Text

Offsite Dose Calculation Manual, Revision 9
	ML041400430
Person / Time
Site:	Pilgrim
Issue date:	10/06/2003
From:	; Entergy Nuclear Operations
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML041400430 (145)
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PNPS-ODCM Rev. 9 INFORMATION ONLY Use restricted to reference PILGRIM NUCLEAR POWER STATION OFFSITE DOSE CALCULATION MANUAL I

APPROVED BY:

CHEM>Ay [5 ate' DEPARTMENT MANA(aRg APPROVED BY: .tQAv (; Li41 RADIATION Date PROTECTION MANAGER REVIEWED BY:

bSRC AIRMAN bate I Rev. 0 was originally reviewed by ORC on June 10, 1983.

OSRC REVIEW REQUIRED I SAFETY REVIEW REQUIRED

PNPS-ODCM Rev. 9 RECORD OF DOCUMENT CHANGES DOCUMENT REV. DATE SECTION NO. IDENTIFICATION OF CHANGE APPROVED AND PAGE 0 Original Submittal 06/10/1983 All Sections 1 Update of TLD and Air Sample Locations 06/01/1987 7.0/7-7 & 7-8 2 Changes in response to NRC questions on PNPS 07/15/1988 All Sections ODCM (TAC #63012). Changes in response to technical review performed by BECo Radiological Section.

3 Changes in response to NRC comments on PNPS 07/12/1989 Preliminary pages, ODCM Rev. 2 (TAC #69867). Correct typographical 3.3, 4.2, 6.1,7.0 error in Table A-3. Incorporate new TLD locations. (7-3 & 7-5), 8.1, Change responsible division. A-3 4 Update signature page to reflect new responsible 09/27/1991 Page i through vii; organization. Update record of document changes. pages 13-15, Renumber pages iii through vii to include list of 17-23, 25-28, effective page revisions. Revise pages containing 30-32, 49, and equations and definitions to include machine- A-4; Appendix B.

generated scientific characters. Address gardens identified during 1990 garden census in Table 7-5 in accordance with Technical Specification 7.1.B.2.

Expand definition of Lower Limit of detection in Appendix B.

5 Add Steam Jet Air Ejector Monitor to section 10/30/1991 Pages i, ii, iii, v, addressing ironitor setpoints. 34a 6 Update revision Log; renumber pages ii through viii; 08/11/1994 Pages i through clarify definition of dilution flow used for liquid viii; 14, 17, 33, effluent discharges; clarify assumptions used in 34a, A-35 gaseous effluent dose calculations and SJAE monitor setpoints.

7 Reference NRC Safety Evaluation and 11/22/1995 Pages i through vi, 10CFR20.302 permit for onsite disposal of slightly Appendix C, page contaminated construction soil; repaginate C-1 preliminary pages.

8 Relocate Effluent Controls from PNPS Technical 08/27/1998 Entire document Specifications to the ODCM in accordance with Generic Letter 89-01; Repaginate and sectionalize entire ODCM; update distance and direction information for environmental sampling locations.

9 Relocate Effluent Control Bases within Control; 06/19/2003 Pages i through v, align Definitions with NUREG-1302; align gaseous vii, viii; page 1-1; sampling requirements with NUREG-1302; revise section 2; section REMP sampling program for samples and locations 3/4; page 7-5; no longer required; align REMP LLDs and reporting section 8; page 9-levels with NUREG-1 302; enhance discussion of 1, section 11, page alarm setpoint methodologies. 13-2 ii

PNPS-ODCM Rev. 9 LIST OF EFFECTIVE PAGE REVISIONS

) Page Rev. [ Page i Rev. l[Page Rev. Page i Rev. i Page j Rev. l Page i Rev.

i 9 3/4-16 9 5-1 9 9-1 9 A-1l 9 B-1 9 ii 9 3/4-17i 9 5-2l 9 9-2 9 A-2 9 B-2 9 iii 19 3/4-18 9 _ 9-3 9 A-3 l9 B-3 9 iv 1 9 3/4-197 9 _ 9-4 19 A-47 9 .i v l 9 3/4-201 9 _ 9 9-5 l 9 A-5 1 9 _ _j vi 9 3/4-21 1 9 _ 9-6 9 A-6 l9_

vii 9 3/4-22l 9 [ 9-7 9 A-7l 9 i viii 9 3/4-23J 9 1 9-8 9 A-81 9 ix l 9 3/4-24 9 6-1 9 9-9 9 A-9i 9 C-i 9

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1. -1 9 3/4-30 9 9-15 9 A-15: 9 1-2 l 9 3/4-31 9 I_ _ A-16 l 9 i 1-3 9 3/4-32 9 7-1 19 _ A-17l 9 i 3/4-33T 9 7-2 9 A-18 9_I 9

3/4-34 9 7-3 9 I A-19l 9 .

3/4-35J 9 7-4 1 9 ______ A-20 79 I _

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3/4-5l 9 I . A-35l 9 3/4-61 9 i A-36I 9 3/4-7 j 9 i 12-1 j 9 A-37 j 9 i 3/4-8 9A-38 j 9i 3/4-9 9 I I I A-39 9 _

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PNPS-ODCM Rev. 9 TABLE OF CONTENTS i SECTION TITLE PAGE RECORD OF DOCUMENT CHANGES ii LIST OF EFFECTIVE PAGE REVISIONS iii TABLE OF CONTENTS Iv LIST OF FIGURES Vii LIST OF TABLES Viii

1.0 INTRODUCTION

1-1 2.0 DEFINITIONS 2-1 3/4.0 EFFLUENT AND ENVIRONMENTAL CONTROLS 3/4-1 -

3/4.1 INSTRUMENTATION 3/4-2 3/4.1.1 Radioactive Liquid Effluent Instrumentation 3/4-3 I 3/4.1.2 Radioactive Gaseous Effluent Instrumentation 3/4-6 I 3/4.2 RADIOACTIVE LIQUID EFFLUENTS 3/4-11 I 3/4.2.1 Liquid Effluents Concentration 3/4-11 I 1 3/4.2.2 Dose - Liquids 3/4-13 I 314.2.3 Liquid Radwaste Treatment 3/4-14 I 3/4.3 RADIOACTIVE GASEOUS EFFLUENTS 3/4-16 I 3/4.3.1 Gaseous Effluents Dose Rate 3/4-16 I 314.3.2 Dose - Noble Gases 3/4-19 I 3/4.3.3 Dose - Iodine-131, Iodine-133, Radioactive Material in Particulate 3/4-20 I Form, and Tritium 3/4.3.4 Gaseous Effluent Treatment 3/4 I 3/4.4 TOTAL DOSE 3/4-23 I 3/4.4.1 Total Dose 314-23 I 314.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4-24 I 3/4.5.1 Environmental Monitoring Program 3/4-24 I 3/4.5.2 Land Use Census 3/4-46 I

iv

PNPS-ODCM Rev. 9 TABLE OF CONTENTS (continued)

N I SECTION TITLE PAGE 5.0 RADIOLOGICAL EFFLUENT CONTROLS AND METHODOLOGY 5-1 CROSS REFERENCE

6.0 DESCRIPTION

OF RADWASTE SYSTEMS 6-1 6.1 Liquid Radwaste System 6-1 6.2 Treated Gaseous Radwaste System 6-1 7.0 RELEASE POINT AND MONITOR DESCRIPTION 7-1 7.1 Radioactive Effluent Release Point Description 7-1 7.1.1 Liquid Radioactive Waste Effluent Release 7-1 7.1.2 Main Stack Gas Release 7-1 7.1.3 Reactor Building Exhaust Vent Release 7-2 7.2 Radioactive Effluent Monitoring System Description 7-3 7.2.1 Liquid Radioactive Waste Effluent Monitoring System 7-3 7.2.2 Main Stack Gas Monitoring System 7-3 7.2.3 Reactor Building Exhaust Vent Monitoring System 7-4 7.3 Measurement Method During Release 7-6 7.3.1 Liquid Effluent 7-6 7.3t2 Gaseous Effluent 7-6 7.3.3 Limitations 7-6 8.0 MONITOR SETPOINTS 8-1 8.1 Liquid Effluent Monitor 8-1 8.2 Gaseous Effluent Monitors 8-2 8.3 Steam Jet Air Ejector Monitor 8-3 I 8.4 Post-Treatment Radiation Monitor 8-4 I 9.0 CALCULATIONAL METHODS 9-1 9.1 Concentrations of Liquid Effluents 9-1 9.2 Liquid Effluents Dose Assessment Methodology 9-2 9.2.1 Liquid Pathways Annual Dose Rates 9-2 9.2.1.1 Aquatic Foods Ingestion (Fish, shellfish) 9-2 9.2.1.2 Shoreline Deposits (Discharge Canal and Recreational Area) 9-3 9.2.1.3 Swimming (White Horse Beach) 9-3 9.2.1.4 Yachting/Boating (Cape Cod Bay) 9-3 9.2.2 Definitions 9-4 v

PNPS-ODCM Rev. 9 TABLE OF CONTENTS (continued)

SECTION TITLE PAGE 9.3 Gaseous Effluents Dose Assessment Methodology 9-6 9.3.1 Gaseous Pathways Annual Dose Rates from Noble Gases 9-6 9.3.1.1 Gamma Air Dose 9-6 9.3.1.2 Beta Air Dose 9-7 9.3.1.3 Total Body Dose 9-7 9.3.1.4 Skin Dose 9-7 9.3.2 Gaseous Pathways Annual Dose Rates from Iodine 131 and 133, 9-8 Particulates with a Half-Life Greater Than 8 Days, and Tritium 9.3.2.1 Ground Plane Deposition 9-8 9.3.2.2 Breathing/inhalation 9-8 9.3.2.3 Leafy Vegetation Ingestion 9-9 9.3.2.4 Root Crop/Non-Leafy Vegetation Ingestion 9-10 9.3.2.5 Milk Ingestion 9-10 9.3.2.6 Meat Ingestion 9-10 9.3.3 Definitions 9-11 9.4 Total Dose to a Member of the Public 9-15

10.0 RECEPTOR LOCATIONS, HYDROLOGY, AND METEOROLOGY 10-1 11.0 RADIOLOGICAL ENVIRONMENTAL SAMPLING AND 11-1 MEASUREMENT LOCATIONS 12.0 ANNUAL REPORT PREPARATION 12-1 12.1 Annual Effluent and Waste Disposal Report 12-1 12.2 Annual Radiological Environmental Operating Report 12-1

13.0 REFERENCES

13-1 Appendix A DATA REQUIRED FOR EFFLUENT CALCULATIONS A-1 Appendix B DEFINITION OF THE LOWER LIMIT OF DETECTION B-1 Appendix C NRC SAFETY EVALUATION FOR ONSITE DISPOSAL OF C-1 SLIGHTLY CONTAMINATED CONSTRUCTION SOIL vi

PNPS-ODCM Rev. 9 LIST OF FIGURES FIGURE PAGE NUMBER FIGURE TITLE NUMBER 4.2-1 Liquid Radwaste Treatment System Schematic 3/4-15 4.3-1 Gaseous Effluent Treatment System Schematic 3/4-22 3.5-1 Environmental TLD Locations Within the PNPS Protected Area 3/4-32 3.5-2 TLD and Air Sampling Locations: Within 1 Kilometer 3/4-34 3.5-3 TLD and Air Sampling Locations: 1 to 5 Kilometers 3/4-36 3.5-4 TLD and Air Sampling Locations: Greater Than 5 Kilometers 3/4-38 3.5-5 Terrestrial and Marine/Aquatic Sampling Locations 3/4-40 3.5-6 Environmental Sampling and Measurement Control Locations 3/4-42 vii

PNPS-ODCM Rev. 9 LIST OF TABLES TABLE PAGE NUMBER TABLE TITLE NUMBER 1.1 Effluent Controls Cross-Reference 1-2 3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 3/4-4 4.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance 3/4-5 Requirements 3.1-2 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4-7 4.1-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance 3/4-9 Requirements 4.2-1 Radioactive Liquid Waste Sampling and Analysis Program 3/4-12 4.3-1 Radioactive Gaseous Waste Sampling and Analysis Program 3/4-17 3.5-1 Operational Radiological Environmental Monitoring Program 3/4-26 3.5-2 Environmental TLD Locations 3/4-29 3.5-3 Routine Radiological Environmental Sampling Locations 3/4-30 3.5-4 Reporting Levels for Radioactivity Concentrations in Environmental 3/4-44 Samples 4.5-1 Detection Capabilities for Environmental Sample Analysis 3/4-45 5-1 PNPS Effluent Controls And Methodology Cross-Reference 5-2 7-1 Radioactive Effluent Monitor Data 7-5 10-1 Critical Receptor Locations and Atmospheric Dispersion Factors 10-2 A-1 Bioaccumulation Factors To Be Used In The Absence Of Site-Specific A-1 Data A-2 Dose Factors For Immersion In Water A-2 A-3 Recommended Values For Liquid Effluents A-3 A-4 Dose Factors For Exposure To A Semi-infinite Cloud Of Noble Gases A-4 A-5 Stable Element Transfer Data A-5 A-6 Nuclide Transfer Parameters For Goat's Milk A-6 A-7 Animal Consumption Rates A-6 A-8 Recommended Use Factors To Be Applied For The Average Individual A-7 A-9 Recommended Use Factors To Be Applied For The Maximum Exposed A-8 Individual A-10 External Dose Factors For Standing On Contaminated Ground A-9 A-1 1 Inhalation Dose Factors For Adult A-11 A-12 Inhalation Dose Factors ForTeen A-15 A-1 3 Inhalation Dose Factors For Child A-19 A-14 Inhalation Dose Factors For Infant A-23 viii

PNPS-ODCM Rev. 9 LIST OF TABLES (continued)

TABLE PAGE NUMBER TABLE TITLE NUMBER A-15 Ingestion Dose Factors For Adult A-27 A-1 6 Ingestion Dose Factors For Teen A-31 A-17 Ingestion Dose Factors For Child A-35 A-1 8 Ingestion Dose Factors For Infant A-39 A-1 9 Recommended Values For Gaseous Effluents A-43 ix

PNPS-ODCM Rev. 9

1.0 INTRODUCTION

This manual contains the current methodology, parameters, data, and information used in .the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitor alarm/trip setpoints, and in the conduct of the radiological environmental monitoring program.

All effluent controls contained in the Offsite Dose Calculation Manual (ODCM) were originally part of the PNPS Technical Specifications (Reference 1). In response to Generic Letter 89-01 (Reference 2) from the Nuclear Regulatory Commission, these Radiological Effluent Technical Specifications (RETS) were removed from the main body of the Technical Specifications and relocated to the ODCM.

The effluent controls previously existed as parts of Section 3/4.8 and Section 7/8 of the PNPS Technical Specifications. In conjunction with the transfer of the effluent controls from the RETS to the ODCM, the numbering scheme for the individual effluent controls were changed to agree with the numbering scheme present in NUREG-1302, "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Boiling Water Reactors' (reference 27).

The original Technical Specification 3/4.8.F, 'Gaseous Effluent Treatment", addressed both offgas treatment and explosive gas monitoring. In-accordance with the guidance in Generic Letter 89-01, monitoring of explosive gas concentrations was to be retained in the main body of the Technical Specifications. Subsequent to GL89-01, the improved standard technical specifications removed the requirement for explosive gas monitoring, in accordance with NEDO-31466. Therefore, the original Technical Specification 3/4.8.F was partitioned and the portion addressing offgas treatment was relocated to the ODCM Effluent Controls (Control 3/4.3.4). The portion of the original Specification 3/4.8.F addressing explosive gas monitoring was relocated to the FSAR (Reference 3). A cross-reference of the original Technical Specification Section to the revised ODCM Effluent Control Section is included in Table 1.1.

In conjunction with the GL89-01 change, the ODCM was restructured from that which previously existed. None of the requirements or methodologies were changed. Rather, the various sections were reorganized to facilitate support of the effluent controls relocated from the Technical Specifications. Descriptions of effluent monitoring systems and setpoint calculations were moved to the sections immediately following the controls, followed by dose calculation methodologies, and finally by the environmental monitoring program section. Supporting information is listed in the appendices at the rear of the manual.

4s 1-1

PNPS-ODCM Rev. 9 TABLE 1.1 I EFFLUENT CONTROLS CROSS-REFERENCE Original Technical Revised ODCM Effluent Control Topic Specification Section Control Section Liquid Effluents Concentration 3.8.A.1 3.2.1 4.8.A.1 4.2.1.a 4.8.A.2 4.2.1.b Table 4.8-1 Table 4.2-1 Radioactive Liquid Effluent Instrumentation 3.8.B.1 3.1.1 4.8.B.1 4.1.1.a 4.8.B.2 4.1.1.b Table 3.8-1 Table 3.1-1 Table 4.8-2 Table 4.1-1 Liquid Radwaste Treatment 3.8.C.1 3.2.3 4.8.C.1 4.2.3.a 4.8.C.2 4.2.3.b Figure 4.8-1 Figure 4.2-1 Gaseous Effluents Dose Rate 3.8.D.1 3.3.1 4.8.D.1 4.3.1.a 4.8.D.2 4.3.1.b Table 4.8-3 Table 4.3-1 Radioactive Gaseous Effluent 3.8.E.1 3.1.2 Instrumentation 4.8.E.1 4.1.2.a 4.8.E.2 4.1.2.b Table 3.8-2 (partial) Table 3.1-2 Table 4.8-4 (partial) Table 4.1-2 Gaseous Effluent Treatment 3.8.F.a 3.3.4 3.8.F.1 Relocated to FSAR 4.8.F.1 4.3.4 4.8.F.2 Relocated to FSAR Figure 4.8-2 Figure 4.3-1 Environmental Monitoring 7.1.A 3.5.1 8.1.A 4.5.1 Table 7.1-1 Table 3.5-4 Table 8.1-1 Table 3.5-1 Table 8.1-2 Table 3.5-3 Table 8.1-3 Table 3.5-2 Table 8.1-4 Table 4.5-1 Land Use Census 7.1.B 3.5.2 8.1.B 4.5.2 i

1-2

, v .h

PNPS-ODCM Rev. 9 TABLE 1.1 (continued) i EFFLUENT CONTROLS CROSS-REFERENCE Original Technical Revised ODCM Effluent Control Topic Specification Section Control Section Dose - Liquids 7.2.A 3.2.2 8.2.A 4.2.2 Dose - Noble Gases 7.3.A 3.3.2 8.3.A 4.3.2 Dose - lodine-131, Iodine-133, Radioactive 7.4.A 3.3.3 Material in Particulate Form, and Tritium 8.4.A 4.3.3 Total Dose . 7.5.A 3.4.1 8.5.A 4.4.1 1-3

PNPS-ODCM Rev. 9 2.0 DEFINITIONS This section lists definitions which are unique to the ODCM. Other definitions pertaining to actions and surveillance requirements for the various controls can be found in the Technical Specifications (Reference 1).

2.1 ACTION - ACTION shall be that part of a Control that prescribes remedial measures required under designated conditions.

2.2 CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm, interlock and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

2.3 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 channels measuring the same parameter.

2.4 CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.

b. Bistable channels - the injection of a simulated signal into the sensor to verify.

OPERABILITY Including alarm and/or trip functions.

The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is tested.

2.5 DOSE EQUIVALENT 1-131 - DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in ICRP 30, Supplement to Part 1, page 192-212, Table titled, Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity'.

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

2.7 NOMINAL STEADY STATE LEVEL - NOMINAL STEADY STATE LEVEL shall be the baseline level of radionuclide concentrations and/or radiation monitor readings resulting from at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of operation at a given reactor power level and hydrogen injection rate.

2-1

PNPS-ODCM Rev. 9 2.8 OFFSITE DOSE CALCULATION MANUAL (ODCM) - The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain: (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specifications Administrative Controls 5.5.1 and 5.5.4; and, (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Technical Specifications Administrative Controls 5.6.2 and 5.6.3.

2.9 OPERABLE - OPERABILITY - A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its 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).

2.10 RADWASTE TREATMENT SYSTEM

a. Gaseous Radwaste Treatment System - The gaseous radwaste treatment system is that system identified in Figure 4.3-1.

b. Liquid Radwaste Treatment System - The liquid radwaste treatment system is that system identified in Figure 4.2-1.

2.11 RATED THERMAL POWER - RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2028 MWL.

2.12 REPORTABLE EVENT - A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10CFR Part 50.

2.13 SITE BOUNDARY - The SITE BOUNDARY is shown in Figure 1.6-1 in the FSAR (Reference 3).

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

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

2.16 UNRESTRICTED AREA - An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for the purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

2-2

PNPS-ODCM Rev. 9 3/4.0 EFFLUENT AND ENVIRONMENTAL CONTROLS This section includes the effluent and environmental controls that were originally part of the PNPS Technical Specifications. With the exception of the environmental monitoring program previously listed in the Technical Specifications (Reference 1), these controls were relocated into the ODCM without any substantial changes, in accordance with Generic Letter 89-01 (Reference 2). Text and tables were reformatted to the style of the ODCM. The various controls were renumbered from the original numbering scheme of the Technical Specifications. A cross-reference of the old Technical Specifications section to the new ODCM section is presented in Table 1.1.

Prior to the Generic Letter 89-01 change to the ODCM (Revision 8), the ODCM contained an enhanced radiological environmental monitoring program (REMP), above that required by the Technical Specifications. To prevent confusion and capture the more inclusive monitoring program that existed In the ODCM, the original Technical Specification REMP was replaced with the REMP described in the ODCM. Therefore, the monitoring program listed in section 3/4.5 contains more samples and monitoring locations than existed in the Technical Specifications REMP prior to the Generic Letter 89-01 change.

In addition to the changes in the REMP program described above, all of the tables were revised with the latest distance and direction information available. The global positioning system (GPS) was used to verify the locations of the various sampling and monitoring stations, and the tables were updated accordingly. In keeping with governmental efforts to adopt the metric system of measurement, all distances have been listed in metric units (meters and/or kilometers) in the various tables and figures.

Any changes in distances and directions to the various monitoring locations from those originally listed in the Technical Specifications REMP are corrections based on new information. None of the locations of the sampling stations were actually changed. Some of the verbal descriptions, especially those for near-plant TLDs, have been updated to reflect current names of buildings and other areas near Pilgrim Station. Again, none of the physical locations were altered, and the change merely reflects up-to-date place names adopted by station management.

In 1977, Boston Edison Company was pursuing construction of a second unit on the PNPS site.

As part of the preliminary licensing efforts for this second unit, Pilgrim Station committed to a special marine sampling program under the REMP. This program was much more aggressive than that outlined in standard NRC guidance for an environmental monitoring program, and included collecting many more samples, duplicate/split sampling, analysis of special radionuclides, and analysis to detection'limits lower than those recommended by the NRC. This specialized sampling program was agreed to by Boston Edison Company for a period not to exceed 10 years.

Due to the inclusion of the REMP in the Technical Specifications at that time, the program was carried forward beyond the 10-year period.

Following an evaluation of results obtained from this specialized marine sampling program over the past 25 years, it has been determined that the analyses have shown that the impact of radioactivity in liquid discharges on the general public and environment is negligible. In light of the fact that the terms of the sampling program have expired, the specialized program is no longer warranted. Furthermore, replacement of the specialized program with a marine sampling program such astlfiat prescribed by the NRC in NUREG-1302 (reference 27) and the Branch Technical Position on Environmental Monitoring (reference 28) will still allow PNPS personnel to evaluate the impact of its operations on the environment and general public. Therefore, PNPS has dropped most of the'"'4ecialized requirements and has adopted the standard model for marine sampling recommended by the NRC.

