unrestricted Area[jiCi/mL]

The calculated concentration of radionuclide i in the unrestricted area as determined by Equation 2-3.

Concentration of Radionuclide i in the Release Tank [iCi/mL]

The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank.

ECL Effluent Concentration Limit [pCi/mu The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to IOCFR2O.1001 20.2402.

10 Multiplier Fnax Maximum Release Tank Discharge Flow Rate [gpm]

f Circulating Water Blowdown Rate [gpmJ

CY-BY-1 70-301 Revision 14 Page 52 of 188 2.3.3. Other Liquid Effluent Monitors I . For all other liquid effluent monitors, including ORE-PROOI and ORE-PROI 0 when not batch releasing, setpoints are determined such that the concentration limits do not exceed I 0 times the ECL value given in Appendix B, Table 2, Column 2 to IOCFR2O.1001 20.2402 in the unrestricted area. Release mixtures are based on a representative isotopic mixture of the waste stream or inputs to the waste stream, or defaulted to the mix listed in Table 2-4.

2.3.4. Conversion Factors 1 . The readouts for the liquid effluent monitors are in pCi/mi. The cpm to pCi/mi conversion is determined for each monitor.

2.3.5. Allocation of Effluents from Common Release Points 1 . Radioactive liquid effluents released from either release tank (OWXOIT or OWX26T) are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units.

Consequently, allocation is made evenly between units.

2.3.6. Solidification ofWaste/Process Control Program I . The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured.

2.4. Gaseous Effluents System Description I . A simplified HVAC and gaseous effluent flow diagram is provided in Figure 2-1.

The principal release points for potentially radioactive airborne effluents are the two auxiliary building vent stacks (designated Stack I and Stack 2 in Figure 2-1).

In the classification scheme of Section 4.1 .4, each is classified as a vent release point. Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.

2.4.1. Waste Gas Holdup System I . The waste gas holdup system is designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system off-gases from the reactor coolant system and providing for delay or holdup to reduce the total radioactivity by radioactive decay prior to release to the environment.

CY-BY-1 70-301 Revision 14 Page 53 of I 88 2.4.2. Ventilation Exhaust Treatment System I . Ventilation exhaust treatment systems are designed and installed to reduce gaseous radiolodine or radioactive material in particulate form in gaseous effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 2-1.

2. Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.

2.5. Gaseous Effluent Radiation Monitors I . Pertinent information on the Gaseous Effluent Radiation Monitors and associated control devices are shown in Table 2-2, additional information is provided in Byron UFSAR Chapter 11.

2.5.1. Auxiliary Building Vent Effluent Monitors I . Monitors I RE-PR028 (Unit 1) and 2RE-PR028 (Unit 2) continuously monitor the final effluent from the auxiliary building vent stacks.

2. Both vent stack monitors feature automatic noble gas monitoring, isokinetic sampling, grab sampling, and sampling for iodine, particulate, and tritium.

3. These monitors perform no automatic isolation or control functions.

2.5.2. Containment Purge Effluent Monitors I . Monitors I RE-PROOI (Unit I ) and 2RE-PROOI (Unit 2) continuously monitor the effluent from the Unit I and Unit 2 containments, respectively. When airborne radioactivity in the containment purge effluent stream exceeds a specified level station personnel will follow established procedures to terminate the release by manually activating the containment purge valves. Additionally, the auxiliary building vent effluent monitors provide an independent, redundant means of monitoring the containment purge effluent.

2. These monitors perform no automatic isolation or control functions.

3. Monitors IRE-AROII, 2RE-AROII, IRE-AROI2 and 2RE-AROI2 continuously monitor the containment atmosphere for radioactive gas and particulates. On high alarm during a containment purge, these monitors will automatically terminate the purge.

CY-BY-1 70-301 Revision 14 1 Page 54 of 188 2.5.3. Waste Gas Decay Tank Monitors I . Monitors ORE-PROO2A and ORE-PROO2B continuously monitor the noble gas activity released from the gas decay tanks.

2. On high alarm, the monitors automatically initiate closure of the valve OGWI 04 thus terminating the release.

2.5.4. Gland Steam and Condenser Air Ejector Monitors I . Monitors I RE-PR027 and 2RE-PR027 continuously monitor the condenser air ejector gas from Units I and 2, respectively. This monitor performs no automatic isolation or control functions.

2.5.5. Radwaste Building Ventilation Monitor I . Monitor ORE-PR026 continuously monitors radioactivity in the radwaste building ventilation system. On high alarm, ORE-PR026 initiates isolation of the radwaste building ventilation system.

2.5.5.1 Miscellaneous Ventilation Monitors I . Monitor ORE-PROO3 continuously monitors radioactivity in the ventilation exhaust from the laboratory fume hoods. This monitor performs no automatic isolation or control functions.

2.6. Gaseous Effluent Monitor Alarm and Trip Setpoints 2.6.1 . Auxiliary Building Vent Effluent Monitors I . The setpoints for the low range noble gas channel are conservatively established at 2.5% of the maximum permissible release rate for the high alarm and 0.25% of the maximum release rate for the alert alarm.

2. The setpoints for the high range noble gas channel are conservatively established at 50% of the maximum permissible release rate for the high alarm and 5% of the maximum release rate for the alert alarm.

3. The setpoint methodology must ensure simultaneous releases do not exceed the off-site dose rate limits set forth in TRM3.1 I Setpoints can be adjusted based upon operational requirements with the restriction that the sum of the percentages between the Unit I and Unit 2 noble gas channels does not exceed 90% ofthe maximum permissible release rate.

CY-BY-1 70-301 Revision 14 Page 55 of 188 2.6.2. Containment Purge Effluent Monitors 1 . Under normal conditions when the containment atmosphere monitor gas detector is operational, the setpoints are established at I .25 times the containment noble gas activity during purge based on a grab sample obtained from the rad monitor.

2. When the containment atmosphere monitor gas detector is not operational, the setpoints are established at I .5 times the containment noble gas activity during purge to prevent a spurious alarm based on a grab sample that may not be as representative of the containment atmosphere as monitored by the containment purge rad monitor during non-release periods.

2.6.3. Waste Gas Decay lank Effluent Monitors 1 . The setpoints are established at I .25 times the analyzed waste gas tank activity during release.

2.6.4. Gaseous Effluent Release Limits 1 . Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the dose rate limits of TRM Section 3.1 1 .f are not exceeded. The release limits are found by solving Equations 2-5 and 2-6 for the total allowed release rate of vent releases, Q.

(/Q)Q,Kf1 <500mrem/yr (2-5) f{L, (/Q) + (1.11) M (x/Q) }< 3000 mrem/yr (2-6)

The summations are over noble gas radionuclides i.

f Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.

Total Allowed Release Rate, Vent Release [pCi/sec]

The total allowed release rate of all noble gas radionuclides released as vent releases.

CY-BY-1 70-301 Revision 14 I Page56of 188

2. The remaining parameters in Equation 2-5 have the same definitions as in Equation 4-1 of Part 2 Section 4. The remaining parameters in Equation 2-6 have the same definition as in Equation 4-2 of Part 2 Section 4.

3. Equation 2-5 is based on Equation 4-1 of Section 4 and the RE restriction on whole body dose rate (500 mrem/yr) due to noble gases released in gaseous effluents (see Part 2 Section 4.2.1.1). Equation 2-6 is based on Equation 4-2 of Section 4 and the RE restriction on skin dose rate (3000 mrem/yr) due to noble gases released in gaseous effluents (see Part 2 Section 4.2.1.2).

4. Since the solution to Equation 2-6 is more conservative than the solution to Equation 2-5, the value of Equation 2-6 (1 .02 x I O jiCi/sec) is used as the limiting noble gas release rate. During evolutions involving releases from the containment or waste gas decay tanks, the total station release rate is procedurally limited such that the maximum permissible release rate is not exceeded.

2.6.5. Release Mixture I . In the determination of alarm and trip setpoints, the radioactivity mixture in exhaust air is assumed to have the radionuclide composition of Table 2-3.

2.6.6. Conversion Factors.

1. The response curves used to determine the monitor count rates are based on the sensitivity to Xe-I 33 for conservatism.

2.6.7. HVAC Dilution Flow Rates I . The plant vent stack flow rates are obtained from the RMS (or equivalent) console in the control room. If the values cannot be obtained from RMS (or equivalent), flow rates can be estimated from the operating fan combinations.

2.6.8. Allocation of Effluents from Common Release Points I . Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation systems and the gas decay tanks are comprised of contributions from both units. Consequently, allocation is made evenly between units.

2.6.9. Dose Projections for Batch Releases I . The I OCFR2O dose limits have been converted into a station administrative release rate limit using the methodology in the ODCM. Compliance is verified prior to each release. Doses are calculated after purging the containment or venting the waste gas decay tanks. Per procedure, representative samples are obtained and analyzed, and the doses calculated on a monthly basis to verify compliance with IOCFR5O.

CY-BY-1 70-301 Revision 14 Page 57 of 188 Table 2-1 Liquid Radioactive Effluent Monitors Alarm Setpoint Channel Monitor Description Sampling Locations Effluent Control Functions Used Radwaste Release Common release point from Radwaste ORE-PROOI Tank Monitor Release Tanks OWXOIT, OWX26T Radwaste release termination Yes Station Blowdown N*

I RE-PROO2 Reactor Containment 2RE-PROO2 Fan Cooler and I RE-PROO3 Essential Service Water 2RE-PROO3 Outlet Line Monitors RCFC and SX outlet lines None No Turbine Building Fire Terminates release from Fwean dOSu ich s Condensate Polisher Terminates release from Su r M.. Pis cha c.. mp s ORE-PROO9: CCW Heat Exchangers, ORE-PROO9: Closes both CCW surge common discharge tank vents I RE-PROO9: Unit I CCW Heat Exchanger I RE-PROO9: Closes Unit I CCW ORE-PROO9 discharge surge tank vent IRE-PROO9 Component Cooling 2RE-PROO9: Unit 2 CCW Heat Exchanger 2RE-PROO9: Closes Unit 2 CCW 2RE-PROO9 Water (CCW) Monitors discharge surge tank vent Yes

CY-BY-J 70-301 Revision 14 I Page 58 of 188 Table 2-2 Gaseous Radioactive Effluent Monitors Alarm Setpoint Channel Monitor Description Sampling Locations Effluent Control Functions Used Final effluent from auxiliary building vent stack IRE-PR028 Auxiliary Building Vent from Unit I (IRE-PR028) and None ____ Yes giPRQg8 EffluentMonftors . fZQL I RE-PROOJ Containment Purge Effluent from Unit 1 Containment (1 RE-PROOI)

EffluentfromUn[t2Contnmentj-PROO1 .. s ROO :

I RE-AROI I Unit I Containment (1 RE-AROI I I RE-AROI2) 2RE-AROI I Reactor Containment ,

Unit 2 Containment (2RE-AROI 1 2RE-AROI2)

I RE-AROI2 Particulate and Gas Note: not effluent monitors, but have effluent gLçs Jcs s ORE-PROO2A Waste Gas Decay Tank Closes valve OGWI 04, pp 2!5 !J.Y Ys Gland Steam and Condenser Air Ejector (CAE) gas from Unit I I RE-PR027 Condenser Air Ejector (I RE-PR027) and 2R E-P F0 f ° rs c. c N on e Radwaste Building Isolates Radwaste Building Ve .. waste Bu Nd entila s q **q Laboratory Fume Hood ORE-PROO3 Exhaust Monitor Common line from laboratory fume hoods None No

CY-BY-1 70-301 Revision 14 1 Page 59 of 188 Table 2-3 Assumed Composition of the Byron Station Noble Gas Effluent Isotope Percent of Effluent Ar-4 I 0.89 Kr-85m 0.18 Kr-85 24.9 Kr-87 0.04 Kr-88 0.28 Xe-I 31 m I .42 Xe-I 33m 0.57 Xe-I 33 71.1 Xe-135 0.53 Xe-138 0.04

CY-BY-1 70-301 Revision 14 Page 60 of 188 Table 2-4 Assumed Composition of the Byron Station Liquid Effluent Isotope Concentration Isotope Concentration (uCi/mi) (uCi/mI)

H-3 I .16E-05 Ag-I lOm I .70-11 Cr-51 2.39E-12 Te-127 5.40E-13 Mn-54 3.86E-11 Te-129m 1.78E-12 Fe-55 2.08E-1 2 Te-1 29 1 I 6E-1 2 Fe-59 I .35E-I 2 Te-1 31 m I .27E-1 2 Co-58 I .74E-1 0 Te-I 32 2.39E-1 I Co-60 3.40E-1O 1-130 4.24E-12 Br-83 6.59E-13 1-131 3.09E-09 Rb-86 I.8IE-I2 1-132 695E-II Sr-89 5.02E-13 1-133 1.43E-09 Zr-95 5.40E-I1 1-135 I.66E-1O Nb-95 7.72E-1 I Cs-l 34 1 .08E-09 Mo-99 7.72E-I I Cs-l 36 2.66E-1 0 Tc-99m 8.88E-II Cs-137 1.35E-09 Ru-103 5.40E-12 Ce-144 2.OIE-I0 Ru-106 9.26E-II Np-239 8.88E-13

dD NI Cflnfl AD7:]

f dO 133H9) vJvDvIa MO1 IN3fl1d3 SflO3SYD CNV DVAH C3IdfldkIS I- Jfl6!d NOIIVIS NOUA 7VflNW NQLLV1 flOlVO SOG 31ISJdO L- flqL-c?L B s.:]e

[I_1 A1INXIV J]Nfl iNEflNV!1NOD tood C])

l&jrIj VDQ7 dSDd H E H oooc INV1 E)dd H 99[JO [9068d I N UO!S!AOd io:-oz I-A8-A3

CY-BY-1 7O.3O1 Revision 14 I Page 62 of 188 IJNIT 1 CONDENSER H000INGEIJMP +/-- : 1.400 GLANDETEAMCITNDENSER f____,l___

I IRE-PR027 S1E0,M1ETA,IREjECT0P32 Stack Stack IJNIT2CONDENSER HOGGING PUMP I 1,400 8.630 SOLID RADWASTE DRUMMING STATIOFI VOIi.IMEREDIJCTION F tL H G G ti

- i:i- I- ;::L ORE-PRO4O LEGEND NOTES

1. UsED INTERN III ENILY To VENT C[ITA4L4EIF DuFIIIIO NOENqAL OR FREQUENT Fcow PATH NORM/IL OPEFYATloN OcrANorAc Fiow PAiH

2. UsED ONLY DIJEING PosT ACCiDENT OPERATION

3. NOTE REMOVED 4 CHARCOAL FILTRATION REMOVED FROM UNIT 2 CONTAINMENT A CONTAIMFN1 ATMOSPHERE RAGATION I]FJ[)EPI EC101354I.

MONIYOR C CHARCOAL FILlER G NOBLE GM RADIATION MONIYOR H HEPA FILTER M ThREE-CHANNEL RADIATION MONITOR FOR PARTICULATE, OFFS)T DOSE CALCULATION MANUAL GENE, AND NOBLE GAS OFFLINE) BYRON STATION P PARTICULATE MoNLToE)OFruN)

Figure 2-1 R HYDROGEN RECOMBINER SIMPLIFIED HVAC AND GASEOUS S NORMAL RANLA STACK RADIATION MONITOR EFFLUENT FLOW D)AG RAM tEARTIGICATE. IODINE, Argo NOBLE GAS)

(SHEET 2 OF 2)

FLOWS LISTED IS OEM w WIDE-RANGE STACK NOBLE GAS RADIAT1ON MONITOR

CYBY-1 70-301 Revision 14 Page 63 of 188 BLOWDOWN UNIT 1 STEAM GENERATOR BLOWOOWN UNIT 2 STEAM GENERATOR BL0WDOWN FIGURE 2-2 SIMPLIFIED LIQUID RADWASTE PROCESSING DIAGRAM

CY-BY-1 70-301 Revision 14 I Page 64 of 188 iRE -P RO 02 LEGEND Liquid Radwaste Monitor L1

/\ NaturalDraftCooling I ower Essential Service Water CoolingT ower Figure 2-3 Liquid Release Flow Path

CY-BY-1 70-301 Revision 14 Page 65 of I 88

3. LIQUID EFFLUENTS 3.1 . Liquid Effluent Releases General Information 3.1.1. The design objectives of IOCFR5O, Appendix I and RE provide the following limits on the dose to a member of the public from radioactive materials in liquid effluents released from each reactor unit to restricted area boundaries:

I . During any calendar quarter, less than or equal to I .5 mrem to the total body and less than or equal to 5 mrem to any organ.

2. During any calendar year, less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ.

3.1 .2. The organ doses due to radioactivity in liquid effluents are also used as part of the 4OCFRI 90 compliance and are included in the combination of doses to determine the total dose used to demonstrate IOCFR2O compliance. (See Section 5.0, Total Dose) 3.1 .3. Dose assessments for IOCFR5O Appendix I compliance are made for four age groups (adult, teenager, child, infant) using NUREG 0133 (Reference 14) methodology and Regulatory Guide 1.109 (Reference 6) dose conversion factors.

3.1.4. To limitthe consequences oftank overflow, Technical Specification 5.5.12 limits the quantity of radioactivity that may be stored in unprotected outdoor tanks to I 0 Curies.

I . Unprotected tanks are tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

2. The specific objective is to provide assurance that in the event of an uncontrolled release of a tanks contents, the resulting radioactivity concentrations beyond the unrestricted area boundary, at the nearest potable water supply and at the nearest surface water supply, will be less than the limits of IOCFR2O Appendix B, Table 2; Column 2.

3.1 .5. Cases in which normally non-radioactive liquid streams (such as the Service Water) are found to contain radioactive material are non-routine and will be treated on a case specific basis if and when this occurs. Since the station has sufficient capacity to delay a liquid release for reasonable periods of time, it is expected that planned releases will not take place under these circumstances.

Therefore, the liquid release setpoint calculations need not and do not contain provisions for treating multiple simultaneous release pathways.

CY-BY-1 70-301 Revision 14 I Page 66 of 188 3.1 .6. Radioactive liquid effluents released from either release tank (OWXOIT or OWX26T) are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units.

Consequently, allocation is made evenly between units.

3.2. Liquid Effluent Concentrations 3.2.1 . One method of demonstrating compliance to the requirements of IOCFR2O.1301 is to demonstrate that the annual average concentrations of radioactive material released in gaseous and liquid effluents do not exceed the values specified in IOCFR2O Appendix B, Table 2, Column 2. (See IOCFR 20.1302(b)(2).)

However, as noted in Section 5.5, this mode of IOCFR2O.1301 compliance has not been elected.

I . As a means of assuring that annual concentration limits will not be exceeded, and as a matter of policy assuring that doses by the liquid pathway will be ALARA; RE provides the following restriction:

A. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentration values in Appendix B, Table 2, Column 2 to I OCFR2O. I 001-20.2402.

2. This also meets the requirement of Station Technical Specifications and RE.

3.2.2. According to the footnotes to I OCFR2O Appendix B, Table 2, Column 2, if a radionuclide mix of known composition is released, the concentrations must be such that 11OECL)li I

ci (3-1) where the summation is over radionuclide i.

ci Radioactivity Concentration in Liquid Effluents to the Unrestricted Area [iCi/ml]

Concentration of radionuclide i in liquid released to the unrestricted area.

ECL Effluent Concentration Limit in Liquid Effluents Released to the Unrestricted Area [pCi/mi]

CY..BY-1 70-301 Revision 14 I Page 67 of 188 1 . The allowable annual average concentration of radionuclide i in liquid effluents released to the unrestricted area. This concentration is specified in 1 OCFR2O Appendix B, Table 2, Column 2. Concentrations for noble gases are different and are specified in the stations Technical Specifications and RE.

I0 Multiplier to meet the requirements of Technical Specifications.

2. If either the identity or concentration of any radionuclide in the mixture is not known, special rules apply. These are given in the footnotes in IOCFR2O Appendix B, Table 2, Column 2.

3.2.3. When radioactivity is released to the unrestricted area with liquid discharge from a tank (e.g., a radwaste discharge tank), the concentration of a radionuclide in the effluent is calculated as follows:

WasteFlow c.=c (3-2)

Dilution Flow ci Concentration of radionuclide I in liquid released to the unrestricted area. [jiCi/mlJ cit Concentration in the Discharge Tank [iCi/mI]

Measured concentration of radionuclide i in the discharge tank.

I . The RE and Technical Specifications require a specified sampling and analysis program to assure that liquid radioactivity concentrations at the point of release are maintained within the required limits. To comply with this provision, samples are analyzed in accordance with the radioactive liquid waste (or effluent) sampling and analysis program in the TRM 3.11 .c. Radioactivity concentrations in tank effluents are determined in accordance with Equation 3-2. Comparison with the Effluent Concentration Limit is made using Equation 3-1.

CY-BY-1 70-301 Revision 14 I Page 68 of 188 3.3. Liquid Effluent Dose Calculation Requirements 3.3.1 . RE require determination of cumulative and projected dose contributions from liquid effluents for the current calendar quarter and the current calendar year at least once per 31 days. (See TRM Chapter 3.1 1.)

I . For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in section 3.1.6.

3.3.2. Operability and Use of the Liquid Radwaste Treatment System

1. The design objectives of IOCFR5O, Appendix I, RE and Technical Specifications require that the liquid radwaste treatment system be operable and that appropriate portions be used to reduce releases of radioactivity when projected doses due to the liquid effluent from each reactor unit to restricted area boundaries exceed either of the following (see TRM Chapter 3.1 1 RE);,

. 0.06 mrem to the total body in a 31-day period.

0.2 mrem to any organ in a 31-day period.

CY-BY-1 70-301 Revision 14 I Page 69 of 188 3.4. Dose Methodology 3.41. Liquid Effluent Dose Method: General 1 . The dose from radioactive materials in liquid effluents considers the contributions for consumption of fish and potable water. All of these pathways are considered in the dose assessment unless demonstrated not to be present. While the adult is normally considered the maximum individual, the methodology provides for dose to be calculated for all four age groups. The dose to each organ (and to the total body) is calculated by the following expression:

Dq FAtAajpjCi (33)

The summation is over exposure pathways p and radionuclides i.

DIjq Organ and Total Body Dose Due to Liquid Effluents [mrem]

Dose to organ j (including total body) of age group a due to radioactivity in liquid effluents.

F Near Field Average Dilution Factor [dimensionless]

Dilution in the near field averaged over the period of interest.

Defined as:

Waste Flow F

(34)

Dilution Flow x Z Waste Flow Liquid Radioactive Waste Flow [gpm]

The average flow during disposal from the discharge structure release point into the receiving water body.

Dilution Flow Dilution Water Flow During Period of Interest [gpm]

z Discharge Structure Mixing Factor [dimensionless]

CY-BY-1 70-301 Revision 14 Page 70 of 188

2. Site-specific factor to account for the mixing effect of the discharge structure.

The factor addresses the dilution that occurs in the near field between the discharge structure and the body of water containing the fish in the liquid ingestion pathway (See Section 3.5).

At Duration of Release [hrs]

ci Average Radionuclide Concentration [pCi/mi]

Average concentration of radionuciide i, in the undiluted liquid effluent during time period At.

Aaipj Site-Specific Liquid Dose Factor [(mrem/hr)/(pCi/mi)]

3. Site-specific dose factor for age group a, nuciide i, liquid pathway p and organ j.

The pathways included are potable water and fish ingestion. Aaipj IS defined for these pathways in the following sections. Values for Aaipj are provided in Part 2 Section 3.5 of this ODCM.

CY-BY-1 70-301 Revision 14 I Page7l of 188 3.4.2. Potable Water Pathway 1 . The site-specific potable water pathway dose factor is calculated by the following expression:

(uw A

ai(PW)j I

0 J_L w

flI au 35 Where:

Aaj(pW)j Site-Specific Dose Factor for Potable Water Pathway

[(mrem/h r)IQiCiIml)]

Site-specific potable water ingestion dose factor for age group a, nuclide I and organ j.

k0 Conversion Constant (1 14E05) [(yr-pCi-ml)I(hr-pCi-l)]

Units constant to convert years to hours, pCi to iCi and liters to ml.

Ua Potable Water Consumption Rate [1/yr]

Potable water consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109.

Dw Potable Water Dilution Factor [dimensionless]

Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake (See section 3.5).

DFLaij Ingestion Dose Conversion Factor [mrem/pCi]

Ingestion dose conversion factor for age group a, nuclide I and organ j.

Converts pCi ingested to mrem. Taken from Tables E-11 though E-14 of Regulatory Guide 1.109. The values for H-3 and Sr-90 are taken from NUREG 4013 (Reference 107).

CY-BY-1 70-301 Revision I 4 Page 72 of 188 3A.3. Fish Ingestion Pathway I . The site-specific fish ingestion pathway dose factor is calculated by the following expression:

Aai(Fish)j = koUBFjDFLaij (36)

Where:

Aaj(fjsh)j Site-Specific Dose Factor for Fish Ingestion Pathway

[(mrem/h r)IQiC i/mi)]

Site-specific fish ingestion dose factor for age group a, nuclide I and organ j.

UaF Fish Consumption Rate [kg/yrJ Fish consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109.

BF Bioaccumulation Factor [(pCi/kg)/(pCi/l)J Bioaccumulation factor for nuclide i in fresh water fish. Taken from Table 3-8.

All other terms have been previously defined.

3.4.4. Offsite doses due to projected releases of radioactive materials in liquid effluents are calculated using Equation 3-3. Projected radionuclide release concentrations are used in place of measured concentrations, C.

3.5. Site Specific Dose Factors and Bioaccumulation Factors 3.5.1 . There are no public potable water intakes on the Rock River downstream of the station.

3.5.2. There is no irrigation occurring on the Rock River downstream of the station.

3.5.3. Recreation includes one or more ofthe following: boating, water-skiing, swimming, and sport fishing.

CY-BY-J 70-301 Revision 14 I Page 73 of 188 3.54. According to Section 2.4.1 .2 and Figure 2.4-5 of the Byron Environmental Report, there are four downstream dams on the Rock River within approximately 50 miles of the station one at Oregon, one at Dixon and two at Sterling.

3.5.5. Water and Fish Ingestion Parameters 3.5.51 Dw= 10 (potable water dilution factor, dimensionless) 3.5.5.2 Z= 32 (discharge structure mixing factor, dimensionless) 3.5.6. Site-specific dose factors for potable water consumption are shown in Table 3-1 for adult, Table 3-2 for teen, Table 3-3 for child, and Table 3-4 for infant age groups. These tables include dose factors for the bone, liver, total body, thyroid, kidney, lung, and GI (lower large intestines).

3.5.7. Site-specific dose factors for fish ingestion are shown in Table 3-5 for adult, Table 3-6 for teen, and Table 3-7 for child age groups. These tables include dose factors for the bone, liver, total body, thyroid, kidney, lung, and GI (lower large intestines).

CY-BY-1 70-301 Revision 14 I Page 74 of 188 Table 3-1 Site Specific Potable Water Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 4.9$E-O1 4.98E-O1 4.98E-O1 4.98E-O1 4.98E-O1 4.98E-O1 Na-24 1.41E+O1 1.41E+O1 1.41E+O1 1.41E+O1 1.41E+O1 1.41E+O1 1.41E+O1 Cr-51 O.OOE+OO O.OOE+OO 2.21E-02 1.32E-02 4.88E-03 2.94E-02 5.57E+OO Mn-54 O.OOE+OO 3.$OE+O1 7.26E+OO O.OOE+OO 1.13E+O1 O.OOE+OO 1.17E+02 Mn-56 O.OOE+OO 9.57E-O1 1.70E-O1 O.OOE+OO 1.22E+OO O.OOE+OO 3.05E+O1 Fe-55 2.29E+O1 1.58E+O1 3.69E+OO O.OOE--OO O.OOE+OO 8.82E--OO 9.07E+OO Fe-59 3.61E+O1 $.49E+O1 3.25E+O1 O.OOE+ O.OOE+OO 2.37E+O1 2.83E+02 Co-5$ O.OOE+OO 6.20E+OO 1.39E+O1 O.OOE+ O.OOE+OO O.OOE+OO 1.26E+02 Co-60 O.OOE+OO 1.7$E+O1 3.93E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 3.35E+02 Ni-63 1.O$E+03 7.50E+O1 3.63E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 1.56E+O1 Ni-65 4.39E+OO 5.71E-O1 2.60E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 1.45E+O1 Cu-64 O.OOE+OO 6.93E-O1 3.25E-O1 O.OOE+OO 1.75E+OO O.OOE+OO 5.91E+O1 Zn-65 4.03E+O1 1.2$E+02 5.79E+O1 O.OOE+ 0 8.57E+O1 O.OOE+OO $.07E+O1 Zn-69 8.57E-02 1.64E-O1 1.14E-02 O.OOE+ 1.07E-O1 O.OOE+ 2.46E-02 Br-83 O.OOE+OO O.OOE+OO 3.35E-O1 O.OOE+ O.OOE+OO O.OOE+ 4.82E-O1 Br-84 O.OOE+OO O.OOE+OO 4.34E-O1 O.OOE+O O.OOE+OO O.OOE+ 3.40E-06 Br-85 O.OOE+OO O.OOE+OO 1.7$E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.76E+02 8.1$E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 3.46E+O1 Rb-$8 O.OOE+OO 5.03E-O1 2.67E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 6.96E-12 Rb-89 O.OOE+OO 3.34E-O1 2.35E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E-14 f-89 2.56E+03 O.OOE+OO 7.36E+O O.OOE+O O.OOE+OO O.OOE+ 4.1 1E--02 r-90 7.25E+04 O.OOE+OO 1 .46E+03 O.OOE+O O.OOE+OO O.OOE+ 1 .82E+03 Sr-91 4.72E+O1 O.OOE+OO 1.91E+OO O.OOE+O O.OOE+OO O.OOE+ 2.25E+02 Sr-92 179E+O1 O.OOE+OO 7.74E-O O.OOE+O O.OOE+OO O.OOE+ 3.55E+02 Y-90 8.O1E-02 O.OOE+OO 2.15E-03 O.OOE+OO O.OOE+OO O.OOE+O 8A9E+02 Y-91M 7.56E-04 O.OOE+OO 2.93E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.22E-03 Y-91 1.17E+OO O.OOE+OO 3.14E-02 O.OOE+OO O.OOE+OO O.OOE+OO 6.46E+02 Y-92 7.03E-03 O.OOE+OO 2.06E-04 O.OOE+O O.OOE+OO O.OOE+OO 1.23E+02 Y-93 2.23E-02 O.OOE+OO 6.16E-04 O.OOE+O O.OOE+OO O.OOE+ 7.07E+02 Zr-95 2.53E-O1 8.1 1E-02 5.49E-02 O.OOE+O 1 .27E-O1 O.OOE+ 2.57E+02 Zr-97 1.40E-02 2.82E-03 1.29E-03 O.OOE+O 4.26E-03 O.OOE+ 8.74E+02 Nb-95 5.18E-02 2.88E-02 1.55E-02 O.OOE+OO 2.85E-02 O.OOE+ 1.75EmO2 Nb-97 4.35E-04 1.1OE-04 4.02E-05 O.OOE+OO 1.28E-04 O.OOE+ 4.06E-O1 Mo-99 O.OOE+OO 3.59E+O1 6.82E+OO O.OOE+OO 8.12E+O1 O.OOE+O 8.31E+O1 Te- 99M 2.06E-03 5.81E-03 7.40E-02 O.OOE+OO $.82E-02 2.$5E-O 3.44E+OO Tc-1O1 2.1 1E-03 3.05E-03 2.99E-02 O.OOE+OO 5A$E-02 1.56E-O 9.15E-15 Ru-103 1.54E+OO O.OOE+OO 6.63E-O1 O.OOE+OO 5.88E+OO O.OOE+ 1.$OE--02 Ru-105 1.28E-O1 O.OOE+OO 5.06E- O.OOE+OO 1.66E+OO O.OOE+ 7.84E+O1 Ru-106 2.29E+O1 O.OOE+OO 2.90E+ O.OOE+OO 4.42E+O1 O.OOE+ 1.4$E+03 Ag-i 1OM 1.33E+OO i.23E+OO 7.32E- O.OOE-rOO 2.42E+OO O.OOE+ 5.03E+02 Sb-124 2.33E+O1 4.41E-Oi 9.25E+O 5.66E-02 OMOE+OO 1.82E+Oi 6.63E+02 Sb-125 l.49E+O1 i.67E-Oi 3.55E+O i.52E-02 O.OOE+OO 1.15E+Oi 1.64E+02 Te-125M 2.23E+O 1 8.08E+OO 2.99E+O 6.71E+OO 9.07E+O 1 O.OOE+OO 8.90E+O 1 Sb-126 9.58E+OO 1.95E-O1 3.46E+O 5.87E-02 O.OOE+OO 5.88E+OO 7.83E+02

CY-BY-J 70-301 Revision 14 I Page 75 of 188 Table 3-1 (continued)

Site Specific Potable Water Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Ye- 1 27M 5 .63E+O 1 2.0 1 E+O 1 6.87E+OO 1 .44E+O 1 2.29E+02 O.OOE+OO 1 .89E+02 Te-127 9.15E-O1 3.29E-O1 1.98E-O1 6.78E-O1 3.73E+OO O.OOE+OO 7.22E+O1 Te-129M 9.57E+O1 3.57E+O1 1.51E+O1 3.29E+O1 3.99E+02 O.OOE+OO 4.82E+02 Te- 1 29 2.6 1 E-O 1 9.82E-02 6.37E-02 2.0 1 E-O 1 1 1 OE+OO O.OOE+OO

. 1 .97E-O 1 Te- 1 3 1 M 1 .44E+O 1 7.04E+OO 5 .87E+OO 1 1 2E+O 1 7. 1 3E+O 1 O.OOE+OO

. 6.99E+02 Te-131 1.64E-O1 6.85E-02 5.18E-02 1.35E-O1 7.18E-O1 O.OOE+OO 2.32E-02 Te- 1 32 2. 1 OE+O 1 1 .36E+O 1 1 .27E+O 1 1 .50E+O 1 1 .3 1 E+02 O.OOE+OO 6.42E+02 I- 1 30 6.29E+OO 1 .86E+O 1 7.32E+OO 1 .57E+03 2.90E+O 1 O.OOE+OO 1 .60E+O 1 1-131 3.46E+O1 4.95E+O1 2.84E+O1 1.62E+04 8.49E+O1 O.OOE+OO 1.31E+O1 1-132 1.69E+OO 4.52E+OO 1.58E+OO 1.58E+02 7.20E+OO O.OOE+OO 8.49E-O1 I- 1 33 1 1 8E+O 1 2.06E+O 1 6.27E+OO 3 .02E+03 3 .59E+O 1 O.OOE+OO

. 1 .85E+O 1 1-134 8.82E-O1 2.40E+OO 8.57E-O1 4.15E+O1 3.81E+OO O.OOE+OO 2.09E-03 I- 1 35 3 .69E+OO 9.65E+OO 3 .56E+OO 6.37E+02 1 .55E+O 1 O.OOE+OO 1 .09E+O 1 Cs- 1 34 5 1 8E+02 1 .23E+03 1 .0 1 E+03 O.OOE+OO 3 .99E+02 1 .32E+02

. 2. 1 6E+O 1 Cs-136 5.42E+O1 2.14E+02 1.54E+02 O.OOE+OO 1.19E+02 1.63E+O1 2.43E+O1 Cs-137 6.63E+02 9.07E+02 5.94E+02 O.OOE+OO 3.08E+02 1.02E+02 1.76E+O1 Cs- 1 3 8 4.59E-O 1 9.07E-O 1 4.49E-O 1 O.OOE+OO 6.67E-O 1 6.5 $E-02 3 .87E-06 Ba-139 $.07E-O1 5.75E-04 2.36E-02 O.OOE+OO 5.38E-04 3.26E-04 1.43E+OO Ba-140 1.69E+02 2.12E-O1 1.1 1E+O1 O.OOE+OO 7.22E-02 1.22E-O1 3.4$E+02 Ba-141 3.92E-O1 2.96E-04 1.32E-02 O.OOE+OO 2.75E-04 1.68E-04 1.85E-1O Ba-142 1.77E-O1 1.82E-04 1.12E-02 O.OOE+OO 1.54E-04 1.03E-04 2.50E-19 La-140 2.08E-02 1.05E-02 2.77E-03 O.OOE+OO O.OOE+OO O.OOE+OO 7.70E+02 La-142 1.07E-03 4.84E-04 1.21E-04 O.OOE+OO O.OOE+OO O.OOE+OO 3.54E+OO Ce-141 7.79E-02 5.27E-02 5.9$E-03 O.OOE+OO 2.45E-02 O.OOE+OO 2.O1E+02 Ce-143 1.37E-02 1.02E+O1 1.12E-03 O.OOE+OO 4.47E-03 O.OOE+OO 3.79E+02 Ce-144 4.06E+OO 1.70E+OO 2.18E-O1 O.OOE+OO 1.O1E+OO O.OOE+OO 1.37E+03 Pr- 1 43 7.66E-02 3 .07E-02 3 .79E-03 O.OOE+OO 1 .77E-02 O.OOE+OO 3 .35E+02 Pr-144 2.50E-04 1.04E-04 1.27E-05 O.OOE+OO 5.87E-05 O.OOE+OO 3.60-11 Nd-147 5.23E-02 6.05E-02 3.62E-03 O.OOE+OO 3.54E-02 O.OOE+OO 2.90E+02 w- 1 87 8 .57E-O 1 7. 1 7E-O 1 2.50E-O 1 O.OOE+OO O.OOE+OO O.OOE+OO 2.35E+02 Np-239 9.90E-03 9.74E-04 5.37E-04 O.OOE+OO 3.04E-03 O.OOE+OO 2.OOE+02 Notes:

I) Units are mrem/hr per iCi/mI.

CY-BY-J 70-301 Revision 14 I Page 76 of 188 Table 3-2 Site Specific Potable Water Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 3.51E-O1 3.51E-O1 3.51E-O1 3.51E-O1 3.51E-O1 3.51E-O1 Na-24 1.34E+O1 1.34E+O1 1.34E+O1 1.34E+O1 1.34E+O1 1.34E+O1 1.34E+O1 Cr-51 O.OOE+OO O.OOE+OO 2.09E-02 1.16E-02 4.59E-03 2.99E-02 3.52E+OO Mn-54 O.OOE+OO 3.43E+O1 6.80E+OO O.OOE+OO 1.02E+O1 O.OOE+ 7.03E+O1 Mn-56 O.OOE+OO 9.19E-O1 1.63E-O1 O.OOE+OO 1.16E+OO O.OOE+ 6.05E+O1 Fe-55 2.20E+O1 1.56E+O1 3.63E+OO O.OOE+OO O.OOE+OO 9.88E+ 6.74E+OO Fe-59 3.41E+O1 7.97E+O1 3.08E+O1 O.OOE+OO O.OOE+OO 2.51E+O 1.88E+02 Co-58 O.OOE+OO 5.65E+OO 1.30E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 7.79E+O1 Co-60 O.OOE+OO 1.63E+O1 3.68E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 2.13E+02 Ni-63 1.03E+03 7.27E+O1 3.49E+O1 O.OOE+OO O.OOE+OO O.OOE+ 1.16E+O1 Ni-65 4.35E+OO 5.56E-O1 2.53E-O1 O.OOE+O O.OOE+ O.OOE+ 3.02E+O1 Cu-64 O.OOE+OO 6.69E-O1 3.15E-O1 O.OOE+O 1.69E+ O.OOE+ 5.19E+O1 Zn-65 3.35E+O1 1.16E+02 5.42E+O1 O.OOE+O 7.44Em O.OOE+ 4.92EmO1 Zn-69 8.55E-02 1.63E-O1 1.14E-02 O.OOE+OO 1.06E-O O.OOE+OO 3.OOE-O1 Br-83 O.OOE+OO O.OOE+OO 3.34E-O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO r-84 O.OOE+OO O.OOE+OO 4.20E-O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO r-85 O.OOELOO O.OOE+OO 1.77E-02 O.OOE+OO O.OOE+ O.OOE+OO O.OOE+OO b-$6 O.OOE+OO 1.73E+ 8.14E+O1 O.OOE+O O.OOE+ O.OOE+ 2.56E+O1 Rb-88 O.OOE+OO 4.95E- 2.64E-O1 O.OOE+O O.OOE+ O.OOE+ 4.24E-08 Rb-89 O.OOE+OO 3.20E-O1 2.26E-O1 O.OOE+O O.OOE+ O.OOE+ 4.90E-1O Sr-$9 2.56E+03 O.OOE+OO 7.33E+O1 O.OOE+O O.OOE+ O.OOE+ 3.05E+02 Sr-90 5.93E+04 O.OOE+OO 1.19E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.35E+03 Sr-91 4.69E+O1 O.OOE+OO 1.87E+OO O.OOE+OO O.OOE+OO O.OOE+O 2.13E+02 Sr-92 1.77E+O1 O.OOE+OO 7.56E-O1 O.OOE+OO O.OOE+OO O.OOE+O 4.52E+02 Y-90 7.97E-02 O.OOE+OO 2.15E-03 O.OOE+O O.OOE+O O.OOE+ 6.57E+02 Y-91M 7.50E-04 O.OOE+OO 2.87E-05 O.OOE+O O.OOE+ O.OOE+ 3.54E-02 Y-91 1.17E+OO O.OOE+OO 3.13E-02 O.OOE+O O.OOE+ O.OOE+ 4.79E+02 Y-92 7.03E-03 O.OOE+OO 2.03E-04 O.OOE-rO O.OOE+ O.OOE+ 1.93E+02 Y-93 2.23E-02 O.OOE+OO 6.1OE-04 O.OOE+O O.OOE+OO O.OOE+ 6.80E+02 Zr-95 2.40E-O1 7.56E-O 5.20E-02 O.OOE+OO 1.1 1E-Ol O.OOE+O 1.74E+02 Zr-97 1.38E-02 2.73E-O 1.26E-03 O.OOE+OO 4.13E-03 O.OOE+O 7.3$E+02 Nb-95 4.7$E-02 2.65E-02 1.46E-02 O.OOE+OO 2.57E-02 O.OOE+O 1.13E+02 Nb-97 4.29E-04 1.07E-04 3.89E-05 O.OOE+OO 1.25E-04 O.OOE+O 2.54E+OO Mo-99 O.OOE+OO 3.51E+ 6.69E+OO O.OOE+ 8.02E+O1 O.OOE+OO 6.28E+O1 Tc- 99M 1.93E-03 5.3$E- 6.98E-02 O.OOE+ 8.02E-02 2.99E-03 3.53E+OO Tc-1O1 2.09E-03 2.98E-03 2.92E-02 O.OOE+ 5.38E-02 1.81E-03 5.09E-1O Ru-103 1.48E+OO O.OOE+OO 6.34E-O1 O.OOE+OO 5.23E+OO O.OOE+OO 1.24E+02 Ru-105 1.27E-O1 O.OOE+OO 4.92E-02 O.OOE+OO 1.60E+OO O.OOE+OO 1.02E+02 Ru-106 2.28E+O1 O.OOE+OO 2.87E+OO O.OOE+OO 4AOE+O O.OOE+OO 1.09E+03 Ag-i 1OM 1 .19E+OO 1 .13E+OO 6.86E-O1 O.OOE+OO 2.15E+O O.OOE+OO 3.17E+02 Sb-124 2.25E+O1 4.15E-O1 8.79E+OO 5.11E-02 O.OOE+O 1.97E+O1 4.54E+02 Sb-125 1A4E+O1 1.5$E-O1 3.38E+OO 1.38E-02 O.OOE+O 1.27E+O1 1.12E+02 Te-125M 2.23E+O1 8.02E+OO 2.98E+OO 6.22E+OO O.OOE+O O.OOE+OO 6.57E+O1 Sb-126 9.26E+OO 1.89E-O1 3.32E+OO 5.23E-02 O.OOE+O 6.64E+OO 5.4$E+02

CY-BY-1 70-301 Revision 14 Page 77 of I 88 Table 3-2 (continued)

Site Specific Potable Water Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-127M 5.62E+O1 1 .99E+O1 6.69E+OO 1 .34E+O1 2.2$E+02 O.OOE+OO 1.40E+02 Te-127 9.19E-O1 3.26E-O1 1.98E-O1 6.34E-O1 3.72E+OO O.OOE+OO 7.09E+O1 Te- 1 29M 9.48E+O 1 3 .52E+O 1 1 .50E+O 1 3 .06E+O 1 3 .97E+02 O.OOE+OO 3 .56E+02 Te-129 2.60E-O1 9.71E-02 6.34E-02 1.86E-O1 1.09E+OO O.OOE+OO 1A2E+OO Te-131M 1.42E+O1 6.80E+OO 5.67E+OO 1.02E+O1 7.09E+O1 O.OOE+OO 5.46E+02 Te-131 1.62E-O1 6.69E-02 5.07E-02 1.25E-O1 7.09E-O1 O.OOE+OO 1.33E-02 Te-132 2.03E+O1 1.28E+O1 1.21E+O1 1.35E+O1 1.23E+02 O.OOE+OO 4.07E+02 1-130 5.99E+OO 1.73E+O1 6.92E+OO 1.41E+03 2.67E+O1 O.OOE+OO 1.33E+O1 1-131 3.40E+O1 4.76E+O1 2.56E+O1 1.39E+04 8.20E+O1 O.OOE+OO 9.42E+OO I- 1 32 1 .62E+OO 4.24E+OO 1 .52E+OO 1 .43E+02 6.69E+OO O.OOE+OO 1 .85E+OO 1-133 1.17E+O1 1.98E+O1 6.05E+OO 2.77E+03 3.48E+O1 O.OOE+OO 1.50E+O1 1-134 $.49E-O1 2.25E+OO 8.08E-O1 3.75E+O1 3.55E+OO O.OOE+OO 2.97E-02 I- 1 35 3 .55E+OO 9. 1 3E+OO 3 .3 8E+OO 5 .87E+02 1 .44E+O 1 O.OOE+OO 1 .0 1 E+O 1 Cs- 1 34 4.87E+02 1 1 5E+03

. 5 .3 1 E+02 O.OOE+OO 3 .64E+02 1 .39E+02 1 .42E+O 1 Cs- 1 36 4.99E+O 1 1 .97E+02 1 .32E+02 O.OOE+OO 1 .07E+02 1 .69E+O 1 1 .58E+O 1 Cs-137 6.51E+02 8.66E+02 3.02E+02 O.OOE+OO 2.95E+02 1.15E+02 1.23E+O1 Cs-138 4.51E-O1 $.66E-O1 4.33E-O1 O.OOE+OO 6.40E-O1 7.44E-02 3.93E-04 Ba- 1 39 8.08E-O 1 5 .69E-04 2.35E-02 O.OOE+OO 5 .36E-04 3 .92E-04 7.2 1 E+OO Ba- 1 40 1 .65E+02 2.02E-O 1 1 .06E+O 1 O.OOE+OO 6.86E-02 1 .36E-O 1 2.55E+02 Ba- 1 4 1 3 .90E-O 1 2.9 1 E-04 1 .30E-02 O.OOE+OO 2.70E-04 1 .99E-04 8.3 1 E-07 Ba-142 1.74E-O1 1.74E-04 1.07E-02 O.OOE+OO 1.47E-04 1.16E-04 5.34E-13 La-140 2.02E-02 9.94E-03 2.65E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.71E+02 La-142 1.04E-03 4.62E-04 1.15E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+O1 Ce-141 7.73E-02 5.16E-02 5.93E-03 O.OOE+OO 2.43E-02 O.OOE+OO 1.48E+02 Ce-143 1.37E-02 9.94E+OO 1.1 1E-03 O.OOE+OO 4.46E-03 O.OOE+OO 2.99E+02 Ce-144 4.05E+OO 1.67E+OO 2.17E-O1 O.OOE+OO 1.OOE+OO O.OOE+OO 1.02E+03 Pr-143 7.62E-02 3.04E-02 3.79E-03 O.OOE+OO 1.77E-02 O.OOE+OO 2.51E+02 Pr-144 2.50E-04 1.02E-04 1.27E-05 O.OOE+OO 5.87E-05 O.OOE+OO 2.76E-07 Nd-147 5.45E-02 5.93E-02 3.55E-03 O.OOE+OO 3.48E-02 O.OOE+OO 2.14E+02 w-1 87 $.49E-O1 6.92E-O1 2.42E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 1 .$7E+02 Np-239 1.02E-02 9.65E-04 5.36E-04 O.OOE+OO 3.03E-03 O.OOE+OO 1.55E+02 Notes:

1) Units are mrem/hr per pCi/mi.

