ML061290529

Off-Site Dose Calculation Manual

ML061290529
Person / Time
Site:	Callaway
Issue date:	03/08/2006
From:	AmerenUE
To:	Office of Nuclear Reactor Regulation
References
APA-ZZ-01003, Rev 016
Download: ML061290529 (76)

Text

tI ' I APA-ZZ-01003 Rev. 16 NION EiECTRIC CALLAWAY PLANT OFF-SITE DOSE CALCULATION MANUAL DECEMBER 1, 2005 aRKING COPY ISSUED ON 3/8/2006 @ 11

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APA-ZZ-01003 Revision 016 December 1,2005 CALLAWAY PLANT ADMINISTRATIVE PROCEDURE APA-ZZ-01003 OFF-SITE DOSE CALCULATION MANUAL This procedure contains the following:

Pages 1 Through 65 Attachments Through Tables Through Figures Through Appendices Through Checkoff Lists

• Through This procedure has checkoff list(s) maintained in the mainframe computer.

Conversion of commitments to TRS reference/hidden text completed by Revision Number:

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y APA-ZZ-01003 Rev. 016 Table of Contents I PURPOSE AND SCOPE I 2 LIQUID EFFLUENTS 2 2.1 LIQUID EFFLUENT MONITORS 2 2.2 CALCULATION OF LIQUID EFFLUENT MONITOR SETPOINTS 4 2.3 LIQUID EFFLUENT CONCENTRATION MEASUREMENTS 6 2.4 DOSE DUE TO LIQUID EFFLUENTS 6 2.4.1 The Maximum Exposed Individual 6 2.4.2 Calculation Of Dose From Liquid Effluents 7 2.4.3 Summary, Calculation Of Dose Due To Liquid Effluents 8 2.5 LIQUID RADWASTE TREATMENT SYSTEM 8 2.6 DOSE FACTORS 8 3 GASEOUS EFFLUENTS 13 3.1 GASEOUS EFFLUENT MONITORS 13 3.2 GASEOUS EFFLUENT MONITOR SETPOINTS 14 3.2.1 Total Body Dose Rate Setpoint Calculations 15 3.2.2 Skin Dose Rate Setpoint Calculation 16 3.3 CALCULATION OF DOSE AND DOSE RATE FROM GASEOUS EFFLUENTS 16 3.3.1.1 Dose Rate from Noble Gases 16 3.3.1.2 Dose Rate from Radionuclides Other than Noble Gases 17 3.3.2 Dose Due to Gaseous Effluents 18 3.3.2.1 Air Dose Due to Noble Gases 18 3.3.2.2 Dose Due to Radionuclides Other than Noble Gases 19 3.4 GASEOUS RADWASTE TREATMENT SYSTEM 20 3.5 DOSE FACTORS 20 4 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 44 4.1 CALCULATION OF DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 44 4.1.1 Identification of the MEMBER OF THE PUBLIC 44 4.1.2 Total Dose to the Nearest Resident 44

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APA-ZZ-01003 Rev. 016 Table of Contents 4.1.3 Total Dose to the Critical Receptor Within the SITE BOUNDARY 45 5 RADIOLOGICAL ENVIRONMENTAL MONITORING 49

5.1 DESCRIPTION

OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 49 5.2 PERFORMANCE TESTING OF ENVIRONMENTAL THERMOLUMINESCENCE DOSIMETERS 49 6 DETERMINATION OF ANNUAL AVERAGE AND SHORT TERM ATMOSPHERIC DISPERSION PARAMETERS 49 6.1 ATMOSPHERIC DISPERSION PARAMETERS 49 6.1.1 Long-Term Dispersion Estimates 49 6.1.2 Determination of Long-Term Dispersion Estimates for Special Receptor Locations 50 6.1.3 Short Term Dispersion Estimates 50 6.2 ANNUAL METEOROLOGICAL DATA PROCESSING 51 7 REPORTING REQUIREMENTS 58 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 58 7.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 58 8 IMPLEMENTATION OF ODCM METHODOLOGY (COMN 2791) 59 9 RADIOACHIVE EFFLUENT CONTROLS (REC) 60 10 ADMINISTRATIVE CONTROLS 61 10.1 MAJOR CHANGES TO LIQUID AND GASEOUS RADWASTE TREATMENT SYSTEMS 61 10.2 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) (COMN 2815) 61 11 REFERENCES 62

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I7 APA-ZZ-01003 Rev. 016 Table of Contents FIGURES FIGURE 4.1 ................................. 47 TABLES TABLE 2.1 ................................. 9 TABLE 2.2 ................................. 12 TABLE 3;1................................. 21 TABLE 3.2 ................................. 22 TABLE 3.3 - INHALATION PATHWAY ................................. 24 TABLE 3.3 - MEAT PATHWAY ................................. 26.

TABLE 3.3 - GRASS-COW-MILK PATHWAY ................................. 28 TABLE 3.3 -. GRASS-GOAT-MILK PATHWAY ................................. 30 TABLE 3.3 - VEGETATION PATHWAY .......... ....................... 32 TABLE 3.4 - INHALATION PATHWAY ................................. 34 TABLE 3.4 - MEAT PATHWAY ...... ....36 TABLE 3.4 - GRASS-COW-MILK PATHWAY .38 TABLE 3.4 - GRASS-GOAT-MILK PATHWAY .40 TABLE 3.4 - VEGETATION PATHWAY .42 TABLE 6.1 .52 TABLE 6.2 .53 TABLE 6.3 .54 TABLE 6A.. 55 TABLE 6.5 .....  : 56 TABLE 6.6 .57

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7 APA-ZZ-01003 Rev. 016 RECORD OF REVISIONS Rev. No. 0 Date: March 1983 Rev. No. 1 Date: November, 1983 Revised to support the current RETS submittal and to incorporate NRC Staff comments.

Rev. No. 2 Date: March, 1984 Revised to incorporate NRC Staff comments Rev. No. 3 Date: June, 198S Revised to incorporate errata identified by ULNRC00803 and changes to the Environmental Monitoring Program. Incorporate results of 1984 Land Use Census Rev. No. 4 Date: February, 1987 Minor clarifications, incorporated 31-day projected dose methodology. Change in the utilization of areas within the Site Boundary.

Rev. No. S Date: January, 1988 Minor clarifications, revised descriptions of liquid and gaseous rad monitors, revised liquid setpoint methodology to incorporate monitor background, revised dose calculations for 40CFR190 requirements, Revised Table 6 and Figures 5.IA and 5.1B to refine descriptions of environmental TLD stations, incorporated description of environmental TLD testing required by Reg. Guide 4.13, revised Tables 1, 2, 4 and 5 to add additional nuclides, deleted redundant material from Chapter 6.

Rev. No. 6 Date: May, 1989 Revised methodology for calculating maximum permissible liquid effluent discharge rates and liquid effluent discharge rates and liquid effluent monitor setpoints, provided methodology for calculating liquid effluent monitors response correction factors, provided an enhanced description of controls on liquid monitor background limits, provided additional liquid and gaseous dose conversion factors and bioaccumulation factors (Tables 1, 2, 4 & 5), provided description of the use of the setpoint required by Technical Specification 4.9.4.2 during Core Alterations, added discussion of gaseous and liquid monitor setpoint selection in the event that the sample contains no detectable activity, added minimum holdup requirements for Waste Gas Decay tanks, revised dispersion parameters and accompanying description per FSAR Change Notice 88-42.

APA-ZZ-01003 Rev, No. 0 Date: August, 1989 Radiological Effluent Technical Specifications were moved from the Callaway Plant Technical Specifications to Section 9.0, Radioactive Effluent Controls, of the ODCM as per NRC Generic Letter 89-01. At the same time, in order to formalize control of the entire ODCM, it was converted to APA-ZZ-01003, OFF-SITE DOSE CALCULATION MANUAL.

Rev. No. 1 Date: October, 1990 Revise Action 41 of Table 9.2-A to allow continued purging for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as per Amendment 20 to operating license, issued 4/10/87.

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APA-ZZ-01003 Rev. 016 RECORD OF REVISIONS Rev. No. 2 Date: May, 1991 Section 2.4.2 - Changed gross alpha analysis frequency from 'each batch' to a monthly composite as per Table 9.3-A, and the Callaway Plant NPDES permit (reissued March 15,1991).

Re*. No. 3 Date: June, 1993 Deleted HF-RE-45 and LE-RE-59 as effluent monitors. Revised table numbering for consistency with those in Section 9.0. deleted redundant material, incorporated 1992 Land Use Census results, moved LLD description to Attachment 1, moved REC Bases to Attachment 2. Deleted reporting requirements for solid radwaste, which are described in APA-ZZ-01011, PROCESS CONTROL PROGRAM. Addressed compliance with 10 CFR 20.1301. Revised the dilution flow rate to allow values other than 5000 gpm, based on dilution flow monitor setpoint. Revised IMPCS terminology to 'ECV". Added Action 46 to REC 92 to clarify actions for inoperable mid and high range WRGM Channels. Revised references to be consistent with the revised 10 CFR 20. Added Appendix A. Revised Action 41 of Rec 9.2 and the operability requirements of GT-RE-22133. Incorporated the revised Ri values in Tables 3.2 and 3.3.

Added Section 6.2 and Table 6.5.

Rev. No. 4 Date: September, 1994 Increased the minimum channels OPERABLE requirement of REC 9.2 for GT-RE-22 & 33 from I channel to 2 channels. Revised Action 41 and the Bases for REC 9.2 accordingly. Incorporated the operability requirements from Tech Spec 3.9.9 into the Action statement for clarity. (Refer to CARS 199401176).

Rev. No. 5 Date: February, 1995 Removed the REMP station locations. Removed particulate nuclides with a half-life of less than 8 days from Tables 3.2-3.4 and removed C'4 , P32, Nis', TeI25P, and from Tables 2.1, 2.2, 3.2, 3.3. and 3.4.

Changed the reporting frequency of the Effluent Release Report from semiannual to annual. Removed the meat, milk and vegetable pathway dispersion parameters from Tables 6.1, 6.2, and 6.3, and clarified the applicability of the dispersion parameters and dose locations in Table 6.4. Relocated REC 9.1 and 92 to the FSAR. Revised footnotes 3 and 7 of Table 16.11-4 to require additional sampling of the Unit Vent in the event of a reactor power transient, only if the Unit Vent noble gas activity increases by a factor of 3 or greater. Added Section 4.1.3.1.3 for determination of dose due to the on-site storage of low level radioactive waste.

Rev. No. 6 Date September, 1996 Seetion 2: Added dose factors (Ah)for Ag '"m, Np7, Purn, Pu" Pu24, Am"', Cmn2, and Cm'-4 to Table 2.1, and Bioaccumulation Factors (Bfi) for Ag, Pu, Am, and Cm to Table 2.2 due to a change in the liquid radwaste treatment process. Revised the description of the methodology for performing the 31 day dose projection in Section 2.5. Revised the maximum allowable background for HB-RE-1 8.

Section 3: Eliminated Y9"a and Tc99 from Table 3.4 (Meat Pathway) due to a half-life of < 8 days.

Substituted the phrase "more restrictive" in lieu of lesser" in Section 3.2. Revised the definition of F. in equation 3. 1. Added description of use of samples to verify dose rates in Section 3.3.1.2. Augmented the definition of qi in Section 3.3.2.1. Edited equations 3.13 and 3.14 and added equation 3.15 to clarify dose calculations. Revised the methodology for performing the 31 day dose projection in Section 3.4.

Section 4: Strengthened the discussion of the reevaluation of assumptions in Section 4.1.3.

Section 6: Added new table 6.6 to describe the selection and use of dispersion parameters during the preparation of the Effluent Release Report. Updated Tables 6.1 and 6.2 to reference the 1995 Land Use Census. There were no changes in the receptor locations.

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I IS APA-ZZ-01003 Rev. 016 RECORD OF REVISIONS Section 8: Replaced the reference to HDP-ZZ-04500 to a more generic reference to the plant operating procedures, due to change in organizational structure and responsibilities.

Section 9: (1) Eliminated 9.0.1 and 9.0.2 due to redundancy with Technical Specifications 3.0.1 and 3.0.2; (2) Revised Table 9.3-A to incorporate sampling and analysis requirements for TRU nuclides in liquid effluents; (3) Eliminated sampling of Fuel Building Exhaust from Table 16.11-4 and the associated footnotes due to redundancy with Unit Vent sampling; revised the continuous sampling requirements for the gaseous batch release points consistent with plant design; revised the H3 analysis frequency for Purges from weekly to "prior to each purge"; and. (4) Revised the air sampling station location criteria on Table 9. 1-A and footnote # 1, and eliminated footnote #3 in order to be less generic and more descriptive of the parameters used in determining the station locations (See CARS 199502280). Revised the location requirements for milk and vegetables. Revised description of use of baseline samples to trigger gamma isotopic analysis in footnote #4, revised requirement for location of downstream sample station in footnote

1. 6. Revised Surveillance Requirement 9.10.2.1 to eliminate liquid effluents from the surveillance. (5)

Revised REC 9.5 and REC 9.9 to eliminate exceptions for partially tested effluents being released in excess of the respective limit Section 11: Added reference 11.14.13.

Attachment 2: Revised the Bases for REC 9.10 to support the elimination of liquid effluents from Surveillance 9.10.2.1.

The remaining changes are editorial in nature and have no technical impact.

(This revision implements CARS 199502055, CARS 199600167, CARS 199600961, CARS 199502280, and CARS 199600986).

Rev. No. 7 Date February, 1997 Section 9: (1) REC 9.5, "Liquid Radwaste Treatment System", Action statement: Eliminated reference to COMN 1161, (2) Table 9.11-A, items 4a (milk) and 4c (vegetation): revised to required control stations in the least prevalent wind direction. (See CARS 199700166)

Appendix A: revised the discussion relative to the appropriate gross alpha Effluent Concentration Value.

Rev. No. 8 Date May, 1997 Section 1: The Purpose and Scope was revised to describe the split of the ODCM into two sections per FSAR Change Notice 95-058. Section 2: Sections 2.2 and 2.3 were revised to clarify the use of nuclide-specific alpha activity vice gross alpha activity for setpoint determination. Section 2.5 was revised to delete the description of the Liquid Radwaste Treatment System. Section 6: Tables 6.1, 6.2, and 6.3 were revised to reflect the results of the 1996 Annual Land Use Census. Section 7: The reporting requirements for the Annual Radiological Environmental Operating Report and the Effluent Release Report were relocated to the FSAR per FSAR Change Notice 95.058. Section 9: RECs and the supporting Attachments I and 2 were relocated to the FSAR per FSAR Change Notice 95-058. Appendix A:

Appendix A was deleted. Editorial changes were made throughout the ODCM reflecting the relocation of the REC's to the FSAR.

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.7 I APA-ZZ-01003 Rev. 016 RECORD OF REVISIONS Rev. No. 9 Date March, 1998 Section 2.5: Revised projected liquid dose calculation to use previous 31 day cumulative doses.

Section 3.1.1: Added GL-RE-202, Laundry Decon Facility Dryer Exhaust Monitor. Added action to be taken when the particulate and/or iodine grab sampler is not operable. Section 3.2: Added setpoint calculation for GL-RE-202.

Section 3.2.1 and 3.3.2.2: Changes were made to correct typographical errors and have no technical impact.

Section 3.4: Revised projected gas dose calculation to use previous 31 day cumulative doses.

Section 3.5: Removed the word secular from "secular equilibrium" since the equilibrium mode could be secular or transient depending on the isotope. Table 6.2: Added Laundry Decon Facility Dryer Exhaust to title of table since these will be the dispersion factors used for this release point.

Rev. No. 10 Date December 20, 1999 Section 3.1: Added explanation that GL-RE-202 only monitors particulate. Section 3.2: Changed Laundry Decon Facility Exhaust Monitor setpoint to less than or equal to 2000 cpm above equilibrium background with a maximum allowed background of 2000 cpm as calculated in HPCI 99-05.Tables 6.1.

6.2. 6.3: Updated values as calculated in HPCI 99-02. Section 5.1: Defined how REMP sample locations were determined. Removed reference to Plant Operating manual since it no longer exists.

Rev. No. 11 Date December 22,1999 Changes required to go from old Technical Specifications to Improved Technical Specifications.

Technical Specification 4.9A.2 changed toFSAR 16.11.2A.I. Technical Specification 6.8.4.F changed to FSAR 16.11.4. Technical Specification 6.81.F changed to Improved Technical Specification 5.4.1.

Technical Specification 6.14 changed to Improved Technical Specification 5.5.1. Technical Specification 6.8.4E changed to Improved Technical Specification 5.5.4. Technical Specification 6.9.1.6 changed to Improved Technical Specification 5.6.2. Technical Specification 6.9.1.7 changed to Improved Technical Specification 5.6.3. Changed name of Annual Radiological Effluent Release Report to Effluent Release Report as stated in iTS. Added liquid releases are limited to 10 times the Appendix B, Table 2. Column 2 limits per FSAR CN 98-041 supporting implementation of ITS.

Rev. No. 12 Date December 01, 2000 Section 2.1 and 2.2.1: Updated 10CFR20, Appendix B, TableII, Column 2 reference to the new IOCFR20 format. Corrected typo for "f', flow setpoint should be undiluted waste flowrate. Section 3.2.1: Corrected typo, default value for safety factor should be0.1. Section 5.1: Updated crosscheck program used to EML since EPA program is no longer available. Section 6.2: Added vertical height of highest adjacent building used to perform concurrent year annual average atmospheric dispersion (XIQ) calculations and reference for this value. This information should be documented in the ODCM. Added responsibility for validation of meteorological data, since responsibility has changed from engineering to HPTS. Section 10.1.1: Revised to require a summary of Major Radwaste System changes to be included in the annual report. This was done to be consistent with FSAR 16.11.5.2. Several changes were made throughout the procedure to correct typographical errors and have no technical impact.

Rev. No. 13 Date September 19, 2002 Section 3.2: Revised to implement the approved OL 1218, Rev. 1; License Amendment no. 152 allowing equipment hatch and emergency air lock to remain open during refueling activities (FSAR CN-01-030 and CN-02-049). The amendment eliminated FSAR 16.11.2.4. lB and subsequently deleted the core alteration setpoint value 5.0 E-3 pCilcc for Containment Purge Monitors GT-RE-22 and GT-RE-33. The alarm setpoints for the Containment Purge Monitors will be based on the methodology described in Section 3 of the ODCM.

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y I APA-ZZ-01003 Rev. 016 RECORD OF REVISIONS Rev. No. 14 Date June 17,2003 Revised Table 2.1 (Ingestion Dose Commitment Factor for Adult Age Group) to include dose factors for Pr-144. (CARS 200303251). Revised Section 4.1.3.1 to adjust the Farner's residence (critical receptor) from 3830 meters in dhe SE sector to 2897 meters in the NNW sector. The Farmer's residence (critical receptor) was changed in 2002 to a location directly across the street from the Nearest residence. For conservatism and ease in calculation, Table 6.1 and 6.2 were revised making the distances and dispersion parameters for the Farmer's residence (critical receptor) and the Nearest residence the same. Revised section 7.2 to reference Table 6.6. Revised section 10.2.2 to remove the requirement for QA department review of the ODCM for reach revision (CARS 200304509). Added a reference to 11.14.14, Calculation HPCI 03-004 (Rev. 0). "Calculation of Liquid Effluent Dose Commitment factor for Pr-144 (Ait) for the Adult Age Group', June, 2003.

Rev. No. is Date December 9,2004 Reformatted references to FSAR-SP Chapter 16.11 insection 1, 2.1.1,2.1.2, 2.2.1,2.3.2A.2,2.5.

2.6, 3.1, 3.2.1, 35, 5.1,7.1, 7.2, and 9. References to Ni-63 were added to section 2.2.1 for the calculation of ECVSUM, section 2.3, and described in section 2.6 since it is an exception to non gamma FSAR-SP Table16.11-1. Ni-63 was emitters not listed in added to the ODCM based on previous IOCFR 61 sample results and 2Vd quarter liquid composite analyses.

Consolidated references listed in section 2.4.2 and 2.6 for the site related ingestion dose commitment factors (AT) of Table 2.1 into HPCI 04-06, Revision I. References to HPCIs95-004 (Ref: 11.14.13) and 03.004 (Ref: 11.14.14) were deleted and replaced with HPCI 04-06, Revision I which is now listed as Ref. 11.14.13. Added Ni-63 and Sb-122 to Table 2.1- INGESTION DOSE COMMITMENT FACTOR (AT) FOR ADULT AGE GROUP. Revised the reference for Table 2.1 to 11.14.13.