3/4-1 I

PNPS-ODCM Rev. 9 In order to streamline the flow of information for each of the applicable effluent controls, the technical bases for the controls were relocated from the end of Section 3/4 to within the applicable control. As is the case with Technical Specifications, the bases are not considered to be part of the control or its requirements. Rather, the bases provide the technical rationale behind the applicable control, and are listed to provide additional clarification regarding the specific control.

3/4-2

PNPS-ODCM Rev. 9 3/4.1 INSTRUMENTATION 3/4.1.1 Radioactive Liquid Effluent Instrumentation CONTROLS 3.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.1-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Controls 3.2.1 are not exceeded during periods when liquid wastes are being discharged via the radwaste discharge header.

For releases other than the radwaste discharge header, the above specification does not apply, these releases shall be made in accordance with Action 1 of Table 3.1-1.

APPLICABILITY: As shown in Table 3.1-1.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of Control 3.2.1 are met, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or change the setpoint so that it is acceptably conservative or declare the channel inoperable.

b. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the action shown in Table 3.1-1.

SURVEILLANCE REQUIREMENTS 4.1.1.a The setpoints for monitoring instrumentation shall be determined in accordance with the ODCM.

4.1.1.b Each radioactive liquid effluent monitoring instrumentation channel shall be

demonstrated OPERABLE at the frequencies shown in Table 4.1-1.

BASES 3/4.1.1 Radioactive Liquid Effluent Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the Offsite Dose Calculation Manual (ODCM) to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CFR50.

3/4-3 I

PNPS-ODCM Rev. 9 TABLE 3.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Operable Applicabilitv Action(')

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE I

a. Liquid Radwaste 1 During actual discharge of 1 Effluent Line liquid wastes

2. FLOW RATE MEASUREMENT DEVICES I

a. Liquid Radwaste 1 During actual discharge of 2 Effluent Line liquid wastes

b. Discharge Canal N/A During actual discharge of 3 liquid wastes

3. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Reactor Building Closed 1 During operation of the reactor building 4 Cooling Water Loop HA" closed cooling system

b. Reactor Building Closed During operation of the reactor building Cooling Water Loop AB" 1 closed cooling system 4 1)Action's Required--

ACTION 1: With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases may be resumed provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Control 4.2.1.a; and,

b. An independent verification of the release rate calculations is performed; and,

c. An independent verification of the discharge line valving is performed.

ACTION 2: With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided that the flow rate isverified at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Flow will be estimated based on design flow rate of the operating circulating water pumps and/or operating salt service water pumps.

ACTION 3: Flow will be estimated based on the sum of the operating waste discharge pumps, operating circulating water pumps, and/or operating salt service water pumps.

ACTION 4: With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided that at least i once per day grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than 5E-07 uCI/mL.

3/4-4 I

PNPS-ODCM Rev. 9 TABLE 4.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Source Channel Channel Instrument Check Check Calibration Functional Test

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE I

a. Liquid Radwaste N/A Once per Quarterly Effluents Line 24 months 2 )

2. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste (1) N/A Once per Quarterly Effluents Line 24 months

3. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Reactor Building Closed (3) N/A Once per Quarterly Cooling Water Loop 'A' 24 months 2)

b. Reactor Building Closed (3) N/A Once per Quarterly Cooling Water Loop 'B" 24 months 2 )

Z During or prior to release via this pathway.

(2) Previously established calibration procedures will be used for these requirements.

(3) During operation of the reactor building closed cooling water system.

3/4-5 I

PNPS-ODCM Rev. 9 3/4.1 INSTRUMENTATION

) 3/4.1.2 Radioactive Gaseous Effluent Instrumentation CONTROLS 3.1.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.3.1 are not exceeded.

APPLICABILITY: As shown in Table 3.1-2 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of Control 3.3.1 are met, change the setpoint so that it is acceptably conservative or declare the channel inoperable.

b. With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the action shown in Table 3.1-2.

SURVEILLANCE REQUIREMENTS 4.1.2.a The setpoints shall be determined in accordance with ODCM.

4.1.2.b Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE at the frequencies shown in Table 4.1-2.

BASES.*

3/4.1.2 Radioactive Gaseous Effluent Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General design Criteria 60, 63, and 64 of Appendix A to 1 OCFR50.

3/4-6 I

PNPS-ODCM Rev. 9 TABLE 3.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Operable Applicability Parameter Action~')

1. MAIN STACK EFFLUENT MONITORING SYSTEM

a. Noble Gas Activity 1 (2) Radioactivity Rate 1 Monitor Providing Alarm Measurement

b. Iodine Sampler 1 (2) Collect Halogen 2 Cartridge Sample

c. Particulate Sampler 1 (2) Collect Particulate 2 Filter Sample

d. Effluent System Flow 1 (2) System Flow Rate 3 Rate Measuring Device Measurement

e. Sampler Flow Rate 1 (2) Sampler Flow Rate 3 Measuring Device Measurement

2. REACTOR BUILDING VENTILATION EFFLUENT MONITORING SYSTEM

a. Noble Gas Activity 1 (2) Radioactivity Rate 1 Monitor Providing Alarm Measurement

b. Iodine Sampler 1 - (2) Collect Halogen 2 Cartridge Sample

c. Particulate Sampler 1 (2) Collect Particulate 2 Filter Sample

d. Effluent System Flow 1 (2) System Flow Rate 3 Rate Measuring Device Measurement

e. Sampler Flow Rate 1 (2) Sampler Flow Rate 3 Measuring Device Measurement

3. STEAM JET AIR EJECTOR RADIOACTIVITY MONITOR

a. Noble Gas Activity Monitor 1 (3) Noble Gas Radioactivity 4 (Providing Alarm and Rate Measurement Auto-isolation of Stack) 3/4-7 I ;.- .

PNPS-ODCM Rev. 9 TABLE 3.1-2 (continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Operable Applicability Parameter Action<1 )

4. POST-TREATMENT RADIATION MONITOR

a. Noble Gas Activity Monitor 1 (4) Noble Gas Radioactivity 1 (Providing Alarm and Rate Measurement Auto-isolation of Stack)

(1) Actions Required --

ACTION 1*: With the number of OPERABLE channels 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 2': With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.3-1.

ACTION 3*: With the number of OPERABLE channels 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 4: With the number of OPERABLE channels less than required by the, minimum channels OPERABLE requirement, gases from the steam jet air ejector may be released to the offgas system for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided:

a. The augmented offgas treatment system-iis not bypassed; and,

b. The post-treatment radiation monitor (downstream) is OPERABLE; Otherwise, be in at least hot standby within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 5*: With the number of OPERABLE channels 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 week and these samples are analyzed for activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

'Note: (For Actions 1, 2, 3, and 5) If the instruments are not returned to OPERABLE status within 30 days, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

(2) During releases via this pathway.

(3) During operation of steam jet air ejector.

(4) During operation of augmented offgas treatment system.

3/4-8 I

PNPS-ODCM Rev. 9 TABLE 4.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Source Channel Channel Instrument Check Check Calibration Functional Test

1. MAIN STACK EFFLUENT MONITORING SYSTEM

a. Noble Gas Activity DaWlV) Monthly Once per Quarterly Monitor (2channels) 24 months (2)

b. Iodine Sampler N/A N/A N/A N/A Cartridge

c. Particulate Sampler N/A N/A NIA N/A Filter

d. Effluent System Flow Daily 1) N/A Once per Quarterly Rate Measuring Device 24 months

e. Sampler Flow Rate Daily(1) NIA Once per Quarterly Measuring Device 24 months

2. REACTOR BUILDING VENTILATION EFFLUENT MONITORING SYSTEM

a. Noble Gas Activity Dail( 1 ) Monthly Once per Quarterly Monitor (2channels) 24 months (2)

b. Iodine Sampler N/A N/A N/A N/A Cartridge

c. Particulate Sampler N/A N/A N/A N/A Filter

d. Effluent System Flow Daily(1) N/A Once per Quarterly Rate Measuring Device 24 months

e. Sampler Flow Rate Daily(t) N/A Once per Quarterly Measuring Device 24 months

3. STEAM JET AIR EJECTOR RADIOACTIVITY MONITOR

a. Noble Gas Activity Daily(3) N/A Once per Quarterly Monitor (2channels) 24 months( 2) 3/4-9 I

PNPS-ODCM Rev. 9 TABLE 4.1-2 (continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Source Channel Channel Instrument Check Check Calibration Functional Test

4. POST-TREATMENT RADIATION MONITOR

a. Noble Gas Activity Daily(4) N/A Once per Quarterly Monitor (2 channels) 24 months(2 )

( During releases via this pathway.

2 Previously established calibration procedures will be used for these requirements.

° During operation of the steam jet air ejector.

(4) During operation of the augmented offgas treatment system.

3/4-10 I

PNPS-ODCM Rev. 9 3/4.2 RADIOACTIVE LIQUID EFFLUENTS 3/4.2.1 Liquid Effluents Concentration CONTROLS 3.2.1 The concentration of radioactive material released at any time from the site to areas at and beyond the SITE BOUNDARY shall be limited to the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration of individual Isotopes shall be limited to 2E-04 +/-iCVmL.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released from the site to areas at and beyond the SITE BOUNDARY exceeding the above limits, without delay restore concentration within the above limits.

SURVEILLANCE REQUIREMENTS 4.2.1.a The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.2-1.

4.2.1.b The results of pre-release analyses shall be used with calculational methods in the Offsite Dose Calculation Manual (ODCM) to assure that the concentration at the point of release is limited to the values in Control 3.2.1.

BASES N 3/4.2.1 Liquid Effluents Concentration This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents at and beyond the SITE BOUNDARY will be less than the concentration levels specified in 10CFR20, Appendix B, Table 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water at and beyond the SITE BOUNDARY will not result in exposures within (1) the Section I.A design objectives of Appendix I, 10CFR50, to a MEMBER OF THE PUBLIC and (2) restrictions authorized by 10 CFR 20.1301 (e).

3/4-11 I

PNPS-ODCM Rev. 9 TABLE 4.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Activity Detections')

Liquid Release Type Frequency Frequency Analysis

1. Batch Waste Release Tankst'~ Principal Each Prior to Gamma 5E-07

a. Non-treatable Releases Batch Each Emitters(3)

(e.g., Neutralizer Sumps), Batch 1-131 1E-06 AND Release Dissolved and

b. Treatable Releases Entrained 1E-05 (e.g., Radwaste Tanks) . Gases Composite Monthly H-3 1 E-05 from Each Composite' 4 ) Gross Alpha 1E-07 Batch Quarterly Sr-89, Sr-90 5E-08 Composite(4) Fe-55 1E-06

2. Continuous Releases Weekly Principal Grab Weekly Gamma 5E-07

a. Salt Service Water Sample Emitters(3 )

(1) Refer to Appendix B of the ODCM for definition of lower limit of detection (LLD).

(2) A batch release is the discharge of liquid wastes of a discrete volume.

3) The principal gamma emitters for which the LLD control 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. 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 be analyzed and reported in the Annual Radioactive Effluent Release Report.

(4) A composite sample is one inwhich 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.

3/4-12 I

PNPS-ODCM Rev. 9 3/4.2 RADIOACTIVE LIQUID EFFLUENTS 3/4.2.2 Dose - Liquids CONTROLS 3.2.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released at and beyond the SITE BOUNDARY shall be limited:

a. During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ; and,

b. During any calendar year to < 3 mrem to the total body and to < 10 mrem to any organ.

APPLICABILITY: At all times ACTION:

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a special report that identifies the cause(s), corrective actions taken, and corrective actions to be taken.

SURVEILLANCE REQUIREMENTS 4.2.2 Dose Calculations - Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM for each calendar month during which releases occurred.

BASES 3/4.2.2 Dose - Liquids This section is provided to implement the requirements of Sections Il.A, III.A, and IV.A of 10CFR50, Appendix I, to assure that the releases of radioactive material in liquid effluents will be kept 'as low as is reasonably achievable." Because Pilgrim is not a site where plant operations can conceivably affect drinking water, none of these requirements are intended to assure compliance with 40CFR141. The dose calculations in the ODCM implement the requirements of 10CFR50, Appendix I, Section II.A to ensure 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 will be 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 10CFR50, 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.

3/4-13 I

PNPS-ODCM Rev. 9 3/4.2 RADIOACTIVE LIQUID EFFLUENTS 3/4.2.3 Liquid Radwaste Treatment CONTROLS 3.2.3 The liquid radwaste treatment system shall be maintained and used to reduce the radioactive materials in liquid wastes prior to their discharge when the dose due to liquid effluent releases to areas at and beyond the SITE BOUNDARY averaged over a 31-day period would exceed 0.06 mrem to the total body or 0.20 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a special report which includes the following information:

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

2. Action(s) taken to-restore the inoperable equipment to OPERABLE status; and,

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

SURVEILLANCE REQUIREMENTS 4.2.3.a Doses due to liquid releases at and beyond the SITE BOUNDARY shall be calculated at least once per 31-day period in accordance with the ODCM, only if releases in that period have occurred.

4.2.3.b The liquid radwaste treatment system schematic is shown in Figure 4.2-1.

BASES 3/4.2.3 Liquid Radwaste Treatment 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 10CFR50.36a, General Design Criteria 60 of Appendix A to 10CFR50 and design objective Section IL.D of Appendix I to 1bCFR50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10CFR50, for liquid effluents.

3/4-14 I

PNPS-ODCM Rev. 9 HIGH PURITY WASTE SYSTEM Clean Waste Mixed Bed Treated Water Discharge or Tanks Ion Exchange Tanks Recycle LOW PURITY WASTE SYSTEM Chemical Waste I-Tanks Discharge i

DETERGENT WASTE SYSTEM (Decon Areas)

Miscellaneous Waste Tanks or Non-treatable Releases 0 Discharge (e.g., Neutralizer Sum s Figure 4.2-1 Liquid Radwaste Treatment System Schematic 3/4-15 I

PNPS-ODCM Rev. 9 3/4.3 RADIOACTIVE GASEOUS EFFLUENTS 3/4.3.1 Gaseous Effluents Dose Rate CONTROLS 3.3.1 The instantaneous dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see FSAR Figure 1.6-1) 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 iodine-131, iodine-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:

With the instantaneous dose rate(s) exceeding the above limits, without delay restore the release rate to within the above limit(s).

SURVEILLANCE REQUIREMENTS 4.3.1.a The instantaneous dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 3.3.1.a on a continuous basis using the noble gas activity monitors with appropriate setpoints and in accordance with the ODCM.

4.3.1.b The instantaneyous dose rate due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the limits of Control 3.3.1.b in accordance with the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.3-1.

BASES 3/4.3.1 Gaseous Effluents Dose Rate This control is provided to ensure that the dose rate at anytime at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20. The annual dose limits are the doses associated with the concentration of 100FR20, Appendix B, Table 2. 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 10CFR20.1001-20.2401. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the individual will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBERS OF THE PUBLIC at or beyond the SITE BOUNDARY to

500 mrem/year to the total body or to

3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to < 1500 mrem/year for the nearest cow to the plant.

3/4-16

PNPS-ODCM Rev. 9 TABLE 4.3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Type of Activity Lower Limit of Sampling Analysis Analysis Detection~')

Gaseous Release Type Frequency Frequency _CimL Y(2) Principal Main Stack Monthly Monthl/ 2 ) Gamma) 1 E-04 and Grab Emitters<3 )

Reactor Building Vent Sample H-3 1E-06 Weeklyl5 Continuoust4 ) Charcoal 1-131 1E-12 Sample Weeklytb) Principal Continuous~4 l Particulate Gamma 1E-11 Sample Emitters, 3 Monthly ContinuousP4 ) Composite Gross Alpha 1E-11 Particulate Sample Quarterly Continuous( 4 ) Composite Sr-89, Sr-90 1E-11 Particulate Sample Continuous Noble Gas Continuous(4) Noble Gas Gross 1E-06 Monitor Gamma

)

Post-Treatment Radiation"A Monthly Monthly Principal Monitor Grab Gamma 1 E-04 Sample Emitters( 3)

1) Refer to Appendix B of the ODCM for definition of lower limit of detection (LLD).

(2) A noble gas sample shall be collected and analyzed as soon as practicable following any 15-minute or longer sustained increase in noble gas release rates more than a factor of 3 above NOMINAL STEADY STATE LEVEL.

(3) The principal gamma emitters for which the LLD control applies are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases; and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall be analyzed and reported in the Annual Radioactive Effluent Release Report.

(4) 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 3.3.1, 3.3.2, and 3.3.3.

(5) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from the sampler. Sampling of the affected release point shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the

) corresponding LLDs may be increased by a factor of 10. This requirement applies ONLY IF: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in reactor coolant has increased more than a factor of 3 above NOMINAL STEADY STATE LEVEL; OR (2) the noble gas monitor shows that effluent activity has Increased by more than a factor of 3 above NOMINAL STEADY STATE LEVEL. Increased 3/4-17 I

PNPS-ODCM Rev. 9 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sampling can be terminated when BOTH: (1) DOSE EQUIVALENT 1-131 concentration in reactor coolant, AND (2) noble gas effluent release rate are less than a factor of 3 times above NOMINAL STEADY STATE LEVEL. When comparison is made using levels under which 72-hour steady state operation has not been achieved, DOSE EQUIVALENT 1-131 concentrations and noble gas release rates should be adjusted for expected changes in response to changes in reactor power level and/or hydrogen injection rate.

3/4-18 I

PNPS-ODCM Rev. 9 3/4.3 RADIOACTIVE GASEOUS EFFLUENTS 3/4.3.2 Dose - Noble Gases CONTROLS 3.3.2 The air dose in areas at and beyond the SITE BOUNDARY due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, to < 5 mrad for gamma radiation and < 10 mrad for beta radiation; and,

b. During any calendar year, to < 10 mrad for gamma radiation and < 20 mrad for beta radiation.

APPLICABILITY: At all times ACTION:

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a special report which identifies' the cause(s), the corrective actions taken, and corrective actions to be taken.

SURVEILLANCE REQUIREMENTS 4.3.2 Dose Calculations - Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM for each calendar month during which releases occurred.

BASES '

3/4.3.2 Dose - Noble Gases This section is provided to implement the requirements of 10CFR50, Appendix I, Sections lI.B, III.A, and IV.A to ensure that the releases of radioactive material in gaseous effluents will be kept Ras low as is reasonably achievable." The surveillance requirements implement the requirements of 10CFR50, Appendix I, Section III.A to ensure that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations 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 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 will be based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

3/4-19 I

PNPS-ODCM Rev. 9 3/4.3 RADIOACTIVE GASEOUS EFFLUENTS 3/4.3.3 Dose - Iodine-131. Iodine-133. Radioactive Material in Particulate Form, and Tritium CONTROLS 3.3.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, radioactive materials in particulate form with half-lives greater than 8 days, and tritium in gaseous effluents released to areas at and beyond the SITE BOUNDARY shall be

-limited to the following:

a. During any calendar quarter to < 7.5 mrem to any organ; and,

b. During any calendar year to < 15 mrem to any organ.

APPLICABILITY: At all times ACTION:

With the calculated dose from the release of iodine-131, iodine-133, radioactive materials in particulate form, and tritium in gaseous effluents exceeding any of the above limits; prepare and submit to the Commission within 30 days, a special report which identifies the cause(s), corrective actions taken, and the corrective actions to be taken.

SURVEILLANCE REQUIREMENTS 4.3.3 Dose Calculations - Cumulative dose contributions for the total time period shall be determined for iodine-131, iodine-133, radioactive material in particulate form with half-lives greater than 8 days, and tritium in accordance with the ODCM for each calendar month during which releases occurred.

BASES 3/4.3.3 Dose - lodine-131. lodine-133. Radioactive Material In Particulate Form, And Tritium This section is provided to implement the requirements of Sections II.C, III.A and IV.A of 10CFR50, 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 of 10CFR50, Appendix I, Section' lIl.A to ensure that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods approved by the NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guides 1.109 and 1.111. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, radioactive material in particulate form with half-lives greater than 8 days, and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are:

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.

3/4-20 I

PNPS-ODCM Rev. 9 3/4.3 RADIOACTIVE GASEOUS EFFLUENTS 3/4.3.4 Gaseous Effluent Treatment CONTROLS 3.3.4 The augmented offgas system shall be put into service prior to reaching 50 percent reactor power during startup.

APPLICABILITY: Whenever the plant is operating at or above 50 percent reactor power.

ACTION:

With gaseous effluents being discharged for more than 14 days without treatment, prepare and submit to the Commission within 30 days, a special report which includes the following Information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability; and,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status; and,

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

SURVEILLANCE REQUIREMENTS 4.3.4.a Augmented offgas (post-treatment radiation monitor) annunciator OPERABILITY shall be verified once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the augmented offgas system is in use.

M4.3.4.b The gaseous effluent treatment system schematic is shown in Figure 4.3-1.

BASES 3/4.3.4 Gaseous Effluent Treatment The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable.' This control implements the requirements of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFR50, and design objective Section II.D of Appendix I to 10CFR50. The specified limits governing the use of appropriate p5ortions of the systems were specified as a suitable fraction of the guide set forth in Sections Il.B and IL.C of Appendix 1,10CFR50, for gaseous effluents.

3/4-21. I

PNPS-ODCM Rev. 9 SJAE from1 l F7[, Dischargel Main Recombiner Conden Drier Charcoal - to Main Condenser 1LStack lGLAND SEALS 1.7 Minute I ,I Discharge to I from Turbine Gland Seals 1---*l Holdup' I I Main Stack I MECHANICAL VACUUM PUMP I Discharge to I from Main Condenser Main Stack I DRYWELL I Discharge to I.

I from Drywell I Main Stack

]'

REACTOR BUILDING Discharge to from Reactor Building Reactor Building Vent

]'

RADWASTE BUILDING Discharge to from Radwaste Building Reactor Building Vent 1'

TURBINE BUILDING Discharge to from Turbine Building Reactor Building Vent (1)No significant effect in reducing offsite doses when compared to transit time required for releases to reach SITE BOUNDARY.

Figure 4.3-1 Gaseous Effluent Treatment System Schematic 3/4-22 I

PNPS-ODCM Rev. 9 3/4.4 TOTAL DOSE 3/4.4.1 Total Dose CONTROLS 3.4.1 The dose or dose commitment to any MEMBER OF THE PUBLIC from Pilgrim Station sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over a period of any calendar year.

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 3.2.2, 3.3.2 or 3.3.3; prepare and submit a special report to the Commission and limit the subsequent releases such that the dose or dose commitment to any MEMBER OF THE PUBLIC from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except thyroid, which is limited to < 75 mrem) over any calendar year. This special report shall include an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR190 standard.

Otherwise, obtain a variance from the Commission to permit releases which exceed the 40CFR1 90 standard.

SURVEILLANCE REQUIREMENTS 4.4.1 Dose Calculations - Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 3.2.2, 3.3.2, and 3.3.3; and in accordance with the ODCM.

BASES 3/4.4.1 Total Dose This section is provided to meet the dose limitations of 40CFR190 that have now been incorporated into 10CFR20 by 46FR18525. The control requires the preparation and submittal of a special report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of 10CFR50, Appendix I. 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 40CFR190 if the individual reactors remain within the reporting requirement level. 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 40CFR190 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, except 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 limits of 40CFR190, a request for a variance in a special report in accordance with 40CFR190.11 and 10CFR20.2203(a)(4) is considered to be a timely request and fulfills the requirements of 40CFR190 until NRC staff action is completed. This is provided that the release conditions resulting in violation of 40CFR1 90 have not already been corrected. The variance only relates to the limits of 40CFR190, and does not apply in any way to the other requirements for dose limitation of 10CFR20. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in any operation that is part of the nuclear fuel cycle.

