ML18121A155

Three Miles Island, Units 1 and 2, Combined 2017 Annual Radioactive Effluent Release Report - ODCM Change for TMI Offsite Dose Calculation Manual, Revision 5, CY-TM-170-300

ML18121A155
Person / Time
Site:	Three Mile Island
Issue date:	04/30/2018
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
References
TMl-18-025 CY-TM-170-300, Rev 5
Download: ML18121A155 (232)

Text

{{#Wiki_filter:2017 Annual Radioactive Effluent Release Report for TMI Enclosure 1 -Page 1 of 1 ODCM Change for TMI Offsite Dose Calculation Manual, Revision 5 CY-TM-170-300 (Revision 5 approved in 2017 and issued on December 8, 2017) Document Site Approval Form Page 1 of 2 AD-AA-101

• F-01 Revision 7 Sas AD-AA-101 for the procedural requirements associated with this Form. I Facility:

TMI Desktop Instruction avallable an Intranet or thrauah AD functional area. Document Number: CY-TM-170-300 Revision: 5 Title: Offsite Dose Calculation Manual (ODCM) Superseded Documents: NIA l'8l or List: If superseding document(s) containing commitments, then PROCESS commitment change per LS-AA-110. Environmental Review Applicability-Is an Environmental Review applicable per EN-AA-103? No l'8] or Yes L.J If Yes, then attach Environmental Review documentation required per EN-AA-103. Is this a Fleet Standard Document being processed with form AD-AA-101-F-09? No 181 or Yes D If yes, then h h D AA k' h ' attac t e comp1 eted orm A --101-F-09, s *1p t e fo/lowmg

section, and go to Continuation A. Batch -Are multiple document creations/revisions/cancelations being Issued to add/revise/cancel them for similar requirements?

No !81 or Yes D If Yes, then identifvthe hi!:ihest level Document and Issue Type below. Check onl'.J! one Document T~ee: Check onl~ one Issue T)lE!e: lncoreorated Site Items (EC1 AR1 Level 1 -Continuous Use Procedure D NewD PCR1 etc}: Level 2-Reference Use Procedure 0 Revision t8I IA 2665375-49 Level 3 -Information Use Procedure [8) Cancel/Supersede Document D NER-NC-17-001 T&RMD Cancel Revision D Non-Permanent D FormO CancelNon-Permanent[J OtherD Editorial Revision D Revision Summary: See attached Summarv Matrix (Attach additional description if required) CONFIRM that~ commitments (i.e., those steps annotated with CM-X) have been changed or deleted unless evaluated via completion of LS-M-11 O commitment change/deletion form and INITIAL [Preparer]: LKW Preparer L.K.Weber 10/18/17 8947 Print Date Extension Validation -Is validation required per AD-M-101? No QSJ or Yes 0 If Yes, then attach completed AD-AA-101-F-03. Consequence Risk Factors-ls a Risk Assessment required per HU-AA-1212 applicability (e.g. design changes, equipment operating procedures)? No [8) or Yes D If Hiah or Medium Risk Factors exist, the orocedure validallon Is reauired oer AD*AA-101-F-03 NOS Review -Excluding NOE, ISi, Peer Inspection or Independent Verification, is this document used to perform independent inspection for acceptance (including field installation inspections, fabrication inspections, receipt inspections, new fuel inspection, etc.), or tor certification of Inspection personnel? No [8J or Yes D If Yes, then NOS Reviewer to print name & sign for acceptance: C~ntinuation A -Is this a T&RM, Form, or Editorial Revision? No or Yes LJ If yes, then skip the following section and o Continuation B. Impact on Operating and Design Margins -NIA t8J or explain: Attach additional desert lion if re ulred 181 No O Yes 1 OCFRS0.59 Applicable? t8J No O Yes 1 OCFR72.48 Applicable? Tracking Number: -----------11 D No 181 Yes Other Regulatory Process Applicable? Other Regulatory Process Number: CY-AA-170-3100 t8J No D Yes Potential security impact per SY-AA-S00-1277 It Yes, then Security Reviewer acceptance documented by cross discipline review below t8I No D Yes Surveillance Coordinator Review Required? Cross Discipline Reviews: (list below) 4re "r I ,,.1 or\ SOR Approval indicates that all required Cross-Disciplinary revie procedure is technically and func

• all ccurate for all function SQR Approval:

, "e/~~ It Yes, then Surveillance Coordinator/Predefine Reviewer acceptance documented by cross discipline review below 11/1 /,2017 GPU Cog. Officer Oare lf/2-/1'7 Dale Discipline Document Site Approval Form Page 2 of 2 AD-AA-101-F-01 Revision 7 Continuation B -Is this a T&RM, or Form? No [81 or Yes D If yes, then skip the following section and go Continuation C. PORC Required: D No [8] Yes Date es D If yes, then skip the following section and go to Applicable Site Contact/Site Change Agents (SME): D. Brookhart -Responsible for Change Management information in [81 this form or D HU-AA-1101 Checklist (attached) -Responsible to shepherd the document through site review, approval/authorization, and implementation. Affected Functional Area(s) or Individuals: Print Signature Date Affected FA Print Signature Date Affected FA Print Signature Dale Affected FA Attach additional if req'd Resources needed to Implement Change: LOE (Only list, if other than Level of Effort.) For ongoing impacts, estimate number of Full Time Equivalents (FTE). If additional resources are needed go to HU-AA-1101. Communication Plan: N/A (e.g., e-mail, Site Paper, Supervisor

Briefing, Voice Mail, etc.) Training Required

/ Qualifications affected: [81 No 0 Yes If yes, list: __ (e.g., Supervisory

Briefing, Tailgate

Briefing, Required

Reading, Formal Training, recertification etc.) Update to information infrastructure (e.g. PassPort, PIMS, EDMS workflows, etc.) required to support implementation (including updated forms loaded into PassPort):

N/A Controlled Document distribution (ref. RM-AA-102) or Records Retention Schedule (ref. RM-AA-101-1004) impacted: IZ! No D Yes If yes, describe change and list Records Management Person contacted: __ Continuation D -If all procedurally required activities associated with this document revision have been completed and the document is ready for implementation, then SFAM to print name, sign & date for authorization to implement. Provide implementation date or, if the Implementation Date is blank or NIA then implementation will be upon the issuance by Records Management per RM requirements. Authorization below indicates the SFAM or a designee of the SFAM has verified the document does not alter or negatively impact compliance with regulatory requirements or station commitments. Is this a non-permanent site specific revision to a fleet standard procedure or T&RM or Form? No [81 or Yes D If yes, then CFAM approval must been obtained. Is this a site specific revision that deviates from fleet standard procedure or T&RM or Form requirements? No [81 or Yes D If yes, then CFAM approval must been obtained. CFAM Authorization when required: _N_/A ___________________ _ Site Authorization: . I U\.-,. SRRS Number 1B.100 Interim Chg#: N/A N/A lmpl. Date Exp. Date 50.59 REVIEW COVERSHEET FORM Station/Unit(s): --=T=M=I=------------- LS-AA-104-1001 Revision 4 Page l of2 Activity/Document Number: Title: Offsite Dose Calculation Manual (ODCM) Revision Number: ~5 ____ _ NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2). Description of Activity: (Provide a brief, concise description of what the proposed activity involves.) The ODCM is being revised to remove plant shutdown statements from the ODCM as directed by NER -NC-17-001, and to replace the shutdown statements related to primary secondary leakrate with a reference to the corporate procedure CY-AA-120-340 which implements the EPRI Primary to Secondary Leakrate (PSLR) guidelines. Reason for Activity: (Discuss why the proposed activity is being performed.) NUREG 1303-Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, Table 3.3-13 for Condenser evacuation systems requires one noble gas activity operable channel or take the action to perform grab samples every 12 hours. The EPRI SGMP-PWR PSLR guidelines (1022832)- do not require any additional actions beside compensatory sampling for only the condenser offgas monitor being out of service. Plant shutdown requirements are based on the amount of PSLR not whether the rad monitor is operable. Effect of Activity: (Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.) None. The ODCM will continue to describe the compensatory sampling actions required when the condenser offgas noble gas monitor is not operable. The ODCM and Tech Spec 6.8.4.a will continue to require operability of the rad monitor and the 30 day ODCM timeclock for a not operable offgas noble gas monitor. Requirements to report in the NRC annual report why the inoperability was not corrected in a timely manner ( <30 days) will remain unchanged. Summary of Conclusion for the Activity's 50.59 Review: (Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment

Request, as applicable, is not required.)

Per Technical Specification 6.14, ODCM changes do not require pre-NRC approval, but they do require submittal with the next annual Radiological Effluents Report to the NRC, proper justification and appropriate cross-disciplinary, RTR/SQR and PORC review. Attachments: Attach all 50.59 Review forms completed, as appropriate. Forms Attached: (Check all that apply.) [8J Applicability Review D D 50.59 Screening 50.59 Evaluation 50.59 Screening No. 50.59 Evaluation No. Rev. Rev. 50.59 APPLICABILITY REVIEW FORM LS-AA-104-1002 Revision 6 Page 1 of2 Activity/Document Number: CY-TM-170-300 Revision Number: s Title: TMI Offsite Dose Calculation Manual (ODCM) Address the questions below for all aspects of the Activity. If the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity. Note that it is not unusual to have more than one process apply to a given Activity. See Section 4 of the Resource Manual (RM) for additional guidance. I. Does the proposed Activity involve a change: I. Technical Specifications or Facility Operating License (IOCFR50.90)? [g]NO DYES See Section 4.2.1.1 of the RM 2. Conditions of License Quality Assurance program (IOCFRS0.54(a))? (g] NO DYES See Section 4.2.1.2 of the RM Security Plan (10CFR50.54(p))? (g]NO DYES Emergency Plan (IOCFR50.54(q))? (g]NO DYES 3. Codes and Standards IST Program Plan (10CFR50.55a(f))? (g]NO DYES See Section 4.2.1.3 of the RM ISi Program Plan (IOCFRS0.55a(g))? (g]NO DYES 4. ECCS Acceptance Criteria (I OCFR50.46)? (g] NO DYES See Section 4.2.1.4 of the RM 5. Specific Exemptions (IOCFR50.12)? (g] NO DYES See Section 4.2.1.S of the RM 6. Radiation Protection Program ( I OCFR20)? [g] NO DYES See Section 4.2.1.6 of the RM 7. Fire Protection Program (applicable UFSAR or operating license (g]NO DYES See Section 4.2.1.7 of the RM condition)?

8. Programs controlled by the Operating License or the Technical ONO (g] YES See Section 4.2.1.7 of the R.J.\1 Specifications (such as the ODCM). 9. Environmental Protection Program (g] NO DYES See Section 4.2.1. 7 of the RM I 0 Diverse and Fkxihk Coping Stratel!ies (FLEX! and Spent Fud P,101 (g] l'\O DYES See Section ct.2.1.7 01* 1he RM Instrumentation Program.

-WU. Other programs controlled by other regulations. (g] NO DYES See Section 4.2.1 of the RM II. Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting (g] NO DYES See Section 4.2.2 of the RM maintenance that will be in effect during at-power operations for 90 days or less? III. Does the proposed Activity involve a change to the: I. UFSAR (including documents incorporated by reference) that is limited to reformatting, simplification, removing excessive detail, or minor [g] NO DYES See Section 4.2.3 of the RM editorial changes as discussed in NEI 96-07 or NEI 98-03? 2. Managerial or administrative proc~dures governing the conduct of (g] NO DYES See Section 4.2.4 of the R.J.\1 facility operations (subject to the control of 10CFR50, Appendix B) 3. Procedures for performing maintenance activities (subject to 10CFR50, [g] NO DYES See Section 4.2.4 of the RM Appendix B )? 4. Regulatory commitment as defined by NEI 99-04 that is outside the scope of 10 CFR 50.59, i.e., the commitment does not involve the facility or a procedure as described in the UFSAR pursuant to 10 CFR (g] NO DYES See Section 4.2.3/4.2.4 of the R.J.\1 50.59, the commitment change does not meet the criteria for a change pursuant to 10 CFR 50.59, and the commitment is not otherwise mandated by the NRC to require a 50.59 review? IV. Does the proposed Activity involve a change to the Independent Spent Fuel (g] NO DYES See Section 4.2.6 of the R.J.\1 Storage Installation (ISFSI) (subject to control by 10 CFR 72.48) tern (old) Rev. (new) Rev. No. 4 page No. 5 page No. 1 23 23 2 28 28 3 29 29 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 ATTACHMENT 1 ODCM Change Summary Matrix a~e 0 P 1 f 1 CY-AA-170-3100 Revision 6 Page 1 *of 1 Determination Description of Change Identifier A Remove reference to obsolete Amergen letter #5928-06-20449 A Remove 'for up to 14 days' from Action 32, paragraph

1. A Remove plant shutdown statements and refer to PSLR guidance ATTACHMENT 2 ODCM Change Determination Station:

____________ T~h~r~ee~M=il~e~ls~l=an~d~-- CY-AA-170-3100 Revision 6 Page 1 of 3 Page _1,____ of --=3'--ODCM Revision No. 5 Determination No. A ----=-.,___ ____ _ I. Determination Questions (Check correct response)

1. Does the ODCM change maintain the level of radioactive effluent control required by 1 OCFR20.1301?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 1 O CFR 20.1301 (a)(1) requires that each licensee conduct operations so that the total effective dose equivalent to individual members of the public from TMI operation does not exceed 100 mrem in one year. Removing plant shutdown statements and following EPRI Primary to Secondary Leakrate (PSLR) guidelines will not increase the dose to the public or reduce TM l's ability to control or quantify releases.

2. Does the ODCM change maintain the level of radioactive effluent control required by 1 OCFR20.1302?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 10 CFR 20.1302 requires licensees to perform appropriate surveys in unrestricted areas and controlled areas to demonstrate compliance with dose limits for individual members of the public. The ability to perform surveys is not impacted by removing plant shutdown statements and following EPRI PSLR guidelines. Effluent concentration limits will not be impacted by these changes. TMI will still control its effluent paths to ensure dose to the public is ALARA. 3. Does the ODCM change maintain the level of radioactive effluent control required by 40CFR190 and 10CFR72.104? Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 1OCFR72.104 has requirements for Independent Spent Fuel Storage Installations (ISFSI) and Monitored Retrievable Storage (MRS) which is not applicable at TMI. 40CFR190 requires tharthe annual dose equivalent does not exceed 25 mrem to the whole body, 75 mrem to the thyroid and 25 mrem to any other organ of any member of the public as a result of exposure to planned discharges of radioactive materials to the environment from uranium fuel cycle operations. Removing plant shutdown statements and following EPRI PSLR guidelines will not increase discharges of radioactive materials nor will they negatively impact TMl's ability to control or quantify radioactive releases to the environment. __x_ YES NO __x_ YES NO _x_ YES NO ATTACHMENT 2 ODCM Change Determination

4. Does the ODCM change maintain the level of radioactive effluent control required by 1 OCFR50.36a?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 1 OCFR 50.36a requires that operating procedures be developed and followed for the control of effluents and that the radioactive waste system be maintained and used. It also specifies that each licensee shall submit a report annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous 12 months. These requirements will keep average annual releases of radioactive material in effluents and their resultant committed effective dose equivalents (CEDE) at small percentages of the dose limits. Operation of the rad waste system is not affected by these changes. The operation of the plant releasing and monitoring the effluents from the plant will not be impacted by removing plant shutdown statements or following EPRI PSLR guidelines. The revision will not impact the annual reporting of radiological effluents to the NRC. 5. Does the ODCM change maintain the level of radioactive effluent control required by Appendix I to 1 OCFR50? Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 1 OCFR50 Appendix I,, Section II.A establishes the design objectives and limiting conditions for operation to meet ALARA criteria such that the calculated annual total quantity of all radioactive material above background released to unrestricted areas will not result in an estimated annual dose or dose commitment from liquid effluents in excess of 3 mrems to the total body or 10 mrems to any organ. For gaseous effluents the estimated annual air dose can not exceed 1 O mrems for gamma radiation and 20 mrems for beta radiation. Section Ill establishes that implementation of Section II be demonstrated by calculational procedures based upon models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated and that the cumulative effect of all sources and pathways being influenced by the plant be considered. Section IV provides guides on limiting conditions for operation. The licensee shall establish appropriate surveillance and monitoring programs for reporting of rad effluents data, environmental monitoring data and resulting radiation doses and changes in the use of unrestricted areas surrounding the plant. If releases of effluents result in exceeding one-half the annual exposure, there are investigative and reporting requirements. Removing plant shutdown statements and following EPRI PSLR guidelines will not adversely impact ODCM calculations or methodologies for evaluating doses to individuals from principal pathways of exposure. CY-AA-170-3100 Revision 6 Page 2 of 3 ...x_ YES NO ...x_ YES NO ATTACHMENT 2 ODCM Change Determination

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

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) Removing plant shutdown statements and following EPRI PSLR guidelines will not impact the accuracy or reliability of effluent, dose, or setpoint calculations. There are no setpoint calculation changes for effluent monitors associated with this ODCM revision. CY-AA-170-3100 Revision 6 Page 3 of 3 ..JL YES NO 7. Does the ODCM change maintain the accuracy of radioactive effluent control ..lL YES NO required by the SAR? Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) Chapter 11 of the UFSAR, specifically sections 11.2.4 and 11.4.3, were reviewed to determine that these ODCM changes will not impact the accuracy of radioactive effluent control required by the SAR. As stated before removing plant shutdown statements and following EPRI PSLR guidelines does not change the release paths of effluents to the environment or any ability to control or calculate doses via these pathways. II. If all questions are answered YES, then complete the ODCM Change Determination and implement the Change per this procedure. Ill. If any question is answered NO, then a change to the ODCM is not permitted IV. Review and Approval: Date Exelon Generation CY-TM-170-300 Revision 5 Page 1 of 222 Level 3 -Information Use OFFSITE DOSE CALCULATION MANUAL (ODCM) INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the Three Mile Island Nuclear Station (TMI) Unit 1 and Unit 2 PDMS Technical Specifications and implements TMI radiological effluent controls. The ODCM contains the controls, bases, and surveillance requirements for liquid and gaseous radiological effluents. In addition, the ODCM describes the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents. This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm/trip set points. Liquid and Gaseous Radwaste Treatment System configurations are also included. The ODCM also is used to define the requirements for the TMI radiological environmental monitoring program (REMP) and contains a list and graphical description of the specific sample locations used in the REMP. The ODCM is maintained at the Three Mile Island (TMI) site for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM to ensure the ODCM represents the present methodology in all applicable areas. Changes to the ODCM will be implemented in accordance with the TMl-1 and TMl-2 PDMS Technical Specifications. The ODCM follows the methodology and models suggested by NUREG-0133, and Regulatory Guide 1.109, Revision 1 for calculation of off-site doses due to plant effluent releases. TMI implements the TMI Radiological Effluent Controls Program and Regulatory Guide 1.21, Revision 1 (Annual Radioactive Effluent Release Report) requirements by use of a computerized system used to determine TMI effluent releases and to update cumulative effluent doses. TABLE OF CONTENTS PARTI TMl-1 RADIOLOGICAL EFFLUENT CONTROLS Section 1.0 DEFINITIONS CY-TM-170-300 Revision 5 Page 2 of 222 13 Table 1-1, Frequency Notation 18 Map1 .1, Gaseous Effluent Release Points and Liquid Effluent Outfall Locations 19 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation Table 2.1-1, Radioactive Liquid Effluent Instrumentation 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring 20 20 20 22 23 Instrumentation 24 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.2 Gaseous Effluent Controls 2.2.3 Total Radioactive Effluent Controls 3.0 SURVEILLANCES 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation Table 3.1-1, Radioactive Liquid Effluent Monitoring Instrumentation 30 30 34 41 44 44 44 Surveillance Requirements 45 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 47 Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 48 PARTI Section TABLE OF CONTENTS (Cont'd) TMl-1 RADIOLOGICAL EFFLUENT CONTROLS 3.2 Radiological Effluents 3.2.1 Liquid Effluents CY* TM-170-300 Revision 5 Page 3 of 222 Page 53 53 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 55 3.2.2 Gaseous Effluents 58 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 60 3.2.3 Total Radioactive Effluents 4.0 PART I REFERENCES 64 65 PART II Section TABLE OF CONTENTS (Cont'd) TMl-2 RADIOLOGICAL EFFLUENT CONTROLS 1.0 DEFINITIONS Table 1.1, Frequency Notation 2.0 CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluentlnstrumentation 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CY-TM-170-300 Revision 5 Page 4 of 222 67 70 71 71 71 71 Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 73 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.2 Gaseous Effluent Controls 2.2.3 Total Radioactive Effluent Controls 3.0 SURVEILLANCES 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring 74 74 78 85 87 87 87 87 Instrumentation Surveillance Requirements 88 3.2 Radioactive Effluents 89 3.2.1 Liquid Effluents 89 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 90 3.2.2 Gaseous Effluents 91 PART II Section TABLE OF CONTENTS (Cont'd) TMl-2 RADIOLOGICAL EFFLUENT CONTROLS CY-TM-170-300 Revision 5 Page 5-of 222 Page Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 92 3.2.3 Total Radioactive Effluents 95 4.0 PART II REFERENCES 96 TABLE OF CONTENTS (Cont'd) CY-TM-170-300 Revision 5 Page 6 of 222 PART Ill EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section 1.0 LIQUID EFFLUENT MONITORS 98 1.1 TMl-1 and TMl-2 Liquid Radiation Monitor Set Points 98 1.2 TMI Liquid Effluent Release Points and Liquid Radiation Monitor Data 99 1.3 Control of Liquid Releases 101 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liquid Effluents -10 CFR 50 Appendix I 2.2 TMI Liquid Radwaste System Dose Cales Once Per Month 3.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEM 106 106 107 126 3.1 TMl-1 Liquid Effluent Waste Treatment System 126 3.2 Operability of the TMl-1 Liquid Effluent Waste Treatment System 127 3.3 TMl-2 Liquid Effluent Waste Treatment System 127 4.0 GASEOUS EFFLUENT MONITORS 130 4.1 TMl-1 Noble Gas Monitor Set Points 130 4.2 TMl-1 Particulate and Radioiodine Monitor Set Points 132 4.3 TMl-2 Gaseous Radiation Monitor Set Points 133 4.4 TMl-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor D~ 1~ 4.5 TMl-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 136 4.6 Control of Gaseous Effluent Releases 137 TABLE OF CONTENTS (Cont'd) CY-TM-170-300 Revision 5 Page 7 of 222 PART 111 Section EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT

• 5.1 Gaseous Effluents

-Instantaneous Release Limits 5.1.1 Noble Gases 5.1.1.1 Total Body 5.1.1.2 Skin 5.1.2 Iodines, Tritium and Particulates 5.2 Gaseous Effluents -10 CFR 50 Appendix I 5.2.1 Noble Gases 5.2.2 Iodines, Tritium and Particulates 149 149 149 149 150 151 152 152 153 5.3 Gaseous Radioactive System Dose Calculations Once per Month 156 6.0 TMl-1 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 178 6.1 Description of the TMl-1 Gaseous Radwaste Treatment System 178 6.2 Operability of the TMl-1 Gaseous Radwaste Treatment System 178 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitoring Program Requirements 8.2 Land Use Census 8.3 lnterlaboratory Comparison Program 9.0 PART Ill REFERENCES 180 181 181 184 186 204 TABLE OF CONTENTS (Cont'd) CY-TM-170-300 Revision 5 Page 8 of 222 PART Ill EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section TABLES Table 1.1 TMI Liquid Release Point and Liquid Radiation Monitor Data 102 Table 1.2 TMl-2 Sump Capacities 103 Table 2.1 Liquid Dose Conversion Factors (DCF): DFii 109 Table 2.2 Bioaccumulation

Factors, BFi 125 Table 4.1 TM 1-1 Gaseous Release Point and Gaseous Radiation Monitor Data 138 Table 4.2 TMl-2 Gaseous Release Point and Gaseous Radiation Monitor Data 139 Table 4.3 Dose Factors for Noble Gases and Daughters 140 Table 4.4 Atmospheric Dispersion Factors for Three Mile Island -Station Vent 141 Table 4.5 Atmospheric Dispersion Factors for Three Mile Island -Ground Release 142 Table 4.6 Dose Parameters for Radioiodines and Radioactive Particulate In Gaseous Effluents 143 Table 5.2.1 Pathway Dose Factors, Ri -Infant, Inhalation 157 Table 5.2.2 Pathway Dose Factors, Ri -Child, Inhalation Table 5.2.3 Pathway Dose Factors, Ri -Teen, Inhalation Table 5.2.4 Pathway Dose Factors, Ri -Adult, Inhalation Table 5.3.1 Pathway Dose Factors, Ri -All Age Groups, Ground Plane Table 5.4.1 Pathway Dose Factors, Ri -Infant, Grass:..Cow-Milk Table 5.4.2 Pathway Dose Factors, Ri -Child, Grass-Cow-Milk Table 5.4.3 Pathway Dose Factors, Ri -Teen, Grass-Cow-Milk Table 5.4.4 Pathway Dose Factors, Ri -Adult, Grass-Cow-Milk Table 5.5.1 Pathway Dose Factors, Ri -Infant, Grass-Goat-Milk 158 159 160 161 162 163 164 165 166 TABLE OF CONTENTS (Cont'd)

CY-TM-170-300 Revision 5 Page 9 of 222 PART Ill EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section TABLES Table 5.5.2 Pathway Dose Factors, Ri -Child, Grass-Goat-Milk Table 5.5.3 Pathway Dose Factors, Ri -Teen, Grass-Goat-Milk Table 5.5.4 Pathway Dose Factors, Ri -Adult, Grass-Goat-Milk Table 5.6.1 Pathway Dose Factors, Ri -Infant, Grass-Cow-Meat Table 5.6.2 Pathway Dose Factors, Ri -Child, Grass-Cow-Meat Table 5.6.3 Pathway Dose Factors, Ri -Teen, Grass-Cow-Meat Table 5.6.4 Pathway Dose Factors, Ri -Adult, Grass-Cow-Meat Table 5.7.1 Pathway Dose Factors, Ri -Infant, Vegetation Table 5.7.2 Pathway Dose Factors, Ri -Child, Vegetation Table 5.7.3 Pathway Dose Factors, Ri -Teen, Vegetation Table 5.7.4 Pathway Dose Factors, Ri -Adult, Vegetation 167 168 169 170 171 172 173 174 175 176 177 Table 8.1 Sample Collection and Analysis Requirements 187 Table 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 193 Table 8.3 Detection Capabilities for Environmental Sample Analysis 194 Table 8.4 TMINS REMP Station Locations -Air Particulate and Air Iodine 197 Table 8.5 TMINS REMP Station Locations -Direct Radiation 197 Table 8.6 TMINS REMP Station Locations -Surface Water 199 Table 8.7 TMINS REMP Station Locations -Aquatic Sediment 199 Table 8.8 TMINS REMP Station Locations -Milk 200 Table 8.9 TMINS REMP Station Locations -Fish 200 Table 8.10 TMINS REMP Station Locations -Food Products 200 PART Ill Section MAPS MAP 8.1 MAP 8.2 MAP 8.3 FIGURES Figure 1.1 Figure 1.2 Figure 3.1 Figure 3.2 Figure 4.1 Figure 4.2 Figure 4.3 Figure 4.4 Figure 4.5 Figure 6.1 CY-TM-170-300 Revision 5 Page 10 of 222 TABLE OF CONTENTS (Cont'd) EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 1 Mile of the Site Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 5 miles of the Site Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Greater than 5 miles from the Site TMl-1 Liquid Effluent Pathways TMl-2 Liquid Effluent Pathways TMl-1 Liquid Radwaste TMl-1 Liquid Waste Evaporators TMl-1 Gaseous Effluent Pathways TMl-1 Auxiliary and Fuel Handling Buildings Effluent Pathways TMl-1 Reactor Building Effluent Pathway TMl-1 Condenser Offgas Effluent Pathway TMl-2 Gaseous Effluent Filtration System/Pathways Waste Gas System 201 202 203 104 105 128 129 144 145 146 147 148 179 PART IV Section TABLE OF CONTENTS (Cont'd) REPORTING REQUIREMENTS CY-TM-170-300 Revision 5 Page 11 of 222 1.0. TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 207 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 3.0 PART IV REFERENCES APPENDICES A. Pathway Dose Rate Parameter (Pi) B. Inhalation Pathway Dose Factor (Ri) C. Ground Plane Pathway Dose Factor (Ri) D. Grass-Cow-Milk Pathway Dose Factor (Ri) E. Cow-Meat Pathway Dose Factor (Ri) F. Vegetation Pathway Dose Factor (Ri) APPENDIX A -F REFERENCES 208 210 211 212 213

• 214 216 218 219 PARTI TMl-1 RADIOLOGICAL EFFLUENT CONTROLS CY-TM-170-300 Revision 5 Page 12 of 222 CY-TM-170-300 Revision 5 Page 13 of 222 1.0 DEFINITIONS L__ _______ _ The following terms are defined for uniform interpretation of these controls and surveillances.

1.1 Reactor Operating Conditions 1.1.1 Cold Shutdown The reactor is in the cold shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is no more than 200°F. Pressure is defined by Technical Specification 3.1.2. 1.1.2 Hot Shutdown The reactor is in the hot shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is at or greater than 525°F. 1.1.3 Reactor Critical The reactor is critical when the neutron chain reaction is self-sustaining and Keff = 1.0. 1.1.4 Hot Standby The reactor is in the hot standby condition when all of the following conditions exist: a. Tavg is greater than 525°F b. The reactor is critical

c. Indicated neutron power on the power range channels is less than two percent of rated power. Rated power is defined in Technical Specification Definition 1.1. 1.1.5 Power Operation The reactor is in a power operating condition when the indicated neutron power is above two percent of rated power as indicated on the power range channels.

Rated power is defined in Technical Specification Definition 1.1. 1.1.6 Refueling Shutdown CY-TM-170-300 Revision 5 Page 14 of 222 The reactor is in the refueling shutdown condition when, even with all rods removed, the reactor would be subcritical by at least one percent delta k/k and the coolant temperature at the decay heat removal pump suction is no more than 140°F. Pressure is defined by Technical Specification 3.1.2. A refueling shutdown refers to a shutdown to replace or rearrange all or a portion of the fuel assemblies and/or control rods. 1.1. 7

• Refueling Operation An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.

1.1.8 Refueling Interval The time between normal refuelings of the reactor. This is defined as once per 24 months. 1.1.9 Startup The reactor shall be considered in the startup mode when the shutdown margin is reduced with the intent of going critical. 1.1.10 Tave Tave is defined as the arithmetic average of the coolant temperatures in the hot and cold legs of the loop with the greater number of reactor coolant pumps operating; if such a distinction of loops can be made. 1 .1.11 Heatup -Cooldown Mode The heatup-cooldown mode is the range of reactor coolant temperature greater than 200°F and less than 525°F. 1 .2 Operable A system, subsystem, train, component or device, shall be OPERABLE or have OPERABILITY when it is capable of performing it's specified function(s), and when all necessary attendant instrumentation,

controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s),

are also capable of performing their related support function(s). CY-TM-170-300 Revision 5 Page 15 of 222 1.3 Instrument Channel An instrument channel is the combination of sensor, wires, amplifiers, and output devices, which are connected for the purpose of measuring the value of a process variable, for the purpose of observation,

control, and/or protection.

An instrument channel may be either analog or digital. 1.4 Instrumentation Surveillance 1.4.1 Channel Test A CHANNEL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practical to verify OPERABILITY, including alarm and/or trip functions. 1.4.2 Channel Check A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter. 1.4.3 Source Check A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. 1.4.4 Channel Calibration 1.5 Deleted An instrument CHANNEL CALIBRATION is a test, and adjustment (if necessary), to establish that the channel output responds with acceptable range and accuracy to known values of the parameter, which the channel measures, or an accurate simulation of these values. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test. 1.6 Offsite Dose Calculation Manual (ODCM) CY-TM-170-300 Revision 5 Page 16 of 222 The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, 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 (1) the Radiological Effluent

Controls, (2) the Radiological Environmental Monitoring Program and (3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

1. 7 Gaseous Radwaste Treatment The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluent by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

1.8 Ventilation Exhaust Treatment System A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluent by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodine or particulates from the gaseous exhaust system prior to the release to the environment. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEMS. 1.9 Purge -Purging PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature,

pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is required to purify the confinement.

1.10 Venting VENTING is the controlled process of discharging air as gas from a confinement to maintain temperature,

pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is not provided.

Vent used in system name does not imply a VENTING process. 1.11 Member(s) of the Public MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose. 1.12 Site Boundary CY-TM-170-300 Revision 5 Page 17 of 222 The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMl-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile Island and between Three Mile Island and Shelley Island. The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM. 1.13 Frequency Notation The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1-1. All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. The 25% extension applies to all frequency intervals with the exception of "F." No extension is allowed for intervals designated "F." 1.14 Occupational Dose OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under 1 OCFR35.75, from voluntary participation in medical research

programs, or as a member of the public.

Bases Notation s D w M Q S/A R P S/U p N/A (NA) E F Table 1-1 Frequency Notation Frequency CY-TM-170-300 Revision 5 Page 18 of 222 Shiftly (once per 12 hours) Daily (once per 24 hours) Weekly (once per 7 days) Monthly (once per 31 days) Quarterly ( once per 92 days) Semi-Annually (once per 184 days) Refueling Interval (once per 24 months) Prior to each reactor startup, if not done during the previous 7 days Completed prior to each release Not applicable Once per 18 months Not to exceed 24 months Section 1.13 establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are specified to be performed at least once each REFUELING INTERVAL. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed once each REFUELING INTERVAL.

Likewise, it is not the intent that REFUELING INTERVAL surveillances be performed during power operation unless it is consistent with safe plant operation.

The limitation of Section 1.13 is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval. --Map 1.1 Gaseous Effluent Release Points and Liquid Effluent Outfall Locations II c ... c. ** _, --_....__........ t UNIT NO. I S T4C:fli UNIT NO., FUEL HANDLING BLOG £SF VENT STACK D5N003 CY-TM-170-300 Revision 5 Page 19 of 222 ~(tbO. ---;--:~ . -.......... ... ,.. .... _ ... **-.. *-.... -......... ._. ... .. ..., .. i 1 CY* TM-170-300 Revision 5 Page 20 of 222 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation CONTROL: The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.1-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: At all times

• ACTION: a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluent monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels

OPERABLE, take the ACTION shown in Table 2.1-1. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner. * *

• For WDL-FT-84, and RM-L-6, operability is not required when discharges are positively controlled through the closure of WDL-V-257.

For RM-L-12 and associated IWTS/IWFS flow interlocks, operability is not required when discharges are positively controlled through the closure of IW-V-72, 75 and IW-V-280, 281. For SR-FT-146, operability is not required when discharges are positively controlled through the closure of WDL-V-257, IW-V-72, 75 and IW-V-280, 281. BASES CY-TM-170-300 Revision 5 Page 21 of 222 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten times the effluent concentrations of 10 CFR Part 20. Instrument Table 2.1-1 Radioactive Liquid Effluent Instrumentation Minimum Channels Operable CY-TM-170-300 Revision 5 Page 22 of 222 ACTION 1. Gross Radioactivity Monitors Providing Automatic Termination of Release a. b. Unit 1 Liquid Radwaste Effluent Line (RM-L6) IWTS/IWFS Discharge Line (RM-L 12) 1 1 18 20 2. Flow Rate Measurement Devices a. b. Unit 1 Liquid Radwaste Effluent Line (WDL-FT-84) Station Effluent Discharge (SR-FT-146) Table Notation 1 21 21 ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue, provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Surveillances 3.2.1.1.1 and 3.2.1.1.2 and; 2. At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup. 3. The TMI Plant Manager shall approve each release.

Otherwise, suspend release of radioactive effluents via this pathway. ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may commence or continue provided that grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 1x10-7 microcuries/ml, prior to initiating a release and at least once per 12 hours during release. ACTION 21 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, radioactive effluent releases via this pathway may continue, provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow. CY-TM-170-300 Revision 5 Page 23 of 222 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL: The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: As shown in Table 2.1-2 ACTION: a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels

OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in* a timely manner. BASES The radioactive gaseous effluent instrumentation is provided to m*onitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases.

The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC a*pproved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301. The low range condenser offgas noble gas activity monitors also provide data for determination of steam generator primary to secondary leakage rate.

• Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation INSTRUMENT

1. Waste Gas Holdup System a. Noble Gas Activity Monitor (RM-A-7) B. Effluent System Flow Rate Measuring Device (WDG-FT-123)

2. Waste Gas Holdup System Explosive Gas Monitoring System a. Hydrogen Monitor (CA-G-1A/B)

b. Oxygen Monitor (CA-G-1A/B)

3. Containment Purge Monitoring System a. Noble Gas Activity Monitor (RM-A-9)

b. Iodine Sampler (RM-A-9)

c. Particulate Sampler (RM-A-9)

d. Effluent System Flow Rate Measuring Device (AH-FR-148A, AH-FR-148B)

e. Sampler Flow Rate Monitor (RM-Fl-1231)

4. Condenser Vent System a. Low Range Noble Gas Activity Monitor (RM-A-5Lo or RM-A-15)

MINIMUM CHANNEL OPERABLE 1 1 2 2 1 1 1 1 1 1 APPLICABILITY

• • • *** ** ** # # # # # CY-TM-170-300 Revision 5 Page 24 of 222 ACTION 25 26 30 30 27 31 31 26 26 32 Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation INSTRUMENT

5. Auxiliary and Fuel Handling Building Ventilation System a. Noble Gas Activity Monitor (RM-A-8) or (RM-A-4 and RM-A-6) b. Iodine Sampler (RM-A-8 or (RM-A-4 and RM-A-6) c. Particulate Sampler (RM-A-8 or (RM-A-4 and RM-A-6) d. Effluent System Flow Rate Measuring Devices (AH-FR-149 and AH-FR-150)

e. Sampler Flow Rate Monitor (RM-Fl-1230 or RM-A-4\FI and RM-A-6\FI)

6. Fuel Handling Building ESF Air Treatment System a. Noble Gas Activity Monitor (RM-A-14 or suitable equivalent)

b. Iodine Cartridge

c. Particulate Filter d. Effluent System Flow (AH-UR-1104A/B)

e. Sampler Flow Rate Monitor (RM-A-14Fl14)

MINIMUM CHANNEL OPERABLE 1 1 1 1 1 1 N/A<2l N/A(2l 1 1 APPLICABILITY

• * * * * **** **** **** **** **** CY-TM-170-300 Revision 5 Page 25 of 222 ACTION 27 31 31 26 26 27,33 31,33 31,33 26,33 26,33 NOTE 2: No instrumentation channel is provided.

However, for-determining operability, the equipment named must be installed and functional or the ACTION applies.

Table 2.1-2 (Cont'd) Radioactive Gaseous Process and Effluent Monitoring Instrumentation INSTRUMENT

7. Chemical Cleaning Building Ventilation System a. Noble Gas Activity Monitor (ALC RM-1-18)

b. Iodine Sampler (ALC RM-1-18)

c. Particulate Sampler (ALC RM-1-18)

8. Waste Handling and Packaging Facility Ventilation System a. Particulate Sampler (WHP-RIT-1)

9. Respirator and Laundry Maintenance Facility Ventilation System a. Particulate Sampler (RLM-RM-1)

MINIMUM CHANNEL OPERABLE 1(3) 1(3) 1 1 APPLICABILITY

1. l#f. #l#f. #l#f. #l#f. #l#f. CY-TM-170-300 Revision 5 Page 26 of 222 ACTION 27 31 31 31 31 NOTE 3: Channel only required when liquid radwaste is moved or processed within the facility (e.g., includes recirculation,

cleanup, transfers out of, within, or into Chemical Cleaning

Building, etc.).

• ** *** **** # ## ### At all times Table 2.1-2 (Cont'd)

Table Notation During waste gas holdup system operation CY-TM-170-300 Revision 5 Page 27 of 222 Operability is not required when discharges are positively controlled through the closure of WDG-V-47 or where RM-A-8, AH-FT-149 and AH-FT-150 are operable and RM-A-8 is capable of automatic closure of WDG-V-47 During Fuel Handling Building ESF Air Treatment System Operation At all times during containment purging At all times when condenser vacuum is established During operation of the ventilation system ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed in accordance with Table 3.2-2, Item A, and 2. At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup. 3. The TMI Plant Manager shall approve each release.

Otherwise, suspend release of radioactive effluent via this pathway. ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and the initial samples are analyzed for gross activity (gamma scan) within 24 hours after the channel has been declared inoperable. If RM-A-9 is declared inoperable, see also Technical Specification 3.5.1, Table 3-5.1, Item C.3.f. ACTION 30 1. Table 2.1-2 Notations (Cont'd) CY-TM-170-300 Revision 5 Page 28 of 222 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, a grab sample shall be collected and analyzed for the inoperable gas channel(s) at least once per 24 hours. With both channels inoperable, a grab sample shall be collected and analyzed for the inoperable gas channel(s): (a) at least once per 4 hours during degassing operations. (b) at least once per 24 hours during other operations (e.g. Feed and Bleed). 2. If the inoperable gas channel(s) is not restored to service within 14 days, a special report shall be submitted to the Regional Administrator of the NRG Region I Office and a copy to the Director, Office of Inspection and Enforcement within 30 days of declaring the channel(s) inoperable. The report shall describe (a) the cause of the monitor inoperability, (b) action being taken to restore the instrument to service, and (c) action to be taken to prevent recurrence. ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within four hours after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment. ACTION 32 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that grab samples are taken and analyzed. If the primary-to-secondary leak rate was unstable*, or was indicating an increasing trend at the initial time when there was no operable channel of the Condenser Vent System Low Range Noble Gas Activity

Monitor, analyze grab samples of the reactor coolant system and Condenser OffGas once every 4 hours to provide an indication of primary-to-secondary leakage.

Subsequent sample frequency shall be in accordance with Table 1 based on the last sample result. Otherwise, analyze grab samples of the reactor coolant system and Condenser OffGas to provide an indication of primary-to-secondary leakage at the minimum frequency indicated in Table 1, below: Table 2.1-2 Notations (Cont'd) Table 1 CY-TM-170-300 Revision 5 Page 29 of 222 Minimum Frequency of Grab Samples When No Condenser Vent System Low Range Noble Gas Activity Monitor is Operable Existing Total Primary-to-Secondary Leak Rate Frequency of Grab Samples (based on last monitor reading or sample result) 0 to< 5 GPO Once per 24 hours 5 to< 30 GPO Once per 12 hours 30 to< 75 GPO Once per 4 hours 75 GPO or Qreater Refer to CY-AP-120-340

• Unstable is defined as > 10% increase during a 1 hour period, as stated in the EPRI Guidelines.

Condenser Vent System Low Range Noble Gas Activity Monitor inoperable channels should be restored to operability as rapidly as practical.

• ACTION 33 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel to OPERABLE status within 7 days, or prepare and submit a special report within 30 days outlining the action(s) taken, the cause of the inoperability, and plans and schedule for restoring the system to OPERABLE status.

2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL: CY-TM-170-300 Revision 5 Page 30 of 222 The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 3E-3 uCi/cc total activity. APPLICABILITY: At all times ACTION: With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits. BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures with (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301 to the population. The concentration limit for noble gases is based upon the assumption the Xe-135 is the controlling radioisotope and its MPG in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication

2.

2.2.1.2 Liquid Effluent Dose CONTROL CY-TM-170-300 Revision 5 Page 31 of 222 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ. b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ. APPLICABILITY:

At all times ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report, which identifies the cause(s) for exceeding the limit(s), and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act. BASES CY-TM-170-300 Revision 5 Page 32 of 222 This control and associated action is provided to implement the requirements of Sections II.A, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 10 CFR 20. The dose calculations in the ODCM implement the requirements in Section Ill.A. of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113. CY-TM-170-300 Revision 5 Page 33 of 222 2.2.1.3 Liquid Radwaste Treatment System CONTROL: The appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month. APPLICABILITY: At all times ACTION: a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRG Region I Administrator within 30 days, a Special Report which includes the following information: BASES 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and, 3. A summary description of action(s) taken to prevent a recurrence The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable.

This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.D of Appendix I to 10 CFR Part 50. The intent of Section 11.D. is to reduce effluents to as low as is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section II.A of Appendix I, 10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction. 2.2.1.4 Liquid Holdup Tanks CONTROL CY-TM-170-300 Revision 5 Page 34 of 222 The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases. a. Outside temporary tank APPLICABILITY: At all times. ACTION: a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. BASES Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20.1001-20-20.2401, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area. 2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL: The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and b. For 1-131, 1-133, tritium and all radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem/yr to any organ. APPLICABILITY:

At all times ACTION: CY-TM-170-300 Revision 5 Page 35 of 222 With the release rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limit(s). BASES J The control implements the requirement in Technical Specification (6.8.4.b (7). This specification is provided to ensure that the dose from radioactive materials in gaseous effluents at and beyond the SITE BOUNDARY will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with 10 times the concentrations of 10 CFR Part 20, Appendix B, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR Part 20.1302. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body, or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year (NU REG 1301 ). 2.2.2.2 Gaseous Effluents Dose-Noble Gases CONTROL: The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter:

less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, CY-TM-170-300 Revision 5 Page 36 of 222 b. During any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation. APPLICABILITY: At all times ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. BASES This control applies to the release of radioactive materials in gaseous effluents from TMl-1. This control and associated action is provided to implement the requirements of Section 11.B, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section 11.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably ac~ievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in CY .. TM-170-300 Revision 5 Page 37 of 222 Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. 2.2.2.3 Dose -lodine-131, lodine-133,

Tritium,

• and Radionuclides in Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-133,

Tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter:

less than or equal to 7.5 mrem to any organ, and b. During any calendar year: less than or equal to 15 mrem to any organ. APPLICABILITY: At all times ACTION: With the calculated dose from the release of lodine-131, lodine-133,

Tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. BASES This control applies to the release of radioactive materials in gaseous effluents from TMl-1. This control and associated action is provided to implement the requirements of Section 11.C, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in CY-TM-170-300 Revision 5 Page 38 of 222 Section 11.C of Appendix I. The ACTION statement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors" Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, iodine-133, tritium and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. 2.2.2.4 Gaseous Radwaste Treatment System CONTROL The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE.

The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in the gaseous waste prior to their discharge when the monthly projected gaseous effluent air doses due to untreated gaseous effluent releases from the unit CY-TM-170-300 Revision 5 Page 39 of 222 would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ. APPLICABILITY: At all times ACTION: a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRG Region I Administrator within 30 days, a Special Report which includes the following information: BASES 1. Identification

• of the inoperable equipment or subsystems and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3. A summary description of action(s) taken to prevent a recurrence The use of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment.

The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections 11.B and 11.C of Appendix I, 10 CFR Part 50, for gaseous effluents. 2.2.2.5 Explosive Gas Mixture CONTROL CY-TM-170-300 Revision 5 Page 40 of 222 The concentration of oxygen in the Waste Gas Holdup System shall be limited to less than or equal to 2% by volume whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume. AVAILABILITY: At all times ACTION: Whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume, and: a. The concentration of oxygen in the Waste Gas Holdup System is greater than 2% by volume, but less than 4% by volume, without delay, begin to reduce the oxygen concentration to within its limit. b. The concentration of oxygen in the Waste Gas Holdup System is greater than or equal to 4% by volume, immediately suspend additions of waste gas to the Waste Gas Holdup System and without delay, begin to reduce the oxygen concentration to within its limit. BASES: Based on experimental data (Reference 1 ), lower limits of flammability for hydrogen is 5% and for oxygen is 5% by volume. Therefore, if the concentration of either gas is kept below it lower limit, the other gas may be present in higher amounts without the danger of an explosive mixture. Maintaining the concentrations of hydrogen and oxygen such that an explosive mixture does not occur in the waste gas holdup system provides assurance that the release of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR 50. REFERENCES (1) Bulletin 503, Bureau of Mines; Limits of Flammability of Gases and Vapors 2.2.2.6 Waste Gas Decay Tanks CONTROL: CY-TM-170-300 Revision 5 Page 41 of 222 The quantity of radioactivity contained in each waste gas decay tank shall be limited to less than or equal to 8800 curies noble gases (considered as Xe-133). APPLICABILITY: At all times ACTION: a. With the quantity of radioactive material in any waste gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. BASES Restricting the quantity of radioactivity contained in each waste gas decay tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure." 2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL: The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. APPLICABILITY: At all times ACTION: With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a, 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b, 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including CY-TM-170-300 Revision 5 Page 42 of 222 direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b ), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material

involved, and the cause of the exposure levels or concentrations.

If the estimated dose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. BASES This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301 (d). This control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be CY-TM-170-300 Revision 5 Page 43 of 222 considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected) in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRG staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 3.0 SURVEILLANCES 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation Surveillance Requirements CY-TM-170-300 Revision 5 Page 44 of 222 3.1.1.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, AND CHANNEL TEST operations during the MODES and at the frequencies shown in Table 3.1-1. Table 3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements INSTRUMENT

1. Radioactivity Monitors Providing Alarm and Automatic Isolation

a. b. Unit 1 Liquid Radwaste Effluents Line (RM-L-6)

IWTS/IWFS Discharge Line (RM-L-12)

2. Flow Rate Monitors

a. b. Unit 1 Liquid Radwaste Effluent Line (WOL-FT-84)

Station Effluent Discharge (SR-FT-146) CHANNEL CHECK 0 0 0(3) 0(3) SOURCE CHECK p p NIA NIA CHANNEL CALIBRATION R(2) R(2) R R CY-TM-170-300 Revision 5 Page 45 of 222 CHANNEL TEST Q(1) Q(1) Q Q Table 3.1-1 (Cont'd) Table Notation CY-TM-170-300 Revision 5 Page 46 of 222 (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the following condition exists: 1. Instrument indicates measured levels above the high alarm/trip setpoint. (Includes -circuit failure)

2. Instrument indicates a down scale failure.

(Alarm function only.) (Includes -circuit failure)

3. Instrument controls moved from the operate mode (Alarm function only). (2) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participated in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may

• substitute previously established calibration procedures for this requirement)

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous,

periodic, or batch releases are made.

. CY-TM-170-300 Revision 5 Page 4 7 of 222 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.

1. 2. 3. 4. Table 3.1-2 CY-TM-170-300 Revision 5 Page 48 of 222 Radioactiv.e Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY Waste Gas Holdup System a. Noble Gas Activity Monitor (RM-A7) p p E(3) Q(1) *** b. Effluent System Flow Rate Measuring Device (WDG-FT-123) p NIA E Q *** Waste Gas Holdup System Explosive Gas Monitoring System a. Hydrogen Monitor (CA-G-1A/B)

D N/A Q(4) M ** b. Oxygen Monitor (CA-G-1A/B) D N/A Q(S) M ** Containment Purge Vent System a. Noble Gas Activity Monitor (RM-A9) D p E(3) M(1) # b. *Iodine Sampler (RM-A9) w N/A N/A N/A # c. Particulate Sampler (RM-A9) w N/A N/A N/A # d. Effluent System Flow Rate Measuring Device (AH-FR-148) D N/A E Q # e. Sampler Flow Rate Monitor (RM-Fl-1231) b N/A E N/A # Condenser Vent System a. Noble Gas Activity Monitor (RM-AS and Suitable D M E(3) Q(2) ## Equivalent -See Table 2.1-2, Item 4.a) Table 3.1-2 (Cont'd) CY-TM-170-300 Revision 5 Page 49 of 222 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY

5. Auxiliary and Fuel Handling Building Ventilation System a. Noble Gas Activity Monitor (RM-AB) or (RM-A4 and RM-A6) D M E(3) 0(1)

• b. Iodine Sampler (RM-AB) or (RM-A4 and RM-A6) w N/A N/A N/A
• C. Particulate Sampler (RM-AB) or (RM-A4 and RM-A6) w N/A N/A N/A
• d. System Effluent Flow Rate Measurement Devices (AH-FR-149 D N/A E 0
• and AH-FR-150)

D N/A E N/A

• e. Sampler Flow Rate Monitor (RM-Fl-1230 or RM-A-4\FI and RM-A-6\FI)

6. Fuel Handling Building ESF Air Treatment System a. Noble Gas Activity Monitor (RM-A14)

D M R(3) 0(2) **** b. System Effluent Flow Rate (AH-UR-1104 A/B) D N/A R 0 **** C. Sampler Flow Rate Measurement Device (RM-A-14Fl14) D N/A R 0 **** Table 3.1-2 (Cont'd) CY* TM-170-300 Revision 5 Page 50 of 222 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements INSTRUMENT

7. Chemical Cleaning Building Ventilation System a. b. C. Noble Gas Activity Monitor (ALC RM-1-18)

Iodine Sampler (ALC RM-1-18) Particulate Sampler (ALC RM-1-18)

8. Waste Handling and Packaging Facility Ventilation System a. Particulate Sampler (WHP-RIT-1)

9. Respirator and Laundry Maintenance Ventilation System a. Particulate Sampler (RLM-RM-1)

CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION D w w D D M N/A N/A w w E(3) N/A N/A SA SA CHANNEL TEST APPLICABILITY Q(2) N/A N/A w w #II# #II# #II#

• ** *** **** # ## ### Table 3.1-2 (Cont'd)

Table Notation At all times During waste gas holdup system operation CY-TM-170-300 Revision 5 Page 51 of 222 Operability is not required when discharges are positively controlled through the closure ofWDG-V-47, or where RM-A-8, AH-FT-149, and AH-FT-150 are operable and RM-A-8 is capable of automatic closure of WDG-V-47 During Fuel Handling Building ESF Air Treatment System Operation At all times during containment purging At all times when condenser vacuum is established During operation of the ventilation system (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway for the Auxiliary _and Fuel Handling Building Ventilation System, the sµpply ventilation is isolated and control room alarm annunciation occurs if the following condition exists: 1. Instrument indicates measured levels above the high alarm/trip setpoint (Includes circuit failure).

2. Instrument indicates a down scale failure (Alarm function only) (Includes circuit failure).

3. Instrument controls moved from the operate mode (Alarm function only). (2) The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1 Instrument indicates measured levels above the alarm setpoint.

(includes circuit failure)

2. Instrument indicates a down scale failure (includes circuit failure).

3. Instrument controls moved from the operate mode.

Table 3.1-2 NOTATIONS (Cont'd) CY-TM-170-300 Revision 5 Page 52 of 222 (3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement.) (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent hydrogen, balance nitrogen, and 2. Four volume percent hydrogen, balance nitrogen (5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and 2. Four volume percent oxygen, balance nitrogen 3.2 Radiological Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration CY-TM-170-300 Revision 5 Page 53 of 222 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release, by sampling and analysis in accordance with Table 3.2-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.1.2 Post-release analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1. 3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1. 3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative qose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month. 3.2.1.3 Liquid Waste Treatment 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM. 3.2.1.4 Liquid Holdup Tanks CY-TM-170-300 Revision 5 Page 54 of 222 3.2.1.4.1 The quantity of radioactive material contained in each of the tanks specified in Control 2.2.1.4 shall be determined to be within the limit by analyzing a representative sample of the tank's content weekly when radioactive materials are being added to the tank. Table 3.2-1 Radioactive Liquid Waste Sampling and Analysis Program Sampling Minimum Analysis Liguid Release Ty~e Freguency Freguency Ty~e of Activity Analysis A.1 Batch Waste Release Tanks (Noted) p p H-3 Each Batch Each Batch Principal Gamma Emitters (Note f) 1-131 Dissolved and Entrained Gases (Gamma Emitters} (Note g} p M Gross alpha Each Batch Com~osite (Note b} p Q Sr-89, Sr-90 Each Batch Com osite Note b Fe-55 A.2 Continuous Releases (Note e) Continuous w Principal Gamma Emitters (Note f) (Note c) Composite (Note c) 1-131 Grab Sample M Dissolved and Entrained Gases M (Gamma Emitters) (Note g) Continuous M H-3 (Note c} Com~osite (Note c} Gross al~ha Continuous Q Sr-89, Sr-90 (Note c} Com~osite (Note c} Fe-55 CY-TM-170-300 Revision 5 Page 55 of 222 Lower Limit of Detection (LLD} (~Ci/ml} (Note a} 1 X 10*5 5 X 10*7 1 X 10*6 1 X 10*5 1 X 10*7 5 X 10*8 1 X 10*6 5 X 10*7 1 X 10*6 1 X 10*5 1 X 10*5 1 X 10*7 5 X 10*8 1 X 10*6 Table 3.2-1 (Cont'd) Table Notation CY-TM-170-300 Revision 5 Page 56 of 222 a. The LLD is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. Where: For a particular measurement system (which may include radiochemical separation): 4.66Sb E x V x 2.22 x 106 x Y x exp (-JM) LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume) Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per disintegration) Vis the sample size (in units of mass or volume) 2.22 E6 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable) '"A is the radioactive decay constant for the particular radionuclide, and ~t is the elapsed time between midpoint of sample collection and time of counting Typical values of E, V, Y and ~t shall be used in the calculation It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released Table 3.2-1 Notations (Cont'd)

CY-TM-170-300 Revision 5 Page 57 of 222 c. To be representative of the quantities and concentrations of radioactive materials in liquid effluent, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and be thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e. A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume or system that has an input flow during the continuous release.

f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mb-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4. g. The gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, and Xe-135. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Effluent Release Report pursuant to T.S. 6.9.4. 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates CY-TM-170-300 Revision 5 Page 58 of 222 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.a in accordance with the methods and procedures of the ODCM. 3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis

program, specified in Table 3.2-2. 3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.3 Dose, lodine-131, lodine-133,

Tritium, and Radionuclides in Particulate Form 3.2.2.3.1 Cumulative dose contributions from lodine-131, lodine-133,

Tritium, and radionuclides in particulate form with half lives greater than 8 days for the current calendar

_quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly. 3.2.2.4 Gaseous Waste Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM. 3.2.2.5 Explosive Gas Mixture CY-TM-170-300 Revision 5 Page 59 of 222 3.2.2.5.1 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the limits of Control 2.2.2.5 by monitoring the waste gases in the Waste Gas Holdup System with the hydrogen and oxygen monitors covered in Table 2.1-2 of Control 2.1.2. 3.2.2.6 Waste Gas Decay Tank 3.2.2.6.1 The concentration of radioactivity contained in the vent header shall be determined weekly. If the concentration of the vent header exceeds 10. 7 µCi/cc, daily samples shall be taken of each waste gas decay tank being added to, to determine if the tank(s) is less than or equal to 8800 Ci/tank. CY-TM-170-300 Revision 5 Page 60 of 222 Table 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program Minimum Lower Limit of Sampling Analysis Type of Activity Detection (LLD) Gaseous Release Type Frequency Frequency Analysis µCi/ml) (Note a) p p Principal Gamma Each Tank 1 X 1 Q-4 A. Waste Gas Decay Tank Grab Sample Each Tank Emitters (Note g) B. Containment Purge H-3 1 X 10-6 P (Note b)Each P (Note b) Each Principal Gamma Purge Grab Sample Purge Emitters (Note g) 1 X 1 Q-4 C. Auxiliary and Fuel Handling Building H-3 1 X 10-6 Air Treatment System M (Notes c, e) Grab M Principal Gamma Sample Emitters (Note g) 1 X 104 D. Fuel Handling Building ESF Air Treatment System M (during System M (during H-3 1 X 10-6 Operation) System Principal Gamma Grab Sam le Operation) Emitters Note 1 X 104 E. Condenser Vacuum Pumps Exhaust (Note h) M (Note h) H-3 1 X 1 Q-6 M Principal Gamma Grab Sample (Note h) Emitters (Note g) 1 X 104 F. Chemical Cleaning Building Air Treatment System M (Note I) H-3 1 X 1 Q-6 M Principal Gamma Grab Sample Emitters (Note g) 1 X 1 Q-4 G. Waste Handling and Packaging Facility See Section I See Section I See Section I See Section I Air Treatment System of this table of this table of this table of this table H. Respirator and Laundry Maintenance Facility See Section I See Section I See Section I See Section I Air Treatment System of this table of this table of this table of this table I. J. Table 3.2-2 (Cont'd) Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release T e All Release Types as Listed Above in B, C, D, F, G, Continuous and H (During System Operation) (Note f) (Note i) Continuous (Note f) Continuous (Note f) Continuous (Note f) Continuous (Note f) Condenser Vent Stack Continuous Iodine Continuous Sampler (Note j) (Note k) W (Noted) Charcoal Sample W (Noted) Particulate Q Composite Particulate Sample Q Composite Particulate Sample Noble Gas Beta or Gamma W (Noted} Charcoal Sample Type of Activity Anal sis 1-131 Principal Gamma Emitters (Note g) (1-131, Others) Gross Alpha Sr-89, Sr-90 Noble Gases 1-131 CY-TM-170-300 Revision 5 Page 61 of 222 1 X 10-12 1 X 10-11 1 X 10-11 1 X 10-11 1 X 10-6 1 X 10-12 Table 3.2-2 (Cont'd) Table Notation CY-TM-170-300 Revision 5 Page 62 of 222 a. The LLD is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. Where: For a particular measurement system (which may include radiochemical separation): 4.66Sb LLD=----------- E x V x 2.22 x 106 x Y x exp (-AAt) LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume) Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per disintegration) Vis the sample size (in units of mass or volume) 2.22 E6 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable) "-is the radioactive decay constant for the particular radionuclide, and ~t is the elapsed time between midpoint of sample collection and time of counting. Typical values of E, V, Y and ~t shall be used in the calculation. It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

b. Sampling and analysis shall also be performed following

shutdown, startup, or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour, unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. c. Tritium grab samples from the spent fuel pool area shall be taken at least once per 24 hours when the refueling canal is flooded.

Table 3.2-2 Notations (Cont'd) CY-TM-170-300 Revision 5 Page 63 of 222 d. Charcoal cartridges and particulate filters shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler).

e. Tritium grab samples shall be taken weekly from the spent fuel pool area whenever spent fuel is in the spent fuel pool. f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 2.2.2.1, 2.2.2.2, and 2.2.2.3.

g. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4. h. Applicable only when condenser vacuum is established. Sampling and analysis shall also be performed following

shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. i. Gross Alpha, Sr-89, and Sr-90 analyses do not apply to the Fuel Handling Building ESF Air Treatment System. j. If the Condenser Vent Stack Continuous Iodine Sampler is unavailable, then alternate sampling equipment will be placed in service within 48 hours or a report will be prepared, and submitted within 30 days from the time the sampler is found or made inoperable, which identifies (a) the cause of the inoperability, (b) the action taken to restore representative sampling capability, (c) the action taken to prevent recurrence, and (d) quantification of the release via the pathway during the period and comparison to the limits prescribed by Control 2.2.2.1.b.

k. Applicable only when condenser vacuum is established.

I. Applicable when liquid radwaste is moved or processed within the facility (e.g. includes recirculation,

cleanup, transfers out, within, or into Chemical Cleaning

Building, etc). m. Iodine samples only required in the Chemical Cleaning Building when TMl-1 liquid radwaste is stored or processed in the facility.

3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation CY-TM-170-300 Revision 5 Page 64 of 222 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM. 4.0 PART I REFERENCES 4.1 Title 10, Code of Federal Regulations, "Energy" CY-TM-170-300 Revision 5 Page 65 of 222 4.2 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routing Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "Revision 1, October 1977 4.3 TMl-1 Technical Specifications, attached to Facility Operating License No. DPR-50 4.4 TMl-1 FSAR PART II TMl-2 RADIOLOGICAL EFFLUENT CONTROLS CY-TM-170-300 Revision 5 Page 66 of 222 1.0 DEFINITIONS DEFINED TERMS PART II Definitions CY-TM-170-300 Revision 5 Page 67 of 222 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part II of the ODCM. PDMS 1.2 Post-Defueling Monitored Storage (PDMS) is that condition where TMl-2 defueling has been completed, the core debris removed from the reactor during the clean-up period has been shipped off-site, and the facility has been placed in a stable, safe, and secure condition. ACTION 1.3 ACTION shall be those additional requirements specified as corollary statements to each control and shall be part.of the controls. OPERABLE -OPERABILITY 1.4 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation,

controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function(s),

are also capable of performing their related support function(s). CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter, which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. CHANNEL CHECK CY-TM-170-300 Revision 5 Page 68 of 222 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be: a. Analog channels -the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channels

-the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions. SOURCE CHECK 1.8 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. COMPOSITE SAMPLE 1.9 A COMPOSITE SAMPLE is a combination of individual samples obtained at regular intervals over a time period. Either the volume of each individual sample is proportional to the flow rate discharge at the time of sampling or the number of equal volume samples is proportional to the time period used to produce the composite. GRAB SAMPLE 1.10 A GRAB SAMPLE is an individual sample collected in less than fifteen minutes. BATCH RELEASE 1.11 A BATCH RELEASE is the discharge of fluid waste of a discrete volume. CONTINUOUS RELEASE 1.12 A CONTINUOUS RELEASE is the discharge of fluid waste of a non-discrete volume, e.g., from a volume or system that has an input flow during the CONTINUOUS RELEASE. SITE BOUNDARY CY-TM-170-300 Revision 5 Page 69 of 222 1.13 The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMl-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile Island and between Three Mile Island and Shelley Island. The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM. FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. NOTATION S (Shiftly) D (Daily) W (Weekly) M (Monthly) Q (Quarterly) TABLE 1.1 Frequency Notation SA (Semi-Annually) A (Annually) E N.A. p CY-TM-170-300 Revision 5 Page 70 of 222 FREQUENCY At least once per 12 hours At least once per 24 hours At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 12 months At least once per 18 months Not applicable Completed prior to each release 2.0 CONTROLS AND BASES CY-TM-170-300 Revision 5 Page 71 of 222 2.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control. 2.0.2 Adherence to the requirements of the Control and/or associated ACTION within the specified time interval shall constitute compliance with the control. In the event the Control is restored prior to expiration to the specified time interval, completion of the ACTION statement is not required. 2.0.3 In the event the Control and associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the Control, initiate appropriate actions to rectify the problem to the extent possible under the circumstances, and submit a special report to the Commission pursuant to TMl-2 PDMS Technical Specification (Tech. Spec.) Section 6.8.2 within 30 days, unless otherwise specified. 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation Radioactive Liquid Effluent Instrumentation is common between TMl-1 and TMl-2. Controls, applicability, and actions are specified in ODCM Part I, Control 2.1.1 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL: The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: As shown in Table 2.1-2 ACTION: a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable. CY-TM-170-300 Revision 5 Page 72 of 222 b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels

OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner. BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases.

The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301. Table 2.1-2 CY-TM-170-300 Revision 5 Page 73 of 222 Radioactive Gaseous Process and Effluent Monitoring Instrumentation INSTRUMENT

1. Containment Purge Monitoring System a. b. C. Noble Gas Activity Monitor (2HP-R-225)

Particulate Monitor (2HP-R-225) Effluent System Flow Rate Measuring Device (2AH-FR-5907 Point 1) 2. Station Ventilation System a. Noble Gas Activity Monitor (2HP-R-219) or (2HP-R-219A)

b. Particulate Monitor (2HP-R-219) or (2HP-R-219A)

c. Effluent System Flow Rate Monitoring Device (2AH-FR-5907 Point 6) NOTES: 1. During operation of the monitored system. MINIMUM CHANNELS OPERABLE 1 1 1 1 1 APPLICABILITY NOTE 1 NOTE 1 NOTE 1 NOTE 1 NOTE 1 NOTE 1 ACTION NOTE2 NOTE2 NOTE3 NOTE2 NOTE2 NOTE3 2. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, secure Reactor Building Purge if in progress.

3. With flow rate monitoring instrumentation out of service, flow rates from the Auxiliary (2AH-FR-5907 Point 2), Fuel Handling (2AH-FR-5907 Point 4 ), Soiled Exhaust System (2AH-FR-5907 Point 5), and Reactor Buildings (2AH-FR-5907 Point 1) may be summed individually.

Under these conditions, the flow rate monitoring device is considered operable. If the flow rates cannot be summed individually, they may be estimated using the maximum design flow for the exhaust fans, and the reporting requirements of Control 2.1.2.b are applicable. 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL: CY-TM-170-300 Revision 5 Page 7 4 of 222 The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2. APPLICABILITY: At all times ACTION: With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within.the above limits. BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. These Controls permit flexibility under unusual conditions, which may temporarily result in higher than normal releases, but still within ten times the concentrations, specified in 10 CFR 20. It is expected that by using this flexibility under unusual conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the annual average concentrations specified in 10 CFR 20. As a result, this Control provides reasonable assurance that the resulting annual exposure to an individual in off-site areas will not exceed the design objectives of Section II.A of Appendix I to 10 CFR Part 50, which were established as requirements for the cleanup of TMl-2 in the NRC's Statement of Policy of April 27, 1981. I 2.2.1.2 Liquid Effluent Dose CONTROL CY-TM-170-300 Revision 5 Page 75 of 222 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ. b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ. APPLICABILITY:

At all times ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act. BASES CY-TM-170-300 Revision 5 Page 76 of 222 This Control requires that the dose to offsite personnel be limited to the design objectives of Appendix I of 10 CFR Part 50. This will assure the dose received by the public during PDMS is equivalent to or less than that from a normal operating reactor. The limits also assure that the environmental impacts are consistent with those assessed in NUREG-0683, the TMl-2 Programmatic Environmental Impact Statement (PEIS). The ACTION statements provide the required flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculations in the ODCM implement the requirements in Section Ill.A. of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1 O CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113. CY-TM-170-300 Revision 5 Page 77 of 222 2.2.1.3 Liquid Radwaste Treatment System CONTROL: The appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month. APPLICABILITY: At all times ACTION: a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information: BASES 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and, 3. A summary description of action(s) taken to prevent a recurrence.

The requirement that the appropriate portions of this system (shared with TMl-1) be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable. This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.D of Appendix I to 10 CFR Part 50. The intent of Section 11.D. is to reduce effluents to as low as is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section I I.A of Appendix I, 10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction. 2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL: CY-TM-170-300 Revision 5 Page 78 of 222 The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and b. For tritium and all radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem/yr to any organ. APPLICABILITY:

At all times. ACTION: With the release rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limit(s). BASES CY-TM-170-300 Revision 5 Page 79 of 222 The control provides reasonable assurance that the annual dose at the SITE BOUNDARY from gaseous effluent from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. At the same time, these Controls permit flexibility under unusual conditions, which may temporarily result in higher than the design objective levels, but still within the dose limits specified in 10 CFR 20 and within the design objectives of Appendix I to 10 CFR 50. It is expected that using this flexibility under unusual conditions, and by exerting every effort to keep levels of radioactive material in gaseous wastes as low as practicable, the annual releases will not exceed a small fraction of the annual dose limits specified in 10 CFR 20 and will not result in doses which exceed the design objectives of Appendix I to 10 CFR 50, which were endorsed as limits for the cleanup of TMl-2 by the NRC's Statement of Policy of April 27, 1981. These gaseous release rates provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in the exposure of a MEMBER OF THE PUBLIC in an unrestricted area, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the values specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. The absence of iodine ensures that the corresponding thyroid dose rate above background to a child via the inhalation pathway is less than or equal to 1500 mrem/yr (NU REG 1301 ), thus there is no need to specify dose rate limits for these nuclides. 2.2.2.2 Gaseous Effluents Dos.e-Noble Gases CONTROL: CY-TM-170-300 Revision 5 Page 80 of 222 The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter:

less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b. During any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation. APPLICABILITY: At all times. ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. BASES This control applies to the release of radioactive materials in gaseous effluents from TMl-2. CY-TM-170-300 Revision 5 Page 81 of 222 This control and associated action is provided to implement the requirements of Section 11.B, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section 11.B of Appendix I. The ACTION statements provide flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. 2.2.2.3 Dose -lodine-131, lodine-133,

Tritium, and Radionuclides In Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from Tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter:

less than or equal to 7.5 mrem to any organ, and b. During any calendar year: less than or equal to 15 mrem to any organ. APPLICABILITY: At all times. ACTION: CY-TM-170-300 Revision 5 Page 82 of 222 With the calculated dose from the release of Tritium and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRG Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. BASES CY-TM-170-300 Revision 5 Page 83 of 222 This control applies to the release of radioactive materials in gaseous effluents from TMl-2. This control and associated action is provided to implement the requirements of Section 11.C, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in Section 11.C of Appendix I. The ACTION statement provides flexibility during unusual conditions and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, iodine-133, tritium and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. The absence of iodines at the site eliminates the need to specify dose limits for these nuclides.

~--------- 1 CY-TM-170-300 Revision 5 Page 84 of 222 2.2.2.4 Ventilation Exhaust Treatment System CONTROL The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ. APPLICABILITY: At all times. ACTION: a. With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days,* a Special Report which includes the following information: BASES 1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3. A summary description of action(s) taken to prevent a recurrence.

The use of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in -Sections 11.B and 11.C of Appendix I, 10 CFR Part 50, for gaseous effluents. 2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL: CY-TM-170-300 Revision 5 Page 85 of 222 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. APPLICABILITY: At all times. ACTION: With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a, 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b,

• 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded.

If such is the case, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b ), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material

involved, and the cause of the exposure levels or concentrations.

If the estimated dose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. BASES CY-TM-170-300 Revision 5 Page 86 of 222 This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301 (d). This control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b ), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRG staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 3.0 SURVEILLANCES CY-TM-170-300 Revision 5 Page 87 of 222 3.0.1 Surveillance Requirements shall be applicable during the conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement. The Surveillance Requirements shall be performed to demonstrate compliance with the OPERABILITY requirements of the Control. 3.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. 3.0.3 f=ailure to perform a Surveillance Requirement within the time interval specified in Section 3.0.2 shall constitute non-compliance with OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours to permit completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours. Surveillance Requirements do not have to be performed on inoperable equipment. 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation SURVEILLANCE REQUIREMENTS 3.1.1.1 Radioactive Liquid Effluent Instrumentation is common between TMl-1 and TMl-2. Surveillances for this instrumentation are specified in ODCM Part I, Surveillance 3.1.1. 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation SURVEILLANCE REQUIREMENTS 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2. Table 3.1-2 CY-TM-170-300 Revision 5 Page 88 of 222 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements INSTRUMENT

1. Containment Purge Monitoring System a. b. Noble Gas Activity Monitor (2HP-R-225)

Particulate Sampler (2HP-R-225)

2. Station Ventilation Monitoring System a. b. NOTES: Noble Gas Activity Monitor (2HP-R-219) and (2HP-R-219A)

Particulate Sampler (2HP-R-219) and (2HP-R-219A)

1. During operation of the monitored system. CHANNEL CHECK D w D w CHANNEL CALIBRATION E N/A E N/A CHANNEL FUNCTIONAL TEST M N/A M N/A APPLICABILITY NOTE 1 NOTE 1 NOTE 1 NOTE 1 3.2 Radioactive Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration CY-TM-170-300 Revision 5 Page 89 of 222 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 3.2-1. The results of analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.1.2 Analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1. 3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1. 3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month. 3.2.1.3 Dose Projections 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM. TABLE 3.2-1 CY-TM-170-300 Revision 5 Page 90 of 222 Radioactive Liquid Waste Sampling and Analysis Program (4, 5) A. Liquid Releases Sampling Frequency Type of Detectable Activity Analysis Concentration (3) p Individual Gamma SE-7 µCi/ml (2) Each Batch H-3 1E-5 µCi/ml Q Gross Alpha 1E-7 µCi/ml Quarterly Composite (1) Sr-90 SE-8 µCi/ml NOTES: (1) A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant. (2) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near this. sensitivity limit when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with those radionuclides, which are routinely identified and measured. (3) The detectability limits for radioactivity analysis are based on the technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported. (4) The results of these analyses should be used as the basis for recording and reporting the quantities of radioactive material released in liquid effluents during the sampling period. In estimating releases for a period when analyses were not performed, the average of the two adjacent data points spanning this period should be used. Such estimates should be included in the effluent records and reports;

however, they should be clearly identified as estimates, and the method used to obtain these data should be described.

(5) Deviations from the sampling/analysis regime will be noted in the report specified in ODCM Part IV. 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates CY-TM-170-300 Revision 5 Page 91 of 222 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.a in accordance with the methods and procedures of the ODCM. 3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis

program, specified in Table 3.2-2. 3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.3 Dose, Tritium and Radionuclides In Particulate Form 3.2.2.3.1 Cumulative dose contributions from Tritium and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CAL.CULATION MANUAL (ODCM) monthly. 3.2.2.4 Ventilation Exhaust Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM. TABLE 3.2-2 CY-TM-170-300 Revision 5 Page 92 of 222 Radioactive Gaseous Waste Sampling and Analysis Program (3) SAMPLING TYPE OF DETECTABLE SAMPLE FREQUENC ACTIVITY* CONCENTRATION SAMPLE POINT TYPE y ANALYSIS (1 )(a) p H-3 1E-6 uCi/cc Reactor Building Purge Gas Each Purge Individual 1 E-4 µCi/cc (2) Releases Gamma Emitters M H-3 1E-6 µCi/cc Unit Exhaust Vent Release Gas Individual Points Monthly Gamma Emitters 1 E-4 µCi/cc (2) w Individual (b) 1E-10 µCi/cc (2) Weekly Gamma Emitters M Particulate Monthly Sr-90 1 E-11 µCi/cc s Composite M Gross Alpha Monthly 1 E-11 µCi/cc Composite Emitters lndv. Gamma 1E-10 µCi/cc (2) Reactor Building Breather SA Emitters (b) Particulate Semi-Annual Sr-90 1 E-11 uCi/cc s ly Gross Alpha 1 E-11 µCi/cc Emitters (1) The above detectability limits are based on technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported. (2) For certain mixtures of gamma emitters, it may be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios in the gaseous component in the reactor coolant for those radionuclides which are measurable. (3) Deviations from the sampling and analysis regime will be noted in the report specified in ODCM Part IV. Where TABLE 3.2-2 (Cont'd) CY-TM-170-300 Revision 5 Page 93 of 222 Radioactive Gaseous Waste Sampling and Analysis Program Table Notation

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a llreal" signal. For a particular measurement system (which may include radiochemical separation):

LLD= _____ 4_.6_6_s_p ____ _ E x V x 2.22 x 106 x Y x exp (-A.L1t) LLD is the lower limit of detection as defined above (as picocurie per unit mass or volume). Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute). E is the counting efficiency (as counts per transformation), Vis the sample size (in units of mass or volume), 2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable), ')..., is the radioactive decay constant for the particular radionuclide, and ~t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples),* The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and ~t shall be used in the calculation. The background count rate is calculated from the background counts that are.determined to be with+/- one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quantitative analysis for that radionuclide. TABLE 3.2-2 Notation (Cont'd) CY-TM-170-300 Revision 5 Page 94 of 222 b. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations. 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation CY-TM-170-300 Revision 5 Page 95 of 222 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM. 4.0 PART II REFERENCES CY-TM-170-300 Revision 5 Page 96 of 222 4.1 NUREG-0683, "Final Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident Three Mile Island Nuclear Station, Unit 2," March 1981, and its supplements. 4.2 TMl-2 PDMS Technical Specifications, attached to Facility License No. DPR-73 4.3 Title 10, Code of Federal Regulations, "Energy" 4.4 "Statement of Policy Relative to the NRG Programmatic Environmental Impact Statement on the Cleanup of Three Mile Island Unit 2," dated April 27, 1981 4.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 4.6 DOE/TIC-27601, Atmospheric Science and Power Reduction 4.7 TMl-1 Technical Specifications, attached to Facility Operating License No. DPR-50 4.8 PDMS -SAR PART Ill CY-TM-170-300 Revision 5 Page 97 of 222 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES CY-TM-170-300 Revision 5 Page 98 of 222 1.0 LIQUID EFFLUENT MONITORS 1.1 TMl-1 and TMl-2 Liquid Radiation Monitor Set Points The liquid effluent off-line monitors are set such that the concentration(s) of radionuclides in the liquid effluents will not exceed ten times the concentrations specified in 10 CFR 20, Appendix B Table 2, Col 2. Table 1.1 lists the Liquid Effluent Release Points and their parameters; Figure 1.1 provides a Liquid Release Pathway Diagram. To meet the above limit, the alarm/trip set points for liquid effluent monitors and flow measuring devices are set in accordance with the following equation: C

• f --<C F + f -(eq 1.1) Where: C = ten times the effluent concentration of 10 CFR 20 for the site, in µCi/ml. c = the set point, in µCi/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and release.