Corrected a typo in section 3.1.2 referring to the Radwaste Building Vent system designator as GT vs.GH (CAR 200406851).

References 11.19 and 11.20 weredeleted in section 4.1.3.1.1. Reference 11.18 was changed to MICROSHIELD (Grove Engineering, Inc.) vs. ISOSHLD. Reference 11.24 in section 4.1.3.1.3 was corrected to 11.18.

Section 5.1 and 5.2 were revised to indicate that the Radiological Environmental Monitoring Program TLDs will be processed and provided by a vendor laboratory beginning inthe first quarter of 2005.

Section 5.2 was revised to delete reference 11.14.10 which refers toHPCI 88-08,'Performnce Testing of the Environment TLD System at Callaway Plant", August 1989.

Reference 11.14.7 was corrected withHPCI87-10 vs. 88-10. Revised Table 6.1, Note (c) to reference FSAR TABLE 2.3-83 vs. TABLE 2.3-82. Revised Table 6.1 and 6.2 Note (b) to reference data is fromthe 2002 Land Use Census.

Changed and/or corrected the Skin dose factor (L;)units in Table 3.1 (Dose Factor for exposure to a 3

Semi-Infinite Cloud of Noble Gases) to mremnyr peruCi/m . Revised section 3.3.1.2: Added units for the term BR in m'/yr.

Removed paragraph in section 3.3.2.2 that describes actions for implementing the use of appropriate RXIJ values. This paragraph was taken directly from section 5.3.1 of NUREG 0133, U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specification for Nuclear Power Plants", USNRC NUREG-0133, Washington, D.C. 20555, October, 1978. This paragraph does not apply since the use of pathways is already considered as described in sections 4.1.2 and 4.1.3.1.

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APA-ZZ-01003 Rev. 016 RECORD OF REVISIONS Revised note (c) of Table 6.1 to reference FSAR-SA Table 2.3-83. Revised note (a) from Table 6.1 to reference FSAR-SA Table 2.3-82. In addition, revised Note (b) from Table 6.1 to reference data taken from the 2002 Land Use Census. Revised Notes (a) and (c) from Table 6.2 to reference FSAR-SA Table 2.3-84 and 2.3-81 respectively.

Added a 0.95 conservatism factor to section 2.2.3 - Calculation of Liquid Effluent Monitor Setpoint.

This will conservatively reduce the liquid monitor setpoint to further ensure the section 4.4.1 of NUREG 0133, US. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specification for Nuclear Power Plantse, USNRC NUREG-0133, Washington, D.C. 20555. October, 1978 which states the alarm and trip setpoints for each instrument channel listed in Table 3.3-11 should be provided and should correspond to a value(s) which represents a safe margin of assurance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded.

A determination was made 1AW T/S 5.5.1 that the associated changes with Revision 15 maintain the levels of radioactive effluent control required by 10 CFR 20.1302,40 CFR 190. 10 CFR 50.36a, and 10 CFR 50 Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Rev. No. 16 Date December 1, 2005 Section 5.1 was revised to remove an invalid requirement that a third-party laboratory performing analysis specifically state the Interlaboratory Comparison (crosscheck) requirements for the Radiological Environmental Monitoring Program (REMP) contract lab. Reference 11.14.14 to Reg. Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment, was added to provide supporting documentation for contract lab Interlaboratory Comparison requirements. Additional information on REMP contract lab participation in Interlaboratory Comparisons was also added in section 5.1. (CAR 200500891) x\( Revised reference 11.14.7 by adding normalization and standardization factors for radionuclides

) blisted in Table 2.1 of the ODCM that were not included in the original calculation.

Added section 4.1.3.1.4 to describe direct dose to a MEMBER OF THE PUBLIC from the Old Steam Generator Storage Facility (OSGSF).

Reworded step 4.1.2 to describe the sources of direct radiation from "outside storage tanks" to "storage of radioactive material".

Revised section 4.1.3.1.2 to include and describe direct dose calculations in support of Modification 03-1008, Equipment Hatch Platform and Missile Shield Modification. Reference 11.14.10 was added to reference direct dose calculation to the MEMBER OF THE PUBLIC from Modification 03-1008.

Revised section 4.1.3.1.3 to include and describe direct dose calculations from the Radwaste Yard RAM storage and Stores I. Reference 11.19 and 11.20 were added to reference direct dose calculations to the MEMBER OF THE PUBLIC from RAM storage at Stores II and the Radwaste Yard.

A determination was made 1AW T/S 5.5.1 that the associated changes with Revision 16 maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40CFR 190, 10 CFR 50.36a, and 10 CFR 50 Appendix 1, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

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APA-ZZ-01003 Rev. 016 OFF-SITE DOSE CALCULATION MANUAL PURPOSE AND SCOPE The OFF-SITE DOSE CALCULATION MANUAL (ODCM) describes the methodology and parameters used in the calculation of off-site 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 also contains the Radioactive Effluent Controls and Radiological Environmental Monitoring Program required by T/S AC 5.5.4 and FSAR-SP CHAPTER 16.11.4, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Effluent Release Reports required by TIS AC 5.6.2 and T/S AC 5.63.

Compliance with the Radiological Effluent Controls limits demonstrates compliance with the limits of 10 CFR 20.1301. (Ref. 11.1.1, 112.1, 11.23.3)

The ODCM consists of two parts: FSAR-SP CHAPTER 16.11 which contains the Radiological Effluent Controls (REC's), and APA-ZZ-01003, which contains the methodology and parameters used to implement the RECs.

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APA-ZZ-01003 Rev. 016 2 LIQUID EFFLUENTS 2.1 LIOUID EFFLUENT MONITORS Gross radioactivity monitors which provide for automatic termination of liquid effluent releases are present on the liquid effluent lines. Flow rate measurement devices are present on the liquid effluent lines and the discharge line (cooling tower blowdown). Setpoints, precautions, and limitations applicable to the operation of the Callaway Plant liquid effluent monitors are provided in the appropriate Plant Procedures. Setpoint values are calculated to assure that alarm and trip actions occur prior to exceeding ten times the Effluent Concentration Values (ECV) limits in 10 CFR Part 20 at the release point to the UNRESTRICTED AREA. The calculated alarm and trip action setpoints for the liquid effluent line monitors and flow measuring devices must satisfy the following equation:

cf *0 F +f Where:

C = The liquid effluent concentration value (ECV) implementing REC 16.11.1.1 for the site in (11Ci/ml).

c = The setpoint, in (pCi/ml). of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely related to the volumetric flow of the effluent line and directly related to the volumetric flow of the dilution stream plus the effluent steam, represents a value, which, if exceeded, would result in concentrations exceeding ten times the values of 10 CER Part 20 Appendix B, Table 2, Column 2, in the UNRESTRICTED AREA.

f = The undiluted waste flow rate as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below.

F = The dilution water flow rate setpoint as measured prior to the release point, in volume per unit time. {If (F) is large compared to (f), then F + f _ Fl.

(Ref. 11.8.1)

If no dilution is provided then c < C.

The radioactive liquid waste stream is diluted by the plant discharge line prior to entry into the Missouri River. Normally, the dilution flow is obtained from the cooling tower blowdown, but should this become unavailable, the plant water treatment facility supplies the necessary dilution flow via a bypass line. The limiting concentration which corresponds to the liquid radwaste effluent monitor setpoint is to be calculated using methodology from the expression above.

Thus, the expression for determining the setpoint of the liquid radwaste effluent line monitor becomes:

c < C(F + f) (kji ml) (2.2) f The alarm/trip setpoint calculations are based on the minimum dilution flow rate (corresponding to the dilution flow rate setpoint), the maximum effluent stream flow rate, and the actual isotopic analysis. Due to the possibility of a simultaneous release from more than one release pathway, a portion of the total site release limit is allocated to each pathway. The determination and usage of the allocation factor is discussed in Section 2.2. In the event the alarm/trip setpoint is reached, an evaluation will be performed using actual dilution and effluent flow values and actual isotopic analysis to ensure that REC 16.11.1.1 limits were not exceeded.

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APA-ZZ-01003 Rev. 016 2.1.1 Continuous Liquid Effluent Monitors The radiation detection monitor associated with continuous liquid effluent releases is (Ref. 11.6.1, 11.6.2):

Monitor I.D. Description BM-RE-52 Steam Generator Blowdown Discharge Monitor The Steam Generator Blowdown discharge is not considered to be radioactive unless radioactivity has been detected by the associated effluent radiation monitor or by laboratory analysis. The sampling frequency, minimum analysis frequency, and type of analysis performed are as per FSAR-SP TABLE 16.11-1.

2.1.2 Radioactive Liquid Batch Release Effluent Monitors The radiation monitor which is associated with the liquid effluent batch release system is (Ref. 11.6.4):

Monitor I.D. Description HB-RE-18 Liquid Radwaste Discharge Monitor This effluent stream is normally considered to be radioactive. The sampling frequency, minimum analysis frequency, and the type of analysis performed are as per FSAR.

SP TABLE 16.11-1.

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APA-ZZ-01003 Rev. 016 2.2 CALCULATION OF LIQUID EFFLUENT MONITOR SETPOINTS The dependence of the setpoint (c), on the radionuclide distribution, yields, calibration, and monitor parameters, requires that several variables be considered in setpoint calculations. (Ref. 11.8.1) 2.2.1 Calculation of the ECV Sum The isotopic concentration of the release(s) being considered must be determined. This is obtained from the analyses required per FSAR-SP TABLE 16.11-1, and is used to calculate an ECV sum (ECVSUM):

ECVSUM 3 (a (Cj(ECV,))

i= g. a, a, t, t (2.3)

Where:

Cg = the concentration of each measured gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample.

24 242 Ca* = the concentration of Np 237

. Pu. Pu2 39. Pu .Am24 , Cm & CmssJ2, in the quarterly composite sample.

Cs* = the measured concentrations of Sr-89 and Sr-90 as determined by analysis of the quarterly composite sample.

Ct = the measured concentration of H-3 in the waste sample.

Cf = the measured concentration of Fe-55 & Ni-63 as determined by analysis of the quarterly composite sample.

ECVg. ECV 5, ECVa, ECVf. ECVt = are ten times the limiting concentrations of the appropriate radionuclides from 10 CFRR 20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2xlO4 jICi/ml total activity.

For the case ECVSUM 5l, the monitor tank effluent concentration meets the limits of REC 16.11.1.1 without dilution and the effluent may be released at any desired flow rate. If ECVSUM > I then dilution is required to ensure compliance with the concentration limits REC 16.11.1.1. If simultaneous releases are occurring or are anticipated, an allocation fraction, N, must be applied so that available dilution flow may be apportioned among simultaneous discharge pathways. The value of N may be any value between ( and 1for a particular discharge point, provided that the sum of the allocation fractions for all discharge points must be *1.

2.2.2 Calculation of the Maximum Permissible Liquid Effluent Discharge Flowrate The maximum permissible liquid effluent discharge flowrate is calculated by:

fmax S (F+ fp) (SIF (N)+ (ECVSUM) (2.4)

Where:

fmax = maximum permissible liquid effluent discharge flowrate, (in gallons/minute);

fp = the expected undiluted liquid effluent flowrate, ingpm.

N = the allocation fraction which apportions dilution flow among simultaneous discharge pathways (see discussion above)

SF = the safety factor, an administrative factor used to compensate for statistical fluctuations and errors of measurements. This factor also provides a margin of safety in the calculation of the maximum liquid effluent discharge flowrate (fmax). The value of SF should be < 1.

F & ECVSUM, are previously defined.

The dilution water supply is furnished with a flow monitor which isolates the liquid effluent discharge if the dilution flow rate falls below its setpoint value.

Values for these concentrations are based on previous composite sample analyses as required by FSAR-SP Table 16.11-1.

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APA-ZZ-01003 Rev. 016 In the event that fmax is less than fp, then the value of fmax is substituted into the equation for fp, and a new value of fmax is calculated. This substitution is performed for three iterations in order to calculate the correct value of fmax-2.2.3 Calculation Of Liquid Effluent Monitor SetIoint The liquid effluent monitors are Nal(Tl) based systems and respond primarily to gamma radiation. Accordingly, their setpoint is based on the total concentration of gamma emitting nuclides in the effluent:

c = (BKG + ( : (Cg) + SF ))XO.95) = IiCi/lm (25)

Where:

c = the monitor setpoint as previously defined, in (pCi/ml);

BKG = the monitor background prior to discharge, in (pCi/ml);

0.95 = Conservatism toensuremonitortrips priorto REC 16.11.1.1

( (Cg) and SF are as previously defined.

The monitor's background is controlled at an appropriate limit to ensure adequate sensitivity.

Utilizing the methodology of ANSI N13.10-1974 (Ref. 11.21), the background must be maintained at a value of less than or equal to 9E-6 pCi/mI (relative to Cs-137) in order to detect a change of 4E-7 jxCi/rnm of Cs-137. (Ref. 11.25).

In the event that there is no detectable gamma activity in the effluent or if the value of (E(Cg) + SF) is less than the background of the monitor, then the monitor setpoint will be set at twice the current background of the monitor.

As previously stated, the monitois response is dependent on the gamma emitting radionuclide distribution of the effluent. Accordingly, a new database conversion factor is calculated for each release based upon the results of the gamma spectrometric analysis of the effluent sample and the measured response of the monitor to National Institute of Standards and Technology (NIST) traceable calibration sources:

DBCFC = (y(Cg)) + (CMR) x (ECF) (2.6)

DBCFc = the monitor data base conversion factor which converts count rate into concentration (ACi/ml);

CMR = the calculated response of the radiation monitor to the liquid effluent; ECF = the conversion factor for Cs4137, which converts count rate into concentration (Cil/nm).

Cg is as previously defined.

The new value of the DBCFc is calculated and entered into the monitor data base prior to each discharge. A more complete discussion of the derivation and calculation of the CMR is given in reference 11.14.7.

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P , 0 APA-ZZ-01003 Rev. 016 2.3 LIQUID EFFLUENT CONCENTRATION MEASUREMENTS Liquid batch releases are discharged as a discrete volume and each release is authorized based upon the sample analysis and the dilution flow rate existing in the discharge line at the time of release. To assure representative sampling, each liquid monitor tank is isolated and thoroughly mixed by recirculation of tank contents prior to sample collection. The methods for mixing, sampling, and analyzing each batch are outlined in applicable plant procedures. The allowable release rate limit is calculated for each batch based upon the pre-release analysis, dilution flow-rate, and other procedural conditions, prior to authorization for release. The liquid effluent discharge is monitored prior to entering the dilution discharge line and will automatically be terminated if the pre-selected alarm/trip setpoint is exceeded. Concentrations are determined prnmaril from the gamma isotopic and H-3 analyses of the liquid batch sample. For Sr". Sr'0.

Fe5', Ni , Np9,Pu3%, Pue"9, Pue',Am r,2 Cm242 " & Cm23u the measured concentrations from the previous quarterly composite analyses are used until laboratory results become available. Composite samples are collected for each batch release and analyzed in accordance with FAR-SP TABLE 16.11-1. The dose from liquids discharged as continuous releases is calculated by utilizing the last measured values of samples in accordance with FSAR-SP TABLE 16.11-1.

2.4 DOSE DUE TO LIQUID EFFLUENTS 2.4.1 TBE MAXIMUM EXPOSED INDIVIDUAL The cumulative dose determination considers the dose contributions from the maximum exposed individual's consumption of fish and potable water, as appropriate. Normally, the adult is considered to be the maximum exposed individual. (Ref. 11.8.3)

The Callaway Plant's liquid effluents are discharged to the Missouri River. As there are no potable water intakes within 50 miles of the discharge point (Ref. 11.7.1, 11.6.6), this pathway does not require routine evaluation. Therefore, the dose contribution from fish consumption is expected to account for more than 95% of the total man-rem dose from discharges to the Missouri River. Dose from recreational activities is expected to contribute the additional 5%,

which is considered to be negligible. (Ref. 11.6.7)

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APA-ZZ-01003 Rev. 016 2.4.2 CALCULATION OF DOSE FROM LIQUID EFFLUENTS The dose contributions for the total time period.

m

^t, l11 are calculated at least once each 31 days and a cumulative summation of the total body and individual organ doses is maintained for each calendar quarter. Dose is calculated for all radionuclides identified in liquid effluents released to UNRESTRICTED AREAS using the following expression (Ref. 11.8.3):

DT=F [AirE At, Cu F, (2.12) i ,.

Where:

Dr = the cumulative dose commitment to the total body or any organ, a, from the liquid effluents for the total period 1-l in mrem.

At, = the length of the I the time period over which C; I and F1 are averaged for all liquid releases, in hours. At, corresponds to the actual duration of the release(s).

C = the average measured concentration of radionuclide, i, in undiluted liquid effluent during time period At, from any liquid release, in (IiCi/mI).

Aid = the site related ingestion dose commitment factor to the total body or any organ i for each identified principal alpha, gamma and beta emitter listed in FSAR-SP TABLE 16.11-1, (in mrem/hr) per (QCi/ml).The calculation of the Aid values given in Table 2.1 are detailed in Ref. 11.14.13.

F, = the near field average dilution factor for Cj, during any liquid effluent release:

F,- fez

'(F+f,,mx)89.77 Where:

fmax = maximum undiluted effluent flow rate during the release F = average dilution flow 89.77 = site specific applicable factor for the mixing effect of the discharge structure.

(Ref. 11.5.1 and 11.14.12)

The term Ci, is the undiluted concentration of radioactive material in liquid waste at the common release point determined in accordance with REC 16.11.1.1, Table 16.1 1-1, 'Radioactive Liquid Waste Sampling and Analysis Program". All dilution factors beyond the sample point(s) are included in the F, term.

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APA-ZZ-01003 Rev. 016 The nearest municipal potable water intake downstream from the liquid effluent discharge point into the Missouri River is located near the city of St. Louis, Missouri, approximately 78 miles downstream. As there are currently no potable water intakes within 50 river miles of the discharge point, the drinking water pathway is not included in dose estimates to the maximally exposed individual, or in dose estimates to the population. Should future potable water intakes be constructed within 10 river miles downstream of the discharge point, then this manual will be revised to include this pathway in dose estimates. (Ref. 11.6.6).

2A.3

SUMMARY

. CALCULATION OF DOSE DUE TO LIOUID EFFLUENTS The dose contribution for the total time period At 1

'-1 is determined by calculation at least once per 31 days and a cumulative summation of the total body and organ doses is maintained for each calendar quarter. The projected dose contribution from liquid effluents for which radionuclide concentrations are determined by periodic composite and grab sample analysis, may be approximated by using the last measured value.

Dose contributions are determined for all radionuclides identified in liquid effluents released to UNRESTRICTED AREAS. Nuclides which are not detected in the analyses are reported as 'less than' the nuclide's Minimum Detectable Activity (MDA) and are not reported as being present at the Lower Level of Detection (LLD) level for that nuclide. The 'less than" values are not used in the dose calculations.

'2.5 LOQID RADWASTE TREATMENT SYSTEM The LIQUID RADWASTE TREATMENT SYSTEM is described in FSAR-SP CHAPTER 11.2.

The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures this system will be available for use when liquids require treatment prior to their release to the environment.

OPERABILITY is demonstrated through compliance with REC 16.11.1.1. and 16.11.1.2.

Projected doses due to liquid releases to UNRESTRICTED AREAS are determined each 31 days. The prior 31 day period is used to calculate compliance. This may be modified as appropriate to account for changes in radwaste treatment which may have a significant effect on the projected doses.

2.6 DOSEFACTORS The dose conversion factors provided in Table 2.1 were derived from the appropriate dose conversion factors of Regulatory Guide 1.109, Table 2.2 and other sources as necessary (Ref: 11.14.13) Non-gamma emitting nuclides, other than those listed in FSAR-SP TABLE 16.11-1 and Ni-63 will not be considered.