3/4-23 I

PNPS-ODCM Rev. 9 3/4.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.5.1 Environmental Monitoring Program CONTROLS 3.5.1 An environmental monitoring program shall be conducted to evaluate the effects of station operation on the environs and to verify the effectiveness of the source controls on radioactive materials The radiological environmental monitoring program shall be conducted as specified in Tables 3.5-1 through 3.5-3.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Tables 3.5-1 through 3.5-3, prepare and submit to the Commission, in the Annual Radiological Environmental Monitoring Report required by Technical Specifications Administrative Control 5.6.2, 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 at a specified location exceeding the reporting levels of Table 3.5-4 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, 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 Controls 3.2.2, 3.3.2, or 3.3.3.

When more than one of the radionuclides in Table 3.5-4 are detected in the sampling medium, this report shall be submitted if:

Concentration (1) + Concentration (2) + ..... 1.0 Reporting Level (1) Reporting Level (2)

When radionuclides other than those in Table 3.5-4 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater-than the calendar year limits of Controls 3.2.2, 3.3.2, or 3.3.3. 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 Monitoring Report.

3/4-24 I

PNPS-ODCM Rev. 9 3/4.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.5.1 Environmental Monitoring Program (Continued)

CONTROLS ACTION: (continued)

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.5-1, identify locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specifications Administrative Control 5.6.2, identify the cause of the unavailability of samples and identify the new location(s) obtaining replacement samples in the next Annual Radiological Environmental Monitoring Report and also include in the report the table for the ODCM reflecting the new location(s).

SURVEILLANCE REQUIREMENTS 4.5.1 The radiological environmental monitoring samples shall be collected pursuant to Tables 3.5-1 through 3.5-3 in the Offsite Dose Calculation Manual (ODCM) and shall be analyzed pursuant to the requirements of Table 3.5-1 and the detection capabilities required by Table 4.5-1.

1. Cumulative dose contributions from the current calendar year from radionuclides detected in environmental samples shall be determined in accordance with the methodology and parameters in the ODCM. These results will be reported in the Annual Radiological Environmental Monitoring Report.

BASES 3/4.5.1 Environmental Monitoring Program An environmental radiological monitoring program is conducted to verify the adequacy of in-plant controls on the release of radioactive materials. The program is designed to detect radioactivity concentrations to ensure that radiation doses to individuals do not exceed the levels set forth in 10CFR50, Appendix I.

Groundwater flow at the plant site is into Cape Cod Bay; therefore, terrestrial monitoring of groundwater is not included in this program.

Detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD). The LLD in Table 4.5-1 is considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori(aftbr the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually); Currie, L.A., 'Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry", Anal. Chem. 40, 586-93 (1968); and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4-25 I

PNPS-ODCM Rev. 9 TABLE 3.5-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway, Sampling, Sampling, Sample, or Measurement, Measurement, Type and Frequency Measurement and/or Collection and/or Collection of Analysis or Type Locations<1 ) Frequency Measurement DIRECT RADIATION Environmental TLD 110 Locations, Quarterly Collection Gamma exposure (2);

See Table 3.5-2 Quarterly AIRBORNE Particulates 11 Locations, Continuous sampling with Gross beta radioactivity See Table 3.5-3 particulate filter; analysis 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or Weekly Collection more after weekly filter change (3); Weekly AND Gamma isotopic (4) of composite by location; Quarterly Radioiodines 11 Locations, Continuous sampling with 1-131 analysis; Weekly See Table 3.5-3 charcoal cartridge; Weekly Collection TERRESTRIAL Green Leafy Vegetables Plymouth County Farm( 5 ), At time of harvest Gamma isotopic Bridgewater Farm analysis (4) on edible Control (6) portions Cranberries Manomet Point Bog, At time of harvest Gamma isotopic Bartlett Rd. Bog, . analysis (4) on edible Pine St. Bog Control (6) portions 3/4-26 I

PNPS-ODCM Rev. 9 TABLE 3.5-1 (continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway, Sampling, Sampling, Sample, or Measurement, Measurement, Type and Frequency Measurement and/or Collection and/or Collection of Analysis or Type Locations( 1 ) Frequency Measurement MARINEIAQUATIC Surface Water M Discharge Canal, Continuous Composite Gamma isotopic (4),

Sample analysis of monthly

_-__ _ _ _ -__ -- --- - composite samples; Bartlett Pond, Weekly grab sample AND Powder Point Control (6) H-3 analysis of quarterly composite samples Sediment Discharge Canal Outfall, - Semiannual Collection Gamma isotopic Manomet Point, analysis (4)

Plymouth Beach, Plymouth Harbor, Duxbury Bay Control (6)

Green Harbor Control (6)

Irish Moss (Algae) Discharge Canal Outfall, Semiannual Collection Gamma isotopic Manomet Point, analysis (4)

Ellisville, BErant Rock Control (6)

Shellfish (mussels and Discharge Canal Outfall, Semiannual Collection Gamma isotopic clams) Manomet Point, analysis (4)on edible Plymouth Harbor, portions Duxbury Bay Control (6)

Green Harbor Control (6)

Lobster Discharge Canal Outfall . Four times per season, Gamma isotopic from May through analysis (4)on edible October portions Offshore Control (6) Once per season Fishes Discharge Canal Outfall Semiannual for Groups I Gamma isotopic and 11(8); annually in analysis (5)on edible season for Groups Ill and portions IV (8)

Offshore Control (3) Annualpy for each group 1) 3/4-27 I

PNPS-ODCM Rev. 9 TABLE 3.5-1 (continued)

NOTES (1) Specific parameters of distance -and direction sector from centerline of the reactor, and additional description where pertinent, are provided for each sample location in Table 3.5-1 in a subsequent tables and figures in the ODCM. Deviation are permitted from the required sampling schedule if samples are unobtainable due to circumstances such as hazardous conditions, extreme inclement weather, seasonable unavailability, and malfunction of automatic sampling equipment. If samples are unobtainable due to sampling equipment malfunction, efforts shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to PNPS Technical Specification Administrative Control 5.6.2. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program outlined in ODCM Table 3.5-1 and subsequent tables. Pursuant to PNPS Technical Specification Administrative Control 5.5.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including revised figure(s) and table(s) for the ODCM reflecting the new location(s) with supporting Information identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples.

(2) Minimum sensitivity for TLD exposure measurements is 1 j+/-R/hr, or 2.19 mR/standard quarter.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow of radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

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

(5) These locations may be altered in accordance with results of land use census surveys discussed in Effluent Control 4.5.2.

(6) Indicates control location.

(7) Groundwater flow at the plant site is into Cape Cod Bay; therefore, terrestrial monitoring of groundwater and/or drinking water is not included in this program.

(8) Fish analyses will be performed on samples from each of the following groups:

I. Bottom Oriented II. Near Bottom l1l. Anadromous IV. Coastal Migratory Distribution Winter Flounder Tautog Alewife Bluefish Yellowtail Flounder Cunner Rainbow Smelt Atlantic Herring Atlantic Cod Striped Bass Atlantic Menhaden Pollock Atlantic Mackerel Hakes 3/4-28 I

PNPS-ODCM Rev. 9 TABLE 3.5-2 ENVIRONMENTAL TLD LOCATIONS TLD Station I Location"' I TLD Station I LocationkiN Description i Code Distance/Direction I Description I Code Distance/Direction TLDs Within Protected Area Zone 1 TLDs: 0-3 km O&M/RXB. BREEZEWAY P21 50 m SE EMERSON ROAD EM 1.53 km SSE EXEC.BUILDING P24 57 m W EMERSON/PRISCILLA EP 1.55 km SE FENCE-R SCREENHOUSE P04 66 m N ACCESS ROAD AR 1.59 km SSE O&M - 2ND W WALL P20 67 m SE BAYSHORE BS 1.76 km W EXEC.BUILDING LAWN P25 76 m WNW STATION E E 1.86 km S FENCE-WATER TANK P05 81 m NNE JOHN GAULEY JG 1.99 km W FENCE-OIL STORAGE P06 85 m NE STATION J J 2.04 km SSE O&M - 2ND SW CORNER P19 86 m S WHITEHORSE ROAD WH 2.09 km SSE O&M - 1ST SW CORNER P18 90 m S PLYMOUTH YMCA RC 2.09 km WSW COMPRESSED GAS STOR P08 92 m E STATION K K 2.17 km S FENCE-L SCREENHOUSE P03 100 m NW TAYLOR/THOMAS TT 2.26 km SE FENCE-EXEC.BUILDING P17 107 m W YANKEE VILLAGE YV 2.28 km WSW O&M - 2ND S WALL P23 121 m ENE GOODWIN PROPERTY GN 2.38 km SW FENCE-INTAKE BAY P07 121 m SSE RIGHT OF WAY RW 2.83 km S FENCE-WAREHOUSE P26 134 m ESE TAYLOR/PEARL TP 2.98 km SE FENCE-SHOREFRONT P02 135 m NW FENCE-W BOAT RAMP P09 136 m E Zone 2 TLDs: 3-8 km O&M - 2ND N WALL P22 137 m SE VALLEY ROAD VR 3.26 km SSW FENCE-W SWITCHYARD P16 172 m SW MANOMET ELEM ME 3.29 km SE FENCE-TCF GATE P11 183 m ESE WARREN/CLIFFORD WC 3.31 km W FENCE-TCF/BOAT RAMP P27 185 m ESE RT.3A18ARTLETT RD BB 3.33 km SSE FENCE-ACCESS GATE P12 202 m SE MANOMET POINT MP 3.57 km SE FENCE-E SWITCHYARD P15 220 m S MANOMET SUBSTATION MS 3.60 km SSE FENCE-TCF/INTAKE BAY P10 223 m E BEACHWOOD ROAD BW 3.93 km SE FENCE-MEDICAL BLDG. P13 224 m SSE PINES ESTATE PT 4.44 km SSW FENCE-BUTLER BLDG P14 228 m S EARL ROAD EA 4.60 km SSE FENCE-TCF/PRKNG LOT P28 259 m ESE S PLYMOUTH SUBST SP 4.62 km W ROUTE 3 OVERPASS RP 4.81 km SW Zone 1 TLDs: 0-3 km RUSSELL MILLS RD RM 4.85 km WSW BOAT LAUNCH WEST BLW 0.11 km E HILLDALE ROAD HD 5.18 km W OVERLOOK AREA OA 0.15 km W MANOMET BEACH MB 5.43 km SSE HEALTH CLUB TC 0.15 km WSW BEAVERDAM ROAD BR 5.52 km S BOAT LAUNCH EAST BLE 0.16 km ESE PLYMOUTH CENTER PC 6.69 km W PEDESTRIAN BRIDGE PB 0.21 km N LONG POND/DREW RD LD 6.97 km WSW SHOREFRONT SECURITY P0l 0.22 km NNW HYANNIS ROAD HR 7.33 km SSE MEDICAL BUILDING WS 0.23 km SSE MEMORIAL HALL MH 7.58 km WNW PARKING LOT CT 0.31 km SE SAQUISH NECK SN 7.58 km NNW SHOREFRONT PARKING PA 0.35 km NNW COLLEGE POND CP 7.59 km SW STATION A A 0.37 km WSW STATION F F 0.43 km NW Zone 3 TLDs: 8-1 5 km STATION B B 0.44 km S DEEP WATER POND DW 8.59 km W EAST BREAKWATER EB 0.44 km ESE LONG POND ROAD LP 8.88 km SSW PNPS MET TOWER PMT 0.44 km WNW NORTH PLYMOUTH NP 9.38 km WNW STATION H H 0.47 km SW STANDISH SHORES SS 10.39 km NW STATION I I 0.48 km WNW ELUSVILLE ROAD EL 11.52 km SSE STATION L L 0.50 km ESE UP COLLEGE POND RD UC 11.78 km SW STATION G G 0.53 km W SACRED HEART SH 12.92 km W STATION D D 0.54 km NW KING CAESAR ROAD KC 13.11 km NNW PROPERTY LINE PL 0.54 km NNW BOURNE ROAD BE 13.37 km S STATION C C 0.57 km ESE SHERMAN AIRPORT SA 13.43 km WSW HALL'S BOG HB 0.63 km SE GREENWOOD HOUSE GH 0.65 km ESE Zone 4TLDs: >15 km(2)

W ROCKY HILL ROAD WR 0.83 km WNW CEDARVILLE SUBST CS 15.93 km S E ROCKY HILL ROAD ER 0.89 km SE KINGSTON SUBST KS 16.15 km WNW MICROWAVE TOWER MT 1.03 km SSW LANDING ROAD LR 16.46 km NNW CLEFT ROCK CR 1.27 km SSW CHURCHIWEST CW 16.56 km NW BAYSHOREIGATE RD BD 1.34 km WNW MAIN/MEADOW MM 17.02 km WSW MANOMET ROAD MR 1.38 km S DIV MARINE FISH DMF 20.97 km SSE DIRT ROAD -

DR 1 1.48 km SW EAST WEYMOUTH SUBST EW 39.69 km NW

('DDistance and direction are measured from the centerline of the Reactor Building to the monitoring location.

(2) Indicates control locations.

3/4-29 I

PNPS-ODCM Rev. 9 TABLE 3.5-3

) ROUTINE RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Description No. Code Distance Direction Air Particulate Filters, Charcoal Cartridges Overlook Area. 08 OA 0.1 km W Pedestrian Bridge 07 PB 0.2 km N Medical Building 00 WS 0.2 km SSE East Breakwater 09 EB 0.5 km ESE Property Line 06 PL 0.5 km NNW West Rocky Hill Road 03 WR 0.8 km WNW East Rocky Hill Road 01 ER 0.9 km SE Cleft Rock 10 CR 1.3 km SSW Manomet Substation 17 MS 3.6 km SSE Plymouth Center 15 PC 6.7 km W East Weymouth Control 21 EW 40 km NW Vegetation (1)

Plymouth County Farm 11 CF 5.6 km W Bridgewater Farm Control 27 BF 31 km W Cranberries Manomet Point Bog 13 MR 3.9 km SE Bartlett Road Bog 14 BT 4.3 km SSE Pine Street Bog Control 23 PS 26 km WNW (1)

Additional samples of vegetables/vegetation will be collected each year at or near selected gardens*

identified during the most recent land use census. The locations of these selected gardens are listed in the station procedure describing crop sampling.

3/4-30 I

PNPS-ODCM Rev. 9 TABLE 3.5-3 (CONTINUED)

I ROUTINE RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Description No. Code Distance Direction Surface Water Discharge Canal 11 DIS 0.2 km N Bartlett Pond 17 BP 2.7 km SE Powder Point Control 23 PP 13 km NNW Sediment Discharge Canal Outfall 11 DIS 0.8 km NE Manomet Point 15 MP 3.3 km ESE Plymouth Beach 14 PLB 4.0 km WNW Plymouth Harbor 12 Ply-H 4.1 km W Duxbury Bay Control 13 Dux-Bay 14 km NNW Green Harbor Control 24 GH 16 km NNW Irish Moss Discharge Canal Outfall 11 DIS 0.7 km NNE Manomet Point 15 MP 4.0 km ESE Ellisville 22 EL 12 km SSE Brant Rock Control 34 BR 18 km NNW Shellfish Discharge Canal Outfall 11 DIS 0.7 km NNE Manomet Point 15 MP 4.0 km ESE Plymouth Harbor 12 Ply-H 4.1 km W Duxbury Bay Control 13 Dux-Bay 13 km NNW Green Harbor Control 24 GH 16 km NNW Lobster Discharge Canal Outfall 11 DIS 0.5 km N Duxbury Bay Control 13 Dux-Bay 11 km NNW Fishes Discharge Canal Ouffall 11 DIS 0.5 km N Jones River Control- 30 JR 13 km WNW Cape Cod Bay Control 98 CC-Bay 24 km ESE Buzzard's Bay Control 90 BB 40 km SSW Priest Cove Control 29 PC 48 km SW Vineyard Sound Control 92 MV 64 km SSW (1) Additional samples of vegetables/vegetation will be collected each year at or near selected gardens identified during the most recent land use census. The locations of these selected gardens are listed in the station procedure describing crop sampling.

3/4-31 I

PNPS-ODCM Rev. 9 Figure 3.5-1 Environmental TLD Locations Within the PNPS Protected Area TLD Station Location-Description ! Code Distance/Direction TLDs Within Protected Area O&M/RXB. BREEZEWAY P21 50 m SE EXEC.BUILDING P24 57 m W FENCE-R SCREENHOUSE P04 66 m N O&M - 2ND W WALL P20 67 m SE EXEC.BUILDING LAWN P25 76 m WNW FENCE-WATER TANK P05 81 m NNE FENCE-OIL STORAGE P06 85 m NE O&M - 2ND SW CORNER P19 86 m S O&M - IST SW CORNER P18 90 m S COMPRESSED GAS STOR P08 92 m E FENCE-L SCREENHOUSE P03 100 m NW FENCE-EXEC.BUILDING P17 107 m W O&M - 2ND S WALL P23 121 m ENE FENCE-INTAKE BAY P07 121 m SSE FENCE-WAREHOUSE P26 134 m ESE FENCE-SHOREFRONT P02 135 m NW FENCE-W BOAT RAMP P09 136 m E O&M - 2ND N WALL P22 137 m SE FENCE-W SWITCHYARD P16 172 m SW FENCE-TCF GATE P11 183 m ESE FENCE-TCF/BOAT RAMP P27 185 m ESE FENCE-ACCESS GATE P12 202 m SE FENCE-E SWITCHYARD P15 220 m S FENCE-TCF/INTAKE BAY P10 223 m E FENCE-MEDICAL BLDG. P13 224 m SSE FENCE-BUTLER BLDG P14 228 m S FENCE-TCF/PRKNG LOT P28 259 m ESE Distance and direction are measured from the centerline of the Reactor Building to the monitoring location.

3/4-32 I

PNPS-ODCM Rev. 9 Figure 3.5-1 (continued)

Environmental TLD Locations Within the PNPS Protected Area 100 mete eCd a r~

-Compaction NO--

~~ntae Cha tl e~oe Main)/Stack Execut Illi Ir Facflit HealD \ Reactr ° Bldg

!Building F-- -"Nr~ce 3/4-33 I .

PNPS-ODCM Rev. 9 Figure 3.5-2 TLD and Air Sampling Locations: Within 1 Kilometer TLD Station Location Air Sampling Station Location' I Description ! Code Distance/Direction Description I Code Distance/Direction Zone 1 TLDs: 0-3 km BOAT LAUNCH WEST BLW 0.11 km E OVERLOOK AREA OA 0.15 km W OVERLOOK AREA OA 0.15 km W PEDESTRIAN BRIDGE PB 0.21 km N HEALTH CLUB TC 0.15 km WSW MEDICAL BUILDING WS 0.23 km SSE BOAT LAUNCH EAST BLE 0.16 km ESE EAST BREAKWATER EB 0.44 km ESE PEDESTRIAN BRIDGE PB 0.21 km N PROPERTY LINE PL 0.54 km NNW SHOREFRONT SECURITY P01 0.22 km NNW W ROCKY HILL ROAD WR 0.83 km WNW MEDICAL BUILDING WS 0.23 km SSE E ROCKY HILL ROAD ER 0.89 km SE PARKING LOT CT 0.31 km SE SHOREFRONT PARKING PA 0.35 km NNW STATION A A 0.37 km WSW STATION F F 0.43 km NW STATION B B 0.44 km S EAST BREAKWATER EB 0.44 km ESE PNPS MET TOWER PMT 0.44 km WNW STATION H H 0.47 km SW STATION I I 0.48 km WNW STATION L L 0.50 km ESE STATION G G 0.53 km W STATION D D 0.54 km NW PROPERTY LINE PL 0.54 km NNW STATION C C 0.57 km ESE HALLS BOG HB 0.63 km SE GREENWOOD HOUSE GH 0.65 km ESE W ROCKY HILL ROAD WR 0.83 km WNW E ROCKY HILL ROAD ER 0.89 km SE

Distance and direction are measured from the centerline of the Reactor Building to the monitoring location.

3/4-34 *I

PNPS-ODCM Rev. 9 Figure 3.5-2 (continued)

TLD and Air Sampling Locations: Within 1 Kilometer 3/4-35 I

PNPS-ODCM Rev. 9 Figure 3.5-3 I

TLD and Air Sampling Locations: 1 to 5 Kilometers I TLD Station Location' Air Sampling Station Location' Description Code Distance/Dlrection Descriotion Code DistancelDirection Zone 1 TLDs- 0-3 km MICROWAVE TOWER MT 1.03 km SSW CLEFT ROCK CR 1.27 km SSW CLEFT ROCK CR 1.27 km SSW MANOMET SUBSTATION MS 3.60 km SSE BAYSHORE/GATE RD BD 1.34 km WNW MANOMETROAD MR 1.38 km S DIRT ROAD DR 1.48 km SW EMERSON ROAD EM 1.53 km SSE EMERSON/PRISCILLA EP 1.55 km SE ACCESS ROAD AR 1.59 km SSE BAYSHORE BS 1.76 km W STATION E E 1.86 km S JOHN GAULEY JG 1.99 km W STATIONJ J 2.04 km SSE WHITEHORSE ROAD WH 2.09 km SSE PLYMOUTH YMCA RC 2.09 km WSW STATION K K 2.17 km S TAYLOR/THOMAS TT 2.26 km SE YANKEE VILLAGE YV 2.28 km WSW GOODWIN PROPERTY GN 2.38 km SW RIGHT OF WAY RW 2.83 km S TAYLOR/PEARL TP 2.98 km SE Zone 2 TLDs- 3"8 km VALLEY ROAD VR 3.26 km SSW MANOMET ELEM ME 3.29 km SE WARREN/CLIFFORD WC 3.31 km W RT.3A/BARTLETT RD BB 3.33 km SSE MANOMET POINT MP 3.57 km SE MANOMET SUBSTATION MS 3.60 km SSE BEACHWOOD ROAD BW 3.93 km SE PINES ESTATE PT 4.44 km SSW EARL ROAD EA 4.60 km SSE S PLYMOUTH SUBST SP 4.62 km W ROUTE 3 OVERPASS RP 4.81 km SW RUSSELL MILLS RD RM 4.85 km WSW

Distance and direction are measured from the centerline of the Reactor Building to the monitoring location.

3/4-36 I

PNPS-ODCM Rev. 9 Figure 3.5-3 (continued)

I TLD and Air Sampling Locations: 1 to 5 Kilometers I 3/4-37 I

PNPS-ODCM Rev. 9 Figure 3.5-4 i TLD and Air Sampling Locations: Greater Than 5 Kilometers l TLD Station Location' Air Sampling Station Location' Description i Code Distance/Directon Description I Code Distance/Direction Zone 2 TLDs: 3-8 km HILLDALE ROAD HD 5.18 km W PLYMOUTH CENTER PC 6.69 km W MANOMET BEACH Ms 5.43 km SSE EAST WEYMOUTH SUBST EW 39.69 km NW BEAVERDAM ROAD BR 5.52 km S PLYMOUTH CENTER PC 6.69 km W LONG POND/DREW RD LD 6.97 km WSW HYANNIS ROAD HR 7.33 km SSE MEMORIAL HALL MH 7.58 km WNW SAQUISH NECK SN 7.58 km NNW COLLEGE POND CP 7.59 km SW Zone 3 TLDs: 8-15 km DEEP WATER POND DW 8.59 km W LONG POND ROAD LP 8.88 km SSW NORTH PLYMOUTH NP 9.38 km WNW STANDISH SHORES SS 10.39 km NW ELLISVILLE ROAD EL 11.52 km SSE UP COLLEGE POND RD UC 11.78 km SW SACRED HEART SH 12.92 km W KING CAESAR ROAD KC 13.11 km NNW BOURNE ROAD BE 13.37 km S SHERMAN AIRPORT SA 13.43 km WSW Zone 4 TLDs: >15 km CEDARVILLE SUBST CS 15.93 km S KINGSTON SUBST KS 16.15 km WNW LANDING ROAD LR 16.46 km NNW CHURCH/WEST CW 16.56 km NW MAIN/MEADOW MM 17.02 km WSW DIV MARINE FISH DMF 20.97 km SSE EAST WEYMOUTH SUBST EW 39.69 km NW Distance and direction are measured from the centerline of the Reactor Building to the monitorin' location.