The set point is inversely proportional to the maximum volumetric flow of the effluent line and proportional to the minimal volumetric flow of the dilution stream plus the effluent stream. The alert set point value is set to ensure that advance warning occurs prior to exceeding any limits. The high alarm set point value is such that if it were exceeded, it would result in concentrations exceeding ten times the 10 CFR 20 concentrations for the unrestricted area. f = flow set point as measured at the radiation monitor location, in volume per unit time, but in the same units as F below. F = flow rate of dilution water measured prior to the release point, in volume per unit time. The set point concentration is reduced such that concentration contributions from multiple release points would not combine to exceed ten times 10 CFR 20 concentrations. The set point concentration is converted to set point scale uriits using appropriate radiation monitor calibration factors. This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and, for batch releases, the Releasing Radioactive Liquid Waste procedure. CY-TM-170-300 Revision 5 Page 99 of 222 1.2 TMI Liquid Effluent Release Points and Liquid Radiation Monitor Data TMl-1 has two required liquid radiation monitors. These are RM-L6 and RM-L 12. These liquid release point radiation monitors and sample points clre shown in Table 1.1. (The TMI outfall radiation

monitor, RM-L7, is also listed for information only.) TMl-2 does not have any required liquid radiation

monitors, but does utilize RM-L 12, and RM-L7 for release of liquid waste. 1.2.1 RM-L6 RM-L6 is an off-line system, monitoring radioactive batch discharges from the TMl-1 liquid radwaste system (see Figure 1.1 ). These batch releases are sampled and analyzed per site procedures prior to release.

The release rate is based on releasing one of two Waste Evaporator Condensate Storage Tanks (WECST) at a flow which will add less than 10%, of ten times the 10 CFR 20 concentrations [20% for H-3] to radionuclide concentrations in the unrestricted area, including recent values for Sr-89, Sr-90, and Fe-55. The release flow rate used is the most restrictive of two flow rates calculated for each liquid batch release, per the approved plant procedure. Two Dilution Factors (OF) are calculated to ultimately calculate the batch release flow rate. These two DF's are calculated to insure each radionuclide released to the unrestricted area is less than 10 percent of ten times the 1 OCFR20 radionuclide concentrations, (20% for H-3), and to ensure each liquid batch release boron concentration to the river will not exceed 0.7 ppm. The maximum release flow rate is then calculated by dividing the most restrictive (largest) OF into 90 percent of the current dilution flow rate of the Mechanical Draft Cooling Tower (MDCT). This conservative flow rate is then multiplied by 0.9 for the allowable flow rate.

• Calculation of the 10CFR20 concentration DF: DF1 = ~i (SAi) + (10% [20% for H-3] of ten times the 10CFR20 concentration)

SA = Specific Activity of each identified radionuclide

• Calculation of Boron DF: DF2 = Actual Tank Boron Concentration+

0.7. CY-TM-170-300 Revision 5 Page 100 of 222

• Maximum release flow rate calculation:

Max Flow = [(MDCT flow gpm

• 0.9) + (Most Restrictive DF)]
• 0.9 The dilution flow rate used is the current flow rate at the site. The minimum dilution flow rate is 5000 gpm per the TMl-1 FSAR. This ensures this batch release will meet the following equation.

Where: Ci= Xi= CH-3 = XH-3 = }.;(Ci/Xi) + (CH-312XH-3) 0.1, (eq 1.2) diluted concentration of the i1h radionuclide, other than H-3 Ten times the concentration for that radionuclide in the unrestricted area (10 CFR 20, App. B, Table 2, Col. 2). A value of 3E-3 µCi/ml for dissolved and entrained noble gases shall be used. diluted concentration of H-3 Ten times the concentration for H-3 in the restricted area (10 CFR 20, App. B, Table 2, Col. 2). The set points for RM-L6 are based on the maximum release rate (30 gpm), a minimum dilution flow (5000 gpm), and 25% of ten times the 10CFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentration of 1.0E-5 uCi/ml. These inputs are used in Equation 1.1 to determine the RM-L-6 High Alarm setpoint for all radionuclides being released. A high alarm on RM-L-6 will close valve WDL-V-257 and terminate any WECST releases to the environment. 1.2.2 RM-L 12 RM-L 12 is an off-line system, monitoring periodic combined releases from the Industrial Waste Treatment System/Industrial Waste Filtration System (IWTS/IWFS). The input to IWTS/IWFS originates in TMl-2 sumps, (see Figures 1.1 and 1.2) and the TMl-1 Turbine Building sumps (see Figure 1.1 ). The set points are based on the maximum release rate from both IWTS and IWFS simultaneously, (see Figure 1.1) a minimum dilution flow rate, and 50% of ten times the 1 OCFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentration of 1 E-5 µCi/ml. These inputs are used in equation 1.1 to determine the RM-L 12 High Alarm set point for all radionuclides being released. A high alarm on RM-L 12 will close IWTS and IWFS release valves and trip release pumps to stop the release. 1.2.3 RM-L 10 CY-TM-170-300 Revision 5 Page 101 of 222 RM-L 10 was a Nal detector submerged in the TMl-1 Turbine Building Sump. This detector has been removed from service. 1.2.4 RM-L7 RM-L7 is not an ODCM required liquid radiation monitor. RM-L7 is an off-line system, monitoring the TMI outfall to the Susquehanna River (see Figures 1.1 and 1.2). This monitor is the final radiation monitor for TMl-1 and TMl-2 normal liquid effluent releases. 1.3 Control of Liquid Releases TMI liquid effluent releases are controlled to less than ten times the 1 OCFR20 concentrations by limiting the percentage of this limit allowable from the two TMI liquid release points. RM-L6 and effluent sampling limit batch releases to less than or equal to 25% for all radionuclides, and RM-L 12 and effluent sampling limit releases from TMl-1 and TMl-2 to less than or equal to 50% for Cs-137. These radiation monitor set points also include built in meter error factors to further ensure that TMI liquid effluent releases are less than ten times the 1 OCFR20 concentrations to the environment. The radioactivity content of each batch of radioactive liquid waste is determined prior to release by sampling and analysis in accordance with ODCM Part I Table 3.2-1 or ODCM Part II, Table 3.2-1. The results of analyses are used with the calculational methods in Section 1.1, to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1. Post-release analysis of samples composited from batch releases are performed in accordance with ODCM Part I Table 3.2-1 or ODCM Part II Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1. The radioactivity concentration of liquids discharged from continuous release points are determined by collection and analysis of samples in accordance with ODCM Part I Table 3.2-1, or ODCM Part II Table 3.2-1. The tesults of the analysis are used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1. TABLE 1.1 CY-TM-170-300 Revision 5 Page 102 of 222 TMI Liquid Release Point and Liquid Radiation Monitor Data LIQUID RADIATION LIQUID RELEASE MONITOR POINT (Maximum DISCHARGE FLOW (DETECTOR) LOCATION Volume) RECORDER RM-L6 281' Elevation WECST Batch WDL-FT-84 (Nal) TMl-1 Auxiliary Bldg Releases (8000 gal.) RM-L7 South end of TMl-1 Station Discharge (Nal) MDCT TMl-1 and SR-FT-146

• • TMl-2, IWTS/IWFS RM-L 12 IWFS Building NW Continuous Releases IW-FT-342/

(Nal) Corner (300,000/ IW-FT-373 80,000 gal.)

• WDL-R-1311 has been flanged off as a TMl-2 liquid outfall.
  • RM-L7 is not an ODCM required liquid radiation monitor.

RELEASE TERMINATION INTERLOCK (YES/NO) VALVES YES WDL-V257 YES WDL-V257

• WDL-R-1311 YES IW-V73, IW-P16,17,18 IW-V279, IW-P29,30 TABLE 1.2 TMl-2 Sump Capacities I I Total Capacity Sume Gallons Turbine Building Sump 1346 Control Building Area Sump 718 Tendon Access Galley Sump 538 Control and Service Building Sump 1346 Air Intake Tunnel Normal Sump 700 Air Intake Tunnel Emergency Sump 100000 I CY-TM-170-300 Revision 5 Page 103 of 222 Units I 22.43 gals/in 9.96 gals/in 9.96 gals/in 22.43 gals/in ----8200 gal/ft

, :lnter:mediate . Btiilcllng;SiJmp . :east, lntenrieci1ate,

• B~ii8irjgiSuajp Wesf ** 9ompon(:ln, Coc:,lio'g..

. .,Wate,<:rM1~1

FIGURE 1-1 TMl-1 Liquid Effluent Pathways Page 1 of 1 CY-TM-170-300 Revision 5 Page 104 of 222 © *eomposite~R d ... .'.' . . :$ami:;,l~r

. a lation Monitor Auxiliary E!oiler ,Blow.down

• , .l:ID . Turbine Building

-Surtr . Mechanical Draft . I fr:,] Radwaste 151 .Grab l..n.J :01sposa.1 ,sample Pc:>Wdex Vessels Solids

• Graver system P<!Wdex *sun,p [BJ Intermediate

Building.

Sanitary WastaTMJ.1 andTM!-2

• Industrial
• Ooolors 'Sewage:

Treatinant .Plant . -+© + © .. Industrial* ,was'te;

• * *Ftitri!ltion system *,solids

Filter . Cake *~ t------=_.

@ . Cooling Tower Basin '51 TMl-1 ,.........,_..., _________ .....,;:t..,_;;~~~.,\;~~~ .... *,*RIVER FIGURE 1.2 TMl-2 Liquid Effluent Pathways CONTROL BUILDING SUMP TURBINE BUILDING SUMP .. . . ,,. IWTS SUMP ., CONTROL & SE~VICE AREA SUMP TENDON ACCESS GALLERY SUMP INDUSTRIAL WASTE TREATMENT SYSTEM *,_r -----,~,__---,.--+ RM*L-12 CY-TM-170-300 Revision 5 Page 105 of 222 CY-TM-170-300 Revision 5 Page 106 of 222 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liquid Effluents -10 CFR 50 Appendix I The dose from liquid effluents results from the consumption of fish and drinking water. The location of the nearest potable water intake is PP&L Brunner Island Steam Electric Station located downstream of TMI. The use of the flow of the Susquehanna River as the dilution flow is justified based on the complete mixing in the river prior tq the first potable water supply, adequately demonstrated by flume tracer die studies and additional liquid effluent release studies conducted using actual TMl-1 tritium releases. Other pathways contribute negligibly at Three Mile Island. The dose contribution from all radionuclides in liquid effluents released to the unrestricted area is calculated using the following expression: (eq 2.1) Where: Dose j = the cumulative dose commitment to the total body or any organ, j, from the liquid effluents for the total time period, in mrem. 11t = the length of the time period of actual releases, over which Ci and fare averaged for all liquid releases, in hours. Ci = the average concentration of radionuclide, i, in undiluted liquid effluent during time period 11t from any liquid release, in µCi/ml. NOTE: For Fe-55, Sr-89, Sr-90, prior to batch releases recent composite values will be used in the initial dose calculation. f = undiluted liquid waste flow, in gpm. FD = plant dilution water flowrate during the period of release, in gpm FR = actual river flowrate during the period of release or average river lowrate for the month the release is occurring, in gpm. DF = dilution factor as a result of mixing effects in the near field of the discharge structure of 0.2 (NU REG 0133) or taken to be 5 based on the inverse of 0.2. AWij and AFij = the site-related ingestion dose commitment factor to the total body or any organ, j, for each identified principle gamma and beta emitter, in mrem/hr per µCi/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway. Values for AWij are determined by the following equation: AWij = (1.14E5) x {Uw) x {DFij) Where: 1.14E5 = (1.0E6 pCi/µCi) x (1.0E3 ml/kg)+ (8760 hr/yr) Uw = Water consumption rate forceach age group in kg/yr (based on Table E-5 Reg. Guide 1.109, Rev. 1). CY-TM-170-300 Revision 5 Page 107 of 222 (eq 2.2) DFij = ingestion dose conversion factor for radionuclide, i, and for organ, j, in mrem/pCi, from Table 2.1 (Reg. Guide 1.109) Values for AFii are determined by the following equation: AFij = where: (1.14E5) x (Uf) x (DFij) x (BFi) (eq 2.2.2) 1.14E5 = defined above Uf= DFij = BFi = Fish consumption rate for each applicable age group in kg/yr (based on Table E-5 Reg. Guide 1.10_9, Rev. 1 ). ingestion dose conversion factor for radionuclide, i, and for organ, j, in mrem/pCi, from Table 2.1 (Reg. Guide 1.109, Rev. 1 ). Bioaccumulation factor for radionuclide, i, in fish, in pCi/kg per pCi/L from Table 2.2 (Reg. Guide 1.109, Rev. 1 ). 2.2 TMI Liquid Radwaste System Dose Cales Once Per Month ODCM Part I Control 2.2.1.3 and TMl-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent releases from each unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month. The following calculational method is provided for performing this dose projection. At least once per month, the total dose from all liquid releases for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual releases during the period for which the projection is made. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, appropriate portions of the Liquid Radwaste Treatment System, as defined in Section 3.1, shall be used to reduce radioactivity levels prior to release. CY-TM-170-300 Revision 5 Page 108 of 222 At the discretion of the ODCM Specialist, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter-to-date is not believed to be representative of the dose per day projected for the next month. CY-TM-170-300 Revision 5 Page 109 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 1 of 16 INGESTION DOSE FACTORS FOR ADULTS (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14(inorg) 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA-22 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 NA-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06

• 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-05 CA-41 1.85E-04 O.OOE+OO 2.00E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.84E-07 SC-46 5.51E-09 1.07E-08 3.11E-09 O.OOE+OO 9.99E-09 O.OOE+OO 5.21E-05 CR-51 O.OOE+OO O.OOE+OO 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN-54 O.OOE+OO 4.57E-06 8.72E-07 O.OOE+OO 1.36E-06 O.OOE+OO 1.40E-05 FE-55 2.75E-06 1.90E-06 4.43E-07 O.OOE+OO O.OOE+OO 1.06E-06 1.09E-06 MN-56 O.OOE+OO 1.15E-07 2.04E-08 0.00E+OO 1.46E-07 O.OOE+OO 3.67E-06 C0-57 O.OOE+OO 1.75E-07 2.91E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.44E-06 C0-58 O.OOE+OO 7.45E-07 1.67E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.51 E-05 FE-59 4.34E-06 1.02E-05 3.91E-06 O.OOE+OO O.OOE+OO 2.85E-06 3.40E-05 C0-60 O.OOE+OO 2.14E-06.

4.72E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.02.E-05 Nl-59 9.76E-06 3.35E-06 1.63E-06 O.OOE+OO O.OOE+OO O.OOE+OO 6.90E-07 Nl-63 1.30E-04 9.01E-06 4.36E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.88E-06 CU-64 O.OOE+OO 8.33E-08 3.91E-08 O.OOE+OO 2.10E-07 O.OOE+OO 7.10E-06 Nl-65 5.28E-07 6.86E-08 3.13E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.74E-06 ZN-65 4.84E-06 1.54E-05 6.96E-06 O.OOE+OO 1.03E-05 O.OOE+OO 9.70E-06 ZN-69M 1.70E-07 4.0BE-07 3.73E-08 O.OOE+OO 2.47E:07 O.OOE+OO 2.49E-05 ZN-69 1.03E-08 1.97E-08 1.37E-09 O.OOE+OO 1.28E-08 O.OOE+OO 2.96E-09 SE-79 O.OOE+OO 2.63E-06 4.39E-07 O.OOE+OO 4.55E-06 O.OOE+OO 5.38E-07 BR-82 O.OOE+OO O.OOE+OO 2.26E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.59E-06 BR-83 O.OOE+OO O.OOE+OO 4.02E-08 O.OOE+OO O.OOE+OO O.OOE+OO 5.79E-08 BR-84 O.OOE+OO O.OOE+OO 5.21E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.09E-13 BR-85 O.OOE+OO O.OOE+OO 2.14E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 2.11 E-05 9.83E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.16E-06 RB-87 O.OOE+OO 1.23E-05 4.28E-06 O.OOE+OO O.OOE+OO O.OOE+OO 5.76E-07 RB-88 O.OOE+OO 6.05E-08 3.21E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.36E-19 RB-89 O.OOE+OO 4.01E-08 2.82E-08 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-21 SR-89 3.08E-04 O.OOE+OO 8.84E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.94E-05 SR-90 7.58E-03 O.OOE+OO 1.86E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.19E-04 Y-90 9.62E-09 O.OOE+OO 2.58E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E-04 SR-91 5.67E-06 O.OOE+OO 2.29E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.70E-05 Y-91M 9.09E-11 O.OOE+OO 3.52E-12 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-10 Y-91 1.41E-07 O.OOE+OO 3.77E-09 O.OOE+OO O.OOE+OO O.OOE+OO 7.76E-05 SR-92 2.15E-06 O.OOE+OO 9.30E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.26E-05 Y-92 8.45E-10 O.OOE+OO 2.47E-11 O.OOE+OO O.OOE+OO O.OOE+OO 1.48E-05 Y-93 2.68E-09 O.OOE+OO 7.40E-11 O.OOE+OO O.OOE+OO O.OOE+OO 8.50E-05 NB-93M 2.55E-08 8.32E-09 2.05E-09 O.OOE+OO 9.57E-09 O.OOE+OO 3.84E-06 NB-95 6.22E-09 3.46E-09 1.86E-09 O.OOE+OO 3.42E-09 O.OOE+OO 2.10E-05 NB-97 5.22E-11 1.32E-11 4.82E-12 O.OOE+OO 1.54E-11 O.OOE+OO 4.87E-08 CY-TM-170-300 Revision 5 Page 110 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 2 of 16 INGESTION DOSE FACTORS FOR ADULTS (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI ZR-93 4.18E-08 2.34E-09 1.09E-09 O.OOE+OO 8.87E-09 O.OOE+OO 2.43E-06 ZR-95 3.04E-08 9.75E-09 6.60E-09 O.OOE+OO 1.53E-08 O.OOE+OO 3.09E-05 ZR-97 1.68E-09 3.39E-10 1.55E-10 O.OOE+OO 5.12E-10 O.OOE+OO 1.05E-04 M0-93 O.OOE+OO 7.51E-06 2.03E-07 O.OOE+OO 2.13E-06 O.OOE+OO 1.22E-06 M0-99 O.OOE+OO 4.31 E-06 8.20E-07 O.OOE+OO 9.76E-06 O.OOE+OO 9.99E-06 TC-99 1.25E-07 1.86E-07 5.02E-08 O.OOE+OO 2.34E-06 1.58E-08 6.0BE-06 TC-99M 2.47E-10 6.98E-10 8.89E-09 O.OOE+OO 1.06E-08 3.42E-10 4.13E-07 TC-101 2.54E-10 3.66E-10 3.59E-09 O.OOE+OO 6.59E-09 1.87E-10 1.1 OE-21 RU-103 1.85E-07 O.OOE+OO 7.97E-08 O.OOE+OO 7.06E-07 O.OOE+OO 2.16E-05 RU-105 1.54E-08 O.OOE+OO 6.0BE-09 O.OOE+OO 1.99E-07 O.OOE+OO 9.42E-06 RU-106 2.75E-06 O.OOE+OO 3.48E-07 O.OOE+OO 5.31E-06 O.OOE+OO 1.78E-04 RH-105 1.21E-07 8.85E-08 5.83E-08 O.OOE+OO 3.76E-07 O.OOE+OO 1.41 E-05 PD-107 O.OOE+OO 1.47E-07 9.40E-09 O.OOE+OO 1.32E-06 O.OOE+OO 9.11E-07 PD-109 O.OOE+OO 1.77E-07 3.99E-08 O.OOE+OO 1.01E-06 O.OOE+OO 1.96E-05 AG-110M 1.60E-07 1.48E-07 8.79E-08 O.OOE+OO . 2.91E-07 O.OOE+OO 6.04E-05 AG-111 5.81E-08 2.43E-08 1.21 E-08 O.OOE+OO 7.84E-08 O.OOE+OO 4.46E-05 CD-113M O.OOE+OO 3.18E-06 1.02E-07 O.OOE+OO 3.50E-06 O.OOE+OO 2.56E-05 CD-115M O.OOE+OO 1.84E-06 5.87E-08 O.OOE+OO 1.46E-06 O.OOE+OO 7.74E-05 SN-123 3.11E-05 5.15E-07 7.59E-07 4.38E-07 O.OOE+OO O.OOE+OO 6.33E-05 SN-125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 O.OOE+OO O.OOE+OO 1.04E-04 SN-126 8.45E-05 1.67E-06 2.40E-06 4.92E-07 O.OOE+OO O.OOE+OO 2.43E-05 SB-124 2.80E-06 5.29E-08 1.11 E-06 6.79E-09 O.OOE+OO 2.18E-06 7.95E-05 SB-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 O.OOE+OO 1.38E-06 1.97E-05 SB-126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 O.OOE+OO 7.05E-07 9.40E-05 SB-127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 O.OOE+OO 1.53E-07 5.90E-05 TE-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+OO 1.0?E-05 TE-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 O.OOE+OO 2.27E-05 TE-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 O.OOE+OO 8.68E-06 TE-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.BOE-05 O.OOE+OO 5.79E-05 TE-129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 O.OOE+OO 2.37E-08 TE-133M 4.62E-08 2.?0E-08 2.60E-08 3.91 E-08 2.67E-07 O.OOE+OO 9.26E-09 TE-134 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 O.OOE+OO 3.59E-11 1-129 3.27E-06 2.81E-06 9.21E-06 7.23E-03 6.04E-06 O.OOE+OO 4.44E-07 1-130 7.56E-07 2.23E-06 8.BOE-07 1.89E-04 3.48E-06 O.OOE+OO 1.92E-06 1-131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 O.OOE+OO 1.57E-06 TE-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 O.OOE+OO 8.40E-05 TE-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 O.OOE+OO 2.79E-09 1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 O.OOE+OO 1.02E-07 TE-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 O.OOE+OO 7.71E-05 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 O.OOE+OO 2.22E-06 CS-134M 2.13E-08 4.48E-08 2.29E-08 O.OOE+OO 2.43E-08 3.83E-09 1.58E-08 CS-134 6.22E-05 1.48E-04 1.21E-04 O.OOE+OO 4.79E-05 1.59E-05 2.59E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+OO 2.51E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 O.OOE+OO 1.31 E-06 CY-TM-170-300 Revision 5 Page 111 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 3 of 16 INGESTION DOSE FACTORS FOR ADULTS (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI CS-135 1.95E-05 1.BOE-05 7.99E-06 O.OOE+OO 6.81E-06 2.04E-06 4.21E-07 CS-136 6.51E-06 2.57E-05 1.85E-05 O.OOE+OO 1.43E-05 1.96E-06 2.92E-06 CS-137 7.97E-05 1.09E-04 7.14E-05 O.OOE+OO 3.70E-05 1.23E-05 2.11E-06 CS-138 5.52E-08 1.09E-07 5.40E-08 O.OOE+OO 8.01E-08 7.91E-09 4.65E-13 CS-139 3.41E-08 5.0BE-08 1.85E-08 0.00E+OO 4.0?E-08 3.70E-09 1.10E-30 BA-139 9.70E-08 6.91 E-11 2.84E-09 O.OOE+OO 6.46E-11 3.92E-11 1.72E-07 BA-140 2.03E-05 2.55E-08 1.33E-06 O.OOE+OO 8.67E-09 1.46E-08 4.18E-05 LA-140 2.50E-09 1.26E-09 3.33E-10 O.OOE+OO O.OOE+OO O.OOE+OO 9.25E-05 BA-141 4.71E-08 3.56E-11 1.59E-09 O.OOE+OO 3.31 E-11 2.02E-11 2.22E-17 LA-141 3.19E-10 9.90E-11 1.62E-11 O.OOE+OO O.OOE+OO O.OOE+OO 1.18E-05 CE-141 9.36E-09 6.33E-09 7.18E-10 O.OOE+OO 2.94E-09 O.OOE+OO 2.42E-05 BA-142 2.13E-08 2.19E-11 1.34E-09 O.OOE+OO 1.85E-11 1.24E-11 3.00E-26 LA-142 1.28E-10 5.82E-11 1.45E-11 O.OOE+OO O.OOE+OO O.OOE+OO 4.25E-07 CE-143 1.65E-09 1.22E-06 1.35E-10 O.OOE+OO 5.37E-10 O.OOE+OO 4.56E-05 PR-143 9.20E-09 3.69E-09 4.56E-10 O.OOE+OO 2:13E-09 O.OOE+OO 4.03E-05 CE-144 4.BBE-07 2.04E-07 2.62E-08 O.OOE+OO 1.21E-07 O.OOE+OO 1.65E-04 PR-144 3.01 E-11 1.25E-11 1.53E-12 O.OOE+OO 7.05E-12. O.OOE+OO 4.33E-18 ND-147 6.29E-09 7.27E-09 4.35E-10 O.OOE+OO 4.25E-09 O.OOE+OO 3.49E-05 PM-147 7.54E-08 7.09E-09 2.87E-09 O.OOE+OO 1.34E-08 O.OOE+OO 8.93E-06 PM-148M 3.07E-08 7.95E-09 6.0BE-09 O.OOE+OO 1.20E-08 O.OOE+OO 6.74E-05 PM-148 7.17E-09 1.19E-09 5.99E-10 O.OOE+OO 2.25E-09 O.OOE+OO 9.35E-05 PM-149 1.52E-09 2.15E-10 8.78E-11 O.OOE+OO 4.06E-10 O.OOE+OO 4.03E-05 PM-151 6.97E-10 1.17E-10 5.91 E-11 O.OOE+OO 2.09E-10 O.OOE+OO 3.22E-05 SM-151 6.90E-08 1.19E-08 2.85E-09 O.OOE+OO 1.33E-08 O.OOE+OO 5.25E-06 SM-153 8.57E-10 7.15E-10 5.22E-11 O.OOE+OO 2.31 E-10 O.OOE+OO 2.55E-05 EU-152 1.95E-07 4.44E-08 3.90E-08 O.OOE+OO 2.75E-07 O.OOE+OO 2.56E-05 EU-154 6.15E-07 7.56E-08 5.38E-08 O.OOE+OO 3.62E-07 O.OOE+OO 5.48E-05 EU-155 8.60E-08 1.22E-08 7.87E-09 O.OOE+OO 5.63E-08 O.OOE+OO 9.60E-06 EU-156 1.37E-08 1.06E-08 1.71E-09 O.OOE+OO 7.0BE-09 O.OOE+OO 7.26E-05

• TB-160 4.70E-08 O.OOE+OO 5.86E-09 O.OOE+OO 1.94E-08 O.OOE+OO 4.33E-05 H0-166M 2.70E-07 8.43E-08 6.40E-08 O.OOE+OO 1.26E-07 O.OOE+OO 2.56E-05 W-181 9.91E-09 3.23E-09 3.46E-10 O.OOE+OO O.OOE+OO O.OOE+OO 3.68E-07 W-185 4.05E-07 1.35E-07 1.42E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.56E-05 W-187 1.03E-07 8.61E-08 3.01E-08 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E-05 NP-239 1.19E-09 1.17E-10 6.45E-11 O.OOE+OO 3.65E-10 O.OOE+OO 2.40E-05 U-232 4.13E-03 O.OOE+OO 2.95E-04 O.OOE+OO 4.47E-04 O.OOE+OO 6.78E-05 U-233 8.71 E-04 O.OOE+OO 5.28E-05 O.OOE+OO 2.03E-04 O.OOE+OO 6.27E-05 U-234 8.36E-04 O.OOE+OO 5.17E-05 O.OOE+OO 1.99E-04 O.OOE+OO 6.14E-05 U-235 8.01E-04 O.OOE+OO 4.86E-05 O.OOE+OO 1.87E-04 O.OOE+OO 7.81E-05 U-236 8.01E-04 O.OOE+OO 4.96E-05 O.OOE+OO 1.91E-04 O.OOE+OO 5.76E-05 U-237 5.52E-08 O.OOE+OO 1.47E-08 O.OOE+OO 2.27E-07 O.OOE+OO 1.94E-05 U-238 7.67E-04 O.OOE+OO 4.54E-05 O.OOE+OO 1.75E-04 O.OOE+OO 5.50E-05 CY-TM-170-300 Revision 5 Page 112 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 4 of 16 INGESTION DOSE FACTORS FOR ADULTS (mrem per pCi ingested)

Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI NP-237 1.26E-03 8.96E-05 5.54E-05 O.OOE+OO 4.12E-04 O.OOE+OO 7.94E-05 NP-238 1.37E-08 3.69E-10 2.13E-10 O.OOE+OO 1.25E-09 O.OOE+OO 3.43E-05 PU-238 6.30E-04 7.98E-05 1.71 E-05 O.OOE+OO 7.32E-05 O.OOE+OO 7.30E-05 PU-239 7.25E-04 8.71E-05 1.91 E-05 O.OOE+OO 8.11 E-05 O.OOE+OO 6.66E-05 PU-240 7.24E-04 8.?0E-05 1.91 E-05 O.OOE+OO 8.10E-05 O.OOE+OO 6.78E-05 PU-241 1.57E-05 7.45E-07 3.32E-07 O.OOE+OO 1.53E-06 O.OOE+OO 1.40E-06 PU-242 6.72E-04 8.39E-05 1.84E-05 O.OOE+OO 7.81E-05 O.OOE+OO 6.53E-05 PU-244 7.84E-04 9.61E-05 2.11E-05 O.OOE+OO 8.95E-05 O.OOE+OO 9.73E-05 AM-241 7.55E-04 7.05E-04 5.41 E-05 O.OOE+OO 4.0?E-04 O.OOE+OO 7.42E-05 AM-242M 7.61E-04 6.63E-04 5.43E-05 O.OOE+OO 4.05E-04 O.OOE+OO 9.34E-05 AM-243 7.54E-04 6.90E-04 5.30E-05 O.OOE+OO 3.99E-04 O.OOE+OO 8.?0E-05 CM-242 2.06E-05 2.19E-05 1.37E-06 O.OOE+OO 6.22E-06 O.OOE+OO 7.92E-05 CM-243 5.99E-04 5.49E-04 3.75E-05 O.OOE+OO 1.75E-04 O.OOE+OO 7.81E-05 CM-244 4.56E-04 4.27E-04 2.87E-05 O.OOE+OO 1.34E-04 O.OOE+OO 7.55E-05 CM-245 9.38E-04 8.17E-04

• 5.76E-05 O.OOE+OO 2.69E-04 O.OOE+OO 7.04E-05 CM-246 9.30E-04 8.16E-04 5.75E-05 O.OOE+OO 2.68E-04 O.OOE+OO 6.91E-05 CM-247 9.0?E-04 8.04E-04 5.67E-05 O.OOE+OO 2.64E-04 O.OOE+OO 9.09E-05 CM-248 7.54E-03 6.63E-03 4.67E-04 O.OOE+OO 2.18E-03 O.OOE+OO 1.47E-03 CF-252 2.61 E-04 O.OOE+OO 6.29E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.88E-04 CY-TM-170-300 Revision 5 Page 113 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 5 of 16 INGESTION DOSE FACTORS FOR TEENAGER (mrem per pCi ingested)

Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14(inorg) 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA-22 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 NA-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71 E-05 1.07E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E-05 CA-41 1.97E-04 O.OOE+OO 2.13E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.95E-07 SC-46 7.24E-09 1.41 E-08 4.18E-09 O.OOE+OO 1.35E-08 O.OOE+OO 4.BOE-05 CR-51 O.OOE+OO O.OOE+OO 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN-54 O.OOE+OO 5.90E-06 1.17E-06 O.OOE+OO 1.76E-06 O.OOE+OO 1.21E-05 FE-55 3.78E-06 2.68E-06 6.25E-07 O.OOE+OO O.OOE+OO 1.70E-06 1.16E-06 MN-56 O.OOE+OO 1.58E-07 2.81E-08 O.OOE+OO 2.00E-07 O.OOE+OO 1.04E-05 C0-57 O.OOE+OO 2.38E-07 3.99E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.44E-06 C0-58 O.OOE+OO 9.72E-07 2.24E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.34E-05 FE-59 5.87E-06 1.37E-05 5.29E-06 O.OOE+OO O.OOE+OO 4.32E-06 3.24E-05 C0-60 O.OOE+OO 2.81E-06 6.33E.-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.66E-05 Nl-59 1.32E-05 4.66E-06 2.24E-06 O.OOE+OO O.OOE+OO O.OOE+OO 7.31 E-07 Nl-63 1.77E-04 1.25E-05 6.00E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.99E-06 CU-64 O.OOE+OO 1.15E-07 5.41 E-08 O.OOE+OO 2.91E-07 O.OOE+OO 8.92E-06 Nl-65 7.49E-07 9.57E-08 4.36E-08 O.OOE+OO O.OOE+OO O.OOE+OO 5.19E-06 ZN-65 5.76E-06 2.00E-05 9.33E-06 O.OOE+OO 1.28E-05 O.OOE+OO 8.47E-06 ZN-69M 2.40E-07 5.66E-07 5.19E-08 O.OOE+OO 3.44E-07 O.OOE+OO 3.11 E-05 ZN-69 1.47E-08 2.BOE-08 1.96E-09 O.OOE+OO 1.83E-08 O.OOE+OO 5.16E-08 SE-79 O.OOE+OO 3.73E-06 6.27E-07 O.OOE+OO 6.50E-06 O.OOE+OO 5.70E-07 BR-82 O.OOE+OO O.OOE+OO 3.04E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-83 O.OOE+OO O.OOE+OO 5.74E-08. O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-84 O.OOE+OO O.OOE+OO 7.22E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 3.05E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 2.98E-05 1.40E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.41E-06 RB-87 O.OOE+OO 1.75E-05 6.11E-06 O.OOE+OO O.OOE+OO O.OOE+OO 6.11E-07 RB-88 O.OOE+OO 8.52E-08 4.54E-08 O.OOE+OO O.OOE+OO O.OOE+OO 7.30E-15 RB-89 O.OOE+OO 5.50E-08 3.89E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.43E-17 SR-89 4.40E-04 O.OOE+OO 1.26E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.24E-05 SR-90 8.30E-03 O.OOE+OO 2.05E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-04 Y-90 1.37E-08 O.OOE+OO 3.69E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.13E-04 SR-91 8.07E-06 O.OOE+OO 3.21E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.66E-05 Y-91M 1.29E-10 O.OOE+OO 4.93E-12 O.OOE+OO O.OOE+OO O.OOE+OO 6.09E-09 Y-91 2.01E-07 O.OOE+OO 5.39E-09 O.OOE+OO O.OOE+OO O.OOE+OO 8.24E-05 SR-92 3.05E-06 O.OOE+OO 1.30E-07 O.OOE+OO

• O.OOE+OO O.OOE+OO 7.77E-05 Y-92 1.21 E-09 O.OOE+OO 3.50E-11 O.OOE+OO O.OOE+OO O.OOE+OO 3.32E-05 Y-93 3.83E-09 O.OOE+OO 1.05E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E-04 NB-93M 3.44E-08 1.13E-08 2.83E-09 O.OOE+OO 1.32E-08 O.OOE+OO 4.07E-06 NB-95 8.22E-09 4.56E-09 2.51E-09 O.OOE+OO 4.42E-09 O.OOE+OO 1.95E-05 NB-97 7.37E-11 1.83E-11 6.68E-12 O.OOE+OO 2.14E-11 O.OOE+OO 4.37E-07 CY-TM-170-300 Revision 5 Page 114 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 6 of 16 INGESTION DOSE FACTORS FOR TEENAGER (mrem per pCi ingested)

Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI ZR-93 5.53E-08 2.73E-09 1.49E-09 O.OOE+OO 9.65E-09 O.OOE+OO 2.58E-06 ZR-95 4.12E-08 1.30E-08 8.94E-09 O.OOE+OO 1.91 E-08 O.OOE+OO 3.00E-05 ZR-97 2.37E-09 4.69E-10 2.16E-10 O.OOE+OO 7.11E-10 O.OOE+OO 1.27E-04 M0-93 O.OOE+OO 1.06E-05 2.90E-07 O.OOE+OO 3.04E-06 O.OOE+OO 1.29E-06 M0-99 O.OOE+OO 6.03E-06 1.15E-06 O.OOE+OO 1.38E-05 O.OOE+OO 1.0BE-05 TC-99 1.79E-07 2.63E-07 7.17E-08 O.OOE+OO 3.34E-06 2.72E-08 6.44E-06 TC-99M 3.32E-10 9.26E-10 1.20E-08 O.OOE+OO 1.38E-08 5.14E-10 6.0BE-07 TC-101 3.60E-10 5.12E-10 5.03E-09 O.OOE+OO 9.26E-09 3.12E-10 8.75E-17 RU-103 2.55E-07 O.OOE+OO 1.09E-07 O.OOE+OO 8.99E-07 O.OOE+OO 2.13E-05 RU-105 2.18E-08 O.OOE+OO 8.46E-09 O.OOE+OO 2.75E-07 O.OOE+OO 1.76E-05 RU-106 3.92E-06 O.OOE+OO 4.94E-07 O.OOE+OO 7.56E-06 O.OOE+OO 1.88E-04 RH-105 1.73E-07 1.25E-07 8.20E-08 O.OOE+OO 5.31E-07 O.OOE+OO 1.59E-05 PD-107 O.OOE+OO 2.0BE-07 1.34E-08 O.OOE+OO 1.88E-06 O.OOE+OO 9.66E-07 PD-109 O.OOE+OO 2.51 E-07 5.70E-08 O.OOE+OO 1.45E-06 O.OOE+OO 2.53E-05 AG-110M 2.05E-07 1.94E-07 1.18E-07 O.OOE+OO 3.70E-07 O.OOE+OO 5.45E-05 AG-111 8.29E-08 3.44E-08 1.73E-08 O.OOE+OO 1.12E-07 O.OOE+OO 4.BOE-05 CD-113M O.OOE+OO 4.51E-06 1.45E-07 O.OOE+OO 4.99E-06 O.OOE+OO 2.71E-05 CD-115M O.OOE+OO 2.60E-06 8.39E-08 O.OOE+OO 2.0BE-06 O.OOE+OO 8.23E-05 SN-123 4.44E-05 7.29E-07 1.0BE-06 5.84E-07 O.OOE+OO O.OOE+OO 6.71E-05 SN-125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 O.OOE+OO O.OOE+OO 1.12E-04 SN-126 1.16E-04 2.16E-06 3.30E-06 5.69E-07 O.OOE+OO O.OOE+OO 2.58E-05 SB-124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 O.OOE+OO 3.38E-06 7.BOE-05 SB-125 2.48E-06 2.71E-08 5.BOE-07 2.37E-09 O.OOE+OO 2.18E-06 1.93E-05 SB-126 1.59E-06 3.25E-08 5.71E-07 8.99E-09 O.OOE+OO 1.14E-06 9.41 E-05 SB-127 3.63E-07 7.76E-09 1.37E:07 4.0BE-09 O.OOE+OO 2.47E-07 6.16E-05 TE-125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 O.OOE+OO O.OOE+OO 1.13E-05 TE-127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 . O.OOE+OO 2.41 E-05 TE-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 O.OOE+OO 1.22E-05 TE-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 O.OOE+OO 6.12E-05 TE-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 O.OOE+OO 2.45E-07 TE-133M 6.44E-08 3.66E-08 3.56E-08 5.11E-08 3.62E-07 O.OOE+OO 1.48E-07 TE-134 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 O.OOE+OO 1.66E-09 1-129 4.66E-06 3.92E-06 6.54E-06 4.77E-03 7.01E-06 O.OOE+OO 4.57E-07 1-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 O.OOE+OO 2.29E-06 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 O.OOE+OO 1.62E-06 TE-131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-0/5 O.OOE+OO 9.39E-05 TE-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 O.OOE+OO 2.29E-09 1-132 . 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 O.OOE+OO 3.18E-07 TE-132 3.49E-06 2.21E-06 2.0BE-06 2.33E-06 2.12E-05 O.OOE+OO 7.00E-05 1-133 2.01E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 O.OOE+OO 2.58E-06 CS-134M 2.94E-08 6.09E-08 3.13E-08 O.OOE+OO 3.39E-08 5.95E-09 4.05E-08 CS-134 8.37E-05 1.97E-04 9.14E-05 O.OOE+OO 6.26E-05 2.39E-05 2.45E-06 CY-TM-170-300 Revision 5 Page 115 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 7 of 16 INGESTION DOSE FACTORS FOR TEENAGER (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI 1-134 1.46E-07 3.B?E-07 1.39E-07 6.45E-06 6.10E-07 O.OOE+OO 5.10E-09 1-135 6.10E-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0.00E+OO 1.74E-06 CS-135 2.?BE-05 2.55E-05 5.96E-06 O.OOE+OO 9.73E-06 3.52E-06 4.46E-07 CS-136 8.59E-06 3.38E-05 2.27E-05 O.OOE+OO 1.84E-05 2.90E-06 2.72E-06 CS-137 1.12E-04 1.49E-04 5.19E-05 O.OOE+OO 5.0?E-05 1.97E-05 2.12E-06 CS-138 7.76E-08 1.49E-07 7.45E-08 O.OOE+OO 1.10E-07 1.28E-08 6.76E-11 CS-139 4.B?E-08 7.17E-08 2.63E-08 O.OOE+OO 5.79E-08 6.34E-09 3.33E-23 BA-139 1.39E-07 9.78E-11 4.05E-09 O.OOE+OO 9.22E-11 6.74E-11 1.24E-06 BA-140 2.84E-05 3.48E-08 1.83E-06 O.OOE+OO 1.18E-08 2.34E-08 4.38E-05 LA-140 3.48E-09 1.71E-09 4.55E-10 O.OOE+OO 0.00E+OO O.OOE+OO 9.82E-05 BA-141 6.71E-08 5.01 E-11 2.24E-09 O.OOE+OO 4.65E-11 3.43E-11 1.43E-13 LA-141 4.55E-10 1.40E-10 2.31E-11 O.OOE+OO O.OOE+OO O.OOE+OO 2.48E-05 CE-141 1.33E-08 8.88E-09 1.02E-09 O.OOE+OO 4.18E-09 O.OOE+OO 2.54E-05 BA-142 2.99E-08 2.99E-11 1.84E-09 O.OOE+OO 2.53E-11 1.99E-11 9.18E-20 LA-142 1.79E-10 7.95E-11 1.98E-11 O.OOE+OO O.OOE+OO O.OOE+OO

• 2.42E-06 CE-143 2.35E-09 1.71E-06 1.91E-10 O.OOE+OO 7.67E-10 0.00E+OO 5 .. 14E-05 PR-143 1.31 E-08 5.23E-09 6.52E-10 O.OOE+OO 3.04E-09 O.OOE+OO 4.31E-05 CE-144 6.96E-07 2.88E-07 3.74E-08 O.OOE+OO 1.72E-07 O.OOE+OO 1.75E-04 PR-144 4.30E-11 1.76E-11 2.18E-12 O.OOE+OO 1.01E-11 O.OOE+OO 4.74E-14 ND-147 9.38E-09 1.02E-08 6.11E-10 O.OOE+OO 5.99E-09 O.OOE+OO 3.68E-05 PM-147 1.05E-07 9.96E-09 4.06E-09 O.OOE+OO 1.90E-08 O.OOE+OO 9.47E-06 PM-148M 4.14E-08 1.05E-08 8.21E-09 O.OOE+OO 1.59E-08 O.OOE+OO 6.61E-05 PM-148 1.02E-08 1.66E-09 8.36E-10 O.OOE+OO 3.00E-09 O.OOE+OO 9.90E-05 PM-149 2.17E-09 3.05E-10 1.25E-10 O.OOE+OO 5.81E-10 O.OOE+OO 4.49E-05 PM-151 9.87E-10 1.63E-10 8.25E-11 O.OOE+OO 2.93E-10 O.OOE+OO 3.66E-05 SM-151 8.73E-08 1.68E-08 3.94E-09 O.OOE+OO 1.84E-08 O.OOE+OO 5.?0E-06 SM-153 1.22E-09 1.01E-09 7.43E-11 O.OOE+OO 3.30E-10 O.OOE+OO 2.85E-05 EU-152 2.45E-07 5.90E-08 5.20E-08 O.OOE+OO 2.74E-07 O.OOE+OO 2.17E-05 EU-154 7.91 E-07 1.02E-07 7.19E-08 O.OOE+OO 4.56E-07 O.OOE+OO 5.39E-05 EU-155 1.74E-07 1.68E-08 1.04E-08 O.OOE+OO 6.57E-08 O.OOE+OO 9.63E-05 EU-156 1.92E-08 1.44E-08 2.35E-09 O.OOE+OO 9.69E-09 O.OOE+OO 7.36E-05 TB-160 6.47E-08 O.OOE+OO 8.0?E-09 O.OOE+OO 2.56E-08 O.OOE+OO 4.19E-05 H0-166M 3.57E-07 1.10E-07 7.96E-08 O.OOE+OO 1.61E-07 O.OOE+OO 2.71E-05 W-181 1.42E-08 4.58E-09 4.79E-10 O.OOE+OO O.OOE+OO O.OOE+OO 3.90E-07 W-185 5.79E-07 1.91 E-07 2.02E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.65E-05 W-187 1.46E-07 1.19E-07 4.17E-08 O.OOE+OO O.OOE+OO O.OOE+OO 3.22E-05 NP-239 1.76E-09 1.66E-10 9.22E-11 O.OOE+OO 5.21E-10 O.OOE+OO 2.67E-05 U-232 5.89E-03 O.OOE+OO 4.21 E-04 O.OOE+OO 6.38E-04 O.OOE+OO 7.19E-05 U-233 1.24E-03 O.OOE+OO 7.54E-05 O.OOE+OO 2.90E-04 O.OOE+OO 6.65E-05 U-234 1.19E-03 O.OOE+OO 7.39E-05 O.OOE+OO 2.85E-04 O.OOE+OO 6.51E-05 CY-TM-170-300 Revision 5 Page 116 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 8 of 16 INGESTION DOSE FACTORS FOR TEENAGER (mrem per pCi ingested)

Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI U-235 1.14E-03 O.OOE+OO 6.94E-05 O.OOE+OO 2.67E-04 O.OOE+OO 8.28E-05 U-236 1.14E-03 O.OOE+OO 7.09E-05 O.OOE+OO 2.73E-04 O.OOE+OO 6.11E-05 U-237 7.89E-08 O.OOE+OO 2.10E-08 O.OOE+OO 3.24E-07 O.OOE+OO 2.09E-05 U-238 1.09E-03 O.OOE+OO 6.49E-05 O.OOE+OO 2.50E-04 O.OOE+OO 5.83E-05 NP-237 1.33E-03 9.55E-05 5.85E-05 O.OOE+OO 4.33E-04 O.OOE+OO 8.41E-05 NP-238 1.95E-08 5.22E-10 3.04E-10 O.OOE+OO 1.79E-09 O.OOE+OO 3.83E-05 PU-238 6.?0E-04 8.58E-05 1.82E-05 O.OOE+OO 7.BOE-05 O.OOE+OO 7.73E-05 PU-239 7.65E-04 9.29E-05 2.01E-05 O.OOE+OO 8.57E-05 O.OOE+OO 7.06E-05 PU-240 7.64E-04 9.27E-05 2.01E-05 O.OOE+OO 8.56E-05 O.OOE+OO 7.19E-05 PU-241 1.75E-05 8.40E-07 3.69E-07 O.OOE+OO 1.71E-06 O.OOE+OO 1.48E-06 PU-242 7.09E-04 8.94E-05 1.94E-05 O.OOE+OO 8.25E-05 O.OOE+OO 6.92E-05 PU-244 8.28E-04 1.02E-04 2.22E-05 O.OOE+OO 9.45E-05 O.OOE+OO 1.03E-04 AM-241 7.98E-04 7.53E-04 5.75E-05 O.OOE+OO 4.31E-04 O.OOE+OO 7.87E-05 AM-242M 8.0?E-04 7.11E-04 5.BOE-05 O.OOE+OO 4.30E-04 O.OOE+OO 9.90E-05 AM-243 7.96E-04 7.35E-04 5.62E-05 O.OOE+OO 4.22E-04 O.OOE+OO 9.23E-05 CM-242 2.94E-05 3.10E-05 1.95E-06 O.OOE+OO 8.89E-06 O.OOE+OO 8.40E-05 CM-243 6.50E-04 6.03E-04 4.09E-05 O.OOE+OO 1.91E-04 O.OOE+OO 8.28E-05 CM-244 5.04E-04 4.77E-04 3.19E-05 O.OOE+OO 1.49E-04 O.OOE+OO 8.00E-05 CM-245 9.90E-04 8.71E-04 6.10E-05 O.OOE+OO 2.85E-04 O.OOE+OO 7.46E-05 CM-246 9.82E-04 8.?0E-04 6.09E-05 O.OOE+OO 2.84E-04 O.OOE+OO 7.33E-05 CM-247 9.57E-04 8.57E-04 6.00E-05 O.OOE+OO 2.80E-04 O.OOE+OO 9.63E-05 CM-248 7.95E-03 7.06E-03 4.95E-04 O.OOE+OO 2.31E-03 O.OOE+OO 1.55E-03 CF-252 3.47E-04 O.OOE+OO 8.37E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.05E-04 CY-TM-170-300 Revision 5 Page 117 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 9 of 16 INGESTION DOSE FACTORS FOR CHILD (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14(inorg) 1.21 E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA-22 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 NA-24 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 P-32 8.25E-04 3.86E-05 3.18E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.28E-05 CA-41 3.47E-04 O.OOE+OO 3.79E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.90E-07 SC-46 1.97E-08 2.70E-08 1.04E-08 O.OOE+OO 2.39E-08 O.OOE+OO 3.95E-05 CR-51 O.OOE+OO O.OOE+OO 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN-54 O.OOE+OO 1.07E-05 2.85E-06 O.OOE+OO 3.00E-06 O.OOE+OO 8.98E-06 FE-55 1.15E-05 6.10E-06 1.89E-06 O.OOE+OO O.OOE+OO 3.45E-06 1.13E-06 MN-56 O.OOE+OO 3.34E-07 7.54E-08 O.OOE+OO 4.04E-07 O.OOE+OO 4.84E-05 C0-57 O.OOE+OO 4.93E-07 9.98E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.04E-06 C0-58 O.OOE+OO 1.BOE-06 5.51E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.0SE-05 FE-59 1.65E-05 2.67E-05 1.33E-05 O.OOE+OO O.OOE+OO 7.74E-06 2.78E-05 C0-60 O.OOE+OO 5.29E-06 1.56E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.93E-05 Nl-59 4.02E-05 1.07E-05 6.82E-06 O.OOE+OO O.OOE+OO O.OOE+OO 7.10E-07 Nl-63 5.38E-04 2.88E-05 1.83E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E-06 CU-64 O.OOE+OO 2.45E-07 1.48E-07 O.OOE+OO 5.92E-07 O.OOE+OO 1.15E-05 Nl-65 2.22E-06 2.09E-07 1.22E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.56E-05 ZN-65 1.37E-05 3.65E-05 2.27E-05 O.OOE+OO 2.30E-05 O.OOE+OO 6.41 E-06 ZN-69M 7.10E-07 1.21 E-06 1.43E-07 O.OOE+OO 7.03E-07 O.OOE+OO 3.94E-05 ZN-69 4.38E-08 6.33E-08 5.85E-09 O.OOE+OO 3.84E-08 O.OOE+OO 3.99E-06 SE-79 O.OOE+OO 8.43E-06 1.87E-06 O.OOE+OO 1.37E-05 O.OOE+OO 5.53E-07 BR-82 O.OOE+OO O.OOE+OO 7.55E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-83 O.OOE+OO O.OOE+OO 1.71 E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-84 O.OOE+OO O.OOE+OO 1.98E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 9.12E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 6.70E-05 4.12E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.31E-06 RB-87 O.OOE+OO 3.95E-05 1.83E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.92E-07 RB-88 O.OOE+OO 1.90E-07 1.32E-07 O.OOE+OO O.OOE+OO O.OOE+OO 9.32E-09 RB-89 O.OOE+OO 1.17E-07 1.04E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E-09 SR-89 1.32E-03 O.OOE+OO 3.77E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.11E-05 SR-90 1.70E-02 O.OOE+OO 4.31E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-04 Y-90 4.11E-08 O.OOE+OO 1.10E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E-04 SR-91 2.40E-05 O.OOE+OO 9.06E-07 O.OOE+OO O.OOE+OO O.OOE+OO 5.30E-05 Y-91M 3.82E-10 O.OOE+OO 1.39E-11 O.OOE+OO O.OOE+OO O.OOE+OO 7.48E-07 Y-91 6.02E-07 O.OOE+OO 1.61 E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.02E-05 SR-92 9.03E-06 O.OOE+OO 3.62E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.71 E-04 Y-92 3.60E-09 O.OOE+OO 1.03E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E-04 Y-93 1.14E-08 O.OOE+OO 3.13E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.70E-04 NB-93M 1.0SE-07 2.62E-08 8.61E-09 O.OOE+OO 2.83E-08 O.OOE+OO 3.95E-06 NB-95 2.25E-08 8.76E-09 6.26E-09 O.OOE+OO 8.23E-09 O.OOE+OO 1.62E-05 CY-TM-170-300 Revision 5 Page 118 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 10 of 16 INGESTION DOSE FACTORS FOR CHILD (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI NB-97 2.17E-10 3.92E-11 1.83E-11 O.OOE+OO 4.35E-11 O.OOE+OO 1.21 E-05 ZR-93 1.67E-07 6.25E-09 4.45E-09 O.OOE+OO 2.42E-08 O.OOE+OO 2.37E-06 ZR-95 1.16E-07 2.55E-08 2.27E-08 O.OOE+OO 3.65E-08 O.OOE+OO 2.66E-05 ZR-97 6.99E-09 1.01 E-09 5.96E-10 O.OOE+OO 1.45E-09 O.OOE+OO 1.53E-04 M0-93 O.OOE+OO 2.41E-05 8.65E-07 O.OOE+OO 6.35E-06 O.OOE+OO 1.22E-06 M0-99 O.OOE+OO 1.33E-05 3.29E-06 O.OOE+OO 2.84E-05 O.OOE+OO 1.10E-05 TC-99 5.35E-07 5.96E-07 2.14E-07 O.OOE+OO 7.02E-06 5.27E-08 6.25E-06 TC-99M 9.23E-10 1.81 E-09 3.00E-08 O.OOE+OO 2.63E-08 9.19E-10 1.03E-06 TC-101 1.0?E-09 1.12E-09 1.42E-08 O.OOE+OO 1.91 E-08 5.92E-10 3.56E-09 RU-103 7.31E-07 O.OOE+OO 2.81E-07 O.OOE+OO 1.84E-06 O.OOE+OO 1.89E-05 RU-105 6.45E-08 O.OOE+OO 2.34E-08 O.OOE+OO 5.67E-07 O.OOE+OO 4.21E-05 RU-106 1.17E-05 O.OOE+OO 1.46E-06 O.OOE+OO 1.58E-05 O.OOE+OO 1.82E-04 RH-105 5.14E-07 2.76E-07 2.36E-07 O.OOE+OO 1.10E-06 O.OOE+OO 1.71E-05 PD-107 O.OOE+OO 4.72E-07 4.01E-08 O.OOE+OO 3.95E-06 O.OOE+OO 9.37E-07 PD-109 O.OOE+OO 5.67E-07 1.?0E-07 O.OOE+OO 3.04E-06 O.OOE+OO 3.35E-05 AG-110M 5.39E-07 3.64E-07 2.91E-07 O.OOE+OO 6.78E-07 O.OOE+OO 4.33E-05 AG-111 2.48E-07 7.76E-08 5.12E-08 O.OOE+OO 2.34E-07 O.OOE+OO 4.75E-05 CD-113M O.OOE+OO 1.02E-05 4.34E-07 O.OOE+OO 1.0SE-05 O.OOE+OO 2.63E-05 CD-115M O.OOE+OO 5.89E-06 2.51E-07 O.OOE+OO 4.38E-06 O.OOE+OO 8.01E-05 SN-123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 O.OOE+OO O.OOE+OO 6.52E-05 SN-125 3.55E-05 5.35E-07 1.59E-06 5.55E-07 O.OOE+OO O.OOE+OO 1.10E-04 SN-126 3.33E-04 4.15E-06 9.46E-06 1.14E-06 O.OOE+OO O.OOE+OO 2.SOE-05 SB-124 1.11 E-05 1.44E-07 3.89E-06 2.45E-08 O.OOE+OO 6.16E-06 6.94E-05 SB-125 7.16E-06 5.52E-08 1.SOE-06 6.63E-09 O.OOE+OO 3.99E-06 1.71 E-05 SB-126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 O.OOE+OO 2.10E-06 8.87E-05 SB-127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 O.OOE+OO 4.60E-07 5.97E-05 TE-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 O.OOE+OO O.OOE+OO 1.10E-05 TE-127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 O.OOE+OO 2.34E-05 TE-127 4.71E-07 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 O.OOE+OO 1.84E-05 TE-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 O.OOE+OO 5.94E-05 TE-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 O.OOE+OO 8.34E-06 TE-133M 1.87E-07 7.56E-08 9.37E-08 1.45E-07 7.18E-07 O.OOE+OO 5.77E-06 TE-134 1.29E-07 5.BOE-08 7.74E-08 1.02E-07 5.37E-07 O.OOE+OO 5.89E-07 1-129 1.39E-05 8.53E-06 7.62E-06 5.58E-03 1.44E-05 O.OOE+OO 4.29E-07 1-130 2.92E-06 5.90E-06 3.04E-06 6.SOE-04 8.82E-06 O.OOE+OO 2.76E-06 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 O.OOE+OO 1.54E-06 TE-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 O.OOE+OO 1.01 E-04 TE-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 O.OOE+OO 4.36E-07 1-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 O.OOE+OO 1.73E-06 TE-132 1.01 E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 O.OOE+OO 4.SOE-05 CY-TM-170-300 Revision 5 Page 119 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 11 of 16 INGESTION DOSE FACTORS FOR CHILD (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LU 1-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 O.OOE+OO 2.95E-06 CS-134M 8.44E-08 1.25E-07 8.16E-08 O.OOE+OO 6.59E-08 1.09E-08 1.58E-07 CS-134 2.34E-04 3.84E-04 8.10E-05 O.OOE+OO 1.19E-04 4.27E-05 2.0?E-06 1-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 O.OOE+OO 5.16E-07 1-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 O.OOE+OO 2.40E-06 CS-135 8.30E-05 5.78E-05 5.93E-06 O.OOE+OO 2.04E-05 6.81E-06 4.33E-07 CS-136 2.35E-05 6.46E-05 4.18E-05 O.OOE+OO 3.44E-05 5.13E-06 2.27E-06 CS-137 3.27E-04 3.13E-04 4.62E-05 O.OOE+OO 1.02E-04 3.67E-05 1.96E-06 CS-138 2.28E-07 3.17E-07 2.01E-07 O.OOE+OO 2.23E-07 2.40E-08 1.46E-07 CS-139 1.45E-07 1.61 E-07 7.74E-08 O.OOE+OO 1.21E-07 1.22E-08 1.45E-11 BA-139 4.14E-07 2.21E-10 1.20E-08 O.OOE+OO 1.93E-10 1.30E-10 2.39E-05 BA-140 8.31E-05 7.28E-08 4.85E-06 O.OOE+OO 2.37E-08 4.34E-08 4.21 E-05 LA-140 1.01 E-08 3.53E-09 1.19E-09 O.OOE+OO O.OOE+OO O.OOE+OO 9.84E-05 BA-141 2.00E-07 1.12E-10 6.51E-09 O.OOE+OO 9.69E-11 6.58E-10 1.14E-07 LA-141 1.36E-09 3.17E-10 6.88E-11 O.OOE+OO O.OOE+OO O.OOE+OO 7.05E-05 CE-141 3.97E-08 1.98E-08 2.94E-09 O.OOE+OO 8.68E-09 O.OOE+OO 2.47E-05 BA-142 8.74E-08 6.29E-11 4.88E-09 O.OOE+OO 5.09E-11 3.?0E-11 1.14E-09 LA-142 5.24E-10 1.67E-10 5.23E-11 O.OOE+OO O.OOE+OO O.OOE+OO 3.31E-05 CE-143 6.99E-09 3.79E-06 5.49E-10 O.OOE+OO 1.59E-09 O.OOE+OO 5.55E-05 PR-143 3.93E-08 1.18E-08 1.95E-09 O.OOE+OO 6.39E-09 O.OOE+OO 4.24E-05 CE-144 2.0BE-06 6.52E-07 1.11 E-07 O.OOE+OO 3.61E-07 O.OOE+OO 1.?0E-04 PR-144 1.29E-10 3.99E-11 6.49E-12 O.OOE+OO 2.11E-11 O.OOE+OO 8.59E-08 ND-147 2.79E-08 2.26E-08 1.75E-09 O.OOE+OO 1.24E-08 O.OOE+OO 3.58E-05 PM-147 3.18E-07 2.27E-08 1.22E-08 O.OOE+OO 4.01E-08 O.OOE+OO 9.19E-06 PM-148M 1.03E-07 2.05E-08 2.05E-08 O.OOE+OO 3.04E-08 O.OOE+OO 5.78E-05 PM-148 3.02E-08 3.63E-09 2.35E-09 O.OOE+OO 6.17E-09 O.OOE+OO 9.?0E-05 PM-149 6.49E-09 6.90E-10 3.74E-10 O.OOE+OO 1.22E-09 O.OOE+OO 4.71 E-05 PM-151 2.92E-09 3.55E-10 2.31E-10 O.OOE+OO 6.02E-10 O.OOE+OO 4.03E-05 SM-151 2.56E-07 3.81E-08 1.20E-08 O.OOE+OO 3.94E-08 O.OOE+OO 5.53E-06 SM-153 3.65E-09 2.27E-09 2.19E-10 O.OOE+OO 6.91E-10 O.OOE+OO 3.02E-05 EU-152 6.15E-07 1.12E-07 1.33E-07 O.OOE+OO 4.73E-07 O.OOE+OO 1.84E-05 EU-154 2.30E-06 2.0?E-07 1.89E-07 O.OOE+OO 9.09E-07 O.OOE+OO 4.81E-05 EU-155 4.82E-07 3.47E-08 2.72E-08 O.OOE+OO 1.30E-07 O.OOE+OO 8.69E-05 EU-156 5.62E-08 3.01E-08 6.23E-09 O.OOE+OO 1.94E-08 O.OOE+OO 6.83E-05 TB-160 1.66E-07 O.OOE+OO 2.06E-08 O.OOE+OO 4.94E-08 O.OOE+OO 3.68E-05 H0-166M 1.0BE-06 2.26E-07 1.91 E-07 O.OOE+OO 3.22E-07 O.OOE+OO 2.63E-05 W-181 4.23E-08 1.04E-08 1.43E-09 O.OOE+OO O.OOE+OO O.OOE+OO 3.79E-07 W-185 1.73E-06 4.32E-07 6.05E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.61 E-05 W-187 4.29E-07 2.54E-07 1.14E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.57E-05 NP-239 5.25E-09 3.77E-10 2.65E-10 O.OOE+OO 1.09E-09 O.OOE+OO 2.79E-05 U-232 1.76E-02 O.OOE+OO 1.26E-03 O.OOE+OO 1.34E-03 O.OOE+OO 6.98E-05 U-233 3.72E-03 O.OOE+OO 2.25E-04 O.OOE+OO 6.10E-04 O.OOE+OO 6.45E-05 CY-TM-170-300 Revision 5 Page 120 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 12 of 16 INGESTION DOSE FACTORS FOR CHILD (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI U-234 3.57E-03 O.OOE+OO 2.21E-04 O.OOE+OO 5.98E-04 O.OOE+OO 6.32E-05 U-235 3.42E-03 O.OOE+OO 2.0?E-04 O.OOE+OO 5.61E-04 O.OOE+OO 8.03E-05 U-236 3.42E-03 O.OOE+OO 2.12E-04 O.OOE+OO 5.73E-04 O.OOE+OO 5.92E-05 U-237 2.36E-07 O.OOE+OO 6.27E-08 O.OOE+OO 6.81E-07 O.OOE+OO 2.0BE-05 U-238 3.27E-03 O.OOE+OO 1.94E-04 O.OOE+OO 5.24E-04 O.OOE+OO 5.66E-05 NP-237 2.23E-03 1.47E-04 9.79E-05 O.OOE+OO 6.05E-04 O.OOE+OO 8.16E-05 NP-238 5.83E-08 1.18E-09 9.0BE-10 O.OOE+OO 3.76E-09 0.00E+OO 4.04E-05 PU-238 1.19E-03 1.38E-04 3.16E-05 O.OOE+OO 1.15E-04 O.OOE+OO 7.50E-05 PU-239 1.29E-03 1.38E-04 3.31E-05 O.OOE+OO 1.22E-04 O.OOE+OO 6.85E-05 PU-240 1.28E-03 1.43E-04 3.31E-05 O.OOE+OO 1.22E-04 O.OOE+OO 6.98E-05 PU-241 3.87E-05 1.58E-06 8.04E-07 O.OOE+OO 2.96E-06 O.OOE+OO 1.44E-06 PU-242 1.19E-03 1.38E-04 3.19E-05 O.OOE+OO 1.17E-04 O.OOE+OO 6.71E-05 PU-244 1.39E-03 1.58E-03 3.65E-05 O.OOE+OO 1.35E-04 O.OOE+OO 1.00E-04 AM-241 1.36E-03 1.17E-03 1.02E-04 O.OOE+OO 6.23E-04 O.OOE+OO 7.64E-05 AM-242M 1.40E-03 1.12E-03 1.04E-04 O.OOE+OO 6.30E-04 O.OOE+OO 9.61E-05 AM-243 1.34E-03 1.13E-03 9.83E-05 O.OOE+OO 6.06E-04 O.OOE+OO 8.95E-05 CM-242 8.78E-05 7.01E-05 5.84E-06 O.OOE+OO 1.87E-05 O.OOE+OO 8.16E-05 CM-243 1.28E-03 1.04E-03 8.24E-05 O.OOE+OO 3.0BE-04 O.OOE+OO 8.03E-05 CM-244 1.0BE-03 8.74E-04 6.93E-05 O.OOE+OO 2.54E-04 O.OOE+OO 7.77E-05 CM-245 1.67E-03 1.34E-03 1.05E-04 O.OOE+OO 4.11E-04 O.OOE+OO 7.24E-05 CM-246 1.65E-03 1.34E-03 1.05E-04 O.OOE+OO 4.10E-04 O.OOE+OO 7.11 E-05 CM-247 1.61E-03 1.32E-03 1.03E-04 O.OOE+OO 4.04E-04 O.OOE+OO 9.35E-05 CM-248 1.34E-02 1.09E-02 8.52E-04 O.OOE+OO 3.33E-03 O.OOE+OO 1.51 E-03 CF-252 1.05E-03 O.OOE+OO 2.54E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.96E-04 CY-TM-170-300 Revision 5 Page 121 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 13 of 16 INGESTION DOSE FACTORS FOR INFANT (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 3.0BE-07 3.0BE-07 3.0BE-07 3.0BE-07 3.0BE-07 3.08E-07 C-14(inorg) 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA-22 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 NA-24 1.01 E-05 1.01 E-05 1.01 E-05 1.01E-05 1.01 E-05 1.01E-05 1.01 E-05 P-32 1.70E-03 1.00E-04 6.59E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.30E-05 CA-41 3.74E-04 O.OOE+OO 4.0BE-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.91 E-07 SC-46 3.75E-08 5.41E-08 1.69E-08 O.OOE+OO 3.56E-08 O.OOE+OO 3.53E-05 CR-51 O.OOE+OO O.OOE+OO 1.41 E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN-54 O.OOE+OO 1.99E-05 4.51E-06 O.OOE+OO 4.41E-06 O.OOE+OO 7.31E-06 FE-55 1.39E-05 8.98E-06 2.40E-06 0.00E+OO O.OOE+OO 4.39E-06 1.14E-06 MN-56 O.OOE+OO 8.18E-07 1.41 E-07 O.OOE+OO 7.03E-07 O.OOE+OO 7.43E-05 C0-57 O.OOE+OO 1.15E-06 1.87E-06 O.OOE+OO O.OOE+OO O.OOE+OO .3.92E-06 C0-58 O.OOE+OO 3.60E-06 8.98E-06 O.OOE+OO O.OOE+OO O.OOE+OO 8.97E-06 FE-59 3.08E-05 5.38E-05 2.12E-05 O.OOE+OO O.OOE+OO 1.59E-05 2.57E-05 C0-60 O.OOE+OO 1.08E-05 2.55E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.57E-05 Nl-59 4.73E-05 1.45E-05 8.17E-06 O.OOE+OO O.OOE+OO O.OOE+OO 7.16E-07 Nl-63 6.34E-04 3.92E-05 2.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.95E-06 CU-64 O.OOE+OO 6.09E-07 2.82E-07 O.OOE+OO 1.03E-06 O.OOE+OO 1.25E-05 Nl-65 4.70E-06 5.32E-07 2.42E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.05E-05 ZN-65 1.84E-05 6.31E-05 2.91E-05 O.OOE+OO 3.06E-05 O.OOE+OO 5.33E-05 ZN-69M 1.50E-06 3.06E-06 2.79E-07 O.OOE+OO 1.24E-06 O.OOE+OO 4.24E-05 ZN-69 9.33E-08 1.68E-07 1.25E-08 O.OOE+OO 6.98E-08 O.OOE+OO 1.37E-05 SE-79 O.OOE+OO 2.10E-05 3.90E-06 O.OOE+OO 2.43E-05 O.OOE+OO 5.58E-07 BR-82 O.OOE+OO O.OOE+OO 1.27E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-83 O.OOE+OO O.OOE+OO 3.63E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-84 O.OOE+OO O.OOE+OO 3.82E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 1.94E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 1.70E-04 8.40E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.35E-06 RB-87 O.OOE+OO 8.88E-05 3.52E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.98E-07 RB-88 O.OOE+OO 4.98E-07 2.73E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.85E-07 RB-89 O.OOE+OO 2.86E-07 1.97E-07 O.OOE+OO O.OOE+OO O.OOE+OO 9.74E-08 SR-89 2.51E-03 O.OOE+OO 7.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.16E-05 SR-90 1.85E-02 O.OOE+OO 4.71 E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.31 E-04 Y-90 8.69E-08 O.OOE+OO 2.33E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.20E-04 SR-91 5.00E-05 O.OOE+OO 1.81E-06 O.OOE+OO O.OOE+OO O.OOE+OO 5.92E-05 Y-91M 8.10E-10 O.OOE+OO 2.76E-11 O.OOE+OO O.OOE+OO O.OOE+OO 2.70E-06 Y-91 1.13E-06 O.OOE+OO 3.01E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.10E-05 SR-92 1.92E-05 O.OOE+OO 7.13E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.07E-04 Y-92 7.65E-09 O.OOE+OO 2.15E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.46E-04 Y-93 2.43E-08 O.OOE+OO 6.62E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.92E-04 NB-93M 1.23E-07 3.33E-08 1.04E-08 O.OOE+OO 3.25E-08 O.OOE+OO 3.98E-06 CY-TM-170-300 Revision 5 Page 122 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 14 of 16 INGESTION DOSE FACTORS FOR INFANT (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI NB-95 4.20E-08 1.73E-08 1.00E-08 O.OOE+OO 1.24E-08 O.OOE+OO 1.46E-05 NB-97 4.59E-10 9.79E-11 3.53E-11 O.OOE+OO 7.65E-11 O.OOE+OO 3.09E-05 ZR-93 1.93E-07 9.19E-09 5.54E-09 O.OOE+OO 2.71E-08 O.OOE+OO 2.39E-06 ZR-95 2.06E-07 5.02E-08 3.56E-08 O.OOE+OO 5.41E-08 O.OOE+OO 2.50E-05 ZR-97 1.48E-08 2.54E-09 1.16E-09 O.OOE+OO 2.56E-09 O.OOE+OO 1.62E-04 M0-93 O.OOE+OO 5.65E-05 1.82E-06 O.OOE+OO 1.13E-05 O.OOE+OO 1.21 E-06 M0-99 O.OOE+OO 3.40E-05 6.63E-06 O.OOE+OO 5.08E-05 O.OOE+OO 1.12E-05 TC-99 1.08E-06 1.46E-06 4.55E-07 O.OOE+OO 1.23E-05 1.42E-07 6.31E-06 TC-99M 1.92E-09 3.96E-09 5.10E-08 O.OOE+OO 4.26E-08 2.07E-09 1.15E-06 TC-101 2.27E-09 2.86E-09 2.83E-08 O.OOE+OO 3.40E-08 1.56E-09 4.86E-07 RU-103 1.48E-06 O.OOE+OO 4.95E-07 O.OOE+OO 3.08E-06 O.OOE+OO 1.80E-05 RU-105 1.36E-07 O.OOE+OO 4.58E-08 O.OOE+OO 1.00E-06 O.OOE+OO 5.41 E-05 RU-106 2.41E-05 O.OOE+OO 3.01E-06 O.OOE+OO 2.85E-05 O.OOE+OO 1.83E-04 RH-105 1.09E-06 7.13E-07 4.79E-07 O.OOE+OO 1.98E-06 O.OOE+OO 1.77E-05 PD-107 O.OOE+OO 1.19E-06 8.45E-08 O.OOE+Ob 6.79E-06 O.OOE+OO 9.46E-07 PD-109 O.OOE+OO 1.50E-06 3.62E-07 O.OOE+OO 5.51E-06 O.OOE+OO 3.68E-05 AG-110M 9.96E-07 7.27E-07 4.81E-07 O.OOE+OO 1.04E-06 O.OOE+OO 3.77E-05 AG-111 5.20E-07 2.02E-07 1.07E-07 O.OOE+OO 4.22E-07 O.OOE+OO 4.82E-05 CD-113M O.OOE+OO 1.77E-05 6.52E-07 O.OOE+OO 1.34E-05 O.OOE+OO 2.66E-05 CD-115M O.OOE+OO 1.42E-05 4.93E-07 O.OOE+OO 7.41E-06 O.OOE+OO 8.09E-05 SN-123 2.49E-04 3.89E-06 6.50E-06 3.91E-06 O.OOE+OO O.OOE+OO 6.58E-05 SN-125 7.41E-05 1.38E-06 3.29E-06 1.36E-06 O.OOE+OO O.OOE+OO 1.11E-04 SN-126 5.53E-04 7.26E-06 1.80E-05 1.91 E-06 O.OOE+OO O.OOE+OO 2.52E-05 SB-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 O.OOE+OO 1.34E-05 6.60E-05 SB-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 O.OOE+OO 7.12E-06 1.64E-05 SB-126 8.06E-06 1.58E-07 2.91E-06 6.19E-08 O.OOE+OO 5.07E-06 8.35E-05 SB-127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 O.OOE+OO 1.15E-06 5.91E-05 TE-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 . O.OOE+OO O.OOE+OO 1.11 E-05 TE-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+OO 2.36E-05 TE-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 O.OOE+OO 2.10E-05 TE-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 O.OOE+OO 5.97E-05 TE-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 O.OOE+OO 2.27E-05 TE-133M 3.91E-07 1.79E-07 1.71E-07 3.45E-07 1.22E-06 O.OOE+OO 1.93E-05 TE-134 2.67E-07 1.34E-07 1.38E-07 2.39E-07 9.03E-07 O.OOE+OO 3.06E-06 1-129 2.86E-05 2.12E-05 1.55E-05 1.36E-02 2.51E-05 O.OOE+OO 4.24E-07 1-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 O.OOE+OO 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 O.OOE+OO 1.51E-06 TE-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 O.OOE+OO 1.03E-04 TE-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 O.OOE+OO 7.11 E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+OO 2.73E-06 TE-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 O.OOE+OO 3.81E-05 CY-TM-170-300 Revision 5 Page 123 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 15 of 16 INGESTION DOSE FACTORS FOR INFANT (mrem per pCi ingested) Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI 1-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 O.OOE+OO 3.08E-06 CS-134M 1.76E-07 2.93E-07 1.48E-07 O.OOE+OO 1.13E-07 2.60E-08 2.32E-07 CS-134 3.77E-04 7.03E-04 7.10E-05 O.OOE+OO 1.81 E-04 7.42E-05 1.91 E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+OO 1.84E-06 1-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+OO 2.62E-06 CS-135 1.33E-04 1.21 E-04 6.30E-06 O.OOE+OO 3.44E-05 1.31 E-05 4.37E-07 CS-136 4.59E-05 1.35E-04 5.04E-05 O.OOE+OO 5.38E-05 1.10E-05 2.0SE-06 CS-137 5.22E-04 6.11E-04 4.33E-05 O.OOE+OO 1.64E-04 6.64E-05 1.91 E-06 CS-138 4.81 E-07 7.82E-07 3.79E-07 O.OOE+OO 3.90E-07 6.09E-08 1.25E-06 CS-139 3.10E-07 4.24E-07 1.62E-07 O.OOE+OO 2.19E-07 3.30E-08 2.66E-08 BA-139 8.81E-07 5.84E-10 2.55E-08 O.OOE+OO 3.51E-10 3.54E-10 5.58E-05 BA-140 1.71E-04 1.71 E-07 8.81E-06 O.OOE+OO 4.06E-08 1.0SE-07 4.20E-05 LA-140 2.11 E-08 8.32E-09 2.14E-09 O.OOE+OO O.OOE+OO O.OOE+OO 9.77E-05 BA-141 4.25E-07 2.91E-10 1.34E-08 O.OOE+OO 1.75E-10 1.77E-10 5.19E-06 LA-141 2.89E-09 8.38E-10 1.46E-10 O.OOE+OO O.OOE+OO O.OOE+OO 9.61E-05 CE-141 7.87E-08 4.80E-08 5.65E-09 O.OOE+OO 1.48E-08 O.OOE+OO 2.48E-05 BA-142 1.84E-07 1.53E-10 9.06E-09 O.OOE+OO 8.81E-11 9.26E-11 7.59E-07 LA-142 1.1 OE-09 4.04E-10 9.67E-11 O.OOE+OO O.OOE+OO O.OOE+OO 6.86E-05 CE-143 1.48E-08 9.82E-06 1.12E-09 O.OOE+OO 2.86E-09 O.OOE+OO 5.73E-05 PR-143 8.13E-08 3.04E-08 4.03E-09 O.OOE+OO 1.13E-08 O.OOE+OO 4.29E-05 CE-144 2.98E-06 1.22E-06 1.67E-07 O.OOE+OO 4.93E-07 O.OOE+OO 1.71 E-04 PR-144 2.74E-10 1.06E-10 1.38E-11 O.OOE+OO 3.84E-11 O.OOE+OO 4.93E-06 ND-147 5.53E-08 5.68E-08 3.48E-09 O.OOE+OO 2.19E-08 O.OOE+OO 3.60E-05 PM-147 3.88E-07 3.27E-08 1.59E-08 O.OOE+OO 4.88E-08 O.OOE+OO 9.27E-06 PM-148M 1.65E-07 4.18E-08 3.28E-08 O.OOE+OO 4.80E-08 O.OOE+OO 5.44E-05 PM-148 6.32E-08 9.13E-09 4.60E-09 O.OOE+OO 1.09E-08 O.OOE+OO 9.74E-05 PM-149 1.38E-08 1.81 E-09 7.90E-10 O.OOE+OO 2.20E-09 O.OOE+OO 4.86E-05 PM-151 6.18E-09 9.01E-10 4.56E-10 O.OOE+OO 1.07E-09 O.OOE+OO 4.17E-05 SM-151 2.90E-07 6.67E-08 1.44E-08 O.OOE+OO 4.53E-08 O.OOE+OO 5.58E-06 SM-153 7.72E-09 5.97E-09 4.58E-10 O.OOE+OO 1.25E-09 O.OOE+OO 3.12E-05 EU-152 6.74E-07 1.79E-07 1.51 E-07 O.OOE+OO 5.02E-07 O.OOE+OO 1.59E-05 EU-154 2.64E-06 3.67E-07 2.20E-07 O.OOE+OO 9.95E-07 O.OOE+OO 4.58E-05 EU-155 5.42E-07 6.25E-08 3.23E-08 O.OOE+OO 1.40E-07 O.OOE+OO 8.37E-05 EU-156 1.14E-07 7.06E-08 1.12E-08 O.OOE+OO 3.26E-08 O.OOE+OO 6.67E-05 TB-160 2.59E-07 O.OOE+OO 3.24E-08 O.OOE+OO 7.37E-08 O.OOE+OO 3.45E-05 H0-166M 1.25E-06 2.69E-07 2.13E-07 O.OOE+OO 3.57E-07 O.OOE+OO 2.66E-05 W-181 8.85E-08 2.72E-08 3.04E-09 O.OOE+OO O.OOE+OO O.OOE+OO 3.82E-07 W-185 3.62E-06 1.13E-06 1.29E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.62E-05 W-187 9.03E-07 6.28E-07 2.17E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.69E-05 NP-239 1.11 E-08 9.93E-10 5.61E-10 O.OOE+OO 1.98E-09 O.OOE+OO 2.87E-05 U-232 2.42E-02 O.OOE+OO 2.16E-03 O.OOE+OO 2.37E-03 O.OOE+OO 7.04E-05 U-233 5.08E-03 O.OOE+OO 3.87E-04 O.OOE+OO 1.08E-03 O.OOE+OO 6.51E-05 CY-TM-170-300 Revision 5 Page 124 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 16 of 16 INGESTION DOSE FACTORS FOR INFANT (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI U-234 4.88E-03 O.OOE+OO 3.80E-04 O.OOE+OO 1.06E-03 O.OOE+OO 6.37E-05 U-235 4.67E-03 O.OOE+OO 3.56E-04 O.OOE+OO 9.93E-04 O.OOE+OO 8.10E-05 U-236 4.67E-03 O.OOE+OO 3.64E-04 O.OOE+OO 1.01 E-03 O.OOE+OO 5.98E-05 U-237 4.95E-07 O.OOE+OO 1.32E-07 O.OOE+OO 1.23E-06 O.OOE+OO 2.11E-05 U-238 4.47E-03 O.OOE+OO 3.33E-04 O.OOE+OO 9.28E-04 O.OOE+OO 5.71E-05 NP-237 2.40E-03 1.59E-04 1.0SE-04 O.OOE+OO 6.34E-04 O.OOE+OO 8.23E-05 NP-238 1.24E-07 3.12E-09 1.92E-09 O.OOE+OO 6.81E-09 O.OOE+OO 4.17E-05 PU-238 1.28E-03 1.SOE-04 3.40E-05 O.OOE+OO 1.21E-04 O.OOE+OO 7.57E-05 PU-239 1.38E-03 1.SSE-04 3.54E-05 O.OOE+OO 1.28E-04 O.OOE+OO 6.91E-05 PU-240 1.38E-03 1.SSE-04 3.54E-05 O.OOE+OO 1.28E-04 O.OOE+OO 7.04E-05 PU-241 4.25E-05 1.76E-06 8.82E-07 O.OOE+OO 3.17E-06 O.OOE+OO 1.45E-06 PU-242 1.28E-03 1.49E-04 3.41E-05 O.OOE+OO 1.23E-04 O.OOE+OO 6.77E-05 PU-244 1.49E-03 1.71E-04 3.91E-05 O.OOE+OO 1.41E-04 O.OOE+OO 1.01 E-04 AM-241 1.46E-03 1.27E-03 1.09E-04 O.OOE+OO 6.SSE-04 O.OOE+OO 7.?0E-05 AM-242M 1.51 E-03 1.22E-03 1".13E-04 O.OOE+OO 6.64E-04 O.OOE+OO 9.69E-05 AM-243 1.44E-03 1.23E-03 1.06E-04 O.OOE+OO 6.36E-04 O.OOE+OO 9.03E-05 CM-242 1.37E-04 1.27E-04 9.10E-06 O.OOE+OO 2.62E-05 O.OOE+OO 8.23E-05 CM-243 1.40E-03 1.15E-03 8.98E-05 O.OOE+OO 3.27E-04 O.OOE+OO 8.10E-05 CM-244 1.18E-03 9.?0E-04 7.59E-05 0.00E+OO 2.71E-04 O.OOE+OO 7.84E-05 CM-245 1.79E-03 1.45E-03 1.13E-04 O.OOE+OO 4.32E-04 O.OOE+OO 7.30E-05 CM-246 1.77E-03 1.45E-03 1.13E-04 O.OOE+OO 4.31 E-04 O.OOE+OO 7.17E-05 CM-247 1.73E-03 1.43E-03 1.11E-04 O.OOE+OO 4.24E-04 O.OOE+OO 9.43E-05 CM-248 1.43E-02 1.18E-02 9.16E-04 O.OOE+OO 3.SOE-03 O.OOE+OO 1.52E-03 CF-252 1.22E-03 O.OOE+OO 2.95E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.99E-04

• ** TABLE 2.2 Bioaccumulation

Factors, BFi CY-TM-170-300 Revision 5 Page 125 of 222 Bioaccumulation Factors to be Used in the Absence of Site-Specific Data* (pCi/kg per pCi/liter)

FRESHWATER ELEMENT FISH INVERTEBRATE H 9.0E-01 9.0E-01 C 4.6E+03 9.1 E+03 NA 1.0E+02 2.0E+02 CR 2.0E+02 2.0E+03 MN 4.0E+02 9.0E+04 FE 1.0E+02 3.2E+03 co 5.0E+01 2.0E+02 NI 1.0E+02 1.0E+02 cu 5.0E+01 4.0E+02 ZN 2.0E+03 1.0E+04 BR 4.2E+02 3.3E+02 RB 2.0E+03 1.0E+03 SR 3.0E+01 1.0E+02 y 2.5E+01 1.0E+03 ZR 3.3E+OO 6.7E+OO NB 3.0E+04 1.0E+02 MO 1.0E+01 1.0E+01 TC 1.5E+01 5.0E+OO RU 1.0E+01 3.0E+02 RH 1.0E+01 3.0E+02 **AG-110m 2.3E+OO 7.70E+2 **SB 1.0E+OO 1.0E+01 TE 4.0E+02 6.1E+03 I 1.5E+01 5.0E+OO cs 2.0E+03 1.0E+03 BA 4.0E+OO 2.0E+02 LA 2.5E+01 1.0E+03 CE 1.0E+OO 1.0E+03 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 w 1.2E+03 1.0E+01 NP 1.0E+01 4.0E+02 Bioaccumulation factor values are taken from Reg. Guide 1.109 (Rev. 1 ), Table A-1j. Sb and Ag bioaccumulation factor value is taken from NUREG/CR-4013 LADTAP II Reference Manual. CY-TM-170-300 Revision 5 Page 126 of 222 3.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEM 3.1 TMl-1 Liquid Effluent Waste Treatment System 3.1.1 Description of the Liquid Radioactive Waste Treatment System (see Figure 3.1) Reactor Coolant Train a. Water Sources -(3) Reactor Coolant Bleed Tanks (RCBT) -(1) Reactor Coolant Drain Tank (RCDT) b. Liquid Processing -Reactor Coolant Waste Evaporator -Demineralizers prior to release (see Figure 3.2) c. Liquid Effluent for Release -(2) Waste Evaporator Condensate Storage Tanks -(WECST) d. Dilution -Station Effluent Flow -River Flow Miscellaneous Waste Train a. Water sources: -Auxiliary Building Sump -Reactor Building Sump -Miscellaneous Waste Storage Tank -Laundry Waste Storage Tank -Neutralizer Mixing Tank -Neutralizer Feed Tank -Used Precoat Tank -Borated Water Tank Tunnel Sump -Heat Exchanger Vault Sump -Tendon Access Galley Sump -Spent Fuel Pool Room Sump -TMl-2 Miscellaneous Waste Holdup Tank CY-TM-170-300 Revision 5 Page 127 of 222 b. Liquid Processing -Miscellaneous Waste Evaporator, MWE -Oemineralizers prior to release (see Figure 3.2) c. Liquid Effluent for Release -(2) Waste Evaporator Condensate Storage Tanks-(WECST) d. Dilution -Station Effluent Flow -River Flow 3.2 Operability of the TMl-1 Liquid Effluent Waste Treatment System 3.2.1 The TMl-1 Liquid Waste Treatment System as described in Section 11 of the TMl-1 Final Safety Analysis Report is considered to be operable when one of each of the following pieces of equipment is available to perform its intended function: a) Miscellaneous Waste Evaporator (WDL-Z-1 B) or Reactor Coolant Evaporator (WDL-Z-1A) b) Waste Evaporator Condensate Demineralizer (WDL-K-3 A or B) c) Waste Evaporator Condensate Storage Tank (WDL-T-11 A or B) d) Evaporator Condensate Transfer Pumps (WDL-P-14 A or B) 3.2.2 TMl-1 Representative Sampling Prior to Discharge All liquid releases from the TMl-1 Liquid Waste Treatment System are made through the Waste Evaporator Condensate Storage Tanks. To provide thorough mixing and a representative sample, the contents of the tank are recirculated using one of the Waste Evaporator Condensate Transfer Pumps. 3.3 TMl-2 Liquid Effluent Waste Treatment System

• 3.3.1 Description of the TMl-2 Liquid Radioactive Waste Treatment System The TMl-2 Liquid Radioactive Waste Treatment System has been out of service since the TMl-2 Accident in 1979. TMl-2 Liquid Radioactive Waste is processed by the TMl-1 system described in Section 3.1 prior to release.