CY-BY-1 70-301 Revision 14 Page 78 of 188 Table 3-3 Site Specific Potable Water Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 6.74E-O1 6.74E-O1 6.74E-O1 6.74E-O1 6.74E-O1 6.74E-O1 Na-24 3.37E+O1 3.37E+O1 3.37E+O1 3.37E+O1 3.37E+O1 3.37E+O1 3.37E+O1 Cr-51 O.OOE+OO O.OOE+OO 5.17E-02 2.$7E-02 7.85E-03 5.24E-02 2.74E+OO Mn-54 O.OOE+OO 6.22E+O1 1.66E+O1 O.OOE+OO 1.74E+O1 O.OOE+OO 5.22E+O1 Mn-56 O.OOE+OO 1.94E+OO 4.3$E-O1 O.OOE+OO 2.35E+OO O.OOE+OO 2.81E+02 fe-55 6.69E+O1 3.55E+O1 1.1OE+O1 O.OOE+OO O.OOE+OO 2.O1E+O1 6.57E+OO Fe-59 9.59E+O1 1.55E+02 7.73E+O1 O.OOE+O O.OOE+ 4.50E+O1 1.62E+02 Co-58 O.OOE+OO 1.05E+O1 3.20E+O1 O.OOE+O O.OOE+ O.OOE+OO 6.1OE+O1 Co-60 O.OOE+OO 3.O$E+O1 9.07E+O1 O.OOE+O O.OOE+ O.OOE+OO 1.70E+02 Ni-63 3.13E+03 .67E+02 1.06E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.13E+O1 Ni-65 1.29E+O1 .22E+OO 7.09E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 1.49E+02 Cu-64 O.OOE+OO .42E+OO 8.60E-O1 O.OOE+OO 3.44E+OO O.OOE+OO 6.69E+O1 Zn-65 7.97E+O1 2.12E+02 1.32E+02 O.OOE+OO 1.34E+02 O.OOE+OO 3.73E+O1 Zn-69 2.55E-O1 3.68E-O1 3.40E-02 O.OOE+O 2.23E- O.OOE+O 2.32E+O1 Br-83 O.OOE+OO O.OOE+OO 9.94E-O1 O.OOE+O O.OOE+ O.OOE+O O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 1.15E+OO O.OOE-i-O O.OOE+ O.OOE+O O.OOE+OO Br-$5 O.OOE+OO O.OOE+OO 5.30E-02 O.OOE+O O.OOE+ O.OOE+O O.OOE+OO Rb-86 O.OOE+OO 3.90E+02 2.40E+02 O.OOE+OO O.OOE+OO O.OOE+O 2.51E+O1 Rb-$8 O.OOE+OO 1.1OE+OO 7.67E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 5.42E-02 Rb-89 O.OOE+OO 6.80E-O1 6.05E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 5.93E-03 Sr-89 7.67E+03 O.OOE+OO 2.19E+02 O.OOE+O O.OOE+OO O.OOE+OO 2.97E+02 Sr-90 1 .49E+05 O.OOE+OO 2.99E+03 O.OOE+O O.OOE+ O.OOE+O 1 .33E+03 Sr-91 1 .40E+02 O.OOE+OO 5.27E+OO O.OOE+O O.OOE+ O.OOE+O 3.08E+02 Sr-92 5.25E+O1 O.OOE+OO 2.1OE+OO O.OOE+ O.OOE+ O.OOE+O 9.94E+02 Y-90 2.39E-O1 O.OOE+OO 6.40E-03 O.OOE+ O.OOE+OO O.OOE+O 6.80E+02 Y-91M 2.22E-03 O.OOE+OO 8.08E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.35E+OO Y-91 3.50E+OO O.OOE+OO 9.36E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.66E+02 Y-92 2.09E-02 O.OOE+OO 5.99E-04 O.OOE+OO O.OOE+OO O.OOE+OO 6.05E+02 Y-93 6.63E-02 O.OOE+OO 1.82E-03 O.OOE+OO O.OOE+OO O.OOE+OO 9.$8E+02 Zr-95 6.74E-O 1 1 .48E- 1 .32E-O 1 O.OOE+ 2. 12E-O1 O.OOE+O 1 .55E+02 Zr-97 4.06E-02 5.87E- 3.47E-03 O.OOE+ 8.43E-03 O.OOE+O 8.90E+02 Nb-95 1.31E-O1 5.09E- 3.64E-02 O.OOE+ 4.78E-02 O.OOE+O 9.42E+O1 Nb-97 1.26E-03 2.28E-04 1.07E-04 O.OOE+ 2.53E-04 O.OOE+O 7.04E+O1 Mo-99 O.OOE+OO 7.73E+O1 1.91E+O1 O.OOE+OO 1.65E+02 O.OOE+O 6.40E+O1 Tc- 99M 5.37E-03 1.05E-02 1.74E-O1 O.OOE+OO 1.53E-O1 5.34E-03 5.99E+OO Tc-1O1 6.22E-03 6.51E-03 $.26E-02 O.OOE+OO 1.11E-O1 3.44E-03 2.07E-02 Ru-103 4.25E+OO O.OOE+OO 1.63E+OO O.OOE+OO 1.07E+O1 O.OOE+OO 1.1OE+02 Ru-105 3.75E-O1 O.OOE+OO 1.36E-O1 O.OOE+ 3.30E+OO O.OOE+O 2.45E--O2 Ru-106 6.80E+O1 O.OOE+OO 8.49E+OO O.OOE+ 9.19E+O1 O.OOE+O 1.06E+03 Ag-i 1OM 3.13E+OO 2.12E+OO i.69E+OO O.OOE+ 3.94E+OO O.OOE+O 2.52E+02 Sb-i24 6.46E+O1 8.38E-O1 2.26E+O1 i.43E-Oi O.OOE+OO 3.59E+Oi 4.04E+02 Sb-125 4. 1 7E+O 1 3 .21E-O 1 8.73E+OO 3.86E-02 O.OOE+OO 2.32E+Oi 9.96E+O 1 Te-125M 6.63E+Oi i.20E+O1 $.84E+OO i.86E+O1 O.OOE+OO O.OOE+OO 6.40E+Oi Sb-126 2.56E+O 1 3 .92E-O 1 9.20E+OO 1 .50E-O 1 O.OOE+OO 1 .22E+O 1 5. 16E+02

CY-BY-1 70-301 Revision 14 Page 79 of 188 Table 3-3 (continued)

Site Specific Potable Water Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-127M 1.6$E+02 4.52E+O1 1.99E+O1 4.02E+O1 4.79E+02 O.OOE+OO 1.36E+02 Te- 1 27 2.74E+OO 7.3 8E-O 1 5 .87E-O 1 1 .90E+OO 7.79E+OO O.OOE+OO 1 .07E+02 Te- 1 29M 2.83E+02 7.9 1 E+O 1 4.40E+O 1 9. 1 3E+O 1 8.3 1 E+02 O.OOE+OO 3 .45E+02 Te- 1 29 7.79E-O 1 2. 1 7E-O 1 1 .85E-O 1 5 .56E-O 1 2.28E+OO O.OOE+OO 4.85E+O 1 Te-131M 4.19E+O1 1.45E+O1 1.54E+O1 2.98E+O1 1.40E+02 O.OOE+OO 5.87E+02 Te- 1 3 1 4.83E-O 1 1 .47E-O 1 1 .44E-O 1 3 .69E-O 1 1 .46E+OO O.OOE+OO 2.53E+OO Te-132 5.87E+O1 2.60E+O1 3.14E+O1 3.78E+O1 2.41E+02 O.OOE+OO 2.62E+02 I- 1 30 1 .70E+O 1 3 .43E+O 1 1 .77E+O 1 3 .78E+03 5 1 3E+O 1

. O.OOE+OO 1 .60E+O 1 1-131 1.OOE+02 1.O1E+02 5.72E+O1 3.33E+04 1.65E+02 O.OOE+OO 8.95E+OO 1-132 4.65E+OO 8.55E+OO 3.93E+OO 3.97E+02 1.31E+O1 O.OOE+OO 1.O1E+O1 1-133 3.44E+O1 4.26E+O1 1.61E+O1 7.91E+03 7.09E+O1 O.OOE+OO 1.72E+O1 1-134 2.44E+OO 4.52E+OO 2.08E+OO 1.04E+02 6.92E+OO O.OOE+OO 3.OOE+OO 1-135 1.02E+O1 1.83E+O1 8.66E+OO 1.62E+03 2.81E+O1 O.OOE+OO 1.40E+O1 Cs- 1 34 1 .36E+03 2.23E+03 4.7 1 E+02 O.OOE+OO 6.92E+02 2.48E+02 1 .20E+O 1 Cs-136 1.37E+02 3.76E+02 2.43E+02 O.OOE+OO 2.OOE+02 2.98E+O1 1.32E+O1 Cs-137 1.90E+03 1.82E+03 2.69E+02 O.OOE+OO 5.93E+02 2.13E+02 1.14E+O1 Cs-138 1.33E+OO 1.84E+OO 1.17E+OO O.OOE+OO 1.30E+OO 1.40E-O1 8.49E-O1 Ba- 1 39 2.4 1 E+OO 1 .28E-03 6.98E-02 O.OOE+OO 1 1 2E-03

. 7.56E-04 1 .39E+02 Ba- 1 40 4.83E+02 4.23E-O 1 2.82E+O 1 O.OOE+OO 1 .3 $E-O 1 2.52E-O 1 2.45E+02 Ba-141 1.16E+OO 6.51E-04 3.78E-02 O.OOE+OO 5.63E-04 3.83E-03 6.63E-O1 Ba-142 5.02E-O1 3.66E-04 2.84E-02 O.OOE+OO 2.96E-04 2.15E-04 6.63E-03 La-140 5.87E-02 2.05E-02 6.92E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.72E+02 La- 1 42 3 .05E-03 9.7 1 E-04 3 .04E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1 .92E+02 Ce-141 2.31E-O1 1.15E-O1 1.71E-02 O.OOE+OO 5.05E-02 O.OOE+OO 1.44E+02 Ce-143 4.06E-02 2.20E+O1 3.19E-03 O.OOE+OO 9.24E-03 O.OOE+OO 3.23E+02 Ce-144 1.21E+O1 3.79E+OO 6.45E-O1 O.OOE+OO 2.IOE+OO O.OOE+OO 9.88E+02 Pr-143 2.28E-O1 6.86E-02 113E-02 O.OOE+OO 3.72E-02 O.OOE+OO 2.47E+02 Pr-144 7.50E-04 2.32E-04 3.77E-05 O.OOE+OO 1.23E-04 O.OOE+OO 4.99E-O1 Nd- 1 47 1 .62E-O 1 1 .3 1E-O 1 1 .02E-02 O.OOE+OO 7.2 1 E-02 O.OOE+OO ZO8E+02 W-187 2.49E+OO 1.48E+OO 6.63E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 2.08E+02 Np-239 3.05E-02 2.19E-03 1.54E-03 O.OOE+OO 6.34E-03 O.OOE+OO 1.62E+02 Notes:

1) Units are mrem/hr per tCi/mI.

CY-BY-J 70-301 Revision 14 Page 80 of 188 Table 3-4 Site Specific Potable Water Dose Factors for Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 6.62E-O1 6.62E-O1 6.62E-O1 6.62E-O1 6.62E-O1 6.62E-O1 Na-24 3 .8OE+O 1 3 .20E+O 1 3 .80E+O 1 3.80E+O 1 3 .$OE+O1 3.80E+O1 3.80E+O1 Cr-51 O.OOE+OO O.OOE+OO 5.30E-02 3.46E-02 7.56E-03 6.73E-02 1.55E+OO Mn-54 O.OOE+OO 7.49E+O1 1.70E+O1 O.OOE+OO 1.66E+O1 O.OOE+OO 2.75E+O1 Mn-56 O.OOE+OO 3.08E+OO 5.30E-O1 O.OOE+OO 2.64E+OO O.OOE+OO 2.80E+02 fe-55 5.23E+O1 3.38E+O1 9.03E+OO O.OOE+ OMOE+OO 1.65E+O1 4.29E+OO Fe-59 1 16E+02

. 2.02E+02 7.9$E+O 1 O.OOE+ O.OOE+OO 5.98E+O 1 9.67E+O 1 Co-58 O.OOE+OO 1.35E+O1 3.38E+O1 O.OOE+ O.OOE+OO O.OOE+OO 3.37E+O1 Co-60 O.OOE+OO 4.06E+O 1 9.59E+O 1 O.OOE+ O.OOE+OO O.OOE+OO 9.67E+O1 Ni-63 2.39E+03 1.47E+02 8.2$E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 7.34E+OO Ni-65 1.77E+O1 2.OOE+OO 9.1OE-O1 O.OOE+OO O.OOE+OO O.OOE+OO 1.52E+02 Cu-64 O.OOE+OO 2.29E+OO 1.06E+OO O.OOE+OO 3.87E+OO OMOE+OO 4.70E+O1 Zn-65 6.92E+O1 2.37E+02 1.09E+02 O.OOE+ 1.15E+02 O.OOE+OO 2.O1E+02 Zn-69 3.51E-O1 6.32E-O1 4.70E-02 O.OOE+ 2.63E-O1 O.OOE+O 5.15E+O1 Br-$3 O.OOE+OO O.OOE+OO 1.37E+OO O.OOE+ O.OOE+OO O.OOE+O O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 1.44E+OO O.OOE+ O.OOE+OO O.OOE+O O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 7.30E-02 O.OOE+OO O.OOE+OO O.OOE+O O.OOE+OO Rb-86 O.OOE+OO 6.40E+02 3.16E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.64E+O1 Rb-88 O.OOE+OO 1.87E+OO l.03E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.82E+OO Rb-89 O.OOE+OO 1.08E+OO 7.41E-O1 O.OOE+O O.OOE+OO O.OOE+ 3.66E-O1 Sr-89 9.44E+03 O.OOE+OO 2.71E+02 OMOE+ O.OOE+OO O.OOE+ 1.94E--O2 Sr-90 1.06E+05 O.OOE+OO 2.16E+03 O.OOE+ O.OOE+OO O.OOE+ 8.69E+02 Sr-91 1.88E+02 O.OOE+OO 6.81E+OO O.OOE+ O.OOE+OO O.OOE+ 2.23E+02 Sr-92 7.22E+O1 O.OOE+OO 2.68E+OO O.OOE+ O.OOE+OO O.OOE+ 779E-r02 Y-90 3.27E-O1 O.OOE+OO $.77E-03 O.OOE+OO OMOE+OO O.OOE+OO 4.51E+02 Y-91M 3.05E-03 O.OOE+OO 1.04E-04 O.OOE+O O.OOE+OO O.OOE+OO 1.02E+O1 Y-91 4.25E+OO O.OOE+OO 1.13E-O1 OOOE+O O.OOE+OO O.OOE+OO 3.05E+02 Y-92 2.8$E-02 O.OOE+OO 8.09E-04 O.OOE+O O.OOE+OO O.OOE+OO 5.49E+02 Y-93 9.14E-02 O.OOE+OO 2.49E-03 O.OOE+ O.OOE+OO O.OOE+ 7.22E+02 Zr-95 7.75E-O1 1.89E-O1 1.34E-O1 0.0 2.04E-O1 O.OOE+ 9.41E+O1 Zr-97 5.57E-02 9.56E-03 4.36E-03 0.0 9.63E-03 O.OOE+ 6.09E+02 Nb-95 I .58E-O1 6.5 1E-02 3.76E-02 0. 4.66E-02 O.OOE+ 5.49E+O1 Nb-97 1.73E-O 3.69E-04 1.33E-04 O.OOE+O 2.$8E-04 O.OOE+OO 1.16E+02 Mo-99 O.OOE+O 1.28E+02 2.49E+O1 O.OOE+O 1.91E+02 O.OOE+OO 4.21E+O1 Ic- 99M 7.22E-O 1.49E-02 1.92E-O1 O.OOE+O 1.60E-O1 7.79E-03 4.33E+OO Tc-1O1 8.54E-O 1.O$E-02 1.06E-O1 O.OOE+O 1.28E-O1 5.87E-03 1.83E+OO Ru-103 5.57E+ O.OOE+OO 1.$6E+OO O.OOE+O 1.16E+O1 O.OOE+OO 6.77E+O1 Ru-105 5.12E- O.OOE+OO 1.72E-O1 O.OOE+O 3.76E+OO O.OOE+OO 2.04E+02 Ru-106 9.07E+ O.OOE+OO 1.13E+O1 O.OOE+O 1.07E+02 O.OOE+OO 6.88E+02 Ag-i 1OM 3.75E+OO 2.73E+OO i.21E+OO O.OOEmO 3.91E+OO O.OOE+OO 1.42E+02 Sb-124 8.06E+Oi i.i9E+OO 2.50E+Oi 2.i4E-Oi O.OOE+OO 5.05E+Oi 2.49E+02 Sb-125 4.63E+Oi 4.48E-O1 9.53E+OO 5.80E-02 O.OOE+OO 2.68E+Oi 6. 8E+Oi Te-i25M 8.77E+Oi 2.93E+Oi i.i9E+Oi 2.95E+O1 O.OOE+OO O.OOE+OO 4. 8E+O1 Sb-i26 3.04E+Oi 5.95E-O1 i.iOE+Oi 2.33E-Oi O.OOE+OO i.9iE+Oi 3. 5E+02

CY-BY-1 70-301 Revision 14 I Page8l of 188 Table 3-4 (continued)

Site Specific Potable Water Dose Factors for Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te- 1 27M 2.20E+02 7.30E+O 1 2.66E+O 1 6.36E+O 1 5 .42E+02 O.OOE+OO 8.88E+O 1 Te-127 3.76E+OO 1.26E+OO 8.09E-O1 3.06E+OO 9.18E+OO O.OOE+OO 7.90E+O1 Te-129M 3.76E+02 1.29E+02 5.79E+O1 1.44E+02 9.41E+02 O.OOE+OO 2.25E+02 Te-129 1.07E+OO 3.68E-O1 2.49E-O1 8.95E-O1 2.66E+OO O.OOE+OO 8.54E+O1 Te-13 1M 5.72E+O1 2.30E+O1 1 .90E+O1 4.66E+O1 1 .58E+02 O.OOE+OO 3.87E+02 Te-131 6.62E-O1 2.45E-O1 1.$6E-O1 5.91E-O1 1.69E+OO O.OOE+OO 2.67E+O1 Te- 1 32 7.82E+O 1 3 .87E+O 1 3 .62E+O 1 5 .72E+O 1 2.42E+02 O.OOE+OO 1 .43E+02 I- 1 30 2.26E+O 1 4.97E+O 1 1 .99E+O 1 5 .57E+03 5.45E+O 1 O.OOE+OO 1 .06E+O 1 I- 1 3 1 1 .35E+02 1 .59E+02 7.OOE+O 1 5.23E+04 1 .$6E+02 O.OOE+OO 5.68E+OO 1-132 6.24E+OO 1.27E+O1 4.51E+OO 5.94E+02 1.41E+O1 O.OOE+OO 1.03E+O1 I- 1 33 4.70E+O I 6.85E+O 1 2.0 1E+O 1 1 .25E+04 8.05E+O 1 O.OOE+OO 1 1 6E+O 1 1-134 3.27E+OO 6.70E+OO 2.38E+OO 1.56E+02 7.49E+OO O.OOE+OO 6.92E+OO I- 1 35 1 .37E+O 1 2.72E+O 1 9.93E+OO 2.44E+03 3 .04E+O 1 O.OOE+OO 9.86E+OO Cs-134 1.42E+03 2.64E+03 2.67E+02 O.OOE+OO 6.$1E+02 2.79E+02 7.19E+OO Cs-136 1.73E+02 5.08E+02 1.90E+02 O.OOE+OO 2.02E+02 4.14E+O1 7.71E+OO Cs-137 1.96E+03 2.30E+03 1.63E+02 O.OOE+OO 6.17E+02 2.50E+02 7.19E+OO Cs-138 1.81E+OO 2.94E+OO 1.43E+OO O.OOE+OO 1.47E+OO 2.29E-O1 4.70E+OO Ba- 1 39 3 .3 1 E+OO 2.20E-03 9.59E-02 O.OOE+OO 1 .32E-03 1 .33E-03 2. 1 OE+02 Ba- 1 40 6.43E+02 6.43E-O 1 3 .3 1 E+O 1 O.OOE+OO 1 .53E-O 1 3 .95E-O 1 1 .58E+02 Ba-141 1.60E+OO 1.09E-03 5.04E-02 O.OOE+OO 6.58E-04 6.66E-04 1.95E+O1 Ba- 1 42 6.92E-O 1 5 .76E-04 3 .4 1 E-02 O.OOE+OO 3 .3 1 E-04 3 .48E-04 2.86E+OO La-140 7.94E-02 3.13E-02 8.05E-03 O.OOE+OO O.OOE+OO O.OOE+OO 3.68E+02 La-142 4.14E-03 1.52E-03 3.64E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.52E+02 Ce- 1 4 1 2.96E-O 1 1 .8 1 E-O 1 2. 1 3E-02 O.OOE+OO 5 .57E-02 O.OOE+OO 9.33E+O 1 Ce-143 5.57E-02 3.69E+O1 4.21E-03 O.OOE+OO 1.08E-02 O.OOE+OO 2.16E+02 Ce-144 1.12E+O1 4.59E+OO 6.28E-O1 O.OOE+OO 1.85E+OO O.OOE+OO 6.43E+02 Pr-143 3.06E-O1 1.14E-O1 1.52E-02 O.OOE+OO 4.25E-02 O.OOE+OO 1.61E+02 Pr-144 1.03E-03 3.99E-04 5.19E-05 O.OOE+OO 1.44E-04 O.OOE+OO 1.85E+O1 Nd-147 2.08E-O1 2. 14E-O1 1 .3 1E-02 O.OOE+OO 8.24E-02 O.OOE+OO 1 .35E+02 W-187 3.40E+OO 2.36E+OO 8.16E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+02 Np-239 4.18E-02 3.74E-03 2.1 1E-03 O.OOE+OO 7.45E-03 O.OOE+OO 1.08E+02 Notes:

I) Units are mrem/hr per pCi/mi.

CY-BY-1 70-301 Revision 14 Page 82 of 188 Table 3-5 Site Specific Fish Ingestion Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 1.29E-O1 1.29E-O1 1.29E-O1 1.29E-O1 1.29E-O1 1.29E-O1 Na-24 4.07E+02 4.O7ELO2 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 Cr-5 1 O.OOE+OO O.OOE+OO 1 .27E+OO 7.61E-O1 2.8 1E-Ol 1 .69E+OO 3.20E+02 Mn-54 O.OOE+OO 4.38E+03 8.35E+02 O.OOE+ 1.30E+03 O.OOE+ 1.34E+04 Mn-56 O.OOE+OO 1.1OE+02 1.95E+O1 O.OOE+ 1.40E+02 O.OOE+ 3.51E+03 fe-55 6.58E+02 4.55E+02 1.06E+02 O.OOE+ O.OOE+OO 2.54E+ 2 2.61E-r02 Fe-59 1 .04E+03 2.44E+03 9.36E+02 O.OOE+OO O.OOE+OO 6.82E+ 8.14E+03 Co-58 O.OOE+OO 2.92E+O1 2.OOE+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.81E+03 Co-60 O.OOE+OO 2.56E+02 5.65E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.81E+03 Ni-63 3.1 1E+04 2.16E+03 1.04E+03 O.OOE+ O.OOE+OO O.OOE+OO 4.50E+02 Ni-65 L26E+02 1.64E+O1 7.49E+OO O.OOE+ O.OOE+OO O.OOE+ 4J7E+02 Cu-64 O.OOE+OO 9.97E+OO 4.68E+OO O.OOE+ 2.51E+O1 O.OOE+ 8.50E+02 Zn-65 2.32E+04 7.37E+04 3.33E+04 O.OOE+ 4.93EmO4 O.OOE+ 4.64E+04 Zn-69 4.93E+O1 9.43E+O1 6.56E+OO O.OOE+ 6.13E+O1 O.OOE+OO 1.42EmO1 Br-83 O.OOE+OO O.OOE+OO 4.04E+O1 O.OOE+O O.OOE+OO O.OOE+OO 5.82E+O1 Br-84 O.OOE+OO O.OOE+OO 5.24E+O1 O.OOE+O OMOE+OO O.OOE+OO 4.11E-04 Br-85 O.OOE--OO O.OOE+OO 2.15E+OO O.OOE+ O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.O1E+05 4.71E+04 O.OOE-- O.OOE+OO O.OOE+ 1.99E+04 Rb-88 O.OOE+OO 2.90E+02 1.54E+02 O.OOE+ O.OOE+O O.OOE+ 4.OOE-09 Rb-89 O.OOE+OO 1.92E+02 1.35E+02 O.OOE+ O.OOE+O O.OOE+ 1.12E-11 Sr-89 2.21E+04 O.OOE+OO 6.35E+02 O.OOE+ O.OOE+O O.OOE-r 3.55E+03 Sr-90 6.26E+05 O.OOE+OO 1.26E+04 O.OOE+O O.OOE+OO O.OOE+OO 1.57E+04 Sr-91 4.07E+02 O.OOE+OO 1.64E+O1 O.OOE+O O.OOE+OO O.OOE+OO 1.94E+03 Sr-92 1.54E+02 O.OOE+OO 6.68E+OO O.OOE+O O.OOE+OO O.OOE+OO 3.06E+03 Y-90 5.76E-O1 O.OOE+OO 1.54E-02 O.OOE+O O.OOE+OO O.OOE+OO 6.1OE+03 Y-91M 5.44E- O.OOE+OO 2.11E-04 O.OOE+ O.OOE+O O.OOE+ 1.60E-02 Y-91 $.44E+ O.OOE+OO 2.26E-O1 O.OOE+ O.OOE+O O.OOE+ 4.64E+03 Y-92 5.06E- O.OOE+OO 1.4$E-03 O.OOE+ O.OOE+O O.OOE+ 8.86E+02 Y-93 1.60E- O.OOE-rOO 4.43E-03 O.OOE+O O.OOEmO O.OOE+ 5.09E+03 Zr-95 2.40E-O 7.70E-02 5.21E-02 O.OOE+OO 1.21E-O1 O.OOE+ 2.44E+02 Zr-97 1.33E-02 2.68E-03 1.22E-03 O.OOE+OO 4.04E-03 O.OOE+OO 8.30E+02 Nb-95 4.47E+02 2.4$E+02 1 .34E+02 O.OOE+OO 2.46E+02 O.OOE+OO 1 .5 1E+06 Nb-97 3.75E+OO 9.49E-O1 347E-O O.OOE+OO 1.11E+OO O.OOE+OO 3.50E+03 Mo-99 O.OOE+ 1.03E+02 1.96E+ O.OOE+OO 2.34E+02 O.OOE+ 2.39E+02 Tc- 99M 8.87E- 2.51E-02 3.19E- O.OOE+OO 3.$1E-O1 1.23E- 1.48E+O1 Tc-1O1 9.12E-03 1.31E-02 1.29E- O.OOE+OO 2.37E-O1 6.72E- 3.95E-14 Ru-103 4.43E+OO O.OOE+OO 1.91E+OO O.OOE+OO 1.69E+O1 O.OOE+ 5.17E+02 Ru-105 3.69E-O1 O.OOE+OO 1.46E-O1 O.OOE+OO 4.76E+OO O.OOE+OO 2.26E+02 Ru-106 6.58E+O1 O.OOE+OO 8.33E+OO O.OOE+OO 1.27E+02 O.OOE+OO 4.26E+03 Ag-11OM 8.81E-O1 $.15E-O1 4.84E-O1 O.OOE+OO 1.60E+OO O.OOE+OO 3.33E+02 Sb-124 6.71E+OO 1.27E-O1 2.66E+OO 1.63E-02 O.OOE+OO 5.23E+OO 1.91E+02 Sb-125 4.29E+OO 4.$OE-02 1.02E+OO 4.36E-03 O.OOE+OO 3.31E+OO 4.72E+O1 Te-125M 2.57E+03 9.30E+02 3.44E+02 7.72E+02 1.04E+04 O.OOE+OO 1.02E+04 Sb-126 2.76E+OO 5.61E-02 9.95E-O1 1.69E-02 O.OOE+OO 1.69E+OO 2.25E+02

CY-BY-1 70-301 Revision 14 1 Page 83 of 188 Table 3-5 (continued)

Site Specific Fish Ingestion Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-127M 6.48E+03 2.32E+03 7.90E+02 1.66E+03 2.63E+04 O.OOE+OO 2.17E+04 Te-127 .05E+02 3.78E+O1 2.28E+O1 7.80E+O1 4.29E+02 O.OOE+OO 8.3 1E+03 Te- 1 29M . 1 OE+04 4. 1 1 E+03 1 .74E+03 3 .78E+03 4.60E+04 O.OOE+OO 5 .54E+04 Te-129 3.O1E+O1 1.13E+O1 7.33E+OO 2.31E+O1 1.26E+02 O.OOE+OO 2.27E+O1 Te-131M .66E+03 8.1OE+02 6.75E+02 1.28E+03 8.21E+03 O.OOE+OO 8.04E+04 Te-131 .89E+O1 7.88E+OO 5.96E+OO 1.55E+O1 8.26E+O1 O.OOE+OO 2.67E+OO Te- 1 32 2.4 1 E+03 1 .56E+03 1 .47E+03 1 .72E+03 1 .50E+04 O.OOE+OO 7.3 8E+04 I- 1 30 2.7 1 E+O 1 8.0 1 E+O 1 3 1 6E+O 1

. 6.79E+03 1 .25E+02 O.OOE+OO 6.89E+O 1 1-131 1.49E+02 2.14E+02 1.22E+02 7.OOE+04 3.66E+02 O.OOE+OO 5.64E+O1 I- 1 32 7.29E+OO 1 .95E+O 1 6.82E+OO 6.82E+02 3 1 1 E+O 1

. O.OOE+OO 3 .66E+OO I- 1 33 5 1 OE+O 1

. 8.87E+O 1 2.70E+O 1 1 .30E+04 1 .55E+02 O.OOE+OO 7.97E+O 1 1-134 3.$1E+OO 1.03E+O1 3.70E+OO 1.79E+02 1.64E+O1 O.OOE+OO 9.O1E-03 I- 1 35 1 .59E+O 1 4. 1 7E+O 1 1 .54E+O 1 2.75E+03 6.6$E+O 1 O.OOE+OO 4.70E+O 1 Cs-134 2.98E+05 7.09E+05 5.79E+05 O.OOE+OO 2.29E+05 7.61E+04 1.24E+04 Cs- 1 36 3 1 2E+04

. 1 .23E+05 8.86E+04 O.OOE+OO 6.85E+04 9.3 8E+03 1 .40E+04 Cs-137 3.82E+05 5.22E+05 3.42E+05 O.OOE+OO 1.77E+05 5.$9E+04 1.O1E+04 Cs-138 2.64E+02 5.22E+02 2.59E+02 O.OOE+OO 3.$4E+02 3.79E+O1 2.23E-03 Ba-139 9.29E-O1 6.62E-04 2.72E-02 O.OOE+OO 6.19E-04 3.75E-04 1.65E+OO Ba-140 1 .94E+02 2.44E-O1 1 .27E+O1 O.OOE+OO 8.30E-02 1 .40E-O1 4.OOE+02 Ba-141 4.51E-O1 3.41E-04 1.52E-02 O.OOE+OO 3.17E-04 1.93E-04 2.13E-1O Ba-142 2.04E-O1 2.1OE-04 1.28E-02 O.OOE+OO 1.77E-04 1.19E-04 2.87E-19 La-140 1.50E-O1 7.54E-02 1.99E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.54E+03 La-142 7.66E-03 3.48E-03 8.68E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.54E+O1 Ce-141 2.24E-02 1.52E-02 1.72E-03 O.OOE+OO 7.04E-03 O.OOE+OO 5.79E+O1 Ce-143 3.95E-03 2.92E+OO 3.23E-04 O.OOE+OO 1.29E-03 O.OOE+OO 1.09E+02 Ce-144 1.17E+OO 4.88E-O1 6.27E-02 O.OOE+OO 2.90E-O1 O.OOE+OO 3.95E+02 Pr- 1 43 5 .5 1 E-O 1 2.2 1 E-O 1 2.73E-02 O.OOE+OO 1 .27E-O 1 O.OOE+OO 2.4 1 E+03 Pr-144 1.80E-03 7.48E-04 9.16E-05 O.OOE+OO 4.22E-04 O.OOE+OO 2.59E-1O Nd-147 3.76E-O1 4.35E-O1 2.60E-02 O.OOE+OO 2.54E-O1 O.OOE+OO 2.09E+03 W-187 2.96E+02 2.47E+02 8.65E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 8.1OE+04 Np-239 2.85E-02 2.80E-03 1.54E-03 O.OOE+OO 8.74E-03 O.OOE+OO 5.75E+02 Notes:

1) Units are mrem/hr per iCi/mI.