3/4-38 I

PNPS-ODCM Rev. 9 Figure 3.5-4 (continued)

TLD and Air Sampling Locations: Greater Than 5 Kilometers I n

N I,

Ii I_

3/4-39 I

PNPS-ODCM Rev. 9 Figure 3.5-5 Terrestrial and Marine/Aquatic Sampling Locations Description Cod Distance/Directfon I Description Code Distance/Dlrectlonl e ..

FORAGE SURFACE WATER Whipple Farm WH 2.9 km SW Discharge Canal DIS 0.2 km N Plymouth County Farm CF 5.6 km W Bartlett Pond BP 2.7 km SE Whitman Farm Control WF 34 km WNW Powder Point Control PP 13 km NNW VEGETABLESNEGETATION SEDIMENT Plymouth County Farm CF 5.6 kmW Discharge Canal Outfall DIS 0.8 km NE Bridgewater Farm Control BF 31 km W Manomet Point MP 3.3 km ESE Plymouth Beach PLB 4.0 km WNW CRANBERRIES Plymouth Harbor PLY-H 4.1 km W Manomet Point Bog MR 3.9 km SE Duxbury Bay Control DUX-BAY 14 km NNW Bartlett Road Bog BT 4.3 km SSE Green Harbor Control GH 16 km NNW Pine Street Bog Control PS 26 km WNW IRISH MOSS Discharge Canal Outfall DIS 0.7 km NNE Manomet Point MP 4.0 km ESE Ellisville EL 12 km SSE Brant Rock Control BK 18 km NNW SHELLFISH Discharge Canal Outfall DIS 0.7 km NNE Manomet Point MP 4.0 km ESE Plymouth Harbor PLY-H 4.1 km W Duxbury Bay Contras DUX-BAY 13 km NNW Green Harbor Contro' GH 16 km NNW LOBSTER Discharge Canal Outfall DIS 0.5 km N Duxbury Bay Control DUX-BAY 11 km NNW FISHES Discharge Canal Outfall DIS 0.5 km N Plymouth Beach PLB 4.0 km W Jones River Control JR 13 km WNW Cape Cod Bay Control CC-BAY 24 km ESE N River-Hanover Control NR 24 km NNW Cataumet Control CA 32 km SSW Provincetown Control PT 32 km NE Buzzards Bay Control BB 40 km SSW Priest Cove Control PC 48 km SW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Control AO 48 km E Vineyard Sound Control MV

- 64 km SSW Distance and direction are measured from the centerine of the Reactor Building to the sampling/monitoring location.

3/4-40 I

PNPS-ODCM Rev. 9 Figure 3.5-5 (continued)

Terrestrial and Marine/Aquatic Sampling Locations 24 KfONMT1RS

'6WORMMTwHWEST N' 3KW3Lta Nx .3Mrmi WWT41CTH

-2: Z W IA-MTF 19 4K1Dacr:D wm~As d

3/4-41 I

PNPS-ODCM -

Rev. 9 Figure 3.5-6 Environmental Sampling And Measurement Control Locations Description Code DistancelDirection Description Code Distance/Direction' TLD SURFACE WATER Cedarville Substation CS 16 km S Powder Point Control PP 13 km NNW Kingston Substation KS 16 km WNW Landing Road LR 16 km NNW SEDIMENT Church & West Street CW 17 km NW Duxbury Bay Control DUX-BAY 14 km NNW Main & Meadow Street MM 17 km WSW Green Harbor Control GH 16 km NNW Div. Marine Fisheries DMF 21 km SSE East Weymouth EW 40 km NW IRISH MOSS Substation Brant Rock Control BK 18 km NNW AIR SAMPLING I East Weymouth EW 40 km NW SHELLFISH Substation Duxbury Bay Control DUX-BAY 13 km NNW Green Harbor Control GH 16 km NNW I

LOBSTER Duxbury Bay Control DUX-BAY 11 km NNW I

FISHES VEGETABLESNEGETATION Jones River Control JR 13 km WNW Bridgewater Farm Control BF 31 km W Cape Cod Bay Control CC-BAY 24 km ESE N River-Hanover Control NR 24 km NNW CRANBERRIES Cataumet Control CA 32 km SSW Pine Street Bog Control PS 26 km WNW Provincetown Control PT 32 km NE Bzzzards Bay Control BB 40 km SSW Priest Cove Control PC 48 km SW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Control AO 48 km E Vineyard Sound Control MV 64 km SSW

Distance and direction are measured from the centerline of the Reactor Building to the sampling/monitoring location.

3/4-42 I

PNPS-ODCM Rev. 9 Figure 3.5-6 (continued)

Environmental Sampling And Measurement Control Locations SYMBOL KEY SMI=

S-U (M BLUE MUSSEL)

(S SOFT-SMLCLAM) aH EARDRSUM CLAM)

[ LOBS2U MACHA~tUSEBAY Cx FIS=

SU RFACE WA2II O1 CRANBERRY VlONMOORAGE VEGET o TLD 0 AM SAMLER 0 MILES 10 SCALE

.lAYH CAP! DEAT LumBAY NA2MUCI:Er SOUND 3/4-43 I

PNPS-ODCM Rev. 9 TABLE 3.5-4 1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Water or Gases Fish Milk Food Products Analysis pCi/L PCim 3 pCi/kg, wet pCi/L _pCi/kg, wet H-3 30,000 ---

Mn-54 1,000 30,000 _

Fe-59 400 10,000 Co-58 1,000 30,000 _

Co-60 300 10,000 Zn-65 300 _ 20,000 l Zr-95 400 --

Nb-95 400 -- --

1-131 20' ) 0.9 -- 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 - - 300 La-140 200 - 300 (1)Value adjusted for fact that no drinking water pathway exists at Pilgrim Station.

3/4-44 I

- PNPS-ODCM Rev. 9 TABLE 4.5-1 i DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLDWO Airborne Marine and Surface Particulate Aquatic Food Water or Gases Foods Milk Products Sediment Analysis pCiL pCim 3 pClkg,wet pCiL pCi/kg,wet pCVk ,d Gross Beta - 0.01 H-3 3000 (2) _ , -- __ _ __

Mn-54 15 130 Fe-59 30 - 260 -

Co-58 15 _ 130 _ _

Co-60 15 130 Zn-65 30 260 Zr-95 30 --

Nb-95 15 _

1-131 15 (2) 0.07 - 1 60 -

Cs-134 15 0.05 130 15 60 150 Cs-137 18 ' 0.06 150 18 80 180 Ba-140 60 - - 60 -- --

La-140 15 15

( Refer to Appendix B of the ODCM for definition of lower limit of detection (LLD).

(2) Value adjusted for fact that no drinking water pathway exists at Pilgrim Station.

3/4-45 I

PNPS-ODCM Rev. 9 3/4.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.5.2 Land Use Census CONTROLS 3.5.2 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 ft 2) producing broad leaf vegetation. For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify, within a distance of 5 km (3 miles), the locations in each of the 16 meteorological sectors of all milk animals and ail gardens of greater than 50 m2 producing broad leaf vegetation.

APPLICABILITY: At all times.

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 Control 4.3.3, identify the new location(s) in the next Annual Radiological Environmental Monitoring 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 percent greater than at a location from which samples are currently being obtained in accordance with Control 3.5.1, add the new location(s) to the Radiological Environmental Monitoring Program within 30 days. 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. Identify the new location(s) in the next Annual Radiological Environmental Monitoring Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

SURVEILLANCE REQUIREMENTS 4.5.2 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 agriculture authorities.

The results of the land use census shall be included in the Annual Radiological Environmental Monitoring Report.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of the two different direction sectors with the highest predicted D/Qs, in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.5-1 shall be followed, including analysis of control samples.

BASES 3/4.5.2 Land Use Census This section is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring 3/4-46 I

PNPS-ODCM Rev. 9 program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey, or from consulting with local agricultural authorities shall be used.

This census satisfies the requirements of 10CFR50, Appendix 1,Section IV.B.3. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored, since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% of the garden was used for growing broad leaf vegetation (i.e.,

similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/M2 .

3/4-47 I

PNPS-ODCM Rev. 9 5.0 RADIOLOGICAL EFFLUENT CONTROLS CROSS REFERENCE Table 5-1 presents a summary of the limits contained in the PNPS Effluent Controls, Sections 3/4.2.1, 3/4.2.2, 3/4.2.3, 3/4.3.1, 3/4.3.2, 3/4.3.3, and 3/4.4.1. This table also presents cross-references to applicable portions of Methodology Section 9.0.

This table is intended to serve as a summary of the PNPS Effluent Controls and does not, in itself, establish limits. The specific effluent controls presented in Section 3/4 should be consulted for exact wording and specifics.

5-1 I

PNPS-ODCM Rev. 9 TABLE 5-1 PNPS EFFLUENT CONTROLS AND METHODOLOGY CROSS-REFERENCE Effluent Control Methodology Applicable Limit Exposure l Section Section or Objective I Period I Required Action 3/4.2.1 10CFR20, App. B, Table 2 Liquid Effluent 9.1 Column 2, and Instantaneous Restore concentration to Concentration 2x1 OgCVmL for dissolved within limits noble gases 3/4.2.2 1.5 mrem T.B. Calendar Dose- Liquids 9.2 5 mrem Organ Quarter 30-day report if exceeded 3 mrem T.B. Calendar Year 10 mrem Organ 3/4.2.3 0.06 mrem T.B. Projected for Operate Liquid Waste Liquid Radwaste 9.2 0.2 mrem Organ 31 days Treatment System Treatment 3/4.3.1 9.3.1.3 500 mrem/yr T.B. from Gaseous Noble Gases Instantaneous Restore release rates to Effluents ... .............................................. within specifications Dose Rate 9.3.1.4 3000 mrem/yr Skin from Noble Gases 9.3.2 1500 mnrem/yr Organ from particulates with TY2 > 8d.,

1-131,1-133 and tritium 3/4.3.2 5 mrad gamma air Calendar Dosq- .9.3.1.1 and 10 mrad beta air Quarter 30-day report if exceeded Noble Gases 9.3.1.2 .......................................... ......................

10 mrad gamma air Calendar Year 20 mrad beta air 3/4.3.3 7.5 mrem Organ Calendar Dose- 1-131, 9.3.2 Quarter 30-day report if exceeded 1-133 ..........................

Particulates, H-3 15 mrem Organ Calendar"Year 3/4.4.1 9.2, 9.3.1, 25 mrem T.B. Calendar Year 30-day report if controls Total Dose 9.3.2, and 9.4 25 mrem Organ 3/4.2.2, 3/4.3.2, or 3/4.3.3 75 mrem Thyroid are exceeded by a factor of

2. Restore dose to public to within the applicable EPA limit(s) or obtain a variance.

NOTE: T.B. means total body.

5-2 I

PNPS-ODCM Rev. 9

6.0 DESCRIPTION

OF RADWASTE SYSTEMS 6.1 Liquid Radwaste System Liquid wastes from Pilgrim Station originates from a variety of sources which have a considerable disparity in chemical and radio-chemical composition and concentration (see section 9.2 of Reference 3). Normally these wastes are collected and treated separately. The liquid wastes fall into the following categories:

1) High Purity

2) Low Purity

3) Detergent High purity clean wastes are typically characterized by having variable solids content, low conductivity, and variable radioactivity. They come from equipment drain sumps, ultrasonic resin cleaner (URC) operation, and the backwash and resin transfer water used to change out the condensate demineralizers. Reuse of processed high-purity waste is highly desirable.

Low purity chemical wastes have moderate conductivity and solids content. They come from building floor sumps and are generally high-purity wastes which have been contaminated by dirt, oil, etc. When processed, this stream may or may not be reused depending on the water balance in the plant and the quality of the product.

Detergent wastes are low radioactivity concentration wastes that have the potential to contain detergents. This waste is generated from washing and decontamination of equipment, the plant, and personnel. This detergent waste is collected in the miscellaneous waste tank and is not treatable. The waste is passed through strainers, prior to discharge through the radwaste discharge header and into the circulating water discharge canal.

A schematic of the system as determined in Reference 4 is shown in Figure 4.2-1, in Section 3/4.2. In the system, the high purity waste is collected in one of two 15,000-gal clean waste tanks.

Low purity waste is collected -in one of two 15,000 gallon chemical waste tanks. This low purity waste is batched to the clean waste tanks where both types of waste are processed through a mixed bed ion exchange demineralizer. The processed liquid is collected in one of four 18,000 gal treated water holdup tanks. It is reused to the greatest extent possible.

6.2 Treated Gaseous Radwaste System The air ejector and augmented offgas system (see Section 9.4 of Reference 3) includes the subsystems that process and/or dispose of the gases from the main condenser air ejectors, the startup mechanical vacuum pump, and the gland seal condensers. All such gases from the unit are routed to the main stack for dilution and elevated release to the atmosphere. Discharges from the air ejector, the charcoal vault, and the stack are continuously monitored by radiation monitors.

Gases routed to the main stack include air ejector and gland seal offgases, and gases from the standby gas treatment system (SGTS). Dilution air input to the stack is supplied by one of two fans located in the filter building at the base of the main stack. The stack is designed such that prompt mixing of all gas inlet streams occurs in the base to allow location of sample points as near the base as possible.

6-1

PNPS-ODCM Rev. 9 The augmented offgas system uses a high temperature catalytic recombiner to recombine radiolytically dissociated hydrogen and oxygen from the air ejector system. Noncondensable radioactive offgas is continuously removed from the main condenser by the air ejector during plant operation. The air ejector offgas normally contains activation gases, principally N-16, 0-19, and N-13. The N-16 and 0-19 have short half-lives and quickly decay. The 10 min half-life N-13 is present in small amounts which is further reduced by decay. The air ejector offgas also contains Sr-90, Ba-140, and Cs-137. After hydrogen/oxygen recombination and chilling to strip the condensable to reduce the volume, the remaining noncondensables, principally the kryptons, xenons, and air, are delayed in a 30 minute holdup system before reaching the adsorption bed.

Radioactive particulate daughters of the noble gases are retained on the HEPA filters and on the charcoal. The charcoal adsorption bed, operating in a constant temperature vault, selectively adsorbs and delays the xenons and kryptons from the bulk carrier gas, principally air. This delay on the charcoal permits the xenons and kryptons to decay in place. The offgas is discharged to the environs via the main stack. The activity of the gas leaving the offgas treatment system is continuously monitored as described in Section 7.2.2. This system results in a reduction of the offgas activity (Curies) released by factor of approximately 185 relative to a 30 minute holdup system.

The system as determined in Reference 4 for handling gaseous waste is shown in Figure 4.3-1, in Section 3/4.3.

6-2

PNPS-ODCM Rev. 9 7.0 RELEASE POINT AND MONITOR DESCRIPTION 7.1 Radioactive Effluent Release Point Description (Reference 3) 7.1.1 Liquid Radioactive Waste Effluent Release The liquid radwaste discharge header receives discharge from the chemical radwaste monitor tank pumps, the clean radwaste treated water transfer pumps, and the miscellaneous waste drain tank pump (see Figure 4.2-1). The header provides controlled discharge through either a low flow discharge path or a high flow discharge path. The high flow path is normally used with a variable liquid radwaste effluent flow from 1-200 gpm. The common discharge header extends from both the low and high flow-paths and is monitored for radiation prior to discharge (see Section 7.2.1).

The monitor trips the discharge pumps, closes the flow control valves, and provides an alarm on high radiation. The liquid radwaste effluent is finally discharged through an outlet diffuser to the circulating water discharge canal. Liquid effluent releases enter the Cape Cod Bay at the outfall of the discharge canal which is located about 1100 feet north from the center of the reactor building.

In addition, batch releases from sources other than the radwaste tanks are permitted provided at least two independent samples are analyzed in accordance with PNPS Effluent Control Section 4.1.1.a, an independent verification of the release rate calculations is performed, and an independent verification of the discharge valving is performed. Concentrations released to unrestricted areas must be limited to the values specified in 10CFR20.

All batch releases which are not processed through the liquid radwaste treatment system are also discharged through an outlet to the circulating water discharge canal. These untreated liquid effluent releases also enter the Cape Cod Bay at the outfall of the discharge canal.

7.1.2 Main Stack Gas Release The processed gases from the unit are routed to the main stack for dilution and elevated release to the atmosphere (see Figure 4.3-1). The main stack is continuously monitored by a radiation monitor (see Section 7.2.2).

Dilution air input to the stack is provided to reduce the hydrogen in the air ejector offgases to a concentration of less than 4 percent by volume. Dilution air is supplied by one of two fans located in the filter building at the base of the main stack. The stack is designed such that prompt mixing of all gas inlet streams occurs in the base to provide prompt dilution of hydrogen and to allow location of sample points as near to the base as possible.

The main stack is a pipe with a top elevation of about 400 feet mean sea level (MSL). The main stack is supported by the filter building. The filter building is a reinforced concrete structure which houses the dilution fans (16,860 cfm each fan), offgas filters, and heaters. The main stack is located about 700 feet west northwest of the reactor building.

7-1

PNPS-ODCM Rev. 9 7.1.3 Reactor Building Exhaust Vent Release Air from areas containing potential sources of radioactive contamination such as the reactor building, radwaste building basement, and turbine building basement are discharged through the reactor building exhaust vent (see Figure 4.3-1). Normal airflow is routed from lesser to progressively greater areas of radioactive contamination potential prior to final exhaust. The reactor building exhaust vent is continuously monitored by a radiation monitor (see Section 7.2.3).

The operating floor ventilation is normally supplied with 40,000 cfm of filtered and tempered outside air which enters the reactor building through louvers in the east wall. Air is exhausted from the operating floor through ducts located in the roof truss area and the south wall; adjacent to the floor (54,000 cfm per fan). Additional exhaust ducts are located above the water level in the fuel pool, steam dryer/separator storage pool, and the reactor cavity.

Two contaminated area exhaust fans (25,000 cfm per fan), each rated at design capacity, are located in the reactor building. The fans discharge to the main exhaust plenum at the base of the reactor building. An additional smaller exhaust fan (5,000 cfm), located in the reactor building, exhausts only from the control rod drive maintenance shop and discharges to the main exhaust plenum. Constant volume control is maintained by inlet vanes which are automatically positioned.

The reactor building exhaust vent Is a square plenum extending from the top of the west corner of the reactor building. The exhaust plenum releases to the atmosphere at an elevation of 182 feet MSL.

7-2

PNPS-ODCM Rev. 9 7.2 Radioactive Effluent Monitoring System Description (References 3, 5, and 6) 7.2.1 Liquid Radioactive Waste Effluent Monitoring System The liquid radiation waste effluent monitoring system consists of a single channel (see Section 7.12 of Reference 3). This channel includes a scintillation detector, a seven decade logarithmic radiation monitor, and a strip chart recorder. The detector is located in a shielded sampler that is located in a section of the radwaste liquid discharge header to minimize background radiation.

The meter and recorder are located in the main control room. This channel is connected to the 24 volt DC power bus.

The channel has an upscale trip to Indicate high radiation level and a downscale trip to indicate instrument trouble. The upscale trip alarms in the main control room (see Section 8.1 for liquid effluent monitor setpoints), trips the monitor tank pumps, and terminates the discharge. The downscale trip alarms in the main control room. The waste discharge valve is the isolation control device for the liquid radwaste effluent stream and it is automatically closed when the alarm is tripped. There are two waste discharge valves, one is situated on a two inch line and the other is situated on a one inch line. Both valves are located prior to the radiation waste effluent monitor and prior to the discharge canal. The valves are air operated valves. The waste discharge valves are: A07216A and SV7216A, which are on the 2 inch line; and A07216B and SV7216B, on the 1 inch line. The power source is the 24 volt DC power bus.

Alarm trip circuits can be tested using test signals. The channel is calibrated by laboratory analysis of a grab sample from the liquid radwaste system.

7.2.2 Main Stack Gas Monitoring System The main stack gas monitoring system consists of two individual channels (see Section 7.12 of Reference 3) to monitor the release of noble gases. Each channel consists of a gamma-sensitive scintillation detector and a seven decade logarithmic count rate monitor that includes a power supply and a meter. Both channels are recorded on a two-pen recorder located in the main control room. Both channels are connected to the 24 volt DC power bus and to the AC radiation protection system via a transfer switch to the emergency diesel generators.

Each monitor has two upscale alarms and one downscale alarm. Exceeding a setpoint initiates an alarm in the main control room, but no control action is provided. The upscale alarms indicate high radiation (see Section 8-2 for gaseous effluent monitor setpoint), and the downscale alarm indicates instrument trouble.

To monitor noble gases in the gaseous effluent from the main stack, a sample is drawn through an isokinetic probe which is located in the stream to assure representative sampling. The sample passes through a particulate filter and charcoal cartridge. The filtered gas then flows to two shielded chambers where the radiation level of the noble gases is measured by two scintillation detectors, one located in each shielded chamber.

The system also provides for sampling of particulates and iodines by the use of a filter and charcoal cartridge located upstream of the gas being monitored in the shielded chambers. The filter and cartridge are routinely analyzed In a chemistry laboratory in accordance with PNPS Effluent Controls.

Each individual channel includes a built-in check source and a purge line to purge the stack gas from the sampling chamber. Both the purge valve and the check source are operated from the main control room. Each channel is calibrated by laboratory analysis of a grab sample in the off gas line. Alarm trip circuits can be tested using a test source.

7-3

PNPS-ODCM Rev. 9 7.2.3 Reactor Building Exhaust Vent Monitoring System The reactor building exhaust vent monitoring system consists of two channels (see Section 7.12 of Reference 3). Each channel consists of a gamma-sensitive detector and a seven decade logarithmic count rate monitor that includes a power supply and a meter. Both channels are recorded on a two-pen recorder located in the main control room. Both channels are connected to the 24 volt DC power bus and the AC radiation protection system via a transfer switch to the emergency diesel generators.

Each monitor has two upscale alarms and one downscale alarm. Exceeding a setpoint initiates an alarm in the main control room, but no control action is provided. The upscale alarms indicate high radiation and the downscale alarm indicates instrument trouble.

To monitor noble gases from the gaseous effluent in the reactor building exhaust vent, a sample is drawn through an isokinetic probe which is located to assure representative sampling. The sample passes through a particulate filter and iodine cartridge. The filtered gas then flows to two shielded chambers where the radiation level of the gas is measured by two scintillation detectors, one located in each shielded chamber.

The system also provides for sampling of particulates and iodines by the use of a filter and charcoal cartridge located upstream of the gas being monitored in the shielded chamber. The filter and cartridge are routinely analyzed In a chemistry laboratory in accordance with PNPS Effluent Controls.

Each individual channel includes a built-in check source and a purge line to purge the gas from the sampling chamber. Both .the purge valve and the check source are operable from the main control room. Each channel is calibrated by laboratory analysis of a grab sample from the reactor building ventilation system. Alarm trip circuits are tested using test signals.