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APA-ZZ-01003 Rev. 016 TABLE 2.1 INGESTION DOSE COMMITMENT FACTOR (Aft) FOR ADULT AGE GROUP (mremlhr) per (glCi/mI)

Li= Total bus No Data 2.26E-01 2.261-01 2.26E-O1 2.26E-O1 2.26E-OI 2.26E-Ol H-3 1.31EV2 2.98E-02 145E-02 No Data 3.15E-02 No Data 5. 17E+OO Be-7 Na-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 Cr-51 No Data No Data 1.27E+OO 7.61E-O1 2.81E-OI 1.69E+OO 3.20E+02 Mn-54 No Data 4.38E-i03 8.35E+02 No Data 1.30E+03 No Data 134E+04 Mn-56 No Data 1.IOE+02 1.95E+OI No Data 1.40E+02 No Data 3.51E+03 Fe-55 6.58E+02 4.55E+02 1.06E+02 No Data No Data 2.54E+02 2.61E+02 Fe-59 1.04E+03 2.44E+03 9.36E+02 No Data No Data 6.821Ee02 8.14E+03 Co-57 No Data 2.09E+OI 3.48E+O1 No Data No Data No Data 5.31E1f02 Co-58 No Data 8.92E01 2.00E+02 No Data No Data No Data I.81E+03 Co-60 No Data 2.56E+02 5.65E+02 No Data No Data No Data 4.81E+03 Ni-63 3.1 1E+04 2.16E+03 1.04E+03 No Data No Data No Data 4.50E+02

\() Ni-65 1.26E+02 1.64E+01 7.49E3+OO No Data No Data No Data 4.17E+02 Cu-64 No Data 9.97E+OO 4.68E+oo No Data 2.51E+O1 No Data 8.50E+02 Zn-65 2.32E404 7.37E +04 3.33E+04 No Data 4.93E+04 No Data 4.64E+04 Zn-69 4.93E+01 9.43E+O1 6.56E+OO No Data 6. 31E+Ol No Data 1.42E+OI Br-82 No Data No Data 2.27E+03 No Data No Data No Data 2.60E1303 Br-83 No Data No Data 4.04E+O1 No Data No Data No Data 5.82E+OI Br-84 No Data No Data 5.24E+O1 No Data No Data No Data 4.1IE-04 Br-85 No Data No Data 2.15E+OO No Data No Data No Data I.O1E-15 Rb-86 No Data 1.01E+05 4.71E+04 No Data No Data No Data I.99E+04 Rb-88 No Data 2.90E+02 1.54E+02 No Data No Data No Data 4.OOE-09 Rb-89 No Data 1.92E+02 1.35E+02 No Data No Data No Data 1.12E-1I Sr-89 2.21E+04 No Data 6.35E+02 No Data No Data No Data 3.55E+03 5.44Et+05 No Data i.34E+05 No Data No Data No Data 157B+04 Sr-90 4.07E+02 No Data 1.64E+O1 No Data No Data No Data 1.94E+03 Sr-91 Sr-92 1.54E+02 No Data 6.68E3+OO No Data No Data No Data 3.06E+03 Y-90 5.76E1-1 No Data 1.54E-02 No Data No Data No Data 6.10E+03 Y-91M 5.44E-03 No Data 2.1 IE-04 No Data No Data No Data 1.60E-02 Y-91 8.44E+OO No Data 2.26E-OI No Data No Data No Data 4.64E+03 Y-92 5.06E-02 No Data 1.48E-03 No Data No Data No Data 8.86E+02 Y-93 1.60E-O1 No Data 4.43E-03 No Data No Data No Data 5.09E+03 2.40E4-1 7.70E-02 5.21E-02 No Data J.2JE-O1 No Data 2.44E+02 Zr-95 Zr-97 1.33E-02 2.68E-03 1.22E-03 No Data 4.04E-03 No Data 8.30E+02 Nb-95 4.47E+02 2.48E+02 1.34E+02 No Data 2.46E+02 No Data 1.51E+06 Mo-99 No Data 1.03E+02 1.96E+O1 No Data 2.34E+02 No Data 2.39E+02 Tc-99M 8.87E-03 2.5IE-02 3.19E-01 No Data 3.81E-O1 1.23E-02 1.48E+01 Tc-101 9.12E-03 1.311E-02 1.29E-O1 No Data 2.37E-O1 6.72E-03 3.95E-14 APA-ZZ01 003 (016) wRKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS

APA-ZZ-01003 Rev. 016 TABLE 2.1 (Cont'd)

INGESTION DOSE COMIMITMENT FACrOR (Aj.Z) FOR ADULT AGE GROUP (mremlhr) per (QCihmI)

Total um ILU Ru-103 4A3E+O0 No Data 1.91E+00 No Data 1.69E+OI No Data 5.17E+02 Ru-105 3.69E-O1 No Data 1.46E-01 No Data 4.76E+O0 No Data 2.26E02 Ru-106 6.58E+I1 NoData 833E+00 No Data 1.27E+02 No Data 4.26E+03 Cd-109 No Data 5.55E+02 1.94E+O1 No Data 5.31E+02 No Data 5.60E+03 Ag-l lOIm 8.85E-01 818E-01 4.86E-01 No Data 1.61E+OO No Data 3.34E+C2 Sn-113 5.67E+04 1.61E03 3.26E403 9.19E+02 No Data No Data 1.69E+05 Sb-122 5.48E-01 1.12E-02 1.66E-41 7.73E-03 No Data 2.94E-41 NoData Sb-124 6.70E+00 1.27E-01 2.66E+00 1.63E-02 No Data 5.22E+OO 1.90E+02 Sb-125 4.29E+00 4.79E-02 1.02E+00 4.36E-03 No Data 3.30E+00 4.72E+01 Te-127m 6.48E+03 2.32E+03 7.90E+02 1.66E+03 2.63E+04 No Data 2.17E+04 Te-127 1.05E+02 3.78E+01 2.28E+01 7.80E+O1 4.29E+02 No Data 8.31E+03 Te-129M 1.IOE+04 4.1 IE+03 1.74E+03 3.78E+03 4.60E+04 No Data 5.54E+04 Te-129 3.01E+01 1.13E+01 7.33E+00 2.31E+O1 1.26E+02 No Data 2.27E+O1 Te-131M 1.66E+03 8.10E+02 6.75E+02 1.28E+03 8.21E+03 No Data 8.04E+04 Te-131 1.89E+01 7.88E+00 5.96E+00 155E+01 8.26E+O1 No Data 2.67E+OO Te-132 '2.41E+03 1.56E+03 1.47E+03 1.72E+03 150E+04 No Data 738E+04 1-130 2.71E+01 8.01E+01 3.16E+01 6.79E+03 1.25E+02 No Data 6.89E+O1 1-131 1.49E+02 2.14E+02 122E-02 7.0ME+04 3.66E+02 No Data 5.64B+O1 1-132 7.29E+OO 1.95E+01 6.82E+00 6.82E+02 3.1IE+01 No Data 3.66E+OO 1-133 5.14E+01 8.87E+01 2.70E+01 1.30E+04 155E+02 No Data 7.97E+O1 1-134 3.81E+O0 1.03E+01 3.70E+00 1.79E-02 1.64E+01 No Data 9.O1E-03 1-135., 1.59E+01 4.17E+01 1.54E+01 2.75E+03 6.68E+01 No Data 4.70E+01 2.98E+05 7.09E+05 5.79E+05 No Data 2.29E+05 7.61E+04 1.24E+04 Cs-134 3.12E+04 1.23E-+05 8.86E+04 No Data 6.85E+04 9.38E+03 140E+04 Cs-136 3.82E+05 522E+05 3.42E+05 No Data 1.77E+05 5.89E+04 1.OIE+04 Cs-137 2.64E+02 522E+02 2.59E+02 No Data 3.84E+02 3.79E+01 2.23E-03 Cs-138 1.65E+00 Ba-139 9.29E-01 6.62E-04 2.72E-02 No Data 6.19E-04 3.75E-04 Ba-140 1.94E+02 2.44E-0I 1.27E+O1 No Data 8.30E-02 1.40E-01 4.0OE+02 Ba-141 451E-01 3AIE-04 152E-02 No Data 3.17E-04 13E-04 2.13E-10 2.04E-01 2.10 04 128E-02 No Data 1.77E-04 ti19E-04 2.87E-19 Ba-142 1.50E-01 7.54E-02 1.99E-02 No Data No Data K No Data 5.54E+03 La-140 7.66E-03 3A8E-03 8.68E-04 No Data No Data No Data 2.54E+OI La-142 Ce-141 2.24E-02 1.52E-02 1.72E-03 No Data 7.04E-03 No Data 5.79E+O1 3.95E-03 2.92E+00 3.23E-04 No Data 1.29E-03 No Data 1.09E+02 Ce-143 1.17E+00 4.88E-01 6.27E-02 No Data 2.9QE-O1 No Data 3.95E+02 Ce-144 5.51E-41 2.21E-01 2.73E-02 No Data 1.27E-0I No Data 2.41E+03 Pr-143 1.80E-03 7.48E-04 9.16E-45 No Data 4.22E-04 No Data 2.59E-I0 Pr-144 3.76E-01 4.35E-01 2.60E-02 No Data 2.54E-O1 No Data 2.09E+03 Nd-147 EU-154 3.68E+01 4.52E+00 3.22E+00 No Data 2.17E+Ol No Data 3.28E+03 4.OOE-02 1.94E-01 1.80E-02 No Data 4.18E-02 No Data 2.21E+02 Hf-181 2.96E+02 2.47E+02 8.65E+O1 No Data No Data No Data 8.10E+04 W-187 APA-ZZ-01 003 (016)

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APA-ZZ-01003 Rev. 016 TABLE 2.1 (Cont'd)

INGESTION DOSE COMMITMENT FACTOR (AjT) FOR ADULT AGE GROUP (mrem/hr) per (ACi/mI)

LIa= Total Kmm kmd Np-237 3.28E+04 2.85E+03 1.33E+03 No Data 9.86E+03 No Data 1.90E+03 Np-239 2.85E-^2 2.80E-03 154E-03 No Data 8.74E-03 No Data 5.75E+02 Pu-238 5.70E+03 8.03E+02 1.43E+02 No Data 6.13E+02 No Data 6.12E+02 Pu-239 6.59E+03 8.88E+02 1.60E+02 No Data 6.80E+02 No Data 5.68E+02 Pu-241 1.38E+02 7.07E+00 2.78E+00 No Data 1.28E+01 No Data 1.17E+01 Am-241 4.90E+04 1.72E+04 3.24E+03 No Data 2.44E+04 No Data 4.44E+03 Cm-242 1.23E+03 1.26E+03 8.20E+01 No Data 3.72E+02 No Data 4.74E+03 Cm-243* 3.82E+04 1.44E+04 2.24E+03 No Data 1.05E+04 No Data 4.67E+03

• Includes Pu-240 contribution

• • Includes Cm-244 contribution

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4i APA-ZZ-01003 Rev. 016 TABLE 2.2 BIOACCUMULATION FACTOR (Bf))

(DCi/kg) p (pCi/liter)

Bfi Element F5sh (Freshwater)

H 9.OE-01 Be 2.0E+00 Na 1.OE+02 Cr 2.0E+02 Mn 4.0E+02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu S.OE+O1 Zn 2.0E+03 Br 4.2E+02 Rb 2.0 E +03 Sr 3.0E+01 Y 252E+01 Zr 3.3E+00 Nb 3.0E+04 Mo l.OE+0I Tc 1.5E+01 Ru l.OE+01 Rh 1.0E+01 Ag 2.3E+00 Cd 2.0E+02 Sn 3.0E+03 Sb 1.0 E + 00 Te 4.0E+02 I l.SE+01 Cs 2.OE+03 Ba 4.OE+O0 La 2.5E+O1 Ce l.OE+00 Pr 2.SE+01 Nd 2.5E+01 Eu 2.5E+01 Hf 3.3E+00 W 1.2E+03 Np l.OE+01 Pu 3.5E+00 Am 2.5E+01 Cm 2.5E+01

'"' Values from Regulatory Guide 1.109. Rev. 1.Table A-I and Reference 11.14.13.

APA-ZZ-01 003 (01 6)

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APA-ZZ-01003 Rev. 016 3 GASEOUS EFFLUENTS 3.1 GASEOUS EFFLUENT MONITORS Noble gas activity monitors are present on the containment building ventilation system, plant unit ventilation system, and radwaste building ventilation system.

The alarm/trip (alarm &trip) setpoint for any gaseous effluent radiation monitor is determined based on the instantaneous noble gas total body and skin dose rate limits of REC 16.1 1.2.1, at the SITE BOUNDARY location with the highest annual average XIQ value.

Each gaseous monitor channel is provided with a two level system which provides sequential alarms on increasing radioactivity levels. These setpoints are designated as alert setpoints and alarm/trip setpoints. (Ref. 11.6.3)

The radiation monitor alarmitrip setpoints for each release point are based on the radioactive noble gases in gaseous effluents. It is not considered practicable to apply instantaneous alarmtirip setpoints to integrating radiation monitors sensitive to radioiodines, radioactive materials in particulate form and radionuclides other than noble gases. The exception is GL-RE-202. The only effluent released from the Laundry Decon Facility Dryer Exhaust is in the particulate form.

Conservative assumptions may be necessary in establishing setpoints to account for system variables, such as the measurement system efficiency and detection capabilities during normal, anticipated, and unusual operating conditions, variability in release flow and principal radionuclides, and the time lag between alarmitrip action and the final isolation of the radioactive effluent (Ref. 11.8.5) FSAR-SP TABLE 16.11-6 provides the instrument surveillance requirements, such as calibration, source checking, functional testing, and channel checking.

3.1.1 Continuous Release Gaseous Effluent Monitors The radiation detection monitors associated with continuous gaseous effluent releases are (Ref. 11.6.8, 11.6.9):

Monitor I.D. Description GT-RE-21 Unit Vent GH-RE-10 Radwaste Building Vent GL-RE-202 Laundry Decon Facility Dryer Exhaust Monitor Each of the above continuously monitors gaseous radioactivity concentrations downstream of the last point of potential influent, and therefore measures effluents and not inplant concentrations.

The unit vent monitor continuously monitors the effluent from the unit vent for gaseous radioactivity. The unit vent, via ventilation exhaust systems, continuously purges various tanks and sumps normally containing low-level radioactive aerated liquids that can potentially generate airborne activity. The exhaust systems which supply air to the unit vent are from the fuel building, auxiliary building, the access control area, the containment purge, and the condenser air discharge.

The unit vent monitor provides alarm functions only, and does not terminate releases from the unit vent.

The Radwaste Building ventilation effluent monitor continuously monitors for gaseous radioactivity in the effluent duct downstream of the exhaust filter and fans. The flow path provides ventilation exhaust for all parts of the building structure and components within the building and provides a discharge path for the waste gas decay tank release line. These components represent potential sources for the release of gaseous and air particulate and iodine activities in addition to the drainage sumps, tanks, and equipment purged by the waste processing system.

This monitor will isolate the waste gas decay tank discharge line upon a high gaseous radioactivity alarm.

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APA-ZZ-01003 Rev. 016 The Laundry Decon Facility Dryer Exhaust Monitor continuously monitors the effluent of the dryer exhaust for particulate radioactivity during operation of the dryers. This effluent point is designed to release an insignificant quantity of radioactivity. The items to be placed in the dryers are typically washed before drying removing most of the radioactive material. The dryer effluent then passes through a HEPA filter before being sampled and released.

The Laundry Decon Facility Dryer Exhaust Monitor will secure the dryers and exhaust fans and isolate the dryer effluent upon a high radioactivity alarm or for a monitor failure.

The continuous Unit Vent and Radwaste Building Vent gaseous effluent monitor setpoints are established using the methodology described in Section 3.2. Since there are two continuous gaseous effluent release points, a fraction of the total dose rate limit (DRL) will be allocated to each release point. Neglecting the batch releases, the plant Unit Vent monitor has been allocated 0.7 DRL and the Radwaste Building Vent monitor has been allocated 0.3 DRL. These allocation factors may be changed as required to support plant operational needs, but shall not be allowed to exceed unity (i.e., 1.0). Therefore, a particular monitor reaching the setpoint would not necessarily mean the dose rate Umit at the SITE BOUNDARY is being exceeded; the alarm only indicates that the specific release point is contributing a greater fraction of the dose rate limit than was allocated to the associated monitor, and will necessitate an evaluation of both systems.

For a loss of all isokinetic sampling and/or all heat tracing for the Unit Vent or Radwaste Building Vent grab samplers, one hour is allowed to restore a sampler to service. If sampling cannot be restored within one hour, all batch releases and ventilation not required for the operation of the plant should be secured. The best available sampling should be maintained during this period and normal sampling returned to service as soon as possible.

3.1.2 Batch Release Gaseous Monitors The radiation monitors associated with batch release gaseous effluents are (Ref. 11.6.9, 11.6.10, 11.6.11):

Monitor I.D. Description GT-RE-22 Containment Purge System GT-RE-33 GH-RE-10 Radwaste Building Vent The Containment Purge System continuously monitors the containment purge exhaust duct during purge operations for gaseous radioactivity. The primary purpose of these monitors is to isolate the containment purge system on high gaseous activity via the ESFAS.

The sample points are located outside the containment between the containment isolation dampers and the containment purge filter adsorber unit.

The Radwaste Building Vent monitor was previously described.

A pre-release isotopic analysis is performed for each batch release to determine the identity and quantity of the principal radionuclides. The alarm/trip setpoint(s) is adjusted accordingly to ensure that the limits of REC 16.11.2.1 are not exceeded.

3.2 GASEOUS EFFLUENT MONITOR SETPOINTS The alarm/trip setpoint for Unit Vent and Radwaste Building Vent gaseous effluent monitors is determined based on the more restrictive of the total body dose rate (equation 3.1) and skin dose rate (equation 3.3), as calculated for the SITE BOUNDARY.

The alarm trip setpoint for the Laundry Decon Facility Exhaust Monitor is set to less then or equal to 2,000 cpm above equilibrium background. The maximum allowed background is 2,000 cpm as discussed in reference 11.27.

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4 i APA-ZZ-01003 Rev. 016 3.2.1 TOTAL BODY DOSE RATE SETPOINT CALCULATIONS To ensure that the limits of REC 16.11.2.1 are met, the alarm/trip setpoint based on the total body dose rate is calculated according to:

Sub < DeR~bFF (3.1)

Where:

Sth = the alarm/trip setpoint based on the total body dose rate (PCi/cc).

Dtb = REC 16.11.2.1 limit of 500 mremlyr, conservatively interpreted as a continuous release over a one year period.

Fs = the safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurement. (For example, Fs = 0.5 corresponds to a 100% variation.) Default value is F. = 0.1.

Fa = the allocation factor which will modify the required dilution factor such that simultaneous gaseous releases may be made without exceeding the limits of REC 16.11.21.

Rtb = factor used to convert dose rate to the effluent concentration as measured by the effluent monitor, in (pCi/cc) per (mremlyr) to the total body, determined according to:

Rtb C + [(T) E Ki A1 (3.2)

Where:

C = monitor reading of a noble gas monitor corresponding to the sample radionuclide concentrations for the release. Concentrations are determined in accordance with FSAR-SP TABLE 16.114. The mixture of radionuclides determined via grab sampling of the effluent stream or source is correlated to a calibration factor to determine monitor response. The monitor response is based on concentrations, not release rate, and is in units of (liCi/cc).

XIQ = the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY in (sec/m 3). Refer to Tables 6.1, 6.2 and 6.4.

Kj1 = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrem/yr) per (pCilm3 ). (Table 3.1)

Q; = rate of release of noble gas radionuclide, i, in (pCi/sec).

Qi is calcfilated as the product of the ventilation path flow rate and the measured activity of the effluent stream as determined by sampling.

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1*

APA-ZZ-01003 Rev. 016 3.2.2 SKIN DOSE RATE SETPOINT CALCULATION To ensure that the limits of REC 16.11.2.1 are met, the alarrr/trip setpoint based on the skin dose rate is calculated according to:

Ss < D.R.FF (3.3)

Where:

Fs and Fa are as previously defined.

Ss = the alarnmtrip setpoint based on the skin dose rate.

Ds = REC 16.11.2.1 limit of 3000 mremlyr, conservatively interpreted as a continuous release over a one year period.

Rs = factor used to convert dose rate to the effluent concentration as measured by the effluent monitor, in (pCilbc) per (mrem/yr) to the skin, determined according to:

Rs =C R-[(H) (Li + 1.1 MI) Q, (3-4)

Where:

L = the skin dose factor due to beta emissions for each identified noble gas radionuclide, in (mrem/yr) per (iCilm3).

1.1 = conversion factor: I mrad air dose = 1.1 mrem skin dose.

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrad/yr) per (pCi/m 3).

C, (X IQ) and Qi are previously defined.

3.3 CALCULATION OF DOSE AND DOSE RATE FROM GASEOUS EFFLUENTS 3.3.1 Dose Rate from Gaseous Effluents The following methodology is applicable to the location (STEl BOUNDARY or beyond) characterized by the values of the parameter (XIQ) which results in the maximum total body or skin dose rate. In the event that the analysis indicates a different location for the total body and skin dose limitations, the location selected for consideration is that which minimizes the allowable release values. (Ref. 11.8.6)

The factors Ki, Lj, and Mi relate the radionuclide airborne concentrations to various dose rates, assuming a semi-infinite cloud model.