In addition, TMl-2 releases water from various sumps and tanks to the river (see Figures 1.1 and 1.2). These processes are governed by plant procedures that encompass proper sampling, sample analysis, and radiation monitoring techniques. FIGURE 3.1 TMl-1 Liquid Radwaste TMl-2 MWHT PRECOAT FILTER ( 1 OF 2) EJ.-.'-----.i BWST SUMP S.F.SUMP TEND. GAL. SUMP CATION DEMIN (1 OF 2) MISC. WASTE EVAP. 8. A. MIX TANK AUX HITTMAN I. .__s_u_1L_D_IN_G _ _,.,.r1------: MDCT EFFLUENT DEMIN WATER RECLAIM WATER STOA TANK RECLAIMED WATER SYSTEM MU-VS E CY-TM-170-300 Revision 5 Page 128 of 222 RC DRAIN MAKE UP RC DRAIN TANK RC WASTE EVAP. RBAT (1 OF 2) PORV SAFETY VALVES MAKE UP TO MU-V9 DISTILLATE COND. DEMIN (1 OF 2) FIGURE 3.2 TMl-1 Liquid Waste Evaporators CCH:ENTRATOR ow ---HfAre:1'"*-:.;:- t,=:~~C:.:::..~-- ~~-:::;: F E E D VENT CHEM HOR FEED TANK --1-1~ .... :) DIST. TANK REJECT WASTE FIL E CY-TM-170-300 Revision 5 Page 129 of 222 CY-TM-170-300 Revision 5 Page 130 of 222 4.0 GASEOUS EFFLUENT MONITORS 4.1 TMl-1 Noble Gas Monitor Set Points The gaseous effluent monitor set points are established for each gaseous effluent radiation monitor to assure concentrations of radionuclides in gaseous effluents do not exceed the limits set forth in ODCM Part I Control 2.2.2.1. Table 4.1 lists Gaseous Effluent Release Points and their associated parameters; Figure 4.1 provides a Gaseous Effluent Release Pathway Diagram. The set points are established to satisfy the more restrictive set point concentration in the following two equations: 500 > f (Ci)(F)(Ki)(Dv) and 3000 > f (Ci)(Li + 1.1 Mi)(Dv)(F) Where: Ci = set point concentration based on Xe-133 equivalent, in µCi/cc F =gaseous effluent flowrate at the monitor, in cc/sec Ki =total body dose factor, in mrem/yr per µCi/m3 from Table 4.3 (eq 4.1.1) (eq 4.1.2) Dv = highest sector annual average gaseous atmospheric dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for station vent releases and Table 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground releases). Maximum values presently used are 1.23E-6 sec/m3 at sector NNE for station vent, and 1.30E-5 sec/m3 at sector E for all other releases. Li = skin dose factor due to beta emissions from radionuclide i, in mrem/yr per µCi/m3 from Table 4.3. Mi = air dose factor due to gamma emissions from radionuclide i, in mrad/yr per µCi/m3 from Table 4.3. 1.1 = mrem skin dose per mrad air dose. 500 = annual whole body dose rate limit for unrestricted areas, in mrem/yr. 3000 = annual skin dose rate limit for unrestricted areas, in mrem/yr. CY-TM-170-300 Revision 5 Page 131 of 222 The set point concentration is further reduced such that the concentration contributions from multiple release points would not combine to exceed ODCM Control limits.* The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors. This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste. 4.2 TMl-1 Particulate and Radioiodine Monitor Set Points CY-TM-170-300 Revision 5 Page 132 of 222 Set points for monitors which detect radionuclides other than noble gases are also established to assure that concentrations of these radionuclides in gaseous effluents do not exceed the limits of ODCM Part I Control 2.2.2.1. Set points are established so as to satisfy the following equations: 1500 > f {ci)(F)(Pi)(Dv) (eq 4.2) Where: Ci= set point concentration based on 1-131 equivalent for radioiodine monitor and Sr-90 for particulate

monitor, in µCi/cc F = gaseous effluent flow rate at the monitor, in cc/sec Pi = pathway dose parameter, in mrem/yr per µCi/m3 for the inhalation pathway from Table 4.6. The dose factors are based on the actual . individual organ and most restrictive age group (child) (NUREG-0133).

NOTE: Appendix A contains Pi calculational methodology. 1500 = annual dose rate limit to any organ from particulates and radioiodines and radionuclides (other than noble gases) with half lives greater than eight days in mrem/yr. Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) at or beyond the unrestricted area boundary from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 1.23E-6 sec/m3 for station vent, at sector NNE, and 1.30E-5 sec/m3 for all other releases, at sector E. The set point concentration is further reduced such that concentration contributions from multiple release points would not combine to exceed ODCM Control limits. The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors. This section of the ODCM is implemented by the Radiation Monitor Systems Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste. 4.3 TMl-2 Gaseous Radiation Monitor Set Points CY-TM-170-300 Revision 5 Page 133 of 222 TMl-2 Gaseous Radiation Monitors have their set points described in TMI Plant Procedure 1101-2.1. Figure 4.5 provides a gaseous effluent release pathway diagram. Table 4.2 provides TMl-2 Radiation Monitor Data. These set points are set in accordance with the Controls delineated in Part II of this ODCM. CY-TM-170-300 Revision 5 Page 134 of 222 4.4 TMl-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMl-1 has eleven (11) required effluent gaseous radiation monitors. These are RM-A4, RM-A5, RM-A15, RM-A6, RM-A?, RM-AB, RM-A9, RM-A14, ALC-RMl-1 B, WHP-RIT-1, and RLM-RM-1. These gaseous release points, radiation

monitors, and sample points are shown in Table 4.1. 4.4.1 RM-A4/RM-A6 Fuel Handling and Auxiliary Building Exhaust RM-A4 is the radiation monitor for the TMl-1 Fuel Handling Building Ventilation (see Figures 4.1 and 4.2). RM-A6 is the radiation monitor for the TMl-1 Auxiliary Building Ventilation (see Figures 4.1 and 4.2). High alarms on RM-A4 or RM-A6 noble gas channels will initiate shutdown of the related building ventilation air supply system. These two radiation monitors concurrently will satisfy requirements for the Station Vent release point in place of RM-AB. 4.4.2 RM-AB Station Ventilation Exhaust RM-AB is the particulate, radioiodine and gaseous radiation monitor for the TMl-1 Station Ventilation (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters.

High alarm on RM-AB noble gas low channel will initiate shutdown of the Station Ventilation air supply systems. (The Fuel Handling and Auxiliary Building Ventilation). This radiation monitor satisfies requirements for the Station Vent release point in place of RM-A4 and RM-A6. 4.4.3 RM-A5/RM-A 15 Condenser Off Gas Exhaust RM-A5 is the gaseous radiation monitor for the TMl-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 is the back up gaseous radiation monitor for the TMl-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4 ). High alarms on RM-A5 low channel or RM-A 15 noble gas channels will initiate the MAP-5 Radioiodine Processor Station. These two radiation monitors together satisfy requirements for the Condenser Off Gas release point. 4.4.4 RM-A? Waste Gas Decay Tank Exhaust RM-A? is the gaseous radiation monitor for the TMl-1 Waste Gas Decay tanks (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel. High alarm on RM-A? noble gas channel will initiate shutdown of the Waste Gas Decay Tank release in progress. This radiation monitor satisfies requirements for batch gaseous releases to the Station Vent release point. 4.4.5 RM-A9 Reactor Building Purge Exhaust CY-TM-170-300 Revision 5 Page 135 of 222 RM-A9 is the particulate, radioiodine and gaseous radiation monitor for the TMl-1 Reactor Building Purge system (see Figures 4.1 and 4.3). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-A9 noble gas low channel will initiate shutdown of the Reactor Building Purge System. This radiation monitor satisfies requirements for the Reactor Building Purge System release point. 4.4.6 RM-A 14 ESF FHB Ventilation System RM-A14 is the gaseous radiation monitor for the TMl-1 Emergency Safeguards Features (ESF) Fuel Handling Building Exhaust system (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sampler filters. High alarm on RM-A14 noble gas channel will initiate shutdown of the ESF Fuel Handling Building Exhaust System. This radiation monitor satisfies requirements for the ESF Fuel Handling Building Exhaust System release point. 4.4.7 ALC-RMl-18 Chemical Cleaning Facility (CCF) Ventilation Exhaust ALC-RMl-18 is an Victoreen particulate, radioiodine, and gaseous radiation monitor for the Chemical Cleaning building exhaust. This monitor is located in the Chemical Cleaning building on the ground floor, and has an associated sample panel. Sampling for particulate activity is performed off of the monitor. 4.4.8 WHP-RIT-1 Waste Handling and Packaging Facility (WHPF) Exhaust WHP-RIT-1 is an Eberline AMS-3 particulate radiation monitor for the TMI WHPF. The monitor is located in the Mechanical Equipment Room in the WHPF. Sampling for particulate activity is performed off of the monitor. A high alarm will initiate shutdown of the ventilation air exhaust system. 4.4.9 RLM-RM-1 Respirator Cleaning and Laundry Maintenance (RLM) Facility RLM-RM-1 is an Eberline AMS-3 particulate radiation monitor for the TMI RLM Facility. The monitor is located in the Mechanical Equipment Room in the RLM. Sampling for particulate activity is performed off of the monitor. CY-TM-170-300 Revision 5 Page 136 of 222 4.5 TMl-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMl-2 has three (3) regulatory required gaseous effluent radiation monitors. These are HP-R-219, HP-R-219A and HP-R-225. These gaseous release points, radiation

monitors, and sample points are shown in Table 4.2, and various gaseous effluent pathways are depicted in Figure 4.5. 4.5.1 HP-R-219 Station Ventilation Exhaust HP-R-219 is a Victoreen particulate and gaseous radiation monitor for the TMl-2 ventilation exhaust.

This in-plant effluent radiation monitor is located in the TMl-2 Auxiliary Building 328 foot elevation and has an associated sample panel. 4.5.2 HP-R-219A Station Ventilation Exhaust HP-R-219A is a Victoreen particulate and gaseous radiation monitor for the TMl-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMl-2 Auxiliary Building 328 foot elevation. 4.5.3 HP-R-225 Reactor Building Purge Air Exhaust Duct "A" HP-R-225 is a Victoreen particulate and gaseous radiation monitor for the TMl-2 Reactor Building Purge Air Exhaust System. This in-plant effluent radiation monitor is located in the TMl-2 Auxiliary Building 328' elevation area. 4.6 Control of Gaseous Effluent Releases CY-TM-170-300 Revision 5 Page 137 of 222 TMI gaseous effluent combined releases are controlled (per ODCM Part I for TMl-1 and ODCM Part II for TMl-2) by effluent sampling and radiation monitor set points. These measures assure that releases from the various vents do not qombine to produce dose rates at the site boundary exceeding the most restrictive of 500 mrem per year to the total body or 3000 mrem per year to the skin, and 1500 mrem per year to the thyroid. This is done by restricting simultaneous releases and by limiting the dose rates that may be contributed by the various vents at any time. The various vent radiation monitor set points are each based on fractions of the above limits and do not exceed the above limits when summed together. These effluent radiation monitor set points are calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2. The actual set points are then listed in TMl-1 Operations Procedure 1101-2.1. The radioactive content of each batch of gaseous waste is determined prior to release by sampling and analyses in accordance with ODCM Part I for TMl-1 and ODCM Part II for TMl-2. The results of pre-release analyses are used with the calculational methods in Sections 4.1 and 4.2 to assure that the dose rates at the site boundary are maintained below the limits in ODCM Part I for TMl-1 and ODCM Part II for TMl-2. Post-release analyses of samples composited from batch and continuous releases are performed in accordance with ODCM Part I for TMl-1 and ODCM Part II for TMl-2. The results of the analyses are used to assure that the dose rates at the site boundary are maintained within the limits of ODCM Part I for TMl-1 and ODCM Part II for TMl-2. TABLE 4.1 CY-TM-170-300 Revision 5 Page 138 of 222 TMl-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUS RADIATION (F) RELEASE TERMINATION MONITOR GASEOUS FLOW INTERLOCK (YES/NO) (DETECTOR) LOCATION RELEASE POINT RECORDER VALVES YES 306' Elevation Fuel Hand. AH-E-10 RM-A4 Auxiliary Bldg. Building Exhaust AH-FR-149 AH-D-120 AH-D-121 AH-D-122 RM-A6 306' Elevation Auxiliary Building AH-FR-150 YES Auxiliary Bldq. Exhaust AH-E-11 YES RMA-8/9 Bldg. WDG-V47 AH-FR-149 AH-E-10 RM-AB Near BWST Station Vent &AH-FR-150 AH-E-11 Exhaust Starts MAP-5 Radioiodine Sampler 322' Elevation Condenser Off YES RM-A5 Second Floor Gas Exhaust VA-FR-1113 Starts MAP-5 Turbine Bldq. Radioiodine Sampler 322' Elevation Condenser Off YES RM-A15 Second Floor Gas Exhaust VA-FR-1113 Starts MAP-5 Turbine Bldq. Radioiodine Sampler 306' Elevation Waste Gas YES RM-A7 Auxiliary Bldg. Decay Tanks WDG-FR-123 WDG-V47 (A,B,C) YES RMA-8/9 Bldg. Reactor Building AH-FT-909/ AH-V-1 A/B/C/D RM-A9 WDL-V-534/535 Near BWST Purge Exhaust AH-FR-148 Starts MAP-5 Radioiodine Sampler 331' Elevation ESF Fuel RM-A14 ESF FHB Handling AH-UR-1104A/B NO Outside Chem. Building Manual Actions only Addition Bldg. Exhaust TABLE 4.1 (Cont'd) CY-TM-170-300 Revision 5 Page 139 of 222 TMl-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUS RADIATION RELEASE TERMINATION MONITOR INTERLOCK (YES/NO) (DETECTOR) LOCATION GASEOUS RELEASE POINT VALVES ALC-RMl-18 Chemical Cleaning Bldg. CCB Exhaust System NONE 304' Elevation (Typical flow rate is 10,000 cfm) WHP-RIT-1 WHPF Mechanical WHPF Exhaust System YES Equipment Room (Typical flow rate is 7,500 cfm) WHPF Ventilation Trips RLM-RM-1 RLM-Mechanical RLM Exhaust System NONE Equipment Room (Typical flow rate is 900 cfm) TABLE 4.2 TMl-2 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION GASEOUS INTERLOCK MONITOR RELEASE (YES/NO) (DETECTOR) LOCATION POINT VALVES HP-R-219 328' Elevation Station Vent Exhaust NONE Auxiliary Buildino (Typical flow rate is 70,000 cfm) HP-R-219A 328' Elevation Station Vent Exhaust NONE Auxiliary Buildinq (Typical flow rate is 70,000 cfm) 328' Elevation Reactor Bldg Purge Exhaust HP-R-225 Auxiliary Building Duct "A" NONE (Typical flow rate is 20,000 cfm) TABLE 4.3 Dose Factors for Noble Gases and Daughters* Gamma Beta Total Body Skin Dose Dose Factor(b) Gamma Air Factor(a) Li Dose Factor Ki (mrem/yr M (mrem/yr per per (mrad/yr per Radionuclide µCi/m3) uCi/m3) uCi/m3) Kr-83m 7.56E-02** ---1.93E+01 Kr-85m 1.17E+03 1.46E+03 1.23E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 Kr-87 5.92E+03 9.73E+03 6.17E+03 Kr-88 1.47E+04 2.37E+03 1.52E+04 Kr-89 1.66E+04 1.01E+04 1.73E+04 Kr-90. 1.56E+04 7.29E+03 1.63E+04 Xe-131m 9.15E+01 4.76E+02 1.56E+02 Xe-133m 2.51E+02 9.94E+02 3.27E+02 Xe-133 2.94E+02 3.06E+02 3.53E+02 Xe-135m 3.12E+03 7.11E+02 3.36E+03 Xe-135 1.81E+03 1.86E+03 1.92E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 Xe-138 8.83E+03 4.13E+03 9.21E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 CY-TM-170-300 Revision 5 Page 140 of 222 Beta Air Dose Factor Ni (mrad/yr per µCi/m3) 2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03

• Dose factors are for immersion exposure in uniform semi-infinite cloud of noble gas radionuclides that may be detected in gaseous effluents.

Dose factor values are taken from Regulatory Guide 1.109 (Rev. 1 ), Table B-1. ** 7.56E-02 = 7.56 x 10-2. (a) Total body dose factor for gamma penetration depth of 5 cm into the body. (b) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm2. TABLE 4.4 Atmospheric Dispersion Factors for Three Mile Island STATION VENT DISTANCE SECTOR AVERAGE X/Q (IN SEC/M3) (IN METERS) SECTOR 610 2413 4022 5631 7240 12067 24135 40225 N 2.12E-07 7.30E-07 4.35E-07 2.56E-07 1.84E-07 8.12E-08 3.22E-08 1.65E-08 NNE 3.19E-07 1.23E-06 6.02E-07 3.37E-07 2.13E-07 9.12E-08 3.45E-08 1.76E-08 NE 2.08E-07 3.87E-07 2.73E-07 3.76E-07 2.45E-07 1.08E-07 4.08E-08 2.08E-08 ENE 1.18E-07 4.36E-07 6.10E-07 3.33E-07 2.16E-07 1.08E-07 4.21E-08 2.14E-08 E 2.56E-07 3.80E-07 3.28E-07 3.74E-07 2.59E-07 1.11E-07 4.15E-08 2.10E-08 ESE 7.92E-07 5.47E-07 5.71E-07 3.47E-07 2.19E-07 9.24E-07 3.42E-08 1.72E-08 SE 9.50E-07 8.69E-07 6.06E-07 3.23E-07 2.06E-07 9.07E-08 3.72E-08 1.87E-08 SSE 4.82E-07 7.12E-07 5.00E-07 2.77E-07 1.85E-07 9.02E-08 3.38E-08 1.71E-08 s 8.33E-08 8.20E-08 3.05E-07 1.64E-07 1.06E-07 5.30E-08 1.99E-08 1.00E-08 SSW 2.61E-08 4.97E-08 2.38E-07 1.25E-07 7.96E-08 3.47E-08 1.37E-08 6.90E-09 SW 2.98E-08 1.78E-07 2.64E-07 1.46E-07 9.13E-08 3.92E-08 1.45E-08 7.24E-09 WSW 7.49E-08 4.55E-07 2.85E-07 1.51E-07 9.59E-08 4.05E-08 1.50E-08 7.51 E-09 w 1.17E-07 2.80E-07 3.15E-07 1.82E-07 1.28E-07 6.02E-08 2.25E-08 1.14E-08 WNW 2.01E-07 2.70E-07 3.83E-07 2.67E-07 1.67E-07 7.13E-08 2.68E-08 1.36E-08 NW 1.48E-07 5.78E-07 3.83E-07 2.11E-07 1.37E-07 6.85E-08 2.66E-08 1.43E-08 NNW 9.13E-08 5.81 E-07 3.54E-07 1.98E-07 1.34E-07 6.58E-08 2.52E-08 1.29E-08 STATION VENT DISTANCE SECTOR AVERAGE D/Q (IN M2) (IN METERS) SECTOR 610 2413 4022 5631 7240 12067 24135 40225 N 8.19E-09 1.62E-09 6.74E-10 4.88E-10 3.59E-10 1.29E-10 4.14E-11 1.72E-11 NNE 1.34E-08 2.84E-09 1.38E-09 6.89E-10 4.03E-10 1.42E-10 4.35E-11 1.78E-11 NE 7.28E-09 1.29E-09 4.55E-10 6.84E-10 4.03E-10 1.48E-10 4.55E-11 1.85E-11 ENE 3.69E-09 8.45E-10 7.16E-10 3.51E-10 2.19E-10 1.20E-10 3.95E-11 1.61E-11 E 8.16E-09 1.91 E-09 7.04E-10 8.28E-10 5.35E-10 1.91 E-10 5.87E-11 2.39E-11 ESE 2.48E-08 4.51E-09 2.47E-09 1.33E-09 7.69E-10 2.72E-10 8.33E-11 3.40E-11 SE 2.98E-08 4.85E-09 2.44E-09 1.14E-09 6.67E-10 2.55E-10 8.79E-11 3.57E-11 SSE 1.58E-08 2.51E-09 1.08E-09 5.97E-10 4.28E-10 1.94E-10 5.95E-11 2.45E-11 s 2.94E-09 6.13E-10 6.48E-10 3.08E-10 1.84E-10 8.81 E-11 2.74E-11 1.13E-11 SSW 8.48E-10 2.80E-10 4.72E-10 2.20E-10 1.28E-10 4.72E-11 1.64E-11 6.68E-12 SW 1.51E-09 5.68E-10 5.89E-10 2.93E-10 1.67E-10 6.11 E-11 1.87E-11 7.59E-12 WSW 2.58E-09 8.26E-10 6.63E-10 3.09E-10 1.83E-10 6.47E-11 1.99E-11 8.17E-12 w 5.46E-09 1.20E-09 6.34E-10 3.55E-10 2.64E-10 1.06E-10 3.28E-11 1.33E-11 WNW 7.60E-09 1.51E-09 8.91E-10 6.25E-10 3.57E-10 1.27E-10 3.87E-11 1.57E-11 NW 5.19E-09 1.02E-09 5.49E-10 2.64E-10 1.62E-10 8.34E-11 2.64E-11 1.14E-11 NNW 3.32E-09 7.92E-10 4.85E-10 2.32E-10 1.59E-10 7.50E-11 2.35E-11 9.63E-12 DATA FROM 2010-2015 USED IN CALCULATIONS CY-TM-170-300 Revision 5 Page 141 of 222 ANNUAL 56315 72405 1.07E-08 7.71E-09 1.14E-08 8.23E-09 1.34E-08 9.68E-09 1.38E-08 9.96E-09 1.35E-08 9.70E-09 1.09E-08 7.85E-09 1.20E-08 8.60E-09 1.10E-08 7.89E-09 6.41E-09 4.61E-09 4.42E-09 3.17E-09 4.62E-09 3.31E-09 4.78E-09 3.43E-09 7.30E-09 5.26E-09 8.79E-09 6.35E-09 9.25E-09 6.70E-09 8.33E-09 6.04E-09 ANNUAL 56315 72405 9.25E-12 5.75E-12 9.55E-12 5.93E-12 9.95E-12 6.19E-12 8.68E-12 5.40E-12 1.30E-11 8.09E-12 1.84E-11 1.14E-11 1.93E-11 1.20E-11 1.32E-11 8.20E-12 6.10E-12 3.79E-12 3.60E-12 2.24E-12 4.09E-12 2.54E-12 4.40E-12 2.73E-12 7.16E-12 4.44E-12 8.46E-12 5.25E-12 6.11E-12 3.79E-12 5.18E-12 3.22E-12 TABLE 4.5 Atmospheric Dispersion Factors for Three Mile Island GROUND RELEASE DISTANCE SECTOR AVERAGE X/Q (IN SEC/M3) (IN METERS) SECTOR 610 2413 4022 5631 7240 12067 24135 40225 N 8.46E-06 1.05E-06 5.27E-07 3.35E-07 2.39E-07 1.22E-07 4.92E-08 2.55E-08 NNE 9.97E-06 1.23E-06 6.16E-07 3.92E-07 2.80E-07 1.42E-07 5.75E-08 2.98E-08 NE 1.17E-05 1.47E-06 7.32E-07 4.64E-07 3.31E-07 1.68E-07 6.76E-08 3.50E-08 ENE 1.20E-05 1.54E-06 7.65E-07 4.84E-07 3.45E-07 1.74E-07 7.00E-08 3.61E-08 E 1.30E-05 1.67E-06 8.26E-07 5.21E-07 3.70E-07 1.86E-07 7.43E-08 3.82E-08 ESE 1.13E-05 1.43E-06 7.00E-07 4.39E-07 3.11 E-07 1.55E-07 6.12E-08 3.13E-08 SE 1.21 E-05 1.52E-06 7.41E-07 4.64E-07 3.27E-07 1.63E-07 6.41 E-08 3.27E-08 SSE 1.13E-05 1.44E-06 7.05E-07 4.43E-07 3.14E-07 1.57E-07 6.23E-08 3.19E-08 s 7.37E-06 9.52E-07 4.67E-07 2.93E-07 2.08E-07 1.04E-07 4.10E-08 2.09E-08 SSW 4.67E-06 6.09E-07 2.97E-07 1.86E-07 1.31 E-07 6.51E-08 2.55E-08 1.30E-08 SW 4.67E-06 6.05E-07 2.95E-07 1.84E-07 1.30E-07 6.45E-08 2.53E-08 1.28E-08 WSW 5.42E-06 6.92E-07 3.39E-07 2.13E-07 1.51 E-07 7.53E-08 2.98E-08 1.52E-08 w 8.19E-06 1.04E-06 5.15E-07 3.25E-07 2.30E-07 1.16E-07 4.60E-08 2.36E-08 WNW 9.23E-06 1.16E-06 5.76E-07 3.64E-07 2.59E-07 1.31 E-07 5.25E-08 2.71 E-08 NW 8.88E-06 1.10E-06 5.53E-07 2.52E-07 2.52E-07 1.29E-07 5.23E-08 2.72E-08 NNW 7.55E-06 9.37E-07 4.71E-07 3.01E-07 2.15E-07 1.10E-07 4.48E-08 2.33E-08 GROUND RELEASE DISTANCE SECTOR AVERAGE D/Q (IN M2 (IN METERS) SECTOR 610 2413 4022 5631 7240 12067 24135 40225 N 1.58E-08 1.59E-09 6.52E-10 3.60E-10 2.29E-10 9.29E-11 2.95E-11 1.20E-11 NNE 2.15E-08 2.17E-09 8.89E-10 4.90E-10 3.13E-10 1.27E-10 4.02E-11 1.63E-11 NE 1.99E-08 2.01E-09 8.26E-10 4.55E-10 2.90E-10 1.18E-10 3.73E-11 1.51E-11 ENE 1.76E-08 1.78E-09 7.29E-10 4.02E-10 2.56E-10 1.04E-10 3.29E-11 1.34E-11 E 2.57E-08 2.59E-09 1.06E-09 5.85E-10 3.73E-10 1.51E-10 4.80E-11 1.95E-11 ESE 3.49E-08 3.53E-09 1.45E-09 7.97E-10 5.08E-10 2.06E-10 6.53E-11 2.65E-11 SE 4.22E-08 4.26E-09 1.75E-09 9.62E-10 6.14E-10 2.49E-10 7.89E-11 3.20E-11 SSE 2.91E-08 2.93E-09 1.20E-09 6.63E-10 4.23E-10 1.71 E-10 5.44E-11 2.21 E-11 s 1.49E-08 1.50E-09 6.17E-10 3.40E-10 2.17E-10 8.79E-11 2.79E-11 1.13E-11 SSW 7.64E-09 7.71E-10 3.16E-10 1.74E-10 1.11E-10 4.51 E-11 1.43E-11 5.80E-12 SW 8.06E-09 8.14E-10 3.34E-10 1.84E-10 1.17E-10 4.76E-11 1.51E-11 6.12E-12 WSW 9.82E-09 9.91E-10 4.07E-10 2.24E-10 1.43E-10 5.79E-11 1.84E-11 7.45E-12 w 1.55E-08 1.57E-09 6.43E-10 3.54E-10 2.26E-10 9.16E-11 2.91 E-11 1.18E-11 WNW 1.87E-08 1.89E-09 7.75E-10 4.27E-10 2.72E-10 1.10E-10 3.50E-11 1.42E-11 NW 1.32E-08 1.33E-09 5.46E-10 3.01E-10 1.92E-10 7.77E-11 2.46E-11 1.00E-11 NNW 1.04E-08 1.05E-09 4.30E-10 2.37E-10 1.51E-10 6.12E-11 1.94E-11 7.88E-12 DATA FROM 2010-2015 USED IN CALCULATIONS CY-TM-170-300 Revision 5 Page 142 of 222 ANNUAL 56315 72405 1.67E-08 1.21 E-08 1.95E-08 1.42E-08 2.28E-08 1.66E-08 2.34E-08 1.70E-08 2.47E-08 1.79E-08 2.02E-08 1.46E-08 2.10E-08 1.52E-08 2.06E-08 1.49E-08 1.35E-08 9.74E-09 8.32E-09 5.99E-09 8.23E-09 5.93E-09 9.81E-09 7.09E-09 1.53E-08 1.11 E-08 1.76E-08 1.28E-08 1.78E-08 1.30E-08 1.52E-08 1.11 E-08 ANNUAL 56315 72405 6.44E-12 4.00E-12 8.77E-12 5.45E-12 8.15E-12 5.06E-12 7.19E-12 4.47E-12 1.05E-11 6.51E-12 1.43E-11 8.86E-12 1.72E-11 1.07E-11 1.19E-11 7.37E-12 6.08E-12 3.78E-12 3.12E-12 1.94E-12 3.29E-12 2.05E-12 4.01 E-12 2.49E-12 6.34E-12 3.94E-12 7.64E-12 4.75E-12 5.38E-12 3.34E-12 4.24E-12 2.63E-12 TABLE4.6 Dose Parameters for Radioiodines and Radioactive Particulate in Gaseous Effluents* CRITICAL ORGAN CRITICAL CY-TM-170-300 Revision 5 Page 143 of 222 ORGAN NUCLIDE ORGAN FACTOR Pi*** NUCLIDE ORGAN FACTOR Pi*** H-3** TOTAL BODY 3.04E-07 1.12E+03 RU-103 LUNG 1.79E-04 6.62E+05 C-14 BONE 9.70E-06 3.59E+04 RU-105 GI-LU 2.69E-05 9.95E+04 NA-24 TOTAL BODY 4.35E-06 1.61E+04 RU-106 LUNG 3.87E-03 1.43E+07 P-32 BONE 7.04E-04 2.60E+06 AG-110M LUNG 1.48E-03 5.48E+06 CR-51 LUNG 4.59E-06 1.70E+04 TE-125M LUNG 1.29E-04 4.77E+05 MN-54 LUNG 4.26E-04 1.58E+06 SB-125 LUNG 6.27E-04 2.32E+06 MN-56 GI-LU 3.33E-05 1.23E+05 TE-127M LUNG 4.00E-04 1.48E+06 FE-55 LUNG 3.00E-05 1.11 E+05 TE-127 GI-LU 1.52E-05 5.62E+04 FE-59 LUNG 3.43E-04 1.27E+06 TE-129M

• LUNG 4.76E-04 1.76E+06 C0-58 LUNG 2.99E-04 1.11 E+06 TE-129 GI-LU 6.89E-06 2.55E+04 C0-60 LUNG 1.91 E-03 7.07E+06 TE-131M GI-LU 8.32E-05 3.08E+05 Nl-63 BONE 2.22E-04 8.21E+05 TE-131 LUNG 5.55E-07 2.05E+03 Nl-65 GI-LU 2.27E-05 8.40E+04 TE-132 LUNG 1.02E-04 3.77E+05 CU-64 GI-LU 9.92E-06 3.67E+04 1-130 THYROID 4.99E-04 1.85E+06 ZN-65 LUNG 2.69E-04 9.95E+05 1-131 THYROID 4.39E-03 1.62E+07 ZN-69 GI-LU 2.75E-06 1.02E+04 1-132 THYROID 5.23E-05 1.94E+05 BR-83 TOTAL BODY 1.28E-07 4.74E+02 1-133 THYROID 1.04E-03 3.85E+06 BR-84 TOTAL BODY 1.48E-07 5.48E+02 1-134 THYROID 1.37E-05 5.07E+04 BR-85 TOTAL BODY 6.84E-09 2.53E+01 1-135 THYROID 2.14E-04 7.92E+05 RB-86 LIVER 5.36E-05 1.98E+05 CS-134 LIVER 2.74E-04 1.01E+06 RB-88 LIVER 1.52E-07 5.62E+02 CS-136 LIVER 4.62E-05 1.71 E+05 RB-89 LIVER 9.33E-08 3.45E+02 CS-137 BONE 2.45E-04 9.07E+05 SR-89 LUNG 5.89E-04 2.16E+06 CS-138 LIVER 2.27E-07 8.40E+02 SR-90 BONE 2.73E-02 1.01E+08 BA-139 GI-LU 1.56E-05 5.77E+04 SR-91 GI-LU 4.70E-05 1.74E+05 BA-140 LUNG 4.71 E-04 1.74E+06 SR-92 GI-LU 6.55E-05 2.42E+05 BA-141 LUNG 7.89E-07 2.92E+03 Y-90 GI-LU 7.24E-05 2.68E+05 BA-142 LUNG 4.44E-07 1.64E+03 Y-91M LUNG 7.60E-07 2.81E+03 LA-140 GI-LU 6.10E-05 2.26E+05 Y-91 LUNG 7.10E-04 2.63E+06 LA-142 GI-LU 2.05E-05 7.59E+04 Y-92 GI-LU 6.46E-05 2.39E+05 CE-141 LUNG 1.47E-04 5.44E+05 Y-93 GI-LU 1.05E-04 3.89E+05 CE-143 GI-LU 3.44E-05 1.27E+05 ZR-95 LUNG 6.03E-04 2.23E+06 CE-144 LUNG 3.23E-03 1.20E+07 ZR-97 GI-LU 9.49E-05 3.51E+05 PR-143 LUNG 1.17E-04 4.33E+05 NB-95 LUNG 1.66E-04 6.14E+05 PR-144 LUNG 4.23E-07 1.57E+03 M0-99 LUNG 3.66E-05 1.35E+05 ND-147 LUNG 8.87E-05 3.28E+05 TC-99M GI-LU 1.30E-06 4.81 E+03 W-187 GI-LU 2.46E-05 9.10E+04 TC-101 * ** LUNG 1.58E-07 5.85E+02 NP-239 GI-LU 1.73E-05 6.40E+04 The listed dose parameters are for radionuclides, other than noble gases that may be detected in gaseous effluents.

Pi factors include all nonatmospheric pathway transport parameters, the receptor's usage of pathway media, and are based on the most restrictive age group (child) critical organ. Additional dose parameters for nuclides not included in this Table may be calculated using the methodology described in NUREG-0133. Tritium dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin. *** mrem/year per µCi/m3* FIGURE 4.1 TMl-1 Gaseous Effluent Pathways FIGURE 4.1 ESF VENTILATION SYSTEM A p 1:11,IDI CfM FUEL HANDLING BUILDING RM*A4 ~----~ 40,000CFM STATION VE!:NT ,:ao,oooc~ DlillUON FLOW REACTOR 8Ull-C>INO PURGE 80.0000P'M IOe.OJGN P"I.OW CONDEN&EA OFF QA.8 STACI< 0-30 CFM PUMP6 CY-TM-170-300 Revision 5 Page 144 of 222 P-PRE FILTER A-ABSOLUTE HEPA C-CHARCOAL FILTER L VACUUM =========

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FIGURE 4.2 CY-TM-170-300 Revision 5 Page 145 of 222 TMl-1 Auxiliary and Fuel Handling Buildings Effluent Pathways HAXIIUI 91001 Cf'M FLOV AUXILIARY BUILDING 0-10 CfH Plm: STACK P A C MAXIIIM 41UO) CfN ESF FUEL HANDLING BUILDING RM-A8 HI RM-AB BO f"EET P A C 71m CfN MX. FLOV FUEL HANDLING BUILDING P: P~TIQUT[ A: AIS(l.UT( (:~ FIGURE 4.3 CY-TM-170-300 Revision 5 Page 146 of 222 TMl-1 Reactor Building Effluent Pathway REACTOR BUILDING PURGE EXHAUST RADIATION MONITORS ANO SAMPLING STATIONS REACT[R JJILDINi SNfl.lKi SYSTDtS Pij TICtl.A T£/TRil lUf IOD[t(JN]l( !i\S REACTOR BUILDING 170 FEET r--.......... --'--~ RM-G24 RM-A9 H[Gi p AC.,..____.__- HAXDUI* FILTERS Cfll Pl.RI"£ flOV P: PARTIC11.ATE A : ABS[I.UT( C = CWtRCllll FIGURE 4.4 CY-TM-170-300 Revision 5 Page 147 of 222 TMl-1 Condenser Offgas Effluent Pathway CONDENSER OFF GAS STACK 115 FEET D TO 200 crM CONDENSER OFF GAS EXHAUST RADIATION MONITORS AND SAMPLING STATIONS _.,__-t MAIN CONDENSE* I --..I,. AUXILIARY BUILDING FUEL HANDLING BUILDING

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FIGURE 4.5 CY-TM-170-300 Revision 5 Page 148 of 222 TMl-2 Gaseous Effluent Filtration System/Pathways STATION VENT j * . -u2,ooo c,11 HP-R-:219 HP-R-219A HP-R-219 SAMPLE RACK RB BREATHER

.J,. ----------_,... '*---------------I 0-10,000~ ~,OOOCt'M I I FILTERS I I HP-R*Z25 FILTERS}---- I I I REACTOR BUILDING 0.,3,000~ I FILTERS I I I . "' o * -e.~oo c,rw NO MONITOR CONTROL AND SERVICE BUILDING UNIT 2 EXHAUST AIR FLOW AND RMS SCHEMATIC CY-TM-170-300 Revision 5 Page 149 of 222 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents -Instantaneous Release Limits 5.1.1 Noble Gases For noble gases, the following equations apply for total body and skin dose rate at the unrestricted area boundary: 5.1.1.1 Total Body Dose Ratetb = T (Ki) x (Dv) x (Qi) ( eq 5.1.1.1) Where: Dose Rate b = instantaneous total body dose rate limit, at the site boundary, in mrem/yr. Ki = total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem/yr per µCi/m3 from Table 4.3. Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use are 1.23E-6 sec/m3 at sector NNE for station vent, and 1.30E-5 sec/m3 for all other releases at sector E. Oi = Release rate of radionuclide, i, in µCi/sec as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in µCi/cc, times the release pathway flow rate, in cc/second. CY-TM-170-300 Revision 5 Page 150 of 222 5.1.1.2 Skin Where: Dose Ratesk = T (Li + 1.1 Mi) X (Dv) X (Qi) (eq 5.1.1.2) Dose Ratesk = instantaneous mrem/year skin dose rate limit, at the site boundary, in mrem/yr. Li = skin dose factor due to beta emissions for. each identified noble gas radionuclide, in mrem/yr per µCi/m3 from Table 4.3. Mi = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per µCi/m3 from Table 4.3. 1.1 = mrem skin dose per mrad air dose. Converts air dose to skin dose. Oi = release rate of radionuclide, i, in µCi/sec, as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in µCi/cc, times the release pathway flow rate, in cc/second. Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use are 1.23E-6 sec/m3 at sector NNE for station vent, and 1.30E-5 sec/m3 for all other releases at E. CY-TM-170-300 Revision 5 Page 151 of 222 5.1.2 lodine-131, lodine-133, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days Where: For 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation applies: Dose Rate1p = 7 (Pi) (Dv) (Qi) (eq 5.1.2) Dose Rate1p = mrem/year organ dose rate. Pi = dose parameter for 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater 'than 8 days, for the inhalation

pathway, in mrem/yr per µCi/m3, from Table 4.6. The dose factors are based on the critical individual organ and most restrictive age group (child).

Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for the station vent releases and Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 1.23E-6 sec/m3 for station vent, at sector NNE, and 1.30E-5 sec/m3 for all other releases at sector E. Oi = release rate of each radionuclide, i, in µCi/sec. Calculated using the concentration of each radionuclide, i, in µCi/cc, times the release pathway flow rate, in cc/second. CY-TM-170-300 Revision 5 Page 152 of 222 5.2 Gaseous Effluents -10 CFR 50 Appendix I 5.2.1 Noble Gases Where: The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using the following expressions: Dose r = (3.17E-8) x T (Mi) x (Dv) x (Qi) and Dose J3 = (3.17E-8) x (Ni) x (Dv) x (Qi) I . (eq 5.2.1) (eq 5.2.2) Dose r = mrad gamma air dose due to gamma emissions from noble gas radionuclides. Dose j3 = mrad beta air dose due to beta emissions from noble gas radionuclides. Mi = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per µCi/m3, from Table 4.3. Ni = air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per µCi/m3, from Table 4.3. Dv = highest sector annual average gaseous dispersion factor, X/Q, at or beyond the unrestricted area boundary, in sec/m3* Values may be read or interpolated from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. Maximum values of X/Q presently used are 1.23E-6 sec/m3 for station vent at sector NNE, and 1.30E-5 sec/m3 for all other releases at sector E. Oi = release of noble gas radionuclide, i, in µCi, over the specified time period, (µCi/second* seconds). 3.17E-8 = inverse of the number of seconds in a year. CY-TM-170-300 Revision 5 Page 153 of 222 NOTE: If the methodology in this section is used in determining dose to an individual, rather than air dose due to noble gases, substitute Ki, from Table 4.3, for Mi, and (Li + 1.1 Mi) for Ni. 5.2.2 lodine-131, lodine-133, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days Where: The dose to an individual from 1-131, 1-133, Tritium and Radionuclides in Particulate Form with half-lives greater than 8 days in gaseous effluents released from the site to an unrestricted area is determined by solving the following expression: Doseo = T (3.17E-8) x T (Ri) (Dv) (Qi) (eq 5.2.2) Dosea = dose to all real pathways, p, to organ, o, of an individual in age group, a, from 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, in mrem, during any desired time period. Ri = the dose factor for each identified radionuclide, i, pathway, p, age group, a, and organ, o, in mrem/yr per µCi/m3 for the inhalation pathway and m2 -mrem/yr per µCi/sec for other pathways, from Tables 5.2 to 5.7. NOTE: When condenser offgas activity in µCi is above detectable limits, it is multiplied by 1.05 to account for an additional 5 percent activity released due to the Aux Condenser, Gland Seal Exhaust, Emergency Feedwater or the Turbine Building IAW Reference 9.11. NOTE: Tritium, H-3, dose factor is mrem/year per µCi/m3 for all pathways. Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, for the inhalation

pathway, and D/Q, in m2, for other pathways.

Table 4.4 is used to derive the values for station vent releases and Table 4.5 is used to derive the values for all other releases. The values used to calculate site boundary and critical receptor doses are as follows: Station Vent Releases -Boundary Inhalation X/Q Ground D/Q

• 1.23E-6 in sector NNE 2.98E-8 in sector SE Station Vent Releases

-Critical Receptor Inhalation X/Q 1.04E-6 in sector SE Ground D/Q 1.84E-8 in sector SE Meat D/Q 7.45E-9 in sector ESE X/Q 6.62E-7 in sector ESE Vegetation D/Q 8.68E-9 in sector SSE X/Q 6.30E-7 in sector SSE Cow/Milk/Infant D/Q 5.45E-9 in sector SE X/Q 8.87E-7 in section SE Ground or Other Releases -Boundary Inhalation X/Q Ground D/Q 1.30E-5 in sector E 4.22E-8 in sector SE Ground or Other Releases -Critical Receptor Inhalation X/Q Ground D/Q Meat D/Q X/Q Vegetation D/Q X/Q 1.04E-5 in sector E 2.06E-8 in sector E 5.84E-9 in sector ESE 2.16E-6 in sector ESE 1.66E-8 in sector E 8.43E-6 in sector E Cow/Milk/Infant D/Q 4.63E-9 in sector SE X/Q 1.63E-6 in sector SE CY-TM-170-300 Revision 5 Page 154 of 222 CY-TM-170-300 Revision 5 Page 155 of 222 Dv(H-3) = In the case of H-3 only the X/Q's above are used for all pathways. Oi = release of 1-131, 1-133, Tritium and Radionuclides, i, in Particulate Form with half-lives greater than 8 days, in µCi, cumulative over the specified time period (µCi/second* seconds). 3.1 ?E-8 = inverse of the number of seconds in a year. CY-TM-170-300 Revision 5 Page 156 of 222 5.3 Gaseous Radioactive System Dose Calculations Once per Month ODCM Part I Control 2.2.2.4 and TMl-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate subsystem of the Gaseous Radwaste Treatment System shall be used to reduce the radioactive materials in gaseous waste prior to their discharge. When the monthly projected doses due to the gaseous effluent releases from the site would exceed: 0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ. The following calculational method is provided for performing this dose projection. At least once per month the gamma air dose, beta air dose and the maximum organ dose for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual release during the period for which the projection is made. If these projected doses exceed any of the values listed above, appropriate portions of the TMl-1 Gaseous Waste Treatment System, as defined in Section 6.0, or appropriate portions of the TMl-2 Gaseous Effluent Filtration System as shown on Figure 4.5, shall be used to reduce radioactivity levels prior to release. At the discretion of the ODCM Specialist, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter-to-date is not believed to be representative of the dose per day projected for the next month. TABLE 5.2.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: INHALATION CY-TM-170-300 Revision 5 Page 157 of 222 -~~~~~~~--1-~----------------~~~~~~~~~~§~§-~~~-~~-~§-~~~i~~~i~iii~~~7-~~~~-P.~~-~~!~~~~~~~~~~~~~~~------------------: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

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.. ---------------------------------------------------* H-3 O.OOE+OO 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 C-14 2.65E+04 5.31 E+03 5.31 E+03 5.31 E+03 5.31 E+03 5.31 E+03 5.31 E+03 CR-51 O.OOE+OO O.OOE+OO 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN-54 O.OOE+OO 2.53E+04 4.98E+03 O.OOE+OO 4.98E+03 1.00E+06 7.06E+03 FE-55 1.97E+04 1.17E+04 3.33E+03 O.OOE+OO O.OOE+OO 8.69E+04 1.09E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 O.OOE+OO O.OOE+OO 1.02E+06 2.48E+04

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*

C0-58 O.OOE+OO 1.22E+03 1.82E+03 O.OOE+OO O.OOE+OO 7.77E+05 1.11 E+04 C0-60 O.OOE+OO 8.02E+03 1.18E+04 O.OOE+OO O.OOE+OO 4.51E+06 3.19E+04 Nl-63 3.39E+05 2.04E+04 1.16E+04 O.OOE+OO O.OOE+OO 2.09E+05 2.42E+03 ZN-65 1.93E+04 6.26E+04 3.11E+04 O.OOE+OO 3.25E+04 6.47E+05 5.14E+04 RB-86 O.OOE+OO 1.90E+05 8.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 SR-89 3.98E+05 O.OOE+OO 1.14E+04 O.OOE+OO O.OOE+OO 2.03E+06 6.40E+04

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. ----------------------------------------------------------------------------------------------* SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 4.09E+07 O.OOE+OO 2.59E+06 O.OOE:+00 O.OOE+OO 1.12E+07 5.88E+05 O.OOE+OO 1.57E+04 O.OOE+OO O.OOE+OO 2.45E+06 1.15E+05 2.79E+04 2.03E+04 O.OOE+OO 3.11E+04 1.75E+06 1.57E+04 6.43E+03 3.78E+03 O.OOE+OO 4.72E+03 4.79E+05 2.02E+03 O.OOE+OO

6. 79E+02 O.OOE+OO 4.24E+03 5.52E+05 8.68E+04 O.OOE+OO 1.09E+04 O.OOE+OO 1.07E+05 1.16E+07 AG-110M 9.98E+03 TE-125M 4.76E+03 TE-127M 1.67E+04 7.22E+03 5.00E+03 1.99E+03 6.58E+02 6.90E+03 2.07E+03 O.OOE+OO 1.62E+03 4.87E+03 1.09E+04 3.67E+06 O.OOE+OO 4.47E+05 3.75E+04 1.31 E+06 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 1.41 E+04 6.09E+03 2.23E+03 3.79E+04 4.44E+04 1.96E+04 1.32E+04 1.92E+04 5.60E+03 5.47E+03 1.48E+07 3.56E+06 3.96E+05 7.03E+05 7.45E+04 O.OOE+OO 4.83E+04 1.35E+05 5.29E+04 O.OOE+OO 5.49E+05 6.12E+05 4.55E+04 O.OOE+OO 5.60E+04 2.77E+04 3.19E+06 5.60E+01 1.67E+04 1.21E+06 2.90E+03 1.99E+03 1.76E+05 O.OOE+OO O.OOE+OO O.OOE+OO 3.18E+04 5.18E+04 2.24E+04 1.90E+05 5.64E+04 1.72E+05 1.34E+01 5.25E+03 5.38E+05 1.68E+06 O.OOE+OO O.OOE+OO 7.97E+04 1.18E+04 7.13E+04 1.60E+06 5.17E+05 9.84E+06 1.31E+05 7.03E+04 2.17E+04 1.27E+04 1.61E+04 1.64E+05 3.30E+04 1.29E+04 2.73E+04 6.90E+04 1.06E+03 2.16E+03 1.33E+03 1.43E+03 1.33E+03 3.84E+04 2.16E+04 1.48E+05 PR-143 1.40E+04 5.24E+03 6.99E+02 O.OOE+OO 1.97E+03 4.33E+05 3.72E+04 ND-147 7.94E+03 8.13E+03 5.00E+02 O.OOE+OO 3.15E+03 3.22E+05 3.12E+04 TABLE 5.2.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY:

INHALATION CY-TM-170-300 Revision 5 Page 158 of 222 ~~~~=E~i;i~=~~y~~!:~if~i:~~~~~i=:=~iI= H-3 O.OOE+OO 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 CR-51 O.OOE+OO O.OOE+OO 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 . ZN-65 RB-86 SR-89 O.OOE+OO 4.29E:+-04 4.74E+04 2.52E+04 2.07E+04 3.34E+04 9.51 E+03 7.77E+03 1.67E+04 O.OOE+OO 1.00E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. 77E+03 3.16E+03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.31 E+04 2.26E+04 O.OOE+OO 8.21 E+05 4.63E+04 2.80E+04 O.OOE+OO 4.26E+04 1.13E+05 7.03E+04 O.OOE+OO 7.14E+04 O.OOE+OO 1.98E+05 1.14E+05 O.OOE+OO O.OOE+OO 5.99E+05 O.OOE+OO 1.72E+04 O.OOE+OO O.OOE+OO 1.58E+06 2.29E+04 1.11 E+05 2.87E+03 1.27E+06 7.07E+04 1.11 E+06 3.44E+04 7.07E+06 9.62E+04 2.75E+05 6.33E+03 9.95E+05 1.63E+04 O.OOE+OO 7.99E+03 2.16E+06 1.67E+05

---

*

SR-90 1.01E+o8* O.OOE+OO 6.44E+06 O.OOE+OO O.OOE+OO 1.48E+07 3.43E+05 Y-91 9.14E+05 O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1.84E+05 ZR-95 1.90E+05 4.18E+04 3.70E+04 O.OOE+OO 5.96E+04 2.23E+06. 6.11E+04 NB-95 2.35E+04 9.18E+03 6.55E+03 O.OOE+OO 8.62E+03 6.14E+05 3.70E+04 RU-103 2.79E+03 O.OOE+OO 1.07E+03 O.OOE+OO 7.03E+03 6.62E+05 4.48E+04 RU-106 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+OO 1.84E+05 1.43E+07 4.29E+05

---

*

AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 PR-143 ND-147 1.69E+04 1.14E+04 9.14E+03 O.OOE+OO 2.12E+04 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+OO 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.92E+04 6.85E+03 3.04E+03 . 6.33E+03 5.03E+04 7.88E+04 3.38E+04 4.81 E+04 4.81 E+04 2.73E+04 1.62E+07 1.66E+04 2.03E+04

7. 70E+03 3.85E+06 6.51E+05 6.51E+04 9.07E+05 7.40E+04 3.92E+04 6.77E+06 1.01 E+06 2.25E+05 1.71E+05 1.16E+05 8.25E+05 1.28E+05 6.48E+01 4.33E+03 1.95E+04

. 2.90E+03 2.12E+06 3.61 E+05 O.OOE+OO 3.30E+05 O.OOE+OO 9.55E+04 O.OOE+OO 2.82E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.11E+01 8.55E+03 1.17E+06 5.48E+06 1.00E+05 4.77E+05 3.38E+04 1.48E+06 7.14E+04

1. 76E+06 1.82E+05 O.OOE+OO 2.84E+03 O.OOE+OO 5.48E+03 1.21 E+05 3.85E+03 1.45E+04 4.18E+03 1.04E+05 3.62E+03 1.74E+06 5.44E+05 1.20E+07 1.02E+05 5.66E+04 3.89E+05 1.85E+04 5.55E+03 9.14E+02 O.OOE+OO 3.00E+03 4.33E+05

9. 73E+04 1.08E+04

8. 73E+03 6.81 E+02

• O.OOE+OO 4.81 E+03 3.28E+05 8.21 E+04 TABLE 5.2.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY:

INHALATION CY-TM-170-300 Revision 5 Page 159 of 222 H-3 O.OOE+OO 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 CR-51 O.OOE+OO O.OOE+OO 1.35E+02 7.50E+01 3.07E+01 2.1 OE+04 3.00E+03 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 5.11 E+04 3.34E+04 2.38E+04 1.59E+04

3. 70E+04 8.40E+03 O.OOE+OO 5.54E+03 O.OOE+OO 1.43E+04 O.OOE+OO 1.27E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.07E+03 2.78E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.51 E+04 1.98E+04 O.OOE+OO O.OOE+OO 5.80E+05 4.34E+04 1.98E+04 O.OOE+OO O.OOE+OO 3.86E+04 1.34E+05 6.24E+04 O.OOE+OO 8.64E+04 O.OOE+OO 1.90E+05 8.40E+04 O.OOE+OO O.OOE+OO 4.34E+05 O.OOE+OO 1.25E+04 O.OOE+OO O.OOE+OO 1.98E+06 1.24E+05 1.53E+06 1.34E+06 8.72E+06 3.07E+05 1.24E+06 O.OOE+OO 2.42E+06 6.68E+04 6.39E+03 1.78E+05 9.52E+04 2.59E+05 1.42E+04 4.66E+04 1.77E+04 3.71 E+05 -------------------------------------------------------------------------------------------------------------------------------------------------------*

SR-90 1.08E+08 O.OOE+OO 6.68E+06 O.OOE+OO O.OOE+OO 1.65E+07 7.65E+05 Y-91 6.61E+05 O.OOE+OO 1.77E+04 O.OOE+OO O.OOE+OO 2.94E+06 4.09E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04 O.OOE+OO 6.74E+04 2.69E+06 1.49E+05 NB-95 1.86E+04 1.03E+04 5.66E+03 O.OOE+OO 1.00E+04 7.51E+05 9.68E+04 RU-103 2.10E+03 O.OOE+OO 8.96E+02 O.OOE+OO 7.43E+03 7.83E+05 1.09E+05 RU-106 9.84E+04 O.OOE+OO 1.24E+04 O.OOE+OO 1.90E+05 1.61 E+07 9.60E+05

---

*

AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-134 cs~136 CS-137 BA-140 CE-141 CE-144 1.38E+04 1.31 E+04 7.99E+03 O.OOE+OO 2.50E+04 4.88E+03 2.24E+03 6.67E+02 1.40E+03 O.OOE+OO 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 3.54E+04 4.91 E+04 2.64E+04 1.46E+07 8.40E+04 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 5.02E+05 5.15E+04 6.70E+05 1.13E+06 5.49E+05 1.94E+05 1.37E+05 8.48E+05 3.11 E+05 O.OOE+OO O.OOE+OO O.OOE+OO 3.75E+05 1.10E+05 3.04E+05 5.47E+04 6.70E+01 3.52E+03 O.OOE+OO 2.28E+01 2.84E+04 1.90E+04 2.17E+03 O.OOE+OO 8.88E+03 4.89E+06 2.02E+06 2.62E+05 O.OOE+OO 1.21 E+06 6.75E+06 2.73E+05 5.36E+05 7.50E+04 1.66E+06 1.59E+05 1.98E+06 4.05E+05 O.OOE+OO 6.49E+03 O.OOE+OO 1.03E+04 1.46E+05 1.78E+04 1.21E+05 2.03E+06 6.14E+05 1.34E+07 9.76E+03 1.09E+04 8.48E+03 2.29E+05 1.26E+05 8.64E+05 PR-143 1.34E+04 5.31 E+03 6.62E+02 O.OOE+OO 3.09E+03 4.83E+05 2.14E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 O.OOE+OO 5.02E+03 3.72E+05 1.82E+05 TABLE 5.2.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: INHALATION CY-TM-170-300 Revision 5 Page 160 of 222 H-3 O.OOE+OO 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 C-14 1.82E+04 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 CR-51 O.OOE+OO O.OOE+OO 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 O.OOE+OO 3.96E+04 6.30E+03 O.OOE+OO 9.84E+03 1.40E+06 7.74E+04 FE-55 2.46E+04 1.70E+04 3.94E+03 O.OOE+OO O.OOE+OO 7.21E+04 6.03E+03 FE-59 1.18E+04 2.78E+04 1.06E+04 O.OOE+OO O.OOE+OO 1.02E+06 1.88E+05

---

*

C0-58 O.OOE+OO 1.58E+03 2.07E+03 O.OOE+OO O.OOE+OO 9.28E+05 1.06E+05 C0-60 O.OOE+OO 1.15E+04 1.48E+04 O.OOE+OO O.OOE+OO 5.97E+06 2.85E+05 Nl-63 4.32E+05 3.14E+04 1.45E+04 O.OOE+OO O.OOE+OO 1.78E+05 1.34E+04 ZN-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+OO 6.90E+04 8.64E+05 5.34E+04 RB-86 O.OOE+OO 1.35E+05 5.90E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.66E+04 SR-89 3.04E+05 O.OOE+OO 8.72E+03 O.OOE+OO O.OOE+OO 1.40E+06 3.50E+05

---

*

SR-90 Y-91 ZR-95 NB-95

• RU-103 RU-106 9.92E+07 4.62E+05 1.07E+05 1.41E+04 1.53E+03 6.91E+04 AG-11 OM 1.08E+04 TE-125M 3.42E+03 TE-127M 1.26E+04 O.OOE+OO 6.10E+06 O.OOE+OO O.OOE+OO 1.24E+04 O.OOE+OO 3.44E+04 2.33E+04 O.OOE+OO 7.82E+03 4.21 E+03 O.OOE+OO O.OOE+OO 6.58E+02 O.OOE+OO O.OOE+OO 8.72E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.42E+04 7.74E+03 5.83E+03 1.34E+05 9.60E+06 1.70E+06 1.77E+06 5.05E+05 5.05E+05 9.36E+06 1.00E+04 5.94E+03 1.58E+03 4.67E+02 5.77E+03 1.57E+03 O.OOE+OO 1.97E+04 4.63E+06 1.05E+03 1.24E+04 3.14E+05 3.29E+03 4.58E+04 9.60E+05

-7.22E+05 3.85E+05 1.50E+05 1.04E+05 1.10E+05 9.12E+05 3.02E+05 7.06E+04 1.50E+05

---

*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 3.73E+05 8.48E+05 7.28E+05 O.OOE+OO 2.87E+05 3.90E+04 1.46E+05 1.10E+05 O.OOE+OO 8.56E+04 4.78E+05 6.21E+05 4.28E+05 O.OOE+OO 2.22E+05 1.16E+06 3.83E+05 O.OOE+OO 6.28E+03 O.OOE+OO 8.88E+03 9.76E+04 1.04E+04 1.20E+04 1.17E+04 7.52E+04 8.40E+03

---

*

BA-140 3.90E+04 4.90E+01 2.57E+03 O.OOE+OO 1.67E+01 1.27E+06 2.18E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 O.OOE+OO 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 O.OOE+OO 8.48E+05 7.78E+06 8.16E+05

---

*

PR-143 9.36E+03 3.75E+03 4.64E+02 O.OOE+OO 2.16E+03 2.81E+05 2.00E+05 ND-147 5.27E+03 6.10E+03 3.65E+02 O.OOE+OO 3.56E+03 2.21 E+05 1.73E+05 TABLE 5.3.1 Pathway Dose Factors, Ri AGE GROUP: ALL PATHWAY: GROUND PLANE CY-TM-170-300 Revision 5 Page 161 of 222 ---------------------------------------------------------r-----------------

---

ORGAN DOSE FACTORS* N UCL I DE ------------------------------------------- 1 I T.BODY SKIN ! I 1------------------

---

1

! H-3 O.OOE+OO O.OOE+OO ! i C-14 O.OOE+OO O.OOE+OO i i CR-51 4.65E+06 5.50E+06 i l--------------------------------------------------------------1 ! MN-54 1.39E+09 1.62E+09 ! i FE-55 O.OOE+OO O.OOE+OO i i FE-59 2.73E+08 3.21 E+08 i l--------------------------------------------------------------1 ! C0-58 3.79E+08 4.44E+08 ! i C0-60 2.15E+10 2.53E+10 i i Nl-63 O.OOE+OO O.OOE+OO i l--------------------------------------------------------------1 ! ZN-65 7.47E+08 8.59E+08 ! i RB-86 8.97E+06 1.03E+07 i i SR-89 2.16E+04 2.51 E+04 i l--------------------------------------------------------------1 ! SR-90 O.OOE+OO O.OOE+OO ! i Y-91 1.07E+06 1.21 E+06 i i ZR-95 2.45E+08 2.84E+08 i l--------------------------------------------------------------1 ! NB-95 1.37E+08 1.61 E+08 ! i RU-103 1.08E+08 1.26E+08 i i RU-106 4.22E+08 5.06E+08 i l--------------------------------------------------------------1 ! AG-11 OM 3.44E+09 4.01 E+09 ! i TE-125M 1.55E+06 2.13E+06 i i TE-127M 9.17E+04 1.08E+05 i l--------------------------------------------------------------1 ! TE-129M 1.98E+07 2.31 E+07 ! i 1-131 1.72E+07 2.09E+07 i i 1-133 2.45E+06 2.98E+06 i l--------------------------------------------------------------1 ! CS-134 6.86E+09 8.00E+09 ! i CS~136 1.51E+08 1.71E+08 i i CS-137 1.03E+10 1.20E+10 i l--------------------------------------------------------------1 ! BA-140 2.06E+07 2.36E+07 ! i CE-141 1.37E+07 1.54E+07 i i CE-144 6.96E+07 8.05E+07 i t--------------------------------------------------------------1 i PR-143 O.OOE+OO O.OOE+OO i i ND-147 8.39E+06 1.01 E+07 i I I L-------------------------------------------------------------J

• m2 -mrem/year per µCi/sec.