7-4

PNPS-ODCM Rev. 9 TABLE 7-1 RADIOACTIVE EFFLUENT MONITOR DATA Stack Gas Reactor Building Vent Item Channel 1i Channel 2 Channel A J Channel B Liquid Effluent Manufacturer GE j GE GE GE GE Model Number 194X900G9 l_194X900G11- 194X900G11 194X900G11 194X900G9 Serial Number 6,343,901 PPA 6,550,PA6,343 6,550,733 6,550,789 6,342,995 PPA 6,342,790 PRM 907 6,342,788 PRM Scale cps cps cps cps cps Range 1E-1 to 1E+6 1E-1 to 1E+6 I E-1 to 1E+6 1E-1 to 1E+6 1E-1 to 1E+6 Power 24 VDC l 24 VDC 24 VDC f 24 VDC 24 VDC Location Panel C910 Panel C910 Panel C910 Panel C910 Panel C910 Installation Date 8/20/71 8120171 8/20/71 8/20/71 9/13/71 Surveillance Test

a. Daily Channel Check Channel Check Channel Check

b. Monthly Source Check Source Check

c. Quarterly Channel Functional Test Channel Functional Test Channel Functional Test Calibration

a. Quarterly Check Source Check Source Check Source

b. 24-month Known radiation source Known radiation source Known radiation I source Alarm Set Points

...... See Section 8.2 See Section 8.2 See Section 8.1

a. HI-i Alarm

b. Hi-Hi Alarm _ _ _ _ _ _ _ _ _ .__

Isolation Control None None Waste Device II __Discharge Valve 7-5

PNPS-ODCM Rev. 9 7.3 Measurement Method During Release (References 3 and 7) 7.3.1 Liquid Effluent Prior to the release of any liquid waste, a sample of the release is collected and the specific activity is determined by isotopic analysis. The waste discharge tank is recirculated at least 60 minutes prior to the collection of a sample. The release of any liquid waste is controlled on a mixed effluent concentration limit (ECL) basis, where the sum of the ratios between the isotopic concentration and the ECL is less than one. The specified waste discharge flow rate must be at least 10% less than the maximum waste discharge flow rate which shall not exceed 200 gpm. The discharge of the liquid effluent is made from the liquid radwaste discharge header.

7.3.2 Gaseous Effluent The gaseous effluent radiation level is continuously monitored as it is being vented to the atmosphere. Periodic samples are collected from the reactor building vent and the main stack.

The particulate filters, charcoal cartridges, gas samples, and condensed water samples are analyzed for isotopic identification and quantification, in accordance with the PNPS Effluent Controls.

7.3.3 Limitations

a. Gaseous Effluent

1) PNPS Effluent Controls for gaseous release values.

b. Liquid Effluent

1) PNPS Effluent Controls for liquid release values.

2) Ifone pump is used to discharge the liquid waste and fails, the release is immediately discontinued.

3) Ifthe discharge flow rate recorder fails, the release is immediately discontinued.

7-6

PNPS-ODCM Rev. 9 8.0 MONITOR SET POINTS Radiation monitors are typically used to measure levels of radioactivity in given process and effluent streams. In the case of effluent monitors, various setpoints can be established to cause an annunciator alarm to sound to warn an operator to take a specific action, or in other cases to cause an automated system to isolate the system to curtail the release of radioactivity from that system.

In most cases, two levels of alarm are established. Typically, the highest level, or 'Hi-Hi' alarm, is established at or below the level that would correspond to exceeding one of the effluent controls in Section 3/4. In the cases of the liquid radwaste effluent monitor, steam jet air ejector monitor, and post-treatment radiation monitor, such a high level alarm would cause the system to automatically isolate to prevent additional release.

A second level of alert, or 'Hi' alarm, is often set at a lower level to provide early warning of unanticipated elevated levels of radioactivity in the system. This level of alarm is meant to alert the operators of the level of radioactivity, so that evaluations can be performed or additional samples collected to characterize the effluent or process stream. This 'Hi' alarm is typically set at some level that is a fraction of the limit, and is often administratively controlled through procedure guidance.

8.1 Liquid Effluent Monitor The setpoint for the liquid effluent monitor (see Section 7.2.1) is established as follows:

1) Prior to a liquid batch release, the waste discharge tank is recirculated for at least 60 minutes and a sample is taken.

2) The liquid effluent sample is analyzed (see Section 7.3) to determine the concentrations of each detectable isotope in [tCVmL. (See Appendix B for the definitions of lower limit of detection.)

3) The efficiency (in counts/sec per gCVmL) of the liquid discharge monitor is calculated based on prior release experience.

4) The setpoint for the liquid effluent monitor is calculated as follows:

a) Monitor setqoint based on activity concentration c = C(F+f) f where:

c = the setpoint of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is proportional to the volumetric flow of the effluent line and inversely proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value, which if exceeded, would result in concentrations exceeding the limits of 10CFR20 in the unrestricted area,

([tCVmL);

C = the effluent concentration limit implementingl OCFR20 for the site (pCVmL);

F = the dilution water flow setpoint as measured at the release point, (gpm); l 8-1

PNPS-ODCM Rev. 9 f = the effluent flow setpoint as measured at the radiation monitor location, (gpm);

where:

C= I i ECL1 Cwi= concentration of nuclide i in the liquid waste discharge volume prior to any dilution as determined by current isotopic analysis for gamma emitting nuclides and most recent results from pure beta emitters as specified in Table 4.2-1 of PNPS Effluent Controls, (pCVmL);

ECL1 = Effluent Concentration Limit of each nuclide i from 10CFR20 Appendix B, Table 2, Column 2, (jiCimL);

b) Monitor setDoint based on monitor count rate Cs= (C*X)+z where:

ps = the setpoint of the radioactivity monitor measuring the radionuclide concentration in the effluent line prior to dilution, (counts/sec);

c = the liquid effluent monitor setpoint based on activity concentration as calculated in step 4.a above, (pCVmL);

x = the liquid effluent monitor efficiency/conversion factor for activity concentration to count rate, (counts-m!LJCi-sec);

z = the liquid effluent monitor background count rate, (counts/sec).

The setpoint will ensure that the concentration of liquid effluents discharged does not increase above the value for which the maximum permissible discharge flow rate was established (see Section 9.1 of this manual).

8.2 Gaseous Effluent Monitors The only components of the station's gaseous effluent and discharge which are continuously monitored are the noble gases. The method of determining the main stack gas monitor (see Section 7.2.2) and reactor building exhaust vent monitor (see Section 7.2.3) Hi and Hi-Hi alarms is as follows:

1) At the time a gas grab sample is taken at the discharge point, the gross monitor reading is recorded (in counts/sec).

2) The results of the isotopic analyses on this sample in terms of p.CVcc of each isotope detected are used along with estimates of gaseous discharge flow rate (SCFM) to determine the current release rate of each detected isotope in p.CVsec.

8-2

PNPS-ODCM Rev. 9

3) These calculated release rates (gtCVsec) are used along with the equations given in Sections 9.3.1.3 and 9.3.1.4 of this manual to calculate the maximum offsite dose rate due to noble gases.

4) The ratio of this calculated dose rate to the PNPS Effluent Control instantaneous dose rate limit (500 mrem/yr for the total body and 3000 mrem/yr for the skin, or some fraction thereof) is used to scale the observed monitor reading at the time at which the grab sample was obtained as follows:

(Cs- Bg) DRLimit SG - + *9 DRcalc where:

SG = gaseous monitor setpoint corresponding to 500 mrem/yr to the total body or 3000 mrem/yr to the skin, whichever is more limiting (in counts/sec)

Cs = observed monitor reading at the time of the grab sample (in counts/sec) 8g = measured background count rate at the sampler with no sample present (in counts/sec)

DRLImIt = the applicable dose rate limit, 500 mrem/yr for the total body or 3000 mrem/yr for the skin or some fraction thereof DRCalc = the calculated dose rate for the maximum individual from the methods of Section 9.3.1.3 and 9.3.1.4 of this manual using the release rates determined from the grab sample, mrem/yr The resulting setpoint will be valid until the next grab sample is taken from the release point.

This method will be used to establish the Hi-Hi alarm at 500 mrem/yr to the total body or 3000 mrem/yr to the skin, whichever is more restrictive.

Since two release points exist for noble gas effluents, the setpoints may be varied to allow greater release rates from one point than the other, provided the total limit is below 500 mrem/yr for the total body or 3000 mrem/yr for the skin, whichever is more restrictive.

The Hi-Hi alarm setpoint for the gaseous monitors will be based on the equation in this section.

The Hi alarm setpoint may be set at or below, but in no case above, the Hi-Hi alarm setpoint.

8.3 Steam Jet Air Eiector Monitor The steam jet air ejector (SJAE) monitor is used to measure the release rate of noble gases in main condenser offgas prior to its further treatment and release from the main stack. This monitor's primary function is to provide alarm and isolation of this process flow stream in the event of excessively high release rates of noble gases from the condenser and recombiner. The maximum allowable release rate of noble gases in the SJAE offgas is 500,000 pCifsec, as established in Technical Specification 3.8.1. For conservatism, the Hi-Hi alarm is set at 75% of this limit, or 375,000 giCVsec. In association with changing to a 24-month refueling cycle, the frequency of equipment calibrations has also been extended from the typical 18-month cycle. In order to accommodate for any drift which may occur in SJAE monitor response during the 8-3

PNPS-ODCM Rev. 9 additional 6-months in the calibration interval, the Hi-Hi alarm has been further derated to a release rate of 300,000 jiCVsec. In response to guidance from the Institute of Nuclear Power Operations outlined in SOER 90-02, Pilgrim Station has chosen to administratively control the SJAE noble gas rate to a lower value to determine the desirability of a plant derate.

Since this gaseous stream undergoes further processing downstream of the SJAE monitor and is ultimately released via the main stack and monitored by the main stack gaseous effluent monitor, the SJAE monitor does not strictly qualify as a primary effluent monitor. Therefore, it is not normally recognized as such. However, the methodology for establishment of alarm setpoints is included in this section for completeness. These setpoints are established as follows:

1) A grab sample of the SJAE offgas is collected. The SJAE monitor reading (mR/hr) is recorded in conjunction with this sample.

2) Isotopic analyses are performed on the off gas sample and the total noble gas concentration (glCVcc) is coupled with the flow rate (CFM) to calculate the SJAE release rate (.tClsec).

3) The release rate fliCVsec) is divided by the monitor reading (mR/hr) to determine the SJAE monitor conversion factor (g.CVsec/mR/hr).

4) The Hi-Hi alarm setpoint (mRlhr) is determined by dividing the administratively-determined maximum tolerable release rate by the SJAE monitor conversion factor (giC~sec/mR/hr).

5) The Hi alarm setpoint is set at a maximum of 50% of the corresponding Hi-Hi alarm setpoint, or at other levels procedurally controlled to initiate evaluation of the system (e.g., sampling to determine noble gas mix and/or evaluate conversion factors).

Grab samples of the SJAE offgas are collected: 1) at least once every 31 days; or, 2) if the gross radioactivity release rate increases by 50% or more over the nominal steady state fission gas release after factoring out increases due to changes in thermal power level and hydrogen injection.

Upon collection of these grab samples, new values are established for the total noble gas concentration, SJAE monitor conversion factor, and alarm setpoints. Typically, existing setpoints will be used unless the newly calculated setpoints yield lower values. In this case, the setpoints will be lowered to the newer, more conservative values.

8.4 Post-Treatment Radiation Monitor The post-treatment radiation monitoring system takes a continuous sample from the outlet of the augmented offgas treatment system. This system has two instrumentation channels, each of which is equipped with a gamma-sensitive scintillation detector, a pulse preamplifier, a logarithmic radiation monitor, and an electroluminescent display. Both channels are recorded on a two-pen recorder located in the main control room. The two scintillation detectors are mounted in two shielded sample chambers. The sample is drawn from the offgas line through the sample line by the sample pump.

Each monitor has two upscale trips and a downscale trip. Any one upscale high radiation trip of the augmented offgas monitor closes the carbon bed filter bypass valve, if open, and opens the offgas line to the carbon bed, if closed, in the augmented offgas system. This upscale high radiation trip also provides an annunciator alarm in the control room.

Any combination of two high-high upscale radiation trips, one high-high upscale trip and one downscale trip, or two downscale trips of each monitor will actuate a time delay switch through a 8-4

PNPS-ODCM Rev. 9 keylock selector switch. This is the same 0-15 minute time delay switch located in the SJAE radiation monitor which closes the drain valve and the outlet valve in the offgas discharge line.

Since the gaseous stream from the augmented offgas treatment system undergoes further processing (delay decay) downstream of the post-treatment radiation monitor and is ultimately released via the main stack and monitored by the main stack gaseous effluent monitor, the post-treatment radiation monitor does not strictly qualify as a primary effluent monitor. Therefore, it is not normally recognized as such. The methodology for establishing alarm setpoints for the post-treatment radiation monitor is similar to that described in Section 8.3 for the SJAE monitors.

8-5

PNPS-ODCM Rev. 9 9.0 CALCULATIONAL METHODS This section presents the calculational specifics required to demonstrate compliance with each of the Effluent Controls identified in Section 3/4 of this document.

The equations in this section are based on the equations and calculational methods described in Reference 8, unless otherwise specified. These equations have, in some cases, been presented in a slightly different form in an effort to simplify their use. The subscripts used are 'a" for age group, "j" for organ, jiB for radionuclide, 'p' for pathway and "lI for location. Capital letters have been used on the dose/dose rate, use factor, concentration, and dose conversion factor abbreviations to designate pathways. "A" is for aquatic foods, "Su for shoreline deposits, "W" for swimming, "Y" for yachting/boating, WN for noble gas, EGO for ground plane deposition, "BT for breathing/inhalation, "Lo for leafy vegetation, OR" for root crops/non-leafy vegetation, "M" for milk, and 'C' for meat.

The descriptions of constants, variables, and parameters in this section are also based on those described in Reference 8, unless otherwise specified. The descriptions have, in some cases, been modified to describe the constant, variable, and parameter specific application in the corresponding equation. In addition, some of the constant and variable values have been revised to include more site specific values, to include more technically correct information, or to provide uniformity (e.g., XI values always presented in hr-1). Values for parameters which only have a single value will appear along with the definition. For those parameters which can take on different values for different conditions, the appropriate value will appear in the referenced tables. All numerical constants have been derived from the indicated base conversion factors and are represented in scientific notation to the third significant digit.

9.1 Concentrations of Liquid Effluents The following equation shall be used to determine the discharge flow rate such that concentrations of radioactive effluents released to unrestricted areas do not exceed the concentration limits specified in 10CFR20 Appendix B, Table 2, Column 2:

cw DFR =

, ECLI where:

DFR = Maximum discharge release rate of liquid effluent, (gal/min).

CW = Flow rate of dilution water, (sum of waste discharge pumps, circulating water pumps, and/or salt service water pumps), (gal/min).

Cw1 = Concentration of nuclide i in the liquid waste discharge volume prior to any dilution as determined by current isotopic analysis for gamma emitting nuclides and most recent results from pure beta and alpha emitters, (giCVmL).

ECLi = Effluent Concentration Limit of each nuclide ifrom 10CFR20 Appendix B, Table 2, Column 2, (piCVmL).

9-1

PNPS-ODCM Rev. 9 9.2 Liquid Effluents Dose Assessment Methodoloav The following equations shall be used to estimate the annual dose rates due to a release of radioactive liquid effluents. All input parameters (i.e., activity and volume) must be normalized to a 1 year release period. Modification of the final results is necessary for comparison to dose rate limits for periods different than one year. For comparison to monthly limits and quarterly limits, results would be scaled by 1/12 and 1/4, respectively. To determine the dose or dose commitment for a desired period, multiply the annual dose rate by the fraction of the year for the dose period desired. For purposes of projecting resulting dose estimates for the subsequent month, the release rates and concentrations are assumed to be equal to the previous month's release.

Pathways assuming internal deposition of radionuclides (i.e., ingestion) involve the use of a 50-year committed dose conversion factor. This entire prospective dose will be assigned to the individual for the year of intake (Reference 8). In the original version of the ODCM, values from Regulatory Guide 1.109 (Reference 8) were used for calculating doses. Upon incorporation of the Generic Letter 89-01 change (Revision 8), and conversion to an electronic document, dose conversion factors were obtained from updated tables used by the NRC in the computer program GASPAR-Il (Reference 9). For pathways involving external radiation to the total body (i.e.,

shoreline activity, swimming, boating), the dose to all other organs is assumed equal to that for the total body (Reference 8, Appendix E).

Summation of the dose rates from the equations below should be performed for all significant pathways.

9.2.1 Liquid Pathways Annual Dose Rates 9.2.1.1 Aquatic Food Ingestion (Fish. Shellfish)

DAajp UAap [CA 1p DFIay]

where:

Cp= CW%, Bp e-AIth

_ 1.00E12 Q. M, eAltI AIb V Above equations derived from Reference 8, equations 2 and A-3.

9-2

PNPS-ODCM Rev. 9 9.2.1.2 Shoreline Deposits (Discharge Canal and Recreational Area)

DSaj- USal WI E [CS, DFGIj]

where:

(1 e-Aetb)

CS 1=2.89 CWj, A CW#j = same as indicated in Equation 9.2.1.1 Above equation derived from Reference 8, equations A-4 through A-7.

9.2.1.3 Swimming (White Horse Beach)

DWai= UWal Z[CWi DFWj]

where:

OWj = same as indicated in Equation 9.2.1.1 Above equations derived from Reference 10, equation 41 on page 151.

9.2.1.4 Yachting/Boating (Cape Cod Bay)

DYa81 = 0.5 UYal E[CW 1, DFW11]

where:

CW1, = same as indicated in Equation 9.2.1.1 Above equations derived from Reference 10, equation 41 on page 151.

9-3

PNPS-ODCM Rev. 9

9.2.2 Definitions

BIp = equilibrium bloaccumulation factor for radionuclide i, in aquatic foods pathway p, expressed as the concentration in biota (pCVkg), divided by the concentration in water (pC/liter) from Table A-1, (liters/kg);

Calp = concentration of radionuclide i in pathway p of aquatic foods, (pCi/kg);

CSsj = effective surface concentration of radionuclide i in sediments at location 1,(pCiM 2);

CWil = concentration of radionuclide i in seawater at location 1,(pCi/liter);

DAajp = total annual dose rate from ingestion of aquatic foods to organ j, of individuals of age group a, from pathway p, (mremlyr);

DFG11 = open field ground plane dose conversion factor for organ j, from radionuclide i, from Table A-10, (mrem-m 2 /pCi-hr);

DFlaiJ = ingestion 50-year committed dose conversion factor for organ j, of individuals in age group a, from radionuclide i, from Table A-15 through A-18 (mrem/pCi ingested);

DFWj1 = submersion dose conversion factor in water, for organ j, of individuals in age group a, from radionuclide i, from Table A-2, (mrem-liter/pCi-hr);

DSa1 = total annual dose rate from exposure received during shoreline activities, to organ j, of individuals of age group a, at location 1,(mrem/yr);

DWaf = total annual dose rate from exposure received during swimming, to organ j, of individuals of age group a, at location 1,(mrem/yr);

DYap = total annual dose rate from exposure received during yachting/boating, to organ j, of individuals in age group a, at location 1,(mrem/yr);

Ml = mixing ratio (reciprocal of dilution factor) at location I of exposure or harvest of aquatic food, from Table A-3, (dimensionless);

QJ = annual release rate of radionuclide i in liquid effluents, (CVyr);

tb = period of time for which sediment is exposed to radionuclides in seawater, including buildup, (hr, assumed to be 1.31 E5 hr = 15y);

th = time between exposure of aquatic foods to radionuclides in sea water and their consumption by an individual, from Table A-3, (hr);

t4 = transit time required for radionuclides to reach location 1,(hr, assumed to be 0.0 hr from the liquid waste tank to the discharge canal);

UAap = use factor of aquatic foods from pathway p, by individuals in age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (kg/yr);

9-4

PNPS-ODCM Rev. 9 USaj = use factor (amount of time) an individual in age group a, engages in shoreline activities at location 1,from Table A-9 for maximum individual, Table A-8 for average individual, (hrlyr);

UWal = use factor (amount of time) an individual in age group a, engages in swimming at location 1,from Table A-9 for maximum individual, Table A-8 for average individual, (hr/yr);

UYaj = use factor (amount of time) an individual in age group a, engages in yachting/boating at location 1,from Table A-9 for maximum individual, Table A-8 for average individual, (hrlyr);

V = total annual discharge rate of liquids, represented by the sum of liquid effluents, circulating water pumps, and/or salt service water pumps, (liters/yr);

WI = shoreline width factor for location 1,from Table A-3, (dimensionless);

Al = radioactive decay constant of radionuclide i, (hr');

0.50 = scaling factor for yachting/boating assuming that doses received while on the surface of the water are 1/2 of doses received while immersed in water from Reference 10, (dimensionless);

2.89 = factor to convert for transfer of nuclides from water to sediment, equal to 100 liters/m2-day from Reference 11 multiplied by 1 day/24 hr and by natural log of 2 (to convert reciprocal Xi to half-life), as calculated in Reference 8, equation A-5, (liter/m 2 -hr);

1.OOE12 = factor to convert from Ci to pCi, (pCVCi);

9-5

PNPS-ODCM Rev. 9 9.3 Gaseous Effluents Dose Assessment Methodoloav The following equations shall be used to estimate the annual dose rates due to release of radioactive gaseous effluents. All input parameters (i.e., activity and volume) must be normalized to a 1 year release period. Modification of final results is necessary for comparison to dose rate limits for periods different than one year. For comparison to monthly limits and quarterly limits, results would be scaled by 1/12 and 1/4, respectively. To determine the dose or dose commitment for a desired period multiply the annual dose rate by the fraction of the year for the dose period desired.

For conservatism, the shielding factor (S) used for calculating total body dose and skin dose from noble gases is normally assumed to be unity (1.0), as specified in NUREG-0133 (Reference 12).

Also, although iodine deposition on vegetation is assumed to be 50% (Reference 8), 100% of airborne iodine is assumed to be deposited on the ground surface when calculating direct radiation (ground plane) exposure.

Pathways assuming internal deposition of radionuclides (i.e., inhalation, ingestion) involve the use of a 50-year committed dose conversion factor. This entire prospective dose will be assigned to the individual for the year of intake (Reference 8). In the original version of the ODCM, values from Regulatory Guide 1.109 (Reference 8) were used for calculating doses. Upon incorporation of the Generic Letter 89-01 change (Revision 8), and conversion to an electronic document, dose conversion factors were obtained from updated tables used by the NRC in the computer program GASPAR-I1 (Reference 9). For pathways involving external radiation to the total body (i.e., noble gas total body dose, ground plane deposition), the dose to all other organs is assumed equal to that for the total body (Reference 8, Appendix E).

Summation of the doses rates from the equations below should be performed for all significant pathways and all release points from which significant radioactive effluent releases have occurred (i.e., Main Stack and Reactor Building Exhaust Vent).

9.3.1 Gaseous Pathways Annual Dose Rates from Noble Gases 9.3.1.1 Gamma Air Dose DNrj [Ci DFNy]

where:

Cir = 3.17E4 [/]Qj Above equations derived from Reference 8, equations 6, 7, B-1, B-2, B-4, and B-5, as well as References 13 and 14.

9-6

PNPS-ODCM Rev. 9 9.3.1.2 Beta Air Dose DNfi = 4[C, DFNp]

where:

C6= 3.17E4 [IyQ]s Q1 Above equations derived from Reference 8, equations 7, B-4, and B-5.