3.3.1.1 DOSE RATE FROM NOBLE GASES The release rate limit for noble gases is determined according to the following general relationships (Ref. 11.8.6):

De} 2 [K1 ((JX Q)Q1)]

• soomrem I yr (3.5)

Ds = llLi +1.1 Mj)(III)0,i)j]5 3000 mrem/yr (3.6)

Where:

Qi = The release rate of noble gas radionuclides, i, in gaseous effluents, from all vent releases in (iCi/sec).

1.1 = Units conversion factor; I mrad air dose = 1.1 mrem skin dose.

Li, Mi, Ki, (X Q),Dband Ds are as previously identified.

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APA-ZZ-01003 Rev. 016 3.3.1.2 DOSE RATE FROM RADIONUCLIDES OTHER THAN NOBLE GASES The release rate limit for Iodine-131 and lodine-133. for tritium, and for all radioactive materials in particulate form with half lives greater than 8 days is determined according to (Ref. 11.8.7):

Do =E Rj1 TiX] Qi

• 1500 mrem/yr (3.7)

Where:

Do = Dose rate to any critical organ, in (mrremlyr).

R = Dose parameter for radionuclides other than noble gases for the Inhalation pathway for the child, based on the critical organ, in (mrem/yr) per (pCi/rn 3).

= The release rate of radionuclides other than noble gases, i, in gaseous effluents, from all vent releases in (pCilsec).

(X/ 0) is as previously defined.

The dose parameter (Ri) includes the internal dosimetry of radionuclide, i, and the receptor's breathing rate, which are functions of the receptor's age. The child age group has been selected as the limiting age group. All radiodines are assumed to be released in elemental form (ref. 11.8.7).

Ri values were calculated according to (Ref. 11.8.8):

RI = K (BR) DFAj (3.8)

Where:

K = Units conversion factor: IE06 pCi/tCi BR = The breathing rate. (Regulatory Guide 1.109, Table E-5). (m3lyr)

DFA, = The maximum organ inhalation dose factor for the ith radionuclide, in (mrem/pCi).

The total body is considered as an organ in the selection of DFAi. (Ref. 11.11.5 and 11.14.4)

The results of periodic tritium, iodine and particulate samples of the Unit Vent and Radwaste Vent are used to verify the dose rate limit was not exceeded for the period during which the samples or composite samples were obtained.

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16 APA-ZZ-01003 Rev. 016 3.3.2 DOSE DUE TO GASEOUS EFFLUEJNTS 3.3.2.1 AIR DOSE DUE TO NOBLE GASES The air dose at the SITE BOUNDARY due to noble gases is calculated according to the following methodology (Ref. 11.8.9):

During any calendar quarter, for gamma radiation:

Do =3.17E-08 [M,(XQl )4 5mrad (3.9)

During any calendar quarter, for beta radiation:

Db = 3.17E-08 [N, (x) qij < 10 mrad (3.10)

During any calendar year, for gamma radiation:

Do = 3.17E-08 [M,(X/Q)q1 S10 mrad (3.11)

During any calendar year, for beta radiation:

Db = 3.17E-08 [NE ( 6)aq; I *20mrad (3.12)

Where:

Dg = Air dose in mrad, from gamma radiation due to noble gases released in gaseous effluent.

Db = Air dose in mrad, from beta radiation due to noble gases released in gaseous effluents.

Ni= The air dose factordue to beta emissions for each identified noble gas radionuclide, i, in (mrad/yr) per (+/-CiUm 3).

qi The releases of noble gas radionuclides, i, in gaseous effluents, for all gaseous releases in (tCi). Releases are cumulative over the calendar quarter or year as appropriate. qu is calculated as the product of the ventilation flow rate and the measured activity of the effluent stream as determined by sampling.

3.17E-08 = The inverse of tie number of seconds per year.

X / Q & M; are as previously defined.

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APA-ZZ-01003 Rev. 016 3.3.2.2 DOSE DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES The dose to a MEMBER OF THE PUBLIC from lodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY, is calculated according to the following expressions:

During any calendar quarter:

Dd <75 mr7m (3.13)

During any calendar year:

1j Di4j-15 mren (3.14)

For each pathway, j, (i.e., for inhalation, ground plane, meat, cow- milk, goat- milk, and vegetation) Dug is calculated according to the expression:

1,, 3.17E-8 1i Ruj [Wj q,] (3.15)

Where:

Dig} = Dose in mrem, to a MEMBER OF THE PUBLIC from radionuclides other than noble gases, from pathway j, received by organ I (including total body).

Rii = The dose factor for each identified radionuclide, i, in m2 (mrem/yr) per (gCi/sec) or (mremlyr) per (pCi/m 3) as appropriate, for the pathway j, and exposed organ 1, appropriate to the age group of the critical MEMBER OF THE PUBLIC receptor.

Wj = (X/Q) for the inhalation and tritium pathways, in (sec/m3). Refer to Tables 6.1, 6.2, and 6.4 for applicability.

W; = (aDI(2 for the food and ground plane pathways, in (metersf). Refer to Tables 6.1, 6.2 and 6.4 for applicability.

(D /Q) = the average relative deposition of the effluent at or beyond the SITE BOUNDARY, considering depletion of the plume during transport.

qi = The releases of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases, i, in gaseous effluents, for all gaseous releases in (hCi). Releases are cumulative over the calendar quarter or year as appropriate.

q, is calculated as the product of ventilation flow rate and the measured activity of the effluent stream as determined by sampling.

3.17 E-08 = The inverse of the number of seconds per year.

X/ Q is as previously defined.

Although the annual average relative concentration(X/Q) and the average relative deposition rate (-D Q)are generally considered to be at the approximate receptor location in lieu of the SITE BOUNDARY for these calculations, it is acceptable to consider the ingestion, inhalation, and ground plane pathways to coexist at the location of the nearest residence with the highest value of (XIQ). (Ref. 11.8.9) The Total Body dose from ground plane deposition is added to the dose for each individual organ. (Ref. 11.11.3)

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APA-ZZ-01003 Rev. 016 3.4 GASEOUS RADWAMTE TREATMENT SYSTEM The gaseous radwaste treatment system and the ventilation exhaust system are available for use whenever gaseous effluents require treatment prior to being released to the environment. The gaseous radwaste treatment system is designed to allow for the retention of all gaseous fission products to be discharged from the reactor coolant system. The retention system consists of eight (8) waste gas decay tanks. Normally, waste gases will be retained for at least 60 days prior to discharge. These systems will provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept ALARA.

The OPERABILITY of the gaseous radwaste treatment system ensures this system will be available for use when gases require treatment prior to their release to the environment.

OPERABILITY is demonstrated through compliance with REC 16.11.2.1, 16.11.2.2, and 16.11.2.3.

Projected doses (gamma air, beta air, and organ dose) due to gaseous effluents at or beyond the SITE BOUNDARY are determined each 31 days. The prior 31 day period is used to calculate compliance. This may be modified as appropriate to account fbr changes in radwaste treatment which may have a significant effect on the projected doses.

3.5 DOSE FACTORS The dose conversion factors provided in the following tables were derived from the appropriate dose conversion factors in Regulatory Guide 1.109 and other sources as necessary (Ref: 11.14.9 and 11.14.11). Per USNRC guidance, particulate nuclides with a half-life of less than 8 days are not considered (Ref: 11.24). Y-90, La-140, and Pr-144 are included because the parent half-life is greater than 8 days, and equilibrium is assumed. Non-gamma emitting nuclides not listed in FSAR-SP TABLE 16.11-4 are also not considered. (COMN 43121)

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co 0

0 V-.

APA-ZZ-01003 Rev. 016 a-

<C DOSE FACTOR FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GAS1S Total Body Gamrna Air Dose Factor Beta Air Skin Dose Factor Dose Factor Dose Factor K i Li

• Mr-Radionuclide (mremlyr) per (CIOM13) Ni (mren/yr) per (,uCi/m 3) (mrad/yr) per (,Ci/m 3 ) (mrad/yr per (pCi/m 3 )

, ~ -,-M X"M Kr-83m 7.56 E-02 1.93 E+01 2.88 E+02 Kr-85m 1.17E+03 1.46E+03 1.23 E+03 1.97 E+03 Kr-85 1.61 E+01 1.34 E+03 1.72 E+01 1.95 E+03 Kr-87 5.92 E+03 9.73 E+03 Kr-88 6.17 E+03 1.03 E+04 1A7 E+04 2.37 E+03 1.52 E+04 Kr-89 1.66 E+04 2.93 E+03 1.01 E+04 1.73 E+04 1.06 E+04 Kr-90 1.56 E+04 7.29 E+03 Xe-131m 1.63 E+04 7.83 E+03 9.15 E+01 4.76 E+02 1.56 E+02 Xe-133m 2.51 E+02 1. II E+03 9.94 E+02 3.27 E+02 1.48 E+03 Xe-133 2.94 E+02 3.06 E+02 Xe-135m 3.53 E+02 1.05 E+03 3.12 E+03 7.11 E+02 3.36 E+03 Xe--135 1.81 E+03 7.39 E+02 CD) 1.86 E+03 1.92 E+03 2.46 E+03 cc Xe-137 1.42 E+03 1.22 E+04 1.51 E+03 x Xe-138 8.83 E+03 1.27 E+04 4.13 E+03 9.21 E+03 4.75 E+03 Ar-41 8.84 E+03 2.69 E+03 9.30 E+03 3.28 E+03 z

0 0

w CD)

CD, 21 C.)

z

APA-ZZ-01003 Rev. 016 TABLE 3.2 PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Ground Plane Pathway (m2mrenimlyr) per (ILCi/sec)

NUCLIDE TOTAL BODY SKIN Be-7 2.24E+07 3.21E+07 Cr-51 4.66E+06 5.51E+06 Mn-54 1.39E+09 1.63E+09 Fe-59 2.73E+08 321E+08 Co-57 2.98E+08 4.37E+08 Co-58 3.79E+08 4.44E+08 Co-60 2.15E+10 2.53E+10 Zn-65 7.47E+08 8.59E+08 Rb-86 8.99E+06 1.03E+07 Sr-89 2.16E+04 2.51E+04 Y-90 5.36E+06 6.32E+06 Y-91 1.07E+06 1.21E+06 Zr-95 2A5E+08 2.84E+08 Nb-95 2.50E+08 2.94E+08 Ru-103 1.08E+08 1.26E+08 Ru-106 4.22E+08 5.07E+08 Ag-l lOm 3.44E+09 4-01E+09 Cd-109 3.76E+07 1.54E+08 Sn-113 IA3E+07 4.09E+07 Sb-124 8.74E+08 1.23E+09 Sb-125 3.57E+09 5.19E+09 Te-127m 9.17E+04 1.08E+05 Te-129m 1.98E+07 2.31E+07 22 IRKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.2 PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Ground Plane Pathway (m2mremlyr) per (ipCi/sec)

NUCLIDE TOTAL BODY SKIN 1-130 5.51E+06 6.69E.06 1-131 1.72E+O07 2.09E4W7 1-132 1.25E+06 1.47Eh06 1-133 2.45E+06 2.98E+06 1-134 4.47E+05 5.31E+05 1-135 2.53E+06 2.95E+06 Cs-134 6.85E+09 8.00E+09 Cs-136 lSlE+08 1.71E+08 Cs-137 1.03E+10 l20E+10 Ba-140 2.05E+07 2.35E+07 La-140 1.47E+08 i.66E+08 Ce-141 1.37E+07 1.54E+07 Cb-144 6.96E+07 8.04E+07 Pr-144 4.35E+07 5.00E+07 Nd-147 8.39E+06 1.O1E+07 Eu-154 2.21E+10 3.15£+10 Hf-181 1.97E+08 2.82E+08 23 RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01 003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Inhalation Pathway (mrem/yr) per (LCVm 3)

Total Diz1d Kid=g Gl-.ll H-3 ND' 1.12E+03 I.12E+03 1.12E+03 1.12E1+03 1.12E+03 1.12E+03 Be-7 8A7E+02 1.44E1+03 9.25E+02 ND ND 6.47E+04 2.55E+03 Cr-SJ ND ND 1-54E+02 8.55E+01 2.43E+01 I.70E+04 1.081E+03 Mn-54 ND 4.29E+04 9.511E+03 ND 1.OOE+04 I.58E+06 2.29E+04 Fce55 4.74E+04 2.52E+04 7.77E+03 ND ND I.lIE+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 I.67E+04 ND ND 1.27E+06 7.07E+04 Co-57 ND 9.03E+02 1.07Ef+03 ND ND 5.07E+05 1.32E+04 Co-58 ND 1.77E+03 3.16EP+03 ND ND 1.IIE+06 3.44E+04 Co-60 ND 1.311E+04 2.26E+04 ND ND 7.07E+06 9.62E+04 Zn-65 4.25E+04 1.13E+05 7.03E+04 ND 7.14E+04 9.95E+05 i.63E+04 R-b-86 ND 1.98E+05 1.14E+05 ND ND ND 7.99E+03 Sr-89 5.99E+05 ND 1.72E+04 ND ND 2.16E+06 1.67E+05 Sr-90 I .OlE+08 ND 6.44E+06 ND ND IA8E+07 3.43E+05 Y-90 4.1 IE+03 ND 1.1 IE+02 ND ND 2.62E+05 2.68E+05 Y-91 9.14E+05 ND 2.44E+04 ND ND 2.63E+06 I.84E+05 Zr-95 I.9O0E5 4.18E+04 3.70E+04 ND 5.96E+04 2.231E+06 6.IIE+04 Nb-95 2.35E+04 9.188E+03 6.55E+03 ND 8.62E+03 6.14E+05 3.70E+04 Ru-103 2.79E+03 ND 1.07E+03 ND 7.03E+03 6.62E+05 4.48E+04 Ru-106 1.36E+05 ND 1.69E+04 ND 1.84E+05 1IA3E+07 4.29E+05 Ag-l1Om 1.69E+04 1.14E+04 9.14E+03 ND 2.12E+04 5.48E+06 I.OOE+05 Cd-109 ND 5.48E+05 2.59EQ-04 ND 4.96E+05 I.05E+06 2.78E+04 Sn-l 13 1.13E+05 3.12E+i3 8.62E+03 2.33E+03 ND 1.46E+06 2.26E+05 Sb-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 ND 3.24E+06 1.64E+05 Sb-125 9.84E+04 7.59E+02 2.07E+04 9. IOE+ol ND 2.32E+Q6 4.03E+04 Te-127m 2.49E+04 8.55E+03 3.Q2E+03 6.07E+03 6.36E+04 I.48E+06 7.14E+04 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 I.76E+06 I.82E+05 24 RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ- -01003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Inhalation Pathway (mrem/yr) per (iCVm3)

BKuM Lur Total num4 yi Lgg L 1-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 ND 5.1 IE+03 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 ND 2.84E+03 1-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 ND 3.20E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 ND 5.48E+03 1-134 1.17E+03 2.16E+03 9.95E1+02 5.07E+04 3.30E+03 ND 9.55E+02 1-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 ND 4.44E+03 Cs- 134 6.51E+05 1.OIE+06 2.25E+05 ND 3.30E+05 1.21E+05 3.85E+03 Cs- 136 6.51E+04 1.711E+05 1.16E+05 ND 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 825EI+05 1.28E+05 ND 2.82E+05 1.04E+05 3.62E1+03 Ba-140 7.40E+04 6A8E+01 4.33E+03 ND 2.1 IE+OI 1.74E+06 1.02E+05 La-140 6.44E+02 2.25E+02 7.55E+01 ND ND 1.83E+05 2.26E+05 Ce-141 3.92E+04 1.95E+04 2.90E+03 ND 8.55E+03 5.44E+05 5.66E1+04 Ce-144 6.77E+06 2.12E+06 3.61E+05 ND 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5-555E+03 9.14E+02 ND 3.OOE+03 4.33E+05 9.73E+04 Pr-144 5.96E-02 1.85E-02 3.OOE-03 ND 9.77E-03 157E+03 1.97E+02 Nd-147 1.08E1+04 8.73E1+03 6.81Ei+02 ND 4.81E+03 3.28E+05 8.21E+04 Eu-154 I.OIE+07 9.211E+05 8.40E+05 ND 4.03E+06 6.14E+06 I.lOE+05 Hf-181 2.78E+04 I .O1E+05 1.25E+04 ND 2.05E+04 1.06E+06 6.62E+04 25 RKING COPY ISSUED ON 3/8/2006 @11:52 AM HRS APA-ZZ-01003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Meat Pathway 2

(m mrem/yr) per (pCilsec)

Nuoelide hi Total Thm Kidn e (1L1 H-3 ND 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 Be-7 7.38E+03 1.26E+04 8.07E+03 O.OQE+O0 1.23E+e04 0.00E+00 I7.00E+05 Cr-51 0.00E+00 O.OOE+00 8.80E+03 4.88E+03 1.33E+03 8.92E+03 4.67E+05 Mn-54 0.0DE+00 8.02E+06 2.14E+06 O.OOE+00 2.25E+06 O.OOE+00 6.73E+06 Fe-55 4.58E+08 2.43E+08 7.52E+07 O.OOE+O0 O.OOE+00 I.37E+18 4.50E+07 Fe-59 3.77E+08 6.10E+08 3.04E+08 O.OOE+00 O.00E+OO 1.77E+08 6.35E+08 Co-57 0.00E+00 5.92E+06 1.20E+07 O.OOE+00 O.OOE+00 O.OOE+O0 4.85E+07 Co-58 0.00E+00 1.64E+07 5.03E+07 O.OOE+00 O.00E+00 O.OOE+00 9.59E+07 Co-60 0.00E+00 6.94E+07 2.05E+08 O.OOE+00 O.00E+00 O.OOE+00 3.84E+08 Zn-65 3.76E+08 1.00E+09 6.23E+08 O.OOE+00 631E+08 O.OOE+00 1.76E+08 Rb-86 O.OOE+00 5.77E+08 3.55E+08 O.OOE+00 O.OOE+O0 O.OOE+00 3.71E+07 Sr-89 4.82E+08 0.00E+00 1.38E+07 O.00E+00 O.00E+00 O.OOE+00 1.87E+07 Sr-90 1.04E+10 O.OOE+O0 2.64E+09 Q.OOE+00 O.OOE+00 0.OOE+00 1.40E+08 Y-90 1.93E+05 O.OOE+00 5.16E+03 O.OOE+00 O.00E+00 O.OOE+00 5.49E+08 Y-91 1.80E+06 O.OOE+00 4.82E+04 0.OOE+00 O.OOE+00 O.OOE+00 2.40E+08 Zr-95 2.67E+06 5.86E+05 5.22E+05 0.OOE+03 8.39E+05 0.OOE+00 6.111E+08 Nb-95 4.26E+06 1.66E+06 1.18E+06 O.ODE+O0 1.56E+06 0.00E+00 3.07E+09 Ru-103 I.55E+08 Q.OOE+00 5.96E+07 O.OOE+00 3.90E+08 0.OOE+00 4.01E+09 Ru-106 4.44Ed 09 O.OOE+OO 5.54E+08 O.00E-00 6.00E+09 O.OOE+O0 6.91E+1O Ag-lI1m 8.40E+06 5.67E+06 4.53E+06 Q.OOE+00 1.06E+07 O.OOE+00 6.75E+08 Cd109 0.001E+00 1.91E+06 8.84E+04 O.OOE+00 1.70E+06 O.OOE+00 6.18E+06 Sn-113 2.18E+09 4.48E+07 1.24E+08 3.31E+09 O.OOE+00 O.OOE+00 1.54E+09 Sb-124 2.93E+07 3.80E+05 1.03E+07 6.46EE+04 0.00E+OO 1.62E+07 1.83E+08 Sb-125 2.85E+07 2.20E+05 5.97E+06 2.64E+04 O.O0E+00 1.59E+07 6.81E+07 Te-127m 1.78E+09 4.78E+08 2.1 IE+08 4.25E+08 5.07E+09 O.OOE+00 1.44E+09 Te-129m 1.79E+09 5.00E+08 2.78E+08 5.78E+08 5.26E+09 O.OOE+00 2.19E+09 1-130 3.06E-06 6.18E-06 3.18E-06 6.80E-04 9.23E-06 O.OOE+00 2.89E-06 26 RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Meat Pathway (m2 mremlyr) per (gCi/sec) od& DM Llbm Total K= Ly 1-131 1.66E+07 1.67E+07 9.47E+06 5.51E+09 2.74E+O7 0.OOE+00 1.48E+06 1-132 0.OOE+OO O.OOE+00 O.OOE+O0 O.OOE+OO QOOEE+OD O.OOE+00 O.OOE+O0 I-133 5.70E-01 7.05E-01 2.67E-01 1.31E+02 1.17E+O0 0.OOE+00 2.84E-01 1-134 .OOE+OO O.OOE+00 O. O.OOE+O0 0QOOE+OO O.OOE+O0 O.OOE+O0 O.OOE+OO I-135 O.OOE+OO O.OOE+0O O.OOE+0O O.OOE+0 O.OOE+0 O O.OOE+O0 Cs-134 9.23E+08 1.51E+09 3.20E+08 O.OOE+O0 4.69E+08 1.68E+08 8.17E+06 Cs-136 1.62E+07 4.46E+07 2.89E+07 O.OOE+O0 2.38E+07 3.54E+06 1.57E+06 Cs-137 1.33E*09 1.28E+09 1.89E+08 O.OOE+O0 4.16E+08 1.50E+08 8.0QE+06 Ba-140 4.39E+07 3.85E+04 2.56E+06 0.OOE+OO 1.25E+04 2.29E+04 2.22E+07 La-140 3.33E+02 I.17E+02 3.93E+01 0.OOE+00 O.OOE+OO 0.OOE+O0 3.25E+06 Ce-141 2.22E+04 IIllE+04 1.65E+03 0.OOE+00 4.86E+03 O.OOE+O0 1.38E+07 Ce-144 2.32E+06 7.27E+05 1.24E+05 O.OOE+O0 4.02E+05 .OOE+CO 1.89E+08 Pr-143 3.34E+04 1.OOE+04 1.66E+03 0.00E+00 5.43E+03 O.OOE+00 3.61E+07 Pr-144 5.63E+02 1.74E+02 2.83E+01 O.OOE+00 9.21E+01 O.OOE+00 3.75E+05 Nd-147 1.17E+04 9.48E+03 7.34E+02 0.OOE+00 5.20E+03 O.OOE+O0 1.50E+07 Eu-154 1.12E+07 I.O1E+06 9.20E+05 Q.OOE+O0 4.43E+06 0.OOE+00 2.34E+08 Hf-181 4.77E+06 1.74E+07 2.15E+06 0.OOE+00 3.53E+06 0.OOE+00 6.41E+09 27 IRKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01003 (01 6)