TABLE 5.4.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK CY-TM-170-300 Revision 5 Page 162 of 222 H-3 O.OOE+OO 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+OB 5.00E+OB 5.00E+08 5.00E+OB CR-51 O.OOE+OO O.OOE+OO 1.61 E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 O.OOE+OO 1.35E+08 2.25E+08 O.OOE+OO O.OOE+OO 3.50E+10 3.91 E+07 8.85E+06 8.74E+07 2.34E+07 3.93E+08 1.55E+08 2.43E+07 6.06E+07 8.83E+07 2.08E+08 2.16E+09 1.21E+09 O.OOE+OO O.OOE+OO O.OOE+OO O .. OOE+OO O.OOE+OO O.OOE+OO 8.65E+06 O.OOE+OO O.OOE+OO 4.27E+07 O.OOE+OO 1.16E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.43E+07 1.11 E+07 1.88E+08 6.05E+07 2.10E+08 1.08E+08

---

*

ZN-65 5.56E+09 1.91E+10 8.79E+09 O.OOE+OO 9.24E+09 O.OOE+OO 1.61E+10 RB-86 O.OOE+OO 2.23E+10 1.10E+10 O.OOE+OO O.OOE+OO O.OOE+OO 5.70E+08 SR-89 1.26E+10 O.OOE+OO 3.62E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.59E+08

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 AG-110M TE-125M TE-127M 1.22E+11 O.OOE+OO 3.10E+10 O.OOE+OO O.OOE+OO 7.34E+04 O.OOE+OO 1.95E+03 O.OOE+OO O.OOE+OO 6.81 E+03 1.66E+03 1.18E+03 O.OOE+OO 1.79E+03 5.94E+05 2.45E+05 1.41 E+05 O.OOE+OO

1. 75E+05 8.68E+03 O.OOE+OO 2.90E+03 O.OOE+OO 1.81 E+04 1.91 E+05 O.OOE+OO 2.38E+04 O.OOE+OO 2.25E+05 3.86E+08 2.82E+08 1.87E+08 O.OOE+OO 4.03E+08 1.51E+08 5.05E+07 2.04E+07 5.08E+07 O.OOE+OO 4.22E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 O.OOE+OO 1.52E+09 O.OOE+OO 5.26E+06 O.OOE+OO 8.27E+05 O.OOE+OO 2.07E+08 O.OOE+OO 1.06E+05 O.OOE+OO 1.45E+06 O.OOE+OO 1.46E+10 O.OOE+OO 7.19E+07 O.OOE+OO 1.70E+08

---

*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 5.58E+08 1.91E+08 8.59E+07 2.14E+08 1.39E+09 O.OOE+OO 2.72E+09 3.21 E+09 1.41E+09 1.05E+12 3.75E+09 O.OOE+OO 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 O.OOE+OO 3.65E+10 6.81E+10 6.88E+09 O.OOE+OO 1.75E+10 7.19E+09 1.98E+09 5.83E+09 2.18E+09 O.OOE+OO 2.32E+09

4. 75E+08 5.15E+10 6.03E+10 4.27E+09 O.OOE+OO 1.62E+10 6.55E+09 2..42E+08 2.42E+05 1.25E+07 O.OOE+OO 5.75E+04 4.34E+04 2.65E+04 3.12E+03 O.OOE+OO 8.17E+03 2.33E+06 9.53E+05 1.30E+05 O.OOE+OO 3.85E+05 1.49E+05 O.OOE+OO O.OOE+OO 3.33E+08 1.15E+08 8.96E+06 1.85E+08 8.85E+07 1.89E+08 5.94E+07 1.37E+07 1.34E+08 PR-143 1.49E+03 5.56E+02 7.37E+01 O.OOE+OO 2.07E+02 O.OOE+OO 7.84E+05 ND-147 8.83E+02 9.07E+02 5.55E+01 O.OOE+OO 3.50E+02 O.OOE+OO 5.75E+05 TABLE 5.4.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY:

GRASS-COW-MILK CY-TM-170-300 Revision 5 Page 163 of 222 H-3 O.OOE+OO 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 CR-51 O.OOE+OO O.OOE+OO 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 1.12E+08 1.20E+08 2.1 OE+07 5.59E+06 5.94E+07 1.84E+07 1.95E+08 ' 9. 70E+07 O.OOE+OO 1.21 E+07 3. 72E+07 O.OOE+OO 4.32E+07 1.27E+08 2.97E+10 1.59E+09 1.01 E+09 4.14E+09 1.10E+10 6.86E+09 O.OOE+OO 8.78E+09 5.40E+09 6.63E+09 O.OOE+OO 1.89E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.89E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.95E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.36E+07 5.65E+07 1.76E+07 1.10E+07 2.03E+08 O.OOE+OO 7.08E+07 O.OOE+OO 2.39E+08 O.OOE+OO 1.07E+08 O.OOE+OO 1.94E+09 O.OOE+OO 5.65E+08 O.OOE+OO 2.57E+08

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 1.12E+11 3.91E+04 3.84E+03 3.18E+05 4.29E+03 9.25E+04 O.OOE+OO 2.84E+10 O.OOE+OO 1.05E+03 8.43E+02 7.51 E+02 1.24E+05 8.86E+04 O.OOE+OO 1.65E+03 O.OOE+OO 1.15E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.21E+03 1.16E+05 1.08E+04 1.25E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO AG-11 OM 2.09E+08 1.41 E+OB 1.13E+08 O.OOE+OO 2.63E+08 O.OOE+OO TE-125M 7.39E+07 2.00E+07 9.85E+06 2.07E+07 O.OOE+OO O.OOE+OO TE-127M 2.0BE+OB 5.61 E+07 2.47E+07 4.98E+07 5.94E+08 O.OOE+OO TE-129M 1-131 1-133 CS-134 CS-136 CS-137 2.72E+08 7.59E+07 4.22E+07 8.76E+07 1.31 E+09 1.31 E+09 7.46E+08 4.34E+11

1. 72E+07 2.13E+07 8.05E+06 3.95E+09 2.27E+10 3.72E+10 7.85E+09 O.OOE+OO 1.01E+09 2.79E+09 1.80E+09 O.OOE+OO 3.23E+10 3.09E+10 4.56E+09 O.OOE+OO 7.98E+08 2.16E+09 3.55E+07 1.15E+10 1.49E+09 1.01E+10 O.OOE+OO O.OOE+OO O.OOE+OO 4.14E+09 2.21 E+OB 3.62E+09 1.51 E+09 5.21 E+06 8.80E+05 2.29E+08 1.11 E+05 1.44E+06 1.68E+10 7.13E+07 1.69E+08 3.31 E+OB 1.17E+08 8.58E+06 2.01E+08 9.80E+07 1.93E+08

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*

BA-140 1.18E+08 1.03E+05 6.86E+06 O.OOE+OO 3.35E+04 6.14E+04 5.96E+07 CE-141 2.19E+04 1.09E+04 1.62E+03 O.OOE+OO 4.79E+03 O.OOE+OO 1.36E+07 CE-144 1.63E+06 5.09E+05 8.67E+04 O.OOE+OO 2.82E+05 O.OOE+OO 1.33E+08 PR-143 7.18E+02 2.16E+02 3.56E+01 O.OOE+OO 1.17E+02 O.OOE+OO 7.75E+05 ND-147 4.45E+02 3.61 E+02 2.79E+01 O.OOE+OO 1.98E+02 O.OOE+OO 5.71 E+05 ' -------------------------------------------------------------------------------------------------------------------------------------------------------- TABLE 5.4.3 Pathway Dose Factors, Ri CY-TM-170-300 Revision 5 Page 164 of 222 AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK ~y~~~~t=:i;i::=: H-3 O.OOE+OO 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 C-14 4.86E+08 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 CR-51 O.OOE+OO O.OOE+OO 4.99E+04

2. 77E+04 1.09E+04 7.13E+04 8.39E+06 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 4.46E+07 5.19E+07 O.OOE+OO O.OOE+OO 1.18E+10 2.11E+09 O.OOE+OO 2.68E+09 1.40E+07

2. 78E+06 3.16E+07 7.37E+06 1.21 E+08 4.68E+07 7.94E+06 1.83E+07

2. 78E+07 6.27E+07 8.36E+08 4.01 E+08 7.32E+09 3.42E+09 4.73E+09 2.22E+09 O.OOE+OO 7.67E+07 O.OOE+OO 4.19E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO 4.69E+09 O.OOE+OO 0.00E+OO O.OOE+OO 2.88E+07 2.01 E+07 1.37E+07 3.82E+07 2.86E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.10E+08 3.62E+08 1.33E+08 3.10E+09 7.00E+08 3.19E+08

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 6.62E+10 1.58E+04 1.65E+03 1.41 E+OS 1.81E+03 3.76E+04 AG-11 OM 9.64E+07 TE-125M 3.01E+07 TE-127M 8.45E+07 TE-129M 1.10E+08 1-131 5.38E+08 1-133 7.08E+06 O.OOE+OO 1.63E+10 O.OOE+OO O.OOE+OO O.OOE+OO 4.24E+02 O.OOE+OO O.OOE+OO 5.21 E+02 3.58E+02 O.OOE+OO 7.65E+02 7.82E+04 4.30E+04 O.OOE+OO 7.58E+04 O.OOE+OO 7.75E+02 O.OOE+OO 6.39E+03 O.OOE+OO 4.73E+03 O.OOE+OO 7.24E+04 9.12E+07 5.55E+07 O.OOE+OO 1.08E+07 4.02E+06 8.40E+06 3.00E+07 1.00E+07 2.01 E+07 4.09E+07 1.74E+07 3.56E+07 7.53E+08 4.05E+08 2.20E+11 1.20E+07 3.66E+06 1.68E+09 1.74E+08 0.00E+OO 3.42E+08 4.61 E+08 1.30E+09 2.11 E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1".86E+09 6.48E+06 1.20E+06 3.34E+08 1.51E+05 1.80E+06 O.OOE+OO 2.56E+10 O.OOE+OO 8.87E+07 O.OOE+OO 2.11E+08 O.OOE+OO 4.14E+08 O.OOE+OO 1.49E+08 O.OOE+OO 9.09E+06

---

*

CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 9.83E+09 4.49E+08 1.34E+10 4.87E+07 8.89E+03 6.59E+05 2.31 E+10 1.77E+09 1.78E+10 5.97E+04 5.94E+03 2.73E+05 1.07E+10 1.19E+09 6.21E+09 3.14E+06 6.82E+02 3.54E+04 O.OOE+OO 7.35E+09 2.81 E+09 O.OOE+OO 9.63E+08 1.52E+08 O.OOE+OO 6.06E+09 2.36E+09 O.OOE+OO 2.02E+04 4.01 E+04 O.OOE+OO 2.80E+03 O.OOE+OO O.OOE+OO 1.63E+05 O.OOE+OO 2.88E+08 1.42E+08 2.54E+08 7.51 E+07 1.70E+07 1.66E+08 PR-143 2.90E+02 1.16E+02 1.44E+01 O.OOE+OO 6.73E+01 O.OOE+OO 9.55E+05 ND-147 1.81 E+02 1.97E+02 1.18E+01 O.OOE+OO 1.16E+02 O.OOE+OO 7.12E+05 TABLE 5.4.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK CY-TM-170-300 Revision 5 Page 165 of 222 BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

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*

H-3 O.OOE+OO 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 C-14 2.63E+08 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 CR-51 O.OOE+OO O.OOE+OO 2.85E+04

1. 70E+04 6.28E+03

3. 78E+04 7.17E+06 MN-54 O.OOE+OO 8.40E+06 1.60E+06 O.OOE+OO 2.50E+06 O.OOE+OO 2.57E+07 FE-55 2.51E+07 1.73E+07 4.04E+06 O.OOE+OO O.OOE+OO 9.66E+06 9.93E+06 FE-59 2.97E+07 6.97E+07 2.67E+07 O.OOE+OO O.OOE+OO 1.95E+07 2.32E+08

---

*

C0-58 O.OOE+OO 4.71E+06 1.05E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.54E+07 C0-60 O.OOE+OO 1.64E+07 3.61E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.08E+08 Nl-63 6.72E+09 4.65E+08 2.25E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.71E+07 ZN-65 1.37E+09 4.36E+09 1.97E+09 O.OOE+OO 2.91E+09 O.OOE+OO 2.74E+09 RB-86 O.OOE+OO 2.59E+09 1.21 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.10E+08 SR-89 1.45E+09 O.OOE+OO 4.16E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+08

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 4.67E+10 O.OOE+OO 1.15E+10 O.OOE+OO O.OOE+OO 8.57E+03 O.OOE+OO 2.29E+02 O.OOE+OO O.OOE+OO 9.41 E+02 3.02E+02 2.04E+02 O.OOE+OO 4.74E+02 8.24E+04 4.58E+04 2.46E+04 O.OOE+OO 4.53E+04 1.02E+03 O.OOE+OO 4.38E+02 O.OOE+OO 3.88E+03 2.04E+04 O.OOE+OO 2.58E+03 O.OOE+OO 3.93E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.35E+09 4.72E+06 9.57E+05 2.78E+08 1.19E+05 1.32E+06 AG-110M 5.81E+07 5.38E+07 3.19E+07 O.OOE+OO 1.06E+08 O.OOE+OO 2.19E+10 TE-125M 1.63E+07 5.89E+06 2.18E+06 4.89E+06 6.61 E+07 O.OOE+OO 6.49E+07 TE-127M 4.57E+07 1.63E+07 5.57E+06 1.17E+07 1.86E+08 O.OOE+OO 1.53E+08 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 6.01 E+07 2.24E+07 9.51 E+06 2.06E+07 2.51 E+08 2.96E+08 4.23E+08 2.42E+08 1.39E+11 7.25E+08 3.87E+06 6.73E+06 2.05E+06 9.88E+08 1.17E+07 5.64E+09 1.34E+10 1.10E+10 O.OOE+OO 4.34E+09 2.63E+08 1.04E+09 7.48E+08 O.OOE+OO 5.78E+08 7.37E+09 1.01E+10 6.60E+09 O.OOE+OO 3.42E+09 O.OOE+OO 3.02E+08 O.OOE+OO 1.12E+08 O.OOE+OO 6.04E+06 1.44E+09 2.35E+08 7.92E+07 1.18E+08 1.14E+09 1.95E+08

---

*

BA-140 2.69E+07 3.38E+04 1.76E+06 O.OOE+OO 1.15E+04 1.94E+04 5.54E+07 CE-141 4.84E+03 3.27E+03 3.71 E+02 O.OOE+OO 1.52E+03 O.OOE+OO 1.25E+07 CE-144 3.57E+05 1.49E+05 1.92E+04 O.OOE+OO 8.85E+04 O.OOE+OO 1.21E+08 PR-143 1.57E+02 6.32E+01 7.81 E+OO O.OOE+OO 3.65E+01 O.OOE+OO 6.90E+05 ND-147 9.40E+01 1.09E+02 6.50E+OO O.OOE+OO 6.35E+01 O.OOE+OO 5.22E+05 TABLE 5.5.1 Pathway Dose Factors, Ri C AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK CY-TM-170-300 Revision 5 Page 166 of 222 --~-~~-~~~~-1-~----------------~-~~~~§-~~~~~~~~~-~~-~i~~~;~~~~~~~!~~7X~~~-E~~~~[[~-~-~~~~~~~~------------------: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU ------------------

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*

H-3 O.OOE+OO 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 CR-51 O.OOE+OO O.OOE+OO 1.94E+04 1.26E+04

2. 76E+03 2.46E+04 5.64E+05 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 4.68E+06

1. 76E+06 1.14E+06 2.92E+06 5.1 OE+06 1.06E+06 3.03E+05 2.01 E+06 O.OOE+OO O.OOE+OO 4.19E+09 2.91 E+06 7.26E+06 1.06E+07 2.50E+07 2.59E+08 1.46E+08 6.67E+08 2.29E+09 1.05E+09 O.OOE+OO 2.67E+09 1.32E+09 2.65E+10 O.OOE+OO 7.59E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.11E+09 O.OOE+OO O.OOE+OO O.OOE+OO

1. 72E+06 5.55E+05 1.44E+05 1.51 E+06 2.44E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.25E+06 2.52E+07 1.29E+07 1.93E+09 6.83E+07 5.44E+08

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*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 AG-110M TE-125M TE-127M 2.55E+11 8.80E+03 8.17E+02 7.13E+04 1.04E+03 2.28E+04 4.63E+07 1.81 E+07 5.06E+07 O.OOE+OO 6.50E+10 O.OOE+OO 2.34E+02 1.99E+02 1.41E+02 2.93E+04

1. 70E+04 O.OOE+OO 3.48E+02 O.OOE+OO 2.85E+03 3.38E+07 2.24E+07 6.05E+06 2.45E+06 1.68E+07 6.12E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.15E+02 O.OOE+OO 2.1 OE+04 O.OOE+OO 2.17E+03 O.OOE+OO

2. 70E+04 O.OOE+OO 4.84E+07 6.09E+06 O.OOE+OO 1.46E+07 1.24E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.19E+09 6.31E+05 9.91E+04 2.48E+07 1.27E+04 1.73E+05 1.75E+09 8.62E+06 2.04E+07

---

*

TE-129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 O.OOE+OO 3.99E+07 1-131 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 O.OOE+OO 1.37E+08 1-133 4.36E+07 6.35E+07 1.86E+07 1.15E+10 7.46E+07 O.OOE+OO 1.07E+07 CS-134 1.09E+11 2.04E+11 2.06E+10 O.OOE+OO 5.26E+10 2.15E+10 5.55E+08 CS-136 5.94E+09 1.75E+10 6.52E+09 O.OOE+OO 6.96E+09 1.42E+09 2.65E+08 CS-137 1.54E+11 1.81E+11 1.28E+10 O.OOE+OO 4.85E+10 1.96E+10 5.65E+08

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*

BA-140 CE-141 CE-144 PR-143 ND-147 2.90E+07 2.90E+04 1.50E+06 O.OOE+OO 6.89E+03 1.78E+04 7.13E+06 5.21 E+03 3.18E+03 3.74E+02 O.OOE+OO 9.79E+02 O.OOE+OO 1.64E+06 2.79E+05 1.14E+05 1.56E+04 O.OOE+OO 4.62E+04 O.OOE+OO 1.60E+07

1. 78E+02 6.66E+01 8.83E+OO O.OOE+OO 2.48E+01 O.OOE+OO 9.40E+04 1.06E+02 1.09E+02 6.66E+OO O.OOE+OO 4.19E+01 O.OOE+OO 6.89E+04 TABLE 5.5.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY:

GRASS-GOAT-MILK CY-TM-170-300 Revision 5 Page 167 of 222

• BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU ------------------

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*

H-3 O.OOE+OO 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 CR-51 O.OOE+OO O.OOE+OO 1.22E+04

6. 78E+03 1.85E+03 1.24E+04 6.48E+05 MN-54 O.OOE+OO 2.52E+06 6.71 E+05 O.OOE+OO 7.06E+05 O.OOE+OO 2.11 E+06 FE-55 1.45E+06 7.71E+05 2.39E+05 O.OOE+OO O.OOE+OO 4.36E+05 1.43E+05 FE-59 1.56E+06 2.53E+06 1.26E+06 O.OOE+OO O.OOE+OO 7.34E+05 2.64E+06

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*

C0-58 . O.OOE+OO 1.46E+06 4.46E+06 O.OOE+OO O.OOE+OO O.OOE+OO 8.49E+06 C0-60 O.OOE+OO 5.18E+06 1.53E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+07 Nl-63 3.56E+09 1.91 E+08 1.21E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.28E+07 ZN-65 4.96E+08 1.32E+09 8.22E+08 O.OOE+OO 8.33E+08 O.OOE+OO 2.32E+08 RB-86 O.OOE+OO 1.05E+09 6.47E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.77E+07 SR-89 1.39E+10 O.OOE+OO 3.97E+08 O.OOE+OO O.OOE+OO O.OOE+OO 5.39E+08

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*

SR-90 2.35E+11 O.OOE+OO 5.95E+10 O.OOE+OO O.OOE+OO O.OOE+OO 3.16E+09 Y-91 4.69E+03 O.OOE+OO 1.25E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+05 ZR-95 4.60E+02 1.01E+02 9.00E+01 O.OOE+OO 1.45E+02 O.OOE+OO 1.05E+05 NB-95 3.82E+04 1.49E+04 1.06E+04 O.OOE+OO 1.40E+04 O.OOE+OO 2.75E+07 RU-103 5.14E+02 O.OOE+OO 1.98E+02 O.OOE+OO 1.29E+03 O.OOE+OO 1.33E+04 RU-106 1.11 E+04 O.OOE+OO 1.38E+03 O.OOE+OO 1.50E+04 O.OOE+OO 1.73E+05

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*

AG-110M 2.51E+07 1.69E+07 1.35E+07 O.OOE+OO 3.15E+07 O.OOE+OO 2.01E+09 TE-125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 O.OOE+OO O.OOE+OO 8.55E+06 TE-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 O.OOE+OO 2.02E+07 TE-129M 3.26E+07 9.10E+06 5.06E+06 1.05E+07 9.56E+07 O.OOE+OO 3.97E+07 1-131 1.57E+09 1.57E+09 8.95E+08 5.21 E+11 2,58E+09 O.OOE+OO 1.40E+08 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 O.OOE+OO 1.03E+07

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*

CS-134 6.80E+10 1.12E+11 2.35E+10 O.OOE+OO 3.46E+10 1.24E+10 6.01E+08 CS-136 3.04E+09 8.36E+09 5.41 E+09 O.OOE+OO 4.45E+09 6.64E+08 2.94E+08 CS-137 9.68E+10 9.26E+10 1.37E+10 O.OOE+OO 3.02E+10 1.09E+10 5.80E+08

---

*

BA-140 1.41E+07 1.24E+04 8.23E+05 O.OOE+OO 4.02E+03 7.37E+03 7.15E+06 CE-141 2.63E+03 1.31E+03 1.95E+02 O.OOE+OO 5.74E+02 O.OOE+OO 1.63E+06 CE-144 1.95E+05 6.11 E+04 1.04E+04 O.OOE+OO 3.38E+04 O.OOE+OO 1.59E+07 PR-143 8.61 E+01 2.59E+01 4.27E+OO O.OOE+OO 1.40E+01 O.OOE+OO 9.29E+04 ND-147 5.34E+01 4.33E+01 3.35E+OO O.OOE+OO 2.37E+01 O.OOE+OO 6.85E+04 TABLE 5.5.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK CY-TM-170-300 Revision 5 Page 168 of 222 H-3 O.OOE+OO 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 CR-51 O.OOE+OO O.OOE+OO 5.99E+03 3.33E+03 1.31 E+03 8.55E+03 1.01 E+06 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 O.OOE+OO 1.68E+06 3.34E+05

5. 79E+05 4.11 E+05 9.58E+04

6. 7 4E+05 1.57E+06 6.08E+05 O.OOE+OO O.OOE+OO 1.42E+09 9.53E+05 2.20E+06 3.34E+06 7.52E+06 1.00E+08 4.81 E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.02E+05 O.OOE+OO O.OOE+OO 2.61 E+05 O.OOE+OO 4.96E+05 3.45E+06 1.78E+05 3.72E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.31 E+07 O.OOE+OO 4.35E+07 O.OOE+OO 1.60E+07

---

*

ZN-65 2.53E+08 8.78E+08 4.10E+08 O.OOE+OO 5.62E+08 O.OOE+OO 3.72E+08 RB-86 O.OOE+OO 5.67E+08 2.67E+08 O.OOE+OO O.OOE+OO O.OOE+OO 8.40E+07 SR-89 5.62E+09 O.OOE+OO 1.61 E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.69E+08

---

.. ---------------------------------------------------------------------------------------------------------------------------------------------* SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 1.39E+11 1.90E+03 1.98E+02 1.69E+04 2.17E+02 4.50E+03 O.OOE+OO O.OOE+OO 6.25E+01 9.38E+03 O.OOE+OO O.OOE+OO 3.43E+10 5.09E+01 4.30E+01 5.16E+03 9.29E+01 5.68E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.18E+01 O.OOE+OO 9.09E+03 O.OOE+OO 7.66E+02 O.OOE+OO 8.69E+03 O.OOE+OO 3.90E+09 O.OOE+OO 7.78E+05 O.OOE+OO 1.44E+05 O.OOE+OO 4.01 E+07 O.OOE+OO 1.82E+04 O.OOE+OO 2.16E+05 AG-110M 1.16E+07 1.09E+07 6.65E+06 1.30E+06 4.82E+05 3.59E+06 1.20E+06 O.OOE+OO 2.09E+07 1.01 E+06 O.OOE+OO 2.41E+06 4.11E+07 O.OOE+OO 3.07E+09 TE-125M 3.61 E+06 O.OOE+OO 1.06E+07

• TE-127M 1.01 E+07 O.OOE+OO 2.52E+07 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 O.OOE+OO 4.96E+07 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 O.OOE+OO 1.79E+08 8.49E+06 1.44E+07 4.40E+06 2.01 E+09 2.53E+07 O.OOE+OO 1.09E+07 2.95E+10 6.93E+10 3.22E+10 O.OOE+OO 2.20E+10 8.41 E+09 8.62E+08 1.35E+09 5.30E+09 3.56E+09 O.OOE+OO 2.89E+09 4.55E+08 4.27E+08 4.02E+10 5.34E+10 1.86E+10 O.OOE+OO 1.82E+10 7.07E+09 7.60E+08 5.84E+06 1.07E+03 7.90E+04 7.16E+03 3.76E+05 7.12E+02 8.18E+01 3.27E+04 4.25E+03 O.OOE+OO 2.43E+03 4.81 E+03 O.OOE+OO 3.35E+02 O.OOE+OO O.OOE+OO 1.95E+04 O.OOE+OO 9.01E+06 2.04E+06 1.99E+07 PR-143 3.48E+01 1.39E+01 1.73E+OO O.OOE+OO 8.08E+OO O.OOE+OO 1.15E+05 ND-147 2.18E+01 2.37E+01 1.42E+OO O.OOE+OO 1.39E+01 O.OOE+OO 8.54E+04 TABLE 5.5.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY:

GRASS-GOAT-MILK CY-TM-170-300 Revision 5 Page 169 of 222 --~-~~-~~~;-I-~----------------~~~~~~§B~~~~~~~~-~~~i~~~;~~~~~~~~~~~i1-~~~-P-~~~~~~-~-~~~~~~~~------------------: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

---

*

H-3 O.OOE+OO 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 C-14 2.64E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 CR-51 O.OOE+OO O.OOE+OO 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 MN-54 O.OOE+OO 1.01 E+06 1.93E+05 O.OOE+OO 3.01 E+05 O.OOE+OO 3.10E+06 FE-55 3.27E+05 2.26E+05 5.26E+04 O.OOE+OO O.OOE+OO 1.26E+05 1.30E+05 FE-59 3.87E+05 9.09E+05 3.48E+05

• O.OOE+OO O.OOE+OO 2.54E+05 3.03E+06

---

*

C0-58 O.OOE+OO 5.66E+05 1.27E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+07 C0-60 O.OOE+OO 1.97E+06 4.35E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+07 Nl-63 8.08E+08 5.60E+07 2.71 E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E+07

---

*

ZN-65 1.65E+08 5.24E+08 2.37E+08 O.OOE+OO 3.51E+08 O.OOE+OO 3.30E+08 RB-86 O.OOE+OO 3.12E+08 1.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.14E+07 SR-89 3.05E+09 O.OOE+OO 8.76E+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.89E+08

---

*

SR-90 9.84E+10 O.OOE+OO 2.41 E+10 O.OOE+OO 0.00E+OO O.OOE+OO 2.84E+09 Y-91 1.03E+03 O.OOE+OO 2.76E+01 O.OOE+OO O.OOE+OO O.OOE+OO 5.68E+05 ZR-95 1.13E+02 3.63E+01 2.46E+01 O.OOE+OO 5.70E+01 O.OOE+OO 1.15E+05 NB-95 9.92E+03 5.52E+03 2.97E+03 O.OOE+OO 5.45E+03 O.OOE+OO 3.35E+07 RU-103 1.22E+02 O.OOE+OO 5.27E+01 O.OOE+OO 4.67E+02 O.OOE+OO 1.43E+04 RU-106 2.45E+03 O.OOE+OO 3.10E+02 O.OOE+OO 4.73E+03 O.OOE+OO 1.59E+05

---

*

AG-110M 6.99E+06 6.47E+06 3.84E+06 O.OOE+OO 1.27E+07 O.OOE+OO 2.64E+09 TE-125M 1.96E+06 7.09E+05 2.62E+05 5.89E+05 7.96E+06 O.OOE+OO 7.81E+06 TE-127M 5.50E+06 1.97E+06 6.70E+05 1.41E+06 2.23E+07 O.OOE+OO 1.84E+07

---

*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 PR-143 ND-147 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.56E+08 5.09E+08 2.92E+08 1.67E+11 4.65E+06 8.10E+06 2.47E+06 1.19E+09 1.70E+10 4.04E+10 3.30E+10 O.OOE+OO 7.92E+08 3.13E+09 2.25E+09 O.OOE+OO 2.22E+10 3.03E+10 1.99E+10 O.OOE+OO 3.24E+06 4.07E+03 2.12E+05 5.82E+02 3.94E+02 4.47E+01 4.30E+04 1.80E+04 2.31 E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.02E+07 O.OOE+OO 8.73E+08 O.OOE+OO 1.41E+07 O.OOE+OO 1.31E+10 4.34E+09 1.74E+09 2.38E+08 1.03E+10 3.42E+09 1.38E+03 1.83E+02 1.07E+04 2.33E+03 O.OOE+OO O.OOE+OO 3.64E+07 1.34E+08 7.28E+06 7.07E+08 3.55E+08 5.87E+08 6.67E+06 1.51E+06 1.45E+07 1.90E+01 7.60E+OO 9.40E-01 O.OOE+OO 4.39E+OO O.OOE+OO 8.30E+04 1.13E+01 1.31 E+01 7.82E-01 O.OOE+OO 7.65E+OO O.OOE+OO 6.28E+04 TABLE, 5.6.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT CY-TM-170-300 Revision 5 Page 170 of 222 --~-~~-~~~~-I------------------~~~~~~§~~~~~Q9-~~-~~-~i~~~~~~~~~~~~~~!I~~~-E~~~~[i~~-~~~~~~~~------------------: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

---

*

H-3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C-14 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CR-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO MN-54 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO FE-55 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

---

*

C0-58 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C0-60 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nl-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . . -------------------------------------------------------------------------------------------------------------------------------------------------------* ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.001::+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.001::+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

---

*

AG-110M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-125M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-127M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

---

*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 O.OOE+OO O.QOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO b.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO PR-143 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND-147 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TABLE 5.6.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-COW-MEAT CY-TM-170-300 Revision 5 Page 171 of 222 ~0~~~E}i~i=~if~~~~~~~3~~~:[[~if§~E=~ii:= H-3 O.OOE+OO 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 C-14 3.84E+08 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 CR-51 O.OOE+OO O.OOE+OO

8. 78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 8.01 E+06 2.13E+06 O.OOE+OO 2.25E+06 4.57E+08 2.43E+08 7.52E+07 O.OOE+OO O.OOE+OO

3. 77E+08 6.1 OE+08 3.04E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.91 E+10 3.76E+08 O.OOE+OO 4.82E+08 1.64E+07 5.03E+07 6.93E+07 2.04E+08 1.56E+09 9.91 E+08 1.00E+09 6.22E+08 5.76E+08 3.54E+08 O.OOE+OO 1.38E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.31E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.73E+06 1.37E+08 4.49E+07 1.77E+08 6.35E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.58E+07 3.84E+08 1.05E+08 1.76E+08 3.71E+07 1.87E+07

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 AG-110M TE-125M TE-127M 1.04E+10 1.80E+06 2.66E+06 3.10E+06 1.55E+08 4.44E+09 8.39E+06 5.69E+08 1.78E+09 O.OOE+OO 2.64E+09 O.OOE+OO 4.82E+04 5.86E+05 5.21E+05 1.21 E+06 8.63E+05 O.OOE+OO 5.96E+07 O.OOE+OO 5.54E+08 5.67E+06 4.53E+06 1.54E+08 7.59E+07 4.78E+08 2.11 E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.38E+05 O.OOE+OO 1.13E+06 O.OOE+OO 3.90E+08 O.OOE+OO 6.00E+09 O.OOE+OO 1.06E+07 1.60E+08 O.OOE+OO 4.25E+08 5.06E+09 O.OOE+OO 1.40E+08 O.OOE+OO 2.40E+08 O.OOE+OO 6.11 E+08 O.OOE+OO 2.23E+09 O.OOE+OO 4.01 E+09 O.OOE+OO 6.91E+10 O.OOE+OO 6.74E+08 O.OOE+OO 5.49E+08 O.OOE+OO 1.44E+09

---

*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 1.79E+09 5.00E+08 2.78E+08 5.77E+08 5.26E+09 O.OOE+OO 2.18E+09 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 O.OOE+OO 1.48E+06 5.72E-01 7.08E-01 2.68E-01 1.31E+02 1.18E+OO O.OOE+OO 2.85E-01 9.23E+08 1.51 E+09 3.19E+08 O.OOE+OO 4.69E+08 1.68E+08 1.63E+07 4.48E+07 2.90E+07 O.OOE+OO 2.39E+07 3.56E+06 1.33E+09 1.28E+09 1.89E+08 O.OOE+OO 4.16E+08 1.50E+08 8.16E+06 1.57E+06 8.00E+06 4.42E+07 2.22E+04 2.32E+06 3.87E+04 2.58E+06 1.11 E+04 1.65E+03 7.26E+05 1.24E+05 O.OOE+OO 1.26E+04 O.OOE+OO 4.86E+03 O.OOE+OO 4.02E+05 2.31 E+04 2.24E+07 O.OOE+OO 1.38E+07 O.OOE+OO 1.89E+08 PR-143 3.33E+04 1.00E+04 1.65E+03 O.OOE+OO 5.42E+03 O.OOE+OO 3.60E+07 ND-147 1.17E+04 9.48E+03 7.34E+02 O.OOE+OO 5.20E+03 O.OOE+OO 1.50E+07 \ ' TABLE 5.6.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT CY-TM-170-300 Revision 5 Page 172 of 222 --~:;-~~~~-1-~----------------=~~~~~~~9-~~~~~~~-~~~i9.~~;~~~~~~~~!~~7i~~~-P-~~~~~~~~~~~~-~~------------------: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

---

*

H-3 O.OOE+OO 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 C-14 2.04E+08 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 CR-51 O.OOE+OO O.OOE+OO 5.63E+03 3.13E+03 1.23E+03 8.03E+03

• 9.46E+05 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 7.00E+06 1.39E+06 O.OOE+OO 2.09E+06 2.38E+08 1.69E+08 3.94E+07 O.OOE+OO O.OOE+OO 2.12E+08 4.95E+08 1.91 E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.52E+10 2.50E+08 O.OOE+OO 2.55E+08 1.40E+07 3.24E+07 5.83E+07 1.31 E+08 1.07E+09 5.15E+08 8.68E+08 4.05E+08 4.06E+08 1.91E+08 O.OOE+OO 7.29E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.56E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+08 1.56E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.44E+07 7.31E+07 1.17E+09 1.94E+08 7.60E+08 1.71 E+08 3.68E+08 6.00E+07 3.03E+07

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 8.04E+09 9.54E+05 1.50E+06 1.79E+06 8.56E+07 2.36E+09 O.OOE+OO 1.99E+09 O.OOE+OO 2.56E+04 4.73E+05 3.25E+05 9.95E+05 5.48E+05 O.OOE+OO 3.66E+07 O.OOE+OO 2.97E+08 O.OOE+OO O.OOE+OO. O.OOE+OO O.OOE+OO O.OOE+OO 6.95E+05 O.OOE+OO 9.64E+05 O.OOE+OO 3.02E+08 O.OOE+OO 4.54E+09 O.OOE+OO 2.26E+08 O.OOE+OO 3.91E+08 O.OOE+OO 1.09E+09 O.OOE+OO 4.25E+09 O.OOE+OO 7.15E+09 O.OOE+OO 1.13E+11 AG-110M 5.06E+06 4.78E+06 2.91E+06 O.OOE+OO 9.13E+06 O.OOE+OO 1.34E+09 8.94E+08 2.35E+09 TE-125M 3.03E+08 1.09E+08 4.05E+07 8.46E+07 O.OOE+OO O.OOE+OO TE-127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.81E+09 O.OOE+OO TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 9.49E+08 8.93E+06 3.08E-01 5.23E+08 9.43E+06 7.24E+08 3.52E+08 1.50E+08 1.25E+07

6. 72E+06 5.22E-01 1.59E-01 1.23E+09 5.71 E+08 3.71 E+07 2.49E+07 9.63E+08 3.35E+08 3.06E+08 3.65E+09 7.29E+01 3.97E+09 2.15E+07 9.16E-01 O.OOE+OO 3.91 E+08 O.OOE+OO 2.02E+07 O.OOE+OO 3.28E+08 2.39E+07 2.93E+04 1.54E+06 O:OOE+OO 9.94E+03 1.18E+04 7.87E+03 9.05E+02 O.OOE+OO 3.71 E+03 1.23E+06 5.08E+05 6.60E+04 O.OOE+OO 3.03E+05 O.OOE+OO 3.56E+09 O.OOE+OO 2.47E+06 O.OOE+OO 3.95E-01 1.49E+08 1.53E+07 3.18E+06 2.99E+06 1.27E+08 1.37E+07 1.97E+04 3.69E+07 O.OOE+OO 2.25E+07 O.OOE+OO 3.09E+08 PR-143 1.76E+04 7.03E+03 8.76E+02 O.OOE+OO 4.08E+03 O.OOE+OO 5.79E+07 ND-147 6.23E+03 6.78E+03 4.06E+02 O.OOE+OO 3.98E+03 O.OOE+OO 2.44E+07 TABLE 5.6.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY:

GRASS-COW-MEAT CY-TM-170-300 Revision 5 Page 173 of 222 H-3 O.OOE+OO 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 C-14 2.42E+08 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 CR-51 O.OOE+OO O.OOE+OO 7.04E+03 4.21 E+03 1.55E+03 9.35E+03 1.77E+06 MN-54 O.OOE+OO 9.18E+06 1.75E+06 O.OOE+OO

• 2.73E+06 O.OOE+OO 2.81E+07 FE-55 2.93E+08 2.03E+08 4.73E+07 O.OOE+OO O.OOE+OO 1.13E+08 1.16E+08 FE-59 2.66E+08 6.25E+08 2.39E+08 O.OOE+OO O.OOE+OO 1.75E+08 2.08E+09

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*

C0-58 O.OOE+OO 1.82E+07 4.09E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+08 C0-60 O.OOE+OO 7.52E+07 1.66E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.41 E+09 Nl-63 1.89E+10 1.31E+09 6.33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.73E+08 ZN-65 3.56E+08 1.13E+09 5.12E+08 O.OOE+OO 7.57E+08 O.OOE+OO 7.13E+08 RB-86 O.OOE+OO 4.87E+08 2.27E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.59E+07 SR-89 3.02E+08 O.OOE+OO 8.66E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.84E+07

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*

SR-90 1.24E+10 . O.OOE+OO 3.05E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.60E+08 Y-91 1.13E+06 O.OOE+OO 3.03E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+08 ZR-95 1.87E+06 6.01E+05 4.07E+05 O.OOE+OO 9.43E+05 O.OOE+OO 1.90E+09

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*

NB-95 2.30E+06 1.28E+06 6.87E+05 O.OOE+OO 1.26E+06 O.OOE+OO 7.76E+09 RU-103 1.05E+08 O.OOE+OO 4.53E+07 O.OOE+OO 4.02E+08 O.OOE+OO 1.23E+10 RU-106 2.80E+09 O.OOE+OO 3.54E+08 O.OOE+OO 5.41E+09 O.OOE+OO 1.81E+11

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*

AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 6.68E+06 6,18E+06 3.67E+06 3.59E+08 1.30E+08 4.81 E+07 1.12E+09 3.99E+08 1.36E+08 1.13E+09 4.23E+08 1.79E+08 1.08E+07 1.54E+07 8.82E+06 3.68E-01 6.41 E-01 1.95E-01 O.OOE+OO 1.22E+07 1.08E+08 1.46E+09 2.85E+08 4.53E+09 3.89E+08 4.73E+09 5.04E+09 2.64E+07 9.42E+01 1.12E+OO 6.58E+08 1.57E+09 1.28E+09 O.OOE+OO 5.07E+08 1.21 E+07 4. 78E+07 3.44E+07 O.OOE+OO 2.66E+07

8. 72E+08 1.19E+09 7.82E+08 O.OOE+OO 4.05E+08 O.OOE+OO 2.52E+09 O.OOE+OO 1.43E+09 O.OOE+OO 3.74E+09 O.OOE+OO

5. 71 E+09 O.OOE+OO 4.06E+06 O.OOE+OO 5.76E-01 1.68E+08 3.65E+06 1.35E+08 2.74E+07 5.43E+06 2.31E+07 2.90E+07 3.64E+04 1.90E+06 O.OOE+OO 1.24E+04 2.08E+04 5.96E+07 1.41E+04 9.51E+03 1.08E+03 O.OOE+OO 4.42E+03 O.OOE+OO 3.64E+07 1.46E+06 6.10E+05 7.83E+04 O.OOE+OO 3.62E+05 O.OOE+OO 4.93E+08 PR-143 2.09E+04 8.40E+03 1.04E+03 O.OOE+OO 4.85E+03 O.OOE+OO 9.17E+07 ND-147 7.08E+03 8.18E+03 4.90E+02 O.OOE+OO 4.78E+03 O.OOE+OO 3.93E+07 TABLE 5.7.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY:

VEGETATION CY-TM-170-300 Revision 5 Page 174 of 222 ------------------1-------------------------------------------------------------------------------------------------- .-----------------------------------* ORGAN DOSE FACTORS; m2 -mrem/year per µCi/sec NU CL I DE ------------------------------------------------------------------------------------------------------------------------------------* BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

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*

H-3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C-14 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CR-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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*

SR-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO. Y-91 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ZR-95 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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*

NB-95 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-106 O.OOE+OO O.OOE+OO

• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO AG-110M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-125M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
• O.OOE+OO O.OOE+OO TE-127M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO PR-143 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND-147 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TABLE 5.7.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: VEGETATION CY-TM-170-300 Revision 5 Page 175 of 222 H-3 O.OOE+OO 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 C-14 8.89E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 CR-51 O.OOE+OO O.OOE+OO 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 O.OOE+OO 6.65E+08 8.01 E+OS 4.25E+08 3.98E+08 6.44E+08 O.OOE+OO 6.44E+07 O.OOE+OO.

3. 78E+08 3.95E+10 2.11 E+09 1. 77E+08 O.OOE+OO 1.32E+08 O.OOE+OO 3.21 E+OS O.OOE+OO 1.97E+08 1.12E+09 1.34E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.86E+08 O.OOE+OO O.OOE+OO 2.40E+08 O.OOE+OO 1.87E+08 5.58E+08 7.87E+07 6.71E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. 76E+08 O.OOE+OO 2.1 OE+09 O.OOE+OO 1.42E+08 8.12E+08 2.16E+09 1.35E+09 O.OOE+OO 1.36E+09 O.OOE+OO 3.80E+08 2.90E+07 1.39E+09 O.OOE+OO 4.51 E+OS 2. 77E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.60E+10 O.OOE+OO 1.03E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.24E+12 1.87E+07 3.86E+06 4.11 E+05 1.53E+07 7.45E+08 O.OOE+OO 3.15E+11 O.OOE+OO 4.99E+05 8.48E+05 7.55E+05 1.60E+05 1.14E+05 O.OOE+OO 5.90E+06 O.OOE+OO 9.30E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.21E+06 1.50E+05 3.86E+07 1.01E+09 O.OOE+OO 1.67E+10 O.OOE+OO 2.49E+09 O.OOE+OO 8.85E+08 O.OOE+OO 2.96E+08 O.OOE+OO 3.97E+08 O.OOE+OO 1.16E+10

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*

AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 3.21E+07 2.17E+07 3.51E+08 9.50E+07 1.32E+09 3.56E+08 8.40E+08 2.35E+08 1.43E+08 1.44E+08 3.53E+06 4.37E+06 1.60E+10 2.63E+10 8.28E+07 2.28E+08 2.39E+10 2.29E+10 1.73E+07 O.OOE+OO 4.67E+07 9.84E+07 1.57E+08 3.16E+08 1.30E+08 2.71 E+OS 8.18E+07 4.76E+10 1.65E+06 8.12E+08 5.55E+09 1.47E+08 3.38E+09 O.OOE+OO O.OOE+OO O.OOE+OO

2. 79E+08 2.44E+05 1.63E+07 O.OOE+OO 6.57E+05 3.28E+05 4.86E+04 O.OOE+OO 1.27E+08 3.99E+07 6.79E+06 O.OOE+OO 4.04E+07 O.OOE+OO 3.77E+09 2.47E+09 2.36E+08 7.28E+06 8.15E+09 1.21E+08 7.46E+09 7.96E+04 1.44E+05 2.21E+07 O.OOE+OO O.OOE+OO O.OOE+OO.

O.OOE+OO O.OOE+OO O.OOE+OO 2.93E+09 1.81E+07 2.68E+09 2.58E+09 3.38E+08 1.07E+09 1.02E+09 1.28E+07 1.76E+06 1.42E+08 8.00E+06 1.43E+08 1.46E+05 1.41 E+OS O.OOE+OO 4.09E+08 O.OOE+OO 1.04E+10 PR-143 1.45E+05 4.36E+04 7.21 E+03 O.OOE+OO 2.36E+04 O.OOE+OO 1.57E+08 ND-147 7.15E+04 5.79E+04 4.49E+03 O.OOE+OO 3.18E+04 O.OOE+OO 9.18E+07 TABLE 5.7.3 Pathway Dose Factors, Ri CY-TM-170-300 Revision 5 Page 176 of 222 AGE GROUP: TEEN PATHWAY: VEGETATION H-3 O.OOE+OO 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 C-14 3.69E+08 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 CR-51 O.OOE+OO O.OOE+OO 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 4.54E+08 3.26E+08 2.31 E+08 1.80E+08 4.19E+08 O.OOE+OO 4.36E+07 O.OOE+OO 2.49E+08 1.61 E+10 1.13E+09 4.24E+08 1.47E+09 O.OOE+OO 2.73E+08 1.52E+10 O.OOE+OO 9.01 E+07 5.39E+07 1.62E+08 1.01E+08 5.60E+08 5.45E+08 6.86E+08 1.28E+08 4.34E+08 O.OOE+OO 1.36E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.42E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.47E+08 1.32E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.32E+08 1.00E+08 9.91E+08 6.01E+08 3.24E+09 1.81E+08 6.23E+08 4.04E+07 1.80E+09 . . SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 7.51 E+11 7.84E+06 1.72E+06 1.92E+05 6.82E+06 3.09E+08 AG-110M 1.52E+07 TE-125M 1.48E+08 TE-127M 5.52E+08 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 3.61E+08 7.69E+07 1.94E+06 7.10E+09 4.39E+07 1.01E+10 O.OOE+OO 1.85E+11 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+05 O.OOE+OO O.OOE+OO 5.43E+05 3.73E+05 O.OOE+OO 7.98E+05 1.07E+05 5.87E+04 O.OOE+OO 2.92E+06 O.OOE+OO 3.90E+07 O.OOE+OO 1.03E+05 O.OOE+OO 2.41 E+07 O.OOE+OO 5.97E+08 1.43E+07 5.34E+07 1.96E+08 1.34E+08 1.08E+08 3.29E+06 1.67E+10 1.73E+08 1.35E+10 8.72E+06 O.OOE+OO 2.74E+07 1.98E+07 4.14E+07 O.OOE+OO 6.56E+07 1.31 E+08 2.24E+09

5. 72E+07 1.17E+08 5.78E+07 3.14E+10 1.00E+06 4.59E+08 7.75E+09 O.OOE+OO 1.16E+08 O.OOE+OO 4.69E+09 O.OOE+OO 1.51E+09 1.85E+08 5.77E+06 5.31E+09 9.41E+07 4.59E+09 O.OOE+OO 2.11E+10 O.OOE+OO 3.22E+09 O.OOE+OO 1.25E+09 O.OOE+OO 4.56E+08 O.OOE+OO

5. 70E+08 O.OOE+OO 1.48E+10 O.OOE+OO 4.03E+09 O.OOE+OO 4.37E+08 O.OOE+OO 1.37E+09 O.OOE+OO 1.36E+09 O.OOE+OO 2.13E+07 O.OOE+OO 2.49E+06 2.03E+09 2.08E+08 1.48E+07 1.39E+07 1.78E+09 1.92E+08

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BA-140 1.39E+'08 1.71E+05 8.97E+06 O.OOE+OO 5.78E+04 1.15E+05 2.15E+08 CE-141 2.83E+05 1.89E+05 2.17E+04 O.OOE+OO 8.90E+04 O.OOE+OO 5.41E+08 CE-144 5.28E+07 2.18E+07 2.83E+06 O.OOE+OO 1.30E+07 O.OOE+OO 1.33E+10 PR-143 6.99E+04 2.79E+04 3.48E+03 O.OOE+OO 1.62E+04 O.OOE+OO 2.30E+08 ND-147 3.62E+04 3.94E+04 2.36E+03 O.OOE+OO 2.31 E+04 O.OOE+OO 1.42E+08 L__ __ _ TABLE 5.7.4* Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: VEGETATION CY-TM-170-300 Revision 5 Page 177 of 222 BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

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H-3 O.OOE+OO 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 C-14 2.28E+08 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 CR-51 O.OOE+OO O.OOE+OO 4.64E+04

2. 77E+04 1.02E+04 6.15E+04 1.17E+07 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 2.10E+08 1.26E+08 O.OOE+OO o:ooE+oo 1.04E+10 3.17E+08 O.OOE+OO 9.98E+09 3.13E+08 1.45E+08 2.97E+08 5.97E+07 3.38E+07 1.14E+08 3.07E+07 6.89E+07 1.67E+08 3.69E+08 7.21 E+08 3.49E+08 1.01E+09 4.56E+08 2.19E+08 1.02E+08 O.OOE+OO 2.86E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.31E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.75E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.08E+07 8.29E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.58E+08 8.31E+07 9.89E+08 6.23E+08 3.14E+09 1.50E+08 6.36E+08 4.32E+07 1.60E+09

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*

SR-90 6.05E+11 O.OOE+OO 1.48E+11. O.OOE+OO O.OOE+OO O.OOE+OO 1.75E+10 Y-91 5.12E+06 O.OOE+OO 1.37E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E+09 ZR-95 1.17E+06 3.77E+05 2.55E+05 O.OOE+OO 5.91E+05 O.OOE+OO 1.19E+09 NB-95 1.42E+05 7.92E+04 4.26E+04 O.OOE+OO 7.83E+04 O.OOE+OO 4.81E+08 RU-103 4.77E+06 O.OOE+OO 2.06E+06 O.OOE+OO 1.82E+07 O.OOE+OO 5.57E+08 RU-106 1.93E+08 O.OOE+OO 2.44E+07 O.OOE+OO 3.72E+08 O.OOE+OO 1.25E+10

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AG-110M 1.05E+07 9.75E+06 5.79E+06 O.OOE+OO 1.92E+07 O.OOE+OO 3.98E+09 TE-125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 O.OOE+OO 3.86E+08 TE-127M 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 O.OOE+OO 1.17E+09

---

*

TE-129M 2.51E+08 9.37E+07 3.97E+07 8.63E+07 1.05E+09 O.OOE+OO 1.26E+09 1-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 O.OOE+OO 3.05E+07 1-133 2.09E+06 3.63E+06 1.11 E+06 5.34E+08 6.33E+06 O.OOE+OO 3.26E+06

---

*

CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 4.67E+09 4.28E+07 6.36E+09 1.29E+08 1.97E+05 3.29E+07 1.11E+10 1.69E+08 8.70E+09 1.62E+05 1.33E+05 1.38E+07 9.08E+09 1.22E+08 5.70E+09 8.47E+06 1.51 E+04 1.77E+06 O.OOE+OO 3.59E+09 O.OOE+OO 9.41E+07 O.OOE+OO 2.95E+09 O.OOE+OO 5.52E+04 O.OOE+OO 6.20E+04 O.OOE+OO 8.16E+06 1.19E+09 1.94E+08 1.29E+07 1.92E+07 9.81E+08 1.68E+08 9.29E+04 2.66E+08 O.OOE+OO 5.1 OE+08 O.OOE+OO 1.11E+10 PR-143 6.25E+04 2.51 E+04 3.1 OE+03 O.OOE+OO 1.45E+04 O.OOE+OO 2.74E+08 ND-147 3.34E+04 3.85E+04 2.31 E+03 O.OOE+OO 2.25E+04 O.OOE+OO 1.85E+08 6.0 TMl-1 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM CY-TM-170-300 Revision 5 Page 178 of 222 6.1 Description of the TMl-1 Gaseous Radwaste Treatment System (see Figure 6.1) 6.1.1 Waste Gas System a. Reactor Building: -Reactor Coolant Drain Tank (RCDT) header b. Auxiliary Building: -Vent Header from 1. Miscellaneous Waste Storage Tank (MWST) 2. Three (3) Reactor Coolant Bleed Tanks (RCBT) -Waste Gas Delay Tank -Two (2) Waste Gas Compressors -Three (3) Waste Gas Decay Tanks (WGDT) c. Filtration and dilution provided by the Station Ventilation System. 6.2 Operability of the TMl-1 Gaseous Radwaste Treatment System Operability of the Gaseous Waste Treatment System is defined as the ability to remove gas from the vent header/tank gas spaces and store it under a higher pressure in the Waste Gas Decay Tanks for subsequent release. Except for initiating the make up tank sample and waste gas venting and the recycle or disposal of compressed waste gases stored in the waste gas decay tanks, the operation of the waste gas system is entirely automatic. One waste gas compressor comes on automatically, removing gases from the vent header system as required, to maintain the pressure in the system at a maximum of about 16.4 psia. FIGURE 6.1 Waste Gas System Plllllllllll IUCfll llMl... IIUlfl IUIIS II. .... ,, , ...... .-----1 r------1 _ _.._ ...... __ .... I I alCWAIII lllUlltMI U.-----~-~ WN-ft4 TlftlJUI* HICI llflU t*tlll 11, ....... IIH'lf H *AIIIIAI 11ca, 1&111 C n () *>J ) + --~ -. u 0 II WUHUI ltCAIIMI

• tllTM.IIH WAIUIAI NCAIIMI A
• l _____ .1-t _______ __._ _______ ---J CY-TM-170-300 Revision 5 Page 179 of 222 WAIHUI t+~J IIUIIAU 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 7 .1 Total Dose Calculation CY-TM-170-300 Revision 5 Page 180 of 222 The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. This control is provided in order to meet the dose limitations of 40 CFR 190. The total dose from TMl-1 and TMl-2 (uranium fuel cycle facilities within 8 kilometers) is calculated by summing the calculated annual doses to critical organs of a real individual for liquid effluent using Section 2.1 methodology, for gaseous effluent using Section 5.2.1 and 5.2.2 methodology, and the direct radiation from the site from the environmental monitoring program's direct radiation monitors.

CY-TM-170-300 Revision 5 Page 181 of 222 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitoring Program Requirements 8.1.1 Controls In accordance with the TMl-1 Tech. Specs. and TMl-2 PDMS Tech. Specs., the radiological environmental monitoring program shall be conducted as specified in Table 8.1. 8.1.2 Applicability At all times. 8.1.3 Action a. With the radiological environmental monitoring program not being conducted as specified in Table 8.1, prepare and submit to the Commission in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 8.2 when averaged over any calendar

quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar

quarter, a special report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a member of the public is less than the calendar year limits of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part II Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3.

When more than one of the radionuclides in Table 8.2 are detected as the result of plant effluents in the sampling medium, this report shall be submitted if: concentration (1) concentration (2) > 1 0 reportinglevel(1) + reporting level(2) + -* When radionuclides other than those in Table 8.2 are detected and are the result of plant effluents, this report shall be The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report. CY-TM-170-300 Revision 5 Page 182 of 222 submitted if the potential annual dose* to a member of the public is equal to or greater than the calendar year limits of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part 11, Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents;

however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report. c. With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 8.1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then *be deleted from the monitoring program.

Pursuant to TMl-1 Tech. Spec. 6.14 and TMl-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples. 8.1.4 Bases The radiological monitoring program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and*for those radionuclides which lead to the highest potential radiation exposures of members of the general public resulting from the station operation. This monitoring program implements Section IV 8.2 of Appendix I to 1 OCFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operational experience. 8.1.5 Surveillance Requirements CY-TM-170-300 Revision 5 Page 183 of 222 The radiological environmental monitoring samples shall be collected pursuant to Table 8:1, from the specific locations given in Tables 8.4 through 8.10 and Maps 8.1 through 8.3, and shall be analyzed pursuant to the requirements of Table 8.1 and the detection capabilities required by Table 8.3. 8.2 Land Use Census 8.2.1 Controls CY-TM-170-300 Revision 5 Page 184 of 222 In accordance with the TMl-1 Tech. Specs. and TMl-2 PDMS Tech. Specs., a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation. 8.2.2 Applicability At all times. 8.2.3 Action a. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in ODCM Part I Surveillance 3.2.2.3.1, pursuant to ODCM, Part IV, Section 2.0, identify the new location(s) in the next Annual Radioactive Effluent Release Report. b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Table 8.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure

pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.

Pursuant to TMl-1 Tech. Spec. 6.14 and TMl-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations. Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted D/Qs in lieu of the garden census. Requirements for broad leaf sampling in Table 8.1 shall be followed, including analysis of control samples. 8.2.4 Bases CY-TM-170-300 Revision 5 Page 185 of 222 This Control is provided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial surveys, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR 50. Restricting the census to gardens of greater than 500 square feet (50 m2) provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter. 8.2.5 Surveillance Requirements The Land Use Census shall be conducted during the growing season at least once per 12 months, using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census*shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Part IV, Section 1.0. 8.3 lnterlaboratory Comparison Program 8.3.1 Controls CY-TM-170-300 Revision 5 Page 186 of 222 In accordance with the TMl-1 Tech. Specs. and TMl-2 PDMS Tech. Specs., analyses shall be performed on radioactive materials supplied as part of an lnterlaboratory Comparison Program which has been approved by the Commission (NRC). Only those samples and analyses which are required by Table 8.1 shall be performed. 8.3.2 Applicability At all times. 8.3.3 Action With analysis not being performed as required above, report the corrective action taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. 8.3.4 Bases The requirement for participation in an approved lnterlaboratory Comparison Program is provided to ensure that independent checks on precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV, 8.2 of Appendix I to 10 CFR 50. 8.3.5 Surveillance Requirements A summary of the lnterlaboratory Comparison Program results shall be included in the Annual Radiological Environmental Operating Report. Exposure Pathway and/or Sample 1. Airborne Radioiodine and Particulates TABLE 8.1 CY-TM-170-300 Revision 5 Page 187 of 222 Sample Collection and Analysis Requirements Number of Samples and Sampling and Type and Frequency Sample Locationsa Collection Frequencyb of Analysisb Samples from 5 locations Continuous sampler operation Radioiodine Canister: from Table 8.4. with sample collection weekly, Analyze weekly for 1-131. or more frequently if required Particulate Filter: Three of these samples by dust loading. Analyze for gross beta should be close to the Site radioactivity following filter Boundary, in different changed. Perform gamma sectors, of the highest isotopic analysise on calculated annual average composite (by location) ground level D/Q. sample quarterly. One of the samples should be from the vicinity of a community having the highest calculated annual average ground level D/Q. And one sample should be from a control location 15 to 30 km distant in a less prevalent wind direction. TABLE 8.1 (Cont'd) Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and and/or Sample Sample Locationsa Collection Frequencyb

2. Direct Radiation° Samples from 40 locations from Sample Quarterly Table 8.5 (using either 2 dosimeters or at least 1 instrument for continuously measuring and recording dose rate at each location).

Placed as follows: An inner ring of stations, one in each meteorological sector in the general area of the site boundary; An outer ring of stations, one in each meteorological sector in the 6 to 8 km from the site; and the balance of the stations to be placed in special interest areas such as population

centers, nearby residences,

schools, and in at least one or two areas to serve as control stations.

CY-TM-170-300 Revision 5 Page 188 of 222 Type and Frequency of Analvsisb Analyze for gamma dose quarterly. Exposure Pathway and/or Sample 3. Waterborne

a. Surface1 b. Drinking C. Sediment from Shoreline TABLE 8.1 (Cont'd)

CY-TM-170-300 Revision 5 Page 189 of 222 Sample Collection and Analysis Requirements Number of Samples and Sampling and Type and Frequency Sample Locationsa Collection Frequencyb of Analysisb Samples from 2 locations Composite9 sample over Perform gamma isotopic from Table 8.6. 1 monthly period. analysise monthly. Composite for tritium

• 1 sample from analysis quarterly.

downstream (indicator) location

• 1 sample from upstream (control) location (or location not influenced by the station discharge)

Samples from 2 locations Composite9 sample over Perform gross beta and from Table 8.6. 1 monthly period. gamma isotopic analysise monthly. Perform Sr-90

• 1 sample at the location of analysis if gross beta of the nearest water supply monthly composite

>10 that could be affected by times control. Composite for the station discharge. tritium analysis quarterly.

• 1 sample from a control location.

Samples from 2 locations Sample twice per year Perform gamma isotopic (1 Control and 1 Indicator) (Spring and Fall) analysise on each sample. from Table 8.7. ' I Exposure Pathway and/or Sample 4. Ingestion

a. Milk b. Fish TABLE 8.1 (Cont'd)

CY-TM-170-300 Revision 5 Page 190 of 222 Sample Collection and Analysis Requirements Number of Samples and Sampling and Type and Frequency Sample Locations 0 Collection Frequencyb of Analvsisb Samples from 4 locations from Sample semimonthly Perform gamma isotopic Table 8.8. when animals are on analysise and 1-131 pasture; monthly at other analysis on each sample. Samples should be from milking times. Composite for Sr-90 animals in three locations within 5 analysis quarterly. km distance having the highest dose potential. If there are none, then one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year. One sample from milking animals at a control location 15 to 30 km distant in a less prevalent wind direction. Samples from 2 locations from Sample twice per year Perform gamma isotopic0 Table 8.9. (Spring and Fall). and Sr-90 analysis on edible portions.

• 1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators in the vicinity of the station discharge.
• 1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators from an area not influenced by the station discharge.

TABLE 8.1 (Cont'd) Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and and/or Sample Sample Locationsa Collection Freauencvb

4. Ingestion (contd) c. Food Products Samples from 2 locations from Sample at time of Table 8.10 (when available) harvest.

• 1 sample of each principle class of food products at a location in the immediate vicinity of the station.

(indicator)

• 1 sample of same species or group from a location not influenced by the station discharge.

Samples of three different kinds Monthly during growing of broad leaf vegetation grown season nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milking sampling is not performed. One sample of each of the similar broad leaf vegetation grown 15 to 30 km distant in a less prevalent wind direction if milk sampling is not performed. CY-TM-170-300 Revision 5 Page 191 of 222 Type and Frequency of Analvsisb Perform gamma isotopic0, and 1-131, analysis on edible portions. Sr-90 analysis on green leafy vegetables or vegetation only. Perform gamma isotopic0 1-131 analysis. i I i I I TABLE 8.1 (Cont'd) Sample Collection and Analysis Requirements Table Notation CY-TM-170-300 Revision 5 Page 192 of 222 a. Sampling locations are provided in Tables 8.4 through 8.10. They are depicted in Maps 8.1 through 8.3. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. All deviations from the sampling schedule shall be explained in the Annual Radiological Environmental Operating Report. b. Frequency notation: weekly (7 days), semimonthly (15 days), monthly (31 days), and quarterly (92 days). All surveillance requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. A total maximum combined interval time for any 4 consecutive tests shall not exceed 3.25 times the specified collection or analysis interval.

c. One or more instruments, such as a pressurized ion chamber for measuring and recording dose rate continuously, may be used in place of, or in addition to, integrating dosimeters.

For the purpose of this table, a dosimeter is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

d. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in an air particulate sample(s) is greater than ten times the calendar year mean of control samples, Sr-90 and gamma isotopic analysis shall be performed on the individual sample(s).

e. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

f. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge.

The "downstream sample" shall be taken in an area beyond but near the mixing zone. g. Composite sample aliquots shall be collected at time intervals that are short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample. TABLE 8.2 CY-TM-170-300 Revision 5 Page 193 of 222 Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Particulate Water or gas Fish Milk Food Products Analysis (pCi/L) (pCi/m3) (pCi/kQ,wet) (pCi/L) (pCi/kQ, wet) H-3 20,000(a) Mn-54 1000 30,000 FE-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Sr-90 8 0.1 100 8 100 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 (a) For drinking water samples. This is 40 CFR Part 141 value. Analysis Gross Beta H-3 Mn-54 FE-59 Co-58, 60 Zn-65 Zr-95 Sr-90 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 TABLE 8.3 CY-TM-170-300 Revision 5 Page 194 of 222 Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD)b,c Airborne Particulate Food Water or Gas Fish Milk Products Sediment (pCi/L) (pCi/m3) (pCi/kg wet) (pCi/L) (pCi/kg,wet) (pCi/kg, dry) 4 0.01 2000 15 130 30 260 15 130 30 260 30 2 0.01 10 2 10 15 1d 0.07 1 60 15 0.05 130 15 60 150 18 0.06 150 18 80 180 60 60 15 15 TABLE 8.3 (Cont'd) CY-TM-170-300 Revision 5 Page 195 of 222 Detection Capabilities for Environmental Sample Analysis3 Table Notation

a. This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, which may be related to plant operations, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report. b. Required detection capabilities for dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Rev. 1 ). c. The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): LLD= 4.66Sb E

• V
• 2.22
• Y
• exp (-1c~t) Where: LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume. Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

'A, is the radioactive decay constant for the particular radionuclide and ~t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, a~d time of counting. Typical values of E, V, Y and ~t should be used in the calculation. TABLE 8.3 (Cont'd) CY-TM-170-300 Revision 5 Page 196 of 222 Detection Capabilities for Environmental Sample Analysis3 Table Notation It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small samples sizes, the presence of interfering

nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. d. LLD for drinking water. TABLE 8.4 CY-TM-170-300 Revision 5 Page 197 of 222 TMINS REMP Station Locations-Air Particulate and Air Iodine Station Code Distance (miles) Azimuth (0) Map No. E1-2 0.4 97 8.1 F1-3 0.6 112 8.1 G2-1 1.4 126 8.2 M2-1 1.3 256 8.2 A3-1 2.7 357 8.2 H3-1 2.2 160 8.2 Q15-1 13.4 309 8.3 TABLE 8.5 TMINS REMP Station Locations-Direct Radiation Station Code Distance (miles) Azimuth (0) Map No. A1-4 0.3 6 8.1 B1-1 0.6 25 8.1 B1-2 0.4 24 8.1 C1-2 0.3

• 50 8.1 D1-1 0.2 76 8.1 E1-2 0.4 97 8.1 E1-4 0.2 97 8.1 F1-2 0.2 112 8.1 G1-3 0.2 130 8.1 H1-1 0.5 167 8.1 J1-1 0.8 176 8.1 J1-3 0.3 189 8.1 K1-4 0.2 209 8.1 L 1-1 0.1 236 8.1 M1-1 0.1 249 8.1 N1-3 0.1 274 8.1 P1-1 0.4 303 8.1 P1-2 0.1 292 8.1 CY-TM-170-300 Revision 5 Page 198 of 222 TABLE 8.5 (Cont'd)

TMINS REMP Station Locations-Direct Radiation Station Code Distance (miles) Azimuth (0) Map No. Q1-2 0.2 321 8.1 R1-1 0.2 335 8.1 C2-1 1.5 44 8.2 K2-1 1.2 200 8.2 M2-1 1.3 256 8.2 A3-1 2.7 357 8.2 H3-1 2.2 160 8.2 R3-1 2.6 341 8.2 A5-1 4.4 3 8.2 B5-1 4.9 19 8.2 C5-1 4.7 43 8.2 E5-1 4.7 82 8.2 F5-1 4.7 109 8.2 G5-1 4.8 131 8.2 H5-1 4.1 158 8.2 J5-1 4.9 181 8.2 K5-1 4.9 202 8.2 L5-1 4.1 228 8.2 M5-1 4.3 249 8.2 N5-1 4.9 268 8.2 P5-1 5.0 284 8.2 Q5-1 5.0 317 8.2 R5-1 4.9 339 8.2 D6-1 5.2 66 8.3 E7-1 6.7 88 8.3 Q9-1 8.5 310 8.3 B10-1 9.2 21 8.3 G10-1 9.7 128 8.3 G15-1 14.4 126 8.3 J15-1 12.6 183 8.3 Q15-1 13.4 309 8.3 TABLE 8.6 TMINS REMP Station Locations-Surface Water Station Code Distance (miles) Azimuth (0) J1-2 (SW) 0.5 188 A3-2 (SW) 2.7 356 Q9-1 (OW) 8.5 310 Q9-1 (SW) 8.5 310 G15-2 (OW) 13.3 129 G15-3 (OW) 15.7 124 (SW) = Surface Water (OW) = Drinking Water TABLE 8.7 TMINS REMP Station Locations-Aquatic Sediment Station Code A1-3 K1-3 J2-1 Distance (miles) 0.6 0.2 1.4 Azimuth (0) 359 213 179 CY-TM-170-300 Revision 5 Page 199 of 222 Map No. 8.1 8.2 8.3 8.3 8.3 8.3 Map No. 8.1 8.1 8.2 Station Code E2-2 F4-1 G2-1 P4-1 K15-3 Station Code E1-2 H1-2 810-2 TABLE 8.8 TMINS REMP Station Locations-Milk Distance (miles)

• Azimuth (0) 1.1 96 3.2 104 1.4 126 3.6 295 14.4 205 TABLE 8.9 TMINS REMP Station Locations-Fish Station Location CY-TM-170-300 Revision 5 Page 200 of 222 Map No. 8.2 8.2 8.2 8.2 8.3 Station Code IND BKG Downstream of Station Discharge Upstream of Station Discharge TABLE 8.10 TMINS REMP Station Locations-Food Products Distance (miles) 0.4 1.0 10.0 Azimuth (0) 97 151 31 Map No. 8.1 8.1 8.3

'N MAP 8.1 Three Mile Island Nuclear Station CY-TM-170-300 Revision 5 Page 201 of 222 Locations of Radiological Environmental Monitoring Program Stations Within 1 Mile of the Site ,* rl1i/ /s/(li1it ._;:;/~*..:' \. *m "" ""~ [J] i / i '* ' ' ,* "' " * , , "' ., ., . [ITiJ . .. . * '. Ser;lce Layer Qedits: Swrces: Esrl, Delorme, W.V1EQ, TomTOIT\ lnle[ll13!), ilcrement p Corp., GEBCO, USGS, FAO, NPS, NRCAN, GeoBase, IGN, KadasterNL, Orctlance Survey, Esrl . Jai,a11 METl,,Esrl Clina (Hoog Kong), swlsstopo, and Iha GIS User COrrmmly ' ** _ " I I ' + MAP 8.2 Three Mile Island Nuclear Station CY-TM-170-300 Revision 5 Page 202 of 222 Locations of Radiological Environmental Monitoring Program Stations Within 5 Miles of the Site t1 .. ,:1k-ht':71 ,:~"11 ;t;lj.J \ ; .. T \ t Qi .. ' *.... . Seivlce Layer a-edits: Sources: Esrl, Del.llrme; NAVTEQ, TomT0111*lnlermai>, i'lcrement P Corp., GEB.CO, USGS, FAO, NI'S, NRCAN, GeoBase, IGN, Kadaster NL,,Or<l'lance S<1Vey, Esrl Japan,METl,EsriCtJna(HongKong),(*~st6):<>,andtheGISUser\Cormwrlit~.~*

s 1~* .. 11011*!,hl !\tt \Vofl ', * *, * ',1,1 {.

MAP 8.3 Three Mile Island Nuclear Station CY-TM-170-300 Revision 5 Page 203 of 222 Locations of Radiological Environmental Monitoring Program Stations Greater Than 5 Miles from the Site *1,,.~*.Hl t,, N n 11::" oa T:,p 't *,rn,.,.,.~, /!<_1,f,lt***I 1*.r 10Miles Service Layer o ans: ~~r,~; Esrt, Delorme, NAV'TEO:*To~T6~i~e~ .. ~g~ment P Corp., GEBcd,'Usds, FAO, J.ap~i:i, METI, Esri Ctina1(}:long ~ong), swlsstopo, and the GIS User Commmity r,.~11-, 1 \ .. 1.,,1.*,r,, ,.-,p 11,.1,klt*l*l r.~, f,$,\ L<,, l'*'l'l-' I.',) 9.0 PART Ill REFERENCES CY-TM-170-300 Revision 5 Page 204 of 222 1. EPRI NP-3840, RP 1560-3 Final Report, "Environmental Radiation Doses From Difficult-To-Measure Nuclides," January 1985 2. "Evaluation of the Three Mile Island Nuclear Station Unit 1 to Demonstrate Conformance to the Design Objectives of 10 CFR 50, Appendix I," Nuclear Safety Associates, May 1976 3. TMl-1 Final Safety Analysis Report (FSAR) 4. TMl-2 Post Defueled Monitored Storage Safety Analysis Report (PDMSSAR)

5. Meteorological Information and Dose Assessment System (MIDAS) 6. NUREG-0017, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWR," Revision 1, 1985 7. NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978 8. NUREG-0172, "AgE-Specific Radiation Dose Commitment Factors For A OnE-Year Chronic Intake," November 1977 9. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," Revision 1, June 1974 10. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977 11. TDR-390-TMI Primary to Secondary OTSG Leakage and its Onsite/Offsite Radiological Impact 12. SCR-358-82-063, "Study of Travel Time and Mixing Characteristics for the Susquehanna River Below Three Mile Island Final Report", July 1982 13. TMl-1 Operations Procedure, 1101-2.1, "Radiation Monitor Set Points" 14. Title 10, Code of Federal Regulations, "Energy"

15. TMl-1 Technical Specifications, attached to Facility Operating License No. DPR-50 16. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 1977 CY-TM-170-300 Revision 5 Page 205 of 222 17. TMl-2 PDMS Technical Specifications, attached to Facility License No. DPR-73 18. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 19. Title 40, Code of Federal Regulations, "Protection of Environment"

20. Regulatory Guide 4.13, "Performance,

Testing, and Procedural Specifications for Thermoluminescence Dosimetry:

Environmental Applications," Revision 1, July 1977 PART IV REPORTING REQUIREMENTS CY-TM-170-300 Revision 5 Page 206 of 222 PART IV Reporting Requirements CY-TM-170-300 Revision 5 Page 207 of 222 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT** 1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted to the Commission prior to May 1 of each year. 1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring activities for the report period, including a comparison with pre-operational

studies, with operational controls as appropriate, and with previous environmental monitoring

reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of Land Use Censuses required by Part Ill, Section 8.2. 1.3 The Annual Radiological Environmental Operating Reports shall include the summarized tabulated results of analysis of all radiological environmental samples and environmental radiation measurements required by Part Ill Table 8.1 taken during the period pursuant to the locations specified in the tables and figures in this ODCM, as well as summarized and tabulated results of these analyses and measurements in a format similar to the table in the Radiological Assessment Branch Technical

Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report. 1.4 The reports shall also include the following: A summary description of the radiological environments monitoring program; a map(s) of all sampling locations keyed to a table giving distances and directions from a point that is midway between the Reactor Buildings of TMl-1 and TMl-2; the results of licensee participation in the lnterlaboratory Comparison

Program, required by Part Ill, Section 8.3; discussion of all deviations from the sampling schedule of Part Ill, Table 8.1; discussion of all the required analyses in which the LLD required by Part Ill, Table 8.3 was not achievable.

-A single submittal may be made for the station. 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CY-TM-170-300 Revision 5 Page 208 of 222 NOTE: A single submittal may be made for the station. The submittal should combine those sections that are common to both units at the station however, for units with separate radwaste

systems, the submittal shall specify the release of radioactive material from each unit. 2.1 . Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous 12 months of operation shall be submitted prior to May 1 for TMl-1 and TMl-2. 2.2 The following information shall be included in both Radioactive Effluent Release Reports to be submitted each year: The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev. 1, with data summarized on a quarterly basis following the format of Appendix B thereof.

2.3 The Radioactive Effluent Release Reports shall include the following information for each type of solid waste shipped offsite during the report period: a. Type of waste (e.g., resins/filters/evaporator

bottoms, dry active waste or other b. Total volume of each waste type c. Total activity of each waste type d. Principle radio-nuclides of each waste type and percentages

e. Solid waste disposition (Carrier and Consignee)

f. Irradiated fuel shipments disposition (Carrier and Consignee) 2.4 The Radioactive Effluent Release Reports shall include a summary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period. 2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part Ill Section 8.2.

CY-TM-170-300 Revision 5 Page 209 of 222 2.6 The Radioactive Effluent Release Reports shall include the instrumentation not returned to OPERABLE status within 30 days per ODCM Part I Controls 2.1.1 b and 2.1.2b, and ODCM Part II Control 2.1.2b. 2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmosphere stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability.

• 2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation doses to MEMBERS OF THE PUBLIC at or beyond the site boundary due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The assessment of radiation doses shall be performed in accordance with this ODCM. 2.9 The Radioactive Effluent Release Report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period, to verify compliance with the limits of 1 OCFR20.1301 (a)(1 ). All assumptions used in making these assessments (i.e., specific

activity, exposure time and location) shall be included in these reports.

2.10 The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed real individual from reactor releases, and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation for the previous 12 consecutive months, to show conformance with 40 CFR 190 "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1. 2.11 The Radioactive Effluent Release Report shall also include a report of major changes to Radioactive Waste Treatment Systems. FSAR Section 11.2.6 requires this reporting. 3.0 PART IV REFERENCES CY-TM-170-300 Revision 5 Page 210 of 222 3.1

• Radiological Assessment Branch Technical

Position, Revision 1, November 1979 3.2 Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"

Revision 1, June 197 4 3.3 TMl-1 Technical Specifications, attached to Facility Operating License No. DPR-50 3.4 Title 40, Code of Federal Regulations, "Protection of Environment" 3.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 3.6 Title 10, Code of Federal Regulations, "Energy"

3. 7 Regulatory Guide 1, 111, "Methods of Estimating Atmospheric Transport

~nd Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977 3.8 Regulatory Guide 1.112, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors," Revision 0-R, April 1976 3.9 Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision 1, April 1977 APPENDIX A Page 1 of 1 Pi -Pathway Dose Rate Parameter Pi (inhalation)= k' (BR) DFAi Where: CY-TM-170-300 Revision 5 Page 211 of 222 (Eq A-1) Pi= the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the* inhalation

pathway, in mrem/yr per microcurie/m 3* The dose factors are based on the critical individual organ for the child age group. k' = conversion factor, 1 E6 pCi/microcurie BR= 3700 m3/yr, breathing rate for child (Reg. Guide 1.109, Rev. 1, Table E-5) DFAi = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide (mRem/pCi).

Values are taken from Table E-10, Reg. Guide 1.109 (Rev. 1 ), or NUREG-0172. Resolution of the units yields: (ODCM Part Ill Table 4.6) Pi (inhalation)= 3.7E9 DFAi (mrem/yr per µCi/m3) NOTE: The latest NRC Guidance has deleted the requirement to determine Pi (ground plane) and Pi (food). In addition, the critical age group has been changed from infant to child. (Eq A-2) APPENDIX B Page 1 of 1 Ri -Inhalation Pathway Dose Factor Ri = k' (BR) (DFAi,a,o) (mrem/yr per microcurie/m

3) Where: k' = conversion factor, 1 E6 pCi/microcurie CY-TM-170-300 Revision 5 Page 212 of 222 (Eq 8-1) BR= breathing rate, 1400, 3700, 8000, 8000 m3/yr for infant, child, teenager, and adult age groups, respectively.

(Reg. Guide 1.109, Rev. 1, Table E-5) DFAi,a,o = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrem/pCi. The total body is considered as an organ in the selection of DFAi,a,o. Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Rev. 1 ), or NU REG 0172. Resolutions of the units yields: Ri = (1.4E9) (DFAi,a,o) infant (ODCM Part Ill Table 5.2.1) Ri = (3.7E9) (DFAi,a,o) child (ODCM Part Ill Table 5.2.2) Ri = (8.0E9) (DFAi,a,o) teen and adult (ODCM Part Ill Tables 5.2.3 and 5.2.4) Where: APPENDIXC Page 1 of 1

• Ri -Ground Plane Pathway Dose Factor k' = conversion factor, 1 E6 pCi/microcurie k" = conversion factor, 8760 hr/yr Ai = decay constant for the ith radionuclide, sec -1 CY-TM-170-300 Revision 5 Page 213 of 222 (Eq C-1) t =
• the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec. (15 yrs), Reg. Guide 1.109 (Rev. 1), Appendix C DFGi = the ground plane dose conversion factor for the ith radionuclide (mrem/hr per pCi/m2). Values are taken from Table E-6, Reg. Guide 1.109 (Rev .. 1 ), or NUREG 0172. These values apply to all age groups. SF= 0.7, shielding factor, from Table E-15 Reg. Guide 1.109 (Rev. 1) Reference ODCM Part Ill Table 5.3.1 APPENDIXD Page 1 of 2 CY-TM-170-300 Revision 5 Page 214 of 222 Ri -Grass Cow-Milk Pathway Dose Factor Ri = k' [(QF X UAP)/ {Ai + Aw)] X {Fm) X (r) X {DFLi,a,o)

X [((fp X fs)/Yp) + ((1-fp X fs) e -Aith)/Ys] e -Ai~ (Eq D-1) Where: k' = conversion factor, 1 E6 picocurie/microcurie (pCi/µci) QF = cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1) goat consumption rate, 6 kg/day, (Reg. Guide 1.109, Rev. 1, Table E-2) UAP= Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1) YP = agricultural productivity by unit area of pasture feed grass, 0. 7 kg/m2 (NUREG-0133) Ys = agricultural productivity by unit area of stored feed, 2.0 kg/m2 (NUREG-0133) Fm = stable element transfer coefficient (Table E-1, Reg. Guide 1.109, Rev. 1) r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, Reg. Guide 1.109, Rev. 1) DFLi,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1 ), or NU REG 0172. Ai = decay constant for the ith radionuclide, sec-1 Aw= decay constant for weathering, 5.73 x 10-7 sec-1 (NUREG-0133); based on a 14 day half life tt = 1. 73 x 105 sec, the transport time from pasture to cow to milk to receptor (Table E-15, Reg. Guide 1.109, Rev. 1 ), or 2 days th = 7. 78 x 106 sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-15, Reg. Guide 1.109, Rev. 1 ), or 90 days fp = 1.0, the fraction of the year that the cow is on pasture fs = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture APPENDIX D Page 2 of 2 CY-TM-170-300 Revision 5 Page 215 of 222 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q): Rct,a,o = k'k"' Fm QF UAPDFLt,a,o (.75 [.5/H]) Where: k"' = 1 E3 grams/kg H = 8 grams/m3, absolute humidity of the atmosphere .75 = fraction of the total feed grass mass that is water (Eq D-2) .5 = ratio of the specific activity of the feed grass water to the atmospheric water (NUREG-0133) DFLt,a,o = the ingestion dose factor for tritium and organ, o, for each respective age group, a {Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172. All other parameters and values are as given above. NOTE: Goat-milk pathway factor, Ri, will be computed using the cow-milk pathway factor equation. Fm factor for goat-milk will be from Table E-2 Reg. Guide 1.109, Rev. 1.

Reference:

ODCM Part Ill Tables 5.4.1 to 5.4.4 APPENDIXE Page 1 of 2 CY-TM-170-300 Revision 5 Page 216 of 222 Ri -Grass Cow-Meat Pathway Dose Factor Ri = k' [(QF X UAP)/ (Ai + Aw)] X (Ft) X (r) X (DFLi,a,o) X [((fp X fs)/Yp) + ((1-fpfs) e -Aith)/Ys] Xe -Ai\ (Eq E-1) Where: k' = conversion factor, 1 E6 picocurie/microcurie (pCi/µci) QF = cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1) UAP = Receptor's meat consumption rate; 0, 41, 65, 110 kg/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1) Ft= the stable element transfer coefficients, days/kg (Table E-1, Reg. Guide 1.109, Rev. 1) r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, Reg. Guide 1.109, Rev. 1) DFLi,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1 ), or NU REG 0172. Ai = decay constant for the radionuclide i, sec-1 Aw= decay constant for weathering, 5.73 x 10-7 sec-1 (NUREG-0133), based on a 14 day half life t, = 1. 73 x 106 sec, the transport time from pasture to receptor (NUREG-0133) or 20 days th= 7.78 x 106 sec, the transport time from crop to receptor (NUREG-0133) or 90 days YP = agricultural productivity by unit area of pasture feed grass, 0. 7 kg/m2 (NUREG-0133) Ys = agricultural productivity by unit area of stored feed, 2.0 kg/m2 (NUREG-0133) fp = 1.0, the fraction of the year that the cow is on pasture fs = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture APPENDIX E Page 2 of 2 CY-TM-170-300 Revision 5 Page 217 of 222 The concentration of tritium in meat is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q): Rt,a,o = k'k"' Ft QF UAP (DFLt,a,o) X 0.75 X (0.5/H]) Where: All terms are as defined above and in Appendix D.

Reference:

ODCM Part Ill, Tables 5.6.1 to 5.6.4 (Eq E-2) Where: APPENDIX F Page 1 of 1 Ri -Vegetation Pathway Dose Factor k' =

• 1 E6 picocurie/microcurie (pCi/µci)

CY-TM-170-300 Revision 5 Page 218 of 222 (Eq F-1) ULA = the consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant, child, teenager, or adult age groups, respectively (Reg. Guide 1.109, Rev. 1) U5A = the consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenager, or adult age groups respectively (Reg. Guide 1.109, Rev. 1) fL = the fraction of the annual intake of fresh leafy vegetation grown locally,

1.0 (NUREG-0133) f9 = the fraction of the stored vegetation grown locally

0. 76 (NUREG-0133) tL = the average time between harvest of leafy vegetation and its consumption, 8.6 x 104 seconds [Table E-15, Reg. Guide 1.109, Rev. 1 (24 hrs)] th = the average time between harvest of stored leafy vegetation and its consumption, 5.18 x 106 seconds,

[Table E-15, Reg. Guide 1.109, Rev. 1 (60 days)] Yv = the vegetation area density, 2.0 kg/m2 (Table E-15, Reg. Guide 1.109, Rev. 1) All other parameters are as previously defined. The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q) Rt,a,o = k'k"' [ULA fL + U5A fg] (DFLt,a,o) (.75 [.5/H]) Where: All terms are as defined above and in Appendix D.

Reference:

ODCM Part Ill, Tables 5.7.1 to 5.7.4 (Eq F-2) Parameter DFAi BR r Yv AW DFL UaL fL tL Ua8 fg th H BR DFAi APPENDIX A-F REFERENCES Page 1 of 4 Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Value R.G. 1.109 NUREG-0133

• • • For Pi *** Each radionuclide E-9 3700 m3/yr {child) E-5 ***For Ri (Vegetation)***

Each element type E-1 2.0 kg/m2 E-15 5.73 E-7 sec1 5.3.1.3 Each age group and radionuclide E-11 thru E-14 Each age group E-5 1.0 5.3.1.5 8.6 E + 4 seconds E-15 ' Each age group E-5 0.76 5.3.1.5 5.18 E + 6 seconds E-15 8.0 grams/m3 5.2.1.3 ***For R1 (Inhalation)*** Each age group E-5 Each age group and nuclide E-7 thru E-10 CY-TM-170-300 Revision 5 Page 219 of 222 Site-Specific Note 1 Note 1 Note 1 Parameter SF DFG; t OF(Cow) OF (Goat) Uap AW F1 (Both) r DFL; fp fs Yp th Ys t1 H APPENDIX A-F REFERENCES Page 2 of 4 CY-TM-170-300 Revision 5 Page 220 of 222 Parameters Used in Dose Factor Calculations . Origin of Value Table in Section of Site-Value R.G. 1.109 NUREG-0133 Specific

• • • For Ri (Ground Plane) *** 0.7 E-15 Each radionuclide E-6 4.73 E + 8 sec 5.3.1.2 *** For Ri (Grass/Animal/Meat)
    • 50 kg/day E-3 6 kg/day E-3 Ref. Only Each age group E-5 5.73 E-7 sec1 5.3.1.3 Each element E-1 Each element type E-15 Each age group and nuclide E-11 thru E-14 Note 1 1.0 5.3.1.3 Note 2 1.0 5.3.1.3 Note 2 0.7 kg/m2 E-15 7.78 E + 6 sec E-15 2.0 kg/m2 E-15 1.73 E + 6 sec E-15 8.0 grams/m3 5.2.1.3 Parameter 01 Uap AW Fm r DFL1 Yp th Ys tt fp fs H APPENDIX A-F REFERENCES Page 3 of 4 Parameters Used in Dose Factor Calculations Oriqin of Value Table in Section of Value R.G. 1.109 NUREG-0133
    • For R; (Grass/Cow/Milk)
    • 50 kg/day E-3 Each age group E-5 5.73 E-7 sec1 5.3.1.3 Each element E-1 Each element type E-15 Each age group and nuclide E-11 thru E-14 0.7 kg/m2 E-15 7.78 E + 6 sec E-15 2.0 kg/m2 E-15 1.73 E + 5 sec E-15 1.0 5.3.1.3 1.0 5.3.1.3 8.0 grams/m3 5.2.1.3 CY-TM-170-300
• Revision 5 Page 221 of 222 Site-Specific Note 1 APPENDIX A-F REFERENCES Page 4 of 4 NOTES CY-TM-170-300 Revision 5 Page 222 of 222 1. Inhalation and ingestion dose factors were taken from the indicated source. For each age group, for each nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the referenced table. 2. Typically, beef cattle are raised all year on pasture.