CY-BY-1 70-301 Revision 14 Page 84 of 188 Table 3-6 Site Specific Fish Ingestion Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-O 9.92E-02 Na-24 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+O 4.20E+02 Cr-5 1 O.OOE+OO O.OOE+OO 1 .3 1E+OO 7.30E-O 1 2.88E-O1 1 .88E+OO 2.2 1E+02 Mn-54 O.OOE+OO 4.30E+03 8.54E+02 O.OOE+OO 1.2$E+03 O.OOE+OO 8.83E+03 Mri-56 O.OOE+OO 1.15E+02 2.05E+O1 O.OOE+OO 1.46E+02 O.OOE+OO 7.59E+03 Fe-55 6.$9E+02 4.89E+02 1.14E+02 O.OOE+OO O.OOE+OO 3.1OE+02 2.12E+02 Fe-59 1 .07E+03 2.50E+03 9.65E+02 O.OOE+O O.OOE+OO 7.8$E+O 5.91E--03 Co-58 O.OOE+OO 8.86E+O1 2.04E+02 O.OOE+O O.OOE+OO O.OOE+O 1.22E+03 Co-60 O.OOE+OO 2.56E-r02 5.77E+02 O.OOE+O O.OOE+OO O.OOE+O 3.34E+03 Ni-63 3.23E+04 2.28E+03 1.09E+03 O.OOE+O O.OOE+OO O.OOE+O 3.63E+02 Ni-65 1.37E+02 1.75E+O1 7.95E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.47E+02 Cu-64 O.OOE+OO 1.05E+O1 4.93E+OO O.OOE+OO 2.65E+O1 O.OOE+OO 8.14E+02 Zn-65 2.1OE+04 7.30E+04 3.40E+04 O.OOE+OO 4.67E+04 O.OOE+OO 3.09E+04 Zn-69 5.36E+O1 1.02E+02 7.15E+OO O.OOE+O 6.68E+O1 O.OOE+ 1.88E+02 Br-83 O.OOE+OO O.OOE+ 4.40E+O1 O.OOE+O O.OOE+OO O.OOE+ O.OOE+OO Br-$4 O.OOE+OO O.OOE+ 5.53E+O1 O.OOE+O O.OOE+OO O.OOE+ O.OOE+OO Br-85 O.OOE+OO O.OOEm 2.34E+OO O.OOE+O O.OOE+OO OMOE+ O.OOE+OO Rb-$6 O.OOE+OO 1.09E+05 5.1 1E+04 O.OOE+O O.OOE+OO O.OOE+O 1.61E+04 Rb-88 O.OOE+OO 3.11E+02 1.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.66E-05 Rb-89 O.OOE+OO 2.O1E+02 1.42E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.O8E-07 Sr-$9 2.41E+04 O.OOE+OO 6.89E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+03 r-90 5.58E+05 O.OOE+ 1.12E+04 O.OOE+O O.OOE+OO O.OOE+ 1.27E+04 r-91 4.42E+02 O.OOE+ 1.76E+O1 O.OOE+ O.OOE+ O.OOE+ 2.OOE+

r-92 1.67E+02 O.OOE+ 7.11E+OO O.OOE+ O.OOE+ O.OOE+ 4.25E+

Y-90 6.25E-O1 O.OOE+OO 1.6$E-02 OOOE+ O.OOE+ O.OOE+ 5.15E+

Y-91M 5.88E-03 O.OOE+OO 2.25E-04 O.OOE+ OMOE+ O.OOE+ 2.78E-O1 Y-91 9.17E+OO O.OOE+OO 2.46E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 3.76E+03 Y-92 5.52E-02 O.OOE+OO 1.60E-03 O.OOE+OO OMOE+OO O.OOE+OO 1.51E+03 Y-93 1.75E-O1 O.OOE+OO 4.79E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.34E+03 Zr-95 2.42E-O1 7.82E-02 5.38E-02 O.OOE+ 1.15E- O.OOE+ 1.81E+02 Zr-97 1.43E-02 2.82E-03 1.30E-03 O.OOE+ 4.28E- 3 O.OOE+ 7.64E+02 Nb-95 4.50E+02 2.50E+02 1.37E+02 O.OOE+ 242E+ O.OOE+ 1.07E+06 Nb-97 4.04E+OO 1.OOE+OO 3.66E-O1 O.OOE+ 1.17E+ O.OOE+ 2.40E+04 Mo-99 O.OOE+OO 1.1OE+02 2.1OE+O1 O.OOE+OO 2.52E+ O.OOE+OO 1.97E+02 Te- 99M 9.02E-03 2.53E-02 3.28E-O1 O.OOE+OO 3.78E-O 1.41E- 1.66E+O1 Tc-1O1 9.85E-03 1AOE-02 1.38E-O1 O.OOE+OO 2.53E-O 8.54E-03 2.39E-09 Ru-103 4.65E+OO O.OOE+OO 1.99E+OO O.OOE+OO 1.64E+O1 O.OOE+OO 3.29E+02 Ru-105 398E-O1 O.OOE+OO 1.54E-O1 O.OOE+OO 5.02E+O O.OOE+OO 3.21E+02 Ru-106 7.15E+O1 O.OOE+OO 9.O1E+OO O.OOE+OO 1.32E+ O.OOE+ 343ELO3 Ag-11OM 8.60E-O1 $.14E-O1 4.95E-O1 O.OOE+OO 1.55E+ O.OOE+ 2.29E+02 Sb-124 7.07E+OO 1.30E-O1 2.76E+OO 1.60E-02 O.OOE+ 6.17E+ 1.43E+02 Sb-125 4.53E+OO 4.95E-02 1.06E+OO 4.33E-03 O.OOE+OO 3.9$E+OO 3.53E+O1 Te-125M 2.79E+03 1.O1E+03 3.74E+02 7.81E+02 O.OOE+OO O.OOE+OO $.24E+03 Sb-126 2.90E+OO 5.94E-02 1.04E+OO 1.64E-02 O.OOE+OO 2.08E+OO 1.72E+02

CY-BY-1 70-301 Revision 14 I Page 85 of 188 Table 3-6 (continued)

Site Specific Fish Ingestion Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te- 1 27M 7.06E+03 2.50E+03 $.39E+02 1 .68E+03 2.86E+04 O.OOE+OO 1 .76E+04 Te-127 1.15E+02 4.09E+O1 2.48E+O1 7.95E+O1 4.67E+02 O.OOE+OO $.90E+03 Te-129M 1.19E+04 4.41E+03 1.$8E+03 3.84E+03 4.98E+04 O.OOE+OO 4.47E+04 Te-129 3.27E+O1 1.22E+O1 7.95E+OO 2.33E+O1 1.37E+02 O.OOE+OO 1.79E+02 Te-131M 1.78E+03 8.54E+02 7.12E+02 1.28E+03 8.90E+03 O.OOE+OO 6.$5E+04 Te-131 2.04E+O1 8.39E+OO 6.36E+OO 1.57E+O1 8.90E+O1 O.OOE+OO 1.67E+OO Te-132 2.55E+03 1 .61E+03 1 .52E+03 1 .70E+03 1 .55E+04 O.OOE+OO 5. 1 1E+04 1-130 2.82E+O1 8.15E+O1 3.26E+O1 6.65E+03 1.26E+02 O.OOE+OO 6.27E+O1 1-131 1.60E+02 2.24E+02 1.20E+02 6.54E+04 3.86E+02 O.OOE+OO 4.43E+O1 1-132 7.63E+OO 2.OOE+O1 7.17E+OO 6.73E+02 3.15E+O1 O.OOE+OO 8.70E+OO I- 1 33 5 .50E+O 1 9.33E+O 1 2.85E+O 1 1 .30E+04 1 .64E+02 O.OOE+OO 7.06E+O 1 1-134 3.99E+OO 1.06E+O1 3.80E+OO 1.76E+02 1.67E+O1 O.OOE+OO 1.40E-O1 I- 1 35 1 .67E+O 1 4.30E+O 1 1 .59E+O 1 2.76E+03 6.79E+O 1 O.OOE+OO 4.76E+O 1 Cs- 1 34 3 .05E+05 7. 1 9E+05 3 .33E+05 O.OOE+OO 2.28E+05 8.72E+04 8.94E+03 Cs-136 3.13E+04 1.23E+05 8.28E+04 O.OOE+OO 6.71E+04 1.06E+04 9.92E+03 Cs-137 4.09E+05 5.44E+05 1.89E+05 O.OOE+OO 1.85E+05 7.19E+04 7.73E+03 Cs-138 2.83E+02 5.44E+02 2.72E+02 O.OOE+OO 4.O1E+02 4.67E+O1 2A7E-O1 Ba- 1 39 1 .0 1 E+OO 7. 1 4E-04 2.95E-02 O.OOE+OO 6.73E-04 4.92E-04 9.05E+OO Ba- 1 40 2.07E+02 2.54E-O 1 1 .34E+O 1 O.OOE+OO 8.6 1 E-02 1 .7 1 E-O 1 3 .20E+02 Ba- 1 4 1 4.90E-O 1 3 .66E-04 1 .63E-02 O.OOE+OO 3 .39E-04 2.50E-04 1 .04E-06 Ba- 1 42 2. 1 8E-O 1 2. 1 8E-04 1 .34E-02 O.OOE+OO 1 .85E-04 1 .45E-04 6.70E-13 La-140 1.59E-O1 7.80E-02 2.07E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.48E+03 La-142 8.16E-03 3.63E-03 9.03E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.1OE+02 Ce-141 2.43E-02 1.62E-02 1.86E-03 O.OOE+OO 7.62E-03 O.OOE+OO 4.63E+O1 Ce-143 4.29E-03 3.12E+OO 3.48E-04 O.OOE+OO 1.40E-03 O.OOE+OO 9.38E+O1 Ce-144 1.27E+OO 5.25E-O1 6.82E-02 O.OOE+OO 3.14E-O1 O.OOE+OO 3.19E+02 Pr- 1 43 5 .97E-O 1 2.3 8E-O 1 2.97E-02 O.OOE+OO 1 .39E-O 1 O.OOE+OO 1 .97E+03 Pr-144 1.96E-03 8.03E-04 9.94E-05 O.OOE+OO 4.61E-04 O.OOE+OO 2.16E-06 Nd-147 4.28E-O1 4.65E-O1 2.79E-02 O.OOE+OO 2.73E-O1 O.OOE+OO 1.68E+03 W-187 3.20E+02 2.60E+02 9.13E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 7.05E+04 Np-239 3.21E-02 3.03E-03 1.68E-03 O.OOE+OO 9.50E-03 O.OOE+OO 4.87E+02 Notes:

1) Units are mrem/hr per pCi/mi.

CY-BY-1 70-301 Revision 14 Page 86 of 188 Table 3-7 Site Specific Fish Ingestion Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 8.21E-02 8.21E-02 $.21E-02 8.21E-02 2.21E-02 $.21E-02 Na-24 4.56E+02 4.56E+02 4.56E--O2 4.56E+02 4.56E+02 4.56E--O2 4.56E+02 Cr-51 O.OOE+OO O.OOE+OO 1AOE+OO 7.77E-O1 2.12E-O1 1.42E 7.43E+O1 Mn-54 O.OOE+OO 3.37E+03 8.97E+02 O.OOE+OO 9.44E+02 O.OOE 2.83E+03 Mn-56 O.OOE+OO 1.05E+02 2.37E+O1 O.OOE+OO 1.27E+02 O.OOE 1.52E+04 Fe-55 9.05E+02 4.80E+02 1.49E+02 O.OOE+OO O.OOE+OO 2.71E 02 8.89E+O1 Fe-59 1.30E+03 2.1OE+03 1.05E+03 O.OOE+OO O.OOE+OO 6M9E 102 2.19E+03 Co-58 O.OOE+OO 7.O8E+O1 2.17E+02 O.OOE+OO O.OOE+OO O.OOE 00 4.13E+02 Co-60 O.OOE+OO 2.08E+02 6.14E+02 O.OOE+OO O.OOE+OO O.OOE 1.15E+03 Ni-63 4.23E+04 2.27E+03 1.44E+03 O.OOE+ OMOE+ 0.0 1.53E+02 Ni-65 1 .75E+02 1 .64E+O 1 9.60E+OO O.OOE+ OMOE+ 0.0 2.0 1E+03 Cu-64 O.OOE+OO 9.64E+OO 5.82E+OO O.OOE-r 2.33E+ O.OOE+ 4.52E+02 Zn-65 2.16E+04 5.74E+04 3.57E+04 O.OOE+OO 3.62E+ 4 O.OOE+OO 1.O1E+04 Zn-69 6.89E+O1 9.96E+O1 9.20E+OO O.OOE+OO 6M4E+O O.OOE+O 6.22E+03 Br-$3 O.OOE+OO O.OOE+OO 5.65E+O1 O.OOE+OO O.OOE+OO O.OOE+O O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 6.54E+O1 O.OOE+ O.OOE+ O.OOE+O O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 3.O1E+OO O.OOE+ O.OOE+ O.OOE+ O.OOE+OO Rb-$6 O.OOE+OO 1.05E+05 6.48E+04 O.OOE+ O.OOE+ O.OOE+ 6.78E+03 Rb-88 O.OOE+OO 2.99E+02 2.08E+02 O.OOE+ O.OOE+ O.OOE+ 1.47E+O1 Rb-$9 O.OOE+OO 1.$4E+02 1.64E+02 O.OOE+ O.OOE+ O.OOE+O 1.60E+OO Sr-89 3.11E+04 O.OOE+OO 8.90E+02 O.OOE+OO O.OOE+OO O.OOE+O 1.21E+03 Sr-90 6.04E+05 O.OOE+OO 1 .22E+04 O.OOE+OO O.OOE+O O.OOE+O 5.40E+03 Sr-91 5.66E+02 O.OOE+OO 2.14E+O1 O.OOE+OO O.OOE+OO O.OOE+O 1.25E+03 Sr-92 2.13E+02 O.OOE+OO 8.54E+OO O.OOE+OO O.OOE+ O.OOE+O 4.04E+03 Y-90 $.08E-O1 O.OOE+ 2.16E-02 O.OOE+ O.OOE+ O.OOE+ 2.30E+03 Y-91M 7.51E-03 O.OOE+ 2.73E-04 O.OOE+ O.OOE+ O.OOE+ 1.47E+O1 Y-91 1.18E+O1 O.OOE+ 3.17E-O1 O.OOE+ O.OOE+ O.OOE+ 1.52E+03 Y-92 7.08E-02 O.OOE+ 2.03E-03 O.OOE+ O.OOE+ O.OOE+O 2.05E+03 Y-93 2.24E-O1 O.OOE+OO 6.16E-03 O.OOE+OO O.OOE+OO O.OOE+OO 3.34E+03 Zr-95 3.O1E-O1 6.62E-02 5.89E-02 O.OOE+OO 9.47E-O O.OOE+OO 6.90E+O1 Zr-97 1.81E-02 2.62E-03 1.55E-03 O.OOE+OO 3.76E-O O.OOE+OO 3.97E+02 Nb-95 5.31E+02 2.07E+02 1.48E+02 O.OOE+OO 1.94E+02 O.OOE+OO 3.82E+05 Nb-97 5.13E+OO 9.26E- 4.32E-O1 O.OOE+OO 1.03E+ O.OOE+O 2.86E+05 Mo-99 O.OOE+OO 1.05E+ 2.59E+O1 O.OOE+ 2.23E+ O.OOE+O 8.65E+O1 Tc- 99M 1.09E-02 2.14E- 3.54E-O1 O.OOE+ 3.1OE- 1.08E-02 1.22E+O1 Tc-1O1 1.26E-02 1.32E- 1.68E-O1 O.OOE+OO 2.25E-O1 6.99E-03 4.20E-02 Ru-103 5.75E+OO O.OOE+OO 2.21E+OO O.OOE+OO 1.45E+O1 O.OOE+OO 1.49E+02 Ru-105 5.07E-O1 OMOE+OO 1.84E-O1 O.OOE+OO 4.46E+OO O.OOE+OO 3.31E+02 Ru-106 9.20E+O1 O.OOE+OO 1.15E+O1 O.OOE+OO 1.24E+02 O.OOE+OO .43E+03 Ag-i 1OM 9.75E-O1 6.59E-O1 5.26E-O1 O.OOE+OO 1.23E+OO O.OOE+OO 7.83E+O1 Sb-124 $.74E+OO 1.13E-O1 3.06E+OO 1.93E-02 O.OOE+OO 4.$5E+OO 5A7E+O1, Sb-125 5.64E+OO 4.35E-02 1.18E+OO 5.22E-03 O.OOE+OO 3.14E+OO 1.35E+O1 Te-125M 3.59E+03 9.72E+02 4.78E+02 1.O1E+03 O.OOE+OO O.OOE+OO 3.46E+O3.

Sb-126 3.47E+OO 5.30E-02 1.25E+OO 2.03E-02 O.OOE+OO 1.65E+OO 6.99E+O1I

CY-BY-1 70-301 Revision 14 Page 87 of 188 Table 3-7 (continued)

Site Specific Fish Ingestion Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te- 127M 9.09E+03 2.45E+03 1 .08E+03 2. 1 7E+03 2.59E+04 O.OOE+OO 7.36E+03 Te-127 1.48E+02 4.OOE+O1 3.18E+O1 1.03E+02 4.22E+02 O.OOE+OO 5.79E+03 Te- 1 29M 1 .53E+04 4.28E+03 2.3 8E+03 4.94E+03 4.50E+04 O.OOE+OO 1 .87E+04 Te- 1 29 4.22E+O 1 1 1 8E+O 1

. 1 .OOE+O 1 3 .0 1 E+O 1 1 .23E+02 O.OOE+OO 2.62E+03 Te-13 1M 2.27E+03 7.83E+02 $.34E+02 1 .61E+03 7.58E+03 O.OOE+OO 3. 1 8E+04 Te- 1 3 1 2.6 1 E+O 1 7.96E+OO 7.77E+OO 2.OOE+O 1 7.90E+O 1 O.OOE+OO 1 .3 7E+02 Te-132 3.18E+03 1.41E+03 1.70E+03 2.05E+03 1.31E+04 O.OOE+OO 1.42E+04 I- 1 30 3 .45E+O 1 6.96E+O 1 3 .59E+O 1 7.67E+03 1 .04E+02 O.OOE+OO 3 .26E+O 1 1-131 2.03E+02 2.04E+02 1.16E+02 6.75E+04 3.35E+02 O.OOE+OO 1.82E+O1 1-132 9.44E+OO 1.73E+O1 7.98E+OO $.05E+02 2.65E+O1 O.OOE+OO 2.04E+O1 1-133 6.99E+O1 8.64E+O1 3.27E+O1 1.60E+04 1A4E+02 O.OOE+OO 3.48E+O1 1-134 4.94E+OO 9.18E+OO 4.22E+OO 2.1 1E+02 1.40E+O1 O.OOE+OO 6.09E+OO I- 1 35 2.06E+O 1 3 .72E+O 1 1 .76E+O 1 3 .29E+03 5 .70E+O 1 O.OOE+OO 2.83E+O 1 Cs-134 3.68E+05 6.04E+05 1.27E+05 O.OOE+OO 1.87E+05 6.72E+04 3.26E+03 Cs- 1 36 3 .70E+04 1 .02E+05 6.5 8E+04 O.OOE+OO 5 .4 1 E+04 8.07E+03 3 .57E+03 Cs-137 5.14E+05 4.92E+05 7.27E+04 O.OOE+OO 1.60E+05 5.77E+04 3.08E+03 Cs-138 3.59E+02 4.99E+02 3.16E+02 O.OOE+OO 3.51E+02 3.78E+O1 2.30E+02 Ba- 1 39 1 .30E+OO 6.95E-04 3 .78E-02 O.OOE+OO 6.07E-04 4.09E-04 7.52E+O 1 Ba-140 2.61E+02 2.29E-O1 1 .53E+O1 O.OOE+OO 7.46E-02 1 .37E-O1 1 .32E+02 Ba-141 6.29E-O1 3.52E-04 2.05E-02 O.OOE+OO 3.05E-04 2.07E-03 3.59E-O1 Ba-142 2.75E-O1 1.98E-04 1.54E-02 O.OOE+OO 1.60E-04 1.16E-04 3.59E-03 La-140 1 .99E-O1 6.94E-02 2.34E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1 .94E+03 La-142 1.03E-02 3.28E-03 1.03E-03 O.OOE+OO O.OOE+OO O.OOE+OO 6.51E+02 Ce- 1 4 1 3 1 2E-02

. 1 .56E-02 2.3 1 E-03 O.OOE+OO 6.83E-03 O.OOE+OO 1 .94E+O 1 Ce-143 5.50E-03 2.98E+OO 4.32E-04 O.OOE+OO 1.25E-03 O.OOE+OO 4.37E+O1 Ce-144 1.64E+OO 5.13E-O1 8.73E-02 O.OOE+OO 2.84E-O1 O.OOE+OO 1.34E+02 Pr-143 7.73E-O1 2.32E-O1 3.$3E-02 O.OOE+OO 1.26E-O1 O.OOE+OO 8.34E+02 Pr-144 2.54E-03 7.85E-04 1.2$E-04 O.OOE+OO 4.15E-04 O.OOE+OO 1.69E+OO Nd-147 5.49E-O1 4.44E-O1 3.44E-02 O.OOE+OO 2.44E-O1 O.OOE+OO 7.04E+02 W-187 4.05E+02 2.40E+02 1.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.37E+04 Np-239 4.13E-02 2.97E-03 2.O$E-03 O.OOE+OO $.57E-03 O.OOE+OO 2.19E+02 Notes:

1) Units are mrem/hr per iCi/mI.

2) The infant age group is assumed to receive no dose through the fish ingestion pathway; therefore, no dose factors are supplied.

CY-BY-1 70-301 Revision 14 I Page 88 of 188 Table 3-8 Bioaccumulation Factors (BF) to be Used in the Absence of Site-Specific Data BE1 for Freshwater Fish Element .

• Reference (pCi/kg_per_pCi/L)

H 9.OE-O1 6 Be 2.8E+O1 Footnote 2 C 4.6E+03 6 F 2.2E+02 Footnote 16 Na 1.OE+02 6 Mg 2.8E+O1 Footnote 2 Al 2.2E+03 Footnote I 3 P 1.OE+05 6 Cl 2.2E+02 Footnote 16 Ar NA NA K 1 .OE+03 Footnote 1 Ca 2.8E+O1 Footnote 2 Sc 2.5E+O1 Footnote 3 Ti 33E+OO Footnote 4 V 3.OE+04 Footnote 5 Cr 2.OE+02 6 Mn 4.OE+02 6 Fe 1.OE+02 6 Co 5.OE+O1 6 Ni 1.OE+02 6 Cu 5.OE+O1 6 Zn 2.OE+03 6 Ga 2.2E+03 Footnote 13 Ge 2.4E+03 Footnote 12 As 3.3E+04 Footnote 14 Se 4.OE+02 Footnote 15 Br 4.2E+02 6 Kr NA NA Rb 2.OE+03 6 Sr 3.OE+O1 6 Y 2.5E+O1 6 Zr 33E+OO 6 Nb 3.OE+04 6 Mo 1.OE+O1 6 Tc 1.5E+O1 6 Ru 1.OE+O1 6 Rh 1.OE+O1 6 Pd 1 .OE+02 Footnote 9

CY-BY-1 70-301 Revision 14 Page 89 of 188 Table 3-8 (cont.)

Bloaccumulation Factors (BF1) to be Used in the Absence of Site-Specific Data Cd 2.OE+03 Footnote 11 In 2.2E+03 Footnote 13 Sn 2.4E+03 Footnote 12 Sb 1.OE+OO 98 Ag 2.3E+OO 56 Te 4.OE+02 6 I 1.5E+O1 6 Xe NA NA Cs 2.OE+03 6 Ba 4.OE+OO 6 La 2.5E+O1 6 Ce 1.OE+OO 6 Pr 2.5E+O1 6 Nd 2.5E+O1 6 Pm 3.OE+O1 98 Sm 3.OE+O1 Footnote 3 Eu 1 .OE+02 Footnote 3 Gd 2.6E+O1 Footnote 3 Dy 2.2E+03 Footnote 3 Er 3.3E+04 Footnote 3 Tm 4.OE+02 Footnote 3 Yb 2.2E+02 Footnote 3 Lu 2.5E+O1 Footnote 3 Hf 3.3E+OO Footnote 4 Ta 3.OE+04 Footnote 5 w 1.2E+03 6 Re 2.1 E+02 Footnote 6 Os 5.5E+O1 Footnote 7 Ir 3.OE+O1 Footnote 8 Pt I .OE+02 Footnote 9 Au 2.6E+O1 Footnote 10 Hg 2.OE+03 Footnote 11 TI 2.2E+03 Footnote 13 Pb 3.OE+02 98 Bi 2.OE+01 98 Ra 5.OE+01 98 Th 3.OE+01 98 U 1.OE+01 98 Np 1.OE+01 6 Am 3.OE+01 98

CY-BY-1 70-301 Revision 14 Page 90 of 188 Footnotes:

NA = It is assumed that noble gases are not accumulated.

In Reference 6, see Table A-I in the ODCM Training and Reference Material.

A number of bioaccumulation factors could not be found in literature. In this case, the periodic table was used in conjunction with published element values. This method was used for periodic table columns except where there were no values for column 3A so the average of columns 2B and 4A was assigned.

I . Value is the average of Reference 6 values in literature for H, Na, Rb and Cs.

2. Value is the average of Ref. 6 values in literature for Sr, Ba and Ref. 98 values for Ra.

3. Value is the same as the Reference 6 value used for Y.

4. Value is the same as the Reference 6 value used for Zr.

5. Value is the same as the Reference 6 value used for Nb.

6. Value is the average of Reference 6 values in literature for Mn and Ic.

7. Value is the average of Reference 6 values in literature for Fe and Ru.

8. Value is the average of Reference 6 values in literature for Co and Rh.

9. Value is the same as the Reference 6 value used for Ni.

10. Value is the average of Reference 6 values in literature for Cu and Reference 56 value for Ag.

I1 . Value used is the same as the Reference 6 value used for Zn.

12. Value is the average of Reference 6 value in literature for C and Reference 98 value for Pb.

I 3. Value is the average of columns 2B and 4A, where column 2B is the Reference 6 value for Zn and column 4A is the average of Reference 6 value for C and Reference 98 value for Pb.

14. Value is the average of Ref. 6 value found in literature for P and the Ref. 98 values for Bi and Sb.

I 5. Value is the same as the Reference 6 value used for Te.

16. Value is the average of Reference 6 values found in literature for Br and I.

CY-BY-1 70-301 Revision 14 I Page9l o1188

4. GASEOUS EFFLUENTS 4.1 . Gaseous Effluents General Information This section reviews the offsite radiological limits applicable to the nuclear power stations and presents in detail the equations and procedures used to assess compliance with these limits. This calculational approach uses the methodology ofNUREG-0133 (Reference 14), and incorporates certain simplifications such as the use of average meteorology.

4.1 .1 . Pre-calculated atmospheric transport parameters are based on historical average atmospheric conditions. These historical meteorological conditions have resulted in the dispersion parameters shown in Table 4-1 Table 4-2 and Table 4-8.

4.1 .2. The equations and parameters of this section are for use in calculating offsite radiation doses during routine operating conditions. They are not for use in calculating doses due to non-routine releases (e.g., accident releases).

4.1 .3. An overview of the required compliance is given in Table I -1 The dose components are itemized and referenced, and an indication of their regulatory application is noted. Additionally, the locations of dose receivers for each dose component are given in Table 1-2.

4.1 .4. Airborne Release Point Classifications I . The pattern of dispersion of airborne releases is dependent on the height of the release point relative to adjacent structures. Each release point is classified as one of the following three height-dependent types:

A. Stack (or Elevated) Release Point (denoted by the letter S or subscript s)

B. Ground Level Release Point (denoted by the letter G or subscript g)

C. Vent (or Mixed Mode) Release Point (denoted by the letter V or subscript v)

CY-BY-1 70-301 Revision I 4 Page 92 of 188 4.1 .5. Operability and Use of Gaseous Effluent Treatment Systems I . I OCFR5O Appendix I and ODCM Part I require that the ventilation exhaust treatment system and the waste gas holdup system be used when projected offsite doses in 31 days, due to gaseous effluent releases, from each reactor unit, exceed any ofthe following limits:

A. 0.2 mrad to air from gamma radiation.

B. 0.4 mrad to air from beta radiation.

C. 0.3 mrem to any organ of a member of the public.

2. The station must project doses due to gaseous releases from the site at least once per 31 days. The calculational methods shown in sections 4.2.2 and 4.2.3 are used for this dose projection.

4.1 .6. For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system.

4.2. Gaseous Effluents Dose and Dose Rate Calculation Requirements 4.2.1. Instantaneous Dose Rates 4.2.1.1 Noble Gas: Total Body Dose Rate 1 . ODCM Part I limits the total body dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to 500 mrem/yr at all times.

CY-BY-1 70-301 Revision 14 I Page 93 of 188

2. The total body dose rate due to noble gases released in gaseous effluents is calculated by the following expression:

DTB K {(/Q); Q1 + (/Q) Q + (/); Qig

} (4-1)

The summation is over noble gas radionuclides I.

Since Byron does not have an elevated release point, the Q term is not used.

DTB Total Body Dose Rate [mrem/yr]

Dose rate to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents.

Q1, Q, Qig Release Rate [pCi/sec]

Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively.

K Gamma Total Body Dose Conversion Factor [(mrem/yr)/QiCi/m3)J Gamma total body dose factor due to gamma emissions for noble gas radionuclide i. K values are taken from Table 4-28.

(XIQ)s Relative Concentration Factor [sec/m3]

(XQ)v Radioactivity concentration based on semi-infinite cloud methodology at a specified location per unit of radioactivity (xIQ)g release rate for a stack, vent, or ground level release, respectively.

See Table 4-1.

CY-BY-1 70-301 Revision 14 1 Page 94 of 188

3. To comply with this specification, the effluent radiation monitor has a setpoint corresponding to an offsite total body dose rate at or below the limit (see Part 2 Section 2.6). In addition, compliance is assessed by calculating offsite total body dose rate based on periodic samples obtained per station procedures.

4.2.1.2 Noble Gas: Skin Dose Rate I . ODCM Part I limits the skin dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to a dose rate of 3000 mrem/yr at all times. (See TRM 3.11 .f)

2. The skin dose rate due to noble gases released in gaseous effluents is calculated by the following expression:

DSK { L [ (/Q) Q1 (x/Q) Q,

+ + (X/Q)g Qig]

(4-2)

+ (1 .1 1) M1 [ /Q); + (/Q) Q + (x/Q) Qig I}

The summation is over noble gas radionuclides I.

DSK Skin Dose Rate [mrem/yrJ Dose rate to skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents.

L Skin Dose Conversion Factor [(mrem/yr)/QJCi/m3)]

Skin dose factor due to gamma emissions for noble gas radionuclide I. L values are taken from Table 4-28 M1 Gamma Air Dose Conversion Factor [(mrad/yr)/( tCi/m3)]

3. Gamma air dose rate factor per unit of radioactivity release rate for radionuclide i.

See Table 4-28 for Gamma Air Dose conversion factors (From Table B-I of Regulatory Guide I .109).

4. Since Byron does not have an elevated release point, the Qterm is not used.

CY-BY-J 70-301 Revision 14 1 Page 95 of 188

5. To comply with this specification, gaseous effluent radiation monitors have setpoints corresponding to an offsite skin dose rate at or below the limit (see Part 2 Section 2.6). In addition, compliance is assessed by calculating offsite skin dose rate based on periodic samples obtained per station procedures.

4.2.1.3 Non-Noble Gas Radionuclides: Organ Dose Rate I ODCM Part I limits the dose rate to any organ, due to radioactive materials in gaseous effluents released from a site to areas at and beyond the site boundary, to less than or equal to a dose rate of 1500 mrem/yr (See TRM 3.11 .f)

2. Typically the child is considered to be the limiting receptor in calculating dose rate to organs due to inhalation of non-noble gas radionuclides.in gaseous effluents.

3 The dose rate to any child organ due to inhalation is calculated by the following expression:

NNG D(Child)I(Inhal)j =

R(Child)j(Jnhal)j {(x/Q) Q + (/Q) Q + (X/Q)g Qjg I (4.3)

The summation is over non-noble gas radionuclides I.

. NNG D(ChiId)i(Inhal)J I n halation Dose Rate [mrem/yr]

Dose rate to the child age group from radionuclide I, via the inhalation pathway to organ j due to non-noble gas radionuclides.

R(chjld)j(Inhal)j I n halation Dose Factor [(mremIyr)/(pC i/m3)]

Inhalation dose factor for child age group for radionuclide i, and organ j. Inhalation dose factors for non-noble gas radionuclides (child) are shown in Table 4-11

CY-BY-1 70-301 Revision 14 I Page 96 of 188

4. Since Byron does not have an elevated release point, the Q term is not used.

5. ODCM Part I requires the dose rate due to non-noble gas radioactive materials in airborne effluents be determined to be within the above limit in accordance with a sampling and analysis program specified in IRM Table T3.1 I .f-1.

6. The child organ dose rate due to inhalation is calculated in each sector at the location of the highest offsite IQ (see Table 4-1). The result for the sector with the highest organ inhalation dose rate is compared to the limit.

4.2.2. Time Averaged Dose from Noble Gas 4.2.2.1 Gamma Air Dose I . ODCM and TRM limits the gamma air dose due to noble gas effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:

A. Less than or equal to 5 mrad per calendar quarter.

B. Less than or equal to I 0 mrad per calendar year.

The gamma air dose due to noble gases released in gaseous effluents is calculated by the following expression:

D = (3.IZE 8) M { (x/Q); A + (/Q) + (/Q) Ajg } (44)

The summation is over noble gas radionuclides i.

D, Gamma Air Dose [mrad]

Dose to air due to gamma radiation from noble gas radionuclides released in gaseous effluents.

3.17E-8 Conversion Constant (seconds to years) [yr/sec]

M Gamma Air Dose Conversion Factor [(mrad/yr)/(jiCi/m3)]

CY-BY-1 70-301 Revision 14 I Page 97 of 188 Gamma air dose rate factor per unit of radioactivity release rate for radionuclide i. See Table 4-28 for Gamma Air Dose conversion factors (From Table B-I of Regulatory Guide I .109).

(x/Q); (x/Q); (/Q)

, , Gamma-/Q Factor [sec/m3J Radioactivity concentration based on finite cloud methodology at a specific location per unit of radioactivity release rate from a stack, vent or ground level release, respectively. See Table 4-3 for Gamma-/Q Factors.

A1, Aig Cumulative Radionuclide Release [pCi]

Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively.

Since Byron does not have an elevated release point, the A1 term is not used.

2. TRM 3.1 1 .g requires determination of cumulative and projected gamma air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days.

3. Gamma air dose is calculated for the sector with the highest offsite (Q) and is compared with the Part I limits on gamma air dose.

4. For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system.

4.2.2.2 Beta Air Dose I . TRM Chapter 3.1 1 limits beta air dose due to noble gases in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:

A. Less than or equal to 10 mrad per calendar quarter.

B. Less than or equal to 20 mrad per calendar year.

CY-BY-1 70-301 Revision 14 I Page 98 of 188

2. The beta air dose due to noble gases released in gaseous effluents is calculated by the following expression:

op =

(3.IZE s) {Nt(/Q)A, + (/Q)VA,V + (X/Q)gAjg] I (45)

The summation is over noble gas radionuclides i.

op Beta Dose [mrad]

Dose to air due to beta radiation from noble gas radionuclides released in gaseous effluents.

3.17E-8 Conversion Constant (seconds to years) [yr/sec]

N Beta Air Dose Conversion Factor [(mrad/yr)/(pCi/m3)]

Beta air dose rate per unit of radioactivity concentration for radionuclide i.

See Table 4-28 for Beta Air Dose conversion factors (From Table B-I of Reg u latory Gu ide I I 09).

(xIQ)s Relative Concentration Factor [sec/rn3]

(xIQ)v Rad ioactivity concentration based on semi-infin ite cloud methodology at a specified location per unit of radioactivity release (xIQ)g rate for a stack, vent, or ground level release, respectively. See Table 4-I.

A, A, Aig Cumulative Radionuclide Release [iCi]

Measured cumulative release of radionuclide I over the time period of interest from a stack, vent, or ground level release point, respectively.

Since Byron does not have an elevated release point, the A term is not used.

CY-BY-1 70-301 Revision 14 Page 99 of 188

3. TRM 3.11 .g requires determination of cumulative and projected beta air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days.

4. Beta air dose is calculated for the sector with the highest offsite (Q) and is compared with the ODCM Part 1 limit on beta air dose.

5. For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system.

4.2.2.3 Whole Body Dose I . The total body dose, to any receiver is due, in part, to gamma radiation emitted from radioactivity in airborne effluents. This component is added to others to demonstrate compliance to the requirements of4OCFRI9O and IOCFR2O.

2. The total body dose component due to gamma radiation from noble gases released in gaseous effluents is calculated by the following expression:

DTB =(3.1ZE8)K{(x/Q)A ÷(/Q)A1 +(X/Q)Ajg I (46)

The summation is over noble gas radionuclides i.

DTB Total Body Dose [mremJ Dose to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents.

3.17E-8 Conversion Constant (seconds to years) [yr/sec]

K Gamma Total Body Dose Conversion Factor [(mrem/yr)/QjCi/m3)]

Gamma total body dose factor due to gamma emissions for noble gas radionuclide I released from a stack, vent or ground level release point, respectively. See Table 4-28 for Gamma total body dose conversion factors.

(FromTable B-I ofRegulatoryGuide 1.109)

A1, A, Aig Cumulative Radionuclide Release [iCi]

Measured cumulative release of radionuclide I over the time period of interest from a stack, vent, or ground level release point, respectively.

CY-BY-J 70-301 Revision 14 I Page 100 of 188

3. The total body dose is also calculated for the 4OCFRI 90 and I OCFR2O compliance assessments. In some cases, the total body dose may be required in IOCFR5O Appendix I assessments (See Part 2 Table 1-1).

4.2.2.4 Skin Dose There is no regulatory requirementto evaluate skin dose. However, this component is evaluated for reference as there is skin dose design objective contained in IOCFR5O Appendix I. Note that in the unlikely eventthat beta air dose guideline is exceeded, then the skin dose will require evaluation.

2. The part of skin dose due to noble gases released in gaseous effluents is calculated by the following expression:

DsK (3.IZE 8){ L[ (/Q)A, +(/Q)A1 +(X/Q)gAgJ

+ (1.1J)M, [/Q);A, +(/Q)A, +(,X/Q)Ajg] }

The summation is over noble gas radionuclides i.

DSK Skin Dose [mrem]

Dose to the skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents.

L1 Beta Skin Dose Conversion Factor [(mrem/yr)/QiCi/m3)]

Beta skin dose rate per unit of radioactivity concentration for radionuclide i. Taken from Table 4-28.

I .1 1 Conversion Constant (rads in air to rem in tissue) [mrem/mrad]

All other terms have been previously defined.

The skin dose is calculated for reference only.

CY-BY-1 70-301 Revision 14 I Page 101 of 188 4.2.3. Time Averaged Dose from Non-Noble Gas Radionuclides I . TRM 3.11 provides the following limits, based on IOCFR5O Appendix I, on the dose to a member of the public from specified non-noble gas radionuclides in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary:

A. Less than or equal to 7.5 mrem to any organ during any calendar quarter B. Less than or equal to 15 mrem to any organ during any calendar year

2. The individual dose components are also required as part ofthe 4OCFRI9O assessments and combined as part of the I OCFR2O assessment (Part 2 Table I -

1). The dose due to radionuclides deposited on the ground is considered to be a component of the deep dose equivalent for I OCFR2O compliance and an organ (and total body) dose component for IOCFR5O Appendix I and 4OCFRI9O compliance.

3. The dose is calculated for releases in the time period under consideration.

CY-BY-1 70-301 Revision 14 1 Page 102 of 188

4. Specifically, the dose is calculated as follows:

DNG (3.IZE 8)[WsRaipjAjs + WvRaipjAiv WgRaipjAig] (48)

The summation is over pathways p and non-noble gas radionuclides I.

DG Dose Due to Non-Noble Gas Radionuclides [mrem]

Dose due to non-noble gases (radioiodines, tritium and particulates) to age group a, and to organ j.

3.17E-8 Conversion Constant (seconds to years) [yr/sec]

ws, Wv, Wg Relative Concentration Factor Radioactive concentration at a specific location per unit of radioactivity release rate or concentration for stack, vent or ground level release, respectively.

ws, Wv, or Wg = (xIQ)s, (X/Q)V or (xIQ)g for immersion, inhalation and all tritium pathways.

W, WV, or Wg = (DIQ), (D/Q)V or (DIQ)9 for ground plain and all ingestion pathways.

(xIQ), (xIQ)V, (XIQ)g Relative Concentration Factor [sec/m3]

Radioactivity concentration based on semi-infinite cloud model at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Table 4-1 through Table 4-6.

(DIQ), (DIQ)V, (DIQ)g Relative Deposition Factor [11m2]

Radioactivity concentration at a specified location per unit of radioactivity release concentration for a stack, vent, or ground level release, respectively. See Table 4-1 through Table 4-6.

CY-BY-1 70-301 Revision 14 I Page 103 of 188 Raipj Site-Specific Dose Factor [(m2 mremlyr)IQiCilsec)]

or [(mremIyr)I(pCiIm3)J Site-specific dose factor for age group a, nuclide i, pathway p and organ j. Pathways included are ground plane exposure, inhalation, vegetation ingestion, milk ingestion and meat ingestion. Values of Raipj are provided in Table 4-7 and Table 4-9 through Table 4-26.

A1, A1, Aig Cumulative Radionuclide Release [tCiJ Measured cumulative release of radionuclide I over the time period of interest from a stack, vent, or ground level release point, respectively.

Since Byron does not have an elevated release point, the stack terms for A, W, (xIQ)s, and (DIQ) are not used.

5. TRM 3.1 1 .h requires cumulative and projected dose contributions for the current calendar quarter and the current calendar year for the specified non-noble gas radionuclides in airborne effluents to be determined at least once per 31 days.

6. To comply with this specification, Byron Station obtains and analyzes samples in accordance with the radioactive gaseous waste or gaseous effluent sampling and analysis program (TRM 3.11.f-1). In accordance with NUREG 0133 (Reference 14), dose due to non-noble gases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure. The inhalation and ground plane exposure pathways are considered to exist at all locations. The food ingestion pathways at a specific location are considered based on their existence as determined by land use census. The values used for (Q) and (DIQ) are shown in Table 4-1 through Table 4-6 and correspond to the applicable pathway location.

7. For a release attributable to a processing or effluent system shared by more than one reactor, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system.

8. The dose evaluated is also included as part of the I OCFR2O and 4OCFRI 90 assessment (See Part 2 Section 5).

CY-BY-1 70-301 Revision 14 I Page 104 of 188 4.2.3.1 Ground Plane I . The site-specific dose factor for ground deposition of radioactivity is considered to be a total body dose component and is calculated by the following expression:

r 4jtb 7 RaI(Gp)j[D/Q]

K1KMtO.7)DFGIL

]

Ground Plane Deposition Dose Factor [(m2 mrem/yr)/(tCi/sec)]

Rai(Gp)j[D/Q]

Site-specific ground plane dose factor for age group a, nuclide I and organ j. The ground plane dose is calculated using (DIQ).

K Conversion Constant (1 E6 pCi per jiCi) [pCi/pCi]

K Conversion Constant (8760 hr/yr) [hr/yr]

0.7 Shielding Factor; a factor that accounts for dimensionless shielding due to occupancy of structures.

DFG Ground Plane Dose Conversion Factor [(mrem/hr)/(pCi/m2)]

Dose rate to the total body per unit of surface radioactivity concentration due to standing on ground uniformly contaminated with radionuclide i. Ground Plane Dose Conversion Factors are shown in Table 4-8.

Note that ground plane dose conversion factors are only given for the total body and no age group. Doses to other organs are assumed to be equal to the total body dose. All age groups are assumed to receive the same dose.

Radiological Decay Constant [hr1]

Radiological decay constant for radionuclide I.

tb Time Period of Ground Deposition [hrJ Time period during which the radioactivity on the ground is assumed to have been deposited (see Part 2 Table I -3).

2. The ground plane exposure pathway is considered to exist at all locations.

CY-BY-1 70-301 Revision 14 I Page 105 of 188 4.2.3.2 Inhalation I . The site-specific dose factor for inhalation is calculated by the following expression:

Rai(InhaI)j[/Q] = KBRaDFAajj (4-10)

Rai(lnhal)j [/Q] In halation Pathway Dose Factor [(mremlyr)/(jiCilm3)]

Site-specific inhalation dose factor for age group a, nuclide I and organ j. The inhalation dose is calculated using (/Q).

K Conversion Constant (1 E6 pCi per iCi) [pCi4tCi]

BRa Individual Air Inhalation Rate [m3lyr]

The air intake rate for individuals in age group a. See Table E-5 of Regulatory Guide 1.109.

DFAaij Inhalation Dose Conversion Factor [mrem/pCi]

Dose commitment to an individual in age group a to organ j per unit of activity of radionuclide I inhaled. Taken from Tables E-7 through E-10 of Regulatory Guide I .109. The values for H-3 and Sr-90 are taken from NUREG 4013 (Reference 107).

2. The inhalation exposure pathway is considered to exist at all locations.

4.2.3.3 Ingestion: Vegetation 1 . Food ingestion pathway doses are calculated at locations indicated by the land use census survey. If no real pathway exists within 5 miles of the station, the cow-milk pathway is assumed to be located at 5 miles. Food pathway calculations are not made for sectors in which the offsite regions near the station are over bodies of water.

CY-BY-1 70-301 Revision 14 I Page 1 06 of I 88

2. The dose factor for consumption of vegetables is calculated by the following expression:

Rai(veg)j [D/Q] = K

] (DFLa1j ) [UfLe_1tL Ufge1th

] (4-1 1)

Rai(veg)j[D/Q] Vegetation Ingestion Pathway Dose Factor

[(m2 mrem/yr)/(iCi/sec)]

Site-specific vegetation ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3 and C-14 the vegetation dose is calculated using (D/Q).

K Conversion Constant (1 E6 pCi per pCi) [pCi4tCi]

r Vegetation Retention Factor [dimensionless]

Yv Agricultural Productivity Yield [kg! m2]

wj Radiological Decay Constant [1!sec]

Radiological decay constant for radionuclide i

?4W Weathering Decay Constant [1!sec]

Removal constant for physical loss of activity by weathering. See ODCM Part 2 Table 1-3.

DFLai1 Ingestion Dose Conversion Factor [mrem/pCi]

Ingestion dose conversion factor for age group a, nuclide i and organ j. Converts pCi ingested to mrem. Taken from Tables E-1 I though E-14 of Regulatory Guide 1.109. The values for H-3 and Sr 90 are taken from NUREG 4013 (Reference 107).

UaL Consumption Rate for Fresh Leafy Vegetation [kg!yr]

Consumption rate for fresh leafy vegetation for age group a.

UaS Consumption Rate for Stored Vegetation [kg/yr]

Consumption rate for stored vegetation for age group a.

CY-BY-1 70-301 Revision 14 I Page 107 of 188 fL Local Leafy Vegetation Fraction [dimensionless]

Fraction of the annual intake of fresh leafy vegetation that is grown locally.

fg Local Stored Vegetation Fraction [dimensionless]

Fraction of the annual intake of stored vegetation that is grown locally.

tL Environmental Transport Time Fresh Vegetation [sec]

Average time between harvest of leafy vegetation and its consumption.

th Environmental Transport Time Stored Vegetation [sec]

Average time between harvest of stored vegetation and its consumption.

3. The tritium dose from the vegetation pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium vegetation pathway is:

Ra(H 3Xveg)j[ I QJ K K (UfL Ufg )DFLa(H_3)J [0.75(0.5 I H)1 (4-12)

Ra(p3)(vej [x/c Tritium Vegetation Ingestion Pathway Dose Factor[(mrem/yr)/( iCi/m3)]

Site-specific tritium vegetation ingestion dose factor for age group a and organ j.