9.3.1.3 Total Body Dose DNTB = SZ[Cir DFNITB]

where:

Cir = Same as indicated in Equation 9.3.1.1.

Above equations derived from Reference 8, equations 8, 10, B-1, B-2, B-4, B-5, B-6, and B-8, as well as References 13 and 14.

9.3.1.4 Skin Dose DN =(1.11SDNy)+j[C,1 DFNjs]

I where:

DNMCi, = same as indicated in Equations 9.3.1.1 and 9.3.1.2, respectively.

Above equations derived from Reference 8, equations 6, 7, 9, 11, B-1, B-2, B-4, B-7, and B-9, as well as References 13 and 14.

9-7

PNPS-ODCM Rev. 9 9.3.2 Gaseous Pathways Annual Dose Rates from iodine 131 and 133, Particulates with a Half-life Greater than 8 Days, and Tritium.

PNPS Effluent Controls do not consider doses from C-14 and 1-135 for compliance. However, equations for these radionuclides are included in this section for completeness.

9.3.2.1 Ground Plane Deposition DGj = SE [CGI DFGjj]

where:

CGj = 1.00E12 [D/,] Q ( eitb)

Above equations derived from Reference 8 equations 12, C-1, and C-2.

9.3.2.2 Breathing/inhalation DBaj = UBa GCBi DFBai]

where:

CBj = 317E4 [$/0]C Q1 for H-3, C-14 CB, = 3.17 E4 [ 7/Jd Qj for particulates with T/2 >8d, 1-131, 1-133, and 1-135 Above equations derived from Reference 8, equations 13, C-3, and C-4.

9-8

PNPS-ODCM Rev. 9 9.3.2.3 Leafy Vegetation Ingestion DLaj =ULa 4 cCL' DFIaJI where:

CLj= leafy vegetation concentration as calculated below.

Above equation derived from Reference 8, equations 14 and C-13.

where:

1.1 9E7 Q1 [Y]

CH,,CL,,CP,,CRi = H C for H-3 CHi,CLi,CP1 ,CRI = 2.1 8E7 p Q1 [Ye] for 0-14 t BA, ( i- e -AItb l 1 =5.71E7 Qj [%]*[

________-_-t CH,CLjCPj, CR * + ( e

e-Alth for 1-131, 1-133, and 1-135 (i

CHjCLj,CPj, CR1 = 1.14E8 Qj [%70 * [P

( ____

+

B- - e-AItb)]

Ath *e 2 for particulates with Ty2 >8 days, Above equations derived from Reference 8, equations C-5 through C-9.

9-9.

PNPS-ODCM Rev. 9 9.3.2.4 Root Crop Non-Leafy Vegetation Ingestion DRaj = URa fr 1CRj DFIaI]

where:

CR1 = root crop concentration as calculated in Equation 9.3.2.3.

Above equations derived from Reference 8, equations 14 and C-13.

9.3.2.5 Milk Ingestion DMaj = UMa Z[CM. DFIaij]

where:

CM = Fim CF1 Qf e-Aitf CF,= fp fs CP.Jr (CHj (1 - fp)) Jr CHI fp (1 - fs)

CPiCHi = concentration in pasture grass and harvested/stored feed as calculated in Equation 9.3.2.3.

Above equations derived from Reference 8, equations 14, C-10, C-11, and C-13 9.3.2.6 Meat Ingestion DCaj = UCa [CC, DFIay]

where:

CC,= Ff CF Of eIAts CFi= concentration in forage as calculated in Equation 9.3.2.5 Above equations derived from Reference 8, equations 14, C-12, and C-13

9-10

PNPS-ODCM Rev. 9 9.3.3 Definitions Bjy = concentration factor for uptake of radionuclide i, from soil in the edible portions of crops, in pCi/kg (wet weight) per pCi/kg dry soil, from Table A-5, (kg/kg);

CtB = effective semi-infinite cloud concentration of noble gas i, for the purpose of calculating beta air dose, (pCi/r 3);

Cir = effective finite cloud concentration of noble gas i for the purpose of calculating gamma air dose, (pCVm 3);

CB0 = ground-level airborne concentration of radionuclide i, (pC0t 3);

CCi = concentration of radionuclide i in meat, (pC/kg);

CF, = concentration of radionuclide i on forage, (pCi/kg);

CG1 = ground plane concentration of radionuclide i, (pCi-hr/m 2 -yr);

CHj = concentration of radionuclide i on harvested/stored feed, (pCi/kg);

CMI = concentration of radionuclide i in milk, (pCi/liter);

CLI = concentration of radionuclide i in leafy vegetables, (pCi/kg);

CP1 = concentration of radionuclide i on pasture grass, (pCikg);

CRI = concentration of radionuclide i in root crops/non-leafy vegetables, (pCi/kg);

DBaj = total annual dose rate from breathing/ inhalation to organ j, of an individual in age group a, (mrem/yr);

DCaJ = total annual dose rate from ingestion of meat to organ j; of an individual in age group a, (mrem/yr);

DFBaij = inhalation 50-year committed dose conversion factor for organ j, of individuals in age group a, from radionuclide i, from Tables A-1I through A-14, (mrem/pCi);

DFG 11 = open field ground plane dose conversion factor for organ j, from radionuclide i, from Table A-10, (mrem -m2 /pCi-hr);

DFlaij = ingestion 50-year committed dose conversion factor for organ j, for individuals in age group a, from radionuclide i, from Tables A-15 through A-18, (mrem/pCi);

DFNiS = beta skin dose conversion factor for a semi-infinite cloud of noble gas i, which includes the attenuation by the outer "dead" layer of skin, from Table A-4, (mrem-m 3 /pCi-yr);

DFNITB = total body dose conversion factor for a semi-infinite cloud of noble gas i, which includes the attenuation of 5 g/cm2 of tissue, from Table A-4, (mrem-m 3 /pCi-yr);

DFNjp = beta air dose conversion factor from a semi-infinite cloud of noble gas i, from Table A-4, (mrad-m 3 /pCi-yr);

9-11

PNPS-ODCM Rev. 9 DFN 2,v= gamma air dose conversion factor from a semi-infinite cloud of noble gas i, from Table A-4, (mrad-m 3 /pCi-yr);

DGj = total annual dose rate to organ j from direct exposure to the contaminated ground plane from all radionuclides, (mrem/yr);

DLaJ = total annual dose rate from ingestion of leafy vegetables to organ j, of an individual in age group a, (mrem/yr);

DMaj = total annual dose rate from ingestion of milk to organ j, of an individual in age group a, (mrem/yr);

DNS = total annual skin dose rate due to immersion in a finite cloud of noble gases, (mrem/yr);

DNTB = annual total body dose rate due t6 immersion in a finite cloud of noble gases, (mrem/yr);

DNp = annual beta air dose rate to a semi-infinite cloud of noble gases, (mrad/yr);

DNr = annual gamma air dose rate due to a finite cloud of noble gases, (mrad/yr);

DRaj = total annual dose rate from ingestion of root crop or non-leafy vegetables to organ j, of an individual in age group a, (mrem/yr);

[DIQ] = deposition rate considering depletion at the receptor location in question, from Table 10-1, (m-2);

fj = fraction of the ingestion rate of a leafy vegetable that is produced in the garden of interest, (dimensionless; assumed to be 1.0);

fp = fraction of the year the animals graze on pasture, (dimensionless; assumed to be 1.0);

fr = fraction of root crops/non-leafy vegetable that are produced in the garden of interest, (dimensionless; assumed to be 0.76);

fs = fraction of daily feed that is pasture grass when the animal grazes on pasture, (dimensionless; assumed to be 1.0);

Fjf = average fraction of the animal's daily intake of radionuclide i which appears in each kilogram of meat, from Table A-5, (days/kg);

Fim = average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, from Table A-5 for cows, Table A-6 for goats, (daysAiter);

H = absolute humidity of the atmosphere from Reference 15, (g/M3; assumed to be 5.6 gIm3);

p = fractional equilibrium ratio, (dimensionless; assumed to be 1.0 for continuous release);

P = effective surface density for dry soil, (kg/M 2 ; assumed to be 240 kg/rM2);

Qf = amount of feed consumed by the animal per day from Table A-7, (kg/day);

Q; = annual release rate of radionuclide i in gaseous effluents (CVyr);

9-12

PNPS-ODCM Rev. 9 rl= fraction of deposited radiojodine retained on crops, (dimensionless; assumed to be 1.0 from References 16-19);

rp = fraction of deposited particulates retained on crops, (dimensionless; assumed to be 0.2 from References 20 and 21);

S = attenuation factor that accounts for the dose reduction due to shielding provided by residential structures from Table A-1 9, (dimensionless);

tb = time period over which the radionuclide buildup is evaluated, (hr; assumed to be 1.31 E5 hr = 15 yr);

te - time period that crops are exposed to radionuclide deposition during the growing season, from Table A-19, (hr);

tf = average transport time of the activity from the feed into the milk and to the receptor from Table A-19, (hr);

th = holdup time that represents the time interval between harvest and consumption of the food, from Table A-19, (hr);

ts = average time for radionuclides to pass from feed through meat to the consuming individual, (hr; assumed to be 480 hr = 20 days);

UBa = annual breathing rate, for individuals in the age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (m /yr);

UCa = annual intake of r&eat, for individuals in age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (kg/yr);

ULa - annual intake of leafy vegetables, for individuals in the age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (kg/yr);

UMa = annual intake of milk, for individuals in the age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (liter/yr);

URa = annual intake of root crops/non-leafy vegetables, for individuals in the age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (kg/yr);

YV= agricultural productivity/yield, from Table A-1 9, (kg/M2, wet weight);

1Z/°]c = appropriate value of undepleted atmospheric dispersion factor used to estimate ground level airborne concentration of gaseous, (i.e., non-particulate) radionuclides, from Table 10-1, (sec/m 3 );

[XQ]d = appropriate value of the average gaseous dispersion factor corrected for depletion of particulates and radiolodines, from Table 10-1, (sec/m 3);

PUQ]Y = appropriate value of gamma atmospheric dispersion factor used to estimate ground level gamma dose rate from an elevated or ground level plume as calculated in References 13 and 14, from Table 10-1, (sec/r 3 );

9-13

PNPS-ODCM Rev. 9

= radioactive decay constant of radionuclide i, (hr -1);

AEi = effective removal rate constant for radionuclide i from crops, in hr 1 , where XEi = X+ + w. is the radioactive decay constant, and Xw is the removal rate constant for physical loss by weathering. w = 0.0021 , (hr 1 );

1.11 = average ratio of the tissue to air energy absorption coefficients, (mrem/mrad);

3.17E4= 1.00E12 pCiCl divided by 3.15E7 sec/yr, (pCi-yr/Ci-Sec) 1.19E7= 1.00E12 pCVCi divided by 3.15E7 sec/yr and multiplied by 1.00E3 g/kg and by 0.5 g H-3 in plant water per g H-3 in atmospheric water from Reference 22 (dimensionless) and by 0.75 g water per g plant (dimensionless), as calculated in Reference 8 equation C-9, (pCi-yr-g/Ci-sec-kg);

2.18E7 = 1.00E12 pCVCi divided by 3.15E7 sec/yr and multiplied by 1.00E3 g/kg and by 0.11 g Carbon/g plant mass from References 23 and 24 divided by 0.16 g Carbon/m 3 of air, as calculated in Reference 8 equation C-8, (pCi-yr-m 3/Ci-sec-kg):

5.71E7= conversion factor to correct for activity, time units, and elemental forms of radioiodines, equal to the particulate radionuclide conversion factor 1.14E8 multiplied by an elemental iodine fraction of 0.5 from Reference 25, (pCi-yr/Ci-hr);

1.14E8 = conversion-factor to correct activity units and time units for particulate radionuclides, equal to 1.OOE12 pCVCi multiplied by 1 yr/8760 hr, (pCi-yr/Ci-hr);

1.00E12 = conversion factor to correct for activity units, (p0i/Ci);

9-14

PNPS-ODCM Rev. 9 9.4 Total Dose to a Member of the Public The purpose of this section is to describe the method used to calculate the cumulative dose contributions from liquid and gaseous effluents in accordance with PNPS Effluent Controls for total dose. This method can also be used to demonstrate compliance with the Environmental Protection Agency (EPA) 40CFR1 90, 'Environmental Standards for the Uranium Fuel Cycle".

Compliance with the PNPS Effluent Controls dose objectives for the maximum individual demonstrates compliance with the EPA limits to any member of the public, since the design dose objectives from 10CFR50 Appendix I are much lower than the 40CFR190 dose limits to the general public. With the operational objectives in PNPS Effluent Controls Sections 3.2.2, 3.3.2, and/or 3.3.3 being exceeded by a factor of two, a special analysis must be performed. The purpose of this special analysis is to demonstrate if the total dose to any member of the public (real individual) from all uranium fuel cycle sources (including all real pathways and direct radiation) is limited to less than or equal to 25 mrem per year to the total body or any organ except for the thyroid which is limited to 75 mrem per year.

If required, the total dose to a member of the public will be calculated for all significant effluent release points for all real pathways including direct radiation. Only effluent releases from PNPS (Pilgrim Station) need to be considered since no other nuclear fuel cycle facilities exist within a 50 mile radius. The calculations will be based on the equations contained in this section, with the exception that the usage factors and other site specific parameters will be modified using more realistic assumptions, where appropriate.

The direct radiation component from the facility can be determined by using environmental TLD results. These results will be corrected for natural background and for actual occupancy time of the recreational areas accessible to the general public at the location of maximum direct radiation.

It is recognized that by including the results from the environmental TLDs into the sum of total dose component,'~the direct radiation dose may be overestimated. The TLD measurements may include the exposure from noble gases, ground plane deposition, and shoreline deposition, which have already been included in the summation of the significant dose pathways to the general

- public. However, this conservative method can be used, if required, as well as any other method for estimating the direct radiation dose from contained radioactive sources within the facility. The methodology used to incorporate the direct radiation component into total dose estimates will be outlined whenever total doses are reported.

Therefore, the total dose will be determined based on the most realistic site specific data and parameters to assess the real dose to any member of the general public.

9-15

PNPS-ODCM Rev. 9 10.0 RECEPTOR LOCATIONS, HYDROLOGY, AND METEOROLOGY The purpose of this section is to identify those receptor locations which represent critical pathway locations and the methods used to estimate dilution and dispersion factors for these locations.

For the dose calculations from liquid effluents, the maximum individual is assumed to: 1) ingest fish and shellfish from the discharge canal, 2) receive direct radiation from shoreline deposits at both the discharge canal and PNPS shoreline recreational area, and 3) receive external radiation while swimming at White Horse Beach as well as while boating on the Cape Cod Bay. The doses are calculated for the various age groups (i.e., infant, child, teenager and adult), as well as for the various organs, (i.e., bone, liver, thyroid, kidney, lung, gastrointestinal tract/lower large intestine, skin, and total body). The maximum total body and organ doses are selected from the totals of the various age groups and organ doses calculated as described above.

For liquid effluent pathways, Table A-3 lists the conservative values for the mixing ratio and shore width factor for the various aquatic receptor locations.

For the dose calculations for gaseous effluents, the maximum individual is assumed to reside at the receptor location that provides the highest dose from the dose contributions from all gaseous release points where significant releases have occurred. The locations selected in Table 10-1 are the site boundary, a garden at the site boundary, and the nearest milk animal at the Plimoth Plantation. The dose calculations are performed for each release point and totaled for the following dose pathways; 1) noble gas immersion, 2) ground plane deposition, 3) inhalation, and.

4) ingestion of leafy vegetable, root crops/non-leafy vegetables, milk, and meat. The doses are also calculated for the various age groups and for the various organs as described for liquid effluents. The maximum total body, skin, and organ doses are selected from the totals of the various age groups and organ doses calculated as described above.

In order togstimate atmospheric dispersion and deposition factors for each of these locations, a computer code supplied by the Yankee Atomic Electric Company was used. The code, AEOLUS (Reference 13), was used to calculate quarterly average values of dispersion and deposition factors.

Meteorological data for a three year period, January 1, 1977 to December 31, 1979, were used for these analyses. The most conservative quarterly average values of ground level average atmospheric dispersion factor before depletion [XIO]c, ground level average atmospheric dispersion factor after depletion [IXQ]d, average gamma dilution factor [X/QJy, and average deposition rate [D/Q] for the three year period were chosen for each of the critical receptor locations.

The technique used to estimate- ground level gamma doses from an elevated or ground level plume is based on the sector average finite cloud model of Regulatory Guide 1.109 (Reference 8). The equation has been rearranged into a form similar to the standard semi-infinite cloud equation thereby allowing the use of a "gamma ChVQ" which includes the effects of plume dimensions, gamma energy mix, atmospheric and geometric attenuation, etc. (See References 13 and 14 for a detailed discussion.)

For gaseous effluent pathways, TablelO-1 lists the critical locations for receptors and conservative atmospheric dispersion factors for each atmospheric receptor location.

10-1

PNPS-ODCM Rev. 9 TABLE 10-1 CRITICAL RECEPTOR LOCATIONS AND ATMOSPHERIC DISPERSION FACTORS PC/Q1c R/Q]d R/QJt [D/Q]

Effluent Control Section (sec/Mr3 ) (sec/m 3 ) (sec/M 3 ) (1/m2 )

GROUND-LEVEL RELEASES: Reactor Building Vent, Turbine Building, etc.

3/4.3.1: Gaseous Effluent Dose Rate Site Boundary (1) 7.40E-06 7.04E-06 4.69E-06 5.22E-08 Nearest Garden (2) 7.40E-06 7.04E-06 4.69E-06 5.22E-08 Nearest Milk Animal (3) 4.29E-07 4.21 E-07 1.70E-07 7.93E-1 0 3/4.3.2: Dose - Noble Gases Site Boundary (1) 7.40E-06 N/A 4.69E-06 N/A 3/4.3.3: Dose - Iodine-131, Iodine-133, Radioactive Materials in Particulate Form, and Tritium Site Boundary (1) 7.40E-06 7.04E-06 N/A 5.22E-08 Nearest Garden (2) 7.40E-06 7.04E-06 N/A 5.22E-08 Nearest Milk Animal (3) 4.29E-07 4.21 E-07 N/A 7.93E-1 0 3/4.4.1: Total Dose Site Boundary (2) 7.40E-06 7.04E-06 4.69E-06 5.22E-08 Nearest Garden (2) 7.40E-06 7.04E-06 4.69E-06 5.22E-08 Nearest Milk Animal (3) 4.29E-07 4.21 E-07 1.70E-07 7.93E-10 ELEVATED RELEASES: Main Stack 3/4.3.1: Gaseous Effluent Dose Rate Site Boundary (1) 4.69E-07 4.69E-07 1.68E-06 2.92E-09 Nearest Garden (2) 4.69E-07 4.69E-07 1.68E-06 2.92E-09 Nearest Milk Animal (3) 3.73E-08 3.70E-08 3.22E-08 2.46E-10 3/4.3.2: Dose - Noble Gases N Site Boundary (') 4.69E-07 N/A 1.68E-06 N/A 3/4.3.3: Dose - Iodine-131, lodine-133, Radioactive Materials in Particulate Form, and Tritium Site Boundary (1) 4.69E-07 4.69E-07 N/A 2.92E-09 Nearest Garden (2) 4.69E-07 4.69E-07 N/A 2.92E-09 Nearest Milk Animal (3) 3.73E-08 3.70E-08 N/A 2.46E-1 0 3/4.4.1: Total Dose Site Boundary ( 4.69E-07 4.69E-07 1.68E-06 2.92E-09 Nearest Garden (2) 4.69E-07 4.69E-07 1.68E-06 2.92E-09 Nearest Milk Animal (3) 3.73E-08 3.70E-08 3.22E-08 2.46E-10

' Site Boundary" means the location at or beyond the boundary of the restricted area with the highest calculated dispersion and/or deposition factor.

(2) "Nearest Garden" is considered to be the same as the site boundary due to the abundance of small gardens near Pilgrim Station.

(3) 'Nearest Milk Animal" is presently considered to be at the Plimoth Plantation, 3.7 km (2.3 mi) west of Pilgrim Station.

10-2

PNPS-ODCM Rev. 9 11.0 RADIOLOGICAL ENVIRONMENTAL SAMPLING AND MEASUREMENT LOCATIONS Sampling and measurement locations have been established for Pilgrim Station considering meteorology, population distribution, hydrology, and land use characteristics of the Plymouth area.

The sampling locations are divided into two classes: indicator and control. Indicator locations are those which are expected to show effects from PNPS operations, if any exist. These locations were selected primarily on the basis of where the highest predicted environmental concentrations were calculated to occur. While the indicator locations are typically within a few kilometers of the plant, the control stations are generally located so as to be outside the influence of Pilgrim Station.

They provide a basis on which to evaluate fluctuations at indicator locations relative to natural background radiation, natural radioactivity, and fallout from prior nuclear weapons tests.

The environmental sampling media collected In the vicinity of Pilgrim Station include air particulate filters, charcoal cartridges, seawater, shellfish, Irish moss, American lobster, fishes, sediment, cranberries, vegetation, and animal forage. The media, sample designation location, description, distance, and direction for indicator and control samples are listed in Tables 3.5-1 and 3.5-3 under Control 3/4.5.1. These sampling locations are also displayed on the maps shown in Figures 3.5-1 through 3.5-5. The frequency of collection and types of radioactivity analysis. are described in the PNPS Effluent Control 3/4.5.1, Table 3.5-1. The maximum lower limits of detection (LLD) for the analytical measurements are specified in the PNPS Effluent Controls Table 4.5-1 (see Appendix B for the definitions of the lower limit of detection).

The environmental TLD location designations, distance, and direction from the reactor are listed in Table 3.5-2. The radiation measurement locations for the environmental TLDs are shown in Figures 3.5-1 through 3.5-5. The frequency and type of radiation measurement is described in the PNPS Effluent Control 3/4.5.1, Table 3.5-1.

The pressurized ion chamber measurement locations, distance, and direction from the reactor are

-%listed in Table 3.5-3. These radiation measurement locations for the surveys performed on local beaches. The frequency and type of radiation measurement is described in PNPS Effluent Control 3/4.5.1, Table 3.5-1.*

The atmospheric and land-based samples are collected by Entergy personnel. The aquatic samples are collected by the an external contractor experienced with diving and marine sampling.

The radioactivity analysis of samples and the processing of the environmental TLDs is performed by Entergy personnel at the J.A. Fitzpatrick Environmental Laboratory.

The PNPS staff reviews the radioactivity analysis results from the contractor laboratory. Reporting levels for radioactivity concentrations in environmental samples are listed in PNPS Effluent Controls Table 3.5-4. If the radioactivity concentrations are above the reporting levels, the NRC is notified in writing within 30 days. A determination of the cumulative dose contribution for the current year will be performed for radioactivity which is detected that is attributable to PNPS operation. Depending upon the circumstances, a special study may also be conducted.

If radioactivity levels in the environment become elevated as a result of the station's operation, an investigation is performed, and corrective actions are recommended to reduce the amount of radioactivity to as far below the legal limits as is reasonably achievable.

The radiological environmental sampling and measurement locations are reviewed annually, and modified if necessary. A garden and milk animal census is performed every year to identify changes in the use of the environment in the vicinity of the station to permit modification of the sampling and measurement locations.