Annual land surveys have indicated that the small number of goats raised within 5 miles, typically are used for grass control and not food or milk. Nevertheless, the goats can be treated as full meat sources where present, despite the fact that their numbers cannot sustain the meat consumption rates of Table E-5, NUREG-0133. REFERENCES

1. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance

.with 10 CFR Part 50, Appendix I," Revision 1 , October 1977. 2. TMl-1 Technical Specifications, attached to Facility Operating License No. DPR-50. 3. NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978. 2017 Annual Radioactive Effluent Release Report for TMI Enclosure 2 -Page 1 of 1 Process Control Program for Radioactive Wastes, Revision 12 RW-AA-100 (Revision 12 was issued on September 30, 2017) 2017 Annual Radioactive Effluent Release Report for TMI Enclosure 1 -Page 1 of 1 ODCM Change for TMI Offsite Dose Calculation Manual, Revision 5 CY-TM-170-300 (Revision 5 approved in 2017 and issued on December 8, 2017) Document Site Approval Form Page 1 of 2 AD-AA-101

• F-01 Revision 7 Sas AD-AA-101 for the procedural requirements associated with this Form. I Facility:

TMI Desktop Instruction avallable an Intranet or thrauah AD functional area. Document Number: CY-TM-170-300 Revision: 5 Title: Offsite Dose Calculation Manual (ODCM) Superseded Documents: NIA l'8l or List: If superseding document(s) containing commitments, then PROCESS commitment change per LS-AA-110. Environmental Review Applicability-Is an Environmental Review applicable per EN-AA-103? No l'8] or Yes L.J If Yes, then attach Environmental Review documentation required per EN-AA-103. Is this a Fleet Standard Document being processed with form AD-AA-101-F-09? No 181 or Yes D If yes, then h h D AA k' h ' attac t e comp1 eted orm A --101-F-09, s *1p t e fo/lowmg

section, and go to Continuation A. Batch -Are multiple document creations/revisions/cancelations being Issued to add/revise/cancel them for similar requirements?

No !81 or Yes D If Yes, then identifvthe hi!:ihest level Document and Issue Type below. Check onl'.J! one Document T~ee: Check onl~ one Issue T)lE!e: lncoreorated Site Items (EC1 AR1 Level 1 -Continuous Use Procedure D NewD PCR1 etc}: Level 2-Reference Use Procedure 0 Revision t8I IA 2665375-49 Level 3 -Information Use Procedure [8) Cancel/Supersede Document D NER-NC-17-001 T&RMD Cancel Revision D Non-Permanent D FormO CancelNon-Permanent[J OtherD Editorial Revision D Revision Summary: See attached Summarv Matrix (Attach additional description if required) CONFIRM that~ commitments (i.e., those steps annotated with CM-X) have been changed or deleted unless evaluated via completion of LS-M-11 O commitment change/deletion form and INITIAL [Preparer]: LKW Preparer L.K.Weber 10/18/17 8947 Print Date Extension Validation -Is validation required per AD-M-101? No QSJ or Yes 0 If Yes, then attach completed AD-AA-101-F-03. Consequence Risk Factors-ls a Risk Assessment required per HU-AA-1212 applicability (e.g. design changes, equipment operating procedures)? No [8) or Yes D If Hiah or Medium Risk Factors exist, the orocedure validallon Is reauired oer AD*AA-101-F-03 NOS Review -Excluding NOE, ISi, Peer Inspection or Independent Verification, is this document used to perform independent inspection for acceptance (including field installation inspections, fabrication inspections, receipt inspections, new fuel inspection, etc.), or tor certification of Inspection personnel? No [8J or Yes D If Yes, then NOS Reviewer to print name & sign for acceptance: C~ntinuation A -Is this a T&RM, Form, or Editorial Revision? No or Yes LJ If yes, then skip the following section and o Continuation B. Impact on Operating and Design Margins -NIA t8J or explain: Attach additional desert lion if re ulred 181 No O Yes 1 OCFRS0.59 Applicable? t8J No O Yes 1 OCFR72.48 Applicable? Tracking Number: -----------11 D No 181 Yes Other Regulatory Process Applicable? Other Regulatory Process Number: CY-AA-170-3100 t8J No D Yes Potential security impact per SY-AA-S00-1277 It Yes, then Security Reviewer acceptance documented by cross discipline review below t8I No D Yes Surveillance Coordinator Review Required? Cross Discipline Reviews: (list below) 4re "r I ,,.1 or\ SOR Approval indicates that all required Cross-Disciplinary revie procedure is technically and func

• all ccurate for all function SQR Approval:

, "e/~~ It Yes, then Surveillance Coordinator/Predefine Reviewer acceptance documented by cross discipline review below 11/1 /,2017 GPU Cog. Officer Oare lf/2-/1'7 Dale Discipline Document Site Approval Form Page 2 of 2 AD-AA-101-F-01 Revision 7 Continuation B -Is this a T&RM, or Form? No [81 or Yes D If yes, then skip the following section and go Continuation C. PORC Required: D No [8] Yes Date es D If yes, then skip the following section and go to Applicable Site Contact/Site Change Agents (SME): D. Brookhart -Responsible for Change Management information in [81 this form or D HU-AA-1101 Checklist (attached) -Responsible to shepherd the document through site review, approval/authorization, and implementation. Affected Functional Area(s) or Individuals: Print Signature Date Affected FA Print Signature Date Affected FA Print Signature Dale Affected FA Attach additional if req'd Resources needed to Implement Change: LOE (Only list, if other than Level of Effort.) For ongoing impacts, estimate number of Full Time Equivalents (FTE). If additional resources are needed go to HU-AA-1101. Communication Plan: N/A (e.g., e-mail, Site Paper, Supervisor

Briefing, Voice Mail, etc.) Training Required

/ Qualifications affected: [81 No 0 Yes If yes, list: __ (e.g., Supervisory

Briefing, Tailgate

Briefing, Required

Reading, Formal Training, recertification etc.) Update to information infrastructure (e.g. PassPort, PIMS, EDMS workflows, etc.) required to support implementation (including updated forms loaded into PassPort):

N/A Controlled Document distribution (ref. RM-AA-102) or Records Retention Schedule (ref. RM-AA-101-1004) impacted: IZ! No D Yes If yes, describe change and list Records Management Person contacted: __ Continuation D -If all procedurally required activities associated with this document revision have been completed and the document is ready for implementation, then SFAM to print name, sign & date for authorization to implement. Provide implementation date or, if the Implementation Date is blank or NIA then implementation will be upon the issuance by Records Management per RM requirements. Authorization below indicates the SFAM or a designee of the SFAM has verified the document does not alter or negatively impact compliance with regulatory requirements or station commitments. Is this a non-permanent site specific revision to a fleet standard procedure or T&RM or Form? No [81 or Yes D If yes, then CFAM approval must been obtained. Is this a site specific revision that deviates from fleet standard procedure or T&RM or Form requirements? No [81 or Yes D If yes, then CFAM approval must been obtained. CFAM Authorization when required: _N_/A ___________________ _ Site Authorization: . I U\.-,. SRRS Number 1B.100 Interim Chg#: N/A N/A lmpl. Date Exp. Date 50.59 REVIEW COVERSHEET FORM Station/Unit(s): --=T=M=I=------------- LS-AA-104-1001 Revision 4 Page l of2 Activity/Document Number: Title: Offsite Dose Calculation Manual (ODCM) Revision Number: ~5 ____ _ NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2). Description of Activity: (Provide a brief, concise description of what the proposed activity involves.) The ODCM is being revised to remove plant shutdown statements from the ODCM as directed by NER -NC-17-001, and to replace the shutdown statements related to primary secondary leakrate with a reference to the corporate procedure CY-AA-120-340 which implements the EPRI Primary to Secondary Leakrate (PSLR) guidelines. Reason for Activity: (Discuss why the proposed activity is being performed.) NUREG 1303-Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, Table 3.3-13 for Condenser evacuation systems requires one noble gas activity operable channel or take the action to perform grab samples every 12 hours. The EPRI SGMP-PWR PSLR guidelines (1022832)- do not require any additional actions beside compensatory sampling for only the condenser offgas monitor being out of service. Plant shutdown requirements are based on the amount of PSLR not whether the rad monitor is operable. Effect of Activity: (Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.) None. The ODCM will continue to describe the compensatory sampling actions required when the condenser offgas noble gas monitor is not operable. The ODCM and Tech Spec 6.8.4.a will continue to require operability of the rad monitor and the 30 day ODCM timeclock for a not operable offgas noble gas monitor. Requirements to report in the NRC annual report why the inoperability was not corrected in a timely manner ( <30 days) will remain unchanged. Summary of Conclusion for the Activity's 50.59 Review: (Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment

Request, as applicable, is not required.)

Per Technical Specification 6.14, ODCM changes do not require pre-NRC approval, but they do require submittal with the next annual Radiological Effluents Report to the NRC, proper justification and appropriate cross-disciplinary, RTR/SQR and PORC review. Attachments: Attach all 50.59 Review forms completed, as appropriate. Forms Attached: (Check all that apply.) [8J Applicability Review D D 50.59 Screening 50.59 Evaluation 50.59 Screening No. 50.59 Evaluation No. Rev. Rev. 50.59 APPLICABILITY REVIEW FORM LS-AA-104-1002 Revision 6 Page 1 of2 Activity/Document Number: CY-TM-170-300 Revision Number: s Title: TMI Offsite Dose Calculation Manual (ODCM) Address the questions below for all aspects of the Activity. If the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity. Note that it is not unusual to have more than one process apply to a given Activity. See Section 4 of the Resource Manual (RM) for additional guidance. I. Does the proposed Activity involve a change: I. Technical Specifications or Facility Operating License (IOCFR50.90)? [g]NO DYES See Section 4.2.1.1 of the RM 2. Conditions of License Quality Assurance program (IOCFRS0.54(a))? (g] NO DYES See Section 4.2.1.2 of the RM Security Plan (10CFR50.54(p))? (g]NO DYES Emergency Plan (IOCFR50.54(q))? (g]NO DYES 3. Codes and Standards IST Program Plan (10CFR50.55a(f))? (g]NO DYES See Section 4.2.1.3 of the RM ISi Program Plan (IOCFRS0.55a(g))? (g]NO DYES 4. ECCS Acceptance Criteria (I OCFR50.46)? (g] NO DYES See Section 4.2.1.4 of the RM 5. Specific Exemptions (IOCFR50.12)? (g] NO DYES See Section 4.2.1.S of the RM 6. Radiation Protection Program ( I OCFR20)? [g] NO DYES See Section 4.2.1.6 of the RM 7. Fire Protection Program (applicable UFSAR or operating license (g]NO DYES See Section 4.2.1.7 of the RM condition)?

8. Programs controlled by the Operating License or the Technical ONO (g] YES See Section 4.2.1.7 of the R.J.\1 Specifications (such as the ODCM). 9. Environmental Protection Program (g] NO DYES See Section 4.2.1. 7 of the RM I 0 Diverse and Fkxihk Coping Stratel!ies (FLEX! and Spent Fud P,101 (g] l'\O DYES See Section ct.2.1.7 01* 1he RM Instrumentation Program.

-WU. Other programs controlled by other regulations. (g] NO DYES See Section 4.2.1 of the RM II. Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting (g] NO DYES See Section 4.2.2 of the RM maintenance that will be in effect during at-power operations for 90 days or less? III. Does the proposed Activity involve a change to the: I. UFSAR (including documents incorporated by reference) that is limited to reformatting, simplification, removing excessive detail, or minor [g] NO DYES See Section 4.2.3 of the RM editorial changes as discussed in NEI 96-07 or NEI 98-03? 2. Managerial or administrative proc~dures governing the conduct of (g] NO DYES See Section 4.2.4 of the R.J.\1 facility operations (subject to the control of 10CFR50, Appendix B) 3. Procedures for performing maintenance activities (subject to 10CFR50, [g] NO DYES See Section 4.2.4 of the RM Appendix B )? 4. Regulatory commitment as defined by NEI 99-04 that is outside the scope of 10 CFR 50.59, i.e., the commitment does not involve the facility or a procedure as described in the UFSAR pursuant to 10 CFR (g] NO DYES See Section 4.2.3/4.2.4 of the R.J.\1 50.59, the commitment change does not meet the criteria for a change pursuant to 10 CFR 50.59, and the commitment is not otherwise mandated by the NRC to require a 50.59 review? IV. Does the proposed Activity involve a change to the Independent Spent Fuel (g] NO DYES See Section 4.2.6 of the R.J.\1 Storage Installation (ISFSI) (subject to control by 10 CFR 72.48) tern (old) Rev. (new) Rev. No. 4 page No. 5 page No. 1 23 23 2 28 28 3 29 29 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 ATTACHMENT 1 ODCM Change Summary Matrix a~e 0 P 1 f 1 CY-AA-170-3100 Revision 6 Page 1 *of 1 Determination Description of Change Identifier A Remove reference to obsolete Amergen letter #5928-06-20449 A Remove 'for up to 14 days' from Action 32, paragraph

1. A Remove plant shutdown statements and refer to PSLR guidance ATTACHMENT 2 ODCM Change Determination Station:

____________ T~h~r~ee~M=il~e~ls~l=an~d~-- CY-AA-170-3100 Revision 6 Page 1 of 3 Page _1,____ of --=3'--ODCM Revision No. 5 Determination No. A ----=-.,___ ____ _ I. Determination Questions (Check correct response)

1. Does the ODCM change maintain the level of radioactive effluent control required by 1 OCFR20.1301?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 1 O CFR 20.1301 (a)(1) requires that each licensee conduct operations so that the total effective dose equivalent to individual members of the public from TMI operation does not exceed 100 mrem in one year. Removing plant shutdown statements and following EPRI Primary to Secondary Leakrate (PSLR) guidelines will not increase the dose to the public or reduce TM l's ability to control or quantify releases.

2. Does the ODCM change maintain the level of radioactive effluent control required by 1 OCFR20.1302?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 10 CFR 20.1302 requires licensees to perform appropriate surveys in unrestricted areas and controlled areas to demonstrate compliance with dose limits for individual members of the public. The ability to perform surveys is not impacted by removing plant shutdown statements and following EPRI PSLR guidelines. Effluent concentration limits will not be impacted by these changes. TMI will still control its effluent paths to ensure dose to the public is ALARA. 3. Does the ODCM change maintain the level of radioactive effluent control required by 40CFR190 and 10CFR72.104? Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 1OCFR72.104 has requirements for Independent Spent Fuel Storage Installations (ISFSI) and Monitored Retrievable Storage (MRS) which is not applicable at TMI. 40CFR190 requires tharthe annual dose equivalent does not exceed 25 mrem to the whole body, 75 mrem to the thyroid and 25 mrem to any other organ of any member of the public as a result of exposure to planned discharges of radioactive materials to the environment from uranium fuel cycle operations. Removing plant shutdown statements and following EPRI PSLR guidelines will not increase discharges of radioactive materials nor will they negatively impact TMl's ability to control or quantify radioactive releases to the environment. __x_ YES NO __x_ YES NO _x_ YES NO ATTACHMENT 2 ODCM Change Determination

4. Does the ODCM change maintain the level of radioactive effluent control required by 1 OCFR50.36a?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 1 OCFR 50.36a requires that operating procedures be developed and followed for the control of effluents and that the radioactive waste system be maintained and used. It also specifies that each licensee shall submit a report annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous 12 months. These requirements will keep average annual releases of radioactive material in effluents and their resultant committed effective dose equivalents (CEDE) at small percentages of the dose limits. Operation of the rad waste system is not affected by these changes. The operation of the plant releasing and monitoring the effluents from the plant will not be impacted by removing plant shutdown statements or following EPRI PSLR guidelines. The revision will not impact the annual reporting of radiological effluents to the NRC. 5. Does the ODCM change maintain the level of radioactive effluent control required by Appendix I to 1 OCFR50? Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 1 OCFR50 Appendix I,, Section II.A establishes the design objectives and limiting conditions for operation to meet ALARA criteria such that the calculated annual total quantity of all radioactive material above background released to unrestricted areas will not result in an estimated annual dose or dose commitment from liquid effluents in excess of 3 mrems to the total body or 10 mrems to any organ. For gaseous effluents the estimated annual air dose can not exceed 1 O mrems for gamma radiation and 20 mrems for beta radiation. Section Ill establishes that implementation of Section II be demonstrated by calculational procedures based upon models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated and that the cumulative effect of all sources and pathways being influenced by the plant be considered. Section IV provides guides on limiting conditions for operation. The licensee shall establish appropriate surveillance and monitoring programs for reporting of rad effluents data, environmental monitoring data and resulting radiation doses and changes in the use of unrestricted areas surrounding the plant. If releases of effluents result in exceeding one-half the annual exposure, there are investigative and reporting requirements. Removing plant shutdown statements and following EPRI PSLR guidelines will not adversely impact ODCM calculations or methodologies for evaluating doses to individuals from principal pathways of exposure. CY-AA-170-3100 Revision 6 Page 2 of 3 ...x_ YES NO ...x_ YES NO ATTACHMENT 2 ODCM Change Determination

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

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) Removing plant shutdown statements and following EPRI PSLR guidelines will not impact the accuracy or reliability of effluent, dose, or setpoint calculations. There are no setpoint calculation changes for effluent monitors associated with this ODCM revision. CY-AA-170-3100 Revision 6 Page 3 of 3 ..JL YES NO 7. Does the ODCM change maintain the accuracy of radioactive effluent control ..lL YES NO required by the SAR? Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) Chapter 11 of the UFSAR, specifically sections 11.2.4 and 11.4.3, were reviewed to determine that these ODCM changes will not impact the accuracy of radioactive effluent control required by the SAR. As stated before removing plant shutdown statements and following EPRI PSLR guidelines does not change the release paths of effluents to the environment or any ability to control or calculate doses via these pathways. II. If all questions are answered YES, then complete the ODCM Change Determination and implement the Change per this procedure. Ill. If any question is answered NO, then a change to the ODCM is not permitted IV. Review and Approval: Date Exelon Generation CY-TM-170-300 Revision 5 Page 1 of 222 Level 3 -Information Use OFFSITE DOSE CALCULATION MANUAL (ODCM) INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the Three Mile Island Nuclear Station (TMI) Unit 1 and Unit 2 PDMS Technical Specifications and implements TMI radiological effluent controls. The ODCM contains the controls, bases, and surveillance requirements for liquid and gaseous radiological effluents. In addition, the ODCM describes the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents. This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm/trip set points. Liquid and Gaseous Radwaste Treatment System configurations are also included. The ODCM also is used to define the requirements for the TMI radiological environmental monitoring program (REMP) and contains a list and graphical description of the specific sample locations used in the REMP. The ODCM is maintained at the Three Mile Island (TMI) site for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM to ensure the ODCM represents the present methodology in all applicable areas. Changes to the ODCM will be implemented in accordance with the TMl-1 and TMl-2 PDMS Technical Specifications. The ODCM follows the methodology and models suggested by NUREG-0133, and Regulatory Guide 1.109, Revision 1 for calculation of off-site doses due to plant effluent releases. TMI implements the TMI Radiological Effluent Controls Program and Regulatory Guide 1.21, Revision 1 (Annual Radioactive Effluent Release Report) requirements by use of a computerized system used to determine TMI effluent releases and to update cumulative effluent doses. TABLE OF CONTENTS PARTI TMl-1 RADIOLOGICAL EFFLUENT CONTROLS Section 1.0 DEFINITIONS CY-TM-170-300 Revision 5 Page 2 of 222 13 Table 1-1, Frequency Notation 18 Map1 .1, Gaseous Effluent Release Points and Liquid Effluent Outfall Locations 19 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation Table 2.1-1, Radioactive Liquid Effluent Instrumentation 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring 20 20 20 22 23 Instrumentation 24 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.2 Gaseous Effluent Controls 2.2.3 Total Radioactive Effluent Controls 3.0 SURVEILLANCES 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation Table 3.1-1, Radioactive Liquid Effluent Monitoring Instrumentation 30 30 34 41 44 44 44 Surveillance Requirements 45 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 47 Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 48 PARTI Section TABLE OF CONTENTS (Cont'd) TMl-1 RADIOLOGICAL EFFLUENT CONTROLS 3.2 Radiological Effluents 3.2.1 Liquid Effluents CY* TM-170-300 Revision 5 Page 3 of 222 Page 53 53 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 55 3.2.2 Gaseous Effluents 58 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 60 3.2.3 Total Radioactive Effluents 4.0 PART I REFERENCES 64 65 PART II Section TABLE OF CONTENTS (Cont'd) TMl-2 RADIOLOGICAL EFFLUENT CONTROLS 1.0 DEFINITIONS Table 1.1, Frequency Notation 2.0 CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluentlnstrumentation 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CY-TM-170-300 Revision 5 Page 4 of 222 67 70 71 71 71 71 Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 73 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.2 Gaseous Effluent Controls 2.2.3 Total Radioactive Effluent Controls 3.0 SURVEILLANCES 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring 74 74 78 85 87 87 87 87 Instrumentation Surveillance Requirements 88 3.2 Radioactive Effluents 89 3.2.1 Liquid Effluents 89 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 90 3.2.2 Gaseous Effluents 91 PART II Section TABLE OF CONTENTS (Cont'd) TMl-2 RADIOLOGICAL EFFLUENT CONTROLS CY-TM-170-300 Revision 5 Page 5-of 222 Page Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 92 3.2.3 Total Radioactive Effluents 95 4.0 PART II REFERENCES 96 TABLE OF CONTENTS (Cont'd) CY-TM-170-300 Revision 5 Page 6 of 222 PART Ill EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section 1.0 LIQUID EFFLUENT MONITORS 98 1.1 TMl-1 and TMl-2 Liquid Radiation Monitor Set Points 98 1.2 TMI Liquid Effluent Release Points and Liquid Radiation Monitor Data 99 1.3 Control of Liquid Releases 101 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liquid Effluents -10 CFR 50 Appendix I 2.2 TMI Liquid Radwaste System Dose Cales Once Per Month 3.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEM 106 106 107 126 3.1 TMl-1 Liquid Effluent Waste Treatment System 126 3.2 Operability of the TMl-1 Liquid Effluent Waste Treatment System 127 3.3 TMl-2 Liquid Effluent Waste Treatment System 127 4.0 GASEOUS EFFLUENT MONITORS 130 4.1 TMl-1 Noble Gas Monitor Set Points 130 4.2 TMl-1 Particulate and Radioiodine Monitor Set Points 132 4.3 TMl-2 Gaseous Radiation Monitor Set Points 133 4.4 TMl-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor D~ 1~ 4.5 TMl-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 136 4.6 Control of Gaseous Effluent Releases 137 TABLE OF CONTENTS (Cont'd) CY-TM-170-300 Revision 5 Page 7 of 222 PART 111 Section EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT

• 5.1 Gaseous Effluents

-Instantaneous Release Limits 5.1.1 Noble Gases 5.1.1.1 Total Body 5.1.1.2 Skin 5.1.2 Iodines, Tritium and Particulates 5.2 Gaseous Effluents -10 CFR 50 Appendix I 5.2.1 Noble Gases 5.2.2 Iodines, Tritium and Particulates 149 149 149 149 150 151 152 152 153 5.3 Gaseous Radioactive System Dose Calculations Once per Month 156 6.0 TMl-1 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 178 6.1 Description of the TMl-1 Gaseous Radwaste Treatment System 178 6.2 Operability of the TMl-1 Gaseous Radwaste Treatment System 178 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitoring Program Requirements 8.2 Land Use Census 8.3 lnterlaboratory Comparison Program 9.0 PART Ill REFERENCES 180 181 181 184 186 204 TABLE OF CONTENTS (Cont'd) CY-TM-170-300 Revision 5 Page 8 of 222 PART Ill EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section TABLES Table 1.1 TMI Liquid Release Point and Liquid Radiation Monitor Data 102 Table 1.2 TMl-2 Sump Capacities 103 Table 2.1 Liquid Dose Conversion Factors (DCF): DFii 109 Table 2.2 Bioaccumulation

Factors, BFi 125 Table 4.1 TM 1-1 Gaseous Release Point and Gaseous Radiation Monitor Data 138 Table 4.2 TMl-2 Gaseous Release Point and Gaseous Radiation Monitor Data 139 Table 4.3 Dose Factors for Noble Gases and Daughters 140 Table 4.4 Atmospheric Dispersion Factors for Three Mile Island -Station Vent 141 Table 4.5 Atmospheric Dispersion Factors for Three Mile Island -Ground Release 142 Table 4.6 Dose Parameters for Radioiodines and Radioactive Particulate In Gaseous Effluents 143 Table 5.2.1 Pathway Dose Factors, Ri -Infant, Inhalation 157 Table 5.2.2 Pathway Dose Factors, Ri -Child, Inhalation Table 5.2.3 Pathway Dose Factors, Ri -Teen, Inhalation Table 5.2.4 Pathway Dose Factors, Ri -Adult, Inhalation Table 5.3.1 Pathway Dose Factors, Ri -All Age Groups, Ground Plane Table 5.4.1 Pathway Dose Factors, Ri -Infant, Grass:..Cow-Milk Table 5.4.2 Pathway Dose Factors, Ri -Child, Grass-Cow-Milk Table 5.4.3 Pathway Dose Factors, Ri -Teen, Grass-Cow-Milk Table 5.4.4 Pathway Dose Factors, Ri -Adult, Grass-Cow-Milk Table 5.5.1 Pathway Dose Factors, Ri -Infant, Grass-Goat-Milk 158 159 160 161 162 163 164 165 166 TABLE OF CONTENTS (Cont'd)

CY-TM-170-300 Revision 5 Page 9 of 222 PART Ill EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section TABLES Table 5.5.2 Pathway Dose Factors, Ri -Child, Grass-Goat-Milk Table 5.5.3 Pathway Dose Factors, Ri -Teen, Grass-Goat-Milk Table 5.5.4 Pathway Dose Factors, Ri -Adult, Grass-Goat-Milk Table 5.6.1 Pathway Dose Factors, Ri -Infant, Grass-Cow-Meat Table 5.6.2 Pathway Dose Factors, Ri -Child, Grass-Cow-Meat Table 5.6.3 Pathway Dose Factors, Ri -Teen, Grass-Cow-Meat Table 5.6.4 Pathway Dose Factors, Ri -Adult, Grass-Cow-Meat Table 5.7.1 Pathway Dose Factors, Ri -Infant, Vegetation Table 5.7.2 Pathway Dose Factors, Ri -Child, Vegetation Table 5.7.3 Pathway Dose Factors, Ri -Teen, Vegetation Table 5.7.4 Pathway Dose Factors, Ri -Adult, Vegetation 167 168 169 170 171 172 173 174 175 176 177 Table 8.1 Sample Collection and Analysis Requirements 187 Table 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 193 Table 8.3 Detection Capabilities for Environmental Sample Analysis 194 Table 8.4 TMINS REMP Station Locations -Air Particulate and Air Iodine 197 Table 8.5 TMINS REMP Station Locations -Direct Radiation 197 Table 8.6 TMINS REMP Station Locations -Surface Water 199 Table 8.7 TMINS REMP Station Locations -Aquatic Sediment 199 Table 8.8 TMINS REMP Station Locations -Milk 200 Table 8.9 TMINS REMP Station Locations -Fish 200 Table 8.10 TMINS REMP Station Locations -Food Products 200 PART Ill Section MAPS MAP 8.1 MAP 8.2 MAP 8.3 FIGURES Figure 1.1 Figure 1.2 Figure 3.1 Figure 3.2 Figure 4.1 Figure 4.2 Figure 4.3 Figure 4.4 Figure 4.5 Figure 6.1 CY-TM-170-300 Revision 5 Page 10 of 222 TABLE OF CONTENTS (Cont'd) EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 1 Mile of the Site Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 5 miles of the Site Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Greater than 5 miles from the Site TMl-1 Liquid Effluent Pathways TMl-2 Liquid Effluent Pathways TMl-1 Liquid Radwaste TMl-1 Liquid Waste Evaporators TMl-1 Gaseous Effluent Pathways TMl-1 Auxiliary and Fuel Handling Buildings Effluent Pathways TMl-1 Reactor Building Effluent Pathway TMl-1 Condenser Offgas Effluent Pathway TMl-2 Gaseous Effluent Filtration System/Pathways Waste Gas System 201 202 203 104 105 128 129 144 145 146 147 148 179 PART IV Section TABLE OF CONTENTS (Cont'd) REPORTING REQUIREMENTS CY-TM-170-300 Revision 5 Page 11 of 222 1.0. TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 207 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 3.0 PART IV REFERENCES APPENDICES A. Pathway Dose Rate Parameter (Pi) B. Inhalation Pathway Dose Factor (Ri) C. Ground Plane Pathway Dose Factor (Ri) D. Grass-Cow-Milk Pathway Dose Factor (Ri) E. Cow-Meat Pathway Dose Factor (Ri) F. Vegetation Pathway Dose Factor (Ri) APPENDIX A -F REFERENCES 208 210 211 212 213

• 214 216 218 219 PARTI TMl-1 RADIOLOGICAL EFFLUENT CONTROLS CY-TM-170-300 Revision 5 Page 12 of 222 CY-TM-170-300 Revision 5 Page 13 of 222 1.0 DEFINITIONS L__ _______ _ The following terms are defined for uniform interpretation of these controls and surveillances.

1.1 Reactor Operating Conditions 1.1.1 Cold Shutdown The reactor is in the cold shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is no more than 200°F. Pressure is defined by Technical Specification 3.1.2. 1.1.2 Hot Shutdown The reactor is in the hot shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is at or greater than 525°F. 1.1.3 Reactor Critical The reactor is critical when the neutron chain reaction is self-sustaining and Keff = 1.0. 1.1.4 Hot Standby The reactor is in the hot standby condition when all of the following conditions exist: a. Tavg is greater than 525°F b. The reactor is critical

c. Indicated neutron power on the power range channels is less than two percent of rated power. Rated power is defined in Technical Specification Definition 1.1. 1.1.5 Power Operation The reactor is in a power operating condition when the indicated neutron power is above two percent of rated power as indicated on the power range channels.

Rated power is defined in Technical Specification Definition 1.1. 1.1.6 Refueling Shutdown CY-TM-170-300 Revision 5 Page 14 of 222 The reactor is in the refueling shutdown condition when, even with all rods removed, the reactor would be subcritical by at least one percent delta k/k and the coolant temperature at the decay heat removal pump suction is no more than 140°F. Pressure is defined by Technical Specification 3.1.2. A refueling shutdown refers to a shutdown to replace or rearrange all or a portion of the fuel assemblies and/or control rods. 1.1. 7

• Refueling Operation An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.

1.1.8 Refueling Interval The time between normal refuelings of the reactor. This is defined as once per 24 months. 1.1.9 Startup The reactor shall be considered in the startup mode when the shutdown margin is reduced with the intent of going critical. 1.1.10 Tave Tave is defined as the arithmetic average of the coolant temperatures in the hot and cold legs of the loop with the greater number of reactor coolant pumps operating; if such a distinction of loops can be made. 1 .1.11 Heatup -Cooldown Mode The heatup-cooldown mode is the range of reactor coolant temperature greater than 200°F and less than 525°F. 1 .2 Operable A system, subsystem, train, component or device, shall be OPERABLE or have OPERABILITY when it is capable of performing it's specified function(s), and when all necessary attendant instrumentation,

controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s),

are also capable of performing their related support function(s). CY-TM-170-300 Revision 5 Page 15 of 222 1.3 Instrument Channel An instrument channel is the combination of sensor, wires, amplifiers, and output devices, which are connected for the purpose of measuring the value of a process variable, for the purpose of observation,

control, and/or protection.

An instrument channel may be either analog or digital. 1.4 Instrumentation Surveillance 1.4.1 Channel Test A CHANNEL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practical to verify OPERABILITY, including alarm and/or trip functions. 1.4.2 Channel Check A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter. 1.4.3 Source Check A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. 1.4.4 Channel Calibration 1.5 Deleted An instrument CHANNEL CALIBRATION is a test, and adjustment (if necessary), to establish that the channel output responds with acceptable range and accuracy to known values of the parameter, which the channel measures, or an accurate simulation of these values. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test. 1.6 Offsite Dose Calculation Manual (ODCM) CY-TM-170-300 Revision 5 Page 16 of 222 The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, 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 (1) the Radiological Effluent

Controls, (2) the Radiological Environmental Monitoring Program and (3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

1. 7 Gaseous Radwaste Treatment The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluent by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

1.8 Ventilation Exhaust Treatment System A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluent by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodine or particulates from the gaseous exhaust system prior to the release to the environment. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEMS. 1.9 Purge -Purging PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature,

pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is required to purify the confinement.

1.10 Venting VENTING is the controlled process of discharging air as gas from a confinement to maintain temperature,

pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is not provided.

Vent used in system name does not imply a VENTING process. 1.11 Member(s) of the Public MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose. 1.12 Site Boundary CY-TM-170-300 Revision 5 Page 17 of 222 The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMl-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile Island and between Three Mile Island and Shelley Island. The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM. 1.13 Frequency Notation The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1-1. All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. The 25% extension applies to all frequency intervals with the exception of "F." No extension is allowed for intervals designated "F." 1.14 Occupational Dose OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under 1 OCFR35.75, from voluntary participation in medical research

programs, or as a member of the public.

Bases Notation s D w M Q S/A R P S/U p N/A (NA) E F Table 1-1 Frequency Notation Frequency CY-TM-170-300 Revision 5 Page 18 of 222 Shiftly (once per 12 hours) Daily (once per 24 hours) Weekly (once per 7 days) Monthly (once per 31 days) Quarterly ( once per 92 days) Semi-Annually (once per 184 days) Refueling Interval (once per 24 months) Prior to each reactor startup, if not done during the previous 7 days Completed prior to each release Not applicable Once per 18 months Not to exceed 24 months Section 1.13 establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are specified to be performed at least once each REFUELING INTERVAL. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed once each REFUELING INTERVAL.

Likewise, it is not the intent that REFUELING INTERVAL surveillances be performed during power operation unless it is consistent with safe plant operation.

The limitation of Section 1.13 is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval. --Map 1.1 Gaseous Effluent Release Points and Liquid Effluent Outfall Locations II c ... c. ** _, --_....__........ t UNIT NO. I S T4C:fli UNIT NO., FUEL HANDLING BLOG £SF VENT STACK D5N003 CY-TM-170-300 Revision 5 Page 19 of 222 ~(tbO. ---;--:~ . -.......... ... ,.. .... _ ... **-.. *-.... -......... ._. ... .. ..., .. i 1 CY* TM-170-300 Revision 5 Page 20 of 222 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation CONTROL: The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.1-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: At all times

• ACTION: a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluent monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels

OPERABLE, take the ACTION shown in Table 2.1-1. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner. * *

• For WDL-FT-84, and RM-L-6, operability is not required when discharges are positively controlled through the closure of WDL-V-257.

For RM-L-12 and associated IWTS/IWFS flow interlocks, operability is not required when discharges are positively controlled through the closure of IW-V-72, 75 and IW-V-280, 281. For SR-FT-146, operability is not required when discharges are positively controlled through the closure of WDL-V-257, IW-V-72, 75 and IW-V-280, 281. BASES CY-TM-170-300 Revision 5 Page 21 of 222 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten times the effluent concentrations of 10 CFR Part 20. Instrument Table 2.1-1 Radioactive Liquid Effluent Instrumentation Minimum Channels Operable CY-TM-170-300 Revision 5 Page 22 of 222 ACTION 1. Gross Radioactivity Monitors Providing Automatic Termination of Release a. b. Unit 1 Liquid Radwaste Effluent Line (RM-L6) IWTS/IWFS Discharge Line (RM-L 12) 1 1 18 20 2. Flow Rate Measurement Devices a. b. Unit 1 Liquid Radwaste Effluent Line (WDL-FT-84) Station Effluent Discharge (SR-FT-146) Table Notation 1 21 21 ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue, provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Surveillances 3.2.1.1.1 and 3.2.1.1.2 and; 2. At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup. 3. The TMI Plant Manager shall approve each release.

Otherwise, suspend release of radioactive effluents via this pathway. ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may commence or continue provided that grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 1x10-7 microcuries/ml, prior to initiating a release and at least once per 12 hours during release. ACTION 21 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, radioactive effluent releases via this pathway may continue, provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow. CY-TM-170-300 Revision 5 Page 23 of 222 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL: The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: As shown in Table 2.1-2 ACTION: a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels

OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in* a timely manner. BASES The radioactive gaseous effluent instrumentation is provided to m*onitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases.

The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC a*pproved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301. The low range condenser offgas noble gas activity monitors also provide data for determination of steam generator primary to secondary leakage rate.

• Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation INSTRUMENT

1. Waste Gas Holdup System a. Noble Gas Activity Monitor (RM-A-7) B. Effluent System Flow Rate Measuring Device (WDG-FT-123)

2. Waste Gas Holdup System Explosive Gas Monitoring System a. Hydrogen Monitor (CA-G-1A/B)

b. Oxygen Monitor (CA-G-1A/B)

3. Containment Purge Monitoring System a. Noble Gas Activity Monitor (RM-A-9)

b. Iodine Sampler (RM-A-9)

c. Particulate Sampler (RM-A-9)

d. Effluent System Flow Rate Measuring Device (AH-FR-148A, AH-FR-148B)

e. Sampler Flow Rate Monitor (RM-Fl-1231)

4. Condenser Vent System a. Low Range Noble Gas Activity Monitor (RM-A-5Lo or RM-A-15)

MINIMUM CHANNEL OPERABLE 1 1 2 2 1 1 1 1 1 1 APPLICABILITY

• • • *** ** ** # # # # # CY-TM-170-300 Revision 5 Page 24 of 222 ACTION 25 26 30 30 27 31 31 26 26 32 Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation INSTRUMENT

5. Auxiliary and Fuel Handling Building Ventilation System a. Noble Gas Activity Monitor (RM-A-8) or (RM-A-4 and RM-A-6) b. Iodine Sampler (RM-A-8 or (RM-A-4 and RM-A-6) c. Particulate Sampler (RM-A-8 or (RM-A-4 and RM-A-6) d. Effluent System Flow Rate Measuring Devices (AH-FR-149 and AH-FR-150)

e. Sampler Flow Rate Monitor (RM-Fl-1230 or RM-A-4\FI and RM-A-6\FI)

6. Fuel Handling Building ESF Air Treatment System a. Noble Gas Activity Monitor (RM-A-14 or suitable equivalent)

b. Iodine Cartridge

c. Particulate Filter d. Effluent System Flow (AH-UR-1104A/B)

e. Sampler Flow Rate Monitor (RM-A-14Fl14)

MINIMUM CHANNEL OPERABLE 1 1 1 1 1 1 N/A<2l N/A(2l 1 1 APPLICABILITY

• * * * * **** **** **** **** **** CY-TM-170-300 Revision 5 Page 25 of 222 ACTION 27 31 31 26 26 27,33 31,33 31,33 26,33 26,33 NOTE 2: No instrumentation channel is provided.

However, for-determining operability, the equipment named must be installed and functional or the ACTION applies.

Table 2.1-2 (Cont'd) Radioactive Gaseous Process and Effluent Monitoring Instrumentation INSTRUMENT

7. Chemical Cleaning Building Ventilation System a. Noble Gas Activity Monitor (ALC RM-1-18)

b. Iodine Sampler (ALC RM-1-18)

c. Particulate Sampler (ALC RM-1-18)

8. Waste Handling and Packaging Facility Ventilation System a. Particulate Sampler (WHP-RIT-1)

9. Respirator and Laundry Maintenance Facility Ventilation System a. Particulate Sampler (RLM-RM-1)

MINIMUM CHANNEL OPERABLE 1(3) 1(3) 1 1 APPLICABILITY

1. l#f. #l#f. #l#f. #l#f. #l#f. CY-TM-170-300 Revision 5 Page 26 of 222 ACTION 27 31 31 31 31 NOTE 3: Channel only required when liquid radwaste is moved or processed within the facility (e.g., includes recirculation,

cleanup, transfers out of, within, or into Chemical Cleaning

Building, etc.).

• ** *** **** # ## ### At all times Table 2.1-2 (Cont'd)

Table Notation During waste gas holdup system operation CY-TM-170-300 Revision 5 Page 27 of 222 Operability is not required when discharges are positively controlled through the closure of WDG-V-47 or where RM-A-8, AH-FT-149 and AH-FT-150 are operable and RM-A-8 is capable of automatic closure of WDG-V-47 During Fuel Handling Building ESF Air Treatment System Operation At all times during containment purging At all times when condenser vacuum is established During operation of the ventilation system ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed in accordance with Table 3.2-2, Item A, and 2. At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup. 3. The TMI Plant Manager shall approve each release.

Otherwise, suspend release of radioactive effluent via this pathway. ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and the initial samples are analyzed for gross activity (gamma scan) within 24 hours after the channel has been declared inoperable. If RM-A-9 is declared inoperable, see also Technical Specification 3.5.1, Table 3-5.1, Item C.3.f. ACTION 30 1. Table 2.1-2 Notations (Cont'd) CY-TM-170-300 Revision 5 Page 28 of 222 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, a grab sample shall be collected and analyzed for the inoperable gas channel(s) at least once per 24 hours. With both channels inoperable, a grab sample shall be collected and analyzed for the inoperable gas channel(s): (a) at least once per 4 hours during degassing operations. (b) at least once per 24 hours during other operations (e.g. Feed and Bleed). 2. If the inoperable gas channel(s) is not restored to service within 14 days, a special report shall be submitted to the Regional Administrator of the NRG Region I Office and a copy to the Director, Office of Inspection and Enforcement within 30 days of declaring the channel(s) inoperable. The report shall describe (a) the cause of the monitor inoperability, (b) action being taken to restore the instrument to service, and (c) action to be taken to prevent recurrence. ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within four hours after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment. ACTION 32 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that grab samples are taken and analyzed. If the primary-to-secondary leak rate was unstable*, or was indicating an increasing trend at the initial time when there was no operable channel of the Condenser Vent System Low Range Noble Gas Activity

Monitor, analyze grab samples of the reactor coolant system and Condenser OffGas once every 4 hours to provide an indication of primary-to-secondary leakage.

Subsequent sample frequency shall be in accordance with Table 1 based on the last sample result. Otherwise, analyze grab samples of the reactor coolant system and Condenser OffGas to provide an indication of primary-to-secondary leakage at the minimum frequency indicated in Table 1, below: Table 2.1-2 Notations (Cont'd) Table 1 CY-TM-170-300 Revision 5 Page 29 of 222 Minimum Frequency of Grab Samples When No Condenser Vent System Low Range Noble Gas Activity Monitor is Operable Existing Total Primary-to-Secondary Leak Rate Frequency of Grab Samples (based on last monitor reading or sample result) 0 to< 5 GPO Once per 24 hours 5 to< 30 GPO Once per 12 hours 30 to< 75 GPO Once per 4 hours 75 GPO or Qreater Refer to CY-AP-120-340

• Unstable is defined as > 10% increase during a 1 hour period, as stated in the EPRI Guidelines.

Condenser Vent System Low Range Noble Gas Activity Monitor inoperable channels should be restored to operability as rapidly as practical.

• ACTION 33 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel to OPERABLE status within 7 days, or prepare and submit a special report within 30 days outlining the action(s) taken, the cause of the inoperability, and plans and schedule for restoring the system to OPERABLE status.

2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL: CY-TM-170-300 Revision 5 Page 30 of 222 The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 3E-3 uCi/cc total activity. APPLICABILITY: At all times ACTION: With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits. BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures with (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301 to the population. The concentration limit for noble gases is based upon the assumption the Xe-135 is the controlling radioisotope and its MPG in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication

2.

2.2.1.2 Liquid Effluent Dose CONTROL CY-TM-170-300 Revision 5 Page 31 of 222 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ. b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ. APPLICABILITY:

At all times ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report, which identifies the cause(s) for exceeding the limit(s), and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act. BASES CY-TM-170-300 Revision 5 Page 32 of 222 This control and associated action is provided to implement the requirements of Sections II.A, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 10 CFR 20. The dose calculations in the ODCM implement the requirements in Section Ill.A. of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113. CY-TM-170-300 Revision 5 Page 33 of 222 2.2.1.3 Liquid Radwaste Treatment System CONTROL: The appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month. APPLICABILITY: At all times ACTION: a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRG Region I Administrator within 30 days, a Special Report which includes the following information: BASES 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and, 3. A summary description of action(s) taken to prevent a recurrence The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable.

This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.D of Appendix I to 10 CFR Part 50. The intent of Section 11.D. is to reduce effluents to as low as is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section II.A of Appendix I, 10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction. 2.2.1.4 Liquid Holdup Tanks CONTROL CY-TM-170-300 Revision 5 Page 34 of 222 The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases. a. Outside temporary tank APPLICABILITY: At all times. ACTION: a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. BASES Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20.1001-20-20.2401, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area. 2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL: The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and b. For 1-131, 1-133, tritium and all radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem/yr to any organ. APPLICABILITY:

At all times ACTION: CY-TM-170-300 Revision 5 Page 35 of 222 With the release rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limit(s). BASES J The control implements the requirement in Technical Specification (6.8.4.b (7). This specification is provided to ensure that the dose from radioactive materials in gaseous effluents at and beyond the SITE BOUNDARY will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with 10 times the concentrations of 10 CFR Part 20, Appendix B, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR Part 20.1302. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body, or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year (NU REG 1301 ). 2.2.2.2 Gaseous Effluents Dose-Noble Gases CONTROL: The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter:

less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, CY-TM-170-300 Revision 5 Page 36 of 222 b. During any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation. APPLICABILITY: At all times ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. BASES This control applies to the release of radioactive materials in gaseous effluents from TMl-1. This control and associated action is provided to implement the requirements of Section 11.B, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section 11.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably ac~ievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in CY .. TM-170-300 Revision 5 Page 37 of 222 Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. 2.2.2.3 Dose -lodine-131, lodine-133,

Tritium,

• and Radionuclides in Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-133,

Tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter:

less than or equal to 7.5 mrem to any organ, and b. During any calendar year: less than or equal to 15 mrem to any organ. APPLICABILITY: At all times ACTION: With the calculated dose from the release of lodine-131, lodine-133,

Tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. BASES This control applies to the release of radioactive materials in gaseous effluents from TMl-1. This control and associated action is provided to implement the requirements of Section 11.C, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in CY-TM-170-300 Revision 5 Page 38 of 222 Section 11.C of Appendix I. The ACTION statement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors" Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, iodine-133, tritium and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. 2.2.2.4 Gaseous Radwaste Treatment System CONTROL The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE.

The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in the gaseous waste prior to their discharge when the monthly projected gaseous effluent air doses due to untreated gaseous effluent releases from the unit CY-TM-170-300 Revision 5 Page 39 of 222 would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ. APPLICABILITY: At all times ACTION: a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRG Region I Administrator within 30 days, a Special Report which includes the following information: BASES 1. Identification

• of the inoperable equipment or subsystems and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3. A summary description of action(s) taken to prevent a recurrence The use of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment.

The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections 11.B and 11.C of Appendix I, 10 CFR Part 50, for gaseous effluents. 2.2.2.5 Explosive Gas Mixture CONTROL CY-TM-170-300 Revision 5 Page 40 of 222 The concentration of oxygen in the Waste Gas Holdup System shall be limited to less than or equal to 2% by volume whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume. AVAILABILITY: At all times ACTION: Whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume, and: a. The concentration of oxygen in the Waste Gas Holdup System is greater than 2% by volume, but less than 4% by volume, without delay, begin to reduce the oxygen concentration to within its limit. b. The concentration of oxygen in the Waste Gas Holdup System is greater than or equal to 4% by volume, immediately suspend additions of waste gas to the Waste Gas Holdup System and without delay, begin to reduce the oxygen concentration to within its limit. BASES: Based on experimental data (Reference 1 ), lower limits of flammability for hydrogen is 5% and for oxygen is 5% by volume. Therefore, if the concentration of either gas is kept below it lower limit, the other gas may be present in higher amounts without the danger of an explosive mixture. Maintaining the concentrations of hydrogen and oxygen such that an explosive mixture does not occur in the waste gas holdup system provides assurance that the release of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR 50. REFERENCES (1) Bulletin 503, Bureau of Mines; Limits of Flammability of Gases and Vapors 2.2.2.6 Waste Gas Decay Tanks CONTROL: CY-TM-170-300 Revision 5 Page 41 of 222 The quantity of radioactivity contained in each waste gas decay tank shall be limited to less than or equal to 8800 curies noble gases (considered as Xe-133). APPLICABILITY: At all times ACTION: a. With the quantity of radioactive material in any waste gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. BASES Restricting the quantity of radioactivity contained in each waste gas decay tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure." 2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL: The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. APPLICABILITY: At all times ACTION: With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a, 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b, 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including CY-TM-170-300 Revision 5 Page 42 of 222 direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b ), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material

involved, and the cause of the exposure levels or concentrations.

If the estimated dose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. BASES This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301 (d). This control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be CY-TM-170-300 Revision 5 Page 43 of 222 considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected) in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRG staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 3.0 SURVEILLANCES 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation Surveillance Requirements CY-TM-170-300 Revision 5 Page 44 of 222 3.1.1.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, AND CHANNEL TEST operations during the MODES and at the frequencies shown in Table 3.1-1. Table 3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements INSTRUMENT

1. Radioactivity Monitors Providing Alarm and Automatic Isolation

a. b. Unit 1 Liquid Radwaste Effluents Line (RM-L-6)

IWTS/IWFS Discharge Line (RM-L-12)

2. Flow Rate Monitors

a. b. Unit 1 Liquid Radwaste Effluent Line (WOL-FT-84)

Station Effluent Discharge (SR-FT-146) CHANNEL CHECK 0 0 0(3) 0(3) SOURCE CHECK p p NIA NIA CHANNEL CALIBRATION R(2) R(2) R R CY-TM-170-300 Revision 5 Page 45 of 222 CHANNEL TEST Q(1) Q(1) Q Q Table 3.1-1 (Cont'd) Table Notation CY-TM-170-300 Revision 5 Page 46 of 222 (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the following condition exists: 1. Instrument indicates measured levels above the high alarm/trip setpoint. (Includes -circuit failure)

2. Instrument indicates a down scale failure.

(Alarm function only.) (Includes -circuit failure)

3. Instrument controls moved from the operate mode (Alarm function only). (2) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participated in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may

• substitute previously established calibration procedures for this requirement)

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous,

periodic, or batch releases are made.

. CY-TM-170-300 Revision 5 Page 4 7 of 222 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.

1. 2. 3. 4. Table 3.1-2 CY-TM-170-300 Revision 5 Page 48 of 222 Radioactiv.e Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY Waste Gas Holdup System a. Noble Gas Activity Monitor (RM-A7) p p E(3) Q(1) *** b. Effluent System Flow Rate Measuring Device (WDG-FT-123) p NIA E Q *** Waste Gas Holdup System Explosive Gas Monitoring System a. Hydrogen Monitor (CA-G-1A/B)

D N/A Q(4) M ** b. Oxygen Monitor (CA-G-1A/B) D N/A Q(S) M ** Containment Purge Vent System a. Noble Gas Activity Monitor (RM-A9) D p E(3) M(1) # b. *Iodine Sampler (RM-A9) w N/A N/A N/A # c. Particulate Sampler (RM-A9) w N/A N/A N/A # d. Effluent System Flow Rate Measuring Device (AH-FR-148) D N/A E Q # e. Sampler Flow Rate Monitor (RM-Fl-1231) b N/A E N/A # Condenser Vent System a. Noble Gas Activity Monitor (RM-AS and Suitable D M E(3) Q(2) ## Equivalent -See Table 2.1-2, Item 4.a) Table 3.1-2 (Cont'd) CY-TM-170-300 Revision 5 Page 49 of 222 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY

5. Auxiliary and Fuel Handling Building Ventilation System a. Noble Gas Activity Monitor (RM-AB) or (RM-A4 and RM-A6) D M E(3) 0(1)

• b. Iodine Sampler (RM-AB) or (RM-A4 and RM-A6) w N/A N/A N/A
• C. Particulate Sampler (RM-AB) or (RM-A4 and RM-A6) w N/A N/A N/A
• d. System Effluent Flow Rate Measurement Devices (AH-FR-149 D N/A E 0
• and AH-FR-150)

D N/A E N/A

• e. Sampler Flow Rate Monitor (RM-Fl-1230 or RM-A-4\FI and RM-A-6\FI)

6. Fuel Handling Building ESF Air Treatment System a. Noble Gas Activity Monitor (RM-A14)

D M R(3) 0(2) **** b. System Effluent Flow Rate (AH-UR-1104 A/B) D N/A R 0 **** C. Sampler Flow Rate Measurement Device (RM-A-14Fl14) D N/A R 0 **** Table 3.1-2 (Cont'd) CY* TM-170-300 Revision 5 Page 50 of 222 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements INSTRUMENT

7. Chemical Cleaning Building Ventilation System a. b. C. Noble Gas Activity Monitor (ALC RM-1-18)

Iodine Sampler (ALC RM-1-18) Particulate Sampler (ALC RM-1-18)

8. Waste Handling and Packaging Facility Ventilation System a. Particulate Sampler (WHP-RIT-1)

9. Respirator and Laundry Maintenance Ventilation System a. Particulate Sampler (RLM-RM-1)

CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION D w w D D M N/A N/A w w E(3) N/A N/A SA SA CHANNEL TEST APPLICABILITY Q(2) N/A N/A w w #II# #II# #II#

• ** *** **** # ## ### Table 3.1-2 (Cont'd)

Table Notation At all times During waste gas holdup system operation CY-TM-170-300 Revision 5 Page 51 of 222 Operability is not required when discharges are positively controlled through the closure ofWDG-V-47, or where RM-A-8, AH-FT-149, and AH-FT-150 are operable and RM-A-8 is capable of automatic closure of WDG-V-47 During Fuel Handling Building ESF Air Treatment System Operation At all times during containment purging At all times when condenser vacuum is established During operation of the ventilation system (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway for the Auxiliary _and Fuel Handling Building Ventilation System, the sµpply ventilation is isolated and control room alarm annunciation occurs if the following condition exists: 1. Instrument indicates measured levels above the high alarm/trip setpoint (Includes circuit failure).

2. Instrument indicates a down scale failure (Alarm function only) (Includes circuit failure).

3. Instrument controls moved from the operate mode (Alarm function only). (2) The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1 Instrument indicates measured levels above the alarm setpoint.

(includes circuit failure)

2. Instrument indicates a down scale failure (includes circuit failure).

3. Instrument controls moved from the operate mode.

Table 3.1-2 NOTATIONS (Cont'd) CY-TM-170-300 Revision 5 Page 52 of 222 (3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement.) (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent hydrogen, balance nitrogen, and 2. Four volume percent hydrogen, balance nitrogen (5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and 2. Four volume percent oxygen, balance nitrogen 3.2 Radiological Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration CY-TM-170-300 Revision 5 Page 53 of 222 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release, by sampling and analysis in accordance with Table 3.2-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.1.2 Post-release analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1. 3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1. 3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative qose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month. 3.2.1.3 Liquid Waste Treatment 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM. 3.2.1.4 Liquid Holdup Tanks CY-TM-170-300 Revision 5 Page 54 of 222 3.2.1.4.1 The quantity of radioactive material contained in each of the tanks specified in Control 2.2.1.4 shall be determined to be within the limit by analyzing a representative sample of the tank's content weekly when radioactive materials are being added to the tank. Table 3.2-1 Radioactive Liquid Waste Sampling and Analysis Program Sampling Minimum Analysis Liguid Release Ty~e Freguency Freguency Ty~e of Activity Analysis A.1 Batch Waste Release Tanks (Noted) p p H-3 Each Batch Each Batch Principal Gamma Emitters (Note f) 1-131 Dissolved and Entrained Gases (Gamma Emitters} (Note g} p M Gross alpha Each Batch Com~osite (Note b} p Q Sr-89, Sr-90 Each Batch Com osite Note b Fe-55 A.2 Continuous Releases (Note e) Continuous w Principal Gamma Emitters (Note f) (Note c) Composite (Note c) 1-131 Grab Sample M Dissolved and Entrained Gases M (Gamma Emitters) (Note g) Continuous M H-3 (Note c} Com~osite (Note c} Gross al~ha Continuous Q Sr-89, Sr-90 (Note c} Com~osite (Note c} Fe-55 CY-TM-170-300 Revision 5 Page 55 of 222 Lower Limit of Detection (LLD} (~Ci/ml} (Note a} 1 X 10*5 5 X 10*7 1 X 10*6 1 X 10*5 1 X 10*7 5 X 10*8 1 X 10*6 5 X 10*7 1 X 10*6 1 X 10*5 1 X 10*5 1 X 10*7 5 X 10*8 1 X 10*6 Table 3.2-1 (Cont'd) Table Notation CY-TM-170-300 Revision 5 Page 56 of 222 a. The LLD is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. Where: For a particular measurement system (which may include radiochemical separation): 4.66Sb E x V x 2.22 x 106 x Y x exp (-JM) LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume) Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per disintegration) Vis the sample size (in units of mass or volume) 2.22 E6 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable) '"A is the radioactive decay constant for the particular radionuclide, and ~t is the elapsed time between midpoint of sample collection and time of counting Typical values of E, V, Y and ~t shall be used in the calculation It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released Table 3.2-1 Notations (Cont'd)

CY-TM-170-300 Revision 5 Page 57 of 222 c. To be representative of the quantities and concentrations of radioactive materials in liquid effluent, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and be thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e. A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume or system that has an input flow during the continuous release.

f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mb-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4. g. The gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, and Xe-135. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Effluent Release Report pursuant to T.S. 6.9.4. 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates CY-TM-170-300 Revision 5 Page 58 of 222 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.a in accordance with the methods and procedures of the ODCM. 3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis

program, specified in Table 3.2-2. 3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.3 Dose, lodine-131, lodine-133,

Tritium, and Radionuclides in Particulate Form 3.2.2.3.1 Cumulative dose contributions from lodine-131, lodine-133,

Tritium, and radionuclides in particulate form with half lives greater than 8 days for the current calendar

_quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly. 3.2.2.4 Gaseous Waste Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM. 3.2.2.5 Explosive Gas Mixture CY-TM-170-300 Revision 5 Page 59 of 222 3.2.2.5.1 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the limits of Control 2.2.2.5 by monitoring the waste gases in the Waste Gas Holdup System with the hydrogen and oxygen monitors covered in Table 2.1-2 of Control 2.1.2. 3.2.2.6 Waste Gas Decay Tank 3.2.2.6.1 The concentration of radioactivity contained in the vent header shall be determined weekly. If the concentration of the vent header exceeds 10. 7 µCi/cc, daily samples shall be taken of each waste gas decay tank being added to, to determine if the tank(s) is less than or equal to 8800 Ci/tank. CY-TM-170-300 Revision 5 Page 60 of 222 Table 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program Minimum Lower Limit of Sampling Analysis Type of Activity Detection (LLD) Gaseous Release Type Frequency Frequency Analysis µCi/ml) (Note a) p p Principal Gamma Each Tank 1 X 1 Q-4 A. Waste Gas Decay Tank Grab Sample Each Tank Emitters (Note g) B. Containment Purge H-3 1 X 10-6 P (Note b)Each P (Note b) Each Principal Gamma Purge Grab Sample Purge Emitters (Note g) 1 X 1 Q-4 C. Auxiliary and Fuel Handling Building H-3 1 X 10-6 Air Treatment System M (Notes c, e) Grab M Principal Gamma Sample Emitters (Note g) 1 X 104 D. Fuel Handling Building ESF Air Treatment System M (during System M (during H-3 1 X 10-6 Operation) System Principal Gamma Grab Sam le Operation) Emitters Note 1 X 104 E. Condenser Vacuum Pumps Exhaust (Note h) M (Note h) H-3 1 X 1 Q-6 M Principal Gamma Grab Sample (Note h) Emitters (Note g) 1 X 104 F. Chemical Cleaning Building Air Treatment System M (Note I) H-3 1 X 1 Q-6 M Principal Gamma Grab Sample Emitters (Note g) 1 X 1 Q-4 G. Waste Handling and Packaging Facility See Section I See Section I See Section I See Section I Air Treatment System of this table of this table of this table of this table H. Respirator and Laundry Maintenance Facility See Section I See Section I See Section I See Section I Air Treatment System of this table of this table of this table of this table I. J. Table 3.2-2 (Cont'd) Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release T e All Release Types as Listed Above in B, C, D, F, G, Continuous and H (During System Operation) (Note f) (Note i) Continuous (Note f) Continuous (Note f) Continuous (Note f) Continuous (Note f) Condenser Vent Stack Continuous Iodine Continuous Sampler (Note j) (Note k) W (Noted) Charcoal Sample W (Noted) Particulate Q Composite Particulate Sample Q Composite Particulate Sample Noble Gas Beta or Gamma W (Noted} Charcoal Sample Type of Activity Anal sis 1-131 Principal Gamma Emitters (Note g) (1-131, Others) Gross Alpha Sr-89, Sr-90 Noble Gases 1-131 CY-TM-170-300 Revision 5 Page 61 of 222 1 X 10-12 1 X 10-11 1 X 10-11 1 X 10-11 1 X 10-6 1 X 10-12 Table 3.2-2 (Cont'd) Table Notation CY-TM-170-300 Revision 5 Page 62 of 222 a. The LLD is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. Where: For a particular measurement system (which may include radiochemical separation): 4.66Sb LLD=----------- E x V x 2.22 x 106 x Y x exp (-AAt) LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume) Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per disintegration) Vis the sample size (in units of mass or volume) 2.22 E6 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable) "-is the radioactive decay constant for the particular radionuclide, and ~t is the elapsed time between midpoint of sample collection and time of counting. Typical values of E, V, Y and ~t shall be used in the calculation. It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

b. Sampling and analysis shall also be performed following

shutdown, startup, or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour, unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. c. Tritium grab samples from the spent fuel pool area shall be taken at least once per 24 hours when the refueling canal is flooded.

Table 3.2-2 Notations (Cont'd) CY-TM-170-300 Revision 5 Page 63 of 222 d. Charcoal cartridges and particulate filters shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler).

e. Tritium grab samples shall be taken weekly from the spent fuel pool area whenever spent fuel is in the spent fuel pool. f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 2.2.2.1, 2.2.2.2, and 2.2.2.3.

g. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4. h. Applicable only when condenser vacuum is established. Sampling and analysis shall also be performed following

shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. i. Gross Alpha, Sr-89, and Sr-90 analyses do not apply to the Fuel Handling Building ESF Air Treatment System. j. If the Condenser Vent Stack Continuous Iodine Sampler is unavailable, then alternate sampling equipment will be placed in service within 48 hours or a report will be prepared, and submitted within 30 days from the time the sampler is found or made inoperable, which identifies (a) the cause of the inoperability, (b) the action taken to restore representative sampling capability, (c) the action taken to prevent recurrence, and (d) quantification of the release via the pathway during the period and comparison to the limits prescribed by Control 2.2.2.1.b.

k. Applicable only when condenser vacuum is established.

I. Applicable when liquid radwaste is moved or processed within the facility (e.g. includes recirculation,

cleanup, transfers out, within, or into Chemical Cleaning

Building, etc). m. Iodine samples only required in the Chemical Cleaning Building when TMl-1 liquid radwaste is stored or processed in the facility.

3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation CY-TM-170-300 Revision 5 Page 64 of 222 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM. 4.0 PART I REFERENCES 4.1 Title 10, Code of Federal Regulations, "Energy" CY-TM-170-300 Revision 5 Page 65 of 222 4.2 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routing Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "Revision 1, October 1977 4.3 TMl-1 Technical Specifications, attached to Facility Operating License No. DPR-50 4.4 TMl-1 FSAR PART II TMl-2 RADIOLOGICAL EFFLUENT CONTROLS CY-TM-170-300 Revision 5 Page 66 of 222 1.0 DEFINITIONS DEFINED TERMS PART II Definitions CY-TM-170-300 Revision 5 Page 67 of 222 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part II of the ODCM. PDMS 1.2 Post-Defueling Monitored Storage (PDMS) is that condition where TMl-2 defueling has been completed, the core debris removed from the reactor during the clean-up period has been shipped off-site, and the facility has been placed in a stable, safe, and secure condition. ACTION 1.3 ACTION shall be those additional requirements specified as corollary statements to each control and shall be part.of the controls. OPERABLE -OPERABILITY 1.4 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation,

controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function(s),

are also capable of performing their related support function(s). CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter, which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. CHANNEL CHECK CY-TM-170-300 Revision 5 Page 68 of 222 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be: a. Analog channels -the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channels

-the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions. SOURCE CHECK 1.8 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. COMPOSITE SAMPLE 1.9 A COMPOSITE SAMPLE is a combination of individual samples obtained at regular intervals over a time period. Either the volume of each individual sample is proportional to the flow rate discharge at the time of sampling or the number of equal volume samples is proportional to the time period used to produce the composite. GRAB SAMPLE 1.10 A GRAB SAMPLE is an individual sample collected in less than fifteen minutes. BATCH RELEASE 1.11 A BATCH RELEASE is the discharge of fluid waste of a discrete volume. CONTINUOUS RELEASE 1.12 A CONTINUOUS RELEASE is the discharge of fluid waste of a non-discrete volume, e.g., from a volume or system that has an input flow during the CONTINUOUS RELEASE. SITE BOUNDARY CY-TM-170-300 Revision 5 Page 69 of 222 1.13 The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMl-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile Island and between Three Mile Island and Shelley Island. The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM. FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. NOTATION S (Shiftly) D (Daily) W (Weekly) M (Monthly) Q (Quarterly) TABLE 1.1 Frequency Notation SA (Semi-Annually) A (Annually) E N.A. p CY-TM-170-300 Revision 5 Page 70 of 222 FREQUENCY At least once per 12 hours At least once per 24 hours At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 12 months At least once per 18 months Not applicable Completed prior to each release 2.0 CONTROLS AND BASES CY-TM-170-300 Revision 5 Page 71 of 222 2.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control. 2.0.2 Adherence to the requirements of the Control and/or associated ACTION within the specified time interval shall constitute compliance with the control. In the event the Control is restored prior to expiration to the specified time interval, completion of the ACTION statement is not required. 2.0.3 In the event the Control and associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the Control, initiate appropriate actions to rectify the problem to the extent possible under the circumstances, and submit a special report to the Commission pursuant to TMl-2 PDMS Technical Specification (Tech. Spec.) Section 6.8.2 within 30 days, unless otherwise specified. 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation Radioactive Liquid Effluent Instrumentation is common between TMl-1 and TMl-2. Controls, applicability, and actions are specified in ODCM Part I, Control 2.1.1 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL: The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: As shown in Table 2.1-2 ACTION: a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable. CY-TM-170-300 Revision 5 Page 72 of 222 b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels

OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner. BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases.

The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301. Table 2.1-2 CY-TM-170-300 Revision 5 Page 73 of 222 Radioactive Gaseous Process and Effluent Monitoring Instrumentation INSTRUMENT

1. Containment Purge Monitoring System a. b. C. Noble Gas Activity Monitor (2HP-R-225)

Particulate Monitor (2HP-R-225) Effluent System Flow Rate Measuring Device (2AH-FR-5907 Point 1) 2. Station Ventilation System a. Noble Gas Activity Monitor (2HP-R-219) or (2HP-R-219A)

b. Particulate Monitor (2HP-R-219) or (2HP-R-219A)

c. Effluent System Flow Rate Monitoring Device (2AH-FR-5907 Point 6) NOTES: 1. During operation of the monitored system. MINIMUM CHANNELS OPERABLE 1 1 1 1 1 APPLICABILITY NOTE 1 NOTE 1 NOTE 1 NOTE 1 NOTE 1 NOTE 1 ACTION NOTE2 NOTE2 NOTE3 NOTE2 NOTE2 NOTE3 2. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, secure Reactor Building Purge if in progress.

3. With flow rate monitoring instrumentation out of service, flow rates from the Auxiliary (2AH-FR-5907 Point 2), Fuel Handling (2AH-FR-5907 Point 4 ), Soiled Exhaust System (2AH-FR-5907 Point 5), and Reactor Buildings (2AH-FR-5907 Point 1) may be summed individually.

Under these conditions, the flow rate monitoring device is considered operable. If the flow rates cannot be summed individually, they may be estimated using the maximum design flow for the exhaust fans, and the reporting requirements of Control 2.1.2.b are applicable. 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL: CY-TM-170-300 Revision 5 Page 7 4 of 222 The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2. APPLICABILITY: At all times ACTION: With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within.the above limits. BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. These Controls permit flexibility under unusual conditions, which may temporarily result in higher than normal releases, but still within ten times the concentrations, specified in 10 CFR 20. It is expected that by using this flexibility under unusual conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the annual average concentrations specified in 10 CFR 20. As a result, this Control provides reasonable assurance that the resulting annual exposure to an individual in off-site areas will not exceed the design objectives of Section II.A of Appendix I to 10 CFR Part 50, which were established as requirements for the cleanup of TMl-2 in the NRC's Statement of Policy of April 27, 1981. I 2.2.1.2 Liquid Effluent Dose CONTROL CY-TM-170-300 Revision 5 Page 75 of 222 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ. b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ. APPLICABILITY:

At all times ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act. BASES CY-TM-170-300 Revision 5 Page 76 of 222 This Control requires that the dose to offsite personnel be limited to the design objectives of Appendix I of 10 CFR Part 50. This will assure the dose received by the public during PDMS is equivalent to or less than that from a normal operating reactor. The limits also assure that the environmental impacts are consistent with those assessed in NUREG-0683, the TMl-2 Programmatic Environmental Impact Statement (PEIS). The ACTION statements provide the required flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculations in the ODCM implement the requirements in Section Ill.A. of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1 O CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113. CY-TM-170-300 Revision 5 Page 77 of 222 2.2.1.3 Liquid Radwaste Treatment System CONTROL: The appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month. APPLICABILITY: At all times ACTION: a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information: BASES 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and, 3. A summary description of action(s) taken to prevent a recurrence.

The requirement that the appropriate portions of this system (shared with TMl-1) be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable. This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.D of Appendix I to 10 CFR Part 50. The intent of Section 11.D. is to reduce effluents to as low as is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section I I.A of Appendix I, 10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction. 2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL: CY-TM-170-300 Revision 5 Page 78 of 222 The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and b. For tritium and all radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem/yr to any organ. APPLICABILITY:

At all times. ACTION: With the release rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limit(s). BASES CY-TM-170-300 Revision 5 Page 79 of 222 The control provides reasonable assurance that the annual dose at the SITE BOUNDARY from gaseous effluent from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. At the same time, these Controls permit flexibility under unusual conditions, which may temporarily result in higher than the design objective levels, but still within the dose limits specified in 10 CFR 20 and within the design objectives of Appendix I to 10 CFR 50. It is expected that using this flexibility under unusual conditions, and by exerting every effort to keep levels of radioactive material in gaseous wastes as low as practicable, the annual releases will not exceed a small fraction of the annual dose limits specified in 10 CFR 20 and will not result in doses which exceed the design objectives of Appendix I to 10 CFR 50, which were endorsed as limits for the cleanup of TMl-2 by the NRC's Statement of Policy of April 27, 1981. These gaseous release rates provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in the exposure of a MEMBER OF THE PUBLIC in an unrestricted area, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the values specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. The absence of iodine ensures that the corresponding thyroid dose rate above background to a child via the inhalation pathway is less than or equal to 1500 mrem/yr (NU REG 1301 ), thus there is no need to specify dose rate limits for these nuclides. 2.2.2.2 Gaseous Effluents Dos.e-Noble Gases CONTROL: CY-TM-170-300 Revision 5 Page 80 of 222 The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter:

less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b. During any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation. APPLICABILITY: At all times. ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. BASES This control applies to the release of radioactive materials in gaseous effluents from TMl-2. CY-TM-170-300 Revision 5 Page 81 of 222 This control and associated action is provided to implement the requirements of Section 11.B, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section 11.B of Appendix I. The ACTION statements provide flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. 2.2.2.3 Dose -lodine-131, lodine-133,

Tritium, and Radionuclides In Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from Tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter:

less than or equal to 7.5 mrem to any organ, and b. During any calendar year: less than or equal to 15 mrem to any organ. APPLICABILITY: At all times. ACTION: CY-TM-170-300 Revision 5 Page 82 of 222 With the calculated dose from the release of Tritium and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRG Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. BASES CY-TM-170-300 Revision 5 Page 83 of 222 This control applies to the release of radioactive materials in gaseous effluents from TMl-2. This control and associated action is provided to implement the requirements of Section 11.C, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in Section 11.C of Appendix I. The ACTION statement provides flexibility during unusual conditions and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, iodine-133, tritium and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. The absence of iodines at the site eliminates the need to specify dose limits for these nuclides.

~--------- 1 CY-TM-170-300 Revision 5 Page 84 of 222 2.2.2.4 Ventilation Exhaust Treatment System CONTROL The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ. APPLICABILITY: At all times. ACTION: a. With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days,* a Special Report which includes the following information: BASES 1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3. A summary description of action(s) taken to prevent a recurrence.

The use of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in -Sections 11.B and 11.C of Appendix I, 10 CFR Part 50, for gaseous effluents. 2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL: CY-TM-170-300 Revision 5 Page 85 of 222 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. APPLICABILITY: At all times. ACTION: With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a, 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b,

• 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded.

If such is the case, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b ), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material

involved, and the cause of the exposure levels or concentrations.

If the estimated dose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. BASES CY-TM-170-300 Revision 5 Page 86 of 222 This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301 (d). This control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b ), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRG staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 3.0 SURVEILLANCES CY-TM-170-300 Revision 5 Page 87 of 222 3.0.1 Surveillance Requirements shall be applicable during the conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement. The Surveillance Requirements shall be performed to demonstrate compliance with the OPERABILITY requirements of the Control. 3.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. 3.0.3 f=ailure to perform a Surveillance Requirement within the time interval specified in Section 3.0.2 shall constitute non-compliance with OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours to permit completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours. Surveillance Requirements do not have to be performed on inoperable equipment. 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation SURVEILLANCE REQUIREMENTS 3.1.1.1 Radioactive Liquid Effluent Instrumentation is common between TMl-1 and TMl-2. Surveillances for this instrumentation are specified in ODCM Part I, Surveillance 3.1.1. 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation SURVEILLANCE REQUIREMENTS 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2. Table 3.1-2 CY-TM-170-300 Revision 5 Page 88 of 222 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements INSTRUMENT

1. Containment Purge Monitoring System a. b. Noble Gas Activity Monitor (2HP-R-225)

Particulate Sampler (2HP-R-225)

2. Station Ventilation Monitoring System a. b. NOTES: Noble Gas Activity Monitor (2HP-R-219) and (2HP-R-219A)

Particulate Sampler (2HP-R-219) and (2HP-R-219A)

1. During operation of the monitored system. CHANNEL CHECK D w D w CHANNEL CALIBRATION E N/A E N/A CHANNEL FUNCTIONAL TEST M N/A M N/A APPLICABILITY NOTE 1 NOTE 1 NOTE 1 NOTE 1 3.2 Radioactive Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration CY-TM-170-300 Revision 5 Page 89 of 222 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 3.2-1. The results of analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.1.2 Analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1. 3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1. 3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month. 3.2.1.3 Dose Projections 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM. TABLE 3.2-1 CY-TM-170-300 Revision 5 Page 90 of 222 Radioactive Liquid Waste Sampling and Analysis Program (4, 5) A. Liquid Releases Sampling Frequency Type of Detectable Activity Analysis Concentration (3) p Individual Gamma SE-7 µCi/ml (2) Each Batch H-3 1E-5 µCi/ml Q Gross Alpha 1E-7 µCi/ml Quarterly Composite (1) Sr-90 SE-8 µCi/ml NOTES: (1) A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant. (2) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near this. sensitivity limit when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with those radionuclides, which are routinely identified and measured. (3) The detectability limits for radioactivity analysis are based on the technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported. (4) The results of these analyses should be used as the basis for recording and reporting the quantities of radioactive material released in liquid effluents during the sampling period. In estimating releases for a period when analyses were not performed, the average of the two adjacent data points spanning this period should be used. Such estimates should be included in the effluent records and reports;

however, they should be clearly identified as estimates, and the method used to obtain these data should be described.

(5) Deviations from the sampling/analysis regime will be noted in the report specified in ODCM Part IV. 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates CY-TM-170-300 Revision 5 Page 91 of 222 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.a in accordance with the methods and procedures of the ODCM. 3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis

program, specified in Table 3.2-2. 3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.3 Dose, Tritium and Radionuclides In Particulate Form 3.2.2.3.1 Cumulative dose contributions from Tritium and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CAL.CULATION MANUAL (ODCM) monthly. 3.2.2.4 Ventilation Exhaust Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM. TABLE 3.2-2 CY-TM-170-300 Revision 5 Page 92 of 222 Radioactive Gaseous Waste Sampling and Analysis Program (3) SAMPLING TYPE OF DETECTABLE SAMPLE FREQUENC ACTIVITY* CONCENTRATION SAMPLE POINT TYPE y ANALYSIS (1 )(a) p H-3 1E-6 uCi/cc Reactor Building Purge Gas Each Purge Individual 1 E-4 µCi/cc (2) Releases Gamma Emitters M H-3 1E-6 µCi/cc Unit Exhaust Vent Release Gas Individual Points Monthly Gamma Emitters 1 E-4 µCi/cc (2) w Individual (b) 1E-10 µCi/cc (2) Weekly Gamma Emitters M Particulate Monthly Sr-90 1 E-11 µCi/cc s Composite M Gross Alpha Monthly 1 E-11 µCi/cc Composite Emitters lndv. Gamma 1E-10 µCi/cc (2) Reactor Building Breather SA Emitters (b) Particulate Semi-Annual Sr-90 1 E-11 uCi/cc s ly Gross Alpha 1 E-11 µCi/cc Emitters (1) The above detectability limits are based on technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported. (2) For certain mixtures of gamma emitters, it may be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios in the gaseous component in the reactor coolant for those radionuclides which are measurable. (3) Deviations from the sampling and analysis regime will be noted in the report specified in ODCM Part IV. Where TABLE 3.2-2 (Cont'd) CY-TM-170-300 Revision 5 Page 93 of 222 Radioactive Gaseous Waste Sampling and Analysis Program Table Notation

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a llreal" signal. For a particular measurement system (which may include radiochemical separation):

LLD= _____ 4_.6_6_s_p ____ _ E x V x 2.22 x 106 x Y x exp (-A.L1t) LLD is the lower limit of detection as defined above (as picocurie per unit mass or volume). Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute). E is the counting efficiency (as counts per transformation), Vis the sample size (in units of mass or volume), 2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable), ')..., is the radioactive decay constant for the particular radionuclide, and ~t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples),* The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and ~t shall be used in the calculation. The background count rate is calculated from the background counts that are.determined to be with+/- one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quantitative analysis for that radionuclide. TABLE 3.2-2 Notation (Cont'd) CY-TM-170-300 Revision 5 Page 94 of 222 b. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations. 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation CY-TM-170-300 Revision 5 Page 95 of 222 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM. 4.0 PART II REFERENCES CY-TM-170-300 Revision 5 Page 96 of 222 4.1 NUREG-0683, "Final Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident Three Mile Island Nuclear Station, Unit 2," March 1981, and its supplements. 4.2 TMl-2 PDMS Technical Specifications, attached to Facility License No. DPR-73 4.3 Title 10, Code of Federal Regulations, "Energy" 4.4 "Statement of Policy Relative to the NRG Programmatic Environmental Impact Statement on the Cleanup of Three Mile Island Unit 2," dated April 27, 1981 4.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 4.6 DOE/TIC-27601, Atmospheric Science and Power Reduction 4.7 TMl-1 Technical Specifications, attached to Facility Operating License No. DPR-50 4.8 PDMS -SAR PART Ill CY-TM-170-300 Revision 5 Page 97 of 222 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES CY-TM-170-300 Revision 5 Page 98 of 222 1.0 LIQUID EFFLUENT MONITORS 1.1 TMl-1 and TMl-2 Liquid Radiation Monitor Set Points The liquid effluent off-line monitors are set such that the concentration(s) of radionuclides in the liquid effluents will not exceed ten times the concentrations specified in 10 CFR 20, Appendix B Table 2, Col 2. Table 1.1 lists the Liquid Effluent Release Points and their parameters; Figure 1.1 provides a Liquid Release Pathway Diagram. To meet the above limit, the alarm/trip set points for liquid effluent monitors and flow measuring devices are set in accordance with the following equation: C

• f --<C F + f -(eq 1.1) Where: C = ten times the effluent concentration of 10 CFR 20 for the site, in µCi/ml. c = the set point, in µCi/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and release.