The tritium vegetation dose is calculated using [/Q]

K Conversion Constant (1 E3 gm per Kg) [gm/Kg]

H Absolute Atmospheric Humidity [gm/m3J 0.75 Water Fraction [dimensionless]

The fraction of total vegetation that is water.

0.5 Specific Activity Ratio [d imension less]

CY-BY-1 70-301 Revision 14 I Page 108 of 188

4. The Carbon-14 dose from the vegetation pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the Carbon-14 vegetation pathway is:

R [x I Q I =

K K (U fL + U fg ) (DFL ) [o i 16 ]

(4-1 2a)

K a constant of unit conversion, I E 6 pCi/uCi UaL gm/kg Leafy veg consumption rate adult (kg/yr)

U Fraction of annual intake of fresh, leafy vegetation grown locally Stored veg consumption rate adult (kg/yr) fg Fraction of annual intake of stored vegetation grown locally (DFL1)a Ingestion Dose Factors p The fractional equilibrium ratio (4400 hrs/8760 hrs). The ratio ofthe total annual release time (for C-14) atmospheric releases to the total annual time during which photosynthesis occurs (taken to be 4400 hrs), under the condition that the value of p should never exceed unity. For continuous C-14 releases, p is taken to be unity.

0.1 1 The fraction of total plant mass that is natural carbon (dimensionless) 0.16 The concentration of natural carbon in the atmosphere (gm/m3)

CY-BY-1 70-301 Revision 14 I Page 109 of 188 4.2.3.4 Ingestion Milk I . The dose factor for consumption of milk is calculated by the following expressions:

If (1 ffe_th Rai(MjIk)j[D/Q] = K Fm(r)(DFLaii)[1+ ]e_tf (413)

Rai(MiIk)J[D/Q] Milk Ingestion Pathway Dose Factor

[(m2 mrem/yr)/QiCi/sec)]

Site-specific milk ingestion dose factor for age group a, nuclide I and organ j.

With the exception of H-3 and C-14 the milk dose factor is calculated using (DIQ).

K Conversion Constant (1 E6 pCi per iCi) [pCi4iCi]

QF Feed Consumption [Kg/da]

Amount of feed consumed by milk animal each day. See ODCM Part 2 Table 1-3.

Uam Milk Consumption Rate [1/yr]

Milk consumption rate for age group a.

Fm Stable Element Transfer Coefficient for Milk [dali]

Fraction of animals daily intake of a particular chemical element that appears in each liter of milk (pCi/I in milk per pCilda ingested by animal).

See ODCM Part 2 Table 1-4.

Ip Pasture Time Fraction [dimensionless]

Fraction of year that animal is on pasture.

Is Pasture Grass Fraction [dimensionless]

Fraction of animal feed that is pasture grass while animal is on pasture.

Yp Agricultural Productivity Yield - Pasture Grass [kg/m2J The agricultural productivity by unit area of pasture feed grass.

CY-BY-1 70-301 Revision 14 1 Page 110 of 188 Ys Agricultural Productivity Yield - Stored Feed [kg/rn2]

The agricultural productivity by unit area of stored feed.

th Environrnental Transport Tirne Stored Feed [sec]

Average time between harvest to consumption of stored feed by milk animal.

tf Environmental Transport Time Pasture to Consumption

- [sec]

Average time from pasture, to milk animal, to milk, to consumption.

All other terms have been previously defined.

The tritium dose from the milk pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium milk pathway is:

Ra(3XMjIk)j [/Q] = K Ktm Fm QFUamlDa(H_3)j [0.75(0.5/H)] (414)

R a(F-3)(mi1j [xic Tritium Milk Ingestion Pathway Dose Factor

[(mrem/yr)/(JiCiIm3)]

Site-specific tritium milk ingestion dose factor for age group a and organ j.

The tritium milk dose is calculated using [/Q]

K Conversion Constant (1 E3 gm per Kg) [gm/Kg]

H Absolute Atmospheric Humidity [gm/m3]

0.75 Water Fraction [dimensionless]

The fraction of total feed that is water.

0.5 Specific Activity Ratio [dimensionless]

CY-BY-1 70-301 Revision 14 Pageill of 188

2. The Carbon-14 dose from the milk pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the Carbon-14 milk pathway is:

R1c

[ /Q] = I(K p Fm QF Up (DFL i)a

[o.ii /0.16 ] (4-14a)

K a unit of conversion, I .0E6 pCiluCi K gm/kg p The fractional equilibrium ratio (4400 hrs/8760 hrs). The ratio ofthe total annual release time (for C-14) atmospheric releases to the total annual time during which photosynthesis occurs (taken to be 4400 hrs), under the condition that the value of p should never exceed unity. For continuous C-14 releases, p is taken to be unity.

Fm Stable Element Transfer Data QF Milk cow feed consumption rate (kg/day wet)

Uap Cow milk consumption rate adult (1/yr)

(DFL1)a Ingestion Dose Factors 0.1 1 The fraction of total plant mass that is natural carbon (dimensionless) 0.16 The concentration of natural carbon in the atmosphere (gm/m3) 4.2.3.5 Ingestion: Meat 1 . The dose factor for consumption of meat is calculated by the following expression:

i ff\

]

4jth ff Rai(Meat)j [D/Q] = K QF(Uaf)

F, (r)(DFLaj ) +

et (4-15)

Rai(Meat)j[D/Q] Meat Ingestion Pathway Dose Factor

[(m2 mrem/yr)/(tCi/sec)J

CY-BY-1 70-301 Revision 14 Page 112 of 188 Site-specific meat ingestion dose factor for age group a, nuclide i and organ j.

With the exception of H-3 and C-14 the meat dose factor is calculated using (DIQ).

Uaf Meat Consumption Rate [kglyr]

Meat consumption rate for age group a.

F1 Stable Element Transfer Coefficient for Meat [da/Kg]

Fraction of animals daily intake of a particular chemical element that appears in each Kg of meat (pCi/Kg in meat per pCi/da ingested by animal). See QDCM Part 2 Table 1-4.

th Environmental Transport Time Stored Feed [sec]

Average time between harvest to consumption of stored feed by meat animal.

tf Environmental Transport Time Pasture to Consumption

- [sec]

Average time from pasture, to meat animal, to meat, to consumption.

All other terms have been previously defined.

The tritium dose from the meat pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium meat pathway is:

R a(H-3)(Meat)j I QJ = K K U p; QF U1 (DFJa(H3)j [0.75(0.5 I H)] (4-16)

?a(H3)(Meat)j [x/Q1 Tritium Meat Ingestion Pathway Dose Factor (mrem/yr)/(pci/m3)]

Site-specific tritium meat ingestion dose factor for age group a and organ j.

The tritium meat dose is calculated using Q.

K Conversion Constant (1 E3 gm per Kg) [gm/Kg]

H Absolute Atmospheric Humidity [gm/m3]

0.75 Water Fraction [dimensionless]

The fraction of total feed that is water.

0.5 Specific Activity Ratio [dimensionless]

All other terms have been previously defined.

CY-BY-1 70-301 Revision 14 I Page 113 of 188

2. The Carbon-14 dose from the meat pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the Carbon-14 meat pathway is:

R1M [x 1 = KK p Ff Qf U (DFL, ) [o.i 1/0.16] (4-16a)

K a unit of conversion, I .0E6 pCi/uCi K Conversion Constant (1 E3 gm per kg)[gmlkgJ p The fractional equilibrium ratio (4400 hrs/8760 hrs). The ratio of the total annual release time (for C-14) atmospheric releases to the total annual time during which photosynthesis occurs (taken to be 4400 hrs), under the condition that the value of p should never exceed unity. For continuous C-14 releases, p is taken to be unity.

Ff Days/kg for each stable element QF Milk cow feed consumption rate (kg/day wet)

Uap Meat consumption rate adult (kg/yr)

(DFLj)a Ingestion Dose Factors 0.11 the fraction oftotal plant mass that is natural carbon (dimensionless)

0. 1 6 the concentration of natural carbon in the atmosphere (gm/rn3)

CY-BY-1 70-301 Revision 14 Page 114 of 188 Table 4-1 XIQ and DIQ Maxima at or Beyond the Unrestricted Area Boundary Downwind Mixed Mode(V.nt) Retina Growid Level ReLent b$rKtio(1 Radius XIQ Radius Drn Radius I/O 0/0 (mettrs) Csec/?*3) (meters) (1/V*2) (meters) (secIV*3) C 1/m**2)

N 1875. 11988E07 1575. i983E*09 1875. 8.616E-0? 4.671 E09 HRE 1829. i.mo1 1829. 1.9278*09 1529. 7.531847 4.2718-09 NE 1565. 1.5308-07 1585. f.821E09 1585. T.8768*07 4.3888-09 ENE 1234. 1.3538-01 1236. f.166E-09 1236. 1.8088-01 5.0368-09 E 122T. 1.6888-07 1227. 2.335E-09 1227. 1.7438-06 6.2268-09 8$! 1. 2.519817 99f. 3i40E09 997. 1.6928-06 9.8968-09 SE f006.

• 3.0208-07 f006 3.5788-09 1006. 2.4808-06 1.7188-08

$58 800. 6.4978-07 800. 3J6tE-09 800. 4.1528-06 1.4208-08 S 945. 2.2498-07 945. 2.1928-09 945. 1.9468-06 9.3648-09

$sg 915. t.476E-0T 975. 1.9708-09 975. 1.308816 L6UE-09 sv 1067. 1.1688-07 106?. 1.7868-09 1067. 9.2198-07 5.3168-09.

18W 1212. 1.1998-07 1212. J.903E-09 1212. 7.6468-07 5.0028-09 U 1189. 1.7588-07 1189. 7.8708-09 1189. 9.3488-07 5.3308-09 hug 1227. 1.2056-07 1227. 7.2928-09 1221. 6.5638-0T3.745E-09 NI 1128. 1.6868-07 1128. 1.7198-09 1128. 0.8078-07 4.9848-09 WillS 1064. 3.06N07 1G44. 3.2231-09 1064. 1.4328-06 8.8716-09 Byron Siti Weteorotogicit Pita 1175 - 72/81 Note: Eased on Irrigation from the Rock River letter from G.P. Lahti (Sargent and Lundy) to J.c. Golden (NSEP), June 4, 1990 and the formulas in Reg. Guide 1.109.

is used for beta skin, and inhalation dose pathways. See Sections 4.2.1 4.2.2 ,

and 4.2.3.

DIQ is used for produce and leafy vegetable pathways. See Section 4.2.3.

The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode data.

Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of the highest xQ or DIQ at or beyond the unrestricted area boundary (UAB).

CY-BY-1 70-301 Revision 14 Page 115 of 188 Table 4-2 XIQ and DIQ Maxima at or Beyond the Restricted Area Boundary Do5mwlnd mlx.d I4od.CVant IeI. Growid Liwl *.hss.

Dfrct1cn RadI X/Q Isdius 0/0 RadIus na (meters) Cs.c1w)*3) Ctars) C1Ia2J (tars) (s.cti3) ( 1/SZ)

I m. 6.357!°OZ 777. 7.0041-09 7Th 3.2POIO6 2036E-08 RN! 8. &fl8E*D7 53 1.0461-08 3L 5.0861-06 3193E-O8 E 52B4 6.$03f-O7 528 1J92O9 52L 4.3flE-O6 2=646E-O8 EM! 474. 5341EOT 4T4. 53471-09 474. 4.014E.O6 2346E-O8 E 4M. 6698EOT 468. 793OO9 468. 5.3S9EO6 293OE-O8 ESE 480. Z377E-GT 480. L963t-09 480. .434tO6 3T44E-O8 SE 427. 1.126E-O6 421. 1.063E-08 427. 1.Q24EOS 4352E-O8 SSE 410. 1.349!% 41O L744!49 410. 1.305E-05 4044E08 5 295. 1.4411-06 295. 1.lfl!Q8 295 1.391EOS 5.IOIE-oB su 299. 9.382E-P1 299. L293EC9 299. 9.3r6EO6 4f97E-o8 su 451. 3.c49E-o7 451. 5.O65IO9 451. 3.666E*O6 2.095E08

,su 386. 6.O9SE-GT 3M. 7,4ZSE-09 386 4.679E-06 3.088E-08 U 379. 1.047E-06 379. &lldE-09 379. 6.009!*06 3275E-O8 aIu 385. 1.4541-01 385 6.OIE-O9 35. 6.352EO6 2370E-O8 NV 445k ?394t4f 445. .1fTh-O9 445. 4.O68EO6 2198E08 wIIIa 56dI £.IZS-OT 651. 6.17TE09 658a 298OE 1B74EO8 Byron Sit* Neteorotogtct Data 1t7 - WI?

Note: Based on Irrigation from the Rock River letter from G.P. Lahti (Sargent and Lundy) to J.c. Golden (NSEP), June 4, 1990 and the formulas in Reg. Guide 1.109.

The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode data.

Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of the highest xQ or DIQ at or beyond the restricted area boundary (RAB).

CY-BY-1 70-301 Revision 14 I Page 116 of 188 Table 4-3 Maximum Offsite Gamma-IQ Downwind Ground Vent Direction Radius GammajjQ Gamma-/Q (meters) (seclm**3) (seclm**3)

N 1875 4.80E-07 1.46E-07 NNE 1829 4.16E-07 I .36E-07 NE 1585 4.34E-07 1.31 E-07 ENE 1234 4.83E-07 1.27E-07 E 1227 6.IOE-07 1.50E-07 ESE 991 8.73E-07 2. 1 3E-07 SE I 006 1 .24E-06 2.45 E-OZ SSE 800 1.83E-06 3.02E-07 S 945 9.68E-07 1.85E-07 SSW 975 6.69E-07 1.34E-07 SW I 067 4.84E-07 I .08E-Of wSw 1212 4.19E-07 1.IIE-07 w 1189 5.07E-07 1.39E-07 WNW I 227 3.54E-OZ 9.70E-08 NW 1128 4.61E-07 1.29E-07 NNW 1044 7.43E-07 2.15E-07

CY-BY-1 70-301 Revision 14 Page 117 of 188 Table 4-4 and DIQ at the Nearest Resident Locations within 5 miles Mixed Mode (Vent)

Location Description Direction Distance Ground Level Release Release DIQ DIQ Miles meters seclm3 m2 seclm3 NEAREST RESIDENCE N 2.67 4300 3.70E-07 9.80E-1O 63OE-O8 3.80E-1O NEAREST RESIDENCE NNE 0.99 1600 1.50E-06 5.30E-09 8.30E-08 1.70E-09 NEAREST RESIDENCE NE I .1 8 1 900 1 .OOE-06 3.40E-09 6.60E-08 I .1 OE-09 NEAREST RESIDENCE ENE 1.30 2100 8.20E-07 2.20E-09 4.60E-08 7.30E-1O NEAREST RESIDENCE E 1 .30 21 00 1 .20E-06 2.80E-09 5.90E-08 9.40-10 NEAREST RESIDENCE ESE 1.43 2300 9.IOE-07 2.IOE-09 5.IOE-08 7.IOE-10 NEAREST RESIDENCE SE 0.75 1200 3.60E-06 7.40E-09 6.90E-08 2.OOE-09 NEAREST RESIDENCE SSE 0.62 1000 3.80E-06 8.IOE-09 5.40E-08 1.60E-09 NEAREST RESIDENCE S 0.50 800 3.40E-06 1 .20E-08 8.40E-08 2.40E-09 NEAREST RESIDENCE 55W 0.62 1000 1 .70E-06 6.80E-09 6.40E-08 1 .90E-09 NEAREST RESIDENCE SW 0.75 1200 780E-07 3.IOE-09 3.50E-08 8.80E-10 NEAREST RESIDENCE WSW 1.68 2700 3.30E-07 1.40E-09 5.40E-08 6.50E-10 NEAREST RESIDENCE W 1.68 2700 5.50E-07 1.40E-09 5.20E-08 4.IOE-10 NEAREST RESIDENCE WNW 0.75 1200 1 .70E-06 5.20E-09 4.60E-08 1 .OOE-09 NEARESTRESIDENCE NW 0.99 1600 1.IOE-06 330E-09 4.30E-08 7.30E-10 NEAREST RESIDENCE NNW 1.30 2100 8.50E-07 2.90E-09 6.20E-08 7.90E-10

CY-BY-1 70-301 Revision 14 Page 118 of 188 Table 4-5 and DIQ at the Nearest Cow Milk Locations within 5 miles Mixed Mode (Vent)

Location Description Direction Distance Ground Level Release Release XIQ DIQ DIQ miles meters seclm3 m2 seclm3 m2 cow MILK N 4.97 8000 1.50E-07 3.20E-1O 4.20E-08 1.40E-1O cow MILK NNE 4.97 8000 1.30E-07 3.IOE-1O 3.90E-08 1.60E-1O cow MILK NE I .86 3000 5.OOE-07 I .50E-09 6.70E-08 6.20-10 cow MILK ENE 4.97 8000 1.IOE-07 2.OOE-10 2.90E-08 1.IOE-10 cow MILK E 4.97 8000 1.60E-07 2.70E-10 3.90E-08 1.40E-10 cow MILK ESE 4.97 8000 1.40E-07 2.30E-10 3.50E-08 1.20E-10 cow MILK SE 4.97 8000 200E-07 2.70E-10 3.80E-08 1.40E-10 cow MILK SSE 4.97 8000 1.50E-07 2.20E-10 3.IOE-08 1.20E-10 cow MILK S 4.78 7700 9.IOE-08 2.40E-10 2.90E-08 1.50E-10 cow MILK SSW 4.97 8000 6.IOE-08 1.80E-10 220E-08 1.20E-10 cow MILK SW 4.97 8000 3.90E-08 1.IOE-10 1.50E-08 7.IOE-11 cow MILK WSW 4.97 8000 630E-08 2.IOE-10 2.50E-08 1.30E-10 cow MILK W 2.49 4000 3OOE-07 7.20E-10 4.90E-08 2.60E-10 cow MILK WNW 3.29 5300 1.70E-07 400E-10 3.40E-08 1.50E-10 cow MILK NW 298 4800 2.IOE-07 4.90E-10 3.70E-08 1.80E-10 COW MILK NNW 4.97 8000 1.IOE-07 2.70E-10 3.50E-08 1.20E-10

CY-BY-1 70-301 Revision 14 Page 119 of 188 Table 4-6 and DIQ at the Nearest Cow Meat Locations within 5 mites Mixed Mode (Vent)

Location Description Direction Distance Ground Level Release Release DIQ XIQ DIQ miles meters sec/rn3 m2 seclm3 m2 cow MEAT N 2.98 4800 3.1 OE-07 8.IOE-10 6.OOE-08 3.20E-1 0 cow MEAT NNE 1.49 2400 7.70E-07 2.60E-09 7.60E-08 9.90E-1 0 cow MEAT NE 3.42 5500 2.OOE-07 5.30E-1 0 5.20E-08 2.70E-1 0 cow MEAT ENE 2.30 3700 3.40E-07 8.IOE-10 4.30E-08 3.50E-1 0 cow MEAT E 2.24 3600 5.OOE-07 1.IOE-09 5.80E-08 4.70E-1 0 cow MEAT ESE 1.49 2400 8.50E-07 2.OOE-09 5.IOE-08 6.80E-1 0 cow MEAT SE 1.68 2700 9.80E-07 I .80E-09 5.90E-08 6.90E-1 0 cow MEAT SSE 3.17 5100 2.90E-07 4.90E-1 0 4.IOE-08 2.40E-1 0 cow MEAT S 0.56 900 2.80E-06 9.90E-09 7.70E-08 2.1 OE-09 cow MEAT SSW 2.17 3500 2.1 OE-07 8.OOE-1 0 4.OOE-08 4.30E-1 0 cow MEAT SW 3.17 5100 7.60E-08 2.50E-1 0 2.IOE-08 1.50E-10 cow MEAT WSW I .68 2700 3.30E-07 I .40E-09 5.40E-08 6.50E-1 0 cow MEAT W I .68 2700 5.50E-07 I .40E-09 5.20E-08 4.IOE-10 cow MEAT WNW 3.29 5300 1.70E-07 4.OOE-10 3.40E-08 I .50E-10 cow MEAT NW 3.79 6100 1.50E-07 3.20E-1 0 3.30E-08 I .30E-10 cow MEAT NNW 1.37 2200 7.90E-07 2.70E-09 6.20E-08 7.50E-1 0

CY-BY-1 70-301 Revision 14 I Page 120 of 188 Table 4-7 Ground Plane Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+/-OO OOOE+OO O.OOE+OO C-14 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 I .20E+07 I .20E+07 I .20E+07 I .20E+07 I .20E+07 I .20E+07 I .20E+07 Cr-51 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 Mn-54 1 38E+O9 I .38E+09 I .38E+09 I .38E+09 I .38E+09 I .38E+09 I 38E+O9 Mn-56 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9O3E+O5 9.03E+05 9.03E+05 Fe-55 O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-59 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 Co-58 3.80E+O 3.80E+08 3.80E+08 3.80E+08 3.80E+08 38OE+O8 3.80E+08 Co-60 2.15E+1O 2.15E+1O 2.15E+1O 2.15E+1O 2.15E+1O 2.15E+1O 2.15E÷1O Ni-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ni-65 2.97E+05 Z97E+05 2.97E+05 2.97E+05 2.97E+05 2.97E+05 2.97E+05 Cu-64 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 Zn-65 7.46E+08 7.46E+08 7.46E+08 746E+08 7.46E+08 746E+08 7.46E+08 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 Br-84 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 9.01 E+06 9.01 E+06 9.01 E+06 9.01 E+06 9.01 E+06 9.01 E+06 9.01 E+06 Rb-88 3.31E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 Rb-89 1 .23E+05 I .23E+05 I .23E+05 I .23E+05 I .23E+05 I .23E+05 I .23E+05 Sr-89 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-91 2. 1 4E+06 2. 1 4E+06 2. 1 4E+06 2. 1 4E+06 2. 1 4E+06 2. 1 4E+06 2. 1 4E+06 Sr-92 7.76E+05 7.76E+05 7.76E+05 7.76E+05 7.76E+05 7.76E+05 7.76E+05 Y-90 4.50E+03 45OE+O3 4.50E+03 4.50E+03 4.50E+03 4.50E+03 4.50E+03 Y-91 M I .OOE+05 I .OOE+05 I OOE+05 I .OOE+05 I .OOE+05 I .OOE+05 I .OOE+05 Y-91 I .07E+06 I .07E+06 I .07E+06 I .07E+06 I .07E+06 I .07E+06 I .07E+O Y-92 I .80E+05 I .80E+05 I .80E+05 I 8OE+O5 I .80E+05 I .80E+05 I .80E+05 Y-93 1 .83E+05 I .83E+05 I .83E+05 I .83E+05 I .83E+05 I .83E+05 I .83E+05 Zr-95 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 245E+08 2.45E+O Zr-97 296E+O6 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+O Nb-95 I .37E+08 I .37E+08 I .37E+08 I .37E+08 I .37E+08 I .37E+08 I .37E+08 Mo-99 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 Tc-99M 1.84E+05 1.84E+05 1.84E+05 1.84E+05 184E+05 1.84E+05 1.84E+05 Tc-1O1 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 Ru-103 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 Ru-105 6.36E+05 6.36E+05 6.36E+05 6.36E+05 6.36E+05 6.36E+05 6.36E+05 Ru-106 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 Ag-I I OM 3.45E+09 3.45E+09 345E+09 3.45E+09 3.45E+09 3.45E+09 3.45E+09

CY-BY-J 70-301 Revision 14 Page 121 of 188 Table 4-7 (Continued)

Ground Plane Dose Factors (same for all age groups)

Nuclide Bone Liver I Body Thyroid Kidney Lung Gl-LLI Te-125M 1.56E+06 1.56E+06 1.56E+06 1.56E+06 t56E+06 1.56E+06 1.56E+06 Te-127M 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E÷04 9.16E+04 Te-127 2.99E+03 2.99E+03 2.99E+03 2.99E+03 2.99E+03 Z99E+03 2.99E+03 Te-1 29M I .98E+07 I .98E+Of I .98E+07 I .98E+07 I .98E+07 I .98E+07 I .98E+07 Te-129 2.62E+04 2.62E+04 Z62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 Te-1 31 M 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02 E+06 Te-131 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 Te-1 32 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 1-130 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 I-I 31 1 .72E+07 1 .72E+07 I .72E+07 I .72E+07 I .72E+07 I .72E+07 I .72E+07 1-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1-133 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 1-134 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E÷05 4.46E+05 1-135 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 Cs-134 6.94E+09 6.94E+09 6.94E+09 6.94E+09 6.94E+09 6.94E+09 6.94E+09 Cs-136 I .50E+08 I .50E+08 I .50E+08 I .50E+08 I .50E+08 I .50E+08 I .50E+08

iT 1.76E+10 1.76E+10 1.76E+10 1.76E+10 1.76E+10 1.76E+10 1.76E+10 Cs-138 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E÷05 3.59E+05

• i::i I .06E+05 I .06E+05 I .06E+05 I .06E+05 I .06E+05 I .06E+05 1 .06E+05 Ba-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E÷07 2.05E+07

iW 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 Ba-142 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 La-140 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 La-142 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E÷05 7.60E+05 Ce-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 Ce-143 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 Ce-144 6.96E+0Z 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E÷07 6.96E+07 Pr-143 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Pr-144 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 Nd-147 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 W-187 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 Np-239 I .71 E+06 I .71 E+06 1 .71 E+06 I .71 E+06 I .71 E+06 I .71 E+06 I .71 E+06 Notes:

1) Units are m2 mrem/yr per jtCilsec.

2) All age groups are assumed to receive the same dose.

CY-BY-J 70-301 Revision 14 Page 122 of 188 Table 4-8 External Dose Factors for Standing on Contaminated Ground DFG11 (mremlhr per pCi! m2)

Whole Body Whole Body Element Dose Factor Reference Element Dose Factor Reference H-3 O.OOE+OO 6 Be-7 5.95E-1O 99 C-14 OOOE+OO 6 F-18 1.19E-08 99 Na-22 2.42E-08 99 Na-24 2.50E-08 6 Mg-27 I .1 4E-08 99 Mg-28 I .48E-08 99 AI-26 295E-08 99 AI-28 2.OOE-08 99 P-32 O.OOE+OO 6 CI-38 I 70E-08 99 Ar-41 1.39E-08 99 K-40 2.22E-09 99 K-42 4.64E-09 99 K-43 I .19E-08 99 Ca-47 1.14E-08 99 Sc-44 2.50E-08 99 Sc-46m I .21 E-09 99 Sc-46 224E-08 99 Sc-47 I .46E-09 99 Ti-44 1 .95E-09 99 V-48 3.21E-08 99 Cr-51 2.20E-1O 6 Mn-52m 2.79E-08 99 Mn-52 3.80E-08 99 Mn-54 5.80E-09 6 Mn-56 J1OE-08 6 Fe-52 9.12E-09 99 Fe-55 O.OOE+OO 6 Fe-59 8.OOE-09 6 Co-57 I 65E-09 99 Co-58 7.OOE-09 6 Co-60 I .70E-08 6 Ni-63 O.OOE+OO 6 NE-65 3.70E-09 6 Cu-64 I .50E-09 6 Cu-67 I .52E-09 99 Cu-68 8.60E-091 -- Zn-65 4.OOE-09 6 Zn-69m 5.06E-09 99 Zn-69 O.OOE+OO 6 Ga-66 2.70E-08 99 Ga-67 I .89E-09 99 Ga-68 I .24E-08 99 Ga-72 3OOE-08 99 Ge-77 1.34E-08 99 As-72 2.23E-08 99 As-73 I I 6E-1 0

. 99 As-74 9.41 E-09 99 As-76 6.46E-09 99 As-77 1.79E-1O 99 Se-73 I .38E-08 99 Se-75 4.98E-09 99 Br-77 3.84E-09 99 Br-80 2.OIE-09 99 Br-82 3.OOE-08 99 Br-83 6.40E-11 6 Br-84 I .20E-08 6 Br-85 O.OOE+OO 6 Kr-79 307E-09 99 Kr-81 1.59E-1O 99 Kr-83m I .42E-1 I 99 Kr-85m 2.24E-09 99 Kr-85 1..35E-1O 99 Kr-87 1.03E-08 99 Kr-88 2.07E-08 99 Kr-90 I .56E-08 99 Rb-84 J.OZE-08 99 Rb-86 6.30E-1O 6 Rb-87 O.OOE+OO 99 Rb-88 350E-09 6 Rb-89 150E-08 6 Sr-85 6.16E-09 99 Sr-87m 3.92E-09 99 Sr-89 560E-13 6 Sr-90 1.84E-J1 99 Sr-91 7.IOE-09 6 Sr-92 9.OOE-09 6 Y-86 4.OOE-08 99 Y-87 5.53E-09 99 Y-88 2.88E-08 99 Y-90 220E-12 6 Y-91m 380E-09 6 Y-91 2.40E-1 I 6 Y-92 I .60E-09 6 Y-93 5.70E-1 0 6 Zr-95 5.OOE-09 6 Zr-97 5.50E-09 6 Nb-94 I .84E-08 99 Nb-95 5.IOE-09 6 Nb-97m 8.57E-09 99 Nb-97 8.48E-09 99 Mo-99 I .90E-09 6 Tc-99m 9.60E-JO 6 Tc-1O1 2.70E-09 6 Tc-104 1.83E-081 -- Ru-97 2.99E-09 99 Ru-103 3.60E-09 6 Ru-105 4.50E-09 6 Ru-106 1.50E-09 6 Pc-109 3.80E-JO 99 cd-I 09 1 .1 2E-1 0 99 n-I I I 5.1 1 E-09 99 In-115m 2.OIE-09 99 In-716 O.OOE+002 --

Sn-113 1.15E-09 99 Sn-117m 1.96E-08 99 Sn-119m 7.05E-11 99 Sb-liZ O.OOE+002 --

Sb-122 2.71E-091 -- Sb-124 1.16E-081 --

Sb-125 4.56E-09 99 Sb-126 713E-1O 99 Ag-108m 1.92E-08 99 Ag-108 1.14E-09 99 Ag-Ibm 1.80E-08 6 Ag-Ill 6.75E-1O 99 Te-121m 2.65E-09 99 Te-72J 6.75E-09 99 Te-123m 1.88E-09 99 Te-125m 3.50E-11 6

CY-BY-1 70-301 Revision 14 Page 123 of 188 Table 4-8 (cont.)

External Dose Factors for Standing on Contaminated Ground DFG11 (mrem/hr per pCi! m2)

Whole Body Whole Body Element Dose Factor Reference Element Dose Factor Reference Te-125 O.OOE+002 -- Te-127m 1.1OE-12 6 Te-127 1.OOE-11 6 Te-129m Z.70E-1O 6 Te-129 flOE-JO 6 Te-131m 8.40E-09 6 Ie-131 220E-09 6 Te-132 J.ZOE-08 6 Te-134 1.05E-08 99 1-123 2.72E-09 99

-124 1.23E-08 99 1-125 2.89E-1O 99 1-130 140E-08 6 1-131 2.80E-09 6

-132 1.70E-09 6 1-133 3.ZOE-09 6

-134 1.60E-08 6 -135 1.20E-08 6 Xe-127 3.44E-09 99 Xe-129m 5.57E-1O 99 Xe-131m 2.13E-1O 99 Xe-133m 4.81E-1O 99 Xe-133 5.91E-1O 99 Xe-135m 5.23E-09 99 Xe-135 3.36E-09 99 Xe-137 4.26E-09 99 Xe-138 1.30E-08 99 Cs-129 3.39E-09 99 Cs-132 8.40E-09 99 Cs-134 1.20E-08 6 Cs-136 1.50E-08 6 Cs-137 Z.IZE-094 99 Cs-138 2.IOE-08 6 Cs-139 5.15E-09 99 Ba-131 5.74E-09 99 Ba-133m 8.IOE-JO 99 Ba-133 4.85E-09 99 Ba-135m 7.26E-1O 99 Ba-137m 7.17E-09 99 Ba-137 O.OOE+002 --

Ba-139 240E-09 6 Ba-La-140 1.71E-086 6 Ba-141 4.30E-09 6 Ba-142 7.90E-09 6 La-142 1.50E-08 6 Ce-139 2.04E-09 99 Ce-141 5.50E-1O 6 Ce-143 2.20E-09 6 Ce-Pr-144 520E-107 6 Pr-142 1.84E-09 99 Pr-143 O.OOE+OO 6 Nd-147 1.OOE-09 6 Nd-149 5.32E-09 99 Pm-145 3.38E-1O 99 Pm-148m 2.35E-08 99 Pm-148 Z.22E-09 99 Pm-149 5.32E-1O 99 Sm-153 8.95E-1O 99 Eu-152 1.30E-08 99 Eu-154 141E-08 99 Eu-155 8.27E-1O 99 Gc-153 1.46E-09 99 Dy-157 4.39E-09 99 Er-169 6.12E-14 99 Er-171 5.IIE-09 99 Tm-170 3.41E-1O 99 Yb-169 4.12E-09 99 Yb-175 4.94E-1O 99 Lu-177 460E-1O 99 Hf-181 6.67E-09 99 Ta-182 1.42E-08 99 Ta-183 293E-091 --

W-J87 31OE-09 6 Re-188 1.89E-09 99 Os-191 9.83E-1O 99 Ir-194 2.31E-09 99 Pt-195m 9.79E-1O 99 Pt-197 3.57E-1O 99 Au-195m 2.54E-09 99 Au-195 1.14E-09 99 Au-198 519E-09 99 Au-199 1.18E-09 99 Hg-197 9.33E-fO 99 Hg-203 289E-09 99 Tl-201 1.24E-09 99 TI-206 O.OOE+002 --

Tl-208 3.58E-08 99 Pb-203 388E-09 99 Pb-210 3.57E-11 99 Pb-212 1.91E-09 99 Pb-214 3.18E-09 99 Bi-206 3.74E-08 99 Bi-207 1.77E-08 99 Bi-214 1.71E-08 99 Ra-226 8.78E-1 I 99 Th-232 8.14E-12 99 U-238 7.98E-12 99 Np-239 9.50E-1O 6 Am-241 3.48E-1O 99 1 Value derived by comparing the percentage and MeV of the nuclides gammas and then comparing to Cesium-I 37, as value a was not available in the literature.

2 o.o due to low yield and short half-life. A value was not available in the literature.

4 Cs-I37 value is from daughter product Ba-137m (Z.17E-09) because ground plane dose from Cs-137 is due to gamma radiation emitted by Ba-137m. This value is from reference 99.

CY-BY-1 70-301 Revision 14 Page 124 of 188 Table 4-8 (cont.)

External Dose Factors for Standing on Contaminated Ground DFG1 (mrem/hr per pCi! m2) 6 Value is the sum of Ba-140 (2.JOE-9) and La-140 (1.50E-8) from reference 6. In Reference 6, see Table E-6.

7 Value is the sum ofCe-144 (3.20E-1O) and Pr-144 (2.OOE-1O) from reference 6.

Note: Dose assessments for IOCFR2O and 4OCFRI9O compliance are made for an adult only.

Dose assessments for 10CFR5O Appendix are made using dose factors of Regulatory Guide 1.109 (Reference 6) for all age groups.

CY-BY-1 7O3O1 Revision 14 Page 125 of 188 Table 4-9 Adult Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 7. 1 8E+02 7. 1 8E+/-02 7. 18E+02 7. 1 8E+02 7. 1 8E+/-02 7. 1 8E+02 C-14 I .82E+04 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 Na-24 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 Cr-51 O.OOE+OO O.OOE+OO I .OOE+02 5.95E+O1 2.28E+O1 I .44E+04 3.32E+03 Mn-54 O.OOE+OO 3.96E+04 6.30E+03 O.OOE+OO 9.84E+03 I .40E+06 Z.74E+04 Mn-56 O.OOE+OO I .24E+OO J .83E-O1 O.OOE+OO I .30E+OO 9.44E+03 2.02E+04 Fe-55 2.46E+04 I .70E+04 3.94E+03 O.OOE+OO OOOE+OO 721 E+04 6.03E+03 Fe-59 I .18E+04 2.78E+04 I .06E+04 O.OOE+OO OOOE+OO I .02E+06 I .88E+05 Co-58 O.OOE+OO I .58E+03 2.07E+03 O.OOE+OO O.OOE+OO 9.28E+05 I .06E+05 Co-60 O.OOE+OO I .15E+04 I .48E+04 O.OOE+OO O.OOE+OO 5.97E+06 2.85E+05 Ni-63 4.32E+05 3.14E+04 I .45E+04 O.OOE+OO O.OOE+OO I .78E+05 I 34E+O4 Ni-65 I .54E+OO 2.IOE-O1 9.12E-02 O.OOE+OO O.OOE+OO 5.60E+03 I .23E+04 Cu-64 O.OOE+OO I A6E+OO 6. 1 5E-O1 O.OOE+OO 4.62E+OO 6.78E+03 4.90E+04 Zn-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+OO 6.90E+04 8.64E+05 5.34E+04 Zn-69 3.38E-02 6.51 E-02 4.52E-03 O.OOE+OO 422E-O2 9.20E+02 I .63E+O1 Br-83 O.OOE÷OO O.OOE+OO 2.41 E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+02 Br-84 O.OOE+OO O.OOE+OO 3.13E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.64E-03 Br-85 O.OOE+OO O.OOE+OO I .28E+O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO I .35E+05 5.90E+04 O.OOE+OO O.OOE+OO O.OOE+OO I .66E+04 Rb-88 O.OOE+OO 3.87E+02 I 93E+O2 O.OOE+OO O.OOE+OO O.OOE+OO 3.34E-09 Rb-89 O.OOE+OO 256E+02 1.70E+02 O.OOE+OO O.OOE+OO O.OOE+OO 9.28E-12 Sr-89 3.04E+05 O.OOE+OO 8.72E+03 O.OOE+OO O.OOE+OO I .40E+06 3.50E+05 Sr-90 2.87E+07 OOOE+OO 5.77E+05 O.OOE+OO O.OOE+OO 9.60E+06 7.22E+05 Sr-91 6.19E+O1 O.OOE+OO 2.50E+OO O.OOE+OO O.OOE+OO 3.65E+04 1.91E+05 Sr-92 674E+OO O.OOE+OO 2.91 E-O1 O.OOE+OO O.OOE+OO 1 .65E+04 4.30E+04 Y-90 2.09E+03 O.OOE+OO 5.61 E+O1 O.OOE+OO O.OOE+OO I .70E+05 5.06E+05 Y-91M 2.61E-O1 O.OOE+OO 1.02E-02 O.OOE+OO O.OOE+OO 1.92E+03 133E+OO Y-91 4.62E+05 O.OOE+OO I .24E+04 O.OOE+OO O.OOE+OO I .70E+06 3.85E+05 Y-92 I .03E+O1 O.OOE+OO 3.02E-O1 OOOE+OO O.OOE+OO I .57E+04 7.35E+04 Y-93 9.44E+O1 O.OOE+OO 2.61 E+OO O.OOE+OO O.OOE+OO 485E+04 4.22E+05 Zr-95 I .07E+05 3.44E+04 2.33E+04 O.OOE+OO 5.42E+04 I .77E+06 I .50E+05 Zr-97 9.68E+O1 I .96E+O1 9.04E+OO O.OOE+OO 2.97E+O1 7.87E+04 5.23E+05 Nb-95 1 Al E+04 7.82E+03 4.21 E+03 O.OOE+OO 7.74E+03 5.05E+05 I .04E+05 Mo-99 O.OOE+OO I .21 E+02 2.30E+O1 O.OOE+OO 2.91 E+02 9.12E+04 2.48E+05 Ic- 99M I .03E-03 2.91 E-03 310E-02 O.OOE+OO 4.42E-02 7.64E+02 4.16E+03 Tc-1O1 4.18E-05 6.02E-05 5.90E-04 O.OOE+OO I .08E-03 3.99E+02 I .09E-1 I Ru-103 I.53E+03 O.OOE+OO 6.58E+02 O.OOE+OO 5.83E+03 5.05E+05 I.IOE+05 Ru-I 05 7.90E-OI OOOE+OO 3. 1 I E-O1 O.OOE+OO I .02E+OO I I OE+04

. 4.82E+04 Ru-106 6.91 E+04 O.OOE+OO 8.72E+03 O.OOE+OO I .34E+05 936E+O6 9.12E+05 Ag-I I OM I .08E+04 I .OOE+04 5.94E+03 O.OOE+OO I .97E+04 4.63E+06 3.02E+05

CY-BY-1 70-301 Revision 14 Page 126 of 188 Table 4-9 (Continued)

Adult Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 Te-127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-127 1.40E+OO 6.42E-O1 3.IOE-O1 1.06E+OO 5.IOE+OO 6.51E+03 5.74E+04 Te-129M 976E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 Te-129 4.98E-02 2.39E-02 I .24E-02 3.90E-02 I .87E-O1 I .94E+03 I .57E+02 Te-1 31 M 6.99E+O1 4.36E+O1 2.90E+O1 5.50E+O1 3.09E+02 I .46E+05 5.56E+05 31 1 .1 1 E-02 5.95E-03 3.59E-03 9.36E-03 4.37E-02 I .39E+03 I .84E+O1 Te-132 2.60E+02 2.15E+02 I .62E+02 J .90E+02 I .46E+03 2.88E+05 5.IOE+05 I:io 4.58E+03 1.34E+04 5.28E+03 1.14E+06 2.09E+04 O.OOE+OO 7.69E+03 1-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 O.OOE+OO 6.28E+03 I-I 32 1 .1 6E+03 3.26E+03 I I 6E+03 I I 4E+05 5.1 8E+03

. . O.OOE+OO 4.06E+02 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 O.OOE+OO 8.88E+03 1-134 644E+02 I .73E+03 6.15E+02 2.98E+04 2.75E+03 O.OOE+OO I .01 E+OO 1-135 2.68E+03 6.98E+03 2.57E+03 4.48E+05 1.IIE+04 O.OOE+OO 5.25E+03 Cs-134 3.73E+05 8.48E+05 7.28E+05 O.OOE+OO 2.87E+05 9.76E+04 1.04E+04 Cs-I 36 3.90E+04 I .46E+05 I I OE+05 O.OOE+OO 8.56E+04 I .20E+04 I I 7E+04 Cs-137 4.78E+05 6.21E+05 4.28E+05 O.OOE+OO 2.22E+05 7.52E+04 8.40E+03 Cs-I 38 3.31 E+02 6.21 E+02 3.24E+02 O.OOE+OO 4.80E+02 4.86E+O1 I .86E-03 Ba-I 39 9.36E-O 1 6 .66 E-04 2 .74E-02 0 .OOE+OO 6.22E-04 3. 76E+03 8.96E+02 Ba-140 3.90E+04 4.90E+OI 2.57E+03 O.OOE+OO I .67E+OI 1 27E+06 2.1 8E+05 Ba-141 I .OOE-OI 7.53E-05 3.36E-03 O.OOE+OO 7.OOE-05 I .94E+03 I .1 6E-07 Ba-I 42 2.63E-02 2.70E-05 I .66E-03 O.OOE+OO 2.29E-05 I I 9E+03

. I .57E-I 6 La-140 3.44E+02 I .74E+02 458E+OI O.OOE+OO O.OOE+OO I .36E+05 458E+O5 La-I 42 6.83E-OI 3. 1 OE-OI 7.72E-02 O.OOE+OO O.OOE+OO 6.33E+03 2. 1 1 E+03 Ce-I4I I.99E+04 I.35E+04 I53E+O3 O.OOE+OO 626E+03 3.62E+05 I.20E+05 Ce-143 I .86E+02 I .38E+02 I 53E+OI O.OOE+OO 6.08E+OI 7.98E+04 2.26E+05 Ce-I44 3.43E+06 I.43E+06 1.84E+05 O.OOE+OO 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 O.OOE+OO 2.16E+03 2.81E+05 2.OOE+05 Pr-I44 3OIE-O2 I.25E-02 1.53E-03 O.OOE+OO 7.05E-03 I.02E+03 2.15E-08 Nd-147 5.27E+03 6.IOE+03 3.65E+02 O.OOE+OO 3.56E+03 2.21E+05 I.73E+05 W-187 8.48E+OO 7.08E+OO 2.48E+OO O.OOE+OO O.OOE+OO 2.90E+04 I.55E+05 Np-239 230E+02 2.03E+02 1.24E+O1 O.OOE+OO 7.OOE+OI 3.76E+04 1.19E+05 Notes:

1) Units are mrem/yr per pCi/rn3.