11-1

PNPS-ODCM Rev. 9 The original radiological monitoring program was modeled after guidance from the NRC presented in Regulatory Guide 4.8 (reference 29). Shortly after the inception of Regulatory Guide 4.8 in 1975, the NRC began to solicit comments on the environmental monitoring guidelines. The NRC working group modified the environmental monitoring guidelines, and issued the revised guidance in the form of Revision 1 to the Branch Technical Position on an acceptable radiological environmental monitoring program (reference 28). In turn, the Branch Technical Position became the model for environmental monitoring put forth In NUREG-1302. Notable changes in the Branch Technical Position were the elimination of soil sampling, and increased reliance on direct radiation monitoring using environmental thermoluminescent dosimeters (TLDs).

Upon review of the PNPS radiological environmental monitoring program in 2002, several departures from the model program outlined in NUREG-1302 were noted. PNPS was still using the soil sampling program of once per three years outlined in Regulatory Guide 4.8. Also, PNPS was using an annual assessment of direct radiation at six locations using a pressurized ion chamber, in addition to the 110 TLDs posted around the plant. Based on the extensive monitoring of airborne particulates and iodines above and beyond that prescribed by NUREG-1302, any buildup of plant-related activity in soil would be first indicated in airborne monitoring. Due to the extent and sensitivity of the airborne monitoring efforts, soil sampling and analysis was dropped from the sampling program. In a similar fashion, the integrating nature 6f TLDs makes this approach to monitoring direct radiation the preferred method, and industry standard. Again, since the PNPS TLD placement far exceeds that prescribed by NUREG-1302, assessment of direct radiation through use of pressurized ion chamber measurements was dropped in lieu of the extensive TLD monitoring effort.

In 1977, Boston Edison Company was pursuing construction of a second unit on the PNPS site.

As part of the preliminary licensing efforts for this second unit, Pilgrim Station committed to an special marine sampling program under the REMP. This program was much more aggressive than that outlined in standard NRC guidance for an environmental monitoring program, and included collecting many more samples, duplicate/split sampling, analysis of special radionuclides, and analysis to detection limits lower than those recommended by the NRC. This specialized sampling program was agreed to by Boston Edison Company for a period not to exceed 10 years.

Due to the inclusion of the REMP in the Technical Specifications at that time, the program was carried forward beyond the 10-year period.

Following an evaluation of results obtained by this specialized marine sampling program over the past 25 years, it has been determined that the results have shown that the impact of radioactivity in liquid discharges on the general public and environment is negligible. In light of the fact that the terms of the sampling program have expired, the specialized program is no longer warranted.

Furthermore, replacement of the specialized program with a marine sampling program such as that prescribed by the NRC in NUREG-1302 and the Branch Technical Position on Environmental Monitoring will still allow PNPS personnel to evaluate the impact of its operations on the environment and general public. Therefore, PNPS has dropped most of the specialized requirements and has adopted the standard model for marine sampling prescribed by the NRC.

11-2

PNPS-ODCM Rev. 9 12.0 ANNUAL REPORT PREPARATION 12.1 Annual Effluent and Waste Disposal Report The Annual Radioactive Effluent and Waste Disposal Report covering the operation of Pilgrim Nuclear Power Station during the previous calendar year shall be submitted by May 15 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the facility. This report shall be submitted in accordance with 10CFR50.36a.

General guidance for the preparation of this report can be found in Regulatory Guide 1.21 (Reference 26). In addition to effluent and disposal data, this report should also include summaries of meteorological data in the form of joint frequency distribution tables. This report should present an evaluation of the doses received by members of the public resulting from operation of Pilgrim Station. Liquid and airborne effluent pathways, as discussed in ODCM Section 9, should be used to assess the doses, as well as ambient (direct) radiation exposure resulting from plant operation.

In addition to summarizing effluents and their resulting doses, the Annual Effluent and Waste Disposal Report serves as the vehicle to notify the NRC of any changes in the ODCM. Changes to the ODCM during the previous calendar year shall be submitted in the Annual Effluent and Waste Disposal Report.

12.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of Pilgrim Nuclear Power Station during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in other sections of the ODCM, as well as 10CFR50 Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include tables summarizing the results of analyses of radiological environmental samples and environmental radiation measurements taken during the period, pursuant to the locations specified in Section 3/4.5 of the ODCM. Summarized and tabulated results of these analyses and measurements shall be similar in format to guidance provided in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion in the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

12-1

PNPS-ODCM Rev. 9

13.0 REFERENCES

1) Boston Edison Company, PNPS Technical Specifications.

2) U. S. Nuclear Regulatory Commission, Generic Letter 89-01, Implementation of Programmatic Controls for Radioactive Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program", January 1989.

3) Boston Edison Company, Updated Final Safety Analysis Report for Pilgrim Nuclear Power Station, Volumes 1 through 7.

4) Boston Edison Company, Pilgrim Station Unit 1 Appendix I Evaluation, April, 1977.

5) General Electric Company, GEK-32445A, Pilgrim Process Radiation Monitoring System Manual.

6) Boston Edison Company, PNPS Maintenance Department Recalibration and Malfunction Records.

7) Boston Edison Company, PNPS Operations Manual, Volume 7, Book 2: Chemical and Radiochemical Procedures.

8) U. S. Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", Revision 1, October, 1977.

9) D.L. Strenge, T.J. Bander, and J.K. Soldat, NUREG/CR-4653, UGASPAR II Technical Reference and User Guide", March 1987.

10) 'HERMES', A Digital Computer Code for Estimating Regional Radiological Effects from the Nuclear Power Industry, HEDL-TME-N1-168, December 1971.

11) G. L. Toombs and P. B. Culter, 'Comprehensive Final Report for the Lower Columbia River Environmental Survey in Oregon June 5, 1961 - July 31, 1967," Oregon State Board of Health, Division of Sanitation and Engineering, 1968.

12) U.S. Nuclear Regulatory Commission, NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants', Revision -2, May, 1982.

13) J.N. Hamawi, "AEOLUS', Yankee Atomic Electric Company YAEC-1120,1977.

14) J. N. Hamawi, "SKIRON', Yankee Atomic Electric Company YAEC-1138, 1977.

15) U. S. Nuclear Regulatory Commission, NUREG/CR-3332, "Radiological Assessment",

December 1983.

16) D. F. Bunck (ed.), USAEC Report IDO-12063, "Controlled Environmental Radioiodine Test, Progress Report Number Two", January 1968.

17) J. D. Zimbrick and P. G.Voilleque, USAEC Report IDO-12065, 'Controlled Environmental Radioiodine Tests at the National Reactor Testing Station, Progress Report Number Four,'

December 1968.

13-1

PNPS-ODCM Rev. 9

13.0 REFERENCES

(continued)

18) F. 0. Hoffman, IRS-W-6, "Environmental Variables Involved with the Estimation of the Amount of 1311 in Milk and the Subsequent Dose to the Thyroid," Institute fur Reaktorsicherheit, June 1973.

19) F. 0. Hoffman, IRS-W-13, "A Reassessment of the Parameters Used To Predict the Environmental Transport of 1311 from Air to Milk," Institute fur Reaktorsicherheit, April 1975.

20) C. A. Pelletier and P. G. Voilleque, Health Physics, Vol. 21, p. 777, "The Behavior of 137 Cs and Other Fallout Radionuclides on a Michigan Dairy Farm," 1971.

21) P. G. Voilleque and C. A. Pelletier, Health Physics, Vol. 27, p. 189, "Comparison of External Milk as Critical Pathways for 137 Cs, 54Mn, and Irradiation and Consumption of Cow's 144 Ce- 144 Pr Released to the Atmosphere", 1974.

22) L. R. Anspaugh et al., USAEC Report UCRL-73195, Rev. 1, "The Dose to Man via the Food-Chain Transfer Resulting from Exposure to Tritiated Water Vapor", 1972.

23) Y. C. Ng et al., USAEC Report UCRL-50163, Part IV, 'Prediction of the Maximum Dosage to Man from the Fallout of Nuclear Devices, IV Handbook for Estimating the Maximum Internal Dose from Radionuclides Released to the Biosphere," 1968.

24) R. C. Weast (ed.), "Handbook of Chemistry and Physics," CRC Press, 1970.

25) U.S. Nuclear Regulatory Commission, NUREG-75/021, "Detailed Measurement of 1-131 in Air, Vegetation and Milk Around Three Operating Reactor Sites," March 1975.

26) U.S. Nuclear Regulatory Commission, 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.

27) U.S. Nuclear Regulatory Commission, NUREG-1302, uOffsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors", April 1991.

28) U.S. Nuclear Regulatory Commission, Radiological Assessment Branch Technical Position, Revision 1, November 1979.

29) U.S. Nuclear Regulatory Commission, Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants", December 1975.

13-2

PNPS-ODCM Rev. 9 APPENDIX A DATA REQUIRED FOR EFFLUENT CALCULATIONS

'TABLE A-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA pCVkg per pCi/literO1 )

FRESHWATER SALTWATER ELEMENT FISH INVERTEBRATE FISH l INVERTEBRATE H 9.0E-01 9.0E-01 9.02-01 9.3E-01 C 4.6E+03 9.1 E+03 1.8E+03 I 1.4E+03 Na 1.OE+02 2.0E+02 6.7E-02 l 1.9E-01 P 1.0E+05 2.0E+04 2.9E+04 i 3.0E+04 Cr 2.0E+02 2.0E+03 4.OE+02 l 2.OE+03 Mn 4.0E+02 9.OE+04 5.5E+02 I 4.0E+02 Fe 1.OE+02 l 3.2E+03 3.OE+03 2.OE+04 Co 5.0E+01 I 2.0E+02 1.0E+02 1.0E+03 Ni 1.0E+02 l 1.0E+02 1.0E+02 l 2.5E+02 Cu 5.0E+01 l 4.0E+02 6.7E+02 1.7E+03 Zn 2.0E+03 l 1.0E+04 2.0E+03 l 5.OE+04 Br 4.2E+02 I 3.3E+02 1.5E-02 1 3.1 E+00 Rb 2.0E+03 l 1.0E+03 8.3E+00 l 1.7E+01 Sr 3.0E+01 l 1.0E+02 2.0E+00 l 2.0E+01 Y 2.5E+01 J 1.0E+03 2.5E+01 1.0E+03 Zr 3.3E+00 6.7E+00 2.0E+02 l 8.0E+01 Nb 3.0E+04 1.0E+02 3.OE+04 1.0E+02 Mo 1.0E+01 i 1.0E+01 1.0E+01 1.0E+01 Tc 1.5E+01 [ 5.0E+00 1.0E+01 5.OE+01 Ru 1.0E+01 3.0E+02 3.0E+00 1.0E+03 Rh 1.0E+01 3.0E+02 1.0E+01 2.0E+03 Te 4.0E+02 6.1 E+03 1.OE+01 l 1.OE+02 I 1.5E+01 5.0E+00 1.0E+01 l 5.0E+01 Cs 2.0E+03 I 1.0E+03 4.02+01 l 2.5E+01 Ba 4.0E+00 2.0E+02 1.OE+01 1.0E+02 La 2.5E+01 l 1.0E+03 2.5E+01 1 1.0E+03 Ce 1.0E+00 l 1.0E+03 1.0E+01 l 6.0E+02 Pr 2.5E+01 ! 1.0E+03 2.5E+01 1.0E+03 Nd 2.5E+01 1.02+03 2.5E+01 1.0E+03 W 1.2E+03 1.0E+01 3.0E+01 I 3.0E+01 Np 1.0E+01 4.0E+02 1.0E+01 1.0E+01

1) Data presented in this table are from Reference 8.

A-1

PNPS-ODCM Rev. 9 TABLE A-2 DOSE FACTORS FOR IMMERSION IN WATER(1 )

mrem/hr per pCVLiter(2)

__ _ NUCLIDE SKIN TOTAL BODY'")

H-3 ' O.OE+00 I O.OE+00 N-13 2.6E-06 I 1.9E-06 C-1 4 3.8E-06 i 0.OE+00 Na-22 4.8E-06 4.OE-06 Na-24 9.3E-06 j 7.8E-06 Cr-51 6.4E-08 1 5.2E-08 Mn-54 1.8E-06 l 1.5E-06 Fe-55 . 3.6E-1 0 l 6.4E-1 1 Fe-59 2.6E-06 2.2E-06 Co-58 2.3E-06 i 1.BE-06 Co-60 5.4E-06 4.6E-06 Ni-63 O.OE+00 i _ 0.0E+00 Cu-64 5.2E-07 1_3.7E-07 Zn--65 1.2E-06 1.1 E-06 Sr-89111 5.4E-07 I 4.6E-09 Sr-90-1 1.5E-07 15.4E-1_ 0 Y-90'zJ 9.6E-07 i_1.3E-08 Sr+Y-90J.)Lb) 1.1 E-06 !_1.3E-08 Zr-95 1.8E-06 l 1.5E-06 Nb-95 1.6E-06 1 1.4E-06 Mo-99 9.1 E-07 j 4.7E-07 Ru-103 1.1 E-06 l 8.9E-07 Ru-1 06 1.9E-06 i 3.8E-07 Te-132 4.8E-07 I 4.OE-07 1-129 6.1 E-09 I 2.1 E-09 1-131 9.5E-07 1 6.8E-07 1-132 5.5E-06 l 4.4E-06 1-133 1.5E-06 l 9.6E-07 1-135 4.OE-06 1 3.3E-06 Cs-1 34 3.5E-06 i 2.9E-06 Cs-1 37 1.4E-06 i 1.OE-06 Ba-1 40 7.6E-07 4.6E-07 La-1 40 5.3E-06 4.1 E-06 Ce-141 2.4E-07 i 1.3E-07 Ce-144 6.2E-08 ! 3.0E-08 Pr-1 44 1.3E-06 ! 5.6E-08 Ce+Pr-1 44t) 1.4E-06 ! 8.6E-08 (I)

Data presented in this table are from Reference 10.

(2)

The same factors apply to adult, teenager, and child.

(3)

Total body factors also apply to other internal organs.

(4)

Not including penetration of oxide into skin.

(5)

Includes bremsstrahlung.

(6)

Use these factors for Sr-90 unless Y-90 concentration is given separately.

(7 Use these factors for Ce-144 unless Pr-144 concentration is given separately.

A-2

PNPS-ODCM Rev. 9 TABLE A-3 RECOMMENDED VALUES FOR LIQUID EFFLUENTS(')

Parameter Symbol Parameter Description Values Ml Mixing ratio at location I of exposure 0.2 (Aquatic foods taken from Discharge or harvest of aquatic foods'* Canal Outfall) (2) 0.05 (Shoreline, Pilgrim Station Recreational Area) (3) 1.0 (Shoreline, Discharge Canal) 0.03 (Swimming, White Horse Beach) 0.03 (Boating, Cape Cod Bay) th Period of time between exposure of 24 hr for maximum individual aquatic foods to radionuclides in water and their consumption 168 hr for average individual, sport fish doses 240 hr for average individual, commercial fish doses WI Shoreline width factor for location I 0.5 (Recreational Area) (4) 0.1 (Discharge Canal) (4)

1) Data presented in this table are from Reference 8 unless otherwise noted.

(2) Collection of aquatic foods from within the Discharge Canal is prohibited.

(3) Swimming is prohibited at Pilgrim Station Recreational Area.

(4) From Reference 4.

A-3

PNPS-ODCM Rev. 9 TABLE A-4 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES(')

h P-air (DFNip) p-skin (DFNIS) y-air (DFNy) l -body (DFNiTB)

Nuclide mrad-m 3/pCi-y_ mrem-m 3/pCi-yr mrad-m 3 /pCi-yr lmrem-m3/pCi-yr Kr-83m 2.88E-04 --- 1.93E-05 7.56E-08 Kr-85m 1.97E-03 1.46E-03 1.23E-03 l 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61 E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02 1.01 E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131 m 1.11 E-03 4.76E-04 1.56E-04 9.15E-05 Xe-1 33m 1.48E-03 9.94E-04 3.27E-04 2.51 E-04 Xe-1 33 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-1 35m 7.39E-04 7.11 E-04 3.36E-03 3.12E-03 Xe-1 35 2.46E-03 1.86E-03 1.92E-03 1.81 E-03 Xe-1 37 1.27E-02 1.22E-02 1.51 E-03 1.42E-03 Xe-1 38 4.75E-03 4.13E-03 9.21 E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03

) Data presented in this table are from Reference 8.

A-4

PNPS-ODCM Rev. 9 TABLE A-5 STABLE ELEMENT TRANSFER DATA(')

rBiv Element Veg/SoilBMilFm(daOWte)

Fm(Cow)

Milk (dayiter) j MetgE Ff t (day/kg)

H 4.8E+oo 1.OE-02 1.2E-02 C 5.5E+00 1.2E-02 3.1 E-02 Na 5.2E-02 4.OE-02 3.OE-02' P 1.1 E+OO 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.OE-04 Fe 6.6E-04 1.2E-03 4.0E-02 Co 9.4E-03 1.OE-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.OE-03 Zn 4.OE-01 3.9E-02 3.OE-02 Rb 1.3E-01 3.OE-02 3.1 E-02 Sr 1.7E-02 8.OE-04 6.OE-04 Y 2.6E-03 1.OE-05 4.6E-03 Zr 1.7E-04 5.OE-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 1.2E-01 7.5E-03 8.OE-03 Tc 2.5E-01 2.5E-02 4.OE-01 Ru 5.OE-02 1.OE-06 4.OE-01 Rh 1.3E+01 1.OE-02 1.5E-03 Ag 1.5E-01 5.OE-02 1.7E-02 Te 1.3E+00 1.OE-03 7.7E-02 I 2.OE-02 6.OE-03 2.9E-03 Cs 1.OE-02 1.2E-02 . 4.OE-03 Ba 5.OE-03 4.OE-04 3.2E-03 La 2.5E-03 5.OE-06 2.OE-04 Ce 2.5E-03 1.OE-04 1.2E-03 Pr 2.5E-03 5.OE-06 4.7E-03 Nd 2.4E-03 5.OE-06 3.3E-03 W 1.8E-02 5.OE-04 1.3E-03 Np 2.5E-03 5.OE-06 2.0E-04 (1) Data presented in this table are from Reference 8.

A-5

PNPS-ODCM Rev. 9 TABLE A-6 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK"1)

Element Fm (day/liter)

H 1.70E-01 C 1.OOE-01 P 2.50E-01 Fe 1.30E-04 Cu 1.30E-02 Sr 1.40E-02 1 6.OOE-02 Cs 3.OOE-01 TABLE A-7 ANIMAL CONSUMPTION RATES(')

QF QAW Feed or Forage Water Animal (kg/day [wet weightl) (liter/day)

Milk Cow 50 60 Beef Cattle 50 50 Goats 6 8

" Data presented in these tables are from Reference 8.

A-6

PNPS-ODCM Rev. 9 TABLE A-8 RECOMMENDED USE FACTORS TO BE APPLIED FOR THE AVERAGE INDIVIDUAL" "92 Pathway Adult Teen Child Infant Fruits, vegetables, & grain (kg/yr) 190 240 200 -

Milk (liter/yr) 110 200 170 330 Meat& poultry (kg/yr) 95 59 37 -

Fish (kg/yr) 6.9 5.2 2.2 Seafood (kg/yr) 1.0 0.75 0.33 -

Drinking Water (liter/yr) 370 260 260 330 Shoreline recreation (hrlyr) (3)

Discharge Canal 8.3 47 9.5 -

Pilgrim Station Recreational Area 8.3 47 9.5 -

Swimming (hrlyr) (3) 52 52 29 -

White Horse Beach Boating - Cape Cod Bay (hr/yr) (3) 52 52 29 -

Inhalation (m3 /yr) 8000 8000 3700 1400 (I) Data presented in this table are from Reference 8, unless otherwise indicated.

(2) Usage factors for the average individual are used to determine the annual dose to the total body and thyroid of an average individual and the annual integrated dose to the population within a 50 mile radius.

(3) From Reference 4.

A-7

PNPS-ODCM Rev. 9 TABLE A-9 RECOMMEt 4DED USE FACTORS TO BE APPLIED FOR THE MAXIMUM EXPOSED INDIVIDUAL")

Pathway Adult Teen Child Infant Fruits, vegetables, & grain (kg/yr) 520 630 520 Leafy Vegetables (kg/yr)) 64 42 26 Milk (liter/yr) 310 400 330 330 Meat & poultry (kg/yr) 110 65 41 Fish (fresh or salt) (kg/yr) 21 16 6.9 Shellfish (kg/yr) (2) 9 6 3 Drinking Water (iiter/yr) 730 510 510 330 Shoreline recreation (hr/yr) (2)

Discharge Canal 12 67 14 Pilgrim Station Recreational Area 12 67 14 Swimming (hr/yr) (2) 52 52 29 White Horse Beach Boating-Cape Cod Bay (hr/yr) (2) 52 52 29 Inhalation (m3/yr) 8000 8000 3700 1400

' Data presented in this table are from Reference 8, unless otherwise indicated.

(2) From Reference 4.

A-8

PNPS-ODCM Rev. 9 TABLE A-10 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (1) mrem/hr per pCi/rn 2 Nuclide Total Body l Skin Nuclide Total Body l Skin H-3 O.OOE+00 O.OOE+00 Zr-93 O.OOE+00 O.OOE+00 Be-10 O.OOE+0O O.OOE+00 Zr-95 5.00E-09 5.80E-09 C-14 O.OOE+00 O.OOE+00 Zr-97 5.50E-09 6.40E-09 N-13 7.60E-09 8.80E-09 Nb-93m 8.20E-13 1.OOE-10 F-1 8 6.80E-09 8.00E-09 Nb-95 5.1 OE-09 6.OOE-09 Na-22 1.60E-08 1.80E-08 Nb-97 4.60E-09 5.40E-09 Na-24 2.50E-08 2.90E-08 Mo-93 2.29E-11 9.32E-10 P-32 _ 0.00E+0Q O.OOE+00 Mo-99 1.90E-09 2.20E-09 Ca-41 3.41 E-09 4.01 E-09 Tc-99m J 9.60E-1 0 1.1 OE-09 Sc-46 i 1.30E-08 1.50E-08 Tc-99 O.OOE+00 O.OOE+00 Cr-51 2.20E-10 2.60E-10 Tc-101 2.70E-09 3.OOE-09 Mn-54 5.80E-09 6.80E-09 Ru-1 03 3.60E-09 4.20E-09 Mn-56 1.1 OE-08 1.30E-08 Ru-1 05 4.50E-09 5.1 OE-09 Fe-55 O.OOE+00 O.OOE+00 Ru-106 1.50E-09 1.80E-09 Fe-59 8.OOE-09 9.40E-09 Rh-1 05 6.60E-1 0 7.70E-1 0 Co-57 9.1 E-b10 1.OOE-09 Pd-1 07 O.OOE+00 O.OOE+00 Co-58 7.OOE-09 8.20E-09 Pd-1 09 3.50E-1 1 4.OOE-1 1 Co-60 1.70E-08 2.OOE-08 Ag-1 1Om 1.80E-08 2.1 OE-08 Ni-59 O.OOE+00 O.OOE+00 Ag-1l 1.80E-10 2.1 OE-10 Ni-63 O.OOE+00 O.OOE+00 Cd-1 13m 2.30E-12 2.60E-12 Ni-65 3.70E-09 4.30E-09 Cd-i 15m O.OOE+00 O.OOE+00 Cu-64 1.50E-09 1.70E-09 Sn-1 23 O.OOE+00 6.46E-08 Zn-65 4.OOE-09 4.60E-09 Sn-1 25 5.70E-1 0 6.60E-1 0 Zn-69m 2.90E-09 3.40E-09 Sn-1 26 9.OOE-09 1.OOE-08 Zn-69 O.OOE+00 O.OOE+00 Sb-1 24 1.30E-08 1.50E-08 Se-79 0.OOE+OO O.OOE+00 Sb-1 25 3.1 OE-09 3.50E-09 Br-82 1.90E-08 2.20E-08 Sb-126 8.90E-09 I.OOE-08 Br-83 6.40E-11 9.30E-1I Sb-127 5.70E-09 6.60E-09 Br-84 1.20E-08 1.40E-08 Te-125m 3.50E-1 1 4.80E-1 1 Br-85 O.OOE+00 O.OOE+00 Te-127m 1.1OE-12 1.30E-12 Rb-86 6.30E-10 7.20E-10 l Te-127 1.OOE-11 1.1 OE-11 Rb-87 O.OOE+00 O.OOE+00 Te-1 29m 7.70E-1 0 9.OOE-1 0 Rb-88 3.50E-09 4.OOE-09 Te-129 7.1 OE-10 _ 8.40E-10 Rb-89 1.50E-08 1.80E-08 Te-1 31 m 8.40E-09 9.90E-09 Sr-89 5.60E-13 6.50E-13 Te-131 2.20E-09 2.60E-06 Sr-90 O.OOE+00 O.OOE+00 Te-132 1.70E-09 2.OOE-09 Sr-91 7.1 OE-09 8.30E-09 Te-133m 1.50E-08 1.70E-08 Sr-92 9.OOE-09 I.OOE-08 Te-1 34 1.OOE-09 1.20E-09 Y-90 2.20E-12 2.60E-12 Y-91 m

__~ _ _ _.1__ _ _ _ _

3.80E-09 4.40E-09 Y-91 2.40E-1 1 2.70E-1 I Y-92 1.60E-09 1.90E-09 l . .