The set point is inversely proportional to the maximum volumetric flow of the effluent line and proportional to the minimal volumetric flow of the dilution stream plus the effluent stream. The alert set point value is set to ensure that advance warning occurs prior to exceeding any limits. The high alarm set point value is such that if it were exceeded, it would result in concentrations exceeding ten times the 10 CFR 20 concentrations for the unrestricted area. f = flow set point as measured at the radiation monitor location, in volume per unit time, but in the same units as F below. F = flow rate of dilution water measured prior to the release point, in volume per unit time. The set point concentration is reduced such that concentration contributions from multiple release points would not combine to exceed ten times 10 CFR 20 concentrations. The set point concentration is converted to set point scale uriits using appropriate radiation monitor calibration factors. This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and, for batch releases, the Releasing Radioactive Liquid Waste procedure. CY-TM-170-300 Revision 5 Page 99 of 222 1.2 TMI Liquid Effluent Release Points and Liquid Radiation Monitor Data TMl-1 has two required liquid radiation monitors. These are RM-L6 and RM-L 12. These liquid release point radiation monitors and sample points clre shown in Table 1.1. (The TMI outfall radiation

monitor, RM-L7, is also listed for information only.) TMl-2 does not have any required liquid radiation

monitors, but does utilize RM-L 12, and RM-L7 for release of liquid waste. 1.2.1 RM-L6 RM-L6 is an off-line system, monitoring radioactive batch discharges from the TMl-1 liquid radwaste system (see Figure 1.1 ). These batch releases are sampled and analyzed per site procedures prior to release.

The release rate is based on releasing one of two Waste Evaporator Condensate Storage Tanks (WECST) at a flow which will add less than 10%, of ten times the 10 CFR 20 concentrations [20% for H-3] to radionuclide concentrations in the unrestricted area, including recent values for Sr-89, Sr-90, and Fe-55. The release flow rate used is the most restrictive of two flow rates calculated for each liquid batch release, per the approved plant procedure. Two Dilution Factors (OF) are calculated to ultimately calculate the batch release flow rate. These two DF's are calculated to insure each radionuclide released to the unrestricted area is less than 10 percent of ten times the 1 OCFR20 radionuclide concentrations, (20% for H-3), and to ensure each liquid batch release boron concentration to the river will not exceed 0.7 ppm. The maximum release flow rate is then calculated by dividing the most restrictive (largest) OF into 90 percent of the current dilution flow rate of the Mechanical Draft Cooling Tower (MDCT). This conservative flow rate is then multiplied by 0.9 for the allowable flow rate.

• Calculation of the 10CFR20 concentration DF: DF1 = ~i (SAi) + (10% [20% for H-3] of ten times the 10CFR20 concentration)

SA = Specific Activity of each identified radionuclide

• Calculation of Boron DF: DF2 = Actual Tank Boron Concentration+

0.7. CY-TM-170-300 Revision 5 Page 100 of 222

• Maximum release flow rate calculation:

Max Flow = [(MDCT flow gpm

• 0.9) + (Most Restrictive DF)]
• 0.9 The dilution flow rate used is the current flow rate at the site. The minimum dilution flow rate is 5000 gpm per the TMl-1 FSAR. This ensures this batch release will meet the following equation.

Where: Ci= Xi= CH-3 = XH-3 = }.;(Ci/Xi) + (CH-312XH-3) 0.1, (eq 1.2) diluted concentration of the i1h radionuclide, other than H-3 Ten times the concentration for that radionuclide in the unrestricted area (10 CFR 20, App. B, Table 2, Col. 2). A value of 3E-3 µCi/ml for dissolved and entrained noble gases shall be used. diluted concentration of H-3 Ten times the concentration for H-3 in the restricted area (10 CFR 20, App. B, Table 2, Col. 2). The set points for RM-L6 are based on the maximum release rate (30 gpm), a minimum dilution flow (5000 gpm), and 25% of ten times the 10CFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentration of 1.0E-5 uCi/ml. These inputs are used in Equation 1.1 to determine the RM-L-6 High Alarm setpoint for all radionuclides being released. A high alarm on RM-L-6 will close valve WDL-V-257 and terminate any WECST releases to the environment. 1.2.2 RM-L 12 RM-L 12 is an off-line system, monitoring periodic combined releases from the Industrial Waste Treatment System/Industrial Waste Filtration System (IWTS/IWFS). The input to IWTS/IWFS originates in TMl-2 sumps, (see Figures 1.1 and 1.2) and the TMl-1 Turbine Building sumps (see Figure 1.1 ). The set points are based on the maximum release rate from both IWTS and IWFS simultaneously, (see Figure 1.1) a minimum dilution flow rate, and 50% of ten times the 1 OCFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentration of 1 E-5 µCi/ml. These inputs are used in equation 1.1 to determine the RM-L 12 High Alarm set point for all radionuclides being released. A high alarm on RM-L 12 will close IWTS and IWFS release valves and trip release pumps to stop the release. 1.2.3 RM-L 10 CY-TM-170-300 Revision 5 Page 101 of 222 RM-L 10 was a Nal detector submerged in the TMl-1 Turbine Building Sump. This detector has been removed from service. 1.2.4 RM-L7 RM-L7 is not an ODCM required liquid radiation monitor. RM-L7 is an off-line system, monitoring the TMI outfall to the Susquehanna River (see Figures 1.1 and 1.2). This monitor is the final radiation monitor for TMl-1 and TMl-2 normal liquid effluent releases. 1.3 Control of Liquid Releases TMI liquid effluent releases are controlled to less than ten times the 1 OCFR20 concentrations by limiting the percentage of this limit allowable from the two TMI liquid release points. RM-L6 and effluent sampling limit batch releases to less than or equal to 25% for all radionuclides, and RM-L 12 and effluent sampling limit releases from TMl-1 and TMl-2 to less than or equal to 50% for Cs-137. These radiation monitor set points also include built in meter error factors to further ensure that TMI liquid effluent releases are less than ten times the 1 OCFR20 concentrations to the environment. The radioactivity content of each batch of radioactive liquid waste is determined prior to release by sampling and analysis in accordance with ODCM Part I Table 3.2-1 or ODCM Part II, Table 3.2-1. The results of analyses are used with the calculational methods in Section 1.1, to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1. Post-release analysis of samples composited from batch releases are performed in accordance with ODCM Part I Table 3.2-1 or ODCM Part II Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1. The radioactivity concentration of liquids discharged from continuous release points are determined by collection and analysis of samples in accordance with ODCM Part I Table 3.2-1, or ODCM Part II Table 3.2-1. The tesults of the analysis are used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1. TABLE 1.1 CY-TM-170-300 Revision 5 Page 102 of 222 TMI Liquid Release Point and Liquid Radiation Monitor Data LIQUID RADIATION LIQUID RELEASE MONITOR POINT (Maximum DISCHARGE FLOW (DETECTOR) LOCATION Volume) RECORDER RM-L6 281' Elevation WECST Batch WDL-FT-84 (Nal) TMl-1 Auxiliary Bldg Releases (8000 gal.) RM-L7 South end of TMl-1 Station Discharge (Nal) MDCT TMl-1 and SR-FT-146

• • TMl-2, IWTS/IWFS RM-L 12 IWFS Building NW Continuous Releases IW-FT-342/

(Nal) Corner (300,000/ IW-FT-373 80,000 gal.)

• WDL-R-1311 has been flanged off as a TMl-2 liquid outfall.
  • RM-L7 is not an ODCM required liquid radiation monitor.

RELEASE TERMINATION INTERLOCK (YES/NO) VALVES YES WDL-V257 YES WDL-V257

• WDL-R-1311 YES IW-V73, IW-P16,17,18 IW-V279, IW-P29,30 TABLE 1.2 TMl-2 Sump Capacities I I Total Capacity Sume Gallons Turbine Building Sump 1346 Control Building Area Sump 718 Tendon Access Galley Sump 538 Control and Service Building Sump 1346 Air Intake Tunnel Normal Sump 700 Air Intake Tunnel Emergency Sump 100000 I CY-TM-170-300 Revision 5 Page 103 of 222 Units I 22.43 gals/in 9.96 gals/in 9.96 gals/in 22.43 gals/in ----8200 gal/ft

, :lnter:mediate . Btiilcllng;SiJmp . :east, lntenrieci1ate,

• B~ii8irjgiSuajp Wesf ** 9ompon(:ln, Coc:,lio'g..

. .,Wate,<:rM1~1

FIGURE 1-1 TMl-1 Liquid Effluent Pathways Page 1 of 1 CY-TM-170-300 Revision 5 Page 104 of 222 © *eomposite~R d ... .'.' . . :$ami:;,l~r

. a lation Monitor Auxiliary E!oiler ,Blow.down

• , .l:ID . Turbine Building

-Surtr . Mechanical Draft . I fr:,] Radwaste 151 .Grab l..n.J :01sposa.1 ,sample Pc:>Wdex Vessels Solids

• Graver system P<!Wdex *sun,p [BJ Intermediate

Building.

Sanitary WastaTMJ.1 andTM!-2

• Industrial
• Ooolors 'Sewage:

Treatinant .Plant . -+© + © .. Industrial* ,was'te;

• * *Ftitri!ltion system *,solids

Filter . Cake *~ t------=_.

@ . Cooling Tower Basin '51 TMl-1 ,.........,_..., _________ .....,;:t..,_;;~~~.,\;~~~ .... *,*RIVER FIGURE 1.2 TMl-2 Liquid Effluent Pathways CONTROL BUILDING SUMP TURBINE BUILDING SUMP .. . . ,,. IWTS SUMP ., CONTROL & SE~VICE AREA SUMP TENDON ACCESS GALLERY SUMP INDUSTRIAL WASTE TREATMENT SYSTEM *,_r -----,~,__---,.--+ RM*L-12 CY-TM-170-300 Revision 5 Page 105 of 222 CY-TM-170-300 Revision 5 Page 106 of 222 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liquid Effluents -10 CFR 50 Appendix I The dose from liquid effluents results from the consumption of fish and drinking water. The location of the nearest potable water intake is PP&L Brunner Island Steam Electric Station located downstream of TMI. The use of the flow of the Susquehanna River as the dilution flow is justified based on the complete mixing in the river prior tq the first potable water supply, adequately demonstrated by flume tracer die studies and additional liquid effluent release studies conducted using actual TMl-1 tritium releases. Other pathways contribute negligibly at Three Mile Island. The dose contribution from all radionuclides in liquid effluents released to the unrestricted area is calculated using the following expression: (eq 2.1) Where: Dose j = the cumulative dose commitment to the total body or any organ, j, from the liquid effluents for the total time period, in mrem. 11t = the length of the time period of actual releases, over which Ci and fare averaged for all liquid releases, in hours. Ci = the average concentration of radionuclide, i, in undiluted liquid effluent during time period 11t from any liquid release, in µCi/ml. NOTE: For Fe-55, Sr-89, Sr-90, prior to batch releases recent composite values will be used in the initial dose calculation. f = undiluted liquid waste flow, in gpm. FD = plant dilution water flowrate during the period of release, in gpm FR = actual river flowrate during the period of release or average river lowrate for the month the release is occurring, in gpm. DF = dilution factor as a result of mixing effects in the near field of the discharge structure of 0.2 (NU REG 0133) or taken to be 5 based on the inverse of 0.2. AWij and AFij = the site-related ingestion dose commitment factor to the total body or any organ, j, for each identified principle gamma and beta emitter, in mrem/hr per µCi/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway. Values for AWij are determined by the following equation: AWij = (1.14E5) x {Uw) x {DFij) Where: 1.14E5 = (1.0E6 pCi/µCi) x (1.0E3 ml/kg)+ (8760 hr/yr) Uw = Water consumption rate forceach age group in kg/yr (based on Table E-5 Reg. Guide 1.109, Rev. 1). CY-TM-170-300 Revision 5 Page 107 of 222 (eq 2.2) DFij = ingestion dose conversion factor for radionuclide, i, and for organ, j, in mrem/pCi, from Table 2.1 (Reg. Guide 1.109) Values for AFii are determined by the following equation: AFij = where: (1.14E5) x (Uf) x (DFij) x (BFi) (eq 2.2.2) 1.14E5 = defined above Uf= DFij = BFi = Fish consumption rate for each applicable age group in kg/yr (based on Table E-5 Reg. Guide 1.10_9, Rev. 1 ). ingestion dose conversion factor for radionuclide, i, and for organ, j, in mrem/pCi, from Table 2.1 (Reg. Guide 1.109, Rev. 1 ). Bioaccumulation factor for radionuclide, i, in fish, in pCi/kg per pCi/L from Table 2.2 (Reg. Guide 1.109, Rev. 1 ). 2.2 TMI Liquid Radwaste System Dose Cales Once Per Month ODCM Part I Control 2.2.1.3 and TMl-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent releases from each unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month. The following calculational method is provided for performing this dose projection. At least once per month, the total dose from all liquid releases for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual releases during the period for which the projection is made. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, appropriate portions of the Liquid Radwaste Treatment System, as defined in Section 3.1, shall be used to reduce radioactivity levels prior to release. CY-TM-170-300 Revision 5 Page 108 of 222 At the discretion of the ODCM Specialist, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter-to-date is not believed to be representative of the dose per day projected for the next month. CY-TM-170-300 Revision 5 Page 109 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 1 of 16 INGESTION DOSE FACTORS FOR ADULTS (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14(inorg) 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA-22 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 NA-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06

• 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-05 CA-41 1.85E-04 O.OOE+OO 2.00E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.84E-07 SC-46 5.51E-09 1.07E-08 3.11E-09 O.OOE+OO 9.99E-09 O.OOE+OO 5.21E-05 CR-51 O.OOE+OO O.OOE+OO 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN-54 O.OOE+OO 4.57E-06 8.72E-07 O.OOE+OO 1.36E-06 O.OOE+OO 1.40E-05 FE-55 2.75E-06 1.90E-06 4.43E-07 O.OOE+OO O.OOE+OO 1.06E-06 1.09E-06 MN-56 O.OOE+OO 1.15E-07 2.04E-08 0.00E+OO 1.46E-07 O.OOE+OO 3.67E-06 C0-57 O.OOE+OO 1.75E-07 2.91E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.44E-06 C0-58 O.OOE+OO 7.45E-07 1.67E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.51 E-05 FE-59 4.34E-06 1.02E-05 3.91E-06 O.OOE+OO O.OOE+OO 2.85E-06 3.40E-05 C0-60 O.OOE+OO 2.14E-06.

4.72E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.02.E-05 Nl-59 9.76E-06 3.35E-06 1.63E-06 O.OOE+OO O.OOE+OO O.OOE+OO 6.90E-07 Nl-63 1.30E-04 9.01E-06 4.36E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.88E-06 CU-64 O.OOE+OO 8.33E-08 3.91E-08 O.OOE+OO 2.10E-07 O.OOE+OO 7.10E-06 Nl-65 5.28E-07 6.86E-08 3.13E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.74E-06 ZN-65 4.84E-06 1.54E-05 6.96E-06 O.OOE+OO 1.03E-05 O.OOE+OO 9.70E-06 ZN-69M 1.70E-07 4.0BE-07 3.73E-08 O.OOE+OO 2.47E:07 O.OOE+OO 2.49E-05 ZN-69 1.03E-08 1.97E-08 1.37E-09 O.OOE+OO 1.28E-08 O.OOE+OO 2.96E-09 SE-79 O.OOE+OO 2.63E-06 4.39E-07 O.OOE+OO 4.55E-06 O.OOE+OO 5.38E-07 BR-82 O.OOE+OO O.OOE+OO 2.26E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.59E-06 BR-83 O.OOE+OO O.OOE+OO 4.02E-08 O.OOE+OO O.OOE+OO O.OOE+OO 5.79E-08 BR-84 O.OOE+OO O.OOE+OO 5.21E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.09E-13 BR-85 O.OOE+OO O.OOE+OO 2.14E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 2.11 E-05 9.83E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.16E-06 RB-87 O.OOE+OO 1.23E-05 4.28E-06 O.OOE+OO O.OOE+OO O.OOE+OO 5.76E-07 RB-88 O.OOE+OO 6.05E-08 3.21E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.36E-19 RB-89 O.OOE+OO 4.01E-08 2.82E-08 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-21 SR-89 3.08E-04 O.OOE+OO 8.84E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.94E-05 SR-90 7.58E-03 O.OOE+OO 1.86E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.19E-04 Y-90 9.62E-09 O.OOE+OO 2.58E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E-04 SR-91 5.67E-06 O.OOE+OO 2.29E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.70E-05 Y-91M 9.09E-11 O.OOE+OO 3.52E-12 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-10 Y-91 1.41E-07 O.OOE+OO 3.77E-09 O.OOE+OO O.OOE+OO O.OOE+OO 7.76E-05 SR-92 2.15E-06 O.OOE+OO 9.30E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.26E-05 Y-92 8.45E-10 O.OOE+OO 2.47E-11 O.OOE+OO O.OOE+OO O.OOE+OO 1.48E-05 Y-93 2.68E-09 O.OOE+OO 7.40E-11 O.OOE+OO O.OOE+OO O.OOE+OO 8.50E-05 NB-93M 2.55E-08 8.32E-09 2.05E-09 O.OOE+OO 9.57E-09 O.OOE+OO 3.84E-06 NB-95 6.22E-09 3.46E-09 1.86E-09 O.OOE+OO 3.42E-09 O.OOE+OO 2.10E-05 NB-97 5.22E-11 1.32E-11 4.82E-12 O.OOE+OO 1.54E-11 O.OOE+OO 4.87E-08 CY-TM-170-300 Revision 5 Page 110 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 2 of 16 INGESTION DOSE FACTORS FOR ADULTS (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI ZR-93 4.18E-08 2.34E-09 1.09E-09 O.OOE+OO 8.87E-09 O.OOE+OO 2.43E-06 ZR-95 3.04E-08 9.75E-09 6.60E-09 O.OOE+OO 1.53E-08 O.OOE+OO 3.09E-05 ZR-97 1.68E-09 3.39E-10 1.55E-10 O.OOE+OO 5.12E-10 O.OOE+OO 1.05E-04 M0-93 O.OOE+OO 7.51E-06 2.03E-07 O.OOE+OO 2.13E-06 O.OOE+OO 1.22E-06 M0-99 O.OOE+OO 4.31 E-06 8.20E-07 O.OOE+OO 9.76E-06 O.OOE+OO 9.99E-06 TC-99 1.25E-07 1.86E-07 5.02E-08 O.OOE+OO 2.34E-06 1.58E-08 6.0BE-06 TC-99M 2.47E-10 6.98E-10 8.89E-09 O.OOE+OO 1.06E-08 3.42E-10 4.13E-07 TC-101 2.54E-10 3.66E-10 3.59E-09 O.OOE+OO 6.59E-09 1.87E-10 1.1 OE-21 RU-103 1.85E-07 O.OOE+OO 7.97E-08 O.OOE+OO 7.06E-07 O.OOE+OO 2.16E-05 RU-105 1.54E-08 O.OOE+OO 6.0BE-09 O.OOE+OO 1.99E-07 O.OOE+OO 9.42E-06 RU-106 2.75E-06 O.OOE+OO 3.48E-07 O.OOE+OO 5.31E-06 O.OOE+OO 1.78E-04 RH-105 1.21E-07 8.85E-08 5.83E-08 O.OOE+OO 3.76E-07 O.OOE+OO 1.41 E-05 PD-107 O.OOE+OO 1.47E-07 9.40E-09 O.OOE+OO 1.32E-06 O.OOE+OO 9.11E-07 PD-109 O.OOE+OO 1.77E-07 3.99E-08 O.OOE+OO 1.01E-06 O.OOE+OO 1.96E-05 AG-110M 1.60E-07 1.48E-07 8.79E-08 O.OOE+OO . 2.91E-07 O.OOE+OO 6.04E-05 AG-111 5.81E-08 2.43E-08 1.21 E-08 O.OOE+OO 7.84E-08 O.OOE+OO 4.46E-05 CD-113M O.OOE+OO 3.18E-06 1.02E-07 O.OOE+OO 3.50E-06 O.OOE+OO 2.56E-05 CD-115M O.OOE+OO 1.84E-06 5.87E-08 O.OOE+OO 1.46E-06 O.OOE+OO 7.74E-05 SN-123 3.11E-05 5.15E-07 7.59E-07 4.38E-07 O.OOE+OO O.OOE+OO 6.33E-05 SN-125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 O.OOE+OO O.OOE+OO 1.04E-04 SN-126 8.45E-05 1.67E-06 2.40E-06 4.92E-07 O.OOE+OO O.OOE+OO 2.43E-05 SB-124 2.80E-06 5.29E-08 1.11 E-06 6.79E-09 O.OOE+OO 2.18E-06 7.95E-05 SB-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 O.OOE+OO 1.38E-06 1.97E-05 SB-126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 O.OOE+OO 7.05E-07 9.40E-05 SB-127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 O.OOE+OO 1.53E-07 5.90E-05 TE-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+OO 1.0?E-05 TE-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 O.OOE+OO 2.27E-05 TE-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 O.OOE+OO 8.68E-06 TE-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.BOE-05 O.OOE+OO 5.79E-05 TE-129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 O.OOE+OO 2.37E-08 TE-133M 4.62E-08 2.?0E-08 2.60E-08 3.91 E-08 2.67E-07 O.OOE+OO 9.26E-09 TE-134 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 O.OOE+OO 3.59E-11 1-129 3.27E-06 2.81E-06 9.21E-06 7.23E-03 6.04E-06 O.OOE+OO 4.44E-07 1-130 7.56E-07 2.23E-06 8.BOE-07 1.89E-04 3.48E-06 O.OOE+OO 1.92E-06 1-131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 O.OOE+OO 1.57E-06 TE-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 O.OOE+OO 8.40E-05 TE-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 O.OOE+OO 2.79E-09 1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 O.OOE+OO 1.02E-07 TE-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 O.OOE+OO 7.71E-05 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 O.OOE+OO 2.22E-06 CS-134M 2.13E-08 4.48E-08 2.29E-08 O.OOE+OO 2.43E-08 3.83E-09 1.58E-08 CS-134 6.22E-05 1.48E-04 1.21E-04 O.OOE+OO 4.79E-05 1.59E-05 2.59E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+OO 2.51E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 O.OOE+OO 1.31 E-06 CY-TM-170-300 Revision 5 Page 111 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 3 of 16 INGESTION DOSE FACTORS FOR ADULTS (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI CS-135 1.95E-05 1.BOE-05 7.99E-06 O.OOE+OO 6.81E-06 2.04E-06 4.21E-07 CS-136 6.51E-06 2.57E-05 1.85E-05 O.OOE+OO 1.43E-05 1.96E-06 2.92E-06 CS-137 7.97E-05 1.09E-04 7.14E-05 O.OOE+OO 3.70E-05 1.23E-05 2.11E-06 CS-138 5.52E-08 1.09E-07 5.40E-08 O.OOE+OO 8.01E-08 7.91E-09 4.65E-13 CS-139 3.41E-08 5.0BE-08 1.85E-08 0.00E+OO 4.0?E-08 3.70E-09 1.10E-30 BA-139 9.70E-08 6.91 E-11 2.84E-09 O.OOE+OO 6.46E-11 3.92E-11 1.72E-07 BA-140 2.03E-05 2.55E-08 1.33E-06 O.OOE+OO 8.67E-09 1.46E-08 4.18E-05 LA-140 2.50E-09 1.26E-09 3.33E-10 O.OOE+OO O.OOE+OO O.OOE+OO 9.25E-05 BA-141 4.71E-08 3.56E-11 1.59E-09 O.OOE+OO 3.31 E-11 2.02E-11 2.22E-17 LA-141 3.19E-10 9.90E-11 1.62E-11 O.OOE+OO O.OOE+OO O.OOE+OO 1.18E-05 CE-141 9.36E-09 6.33E-09 7.18E-10 O.OOE+OO 2.94E-09 O.OOE+OO 2.42E-05 BA-142 2.13E-08 2.19E-11 1.34E-09 O.OOE+OO 1.85E-11 1.24E-11 3.00E-26 LA-142 1.28E-10 5.82E-11 1.45E-11 O.OOE+OO O.OOE+OO O.OOE+OO 4.25E-07 CE-143 1.65E-09 1.22E-06 1.35E-10 O.OOE+OO 5.37E-10 O.OOE+OO 4.56E-05 PR-143 9.20E-09 3.69E-09 4.56E-10 O.OOE+OO 2:13E-09 O.OOE+OO 4.03E-05 CE-144 4.BBE-07 2.04E-07 2.62E-08 O.OOE+OO 1.21E-07 O.OOE+OO 1.65E-04 PR-144 3.01 E-11 1.25E-11 1.53E-12 O.OOE+OO 7.05E-12. O.OOE+OO 4.33E-18 ND-147 6.29E-09 7.27E-09 4.35E-10 O.OOE+OO 4.25E-09 O.OOE+OO 3.49E-05 PM-147 7.54E-08 7.09E-09 2.87E-09 O.OOE+OO 1.34E-08 O.OOE+OO 8.93E-06 PM-148M 3.07E-08 7.95E-09 6.0BE-09 O.OOE+OO 1.20E-08 O.OOE+OO 6.74E-05 PM-148 7.17E-09 1.19E-09 5.99E-10 O.OOE+OO 2.25E-09 O.OOE+OO 9.35E-05 PM-149 1.52E-09 2.15E-10 8.78E-11 O.OOE+OO 4.06E-10 O.OOE+OO 4.03E-05 PM-151 6.97E-10 1.17E-10 5.91 E-11 O.OOE+OO 2.09E-10 O.OOE+OO 3.22E-05 SM-151 6.90E-08 1.19E-08 2.85E-09 O.OOE+OO 1.33E-08 O.OOE+OO 5.25E-06 SM-153 8.57E-10 7.15E-10 5.22E-11 O.OOE+OO 2.31 E-10 O.OOE+OO 2.55E-05 EU-152 1.95E-07 4.44E-08 3.90E-08 O.OOE+OO 2.75E-07 O.OOE+OO 2.56E-05 EU-154 6.15E-07 7.56E-08 5.38E-08 O.OOE+OO 3.62E-07 O.OOE+OO 5.48E-05 EU-155 8.60E-08 1.22E-08 7.87E-09 O.OOE+OO 5.63E-08 O.OOE+OO 9.60E-06 EU-156 1.37E-08 1.06E-08 1.71E-09 O.OOE+OO 7.0BE-09 O.OOE+OO 7.26E-05

• TB-160 4.70E-08 O.OOE+OO 5.86E-09 O.OOE+OO 1.94E-08 O.OOE+OO 4.33E-05 H0-166M 2.70E-07 8.43E-08 6.40E-08 O.OOE+OO 1.26E-07 O.OOE+OO 2.56E-05 W-181 9.91E-09 3.23E-09 3.46E-10 O.OOE+OO O.OOE+OO O.OOE+OO 3.68E-07 W-185 4.05E-07 1.35E-07 1.42E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.56E-05 W-187 1.03E-07 8.61E-08 3.01E-08 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E-05 NP-239 1.19E-09 1.17E-10 6.45E-11 O.OOE+OO 3.65E-10 O.OOE+OO 2.40E-05 U-232 4.13E-03 O.OOE+OO 2.95E-04 O.OOE+OO 4.47E-04 O.OOE+OO 6.78E-05 U-233 8.71 E-04 O.OOE+OO 5.28E-05 O.OOE+OO 2.03E-04 O.OOE+OO 6.27E-05 U-234 8.36E-04 O.OOE+OO 5.17E-05 O.OOE+OO 1.99E-04 O.OOE+OO 6.14E-05 U-235 8.01E-04 O.OOE+OO 4.86E-05 O.OOE+OO 1.87E-04 O.OOE+OO 7.81E-05 U-236 8.01E-04 O.OOE+OO 4.96E-05 O.OOE+OO 1.91E-04 O.OOE+OO 5.76E-05 U-237 5.52E-08 O.OOE+OO 1.47E-08 O.OOE+OO 2.27E-07 O.OOE+OO 1.94E-05 U-238 7.67E-04 O.OOE+OO 4.54E-05 O.OOE+OO 1.75E-04 O.OOE+OO 5.50E-05 CY-TM-170-300 Revision 5 Page 112 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 4 of 16 INGESTION DOSE FACTORS FOR ADULTS (mrem per pCi ingested)

Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI NP-237 1.26E-03 8.96E-05 5.54E-05 O.OOE+OO 4.12E-04 O.OOE+OO 7.94E-05 NP-238 1.37E-08 3.69E-10 2.13E-10 O.OOE+OO 1.25E-09 O.OOE+OO 3.43E-05 PU-238 6.30E-04 7.98E-05 1.71 E-05 O.OOE+OO 7.32E-05 O.OOE+OO 7.30E-05 PU-239 7.25E-04 8.71E-05 1.91 E-05 O.OOE+OO 8.11 E-05 O.OOE+OO 6.66E-05 PU-240 7.24E-04 8.?0E-05 1.91 E-05 O.OOE+OO 8.10E-05 O.OOE+OO 6.78E-05 PU-241 1.57E-05 7.45E-07 3.32E-07 O.OOE+OO 1.53E-06 O.OOE+OO 1.40E-06 PU-242 6.72E-04 8.39E-05 1.84E-05 O.OOE+OO 7.81E-05 O.OOE+OO 6.53E-05 PU-244 7.84E-04 9.61E-05 2.11E-05 O.OOE+OO 8.95E-05 O.OOE+OO 9.73E-05 AM-241 7.55E-04 7.05E-04 5.41 E-05 O.OOE+OO 4.0?E-04 O.OOE+OO 7.42E-05 AM-242M 7.61E-04 6.63E-04 5.43E-05 O.OOE+OO 4.05E-04 O.OOE+OO 9.34E-05 AM-243 7.54E-04 6.90E-04 5.30E-05 O.OOE+OO 3.99E-04 O.OOE+OO 8.?0E-05 CM-242 2.06E-05 2.19E-05 1.37E-06 O.OOE+OO 6.22E-06 O.OOE+OO 7.92E-05 CM-243 5.99E-04 5.49E-04 3.75E-05 O.OOE+OO 1.75E-04 O.OOE+OO 7.81E-05 CM-244 4.56E-04 4.27E-04 2.87E-05 O.OOE+OO 1.34E-04 O.OOE+OO 7.55E-05 CM-245 9.38E-04 8.17E-04

• 5.76E-05 O.OOE+OO 2.69E-04 O.OOE+OO 7.04E-05 CM-246 9.30E-04 8.16E-04 5.75E-05 O.OOE+OO 2.68E-04 O.OOE+OO 6.91E-05 CM-247 9.0?E-04 8.04E-04 5.67E-05 O.OOE+OO 2.64E-04 O.OOE+OO 9.09E-05 CM-248 7.54E-03 6.63E-03 4.67E-04 O.OOE+OO 2.18E-03 O.OOE+OO 1.47E-03 CF-252 2.61 E-04 O.OOE+OO 6.29E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.88E-04 CY-TM-170-300 Revision 5 Page 113 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 5 of 16 INGESTION DOSE FACTORS FOR TEENAGER (mrem per pCi ingested)

Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14(inorg) 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA-22 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 NA-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71 E-05 1.07E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E-05 CA-41 1.97E-04 O.OOE+OO 2.13E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.95E-07 SC-46 7.24E-09 1.41 E-08 4.18E-09 O.OOE+OO 1.35E-08 O.OOE+OO 4.BOE-05 CR-51 O.OOE+OO O.OOE+OO 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN-54 O.OOE+OO 5.90E-06 1.17E-06 O.OOE+OO 1.76E-06 O.OOE+OO 1.21E-05 FE-55 3.78E-06 2.68E-06 6.25E-07 O.OOE+OO O.OOE+OO 1.70E-06 1.16E-06 MN-56 O.OOE+OO 1.58E-07 2.81E-08 O.OOE+OO 2.00E-07 O.OOE+OO 1.04E-05 C0-57 O.OOE+OO 2.38E-07 3.99E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.44E-06 C0-58 O.OOE+OO 9.72E-07 2.24E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.34E-05 FE-59 5.87E-06 1.37E-05 5.29E-06 O.OOE+OO O.OOE+OO 4.32E-06 3.24E-05 C0-60 O.OOE+OO 2.81E-06 6.33E.-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.66E-05 Nl-59 1.32E-05 4.66E-06 2.24E-06 O.OOE+OO O.OOE+OO O.OOE+OO 7.31 E-07 Nl-63 1.77E-04 1.25E-05 6.00E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.99E-06 CU-64 O.OOE+OO 1.15E-07 5.41 E-08 O.OOE+OO 2.91E-07 O.OOE+OO 8.92E-06 Nl-65 7.49E-07 9.57E-08 4.36E-08 O.OOE+OO O.OOE+OO O.OOE+OO 5.19E-06 ZN-65 5.76E-06 2.00E-05 9.33E-06 O.OOE+OO 1.28E-05 O.OOE+OO 8.47E-06 ZN-69M 2.40E-07 5.66E-07 5.19E-08 O.OOE+OO 3.44E-07 O.OOE+OO 3.11 E-05 ZN-69 1.47E-08 2.BOE-08 1.96E-09 O.OOE+OO 1.83E-08 O.OOE+OO 5.16E-08 SE-79 O.OOE+OO 3.73E-06 6.27E-07 O.OOE+OO 6.50E-06 O.OOE+OO 5.70E-07 BR-82 O.OOE+OO O.OOE+OO 3.04E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-83 O.OOE+OO O.OOE+OO 5.74E-08. O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-84 O.OOE+OO O.OOE+OO 7.22E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 3.05E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 2.98E-05 1.40E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.41E-06 RB-87 O.OOE+OO 1.75E-05 6.11E-06 O.OOE+OO O.OOE+OO O.OOE+OO 6.11E-07 RB-88 O.OOE+OO 8.52E-08 4.54E-08 O.OOE+OO O.OOE+OO O.OOE+OO 7.30E-15 RB-89 O.OOE+OO 5.50E-08 3.89E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.43E-17 SR-89 4.40E-04 O.OOE+OO 1.26E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.24E-05 SR-90 8.30E-03 O.OOE+OO 2.05E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-04 Y-90 1.37E-08 O.OOE+OO 3.69E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.13E-04 SR-91 8.07E-06 O.OOE+OO 3.21E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.66E-05 Y-91M 1.29E-10 O.OOE+OO 4.93E-12 O.OOE+OO O.OOE+OO O.OOE+OO 6.09E-09 Y-91 2.01E-07 O.OOE+OO 5.39E-09 O.OOE+OO O.OOE+OO O.OOE+OO 8.24E-05 SR-92 3.05E-06 O.OOE+OO 1.30E-07 O.OOE+OO

• O.OOE+OO O.OOE+OO 7.77E-05 Y-92 1.21 E-09 O.OOE+OO 3.50E-11 O.OOE+OO O.OOE+OO O.OOE+OO 3.32E-05 Y-93 3.83E-09 O.OOE+OO 1.05E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E-04 NB-93M 3.44E-08 1.13E-08 2.83E-09 O.OOE+OO 1.32E-08 O.OOE+OO 4.07E-06 NB-95 8.22E-09 4.56E-09 2.51E-09 O.OOE+OO 4.42E-09 O.OOE+OO 1.95E-05 NB-97 7.37E-11 1.83E-11 6.68E-12 O.OOE+OO 2.14E-11 O.OOE+OO 4.37E-07 CY-TM-170-300 Revision 5 Page 114 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 6 of 16 INGESTION DOSE FACTORS FOR TEENAGER (mrem per pCi ingested)

Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI ZR-93 5.53E-08 2.73E-09 1.49E-09 O.OOE+OO 9.65E-09 O.OOE+OO 2.58E-06 ZR-95 4.12E-08 1.30E-08 8.94E-09 O.OOE+OO 1.91 E-08 O.OOE+OO 3.00E-05 ZR-97 2.37E-09 4.69E-10 2.16E-10 O.OOE+OO 7.11E-10 O.OOE+OO 1.27E-04 M0-93 O.OOE+OO 1.06E-05 2.90E-07 O.OOE+OO 3.04E-06 O.OOE+OO 1.29E-06 M0-99 O.OOE+OO 6.03E-06 1.15E-06 O.OOE+OO 1.38E-05 O.OOE+OO 1.0BE-05 TC-99 1.79E-07 2.63E-07 7.17E-08 O.OOE+OO 3.34E-06 2.72E-08 6.44E-06 TC-99M 3.32E-10 9.26E-10 1.20E-08 O.OOE+OO 1.38E-08 5.14E-10 6.0BE-07 TC-101 3.60E-10 5.12E-10 5.03E-09 O.OOE+OO 9.26E-09 3.12E-10 8.75E-17 RU-103 2.55E-07 O.OOE+OO 1.09E-07 O.OOE+OO 8.99E-07 O.OOE+OO 2.13E-05 RU-105 2.18E-08 O.OOE+OO 8.46E-09 O.OOE+OO 2.75E-07 O.OOE+OO 1.76E-05 RU-106 3.92E-06 O.OOE+OO 4.94E-07 O.OOE+OO 7.56E-06 O.OOE+OO 1.88E-04 RH-105 1.73E-07 1.25E-07 8.20E-08 O.OOE+OO 5.31E-07 O.OOE+OO 1.59E-05 PD-107 O.OOE+OO 2.0BE-07 1.34E-08 O.OOE+OO 1.88E-06 O.OOE+OO 9.66E-07 PD-109 O.OOE+OO 2.51 E-07 5.70E-08 O.OOE+OO 1.45E-06 O.OOE+OO 2.53E-05 AG-110M 2.05E-07 1.94E-07 1.18E-07 O.OOE+OO 3.70E-07 O.OOE+OO 5.45E-05 AG-111 8.29E-08 3.44E-08 1.73E-08 O.OOE+OO 1.12E-07 O.OOE+OO 4.BOE-05 CD-113M O.OOE+OO 4.51E-06 1.45E-07 O.OOE+OO 4.99E-06 O.OOE+OO 2.71E-05 CD-115M O.OOE+OO 2.60E-06 8.39E-08 O.OOE+OO 2.0BE-06 O.OOE+OO 8.23E-05 SN-123 4.44E-05 7.29E-07 1.0BE-06 5.84E-07 O.OOE+OO O.OOE+OO 6.71E-05 SN-125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 O.OOE+OO O.OOE+OO 1.12E-04 SN-126 1.16E-04 2.16E-06 3.30E-06 5.69E-07 O.OOE+OO O.OOE+OO 2.58E-05 SB-124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 O.OOE+OO 3.38E-06 7.BOE-05 SB-125 2.48E-06 2.71E-08 5.BOE-07 2.37E-09 O.OOE+OO 2.18E-06 1.93E-05 SB-126 1.59E-06 3.25E-08 5.71E-07 8.99E-09 O.OOE+OO 1.14E-06 9.41 E-05 SB-127 3.63E-07 7.76E-09 1.37E:07 4.0BE-09 O.OOE+OO 2.47E-07 6.16E-05 TE-125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 O.OOE+OO O.OOE+OO 1.13E-05 TE-127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 . O.OOE+OO 2.41 E-05 TE-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 O.OOE+OO 1.22E-05 TE-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 O.OOE+OO 6.12E-05 TE-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 O.OOE+OO 2.45E-07 TE-133M 6.44E-08 3.66E-08 3.56E-08 5.11E-08 3.62E-07 O.OOE+OO 1.48E-07 TE-134 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 O.OOE+OO 1.66E-09 1-129 4.66E-06 3.92E-06 6.54E-06 4.77E-03 7.01E-06 O.OOE+OO 4.57E-07 1-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 O.OOE+OO 2.29E-06 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 O.OOE+OO 1.62E-06 TE-131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-0/5 O.OOE+OO 9.39E-05 TE-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 O.OOE+OO 2.29E-09 1-132 . 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 O.OOE+OO 3.18E-07 TE-132 3.49E-06 2.21E-06 2.0BE-06 2.33E-06 2.12E-05 O.OOE+OO 7.00E-05 1-133 2.01E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 O.OOE+OO 2.58E-06 CS-134M 2.94E-08 6.09E-08 3.13E-08 O.OOE+OO 3.39E-08 5.95E-09 4.05E-08 CS-134 8.37E-05 1.97E-04 9.14E-05 O.OOE+OO 6.26E-05 2.39E-05 2.45E-06 CY-TM-170-300 Revision 5 Page 115 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 7 of 16 INGESTION DOSE FACTORS FOR TEENAGER (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI 1-134 1.46E-07 3.B?E-07 1.39E-07 6.45E-06 6.10E-07 O.OOE+OO 5.10E-09 1-135 6.10E-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0.00E+OO 1.74E-06 CS-135 2.?BE-05 2.55E-05 5.96E-06 O.OOE+OO 9.73E-06 3.52E-06 4.46E-07 CS-136 8.59E-06 3.38E-05 2.27E-05 O.OOE+OO 1.84E-05 2.90E-06 2.72E-06 CS-137 1.12E-04 1.49E-04 5.19E-05 O.OOE+OO 5.0?E-05 1.97E-05 2.12E-06 CS-138 7.76E-08 1.49E-07 7.45E-08 O.OOE+OO 1.10E-07 1.28E-08 6.76E-11 CS-139 4.B?E-08 7.17E-08 2.63E-08 O.OOE+OO 5.79E-08 6.34E-09 3.33E-23 BA-139 1.39E-07 9.78E-11 4.05E-09 O.OOE+OO 9.22E-11 6.74E-11 1.24E-06 BA-140 2.84E-05 3.48E-08 1.83E-06 O.OOE+OO 1.18E-08 2.34E-08 4.38E-05 LA-140 3.48E-09 1.71E-09 4.55E-10 O.OOE+OO 0.00E+OO O.OOE+OO 9.82E-05 BA-141 6.71E-08 5.01 E-11 2.24E-09 O.OOE+OO 4.65E-11 3.43E-11 1.43E-13 LA-141 4.55E-10 1.40E-10 2.31E-11 O.OOE+OO O.OOE+OO O.OOE+OO 2.48E-05 CE-141 1.33E-08 8.88E-09 1.02E-09 O.OOE+OO 4.18E-09 O.OOE+OO 2.54E-05 BA-142 2.99E-08 2.99E-11 1.84E-09 O.OOE+OO 2.53E-11 1.99E-11 9.18E-20 LA-142 1.79E-10 7.95E-11 1.98E-11 O.OOE+OO O.OOE+OO O.OOE+OO

• 2.42E-06 CE-143 2.35E-09 1.71E-06 1.91E-10 O.OOE+OO 7.67E-10 0.00E+OO 5 .. 14E-05 PR-143 1.31 E-08 5.23E-09 6.52E-10 O.OOE+OO 3.04E-09 O.OOE+OO 4.31E-05 CE-144 6.96E-07 2.88E-07 3.74E-08 O.OOE+OO 1.72E-07 O.OOE+OO 1.75E-04 PR-144 4.30E-11 1.76E-11 2.18E-12 O.OOE+OO 1.01E-11 O.OOE+OO 4.74E-14 ND-147 9.38E-09 1.02E-08 6.11E-10 O.OOE+OO 5.99E-09 O.OOE+OO 3.68E-05 PM-147 1.05E-07 9.96E-09 4.06E-09 O.OOE+OO 1.90E-08 O.OOE+OO 9.47E-06 PM-148M 4.14E-08 1.05E-08 8.21E-09 O.OOE+OO 1.59E-08 O.OOE+OO 6.61E-05 PM-148 1.02E-08 1.66E-09 8.36E-10 O.OOE+OO 3.00E-09 O.OOE+OO 9.90E-05 PM-149 2.17E-09 3.05E-10 1.25E-10 O.OOE+OO 5.81E-10 O.OOE+OO 4.49E-05 PM-151 9.87E-10 1.63E-10 8.25E-11 O.OOE+OO 2.93E-10 O.OOE+OO 3.66E-05 SM-151 8.73E-08 1.68E-08 3.94E-09 O.OOE+OO 1.84E-08 O.OOE+OO 5.?0E-06 SM-153 1.22E-09 1.01E-09 7.43E-11 O.OOE+OO 3.30E-10 O.OOE+OO 2.85E-05 EU-152 2.45E-07 5.90E-08 5.20E-08 O.OOE+OO 2.74E-07 O.OOE+OO 2.17E-05 EU-154 7.91 E-07 1.02E-07 7.19E-08 O.OOE+OO 4.56E-07 O.OOE+OO 5.39E-05 EU-155 1.74E-07 1.68E-08 1.04E-08 O.OOE+OO 6.57E-08 O.OOE+OO 9.63E-05 EU-156 1.92E-08 1.44E-08 2.35E-09 O.OOE+OO 9.69E-09 O.OOE+OO 7.36E-05 TB-160 6.47E-08 O.OOE+OO 8.0?E-09 O.OOE+OO 2.56E-08 O.OOE+OO 4.19E-05 H0-166M 3.57E-07 1.10E-07 7.96E-08 O.OOE+OO 1.61E-07 O.OOE+OO 2.71E-05 W-181 1.42E-08 4.58E-09 4.79E-10 O.OOE+OO O.OOE+OO O.OOE+OO 3.90E-07 W-185 5.79E-07 1.91 E-07 2.02E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.65E-05 W-187 1.46E-07 1.19E-07 4.17E-08 O.OOE+OO O.OOE+OO O.OOE+OO 3.22E-05 NP-239 1.76E-09 1.66E-10 9.22E-11 O.OOE+OO 5.21E-10 O.OOE+OO 2.67E-05 U-232 5.89E-03 O.OOE+OO 4.21 E-04 O.OOE+OO 6.38E-04 O.OOE+OO 7.19E-05 U-233 1.24E-03 O.OOE+OO 7.54E-05 O.OOE+OO 2.90E-04 O.OOE+OO 6.65E-05 U-234 1.19E-03 O.OOE+OO 7.39E-05 O.OOE+OO 2.85E-04 O.OOE+OO 6.51E-05 CY-TM-170-300 Revision 5 Page 116 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 8 of 16 INGESTION DOSE FACTORS FOR TEENAGER (mrem per pCi ingested)

Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI U-235 1.14E-03 O.OOE+OO 6.94E-05 O.OOE+OO 2.67E-04 O.OOE+OO 8.28E-05 U-236 1.14E-03 O.OOE+OO 7.09E-05 O.OOE+OO 2.73E-04 O.OOE+OO 6.11E-05 U-237 7.89E-08 O.OOE+OO 2.10E-08 O.OOE+OO 3.24E-07 O.OOE+OO 2.09E-05 U-238 1.09E-03 O.OOE+OO 6.49E-05 O.OOE+OO 2.50E-04 O.OOE+OO 5.83E-05 NP-237 1.33E-03 9.55E-05 5.85E-05 O.OOE+OO 4.33E-04 O.OOE+OO 8.41E-05 NP-238 1.95E-08 5.22E-10 3.04E-10 O.OOE+OO 1.79E-09 O.OOE+OO 3.83E-05 PU-238 6.?0E-04 8.58E-05 1.82E-05 O.OOE+OO 7.BOE-05 O.OOE+OO 7.73E-05 PU-239 7.65E-04 9.29E-05 2.01E-05 O.OOE+OO 8.57E-05 O.OOE+OO 7.06E-05 PU-240 7.64E-04 9.27E-05 2.01E-05 O.OOE+OO 8.56E-05 O.OOE+OO 7.19E-05 PU-241 1.75E-05 8.40E-07 3.69E-07 O.OOE+OO 1.71E-06 O.OOE+OO 1.48E-06 PU-242 7.09E-04 8.94E-05 1.94E-05 O.OOE+OO 8.25E-05 O.OOE+OO 6.92E-05 PU-244 8.28E-04 1.02E-04 2.22E-05 O.OOE+OO 9.45E-05 O.OOE+OO 1.03E-04 AM-241 7.98E-04 7.53E-04 5.75E-05 O.OOE+OO 4.31E-04 O.OOE+OO 7.87E-05 AM-242M 8.0?E-04 7.11E-04 5.BOE-05 O.OOE+OO 4.30E-04 O.OOE+OO 9.90E-05 AM-243 7.96E-04 7.35E-04 5.62E-05 O.OOE+OO 4.22E-04 O.OOE+OO 9.23E-05 CM-242 2.94E-05 3.10E-05 1.95E-06 O.OOE+OO 8.89E-06 O.OOE+OO 8.40E-05 CM-243 6.50E-04 6.03E-04 4.09E-05 O.OOE+OO 1.91E-04 O.OOE+OO 8.28E-05 CM-244 5.04E-04 4.77E-04 3.19E-05 O.OOE+OO 1.49E-04 O.OOE+OO 8.00E-05 CM-245 9.90E-04 8.71E-04 6.10E-05 O.OOE+OO 2.85E-04 O.OOE+OO 7.46E-05 CM-246 9.82E-04 8.?0E-04 6.09E-05 O.OOE+OO 2.84E-04 O.OOE+OO 7.33E-05 CM-247 9.57E-04 8.57E-04 6.00E-05 O.OOE+OO 2.80E-04 O.OOE+OO 9.63E-05 CM-248 7.95E-03 7.06E-03 4.95E-04 O.OOE+OO 2.31E-03 O.OOE+OO 1.55E-03 CF-252 3.47E-04 O.OOE+OO 8.37E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.05E-04 CY-TM-170-300 Revision 5 Page 117 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 9 of 16 INGESTION DOSE FACTORS FOR CHILD (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14(inorg) 1.21 E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA-22 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 NA-24 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 P-32 8.25E-04 3.86E-05 3.18E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.28E-05 CA-41 3.47E-04 O.OOE+OO 3.79E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.90E-07 SC-46 1.97E-08 2.70E-08 1.04E-08 O.OOE+OO 2.39E-08 O.OOE+OO 3.95E-05 CR-51 O.OOE+OO O.OOE+OO 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN-54 O.OOE+OO 1.07E-05 2.85E-06 O.OOE+OO 3.00E-06 O.OOE+OO 8.98E-06 FE-55 1.15E-05 6.10E-06 1.89E-06 O.OOE+OO O.OOE+OO 3.45E-06 1.13E-06 MN-56 O.OOE+OO 3.34E-07 7.54E-08 O.OOE+OO 4.04E-07 O.OOE+OO 4.84E-05 C0-57 O.OOE+OO 4.93E-07 9.98E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.04E-06 C0-58 O.OOE+OO 1.BOE-06 5.51E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.0SE-05 FE-59 1.65E-05 2.67E-05 1.33E-05 O.OOE+OO O.OOE+OO 7.74E-06 2.78E-05 C0-60 O.OOE+OO 5.29E-06 1.56E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.93E-05 Nl-59 4.02E-05 1.07E-05 6.82E-06 O.OOE+OO O.OOE+OO O.OOE+OO 7.10E-07 Nl-63 5.38E-04 2.88E-05 1.83E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E-06 CU-64 O.OOE+OO 2.45E-07 1.48E-07 O.OOE+OO 5.92E-07 O.OOE+OO 1.15E-05 Nl-65 2.22E-06 2.09E-07 1.22E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.56E-05 ZN-65 1.37E-05 3.65E-05 2.27E-05 O.OOE+OO 2.30E-05 O.OOE+OO 6.41 E-06 ZN-69M 7.10E-07 1.21 E-06 1.43E-07 O.OOE+OO 7.03E-07 O.OOE+OO 3.94E-05 ZN-69 4.38E-08 6.33E-08 5.85E-09 O.OOE+OO 3.84E-08 O.OOE+OO 3.99E-06 SE-79 O.OOE+OO 8.43E-06 1.87E-06 O.OOE+OO 1.37E-05 O.OOE+OO 5.53E-07 BR-82 O.OOE+OO O.OOE+OO 7.55E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-83 O.OOE+OO O.OOE+OO 1.71 E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-84 O.OOE+OO O.OOE+OO 1.98E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 9.12E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 6.70E-05 4.12E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.31E-06 RB-87 O.OOE+OO 3.95E-05 1.83E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.92E-07 RB-88 O.OOE+OO 1.90E-07 1.32E-07 O.OOE+OO O.OOE+OO O.OOE+OO 9.32E-09 RB-89 O.OOE+OO 1.17E-07 1.04E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E-09 SR-89 1.32E-03 O.OOE+OO 3.77E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.11E-05 SR-90 1.70E-02 O.OOE+OO 4.31E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-04 Y-90 4.11E-08 O.OOE+OO 1.10E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E-04 SR-91 2.40E-05 O.OOE+OO 9.06E-07 O.OOE+OO O.OOE+OO O.OOE+OO 5.30E-05 Y-91M 3.82E-10 O.OOE+OO 1.39E-11 O.OOE+OO O.OOE+OO O.OOE+OO 7.48E-07 Y-91 6.02E-07 O.OOE+OO 1.61 E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.02E-05 SR-92 9.03E-06 O.OOE+OO 3.62E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.71 E-04 Y-92 3.60E-09 O.OOE+OO 1.03E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E-04 Y-93 1.14E-08 O.OOE+OO 3.13E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.70E-04 NB-93M 1.0SE-07 2.62E-08 8.61E-09 O.OOE+OO 2.83E-08 O.OOE+OO 3.95E-06 NB-95 2.25E-08 8.76E-09 6.26E-09 O.OOE+OO 8.23E-09 O.OOE+OO 1.62E-05 CY-TM-170-300 Revision 5 Page 118 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 10 of 16 INGESTION DOSE FACTORS FOR CHILD (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI NB-97 2.17E-10 3.92E-11 1.83E-11 O.OOE+OO 4.35E-11 O.OOE+OO 1.21 E-05 ZR-93 1.67E-07 6.25E-09 4.45E-09 O.OOE+OO 2.42E-08 O.OOE+OO 2.37E-06 ZR-95 1.16E-07 2.55E-08 2.27E-08 O.OOE+OO 3.65E-08 O.OOE+OO 2.66E-05 ZR-97 6.99E-09 1.01 E-09 5.96E-10 O.OOE+OO 1.45E-09 O.OOE+OO 1.53E-04 M0-93 O.OOE+OO 2.41E-05 8.65E-07 O.OOE+OO 6.35E-06 O.OOE+OO 1.22E-06 M0-99 O.OOE+OO 1.33E-05 3.29E-06 O.OOE+OO 2.84E-05 O.OOE+OO 1.10E-05 TC-99 5.35E-07 5.96E-07 2.14E-07 O.OOE+OO 7.02E-06 5.27E-08 6.25E-06 TC-99M 9.23E-10 1.81 E-09 3.00E-08 O.OOE+OO 2.63E-08 9.19E-10 1.03E-06 TC-101 1.0?E-09 1.12E-09 1.42E-08 O.OOE+OO 1.91 E-08 5.92E-10 3.56E-09 RU-103 7.31E-07 O.OOE+OO 2.81E-07 O.OOE+OO 1.84E-06 O.OOE+OO 1.89E-05 RU-105 6.45E-08 O.OOE+OO 2.34E-08 O.OOE+OO 5.67E-07 O.OOE+OO 4.21E-05 RU-106 1.17E-05 O.OOE+OO 1.46E-06 O.OOE+OO 1.58E-05 O.OOE+OO 1.82E-04 RH-105 5.14E-07 2.76E-07 2.36E-07 O.OOE+OO 1.10E-06 O.OOE+OO 1.71E-05 PD-107 O.OOE+OO 4.72E-07 4.01E-08 O.OOE+OO 3.95E-06 O.OOE+OO 9.37E-07 PD-109 O.OOE+OO 5.67E-07 1.?0E-07 O.OOE+OO 3.04E-06 O.OOE+OO 3.35E-05 AG-110M 5.39E-07 3.64E-07 2.91E-07 O.OOE+OO 6.78E-07 O.OOE+OO 4.33E-05 AG-111 2.48E-07 7.76E-08 5.12E-08 O.OOE+OO 2.34E-07 O.OOE+OO 4.75E-05 CD-113M O.OOE+OO 1.02E-05 4.34E-07 O.OOE+OO 1.0SE-05 O.OOE+OO 2.63E-05 CD-115M O.OOE+OO 5.89E-06 2.51E-07 O.OOE+OO 4.38E-06 O.OOE+OO 8.01E-05 SN-123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 O.OOE+OO O.OOE+OO 6.52E-05 SN-125 3.55E-05 5.35E-07 1.59E-06 5.55E-07 O.OOE+OO O.OOE+OO 1.10E-04 SN-126 3.33E-04 4.15E-06 9.46E-06 1.14E-06 O.OOE+OO O.OOE+OO 2.SOE-05 SB-124 1.11 E-05 1.44E-07 3.89E-06 2.45E-08 O.OOE+OO 6.16E-06 6.94E-05 SB-125 7.16E-06 5.52E-08 1.SOE-06 6.63E-09 O.OOE+OO 3.99E-06 1.71 E-05 SB-126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 O.OOE+OO 2.10E-06 8.87E-05 SB-127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 O.OOE+OO 4.60E-07 5.97E-05 TE-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 O.OOE+OO O.OOE+OO 1.10E-05 TE-127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 O.OOE+OO 2.34E-05 TE-127 4.71E-07 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 O.OOE+OO 1.84E-05 TE-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 O.OOE+OO 5.94E-05 TE-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 O.OOE+OO 8.34E-06 TE-133M 1.87E-07 7.56E-08 9.37E-08 1.45E-07 7.18E-07 O.OOE+OO 5.77E-06 TE-134 1.29E-07 5.BOE-08 7.74E-08 1.02E-07 5.37E-07 O.OOE+OO 5.89E-07 1-129 1.39E-05 8.53E-06 7.62E-06 5.58E-03 1.44E-05 O.OOE+OO 4.29E-07 1-130 2.92E-06 5.90E-06 3.04E-06 6.SOE-04 8.82E-06 O.OOE+OO 2.76E-06 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 O.OOE+OO 1.54E-06 TE-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 O.OOE+OO 1.01 E-04 TE-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 O.OOE+OO 4.36E-07 1-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 O.OOE+OO 1.73E-06 TE-132 1.01 E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 O.OOE+OO 4.SOE-05 CY-TM-170-300 Revision 5 Page 119 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 11 of 16 INGESTION DOSE FACTORS FOR CHILD (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LU 1-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 O.OOE+OO 2.95E-06 CS-134M 8.44E-08 1.25E-07 8.16E-08 O.OOE+OO 6.59E-08 1.09E-08 1.58E-07 CS-134 2.34E-04 3.84E-04 8.10E-05 O.OOE+OO 1.19E-04 4.27E-05 2.0?E-06 1-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 O.OOE+OO 5.16E-07 1-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 O.OOE+OO 2.40E-06 CS-135 8.30E-05 5.78E-05 5.93E-06 O.OOE+OO 2.04E-05 6.81E-06 4.33E-07 CS-136 2.35E-05 6.46E-05 4.18E-05 O.OOE+OO 3.44E-05 5.13E-06 2.27E-06 CS-137 3.27E-04 3.13E-04 4.62E-05 O.OOE+OO 1.02E-04 3.67E-05 1.96E-06 CS-138 2.28E-07 3.17E-07 2.01E-07 O.OOE+OO 2.23E-07 2.40E-08 1.46E-07 CS-139 1.45E-07 1.61 E-07 7.74E-08 O.OOE+OO 1.21E-07 1.22E-08 1.45E-11 BA-139 4.14E-07 2.21E-10 1.20E-08 O.OOE+OO 1.93E-10 1.30E-10 2.39E-05 BA-140 8.31E-05 7.28E-08 4.85E-06 O.OOE+OO 2.37E-08 4.34E-08 4.21 E-05 LA-140 1.01 E-08 3.53E-09 1.19E-09 O.OOE+OO O.OOE+OO O.OOE+OO 9.84E-05 BA-141 2.00E-07 1.12E-10 6.51E-09 O.OOE+OO 9.69E-11 6.58E-10 1.14E-07 LA-141 1.36E-09 3.17E-10 6.88E-11 O.OOE+OO O.OOE+OO O.OOE+OO 7.05E-05 CE-141 3.97E-08 1.98E-08 2.94E-09 O.OOE+OO 8.68E-09 O.OOE+OO 2.47E-05 BA-142 8.74E-08 6.29E-11 4.88E-09 O.OOE+OO 5.09E-11 3.?0E-11 1.14E-09 LA-142 5.24E-10 1.67E-10 5.23E-11 O.OOE+OO O.OOE+OO O.OOE+OO 3.31E-05 CE-143 6.99E-09 3.79E-06 5.49E-10 O.OOE+OO 1.59E-09 O.OOE+OO 5.55E-05 PR-143 3.93E-08 1.18E-08 1.95E-09 O.OOE+OO 6.39E-09 O.OOE+OO 4.24E-05 CE-144 2.0BE-06 6.52E-07 1.11 E-07 O.OOE+OO 3.61E-07 O.OOE+OO 1.?0E-04 PR-144 1.29E-10 3.99E-11 6.49E-12 O.OOE+OO 2.11E-11 O.OOE+OO 8.59E-08 ND-147 2.79E-08 2.26E-08 1.75E-09 O.OOE+OO 1.24E-08 O.OOE+OO 3.58E-05 PM-147 3.18E-07 2.27E-08 1.22E-08 O.OOE+OO 4.01E-08 O.OOE+OO 9.19E-06 PM-148M 1.03E-07 2.05E-08 2.05E-08 O.OOE+OO 3.04E-08 O.OOE+OO 5.78E-05 PM-148 3.02E-08 3.63E-09 2.35E-09 O.OOE+OO 6.17E-09 O.OOE+OO 9.?0E-05 PM-149 6.49E-09 6.90E-10 3.74E-10 O.OOE+OO 1.22E-09 O.OOE+OO 4.71 E-05 PM-151 2.92E-09 3.55E-10 2.31E-10 O.OOE+OO 6.02E-10 O.OOE+OO 4.03E-05 SM-151 2.56E-07 3.81E-08 1.20E-08 O.OOE+OO 3.94E-08 O.OOE+OO 5.53E-06 SM-153 3.65E-09 2.27E-09 2.19E-10 O.OOE+OO 6.91E-10 O.OOE+OO 3.02E-05 EU-152 6.15E-07 1.12E-07 1.33E-07 O.OOE+OO 4.73E-07 O.OOE+OO 1.84E-05 EU-154 2.30E-06 2.0?E-07 1.89E-07 O.OOE+OO 9.09E-07 O.OOE+OO 4.81E-05 EU-155 4.82E-07 3.47E-08 2.72E-08 O.OOE+OO 1.30E-07 O.OOE+OO 8.69E-05 EU-156 5.62E-08 3.01E-08 6.23E-09 O.OOE+OO 1.94E-08 O.OOE+OO 6.83E-05 TB-160 1.66E-07 O.OOE+OO 2.06E-08 O.OOE+OO 4.94E-08 O.OOE+OO 3.68E-05 H0-166M 1.0BE-06 2.26E-07 1.91 E-07 O.OOE+OO 3.22E-07 O.OOE+OO 2.63E-05 W-181 4.23E-08 1.04E-08 1.43E-09 O.OOE+OO O.OOE+OO O.OOE+OO 3.79E-07 W-185 1.73E-06 4.32E-07 6.05E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.61 E-05 W-187 4.29E-07 2.54E-07 1.14E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.57E-05 NP-239 5.25E-09 3.77E-10 2.65E-10 O.OOE+OO 1.09E-09 O.OOE+OO 2.79E-05 U-232 1.76E-02 O.OOE+OO 1.26E-03 O.OOE+OO 1.34E-03 O.OOE+OO 6.98E-05 U-233 3.72E-03 O.OOE+OO 2.25E-04 O.OOE+OO 6.10E-04 O.OOE+OO 6.45E-05 CY-TM-170-300 Revision 5 Page 120 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 12 of 16 INGESTION DOSE FACTORS FOR CHILD (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI U-234 3.57E-03 O.OOE+OO 2.21E-04 O.OOE+OO 5.98E-04 O.OOE+OO 6.32E-05 U-235 3.42E-03 O.OOE+OO 2.0?E-04 O.OOE+OO 5.61E-04 O.OOE+OO 8.03E-05 U-236 3.42E-03 O.OOE+OO 2.12E-04 O.OOE+OO 5.73E-04 O.OOE+OO 5.92E-05 U-237 2.36E-07 O.OOE+OO 6.27E-08 O.OOE+OO 6.81E-07 O.OOE+OO 2.0BE-05 U-238 3.27E-03 O.OOE+OO 1.94E-04 O.OOE+OO 5.24E-04 O.OOE+OO 5.66E-05 NP-237 2.23E-03 1.47E-04 9.79E-05 O.OOE+OO 6.05E-04 O.OOE+OO 8.16E-05 NP-238 5.83E-08 1.18E-09 9.0BE-10 O.OOE+OO 3.76E-09 0.00E+OO 4.04E-05 PU-238 1.19E-03 1.38E-04 3.16E-05 O.OOE+OO 1.15E-04 O.OOE+OO 7.50E-05 PU-239 1.29E-03 1.38E-04 3.31E-05 O.OOE+OO 1.22E-04 O.OOE+OO 6.85E-05 PU-240 1.28E-03 1.43E-04 3.31E-05 O.OOE+OO 1.22E-04 O.OOE+OO 6.98E-05 PU-241 3.87E-05 1.58E-06 8.04E-07 O.OOE+OO 2.96E-06 O.OOE+OO 1.44E-06 PU-242 1.19E-03 1.38E-04 3.19E-05 O.OOE+OO 1.17E-04 O.OOE+OO 6.71E-05 PU-244 1.39E-03 1.58E-03 3.65E-05 O.OOE+OO 1.35E-04 O.OOE+OO 1.00E-04 AM-241 1.36E-03 1.17E-03 1.02E-04 O.OOE+OO 6.23E-04 O.OOE+OO 7.64E-05 AM-242M 1.40E-03 1.12E-03 1.04E-04 O.OOE+OO 6.30E-04 O.OOE+OO 9.61E-05 AM-243 1.34E-03 1.13E-03 9.83E-05 O.OOE+OO 6.06E-04 O.OOE+OO 8.95E-05 CM-242 8.78E-05 7.01E-05 5.84E-06 O.OOE+OO 1.87E-05 O.OOE+OO 8.16E-05 CM-243 1.28E-03 1.04E-03 8.24E-05 O.OOE+OO 3.0BE-04 O.OOE+OO 8.03E-05 CM-244 1.0BE-03 8.74E-04 6.93E-05 O.OOE+OO 2.54E-04 O.OOE+OO 7.77E-05 CM-245 1.67E-03 1.34E-03 1.05E-04 O.OOE+OO 4.11E-04 O.OOE+OO 7.24E-05 CM-246 1.65E-03 1.34E-03 1.05E-04 O.OOE+OO 4.10E-04 O.OOE+OO 7.11 E-05 CM-247 1.61E-03 1.32E-03 1.03E-04 O.OOE+OO 4.04E-04 O.OOE+OO 9.35E-05 CM-248 1.34E-02 1.09E-02 8.52E-04 O.OOE+OO 3.33E-03 O.OOE+OO 1.51 E-03 CF-252 1.05E-03 O.OOE+OO 2.54E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.96E-04 CY-TM-170-300 Revision 5 Page 121 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 13 of 16 INGESTION DOSE FACTORS FOR INFANT (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 3.0BE-07 3.0BE-07 3.0BE-07 3.0BE-07 3.0BE-07 3.08E-07 C-14(inorg) 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA-22 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 NA-24 1.01 E-05 1.01 E-05 1.01 E-05 1.01E-05 1.01 E-05 1.01E-05 1.01 E-05 P-32 1.70E-03 1.00E-04 6.59E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.30E-05 CA-41 3.74E-04 O.OOE+OO 4.0BE-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.91 E-07 SC-46 3.75E-08 5.41E-08 1.69E-08 O.OOE+OO 3.56E-08 O.OOE+OO 3.53E-05 CR-51 O.OOE+OO O.OOE+OO 1.41 E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN-54 O.OOE+OO 1.99E-05 4.51E-06 O.OOE+OO 4.41E-06 O.OOE+OO 7.31E-06 FE-55 1.39E-05 8.98E-06 2.40E-06 0.00E+OO O.OOE+OO 4.39E-06 1.14E-06 MN-56 O.OOE+OO 8.18E-07 1.41 E-07 O.OOE+OO 7.03E-07 O.OOE+OO 7.43E-05 C0-57 O.OOE+OO 1.15E-06 1.87E-06 O.OOE+OO O.OOE+OO O.OOE+OO .3.92E-06 C0-58 O.OOE+OO 3.60E-06 8.98E-06 O.OOE+OO O.OOE+OO O.OOE+OO 8.97E-06 FE-59 3.08E-05 5.38E-05 2.12E-05 O.OOE+OO O.OOE+OO 1.59E-05 2.57E-05 C0-60 O.OOE+OO 1.08E-05 2.55E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.57E-05 Nl-59 4.73E-05 1.45E-05 8.17E-06 O.OOE+OO O.OOE+OO O.OOE+OO 7.16E-07 Nl-63 6.34E-04 3.92E-05 2.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.95E-06 CU-64 O.OOE+OO 6.09E-07 2.82E-07 O.OOE+OO 1.03E-06 O.OOE+OO 1.25E-05 Nl-65 4.70E-06 5.32E-07 2.42E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.05E-05 ZN-65 1.84E-05 6.31E-05 2.91E-05 O.OOE+OO 3.06E-05 O.OOE+OO 5.33E-05 ZN-69M 1.50E-06 3.06E-06 2.79E-07 O.OOE+OO 1.24E-06 O.OOE+OO 4.24E-05 ZN-69 9.33E-08 1.68E-07 1.25E-08 O.OOE+OO 6.98E-08 O.OOE+OO 1.37E-05 SE-79 O.OOE+OO 2.10E-05 3.90E-06 O.OOE+OO 2.43E-05 O.OOE+OO 5.58E-07 BR-82 O.OOE+OO O.OOE+OO 1.27E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-83 O.OOE+OO O.OOE+OO 3.63E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-84 O.OOE+OO O.OOE+OO 3.82E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 1.94E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 1.70E-04 8.40E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.35E-06 RB-87 O.OOE+OO 8.88E-05 3.52E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.98E-07 RB-88 O.OOE+OO 4.98E-07 2.73E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.85E-07 RB-89 O.OOE+OO 2.86E-07 1.97E-07 O.OOE+OO O.OOE+OO O.OOE+OO 9.74E-08 SR-89 2.51E-03 O.OOE+OO 7.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.16E-05 SR-90 1.85E-02 O.OOE+OO 4.71 E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.31 E-04 Y-90 8.69E-08 O.OOE+OO 2.33E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.20E-04 SR-91 5.00E-05 O.OOE+OO 1.81E-06 O.OOE+OO O.OOE+OO O.OOE+OO 5.92E-05 Y-91M 8.10E-10 O.OOE+OO 2.76E-11 O.OOE+OO O.OOE+OO O.OOE+OO 2.70E-06 Y-91 1.13E-06 O.OOE+OO 3.01E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.10E-05 SR-92 1.92E-05 O.OOE+OO 7.13E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.07E-04 Y-92 7.65E-09 O.OOE+OO 2.15E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.46E-04 Y-93 2.43E-08 O.OOE+OO 6.62E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.92E-04 NB-93M 1.23E-07 3.33E-08 1.04E-08 O.OOE+OO 3.25E-08 O.OOE+OO 3.98E-06 CY-TM-170-300 Revision 5 Page 122 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 14 of 16 INGESTION DOSE FACTORS FOR INFANT (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI NB-95 4.20E-08 1.73E-08 1.00E-08 O.OOE+OO 1.24E-08 O.OOE+OO 1.46E-05 NB-97 4.59E-10 9.79E-11 3.53E-11 O.OOE+OO 7.65E-11 O.OOE+OO 3.09E-05 ZR-93 1.93E-07 9.19E-09 5.54E-09 O.OOE+OO 2.71E-08 O.OOE+OO 2.39E-06 ZR-95 2.06E-07 5.02E-08 3.56E-08 O.OOE+OO 5.41E-08 O.OOE+OO 2.50E-05 ZR-97 1.48E-08 2.54E-09 1.16E-09 O.OOE+OO 2.56E-09 O.OOE+OO 1.62E-04 M0-93 O.OOE+OO 5.65E-05 1.82E-06 O.OOE+OO 1.13E-05 O.OOE+OO 1.21 E-06 M0-99 O.OOE+OO 3.40E-05 6.63E-06 O.OOE+OO 5.08E-05 O.OOE+OO 1.12E-05 TC-99 1.08E-06 1.46E-06 4.55E-07 O.OOE+OO 1.23E-05 1.42E-07 6.31E-06 TC-99M 1.92E-09 3.96E-09 5.10E-08 O.OOE+OO 4.26E-08 2.07E-09 1.15E-06 TC-101 2.27E-09 2.86E-09 2.83E-08 O.OOE+OO 3.40E-08 1.56E-09 4.86E-07 RU-103 1.48E-06 O.OOE+OO 4.95E-07 O.OOE+OO 3.08E-06 O.OOE+OO 1.80E-05 RU-105 1.36E-07 O.OOE+OO 4.58E-08 O.OOE+OO 1.00E-06 O.OOE+OO 5.41 E-05 RU-106 2.41E-05 O.OOE+OO 3.01E-06 O.OOE+OO 2.85E-05 O.OOE+OO 1.83E-04 RH-105 1.09E-06 7.13E-07 4.79E-07 O.OOE+OO 1.98E-06 O.OOE+OO 1.77E-05 PD-107 O.OOE+OO 1.19E-06 8.45E-08 O.OOE+Ob 6.79E-06 O.OOE+OO 9.46E-07 PD-109 O.OOE+OO 1.50E-06 3.62E-07 O.OOE+OO 5.51E-06 O.OOE+OO 3.68E-05 AG-110M 9.96E-07 7.27E-07 4.81E-07 O.OOE+OO 1.04E-06 O.OOE+OO 3.77E-05 AG-111 5.20E-07 2.02E-07 1.07E-07 O.OOE+OO 4.22E-07 O.OOE+OO 4.82E-05 CD-113M O.OOE+OO 1.77E-05 6.52E-07 O.OOE+OO 1.34E-05 O.OOE+OO 2.66E-05 CD-115M O.OOE+OO 1.42E-05 4.93E-07 O.OOE+OO 7.41E-06 O.OOE+OO 8.09E-05 SN-123 2.49E-04 3.89E-06 6.50E-06 3.91E-06 O.OOE+OO O.OOE+OO 6.58E-05 SN-125 7.41E-05 1.38E-06 3.29E-06 1.36E-06 O.OOE+OO O.OOE+OO 1.11E-04 SN-126 5.53E-04 7.26E-06 1.80E-05 1.91 E-06 O.OOE+OO O.OOE+OO 2.52E-05 SB-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 O.OOE+OO 1.34E-05 6.60E-05 SB-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 O.OOE+OO 7.12E-06 1.64E-05 SB-126 8.06E-06 1.58E-07 2.91E-06 6.19E-08 O.OOE+OO 5.07E-06 8.35E-05 SB-127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 O.OOE+OO 1.15E-06 5.91E-05 TE-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 . O.OOE+OO O.OOE+OO 1.11 E-05 TE-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+OO 2.36E-05 TE-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 O.OOE+OO 2.10E-05 TE-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 O.OOE+OO 5.97E-05 TE-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 O.OOE+OO 2.27E-05 TE-133M 3.91E-07 1.79E-07 1.71E-07 3.45E-07 1.22E-06 O.OOE+OO 1.93E-05 TE-134 2.67E-07 1.34E-07 1.38E-07 2.39E-07 9.03E-07 O.OOE+OO 3.06E-06 1-129 2.86E-05 2.12E-05 1.55E-05 1.36E-02 2.51E-05 O.OOE+OO 4.24E-07 1-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 O.OOE+OO 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 O.OOE+OO 1.51E-06 TE-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 O.OOE+OO 1.03E-04 TE-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 O.OOE+OO 7.11 E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+OO 2.73E-06 TE-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 O.OOE+OO 3.81E-05 CY-TM-170-300 Revision 5 Page 123 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 15 of 16 INGESTION DOSE FACTORS FOR INFANT (mrem per pCi ingested) Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI 1-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 O.OOE+OO 3.08E-06 CS-134M 1.76E-07 2.93E-07 1.48E-07 O.OOE+OO 1.13E-07 2.60E-08 2.32E-07 CS-134 3.77E-04 7.03E-04 7.10E-05 O.OOE+OO 1.81 E-04 7.42E-05 1.91 E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+OO 1.84E-06 1-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+OO 2.62E-06 CS-135 1.33E-04 1.21 E-04 6.30E-06 O.OOE+OO 3.44E-05 1.31 E-05 4.37E-07 CS-136 4.59E-05 1.35E-04 5.04E-05 O.OOE+OO 5.38E-05 1.10E-05 2.0SE-06 CS-137 5.22E-04 6.11E-04 4.33E-05 O.OOE+OO 1.64E-04 6.64E-05 1.91 E-06 CS-138 4.81 E-07 7.82E-07 3.79E-07 O.OOE+OO 3.90E-07 6.09E-08 1.25E-06 CS-139 3.10E-07 4.24E-07 1.62E-07 O.OOE+OO 2.19E-07 3.30E-08 2.66E-08 BA-139 8.81E-07 5.84E-10 2.55E-08 O.OOE+OO 3.51E-10 3.54E-10 5.58E-05 BA-140 1.71E-04 1.71 E-07 8.81E-06 O.OOE+OO 4.06E-08 1.0SE-07 4.20E-05 LA-140 2.11 E-08 8.32E-09 2.14E-09 O.OOE+OO O.OOE+OO O.OOE+OO 9.77E-05 BA-141 4.25E-07 2.91E-10 1.34E-08 O.OOE+OO 1.75E-10 1.77E-10 5.19E-06 LA-141 2.89E-09 8.38E-10 1.46E-10 O.OOE+OO O.OOE+OO O.OOE+OO 9.61E-05 CE-141 7.87E-08 4.80E-08 5.65E-09 O.OOE+OO 1.48E-08 O.OOE+OO 2.48E-05 BA-142 1.84E-07 1.53E-10 9.06E-09 O.OOE+OO 8.81E-11 9.26E-11 7.59E-07 LA-142 1.1 OE-09 4.04E-10 9.67E-11 O.OOE+OO O.OOE+OO O.OOE+OO 6.86E-05 CE-143 1.48E-08 9.82E-06 1.12E-09 O.OOE+OO 2.86E-09 O.OOE+OO 5.73E-05 PR-143 8.13E-08 3.04E-08 4.03E-09 O.OOE+OO 1.13E-08 O.OOE+OO 4.29E-05 CE-144 2.98E-06 1.22E-06 1.67E-07 O.OOE+OO 4.93E-07 O.OOE+OO 1.71 E-04 PR-144 2.74E-10 1.06E-10 1.38E-11 O.OOE+OO 3.84E-11 O.OOE+OO 4.93E-06 ND-147 5.53E-08 5.68E-08 3.48E-09 O.OOE+OO 2.19E-08 O.OOE+OO 3.60E-05 PM-147 3.88E-07 3.27E-08 1.59E-08 O.OOE+OO 4.88E-08 O.OOE+OO 9.27E-06 PM-148M 1.65E-07 4.18E-08 3.28E-08 O.OOE+OO 4.80E-08 O.OOE+OO 5.44E-05 PM-148 6.32E-08 9.13E-09 4.60E-09 O.OOE+OO 1.09E-08 O.OOE+OO 9.74E-05 PM-149 1.38E-08 1.81 E-09 7.90E-10 O.OOE+OO 2.20E-09 O.OOE+OO 4.86E-05 PM-151 6.18E-09 9.01E-10 4.56E-10 O.OOE+OO 1.07E-09 O.OOE+OO 4.17E-05 SM-151 2.90E-07 6.67E-08 1.44E-08 O.OOE+OO 4.53E-08 O.OOE+OO 5.58E-06 SM-153 7.72E-09 5.97E-09 4.58E-10 O.OOE+OO 1.25E-09 O.OOE+OO 3.12E-05 EU-152 6.74E-07 1.79E-07 1.51 E-07 O.OOE+OO 5.02E-07 O.OOE+OO 1.59E-05 EU-154 2.64E-06 3.67E-07 2.20E-07 O.OOE+OO 9.95E-07 O.OOE+OO 4.58E-05 EU-155 5.42E-07 6.25E-08 3.23E-08 O.OOE+OO 1.40E-07 O.OOE+OO 8.37E-05 EU-156 1.14E-07 7.06E-08 1.12E-08 O.OOE+OO 3.26E-08 O.OOE+OO 6.67E-05 TB-160 2.59E-07 O.OOE+OO 3.24E-08 O.OOE+OO 7.37E-08 O.OOE+OO 3.45E-05 H0-166M 1.25E-06 2.69E-07 2.13E-07 O.OOE+OO 3.57E-07 O.OOE+OO 2.66E-05 W-181 8.85E-08 2.72E-08 3.04E-09 O.OOE+OO O.OOE+OO O.OOE+OO 3.82E-07 W-185 3.62E-06 1.13E-06 1.29E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.62E-05 W-187 9.03E-07 6.28E-07 2.17E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.69E-05 NP-239 1.11 E-08 9.93E-10 5.61E-10 O.OOE+OO 1.98E-09 O.OOE+OO 2.87E-05 U-232 2.42E-02 O.OOE+OO 2.16E-03 O.OOE+OO 2.37E-03 O.OOE+OO 7.04E-05 U-233 5.08E-03 O.OOE+OO 3.87E-04 O.OOE+OO 1.08E-03 O.OOE+OO 6.51E-05 CY-TM-170-300 Revision 5 Page 124 of 222 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFii Page 16 of 16 INGESTION DOSE FACTORS FOR INFANT (mrem per pCi ingested) Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI U-234 4.88E-03 O.OOE+OO 3.80E-04 O.OOE+OO 1.06E-03 O.OOE+OO 6.37E-05 U-235 4.67E-03 O.OOE+OO 3.56E-04 O.OOE+OO 9.93E-04 O.OOE+OO 8.10E-05 U-236 4.67E-03 O.OOE+OO 3.64E-04 O.OOE+OO 1.01 E-03 O.OOE+OO 5.98E-05 U-237 4.95E-07 O.OOE+OO 1.32E-07 O.OOE+OO 1.23E-06 O.OOE+OO 2.11E-05 U-238 4.47E-03 O.OOE+OO 3.33E-04 O.OOE+OO 9.28E-04 O.OOE+OO 5.71E-05 NP-237 2.40E-03 1.59E-04 1.0SE-04 O.OOE+OO 6.34E-04 O.OOE+OO 8.23E-05 NP-238 1.24E-07 3.12E-09 1.92E-09 O.OOE+OO 6.81E-09 O.OOE+OO 4.17E-05 PU-238 1.28E-03 1.SOE-04 3.40E-05 O.OOE+OO 1.21E-04 O.OOE+OO 7.57E-05 PU-239 1.38E-03 1.SSE-04 3.54E-05 O.OOE+OO 1.28E-04 O.OOE+OO 6.91E-05 PU-240 1.38E-03 1.SSE-04 3.54E-05 O.OOE+OO 1.28E-04 O.OOE+OO 7.04E-05 PU-241 4.25E-05 1.76E-06 8.82E-07 O.OOE+OO 3.17E-06 O.OOE+OO 1.45E-06 PU-242 1.28E-03 1.49E-04 3.41E-05 O.OOE+OO 1.23E-04 O.OOE+OO 6.77E-05 PU-244 1.49E-03 1.71E-04 3.91E-05 O.OOE+OO 1.41E-04 O.OOE+OO 1.01 E-04 AM-241 1.46E-03 1.27E-03 1.09E-04 O.OOE+OO 6.SSE-04 O.OOE+OO 7.?0E-05 AM-242M 1.51 E-03 1.22E-03 1".13E-04 O.OOE+OO 6.64E-04 O.OOE+OO 9.69E-05 AM-243 1.44E-03 1.23E-03 1.06E-04 O.OOE+OO 6.36E-04 O.OOE+OO 9.03E-05 CM-242 1.37E-04 1.27E-04 9.10E-06 O.OOE+OO 2.62E-05 O.OOE+OO 8.23E-05 CM-243 1.40E-03 1.15E-03 8.98E-05 O.OOE+OO 3.27E-04 O.OOE+OO 8.10E-05 CM-244 1.18E-03 9.?0E-04 7.59E-05 0.00E+OO 2.71E-04 O.OOE+OO 7.84E-05 CM-245 1.79E-03 1.45E-03 1.13E-04 O.OOE+OO 4.32E-04 O.OOE+OO 7.30E-05 CM-246 1.77E-03 1.45E-03 1.13E-04 O.OOE+OO 4.31 E-04 O.OOE+OO 7.17E-05 CM-247 1.73E-03 1.43E-03 1.11E-04 O.OOE+OO 4.24E-04 O.OOE+OO 9.43E-05 CM-248 1.43E-02 1.18E-02 9.16E-04 O.OOE+OO 3.SOE-03 O.OOE+OO 1.52E-03 CF-252 1.22E-03 O.OOE+OO 2.95E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.99E-04

• ** TABLE 2.2 Bioaccumulation

Factors, BFi CY-TM-170-300 Revision 5 Page 125 of 222 Bioaccumulation Factors to be Used in the Absence of Site-Specific Data* (pCi/kg per pCi/liter)

FRESHWATER ELEMENT FISH INVERTEBRATE H 9.0E-01 9.0E-01 C 4.6E+03 9.1 E+03 NA 1.0E+02 2.0E+02 CR 2.0E+02 2.0E+03 MN 4.0E+02 9.0E+04 FE 1.0E+02 3.2E+03 co 5.0E+01 2.0E+02 NI 1.0E+02 1.0E+02 cu 5.0E+01 4.0E+02 ZN 2.0E+03 1.0E+04 BR 4.2E+02 3.3E+02 RB 2.0E+03 1.0E+03 SR 3.0E+01 1.0E+02 y 2.5E+01 1.0E+03 ZR 3.3E+OO 6.7E+OO NB 3.0E+04 1.0E+02 MO 1.0E+01 1.0E+01 TC 1.5E+01 5.0E+OO RU 1.0E+01 3.0E+02 RH 1.0E+01 3.0E+02 **AG-110m 2.3E+OO 7.70E+2 **SB 1.0E+OO 1.0E+01 TE 4.0E+02 6.1E+03 I 1.5E+01 5.0E+OO cs 2.0E+03 1.0E+03 BA 4.0E+OO 2.0E+02 LA 2.5E+01 1.0E+03 CE 1.0E+OO 1.0E+03 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 w 1.2E+03 1.0E+01 NP 1.0E+01 4.0E+02 Bioaccumulation factor values are taken from Reg. Guide 1.109 (Rev. 1 ), Table A-1j. Sb and Ag bioaccumulation factor value is taken from NUREG/CR-4013 LADTAP II Reference Manual. CY-TM-170-300 Revision 5 Page 126 of 222 3.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEM 3.1 TMl-1 Liquid Effluent Waste Treatment System 3.1.1 Description of the Liquid Radioactive Waste Treatment System (see Figure 3.1) Reactor Coolant Train a. Water Sources -(3) Reactor Coolant Bleed Tanks (RCBT) -(1) Reactor Coolant Drain Tank (RCDT) b. Liquid Processing -Reactor Coolant Waste Evaporator -Demineralizers prior to release (see Figure 3.2) c. Liquid Effluent for Release -(2) Waste Evaporator Condensate Storage Tanks -(WECST) d. Dilution -Station Effluent Flow -River Flow Miscellaneous Waste Train a. Water sources: -Auxiliary Building Sump -Reactor Building Sump -Miscellaneous Waste Storage Tank -Laundry Waste Storage Tank -Neutralizer Mixing Tank -Neutralizer Feed Tank -Used Precoat Tank -Borated Water Tank Tunnel Sump -Heat Exchanger Vault Sump -Tendon Access Galley Sump -Spent Fuel Pool Room Sump -TMl-2 Miscellaneous Waste Holdup Tank CY-TM-170-300 Revision 5 Page 127 of 222 b. Liquid Processing -Miscellaneous Waste Evaporator, MWE -Oemineralizers prior to release (see Figure 3.2) c. Liquid Effluent for Release -(2) Waste Evaporator Condensate Storage Tanks-(WECST) d. Dilution -Station Effluent Flow -River Flow 3.2 Operability of the TMl-1 Liquid Effluent Waste Treatment System 3.2.1 The TMl-1 Liquid Waste Treatment System as described in Section 11 of the TMl-1 Final Safety Analysis Report is considered to be operable when one of each of the following pieces of equipment is available to perform its intended function: a) Miscellaneous Waste Evaporator (WDL-Z-1 B) or Reactor Coolant Evaporator (WDL-Z-1A) b) Waste Evaporator Condensate Demineralizer (WDL-K-3 A or B) c) Waste Evaporator Condensate Storage Tank (WDL-T-11 A or B) d) Evaporator Condensate Transfer Pumps (WDL-P-14 A or B) 3.2.2 TMl-1 Representative Sampling Prior to Discharge All liquid releases from the TMl-1 Liquid Waste Treatment System are made through the Waste Evaporator Condensate Storage Tanks. To provide thorough mixing and a representative sample, the contents of the tank are recirculated using one of the Waste Evaporator Condensate Transfer Pumps. 3.3 TMl-2 Liquid Effluent Waste Treatment System

• 3.3.1 Description of the TMl-2 Liquid Radioactive Waste Treatment System The TMl-2 Liquid Radioactive Waste Treatment System has been out of service since the TMl-2 Accident in 1979. TMl-2 Liquid Radioactive Waste is processed by the TMl-1 system described in Section 3.1 prior to release.