CY-BY-1 70-301 Revision 14 Page 127 of 188 Table 4-10 Teen Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 Na-24 1.38E+04 L38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 Cr-51 O.OOE+OO O.OOE+OO 1.35E+02 7.50E+O1 3.07E+O1 ZIOE+04 3.OOE+03 Mn-54 OOOE+OO 5.1 1 E+04 8.40E+03 O.OOE+OO I .27E+04 1 .98E+06 6.68E+04 Mn-56 O.OOE+OO J .70E+OO 2.52E-O1 O.OOE+OO I .79E+OO I .52E+04 5.74E+04 Fe-55 3.34E+04 2.38E+04 5.54E+03 O.OOE+OO O.OOE+OO 1 .24E+05 6.39E+03 Fe-59 1 59E+O4 3.70E+04 I .43E+04 O.OOE+OO O.OOE+OO 1 .53E+06 I .78E+05 Co-58 O.OOE+OO 2.07E+03 2.78E+03 O.OOE+OO O.OOE+OO I .34E+06 9.52E+04 Co-60 O.OOE+OO 1 .51 E+04 I .98E+04 O.OOE+OO O.OOE+OO 8.72E+06 2.59E+05 Ni-63 5.80E+05 4.34E+04 1 .98E+04 O.OOE+OO O.OOE+OO 3.07E+05 I .42E+04 Ni-65 2.18E+OO 2.93E-O1 1.27E-O1 O.OOE+OO O.OOE+OO 9.36E+03 3.67E+04 Cu-64 O.OOE+OO 2.03E+OO 8.48E-O1 O.OOE+OO 641 E+OO I i 1 E+04 6.14E+04 Zn-65 3.86E+04 I .34E+05 6.24E+04 O.OOE+OO 8.64E+04 I .24E+06 4.66E+04 Zn-69 4.83E-02 9.20E-02 6.46E-03 O.OOE+OO 6.02E-02 1 .58E+03 2.85E+02 Br-83 O.OOE+OO O.OOE+OO 3.44E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 4.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO J .83E+O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO I .90E+05 8.40E+04 O.OOE+OO O.OOE+OO OOOE+OO 1 .77E+04 Rb-88 O.OOE+OO 5.46E+02 2.72E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E-05 Rb-89 O.OOE+OO 3.52E+02 2.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.38E-07 Sr-89 4.34E+05 O.OOE+OO I .25E+04 O.OOE+OO O.OOE+OO 2.42E+06 3.71 E+05 Sr-90 3.31 E+07 O.OOE+OO 6.66E+05 O.OOE+OO O.OOE+OO I .65E+07 7.65E+05 Sr-91 8.80E+O1 O.OOE+OO 351E+OO O.OOE+OO O.OOE+OO 6.07E+04 2.59E+05 Sr-92 9.52E+OO O.OOE+OO 4.06E-O1 O.OOE+OO O.OOE+OO 2 .74E+04 I 1 9E+05 Y-90 2.98E+03 O.OOE+OO 8.OOE+O1 O.OOE+OO O.OOE+OO 2.93E+05 5.59E+05 Y-91M 3.70E-O1 O.OOE+OO 1.42E-02 O.OOE+OO O.OOE+OO 3.20E+03 3.02E+O1 Y-91 6U61 E+05 O.OOE+OO 1 .77E+04 O.OOE+OO O.OOE+OO 2.94E+06 4U09E+05 Y-92 1 .47E+O1 O.OOE+OO 4.29E-O1 O.OOE+OO O.OOE+OO 2.68E+04 I .65E+05 Y-93 I .35E+02 O.OOE+OO 3.72E+OO O.OOE+OO O.OOE+OO 8.32E+04 5.79E+05 Zr-95 1 .46E+05 4.58E+04 3.15E+04 O.OOE+OO 6.74E+04 2.69E+06 I .49E+05 Zr-97 1 .38E+02 2.72E+O1 1 .26E+O1 OUOOE+OO 412E+O1 I .30E+05 6.30E+05 Nb-95 I .86E+04 I UO3EQ4 566E+03 O.OOE+OO 1 .OOE+04 7.51 E+05 9.68E+04 Mo-99 O.OOE+OO I .69E+02 3.22E+O1 O.OOE+OO 4.1 1 E+02 I .54E+05 2U69E+05 Tc- 99M I .38E03 3.86E-03 4.99E-02 O.OOE+OO 5.76E-02 I .15E+03 6.13E+03 Tc-1O1 5.92E-05 8.40E-05 8.24E-04 O.OOE+OO 1U52E-03 6.67E+02 8.72E-07 Ru-103 2.IOE+03 O.OOE+OO 8.96E+02 O.OOE+OO 7.43E+03 f.83E+05 I .09E+05 Ru-105 1 .12E+OO O.OOE+OO 4.34E-O1 O.OOE+OO I .41 E+OO 1 .82E+04 9U04E+04 Ru-106 9.84E+04 O.OOE+OO 1.24E+04 O.OOE+OO 1.90E+05 1.61E+07 9.60E+05 Ag-I I OM I U38E+04 I .31 E+04 7.99E+03 O.OOE+OO 2.50E+04 6.75E+06 2.73E+05

. CY-BY-1 70-301 Revision 14 Page 128 of 188 Table 4-10 (Continued)

Teen Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 O.OOE+OO 5.36E+05 7.50E+04 Te-127M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 Te-127 2.01 E÷OO 9.12E-O1 4.42E-O1 I .42E+OO 728E+OO I 12E+04 8.08E+04 Te-129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 Te-129 7.IOE-02 3.38E-02 I .76E-02 5.18E-02 2.66E-O1 3.30E+03 I .62E+03 Te-131M 9.84E+O1 6O1E+O1 4.02E+O1 7.25E+O1 4.39E+02 2.38E+05 6.21E+05 Te-1 31 1 .58E-02 8.32E-03 5.04E-03 1 .24E-02 6.1 8E-02 2.34E+03 I .51 E+O1 Te-132 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1.95E+03 4.49E+05 4.63E+05 1-130 6.24E+03 1.79E+04 7.17E+03 1.49E+06 2.75E+04 O.OOE+OO 9.12E+03 1-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 O.OOE+OO 6.49E+03 1-132 1.59E+03 438E+O3 J.58E+03 151E+05 6.92E+03 O.OOE+OO 1.27E+03 1-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 O.OOE+OO 1.03E+04 1-134 8.88E+02 2.32E+03 8.40E+02 3.95E÷04 366E+O3 O.OOE+OO 2.04E+O1 1-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 O.OOE+OO 695E+O3 Cs-134 5.02E+05 1.13E+06 5.49E+05 O.OOE+OO 3.75E+05 1.46E+05 9.76E+03 Cs-136 5.15E+04 1.94E+05 1.37E+05 O.OOE+OO 1.IOE+05 1.78E+04 1.09E+04 Cs-137 6.70E+05 8.48E+05 3.IIE+05 O.OOE+OO 3.04E+05 1.21E+05 8.48E+03 Cs-138 4.66E+02 8.56E+02 4.46E+02 O.OOE+OO 6.62E+02 Z.87E+O1 2.70E-O1 Ba-I 39 1 .34E+OO 944E-04 3.90E-02 O.OOE+OO 8.88E-04 6.46E+03 6.45E+03 Ba-140 5.47E+04 6.70E+O1 3.52E+03 O.OOE+OO 2.28E+O1 2.03E+06 229E+05 Ba-141 I .42E-O1 I .06E-04 4.74E-03 O.OOE+OO 9.84E-05 3.29E+03 7.46E-04 Ba-142 3.70E-02 3.70E-05 2.27E-03 O.OOE+OO 3.14E-05 I .91 E+03 4.79E-1O La-140 4.79E+02 2.36E+02 626E+O1 OOOE+OO O.OOE+OO 2.14E+05 4.87E+05 La-142 9.60E-O1 4.25E-O1 1.06E-O1 O.OOE+OO O.OOE+OO 1.02E+04 1.20E+04 Ce-141 2.84E+04 1.90E+04 2.17E+03 O.OOE+OO 8.88E+03 614E+05 1.26E+05 Ce-143 2.66E+02 1.94E+02 2.16E+O1 OOOE+OO 8.64E+O1 1.30E+05 2.55E+05 Ce-144 4.89E+06 2.02E+06 2.62E+05 O.OOE+OO 1.21E+06 1.34E+07 8.64E+05 Pr-I 43 1 .34E+04 5.31 E+03 6.62E+02 O.OOE+OO 3.09E+03 4.83E+05 2.1 4E+05 Pr-144 4.30E-02 1.76E-02 2.18E-03 O.OOE+OO 1.OIE-02 1.75E+03 2.35E-04 Nd-147 7.86E+03 8.56E+03 513E+02 O.OOE+OO 5.02E+03 3.72E+05 I .82E+05 W-187 1.20E+O1 9.76E+OO 3A3E+OO O.OOE+OO O.OOE+OO 4.74E+04 1.77E+05 Np-239 3.38E+02 2.88E+02 I .77E+O1 O.OOE+OO I OOE+02 6.49E+04 I .32E+05 Notes:

1) Units are mrem/yr per iCi/m3.

CY-BY-J 70-301 Revision 14 Page 129 of 188 Table 4-11 Child Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 C-14 359E+04 6.73E+03 673E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 Na-24 1 61 E+04 I .61 E+04 I .61 E+04 1 .61 E+04 I .61 E+04 I .61 E+04 I .61 E+04 Cr-51 O.OOE+OO O.OOE+OO 1.54E+02 8.55E+O1 2.43E+O1 1.70E+04 1.08E+03 Mn-54 O.OOE+OO 4.29E÷04 9.51 E+03 O.OOE+OO I .OOE+04 I .58E+06 2.29E+04 Mn-56 O.OOE+OO I .66E+OO 3.12E-O1 O.OOE+OO I .67E+OO I .31 E+04 I .23E+05 Fe-55 4.74E+04 2.52E+04 7.77E+03 O.OOE+OO O.OOE+OO I .1 1 E+05 2.87E+03 Fe-59 2.07E+04 334E+O4 I .67E+04 O.OOE+OO O.OOE+OO I .27E+06 7.07E+04 Co-58 O.OOE+OO I .77E+03 3.16E+03 OOOE+OO O.OOE+OO I .1 1 E+06 3.44E+04 Co-60 O.OOE+OO I .31 E+04 2.26E+04 O.OOE+OO O.OOE+OO 7.07E+06 9.62E+04 Ni-63 8.21 E+05 4.63E+04 2.80E+04 O.OOE+OO O.OOE+OO 2.75E+05 6.33E+03 Ni-65 2.99E+OO 2.96E-O I I .64E-O1 O.OOE+OO O.OOE+OO 8. 1 8E+03 8.40E+04 Cu-64 O.OOE+OO I .99E+OO I .07E+OO O.OOE+OO 6.03E+OO 9.58E+03 3.67E+04 Zn-65 4.26E+04 1.13E+05 7.03E+04 O.OOE+OO 7.14E+04 9.95E+05 1.63E÷04 Zn-69 6.70E-02 9.66E-02 8.92E-03 O.OOE+OO 5.85E-02 I .42E+03 I .02E+04 Br-83 O.OOE+OO O.OOE+OO 4.74E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 5.48E+02 O.OOE+OO O.OOE÷OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.53E+O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO I .98E+05 I .14E+05 O.OOE+OO O.OOE+OO O.OOE+OO 7.99E+03 Rb-88 O.OOE+OO 5.62E+02 3.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO I .72E+O1 Rb-89 O.OOE+OO 3.45E+02 2.90E+02 O.OOE+OO O.OOE+OO O.OOE+OO I .89E+OO Sr-89 5.99E+05 O.OOE+OO 112E+04 O.OOE+OO O.OOE+OO 2.16E+06 1.67 E+05 Sr-90 3.85E+07 O.OOE+OO 7.66E+05 O.OOE+OO O.OOE+OO I .48E+07 3.43E+05 Sr-91 I .21 E+02 O.OOE+OO 4.59E+OO O.OOE+OO O.OOE+OO 5.33E+04 1 .74E+05 Sr-92 I .31 E+O1 O.OOE+OO 5.25E-O1 O.OOE+OO O.OOE+OO 2.40E+04 2.42E+05 Y-90 4.1 1 E+03 O.OOE+OO I .1 1 E+02 O.OOE+OO O.OOE+OO 2.62E+05 2.68E+05 Y-91 M 5.07E-O1 O.OOE+OO I .84E-02 O.OOE+OO O.OOE+OO 2.81 E+03 I .72E+03 Y-91 9.14E+05 O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1.84E+05 Y-92 2.04E+O1 O.OOE+OO 5.81 E-O1 O.OOE+OO O.OOE+OO 2.39E+04 2.39E+05 Y-93 I .86E+02 O.OOE+OO 5.1 1 E+OO O.OOE+OO O.OOE+OO 7.44E+04 3.89E÷05 Zr-95 I .90E+05 4. 1 8E+04 3.70E+04 O.OOE+OO 5.96E+04 2.23E+06 6. 1 1 E÷04 Zr-97 1.88E+02 2.72E+O1 1.60E+O1 O.OOE+OO 3.89E+O1 1.13E+05 3.51E+05 Nb-95 2.35E+04 9. 1 8E+03 6.55E+03 O.OOE+OO 8.62E+03 6. 1 4E+05 3.70E+04 Mo-99 O.OOE+OO I .72E+02 4.26E+O1 O.OOE+OO 3.92E+02 I .35E+05 I .27E÷05 Ic- 99M I .78E-03 3.48E-03 5.77E-02 O.OOE+OO 5.07E-02 9.51 E+02 4.81 E+03 Tc-1 01 8. 1 OE-05 8.51 E-05 I .08E-03 O.OOE+OO I .45E-03 5.85E+02 I .63E+O1 Ru-103 2.79E+03 O.OOE+OO 1.07E+03 O.OOE+OO 7.03E+03 6.62E+05 4.48E+04 Ru-105 1.53E+OO O.OOE+OO 5.55E-O1 O.OOE+OO 1.34E+OO 1.59E+04 9.95E+04 Ru-106 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+OO 1.84E+05 1.43E+07 4.29E+05 Ag-IbM 1.69E+04 1.14E+04 9.14E+03 O.OOE+OO 2.12E+04 5.48E+06 1.OOE÷05

CY-BY-1 70-301 Revision 14 Page 130 of 188 Table 4-1 1 (Continued)

Child Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-1 25M 6.73E+03 2.33E+03 9. 1 4E+02 I 92E+03 O.OOE+OO 4.77E+05 3.38 E+04 Te-127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E÷06 7.14E+04 Te-127 2.77E+OO 9.51 E-O1 6.1 1 E-O1 I .96E÷OO 7.07E+OO I .OOE+04 5.62E+04 Te-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 J.82E+05 Te-1 29 9.77E-02 3.50E-02 2.38E-02 7. 1 4E-02 2.57E-O1 2.93E+03 2.55E+04 Te-131M 1.34E+02 5.92E+O1 5.07E+O1 9.77E+O1 4.OOE+02 2.06E+05 3.08E+05 Te-1 31 2.1 7E-02 8.44E-03 6.59E-03 I .70E-02 5.88E-02 2.05E+03 I .33E÷03 Te-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 1-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 O.OOE+OO 5.IIE+03 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 O.OOE÷OO 2.84E+03 1-132 2.12E+03 4.OZE+03 1.88E+03 1.94E+05 6.25E+03 O.OOE÷OO 3.20E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+OO 5.48E+03

-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 O.OOE+OO 9.55E+02 1-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 O.OOE+OO 4.44E+03 Cs-I 34 6.51 E+05 I .01 E+06 2.25E+05 O.OOE+OO 3.30E+05 I .21 E÷05 3.85E+03 Cs-136 6.51E+04 1.71E+05 1.16E+05 O.OOE+OO 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 I.28E+05 O.OOE+OO 2.82E+05 1.04E+05 3.62E+03 Cs-138 6.33E+02 8.40E+02 5.55E+02 O.OOE+OO 6.22E+02 6.81E+O1 2.70E+02 Ba-139 1.84E+OO 9.84E-04 5.37E-02 O.OOE+OO 8.62E-04 5.77E+03 5.77E+04 Ba-I 40 7.40E+04 6.48E+OI 4.33E+03 O.OOE+OO 2. 1 I E+OI I .74E+06 I .02E+05 Ba-141 I .96E-OI I .09E-04 6.36E-03 O.OOE+OO 9.47E-05 2.92E+03 2.75E+02 Ba-I42 5.OOE-02 3.60E-05 2.79E-03 O.OOE+OO 2.91E-05 I.64E+03 2.74E+OO La-140 6.44E+02 2.25E+02 7.55E+O1 O.OOE+OO O.OOE+OO 1.83E+05 2.26E+05 La-142 I.30E+OO 4.IIE-OI I.29E-OI O.OOE+OO O.OOE+OO 8.70E+03 7.59E+04 Ce-14I 3.92E+04 I .95E+04 2.90E+03 O.OOE+OO 8.55E+03 5.44E+05 5.66E+04 Ce-I43 3.66E+02 I.99E+02 2.87E+O1 O.OOE+OO 8.36E+OI I.15E+05 I.27E+05 Ce-144 6.77E+06 2.12E+06 3.61E+05 O.OOE+OO I.17E+06 I.20E+07 3.89E+05 Pr-143 I.85E+04 5.55E+03 9.14E+02 O.OOE+OO 3.OOE+03 4.33E+05 9.73E+04 Pr-144 5.96E-02 I .85E-02 3.OOE-03 O.OOE+OO 9.77E-03 I .57E÷03 I .97E+02 Nd-I 47 1 .08E+04 8.73E+03 6.8 I E+02 O.OOE+OO 4.8 I E+03 3.28E+05 8.21 E+04 W-187 I.63E+OI 9.66E+OO 4.33E+OO O.OOE+OO O.OOE+OO 4.IIE÷04 9.IOE+04 Np-239 4.66E+02 3.01 E+02 2.35E+O1 O.OOE+OO 9.73E+OI 5.81 E+04 6.40E+04 Notes:

I) Units are mrem/yr per iCiIm3.

CY-BY-1 70-301 Revision 14 Page 131 of 188 Table 4-12 Infant Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lunq Gl-LLI H-3 O.OOE+OO 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 C-14 2.65E+04 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 Na-24 I .06E+04 I .06E+04 I .06E+04 1 .06E+04 I .06E+04 I .06E+04 I .06E+04 Cr-51 O.OOE+OO OOOE+OO 8.95E+O1 5.75E+O1 1 .32E+O1 I .28E+04 3.57E+02 Mn-54 O.OOE+OO 2.53E+04 4.98E+03 O.OOE+OO 4.98E+03 I .OOE+06 7.06E+03 Mn-56 O.OOE+OO 1.54E+OO 2.21E-O1 O.OOE+OO 1.IOE+OO 1.25E+04 7.17E+04 Fe-55 1.97E÷04 1.17E+04 3.33E+03 O.OOE+OO O.OOE+OO 8.69E+04 1.09E+03 Fe-59 1 .36E+04 2.35E+04 9.48E+03 O.OOE+OO O.OOE+OO I .02E+06 2.48E+04 Co-58 O.OOE+OO 1.22E+03 1.82E+03 O.OOE+OO O.OOE+OO 7.77E+05 1.IIE+04 Co-60 O.OOE+OO 8.02E+03 1.18E+04 O.OOE+OO O.OOE+OO 4.51E+06 3.19E+04 Ni-63 3.39E+05 2.04E+04 1 .16E+04 O.OOE+OO O.OOE+OO 2.09E+05 2.42E+03 Ni-65 2.39E+OO 2.84E-O1 1.23E-O1 O.OOE+OO O.OOE+OO 8.12E+03 5.OIE+04 Cu-64 O.OOE+OO I 88E+OO 7.74E-O1 O.OOE+OO 3.98E+OO 9.30E+03 1 5OE+O4 Zn-65 I .93E+04 6.26E+04 3.1 1 E+04 O.OOE+OO 325E+04 6.47E+05 5.14E+04 Zn-69 539E-O2 9.67E-02 7. 1 8E-03 OOOE+OO 4.02E-02 I .47E+03 I .32E+04 Br-83 O.OOE+OO O.OOE+OO 3.81 E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 OOOE+OO O.OOE+OO 4.OOE+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.04E+O1 O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO Rb-86 O.OOE+OO 1 .90E+05 8.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 Rb-88 O.OOE+OO 5.57E+02 2.87E+02 O.OOE+OO OOOE+OO O.OOE+OO 3.39E+02 Rb-89 O.OOE+OO 3.21 E+02 2.06E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.82E+O I Sr-89 3.98E+05 O.OOE+OO I .14E+04 O.OOE+OO O.OOE+OO 2.03E+06 6.40E+04 Sr-90 I .55E+07 O.OOE÷OO 3.1 2E+05 O.OOE+OO O.OOE+OO I .1 2E+07 I .31 E+05 Sr-91 9.56E+OI O.OOE+OO 3.46E+OO O.OOE+OO O.OOE+OO 5.26E+04 7.34E+04 Sr-92 I .05E+O1 O.OOE+OO 3.91 E-O1 O.OOE+OO O.OOE+OO 2.38E+04 I .40E+05 Y-90 3.29E+03 O.OOE+OO 8.82E+OI O.OOE+OO O.OOE+OO 2.69E+05 I .04E+05 Y-91 M 4.07E-OI O.OOE+OO I .39E-02 OOOE+OO O.OOE+OO 2.79E+03 2.35E+03 Y-91 5.88E+05 O.OOE+OO I .57E+04 O.OOE+OO OOOE+OO 2.45E+06 7.03E+04 Y-92 I .64E+OI O.OOE+OO 4.61 E-O1 O.OOE+OO O.OOE+OO 2.45E+04 I .27E+05 Y-93 1 .50E+02 O.OOE+OO 4.07E+OO O.OOE+OO O.OOE+OO 7.64E+04 I .67E+05 Zr-95 I I 5E+05

. 2.79E+04 2.03E+04 O.OOE+OO 3.1 1 E+04 I .75E+06 2. I ZE+04 Zr-97 I .50E+02 2.56E+O1 I .1 7E+OI O.OOE+OO 2.59E+O1 I .1 OE+05 I .40E+05 Nb-95 I .57E+04 6.43E+03 3.78E+03 O.OOE+OO 4.72E+03 4.79E+05 I .27E+04 Mo-99 O.OOE+OO I 65E+O2 3.23E+O1 O.OOE+OO 2.65E+02 I .35E+05 4.87E+04 Tc- 99M I .40E-03 2.88E-03 3.72E-02 O.OOE+OO 3.1 1 E-02 8.1 I E+02 203E+03 Ic-I 01 65I E-05 8.23E-05 8. 1 2E-04 OOOE+OO 9.79E-04 5.84E+02 8.44E+02 Ru-I 03 2.02E+03 O.OOE+OO 6.79E+02 O.OOE+OO 4.24E+03 5.52E+05 I .61 E+04 Ru-105 1.22E+OO O.OOE+OO 4.IOE-OI O.OOE+OO 8.99E-OI I.57E+04 4.84E+04 Ru-I06 8.68E+04 O.OOE+OO I.09E+04 O.OOE+OO I.07E+05 I.16E+OZ I.64E+05 Ag-I I OM 9.98E+03 7.22E+03 5.OOE+03 O.OOE+OO I .09E+04 3.67E+06 3.30E+04

CY-BY-1 70-301 Revision 14 Page 132 of 188 Table 4-12 (Continued)

Infant Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 4.76E+03 1.99E+03 6.58E+02 162E+03 O.OOE+OO 4.47E+05 1.29E+04 Te-127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 Te-127 2.23E+OO 9.53E-O1 4.89E-O1 1.85E+OO 4.86E+OO 1.03E+04 2.44E+04 Te-129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 168E+06 6.90E+04 Te-1 29 7.88E-02 3.47E-02 I .88E-02 6.75E-02 I .75E-O1 3.OOE+03 2.63E+04 Te-131M 1.07E+02 5.50E+O1 363E+O1 8.93E+O1 2.65E+02 1.99E+05 1.19E+05 Te-1 31 1 .74E-02 8.22E-03 5.OOE-03 I .58E-02 399E-O2 2.06E+03 8.22E+03 Te-132 3.72E+02 2.37E+02 1.76E+02 2.79E+02 1.03E+03 3.40E+05 4AIE+04 I-I 30 6.36E+03 I .39E+04 5.57E+03 I .60E+06 1 .53E+04 O.OOE+OO I .99E+03 1-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 O.OOE+OO 1.06E+03 1-132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 O.OOE+OO 1.90E+03 1-133 1.32E+04 J.92E+04 5.60E+03 3.56E+06 2.24E+04 O.OOE+OO 2.16E+03 1-134 9.21E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 O.OOE+OO 1.29E+03 1-135 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 O.OOE+OO 1.83E+03 Cs-I 34 3.96E÷05 7.03E+05 7.45E+04 O.OOE+OO I .90E+05 7.97E+04 I .33E+03 Cs-136 4.83E+04 I.35E+05 5.29E+04 O.OOE+OO 5.64E+04 I.18E+04 I.43E+03 Cs-137 549E+05 6.12E+05 455E+O4 O.OOE+OO 1.72E+05 7.13E+04 133E+03 Cs-138 5.05E+02 7.81E+02 3.98E+02 O.OOE+OO 4.1OE+02 6.54E+O1 8.76E+02 Ba-139 I .48E+OO 9.84E-04 4.30E-02 O.OOE+OO 5.92E-04 5.95E+03 5.IOE+04 Ba-140 5.60E+04 5.60E+O1 2.90E+03 O.OOE+OO I.34E+OI 1.60E+06 3.84E+04 Ba-141 I.57E-O1 I.08E-04 4.97E-03 O.OOE+OO 65OE-O5 2.97E+03 475E+03 Ba-142 3.98E-02 3.30E-05 1.96E-03 O.OOE+OO 1.90E-05 1.55E+03 6.93E+02 La-140 5.05E+02 2.OOE+02 5.15E+OI O.OOE+OO O.OOE+OO 1.68E+05 8.48E+04 La-142 I .03E+OO 3.77E-O1 9.04E-02 O.OOE+OO O.OOE+OO 8.22E+03 595E+O4 Ce-141 2.77E+04 I.67E+04 I.99E+03 O.OOE+OO 5.25E+03 5.17E+05 2.16E+04 Ce-I 43 2.93E+02 I .93E+02 2.21 E+OI O.OOE+OO 5.64E+OI I I 6E+05

. 4.97E+04 Ce-144 319E+06 I .21 E+06 I .76E+05 O.OOE+OO 5.38E+05 9.84E+06 I .48E+05 Pr-143 1.40E+04 5.24E+03 6.99E+02 O.OOE+OO I.97E+03 4.33E+05 3.72E+04 Pr-144 4.79E-02 I.85E-02 2.41E-03 O.OOE+OO 6.72E-03 I.61E+03 4.28E+03 Nd-I 47 7.94E+03 8. 1 3E+03 5.OOE+02 O.OOE+OO 3. 1 5E+03 3.22E+05 3. 1 2E+04 W-187 1.30E+OI 9.02E+OO 3.12E+OO O.OOE+OO O.OOE+OO 3.96E+04 3.56E+04 Np-239 3.71 E+02 2.98E+02 I .88E+OI O.OOE+OO 6.62E+OI 5.95E+04 2.49E+04 Notes:

I) Units are mrem/yr per j.iCiIm3.

CY-BY-1 70-301 Revision 14 Page 133 of 188 Table 4-13 Adult Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO I .29E+03 I 29E+03 I .29E+03 1 .29E+03 I .29E+03 1 .29E+03 C-14 8.97E+05 I .79E+05 I .79E+05 I .79E+05 I .79E+05 I .79E+05 I .79E+05 Na-24 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 Cr-51 OOOE+OO O.OOE+OO 4.64E+04 2.77E+04 1.02E÷04 6.15E+04 1.IZE÷07 Mn-54 O.OOE+OO 3.13E+08 597E+O7 O.OOE+OO 9.31E+07 O.OOE+OO 9.58E+08 Mn-56 O.OOE+OO I .54E+O1 2.73E+OO O.OOE+OO I .95E+O1 O.OOE+OO 4.91 E+02 Fe-55 2.IOE+08 1.45E+08 3.38E+07 O.OOE+OO O.OOE+OO 8.08E+07 8.31E+07 Fe-59 I .26E+08 2.96E+08 I .13E+08 O.OOE+OO OOOE+OO 8.27E+07 9.87E+08 Co-58 O.OOE+OO 3.08E+07 6.90E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+08 Co-60 O.OOE+OO 1.67E+08 3.69E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.14E÷09 Ni-63 1.04E+1O 7.21E+08 3.49E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.50E+08 Ni-65 5.97E+O1 7.75E+OO 3.54E+OO O.OOE+OO O.OOE+OO O.OOE+OO I .97E+02 Cu-64 O.OOE+OO 9.09E+03 4.27E+03 O.OOE+OO 229E+04 O.OOE+OO 7.75E+05 Zn-65 3.17E+08 1.OIE+09 456E+O8 O.OOE+OO 6.75E+08 O.OOE+OO 6.36E+08 Zn-69 4.95E-06 9A8E-06 6.59E-07 O.OOE+OO 6.16E-06 O.OOE+OO I .42E-06 Br-83 O.OOE+OO O.OOE+OO 3.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.32E+OO Br-84 O.OOE+OO O.OOE+OO 2.20E-1 I O.OOE+OO O.OOE+OO O.OOE+OO I .72E-1 6 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE÷OO Rb-86 O.OOE+OO 2.20E+08 I 03E+08 O.OOE+OO OOOE+OO OOOE+OO 4.34E+O7 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 9.95E+09 O.OOE+OO 2.86E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1 .60E+09 Sr-90 6.95E+11 O.OOE+OO 1.40E+1O O.OOE+OO O.OOE+OO O.OOE+OO 1.75E+1O Sr-91 3.01 E+05 O.OOE+OO I .22E+04 O.OOE+OO O.OOE+OO O.OOE+OO I .43E+06 Sr-92 4. 1 2E+02 O.OOE+OO I .78E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 8. 1 7E+03 Y-90 I .33E+04 O.OOE+OO 3.57E+02 O.OOE+OO O.OOE+OO O.OOE+OO I .41 E+08 Y-91M 4.93E-09 O.OOE+OO 1.91E-1O O.OOE+OO O.OOE+OO O.OOE+OO 1.45E-08 Y-91 5.12E+06 O.OOE+OO I .37E+05 OOOE+OO O.OOE+OO O.OOE+OO 2.82E+09 Y-92 8.95E-O1 O.OOE+OO 2.62E-02 O.OOE+OO O.OOE+OO O.OOE+OO I .57E+04 Y-93 I .67E+02 O.OOE+OO 462E+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.31 E+06 Zr-95 1.18E+06 3.77E+05 2.55E+05 OOOE+OO 5.92E+05 O.OOE+OO 1.20E+09 Zr-97 3.35E+02 6.77E+O1 3.09E+O1 O.OOE+OO 1.02E+02 O.OOE+OO 2.IOE+07 Nb-95 I .43E+05 7.95E+04 4.27E+04 OOOE+OO f.86E+04 O.OOE+OO 4.83E+08 Mo-99 O.OOE+OO 6.14E+06 I .1 7E+06 O.OOE+OO I .39E+07 O.OOE+OO I .42E÷07 Tc- 99M 3.06E+OO 8.64E+OO 1.IOE+02 O.OOE+OO 1.31E+02 4.23E+OO 5.IIE+03 Tc-1O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 4.77E+06 O.OOE+OO 2.05E+06 O.OOE+OO 1.82E+07 O.OOE+OO 5.57E+08 Ru-105 5.27E+O1 O.OOE+OO 208E+O1 O.OOE+OO 6.81E+02 O.OOE+OO 3.23E+04 Ru-106 193E+08 O.OOE+OO 2.44E+07 O.OOE+OO 3.72E+08 O.OOE+OO 1.25E+1O Ag-IbM 105E+07 9.75E+06 5.79E+06 O.OOE+OO 1.92E+OZ O.OOE+OO 3.98E+09

CY-BY-1 70-301 Revision 14 Page 134 of 188 Table 4-13 (Continued)

Adult Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 9.67E+07 3.50E+07 1.30E+07 2.91E+07 3.93E+08 O.OOE+OO 3.86E+08 Te-127M 3.49E+08 1.25E+08 4.26E+Of 8.92E+07 1.42E+09 O.OOE+OO 1.17 E+09 Te-127 5.68E+03 2.04E+03 1.23E+03 4.21E+03 2.31E+04 O.OOE+OO 4.48E+05 Te-129M 2.51E+08 9.37E+O7 3.97E+07 8.62E+07 1.05E+09 O.OOE+OO 1.26E+09 Te-1 29 7 I 4E-04

. 2 .68E-04 I 74E-04

. 5 .48 E-04 3.OOE-03 0 .OOE+OO 5 .39 E-04 Te-131M 9.09E+05 4.45E+05 3.71E+05 7.04E+05 4.50E+06 O.OOE+OO 4.41E+07 Te-131 1.26E-15 5.26E-16 3.97E-16 1.03E-15 5.51E-15 O.OOE+OO 1.78E-16 Te-132 4.28E+06 2.77E+06 2.60E+06 3.06E+06 2.67E+07 O.OOE+OO 1.31E+08 1-130 3.89E+05 1.15E+06 4.52E+05 9.72E+07 1.79E+06 O.OOE+OO 9.87E+05 1-131 8.07E+07 1.15E+08 6.62E+07 3.78E+1O 1.98E+08 O.OOE+OO 3.05E+07 1-132 5.58E+O1 1.49E+02 5.22E+O1 5.22E+03 2.38E+02 O.OOE+OO 2.80E+O1

-133 2.08E+06 3.62E+06 1.IOE+06 5.32E+08 6.31E+06 O.OOE+OO 3.25E+06 1-134 8.55E-05 2.32E-04 8.31E-05 4.02E-03 3.69E-04 O.OOE+OO 2.02E-07 1-135 3.87E+04 1.OIE+05 3.74E+04 6.68E+06 1.62E+05 O.OOE+OO 1.14E+05 Cs-134 4.67E+09 1.IIE+1O 9.08E+09 O.OOE+OO 3.59E+09 1.19E+09 1.94E+08 Cs-136 4.25E+07 1.68E+08 1.21E+08 O.OOE+OO 9.33E+07 1.28E+07 1.90E+07 Cs-137 6.36E+09 8.70E+09 5.70E+09 O.OOE+OO 2.95E+09 9.81E+08 1.68E+08 Cs-138 3.32E-11 6.56E-11 3.25E-11 O.OOE+OO 4.82E-11 4.76E-12 2.80E-16 Ba-I 39 2.71 E-02 I .93E-05 7.92E-04 O.OOE+OO I .80E-05 I .09E-05 4.80E-02 Ba-140 I.29E+08 I.6IE+05 8.42E+06 O.OOE+OO 5.49E+04 9.24E+04 2.65E+08 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-I40 I .98E+03 9.97E+02 2.63E+02 O.OOE+OO O.OOE+OO O.OOE+OO 7.32E+07 La-142 I .94E-04 8.83E-05 2.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO 6.45E-O1 Ce-I41 I .97E+05 I .33E+05 I .51 E+04 O.OOE+OO 6.19E+04 O.OOE+OO 5.09E+08 Ce-I 43 9.94E+02 7.35E+05 8. I 3E+OI O.OOE+OO 3.24E+02 O.OOE+OO 2.75E+07 Ce-I44 3.29E+07 I .38E+07 I .77E+06 O.OOE+OO 8.16E+06 O.OOE+OO I .1 1 E+IO Pr-I 43 6.27E+04 2.51 E+04 3. 1 I E+03 O.OOE+OO I .45E+04 O.OOE+OO 2.75E+08 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 3.37E+04 3.90E+04 2.33E+03 O.OOE+OO 2.28E+04 O.OOE+OO I.87E+08 W-187 3.79E+04 3.17E+04 1.IIE+04 O.OOE+OO O.OOE+OO O.OOE+OO I.04E+07 Np-239 I .42E+03 I .40E+02 7.72E+OI O.OOE+OO 4.37E+02 O.OOE+OO 2.87E+07 Notes:

1) Units are m2 mrem/yr per tCi/sec.

2) For H-3 and C-I4, the units are mrem/yr per jiCiIm3.

CY-BY-i 70-301 Revision 14 Page 135 of 188 Table 4-14 Teen Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lunq GI-LLI H-3 O.OOE+OO I .47E+03 1 .47E+03 I .47E+03 I .47E+03 I .47E+03 I .47E+03 C-14 1 .45E+06 2.91 E+05 2.91 E+05 291 E+05 2.91 E+05 2.91 E+05 2.91 E+05 Na-24 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 Z39E+05 Cr-51 O.OOE+OO O.OOE+OO 6.16E+04 342E+04 1.35E+04 8.79E+04 1.03E+07 Mn-54 O.OOE+OO 4.54E+08 9.OIE+07 O.OOE+OO 1.36E+08 O.OOE+OO 9.32E+08 Mn-56 OOOE+OO 1.39E+O1 2.47E+OO O.OOE+OO 1.76E+O1 OOOE+OO 9.13E+02 Fe-55 3.26E+08 2.31 E+08 5.39E+07 O.OOE+OO O.OOE+OO I .47E+08 1 .OOE+08 Fe-59 1 .79E+08 4.18E÷08 I .61 E+08 O.OOE÷OO O.OOE+OO I .32E+08 9.89E+08 Co-58 O.OOE+OO 4.37E+07 I .01 E+08 O.OOE÷OO O.OOE+OO O.OOE+OO 6.02E+/-08 Co-60 O.OOE+OO 2.49E+08 56OE+O8 O.OOE+OO O.OOE+OO O.OOE+OO 3.24E÷09 Ni-63 I .61 E+1 0 1 .1 3E+09 5.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO I .81 E+08 Ni-65 5.55E+O1 7.IOE+OO 3.23E+OO O.OOE+OO O.OOE+OO O.OOE+OO 385E+O2 Cu-64 O.OOE+OO 8.24E+03 3.87E+03 OOOE+OO 2.08E+04 O.OOE+OO 6.39E+05 Zn-65 4.24E+08 I .47E+09 6.86E+08 O.OOE+OO 9.41 E+08 O.OOE+OO 6.23E+08 Zn-69 4.64E-06 8.84E-06 6.19E-07 O.OOE+OO 578E-06 O.OOE+OO I .63E-05 Br-83 OOOE+OO O.OOE+OO 2.81 E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+/-OO Br-84 O.OOE+OO O.OOE+OO 2.OOE-1 I O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.75E+08 1 .29E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.06 E+07 Rb-88 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Rb-89 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-89 1.51E+10 0.OOE+00 4.33E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.80E+09 Sr-90 9.22E+1 1 0.OOE+00 I .84E+1 0 0.OOE+00 0.OOE+00 0.OOE+00 2. 1 1 E+f 0 Sr-91 2.81 E+05 0.OOE+00 1 .12E+04 0.OOE+00 0.OOE+00 0.OOE+00 1 .27E+06 Sr-92 3.84E+02 0.OOE+00 1 .64E+01 0.OOE+00 0.OOE+00 0.OOE+00 9.78E+03 Y-90 I .24E+04 0.OOE+00 3.35E+02 0.OOE+00 0.OOE+00 0.OOE+00 I .02E+08 Y-91 M 4.59E-09 0.OOE+00 1 .75E-1 0 0.OOE+00 0.OOE+00 0.OOE+00 2.1 fE-Of Y-91 f.84E+06 0.OOE+00 2.IOE+O5 O.OOE+00 0.OOE+00 0.OOE+00 3.21 E+09 Y-92 8.41 E-01 0.OOE+00 2.43E-02 O.OOE+00 0.OOE+00 0.OOE+00 2.31 E+04 Y-93 I .57E+02 0.OOE+00 4.30E+O0 0.OOE+00 0.OOE+00 O.OOE+00 4.80 E+06 Zr-95 1 .f2E+06 5.44E+05 3.74E+05 0.OOE+00 f.99E+05 0.OOE+00 1 .26E+09 Zr-9f 3.IOE+02 6.14E+01 2.83E+01 0.OOE+00 9.31E+01 0.OOE+00 1.66E+Of Nb-95 I .93E+05 I .07E+05 5.90E+04 0.OOE+00 I .04E+05 0.OOE+00 4.58E+O8 Mo-99 0.OOE+00 5.63E+06 I .07E+06 0.OOE+00 I .29E+0f 0.OOE+00 1 .01 E+07 Ic- 99M 2.70E+00 7.52E+00 9.75E+O1 0.OOE+00 I I 2E+02

. 4. 1 ZE+00 4.94E+O3 Tc-101 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+OO Ru-103 6.82E+06 0.OOE+00 2.91E+06 0.OOE+00 2.40E+0f 0.OOE+00 5.69E+08 Ru-105 4.90E+01 0.OOE+00 1.90E+O1 00E+00 6.18E+02 0.OOE+00 3.95E÷O4 Ru-I 06 3.09E+08 0.OOE+0O 3.90E+07 0.OOE+00 5.97E+08 O.OOE+00 I .48E+1 0 Ag-I I OM I .52E+0f I .44E+0f 8.73E+06 i00E+00 2.74E+07 O.OOE+00 4.03E+09

CY-BY-1 70-301 Revision 14 Page 136 of 188 Table 4-14 (Continued)

Teen Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.49E+08 5.35E+07 1.99E+07 4.15E+07 O.OOE+OO O.OOE+OO 4.38E+08 Te-127M 5.51E+08 196E+08 6.56E+07 1.31E+08 2.24E+09 OOOE+OO 1.37 E+09 Te-1 27 5.36E+03 1 .90E+03 I .1 5E+03 3.70E+03 2. 1 7E+04 O.OOE+OO 4. 1 4E+05 Te-129M 3.61E+08 1.34E+08 5.72E+07 1.17E+08 1.51E+09 O.OOE+OO 1.36E+09 Te-1 29 6.68E-04 2.49E-04 1 .63E-04 4.77E-04 2.80E-03 O.OOE+OO 3.65E-03 Te-131M 8.42E+05 4.04E+05 3.37E+05 6.07E+05 4.21E+06 O.OOE+OO 3.24E+07 Te-131 1.17E-15 4.82E-16 3.66E-16 9.OIE-16 5.IIE-15 O.OOE+OO 9.60E-17 Te-132 3.89E+06 2.46E+06 2.32E+06 2.60E+06 2.36E+07 O.OOE+OO 7.81E+07 I-I 30 3.47E+05 I .01 E+06 4.01 E+05 8.20E+07 1 .55E+06 O.OOE+OO 7.73E+05 I-i 31 7.68E+07 I .08E+08 5.78E+07 3. 1 4E+1 0 1 .85E+08 O.OOE+OO 2. 1 3E+07 I-I 32 5.03E+O1 1 .32E+02 4.72E+O1 4.43E+03 2.07E+02 O.OOE+OO 5.73E+O1 I-I 33 1 .93E+06 3.28E+06 I .OOE+06 4.58E+08 5.75E+06 O.OOE+OO 2.48E+06 I-I 34 7.73E-05 2.05E-04 7.36E-05 3.41 E-03 3.23E-04 O.OOE+OO 2.70E-06 1-135 3.49E+04 8.99E+04 3.33E+04 5.78E+06 1.42E+05 O.OOE+OO 9.97E+04 Cs-I 34 7.1 OE+09 I .67E+I 0 7.75E+09 O.OOE+OO 5.31 E+09 2.03E+09 2.08E+08 Cs-I 36 4.35E+07 I .71 E+08 I .1 5E+08 O.OOE+OO 9.31 E+07 I .47E+07 I .38E+07 Cs-137 I.OIE+IO I.35E+IO 4.69E+09 O.OOE+OO 4.59E+09 I.78E+09 I.92E+08 Cs-138 3.07E-II 5.89E-II 2.94E-II O.OOE+OO 4.35E-II 5.06E-12 2.67E-14 Ba-I 39 2.55E-02 I .79E-05 7.42E-04 O.OOE+OO I .69E-05 I .23E-05 2.27E-OI Ba-140 I .38E+08 I .69E+05 8.90E+06 O.OOE+OO 5.74E+04 I .14E+05 2.I3E+08 Ba-I 41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00 E+O0 Ba-142 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 La-I40 I .81 E+03 8.88E+02 2.36E+02 0.OOE+00 0.OOE+00 0.OOE+00 5.IOE+07 La-I42 I .78E-04 7.92E-05 I .97E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.41 E+00 Ce-I4I 2.83E+05 I .89E+05 2.I7E+/-04 0.OOE+00 8.89E+04 0.OOE+00 5.40E+08 Ce-I43 9.29E+02 6.76E+05 7.55E+0I 0.OOE+00 3.03E+02 0.OOE+00 2.03E+07 Ce-I44 5.27E+07 2.18E+07 2.83E+06 0.OOE+00 I .30E+07 0.OOE+00 I .33E+I0 Pr-I 43 7.01 E+04 2.80E+04 3.49E+03 0.OOE+00 I .63E+04 0.OOE+00 2.31 E+08 Pr-I44 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nd-I47 3.67E+04 4.OOE+04 2.39E+03 0.OOE+00 2.35E+04 0.OOE+00 I .44E+08 W-187 3.53E+04 2.87E+04 I.OIE+04 0.OOE+00 0.OOE+00 0.OOE+00 7.78E+06 Np-239 I.38E+03 I.30E+02 7.24E+OI 0.OOE+00 4.09E+02 0.OOE+00 2.IOE+07 Notes:

I) Units are m2 mrem/yr per pCi/sec.