APA-ZZ-01003 Rev. 016 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Cow-Milk Pathway (m2Mremlyr) per (pLC!sec)

NWuli Bde Total 111mmn d=

kkd H-3 Q.OOE+O0 1.57E+03 1.57E+03 157E+03 1.57E+03 1.57E+03 1.57E+03 Be-7 7.50E+03 1.28E+04 8 20E+03 O.OOE+00 1.25E+04 O.OOE+OO 7.12E+05 Cr-51 O.OOE+OO O.OOE+OO 1.02E+O5 5.66E+04 155E+04 1.03E+05 5.40E+06 Mn-54 O.OOE+OO 2.10E+07 5.59E+06 0.OOE+0O 5.89E+06 O.OOE+00 1.76E+07 Fe-55 1.12E+08 5.94E+07 1.84E+07 O.OOE+00O O.OOE+00 3.36E+07 I.IOE+07 Fe-59 1.20E+08 1.95E+08 9.70E+07 0.OOE+OO O.OOE+OO 5.64E+07 2.03E+08 Co-57 O.OOE+OO 3.84E+06 7.78E+06 O.OOE+OO Q.OOE+O0 0.OOE+00 3.15E+07 Co-58 Q.OOE+OO 1.21E+07 3.72E+07 Q.OOE+OO O.OOE+OO 0.OOE+00 7.08E+07

.Co60 O.OOE+OO 4-32E+07 1.27E+08 O.OOE+O0 0.OOE+00 O.OOE+OO 2.39E+08 Zn-65 4.14E+09 1.lOE+10 6.86E+09 O.OOE+00 6.95E+09 0.OOE+O0 1.94E+09 Rb-86 O.OOE+00 8.78E+09 5.40E+09 O.OOE+OO O.OOE+O0 0.OOE+O0 5.65E+08 Sr-89 6.63E+09 0QOOE+00 1.89E+08 O.OOE+00 O.OOE+00 0.OOE.00 2.57E+08 Sr-90 1.12E+1 1 O.OOE+O0 2.84E+10 0.OOE+00 O.OOE+00 O.OOE+OO 1.51E+09 Y-90 338E+03 O.OOE+O0 9.05E+01 O.OOE+O0 0.OOE+O0 Q.OOE+OO 9.62E+06 Y-91 3.91E+04 O.OOE+OO 1.04E+03 O.OOE+OO O.OOE+O0 O.OOE+00 5.20E+06 Zr-95 3.84E+03 8.43E+02 7.51E+02 O.OOE+OO 1.2lE+03 O.OOE+OO 8.80E+05 Nb-95 3.72E+05 1.45E+05 1.03E+05 O.OOE+00 1.36E+05 O.OOE+O0 2.68E+08 Ru-103 4.29E+03 O.OOE+OO 1.65E1+03 0.OOE+OO 1.08E+04 0.OOE+O0 1.1IE+05 Ru-106 9.25E+04 O.OOE+OO I.15E+04 O.OOE+O0 1.25E+05 0.OOE+O0 1.44E+06 Ag-llOmn 2.09E+08 1.41E+08 1.13E+08 0.OOE+O0 2.63E+08 O.OOE+OO 1.68E+10 Cd-109 0.OOE+OO 3.86E+06 1.79E+05 O.OOE+O0 3.45E+i406 O.OOE+iOO 1.25E+07 Sn-113 6.1 IE+08 1.26E+07 3.48E+07 9.29E+08 O.OOE+O0 O.OOE+OO 4.32E+08 Sb-124 1.09E+08 1.41E+06 3.81E+07 2.40E+05 O.OOE+O0 6.03E+07 6.80E+08 Sb-125 8.71E+07 6.72E1+05 1.83E+07 8.07E+04 O.OOE+OO 4.86E+07 2.08E+08 Te-127m 2.08E+08 5.61E1+07 2.47E+07 4.98E+07 5.94E1+08 O.OOE+00 1.69E+08 Te-129m 2.72E+08 7.59E+07 4.22E+07 8.76E+07 7.98E+08 O.OOE+00 3.31E+08 28

)RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01 003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (Rd)FOR RADIONUCLID)ES OTHER THAN NOBLE GASES Grass-Cow-Milk Pathway (m2 mreni/yr) per (pCi/sec) uik Bo_ u Total :ihM Lng llLLI 1-130 1.73E+06 3.50E+06 1.80E+06 3.85E+08 5.23E+06 O.OOE+00 1.64E+06 1-131 1.30E+09 1.31IE+09 7.46E+08 4.34E+ 11 2.15E1+09 0.OOE+00 1.17E+08 1-132 6.92E-01 1.27E+O0 5.85E-01 5.90E+01 l95E1+00 O.OOE+00 1.50E+O0 1-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.54E+07 O.OOE+00 8-57E+06 1-134 O.OOE+OO 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.3OOE00 O.OOE+00 1-135 5.41E+04 9.74E+04 4.61E+04 8.63E1+06 1.49E+05 O.OOE+00 7.42E+04 Cs-134 2.27E+1O 3.72E+10 7.84E+09 0.OOE+00 1.ISE+10 4.14E+09 2.00E*08 Cs-136 1.OIE+09 2.78E+09 1.80E+09 O.OOE+00 1.48E+09 2.21E+08 9.78E+07 Cs-137 3.23E+10 3.09E+10 4.56E+09 O.OOE+00 1.O1E+10 3.62E+09 1.93E+08 Ba-140 1.17E+08 1.03E+05 6.84E+06 0.OOE+00 3.34E+04 6.12E+04 5.94E+07 La-140 1.78E+02 6.23E+01 2.10E+01 0.OOE+00 O.OOE+00 0.OOE+O0 1.74E1+06 Ce-141 2.19E+04 1.09E+04 I.62E1+03 O.OOE+00 4.79E+03 O.OOE+00 1.36E+07 Ce-144 1.62E1+06 5.09E+05 8.67E+04 0.03E+00 2.82E+05 O.OOE+00 1.33E+08 Pr-143 7.19E+02 2.16E+02 3.57E+I01 O.OOE+00 1.17E+02 O.OOE+00 7.76E+05 Pr-144 5.04E+00 1.56E+00 2.53E-01 O.OOE+00 8.24E-01 O.OOE+00 335E+03 Nd-147 4.45E+02 3.61E+02 2.79E+01 O.OOE+OD 1.98E+02 0.OOE+O0 5.71E+05 Eu-154 9.43E+04 8.48E+03 7.75E+03 0.00E+00 3.73E+04 0.00E+00 1.97E+06 Hf-181 6.44E+02 2.35E+03 2.91E+02 O.OOE+00 4.76E+02 O.OOE+00 8.66E+05 29 RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01 003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway (m2 mrem/yr) per (ICi/sec)

N1ur Total DElbl4LLI H-3 Be-7 I. 0.OOE+OC 9.OOE+02 3.20E+03 1.53E+03 3.20E+O13 9.84E+C12 3.20E+03 O.OOE+OO 3.20E+031 1.50E+03 3.20E+031 O.OOE+001 3.20E+03 855E+04 Cr-51 O.OOE+OC 0.OOE+O0 1.22E+O 4 6.79E+03 1.851E+03 124E+04 6.48E+05 Mn-54 O.OOE+O0 2.52E+06 6.71E+O) O.OOE+O0 7.06E+05 0.00E+00 2.1 IE+06 Pc-55 1.45E+06 7.72E+tS 2.39E1+O 5 O.OOE+OO 4.36E+05 1.43E+05 Fe-59 156E+06 2.53E+06 126E+0 6 O.OOE+CO O.OOE+00 7.3413+05 2.64E+06 Co-S7 O.OOE+O0 4.61E+05 9.33E+O 5 O.OOE+O0 0.00E+00 O.OOE+00 3.78E+C6 Co-58 O.OOE+O0 I.46E+06 4.46E+O 5 O.OOE+OO 0.00E+00 O.OOE+00 8.50E+06 Co-60 0.OOE+O0 5.19E+06 1.53E+Or 7 O.OOE+OO O.OOE+OO 0.00E+00 2.87E+07 Zn-65 4.97E+08 1.32E+09 8.23E+018 O.OOE+O0 8.34E+08 0.001+000 2.32E+08 Rb-86 0.OOE+OO 1.05E+09 6.48E+AX8 O.OOE+OO O.OOE+00 6.781+07 Sr-89 1.39E+10 O.OOE+O0 3.97E+Of O.OOE+00 0QWOE+oo 0.OOE+00 5.39E+08 Sr-90 2.35E+I I O.OOE+O0 5.95E+l( 0DOOE+OO O.OOE+00 0.0013+00 3.16E+09 Y-90 4.06E+02 O.OOE+O0 1.09E+OI O.OOE+O0 0.00E+00 O0.001+00 1.15E+06 0.0013+00 Y-91 4.69E+03 0.OOE+00 1.25E+02 O.OOE+00 0.OOE+OO O.OOE+00 6.25E+05 Zr-95 4.60E+02 l.OIE+02 9.01E+0I O.OOE+O0 1.45E+02 O.OOE+00 1.06E+05 Nb-95 4.46E+041 1.74E+04 1.24E+04 Q.OOE+00 1.63E+04 .001E+00 3.21E+07 Ru-103 5.14E+02 O.OOE+O0 1.98E+02 O.OOE+00 1.29E+03 1.33E+04 O.OOE+OO Ru-106 1.1 IE+04 0.OOE+O0 1.38E+03 IO.OOE+00 15013+04 O.OOE+0O 1.73E+05 Ag-I lin 2.51E+07 1.69E+,07 1.35E+07 O.OOE+OO 3.15E+07 O.00E+00 2.01E+09 Cd-109 O.OOE+OO 4.64E1+05 2.15E+04 O.OOE+00 4.14E+05 .001E+00 150E+06 Sn-113 7.33E+07 1.51E+06 4.18E+06 I,.1E+08 0Q00E+00 5.18E+07 Sb-124 1.30E+07 1.69E+05 4.57E+06 2.8813+04 Q.OOE+00 7.24E+06 8.16E+07 Sb-125 1.05E+07 8.06E+04 2.19E+06 9.68E+03 O.OOE+00 5.83E+06 250E+07 Te-i27m 2.50E+07 6.73E+06 2.97E+06 5.98E+06 7.13E+07 O.OOE+00 2.02E+07 Te-129m 3.26E+07 9.10E+06 5.06E+06 1.05E+t7 9.57E+07 O.OOE+00 3.98E+07 I-130 2.08E+06 4.20E+06 2.16E+06 4.62E+08 6.27E+06 7.24E+00 1.96E+06 1-131 1.57E+09 1.57E+09 8.95E+08 5.21E+11 2.58E+09 .803E+00 1.40E+08 1-132 8.30E-O1 1.53E+O0 7.02E-O1 7.08E+01 2.34E+O0 O.OOE+00 1.80E+00 30 RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway (m2 mrem/yr) per (gCi/sec) lia Bone Total L U= fy 1-133 2.06E+07 2-55E+07 9.66E+06 4.74E+09 4.2513+07 Q.OOE+00 1.03E+07 1-134 O.OOE+O0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+00 0.00E+00 0.00E+00 1-135 6A49E+04 1.17E+05 5.53E+04 1.04E+07 I .79E+05 0.OOE+00 8.90E+04 Cs-134 6.80E+10 1.12E+1I 2.35E+10 O.OOE+O0 3.46E+10 1.24E3+10 6.011E+08 Cs-136 3.04E+09 8.35E+09 5.40E+09 0.OOE+O0 4.4513+09 6.63E+08 2.93E+08 Cs-137 9.68E+10 9.27E+10 1.37E+10 O.OOE+OO 3.02E+10 1.09E+10 5.80E+08 Ba-140 lA1E+O7 1.23E+04 8.21E+05 O.OOE+OO 4.0113+03 73513+03 7.1313+06 La-140 2.14E-+OI 7.47E+OO 2.52E+O0 O.OOE+OO O.OOE+00 0.OOE+00 2.08E+05 Ce-141 2.63E+03 1.31E+03 1.95E+02 O.OOE+OO 5.7513+02 O.OOE+00 1.63E+06 Ce-144 1.95E+05 6.1 IE+04 1.04E+04 0.00E+00 3.3813+04 0.OOE+00 1.5913+07 Pr-143 8.63E14O1 2.59E+O1 4.28E+OO O.OOE+00 1.40E+01 O.OOE+00 9.3113+04 Pr-144 6.05E-O1 1.87E-0I 3.04E-02 O.OOE+00 9.89E-02 0001E+00 4.03E+02 Nd-147 5.34E+O1 4.33E+O1 3.35E+OO O.OOE+00 2.37E3+01 O.OOE+00 6.85E+04 Eu-154 1.13E+04 I.02E+03 9.29E+02 O.OOE+00 4.47E1+03 0.OOE+00 2.37E+05 Hf-181 7.73E+OI 2.81E+02 3.49E+0O 0.00E+00 5.72E+01 0.00E+00 1.0413+05 31 RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Vegetation Pathway 2

(m mrem/yr) per (,Ci/sec)

Bge Lir Total Kid= Lm r-1-h H-3 ND 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 Be-7 3.38E+05 5.76E+05 3.70E+05 0.00E+00 5.65E+05 0.00E+00 3.21E+07 Cr-51 0.00E+00P 0.00E+00 1.17E+05 6.50E+04 1.782+04 1.199+05 6.21E+06 Mn-54 0.00+00 6.65E+08 1.771+08 0.00E+00 1.86E+08 0.00E+00 5.58E+08 Fe-55 8.01E+08 425E+08 1.32E+08 O.OOE+00 0.OOE+00 2.40E+08 7.87E+07 Fe-59 3.98E+08 6.43E+08 3.20E+08 0.00E+00 1.87J+08 6.70E+08 0.00E+00 2.99E+07 6.04E+07 0.00E+00 0.002+00 0.ODE+.00 2.45E+08 CD-58 6.44E+07 1.97E+08 O.OOE+00 0.00E+00 0.00E+00 3.76E+08 Co-60 0.00E+00 3.78E+08 1.12E+09 0.00E+00 0.OOE+00 0.00E+00 2.10E+09 0.0023+00 Zn-65 8.13E+08 2.17E+09 1.35E+09 0.00E1+00 1.362+09 O.OOE+00 3.80E+08 0.00E+00 Rb86 O.00E+00 4.52E+08 2.78E+O8 0.00E+00 0.00E+00 2.912+07 Sr-89 3.60E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 O.OOE+00 1.39E+09 Sr-90 1.24E+12 O.00E+00 3.15E+1I 0.00E+00 0.00E+00 O.00E+00 1.67E+10 O.OOE+00 Y-90 3.01E+06 0.00E+00 8.04E+04 0.OOE+00 0.00E+00 0.00E+00 8.56E+09 Y-91 1.86E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.48E+09 Zr-95 3.86E+06 8A8E+05 7.55E+05 0.00E+00 1.21E+06 0.001E+00 8.85'i+08 Nb-95 7.48E+05 2.91E+05 2.08E+05 0.00E+00 2.74E+05 0.0012+00 5.39E+08 Ru-103 1.53E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.002+00 3.97E+08 0.00E+O00 Ru-106 7.45E+08 0.00E+00 9.30E+07 1.01E+09 1.16E+10 O.OOE+OO 0.002E+00 0.002+OO Ag-lOrm 3.21E+07 2.17E+07 1.73E+07 0.00E+00 4.04E+07 2.58E+09 Cd-109 0.00E+00 2.45E+08 1.14E+07 0.00E+00 2.18E+08 O.WOE+00 7.94E+08 O.OOE+00 Sn-113 1.58E+09 3.25E+07 9.OOE+07 2.40E+09 0.O0E+00 1.122+09 O.OOE+O0t Sb- 124 3.52E+08 4.57E+06 1.23E+08 7.77E+05 0.00E+00 0.00E+0Q 2.20E+09 1.9512+08 Sb-125 4.99E+08 3.85E+06 1.05E+08 4.63E+05 0.00E+00 2.78E+08 1.19E+09 Te-127m 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 1.07E+09 Tc-129m 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 0.00E+00 1.03E+09 0.002+00 1-130 6.16E+05 1.24E+06 6.41E+05 1.37E+08 1.86E+06 O.00E+00 5.82E+05 1-131 1.43E+08 1.44E+08 8.17E+07 4.76E+10 2.36E+08 O.OOE+00 1.28E+07 32 IRKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01 003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Vegetation Pathway 2

(m mrem/yr) per (pCi/sec)

,Re Total DlKom Lung 1-132 9.23E+01 1.70E+02 7.80E+01 7.87E+03 2.60E+02 O.OOE+OO 2.00E+02 1-133 3.53E+06 5 4.37E+06 1.65E+06 8.12E+08 7.28E+06 O.OOE+00 1.76E+06 1-134 1.56E-04 2.89E-04 1.33E-04 6.65E-03 4.42-04 0.002+00 1.92E-04 1-135 6.26E+04 1.13E+05 5.33E+04 9.98E+06 1.73E+05 0.00E+00 8.59E+04 Cs-134 1.60E+10 2.63E+10 5.55E+09 0.00E+00 8.15E+09 1.42E+08 Cs-136 8.24E+07 2.27E+08 1.47E+08 0.OOE+O0 1.211E+08 1.801E+07 7.96E+06 Cs-137 2.39E+10 2.29E+10 3.38E+09 O.OOE+00 7.46E+09 2.68E+09 1.43E+08 Ba-140 2.77E+08 2.43E+05 1.62E+07 0.00E+00 7.90E+04 1.45E+05 1.40E+08 La-140 3.36E+04 1.18E+04 3.96E+03 0.OOE+OO 0.002+00 3.28E+08 Ce-141 6.56E+05 3.27E+05 4.86E+04 O.OOE+00 1.43E+05 Q.OOE+00 4.08E+08 O.OOE+OO O.WOE+oo Ce-144 1.27E+08 3.98E+07 6.78E+06 2.21E+07 1.04E+10 Pr-143 1.46E+05 4.37E+04 7.23E+03 0.00E+00 2.37E+04 0.0013+00 1.57E+08 O.OOE+O0 Pr-144 7.88E+03 2.44E+03 3.97E+02 0.00E+00 1.29E+03 525E+06 Nd-147 5.79E+04 4.48E+03 O.OOE+OO 3.18E+04 O.OOE+00 7.15E+04 9.17E+07 Eu-154 1.66E+08 1 50E+07 1.37E+07 0.00E+00 6.57E+07 0.00E+00 3.48E+09 Hf-181 4.90E+05 1.79E+06 2.21E+05 0.00E+00 3.63E+05 O.OOE+00 6.59E+08 33 RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER TIAN NOBLE GASES Inhalation Pathway (mrenlyr) per (ILCi/m 3)

DM Ltm Total Thm l4m 04.