In addition, TMl-2 releases water from various sumps and tanks to the river (see Figures 1.1 and 1.2). These processes are governed by plant procedures that encompass proper sampling, sample analysis, and radiation monitoring techniques. FIGURE 3.1 TMl-1 Liquid Radwaste TMl-2 MWHT PRECOAT FILTER ( 1 OF 2) EJ.-.'-----.i BWST SUMP S.F.SUMP TEND. GAL. SUMP CATION DEMIN (1 OF 2) MISC. WASTE EVAP. 8. A. MIX TANK AUX HITTMAN I. .__s_u_1L_D_IN_G _ _,.,.r1------: MDCT EFFLUENT DEMIN WATER RECLAIM WATER STOA TANK RECLAIMED WATER SYSTEM MU-VS E CY-TM-170-300 Revision 5 Page 128 of 222 RC DRAIN MAKE UP RC DRAIN TANK RC WASTE EVAP. RBAT (1 OF 2) PORV SAFETY VALVES MAKE UP TO MU-V9 DISTILLATE COND. DEMIN (1 OF 2) FIGURE 3.2 TMl-1 Liquid Waste Evaporators CCH:ENTRATOR ow ---HfAre:1'"*-:.;:- t,=:~~C:.:::..~-- ~~-:::;: F E E D VENT CHEM HOR FEED TANK --1-1~ .... :) DIST. TANK REJECT WASTE FIL E CY-TM-170-300 Revision 5 Page 129 of 222 CY-TM-170-300 Revision 5 Page 130 of 222 4.0 GASEOUS EFFLUENT MONITORS 4.1 TMl-1 Noble Gas Monitor Set Points The gaseous effluent monitor set points are established for each gaseous effluent radiation monitor to assure concentrations of radionuclides in gaseous effluents do not exceed the limits set forth in ODCM Part I Control 2.2.2.1. Table 4.1 lists Gaseous Effluent Release Points and their associated parameters; Figure 4.1 provides a Gaseous Effluent Release Pathway Diagram. The set points are established to satisfy the more restrictive set point concentration in the following two equations: 500 > f (Ci)(F)(Ki)(Dv) and 3000 > f (Ci)(Li + 1.1 Mi)(Dv)(F) Where: Ci = set point concentration based on Xe-133 equivalent, in µCi/cc F =gaseous effluent flowrate at the monitor, in cc/sec Ki =total body dose factor, in mrem/yr per µCi/m3 from Table 4.3 (eq 4.1.1) (eq 4.1.2) Dv = highest sector annual average gaseous atmospheric dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for station vent releases and Table 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground releases). Maximum values presently used are 1.23E-6 sec/m3 at sector NNE for station vent, and 1.30E-5 sec/m3 at sector E for all other releases. Li = skin dose factor due to beta emissions from radionuclide i, in mrem/yr per µCi/m3 from Table 4.3. Mi = air dose factor due to gamma emissions from radionuclide i, in mrad/yr per µCi/m3 from Table 4.3. 1.1 = mrem skin dose per mrad air dose. 500 = annual whole body dose rate limit for unrestricted areas, in mrem/yr. 3000 = annual skin dose rate limit for unrestricted areas, in mrem/yr. CY-TM-170-300 Revision 5 Page 131 of 222 The set point concentration is further reduced such that the concentration contributions from multiple release points would not combine to exceed ODCM Control limits.* The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors. This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste. 4.2 TMl-1 Particulate and Radioiodine Monitor Set Points CY-TM-170-300 Revision 5 Page 132 of 222 Set points for monitors which detect radionuclides other than noble gases are also established to assure that concentrations of these radionuclides in gaseous effluents do not exceed the limits of ODCM Part I Control 2.2.2.1. Set points are established so as to satisfy the following equations: 1500 > f {ci)(F)(Pi)(Dv) (eq 4.2) Where: Ci= set point concentration based on 1-131 equivalent for radioiodine monitor and Sr-90 for particulate

monitor, in µCi/cc F = gaseous effluent flow rate at the monitor, in cc/sec Pi = pathway dose parameter, in mrem/yr per µCi/m3 for the inhalation pathway from Table 4.6. The dose factors are based on the actual . individual organ and most restrictive age group (child) (NUREG-0133).

NOTE: Appendix A contains Pi calculational methodology. 1500 = annual dose rate limit to any organ from particulates and radioiodines and radionuclides (other than noble gases) with half lives greater than eight days in mrem/yr. Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) at or beyond the unrestricted area boundary from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 1.23E-6 sec/m3 for station vent, at sector NNE, and 1.30E-5 sec/m3 for all other releases, at sector E. The set point concentration is further reduced such that concentration contributions from multiple release points would not combine to exceed ODCM Control limits. The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors. This section of the ODCM is implemented by the Radiation Monitor Systems Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste. 4.3 TMl-2 Gaseous Radiation Monitor Set Points CY-TM-170-300 Revision 5 Page 133 of 222 TMl-2 Gaseous Radiation Monitors have their set points described in TMI Plant Procedure 1101-2.1. Figure 4.5 provides a gaseous effluent release pathway diagram. Table 4.2 provides TMl-2 Radiation Monitor Data. These set points are set in accordance with the Controls delineated in Part II of this ODCM. CY-TM-170-300 Revision 5 Page 134 of 222 4.4 TMl-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMl-1 has eleven (11) required effluent gaseous radiation monitors. These are RM-A4, RM-A5, RM-A15, RM-A6, RM-A?, RM-AB, RM-A9, RM-A14, ALC-RMl-1 B, WHP-RIT-1, and RLM-RM-1. These gaseous release points, radiation

monitors, and sample points are shown in Table 4.1. 4.4.1 RM-A4/RM-A6 Fuel Handling and Auxiliary Building Exhaust RM-A4 is the radiation monitor for the TMl-1 Fuel Handling Building Ventilation (see Figures 4.1 and 4.2). RM-A6 is the radiation monitor for the TMl-1 Auxiliary Building Ventilation (see Figures 4.1 and 4.2). High alarms on RM-A4 or RM-A6 noble gas channels will initiate shutdown of the related building ventilation air supply system. These two radiation monitors concurrently will satisfy requirements for the Station Vent release point in place of RM-AB. 4.4.2 RM-AB Station Ventilation Exhaust RM-AB is the particulate, radioiodine and gaseous radiation monitor for the TMl-1 Station Ventilation (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters.

High alarm on RM-AB noble gas low channel will initiate shutdown of the Station Ventilation air supply systems. (The Fuel Handling and Auxiliary Building Ventilation). This radiation monitor satisfies requirements for the Station Vent release point in place of RM-A4 and RM-A6. 4.4.3 RM-A5/RM-A 15 Condenser Off Gas Exhaust RM-A5 is the gaseous radiation monitor for the TMl-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 is the back up gaseous radiation monitor for the TMl-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4 ). High alarms on RM-A5 low channel or RM-A 15 noble gas channels will initiate the MAP-5 Radioiodine Processor Station. These two radiation monitors together satisfy requirements for the Condenser Off Gas release point. 4.4.4 RM-A? Waste Gas Decay Tank Exhaust RM-A? is the gaseous radiation monitor for the TMl-1 Waste Gas Decay tanks (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel. High alarm on RM-A? noble gas channel will initiate shutdown of the Waste Gas Decay Tank release in progress. This radiation monitor satisfies requirements for batch gaseous releases to the Station Vent release point. 4.4.5 RM-A9 Reactor Building Purge Exhaust CY-TM-170-300 Revision 5 Page 135 of 222 RM-A9 is the particulate, radioiodine and gaseous radiation monitor for the TMl-1 Reactor Building Purge system (see Figures 4.1 and 4.3). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-A9 noble gas low channel will initiate shutdown of the Reactor Building Purge System. This radiation monitor satisfies requirements for the Reactor Building Purge System release point. 4.4.6 RM-A 14 ESF FHB Ventilation System RM-A14 is the gaseous radiation monitor for the TMl-1 Emergency Safeguards Features (ESF) Fuel Handling Building Exhaust system (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sampler filters. High alarm on RM-A14 noble gas channel will initiate shutdown of the ESF Fuel Handling Building Exhaust System. This radiation monitor satisfies requirements for the ESF Fuel Handling Building Exhaust System release point. 4.4.7 ALC-RMl-18 Chemical Cleaning Facility (CCF) Ventilation Exhaust ALC-RMl-18 is an Victoreen particulate, radioiodine, and gaseous radiation monitor for the Chemical Cleaning building exhaust. This monitor is located in the Chemical Cleaning building on the ground floor, and has an associated sample panel. Sampling for particulate activity is performed off of the monitor. 4.4.8 WHP-RIT-1 Waste Handling and Packaging Facility (WHPF) Exhaust WHP-RIT-1 is an Eberline AMS-3 particulate radiation monitor for the TMI WHPF. The monitor is located in the Mechanical Equipment Room in the WHPF. Sampling for particulate activity is performed off of the monitor. A high alarm will initiate shutdown of the ventilation air exhaust system. 4.4.9 RLM-RM-1 Respirator Cleaning and Laundry Maintenance (RLM) Facility RLM-RM-1 is an Eberline AMS-3 particulate radiation monitor for the TMI RLM Facility. The monitor is located in the Mechanical Equipment Room in the RLM. Sampling for particulate activity is performed off of the monitor. CY-TM-170-300 Revision 5 Page 136 of 222 4.5 TMl-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMl-2 has three (3) regulatory required gaseous effluent radiation monitors. These are HP-R-219, HP-R-219A and HP-R-225. These gaseous release points, radiation

monitors, and sample points are shown in Table 4.2, and various gaseous effluent pathways are depicted in Figure 4.5. 4.5.1 HP-R-219 Station Ventilation Exhaust HP-R-219 is a Victoreen particulate and gaseous radiation monitor for the TMl-2 ventilation exhaust.

This in-plant effluent radiation monitor is located in the TMl-2 Auxiliary Building 328 foot elevation and has an associated sample panel. 4.5.2 HP-R-219A Station Ventilation Exhaust HP-R-219A is a Victoreen particulate and gaseous radiation monitor for the TMl-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMl-2 Auxiliary Building 328 foot elevation. 4.5.3 HP-R-225 Reactor Building Purge Air Exhaust Duct "A" HP-R-225 is a Victoreen particulate and gaseous radiation monitor for the TMl-2 Reactor Building Purge Air Exhaust System. This in-plant effluent radiation monitor is located in the TMl-2 Auxiliary Building 328' elevation area. 4.6 Control of Gaseous Effluent Releases CY-TM-170-300 Revision 5 Page 137 of 222 TMI gaseous effluent combined releases are controlled (per ODCM Part I for TMl-1 and ODCM Part II for TMl-2) by effluent sampling and radiation monitor set points. These measures assure that releases from the various vents do not qombine to produce dose rates at the site boundary exceeding the most restrictive of 500 mrem per year to the total body or 3000 mrem per year to the skin, and 1500 mrem per year to the thyroid. This is done by restricting simultaneous releases and by limiting the dose rates that may be contributed by the various vents at any time. The various vent radiation monitor set points are each based on fractions of the above limits and do not exceed the above limits when summed together. These effluent radiation monitor set points are calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2. The actual set points are then listed in TMl-1 Operations Procedure 1101-2.1. The radioactive content of each batch of gaseous waste is determined prior to release by sampling and analyses in accordance with ODCM Part I for TMl-1 and ODCM Part II for TMl-2. The results of pre-release analyses are used with the calculational methods in Sections 4.1 and 4.2 to assure that the dose rates at the site boundary are maintained below the limits in ODCM Part I for TMl-1 and ODCM Part II for TMl-2. Post-release analyses of samples composited from batch and continuous releases are performed in accordance with ODCM Part I for TMl-1 and ODCM Part II for TMl-2. The results of the analyses are used to assure that the dose rates at the site boundary are maintained within the limits of ODCM Part I for TMl-1 and ODCM Part II for TMl-2. TABLE 4.1 CY-TM-170-300 Revision 5 Page 138 of 222 TMl-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUS RADIATION (F) RELEASE TERMINATION MONITOR GASEOUS FLOW INTERLOCK (YES/NO) (DETECTOR) LOCATION RELEASE POINT RECORDER VALVES YES 306' Elevation Fuel Hand. AH-E-10 RM-A4 Auxiliary Bldg. Building Exhaust AH-FR-149 AH-D-120 AH-D-121 AH-D-122 RM-A6 306' Elevation Auxiliary Building AH-FR-150 YES Auxiliary Bldq. Exhaust AH-E-11 YES RMA-8/9 Bldg. WDG-V47 AH-FR-149 AH-E-10 RM-AB Near BWST Station Vent &AH-FR-150 AH-E-11 Exhaust Starts MAP-5 Radioiodine Sampler 322' Elevation Condenser Off YES RM-A5 Second Floor Gas Exhaust VA-FR-1113 Starts MAP-5 Turbine Bldq. Radioiodine Sampler 322' Elevation Condenser Off YES RM-A15 Second Floor Gas Exhaust VA-FR-1113 Starts MAP-5 Turbine Bldq. Radioiodine Sampler 306' Elevation Waste Gas YES RM-A7 Auxiliary Bldg. Decay Tanks WDG-FR-123 WDG-V47 (A,B,C) YES RMA-8/9 Bldg. Reactor Building AH-FT-909/ AH-V-1 A/B/C/D RM-A9 WDL-V-534/535 Near BWST Purge Exhaust AH-FR-148 Starts MAP-5 Radioiodine Sampler 331' Elevation ESF Fuel RM-A14 ESF FHB Handling AH-UR-1104A/B NO Outside Chem. Building Manual Actions only Addition Bldg. Exhaust TABLE 4.1 (Cont'd) CY-TM-170-300 Revision 5 Page 139 of 222 TMl-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUS RADIATION RELEASE TERMINATION MONITOR INTERLOCK (YES/NO) (DETECTOR) LOCATION GASEOUS RELEASE POINT VALVES ALC-RMl-18 Chemical Cleaning Bldg. CCB Exhaust System NONE 304' Elevation (Typical flow rate is 10,000 cfm) WHP-RIT-1 WHPF Mechanical WHPF Exhaust System YES Equipment Room (Typical flow rate is 7,500 cfm) WHPF Ventilation Trips RLM-RM-1 RLM-Mechanical RLM Exhaust System NONE Equipment Room (Typical flow rate is 900 cfm) TABLE 4.2 TMl-2 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION GASEOUS INTERLOCK MONITOR RELEASE (YES/NO) (DETECTOR) LOCATION POINT VALVES HP-R-219 328' Elevation Station Vent Exhaust NONE Auxiliary Buildino (Typical flow rate is 70,000 cfm) HP-R-219A 328' Elevation Station Vent Exhaust NONE Auxiliary Buildinq (Typical flow rate is 70,000 cfm) 328' Elevation Reactor Bldg Purge Exhaust HP-R-225 Auxiliary Building Duct "A" NONE (Typical flow rate is 20,000 cfm) TABLE 4.3 Dose Factors for Noble Gases and Daughters* Gamma Beta Total Body Skin Dose Dose Factor(b) Gamma Air Factor(a) Li Dose Factor Ki (mrem/yr M (mrem/yr per per (mrad/yr per Radionuclide µCi/m3) uCi/m3) uCi/m3) Kr-83m 7.56E-02** ---1.93E+01 Kr-85m 1.17E+03 1.46E+03 1.23E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 Kr-87 5.92E+03 9.73E+03 6.17E+03 Kr-88 1.47E+04 2.37E+03 1.52E+04 Kr-89 1.66E+04 1.01E+04 1.73E+04 Kr-90. 1.56E+04 7.29E+03 1.63E+04 Xe-131m 9.15E+01 4.76E+02 1.56E+02 Xe-133m 2.51E+02 9.94E+02 3.27E+02 Xe-133 2.94E+02 3.06E+02 3.53E+02 Xe-135m 3.12E+03 7.11E+02 3.36E+03 Xe-135 1.81E+03 1.86E+03 1.92E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 Xe-138 8.83E+03 4.13E+03 9.21E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 CY-TM-170-300 Revision 5 Page 140 of 222 Beta Air Dose Factor Ni (mrad/yr per µCi/m3) 2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03

• Dose factors are for immersion exposure in uniform semi-infinite cloud of noble gas radionuclides that may be detected in gaseous effluents.

Dose factor values are taken from Regulatory Guide 1.109 (Rev. 1 ), Table B-1. ** 7.56E-02 = 7.56 x 10-2. (a) Total body dose factor for gamma penetration depth of 5 cm into the body. (b) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm2. TABLE 4.4 Atmospheric Dispersion Factors for Three Mile Island STATION VENT DISTANCE SECTOR AVERAGE X/Q (IN SEC/M3) (IN METERS) SECTOR 610 2413 4022 5631 7240 12067 24135 40225 N 2.12E-07 7.30E-07 4.35E-07 2.56E-07 1.84E-07 8.12E-08 3.22E-08 1.65E-08 NNE 3.19E-07 1.23E-06 6.02E-07 3.37E-07 2.13E-07 9.12E-08 3.45E-08 1.76E-08 NE 2.08E-07 3.87E-07 2.73E-07 3.76E-07 2.45E-07 1.08E-07 4.08E-08 2.08E-08 ENE 1.18E-07 4.36E-07 6.10E-07 3.33E-07 2.16E-07 1.08E-07 4.21E-08 2.14E-08 E 2.56E-07 3.80E-07 3.28E-07 3.74E-07 2.59E-07 1.11E-07 4.15E-08 2.10E-08 ESE 7.92E-07 5.47E-07 5.71E-07 3.47E-07 2.19E-07 9.24E-07 3.42E-08 1.72E-08 SE 9.50E-07 8.69E-07 6.06E-07 3.23E-07 2.06E-07 9.07E-08 3.72E-08 1.87E-08 SSE 4.82E-07 7.12E-07 5.00E-07 2.77E-07 1.85E-07 9.02E-08 3.38E-08 1.71E-08 s 8.33E-08 8.20E-08 3.05E-07 1.64E-07 1.06E-07 5.30E-08 1.99E-08 1.00E-08 SSW 2.61E-08 4.97E-08 2.38E-07 1.25E-07 7.96E-08 3.47E-08 1.37E-08 6.90E-09 SW 2.98E-08 1.78E-07 2.64E-07 1.46E-07 9.13E-08 3.92E-08 1.45E-08 7.24E-09 WSW 7.49E-08 4.55E-07 2.85E-07 1.51E-07 9.59E-08 4.05E-08 1.50E-08 7.51 E-09 w 1.17E-07 2.80E-07 3.15E-07 1.82E-07 1.28E-07 6.02E-08 2.25E-08 1.14E-08 WNW 2.01E-07 2.70E-07 3.83E-07 2.67E-07 1.67E-07 7.13E-08 2.68E-08 1.36E-08 NW 1.48E-07 5.78E-07 3.83E-07 2.11E-07 1.37E-07 6.85E-08 2.66E-08 1.43E-08 NNW 9.13E-08 5.81 E-07 3.54E-07 1.98E-07 1.34E-07 6.58E-08 2.52E-08 1.29E-08 STATION VENT DISTANCE SECTOR AVERAGE D/Q (IN M2) (IN METERS) SECTOR 610 2413 4022 5631 7240 12067 24135 40225 N 8.19E-09 1.62E-09 6.74E-10 4.88E-10 3.59E-10 1.29E-10 4.14E-11 1.72E-11 NNE 1.34E-08 2.84E-09 1.38E-09 6.89E-10 4.03E-10 1.42E-10 4.35E-11 1.78E-11 NE 7.28E-09 1.29E-09 4.55E-10 6.84E-10 4.03E-10 1.48E-10 4.55E-11 1.85E-11 ENE 3.69E-09 8.45E-10 7.16E-10 3.51E-10 2.19E-10 1.20E-10 3.95E-11 1.61E-11 E 8.16E-09 1.91 E-09 7.04E-10 8.28E-10 5.35E-10 1.91 E-10 5.87E-11 2.39E-11 ESE 2.48E-08 4.51E-09 2.47E-09 1.33E-09 7.69E-10 2.72E-10 8.33E-11 3.40E-11 SE 2.98E-08 4.85E-09 2.44E-09 1.14E-09 6.67E-10 2.55E-10 8.79E-11 3.57E-11 SSE 1.58E-08 2.51E-09 1.08E-09 5.97E-10 4.28E-10 1.94E-10 5.95E-11 2.45E-11 s 2.94E-09 6.13E-10 6.48E-10 3.08E-10 1.84E-10 8.81 E-11 2.74E-11 1.13E-11 SSW 8.48E-10 2.80E-10 4.72E-10 2.20E-10 1.28E-10 4.72E-11 1.64E-11 6.68E-12 SW 1.51E-09 5.68E-10 5.89E-10 2.93E-10 1.67E-10 6.11 E-11 1.87E-11 7.59E-12 WSW 2.58E-09 8.26E-10 6.63E-10 3.09E-10 1.83E-10 6.47E-11 1.99E-11 8.17E-12 w 5.46E-09 1.20E-09 6.34E-10 3.55E-10 2.64E-10 1.06E-10 3.28E-11 1.33E-11 WNW 7.60E-09 1.51E-09 8.91E-10 6.25E-10 3.57E-10 1.27E-10 3.87E-11 1.57E-11 NW 5.19E-09 1.02E-09 5.49E-10 2.64E-10 1.62E-10 8.34E-11 2.64E-11 1.14E-11 NNW 3.32E-09 7.92E-10 4.85E-10 2.32E-10 1.59E-10 7.50E-11 2.35E-11 9.63E-12 DATA FROM 2010-2015 USED IN CALCULATIONS CY-TM-170-300 Revision 5 Page 141 of 222 ANNUAL 56315 72405 1.07E-08 7.71E-09 1.14E-08 8.23E-09 1.34E-08 9.68E-09 1.38E-08 9.96E-09 1.35E-08 9.70E-09 1.09E-08 7.85E-09 1.20E-08 8.60E-09 1.10E-08 7.89E-09 6.41E-09 4.61E-09 4.42E-09 3.17E-09 4.62E-09 3.31E-09 4.78E-09 3.43E-09 7.30E-09 5.26E-09 8.79E-09 6.35E-09 9.25E-09 6.70E-09 8.33E-09 6.04E-09 ANNUAL 56315 72405 9.25E-12 5.75E-12 9.55E-12 5.93E-12 9.95E-12 6.19E-12 8.68E-12 5.40E-12 1.30E-11 8.09E-12 1.84E-11 1.14E-11 1.93E-11 1.20E-11 1.32E-11 8.20E-12 6.10E-12 3.79E-12 3.60E-12 2.24E-12 4.09E-12 2.54E-12 4.40E-12 2.73E-12 7.16E-12 4.44E-12 8.46E-12 5.25E-12 6.11E-12 3.79E-12 5.18E-12 3.22E-12 TABLE 4.5 Atmospheric Dispersion Factors for Three Mile Island GROUND RELEASE DISTANCE SECTOR AVERAGE X/Q (IN SEC/M3) (IN METERS) SECTOR 610 2413 4022 5631 7240 12067 24135 40225 N 8.46E-06 1.05E-06 5.27E-07 3.35E-07 2.39E-07 1.22E-07 4.92E-08 2.55E-08 NNE 9.97E-06 1.23E-06 6.16E-07 3.92E-07 2.80E-07 1.42E-07 5.75E-08 2.98E-08 NE 1.17E-05 1.47E-06 7.32E-07 4.64E-07 3.31E-07 1.68E-07 6.76E-08 3.50E-08 ENE 1.20E-05 1.54E-06 7.65E-07 4.84E-07 3.45E-07 1.74E-07 7.00E-08 3.61E-08 E 1.30E-05 1.67E-06 8.26E-07 5.21E-07 3.70E-07 1.86E-07 7.43E-08 3.82E-08 ESE 1.13E-05 1.43E-06 7.00E-07 4.39E-07 3.11 E-07 1.55E-07 6.12E-08 3.13E-08 SE 1.21 E-05 1.52E-06 7.41E-07 4.64E-07 3.27E-07 1.63E-07 6.41 E-08 3.27E-08 SSE 1.13E-05 1.44E-06 7.05E-07 4.43E-07 3.14E-07 1.57E-07 6.23E-08 3.19E-08 s 7.37E-06 9.52E-07 4.67E-07 2.93E-07 2.08E-07 1.04E-07 4.10E-08 2.09E-08 SSW 4.67E-06 6.09E-07 2.97E-07 1.86E-07 1.31 E-07 6.51E-08 2.55E-08 1.30E-08 SW 4.67E-06 6.05E-07 2.95E-07 1.84E-07 1.30E-07 6.45E-08 2.53E-08 1.28E-08 WSW 5.42E-06 6.92E-07 3.39E-07 2.13E-07 1.51 E-07 7.53E-08 2.98E-08 1.52E-08 w 8.19E-06 1.04E-06 5.15E-07 3.25E-07 2.30E-07 1.16E-07 4.60E-08 2.36E-08 WNW 9.23E-06 1.16E-06 5.76E-07 3.64E-07 2.59E-07 1.31 E-07 5.25E-08 2.71 E-08 NW 8.88E-06 1.10E-06 5.53E-07 2.52E-07 2.52E-07 1.29E-07 5.23E-08 2.72E-08 NNW 7.55E-06 9.37E-07 4.71E-07 3.01E-07 2.15E-07 1.10E-07 4.48E-08 2.33E-08 GROUND RELEASE DISTANCE SECTOR AVERAGE D/Q (IN M2 (IN METERS) SECTOR 610 2413 4022 5631 7240 12067 24135 40225 N 1.58E-08 1.59E-09 6.52E-10 3.60E-10 2.29E-10 9.29E-11 2.95E-11 1.20E-11 NNE 2.15E-08 2.17E-09 8.89E-10 4.90E-10 3.13E-10 1.27E-10 4.02E-11 1.63E-11 NE 1.99E-08 2.01E-09 8.26E-10 4.55E-10 2.90E-10 1.18E-10 3.73E-11 1.51E-11 ENE 1.76E-08 1.78E-09 7.29E-10 4.02E-10 2.56E-10 1.04E-10 3.29E-11 1.34E-11 E 2.57E-08 2.59E-09 1.06E-09 5.85E-10 3.73E-10 1.51E-10 4.80E-11 1.95E-11 ESE 3.49E-08 3.53E-09 1.45E-09 7.97E-10 5.08E-10 2.06E-10 6.53E-11 2.65E-11 SE 4.22E-08 4.26E-09 1.75E-09 9.62E-10 6.14E-10 2.49E-10 7.89E-11 3.20E-11 SSE 2.91E-08 2.93E-09 1.20E-09 6.63E-10 4.23E-10 1.71 E-10 5.44E-11 2.21 E-11 s 1.49E-08 1.50E-09 6.17E-10 3.40E-10 2.17E-10 8.79E-11 2.79E-11 1.13E-11 SSW 7.64E-09 7.71E-10 3.16E-10 1.74E-10 1.11E-10 4.51 E-11 1.43E-11 5.80E-12 SW 8.06E-09 8.14E-10 3.34E-10 1.84E-10 1.17E-10 4.76E-11 1.51E-11 6.12E-12 WSW 9.82E-09 9.91E-10 4.07E-10 2.24E-10 1.43E-10 5.79E-11 1.84E-11 7.45E-12 w 1.55E-08 1.57E-09 6.43E-10 3.54E-10 2.26E-10 9.16E-11 2.91 E-11 1.18E-11 WNW 1.87E-08 1.89E-09 7.75E-10 4.27E-10 2.72E-10 1.10E-10 3.50E-11 1.42E-11 NW 1.32E-08 1.33E-09 5.46E-10 3.01E-10 1.92E-10 7.77E-11 2.46E-11 1.00E-11 NNW 1.04E-08 1.05E-09 4.30E-10 2.37E-10 1.51E-10 6.12E-11 1.94E-11 7.88E-12 DATA FROM 2010-2015 USED IN CALCULATIONS CY-TM-170-300 Revision 5 Page 142 of 222 ANNUAL 56315 72405 1.67E-08 1.21 E-08 1.95E-08 1.42E-08 2.28E-08 1.66E-08 2.34E-08 1.70E-08 2.47E-08 1.79E-08 2.02E-08 1.46E-08 2.10E-08 1.52E-08 2.06E-08 1.49E-08 1.35E-08 9.74E-09 8.32E-09 5.99E-09 8.23E-09 5.93E-09 9.81E-09 7.09E-09 1.53E-08 1.11 E-08 1.76E-08 1.28E-08 1.78E-08 1.30E-08 1.52E-08 1.11 E-08 ANNUAL 56315 72405 6.44E-12 4.00E-12 8.77E-12 5.45E-12 8.15E-12 5.06E-12 7.19E-12 4.47E-12 1.05E-11 6.51E-12 1.43E-11 8.86E-12 1.72E-11 1.07E-11 1.19E-11 7.37E-12 6.08E-12 3.78E-12 3.12E-12 1.94E-12 3.29E-12 2.05E-12 4.01 E-12 2.49E-12 6.34E-12 3.94E-12 7.64E-12 4.75E-12 5.38E-12 3.34E-12 4.24E-12 2.63E-12 TABLE4.6 Dose Parameters for Radioiodines and Radioactive Particulate in Gaseous Effluents* CRITICAL ORGAN CRITICAL CY-TM-170-300 Revision 5 Page 143 of 222 ORGAN NUCLIDE ORGAN FACTOR Pi*** NUCLIDE ORGAN FACTOR Pi*** H-3** TOTAL BODY 3.04E-07 1.12E+03 RU-103 LUNG 1.79E-04 6.62E+05 C-14 BONE 9.70E-06 3.59E+04 RU-105 GI-LU 2.69E-05 9.95E+04 NA-24 TOTAL BODY 4.35E-06 1.61E+04 RU-106 LUNG 3.87E-03 1.43E+07 P-32 BONE 7.04E-04 2.60E+06 AG-110M LUNG 1.48E-03 5.48E+06 CR-51 LUNG 4.59E-06 1.70E+04 TE-125M LUNG 1.29E-04 4.77E+05 MN-54 LUNG 4.26E-04 1.58E+06 SB-125 LUNG 6.27E-04 2.32E+06 MN-56 GI-LU 3.33E-05 1.23E+05 TE-127M LUNG 4.00E-04 1.48E+06 FE-55 LUNG 3.00E-05 1.11 E+05 TE-127 GI-LU 1.52E-05 5.62E+04 FE-59 LUNG 3.43E-04 1.27E+06 TE-129M

• LUNG 4.76E-04 1.76E+06 C0-58 LUNG 2.99E-04 1.11 E+06 TE-129 GI-LU 6.89E-06 2.55E+04 C0-60 LUNG 1.91 E-03 7.07E+06 TE-131M GI-LU 8.32E-05 3.08E+05 Nl-63 BONE 2.22E-04 8.21E+05 TE-131 LUNG 5.55E-07 2.05E+03 Nl-65 GI-LU 2.27E-05 8.40E+04 TE-132 LUNG 1.02E-04 3.77E+05 CU-64 GI-LU 9.92E-06 3.67E+04 1-130 THYROID 4.99E-04 1.85E+06 ZN-65 LUNG 2.69E-04 9.95E+05 1-131 THYROID 4.39E-03 1.62E+07 ZN-69 GI-LU 2.75E-06 1.02E+04 1-132 THYROID 5.23E-05 1.94E+05 BR-83 TOTAL BODY 1.28E-07 4.74E+02 1-133 THYROID 1.04E-03 3.85E+06 BR-84 TOTAL BODY 1.48E-07 5.48E+02 1-134 THYROID 1.37E-05 5.07E+04 BR-85 TOTAL BODY 6.84E-09 2.53E+01 1-135 THYROID 2.14E-04 7.92E+05 RB-86 LIVER 5.36E-05 1.98E+05 CS-134 LIVER 2.74E-04 1.01E+06 RB-88 LIVER 1.52E-07 5.62E+02 CS-136 LIVER 4.62E-05 1.71 E+05 RB-89 LIVER 9.33E-08 3.45E+02 CS-137 BONE 2.45E-04 9.07E+05 SR-89 LUNG 5.89E-04 2.16E+06 CS-138 LIVER 2.27E-07 8.40E+02 SR-90 BONE 2.73E-02 1.01E+08 BA-139 GI-LU 1.56E-05 5.77E+04 SR-91 GI-LU 4.70E-05 1.74E+05 BA-140 LUNG 4.71 E-04 1.74E+06 SR-92 GI-LU 6.55E-05 2.42E+05 BA-141 LUNG 7.89E-07 2.92E+03 Y-90 GI-LU 7.24E-05 2.68E+05 BA-142 LUNG 4.44E-07 1.64E+03 Y-91M LUNG 7.60E-07 2.81E+03 LA-140 GI-LU 6.10E-05 2.26E+05 Y-91 LUNG 7.10E-04 2.63E+06 LA-142 GI-LU 2.05E-05 7.59E+04 Y-92 GI-LU 6.46E-05 2.39E+05 CE-141 LUNG 1.47E-04 5.44E+05 Y-93 GI-LU 1.05E-04 3.89E+05 CE-143 GI-LU 3.44E-05 1.27E+05 ZR-95 LUNG 6.03E-04 2.23E+06 CE-144 LUNG 3.23E-03 1.20E+07 ZR-97 GI-LU 9.49E-05 3.51E+05 PR-143 LUNG 1.17E-04 4.33E+05 NB-95 LUNG 1.66E-04 6.14E+05 PR-144 LUNG 4.23E-07 1.57E+03 M0-99 LUNG 3.66E-05 1.35E+05 ND-147 LUNG 8.87E-05 3.28E+05 TC-99M GI-LU 1.30E-06 4.81 E+03 W-187 GI-LU 2.46E-05 9.10E+04 TC-101 * ** LUNG 1.58E-07 5.85E+02 NP-239 GI-LU 1.73E-05 6.40E+04 The listed dose parameters are for radionuclides, other than noble gases that may be detected in gaseous effluents.

Pi factors include all nonatmospheric pathway transport parameters, the receptor's usage of pathway media, and are based on the most restrictive age group (child) critical organ. Additional dose parameters for nuclides not included in this Table may be calculated using the methodology described in NUREG-0133. Tritium dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin. *** mrem/year per µCi/m3* FIGURE 4.1 TMl-1 Gaseous Effluent Pathways FIGURE 4.1 ESF VENTILATION SYSTEM A p 1:11,IDI CfM FUEL HANDLING BUILDING RM*A4 ~----~ 40,000CFM STATION VE!:NT ,:ao,oooc~ DlillUON FLOW REACTOR 8Ull-C>INO PURGE 80.0000P'M IOe.OJGN P"I.OW CONDEN&EA OFF QA.8 STACI< 0-30 CFM PUMP6 CY-TM-170-300 Revision 5 Page 144 of 222 P-PRE FILTER A-ABSOLUTE HEPA C-CHARCOAL FILTER L VACUUM =========

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FIGURE 4.2 CY-TM-170-300 Revision 5 Page 145 of 222 TMl-1 Auxiliary and Fuel Handling Buildings Effluent Pathways HAXIIUI 91001 Cf'M FLOV AUXILIARY BUILDING 0-10 CfH Plm: STACK P A C MAXIIIM 41UO) CfN ESF FUEL HANDLING BUILDING RM-A8 HI RM-AB BO f"EET P A C 71m CfN MX. FLOV FUEL HANDLING BUILDING P: P~TIQUT[ A: AIS(l.UT( (:~ FIGURE 4.3 CY-TM-170-300 Revision 5 Page 146 of 222 TMl-1 Reactor Building Effluent Pathway REACTOR BUILDING PURGE EXHAUST RADIATION MONITORS ANO SAMPLING STATIONS REACT[R JJILDINi SNfl.lKi SYSTDtS Pij TICtl.A T£/TRil lUf IOD[t(JN]l( !i\S REACTOR BUILDING 170 FEET r--.......... --'--~ RM-G24 RM-A9 H[Gi p AC.,..____.__- HAXDUI* FILTERS Cfll Pl.RI"£ flOV P: PARTIC11.ATE A : ABS[I.UT( C = CWtRCllll FIGURE 4.4 CY-TM-170-300 Revision 5 Page 147 of 222 TMl-1 Condenser Offgas Effluent Pathway CONDENSER OFF GAS STACK 115 FEET D TO 200 crM CONDENSER OFF GAS EXHAUST RADIATION MONITORS AND SAMPLING STATIONS _.,__-t MAIN CONDENSE* I --..I,. AUXILIARY BUILDING FUEL HANDLING BUILDING

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FIGURE 4.5 CY-TM-170-300 Revision 5 Page 148 of 222 TMl-2 Gaseous Effluent Filtration System/Pathways STATION VENT j * . -u2,ooo c,11 HP-R-:219 HP-R-219A HP-R-219 SAMPLE RACK RB BREATHER

.J,. ----------_,... '*---------------I 0-10,000~ ~,OOOCt'M I I FILTERS I I HP-R*Z25 FILTERS}---- I I I REACTOR BUILDING 0.,3,000~ I FILTERS I I I . "' o * -e.~oo c,rw NO MONITOR CONTROL AND SERVICE BUILDING UNIT 2 EXHAUST AIR FLOW AND RMS SCHEMATIC CY-TM-170-300 Revision 5 Page 149 of 222 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents -Instantaneous Release Limits 5.1.1 Noble Gases For noble gases, the following equations apply for total body and skin dose rate at the unrestricted area boundary: 5.1.1.1 Total Body Dose Ratetb = T (Ki) x (Dv) x (Qi) ( eq 5.1.1.1) Where: Dose Rate b = instantaneous total body dose rate limit, at the site boundary, in mrem/yr. Ki = total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem/yr per µCi/m3 from Table 4.3. Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use are 1.23E-6 sec/m3 at sector NNE for station vent, and 1.30E-5 sec/m3 for all other releases at sector E. Oi = Release rate of radionuclide, i, in µCi/sec as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in µCi/cc, times the release pathway flow rate, in cc/second. CY-TM-170-300 Revision 5 Page 150 of 222 5.1.1.2 Skin Where: Dose Ratesk = T (Li + 1.1 Mi) X (Dv) X (Qi) (eq 5.1.1.2) Dose Ratesk = instantaneous mrem/year skin dose rate limit, at the site boundary, in mrem/yr. Li = skin dose factor due to beta emissions for. each identified noble gas radionuclide, in mrem/yr per µCi/m3 from Table 4.3. Mi = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per µCi/m3 from Table 4.3. 1.1 = mrem skin dose per mrad air dose. Converts air dose to skin dose. Oi = release rate of radionuclide, i, in µCi/sec, as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in µCi/cc, times the release pathway flow rate, in cc/second. Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use are 1.23E-6 sec/m3 at sector NNE for station vent, and 1.30E-5 sec/m3 for all other releases at E. CY-TM-170-300 Revision 5 Page 151 of 222 5.1.2 lodine-131, lodine-133, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days Where: For 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation applies: Dose Rate1p = 7 (Pi) (Dv) (Qi) (eq 5.1.2) Dose Rate1p = mrem/year organ dose rate. Pi = dose parameter for 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater 'than 8 days, for the inhalation

pathway, in mrem/yr per µCi/m3, from Table 4.6. The dose factors are based on the critical individual organ and most restrictive age group (child).

Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for the station vent releases and Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 1.23E-6 sec/m3 for station vent, at sector NNE, and 1.30E-5 sec/m3 for all other releases at sector E. Oi = release rate of each radionuclide, i, in µCi/sec. Calculated using the concentration of each radionuclide, i, in µCi/cc, times the release pathway flow rate, in cc/second. CY-TM-170-300 Revision 5 Page 152 of 222 5.2 Gaseous Effluents -10 CFR 50 Appendix I 5.2.1 Noble Gases Where: The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using the following expressions: Dose r = (3.17E-8) x T (Mi) x (Dv) x (Qi) and Dose J3 = (3.17E-8) x (Ni) x (Dv) x (Qi) I . (eq 5.2.1) (eq 5.2.2) Dose r = mrad gamma air dose due to gamma emissions from noble gas radionuclides. Dose j3 = mrad beta air dose due to beta emissions from noble gas radionuclides. Mi = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per µCi/m3, from Table 4.3. Ni = air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per µCi/m3, from Table 4.3. Dv = highest sector annual average gaseous dispersion factor, X/Q, at or beyond the unrestricted area boundary, in sec/m3* Values may be read or interpolated from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. Maximum values of X/Q presently used are 1.23E-6 sec/m3 for station vent at sector NNE, and 1.30E-5 sec/m3 for all other releases at sector E. Oi = release of noble gas radionuclide, i, in µCi, over the specified time period, (µCi/second* seconds). 3.17E-8 = inverse of the number of seconds in a year. CY-TM-170-300 Revision 5 Page 153 of 222 NOTE: If the methodology in this section is used in determining dose to an individual, rather than air dose due to noble gases, substitute Ki, from Table 4.3, for Mi, and (Li + 1.1 Mi) for Ni. 5.2.2 lodine-131, lodine-133, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days Where: The dose to an individual from 1-131, 1-133, Tritium and Radionuclides in Particulate Form with half-lives greater than 8 days in gaseous effluents released from the site to an unrestricted area is determined by solving the following expression: Doseo = T (3.17E-8) x T (Ri) (Dv) (Qi) (eq 5.2.2) Dosea = dose to all real pathways, p, to organ, o, of an individual in age group, a, from 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, in mrem, during any desired time period. Ri = the dose factor for each identified radionuclide, i, pathway, p, age group, a, and organ, o, in mrem/yr per µCi/m3 for the inhalation pathway and m2 -mrem/yr per µCi/sec for other pathways, from Tables 5.2 to 5.7. NOTE: When condenser offgas activity in µCi is above detectable limits, it is multiplied by 1.05 to account for an additional 5 percent activity released due to the Aux Condenser, Gland Seal Exhaust, Emergency Feedwater or the Turbine Building IAW Reference 9.11. NOTE: Tritium, H-3, dose factor is mrem/year per µCi/m3 for all pathways. Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, for the inhalation

pathway, and D/Q, in m2, for other pathways.

Table 4.4 is used to derive the values for station vent releases and Table 4.5 is used to derive the values for all other releases. The values used to calculate site boundary and critical receptor doses are as follows: Station Vent Releases -Boundary Inhalation X/Q Ground D/Q

• 1.23E-6 in sector NNE 2.98E-8 in sector SE Station Vent Releases

-Critical Receptor Inhalation X/Q 1.04E-6 in sector SE Ground D/Q 1.84E-8 in sector SE Meat D/Q 7.45E-9 in sector ESE X/Q 6.62E-7 in sector ESE Vegetation D/Q 8.68E-9 in sector SSE X/Q 6.30E-7 in sector SSE Cow/Milk/Infant D/Q 5.45E-9 in sector SE X/Q 8.87E-7 in section SE Ground or Other Releases -Boundary Inhalation X/Q Ground D/Q 1.30E-5 in sector E 4.22E-8 in sector SE Ground or Other Releases -Critical Receptor Inhalation X/Q Ground D/Q Meat D/Q X/Q Vegetation D/Q X/Q 1.04E-5 in sector E 2.06E-8 in sector E 5.84E-9 in sector ESE 2.16E-6 in sector ESE 1.66E-8 in sector E 8.43E-6 in sector E Cow/Milk/Infant D/Q 4.63E-9 in sector SE X/Q 1.63E-6 in sector SE CY-TM-170-300 Revision 5 Page 154 of 222 CY-TM-170-300 Revision 5 Page 155 of 222 Dv(H-3) = In the case of H-3 only the X/Q's above are used for all pathways. Oi = release of 1-131, 1-133, Tritium and Radionuclides, i, in Particulate Form with half-lives greater than 8 days, in µCi, cumulative over the specified time period (µCi/second* seconds). 3.1 ?E-8 = inverse of the number of seconds in a year. CY-TM-170-300 Revision 5 Page 156 of 222 5.3 Gaseous Radioactive System Dose Calculations Once per Month ODCM Part I Control 2.2.2.4 and TMl-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate subsystem of the Gaseous Radwaste Treatment System shall be used to reduce the radioactive materials in gaseous waste prior to their discharge. When the monthly projected doses due to the gaseous effluent releases from the site would exceed: 0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ. The following calculational method is provided for performing this dose projection. At least once per month the gamma air dose, beta air dose and the maximum organ dose for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual release during the period for which the projection is made. If these projected doses exceed any of the values listed above, appropriate portions of the TMl-1 Gaseous Waste Treatment System, as defined in Section 6.0, or appropriate portions of the TMl-2 Gaseous Effluent Filtration System as shown on Figure 4.5, shall be used to reduce radioactivity levels prior to release. At the discretion of the ODCM Specialist, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter-to-date is not believed to be representative of the dose per day projected for the next month. TABLE 5.2.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: INHALATION CY-TM-170-300 Revision 5 Page 157 of 222 -~~~~~~~--1-~----------------~~~~~~~~~~§~§-~~~-~~-~§-~~~i~~~i~iii~~~7-~~~~-P.~~-~~!~~~~~~~~~~~~~~~------------------: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

---

.. ---------------------------------------------------* H-3 O.OOE+OO 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 C-14 2.65E+04 5.31 E+03 5.31 E+03 5.31 E+03 5.31 E+03 5.31 E+03 5.31 E+03 CR-51 O.OOE+OO O.OOE+OO 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN-54 O.OOE+OO 2.53E+04 4.98E+03 O.OOE+OO 4.98E+03 1.00E+06 7.06E+03 FE-55 1.97E+04 1.17E+04 3.33E+03 O.OOE+OO O.OOE+OO 8.69E+04 1.09E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 O.OOE+OO O.OOE+OO 1.02E+06 2.48E+04

---

*

C0-58 O.OOE+OO 1.22E+03 1.82E+03 O.OOE+OO O.OOE+OO 7.77E+05 1.11 E+04 C0-60 O.OOE+OO 8.02E+03 1.18E+04 O.OOE+OO O.OOE+OO 4.51E+06 3.19E+04 Nl-63 3.39E+05 2.04E+04 1.16E+04 O.OOE+OO O.OOE+OO 2.09E+05 2.42E+03 ZN-65 1.93E+04 6.26E+04 3.11E+04 O.OOE+OO 3.25E+04 6.47E+05 5.14E+04 RB-86 O.OOE+OO 1.90E+05 8.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 SR-89 3.98E+05 O.OOE+OO 1.14E+04 O.OOE+OO O.OOE+OO 2.03E+06 6.40E+04

---

. ----------------------------------------------------------------------------------------------* SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 4.09E+07 O.OOE+OO 2.59E+06 O.OOE:+00 O.OOE+OO 1.12E+07 5.88E+05 O.OOE+OO 1.57E+04 O.OOE+OO O.OOE+OO 2.45E+06 1.15E+05 2.79E+04 2.03E+04 O.OOE+OO 3.11E+04 1.75E+06 1.57E+04 6.43E+03 3.78E+03 O.OOE+OO 4.72E+03 4.79E+05 2.02E+03 O.OOE+OO

6. 79E+02 O.OOE+OO 4.24E+03 5.52E+05 8.68E+04 O.OOE+OO 1.09E+04 O.OOE+OO 1.07E+05 1.16E+07 AG-110M 9.98E+03 TE-125M 4.76E+03 TE-127M 1.67E+04 7.22E+03 5.00E+03 1.99E+03 6.58E+02 6.90E+03 2.07E+03 O.OOE+OO 1.62E+03 4.87E+03 1.09E+04 3.67E+06 O.OOE+OO 4.47E+05 3.75E+04 1.31 E+06 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 1.41 E+04 6.09E+03 2.23E+03 3.79E+04 4.44E+04 1.96E+04 1.32E+04 1.92E+04 5.60E+03 5.47E+03 1.48E+07 3.56E+06 3.96E+05 7.03E+05 7.45E+04 O.OOE+OO 4.83E+04 1.35E+05 5.29E+04 O.OOE+OO 5.49E+05 6.12E+05 4.55E+04 O.OOE+OO 5.60E+04 2.77E+04 3.19E+06 5.60E+01 1.67E+04 1.21E+06 2.90E+03 1.99E+03 1.76E+05 O.OOE+OO O.OOE+OO O.OOE+OO 3.18E+04 5.18E+04 2.24E+04 1.90E+05 5.64E+04 1.72E+05 1.34E+01 5.25E+03 5.38E+05 1.68E+06 O.OOE+OO O.OOE+OO 7.97E+04 1.18E+04 7.13E+04 1.60E+06 5.17E+05 9.84E+06 1.31E+05 7.03E+04 2.17E+04 1.27E+04 1.61E+04 1.64E+05 3.30E+04 1.29E+04 2.73E+04 6.90E+04 1.06E+03 2.16E+03 1.33E+03 1.43E+03 1.33E+03 3.84E+04 2.16E+04 1.48E+05 PR-143 1.40E+04 5.24E+03 6.99E+02 O.OOE+OO 1.97E+03 4.33E+05 3.72E+04 ND-147 7.94E+03 8.13E+03 5.00E+02 O.OOE+OO 3.15E+03 3.22E+05 3.12E+04 TABLE 5.2.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY:

INHALATION CY-TM-170-300 Revision 5 Page 158 of 222 ~~~~=E~i;i~=~~y~~!:~if~i:~~~~~i=:=~iI= H-3 O.OOE+OO 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 CR-51 O.OOE+OO O.OOE+OO 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 . ZN-65 RB-86 SR-89 O.OOE+OO 4.29E:+-04 4.74E+04 2.52E+04 2.07E+04 3.34E+04 9.51 E+03 7.77E+03 1.67E+04 O.OOE+OO 1.00E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. 77E+03 3.16E+03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.31 E+04 2.26E+04 O.OOE+OO 8.21 E+05 4.63E+04 2.80E+04 O.OOE+OO 4.26E+04 1.13E+05 7.03E+04 O.OOE+OO 7.14E+04 O.OOE+OO 1.98E+05 1.14E+05 O.OOE+OO O.OOE+OO 5.99E+05 O.OOE+OO 1.72E+04 O.OOE+OO O.OOE+OO 1.58E+06 2.29E+04 1.11 E+05 2.87E+03 1.27E+06 7.07E+04 1.11 E+06 3.44E+04 7.07E+06 9.62E+04 2.75E+05 6.33E+03 9.95E+05 1.63E+04 O.OOE+OO 7.99E+03 2.16E+06 1.67E+05

---

*

SR-90 1.01E+o8* O.OOE+OO 6.44E+06 O.OOE+OO O.OOE+OO 1.48E+07 3.43E+05 Y-91 9.14E+05 O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1.84E+05 ZR-95 1.90E+05 4.18E+04 3.70E+04 O.OOE+OO 5.96E+04 2.23E+06. 6.11E+04 NB-95 2.35E+04 9.18E+03 6.55E+03 O.OOE+OO 8.62E+03 6.14E+05 3.70E+04 RU-103 2.79E+03 O.OOE+OO 1.07E+03 O.OOE+OO 7.03E+03 6.62E+05 4.48E+04 RU-106 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+OO 1.84E+05 1.43E+07 4.29E+05

---

*

AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 PR-143 ND-147 1.69E+04 1.14E+04 9.14E+03 O.OOE+OO 2.12E+04 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+OO 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.92E+04 6.85E+03 3.04E+03 . 6.33E+03 5.03E+04 7.88E+04 3.38E+04 4.81 E+04 4.81 E+04 2.73E+04 1.62E+07 1.66E+04 2.03E+04

7. 70E+03 3.85E+06 6.51E+05 6.51E+04 9.07E+05 7.40E+04 3.92E+04 6.77E+06 1.01 E+06 2.25E+05 1.71E+05 1.16E+05 8.25E+05 1.28E+05 6.48E+01 4.33E+03 1.95E+04

. 2.90E+03 2.12E+06 3.61 E+05 O.OOE+OO 3.30E+05 O.OOE+OO 9.55E+04 O.OOE+OO 2.82E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.11E+01 8.55E+03 1.17E+06 5.48E+06 1.00E+05 4.77E+05 3.38E+04 1.48E+06 7.14E+04

1. 76E+06 1.82E+05 O.OOE+OO 2.84E+03 O.OOE+OO 5.48E+03 1.21 E+05 3.85E+03 1.45E+04 4.18E+03 1.04E+05 3.62E+03 1.74E+06 5.44E+05 1.20E+07 1.02E+05 5.66E+04 3.89E+05 1.85E+04 5.55E+03 9.14E+02 O.OOE+OO 3.00E+03 4.33E+05

9. 73E+04 1.08E+04

8. 73E+03 6.81 E+02

• O.OOE+OO 4.81 E+03 3.28E+05 8.21 E+04 TABLE 5.2.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY:

INHALATION CY-TM-170-300 Revision 5 Page 159 of 222 H-3 O.OOE+OO 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 CR-51 O.OOE+OO O.OOE+OO 1.35E+02 7.50E+01 3.07E+01 2.1 OE+04 3.00E+03 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 5.11 E+04 3.34E+04 2.38E+04 1.59E+04

3. 70E+04 8.40E+03 O.OOE+OO 5.54E+03 O.OOE+OO 1.43E+04 O.OOE+OO 1.27E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.07E+03 2.78E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.51 E+04 1.98E+04 O.OOE+OO O.OOE+OO 5.80E+05 4.34E+04 1.98E+04 O.OOE+OO O.OOE+OO 3.86E+04 1.34E+05 6.24E+04 O.OOE+OO 8.64E+04 O.OOE+OO 1.90E+05 8.40E+04 O.OOE+OO O.OOE+OO 4.34E+05 O.OOE+OO 1.25E+04 O.OOE+OO O.OOE+OO 1.98E+06 1.24E+05 1.53E+06 1.34E+06 8.72E+06 3.07E+05 1.24E+06 O.OOE+OO 2.42E+06 6.68E+04 6.39E+03 1.78E+05 9.52E+04 2.59E+05 1.42E+04 4.66E+04 1.77E+04 3.71 E+05 -------------------------------------------------------------------------------------------------------------------------------------------------------*

SR-90 1.08E+08 O.OOE+OO 6.68E+06 O.OOE+OO O.OOE+OO 1.65E+07 7.65E+05 Y-91 6.61E+05 O.OOE+OO 1.77E+04 O.OOE+OO O.OOE+OO 2.94E+06 4.09E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04 O.OOE+OO 6.74E+04 2.69E+06 1.49E+05 NB-95 1.86E+04 1.03E+04 5.66E+03 O.OOE+OO 1.00E+04 7.51E+05 9.68E+04 RU-103 2.10E+03 O.OOE+OO 8.96E+02 O.OOE+OO 7.43E+03 7.83E+05 1.09E+05 RU-106 9.84E+04 O.OOE+OO 1.24E+04 O.OOE+OO 1.90E+05 1.61 E+07 9.60E+05

---

*

AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-134 cs~136 CS-137 BA-140 CE-141 CE-144 1.38E+04 1.31 E+04 7.99E+03 O.OOE+OO 2.50E+04 4.88E+03 2.24E+03 6.67E+02 1.40E+03 O.OOE+OO 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 3.54E+04 4.91 E+04 2.64E+04 1.46E+07 8.40E+04 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 5.02E+05 5.15E+04 6.70E+05 1.13E+06 5.49E+05 1.94E+05 1.37E+05 8.48E+05 3.11 E+05 O.OOE+OO O.OOE+OO O.OOE+OO 3.75E+05 1.10E+05 3.04E+05 5.47E+04 6.70E+01 3.52E+03 O.OOE+OO 2.28E+01 2.84E+04 1.90E+04 2.17E+03 O.OOE+OO 8.88E+03 4.89E+06 2.02E+06 2.62E+05 O.OOE+OO 1.21 E+06 6.75E+06 2.73E+05 5.36E+05 7.50E+04 1.66E+06 1.59E+05 1.98E+06 4.05E+05 O.OOE+OO 6.49E+03 O.OOE+OO 1.03E+04 1.46E+05 1.78E+04 1.21E+05 2.03E+06 6.14E+05 1.34E+07 9.76E+03 1.09E+04 8.48E+03 2.29E+05 1.26E+05 8.64E+05 PR-143 1.34E+04 5.31 E+03 6.62E+02 O.OOE+OO 3.09E+03 4.83E+05 2.14E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 O.OOE+OO 5.02E+03 3.72E+05 1.82E+05 TABLE 5.2.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: INHALATION CY-TM-170-300 Revision 5 Page 160 of 222 H-3 O.OOE+OO 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 C-14 1.82E+04 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 CR-51 O.OOE+OO O.OOE+OO 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 O.OOE+OO 3.96E+04 6.30E+03 O.OOE+OO 9.84E+03 1.40E+06 7.74E+04 FE-55 2.46E+04 1.70E+04 3.94E+03 O.OOE+OO O.OOE+OO 7.21E+04 6.03E+03 FE-59 1.18E+04 2.78E+04 1.06E+04 O.OOE+OO O.OOE+OO 1.02E+06 1.88E+05

---

*

C0-58 O.OOE+OO 1.58E+03 2.07E+03 O.OOE+OO O.OOE+OO 9.28E+05 1.06E+05 C0-60 O.OOE+OO 1.15E+04 1.48E+04 O.OOE+OO O.OOE+OO 5.97E+06 2.85E+05 Nl-63 4.32E+05 3.14E+04 1.45E+04 O.OOE+OO O.OOE+OO 1.78E+05 1.34E+04 ZN-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+OO 6.90E+04 8.64E+05 5.34E+04 RB-86 O.OOE+OO 1.35E+05 5.90E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.66E+04 SR-89 3.04E+05 O.OOE+OO 8.72E+03 O.OOE+OO O.OOE+OO 1.40E+06 3.50E+05

---

*

SR-90 Y-91 ZR-95 NB-95

• RU-103 RU-106 9.92E+07 4.62E+05 1.07E+05 1.41E+04 1.53E+03 6.91E+04 AG-11 OM 1.08E+04 TE-125M 3.42E+03 TE-127M 1.26E+04 O.OOE+OO 6.10E+06 O.OOE+OO O.OOE+OO 1.24E+04 O.OOE+OO 3.44E+04 2.33E+04 O.OOE+OO 7.82E+03 4.21 E+03 O.OOE+OO O.OOE+OO 6.58E+02 O.OOE+OO O.OOE+OO 8.72E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.42E+04 7.74E+03 5.83E+03 1.34E+05 9.60E+06 1.70E+06 1.77E+06 5.05E+05 5.05E+05 9.36E+06 1.00E+04 5.94E+03 1.58E+03 4.67E+02 5.77E+03 1.57E+03 O.OOE+OO 1.97E+04 4.63E+06 1.05E+03 1.24E+04 3.14E+05 3.29E+03 4.58E+04 9.60E+05

-7.22E+05 3.85E+05 1.50E+05 1.04E+05 1.10E+05 9.12E+05 3.02E+05 7.06E+04 1.50E+05

---

*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 3.73E+05 8.48E+05 7.28E+05 O.OOE+OO 2.87E+05 3.90E+04 1.46E+05 1.10E+05 O.OOE+OO 8.56E+04 4.78E+05 6.21E+05 4.28E+05 O.OOE+OO 2.22E+05 1.16E+06 3.83E+05 O.OOE+OO 6.28E+03 O.OOE+OO 8.88E+03 9.76E+04 1.04E+04 1.20E+04 1.17E+04 7.52E+04 8.40E+03

---

*

BA-140 3.90E+04 4.90E+01 2.57E+03 O.OOE+OO 1.67E+01 1.27E+06 2.18E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 O.OOE+OO 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 O.OOE+OO 8.48E+05 7.78E+06 8.16E+05

---

*

PR-143 9.36E+03 3.75E+03 4.64E+02 O.OOE+OO 2.16E+03 2.81E+05 2.00E+05 ND-147 5.27E+03 6.10E+03 3.65E+02 O.OOE+OO 3.56E+03 2.21 E+05 1.73E+05 TABLE 5.3.1 Pathway Dose Factors, Ri AGE GROUP: ALL PATHWAY: GROUND PLANE CY-TM-170-300 Revision 5 Page 161 of 222 ---------------------------------------------------------r-----------------

---

ORGAN DOSE FACTORS* N UCL I DE ------------------------------------------- 1 I T.BODY SKIN ! I 1------------------

---

1

! H-3 O.OOE+OO O.OOE+OO ! i C-14 O.OOE+OO O.OOE+OO i i CR-51 4.65E+06 5.50E+06 i l--------------------------------------------------------------1 ! MN-54 1.39E+09 1.62E+09 ! i FE-55 O.OOE+OO O.OOE+OO i i FE-59 2.73E+08 3.21 E+08 i l--------------------------------------------------------------1 ! C0-58 3.79E+08 4.44E+08 ! i C0-60 2.15E+10 2.53E+10 i i Nl-63 O.OOE+OO O.OOE+OO i l--------------------------------------------------------------1 ! ZN-65 7.47E+08 8.59E+08 ! i RB-86 8.97E+06 1.03E+07 i i SR-89 2.16E+04 2.51 E+04 i l--------------------------------------------------------------1 ! SR-90 O.OOE+OO O.OOE+OO ! i Y-91 1.07E+06 1.21 E+06 i i ZR-95 2.45E+08 2.84E+08 i l--------------------------------------------------------------1 ! NB-95 1.37E+08 1.61 E+08 ! i RU-103 1.08E+08 1.26E+08 i i RU-106 4.22E+08 5.06E+08 i l--------------------------------------------------------------1 ! AG-11 OM 3.44E+09 4.01 E+09 ! i TE-125M 1.55E+06 2.13E+06 i i TE-127M 9.17E+04 1.08E+05 i l--------------------------------------------------------------1 ! TE-129M 1.98E+07 2.31 E+07 ! i 1-131 1.72E+07 2.09E+07 i i 1-133 2.45E+06 2.98E+06 i l--------------------------------------------------------------1 ! CS-134 6.86E+09 8.00E+09 ! i CS~136 1.51E+08 1.71E+08 i i CS-137 1.03E+10 1.20E+10 i l--------------------------------------------------------------1 ! BA-140 2.06E+07 2.36E+07 ! i CE-141 1.37E+07 1.54E+07 i i CE-144 6.96E+07 8.05E+07 i t--------------------------------------------------------------1 i PR-143 O.OOE+OO O.OOE+OO i i ND-147 8.39E+06 1.01 E+07 i I I L-------------------------------------------------------------J

• m2 -mrem/year per µCi/sec.