2) For H-3 and C-I4, the units are mrem/yr per pCi/rn3.

CY-BY-1 70-301 Revision 14 Page 137 of 188 Table 4-15 Child Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 C-14 3.50E+06 7.01 E+05 7.01 E+05 7.01 E+05 7.01 E+05 7.01 E+05 7.01 E+05 Na-24 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 Cr-51 O.OOE+OO O.OOE+OO 1.17E+05 6A9E+04 1.77E+04 1.18E+05 6.20E+06 Mn-54 O.OOE+OO 6.65E+08 I .77E+08 O.OOE+OO 1 86E+O8 O.OOE+OO 5.58E+08 Mn-56 O.OOE+OO I 82E+O1 4.IOE+OO O.OOE+OO 2.20E+O1 O.OOE+OO 2.63E+03 Fe-55 8.01 E+08 425E+O8 I .32E+08 O.OOE+OO OOOE+OO 2.40E+08 7.87E+07 Fe-59 3.97E+08 6.42E+08 3.20E+08 O.OOE+OO O.OOE+OO I .86E+08 6.69E+08 Co-58 OOOE+OO 6.45E+07 1 .97E÷08 OOOE+OO O.OOE+OO O.OOE+OO 3.76E+08 Co-60 O.OOE+OO 3.78E+08 I .12E+09 O.OOE+OO OOOE+OO O.OOE+OO 2.IOE+09 Ni-63 3.95E+1O 2.IIE+09 1.34E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.42E+08 Ni-65 I .02E+02 9.59E+OO 5.60E+OO O.OOE+OO O.OOE+OO O.OOE+OO I .18E+03 Cu-64 O.OOE+OO I .09E+04 6.56E+03 O.OOE+OO 2.62E+04 O.OOE+OO 5.IOE+05 Zn-65 8.12E+08 2.16E+09 1 .35E+09 O.OOE+OO I .36E+09 OOOE+OO 3.80E+08 Zn-69 8.56E-06 I .24E-05 1 .14E-06 O.OOE+OO 7.50E-06 O.OOE+OO f.80E-04 Br-83 O.OOE+OO O.OOE+OO 5.18E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 3.39E-1 1 O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.54E+08 2.79E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE÷OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE÷OO O.OOE+OO Sr-89 3.59E+1O O.OOE+OO 1.03E+09 O.OOE+OO O.OOE÷OO O.OOE+OO 1.39E+09 Sr-90 1.87E+12 O.OOE+OO 3.77E+1O O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+1O Sr-91 5.1 7E+05 O.OOE+OO I .95E+04 O.OOE+OO O.OOE+OO O.OOE+OO I .14E+06 Sr-92 7.04E+02 OOOE+OO 2.82E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 1 .33E+04 Y-90 2.31 E+04 O.OOE+OO 6.18E+02 O.OOE+OO OOOE+OO O.OOE+OO 6.57E+07 Y-91M 8.42E-09 O.OOE+OO 3.06E-1O O.OOE+OO O.OOE+OO O.OOE+OO 1.65E-05 Y-91 I 87E+O7 OOOE+OO 4.99E+05 O.OOE+OO OOOE+OO O.OOE+OO 2.49E÷09 Y-92 1 .55E+OO O.OOE+OO 4.43E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.47 E+04 Y-93 2.89E+02 O.OOE+OO 7.94E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.31 E+06 Zr-95 3.86E+06 8.50E+05 7.56E+05 O.OOE+OO 1 .22E+06 O.OOE+OO 8.86 E+08 Zr-97 5.67E+02 8.19E+O1 4.83E+O1 O.OOE+OO I .18E+02 O.OOE+OO I .24E+O7 Nb-95 4.12E+05 1 .61 E+05 1 .15E+05 O.OOE+OO I .51 E+05 O.OOE+OO 2.97E+08 Mo-99 O.OOE+OO 7.69E+06 I .90E+06 O.OOE+OO I .64E+07 O.OOE+OO 6.36E+06 Ic- 99M 4.64E+OO 9.IOE+OO I .51 E+02 O.OOE+OO I .32E+02 4.62E+OO 5.18E+03 Tc-1O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-I 03 1 .53E+07 O.OOE+OO 5.89E+06 O.OOE+OO 3.86E+07 O.OOE+OO 3.96E+08 Ru-I 05 8.97E+OI O.OOE+OO 3.25E+OI O.OOE+OO 7.89E+02 O.OOE+OO 5.86 E+04 Ru-106 7.45E+08 O.OOE+OO 9.30E+07 O.OOE+OO 1.OIE+09 O.OOE+OO I.16E+IO Ag-I 1OM 3.21 E+07 2.17E+07 I .74E+07 O.OOE+OO 4.04E+07 O.OOE+OO 2.58E+09

CY-BY-J 70-301 Revision 14 Page 138 of 188 Table 4-15 (Continued)

Child Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-1 25M 3.51 E+08 9.52E+07 4.68E+07 9.86E+07 O.OOE+OO O.OOE+OO 3.39E+08 Te-127M I 32E+O9 3.56E+08 I .57E+08 3.16E+08 3.77E+09 O.OOE+OO I .07E+09 Te-1 27 9.89E+03 2.67E+03 2. 1 2E+03 6.84E+03 2.81 E+04 O.OOE+OO 3.86E+05 Te-129M 8.40E+08 2.35E+08 1.30E+08 2.71E+08 2.47E+09 O.OOE+OO 1.02E+09 Te-1 29 1 .24E-03 3.45E-04 2.94E-04 8.83E-04 3.62E-03 O.OOE+OO 7.70E-02 Te-131 M I .54E+06 5.32E+05 5.66E+05 I O9E+O6 5.15E+06 O.OOE+OO 2.16E+07 Te-131 2.15E-15 6.57E-16 6.41E-16 J.65E-15 6.51E-15 O.OOE÷OO 1.13E-14 Te-132 6.97E+06 3.09E+06 3.73E+06 4.49E+06 2.86E+07 O.OOE+OO 3.1 1 E+07

-130 6.JOE+05 I .23E+06 6.35E+05 1 .36E+08 1 84E+O6 O.OOE+OO 576E+05

-131 1.43E+08 1.44E+08 8.17E+07 4.75E+1O 2.36E+08 O.OOE+OO 1.28E+07 I-I 32 8.93E+O1 I .64E+02 7.54E+O1 7.61 E+03 2.51 E+02 O.OOE+OO I .93E+02

-133 3.52E+06 4.36E+06 1.65E+06 8.09E+08 7.26E+06 OOOE+OO 1.76E+06 I-I 34 1 .37E-04 2.55E-04 1 I 7E-04

. 5.86E-03 3.90E-04 O.OOE+OO I .69E-04 I-I 35 6.20E+04 I 1 2E+05

. 5.28E+04 989E+O6 I .71 E+05 O.OOE+OO 8.51 E+04 Cs-134 1.60E+1O 2.63E+1O 5.55E+09 O.OOE+OO 8.16E+09 2.93E+09 142E+08 Cs-136 8.18E+07 2.25E+08 I .46E+08 O.OOE+OO I .20E+08 1 .79E+07 7.90E+06 Cs-I 37 2.39E+I 0 2.29E+1 0 3.38E+09 O.OOE+OO 7.46E+09 2.68E+09 I .43E+08 Cs-138 5.58E-1I 7.75E-I1 4.92E-II O.OOE+OO 5.45E-I1 5.87E-12 357E-I1 Ba-139 4.69E-02 2.51 E-05 I .36E-03 OOOE+OO 2.19E-05 I .47E-05 2.71 E+OO Ba-140 2.77E+08 2.43E+05 1.62E+07 O.OOE+OO 7.90E+04 1.45E+05 I.40E+08 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-I 42 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-I 40 3.25E+03 I I 3E+03

. 3.82E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3. 1 6E+07 La-I42 3.23E-04 I .03E-04 3.22E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.04E+O1 Ce-I41 6.55E+05 327E+05 4.85E+04 O.OOE+OO I A3E+05 O.OOE+OO 4.08E+08 Ce-143 I .71 E+03 9.28E+05 I .34E+02 O.OOE+OO 3.89E+02 O.OOE+OO I .36E+07 Ce-I44 I.27E+08 3.98E+07 6.78E+06 O.OOE+OO 2.2IE+07 OOOE+OO I.04E+1O Pr-I43 I .46E+05 438E+O4 7.24E+03 O.OOE+OO 2.37E+04 O.OOE+OO I .57E+08 Pr-I44 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO Nd-I47 727E+04 5.89E+04 4.56E+03 O.OOE+OO 3.23E+04 O.OOE+OO 9.33E+07 W-I 87 6.41 E+04 3.80E+04 I .70E+04 O.OOE+OO O.OOE+OO O.OOE+OO 5.34E+06 Np-239 2.55E+03 I .83E+02 I .29E+02 O.OOE+OO 5.30E+02 O.OOE+OO I .36E+07 Notes:

1) Units are m2 mrem/yr per jtCi/sec.

2) For H-3 and C-14, the units are mrem/yr per pCi/rn3.

3) The infant age group is assurned to receive no dose through the vegetation ingestion pathway therefore no dose factors are supplied.

CY-BY-1 70-301 Revision 14 Page 139 of 188 Table 4-16 Adult Grass-Cow-M ilk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 C-14 3.63E+05 7.26E+04 7.26E+04 7.26E+04 7.26E+04 7.26E+04 7.26E+04 Na-24 2A6E+06 246E+O6 2.46E+06 2.46E+06 2.46E+06 2.46E+06 2.46E+06 Cr-51 O.OOE+OO O.OOE+OO 2.86E+04 I .71 E+04 6.29E+03 3.79E+04 Z.18E+06 Mn-54 O.OOE+OO 8.41 E+06 I .61 E+06 O.OOE+OO 2.50E+06 O.OOE+OO 2.58E+07 Mn-56 O.OOE+OO 4.13E-03 7.32E-04 O.OOE+OO 5.24E-03 O.OOE+OO 1.32E-O1 Fe-55 2.51 E-Of I .74E+07 4.05E+06 O.OOE+OO O.OOE+OO 9.68E+06 9.95E+06 Fe-59 2.97E+07 698E+O7 2.67E+07 O.OOE+OO O.OOE+OO I .95E+07 2.33E+08 Co-58 OOOE+OO 4.72E+06 I O6E+O7 O.OOE+OO O.OOE+OO O.OOE+OO 9.56E+07 Co-60 OOOE+OO I .64E+07 3.62E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.08E+08 Ni-63 6.73E+09 466E+O8 2.26E+08 O.OOE+OO O.OOE+OO OOOE+OO 9.73E+07 Ni-65 3.70E-O1 481E-O2 2.19E-02 O.OOE+OO OOOE+OO O.OOE+OO 1.22E÷OO Cu-64 O.OOE+OO 2.36E+04 I .1 1 E+04 O.OOE+OO 5.95E+04 O.OOE+OO 2.01 E+06 Zn-65 I .37E+09 4.36E+09 I .97E+09 O.OOE+OO 2.92E+09 O.OOE+OO 2.75E+09 Zn-69 2.OIE-12 3.84E-12 2.67E-13 O.OOE+OO 2.50E-12 O.OOE+OO 5.78E-13 Br-83 O.OOE+OO O.OOE+OO 9.65E-02 O.OOE+OO O.OOE+OO O.OOE+OO I .39E-O1 Br-84 O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.60E+09 I .21 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.12E+08 Rb-88 O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 I .45E+09 O.OOE+OO 4.16E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E+08 Sr-90 5.38E+1O O.OOE+OO 1.08E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.35E+09 Sr-91 2.87E+04 O.OOE+OO I 16E+03 O.OOE+OO O.OOE+OO O.OOE+OO I .37E+05 Sr-92 4.84E-O1 O.OOE+OO 2.09E-02 O.OOE+OO O.OOE+OO O.OOE+OO 958E+OO Y-90 71 OE+O1 O.OOE+OO I .90E+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.52 E+05 Y-91 M 6.42E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I .89E-1 9 Y-91 8.59E+03 O.OOE+OO 2.30E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.73E+06 Y-92 5.57E-05 O.OOE+OO I .63E-06 O.OOE+OO O.OOE+OO O.OOE+OO 9.75E-O1 Y-93 2.22E-O1 O.OOE+OO 6.12E-03 O.OOE+OO O.OOE+OO O.OOE+OO 7.03E+03 Zr-95 9.44E+02 3.03E+02 2.05E+02 O.OOE+OO 4.75E+02 O.OOE+OO 9.59E+05 Zr-97 4.32E-O1 8.72E-02 3.99E-02 O.OOE+OO I .32E-O1 O.OOE+OO 2.70E+04 Nb-95 8.26E+04 4.60E+04 2.47E+04 O.OOE+OO 4.54E+04 O.OOE+OO 2.79E+08 Mo-99 O.OOE+OO 2.47E+07 4.70E+06 O.OOE+OO 5.60E+07 O.OOE+OO 5.73E+07 Tc- 99M 3.31 E+OO 9.35E+OO I .19E+02 O.OOE+OO I .42E+02 4.58E+OO 5.53E+03 Tc-1O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.02E+03 O.OOE+OO 4.39E+02 O.OOE+OO 3.88E+03 O.OOE+OO 1.19E+05 Ru-105 8.51E-04 O.OOE+OO 3.36E-04 O.OOE+OO 1.IOE-02 O.OOE+OO 5.20E-O1 Ru-I 06 2.04E+04 O.OOE+OO 2.58E+03 O.OOE+OO 3.94E+04 O.OOE+OO I .32E+06 Ag-IbM 5.82E+07 5.39E+07 3.20E+07 O.OOE+OO I.06E+08 O.OOE+OO 2.20E+IO

CY-BY-1 70-301 Revision 14 Page 140 of 188 Table 4-16 (Continued)

Adult Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.63E+07 5.91E+06 2.18E+06 4.90E+06 6.63E+07 O.OOE+OO 6.51E+07 Te-127M 4.58E+07 I 64E+O7 5.58E+06 I .17E+07 I .86E+08 O.OOE+OO I .54E+08 Te-127 6.66E+02 2.39E+02 1.44E+02 4.94E+02 2.71E+03 OOOE+OO 5.26E+04 Te-1 29M 6.02E+07 224E+O7 9.52E+06 2.07E+07 2.51 E+08 O.OOE+OO 3.03E+08 Te-129 2.83E-1O 1.06E-1O 6.88E-11 2.17E-1O 1.19E-09 O.OOE+OO 2.13E-1O Te-131M 3.61E+05 1.76E+05 1.47E+05 2.79E+05 1.79E+06 O.OOE+OO 175E+07 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-1 32 2.39E+06 I .55E+06 I .45E+06 I .71 E+06 I A9E÷07 O.OOE+OO T32E+OZ I-I 30 4.1 8E+05 I .23E+06 4.86E+05 I .04E+08 I .92E+06 O.OOE+OO I .06E+06 1-131 2.96E+08 4.23E+08 2.43E+08 I .39E+1 I 7.26E+08 O.OOE+OO I .12E+08 1-132 1.65E-O1 4.40E-O1 1.54E-O1 1.54E+O1 7.02E-O1 O.OOE+OO 8.27E-02 1-133 3.88E+06 6.74E+06 2.06E+06 9.91E+08 1.18E+07 O.OOE+OO 6.06E+06 1-134 1.89E-12 5.13E-12 1.83E-12 8.89E-11 8.16E-12 O.OOE+OO 4.47E-15 I-I 35 1 .29E+04 3.38E+04 I .25E+04 2.23E+06 5.42E+04 O.OOE+OO 3.82E+04 Cs-134 5.65E+09 I 35E+1O I IOE+1O O.OOE+OO 435E+O9 I .45E+09 2.35E+08 Cs-136 2.63E+08 I .04E+09 7.46E+08 O.OOE+OO 5.77E+08 7.91 E+07 I .18E+08 Cs-I 37 738E+09 I .01 E+1 0 6.61 E+09 O.OOE+OO 3.43E+09 I .14E+09 I .95E+08 Cs-I 38 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO Ba-139 443E-08 3.16E-I I I .30E-09 O.OOE+OO 295E-I I I .79E-I I 7.86E-08 Ba-140 2.69E+07 3.38E+04 I .76E+06 O.OOE+OO I .15E+04 I .93E+04 5.54E+07 Ba-I 4 1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO Ba-I 42 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO La-140 452E+OO 2.28E+OO 6.02E-OI O.OOE+OO O.OOE+OO O.OOE+OO I 67E+O5 La-I 42 1 .89E-I I 8.59E-I 2 2. 1 4E-I 2 O.OOE+OO O.OOE+OO OOOE+OO 6.28 E-08 Ce-141 4.84E+03 3.28E+03 3.72E+02 O.OOE+OO I .52E+03 O.OOE+OO I .25E+07 Ce-143 4.15E+OI 3.07E+04 3.39E+OO O.OOE+OO I .35E+OI O.OOE+OO I .15E+06 Ce-144 3.58E+05 I .50E+05 I .92E+04 O.OOE+OO 8.87E+04 O.OOE+OO I .21 E+08 Pr-I 43 1 .58E+02 6.34E+OI 7.83E+OO O.OOE+OO 3.66E+OI O.OOE+OO 6.92E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 9.48E+OI I .IOE+02 6.56E+OO O.OOE+OO 6.41 E+OI O.OOE+OO 5.26E+05 W-I87 6.51 E+03 5.44E+03 I .90E+03 O.OOE+OO O.OOE+OO O.OOE+OO I .78E+06 Np-239 3.67E+OO 3.61 E-OI I .99E-OI O.OOE+OO I .12E+OO O.OOE+OO f.40E+04 Notes:

I) Units are m2 mrem/yr per iCi/sec.

2) For H-3 and C-I4, the units are mrem/yr per tCi/m3.

CY-BY-J 70-301 Revision 14 Page 141 of 188 Table 4-17 Teen Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 5.66E+02 5.66E+02 5.66E+02 5.66E+02 5.66E+/-02 5.66E+02 C-14 6.70E+05 I .34E+05 1 .34E+05 1 .34E+05 I .34E+05 1 .34E+05 I .34E÷05 Na-24 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 Cr-51 O.OOE+OO O.OOE+OO 4.99E+04 2.77E+04 I .09E+04 7.12E+04 8.38E+06 Mn-54 O.OOE+OO 1 .40E+07 2.78E+06 O.OOE+OO 4.18E+06 O.OOE+OO 287E÷07 Mn-56 O.OOE+OO 7.32E-03 I .30E-03 O.OOE+OO 9.27E-03 O.OOE+OO 4.82E-O1 Fe-55 4.45E+07 3.16E+07 7.36E+06 O.OOE+OO O.OOE+OO 2.OOE+07 I .37E÷07 Fe-59 5.18E+07 1.21E+08 4.67E+07 OOOE+OO O.OOE+OO 3.81E+07 2.86E+08 Co-58 O.OOE+OO 7.94E+06 I .83E+07 O.OOE+OO O.OOE+OO O.OOE+OO I .09E+08 Co-60 O.OOE+OO 2.78E+07 6.26E+07 OOOE+OO O.OOE+OO O.OOE+OO 3.62E+08 Ni-63 1.18E+1O 8.35E+08 4.OIE+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.33E+08 Ni-65 6.78E-O1 8.66E-02 3.94E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.70E+OO Cu-64 O.OOE+OO 4.21 E+04 I .98E+04 O.OOE+OO I .06E+05 OOOE+OO 3.26E+06 Zn-65 2.1 1 E+09 7.31 E+09 3.41 E+09 O.OOE+OO 4.68E+09 O.OOE+OO 3.IOE+09 Zn-69 3.70E-12 7.05E-12 4.94E-13 O.OOE+OO 4.61E-12 O.OOE+OO 1.30E-11 Br-83 O.OOE+OO O.OOE+OO 1.78E-O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.73E+09 2.22E+09 O.OOE+OO O.OOE+OO O.OOE+OO 7.01 E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 2.67E+09 O.OOE+OO 7.66E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.18E+08 Sr-90 8.13E+1O O.OOE+OO I .63E+09 O.OOE+OO O.OOE+OO O.OOE+OO I .86E÷09 Sr-91 5.27E+04 O.OOE+OO 2. 1 OE+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.39 E+05 Sr-92 8.85E-O1 O.OOE+OO 3.77E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.26E+O1 Y-90 1 .30E+02 O.OOE+OO 3.51 E+OO O.OOE+OO O.OOE+OO O.OOE+OO I .08E÷06 Y-91M 1.18E-19 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.55E-18 Y-91 I .58E+04 O.OOE+OO 4.24E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.48E+06 Y-92 I .03E-04 O.OOE+OO 2.98E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E+OO Y-93 4.09E-O1 O.OOE+OO I .12E-02 O.OOE+OO O.OOE+OO O.OOE+OO I .25E+04 Zr-95 I .65E+03 5.21 E+02 3.58E+02 O.OOE+OO 7.65E+02 O.OOE+OO I .20E+06 Zr-97 7.87E-O1 1.56E-O1 7.17E-02 O.OOE+OO 2.36E-O1 O.OOE+OO 4.22E+04 Nb-95 I .41 E+05 7.82E+04 4.30E+04 O.OOE+OO 7.58E+04 O.OOE+OO 3.34E+08 Mo-99 O.OOE+OO 4.46E+07 8.51 E+06 O.OOE+OO I .02E+08 O.OOE+OO 8.00 E+07 Tc- 99M 5.74E+00 I .60E+01 2.07E+02 0.OOE+00 2.39E+02 8.89E+00 I .05E+04 Tc-101 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-I 03 1 .81 E+03 0.OOE+00 7.74E+02 0.OOE+00 6.38E+03 0.OOE+00 I .51 E+05 Ru-4 05 1 .55E-03 0.OOE+00 6.03E-04 0.OOE+00 I .96E-02 0.OOE+00 I .25E+00 Ru-106 3.75E+04 0.OOE+00 4.73E+03 0.OOE+00 7.24E+04 0.OOE+00 1.80E+06 A:j IOM 9.63E+07 9.1 1 E+07 5.54E+07 0.OOE+00 I .74E+08 0.OOE+00 2.56E+10

CY-BY-1 70-301 Revision 14 Page 142 of 188 Table 4-17 (Continued)

Teen Grass-Cow-Milk Dose Factors Nuclide Bone Liver I Body Thyroid Kidney Lung Gl-LLI Te-125M 3.OIE+07 1.08E+07 4.02E+06 8.40E+06 O.OOE+OO O.OOE+OO 8.87E+07 Te-127M 8.44E+07 2.99E+07 1.OOE+07 2.OIE+07 3.42E+08 OOOE+OO 2.IOE+08 Te-127 1.24E+03 4.38E+02 2.66E+02 8.52E+02 5.OOE+03 O.OOE+OO 9.54E+04 Te-1 29M 1 .1 OE+08 4.09E+07 I .74E+07 3.55E+07 4.61 E+08 O.OOE+OO 4J 3E+08 Te-129 5.20E-1O 1.94E-1O 1.27E-1O 3.72E-1O 2.18E-09 O.OOE+OO 2.84E-09 Te-131M 6.57E+05 3.15E+05 2.63E+05 4.74E+05 3.28E+06 O.OOE+OO 2.53E+07 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-1 32 427E+06 2.71 E+06 2.55E+06 2.85E+06 2.60E+07 O.OOE+OO 8.57E+07 1-130 7.35E+05 2.13E+06 8.49E+05 I .73E+08 3.27E+06 O.OOE+OO I .63E+06 I-I 31 5.37E+08 7.52E+08 4.04E+08 2.1 9E--l I I 29E+O9 O.OOE+OO I .49E+08 1-132 2.92E-O1 7.64E-OJ 2.74E-O1 2.57E+O1 1.20E+OO O.OOE+OO 3.33E-O1 1-133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.IIE+07 O.OOE+OO 9.09E+06 1-134 3.35E-12 8.89E-12 3.19E-12 1.48E-1O 1.40E-11 OOOE+OO 1.17E-13 1-135 2.29E+04 5.91E+04 2.19E+04 3.80E+06 933E+O4 O.OOE+OO 6.54E+04 Cs-134 9.82E+09 2.31E+1O 1.07E+1O OOOE+OO 7.34E+09 2.80E+09 Z87E+08 Cs-136 4.47E+08 I .76E+09 I .18E+09 O.OOE+OO 9.58E+08 I .51 E+08 I .42E+08 Cs-137 1.34E+1O 1.78E+1O 6.20E+09 O.OOE+OO 6.06E+09 2.35E+09 2.53E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 8.20E-08 5.77E-11 2.39E-09 O.OOE+OO 5.44E-11 3.98E-11 7.31E-07 Ba-I 40 4.85E+07 5.95E+04 3. 1 3E+06 OOOE+OO 2 .02E+04 4.OOE+04 7.49E+07 Ba-141 O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-I 42 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO La-140 812E+OO 3.99E+OO I .06E+OO O.OOE+OO O.OOE+OO O.OOE+OO 229E+O5 La-I42 3.41 E-I I I .51 E-I I 3.77E-12 O.OOE+OO O.OOE+OO O.OOE+OO 4.61 E-07 Ce-141 8.88E+03 5.93E+03 68I E+02 O.OOE+OO 2.79E+03 O.OOE+OO I .70E+07 Ce-143 7.62E+OI 5.55E+04 6.20E+OO O.OOE+OO 2.49E+OI O.OOE+OO I .67E+06 Ce-I44 6.58E+05 2.72E+05 3.54E+04 O.OOE+OO I.63E+05 O.OOE+OO I.66E+08 Pr-I 43 290E+02 I 1 6E+02

. I .44E+OI O.OOE+OO 6.74E+OI O.OOE+OO 9.55E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-I 47 I .82E+02 I .98E+02 I I 9E+OI

. O.OOE+OO I I 7E+02

. O.OOE+OO 7. 1 6E+05 W-187 I.19E+04 9.71E+03 3.40E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.63E+06 Np-239 7.OOE+OO 66OE-OI 3.67E-OI O.OOE+OO 2 .07E+OO O.OOE+OO I .06E+05 Notes:

I) Units are m2 mrem/yr per pCi/sec.

2) For H-3 and C-14, the units are mrem/yr per pCi/rn3.

CY-BY-J 70-301 Revision 14 Page 143 of 188 Table 4-18 Child Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 8.97E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 C-14 1.65E+06 3.29E+05 3.29E+05 3.29E+05 3.29E+05 3.29E+05 3.29E+05 Na-24 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 Cr-51 O.OOE+OO O.OOE+OO 1 .02E+05 5.65E+04 I .54E+04 I .03E+05 5.39E+06 Mn-54 O.OOE+OO 2.IOE+07 5.59E+06 O.OOE+OO 5.88E+06 O.OOE+OO I .76E+07 Mn-56 O.OOE+OO I .28E-02 2.88E-03 O.OOE+OO 1 .54E-02 O.OOE+OO I .85E+OO Fe-55 I .12E+08 5.93E+07 I .84E+07 O.OOE+OO O.OOE+OO 3.35E+07 I .IOE+07 Fe-59 I .20E+08 1 .94E+08 9.69E+07 O.OOE+OO O.OOE+OO 5.64E+07 2.02E+08 Co-58 O.OOE+OO I .21 E+07 371 E+07 O.OOE+OO OOOE+OO O.OOE+OO 7.08E+07 Co-60 O.OOE+OO 4.32E+07 I .27E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.39E+08 Ni-63 2.96E+1O 1.59E+09 1.OIE+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+08 Ni-65 I .66E+OO I .56E-O1 9.1 1 E-02 O.OOE+OO O.OOE+OO O.OOE+OO I .91 E+O1 Cu-64 O.OOE+OO 7.39E+04 4.47E+04 O.OOE+OO J .79E+05 O.OOE+OO 3.47E+06 Zn-65 4.13E+09 I .IOE+1O 6.85E+09 O.OOE÷OO 6.94E+09 O.OOE+OO I .93E+09 Zn-69 9.IOE-12 1.32E-11 1.22E-12 O.OOE+OO 7.98E-12 O.OOE+OO 8.29E-1O Br-83 O.OOE+OO O.OOE+OO 4.37E-O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 8.78E+09 5.40E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.65E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 6.62E+09 O.OOE+OO I .89E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.56E+08 Sr-90 I 68E+1 I O.OOE+OO 3.38E+09 O.OOE+OO O.OOE+OO O.OOE+OO I .51 E+09 Sr-91 I 29E+05 O.OOE+OO 4.88E+03 O.OOE+OO OOOE+OO O.OOE+OO 2.86E+05 Sr-92 2. 1 6E+OO O.OOE+OO 8.67E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.09E+O1 Y-90 3.23E+02 O.OOE+OO 8.64E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9. 1 9E+05 Y-91 M 2.87E-1 9 O.OOE+OO I .04E-20 OOOE+OO O.OOE+OO O.OOE+OO 5.62E-1 6 Y-91 3.90E+04 O.OOE+OO I .04E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.20E+06 Y-92 2.53E-04 O.OOE+OO 7.23E-06 O.OOE+OO O.OOE+OO O.OOE+OO 7.30E+OO Y-93 I .OOE+OO O.OOE+OO 2.75E-02 O.OOE+OO O.OOE+OO O.OOE+OO I .50E+04 Zr-95 3.83E+03 8.43E+02 7.50E+02 O.OOE+OO I .21 E+03 O.OOE+OO 8.79E+05 Zr-97 I .91 E+OO 2.77E-O1 I .63E-O1 O.OOE+OO 3.97E-O1 O.OOE+OO 4.1 9E+04 Nb-95 3.18E+05 I 24E+05 8.85E+04 O.OOE+OO I .16E+05 O.OOE+OO 2.29E+08 Mo-99 O.OOE+OO 8.12E+07 2.OIE+07 O.OOE+OO 1.73E+08 O.OOE+OO 6.72E+07 Tc- 99M I .32E+O1 2.58E+O1 4.28E+02 O.OOE+OO 3.75E+02 I .31 E+O1 I .47 E+04 Tc-1O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 4.28E+03 O.OOE+OO 1.65E+03 O.OOE+OO 1.08E+04 O.OOE+OO 1.IIE+05 Ru-105 3.79E-03 O.OOE+OO 1.38E-03 O.OOE+OO 3.33E-02 O.OOE+OO 2.48E+OO Ru-106 9.24E+04 O.OOE+OO 1.15E+04 O.OOE+OO 1.25E+05 O.OOE+OO 1.44E+06 Ag-I I OM 2.09E+08 I .41 E+08 I .1 3E+08 O.OOE+OO 2.63E+08 O.OOE+OO I .68E+I 0

CY-BY-1 70-301 Revision 14 Page 144 of 188 Table 4-18 (Continued)

Child Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 7.38E+07 2.OOE+07 9.84E+06 2.07E+07 O.OOE+OO O.OOE+OO 7.12E+07 Te-127M 2.08E+08 5.60E+07 2.47E+07 4.97E+07 5.93E+08 O.OOE+OO 1.68E+08 Te-127 3.04E+03 8.19E+02 6.51 E+02 210E+03 8.64E+03 O.OOE+OO 1 .19E+05 Te-129M 2.71E+08 7.58E+07 4.21E+07 8.75E+07 7.97E+08 O.OOE+OO 3.31E+08 Te-129 1.28E-09 3.58E-1O 3.05E-1O 9.16E-1O 3.75E-09 O.OOE+OO 7.99E-08 Te-131M 1.60E+06 5.53E+05 5.88E+05 1.14E+06 5.35E+06 O.OOE+OO 2.24E+07 Te-1 31 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 I .02E+07 4.52E+06 5A6E+06 6.58E+06 4.19E+07 O.OOE+OO 4.55E+07 I-I 30 1 .72E+06 3.47E+06 I .79E+06 3.82E+08 5. 1 9E+06 O.OOE+OO I .62E+06 1-131 1.30E+09 1.31E+09 7.45E+08 433E+11 2.15E+09 O.OOE+OO 1.17E+08 I-I 32 691 E-O1 I .27E+OO 5.84E-O1 5.89E+O1 I .94E+OO O.OOE+OO I .49E+OO 1-133 1 .72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 O.OOE+OO 857E+O6 1-134 7.94E-12 1.47E-11 6.79E-12 3.39E-1O 2.26E-11 O.OOE+OO 9.78E-12 I-I 35 5.43E+04 9.78E+04 4.62E+04 8.66E+06 I .50E+05 O.OOE+OO 7.45E+04 Cs-134 2.26E+1O 3.72E+1O 7.84E+09 O.OOE+OO 1.15E+1O 4.13E+09 2.OOE+08 Cs-136 1.OIE+09 2.77E+09 1.80E+09 O.OOE+OO 1.48E+09 2.20E+08 9.75E+07 Cs-I 37 3.22E÷I 0 3.09E+I 0 455E+O9 O.OOE+OO I .01 E+I 0 3.62E+09 I .93E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 2.OIE-07 108E-IO 5.84E-09 O.OOE+OO 9.39E-II 6.33E-II I.I6E-05 Ba-I40 I .I7E+08 I .03E+05 6.84E+06 O.OOE+OO 3.34E+04 6.I2E+04 5.94E+07 Ba-I41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO La-140 I.95E+O1 6.80E+OO 2.29E+OO O.OOE+OO O.OOE+OO O.OOE+OO I.90E+05 La-I 42 8.24E-I I 2.63E-I I 8.22E-I 2 O.OOE+OO O.OOE+OO O.OOE+OO 5.20E-06 Ce-14I 2.19E+04 I.09E+04 I.62E+03 O.OOE+OO 4.78E+03 O.OOE+OO I.36E+07 Ce-I 43 1 .87E+02 I .01 E+05 I .47E+OI O.OOE+OO 426E+OI O.OOE÷OO I .49E+06 Ce-I44 I .62E+06 5.09E+05 8.66E+04 O.OOE+OO 2.82E+05 OOOE+OO I .33E+08 Pr-I 43 7.1 8E+02 2. 1 6E+02 3.57E+OI O.OOE+OO I I 7E+02

. O.OOE+OO 7.75E+05 Pr-I 44 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-I47 4.48E+02 3.63E+02 2.8IE+OI O.OOE+OO I.99E+02 O.OOE+OO 5.75E+05 W-187 2.89E+04 I.71E+04 7.67E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.40E+06 Np-239 I .72E+OI I .24E+OO 8.69E-OI O.OOE+OO 3.58E+OO O.OOE+OO 9.I5E+04 Notes:

1) Units are m2 mrem/yr per iC i/sec.

2) For H-3 and C-14, the units are mrem/yr per pCi/rn3.

CY-BY-J 70-301 Revision 14 Page 145 of 188 Table 4-19 Infant G rass-Cow-M ilk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO I .36E+03 1 .36E+03 I .36E+03 I .36E+03 I .36E+03 I .36E+03 C-14 3.23E+06 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 Na-24 1 .56E+07 I .56E+07 I .56E+07 I .56E+07 I .56E+07 I .56E+07 I .56E+07 Cr-51 OOOE+OO O.OOE+OO I .61 E+05 1 .05E--05 2.30E+04 2.05E+05 4.70E+06 Mn-54 O.OOE+OO 3.90E+07 8.84E+06 O.OOE+OO 8.64E+06 O.OOE+OO I .43E+07 Mn-56 O.OOE+OO 313E-02 5.39E-03 O.OOE+OO 2.69E-02 O.OOE+OO 2.84E+OO Fe-55 I .35E+08 8.73E+07 2.33E+07 O.OOE+OO O.OOE+OO 4.27E+07 I .1 1 E+07 Fe-59 2.24E+08 3.92E+08 I .54E+08 O.OOE+OO O.OOE+OO I .16E+08 I .87E+08 Co-58 O.OOE+OO 2.43E+07 6.05E+07 O.OOE+OO OOOE+OO O.OOE+OO 6.04E+07 Co-60 O.OOE+OO 8.82E+07 2.08E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.IOE+08 Ni-63 3.49E+1O 2.16E+09 1.21E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+08 Ni-65 3.51E+OO 3.97E-O1 1.81E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 3.02E+O1 Cu-64 O.OOE+OO L84E+05 8.51E+04 O.OOE+OO 3.IIE+05 O.OOE+OO 3.77E+06 Zn-65 5.55E+09 1.90E+1O 8.78E+09 O.OOE+OO 9.23E+09 O.OOE+OO t6lE+1O Zn-69 1.94E-11 349E-11 2.60E-12 O.OOE+OO 1.45E-11 O.OOE+OO 2.85E-09 Br-83 O.OOE+OO O.OOE+OO 9.27E-O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 OOOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.23E+1O 1.IOE+1O O.OOE+OO O.OOE+OO O.OOE+OO 570E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.26E+1O O.OOE+OO 3.61E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.59E+08 Sr-90 I .86E+1 I O.OOE+OO 3.77E+09 O.OOE+OO OOOE+OO O.OOE+OO I .52E+09 Sr-91 2.70E+05 O.OOE+OO 9.76E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.19E+05 Sr-92 4.60E+OO O.OOE+OO I .71 E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 4.96E+O1 Y-90 6.82E+02 O.OOE+OO I .83E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 9.42E+05 Y-91M 6.09E-19 O.OOE+OO 2.07E-20 O.OOE+OO O.OOE+OO O.OOE+OO 2.03E-15 Y-91 f.33E+04 O.OOE+OO I .95E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.25E+06 Y-92 5.37E-04 O.OOE+OO I .51 E-05 O.OOE+OO O.OOE+OO O.OOE+OO I .02E+O1 Y-93 2.14E+OO O.OOE+OO 5.83E-02 O.OOE+OO O.OOE+OO O.OOE+OO I .69E+04 Zr-95 6.81 E+03 I .66E+03 I .18E+03 O.OOE+OO I .79E+03 O.OOE+OO 8.26E+05 Zr-97 4O5E+OO 6.96E-O1 3.18E-O1 O.OOE+OO 7.OIE-O1 O.OOE+OO 4.44E+04 Nb-95 5.94E+05 2.45E+05 1.41E+05 O.OOE+OO 1.75E+05 O.OOE+OO 2.07E+08 Mo-99 O.OOE+OO 2.08E+08 4.05E+07 O.OOE+OO 3.IOE+08 O.OOE+OO 6.84E+07 Tc- 99M 2.74E+O1 5.65E+O1 7.27E+02 O.OOE+OO 6.08E+02 2.95E+O1 I .64E+04 Tc-1O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 8.67E+03 O.OOE+OO 2.90E+03 O.OOE+OO 1.80E+04 O.OOE+OO 1.05E+05 Ru-105 8.OOE-03 O.OOE+OO 2.69E-03 OOOE+OO 5.88E-02 O.OOE+OO 3.18E+OO Ru-i 06 1 .90E+05 O.OOE+OO 2.38E+04 O.OOE+OO 2.25E+05 O.OOE+OO I .44E+06 Ag-ibM 3.86E+08 2.82E+08 i.86E+08 O.OOE+OO 4.03E+08 O.OOE+OO 1.46E+1O

CY-BY-1 70-301 Revision 14 Page 146 of 188 Table 4-19 (Continued)

Infant Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M I .51 E+08 5.04E+07 2.04E+07 5.08E+07 O.OOE+OO O.OOE+OO 7.19E+07 Te-127M 4.21 E+08 I AOE+08 5.IOE+07 I .22E+08 I .04E+09 O.OOE+OO I .70E+08 Te-127 6.45E+03 2.16E+03 I .39E+03 5.25E+03 I .57E+04 O.OOE+OO 1 .35E+05 Te-129M 5.57E+08 I .91 E+08 8.58E+07 2.14E+08 I .39E+09 O.OOE+OO 3.33E+08 Te-129 2.72E-09 9.38E-1O 6.35E-1O 2.28E-09 677E-09 O.OOE+OO 2.17E-07 Te-131M 3.37E+06 I .36E+06 I .12E+06 2.75E+06 9.35E+06 O.OOE+OO 2.29E+07 Te-1 31 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.IOE+07 1.04E+07 9.71E+06 1.54E+07 6.51E+07 O.OOE+OO 3.85E+07 1-130 3.53E+06 7.77E+06 3.12E+06 8.71E+08 8.53E+06 O.OOE+OO 1.67E+06 1-131 2.72E+09 3.20E+09 I .41 E+09 I .05E+12 3.74E+09 O.OOE+OO I 14E+08 1-132 1.43E+OO 2.91E+OO 1.04E+OO 1.36E+02 3.25E+OO O.OOE+OO 2.36E+OO I-I 33 3.63E+07 5.29E+07 I .55E+07 9.62E+09 6.22E+07 O.OOE+OO 8.95E+06 1-134 1.65E-JJ 3.37E-11 1.20E-11 7.87E-JO 3.77E-11 O.OOE+OO 3A9E-11 I-I 35 1 .1 3E+05 2.25E+05 8.1 9E+04 2.01 E+07 2.50E+05 O.OOE+OO 8. 1 3E+04 Cs-I 34 365E+1 0 6.80E+ I 0 6.87E+09 O.OOE+OO I .75E+1 0 7. 1 8E+09 I .85E+08 Cs-136 I 97E+O9 5.80E+09 2.16E+09 O.OOE+OO 2.31 E+09 4.72E+08 8.80E+07 Cs-137 5.15E+JO 6.02E+1O 4.27E+09 O.OOE+OO I .62E+IO 6.55E+09 I .88E+08 Cs-I 38 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00 E+OO Ba-I 39 4.29E-07 2.84E-I 0 1 .24E-08 0.OOE+0O I .71 E-I 0 1 .72E-I 0 2.72E-05 Ba-140 2.41 E+08 2.41 E+05 I .24E+07 0.OOE+00 5.72E+04 I .48E+05 5.92E+07 Ba-I41 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-I 42 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00 E+00 La-I40 4.06E+0I I .60E+0I 4.12E+00 0.OOE+00 0.OOE+00 0.OOE+00 I .88E+05 La-I 42 I .73E-I 0 6.35E-I I I .52E-I I 0.OOE+00 0.OOE+00 0.OOE+00 I .08E-05 Ce-I4I 4.34E+04 2.64E+04 3.1 1 E+03 0.OOE+00 8.I5E+03 0.OOE+00 I .37E+07 Ce-I 43 3.96E+02 2.63E+05 3.OOE+0I 0.OOE+OO 7.65E+OI 0.OOE+00 I .53E+06 Ce-I44 2.33E+06 9.52E+05 I.30E+05 0.OOE+00 3.85E+05 0.OOE+00 I.33E+08 Pr-I43 I .49E+03 5.56E+02 7.37E+0I 0.OOE+00 2.07E+02 0.OOE+00 7.84E+05 Pr-I44 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nd-I 47 8 .88E+02 9. 1 2E+02 5.59E+OI 0.OOE+00 3.5 I E+02 0.OOE+00 5.78E+05 W-I87 6.08E+04 4.23E+04 I.46E+04 0.OOE+00 0.OOE+00 0.OOE+00 2.48E+06 Np-239 3.64E+0I 3.26E+00 I .84E+00 0.OOE+00 6.50E+00 0.OOE+00 9.42E+04 Notes:

I) Units are m2 mrem/yr per jiCilsec.