ND 12611+03 1.26E+03 1.261E+03 1.26E+03 1.26E+03 1.26E+03 H-3 4.27E+02 9.68E+02 4.70E+02 ND ND 4.2113+04 5.35E+03 Be-Cr-51 ND ND l.00E+02 5.95E+01 2.28E+0O 1A44E+04 3.32E+03 Mn-54 ND 3.9613+04 63013+03 ND 9.8413+03 1.40E+06 7.74E+04 Fe-55 2.46E+04 1.70E+04 3.9413+03 ND ND 7.21E304 6.03E+03 Fe-59 1.18E+04 2.78E+04 1.06E+04 ND ND 1.02E+06 1.88E+05 ND 6.9213+02 6.71E+02 ND ND 3.701,+05 3.14E+04 Co-57 CoS8 ND 1.58E+03 2.07E+03 ND ND 9ME+05 1.06B+05 Co-60 ND 1.1513+04 1.48E3+04 ND ND 5.97E+06 2.85E+05 Zn-65 3.24E+04 1.03E+05 4.6613+04 ND 6.90E+04 8.64E+05 5.341;+04 Rb-86 ND 1.35E+05 5.90B+04 ND ND ND 1.6613+04 Sr-89 3.04B+05 ND 8.72E+03 ND ND 1AOE+06 3.50E+05 9.92E+07 ND 6.10E+06 ND ND 9.60E+06 7.221+05 Sr-90 ND 5.6113+01 ND ND 1.70E+05 5.06E+05 Y-90 2.09E+03 Y-91 4.62E+05 ND 1.24E+04 ND ND 1.70E+06 3.8513+05 Zr-95 1.07E+05 3.44E+04 233E+04 ND 5.42E+04 1.77E+06 1.50E+05 Nb-95 1.4113+04 7.8213+03 4.21E+03 ND 7.74E+03 5.0513+05 1.04E+05 Ru-103 1.53E+03 ND 6.58E+02 ND 5.83E+03 5.05E+05 1.1013+05 Ru-106 6.91E+04 ND 8.72E +03 ND 1.34E+05 9.36E+06 9.12E+05 Ag-llOm 1.08E+04 I.0013+04 5.9413+03 1.97E+04 4.63E+06 3.0213+05 Cd-109 ND 3.67E+05 1.31E+04 3.57E+05 6.83E +05 5.82E+04 Sn-l 13 5.7213+04 2.1813+03 4.39E+03 I 24E+03 ND 9A4E+05 1.18E+05 Sb-124 3.1213+04 5.8913+02 1.24E+04 7 55E+OI ND 2A8E+06 4.0613+05 Sb-125 5.34E+04 5.95E+02 1.26E1+04 5 40E+OI ND 1.74E+06 1.0113+05 Te-127m 1.26E+04 5.77E+03 157E+03 3.29E+03 4.58E+04 9.601+05 1.50E+05 Te- 129m 9.76E+03 4.67E+03 1589E+03 3 44E+03 3.66E+04 1.16E+06 3.83E+05 1-130 4.5ME+03 1.34E+04 5.28E+03 1 14E+06 2.09E+04 IND 7.69E+03 1-131 2.52E+04 3.58E+04 2.M5E+04 1.1913+07 6.13E+04 IND 6.2813+03 34 APA-ZZ-01 003 (016)

RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS

A APA-ZZ-01003 Rev. 016 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Inhalation Pathway (mremlyr) per (eCi/m 3)

Lb" Total 1mg I-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 ND 4.06E+02 1-133 8.64E+03 1.48E+04 4-52E+03 2.15E+06 2.58E+04 ND 8.88E+03 1-134 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 ND 1.OIE+OO 1-135 2.68E+03 6.98E+03 2.57E+03 4.48E+05 1.1 IE+04 ND 5.25E+03 Cs-134 3.73E+05 8.48E+05 7.28E+05 ND 2.87E+05 9.76E+04 I.04E+04 Cs-136 3.90E+04 1.46E+05 E.IOE+05 ND 8.56E+04 1203E+04 1.17E+04 4.78E+05 6.21E+05 4.28E*05 ND 2.22E+05 7.52E+04 8.40E+03 Cs-137 Ba-140 3.90E+04 4.90E+01 2.57E+03 ND 1.67E+O1 1.27E+06 2.18E1+05 La-140 3.44E+02 1.74E+02 4.58E+01 ND ND 1.36E+05 4-58E+05 Ce-141 1.99E+04 1.35E+04 1.53E+03 ND 6.26E+03 3.62E+05 1.20E+05 Ce-144 3A3E+06 IA3E+06 1.84E+05 ND 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 ND 2.16E+03 2.811E+0S 2.OOE+05 Pr-144 3.01E-02 1.25E-02 1.53E-03 ND 7.05E-03 1.02E1+03 2.15E-08 5.27E+03 6.10E+03 3.65E+02 ND 3:56E+03 2.21E+05 1.73E 005 Nd-147 S.92E+06 7.28E+05 5.18E1+05 ND 3.49E+06 4.67E+06 2.72E+05 Eu-154 Hf-181 1.41E+04 6.82E+04 6.32E+03 ND 1.48E+04 6.85E+05 1.39ES05 35 APA-ZZ-01 003 (016)

RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS

APA-ZZ-01003 Rev. 016 TABLE 3A ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

_ OTHER THAN NOBLE GASES Meat Pathway 2

(m mremn/yr) per (ItCi/sec)

AM LI=er Total 11ld Lmm 1GTLLI H-3 ND 3.25E+02 3.25E+Cr2 3.25E+02 3.25E+02 3.25E+02 3.25E+02 Be-7 4.57E+0)3 1.04E+04 5.07E+C'3 ND 1.10E+04 ND . 1.81E+06 Cr-51 ND ND 7.04E+O)3 4.21E+03 1.55E+03 9.34E+03 1.77E+06 Mn-54 ND 9.17E+06 1.75E+0 6 ND 2.73E+06 ND 2.81E+07 Fe-55 2.93E+0t8 2.02E+08 4.72E+07 ND ND 1.13E+08 1.16E+08 Fe-59 2.65E+0 18 6.24E+08 2.39E+0 8 ND ND 1.74E+08 2.08E+09 Co-57 ND 5.63E+06 9.36E+0 6 ND ND ND 1.43E+08 Co-58 ND 1.82E+07 4.08E+aY7 ND ND ND 3.69E+08 Co-60 ND 7.51E+07 1.66E+018 ND ND ND 1.41E+09 Zn-65 3.56E+01 1.13E+09 5.11E+018 ND 7.57E+08 ND 7.13E+08 Rb-86 ND 4.87E+08 2.27E+DM ND ND ND 9.60E+07 Sr-89 3.01E+0O ND 8.65E+0( 6 ND ND ND 4.83E+07 Sr-90 1.24E+1C D ND 3.05E+099 ND ND ND 3.59E+08 Y-90 1.21E+O5 ND 3.24E+03I ND ND ND 1.28E+09 Y-91 1.13E+06 ND 3.02E+04 ND ND ND 6.23E+08 Zr-95 1.87E+06 6.OOE+05 4.06E+05 ND 9.42E+05 ND 1.90E+09 Nb-95 3.15E+06 1.75E+06 9A3E+05 ND 1.73E+06 ND 1.06E+10 Ru-103 1.05E+08 ND 4.53E+07 ND 4.01E+08 ND 1.23E+10 Ru-106 2.80E+09 ND 3.54E+08 ND 5.40E+09 ND 1.81E+I1 Ag- 1lm 6.68E+06 6.18E+06 3.67E+06

• ND 1.21£+07 ND 2.52E+09 Cd-109 ND 1.59E+06 5.55E+04 ND 1.52E+06 ND 1.60E+07 Sn-i 13 1.37E+09 3.88E+07 7.86E+07 2.22E+07 'ND ND 4.09E+09 Sb124 1.98E+07 3.74E+05 7.84E+06 4.79E+04 ND 154E+07 5.61E+08 Sb-125 1.91E+07 2.13E+05 4.54E+06 1.94E+04 ND 1.47E+07 2.10E+08 Te- 127m 1.I E+09 3.98E+08 1.36E+08 2.85E+08 4.53E+09 ND 3.742+09 Te-129m 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 ND 5.71E+09 1-130 2. 12E-06 6.27E-06 2.47E-06 5.31E-04 9.78E-06 ND 5.40E-06 1-131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 ND 4.06E+06 36

'RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01 003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Meat Pathway 2

(m mremfyr) per (lCi/sec)

Linr Total Ilivrold Kidm lmz GI-LI 1-132 0.OOE+00 0.001+00 0.00E+00 0.00E+00 0.00E+00 ND 0.00E+00 1-133 3.67E-01 6.39E-01 1.9513-01 9.38E+01 1.1lE+00 ND 5.74E-01 1-134 .003E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 ND 0.00E+00 1-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E3+00 ND 0.OOE+00 Cs-134 6.57E+08 1.56E+09 1.28E+09 ND 5.06E3+08 1.68E+08 2.74E+07 Cs- 136 1.20E+07 4.76E+07 3.421+07 ND 2.65E3+07 3.63E+06 5.40E+06 Cs-137 8.71E+08 1.19E+09 7.81E+08 ND 4.04E3+08 1.34E+08 2.31E+07 Ba-140 2.87E+07 3.611+04 1.88E+06 ND 1.23E+04 2.07E+04 5.91E1+07 La-140 2.21E+02 1.11E+02 2.94E+01 ND ND ND 8.183E+06 Ce-141 1.40E+04 9A9E+03 1.08E+03 ND 4.41E+03 ND 3.63E+07 Ce-144 1.46E+06 6.09E+05 7.82E+04 ND 3.61E+05 ND 4.92E+08 Pr-143 2.10E+04 8.40E+03 1.04E+03 ND 4.85E3+03 ND 9.181E+07 Pr-144 3.52E+02 IA6E+02 1.79E+01 ND 8.24E+01 ND 5.06E-05 Nd-147 7.07E+03 8.17E+03 4.89E+02 ND 4.77E+03 ND 3.92E+07 Eu-154 8.02E+06 9.86E+05 7.01E+05 ND 4.72E+06 ND 7.14E+08 Hf-181 3.01E+06 I.46E+07 1.35E+06 ND 3.14E+06 ND 1.66E+10 37 RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Cow-Milk Pathway (m2 mremfyr) per (jtCi/sec) id, Bone Total kmg 1H-3 ND 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 1.63E+03 3.7213.03 1.81E+03 ND 3.93E+03 ND 6.45E+05 Be-7 Cr-51I ND ND 2.86E+04 1.71E+04 6.30E+03 3.79E+04 7.19E4+06 ND 8.42E+06 1.61E+06 ND 2.50E+06 ND 258E+07 Mn-54 Fe-55 I 2.51E+07 1.74E+07 4.05E+06 ND ND 9681E+06 9.96E1+06 Fe-59 2.97E+07 6.98E+07 2.68E+07 ND ND 1.9513E07 2.33E+08 ND 128E.06 2.13E+06 ND ND ND 3.25E+07 Co-57 CW58 ND 4.72E+06 1.06E+07 ND ND ND 956E3+07 CO-60 ND 1.64E+07 3.62E+07 ND ND ND 3.08E+08 Zn65 1.37E+09 4.3713+09 1.97E+09 ND 2.92E+09 ND 2.75E+09 Rb-86 ND 2.60E+09 1.2113+09 ND ND ND 5.12E+08 ND 4.17E+07 ND ND ND 2.33E+08 Sr-89 1.45E+09 4.68E+10 ND 1.15E+10 ND ND ND 1.35E+09 Sr-90 Y-90 7.43E+02 ND 1.99E1301 ND ND ND 7.87E+06 Y-91 8.59E+03 ND 2.30E+02 ND ND ND 4.73E+06 Zr-95 9.44E+02 3.03E+02 2.05E+02 ND 4.75E+02 ND 939E+05 Nb-95 9.65E+04 5.37E+04 2.89E+04 ND 5.31E+04 ND 326E+08 1.02E+O0 ND 4.39E+02 ND 3.89E+03 ND 1.19E+05 Ru-103 Ru-106 2.04S1304 ND 2.58E--03 ND 3.94E+04 ND i.32+06 Ag-llOm 5.82E+07 5.39E+i07 3.20E+07 ND 1.06E+08 ND 220E+10 Cd-109 ND 1.13E+06 3.95E+04 ND 1.08E+06 ND 1.14E+07 Sn-113 1.34E+08 3.81E+06 7.73E+06 2.18E+06 ND ND 4.02E+08 Sb-124 2.57E+07 4.86E+05 I .02E+07 6.24E404 ND 2.00E+07 7.31E+08 Sb-125 2.04E+07 228E+05 4.87E+06 2.08E+04 ND 1.58E+071 2.25E+08 T-127m 4.58E+07 1.64E+07 5.58E+06 1.17E+07 1.8613+08 ND 1.54E+08 6.02E+07 2.25E+07 9.53E+06 2.071E+07 2.51E+08 ND 3.03E+08 Te-129m 1-130 4.21E+05 1.24E+06 4.91E+05 1.05E+08 1.94E+06 ND 1.07E+06 1.131 2.97E+08 4.25E+08 2.43E.08 1.39E+1 I 7.28E+08 ND 1.12E+08 38 APA-ZZI1003 (016)

IRKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS

APA-ZZ-0I 003 Rev. 016 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR IADIONUCLIDES OTHER THAN NOBLE GASES Grass-Cow-Milk Pathway (m2 mremfyr) per (QCi/sec)

___ Total 1-132 1.65E-01 4.421-01 1.55E-01 155E01 7.04E-41 ND 8.30E-02 1-133 3 .88E+06 6.75E+06 2.06E+06 9.92E+08 1.18E+07 ND 6.07E+06 1-134 O.OO.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND O.OOE+OO 1-135 1.29E+04 3.37E+04 125E1+04 2.23E+06 SAIE+04 ND 3.81E+04 Cs-134 5.65E+09 1.35E+10 1.IOE+1O ND 4.3SE+09 1.45E+09 2.35E+08 Cs-136 2.63E+08 1.04E+09 7.48E108 ND 5.79E+08 7.93E+07 1.18E1+08 Cs-137 7.38E+09 1.OIE+10 6.61E+09 ND 3A3E+09 1.14E+09 I.95E+08 Ba-140 2.69E+07 3.38E+04 1.76E+06 ND 1.15E+04 1.93E+04 5.54E+07 La-140 4.14E+01 2.093E+01 5.51E+OO ND ND ND 1.53E+06 Ce-141 4.8511+03 3.28E+03 3.72E+02 ND 1.52E+03 ND 1.25E+07 Ce-144 3.58E+05 1SOE+05 1.92E+04 ND 8.87E+04 ND 1.21E+08 Pr-143 1.58E+02 6.34E+01 7.83E+OO ND 3.66E+OI ND 6.92E+05 Pr-144 I.IOE+OO 4.58E-01 5.61E-02 ND 2.58E-01 ND 1.59E-07 Nd-147 9.42E+O1 1.09E+02 6.51E+OO ND 6.36E+O1 ND 523E+05 Eu-154 2.37E+04 2.91E+03 2.07E+03 ND 1.39E+04 ND 2.1IE+06 Hf-181 I.42E+02 6.92E+02 6.41AE+O1 ND 1.49E+02 ND 7.87E+05 39

,RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01 003 (01 6)

APA-ZZ-01003 Rev. 016 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway (m2mrem/yr) per (gCi/sec) i o ne Unr. Total Kidneyd iLm G1-iL

.Rf H-3 ND . 1.56E+031 1-56E+031 lS6E+03 1.5613+03 1.5613+03 1.56E+03 Be-7 1.96E+02 4.47E+021 2.17E+02 ND 4.7213+02 ND 7.74E+04 Cr-SI ND ND 3.4313+0 3 2.05E+03 7.56E+02 4.56E+031 8.6313+05 Mn-54 ND 1.01E]+06 1.93E+O5 ND 3.0113+05 ND 3.10E+06 Fe-55 3.27E+05 2.26E+05 5.26E+0 4 ND ND 1.2613+05 1.3013+05 Fe-59 3.87E+05 9.08E+05 3A8E+O5 ND ND 2.54E F05 3.0313+06 Co-57 ND 1.5413+05 2.56E+O.5 ND ND ND 3.90E+06 Co-58 ND 5.66E+05 1.27E+0 16 ND ND ND 1.15E+07 Co-60 ND 1.97E+06 4.35E+0i 6 ND ND ND 3.70E+07 Zn-65 1.65E+08 5.24E+08 2.37E+AX8 ND 3.51E+08 ND 3.3013+081 Rb-86 ND 3.12E+08 1.45E+Of ND ND ND 6.15E+107 Sr-89 3.05E+09 ND 8.75E+W07 ND ND ND 4.89E+08 Sr-90 9.84E+10 ND 2.41E+1( ND ND ND 2.84E+09 Y-90 8.92E+01 ND 2.39E+00 I ND ND 'ND 9A6E+05 Y-91 1.03E+03 ND 2.7613+01 ND ND ND 5.68E+05 Zr-95 1.13E+02 3.63E+01 2.46E+01 ND 5.70E+OI ND 1.15E+05 INb-95 1.16E+04 6.45E+03 3.47E+03 ND 637E+03 ND 3.91E+07 Ru-103 1.2213+02 ND 5.27E+01 ND 4.67EE+02 ND 4A313+04 Ru-106 2.45E+03 ND 3.10E.02 ND 4.73E+03 ND 1.59E+05 Ag-I lOm 6.99E+06 6.47E+06 3.84E+06 ND 1.2713+07 ND 2.64E+09 Cd-109 ND 1.36E+05 4.74E+03 ND 1.30E+05 ND 1.37E+06 Sn-113 1.61E+07 4.58E+05 9.28E+05 2.62E+05 ND ND 4.83E+07 Sb-124 3.0913+06 5.84E+04 1.23E+06 7.501E+03 ND 2.4113+06 8.7813+07 Sb-125 2A6E+06 2.74E+04 5.84E+05 2.5013+03 ND 1.89E+06 2.70E+07 Te-127m 5.50E+06 1.9713+06 6.70E+05 1.41E+06 2.23E+07 ND 1.8413+07 Te-129m 7.23E+06 2.70E+06 1.14E+06 2.4813+06 3.02E+07 ND 3.64E+07 1-130 5.05E+05 1.4913+06 5.88E+05 1.26E1+08 2.32E+06 ND 1.28E+06 1-131 3S56E+08 5.09E+08 2.92E+08 1.67E+I I 8.72E+08 ND 1.3413+08 1-132 1.98E-01 S.29E-01 I .8513-01 1.85E+01 8.43E-01 ND 9.95E-02 40

)RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01 003 (01 6)

APA-ZZ-01003 Rev. 016 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway (m2mremx/yr) per (gLCisec) on Mm_ Total :LLI 1-133 4.65E+06 8.09E+06 2.47E+06 1.19E+09 1.41IE+07 ND 7.27E+06 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND O.OOE1+OO 1-135 1.54E+04 4.04E+04 1.49E+04 2.67E+06 6.48E+04 ND 4.57E--04 Cs-134 1.70E+10 4.04E+10 3.30E+10 ND 1.31E+10 4.34E+09 7.07E+08 Cs- 136 7.9IE+OB 3.12E+09 2.25E1+09 ND 1.74E+09 2.38E+O08 3.55E+O8 Cs0137 2.22E+10 3.03E+10 1.99E+10 ND 1.03E+10 3.42E+09 5.87E+08 Ba-140 3.23E+06 4.06E+03 2.12E+05 ND 1.38E+03 2.32E+03 6.65E+06 La-140 4.97E+00 2.51lE+OO 6.62E4-1 ND ND ND 1.84E+Q05 Ce 141 5.82E+02 3.94E+02 4.46E+O1 ND 1.83E+02 ND 1.50E+06 Ce 144 4.30E+04 1.80E+04 2.31E+03 ND 1.07E+04 ND 1.45E+07 Pr-143 1.9OE+01 7.61E+00 9.40E-O1 ND 4.39E+OO ND 8.31E+04 Pr-144 1.33E-01 5.50E-02 6.74E-03 ND 3.IOE-02 ND 1.91E-08 Nd-147 1.13E+01 1.31E+O1 7.82E-OI ND 7.64E+OO ND 6.28E+04 Eu-154 2.84E+03 3.49E+02 2.49E+02 ND 1.67E+03 ND 2.53E+05 Hf-181 1.71IE+OI 8.31IE+O1 7.70E+00 ND I.79E+O1 ND 9.46E+04 41 RKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