TABLE 5.4.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK CY-TM-170-300 Revision 5 Page 162 of 222 H-3 O.OOE+OO 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+OB 5.00E+OB 5.00E+08 5.00E+OB CR-51 O.OOE+OO O.OOE+OO 1.61 E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 O.OOE+OO 1.35E+08 2.25E+08 O.OOE+OO O.OOE+OO 3.50E+10 3.91 E+07 8.85E+06 8.74E+07 2.34E+07 3.93E+08 1.55E+08 2.43E+07 6.06E+07 8.83E+07 2.08E+08 2.16E+09 1.21E+09 O.OOE+OO O.OOE+OO O.OOE+OO O .. OOE+OO O.OOE+OO O.OOE+OO 8.65E+06 O.OOE+OO O.OOE+OO 4.27E+07 O.OOE+OO 1.16E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.43E+07 1.11 E+07 1.88E+08 6.05E+07 2.10E+08 1.08E+08

---

*

ZN-65 5.56E+09 1.91E+10 8.79E+09 O.OOE+OO 9.24E+09 O.OOE+OO 1.61E+10 RB-86 O.OOE+OO 2.23E+10 1.10E+10 O.OOE+OO O.OOE+OO O.OOE+OO 5.70E+08 SR-89 1.26E+10 O.OOE+OO 3.62E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.59E+08

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 AG-110M TE-125M TE-127M 1.22E+11 O.OOE+OO 3.10E+10 O.OOE+OO O.OOE+OO 7.34E+04 O.OOE+OO 1.95E+03 O.OOE+OO O.OOE+OO 6.81 E+03 1.66E+03 1.18E+03 O.OOE+OO 1.79E+03 5.94E+05 2.45E+05 1.41 E+05 O.OOE+OO

1. 75E+05 8.68E+03 O.OOE+OO 2.90E+03 O.OOE+OO 1.81 E+04 1.91 E+05 O.OOE+OO 2.38E+04 O.OOE+OO 2.25E+05 3.86E+08 2.82E+08 1.87E+08 O.OOE+OO 4.03E+08 1.51E+08 5.05E+07 2.04E+07 5.08E+07 O.OOE+OO 4.22E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 O.OOE+OO 1.52E+09 O.OOE+OO 5.26E+06 O.OOE+OO 8.27E+05 O.OOE+OO 2.07E+08 O.OOE+OO 1.06E+05 O.OOE+OO 1.45E+06 O.OOE+OO 1.46E+10 O.OOE+OO 7.19E+07 O.OOE+OO 1.70E+08

---

*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 5.58E+08 1.91E+08 8.59E+07 2.14E+08 1.39E+09 O.OOE+OO 2.72E+09 3.21 E+09 1.41E+09 1.05E+12 3.75E+09 O.OOE+OO 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 O.OOE+OO 3.65E+10 6.81E+10 6.88E+09 O.OOE+OO 1.75E+10 7.19E+09 1.98E+09 5.83E+09 2.18E+09 O.OOE+OO 2.32E+09

4. 75E+08 5.15E+10 6.03E+10 4.27E+09 O.OOE+OO 1.62E+10 6.55E+09 2..42E+08 2.42E+05 1.25E+07 O.OOE+OO 5.75E+04 4.34E+04 2.65E+04 3.12E+03 O.OOE+OO 8.17E+03 2.33E+06 9.53E+05 1.30E+05 O.OOE+OO 3.85E+05 1.49E+05 O.OOE+OO O.OOE+OO 3.33E+08 1.15E+08 8.96E+06 1.85E+08 8.85E+07 1.89E+08 5.94E+07 1.37E+07 1.34E+08 PR-143 1.49E+03 5.56E+02 7.37E+01 O.OOE+OO 2.07E+02 O.OOE+OO 7.84E+05 ND-147 8.83E+02 9.07E+02 5.55E+01 O.OOE+OO 3.50E+02 O.OOE+OO 5.75E+05 TABLE 5.4.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY:

GRASS-COW-MILK CY-TM-170-300 Revision 5 Page 163 of 222 H-3 O.OOE+OO 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 CR-51 O.OOE+OO O.OOE+OO 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 1.12E+08 1.20E+08 2.1 OE+07 5.59E+06 5.94E+07 1.84E+07 1.95E+08 ' 9. 70E+07 O.OOE+OO 1.21 E+07 3. 72E+07 O.OOE+OO 4.32E+07 1.27E+08 2.97E+10 1.59E+09 1.01 E+09 4.14E+09 1.10E+10 6.86E+09 O.OOE+OO 8.78E+09 5.40E+09 6.63E+09 O.OOE+OO 1.89E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.89E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.95E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.36E+07 5.65E+07 1.76E+07 1.10E+07 2.03E+08 O.OOE+OO 7.08E+07 O.OOE+OO 2.39E+08 O.OOE+OO 1.07E+08 O.OOE+OO 1.94E+09 O.OOE+OO 5.65E+08 O.OOE+OO 2.57E+08

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 1.12E+11 3.91E+04 3.84E+03 3.18E+05 4.29E+03 9.25E+04 O.OOE+OO 2.84E+10 O.OOE+OO 1.05E+03 8.43E+02 7.51 E+02 1.24E+05 8.86E+04 O.OOE+OO 1.65E+03 O.OOE+OO 1.15E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.21E+03 1.16E+05 1.08E+04 1.25E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO AG-11 OM 2.09E+08 1.41 E+OB 1.13E+08 O.OOE+OO 2.63E+08 O.OOE+OO TE-125M 7.39E+07 2.00E+07 9.85E+06 2.07E+07 O.OOE+OO O.OOE+OO TE-127M 2.0BE+OB 5.61 E+07 2.47E+07 4.98E+07 5.94E+08 O.OOE+OO TE-129M 1-131 1-133 CS-134 CS-136 CS-137 2.72E+08 7.59E+07 4.22E+07 8.76E+07 1.31 E+09 1.31 E+09 7.46E+08 4.34E+11

1. 72E+07 2.13E+07 8.05E+06 3.95E+09 2.27E+10 3.72E+10 7.85E+09 O.OOE+OO 1.01E+09 2.79E+09 1.80E+09 O.OOE+OO 3.23E+10 3.09E+10 4.56E+09 O.OOE+OO 7.98E+08 2.16E+09 3.55E+07 1.15E+10 1.49E+09 1.01E+10 O.OOE+OO O.OOE+OO O.OOE+OO 4.14E+09 2.21 E+OB 3.62E+09 1.51 E+09 5.21 E+06 8.80E+05 2.29E+08 1.11 E+05 1.44E+06 1.68E+10 7.13E+07 1.69E+08 3.31 E+OB 1.17E+08 8.58E+06 2.01E+08 9.80E+07 1.93E+08

---

*

BA-140 1.18E+08 1.03E+05 6.86E+06 O.OOE+OO 3.35E+04 6.14E+04 5.96E+07 CE-141 2.19E+04 1.09E+04 1.62E+03 O.OOE+OO 4.79E+03 O.OOE+OO 1.36E+07 CE-144 1.63E+06 5.09E+05 8.67E+04 O.OOE+OO 2.82E+05 O.OOE+OO 1.33E+08 PR-143 7.18E+02 2.16E+02 3.56E+01 O.OOE+OO 1.17E+02 O.OOE+OO 7.75E+05 ND-147 4.45E+02 3.61 E+02 2.79E+01 O.OOE+OO 1.98E+02 O.OOE+OO 5.71 E+05 ' -------------------------------------------------------------------------------------------------------------------------------------------------------- TABLE 5.4.3 Pathway Dose Factors, Ri CY-TM-170-300 Revision 5 Page 164 of 222 AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK ~y~~~~t=:i;i::=: H-3 O.OOE+OO 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 C-14 4.86E+08 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 CR-51 O.OOE+OO O.OOE+OO 4.99E+04

2. 77E+04 1.09E+04 7.13E+04 8.39E+06 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 4.46E+07 5.19E+07 O.OOE+OO O.OOE+OO 1.18E+10 2.11E+09 O.OOE+OO 2.68E+09 1.40E+07

2. 78E+06 3.16E+07 7.37E+06 1.21 E+08 4.68E+07 7.94E+06 1.83E+07

2. 78E+07 6.27E+07 8.36E+08 4.01 E+08 7.32E+09 3.42E+09 4.73E+09 2.22E+09 O.OOE+OO 7.67E+07 O.OOE+OO 4.19E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO 4.69E+09 O.OOE+OO 0.00E+OO O.OOE+OO 2.88E+07 2.01 E+07 1.37E+07 3.82E+07 2.86E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.10E+08 3.62E+08 1.33E+08 3.10E+09 7.00E+08 3.19E+08

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 6.62E+10 1.58E+04 1.65E+03 1.41 E+OS 1.81E+03 3.76E+04 AG-11 OM 9.64E+07 TE-125M 3.01E+07 TE-127M 8.45E+07 TE-129M 1.10E+08 1-131 5.38E+08 1-133 7.08E+06 O.OOE+OO 1.63E+10 O.OOE+OO O.OOE+OO O.OOE+OO 4.24E+02 O.OOE+OO O.OOE+OO 5.21 E+02 3.58E+02 O.OOE+OO 7.65E+02 7.82E+04 4.30E+04 O.OOE+OO 7.58E+04 O.OOE+OO 7.75E+02 O.OOE+OO 6.39E+03 O.OOE+OO 4.73E+03 O.OOE+OO 7.24E+04 9.12E+07 5.55E+07 O.OOE+OO 1.08E+07 4.02E+06 8.40E+06 3.00E+07 1.00E+07 2.01 E+07 4.09E+07 1.74E+07 3.56E+07 7.53E+08 4.05E+08 2.20E+11 1.20E+07 3.66E+06 1.68E+09 1.74E+08 0.00E+OO 3.42E+08 4.61 E+08 1.30E+09 2.11 E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1".86E+09 6.48E+06 1.20E+06 3.34E+08 1.51E+05 1.80E+06 O.OOE+OO 2.56E+10 O.OOE+OO 8.87E+07 O.OOE+OO 2.11E+08 O.OOE+OO 4.14E+08 O.OOE+OO 1.49E+08 O.OOE+OO 9.09E+06

---

*

CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 9.83E+09 4.49E+08 1.34E+10 4.87E+07 8.89E+03 6.59E+05 2.31 E+10 1.77E+09 1.78E+10 5.97E+04 5.94E+03 2.73E+05 1.07E+10 1.19E+09 6.21E+09 3.14E+06 6.82E+02 3.54E+04 O.OOE+OO 7.35E+09 2.81 E+09 O.OOE+OO 9.63E+08 1.52E+08 O.OOE+OO 6.06E+09 2.36E+09 O.OOE+OO 2.02E+04 4.01 E+04 O.OOE+OO 2.80E+03 O.OOE+OO O.OOE+OO 1.63E+05 O.OOE+OO 2.88E+08 1.42E+08 2.54E+08 7.51 E+07 1.70E+07 1.66E+08 PR-143 2.90E+02 1.16E+02 1.44E+01 O.OOE+OO 6.73E+01 O.OOE+OO 9.55E+05 ND-147 1.81 E+02 1.97E+02 1.18E+01 O.OOE+OO 1.16E+02 O.OOE+OO 7.12E+05 TABLE 5.4.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK CY-TM-170-300 Revision 5 Page 165 of 222 BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

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*

H-3 O.OOE+OO 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 C-14 2.63E+08 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 CR-51 O.OOE+OO O.OOE+OO 2.85E+04

1. 70E+04 6.28E+03

3. 78E+04 7.17E+06 MN-54 O.OOE+OO 8.40E+06 1.60E+06 O.OOE+OO 2.50E+06 O.OOE+OO 2.57E+07 FE-55 2.51E+07 1.73E+07 4.04E+06 O.OOE+OO O.OOE+OO 9.66E+06 9.93E+06 FE-59 2.97E+07 6.97E+07 2.67E+07 O.OOE+OO O.OOE+OO 1.95E+07 2.32E+08

---

*

C0-58 O.OOE+OO 4.71E+06 1.05E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.54E+07 C0-60 O.OOE+OO 1.64E+07 3.61E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.08E+08 Nl-63 6.72E+09 4.65E+08 2.25E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.71E+07 ZN-65 1.37E+09 4.36E+09 1.97E+09 O.OOE+OO 2.91E+09 O.OOE+OO 2.74E+09 RB-86 O.OOE+OO 2.59E+09 1.21 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.10E+08 SR-89 1.45E+09 O.OOE+OO 4.16E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+08

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 4.67E+10 O.OOE+OO 1.15E+10 O.OOE+OO O.OOE+OO 8.57E+03 O.OOE+OO 2.29E+02 O.OOE+OO O.OOE+OO 9.41 E+02 3.02E+02 2.04E+02 O.OOE+OO 4.74E+02 8.24E+04 4.58E+04 2.46E+04 O.OOE+OO 4.53E+04 1.02E+03 O.OOE+OO 4.38E+02 O.OOE+OO 3.88E+03 2.04E+04 O.OOE+OO 2.58E+03 O.OOE+OO 3.93E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.35E+09 4.72E+06 9.57E+05 2.78E+08 1.19E+05 1.32E+06 AG-110M 5.81E+07 5.38E+07 3.19E+07 O.OOE+OO 1.06E+08 O.OOE+OO 2.19E+10 TE-125M 1.63E+07 5.89E+06 2.18E+06 4.89E+06 6.61 E+07 O.OOE+OO 6.49E+07 TE-127M 4.57E+07 1.63E+07 5.57E+06 1.17E+07 1.86E+08 O.OOE+OO 1.53E+08 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 6.01 E+07 2.24E+07 9.51 E+06 2.06E+07 2.51 E+08 2.96E+08 4.23E+08 2.42E+08 1.39E+11 7.25E+08 3.87E+06 6.73E+06 2.05E+06 9.88E+08 1.17E+07 5.64E+09 1.34E+10 1.10E+10 O.OOE+OO 4.34E+09 2.63E+08 1.04E+09 7.48E+08 O.OOE+OO 5.78E+08 7.37E+09 1.01E+10 6.60E+09 O.OOE+OO 3.42E+09 O.OOE+OO 3.02E+08 O.OOE+OO 1.12E+08 O.OOE+OO 6.04E+06 1.44E+09 2.35E+08 7.92E+07 1.18E+08 1.14E+09 1.95E+08

---

*

BA-140 2.69E+07 3.38E+04 1.76E+06 O.OOE+OO 1.15E+04 1.94E+04 5.54E+07 CE-141 4.84E+03 3.27E+03 3.71 E+02 O.OOE+OO 1.52E+03 O.OOE+OO 1.25E+07 CE-144 3.57E+05 1.49E+05 1.92E+04 O.OOE+OO 8.85E+04 O.OOE+OO 1.21E+08 PR-143 1.57E+02 6.32E+01 7.81 E+OO O.OOE+OO 3.65E+01 O.OOE+OO 6.90E+05 ND-147 9.40E+01 1.09E+02 6.50E+OO O.OOE+OO 6.35E+01 O.OOE+OO 5.22E+05 TABLE 5.5.1 Pathway Dose Factors, Ri C AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK CY-TM-170-300 Revision 5 Page 166 of 222 --~-~~-~~~~-1-~----------------~-~~~~§-~~~~~~~~~-~~-~i~~~;~~~~~~~!~~7X~~~-E~~~~[[~-~-~~~~~~~~------------------: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU ------------------

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*

H-3 O.OOE+OO 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 CR-51 O.OOE+OO O.OOE+OO 1.94E+04 1.26E+04

2. 76E+03 2.46E+04 5.64E+05 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 4.68E+06

1. 76E+06 1.14E+06 2.92E+06 5.1 OE+06 1.06E+06 3.03E+05 2.01 E+06 O.OOE+OO O.OOE+OO 4.19E+09 2.91 E+06 7.26E+06 1.06E+07 2.50E+07 2.59E+08 1.46E+08 6.67E+08 2.29E+09 1.05E+09 O.OOE+OO 2.67E+09 1.32E+09 2.65E+10 O.OOE+OO 7.59E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.11E+09 O.OOE+OO O.OOE+OO O.OOE+OO

1. 72E+06 5.55E+05 1.44E+05 1.51 E+06 2.44E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.25E+06 2.52E+07 1.29E+07 1.93E+09 6.83E+07 5.44E+08

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*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 AG-110M TE-125M TE-127M 2.55E+11 8.80E+03 8.17E+02 7.13E+04 1.04E+03 2.28E+04 4.63E+07 1.81 E+07 5.06E+07 O.OOE+OO 6.50E+10 O.OOE+OO 2.34E+02 1.99E+02 1.41E+02 2.93E+04

1. 70E+04 O.OOE+OO 3.48E+02 O.OOE+OO 2.85E+03 3.38E+07 2.24E+07 6.05E+06 2.45E+06 1.68E+07 6.12E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.15E+02 O.OOE+OO 2.1 OE+04 O.OOE+OO 2.17E+03 O.OOE+OO

2. 70E+04 O.OOE+OO 4.84E+07 6.09E+06 O.OOE+OO 1.46E+07 1.24E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.19E+09 6.31E+05 9.91E+04 2.48E+07 1.27E+04 1.73E+05 1.75E+09 8.62E+06 2.04E+07

---

*

TE-129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 O.OOE+OO 3.99E+07 1-131 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 O.OOE+OO 1.37E+08 1-133 4.36E+07 6.35E+07 1.86E+07 1.15E+10 7.46E+07 O.OOE+OO 1.07E+07 CS-134 1.09E+11 2.04E+11 2.06E+10 O.OOE+OO 5.26E+10 2.15E+10 5.55E+08 CS-136 5.94E+09 1.75E+10 6.52E+09 O.OOE+OO 6.96E+09 1.42E+09 2.65E+08 CS-137 1.54E+11 1.81E+11 1.28E+10 O.OOE+OO 4.85E+10 1.96E+10 5.65E+08

---

*

BA-140 CE-141 CE-144 PR-143 ND-147 2.90E+07 2.90E+04 1.50E+06 O.OOE+OO 6.89E+03 1.78E+04 7.13E+06 5.21 E+03 3.18E+03 3.74E+02 O.OOE+OO 9.79E+02 O.OOE+OO 1.64E+06 2.79E+05 1.14E+05 1.56E+04 O.OOE+OO 4.62E+04 O.OOE+OO 1.60E+07

1. 78E+02 6.66E+01 8.83E+OO O.OOE+OO 2.48E+01 O.OOE+OO 9.40E+04 1.06E+02 1.09E+02 6.66E+OO O.OOE+OO 4.19E+01 O.OOE+OO 6.89E+04 TABLE 5.5.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY:

GRASS-GOAT-MILK CY-TM-170-300 Revision 5 Page 167 of 222

• BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU ------------------

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*

H-3 O.OOE+OO 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 CR-51 O.OOE+OO O.OOE+OO 1.22E+04

6. 78E+03 1.85E+03 1.24E+04 6.48E+05 MN-54 O.OOE+OO 2.52E+06 6.71 E+05 O.OOE+OO 7.06E+05 O.OOE+OO 2.11 E+06 FE-55 1.45E+06 7.71E+05 2.39E+05 O.OOE+OO O.OOE+OO 4.36E+05 1.43E+05 FE-59 1.56E+06 2.53E+06 1.26E+06 O.OOE+OO O.OOE+OO 7.34E+05 2.64E+06

---

*

C0-58 . O.OOE+OO 1.46E+06 4.46E+06 O.OOE+OO O.OOE+OO O.OOE+OO 8.49E+06 C0-60 O.OOE+OO 5.18E+06 1.53E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+07 Nl-63 3.56E+09 1.91 E+08 1.21E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.28E+07 ZN-65 4.96E+08 1.32E+09 8.22E+08 O.OOE+OO 8.33E+08 O.OOE+OO 2.32E+08 RB-86 O.OOE+OO 1.05E+09 6.47E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.77E+07 SR-89 1.39E+10 O.OOE+OO 3.97E+08 O.OOE+OO O.OOE+OO O.OOE+OO 5.39E+08

---

*

SR-90 2.35E+11 O.OOE+OO 5.95E+10 O.OOE+OO O.OOE+OO O.OOE+OO 3.16E+09 Y-91 4.69E+03 O.OOE+OO 1.25E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+05 ZR-95 4.60E+02 1.01E+02 9.00E+01 O.OOE+OO 1.45E+02 O.OOE+OO 1.05E+05 NB-95 3.82E+04 1.49E+04 1.06E+04 O.OOE+OO 1.40E+04 O.OOE+OO 2.75E+07 RU-103 5.14E+02 O.OOE+OO 1.98E+02 O.OOE+OO 1.29E+03 O.OOE+OO 1.33E+04 RU-106 1.11 E+04 O.OOE+OO 1.38E+03 O.OOE+OO 1.50E+04 O.OOE+OO 1.73E+05

---

*

AG-110M 2.51E+07 1.69E+07 1.35E+07 O.OOE+OO 3.15E+07 O.OOE+OO 2.01E+09 TE-125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 O.OOE+OO O.OOE+OO 8.55E+06 TE-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 O.OOE+OO 2.02E+07 TE-129M 3.26E+07 9.10E+06 5.06E+06 1.05E+07 9.56E+07 O.OOE+OO 3.97E+07 1-131 1.57E+09 1.57E+09 8.95E+08 5.21 E+11 2,58E+09 O.OOE+OO 1.40E+08 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 O.OOE+OO 1.03E+07

---

*

CS-134 6.80E+10 1.12E+11 2.35E+10 O.OOE+OO 3.46E+10 1.24E+10 6.01E+08 CS-136 3.04E+09 8.36E+09 5.41 E+09 O.OOE+OO 4.45E+09 6.64E+08 2.94E+08 CS-137 9.68E+10 9.26E+10 1.37E+10 O.OOE+OO 3.02E+10 1.09E+10 5.80E+08

---

*

BA-140 1.41E+07 1.24E+04 8.23E+05 O.OOE+OO 4.02E+03 7.37E+03 7.15E+06 CE-141 2.63E+03 1.31E+03 1.95E+02 O.OOE+OO 5.74E+02 O.OOE+OO 1.63E+06 CE-144 1.95E+05 6.11 E+04 1.04E+04 O.OOE+OO 3.38E+04 O.OOE+OO 1.59E+07 PR-143 8.61 E+01 2.59E+01 4.27E+OO O.OOE+OO 1.40E+01 O.OOE+OO 9.29E+04 ND-147 5.34E+01 4.33E+01 3.35E+OO O.OOE+OO 2.37E+01 O.OOE+OO 6.85E+04 TABLE 5.5.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK CY-TM-170-300 Revision 5 Page 168 of 222 H-3 O.OOE+OO 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 CR-51 O.OOE+OO O.OOE+OO 5.99E+03 3.33E+03 1.31 E+03 8.55E+03 1.01 E+06 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 O.OOE+OO 1.68E+06 3.34E+05

5. 79E+05 4.11 E+05 9.58E+04

6. 7 4E+05 1.57E+06 6.08E+05 O.OOE+OO O.OOE+OO 1.42E+09 9.53E+05 2.20E+06 3.34E+06 7.52E+06 1.00E+08 4.81 E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.02E+05 O.OOE+OO O.OOE+OO 2.61 E+05 O.OOE+OO 4.96E+05 3.45E+06 1.78E+05 3.72E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.31 E+07 O.OOE+OO 4.35E+07 O.OOE+OO 1.60E+07

---

*

ZN-65 2.53E+08 8.78E+08 4.10E+08 O.OOE+OO 5.62E+08 O.OOE+OO 3.72E+08 RB-86 O.OOE+OO 5.67E+08 2.67E+08 O.OOE+OO O.OOE+OO O.OOE+OO 8.40E+07 SR-89 5.62E+09 O.OOE+OO 1.61 E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.69E+08

---

.. ---------------------------------------------------------------------------------------------------------------------------------------------* SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 1.39E+11 1.90E+03 1.98E+02 1.69E+04 2.17E+02 4.50E+03 O.OOE+OO O.OOE+OO 6.25E+01 9.38E+03 O.OOE+OO O.OOE+OO 3.43E+10 5.09E+01 4.30E+01 5.16E+03 9.29E+01 5.68E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.18E+01 O.OOE+OO 9.09E+03 O.OOE+OO 7.66E+02 O.OOE+OO 8.69E+03 O.OOE+OO 3.90E+09 O.OOE+OO 7.78E+05 O.OOE+OO 1.44E+05 O.OOE+OO 4.01 E+07 O.OOE+OO 1.82E+04 O.OOE+OO 2.16E+05 AG-110M 1.16E+07 1.09E+07 6.65E+06 1.30E+06 4.82E+05 3.59E+06 1.20E+06 O.OOE+OO 2.09E+07 1.01 E+06 O.OOE+OO 2.41E+06 4.11E+07 O.OOE+OO 3.07E+09 TE-125M 3.61 E+06 O.OOE+OO 1.06E+07

• TE-127M 1.01 E+07 O.OOE+OO 2.52E+07 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 O.OOE+OO 4.96E+07 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 O.OOE+OO 1.79E+08 8.49E+06 1.44E+07 4.40E+06 2.01 E+09 2.53E+07 O.OOE+OO 1.09E+07 2.95E+10 6.93E+10 3.22E+10 O.OOE+OO 2.20E+10 8.41 E+09 8.62E+08 1.35E+09 5.30E+09 3.56E+09 O.OOE+OO 2.89E+09 4.55E+08 4.27E+08 4.02E+10 5.34E+10 1.86E+10 O.OOE+OO 1.82E+10 7.07E+09 7.60E+08 5.84E+06 1.07E+03 7.90E+04 7.16E+03 3.76E+05 7.12E+02 8.18E+01 3.27E+04 4.25E+03 O.OOE+OO 2.43E+03 4.81 E+03 O.OOE+OO 3.35E+02 O.OOE+OO O.OOE+OO 1.95E+04 O.OOE+OO 9.01E+06 2.04E+06 1.99E+07 PR-143 3.48E+01 1.39E+01 1.73E+OO O.OOE+OO 8.08E+OO O.OOE+OO 1.15E+05 ND-147 2.18E+01 2.37E+01 1.42E+OO O.OOE+OO 1.39E+01 O.OOE+OO 8.54E+04 TABLE 5.5.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY:

GRASS-GOAT-MILK CY-TM-170-300 Revision 5 Page 169 of 222 --~-~~-~~~;-I-~----------------~~~~~~§B~~~~~~~~-~~~i~~~;~~~~~~~~~~~i1-~~~-P-~~~~~~-~-~~~~~~~~------------------: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

---

*

H-3 O.OOE+OO 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 C-14 2.64E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 CR-51 O.OOE+OO O.OOE+OO 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 MN-54 O.OOE+OO 1.01 E+06 1.93E+05 O.OOE+OO 3.01 E+05 O.OOE+OO 3.10E+06 FE-55 3.27E+05 2.26E+05 5.26E+04 O.OOE+OO O.OOE+OO 1.26E+05 1.30E+05 FE-59 3.87E+05 9.09E+05 3.48E+05

• O.OOE+OO O.OOE+OO 2.54E+05 3.03E+06

---

*

C0-58 O.OOE+OO 5.66E+05 1.27E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+07 C0-60 O.OOE+OO 1.97E+06 4.35E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+07 Nl-63 8.08E+08 5.60E+07 2.71 E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E+07

---

*

ZN-65 1.65E+08 5.24E+08 2.37E+08 O.OOE+OO 3.51E+08 O.OOE+OO 3.30E+08 RB-86 O.OOE+OO 3.12E+08 1.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.14E+07 SR-89 3.05E+09 O.OOE+OO 8.76E+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.89E+08

---

*

SR-90 9.84E+10 O.OOE+OO 2.41 E+10 O.OOE+OO 0.00E+OO O.OOE+OO 2.84E+09 Y-91 1.03E+03 O.OOE+OO 2.76E+01 O.OOE+OO O.OOE+OO O.OOE+OO 5.68E+05 ZR-95 1.13E+02 3.63E+01 2.46E+01 O.OOE+OO 5.70E+01 O.OOE+OO 1.15E+05 NB-95 9.92E+03 5.52E+03 2.97E+03 O.OOE+OO 5.45E+03 O.OOE+OO 3.35E+07 RU-103 1.22E+02 O.OOE+OO 5.27E+01 O.OOE+OO 4.67E+02 O.OOE+OO 1.43E+04 RU-106 2.45E+03 O.OOE+OO 3.10E+02 O.OOE+OO 4.73E+03 O.OOE+OO 1.59E+05

---

*

AG-110M 6.99E+06 6.47E+06 3.84E+06 O.OOE+OO 1.27E+07 O.OOE+OO 2.64E+09 TE-125M 1.96E+06 7.09E+05 2.62E+05 5.89E+05 7.96E+06 O.OOE+OO 7.81E+06 TE-127M 5.50E+06 1.97E+06 6.70E+05 1.41E+06 2.23E+07 O.OOE+OO 1.84E+07

---

*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 PR-143 ND-147 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.56E+08 5.09E+08 2.92E+08 1.67E+11 4.65E+06 8.10E+06 2.47E+06 1.19E+09 1.70E+10 4.04E+10 3.30E+10 O.OOE+OO 7.92E+08 3.13E+09 2.25E+09 O.OOE+OO 2.22E+10 3.03E+10 1.99E+10 O.OOE+OO 3.24E+06 4.07E+03 2.12E+05 5.82E+02 3.94E+02 4.47E+01 4.30E+04 1.80E+04 2.31 E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.02E+07 O.OOE+OO 8.73E+08 O.OOE+OO 1.41E+07 O.OOE+OO 1.31E+10 4.34E+09 1.74E+09 2.38E+08 1.03E+10 3.42E+09 1.38E+03 1.83E+02 1.07E+04 2.33E+03 O.OOE+OO O.OOE+OO 3.64E+07 1.34E+08 7.28E+06 7.07E+08 3.55E+08 5.87E+08 6.67E+06 1.51E+06 1.45E+07 1.90E+01 7.60E+OO 9.40E-01 O.OOE+OO 4.39E+OO O.OOE+OO 8.30E+04 1.13E+01 1.31 E+01 7.82E-01 O.OOE+OO 7.65E+OO O.OOE+OO 6.28E+04 TABLE, 5.6.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT CY-TM-170-300 Revision 5 Page 170 of 222 --~-~~-~~~~-I------------------~~~~~~§~~~~~Q9-~~-~~-~i~~~~~~~~~~~~~~!I~~~-E~~~~[i~~-~~~~~~~~------------------: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

---

*

H-3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C-14 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CR-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO MN-54 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO FE-55 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

---

*

C0-58 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C0-60 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nl-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . . -------------------------------------------------------------------------------------------------------------------------------------------------------* ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.001::+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.001::+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

---

*

AG-110M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-125M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-127M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

---

*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 O.OOE+OO O.QOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO b.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO PR-143 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND-147 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TABLE 5.6.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-COW-MEAT CY-TM-170-300 Revision 5 Page 171 of 222 ~0~~~E}i~i=~if~~~~~~~3~~~:[[~if§~E=~ii:= H-3 O.OOE+OO 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 C-14 3.84E+08 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 CR-51 O.OOE+OO O.OOE+OO

8. 78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 8.01 E+06 2.13E+06 O.OOE+OO 2.25E+06 4.57E+08 2.43E+08 7.52E+07 O.OOE+OO O.OOE+OO

3. 77E+08 6.1 OE+08 3.04E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.91 E+10 3.76E+08 O.OOE+OO 4.82E+08 1.64E+07 5.03E+07 6.93E+07 2.04E+08 1.56E+09 9.91 E+08 1.00E+09 6.22E+08 5.76E+08 3.54E+08 O.OOE+OO 1.38E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.31E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.73E+06 1.37E+08 4.49E+07 1.77E+08 6.35E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.58E+07 3.84E+08 1.05E+08 1.76E+08 3.71E+07 1.87E+07

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 AG-110M TE-125M TE-127M 1.04E+10 1.80E+06 2.66E+06 3.10E+06 1.55E+08 4.44E+09 8.39E+06 5.69E+08 1.78E+09 O.OOE+OO 2.64E+09 O.OOE+OO 4.82E+04 5.86E+05 5.21E+05 1.21 E+06 8.63E+05 O.OOE+OO 5.96E+07 O.OOE+OO 5.54E+08 5.67E+06 4.53E+06 1.54E+08 7.59E+07 4.78E+08 2.11 E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.38E+05 O.OOE+OO 1.13E+06 O.OOE+OO 3.90E+08 O.OOE+OO 6.00E+09 O.OOE+OO 1.06E+07 1.60E+08 O.OOE+OO 4.25E+08 5.06E+09 O.OOE+OO 1.40E+08 O.OOE+OO 2.40E+08 O.OOE+OO 6.11 E+08 O.OOE+OO 2.23E+09 O.OOE+OO 4.01 E+09 O.OOE+OO 6.91E+10 O.OOE+OO 6.74E+08 O.OOE+OO 5.49E+08 O.OOE+OO 1.44E+09

---

*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 1.79E+09 5.00E+08 2.78E+08 5.77E+08 5.26E+09 O.OOE+OO 2.18E+09 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 O.OOE+OO 1.48E+06 5.72E-01 7.08E-01 2.68E-01 1.31E+02 1.18E+OO O.OOE+OO 2.85E-01 9.23E+08 1.51 E+09 3.19E+08 O.OOE+OO 4.69E+08 1.68E+08 1.63E+07 4.48E+07 2.90E+07 O.OOE+OO 2.39E+07 3.56E+06 1.33E+09 1.28E+09 1.89E+08 O.OOE+OO 4.16E+08 1.50E+08 8.16E+06 1.57E+06 8.00E+06 4.42E+07 2.22E+04 2.32E+06 3.87E+04 2.58E+06 1.11 E+04 1.65E+03 7.26E+05 1.24E+05 O.OOE+OO 1.26E+04 O.OOE+OO 4.86E+03 O.OOE+OO 4.02E+05 2.31 E+04 2.24E+07 O.OOE+OO 1.38E+07 O.OOE+OO 1.89E+08 PR-143 3.33E+04 1.00E+04 1.65E+03 O.OOE+OO 5.42E+03 O.OOE+OO 3.60E+07 ND-147 1.17E+04 9.48E+03 7.34E+02 O.OOE+OO 5.20E+03 O.OOE+OO 1.50E+07 \ ' TABLE 5.6.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT CY-TM-170-300 Revision 5 Page 172 of 222 --~:;-~~~~-1-~----------------=~~~~~~~9-~~~~~~~-~~~i9.~~;~~~~~~~~!~~7i~~~-P-~~~~~~~~~~~~-~~------------------: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

---

*

H-3 O.OOE+OO 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 C-14 2.04E+08 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 CR-51 O.OOE+OO O.OOE+OO 5.63E+03 3.13E+03 1.23E+03 8.03E+03

• 9.46E+05 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 7.00E+06 1.39E+06 O.OOE+OO 2.09E+06 2.38E+08 1.69E+08 3.94E+07 O.OOE+OO O.OOE+OO 2.12E+08 4.95E+08 1.91 E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.52E+10 2.50E+08 O.OOE+OO 2.55E+08 1.40E+07 3.24E+07 5.83E+07 1.31 E+08 1.07E+09 5.15E+08 8.68E+08 4.05E+08 4.06E+08 1.91E+08 O.OOE+OO 7.29E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.56E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+08 1.56E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.44E+07 7.31E+07 1.17E+09 1.94E+08 7.60E+08 1.71 E+08 3.68E+08 6.00E+07 3.03E+07

---

*

SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 8.04E+09 9.54E+05 1.50E+06 1.79E+06 8.56E+07 2.36E+09 O.OOE+OO 1.99E+09 O.OOE+OO 2.56E+04 4.73E+05 3.25E+05 9.95E+05 5.48E+05 O.OOE+OO 3.66E+07 O.OOE+OO 2.97E+08 O.OOE+OO O.OOE+OO. O.OOE+OO O.OOE+OO O.OOE+OO 6.95E+05 O.OOE+OO 9.64E+05 O.OOE+OO 3.02E+08 O.OOE+OO 4.54E+09 O.OOE+OO 2.26E+08 O.OOE+OO 3.91E+08 O.OOE+OO 1.09E+09 O.OOE+OO 4.25E+09 O.OOE+OO 7.15E+09 O.OOE+OO 1.13E+11 AG-110M 5.06E+06 4.78E+06 2.91E+06 O.OOE+OO 9.13E+06 O.OOE+OO 1.34E+09 8.94E+08 2.35E+09 TE-125M 3.03E+08 1.09E+08 4.05E+07 8.46E+07 O.OOE+OO O.OOE+OO TE-127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.81E+09 O.OOE+OO TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 9.49E+08 8.93E+06 3.08E-01 5.23E+08 9.43E+06 7.24E+08 3.52E+08 1.50E+08 1.25E+07

6. 72E+06 5.22E-01 1.59E-01 1.23E+09 5.71 E+08 3.71 E+07 2.49E+07 9.63E+08 3.35E+08 3.06E+08 3.65E+09 7.29E+01 3.97E+09 2.15E+07 9.16E-01 O.OOE+OO 3.91 E+08 O.OOE+OO 2.02E+07 O.OOE+OO 3.28E+08 2.39E+07 2.93E+04 1.54E+06 O:OOE+OO 9.94E+03 1.18E+04 7.87E+03 9.05E+02 O.OOE+OO 3.71 E+03 1.23E+06 5.08E+05 6.60E+04 O.OOE+OO 3.03E+05 O.OOE+OO 3.56E+09 O.OOE+OO 2.47E+06 O.OOE+OO 3.95E-01 1.49E+08 1.53E+07 3.18E+06 2.99E+06 1.27E+08 1.37E+07 1.97E+04 3.69E+07 O.OOE+OO 2.25E+07 O.OOE+OO 3.09E+08 PR-143 1.76E+04 7.03E+03 8.76E+02 O.OOE+OO 4.08E+03 O.OOE+OO 5.79E+07 ND-147 6.23E+03 6.78E+03 4.06E+02 O.OOE+OO 3.98E+03 O.OOE+OO 2.44E+07 TABLE 5.6.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY:

GRASS-COW-MEAT CY-TM-170-300 Revision 5 Page 173 of 222 H-3 O.OOE+OO 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 C-14 2.42E+08 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 CR-51 O.OOE+OO O.OOE+OO 7.04E+03 4.21 E+03 1.55E+03 9.35E+03 1.77E+06 MN-54 O.OOE+OO 9.18E+06 1.75E+06 O.OOE+OO

• 2.73E+06 O.OOE+OO 2.81E+07 FE-55 2.93E+08 2.03E+08 4.73E+07 O.OOE+OO O.OOE+OO 1.13E+08 1.16E+08 FE-59 2.66E+08 6.25E+08 2.39E+08 O.OOE+OO O.OOE+OO 1.75E+08 2.08E+09

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*

C0-58 O.OOE+OO 1.82E+07 4.09E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+08 C0-60 O.OOE+OO 7.52E+07 1.66E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.41 E+09 Nl-63 1.89E+10 1.31E+09 6.33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.73E+08 ZN-65 3.56E+08 1.13E+09 5.12E+08 O.OOE+OO 7.57E+08 O.OOE+OO 7.13E+08 RB-86 O.OOE+OO 4.87E+08 2.27E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.59E+07 SR-89 3.02E+08 O.OOE+OO 8.66E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.84E+07

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*

SR-90 1.24E+10 . O.OOE+OO 3.05E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.60E+08 Y-91 1.13E+06 O.OOE+OO 3.03E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+08 ZR-95 1.87E+06 6.01E+05 4.07E+05 O.OOE+OO 9.43E+05 O.OOE+OO 1.90E+09

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*

NB-95 2.30E+06 1.28E+06 6.87E+05 O.OOE+OO 1.26E+06 O.OOE+OO 7.76E+09 RU-103 1.05E+08 O.OOE+OO 4.53E+07 O.OOE+OO 4.02E+08 O.OOE+OO 1.23E+10 RU-106 2.80E+09 O.OOE+OO 3.54E+08 O.OOE+OO 5.41E+09 O.OOE+OO 1.81E+11

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*

AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 6.68E+06 6,18E+06 3.67E+06 3.59E+08 1.30E+08 4.81 E+07 1.12E+09 3.99E+08 1.36E+08 1.13E+09 4.23E+08 1.79E+08 1.08E+07 1.54E+07 8.82E+06 3.68E-01 6.41 E-01 1.95E-01 O.OOE+OO 1.22E+07 1.08E+08 1.46E+09 2.85E+08 4.53E+09 3.89E+08 4.73E+09 5.04E+09 2.64E+07 9.42E+01 1.12E+OO 6.58E+08 1.57E+09 1.28E+09 O.OOE+OO 5.07E+08 1.21 E+07 4. 78E+07 3.44E+07 O.OOE+OO 2.66E+07

8. 72E+08 1.19E+09 7.82E+08 O.OOE+OO 4.05E+08 O.OOE+OO 2.52E+09 O.OOE+OO 1.43E+09 O.OOE+OO 3.74E+09 O.OOE+OO

5. 71 E+09 O.OOE+OO 4.06E+06 O.OOE+OO 5.76E-01 1.68E+08 3.65E+06 1.35E+08 2.74E+07 5.43E+06 2.31E+07 2.90E+07 3.64E+04 1.90E+06 O.OOE+OO 1.24E+04 2.08E+04 5.96E+07 1.41E+04 9.51E+03 1.08E+03 O.OOE+OO 4.42E+03 O.OOE+OO 3.64E+07 1.46E+06 6.10E+05 7.83E+04 O.OOE+OO 3.62E+05 O.OOE+OO 4.93E+08 PR-143 2.09E+04 8.40E+03 1.04E+03 O.OOE+OO 4.85E+03 O.OOE+OO 9.17E+07 ND-147 7.08E+03 8.18E+03 4.90E+02 O.OOE+OO 4.78E+03 O.OOE+OO 3.93E+07 TABLE 5.7.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY:

VEGETATION CY-TM-170-300 Revision 5 Page 174 of 222 ------------------1-------------------------------------------------------------------------------------------------- .-----------------------------------* ORGAN DOSE FACTORS; m2 -mrem/year per µCi/sec NU CL I DE ------------------------------------------------------------------------------------------------------------------------------------* BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

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*

H-3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C-14 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CR-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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*

SR-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO. Y-91 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ZR-95 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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*

NB-95 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-106 O.OOE+OO O.OOE+OO

• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO AG-110M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-125M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
• O.OOE+OO O.OOE+OO TE-127M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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*

TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO PR-143 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND-147 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TABLE 5.7.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: VEGETATION CY-TM-170-300 Revision 5 Page 175 of 222 H-3 O.OOE+OO 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 C-14 8.89E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 CR-51 O.OOE+OO O.OOE+OO 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 O.OOE+OO 6.65E+08 8.01 E+OS 4.25E+08 3.98E+08 6.44E+08 O.OOE+OO 6.44E+07 O.OOE+OO.

3. 78E+08 3.95E+10 2.11 E+09 1. 77E+08 O.OOE+OO 1.32E+08 O.OOE+OO 3.21 E+OS O.OOE+OO 1.97E+08 1.12E+09 1.34E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.86E+08 O.OOE+OO O.OOE+OO 2.40E+08 O.OOE+OO 1.87E+08 5.58E+08 7.87E+07 6.71E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. 76E+08 O.OOE+OO 2.1 OE+09 O.OOE+OO 1.42E+08 8.12E+08 2.16E+09 1.35E+09 O.OOE+OO 1.36E+09 O.OOE+OO 3.80E+08 2.90E+07 1.39E+09 O.OOE+OO 4.51 E+OS 2. 77E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.60E+10 O.OOE+OO 1.03E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.24E+12 1.87E+07 3.86E+06 4.11 E+05 1.53E+07 7.45E+08 O.OOE+OO 3.15E+11 O.OOE+OO 4.99E+05 8.48E+05 7.55E+05 1.60E+05 1.14E+05 O.OOE+OO 5.90E+06 O.OOE+OO 9.30E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.21E+06 1.50E+05 3.86E+07 1.01E+09 O.OOE+OO 1.67E+10 O.OOE+OO 2.49E+09 O.OOE+OO 8.85E+08 O.OOE+OO 2.96E+08 O.OOE+OO 3.97E+08 O.OOE+OO 1.16E+10

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*

AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 3.21E+07 2.17E+07 3.51E+08 9.50E+07 1.32E+09 3.56E+08 8.40E+08 2.35E+08 1.43E+08 1.44E+08 3.53E+06 4.37E+06 1.60E+10 2.63E+10 8.28E+07 2.28E+08 2.39E+10 2.29E+10 1.73E+07 O.OOE+OO 4.67E+07 9.84E+07 1.57E+08 3.16E+08 1.30E+08 2.71 E+OS 8.18E+07 4.76E+10 1.65E+06 8.12E+08 5.55E+09 1.47E+08 3.38E+09 O.OOE+OO O.OOE+OO O.OOE+OO

2. 79E+08 2.44E+05 1.63E+07 O.OOE+OO 6.57E+05 3.28E+05 4.86E+04 O.OOE+OO 1.27E+08 3.99E+07 6.79E+06 O.OOE+OO 4.04E+07 O.OOE+OO 3.77E+09 2.47E+09 2.36E+08 7.28E+06 8.15E+09 1.21E+08 7.46E+09 7.96E+04 1.44E+05 2.21E+07 O.OOE+OO O.OOE+OO O.OOE+OO.

O.OOE+OO O.OOE+OO O.OOE+OO 2.93E+09 1.81E+07 2.68E+09 2.58E+09 3.38E+08 1.07E+09 1.02E+09 1.28E+07 1.76E+06 1.42E+08 8.00E+06 1.43E+08 1.46E+05 1.41 E+OS O.OOE+OO 4.09E+08 O.OOE+OO 1.04E+10 PR-143 1.45E+05 4.36E+04 7.21 E+03 O.OOE+OO 2.36E+04 O.OOE+OO 1.57E+08 ND-147 7.15E+04 5.79E+04 4.49E+03 O.OOE+OO 3.18E+04 O.OOE+OO 9.18E+07 TABLE 5.7.3 Pathway Dose Factors, Ri CY-TM-170-300 Revision 5 Page 176 of 222 AGE GROUP: TEEN PATHWAY: VEGETATION H-3 O.OOE+OO 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 C-14 3.69E+08 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 CR-51 O.OOE+OO O.OOE+OO 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 4.54E+08 3.26E+08 2.31 E+08 1.80E+08 4.19E+08 O.OOE+OO 4.36E+07 O.OOE+OO 2.49E+08 1.61 E+10 1.13E+09 4.24E+08 1.47E+09 O.OOE+OO 2.73E+08 1.52E+10 O.OOE+OO 9.01 E+07 5.39E+07 1.62E+08 1.01E+08 5.60E+08 5.45E+08 6.86E+08 1.28E+08 4.34E+08 O.OOE+OO 1.36E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.42E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.47E+08 1.32E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.32E+08 1.00E+08 9.91E+08 6.01E+08 3.24E+09 1.81E+08 6.23E+08 4.04E+07 1.80E+09 . . SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 7.51 E+11 7.84E+06 1.72E+06 1.92E+05 6.82E+06 3.09E+08 AG-110M 1.52E+07 TE-125M 1.48E+08 TE-127M 5.52E+08 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 3.61E+08 7.69E+07 1.94E+06 7.10E+09 4.39E+07 1.01E+10 O.OOE+OO 1.85E+11 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+05 O.OOE+OO O.OOE+OO 5.43E+05 3.73E+05 O.OOE+OO 7.98E+05 1.07E+05 5.87E+04 O.OOE+OO 2.92E+06 O.OOE+OO 3.90E+07 O.OOE+OO 1.03E+05 O.OOE+OO 2.41 E+07 O.OOE+OO 5.97E+08 1.43E+07 5.34E+07 1.96E+08 1.34E+08 1.08E+08 3.29E+06 1.67E+10 1.73E+08 1.35E+10 8.72E+06 O.OOE+OO 2.74E+07 1.98E+07 4.14E+07 O.OOE+OO 6.56E+07 1.31 E+08 2.24E+09

5. 72E+07 1.17E+08 5.78E+07 3.14E+10 1.00E+06 4.59E+08 7.75E+09 O.OOE+OO 1.16E+08 O.OOE+OO 4.69E+09 O.OOE+OO 1.51E+09 1.85E+08 5.77E+06 5.31E+09 9.41E+07 4.59E+09 O.OOE+OO 2.11E+10 O.OOE+OO 3.22E+09 O.OOE+OO 1.25E+09 O.OOE+OO 4.56E+08 O.OOE+OO

5. 70E+08 O.OOE+OO 1.48E+10 O.OOE+OO 4.03E+09 O.OOE+OO 4.37E+08 O.OOE+OO 1.37E+09 O.OOE+OO 1.36E+09 O.OOE+OO 2.13E+07 O.OOE+OO 2.49E+06 2.03E+09 2.08E+08 1.48E+07 1.39E+07 1.78E+09 1.92E+08

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BA-140 1.39E+'08 1.71E+05 8.97E+06 O.OOE+OO 5.78E+04 1.15E+05 2.15E+08 CE-141 2.83E+05 1.89E+05 2.17E+04 O.OOE+OO 8.90E+04 O.OOE+OO 5.41E+08 CE-144 5.28E+07 2.18E+07 2.83E+06 O.OOE+OO 1.30E+07 O.OOE+OO 1.33E+10 PR-143 6.99E+04 2.79E+04 3.48E+03 O.OOE+OO 1.62E+04 O.OOE+OO 2.30E+08 ND-147 3.62E+04 3.94E+04 2.36E+03 O.OOE+OO 2.31 E+04 O.OOE+OO 1.42E+08 L__ __ _ TABLE 5.7.4* Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: VEGETATION CY-TM-170-300 Revision 5 Page 177 of 222 BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ------------------

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*

H-3 O.OOE+OO 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 C-14 2.28E+08 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 CR-51 O.OOE+OO O.OOE+OO 4.64E+04

2. 77E+04 1.02E+04 6.15E+04 1.17E+07 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 O.OOE+OO 2.10E+08 1.26E+08 O.OOE+OO o:ooE+oo 1.04E+10 3.17E+08 O.OOE+OO 9.98E+09 3.13E+08 1.45E+08 2.97E+08 5.97E+07 3.38E+07 1.14E+08 3.07E+07 6.89E+07 1.67E+08 3.69E+08 7.21 E+08 3.49E+08 1.01E+09 4.56E+08 2.19E+08 1.02E+08 O.OOE+OO 2.86E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.31E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.75E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.08E+07 8.29E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.58E+08 8.31E+07 9.89E+08 6.23E+08 3.14E+09 1.50E+08 6.36E+08 4.32E+07 1.60E+09

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*

SR-90 6.05E+11 O.OOE+OO 1.48E+11. O.OOE+OO O.OOE+OO O.OOE+OO 1.75E+10 Y-91 5.12E+06 O.OOE+OO 1.37E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E+09 ZR-95 1.17E+06 3.77E+05 2.55E+05 O.OOE+OO 5.91E+05 O.OOE+OO 1.19E+09 NB-95 1.42E+05 7.92E+04 4.26E+04 O.OOE+OO 7.83E+04 O.OOE+OO 4.81E+08 RU-103 4.77E+06 O.OOE+OO 2.06E+06 O.OOE+OO 1.82E+07 O.OOE+OO 5.57E+08 RU-106 1.93E+08 O.OOE+OO 2.44E+07 O.OOE+OO 3.72E+08 O.OOE+OO 1.25E+10

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*

AG-110M 1.05E+07 9.75E+06 5.79E+06 O.OOE+OO 1.92E+07 O.OOE+OO 3.98E+09 TE-125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 O.OOE+OO 3.86E+08 TE-127M 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 O.OOE+OO 1.17E+09

---

*

TE-129M 2.51E+08 9.37E+07 3.97E+07 8.63E+07 1.05E+09 O.OOE+OO 1.26E+09 1-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 O.OOE+OO 3.05E+07 1-133 2.09E+06 3.63E+06 1.11 E+06 5.34E+08 6.33E+06 O.OOE+OO 3.26E+06

---

*

CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 4.67E+09 4.28E+07 6.36E+09 1.29E+08 1.97E+05 3.29E+07 1.11E+10 1.69E+08 8.70E+09 1.62E+05 1.33E+05 1.38E+07 9.08E+09 1.22E+08 5.70E+09 8.47E+06 1.51 E+04 1.77E+06 O.OOE+OO 3.59E+09 O.OOE+OO 9.41E+07 O.OOE+OO 2.95E+09 O.OOE+OO 5.52E+04 O.OOE+OO 6.20E+04 O.OOE+OO 8.16E+06 1.19E+09 1.94E+08 1.29E+07 1.92E+07 9.81E+08 1.68E+08 9.29E+04 2.66E+08 O.OOE+OO 5.1 OE+08 O.OOE+OO 1.11E+10 PR-143 6.25E+04 2.51 E+04 3.1 OE+03 O.OOE+OO 1.45E+04 O.OOE+OO 2.74E+08 ND-147 3.34E+04 3.85E+04 2.31 E+03 O.OOE+OO 2.25E+04 O.OOE+OO 1.85E+08 6.0 TMl-1 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM CY-TM-170-300 Revision 5 Page 178 of 222 6.1 Description of the TMl-1 Gaseous Radwaste Treatment System (see Figure 6.1) 6.1.1 Waste Gas System a. Reactor Building: -Reactor Coolant Drain Tank (RCDT) header b. Auxiliary Building: -Vent Header from 1. Miscellaneous Waste Storage Tank (MWST) 2. Three (3) Reactor Coolant Bleed Tanks (RCBT) -Waste Gas Delay Tank -Two (2) Waste Gas Compressors -Three (3) Waste Gas Decay Tanks (WGDT) c. Filtration and dilution provided by the Station Ventilation System. 6.2 Operability of the TMl-1 Gaseous Radwaste Treatment System Operability of the Gaseous Waste Treatment System is defined as the ability to remove gas from the vent header/tank gas spaces and store it under a higher pressure in the Waste Gas Decay Tanks for subsequent release. Except for initiating the make up tank sample and waste gas venting and the recycle or disposal of compressed waste gases stored in the waste gas decay tanks, the operation of the waste gas system is entirely automatic. One waste gas compressor comes on automatically, removing gases from the vent header system as required, to maintain the pressure in the system at a maximum of about 16.4 psia. FIGURE 6.1 Waste Gas System Plllllllllll IUCfll llMl... IIUlfl IUIIS II. .... ,, , ...... .-----1 r------1 _ _.._ ...... __ .... I I alCWAIII lllUlltMI U.-----~-~ WN-ft4 TlftlJUI* HICI llflU t*tlll 11, ....... IIH'lf H *AIIIIAI 11ca, 1&111 C n () *>J ) + --~ -. u 0 II WUHUI ltCAIIMI

• tllTM.IIH WAIUIAI NCAIIMI A
• l _____ .1-t _______ __._ _______ ---J CY-TM-170-300 Revision 5 Page 179 of 222 WAIHUI t+~J IIUIIAU 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 7 .1 Total Dose Calculation CY-TM-170-300 Revision 5 Page 180 of 222 The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. This control is provided in order to meet the dose limitations of 40 CFR 190. The total dose from TMl-1 and TMl-2 (uranium fuel cycle facilities within 8 kilometers) is calculated by summing the calculated annual doses to critical organs of a real individual for liquid effluent using Section 2.1 methodology, for gaseous effluent using Section 5.2.1 and 5.2.2 methodology, and the direct radiation from the site from the environmental monitoring program's direct radiation monitors.

CY-TM-170-300 Revision 5 Page 181 of 222 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitoring Program Requirements 8.1.1 Controls In accordance with the TMl-1 Tech. Specs. and TMl-2 PDMS Tech. Specs., the radiological environmental monitoring program shall be conducted as specified in Table 8.1. 8.1.2 Applicability At all times. 8.1.3 Action a. With the radiological environmental monitoring program not being conducted as specified in Table 8.1, prepare and submit to the Commission in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 8.2 when averaged over any calendar

quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar

quarter, a special report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a member of the public is less than the calendar year limits of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part II Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3.

When more than one of the radionuclides in Table 8.2 are detected as the result of plant effluents in the sampling medium, this report shall be submitted if: concentration (1) concentration (2) > 1 0 reportinglevel(1) + reporting level(2) + -* When radionuclides other than those in Table 8.2 are detected and are the result of plant effluents, this report shall be The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report. CY-TM-170-300 Revision 5 Page 182 of 222 submitted if the potential annual dose* to a member of the public is equal to or greater than the calendar year limits of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part 11, Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents;

however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report. c. With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 8.1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then *be deleted from the monitoring program.

Pursuant to TMl-1 Tech. Spec. 6.14 and TMl-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples. 8.1.4 Bases The radiological monitoring program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and*for those radionuclides which lead to the highest potential radiation exposures of members of the general public resulting from the station operation. This monitoring program implements Section IV 8.2 of Appendix I to 1 OCFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operational experience. 8.1.5 Surveillance Requirements CY-TM-170-300 Revision 5 Page 183 of 222 The radiological environmental monitoring samples shall be collected pursuant to Table 8:1, from the specific locations given in Tables 8.4 through 8.10 and Maps 8.1 through 8.3, and shall be analyzed pursuant to the requirements of Table 8.1 and the detection capabilities required by Table 8.3. 8.2 Land Use Census 8.2.1 Controls CY-TM-170-300 Revision 5 Page 184 of 222 In accordance with the TMl-1 Tech. Specs. and TMl-2 PDMS Tech. Specs., a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation. 8.2.2 Applicability At all times. 8.2.3 Action a. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in ODCM Part I Surveillance 3.2.2.3.1, pursuant to ODCM, Part IV, Section 2.0, identify the new location(s) in the next Annual Radioactive Effluent Release Report. b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Table 8.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure

pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.

Pursuant to TMl-1 Tech. Spec. 6.14 and TMl-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations. Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted D/Qs in lieu of the garden census. Requirements for broad leaf sampling in Table 8.1 shall be followed, including analysis of control samples. 8.2.4 Bases CY-TM-170-300 Revision 5 Page 185 of 222 This Control is provided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial surveys, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR 50. Restricting the census to gardens of greater than 500 square feet (50 m2) provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter. 8.2.5 Surveillance Requirements The Land Use Census shall be conducted during the growing season at least once per 12 months, using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census*shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Part IV, Section 1.0. 8.3 lnterlaboratory Comparison Program 8.3.1 Controls CY-TM-170-300 Revision 5 Page 186 of 222 In accordance with the TMl-1 Tech. Specs. and TMl-2 PDMS Tech. Specs., analyses shall be performed on radioactive materials supplied as part of an lnterlaboratory Comparison Program which has been approved by the Commission (NRC). Only those samples and analyses which are required by Table 8.1 shall be performed. 8.3.2 Applicability At all times. 8.3.3 Action With analysis not being performed as required above, report the corrective action taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. 8.3.4 Bases The requirement for participation in an approved lnterlaboratory Comparison Program is provided to ensure that independent checks on precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV, 8.2 of Appendix I to 10 CFR 50. 8.3.5 Surveillance Requirements A summary of the lnterlaboratory Comparison Program results shall be included in the Annual Radiological Environmental Operating Report. Exposure Pathway and/or Sample 1. Airborne Radioiodine and Particulates TABLE 8.1 CY-TM-170-300 Revision 5 Page 187 of 222 Sample Collection and Analysis Requirements Number of Samples and Sampling and Type and Frequency Sample Locationsa Collection Frequencyb of Analysisb Samples from 5 locations Continuous sampler operation Radioiodine Canister: from Table 8.4. with sample collection weekly, Analyze weekly for 1-131. or more frequently if required Particulate Filter: Three of these samples by dust loading. Analyze for gross beta should be close to the Site radioactivity following filter Boundary, in different changed. Perform gamma sectors, of the highest isotopic analysise on calculated annual average composite (by location) ground level D/Q. sample quarterly. One of the samples should be from the vicinity of a community having the highest calculated annual average ground level D/Q. And one sample should be from a control location 15 to 30 km distant in a less prevalent wind direction. TABLE 8.1 (Cont'd) Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and and/or Sample Sample Locationsa Collection Frequencyb

2. Direct Radiation° Samples from 40 locations from Sample Quarterly Table 8.5 (using either 2 dosimeters or at least 1 instrument for continuously measuring and recording dose rate at each location).

Placed as follows: An inner ring of stations, one in each meteorological sector in the general area of the site boundary; An outer ring of stations, one in each meteorological sector in the 6 to 8 km from the site; and the balance of the stations to be placed in special interest areas such as population

centers, nearby residences,

schools, and in at least one or two areas to serve as control stations.

CY-TM-170-300 Revision 5 Page 188 of 222 Type and Frequency of Analvsisb Analyze for gamma dose quarterly. Exposure Pathway and/or Sample 3. Waterborne

a. Surface1 b. Drinking C. Sediment from Shoreline TABLE 8.1 (Cont'd)

CY-TM-170-300 Revision 5 Page 189 of 222 Sample Collection and Analysis Requirements Number of Samples and Sampling and Type and Frequency Sample Locationsa Collection Frequencyb of Analysisb Samples from 2 locations Composite9 sample over Perform gamma isotopic from Table 8.6. 1 monthly period. analysise monthly. Composite for tritium

• 1 sample from analysis quarterly.

downstream (indicator) location

• 1 sample from upstream (control) location (or location not influenced by the station discharge)

Samples from 2 locations Composite9 sample over Perform gross beta and from Table 8.6. 1 monthly period. gamma isotopic analysise monthly. Perform Sr-90

• 1 sample at the location of analysis if gross beta of the nearest water supply monthly composite

>10 that could be affected by times control. Composite for the station discharge. tritium analysis quarterly.

• 1 sample from a control location.

Samples from 2 locations Sample twice per year Perform gamma isotopic (1 Control and 1 Indicator) (Spring and Fall) analysise on each sample. from Table 8.7. ' I Exposure Pathway and/or Sample 4. Ingestion

a. Milk b. Fish TABLE 8.1 (Cont'd)

CY-TM-170-300 Revision 5 Page 190 of 222 Sample Collection and Analysis Requirements Number of Samples and Sampling and Type and Frequency Sample Locations 0 Collection Frequencyb of Analvsisb Samples from 4 locations from Sample semimonthly Perform gamma isotopic Table 8.8. when animals are on analysise and 1-131 pasture; monthly at other analysis on each sample. Samples should be from milking times. Composite for Sr-90 animals in three locations within 5 analysis quarterly. km distance having the highest dose potential. If there are none, then one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year. One sample from milking animals at a control location 15 to 30 km distant in a less prevalent wind direction. Samples from 2 locations from Sample twice per year Perform gamma isotopic0 Table 8.9. (Spring and Fall). and Sr-90 analysis on edible portions.

• 1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators in the vicinity of the station discharge.
• 1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators from an area not influenced by the station discharge.

TABLE 8.1 (Cont'd) Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and and/or Sample Sample Locationsa Collection Freauencvb

4. Ingestion (contd) c. Food Products Samples from 2 locations from Sample at time of Table 8.10 (when available) harvest.

• 1 sample of each principle class of food products at a location in the immediate vicinity of the station.

(indicator)

• 1 sample of same species or group from a location not influenced by the station discharge.

Samples of three different kinds Monthly during growing of broad leaf vegetation grown season nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milking sampling is not performed. One sample of each of the similar broad leaf vegetation grown 15 to 30 km distant in a less prevalent wind direction if milk sampling is not performed. CY-TM-170-300 Revision 5 Page 191 of 222 Type and Frequency of Analvsisb Perform gamma isotopic0, and 1-131, analysis on edible portions. Sr-90 analysis on green leafy vegetables or vegetation only. Perform gamma isotopic0 1-131 analysis. i I i I I TABLE 8.1 (Cont'd) Sample Collection and Analysis Requirements Table Notation CY-TM-170-300 Revision 5 Page 192 of 222 a. Sampling locations are provided in Tables 8.4 through 8.10. They are depicted in Maps 8.1 through 8.3. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. All deviations from the sampling schedule shall be explained in the Annual Radiological Environmental Operating Report. b. Frequency notation: weekly (7 days), semimonthly (15 days), monthly (31 days), and quarterly (92 days). All surveillance requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. A total maximum combined interval time for any 4 consecutive tests shall not exceed 3.25 times the specified collection or analysis interval.

c. One or more instruments, such as a pressurized ion chamber for measuring and recording dose rate continuously, may be used in place of, or in addition to, integrating dosimeters.

For the purpose of this table, a dosimeter is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

d. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in an air particulate sample(s) is greater than ten times the calendar year mean of control samples, Sr-90 and gamma isotopic analysis shall be performed on the individual sample(s).

e. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

f. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge.

The "downstream sample" shall be taken in an area beyond but near the mixing zone. g. Composite sample aliquots shall be collected at time intervals that are short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample. TABLE 8.2 CY-TM-170-300 Revision 5 Page 193 of 222 Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Particulate Water or gas Fish Milk Food Products Analysis (pCi/L) (pCi/m3) (pCi/kQ,wet) (pCi/L) (pCi/kQ, wet) H-3 20,000(a) Mn-54 1000 30,000 FE-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Sr-90 8 0.1 100 8 100 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 (a) For drinking water samples. This is 40 CFR Part 141 value. Analysis Gross Beta H-3 Mn-54 FE-59 Co-58, 60 Zn-65 Zr-95 Sr-90 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 TABLE 8.3 CY-TM-170-300 Revision 5 Page 194 of 222 Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD)b,c Airborne Particulate Food Water or Gas Fish Milk Products Sediment (pCi/L) (pCi/m3) (pCi/kg wet) (pCi/L) (pCi/kg,wet) (pCi/kg, dry) 4 0.01 2000 15 130 30 260 15 130 30 260 30 2 0.01 10 2 10 15 1d 0.07 1 60 15 0.05 130 15 60 150 18 0.06 150 18 80 180 60 60 15 15 TABLE 8.3 (Cont'd) CY-TM-170-300 Revision 5 Page 195 of 222 Detection Capabilities for Environmental Sample Analysis3 Table Notation

a. This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, which may be related to plant operations, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report. b. Required detection capabilities for dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Rev. 1 ). c. The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): LLD= 4.66Sb E

• V
• 2.22
• Y
• exp (-1c~t) Where: LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume. Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

'A, is the radioactive decay constant for the particular radionuclide and ~t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, a~d time of counting. Typical values of E, V, Y and ~t should be used in the calculation. TABLE 8.3 (Cont'd) CY-TM-170-300 Revision 5 Page 196 of 222 Detection Capabilities for Environmental Sample Analysis3 Table Notation It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small samples sizes, the presence of interfering

nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. d. LLD for drinking water. TABLE 8.4 CY-TM-170-300 Revision 5 Page 197 of 222 TMINS REMP Station Locations-Air Particulate and Air Iodine Station Code Distance (miles) Azimuth (0) Map No. E1-2 0.4 97 8.1 F1-3 0.6 112 8.1 G2-1 1.4 126 8.2 M2-1 1.3 256 8.2 A3-1 2.7 357 8.2 H3-1 2.2 160 8.2 Q15-1 13.4 309 8.3 TABLE 8.5 TMINS REMP Station Locations-Direct Radiation Station Code Distance (miles) Azimuth (0) Map No. A1-4 0.3 6 8.1 B1-1 0.6 25 8.1 B1-2 0.4 24 8.1 C1-2 0.3

• 50 8.1 D1-1 0.2 76 8.1 E1-2 0.4 97 8.1 E1-4 0.2 97 8.1 F1-2 0.2 112 8.1 G1-3 0.2 130 8.1 H1-1 0.5 167 8.1 J1-1 0.8 176 8.1 J1-3 0.3 189 8.1 K1-4 0.2 209 8.1 L 1-1 0.1 236 8.1 M1-1 0.1 249 8.1 N1-3 0.1 274 8.1 P1-1 0.4 303 8.1 P1-2 0.1 292 8.1 CY-TM-170-300 Revision 5 Page 198 of 222 TABLE 8.5 (Cont'd)

TMINS REMP Station Locations-Direct Radiation Station Code Distance (miles) Azimuth (0) Map No. Q1-2 0.2 321 8.1 R1-1 0.2 335 8.1 C2-1 1.5 44 8.2 K2-1 1.2 200 8.2 M2-1 1.3 256 8.2 A3-1 2.7 357 8.2 H3-1 2.2 160 8.2 R3-1 2.6 341 8.2 A5-1 4.4 3 8.2 B5-1 4.9 19 8.2 C5-1 4.7 43 8.2 E5-1 4.7 82 8.2 F5-1 4.7 109 8.2 G5-1 4.8 131 8.2 H5-1 4.1 158 8.2 J5-1 4.9 181 8.2 K5-1 4.9 202 8.2 L5-1 4.1 228 8.2 M5-1 4.3 249 8.2 N5-1 4.9 268 8.2 P5-1 5.0 284 8.2 Q5-1 5.0 317 8.2 R5-1 4.9 339 8.2 D6-1 5.2 66 8.3 E7-1 6.7 88 8.3 Q9-1 8.5 310 8.3 B10-1 9.2 21 8.3 G10-1 9.7 128 8.3 G15-1 14.4 126 8.3 J15-1 12.6 183 8.3 Q15-1 13.4 309 8.3 TABLE 8.6 TMINS REMP Station Locations-Surface Water Station Code Distance (miles) Azimuth (0) J1-2 (SW) 0.5 188 A3-2 (SW) 2.7 356 Q9-1 (OW) 8.5 310 Q9-1 (SW) 8.5 310 G15-2 (OW) 13.3 129 G15-3 (OW) 15.7 124 (SW) = Surface Water (OW) = Drinking Water TABLE 8.7 TMINS REMP Station Locations-Aquatic Sediment Station Code A1-3 K1-3 J2-1 Distance (miles) 0.6 0.2 1.4 Azimuth (0) 359 213 179 CY-TM-170-300 Revision 5 Page 199 of 222 Map No. 8.1 8.2 8.3 8.3 8.3 8.3 Map No. 8.1 8.1 8.2 Station Code E2-2 F4-1 G2-1 P4-1 K15-3 Station Code E1-2 H1-2 810-2 TABLE 8.8 TMINS REMP Station Locations-Milk Distance (miles)

• Azimuth (0) 1.1 96 3.2 104 1.4 126 3.6 295 14.4 205 TABLE 8.9 TMINS REMP Station Locations-Fish Station Location CY-TM-170-300 Revision 5 Page 200 of 222 Map No. 8.2 8.2 8.2 8.2 8.3 Station Code IND BKG Downstream of Station Discharge Upstream of Station Discharge TABLE 8.10 TMINS REMP Station Locations-Food Products Distance (miles) 0.4 1.0 10.0 Azimuth (0) 97 151 31 Map No. 8.1 8.1 8.3

'N MAP 8.1 Three Mile Island Nuclear Station CY-TM-170-300 Revision 5 Page 201 of 222 Locations of Radiological Environmental Monitoring Program Stations Within 1 Mile of the Site ,* rl1i/ /s/(li1it ._;:;/~*..:' \. *m "" ""~ [J] i / i '* ' ' ,* "' " * , , "' ., ., . [ITiJ . .. . * '. Ser;lce Layer Qedits: Swrces: Esrl, Delorme, W.V1EQ, TomTOIT\ lnle[ll13!), ilcrement p Corp., GEBCO, USGS, FAO, NPS, NRCAN, GeoBase, IGN, KadasterNL, Orctlance Survey, Esrl . Jai,a11 METl,,Esrl Clina (Hoog Kong), swlsstopo, and Iha GIS User COrrmmly ' ** _ " I I ' + MAP 8.2 Three Mile Island Nuclear Station CY-TM-170-300 Revision 5 Page 202 of 222 Locations of Radiological Environmental Monitoring Program Stations Within 5 Miles of the Site t1 .. ,:1k-ht':71 ,:~"11 ;t;lj.J \ ; .. T \ t Qi .. ' *.... . Seivlce Layer a-edits: Sources: Esrl, Del.llrme; NAVTEQ, TomT0111*lnlermai>, i'lcrement P Corp., GEB.CO, USGS, FAO, NI'S, NRCAN, GeoBase, IGN, Kadaster NL,,Or<l'lance S<1Vey, Esrl Japan,METl,EsriCtJna(HongKong),(*~st6):<>,andtheGISUser\Cormwrlit~.~*

s 1~* .. 11011*!,hl !\tt \Vofl ', * *, * ',1,1 {.

MAP 8.3 Three Mile Island Nuclear Station CY-TM-170-300 Revision 5 Page 203 of 222 Locations of Radiological Environmental Monitoring Program Stations Greater Than 5 Miles from the Site *1,,.~*.Hl t,, N n 11::" oa T:,p 't *,rn,.,.,.~, /!<_1,f,lt***I 1*.r 10Miles Service Layer o ans: ~~r,~; Esrt, Delorme, NAV'TEO:*To~T6~i~e~ .. ~g~ment P Corp., GEBcd,'Usds, FAO, J.ap~i:i, METI, Esri Ctina1(}:long ~ong), swlsstopo, and the GIS User Commmity r,.~11-, 1 \ .. 1.,,1.*,r,, ,.-,p 11,.1,klt*l*l r.~, f,$,\ L<,, l'*'l'l-' I.',) 9.0 PART Ill REFERENCES CY-TM-170-300 Revision 5 Page 204 of 222 1. EPRI NP-3840, RP 1560-3 Final Report, "Environmental Radiation Doses From Difficult-To-Measure Nuclides," January 1985 2. "Evaluation of the Three Mile Island Nuclear Station Unit 1 to Demonstrate Conformance to the Design Objectives of 10 CFR 50, Appendix I," Nuclear Safety Associates, May 1976 3. TMl-1 Final Safety Analysis Report (FSAR) 4. TMl-2 Post Defueled Monitored Storage Safety Analysis Report (PDMSSAR)

5. Meteorological Information and Dose Assessment System (MIDAS) 6. NUREG-0017, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWR," Revision 1, 1985 7. NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978 8. NUREG-0172, "AgE-Specific Radiation Dose Commitment Factors For A OnE-Year Chronic Intake," November 1977 9. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," Revision 1, June 1974 10. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977 11. TDR-390-TMI Primary to Secondary OTSG Leakage and its Onsite/Offsite Radiological Impact 12. SCR-358-82-063, "Study of Travel Time and Mixing Characteristics for the Susquehanna River Below Three Mile Island Final Report", July 1982 13. TMl-1 Operations Procedure, 1101-2.1, "Radiation Monitor Set Points" 14. Title 10, Code of Federal Regulations, "Energy"

15. TMl-1 Technical Specifications, attached to Facility Operating License No. DPR-50 16. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 1977 CY-TM-170-300 Revision 5 Page 205 of 222 17. TMl-2 PDMS Technical Specifications, attached to Facility License No. DPR-73 18. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 19. Title 40, Code of Federal Regulations, "Protection of Environment"

20. Regulatory Guide 4.13, "Performance,

Testing, and Procedural Specifications for Thermoluminescence Dosimetry:

Environmental Applications," Revision 1, July 1977 PART IV REPORTING REQUIREMENTS CY-TM-170-300 Revision 5 Page 206 of 222 PART IV Reporting Requirements CY-TM-170-300 Revision 5 Page 207 of 222 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT** 1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted to the Commission prior to May 1 of each year. 1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring activities for the report period, including a comparison with pre-operational

studies, with operational controls as appropriate, and with previous environmental monitoring

reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of Land Use Censuses required by Part Ill, Section 8.2. 1.3 The Annual Radiological Environmental Operating Reports shall include the summarized tabulated results of analysis of all radiological environmental samples and environmental radiation measurements required by Part Ill Table 8.1 taken during the period pursuant to the locations specified in the tables and figures in this ODCM, as well as summarized and tabulated results of these analyses and measurements in a format similar to the table in the Radiological Assessment Branch Technical

Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report. 1.4 The reports shall also include the following: A summary description of the radiological environments monitoring program; a map(s) of all sampling locations keyed to a table giving distances and directions from a point that is midway between the Reactor Buildings of TMl-1 and TMl-2; the results of licensee participation in the lnterlaboratory Comparison

Program, required by Part Ill, Section 8.3; discussion of all deviations from the sampling schedule of Part Ill, Table 8.1; discussion of all the required analyses in which the LLD required by Part Ill, Table 8.3 was not achievable.

-A single submittal may be made for the station. 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CY-TM-170-300 Revision 5 Page 208 of 222 NOTE: A single submittal may be made for the station. The submittal should combine those sections that are common to both units at the station however, for units with separate radwaste

systems, the submittal shall specify the release of radioactive material from each unit. 2.1 . Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous 12 months of operation shall be submitted prior to May 1 for TMl-1 and TMl-2. 2.2 The following information shall be included in both Radioactive Effluent Release Reports to be submitted each year: The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev. 1, with data summarized on a quarterly basis following the format of Appendix B thereof.

2.3 The Radioactive Effluent Release Reports shall include the following information for each type of solid waste shipped offsite during the report period: a. Type of waste (e.g., resins/filters/evaporator

bottoms, dry active waste or other b. Total volume of each waste type c. Total activity of each waste type d. Principle radio-nuclides of each waste type and percentages

e. Solid waste disposition (Carrier and Consignee)

f. Irradiated fuel shipments disposition (Carrier and Consignee) 2.4 The Radioactive Effluent Release Reports shall include a summary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period. 2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part Ill Section 8.2.

CY-TM-170-300 Revision 5 Page 209 of 222 2.6 The Radioactive Effluent Release Reports shall include the instrumentation not returned to OPERABLE status within 30 days per ODCM Part I Controls 2.1.1 b and 2.1.2b, and ODCM Part II Control 2.1.2b. 2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmosphere stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability.

• 2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation doses to MEMBERS OF THE PUBLIC at or beyond the site boundary due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The assessment of radiation doses shall be performed in accordance with this ODCM. 2.9 The Radioactive Effluent Release Report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period, to verify compliance with the limits of 1 OCFR20.1301 (a)(1 ). All assumptions used in making these assessments (i.e., specific

activity, exposure time and location) shall be included in these reports.

2.10 The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed real individual from reactor releases, and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation for the previous 12 consecutive months, to show conformance with 40 CFR 190 "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1. 2.11 The Radioactive Effluent Release Report shall also include a report of major changes to Radioactive Waste Treatment Systems. FSAR Section 11.2.6 requires this reporting. 3.0 PART IV REFERENCES CY-TM-170-300 Revision 5 Page 210 of 222 3.1

• Radiological Assessment Branch Technical

Position, Revision 1, November 1979 3.2 Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"

Revision 1, June 197 4 3.3 TMl-1 Technical Specifications, attached to Facility Operating License No. DPR-50 3.4 Title 40, Code of Federal Regulations, "Protection of Environment" 3.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 3.6 Title 10, Code of Federal Regulations, "Energy"

3. 7 Regulatory Guide 1, 111, "Methods of Estimating Atmospheric Transport

~nd Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977 3.8 Regulatory Guide 1.112, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors," Revision 0-R, April 1976 3.9 Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision 1, April 1977 APPENDIX A Page 1 of 1 Pi -Pathway Dose Rate Parameter Pi (inhalation)= k' (BR) DFAi Where: CY-TM-170-300 Revision 5 Page 211 of 222 (Eq A-1) Pi= the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the* inhalation

pathway, in mrem/yr per microcurie/m 3* The dose factors are based on the critical individual organ for the child age group. k' = conversion factor, 1 E6 pCi/microcurie BR= 3700 m3/yr, breathing rate for child (Reg. Guide 1.109, Rev. 1, Table E-5) DFAi = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide (mRem/pCi).

Values are taken from Table E-10, Reg. Guide 1.109 (Rev. 1 ), or NUREG-0172. Resolution of the units yields: (ODCM Part Ill Table 4.6) Pi (inhalation)= 3.7E9 DFAi (mrem/yr per µCi/m3) NOTE: The latest NRC Guidance has deleted the requirement to determine Pi (ground plane) and Pi (food). In addition, the critical age group has been changed from infant to child. (Eq A-2) APPENDIX B Page 1 of 1 Ri -Inhalation Pathway Dose Factor Ri = k' (BR) (DFAi,a,o) (mrem/yr per microcurie/m

3) Where: k' = conversion factor, 1 E6 pCi/microcurie CY-TM-170-300 Revision 5 Page 212 of 222 (Eq 8-1) BR= breathing rate, 1400, 3700, 8000, 8000 m3/yr for infant, child, teenager, and adult age groups, respectively.

(Reg. Guide 1.109, Rev. 1, Table E-5) DFAi,a,o = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrem/pCi. The total body is considered as an organ in the selection of DFAi,a,o. Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Rev. 1 ), or NU REG 0172. Resolutions of the units yields: Ri = (1.4E9) (DFAi,a,o) infant (ODCM Part Ill Table 5.2.1) Ri = (3.7E9) (DFAi,a,o) child (ODCM Part Ill Table 5.2.2) Ri = (8.0E9) (DFAi,a,o) teen and adult (ODCM Part Ill Tables 5.2.3 and 5.2.4) Where: APPENDIXC Page 1 of 1

• Ri -Ground Plane Pathway Dose Factor k' = conversion factor, 1 E6 pCi/microcurie k" = conversion factor, 8760 hr/yr Ai = decay constant for the ith radionuclide, sec -1 CY-TM-170-300 Revision 5 Page 213 of 222 (Eq C-1) t =
• the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec. (15 yrs), Reg. Guide 1.109 (Rev. 1), Appendix C DFGi = the ground plane dose conversion factor for the ith radionuclide (mrem/hr per pCi/m2). Values are taken from Table E-6, Reg. Guide 1.109 (Rev .. 1 ), or NUREG 0172. These values apply to all age groups. SF= 0.7, shielding factor, from Table E-15 Reg. Guide 1.109 (Rev. 1) Reference ODCM Part Ill Table 5.3.1 APPENDIXD Page 1 of 2 CY-TM-170-300 Revision 5 Page 214 of 222 Ri -Grass Cow-Milk Pathway Dose Factor Ri = k' [(QF X UAP)/ {Ai + Aw)] X {Fm) X (r) X {DFLi,a,o)

X [((fp X fs)/Yp) + ((1-fp X fs) e -Aith)/Ys] e -Ai~ (Eq D-1) Where: k' = conversion factor, 1 E6 picocurie/microcurie (pCi/µci) QF = cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1) goat consumption rate, 6 kg/day, (Reg. Guide 1.109, Rev. 1, Table E-2) UAP= Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1) YP = agricultural productivity by unit area of pasture feed grass, 0. 7 kg/m2 (NUREG-0133) Ys = agricultural productivity by unit area of stored feed, 2.0 kg/m2 (NUREG-0133) Fm = stable element transfer coefficient (Table E-1, Reg. Guide 1.109, Rev. 1) r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, Reg. Guide 1.109, Rev. 1) DFLi,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1 ), or NU REG 0172. Ai = decay constant for the ith radionuclide, sec-1 Aw= decay constant for weathering, 5.73 x 10-7 sec-1 (NUREG-0133); based on a 14 day half life tt = 1. 73 x 105 sec, the transport time from pasture to cow to milk to receptor (Table E-15, Reg. Guide 1.109, Rev. 1 ), or 2 days th = 7. 78 x 106 sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-15, Reg. Guide 1.109, Rev. 1 ), or 90 days fp = 1.0, the fraction of the year that the cow is on pasture fs = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture APPENDIX D Page 2 of 2 CY-TM-170-300 Revision 5 Page 215 of 222 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q): Rct,a,o = k'k"' Fm QF UAPDFLt,a,o (.75 [.5/H]) Where: k"' = 1 E3 grams/kg H = 8 grams/m3, absolute humidity of the atmosphere .75 = fraction of the total feed grass mass that is water (Eq D-2) .5 = ratio of the specific activity of the feed grass water to the atmospheric water (NUREG-0133) DFLt,a,o = the ingestion dose factor for tritium and organ, o, for each respective age group, a {Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172. All other parameters and values are as given above. NOTE: Goat-milk pathway factor, Ri, will be computed using the cow-milk pathway factor equation. Fm factor for goat-milk will be from Table E-2 Reg. Guide 1.109, Rev. 1.

Reference:

ODCM Part Ill Tables 5.4.1 to 5.4.4 APPENDIXE Page 1 of 2 CY-TM-170-300 Revision 5 Page 216 of 222 Ri -Grass Cow-Meat Pathway Dose Factor Ri = k' [(QF X UAP)/ (Ai + Aw)] X (Ft) X (r) X (DFLi,a,o) X [((fp X fs)/Yp) + ((1-fpfs) e -Aith)/Ys] Xe -Ai\ (Eq E-1) Where: k' = conversion factor, 1 E6 picocurie/microcurie (pCi/µci) QF = cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1) UAP = Receptor's meat consumption rate; 0, 41, 65, 110 kg/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1) Ft= the stable element transfer coefficients, days/kg (Table E-1, Reg. Guide 1.109, Rev. 1) r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, Reg. Guide 1.109, Rev. 1) DFLi,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1 ), or NU REG 0172. Ai = decay constant for the radionuclide i, sec-1 Aw= decay constant for weathering, 5.73 x 10-7 sec-1 (NUREG-0133), based on a 14 day half life t, = 1. 73 x 106 sec, the transport time from pasture to receptor (NUREG-0133) or 20 days th= 7.78 x 106 sec, the transport time from crop to receptor (NUREG-0133) or 90 days YP = agricultural productivity by unit area of pasture feed grass, 0. 7 kg/m2 (NUREG-0133) Ys = agricultural productivity by unit area of stored feed, 2.0 kg/m2 (NUREG-0133) fp = 1.0, the fraction of the year that the cow is on pasture fs = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture APPENDIX E Page 2 of 2 CY-TM-170-300 Revision 5 Page 217 of 222 The concentration of tritium in meat is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q): Rt,a,o = k'k"' Ft QF UAP (DFLt,a,o) X 0.75 X (0.5/H]) Where: All terms are as defined above and in Appendix D.

Reference:

ODCM Part Ill, Tables 5.6.1 to 5.6.4 (Eq E-2) Where: APPENDIX F Page 1 of 1 Ri -Vegetation Pathway Dose Factor k' =

• 1 E6 picocurie/microcurie (pCi/µci)

CY-TM-170-300 Revision 5 Page 218 of 222 (Eq F-1) ULA = the consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant, child, teenager, or adult age groups, respectively (Reg. Guide 1.109, Rev. 1) U5A = the consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenager, or adult age groups respectively (Reg. Guide 1.109, Rev. 1) fL = the fraction of the annual intake of fresh leafy vegetation grown locally,

1.0 (NUREG-0133) f9 = the fraction of the stored vegetation grown locally

0. 76 (NUREG-0133) tL = the average time between harvest of leafy vegetation and its consumption, 8.6 x 104 seconds [Table E-15, Reg. Guide 1.109, Rev. 1 (24 hrs)] th = the average time between harvest of stored leafy vegetation and its consumption, 5.18 x 106 seconds,

[Table E-15, Reg. Guide 1.109, Rev. 1 (60 days)] Yv = the vegetation area density, 2.0 kg/m2 (Table E-15, Reg. Guide 1.109, Rev. 1) All other parameters are as previously defined. The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q) Rt,a,o = k'k"' [ULA fL + U5A fg] (DFLt,a,o) (.75 [.5/H]) Where: All terms are as defined above and in Appendix D.

Reference:

ODCM Part Ill, Tables 5.7.1 to 5.7.4 (Eq F-2) Parameter DFAi BR r Yv AW DFL UaL fL tL Ua8 fg th H BR DFAi APPENDIX A-F REFERENCES Page 1 of 4 Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Value R.G. 1.109 NUREG-0133

• • • For Pi *** Each radionuclide E-9 3700 m3/yr {child) E-5 ***For Ri (Vegetation)***

Each element type E-1 2.0 kg/m2 E-15 5.73 E-7 sec1 5.3.1.3 Each age group and radionuclide E-11 thru E-14 Each age group E-5 1.0 5.3.1.5 8.6 E + 4 seconds E-15 ' Each age group E-5 0.76 5.3.1.5 5.18 E + 6 seconds E-15 8.0 grams/m3 5.2.1.3 ***For R1 (Inhalation)*** Each age group E-5 Each age group and nuclide E-7 thru E-10 CY-TM-170-300 Revision 5 Page 219 of 222 Site-Specific Note 1 Note 1 Note 1 Parameter SF DFG; t OF(Cow) OF (Goat) Uap AW F1 (Both) r DFL; fp fs Yp th Ys t1 H APPENDIX A-F REFERENCES Page 2 of 4 CY-TM-170-300 Revision 5 Page 220 of 222 Parameters Used in Dose Factor Calculations . Origin of Value Table in Section of Site-Value R.G. 1.109 NUREG-0133 Specific

• • • For Ri (Ground Plane) *** 0.7 E-15 Each radionuclide E-6 4.73 E + 8 sec 5.3.1.2 *** For Ri (Grass/Animal/Meat)
    • 50 kg/day E-3 6 kg/day E-3 Ref. Only Each age group E-5 5.73 E-7 sec1 5.3.1.3 Each element E-1 Each element type E-15 Each age group and nuclide E-11 thru E-14 Note 1 1.0 5.3.1.3 Note 2 1.0 5.3.1.3 Note 2 0.7 kg/m2 E-15 7.78 E + 6 sec E-15 2.0 kg/m2 E-15 1.73 E + 6 sec E-15 8.0 grams/m3 5.2.1.3 Parameter 01 Uap AW Fm r DFL1 Yp th Ys tt fp fs H APPENDIX A-F REFERENCES Page 3 of 4 Parameters Used in Dose Factor Calculations Oriqin of Value Table in Section of Value R.G. 1.109 NUREG-0133
    • For R; (Grass/Cow/Milk)
    • 50 kg/day E-3 Each age group E-5 5.73 E-7 sec1 5.3.1.3 Each element E-1 Each element type E-15 Each age group and nuclide E-11 thru E-14 0.7 kg/m2 E-15 7.78 E + 6 sec E-15 2.0 kg/m2 E-15 1.73 E + 5 sec E-15 1.0 5.3.1.3 1.0 5.3.1.3 8.0 grams/m3 5.2.1.3 CY-TM-170-300
• Revision 5 Page 221 of 222 Site-Specific Note 1 APPENDIX A-F REFERENCES Page 4 of 4 NOTES CY-TM-170-300 Revision 5 Page 222 of 222 1. Inhalation and ingestion dose factors were taken from the indicated source. For each age group, for each nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the referenced table. 2. Typically, beef cattle are raised all year on pasture.

Annual land surveys have indicated that the small number of goats raised within 5 miles, typically are used for grass control and not food or milk. Nevertheless, the goats can be treated as full meat sources where present, despite the fact that their numbers cannot sustain the meat consumption rates of Table E-5, NUREG-0133. REFERENCES

1. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance

.with 10 CFR Part 50, Appendix I," Revision 1 , October 1977. 2. TMl-1 Technical Specifications, attached to Facility Operating License No. DPR-50. 3. NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978. 2017 Annual Radioactive Effluent Release Report for TMI Enclosure 2 -Page 1 of 1 Process Control Program for Radioactive Wastes, Revision 12 RW-AA-100 (Revision 12 was issued on September 30, 2017)}}