2) For H-3 and C-I4, the units are mrem/yr per tCiIm3.

CY-BY-1 70-301 Revision 14 Page 147 of 188 Table 4-20 Ad ult Grass-Goat-M ilk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 8.88E+02 8.88E+02 8.88E+02 8.88E+/-02 8.88E+/-02 888E+O2 C-14 363E+O5 7.26E+04 7.26E+04 7.26E+04 7.26E+04 7.26E+04 7.26E+04 Na-24 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 Cr-51 O.OOE+OO O.OOE+OO 3.43E+03 2.05E+03 755E+02 4.55E+03 8.62E+05 Mn-54 O.OOE+OO I .01 E+06 I .93E+05 O.OOE+OO 3.OOE+05 O.OOE+OO 3.09E+06 Mn-56 O.OOE+OO 4.95E-04 8.79E-05 O.OOE+OO 6.29E-04 O.OOE+OO I .58E-02 Fe-55 3.26E+05 2.26E+05 5.26E+04 OOOE+OO O.OOE+OO I .26E+05 I .29E+05 Fe-59 3.86E+05 9O7E+O5 3.48E+05 O.OOE+OO O.OOE+OO 2.53E+05 3.02E+06 Co-58 O.OOE+OO 5.66E+05 1 .27E+06 O.OOE+OO O.OOE+OO O.OOE+OO I .15E+07 Co-60 O.OOE+OO I .97E+06 434E÷06 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E÷07 Ni-63 8.07E+08 56OE+O7 2.71E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E+07 Ni-65 4.44E-02 5.77E-03 2.63E-03 O.OOE+OO O.OOE+OO O.OOE+OO I .46E-O1 Cu-64 O.OOE+OO 263E+03 I .23E+03 O.OOE+OO 6.63E+03 O.OOE+OO 2.24E+05 Zn-65 I .65E+08 5.24E+08 2.37E+08 O.OOE+OO 3.50E+08 O.OOE+OO 3.30E÷08 Zn-69 2.41E-13 4.61E-13 3.21E-14 O.OOE+OO 3.OOE-13 O.OOE+OO 6.93E-14 Br-83 O.OOE+OO O.OOE+OO I .16E-02 O.OOE+OO O.OOE+OO O.OOE+OO I 6ZE-O2 Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 OOOE+OO OOOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 3.12E+08 I .45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.15E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 3.05E+09 OOOE+OO 8.74E+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.88E+08 Sr-90 1.13E+11 O.OOE+OO 2.27E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.84E+09 Sr-91 6O3E+O4 O.OOE+OO 2.44E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+05 Sr-92 I .02E+OO O.OOE+OO 4.39E-02 O.OOE+OO O.OOE+OO O.OOE+OO ZOl E+O1 Y-90 8.52E+OO O.OOE+OO 2.28E-O1 O.OOE+OO O.OOE+OO OOOE+OO 9.03E+04 Y-91 M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.26E-20 Y-91 I .03E+03 O.OOE+OO 2.76E+O1 O.OOE+OO O.OOE+OO O.OOE÷OO 5.67E+05 Y-92 6.68E-06 O.OOE+OO 1.95E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E-O1 Y-93 2 .66E-02 O.OOE+OO 7.34E-04 O.OOE+OO O.OOE+OO O.OOE+OO 8.43E+02 Zr-95 I .13E+02 3.63E+O1 2A6E+O1 O.OOE+OO 5.70E+O1 O.OOE+OO I .15E+05 Zr-97 5.19E-02 I .05E-02 4.79E-03 O.OOE+OO I .58E-02 O.OOE+OO 3.24E+03 Nb-95 9.92E+03 5.52E+03 2.97E+03 O.OOE+OO 5.45E+03 O.OOE+OO 3.35E+07 Mo-99 O.OOE+OO 2.97E+06 5.65E+05 O.OOE+OO 6.72E+06 O.OOE+OO 6.88E+06 Tc- 99M 3.97E-O1 I .12E+OO I .43E+O1 O.OOE+OO I .70E+O1 5.50E-O1 6.64E+02 Tc-1O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.22E+02 O.OOE+OO 5.26E+O1 O.OOE+OO 466E+02 O.OOE+OO 1.43E+04 Ru-I 05 1 .02E-04 O.OOE+OO 4.03E-05 O.OOE+OO I .32E-03 O.OOE+OO 6.25E-02 Ru-106 2.45E+03 O.OOE+OO 3iOE+02 O.OOE+OO 4.73E+03 O.OOE+OO I.58E+05 Ag-IbM 6.99E+06 646E+06 3.84E+06 O.OOE+OO I.27E+07 O.OOE+OO Z64E+09

CY-BY-J 70-301 Revision 14 Page 148 of 188 Table 4-20 (Continued)

Adult Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.96E+06 7.09E+05 2.62E+05 5.88E+05 7.95E+06 OOOE+/-OO 7.81E+06 Te-1 27M 5.49E+06 I .96E+06 6.69E+05 I AOE+06 2.23E+07 O.OOE+OO 1 .84E+07 Te-127 8.OOE+O1 2.87E+O1 1.73E+O1 5.92E+O1 3.26E+02 O.OOE+OO 6.31E+03 Te-129M 7.22E+06 2.69E+06 I .14E+06 2.48E+06 3.01 E+07 OOOE+OO 364E+O7 Te-129 3.39E-11 1.27E-11 8.26E-12 2.60E-11 1.43E-1O O.OOE+OO 2.56E-11 Te-131M 4.33E+04 2.12E+04 116E+04 3.35E+04 2.14E+05 O.OOE+OO 2.IOE+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.87E+05 1.86E+05 1.74E+05 2.05E+05 1.79E+06 O.OOE+OO 8.78E+06 I-I 30 5.01 E+05 I .48E+06 5.84E+05 I .25E+08 2.31 E+06 O.OOE+OO I .27E+06 I-I 31 3.55E+08 5.08E+08 2.91 E+08 I .67E+1 I 871 E+08 O.OOE+OO I .34E+08 1-132 1.98E-O1 5.29E-O1 1.85E-O1 1.85E+O1 8.42E-O1 O.OOE+OO 9.93E-02 1-133 4.65E+06 8.09E+06 2.47E+06 J.19E+09 1.41E+07 O.OOE+OO 7.27E+06 1-134 2.27E-12 6.15E-12 2.20E-12 1.07E-1O 9.79E-12 O.OOE+OO 5.36E-15 I-I 35 1 .55E+04 4.06E+04 1 50E+04 2.68E+06 6.51 E+04 OOOE+OO 4.58E+04 Cs-134 1.70E+1O 4.04E+1O 33OE+1O O.OOE+OO 1.31E+1O 434E+09 7.06E+08 Cs-I 36 788E+08 3.1 I E+09 2.24E+09 O.OOE+OO I .73E+09 2.37E+08 353E+O8 Cs-I37 2.2IE+IO 3.03E+IO I.98E+IO OOOE+OO I03E+IO 3.42E+09 5.86E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 5.32E-09 3.79E-12 I.56E-IO O.OOE+OO 3.54E-12 2.15E-12 9.44E-09 Ba-140 3.23E+06 4.05E+03 2.IIE+05 O.OOE+OO I.38E+03 2.32E+03 6.64E+06 Ba-I4I O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-I42 O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-I 40 5.43E-OI 2.74E-OI 7.23E-02 O.OOE+OO O.OOE+OO O.OOE÷OO 2.01 E+04 La-142 2.27E-12 I.03E-I2 2.57E-I3 O.OOE+OO OOOE+OO OOOE+OO 7.53E-09 Ce-141 5.8IE+02 3.93E+02 446E+OI O.OOE+OO I.83E+02 O.OOE+OO I.50E+06 Ce-143 4.98E+OO 3.68E+03 4.07E-OI O.OOE+OO I .62E+OO O.OOE+OO I 38E+O5 Ce-144 4.29E+04 I.79E+04 2.30E+03 O.OOE+OO I.06E+04 O.OOE+OO I.45E+07 Pr-I43 I.90E+OI 7.60E+OO 9.40E-OI O.OOE+OO 439E+OO O.OOE+OO 8.31E+04 Pr-144 O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 I.I4E+OI I.32E+OI Z.87E-OI O.OOE+OO 7.69E+OO O.OOE+OO 6.3IE+04 W-187 7.82E+02 6.53E+02 2.28E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.14E+05 Np-239 4.40E-OI 433E-O2 2.39E-02 O.OOE+OO I .35E-OI OOOE+OO 8.88E+03 Notes:

1) Units are m2 mrem/yr per iiCilsec.

2) For H-3 and C-I4, the units are mrem/yr per tCiIm3.

CY-BY-1 70-301 Revision 14 Page 149 of 188 Table 4-21 Teen Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO I .16E+03 1 .16E+/-03 I .16E+03 1 .16E+03 1 .16E+03 1 .16E+03 C-14 6.70E+05 I .34E+05 1 .34E+05 I .34E+05 I .34E+05 I 34E+O5 I .34E+05 Na-24 5. 1 5E+05 5. 1 5E+05 5. 1 5E+05 5. 1 5E+05 5. 1 5E+05 5. 1 5E+05 5. 1 5E+05 Cr-51 O.OOE+OO O.OOE+OO 5.99E+03 3.33E+03 I .31 E+03 8.55E+03 I O1 E+06 Mn-54 O.OOE+OO I .68E+06 3.34E+05 O.OOE+OO 5O2E+O5 O.OOE+OO 3.45E+06 Mn-56 O.OOE+OO 8.78E-04 1 .56E-04 O.OOE+OO 1 .1 1 E-03 O.OOE+OO 5.78E-02 Fe-55 5.79E+05 4.IIE+05 9.57E+04 O.OOE+OO O.OOE+OO 2.60E+05 178E+05 Fe-59 6.74E+05 1 .57E+06 6.07E+05 O.OOE+OO O.OOE+OO 496E+O5 3.72E+06 Co-58 O.OOE+OO 9.53E+05 2.20E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1 31 E+07 Co-60 O.OOE+OO 3.34E+06 7.52E+06 O.OOE+OO OOOE+OO O.OOE+OO 4.35E+07 Ni-63 142E+09 1.OOE+08 4.81E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.59E+07 Ni-65 8. 1 3E-02 1 .04E-02 4.73E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.63E-O1 Cu-64 OOOE+OO 4.69E+03 2.20E+03 O.OOE+OO 1.19E+04 O.OOE+OO 3.64E+05 Zn-65 2.53E+08 8.78E+08 4.09E+08 O.OOE+OO 5.62E+08 O.OOE+OO 3.72E+08 Zn-69 4.44E-13 8.46E-13 5.92E-14 O.OOE+OO 5.53E-13 O.OOE+OO 1.56E-12 Br-83 O.OOE+OO O.OOE+OO 2.13E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO OOOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 5.68E+08 2.67E+08 O.OOE+OO OOOE+OO O.OOE+OO 8.41 E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 561E+O9 O.OOE+OO 1.61E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.69E+08 Sr-90 1 .71 E+1 I O.OOE+OO 3.41 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.90E+09 Sr-91 1 .1 1 E+05 O.OOE+OO 4.41 E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.02E+05 Sr-92 I .86E+OO O.OOE+OO 7.92E-02 O.OOE+OO OOOE+OO O.OOE+OO 4.74E+O1 Y-90 1 .56E+O1 O.OOE+OO 4.21 E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 1 .29E+05 Y-91M 1.41E-20 O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO 6.66E-19 Y-91 1 9OE+O3 O.OOE+OO 5.08E+O1 OOOE+OO OOOE+OO O.OOE+OO 7.77 E+05 Y-92 1 .23E-05 O.OOE+OO 3.57E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.39E-O1 Y-93 4.90E-02 O.OOE+OO 1 .34E-03 O.OOE+OO O.OOE+OO O.OOE+OO I .50E+03 Zr-95 1 .98E+02 6.25E+O1 4.30E+O1 O.OOE+OO 9.18E+O1 O.OOE+OO I .44E+05 Zr-97 9.44E-02 1 .87E-02 8.61 E-03 O.OOE+OO 2.83E-02 O.OOE+OO 5.06E+03 Nb-95 1 .69E+04 9.38E+03 5.16E+03 O.OOE+OO 9.09E+03 O.OOE+OO 4.01 E+07 Mo-99 O.OOE+OO 5.36E+06 I .02E+06 O.OOE+OO 1 .23E+07 O.OOE+OO 9.59E+06 Tc- 99M 6.89E-O1 I .92E+OO 2.49E+O1 O.OOE+OO 2.86E+O1 1 .OZE+OO 1 .26E+03 Tc-1O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-I 03 2.1 7E+02 O.OOE+OO 9.29E+OI O.OOE+OO 7.66E+02 O.OOE+OO I .81 E+04 Ru-I 05 I .86E-04 O.OOE+OO 7.24E-05 O.OOE+OO 2.35E-03 O.OOE+OO 1 .51 E-OI Ru-106 4.50E+03 O.OOE+OO 5.67E+02 O.OOE+OO 8.68E+03 O.OOE+OO 2.I6E+05 Ag-I IOM 1 .I6E+07 I .09E+07 6.65E+06 O.OOE+OO 2.09E+07 O.OOE+OO 3.07E+09

CY-BY-1 70-301 Revision 14 Page 150 of 188 Table 4-21 (Continued)

Teen Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.61 E+06 I .30E+06 4.82E+05 I .01 E+06 O.OOE+OO O.OOE+OO I .06E+07 Te-1 27M I .01 E+07 3.59E+06 I .20E+06 2.41 E+06 4. 1 OE+07 O.OOE+OO 2.52E+07 Te-127 1 .48E+02 5.25E+O1 3.19E+O1 I .02E+02 6.OOE+02 O.OOE+OO I .14E+04 Te-129M 1 .32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 O.OOE+OO 4.96E+07 Te-129 6.24E-11 2.33E-11 1.52E-11 4.46E-11 2.62E-1O O.OOE+OO 3.41E-1O Te-131M 7.88E+04 3.78E+04 3.15E+04 5.68E+04 3.94E+05 O.OOE+OO 3.03E+06 To-I 31 O.OOE+OO O.OOE÷OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO Te-I32 5.13E+05 3.25E+05 3.06E+05 3A2E+05 3.12E+06 O.OOE+OO I .03E+07 I-I 30 8.82E+05 2.55E+06 I .02E+06 2.08E+08 3.93E+06 O.OOE+OO I .96E+06 1-131 6.45E+08 9.02E+08 4.85E+08 Z63E+11 155E+09 O.OOE+OO 1.78E+08 1-132 3.50E-O1 9.17E-OI 3.29E-O1 3.09E+O1 1.44E+OO O.OOE+OO 3.99E-O1 1-133 8.50E+06 1.44E+07 4.40E+06 2.OIE+09 2.53E+07 O.OOE+OO I.09E+07 1-134 4.03E-12 I.07E-II 3.83E-12 1.78E-1O I.68E-I1 O.OOE+OO 1.41E-13 1-135 2.75E+04 7.09E+04 2.63E+04 4.56E+06 I .12E+05 O.OOE+OO 7.85E+04 Cs-134 2.94E+1O 6.93E+IO 3.22E+1O O.OOE+OO 2.20E+IO 8.41E+09 8.62E+08 Cs-136 1.34E+09 5.28E+09 3.54E+09 O.OOE+OO Z87E+09 453E+O8 4.25E+08 Cs-137 4.02E+IO 5.34E+lO 1.86E+IO O.OOE+OO I82E+IO 7.06E+09 7.60E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-I39 9.84E-09 6.92E-12 2.87E-IO O.OOE+OO 6.53E-12 4.77E-I2 8.78E-08 Ba-140 5.82E+06 7.14E+03 3.75E+05 O.OOE+OO 2.42E+03 48OE+O3 8.98E+06 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO La-140 9.75E-O1 4.79E-OI I .27E-O1 O.OOE+OO O.OOE+OO OOOE+OO 2.75E+04 La-I 42 4.09E-I 2 1 .82E-I 2 4.53E-I 3 O.OOE+OO O.OOE+OO O.OOE+OO 5.53E-08 Ce-I 41 1 .07E+03 7. 1 2E+02 8.1 7E+OI OOOE+OO 3.35E+02 O.OOE+OO 2.04E+06 Ce-143 9.I5E÷OO 6.66E+03 7.44E-OI O.OOE+OO 2.99E+OO O.OOE+OO 2.OOE+05 Ce-I44 7.90E+04 3.27E+04 4.24E+03 O.OOE+OO 1.95E+04 O.OOE+OO I.99E+07 Pr-143 3.48E+OI I .39E+OI I .73E+OO O.OOE+OO 8.08E+OO O.OOE+OO I .I5E+05 Pr-I 44 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO Nd-I 47 2.1 9E+OI 2.38E+OI I .43E+OO O.OOE+OO I .40E+OI O.OOE+OO 8.59E+04 W-187 I .43E+03 I .17E+03 4.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 315E+05 Np-239 8.40E-OI 7.92E-02 4.40E-02 O.OOE+OO 2.49E-OI O.OOE+OO I .27E+04 Notes:

1) Units are m2 mrem/yr per iC i/sec.

2) For H-3 and C-I4, the units are mrem/yr per iCi/m3.

CY-BY-1 70-301 Revision 14 Pagel5l of 188 Table 4-22 Child Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lunq Gl-LLI H-3 O.OOE+OO I .83E+03 I .83E+03 I .83E+03 I .83E+03 1 .83E+03 I .83E+03 C-14 1.65E+06 3.29E+05 3.29E+05 3.29E+05 3.29E+05 3.29E+05 3.29E+05 Na-24 I .07E+06 I .07E+06 I .07E+06 I .07E+06 1 .07E+06 I O7E+O6 1 .07E+06 Cr-51 OOOE+OO O.OOE+OO 1 .22E+04 6.78E+03 I .85E+03 I .24E+04 6.47E+05 Mn-54 O.OOE+OO 2.52E+06 6.70E+05 O.OOE+OO 7.06E+05 O.OOE+OO 2.1 1 E+06 Mn-56 O.OOE+OO I .53E-03 3.46E-04 O.OOE+OO I .85E-03 O.OOE+OO 2.22E-O1 Fe-55 I .45E+06 7.71 E+05 2.39E+05 O.OOE+OO O.OOE+OO 4.36E+05 I .43E+05 Fe-59 I .56E+06 2.53E+06 I .26E+06 O.OOE+OO O.OOE+OO 7.33E+05 2.63E+06 Co-58 O.OOE+OO I .46E+06 4.46E+06 O.OOE+OO O.OOE+OO O.OOE+OO 8.49E+06 Co-60 O.OOE+OO 5i8E+06 1 .53E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+07 Ni-63 3.56E+09 1.90E+08 1.21E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.28E+07 Ni-65 I .99E-O1 I .87E-02 1 .09E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E+OO Cu-64 O.OOE+OO 824E+O3 4.98E+03 O.OOE+OO I .99E+04 O.OOE+OO 3.87E+05 Zn-65 4.96E+08 1 .32E+09 8.22E+08 O.OOE+OO 8.33E+08 O.OOE+OO 2.32E+08 Zn-69 1.09E-12 1.58E-12 1.46E-13 O.OOE+OO 9.57E-13 O.OOE+OO 9.95E-11 Br-83 O.OOE+OO O.OOE+OO 5.24E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1 .05E+09 6.48E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.78E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE÷OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO Sr-89 1.39E+1O O.OOE+OO 3.97E+08 O.OOE+OO O.OOE+OO O.OOE+OO 5.38E+08 Sr-90 3.53E+1 I O.OOE+OO 7.1 1 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.16E+09 Sr-91 2.72E+05 O.OOE+OO I .03E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.OOE+05 Sr-92 4.54E+OO OOOE+OO I .82E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 8.60E+O1 Y-9o 3.87E+O1 O.OOE+OO 1.04E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.IOE+05 Y-91M 345E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.75E-17 Y-91 4.68E+03 O.OOE+OO 1 .25E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+05 Y-92 3.03E-05 O.OOE+OO 8.67E-07 O.OOE+OO O.OOE+OO O.OOE+OO 8.75E-O1 Y-93 I .20E-O1 O.OOE+OO 3.31 E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1 .80E+03 Zr-95 4.60E+02 I .01 E+02 9.OOE+O1 O.OOE+OO I .45E+02 O.OOE+OO I .05E+05 Zr-97 2.30E-O1 3.32E-02 I .96E-02 O.OOE+OO 4.77E-02 O.OOE+OO 5.03E+03 Nb-95 3.82E+04 I .49E+04 I O6E+O4 O.OOE+OO I .40E+04 O.OOE+OO 275E+07 Mo-99 O.OOE+OO 9.75E+06 2.41 E+06 O.OOE+OO 2.08E+07 O.OOE+OO 8.06E+06 Tc- 99M I .58E+OO 3.JOE+OO 5.14E+O1 O.OOE+OO 45OE+O1 I .57E+OO I .76E+03 Tc-1O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO Ru-103 5.14E+02 O.OOE+OO 1.97E+02 O.OOE+OO 1.29E+03 O.OOE+OO 1.33E+04 Ru-I 05 4.55E-04 O.OOE+OO I .65E-04 O.OOE+OO 4.OOE-03 O.OOE+OO 2.97E-OI Ru-106 1.IIE+04 O.OOE+OO I.38E+03 O.OOE+OO L5OE+04 O.OOE+OO I.72E+05 Ag-I I OM 2.51 E+07 I .69E+07 1 .35E+07 O.OOE+OO 3. I 5E+07 O.OOE+OO 2.01 E+09

CY-BY-1 70-301 Revision 14 Page 152 of 188 Table 4-22 (Continued)

Child Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 8.86E+06 2.40E+06 I .18E+06 2.49E+06 O.OOE+OO O.OOE+OO 8.55E+06 Te-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 O.OOE+OO 202E+07 Te-127 3.64E+02 9.83E+OJ 7.82E+O1 2.52E+02 1.04E+03 O.OOE+OO 1.42E+04 Te-129M 3.26E+07 9.09E+06 5.05E+06 1.05E+07 9.56E+07 O.OOE+OO 3.97E+07 Te-129 1.54E-1O 4.30E-11 3.66E-11 1.IOE-1O 4.51E-1O O.OOE+OO 9.59E-09 Te-1 31 M I .92E+05 6.63E+04 7.06E+04 I .36E+05 6.42E+05 O.OOE+OO 2.69E+06 Te-1 31 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-1 32 1 22E+06 542E+05 6.55E+05 7.89E+05 5.03E+06 O.OOE+OO 5.46E+06 1-130 2.06E+06 417E+06 2.15E+06 4.59E+08 6.23E+06 O.OOE+OO 1.95E+06 I-I 31 1 .56E+09 I 57E+09 8.94E+08 5.20E+1 I 2.58E+09 O.OOE+OO I .40E+08 1-132 8.29E-O1 1.52E+OO 7.OOE-O1 7.07E+O1 2.33E+OO O.OOE+OO 1.79E+OO 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 O.OOE+OO 1.03E+07 1-134 9.53E-12 1.77E-1J 8.14E-12 4.07E-fO 2.71E-11 O.OOE+OO 1.IZE-11 1-135 6.52E+04 1.17E+05 5.55E+04 1.04E+07 1.80E+05 O.OOE+OO 8.94E+04 Cs-134 6.79E+1O 1.IIE+11 2.35E+1O O.OOE+OO 3.45E+1O 1.24E+1O 6.OIE+08 Cs-136 3.03E+09 8.32E+09 5.39E+09 O.OOE+OO 4.43E+09 6.61E+08 2.92E÷08 Cs-137 9.67E+1O 926E+1O 1.37E+1O O.OOE+OO 3.02E+1O 1.09E+1O 5.80E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 2.42E-08 1.29E-11 7.OIE-1O O.OOE+OO 113E-11 7.59E-12 1.40E-06 Ba-140 I .41 E+07 I .23E+04 8.21 E+05 O.OOE+OO 4.01 E+03 7.34E+03 7.12E+06 Ba-141 OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO La-140 2.33E+OO 8.16E-O1 2.75E-O1 O.OOE+OO O.OOE+OO O.OOE+00 2.27E+04 La-142 9.88E-12 3.15E-12 9.87E-13 O.OOE+OO OOOE+OO O.OOE+OO 6.24E-07 Ce-141 2.62E+03 I .31 E+03 I .94E+02 O.OOE+OO 5.74E+02 O.OOE+OO I .63E+06 Ce-143 2.25E+O1 I .22E+04 I .76E+OO O.OOE+OO 5.1 1 E+OO O.OOE+OO 1 .78E+05 Ce-144 1.95E+05 6.IIE+04 104E+04 O.OOE+OO 3.38E+04 O.OOE+OO 1.59E+07 Pr-143 8.62E+O1 2.59E+O1 4.28E+OO O.OOE+OO 1.40E+O1 O.OOE+OO 9.30E+04 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE÷OO O.OOE+OO Nd-147 5.37E+O1 435E+O1 3.37E+OO O.OOE+OO 2.39E+O1 O.OOE+OO 6.89E+04 W-187 3.47E+03 2.05E+03 9.21E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.88E+05 Np-239 2.07E+OO 1.48E-O1 1.04E-O1 O.OOE+OO 4.29E-O1 O.OOE+OO 1.IOE+04 Notes:

1) Units are m2 mrem/yr per tCiIsec.

2) For H-3 and C-14, the units are mremlyr per pCi/rn3.

CY-BY-1 70-301 Revision 14 Page 153 of 188 Table 4-23 Infant Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 C-I 4 3.23E+06 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 Na-24 I .87E+06 I .87E+06 I .87E+06 I .87E+06 I .87E+06 I .87E+06 I .87E+06 Cr-51 O.OOE+OO O.OOE+OO I .93E+04 I .26E+04 2.76E+03 2.46E+04 5.64E+05 Mn-54 O.OOE+OO 468E+O6 I .06E+06 O.OOE+OO I .04E+06 O.OOE+OO I 72E+06 Mn-56 O.OOE+OO 3.75E-03 6.47E-04 O.OOE+OO 3.22E-03 O.OOE+OO 3.41 E-OI Fe-55 I 16E+06 I .13E+06 3.03E+05 O.OOE+OO OOOE+OO 5.55E+05 I .44E+05 Fe-59 2.92E+06 5.09E+06 2.01 E+06 O.OOE+OO O.OOE+OO I .51 E+06 2.43E+06 Co-58 O.OOE+OO 2.91 E+06 7.26E+06 O.OOE+OO O.OOE+OO O.OOE+OO 7.25E+06 Co-60 O.OOE+OO I .06E+07 2.50E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.52E+07 Ni-63 4.19E+09 2.59E+08 I.45E+08 O.OOE+OO OOOE+OO O.OOE+OO 1.29E+07 Ni-65 4.21E-OI 4.77E-02 2.17E-02 O.OOE+OO O.OOE+OO OOOE+OO 3.63E+OO Cu-64 O.OOE+OO 2.05E+04 9.48E+03 O.OOE+OO 3.46E+04 O.OOE+OO 4.20E+05 Zn-65 6.66E+08 2.28E+09 I .05E+09 O.OOE+OO I .1 1 E+09 O.OOE+OO I .93E÷09 Zn-69 2.33E-12 4.19E-12 3.12E-13 O.OOE+OO I.74E-12 O.OOE+OO 3.42E-1O Br-83 O.OOE+OO O.OOE+OO I .1 1 E-O1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.67E+09 I .32E+09 O.OOE+OO O.OOE+OO O.OOE+OO 6.84E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 2.64E+IO O.OOE+OO 7.58E+08 O.OOE+OO O.OOE+OO O.OOE+OO 5.43E+08 Sr-90 3.91 E+I I O.OOE+OO Z.92E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.19E+09 Sr-91 5.66E+05 O.OOE+OO 2.05E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.70E+05 Sr-92 9.65E+OO O.OOE+OO 3.59E-OI O.OOE+OO O.OOE+OO O.OOE+OO I .04E+02 Y-90 8.19E+OI O.OOE+OO 2.20E+OO O.OOE+OO O.OOE+OO O.OOE+OO I.13E+05 Y-91M 7.31E-20 OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2A4E-16 Y-91 8.79E+03 O.OOE+OO 2.34E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.30E+05 Y-92 6.44E-05 O.OOE+OO I .81 E-06 O.OOE+OO O.OOE+OO O.OOE+OO I .23E+OO Y-93 2.57E-O1 OOOE+OO 6.99E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.03E+03 Zr-95 8.1 7E+02 I .99E+02 I .41 E+02 O.OOE+OO 2.1 5E+02 O.OOE+OO 9.91 E+04 Zr-97 4.87E-OI 8.35E-02 3.81 E-02 O.OOE+OO 8.42E-02 O.OOE+OO 5.33E+03 Nb-95 7.13E+04 2.94E+04 I .70E+04 O.OOE+OO 2.IOE+04 O.OOE+OO 2.48E+07 Mo-99 O.OOE+OO 249E+07 4.86E+06 O.OOE+OO 3.72E+07 O.OOE+OO 8.21 E+06 Tc- 99M 3.29E+OO 6.78E+OO 8.73E+O1 O.OOE+OO 7.29E+OI 3.54E+OO I .97 E+03 Tc-I 01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00 E+00 Ru-103 1.04E+03 0.OOE+00 3.48E+02 0.OOE+00 2.16E+03 0.OOE+00 I.27E+04 Ru-I 05 9.60E-04 0.OOE+00 3.23E-04 0.OOE+00 7.06E-03 0.OOE+00 3.82E-0I Ru-I 06 2.28E+04 0.OOE+00 2.85E+03 0.OOE+00 2.70E+04 0.OOE+00 I .73E+05 Ag-IbM 4.63E+07 3.38E+07 2.24E+07 0.OOE+00 4.84E+07 0.OOE+00 I.75E+09

CY-BY-1 70-301 Revision 14 Page 154 of 188 Table 4-23 (Continued)

Infant Grass-Goat-M ilk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1 .81 E+07 6.05E+06 2.45E+/-06 6.09E+06 O.OOE+/-OO O.OOE+OO 8.62E+06 Te-127M 5.05E+07 I .68E+07 6.12E+06 I .46E+07 1 .24E+08 O.OOE+OO 2.04E+07 Te-127 7.74E+02 2.59E+02 I .66E+02 6.30E+02 I .89E+03 O.OOE+OO I .63E+04 Te-129M 6.68E+07 2.29E+07 1 O3E+O7 2.57E+07 I .67E+08 O.OOE+OO 3.99E+07 Te-129 3.26E-1O 1.13E-1O 762E-11 2.74E-1O 8.13E-1O O.OOE+OO 2.61E-08 Te-1 31 M 4.05E+05 I .63E+05 I .35E+05 33OE+O5 I .1 2E+06 O.OOE+OO 2.74E+06 Te-131 O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.52E+06 I .25E+06 1 .17E+06 I .84E+06 7.81 E+06 O.OOE+OO 4.62E+06 I-I 30 4.24E+06 932E+O6 3.74E+06 I .04E+09 1 .02E+07 O.OOE+OO 200E+06 1-131 3.26E+09 3.85E+09 1.69E+09 1.26E+12 4.49E+09 O.OOE+OO 1.37E+08 I-I 32 1 72E+OO 3.49E+OO I .24E+OO I .64E+02 3.90E+OO O.OOE+OO 2.83E+OO I-I 33 4.36E+07 635E+O7 I .86E+07 I 1 5E+1 0

. 7.46E+07 O.OOE+OO I .07E+07 1-134 1.98E-11 4.05E-11 1.44E-11 9.44E-1O 4.53E-11 O.OOE+OO 4.19E-11 1-135 1.36E+05 2.70E+05 9.83E+04 2.42E+07 3.OIE+05 O.OOE+OO 9.76E+04 Cs-134 1.09E+11 2.04E+11 2.06E+1O O.OOE+OO 5.25E+1O 2.15E+1O 5.54E+08 Cs-136 5.91E+/-09 1.74E+1O 6.49E+09 O.OOE+OO 6.93E+09 1.42E+09 264E+08 Cs-137 1.54E+11 1.81E+11 1.28E+1O O.OOE+OO 485E+1O 1.96E+1O 5.65E+08 Cs-I 38 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 5.14E-08 3.41 E-I I I .49E-09 OOOE+OO 2.05E-I I 2.07E-I I 3.26E-06 Ba-140 2.89E+07 2.89E+04 I .49E+06 O.OOE+OO 6.87E+03 I .78E+04 7.1 I E+06 Ba-I 41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-I 42 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 4.88E+OO I .92E+OO 4.95E-OI O.OOE+OO O.OOE+OO O.OOE+OO 2.26E+04 La-I42 2.08E-II 7.62E-I2 I.82E-I2 O.OOE+OO O.OOE+OO O.OOE+OO I.29E-06 Ce-14I 5.20E+03 317E+03 3.73E+02 O.OOE+OO 9.78E+02 O.OOE+OO I.64E+06 Ce-I 43 4.75E+O I 3. 1 5E+04 3.60E+OO O.OOE+OO 9. 1 9E+OO OOOE+OO I .84E+05 Ce-I44 2.79E+05 I .I4E+05 I .56E+04 O.OOE+OO 4.62E+04 OOOE+OO I .60E+07 Pr-I 43 I .78E+02 6.67E+O1 8.84E+OO O.OOE+OO 2.48E+OI O.OOE+OO 9.41 E+04 Pr-144 O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO Nd-147 I .07E+02 I .09E+02 6.70E+OO OOOE+OO 4.22E+OI O.OOE+OO 6.93E+04 W-I87 729E+03 5.07E+03 I .75E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.98E+05 Np-239 4.37E+OO 3.91 E-OI 2.21 E-O1 O.OOE+OO 7.80E-OI O.OOE+OO I I 3E+04 Notes:

I) Units are m2 mrem/yr per iCi/sec.

2) For H-3 and C-14, the units are mrem/yr per tCiIm3.

CY-BY-1 70-301 Revision 14 Page 155 of 188 Table 4-24 Adult Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO I .85E÷02 I .85E+02 1 .85E+02 I .85E+02 I 85E+O2 1 .85E÷02 C-14 3.33E+05 6.66E+04 6.66E+04 6.66E+04 6.66E+04 6.66E+04 6.66E+04 Na-24 I .45E-03 1 .45E-03 1 .45E-03 I .45E-03 I .45E-03 I .45E-03 1 .45E-03 Cr-51 O.OOE+OO O.OOE+OO 7.04E+03 4.21 E+03 I 55E+O3 934E+O3 1 .77E+06 Mn-54 O.OOE+OO 9.18E+06 1 .75E+06 O.OOE+OO 2.73E+06 O.OOE+OO 2.81 E+07 Mn-56 O.OOE+OO OOOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE÷OO O.OOE+OO Fe-55 2.93E+08 2.03E+08 4.72E+07 O.OOE+OO O.OOE+OO 1 .13E+08 I .16E+08 Fe-59 2.65E+08 6.24E+08 2.39E+08 O.OOE+OO O.OOE+OO I .74E+08 2.08E+09 Co-58 O.OOE+OO I .82E÷Of 4.09E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+08 Co-60 O.OOE+OO 7.52E+07 1 .66E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1 .41 E+09 Ni-63 1.89E+09 1.31E+08 6.33E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.73E+07 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 2.52E-07 I I 8E-07 O.OOE+OO 6.36E-07

. O.OOE+OO 2. 1 5E-05 Zn-65 3.56E+08 1 .13E+09 5.12E+08 O.OOE+OO 7.57E+08 O.OOE+OO 7.13E+08 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.88E+08 2.28E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.63E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 3O1 E+08 O.OOE+OO 8.65E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.83E+07 Sr-90 1.43E+1O O.OOE+OO 2.87E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.59E+08 Sr-91 1.43E-1O O.OOE+OO 5.79E-12 O.OOE+OO O.OOE+OO O.OOE+OO 6.83E-1O Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 I .08E+02 O.OOE+OO 2.91 E+OO O.OOE+OO O.OOE+OO O.OOE+OO I .15E+06 Y-91M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 I .1 3E+06 O.OOE+OO 3.03E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.23E+08 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 4.39E-1 2 O.OOE+OO I .21 E-1 3 O.OOE+OO O.OOE+OO O.OOE+OO I 39E-O7 Zr-95 I .87E+06 6.01 E+05 4.07E+05 O.OOE+OO 9.43E+05 O.OOE+OO I .91 E+09 Zr-97 2.04E-05 4.12E-06 I .88E-06 O.OOE+OO 622E-06 OOOE+OO I .28E+OO Nb-95 2.30E+06 I .28E+06 689E+O5 O.OOE+OO I .27E+06 O.OOE+OO 7.78E+09 Mo-99 O.OOE+OO 9.93E+04 I .89E+04 O.OOE+OO 2.25E+05 O.OOE+OO 2.30E+05 Ic- 99M O.OOE+OO I .22E-20 I .56E-1 9 O.OOE+OO I .85E-1 9 O.OOE+OO 7.23E-1 8 Ic-lOl O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-I 03 1 .05E+08 O.OOE+OO 4.53E+07 O.OOE+OO 4.01 E+08 O.OOE+OO I .23E+1 0 Ru-105 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-106 2.80E+09 0.OOE+00 3.54E+08 0.OOE+00 5.40E+09 0.OOE+00 I.81E+11 Ag-IIOM 6.68E+06 6.18E+06 3.67E+06 0.OOE+00 I.22E+07 0.OOE+00 2.52E+09

CY-BY-1 70-301 Revision 14 Page 156 of 188 Table 4-24 (Continued)

Ad ult Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-1 25M 3.59E+08 I .30E+08 4.81 E+07 I .08E+08 I .46E+09 O.OOE+OO I .43E+09 Te-127M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 O.OOE+OO 3.74E+09 Te-127 2.50E-1O 8.98E-J1 5.41E-1J 185E-1O 1.02E-09 O.OOE+OO 1.97E-08 Te-129M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 O.OOE+OO 5.71E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO Te-131M 4.49E+02 2.20E+02 183E+02 3.48E+02 2.23E+03 O.OOE+OO 2.18E+04 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 1.40E+06 9.03E+05 8.48E+05 9.98E+05 8.70E+06 O.OOE+OO 4.27E+07 1-130 203E-06 5.98E-06 2.36E-06 5.07E-04 9.33E-06 O.OOE÷OO 5.15E-06 1-131 1.07E+07 1.54E+07 8.80E+06 5.03E+09 2.63E+07 O.OOE+OO 4.05E+06 1-132 O.OOE÷OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 3.70E-O1 6.43E-O1 1.96E-O1 945E+O1 1.12E+OO O.OOE+OO 5.78E-O1 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO 1-135 466E-17 1.22E-16 4.50E-17 8.04E-15 1.95E-16 O.OOE+OO 1.38E-16 Cs-I 34 6.58E+08 I .57E+09 I .28E+09 O.OOE+OO 5.07E+08 I .68E+08 2.74E+07 Cs-136 I.20E+07 4.73E+07 3.40E+07 O.OOE+OO 2.63E+07 3.61E+06 5.37E+06 Cs-137 8.72E+08 I.19E+09 7.81E+08 O.OOE+OO 4.05E+08 I.35E+08 2.31E+07 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-I 39 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 2.88E+07 3.61 E+04 I .88E+06 OOOE+OO 1 23E+O4 2.07E+04 5.92E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-I 42 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 3.76E-02 I.90E-02 5.OIE-03 O.OOE+OO OOOE+OO O.OOE+OO I.39E+03 La-I 42 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 I.40E+04 9.49E+03 I.08E+03 O.OOE+OO 4.41E+03 O.OOE+OO 3.63E+07 Ce-143 I .99E-02 I .47E+OI I .63E-03 OOOE+OO 6.47E-03 O.OOE+OO 5.49E+02 Ce-I44 I 46E+06 6.09E+05 7.83E+04 O.OOE+OO 3.61 E+05 O.OOE+OO 4.93E+08 Pr-143 2.IOE+04 8.42E+03 I.04E+03 O.OOE+OO 4.86E+03 O.OOE+OO 9.20E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO OOOE+OO Nd-147 7.21 E+03 8.33E+03 4.98E+02 O.OOE+OO 4.87E+03 O.OOE+OO 4.OOE+07 W-187 2.07E-02 I.73E-02 6.04E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.66E+OO Np-239 2.57E-OI 2.53E-02 I .40E-02 O.OOE+OO 7.90E-02 O.OOE+OO 5.I9E+03 Notes:

I) Units are m2 mrem/yr per tCiIsec.

2) For H-3 and C-14, the units are mrem/yr per jiCi/m3.