_ OTHER THAN NOBLE GASES Vegetation Pathway (m2mrem/yr) per (gCilsec) lide Bm mLix Total hizroi4 Mmi LI, RQ-y H-3 ND 2.26E+03 2.26E+031 2.26E+0 )3 2.26E+03 2.26E+03 2.26E+03 Be-7 9.24E+O 2.11E+05 1.03E+051 ND 2.23E+05 ND 3.66E+07 Cr-Sl ND ND 4.64E+04 2.78E+O4 1.02E+04 6.16E+04 1.17E+07 MD-54 ND 3.13E+08 5.97E+07 ND 9.31E+07 ND 959E+08 Fe-55 2.10E+0: 1.45E+08 3.38E+07 ND ND 8.08E+07 8.31E+07 Fe-59 1.262+0 2.96E+08 1.14E+08 ND ND 8.28E+07 9.882+0>8 Co-57 ND 1.17E+07 1.95E+07 ND ND ND 2.97E+08 Co-58 ND 3.07E+07 6.89E+07 ND ND ND 6.23E+08 Co-60 ND 1.67E+08 3.69E+08 ND ND ND 3.14E+09 Zn-65 3.17E+01 I1.lE+09 4.56E+08 ND 6.75E+08 ND 6.36E+08I Rb-86 ND 2.19E+08 1.02E+08 ND ND ND 4.33E+07 Sr-89 9.97E+09 ND 2.86E+08 ND ND ND 1.60E+09 Sr-90 6.05E+11 ND 1.48E+11 ND ND ND 1.75E+10 Y-90 7.67E+05 ND 2.06E+04 ND ND ND 8.14E+09 Y-91 5.11E+06 ND 1.37E+05 ND ND ND 2.81E+09 Zr-95 1.17E+06 3.77E+05 2.55E+05 ND 5.91E+05 ND l.19E+09 Nb.95 2AOE+05 1-34E+051 7.19E+04 ND 132E+05 ND 8.11E+08 Ru-103 4.77E+06 ND 2.06E+06 ND 1.82E+07 ND 557E+08I Ru-106 1.93E+08 ND 2.44E+i07 ND 3.72E+08 ND 1.25E+10 Ag-ll0m 1.05E+07 9.75E+06 5.79E+06 iND.! 1.92E+07 ND 3.98E+09 Cd-109 8.36E+07 2.92E+06 ND 8.00E+07 ND 8.43E+08 Sn-1 13 4.16E+08 1.18E+07 2.40E+07 6.75E+06 ND ND 1.25E+09 Sb-124 1.04E+08 1.96E+06 4.1IE+07 2.51E+05 ND 8.07E+07 2.94E+09 Sb-125 1.37E+08 1.53E+06 3.25E+07 1.39E+05 ND 1.05E+08 ]50E+09 Te-127m 3A9E+08 1.25E+08 4.26E+07 8.92E+07 1.42E+09 ND 1.17E+09 Te-129m 2.5IE+08 9.38E+07 3.98E+07 8.64E+07 1.05E+09 ND 1.27E+09 1-130 3.93E+05 1.16E+06 9.81E+07 1.81E+06 ND 9.97E+05 1-131 8.08E+07 1.16E+08 3.79E+10 1.98E+08 ND 3.05E+07 42 IRKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01003 (016)

APA-ZZ-01003 Rev. 016 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Vegetation Pathway 2

(m mrem/yr) per (lCilsec)

__ LI=m Total L-L 1 1-132 5.77ME+01 1.542+02 5.40E+01 5.40E+03 2.46E+02 ND 2.90E+01 1-133 2.09E+06 3.63E+06 1.1 IE+06 5.33E+08 6.33E+06 ND 3.26E+06 1-134 9.69E405 2.63E-04 9.42E-05 4.56E-03 4.194-04 ND 2.30E-07 1-135 3.90E+04 1.02E+05 3.77E+04 6.74E+06 1.64E+05 ND 1. I5+OS Cs-134 4.67E+09 1.1IE+10 9.082+09 ND 3.59E+09 1.19E+09 1.94E+08 Cs-136 4.27E+07 1.69E+08 1.211I+08 ND 9.38E+07 1.29E+07 1.91E+07 Cs-137 6.36E+09 8.70E+09 5.70E+09 ND 2.95E+09 9.812I+08 1.68E+08 Ba-140 1.29E+08 1.61E+05 8.422+06 ND 5A9E+04 9.24E+04 2.65E+08 La-140 1.58E+04 7.98E+03 2.1 lE+03 ND ND ND 5.86E+08 Ce-141 1.97E+05 1.33E+05 1.51E+04 ND 6.192+04 ND 5.10E+08 Ce-144 3.29E+07 1.38E+07 1.77E+06 ND 8.162+06 ND 1.112I+10 Pr-143 6.26E+04 2.51E+04 3.10E+03 ND 1.45E+04 ND 2.74E+08 Pr-144 2.03E+03 8.43E+02 1.032+02 ND 4.752+02 ND 2.922-04 Nd-147 3.33E+04 3.85E+04 2.31E+03 ND 2.25E+04 ND 1.85E+08 Eu-154 4.85E+07 5.97E+06 4.25E+06 ND 2.86E+07 ND 4.32E+09 Hf-181 1.402+05 6.82E+05 6.32E+04 ND 1.472+05 ND 7.76E+08 43 IRKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01003 (016)

APA-ZZ-01003 Rev. 016 4 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 4.1 CALCULATION OF DOSE AND DOSE COMMiTMENT FROM URANIUM FUEL CYCLE SOURCES The annual dose or dose commitment to a MEMBER OF THE PUBLIC for Uranium Fuel Cycle Sources is determined as:

a) Dose to the total body and internal organs due to gamma ray exposure from submersion in a cloud of radioactive noble gases, ground plane exposure, and direct radiation from the Unit ,

onsite storage of low-level radioactive waste, and outside storage tanks; b) Dose to skin due to beta radiation from submersion in a cloud of radioactive noble gases, and ground plane exposure; c) Thyroid dose due to inhalation and ingestion of radioiodines; and d) Organ dose due to inhalation and ingestion of radioactive material.

It is assumed that total body dose from sources of gamma radiation irradiates internal body organs at the same numerical rate. (Ref. 11.12.5)

The dose from gaseous effluents is considered to be the summation of the dose at the individual's residence and the dose to the individual from activities within the SITE BOUNDARY.

Since the doses via liquid releases are very conservatively evaluated, there is reasonable assurance that no real individual will receive a significant dose from radioactive liquid release pathways. Therefore, only doses to individuals via airborne pathways and doses resulting from direct radiation are considered in determining compliance to 40 CFR 190 (Ref. 11.12.3).

There are no other Uranium Fuel Cycle Sources within 8km of the Callaway Plant.

4.1.1 IDENTIFICATION OF THE MEMBER OF THE PUBLIC The MEMBER OF THE PUBLIC is considered to be a real individual, including all persons not occupationally associated with the Callaway Plant, but who may use portions of the plant site for recreational or other purposes not associated with the plant (Ref. 1.4 and 11.8.10).

Accordingly, it is necessary to characterize this individual with respect to his utilization of areas both within and at or beyond the SITE BOUNDARY and identify, as far as possible, major assumptions which could be reevaluated if necessary to demonstrate continued compliance with 40 CER 190 through the use of more realistic assumptions (Ref. 11.12.3 and 11.12.4).

The evaluation of Total Dose from the Uranium Fuel Cycle should consider the dose to two Critical Receptors: a) The Nearest Resident, and b) The Critical Receptor within the SITE BOUNDARY.

4.1.2 TOTAL DOSE TO THE NEAREST RESIDENT The dose to the Nearest Resident is due to plume exposure from noble gases, ground plane exposure, and inhalation and ingestion pathways. It is conservatively assumed that each ingestion pathway (meat, milk, and vegetation) exists at the location of the Nearest Resident.

It is assumed that direct radiation dose from operation of the Unit and storage of radioactive

/ smaterial, and dose from gaseous effluents due to activities within the SITE BOUNDARY, is negligible for the Nearest Resident. The total Dose from the Uranium Fuel Cycle to the Nearest Resident is calculated using the methodology discussed in Section 3, using concurrent meteorological data for the location of the Nearest Resident with the highest value of X/Q.

The location of the Nearest Resident in each meteorological sector is determined from the Annual Land Use Census conducted in accordance with the Requirements of REC 16.11.4.2.

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APA-ZZ-01003 Rev. 016 4.1.3 TOTAL DOSE TO THE CRITICAL RECEPTOR WITHIN THE SiTE BOUNDARY The Union Electric Company has entered into an agreement with the State of Missouri Department of Conservation for management of the residual lands surrounding the Callaway Plant, including some areas within the SITE BC)UNDARY. Under the terms of this agreement, certain areas have been opened to the public for low intensity recreational uses (hunting, hiking, sightseeing, etc.) but recreational use is excluded in an area immediately surrounding the plant site (refer to Figure 4.1). Much of the residual lands within the SITE BOUNDARY are leased to area farmers by the Department of Conservation to provide income to support management and development costs. Activities conducted under these leases are primarily comprised of farming (animal feed),grazing, and forestry (Ref. 11.7.Z 11.7.3. 11.13, and 11.13.1).

Based on the utilization of areas within the SITE BOUNDARY, it is reasonable to assume that the critical receptor within the SITE BOUNDARY is a farmer, and that his dose from activities within the SITE BOUNDARY is due to exposure incurred while conducting his farming activities. The cm1rent tenant has estimated that he spends approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year working in this area (Ref. 11.5.5). Occupancy of areas within the SITE BOUNDARY is assumed to be averaged over a period of one year.

Any reevaluation of assumptions should consider only real receptors and real pathways using realistic assumption, and should include a reevaluation of the occupancy period at the locations of real exposure (e g. a real individual would not simultaneously exist at each point of maximum exposure).

4.1.3.1 Total Dose to the Farmer from Gaseous Effluent; The Total Dose to the farmer from gaseous effluents is calculated for the adult age group using the methodology discussed in Section 3, utilizing concurrent meteorological data at the farmers residence and historical meteorological data from Table 6.1 for activities within the SITE BOUNDARY. These dispersion parameters were calculated by assuming that the farmers time is equally distributed over the areas fanned within the SITE BOUNDARY, and already have the total occupancy of 1100 hour0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />s/year factored into their value (Ref. 11.5.6).

The residence of the current tenant is located at a distance of 2897 meters in the NNW sector.

The gaseous effluents dose at the fanner's residence is due to plume exposure from Noble Gases and the ground plane, inhalation, and ingestion pathways. For conservatism, it is acceptable to assume that all of the ingestion pathways exist at this location.

It is assumed that food ingestion pathways do not exist within the SITE BOUNDARY, therefore the gaseous effluents dose within the SITE BOUN1DARY is due to plume exposure from Noble Gases and the ground plane and inhalation pathways.

4.1.3.1.1 Direct Radiation Dose flom Outside Storage TanE The Refueling Water Storage Tank (RWST) has the highest potential for receiving significant amounts of radioactive materials, and constitutes the only potentially significant source of direct radiation dose from outside storage tanks to a MEMBER OF THE PUBLUC (Ref. 11.6.14, 11.6.15,11.6.16 and 11.6.17).

Direct radiation dose from the RWST to a MEMBER OF THE PUBLIC is determined at the nearest point of the Owner Controlled Area fence which is not obscured by significant plant structures, which is 450 meters from the RWST.

The RWST is a right circular cylinder approximately 12 meters in diameter, 14 meters in height with a capacity of approximately 1,514,000 liters (Ref. 11.6.17). The walls are of type 304 stainless steel and have an average thickness of .87 cm. (Ref. 11.14.1).

The direct radiation dose from the RWST is calculated based on the tank's average isotopic content and the parameters discussed above, considering buildup and attenuation within the volume source. Appropriate methodology for calculating the dose rate from a volume source is given in TID-7004, 'Reactor Shielding Design Manual" (Ref. 11.17). The computer program MICROSHIELD (Ref. 11. 18) will normally be utilized to perform this calculation.

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APA-ZZ-01003 Rev. 016 4.1.3.1.2 Direct Radiation Dose from the Reactor The maximum direct radiation dose from the Unit to a MEMBER OF THE PUBLIC has been determined to be 7E-2 mrads/calendar year, based on a point source of primary coolant N-16 in the steam generators. This source term was then projected onto the inside surface of the containment dome, taking credit for shielding provided by the containment dome and for distance attenuation. No credit was allowed for shielding by other structures or components within the Containment Building. The number of gammas per second was generated and then converted to a dose rate at the given distance by use of ANSUANS-6.6.1, "Calculation and Measurement of Direct and Scattered Gamma Radiation from LWR Nuclear Power Plant 1979",

which considers attenuation and buildup in air. The final value is based on one unit operating at 100% Power. The distance was determined to be 367 meters, which is approximately the closest point of the boundary of the Owner Controlled Area fence which is not obscured by significant plant structures (Ref. 11.14.3).

The maximum direct radiation dose from the Unit to the farmer is thus approximately 9E-3 mnrads per year, assuming a maximum occupancy of 1-100 hours per year.

Equipment Hatch Platform and Missile Shield Modification 03-1008 was completed in late 2005.

' \lb HPCI 06-01 was generated using actual radiation survey data at 100% Reactor power in order to calculate direct radiation dose from the Unit as a result of the modification. The calculated direct

4) radiation dose from the Unit to a MEMBER OF THE PUBLIC was determined to be 8.99E-06 mremperyear. (Ref. 11.14.10) 4.131.3 Direct Radiation Dose From On-Site Storage Of Low Level Radioactive Waste On-site storage for radioactive wastes is located in Stores II and Plant Southwest of the radwaste building in the Radwaste Yard. The Radwaste Yard consists of a concrete pad enclosed by a fence. The area is also bounded on two sides by the radwaste building and is partially bounded on a third side by the Discharge monitoring tanks dike system. The radioactive wastes are stored in this area using high integrity containers (HIC) inside Onsite Storage Containers (OSC) and LSA type storage containers. The HIC has the highest potential for containing significant amounts of radioactive material, and constitutes the most significant source of direct radiation from on-site radioactive waste storage The HICs typically are right circular cylinders approximately 1.7 meters in diameter and 1.8 meters in height. The HICs are stored inside OSCs which typically are constructed of concrete with additional shielding as necessary to minimize external doses. The individual parameters (e.g., dimensions, shielding material, etc.) fbr each OSC will be accounted for in the calculations.

The direct radiation dose from the HICs is the summation of the individual calculated HIC doses based on the HIC isotopic contents and the OSC design parameters, considering buildup, attenuation, and shielding. Appropriate methodology for calculating the dose rate from the HICs is given in Safety Analysis Calculations ZZ-293 and ZZ-310. The computer program MICROSHIELD (Ref. 11.18) will normally be utilized to perform this calculation.

Direct radiation dose from the HICs and the Radwaste yard (Ref. 11 20) to a MEMBER OF THE PUBLIC is determined at the nearest point of the Owner Controlled Area fence which is not 6-40 obscured by significant plant structures.

X.ypo'v_ Direct radiation dose from radioactive material storage at Stores II to a MEMBER OF THE PUBLIC is determined at the nearest point of the Owner Controlled Area fence which is not obscured by significant plant structures. (Ref. 11.19)

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APA-ZZ-01003 Rev. 016 4.1.3.1.4 Direct Radiation Dose From On-Site Storane Or Steam Generators The Old Steam Generator Storage Facility (OSGSF) was constructed to house steam generators

", 'AlvkP following replacement in Refuel 14. The OSGSF building is located inside the Owner Ali#. Controlled Area (OCA) Plant East of the cooling tower.

The OSGSF is constructed with 2' thick concrete walls and a 2' thick ceiling specifically designed for shielding of residual radioactivity in the steam generators.

Direct radiation dose from the OSGSF to a MEMBER OF THE PUBLIC is determined using radiation survey data at the nearest point of the Owner Controlled Area fence which is unobscured by significant plant structures. The distance was determined to be 420 feet tRKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-01 003 (016)

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APA-ZZ-01003 Rev. 016 5 RADIOLOGICAL ENVIRONMENTAL MONITORING

5.1 DESCRIPTION

OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program is intended to act as a background data base for preoperation and to supplement the radiological effluent release monitoring program during plant operation. Radiation exposure to the public from the various specific pathways and direct radiation can be adequately evaluated by this program.

Some deviations from the sampling frequency may be necessary due to seasonal unavailability, 0 \ hazardous conditions, or other legitimate reasons. Efforts are made to obtain all required samples X MCI

¢within the required time frame. Any deviation(s) in sampling frequency or location is documented In the Annual Radiological Environmental Operating Report.

REMP sampling locations that use meteorological sectors and or distance from the plant site were verified as described in reference 11.28.

Sarnpling, reporting, and analytical requirements are given in FSAR-SP TABLES 16.11-7, 16.114, and 16.11-9.

Airborne, waterborne, direct radiation, and ingestion samples collected under the monitoring program are analyzed by an independent, third-party laboratory. With the exception of direct radiation, the laboratory is required to participate in an Interlaboratory Analyses Program as per Reg. Guide 4.15 (REF 11.14.14). The laboratory participates in an Interlaboratory crosscheck program administered by Environmental Resources Associates (ERA), Mixed Analyte Performance Evaluation Program (MAPEP), or equivalent program. This participation includes all of the determinations (sample median - radionuclide combination) that are both offered by ERA and/or MAPEP and included in the environmental monitoring program.

5.2 PERFORMANCE TESTING OF ENVIRONMENTAL THERMOLUMINESCENCE DOSIMETERS Thermoluminescence Detectors (TLD's) used in the Radiological Environmental Monitoring Program are tested for accuracy and precision to demonstrate compliance with Regulatory Guide 4.13 (Ref. 11.16).

6 DETERMINATION OF ANNUAL AVERAGE AND SHORT TERM ATMOSPHERIC DISPERSION PARAMETERS 6.1 ATMOSPHERIC DISPERSION PARAMETERS The values presented in Table 6.1 and Table 6.2 were determined through the analysis of on-site meteorological data collected during the three year period of May 4, 1973 to May 5, 1975 and March 16, 1978 to March 16, 1979.

6.1.1 LONG-TERM DISPERSION ESTIMATES The variable trajectory plume segment atmospheric transport model MESODIF-Il (NUREG/-CR-0523) and the straight-line Gaussian dispersion model XOQDOQ (NUREG/CR2919) were used for determination of the long-term atmospheric dispersion parameters. A more detailed discussion of the methodology and data utilized to calculate these parameters can be found elsewhere (Ref. 11.6.12).

The Unit Vent and Radwaste Building Vent releases are at elevations of 66.5 meters and 20 meters above grade, respectively. Both release points are within the building wake of the structures on which they are located, and the unit Vent is equipped with a rain cover which effectively eliminates the possibility of the exit velocity exceeding five times the horizontal wind speed. All gaseous releases are thus considered to be ground-level releases, and therefore no mixed mode or elevated release dispersion parameters were determined (Ref. 115.2).

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APA-ZZ-01003 Rev. 016 6.1.2 DETERMINATION OF LONG-TERM DISPERSION ESTIMATES FOR SPECIAL RECEPTOR LOCATIONS Calculations utilizing the PUFF model were performed for 22 standard distances to obtain the desired dispersion parameters. Dispersion parameters at the SITE BOUNDARY and at special receptor locations were estimated by logarithmic interpolation according to (Ref. 11.6.13):

X = XI dlc (6.1)

Wherey B= In(X2 /X1)lln (d/Cl,).

Xl, X2 = Atmospheric dispersion parameters at distance dl and d2 , respectively, from the source.

The distances dl and d2 were selected such that they satisfy the relationship.

d <d<d2 6.1.3 SHORT TERM DISPERSION ESTIMATES Airborne releases are classified as short term if they are less than or equal to 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> during a calendar year and not more than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> in any quarter. Short term dispersion estimates are detennined by multiplying the appropriate long term dispersion estimate by a correction factor (Ref. 11.9.1 and 11.15.1):

F =(T l/Ta.) (6.2)

Where:

Ts The total number of hours of the short term release.

Ta = The total number of hours in the data collection period from which the long term diffusion estimate was determined (Refer to Section 6.1).