CY-BY-1 70-301 Revision 14 Page 157 of 188 Table 4-25 Teen Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 OOOE+OO 1 IOE+02 I .IOE+02 I .IOE+02 I .IOE+02 I .IOE+02 I .IOE+02 C-14 2.81E+05 5.62E+04 5.62E+04 5.62E+04 5.62E+04 5.62E+04 5.62E+04 Na-24 I 16E-03 I .16E-03 I .16E-03 I .16E-03 I .16E-03 I .16E-03 I .16E-03 Cr-51 O.OOE+OO O.OOE+OO 5.63E+03 3.13E+03 1.23E+03 8.04E+03 9.46E+05 Mn-54 O.OOE+OO 7.OOE+06 1 .39E+06 O.OOE+OO 2.09E+06 O.OOE+OO 1 A4E+07 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 2.38E+08 I .69E+08 3.94E+07 O.OOE+OO O.OOE+OO I .07E+08 73J E+07 Fe-59 2.12E+08 4.95E+08 I .91 E+08 O.OOE+OO O.OOE+OO 1 .56E+08 I .17E÷09 Co-58 O.OOE+OO I .41 E+07 3.24E+07 O.OOE+OO OOOE+OO O.OOE+OO I .94E+08 Co-60 O.OOE+OO 5.83E+07 I .31 E+08 O.OOE+OO O.OOE+OO O.OOE+OO 7.60E+08 Ni-63 I .52E+09 I .07E+08 5.15E+07 O.OOE+OO O.OOE+OO O.OOE+OO I .71 E+07 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 2.06E-07 9.68E-08 O.OOE+OO 5.21 E-07 O.OOE+OO 1 .60E-05 Zn-65 2.50E+08 8.69E+08 4.05E+08 O.OOE+OO 5.56E+08 O.OOE+OO 3.68E+08 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.08E+08 I .91 E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.03 E+07 Rb-88 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Rb-89 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-89 2.54E+08 0.OOE+00 7.28E+06 0.OOE+00 0.OOE+00 0.OOE+00 3.03E+07 Sr-90 9.89E+09 0.OOE+00 I .98E+08 0.OOE+00 0.OOE+00 0.OOE+00 2.26E+08 Sr-91 1.21E-10 0.OOE+00 4.80E-12 0.OOE+00 0.OOE+00 0.OOE+00 5.47E-10 Sr-92 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-90 9. 1 3E+01 0.OOE+00 2.46E+00 0.OOE+00 0.OOE+00 0.OOE+00 7.53E+05 Y-91 M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-91 9.54E+05 0.OOE+00 2.56E+04 0.OOE+00 0.OOE+00 0.OOE+00 3.91 E+08 Y-92 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-93 3.71E-12 0.OOE+00 1.02E-13 0.OOE+00 0.OOE+00 0.OOE+00 1.13E-07 Zr-95 I .50E+06 4.74E+05 3.26E+05 0.OOE+00 6.96E+05 0.OOE+00 I .09E+09 Zr-97 1.70E-05 3.37E-06 1.55E-06 0.OOE+00 5.IOE-06 0.OOE+00 9.IIE-01 Nb-95 I .80E+06 9.98E+05 5.49E+05 0.OOE+00 9.67E+05 0.OOE+00 4.27E+09 Mo-99 0.OOE+00 8.21 E+04 1 .57E+04 0.OOE+00 I .88E+05 0.OOE+00 I .47E+05 Tc- 99M 0.OOE+00 0.OOE+00 I .24E-1 9 0.OOE+00 I .43E-1 9 0.OOE+00 6.29E-1 8 Tc-101 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-103 8.56E+07 0.OOE+00 3.66E+07 0.OOE+00 3.02E+08 0.OOE+00 7.15E+09 Ru-I 05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-106 2.36E+09 0.OOE+00 2.97E+08 0.OOE+00 4.55E+09 0.OOE+00 I .13E+I I Ag-I IOM 5.06E+06 4.79E+06 2.91 E+06 0.OOE+00 9.I3E+06 0.OOE+00 I .35E+09

CY-BY-1 70-301 Revision 14 Page 158 of 188 Table 4-25 (Continued)

Teen Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.03E+08 1.09E+08 4.06E+07 8.47E+07 O.OOE+OO O.OOE+OO 8.95E+08 Te-127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.82E+09 O.OOE+OO 2.35E+09 Te-127 2.12E-1O 7.53E-11 4.57E-11 1.46E-1O 8.60E-1O O.OOE+OO 1.64E-08 Te-129M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 O.OOE+OO 3.56E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-1 31 M 3.75E+02 I .80E+02 I .50E+02 2.70E+02 I .87E+03 O.OOE+OO I .44E+04 Te-1 31 O.OOE+OO OOOE+OO OOOE+OO O.OOE+OO OOOE+OO O.OOE+OO 0.00 E+00 Te-132 I .14E+06 7.24E+05 6.81 E+05 7.63E+05 6.94E+06 0.OOE+00 2.29E+07 I-i 30 1 .63E-06 4.72E-06 I .88E-06 3.85E-04 7.27E-06 0.OOE+00 3.63E-06 1-131 8.92E+06 1.25E+07 6.71E+06 3.64E+09 2.15E+07 0.OOE+00 2.47E+06 1-132 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-133 3.09E-01 5.25E-01 1.60E-01 7.32E+01 9.20E-01 0.OOE+00 3.97E-01 1-134 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-135 3.79E-17 9.75E-17 3.61E-17 6.27E-15 1.54E-16 0.OOE+00 1.08E-16 Cs-134 5.23E+08 1.23E+09 5.71E+08 0.OOE+00 3.91E+08 1.49E+08 1.53E+07 Cs-136 9.34E+06 3.68E+07 2.47E+07 0.OOE+00 2.OOE+07 3.15E+06 2.96E+06 Cs-137 7.24E+08 9.63E+08 3.36E+08 0.OOE+00 3.28E+08 1.27E+08 1.37E+07 Cs-138 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-I 39 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00 E+00 Ba-I40 2.38E+07 2.91 E+04 I .53E+06 0.OOE+00 9.88E+03 I .96E+04 3.67E+07 Ba-I 41 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00 E+00 Ba-I 42 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00 E+00 La-140 3.09E-02 I .52E-02 4.04E-03 0.OOE+00 0.OOE+00 0.OOE+00 8.73E+02 La-I 42 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ce-141 I.18E+04 7.87E+03 9.04E+02 0.OOE+00 3.70E+03 0.OOE+00 2.25E+07 Ce-143 I .67E-02 I .22E+0I I .36E-03 0.OOE+00 5.46E-03 0.OOE+00 3.66E+02 Ce-144 I .23E+06 5.08E+05 6.60E+04 0.OOE+00 3.04E+05 0.OOE+00 3.09E+08 Pr-143 I.77E+04 Z.05E+03 8.79E+02 0.OOE+00 4.IOE+03 0.OOE+00 5.81E+07 Pr-144 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nd-147 6.35E+03 6.90E+03 4.14E+02 0.OOE+00 4.05E+03 0.OOE+00 2.49E+07 W-187 I.73E-02 I.41E-02 4.94E-03 0.OOE+00 0.OOE+00 0.OOE+00 3.82E+00 Np-239 2.25E-0I 2.12E-02 I .18E-02 0.OOE+00 6.66E-02 0.OOE+00 3.41 E+03 Notes:

I) Units are m2 mrem/yr per tCiIsec.

2) For H-3 and C-14, the units are mrem/yr per tCiIm3.

CY-BY-1 70-301 Revision 14 Page 1 59 of I 88 Table 4-26 Child Grass-Cow-Meat Dose Factors Nuclide Bone Liver Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO I .34E+02 I .34E+02 I .34E+02 I .34E+02 I .34E+02 I .34E+02 C-14 5.29E+05 I .06E+05 I .06E+05 I .06E+05 I .06E+05 I .06E+05 I .06E+05 Na-24 I .84E-03 I .84E-03 I .84E-03 I .84E-03 I .84E-03 I .84E-03 I .84E-03 Cr-51 O.OOE+OO O.OOE+OO 8.78E+03 4.87E+03 I .33E+03 8.90E+03 4.66 E+05 Mn-54 O.OOE+OO 8.01 E+06 2.1 3E+06 O.OOE+OO 2.25E+06 O.OOE+OO 6.72E+06 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 4.57E+08 2.42E+08 7.51 E+07 O.OOE+OO O.OOE+OO I .37E+08 4.49E+Of Fe-59 3.76E+08 6.08E+08 3.03E+08 O.OOE+OO O.OOE+OO 1.76E+08 6.34E+08 Co-58 O.OOE+OO I .64E+Of 5.03E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.59E+O7 Co-60 O.OOE+OO 6.93E+07 2.04E+08 O.OOE+OO O.OOE+OO O.OOE÷OO 3.84E+08 Ni-63 2.91 E+09 I .56E+08 9.91 E+07 O.OOE+OO O.OOE+OO O.OOE+OO I .05E+07 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 2.77E-07 I .67E-07 O.OOE+OO 6.68E-07 O.OOE+OO I .30E-05 Zn-65 3.75E+08 I .OOE+09 6.22E+08 O.OOE+OO 6.30E+08 O.OOE+OO I .76E+08 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 5.78E+08 3.55E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.72E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 4.81E+08 O.OOE+OO 1.37E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.86E+07 Sr-90 I .57E+1O O.OOE+OO 3.15E+08 O.OOE+OO O.OOE+OO O.OOE+OO I .40E+08 Sr-91 2.26E-1O O.OOE+OO 8.54E-12 O.OOE+OO O.OOE+OO O.OOE+OO 5.OOE-1O Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 I .73E+02 O.OOE+OO 4.62E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.92E+05 Y-91 M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 1.80E+06 O.OOE+OO 4.82E÷04 O.OOE+OO O.OOE+OO O.OOE+OO 2.40E+08 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 6.97E-12 O.OOE+OO 1.91E-13 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E-07 Zr-95 2.67E+06 5.86E+05 5.22E+05 O.OOE+OO 8.39E+05 O.OOE+OO 6.1 1 E+08 Zr-97 3.16E-05 4.57E-06 2.70E-06 O.OOE+OO 6.56E-06 O.OOE+OO 6.93E-O1 Nb-95 3.1 1 E+06 I .21 E+06 8.64E+05 O.OOE+OO I .14E+06 O.OOE+OO 2.24E+09 Mo-99 O.OOE+OO I .14E+05 2.82E+04 O.OOE+OO 2.44E+05 O.OOE+OO 9.44E+04 Tc- 99M O.OOE+OO 1.18E-20 1.96E-19 O.OOE+OO 1.72E-19 O.OOE+OO 6.72E-18 Tc-1 01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00 E+00 Ru-103 1.55E+08 0.OOE+00 5.95E+07 0.OOE+00 3.90E+08 0.OOE+00 4.OOE+09 Ru-105 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-i 06 4.44E+09 0.OOE+00 5.54E+08 0.OOE+00 5.99E+09 0.OOE+00 6.90E+ 10 Ag-ibM 8.39E+06 5.67E+06 4.53E+06 0.OOE+00 1.06E+07 0.OOE+00 6.74E+08

CY-BY-1 70-301 Revision 14 Page 160 of 188 Table 4-26 (Continued)

Child Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 5.70E+08 1.54E+08 7.59E+/-07 1.60E+08 O.OOE+OO O.OOE+/-OO 5.50E+08 Te-127M 1.77E+09 4.78E+08 2.IIE+08 4.24E+08 5.06E+09 O.OOE+OO 1.44E+09 Te-127 3.99E-1O 1.08E-1O 8.56E-11 2.76E-1O 1.14E-09 O.OOE+OO 1.56E-08 Te-129M I .79E+09 5.OOE+08 2.78E+08 5.77E+08 5.25E+09 O.OOE+OO 2.18E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131M 6.97E+02 2.41E+02 2.57E+02 4.96E+02 2.33E+03 O.OOE+OO 9.78E+03 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.09E+06 9.23E+05 I .12E+06 I .34E+06 8.57E+06 O.OOE+OO 9.30E+06 1-130 2.92E-06 5.89E-06 3.04E-06 6.49E-04 8.81 E-06 O.OOE+OO 2.76E-06 I-I 31 1 .65E+07 1 .66E+07 9.45E+06 5.50E+09 2.73E+07 O.OOE+OO I .48E+06 I-I 32 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 5.75E-O1 7.IOE-O1 2.69E-O1 1.32E+02 1.18E+OO O.OOE+OO 2.86E-O1 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-135 6.86E-17 1.23E-16 5.84E-17 1.09E-14 1.89E-16 O.OOE+OO 9.40E-17 Cs-134 9.22E+08 I .51 E+09 3.19E+08 O.OOE+OO 4.69E+08 I .68E+08 8.16E+06 Cs-136 1.61E+07 4.43E+07 2.87E+07 O.OOE+OO 2.36E+07 3.52E+06 1.56E+06 Cs-137 1.33E+09 1.28E+09 1.88E+08 O.OOE+OO 4.16E+08 1.50E+08 7.99E+06 Cs-I 38 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 4.39E+07 3.84E+04 2.56E+06 O.OOE+OO I .25E+04 2.29E+04 2.22E+07 Ba-I 41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 5.66E-02 I .98E-02 6.67E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.52E+02 L::i 42 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 2.22E+04 I .1 1 E+04 I .64E+03 O.OOE+OO 4.85E+03 O.OOE+OO I .38E+07 Ce-143 3.14E-02 I .70E+O1 2.46E-03 O.OOE+OO 7.14E-03 O.OOE+OO 2.49E+02 Ce-144 2.32E+06 7.26E+05 I.24E+05 O.OOE+OO 4.02E+05 O.OOE+OO I.89E+08 Pr-143 3.34E+04 I .OOE+04 I .66E+03 O.OOE+OO 5.44E+03 O.OOE+OO 3.61 E+OZ Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 I .19E+04 9.65E+03 7.47E+02 O.OOE+OO 5.29E+03 O.OOE+OO I .53E+07 W-187 3.21 E-02 I .90E-02 8.52E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.67 E+OO Np-239 4.23E-OI 3.04E-02 2.14E-02 O.OOE+OO 8.79E-02 O.OOE+OO 2.25E+03 Notes:

1) Units are m2 mrem/yr per iCiIsec.

2) For H-3 and 0-14, the units are mrem/yr per iCiIm3.

3) The infant age group is assumed to receive no dose through the meat ingestion pathway therefore no dose factors are supplied.

CY-BY-1 70-301 Revision 14 Pagel6l of 188 Table 4-27 Byron Station Characteristics LOCATION: 3.7 miles SSW of Byron, Illinois Characteristics of Elevated Release Point: Not applicable (NA)

1) Release Height = m 2) Diameter= m

3) Exit Speed _ms1 4) Heat Content_Kcal s Characteristics of Vent Stack Release Point

1) Release Height 60.66 ma 2) Diameter = 2.80 m

3) Exit Speed 13.00 msla Characteristics of Ground Level Point

1) Release Height = 0 m

2) Building Factor (D) = 60.6 ma Meteorological Data A 250 ft Tower is Located I 036 m SW of vent stack release point Tower Data Used in Calculations Wind Speed Differential Release Point and Direction Temperature Elevated (NA) (NA)

Vent 250 ft 250-30 ft Ground 30 ft 250-30 ft a

Used in calculating the meteorological and dose factors in Table 4-1 and Table 4-4.

CY-BY-1 70-301 Revision 14 Page 162 of 188 Table 4-28 Dose Factors for Noble Gases Beta Air Beta Skin Gamma Air Gamma Total Dose Factor Dose Factor Dose Factor Body Dose Factor N1 L M K, Nuclide (mrad/yr per (mrem/yr per (mrad/yr per (mrem/yr per uCiIm3) uCi/m3) uCi/m3) uCi/m3)

Kr-83m 2.88E+02 --- I .93E+O1 7.56E-02 Kr-85m 1.97E+03 1.46E+03 1.23E+03 1.17E+03 Kr-85 I .95E+03 I .34E+03 I .72E+O1 I .61 E+O1 Kr-87 1 .03E+04 9.73E+03 6.1 7E+03 5.92E+03 Kr-88 2.93E+03 2.37E+03 I 52E+O4 I .47E+04 Kr-89 1.06E+04 1.OIE+04 1.73E+04 1.66E+04 Kr-90 7.83E+03 7.29E+03 I .63E+04 I .56E+04 Xe-I 31 m I .1 1 E+03 476E+02 I .56E+02 9.1 5E+O1 Xe-I 33m I .48E+03 9.94E+02 3.27E+02 2.51 E+02 Xe-I 33 1 .05E+03 3.06E+02 3.53E+02 2.94 E÷02 Xe-135m 7.39E+02 7.IIE+02 3.36E+03 3.12E+03 Xe-135 2.46E+03 1.86E+03 1.92E+03 1.81E+03 Xe-137 I.27E+04 1.22E+04 1.51E+03 1.42E+03 Xe-I 38 4.75E+03 4. 1 3E+03 9.21 E+03 8.83E+03 Ar-4I 3.28E+03 2.69E+03 9.30E+03 8.84E+03 Source: Table B-I of US NRC Regulatory Guide 1.109

CY-BY-J 70-301 Revision 14 Page 163 of 188

5. TOTAL DOSE 5.1 . Total Dose Calculation Requirements 5.1.1. Total Effective Dose Equivalent Limits; IOCFR2O and 4OCFRI9O The Byron Station is required to determine the total dose to a member of the public due to all uranium fuel cycle sources in order to assess compliance with 4OCFRI 90 as part of demonstrating compliance with I OCFR2O.

2. The total dose for the uranium fuel cycle is the sum of doses due to radioactivity in airborne and liquid effluents and the doses due to direct radiation from contained sources at the nuclear power station. When evaluation of total dose is required for a station, the following contributions are summed:

A. Doses due to airborne and liquid effluents from the station.

B. Doses due to liquid effluents from nuclear power stations upstream.

C. Doses due to any onsite radioactive waste storage facilities, if applicable.

D. DosesduetolSFSl

3. 1 OCFR2O requires compliance to dose limits expressed as Total Effective Dose Equivalent (TEDE). Although annual dose limits in IOCFR2O are now expressed in terms ofTEDEs, 4OCFRI9O limits remain stated as organ dose. The NRC continues to require IOCFR5O Appendix I and 4OCFRI9O doses to be reported in terms of organ dose and not TEDE. Due to the fact that organ dose limits set forth in 4OCFRI 90 are substantially lower than those of I OCFR2O (25 mrem/yr vs. 100 mrem/yr), the NRC has stated that demonstration of compliance with the dose limits in 4OCFRI 90 will be deemed as demonstration of compliance with the dose limits of IOCFR2O for most facilities (Reference 104). In addition to compliance with 4OCFRI 90, it may be necessary for a nuclear power plant to address dose from on-site activity by members ofthe public.

CYBY-1 70-301 Revision 14 Page 164 of 188 5.1.2. ISFSI I . IOCFR72.104 dose limits are the same as those specified by 4OCFRI9O.

2. ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. The IOCFR72.212 report prepared in accordance with ISFSI requirements assumes a certain array of casks exists on the pad. The dose contribution from this array of casks in combination with historical uranium fuel cycle operations prior to ISFSI operations was analyzed to be within the 400FRI9O and IOCFR72.104 limits, and is documented in Holtec Report No. Hl-2146048, Dose Versus Distance from a HI-STORM 1005 version B containing the MPC-32 for Byron/Braidwood.

3. lfthe dose limits of4OCFRI9O or IOCFR72.104 are exceeded, a special report to the NRC as well as an appropriate request for exemption/variance is required to be submitted to the NRC.

4. The requirement that the dose limits of IOCFR72.104 apply to any real individual is controlled for ISFSI activities in the ISFSI 72.212 report. Therefore, for the purposes of analyzing dose from the ISFSI, the member of the public as defined in 4OCFRI9O is the same as the real individual identified in the 72.212 report.

5.1.3. Total Dose Calculation Methodology 1 . In addition to the total body, skin and single organ dose assessments previously described, an additional assessment is required. The additional assessment addresses radiation dose due to radioactivity contained within the nuclear power station and its structures.

2. Pressurized water reactors have the potential to affect off-site doses from contained sources of radioactivity, primarily due to gamma rays associated with radioactive material contained in onsite radwaste and radioactive material storage facilities.

5.2. Onsite Radwaste and Rad Material Storage Facilities I . A I OCFR5O.59 analysis is required for radwaste storage facilities.

5.2.1 . Process Waste Storage Facilities A. Interim Radwaste Storage Facility (IRSF) structure B. Concrete vaults containing radwaste liners

CY-BY-1 70-301 Revision 14 Page 165 of 188 5.2.2. DAW Storage Facilities I . Dry Active Waste (DAW) facilities (may include Butler buildings/warehouses)

2. Seavans or other temporary warehouses 5.2.3. Replaced Steam Generator Storage Facilities 52.4. lSFSl Facilities I Independent spent fuel storage installation facilities.

5.3. Methodology I . The external total body dose is comprised of the following parts:

A. Total body dose due to noble gas radionuclides in gaseous effluents (Section 4.2.2.3),

B. Dose due to other contained sources and C. Total body dose due to radioactivity deposited on the ground (Section 4.2.3.1).

2. The external total body dose due to radioactivity deposited on the ground is accounted for in the determination of the non-noble gas dose and is considered in section 5.7.

3. The total external total body dose, DEX, is given by:

D= DTB + 0OSF (5-1) 0Ex Total External Total Body Dose [mrem]

Total external total body dose due to irradiation by external sources at the location of interest.

DTB Noble Gas Total Body Dose [mremJ External total body dose due to gamma radiation from noble gas radionuclides released in gaseous effluents at the location of interest. See Section 42.2.3.

DOSF Dose From On-Site Storage Facilities [mrem]

External total body dose due to gamma radiation from on-site storage facilities at the location of interest. See Section 5.2.

CY-BY-1 70-301 Revision 14 Page 1 66 of 188 5.4. Total Dose I . The total dose, DT0t, j the unrestricted area to a member of the public due to plant operations is given by:

DT0t DEX + D.q + DNG (5-2) where:

DT0t Total Dose To Member of Public [mremJ Total off-site dose to a member of public due to plant operations.

DEX Total External Total Body Dose [mrem]

Total body dose due to external exposure to noble gases, N-16 skyshine and on-site storage facilities.

Liquid Effluent Dose [mrem]

Dose due to liquid effluents to age group a and organ j. The age group and organ with the highest dose from liquid effluents is used.

0NNG .

Non-Noble Gaseous Effluent Dose [mrem]

Dose due to non-noble gaseous effluents to age group a and organ j. The age group and organ with the highest dose from non-noble gas effluents is used.

5.5. COMPLIANCE TO TOTAL DOSE LIMITS 5.5.1. Total Effective Dose Equivalent Limit IOCFR2O Compliance I . Each stations RE limits the Total Effective Dose Equivalent (TEDE) to an annual limit of 100 mrem, as required by IOCFR2O.1301 (a)(1). Demonstration of compliance with the limits of4OCFRI9O (per Section 4.2.2) will be considered to demonstrate compliance with the I 00 mrem/year limit.

5.5.2. Dose to a Member of the Public in the Unrestricted Area I . The NRC has stated that demonstration of compliance with the limits of 4OCFRI 90 or with the design objectives of Appendix I to I OCFR5O will be deemed to demonstrate compliance with the limits of IOCFR2O.1301(a)(1).

Power reactors that comply with Appendix I may also have to demonstrate that they are within the 25 mrem limit of4OCFRI9O (See Reference 104).

CY-BY-1 70-301 Revision 14 Page 167 of 188 5.5.3 Dose to a Member of the Public in the Restricted Area I . In August of I 995, a revision to I OCFR2O was implemented that changed the definition of a member of the public. As a result, for each nuclear station, estimated doses were calculated for a member of the public who enters the site boundary, but is not authorized for unescorted access to the protected area of the site and does not enter any radiologically posted areas on the site. Realistic assumptions were made for occupancy times and locations visited while within the site boundary.

2. These evaluations indicate that the doses estimated for these members of the public are well within the 1 OCFR2O limits. These dose evaluations will be performed annually and if necessary, a model will be developed and included in the ODCM.

3. Evaluation ofthe 4OCFRI9O dose is used to demonstrate compliance to IOCFR2O and satisfy station TRM and Technical Specifications (see ODCM Part 1) 5.5.4. Total Dose due to the Uranium Fuel Cycle (4OCFRI9O)

I . RE and 4OCFRI 90 limit the annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources to the following:

A. Less than or equal to 25 mrem to the total body.

B. Less than or equal to 25 mrem to any organ except the thyroid.

C. Less than or equal to 75 mrem to the thyroid.

2. Total Dose Components A. This requirement includes the total dose from operations at the nuclear power station. This includes doses due to radioactive effluents (airborne and liquid) and dose due to direct radiation from non-effluent sources (e.g., sources contained in systems on site). It also includes dose due to plants under consideration, neighboring plants and dose due to other facilities in the uranium fuel cycle.

CY-BY-1 70-301 Revision 14 Page 168 of 188

3. The operations comprising the uranium fuel cycle are specified in 4OCFRI9O.02(b). The following are included to the extent that they directly support the production of electrical power for public use utilizing nuclear energy:

A. Milling of uranium ore.

B. Chemical conversion of uranium.

C. Isotopic enrichment of uranium.

D. Fabrication of uranium fuel.

E. Generation of electricity by a light-watered-cooled nuclear power plant using uranium fuel.

F. Reprocessing of spent uranium fuel.

4. Excluded are:

A. Mining operations.

B. Operations at waste disposal sites.

C. Transportation of any radioactive material in support of these operations.

D. The re-use of recovered non-uranium special nuclear and by-product materials from the cycle.

5.6. When Compliance Assessment is Required I . Compliance with the 4OCFRI 90 regulations is now required as part of demonstration ofcompliance to IOCFR2O regulations per IOCFR2O.1301(d).

2. The dose due to the uranium fuel cycle is determined by equation 5-2

CY-BY-1 70-301 Revision 14 Page 169 of 188

6. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I . The radiological environmental monitoring program for the environs around Byron Station is given in Table 6-1.

2. Figures 6-1 through 6-4 show sampling and monitoring locations.

CY-BY-1 70-301 Revision 14 Page 1 70 of I 88 Table 6-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type or Frequency and/or Sample Samplinci or Monitoring Locations Collection Frequency of Analysis

1. Airborne Radioiodine and a. Indicators-Near Field Continuous sampler operation Radioiodine Canister:

Particulates with particulate sample I-I 31 analysis weekly BY-21 collection weekly, or more on near field and control frequently if required by dust samples)

BY-22 loading, and radioiodine canister collection weekly. Particulate Sampler:

BY-23 Gross beta analysis BY-24 foIlowin weekly filter change and gamma isotopic analysis3 quarterly on composite filters by location on near field and control samples.

b. Indicators-Far Field BY-Ol, Byron BY-04, Paynes Pt.

BY-06, Oregon

c. Controls BY-08, Leaf River

CY-BY-1 70-301 Revision 14 Page 171 of 188 Table 6-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type or Frequency and/or Sample Sampling or Monitoring Locations Collection Frequency of Analysis

2. Direct Radiation a. Indicators-Inner Ring Quarterly Gamma Dose (Two dosimeters at Quarterly each location)

BY-I 01-1 BY-I 01-2 BY-102-I BY-I 02-2 BY-I 03-I BY-I 03-2 BY-I 03-3 BY-I 04-I BY-I 04-2 BY-I 04-3 BY-I 05-I BY-l 05-2 BY-I 06-I BY-I 06-2 BY-107-I BY-I 07-2 BY-I 07-3 BY-I 08-I BY-I 08-2 BY-I 09-I BY-I 09-2 BY-I 10-I BY-I 10-2 BY-III-3 BY-III-4 BY-I 12-3 BY-I 12-4

CY-BY-J 70-301 Revision 14 Page 1 72 of I 88 Table 6-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type or Frequency and/or Sample Sampling or Monitorinci Locations Collection Frequency of Analysis

2. Direct Radiation Indicators-Inner Ring (contd)

(contd) BY-i i 3-i BY-i i3-2 BY-i i4-i BY-i i4-2 BY-ii5-i BY-i i5-2 BY-i i6-i BY-i i6-2 BY-i i6-3

b. Indicators- Outer Ring Quarterly Gamma Dose Quarterly BY-20i -3 BY-20i -4 BY-202-i BY-202-2 BY-203-i BY-203-2 BY-204-i BY-204-2 BY-205-i BY-205-2 BY-206-i BY-206-2 BY-207-i BY-207-2

CY-BY-1 70-301 Revision 14 Page 1 73 of I 88 Table 6-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Sampling or Monitoring Locations Collection Frequency of Analysis

2. Direct Radiation Indicators-Outer Ring (contd)

(contd) BY-208-1 BY-208-2 BY-209-1 BY-209-4 BY-21 0-3 BY-21 0-4 BY-211-1 BY-21 I -4 BY-212-1 BY-212-4 BY-21 3-1 BY-21 3-4 BY-214-1 BY-214-4 BY-21 5-1 BY-21 5-4 BY-21 6-1 BY-216-2

c. Indicators-Other Quarterly Gamma Dose Quarterly At each airborne location Listed in Section 1:

BY-Ol BY-04 BY-06 BY-21

CY-BY-J 70-301 Revision 14 Page 174 of 188 Table 6-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Samrlinq or Monitoring Locations Collection Frequency of Analysis

2. Direct Radiation Indicators-Other (contd)

(contd)

BY-22 BY-23 BY-24

d. Control Quarterly Gamma dose quarterly At each airborne location Listed in Section 1:

BY-08

e. Special Interest Quarterly Gamma dose quarterly BY-301 -1 BY-301 -2 BY-309-1 BY-309-2 BY-309-3 BY-309-4 BY-3 I 4-2

CY-BY-1 70-301 Revision 14 Page 1 75 of I 88 Table 6-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type or Frequency and/or Sample Sampling or Monitorinc Locations Collection Frequency of Analysis

3. Waterborne Ground/Well a. Indicators Quarterly Gamma isotopic3 and tritium analysis BY-14-1, 3200 German Church Rd quarterly.

BY-18-1, Calhoun Well BY-32, Wolford Well BY-35, Vancko Well BY-38, Storz Well BY-37, Alexander Well Drinking There is no drinking water pathway within 6.2 mi downstream of the station.

Surface a. Indicators BY-12, Oregon Pool of Rock River, Weekly grab samples. Gross beta and gamma Downstream of Discharge isotopic analysis on monthly composite; tritium analysis on quarterly composite.

b. Control BY-29, Byron, Upstream of Intake Sediment a. Indicators BY-12, Oregon Pool of Rock River, Semiannually Gamma isotopic3 Downstream of Discharge analysis semiannually.

b. Control BY-34, Rock River Upstream of discharge

CY-BY-J 70-301 Revision 14 Page 1 76 of I 88 Table 6-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type or Frequency and/or Sample Sampling or Monitoring Locations Collection Frequency of Analysis

4. Ingestion jjj a. Indicators Biweekly: May through Gamma isotopic3 and October; monthly: 1-131 analysis4 on each November through April. sample.

BY-20-1 R. Snodgrass,Dairy Farm

b. Controls BY-26-2, Akins Dairy

a. Indicator BY-3J Rock River in vicinity of Discharge Two times annually Gamma isotopic3 analysis on edible portions.

b. Control BY-29, Byron, Upstream of Intake Food Products a. Indicators Annually Gamma isotopic3 analysis on each Two samples from each of the four sample.

major quadrants within 6.2 miles of the station.

CY-BY-1 70-301 Revision 14 Page 177 of 188 Table 6-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Sampling or Monitoring Locations Collection Frequency of Analysis Food Products b. Control Annually Gamma Isotopic3 (contd) analysis on each sample.

Two samples within 9.3 to 18.6 miles of the station.

Sample locations for food products may vary based on availability and therefore are not required to be identified here but shall be taken.

CY-BY-1 70-301 Revision 14 I Page 178 of 188 Table 6-1 (Contd)

Radiological Environmental Monitoring Program 1Far field samples are not required to be analyzed, unless the respective near field sample results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents from the station, or at the discretion of the Chemistry Manager.

2Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

3Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the station.

31 analysis means the analytical separation and counting procedure are specific for this rad ion uclide.

CY-BY-1 70-301 Revision 14 Page 179 of 188 REFERENGE - . -.

UNITED STATES EOLOGtC SURVEY STILLMAN VALLEY QUADRANGLE, OR OFFSITE EOSE CALCULATION MANUAL TOPOGRAPHIC, 7.5 MINUTES SERIES 1976 BYRON STATION 0 1/2 1KM FIGURE 6-1 0 112 IMILf ONSFIE AIR SAMPLING LOCATIONS I and Unrestricted Area Boundary

. MR SAMPUNG LOCAflON

CY-BY-J 70-301 Revision 14 Page 180 of 188 OFFSfE DOSE CALCULATION MANUAL

. AIR SAMPUNG LOCA1E*1 BYRON STATKN S BYRON STAI1ON FIGURE 5-2 OfFSfll! AIR SAMPLING LOCATIONS Page II 6-12

CY-BY-J 70-301 Revision 14 Pagel8l of 188 Figure 6.3a Inner Ring and Special Interest Dosimeter Locations

CY-BY-1 70-301 Revision 14 Page 182 of 188 Figure 6.3b Outer Ring Dosimeter Locations hQure 3b Outer Rinq. Dosimeter LocaUaiis Inner crce dtnce 37 m Cuter circle Wstance = E.O mi

CY-BY-1 70-301 Revision 14 Page 183 of 188 26-2 OfFSITE DOSE CALCULAUON \1AJA1 BYRON SIATION

. ML flGURE 4

• 2

.+ wA: 3NGES flON AND WATERBORNE EXPOSURE a *YR. :TXfl<\N p,THWAv SAMPLE LOCAUONS n PlANT UQUP

CY-BY-1 70-301 Revision 14 Page 184 of 188 Latitude/Longitude Positions ofREMP Samples Table 6-2 Sampling Location Latitude Longitude Distance Distance Direction Sector Compass (deg) (deg) (km) (mi) (deg) Desig Dir Vent Stack 42.07472 -89.28264 N/A N/A N/A N/A N/A

[

Air Samp ing Stations BY-Ol 42.11762 -89.27993 4.77 2.96 3 A N BY-04 42.01867 -89.22213 7.98 4.96 142 G SE BY-06 42.01577 -89.33010 7.63 4.74 211 K 55W BY-08 42.12668 -89.39918 11.20 6.96 301 P WNW BY-21 42.07908 -89.28213 0.49 0.30 5 A N BY-22 42.07168 -89.27693 0.58 0.36 125 G SE BY-23 42.06585 -89.28230 0.98 0.61 178 J S BY-24 42.06790 -89.29278 1.13 0.70 228 L SW Surface Water BY-12 42.01717 -89.32603 7.33 4.55 209 K 55W BY-29 42.11773 -89.27990 4.78 2.97 3 A N Sed ment fl BY-12 42.01717 -89.32603 7.33 4.55 209 K 55W BY-34 42.09355 -89.32638 4.18 2.60 300 P WNW BY-29 42.11773 -89.27990 4.78 2.97 3 A N BY-31 42.09353 -89.32623 4.16 2.58 300 P WNW BY-20-1 42.05898 -89.37455 7.80 4.85 257 M WSW BY-26-2 42.12221 -29.51107 19.60 12.20 286 P WNW Well Water BY-14-1 42.06102 -89.27753 1.58 0.98 164 H SSE BY-iS-i 42.06578 -89.29051 1.19 0.74 213 K 55W BY-32 42.07527 -89.31863 3.00 1.86 271 N W BY-35 42.08097 -89.31802 3.01 1.87 283 P WNW BY-38 42.08259 -89.32021 3.23 2.00 286 P WNW BY-37 42.08225 -89.31928 3.14 1.95 285 P WNW Vegetation BY-Control Varies by Varies by year Varies by Varies by Varies by year Varies by Varies by year year year year year BY-Quad 1 Varies by Varies by year Varies by Varies by Varies by year Varies by Varies by year year year year year BY-Quad 2 Varies by Varies by year Varies by Varies by Varies by year Varies by Varies by year year year year year BY-Quad 3 Varies by Varies by year Varies by Varies by Varies by year Varies by Vanes by year year year year year BY-Quad 4 Varies by Varies by year Varies by Varies by Varies by year Varies by Varies by year year year year year

CY-BY-J 70-301 Revision 14 Page 185 of 188 LATITUDE/LONGITUDE POSITIONS OF REMP SAMPLES Table 6-2 Dosimeter Locations Sampling Location Latitude Longitude Distance Distance Direction Sector Sector (deg) (deg) (km) (mi) (deg)

From Stack Inner Ring BY-1O1-1 42.07908 -89.28243 0.48 0.30 2 A N BY-1O1-2 42.07912 -89.28188 0.49 0.30 8 A N BY-I 02-1 42.08757 -89.27522 1 .56 0.97 23 B NNE BY-I 02-2 42.08752 -89.27438 1 .58 0.98 26 B NNE BY-103-1 4209068 -8925822 2.69 1.67 49 C NE BY-I 03-2 42.09020 -89.25802 2.67 1 .66 50 C NE BY-I 03-3 4207893 -89.27692 0.67 0.42 45 C NE BY-I 04-I 4208345 -89.25798 2.26 1 .40 65 D ENE BY-I04-2 42.08303 -89.25797 2.24 1.39 66 D ENE BY-104-3 42.07720 -89.27717 0.53 0.33 59 D ENE BY-I05-I 42.07462 -89.25777 2.06 1.28 59 E E BY-I 05-2 42.07598 -89.25760 208 1 .29 90 E E BY-I 06-I 42.06822 -89.25770 2. 1 9 1 36 1 09 F ESE BY-I06-2 42.06770 -89.25758 2.22 1.38 III F ESE BY-I0Z-I 42.05870 -89.26647 2.23 1.39 143 G SE BY-107-2 4205873 -89.26580 2.26 1.40 142 G SE BY-I07-3 42.07027 -8927730 0.66 0.41 138 G SE BY-I08-I 42.06588 -89.27790 1.06 066 158 H SSE BY-I 08-2 42.06578 -89.27920 1 .03 0.64 1 64 H SSE BY-I09-I 4206580 -89.28417 1.00 0.62 187 J 5 BY-I09-2 42.06583 -89.28427 1.00 0.62 188 J BY-lb-I 4206578 -8928738 1.07 0.66 201 K BY-I10-2 42.06577 -89.28793 1.08 0.67 204 K ssw BY-I1I-3 42.06573 -89.29173 125 0.78 217 L

CY-BY-1 70-301 Revision 14 Page 186 of 188 LATITUDEILONGITUDE POSITIONS OF REMP SAMPLES Table 6-2 Dosimeter Locations Sampling Latitude Longitude Distanc Distance Direction Sector Sector Location (deg) (deg) e (km) (mi) (deg)

From Stack Inner Ring BY-111-4 42.06565 -89.29363 1.36 0.85 222 L SW BY-112-3 42.06967 -89.29660 1.28 0.80 244 M WSW BY-112-4 42.07010 -89.29653 1.26 0.78 246 M WSW BY-113-1 42.07385 -89.29670 1.16 0.72 265 N w BY-113-2 42.07432 -89.29662 1.15 0.71 268 N W BY-114-1 42.07955 -89.29665 1.27 0.79 295 P WNW BY-114-2 42.08000 -89.29673 1.30 0.81 297 P BY-115-1 42.08433 -89.29705 1.60 0.99 312 Q NW BY-115-2 42.08473 -89.29702 1.63 1.01 313 Q NW BY-116-1 42.09185 -89.29697 2.24 1.39 328 R BY-116-2 42.09227 -89.29705 2.28 1.42 329 R irrw BY-116-3 42.08702 -89.28810 1.44 0.89 342 R NNW

CY-BY-J 70-301 Revision 14 Page 187 of 188 LATITUDEILONGITUDE POSITIONS OF REMP SAMPLES Table 6-2 Dosimeter Locations Continued Sampling Latitude (deg) Longitude Distance Distance Direction Sector Sector Location (deg) (km) (ml) (deg)

From Stack Outer Ring BY-201-3 42.13811 -89.28378 7.04 4.37 359 A N BY-201-4 42.13810 -89.28316 7.04 4.37 360 A N BY-202-1 42.13623 -89.25798 7.13 4.43 17 B NNE BY-202-2 42.14157 -89.25817 7.70 4.78 15 B BY-203-1 42.12840 -89.22405 7.69 4.78 39 C NE BY-203-2 42.12258 -89.21855 7.51 4.67 45 C NE BY-204-1 42.10407 -89.21380 6.57 4.08 60 D ENE BY-204-2 42.09472 -89.20980 6.43 4.00 70 D ENE BY-205-1 42.08028 -89.20923 6.11 3.80 84 E E BY-205-2 42.07587 -89.20907 6.09 3.78 89 E E BY-206-1 42.05707 -89.20862 6.44 4.00 108 F ESE BY-206-2 42.04622 -89.20870 6.89 4.28 117 F ESE BY-207-1 42.02793 -89.23200 6.68 4.15 141 G SE BY-207-2 42.03008 -89.23523 6.32 3.93 142 G SE BY-208-1 42.02425 -89.24565 6.39 3.97 151 H SSE BY-208-2 42.02340 -89.25740 6.07 3.77 160 H SSE BY-209-1 42.01717 -89.27887 6.40 3.98 177 J BY-209-4 42.01657 -89.27917 6.47 4.02 177 J 5 BY-210-3 42.02180 -89.31012 6.30 3.91 201 K 55W BY-210-4 42.02180 -89.31083 6.32 3.93 202 K BY-211-1 42.02658 -89.35338 7.93 4.93 228 L BY-211-4 42.02645 -89.35278 7.90 4.91 227 L SW

CY-BY-J 70-301 Revision 14 Page 188 of 188 LATITUDEILONGITUDE POSITIONS OF REMP SAMPLES Table 6-2 Dosimeter Locations Continued Sampling Latitude (deg) Longitude Distance Distance Direction Sector Sector Location (deg) (km) (ml) (deg)

From Stack Outer Ring BY-212-1 42.04847 -89.36643 7.52 4.67 247 M wsw BY-212-4 42.04888 -89.36672 7.52 4.67 248 M wsw BY-213-1 42.07263 -89.37440 7.59 4.72 268 N w BY-213-4 42.07183 -89.37440 7.60 4.72 268 N w BY-214-1 42.09397 -89.36945 7.49 4.65 287 P wNw BY-214-4 42.09397 -89.36890 7.45 4.63 287 P wtiw BY-215-1 42.11618 -89.34107 6.68 4.15 314 Q NW BY-215-4 42.11710 -89.34100 6.74 4.19 314 Q NW BY-216-1 42.13058 -89.32910 7.30 4.54 328 R BY-216-2 42.13847 -89.31702 7.63 4.74 338 R Special Interest BY-301-1 42.07830 -89.28338 0.40 0.25 352 A N BY-301-2 42.07685 -89.28230 0.24 0.15 7 A N BY-309-1 42.06995 -89.28268 0.53 0.33 183 J S BY-309-2 42.06887 -89.28200 0.65 0.40 175 J S BY-309-3 42.06865 -89.28358 0.68 0.42 186 J S BY-309-4 42.06850 -89.28472 0.71 0.44 194 K SSW BY-314-2 42.07618 -89.28806 0.48 0.29 290 P iW