Values of the slope factor (S), are presented in Table 6.3.

Short term dispersion estimates are not applicable to short term releases which are sufficiently random in both time of day and duration (e.g., the short term release periods are not dependent solely on atmospheric conditions or time of day) to be represented by the annual average dispersion conditions (Ref. 11.8.1).

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APA-ZZ-01003 Rev. 016 6.1.3.1 The Determination of the Slope Factor (S)

The general approach employed by subroutine PURGE of XOQDOQ (Ref. 11.15.1) was utilized to produce values of the slope of the (X/Q) curves for both the Radwaste Building Vent and the Unit Vent. However, instead of using approximation procedures to produce the 15 percentile (X/Q) values, the 15 percentile (X/Q) value for each release and at each location was determined by ranking all the 1-hour((X/Q) 1 ) values for that release and at that location in descending order.

The (X/Q)l value which corresponded to the 15 percentile of all the calculated (X/Q) values within a sector was extracted for use in the intermittent release (X/Q) calculation.

The intermittent release (X/Q) curve was constructed using the calculated 15 percentile (X/QOJ and its corresponding annual average (X/Q)aw A graphic representation of how the computational procedure works is illustrated by Figure 4.8 of reference 11.15.1. The straight line connecting these points represents (X/Q)l values for intermittent releases, ranging in duration from one hour to 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />. The slope (S) of the curve is expressed as:

-log ((X/Q), /(X/Q)a) (6.3) log (Ta IT 1 )

or S= 4lo /), -Iog [X/0)') (6.4) log Ta - log T1 6.1.4 Atmospheric Dispersion Parameters for Farminp Areas within the SITE BOUNDARY The dispersion parameters for farming areas within the SITE BOUNDARY are intended for a narrow scope application: That of calculating the dose to the current farmer from gaseous effluents while he conducts farming activities within the SITE BOUNDARY.

For the purpose of these calculations, it was assumed that all of the farmners time, approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year, is spent on croplands within the SITE BOUNDARY. and that his time is divided evenly over all of the croplands. Fractional acreage/time - weighted dispersion parameters were calculated for each plot as described in reference 11.5.6. The weighted dispersion parameters for each plot were then summed (according to type) in order to produce a composite value of the dispersion parameters which are presented in Tables 6.1 and 6.2. These dispersion parameters therefore represent the distributed activities of the farmer within the SITE BOUNDARY and his estimated occupancy period.

6.2 ANNUAL METEOROLOGICAL DATA PROCESSING The annual atmospheric dispersion parameters utilized in the calculation of doses for demonstration of compliance with the numerical dose objectives of 10 C1R 50, Appendix I, are determined using computer codes and models consistent with XOQDOQ (Ref. 11.15). These codes have been validated and verified by a qualified meteorologist prior to implementation.

Multiple sensors are utilized to ensure 90% valid data recovery for the wind speed, wind direction, and ambient air temperature parameters as required by Regulatory Guide 1.23. The selection hierarchy is presented in Table 6.5.

The vertical height of the highest adjacent building (V) used to perform concurrent year annual average atmospheric dispersion (XIQ) calculations is 169.16 meters (Ref. 11.29).

Meteorological Data is periodically verified to ensure valid data is being collected. Health Physics is responsible to ensure this review is performed.

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(

APA-ZZ- 01003 Rev. 016 TABLE 6.1 HIGHEST ANNUAL AVERAGE ATMOSPHERIC DISPERSION PARAMETERS UNIT VENT:

DISTANCE X/Q X/Q LOCATION (b) SECTOR (METERS) X/Q DECAYED/ DECAYED/ D/Q UNDEPLETED DEPLETED (sec/rn) (sec/m ) (sec/rn) (mi)

SITE BOUNDARY(a) NNW 2200 1.OE-6 9.9B-7 8.5E-7 4.3E-9 Nearest Residence (c) (d) NNW 2897 6.7E-7 6.6E-7 5.6E7 2.6E-9 Farmer's Residence(c) (f) NNW 2897 6.7E-7 6.6E-7 5.6E-7 2.6E-9 Farming Areas within the N/A N/A 2.6E-7 2,6E.7 2.4E-7 - 1.3E-9 Site Boundary (c) (e)

(a) Values given are from PSAR-SA TABLE 23-82 (b) Data from 2002 Land Use Census co I

(c) Values derived from FSAR.SA TABLE 2.3-83, using the methodology presented in Equation (6.1) (Ref. 11.5.6) cc X

(d) All pathways are assumed to exist at the location of the nearest resident.

U-,

(e) These values were derived for a narrow scope application. Extreme caution should be exercised when determining their suitability for use in other applications.

I-J CD (f) In 2002, the Farmer moved to a new location directly across the street from the nearest resident. For conversatism, the same dispersion 0a parameters are used.

0 Building Shape Parameter (C) 0.5 (Ref. 11.5.3) CD C,,

Vertical Height of Highest Adjacent Building (V) = 66.45 meters (Ref. 11.5.3)

CO a

52 0 0

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APA-ZZ-01003 Rev. 016 TABLE 6.3 SHORT DISPERSION PARAMETERS (a) (c)

Slope Factor(s)

Location (b) Sector Distance Unit Vent Radwaste Building Vent Site Boundary S 1300 -.328 -.320 Nearest Residence (d) NNW 2897 -.264 -.268 (a) Reference 11.5.3 (b) Data from 1998 Land Use Census (c) Recirculation Factor = 1.0 (d) All pathways are assumed to exist at the location of the nearest resident.

54

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AD co cq 0

0 APA-2Z-01003 a~

Rev. 016 0E TABLE 6.4 APPLICATION OF ATMOSPHERIC DISPERSION PARAMETERS Dose Pathway Dispersion Parameter Controlling A&eCQuj .12 Controlling Location Noble Gas, X/Q, decayed/undepleted N/A 16.11.2.2 Site Boundary Beta Air & Gamma Air (2.26 day half-life)

Noble Gas, XIQ, decayed/undepleted N/A 16.1 1.2.1 Site Boundary Total Body & Skin (2.26 day half-life)

Inhalation X/Q, decayed/depleted Child 16.11.2.1 Nearest Resident (8 day half-life) 16.11.2.3 Site Boundary Ground Plane Deposition D/Q MA 16.11.2.3 - Nearest Resident Ingestion pathways D/Q* Child 16.11.2.3 Nearest Resident

• For H-3, X/Q, decayed/depleted is used instead of D/Q (Ref. I1.1.1).

to Cr z

FAI cV U,

co 0

c'J 0

S..

0 CA co, 55 0 z

CD, 0

z

APA-ZZ-01003 Rev. 016 TABLE 6.5 METEOROLOGICAL DATA SELECTION HIEARCHY Parameter Primary First Second Third Alternate Alternate Alternate Wind Speed lOm Pri lOn Sec 60mPri 90m Pri Wind Direction lOin Pri lOm1 Sec 60m Pri 90m Pri Air Temperature lOm Pri lOm Sec Wind Variability lOn Pri l0in Sec 60m Pri 90m Pni Temp Different 60-lin Pri 90-lOm Pri 90-60 Pri Dew Point lOm Pri Precipitation Im Pri (a) Pni indicates primary tower (b) Sec indicates secondary tower 56 IRKING COPY ISSUED ON 3/8/2006 @ 11:52 AM HRS APA-ZZ-OtO03 (016)

APA-ZZ-01003 G) Rev. 016 C,

0 Z-5 C,,

C m Table Q.6 0

z ADnlcatLOn of Atmospheric Disversion Parameters: Radloactive Effluent Release Renort 0~

120 Dose Pathway - l soerslon Parameter" Conftrolling Di*6MmiValues Controlling Location 0

0)

Noble Gas, X/Q, decayed/undepleted N/A Concurrent Site Boundary Beta Air & Gamma Air Dose (2.26 day half-life) Nearest Resident Noble Gas, X/Q, decayed/undepleted N/A Concurrent Site Boundary C, Total Body & Skin Dose (2.26 day half-life) Nearest Resident Concurrent Farmer's Residence Historical Inside Site Boundary Ground Plane Deposition Dose D/Q N/A Concurrent Site Boundary Nearest Resident Concurrent Farmer's Residence

_Historical Inside Site Boundary Inhalation Dose X/Q. decayed/depleted Child Concurrent Site Boundary (8 day half-life) Nearest Resident Adult Concurrent Farmer's Residence Historical Inside Site Boundary Ingestion Dose Pathways DIQ* Child Concurrent Site Boundary Nearest Resident Adult Concurrent Farmer's Residence Historical InsideSite Boundary

• For H-3, X/Q, decayed/depleted is used instead of D/Q (Ref. 11.11.1).

57 0

8

-8C' 0s

APA-ZZ-01003 Rev. 016 7 REPORTING REQUIREMENTS 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The reporting requirements for the Annual Radiological Environmental Operating Report (AREOR) have been relocated to FSAR-SP 16.11.5.1.

7.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The reporting requirements for the Annual Radioactive Effluent Release Report (ARERR) have been relocated to FSA*-SP 16.11.5.7. The application of atmospheric dispersion parameters in the report is presented in Table 6.6.

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APA-ZZ-01003 Rev. 016 IMPLEMENTATION OF ODCM METHODOLOGY (COMN 2791)

The ODCM provides the mathematical relationships used to implement the Radioactive Effluent Controls. For routine effluent release and dose assessment, computer codes are utilized to implement the ODCM methodologies. These codes are evaluated in accordance with the requirements of plant operating procedures to ensure that they produce results consistent with the methodologies presented in the ODCM. Plant procedures implement the ODCM methodology.

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APA-ZZ-01003 Rev. 016 9 RADIOACTIVE EFFLUENT CONTROLS (REC)

The Radioactive Effluent Controls have been relocated to FSAR-SP CHAPTER 16.11, "Offsite Dose Calculation Manual Radioactive Effluent Controls". The former ODCM REC numbers appear on each of the RECs in FSAR-SP CHAPTER 16.11, and may be used as a cross-reference between the previous and the current numbering system if necessary.

60-

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6i 4.

APA-ZZ-01003 Rev. 016 10 ADMINISTMATIVE CONTROLS 10.1 MAJOR CHANGES TO LIQUID AND GASEOUS RADWASTE TREATMENT SYSTEMS 10.1.1 Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):

a. A summary of the change MUST be reported to the Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the On-Site Review Committee (ORC). On site documentation MUST contain:

1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50,59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

3) A detailed description of the equipment, components and process involved and the interfaces with other plant systems;

4) 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;

5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto;

6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made,

7) An estimate of the exposure to plant operating personnel as a result of the change; and

8) Documentation of the fact that the change was reviewed and found acceptable by the ORC.

b. Changes to the Radwaste Treatment Systems Shall become effective upon review and approval by the ORC.

10.2 CHANGES TO THE OFFS1TE DOSE CALCULATION MANUAL (ODCM) (COMN 2815) 10.2.1 All changes to the ODCM shall be completed pursuant to T/S AC 5.5.1 and approved as per APA-ZZ-00101, "Preparation, Review, Approval and Control of Procedures".

10.21.1 All changes shall be approved by the ORC prior to implementation.

10.22 Review for each revision of the ODCM must include the Health Physics Department.

10.2.3 A complete and legible copy of each revision of the ODCM that became effective during the last annual period shall be submitted as a part of, or concurrent with that years Radioactive Effluent Release Report pursuant to T/S AC 5.5.1.

I

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APA-ZZ-01003 Rev. 016 II REFERENCES 11.1 Title 10, "Energy", Chapter 1. Code of Federal Regulations, Part 20; U.S. Government Printing Office, Washington, D.C. 20402.

11.1.1 Statements of Consideration, Federal Register, Vol. 56. No. 98, Tuesday, May 21, 1991, Subpart D, page 23374.

11.2 Title 10, 'Energy', Chapter 1, Code of Federal Regulations, Part 50, Appendix I; U.S.

Government Printing Office, Washington, D.C. 20402.

11.2.1 10 CFR 5036 a (b) 11.3 Title 40, "Protection of Environment", Chapter 1, Code of Federal Regulations, Part 190; U.S.

Government Print Office, Washington, D.C 20402.

U.S. Nuclear Regulatory Commission, 'Technical Specifications Callaway Plant, Unit NO. 1"I NUREG-1058 (Rev. 1), October 1984. Section 5A.4I 11.4.

11.5 COMMUNICATIONS 11.5.1 Let NBO-54, D. W. Capone to S. E. Miltenberger, dated January 5,1983; Union Electric Company correspondence.

11.5.2 Letter BLUE 1285, "Callaway Annual Average X/Q and D/Q Values", J. H. Smith (Bechtel Power Corporation), to D. W. Capone (Union Electric Co.), dated February 27,1984.

11.5.3 Letter BLUE 1232, "Callaway Annual Average XIQ Values and "S' Values", J. H.Smith (Bechtel Power Corporation) to D. W. Capone (Union Electric Co.), dated February 9,1984.

11.5.4 Reference Deleted 11.55 Private Communication, H. C. Lindeman & B.F. Holderness, August 6,1986 11.5.6 Calculation 2-67, 'Annual Average Atmospheric Dispersion Parameters", April 1989.

11.6 Union Electric Company Callaway Plant, Unit 1, Final Safety Analysis Report 11.6.1 Section 11.5.2.2.3.1 11.6.2 Section 11.5.2.2.3.4 11.6.3 Section 11.5.2.1.2 11.6.4 Section 11-5.2.2.3.2 11.6.5 Section 11.5.2.2.3.3 11.6.6 Section 11.13.3A 11.6.7 Section 11.2.3.4.3 11.6.8 Section 11.5.2.3.3.1 11.6.9 Section 11.5.2.3.3.2 11.6.10 Section 11.5.2.3.2.3 11.6.11 Section 11.5.2.3.2.2 11.6.12 Section 2.3.5 11.6.13 Section 2.3.5.2.1.2 11.6.14 Section 9.2.6 11.6.15 Section 9.2.7.2.1 11.6.16 Section 6.3.2.2 11.6. 17 Table 11.1-6 11.6.18 Deleted

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APA-ZZ-01003 Rev. 016 11.6.19 Deleted 11.6.20 Deleted 11.6.21 Deleted 11.6.22 Table 2.3-68 11.7 Union Electric Company Callaway Plant Environmental Report, Operating License Stage.

.11.7.1 Table2.1-19 11.7.2 Section 2.1.2.3 11.7.3 Section 2.1.3.3.4 11.7.4 Section 5.2.4.1 11.7.5 Table 2.1-19 11.8 US. Nuclear Regulatory Commission, 1'reparation of Radiological Effiuent Technical Specification forNuclear Power Plants", USNRC NUREG-0133, Washington. D. C. 20555, October 1978.

11.8.1 Pages AA-1 through AA-3 11.8.2 Section 5.3.1.3 11.8.3 Section 4.3 11.8.4 Section 5.3.1.5 11.8.5 Section 5.1.1 11.8.6 Section 5.1.2 11.8.7 Section 5.2.1 11.8.8 Section 5.2.1.1 11.8.9 Section 5.3.1 11.8.10 Section 3.8 11.8.11 Section 3.3 11.9 U.S. Nuclear Regulatory Commission, 'XOQDOQ. Program For the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations". USNRC NUREG-0324, Washington, D. C 20555.

11.9.1 Pages 19-20 Subroutine PURGE 11.10 Regulatory Guide 1.111, "Methods forEstimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from light-Water-Cooled Reactors". Revision 1, U. S.

Nuclear Regulatory Comrission, Washington, D. D. 20555, July, 1977.

11.10.1 Section c.1Lb 11.10.2 Figures 7 through 10 11.10.3 Section c.4 11.11 Regulatory Guide 1.109, 'Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix P",

Revision 1, U. S. Nuclear Regulatory Comnission, Washington, D. C. 20555, October 1977.

11.11.1 Appendix C, Section 3.a 11.11.2 Appendix E, Table E-15 11.11.3 Appendix C,Section I 11.11.4 Appendix E, Table E- II APA-ZZ01 003 (016)

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N%

4 % k APA-ZZ-01003 Rev. 016 11.11.5 Appendix E, Table E-9 11.12 U. S. Nuclear Regulatory Commission, 'Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)", USNRC NUREG-0543, Washington, D.

C. 20555, January 1980.

11.12.1 Section 1,Page 2 11.12.2 Section IV, Page 8 11.12.3 Section IV, Page 9 11.12.4 Section HI, Page 6 11.12.5 Section 111, Page 8 11.13 Management Agreement for the Public Use of Lands, Union Electric Company and the State of Missouri Department of Conservation, December 21,1982 11.13.1 Exhibit A 11.14 MISCELLANEOUS REFERENCES 11.14.1 Drawing Number M-109-0007-06, Revision 5 11.14.2 Callaway Plant Annual Environmental Operating Report (updated annually) 11.14.3 UE Safety Analysis Calculation 87-01-00 11.14A Calculation 22-48, "Calculation of Inhalation and Ingestion Dose Commitment Factors for the Adult and Child", January, 1988 11.14.5 HPCI 89-02, "Calculation of ODCM Dose Comniitment Factors", March, 1989 11.14.6 Deleted 3lot; 11.14. HPCI 87-10, Rev. 1, "Methodology for Calculating the Response of Gross NaI(MI) Monitors to Liquid Effluent Streams", April, 2005 11.14.8 Calculation 2Z-57, "Dose Factors for Eu-154", January, 1989 11.14.9 Calculation 2Z-78, Rev. 2, "ODCM Gaseous Pathway Dose Factors for Adult Age Group",

July, 1992.

G (111.14.10 HPCI 06-01. Rev. 0, "Equipment Hatch Platform and Missile Shield Modification Direct Dose Calculation to the Member of the Public", January, 2006.

11.14.11 Calculation 2Z-250, Rev. 0, "ODCM Gaseous Pathway Dose Factors for Child Age Group and Ground Plane Dose Factors". September, 1992.

11.14.12 UOTH 83-58, "Documentation of ODCM Dose Factors and Parameters", February, 1983.

11.14.13 Calculation HPCI 04-06 (Rev. 1), "Calculation of Liquid Effluent Dose Commitment Factors (A,,) for the Adult Age Group", November, 2004.

l 11.14.14 Regulatory Guide 4.15, 'Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment" (Revision 1), February 1979; USNRC, Washington, D. C. 20555 11.15 U. S. Nuclear Regulatory Commission, "XOQDOQ Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations", USNRC NUREG/CR-2919, September 1982, Washington, D. C. 20555 11.15.1 Section 4, "Subroutine PURGE", pages 27 and 28 11.16 Regulatory Guide 4.13, "Performance, Testing, and procedural specifications for Thermoluminiscence Dosimetry: Environmental Applications "(Revision 1), July 1977; USNRC, Washington, D. C. 20555 11.17 TID-7004, "Reactor Shielding Design Manual", Rockwell, Theodore, Ed; March 1956.

11.18 MICROSHIELD, Grove Engineering Inc.

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7-APA-ZZ-01003 Rev. 016 HPCI 05-09, "Radiological Environmental Monitoring Program (REMP) calculation of direct

,~411.19 dose from RAM storage at Stores II".

11.20 HPCI 05-10, "Radiological Environmental Monitoring Program (REM?) calculation of direct dose from RAM storage in the Radwaste Yard".

11.21 ANSI N13.10-1974, 'Specification & Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents"; September, 1974 11.22 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 Offisite Dose Calculation Manual or Process Control Program", January 1989 11.23 NRC Answers to 10 CFR 20 Implementation Questions 11.23.1 Letter, F. J. Congel to J. F. Schmidt, dated December 9, 1991.

11.23.2 Internal USNRC memo, F. J. Congel to V. L. Miller, et al, dated April 17, 1992.

11.23.3 Letter, F. J. Congel to J. F. Schmidt, dated April 23, 1992.

11.23.4 Letter, F. J. Congel to 1.F. Schmidt, dated September 14, 1992.

11.23.5 Letter, F. J. Congel to J. F. Schmidt, dated June 8, 1993.

11.24 USNRC Inspection Report 50.483/92002(DRSS) Section 5, page 5.

11.25 HPCI 96-005, "Calculation of Maximum Background Value for HB-RE-18".

11.26 EGG-PHY-9703, "Technical Evaluation Report for the evaluation of ODCM Revision 0 (May, 1990) Callaway Plant, Unit 1" transmitted via letter, Samual J. Collins (USNRC) to D. F.

Schnell (UE), dated July 12, 1996.

11.27 HPCI 99-005, "Calculation of Setpoint for GL-RE-202".

11.28 HPCI 99-001, "Documentation of REMP Procedure Changes".

11.29 "Technical Specifications for Callaway Plant Meteorological Data Software k.

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