Y-93 5.70E-1 0 7.80E-10 _ _

(') Data presented in this table are from Reference 9.

A-9

PNPS-ODCM Rev. 9 TABLE A-1 0 (continued)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (

mrern/hr per pCIrm2 Nuclide l Total Body j Skin Nuclide l Total Body j Skin 1-129 4.50E-10 7.50E-10 Pb-210 1.30E-11 1.70E-11 1-130 1.40E-08 1.70E-08 Bi-21 0 O.OOE+00 O.OOE+00 1-131 2.80E-09 3.40E-09 Po-210 5.40E-14 6.20E-14 1-132 1.70E-08 2.OOE-08 Ra-223 1.50E-09 1.80E-09 1-133 3.70E-09 4.50E-09 Ra-224 8.90E-09 1.00E-08 1-134 1.60E-08 1.90E-08 Ra-225 8.40E-11 1.20E-10 1-135 1.20E-08 1.40E-08 Ra-226 6.40E-09 7.40E-09 Cs-134m 6.20E-10 7.30E-10 Ra-228 1.20E-08 1.40E-08 Cs-1 34 1.20E-08 1.40E-08 Ac-225 1.60E-09 1.80E-09 Cs-1 35 O.OOE+00 O.OOE+00 Ac-227 2.00E-09 2.40E-09 Cs-1 36 1.50E-08 1.70E-08 Th-227 5.1 OE-10 6.30E-10 Cs-1 37 4.20E-09 4.90E-09 Th-228 8.90E-09 1.00-08 Cs-1 38 2.1 OE-08 2.40E-08 Th-229 2.20E-09 2.70E-09 Cs-i 39 6.30E-09 7.20E-09 Th-230 6.50E-09 7.50E-09 Ba-1 39 2.40E-09 2.70E-09 Th-232 3.00E-09 4.OOE-09 Ba-1 40 2.1 OE-09 2.40E-09 Th-234 1.1 OE-10 1.30E-10 Ba-1 41 4.30E-09 4.90E-09 Pa-231 2.20E-09 2.70E-09 Ba-1 42 7.90E-09 9.OOE-09 Pa-233 1.30E-09 1.50E-09 La-i 40 1.50E-08 1.70E-08 . U-232 2.59E-1 2 2.69E-1 1 La-1 41 2.50E-1 0 2.80E-10 U-233 2.30E-09 2.80E-09 La-1 42 1.50E-08 1.80E-08 U-234 6.32E-1 3 1.59E-1 0 Ce-1 41 5.50E-10 6.20E-10 U-235 3.202-09 4.00E-09 Ce-1 43 2.20E-09 2.50E-09 U-236 2.1 OE-1 4 1.802-11 Ce-1 44 3.20E-1 0 3.70E-10 U-237 1.OOE-09 1.30E-09 Pr-1 43 O.OOE+00 O.OOE+00 U-238 1.1 OE-1 0 1.50E-10 Pr-1 44 2.OOE-1 0 2.30E-1 0 Np-237 1.40E-09 1.60E-09 Nd-1 47 1.OOE-09 1.20E-09 Np-238 2.80E-09 3.20E-09 Pm-1 47 O.OOE+00 O.OOE+00 Np-239 9.50E-10 1.10E-09 Pm-148m 1.41 E-08 8.16E-08 Pu-238 1.30E-12 . 1.80E-11 Pm-148 4.60E-09 5.30E-09 Pu-239 7.90E-13 7.70E-12 Pm-1 49 2.50E-11 2.90E-11 Pu-240 1.30E-12 1.80E-1 1 Pm-1 51 2.20E-09 2.30E-09 Pu-241 4.60E-12 6.80E-12 Sm-151 4.80E-11 2.10E-10 Pu-242 1.1OE-12 1.60E-11 Sm-153 2.70E-10 3.OOE-10 Pu-244 8.95E-10 9.62E-10 Eu-1 52 7.37E-09 8.53E-09 Am-241 1.80E-10 2.60E-10 Eu-i 54 7.80E-09 9.OOE-09 Am-242m 2.60E-1i1 1.80E-10 Eu-1 55 3.81 E-10 4.33E-10 Am-243 1.30E-09 1.50E-09 Eu-1 56 7.60E-09 8.70E-09 Cm-242 5.50E-12 2.30E-1 1 Tb-1 60 8.60E-09 1.OOE-08 Cm-243 2.30E-09 2.90E-09 Ho-1 66m 8.90E-09 1.OOE-08 Cm-244 2.90E-12 1.80E-11 W-1 81 2.1 OE-12 2.80E-12 Cm-245 9.50E-10 1.20E-09 W-1 85 0.00E+00 O.OOE+00 Cm-246 1.OOE-12 1.50E-11 W-1 87 3.1 OE-09 3.60E-09 Cm-247 2.20E-09 2.60E-09 Cm-248 6.81 E-09 5.23E-09 I

--- '---'--I Cf-252 6.60E-08 7.20E-08 (1)Data presented in this table are from Reference 9.

A-10

PNPS-ODCM Rev. 9 TABLE= A-li1 INHALATION DOSE= FACTORS FOR ADULT(')

rnrem/pCi Inhaled Ncde Bone I

jULver I ~~Total B

IIih~l Kidney LungGI-LLI H-3 No Data 8.98E-08 8.98E-08 8.98E-08 8.98E-08 j8.98E-08 8.98E-08 Be-i 0 1.98E-04 3.06E-05 J4.96E-06 No Data JNo Data 2.22E-04 1.67E-05 0-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 [4.26E-07 4.26E-07 4.26E-07 N-13 6.27E-09 6.27E-09 j6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 F-i 8 4.71 E-07 No Data 15.1 9E-08 No Data No Data No Data 9.242-09 Na-22 1.30E-05 1.30E-05 1i.30E-05 1.30E-05 11.30E-05 I1.30E-05 1.30E-05 Na-24 1.28E-06 1.28E-06 1i.28E-06 1.28E-06 1i.28E-06 I1.28E-06 1.28E-06 P-32 1.65E-04 9.642-06 I6.26E-06 No Data No Data INo Data 1.08E-05 Ca-41 3.83E-05 No Data 4.1 3E-06 No Data No Data 3.83E-06 2.86E-07 Sc-46 5.512E-05 1.072-04 3.112E-05 No Data I9.99E-05 No Data 3.23E-05 Cr-51 No Data No Data [ 1.25E-~08 7.44E-o9 T 2.~85E-09 1.80E-06 4.15E-07 Mn-54 No Data 4.952-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 Mn-56 No Data 1.552-1 0 2.29E-1 1 No Data 1.63E-1 0 1.18BE-06 2.53E-06 Fe-55 3.07E-06 2.122-06 4.93E-07 No Data No Data 9.01 E-06 -7.54E-07 Fe-59 1.47E-06 3.472-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 Co-57 No Data 8.65E-08 8.39E-08 No Data No Data 4.62E-05 3.93E-06 Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.1 6E-04 1.33E-05 Co-60 No Data .1.44E-06 1.85E-06 1No Data No Data 7.46E-04 3.56E-05 Ni-59 4.062-06 1.46E-06 6.77E-07 No Data No Data 8.20E-06 6.1 1E-07 Ni-63 I5.402-05 3.93E-06 1.81 E-06 No Data No Data 2.23E-05 1.67E-06 Ni-65 j1.92E-1 0 2.62E-1 1 1.1 4E-1 1 No Data No Data -7.OOE-07 1.54E-06 Cu-64 INo Data 1.83E-1 0 7.69E-1 1 No Data 5.78E-1 0 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.OBE-04 6.68E-06 Zn-69m 1I.02E-09 2.45E-09 2.24E-1 0 No Data 1.48E-09 2.38E-06 1.71 E-05 Zn-69 4.23E-12 8.14E-1 2 5.652-1 3 No Data 5.27E-12 1.1 5E-07 2.04E-09 Se-79 JNo Data 3.83E-07 6.09E-08 No Data J5.69E-07 4.47E-05 3.33E-06 Br-82 No Data No Data 1.69E-06 No Data oDaa -No Data 1.30E-06 Br-83 No Data No Data 3.01 E-08 No Data No Data No Data 2.90E-08 Br-84 INo Data No Data 3.91 E-08 No Data No Data No Data 2.05E-13 Br-851 NoDa~ta No Data 1.60E-09 No Data No Data No Data No Data Rb-86 No Data 1.692-05 7.37E-06 No Data No Data No Data 2.08E-06 Rb-87 jNo Data 9.86E-06 3.21 E-06 No Data No Data No Data 2.88E-07 Rb-88 jNo Data 4.842-08 2.41 E-08 No Data No Data No Data 4.1 8E-1 9 Rb-89 INo Data 3.20E-08 2.1 2E-08 No Data No Data No Data 1.1 6E-21 j7.74E-09 Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data I1.75E-04 4.37E-05 Sr-90 3.59E-03 No Data 7.21 E-05 No Data No Data 1.20E-03 9.02E-05 Sr-91 No Data 3.13E-1 0 No Data No Data 4.56E-06 2.39E-05 Sr-92 8.43E-1lo No Data 3.642-1 1 No Data No Data 2.06E-06 5.38E-06 Y-90 2.612E-07 No Data 7.0.1 E-09 No Data No Data 2.1 2E-05 6.32E-05 Y-91 m J3.26E-1 1 No Data 1.27E-12 No Data No Data 2.402-07 1.66E-1 0 Y-91 15.78E-05 No Data 1.55E-06 No Data No Data 2.1 32-04 j4.81 E-05 Y-92 J1.29E-09 No Data 3.77E-1 1 No Data No Data 1.96E-06 9.1 9E-06 1-3 1.1 82-08 No Data 3.26 E-1 0 JNo Data No Data 6.06E-06 5.27 E-05

()Data presented in this Table are from Reference 9.

A-li1

PNPS-ODCM Rev. 9 TABLE A-1I (continued)

INHALATION DOSE FACTORS FOR ADULT) mrem/pCi Inhaled Nuclide I

j Bone I

Liver Total TBodid 1 I Kidney I

lLun I

GI-LLI Zr-93 5.22E-05 2.92E-06 1.37E-06 No Data 1.11 E-05 2.13E-05 1.51 E-06 Zr-95 1.34E-05 4.30E-06 2.91 E-06 No Data 6.77E-06 2.21 E-04 1.88E-05 Zr-97 1.21 E-08 2.45E-09 1.1 3E-09 No Data 3.71 E-09 9.84E-06 6.54E-05 Nb-93m 3.1 OE-05 1.01 E-05 2.49E-06 No Data 1.16E-05 3. 1 E-05 2.38E-06 Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31 E-05 1.30E-05 Nb-97 2.78E-1 1 7.03E-12 2.56E-1 2 No Data 8.1 BE-1 2 3.00E-07 3.02E-08 Mo-93 No Data 1.17E-06 3.17E-08 No Data 3.55E-07 5.11E-05 3.79E-06 Mo-99 No Data 1.51 E-08 2.87E-09 No Data 3.64E-08 1.1 4E-05 3.1 OE-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 Tc-99 3.13E-08 4.64E-08 1.25E-08 No Data 5.85E-07 1.01 E-04 7.54E-06 Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21 Ru-1 03 1.91 E-07 No Data 8.23E-08 No Data 7.29E-07 6.31 E-05 1.38E-05 Ru-105 9.88E-11 No Data 3.89E-11 No Data 1.27E-10 1.37E-06 6.02E-06 Ru-1 06 8.64E-06 No Data 1.09E-06 No Data 1.67E-05 1.17E-03 1.14E-04 Rh-105 9.24E-10 6.73E-10 4.43E-10 No Data 2.86E-09 2.41 E-06 1.09E-05 Pd-107 No Data 8.27E-08 5.87E-09 No Data 6.57E-07 9.47E-06 7.06E-07 Pd-109 No Data 4.63E-10 1.16E-10 No Data 2.35E-09 1.85E-06 1.52E-05 Ag-11 Om 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 Ag-111 4.25E-08 1.78E-08 8.87E-09 No Data 5.74E-08 2.33E-05 2.79E-05 Cd-i1 3m No Data 1.54E-04 4.97E-06 No Data 1.71 E-04 2.08E-04 1.59E-05 Cd-i1 5m No Data 2.46E-05 7.95E-07 No Data 1.98E-05 1.76E-04 4.80E-05 Sn-123 3.02E-05 6.67E-07 9.82E-07 5.67E-07 No Data 2.88E-04 3.92E-05 Sn-125 1.16E-06 3.1 2E-08 7.03E-08 2.59E-08 No Data 7.37E-05 6.81 E-05 Sn-126 1.58E-04 4.18E-06 6.OOE-06 1.23E-06 No Data 1.17E-03 1.59E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 No Data 3.1OE-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 No Data 2.18E-04 1.26E-05 Sb-126 4.50E-07 9.13E-09 1.62E-07 2.75E-09 No Data 9.57E-05 6.01 E-05 Sb-127 1 3.30E-08 7.22E-10 1.27E-08 3.97E-10 No Data 2.05E-05 3.77E-05 Te-125m I 4.27E-07 1.98E-07 5.84E-08 i1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1i.58E-06 7.21 E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 j 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129mr 1.22E-06 5.84E-07 l1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-1 2 1.55E-1 2 4.87E-1 2 2.34E-1 1 2.42E-07 1.96E-08 Te-131m i 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 Te-133m 7.24E-12 5.40E-12 4.17E-12 6.27E-12 3.74E-1 1 5.51 E-07 7.65E-09 Te-1 34 3.84E-1 2 3.22E-12 11.57E-1 2 3.44E-1 2 2.18E-1 1 4.34E-07 2.97E-1 1 1-129 2.48E-06 2.11 E-06 6.91 E-06 5.54E-03 4.53E-06 l No Data 2.22E-07 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61 E-06 No Data 9.61 E-07 1-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 1-132 [1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 1-133 1 .08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11 E-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-1 0 1-135 j 3.35E-07 8.73E-07 , 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 1)Data presented in this Table are from Reference 9.

A-12

PNPS-ODCM Rev. 9 TABLE A-11 (continued)

INHALATION DOSE FACTORS FOR ADULT(')

mrem/pCi Inhaled Total Thri Kdn Nuclide l Bone l Liver BThid l Kidne Ll GI-LLI Cs-134m 1.59E-08 3.20E-08 1.72E-08 No Data 1.83E-08 2.9- 7.92E-09 Cs-134 4.66E-05 1.06E-04 9.1 0E-05 No Data 3.59E-05 1 .22E-05 1.30E-06 Cs-1 35 1.46E-05 1.29E-05 5.99E-06 No Data 5.11 E-06 1.57E-06 2.11 E-07 Cs-1 36 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cs-1 37 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 No Data 6.OOE-08 6.07E-09 2.33E-13 Cs-139 2.56E-08 3.63E-08 1.39E-08 No Data 3.05E-08 2.84E-09 5.49E-31 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21 E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41 E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Ba-1 42 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05 La-141 5.34E-1 0 1.66E-10 2.71 E-11 No Data No Data 1.35E-06 _7.31 E-06 La-142 8.54E-11 3.88E-11 9.65E-12 No Data No Data 7.91 E-07 2.64E-07 Ce-1 41 2.49E-06 1.69E-06 1.91 E-07 No Data 7.83E-07 4.52E-05 1.50E-05 Ce-1 43 2.33E-08 1.72E-08 1.91 E-09 No Data 7.60E-09 9.97E-06 2.83E-05 Ce-1 44 4.29E-04 1.79E-04 2.30E-05 No Data 1.06E-04 9.72E-04 1.02E-04 Pr-143 I1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51 E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91 E-13 No Data 8.81 E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 No Data 4.45E-07 2.76E-05 2.16E-05 Pm-147 8.37E-05 7.87E-06 3.19E-06 No Data 1.49E-05 6.60E-05 5.54E-06 Pm-148m 9.82E-06 2.54E-06 1.94E-06 No Data 3.85E-06 2.14E-04 4.1 8E-05 Pm-1 48 3.84E-07 6.37E-08 3.20E-08 No Data 1.20E-07 3.91 E-05 5.80E-05 Pm-1 49 I 3.44E-08 4.87E-09 1.99E-09 No Data 9.19E-09 7.21 E-06 2.50E-05 Pm-151 8.50E-09 1.42E-09 7.21 E-1 0 No Data 2.55E-09 3.94E-06 2.OOE-05 Sm-1 51 8.59E-05 1.48E-05 3.55E-06 No Data I 1.66E-05 4.45E-05 3.25E-06 Sm-153 1.70E-08 1.42E-08 1.04E-09 No Data 4.59E-09 4.14E-06 1.58E-05 Eu-1 52 2.38E-04 5.41 E-05 4.76E-05 No Data 3.35E-04 3.43E-04 1.59E-05 Eu-154 7.40E-04 9.10E-05 6.48E-05 No Data 4.36E-04 5.84E-04 3.40E-05 Eu-1 55 1.01 E-04 1.43E-05 9.21 E-06 No Data 6.59E-05 9.46E-05 5.95E-06 Eu-1 56 1.93E-06 1.48E-06 2.40E-07 No Data 9.95E-07 8.56E-05 4.50E-05 Tb-1 60 2.21 E-05 No Data 2.75E-06 No Data 9.1 OE-06 1.92E-04 2.68E-05 Ho-1 66m 3.37E-04 1.05E-04 8.OOE-05 No Data 1.57E-04 3.94E-04 1.59E-05 W-181 6.23E-09 2.03E-09 2.17E-10 No Data No Data 1.71 E-06 2.53E-07 W-185 1.95E-07 6.47E-08 6.81 E-09 No Data No Data 5.57E-05 1.07E-05 W-187 1i.06E-09 8.85E-10 3.1 OE-10 No Data No Data 3.63E-06 1.94E-05 Pb-21 0 2.64E-02 6.73E-03 8.37E-04 No Data 2.12E-02 2.62E-02 1.51 E-06 Bi-21 0 2.31 E-07 1.59E-06 1.32E-07 No Data 1.92E-05 1.11 E-03 2.95E-05 Po-21 0 3.97E-04 8.60E-04 9.58E-05 No Data 2.95E-03 3.14E-02 4.19E-05 Ra-223 1.80E-04 2.77E-07 3.60E-05 No Data 7.85E-06 2.55E-02 2.84E-04 Ra-224 1.98E-05 4.78E-08 3.96E-06 No Data 1.35E-06 8.77E-03 3.01 E-04 Ra-225 3.OOE-04 3.56E-07 5.99E-05 No Data 1.01 E-05 2.92E-02 2.71 E-04 Ra-226 i125E-01 2.39E-06 9.14E-02 No Data 6.77E-05 1.17E-01i 2.94E-04 Ra-228 4.41 E-02 1.23E-06 4.78E-02 No Data 3.48E-05 11.61 E-01 5.OOE-05 Data presented in this Table are from Reference 9.

A-13

PNPS-ODCM Rev. 9 TABLE A-11 (continued)

INHALATION DOSE FACTORS FOR ADULT(')

mremlpCi Inhaled I I Total Nuclide i Bone _ Liver Body Throid lKidney Lung Gl-LLI Ac-225 4.23E-04 5.82E-04 2.84E-05 No Data 6.63E-05 2.21 E-02 2.52E-04 Ac-227 2.30E+00 3.05E-01 1.36E-01 No Data 9.82E-02 2.41 E-01 5.08E-05 Th-227 7 2.17E-04 3.92E-06 6.25E-06 No Data 2.22E-05 3.77E-02 3.34E-04 Th-228 2.OOE-01 3.39E-03 6.77E-03 No Data 1.89E-02 1.01 E+00 3.49E-04 Th-229 1.51 E+01 4.34E-01 2.51 E-01 No Data 2.13E+00 3.62E+00 4.83E-05 Th-230 2.29E+00 1.31 E-01 6.36E-02 No Data 6.40E-01 6.21 E-01 3.73E-05 Th-232 2.56E+00 1.12E-01 9.04E-04 No Data 5.47E-01 5.96E-01 3.17E-05 Th-234 1.63E-06 9.56E-08 4.70E-08 No Data 5.41 E-07 1.89E-04 7.03E-05 Pa-231 5.08E+00 1.91 E-01 1.98E-01 No Data 1.07E+00 5.75E-02 4.44E-05 Pa-233 1.21 E-06 2.42E-07 2.09E-07 No Data 9.15E-07 3.52E-05 1.02E-05 U-232 5.14E-02 No Data 3.66E-03 No Data 5.56E-03 2.22E-01 4.21 E-05 U-233 11.09E-02 No Data 6.60E-04 No Data 2.54E-03 5.32E-02 3.89E-05 U-234 l1.04E-02 No Data 6.46E-04 No Data 2.49E-03 5.22E-02 3.81 E-05 U-235 1.OOE-02 No Data 6.07E-04 No Data 2.34E-03 4.90E-02 4.84E-05 U-236 1.O0E-02 No Data 6.20E-04 No Data 2.39E-03 5.OOE-02 3.57E-05 U-237 3.67E-08 No Data 9.77E-09 No Data 1.51 E-07 1.02E-05 1.20E-05 U-238 9.58E-03 No Data 5.67E-04 No Data 2.1 8E-03 4.58E-02 3.41 E-05 Np-237 1.56E+00 1.OOE+00 6.87E-02 No Data 5.1 OE-01 5.22E-02 4.92E-05 Np-238 2.96E-07 7.20E-08 4.61 E-09 No Data 2.72E-08 1.02E-05 2.13E-05 Np-239 1 2.87E-08 2.54E-08 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-05 Pu-238 1.43E+00 9.71 E-01 6.90E-02 No Data 2.96E-01 1.82E-01 4.52E-05 Pu-239 1.66E+00 1.07E+00 7.75E-02 No Data 3.30E-01 1.72E-01 4.13E-05 Pu-240 1.65E+00 1.07E+00 7.73E-02 No Data 3.29E-01 1.72E-01 4.21 E-05 Pu-241 3.42E-02 8.69E-03 1.29E-03 No Data 5.93E-03 1.52E-04 8.65E-07 Pu-242 1.53E+00 1.03E+00 7.46E-02 No Data 3.17E-01 1.65E-01 4.05E-05 Pu-244 1.79E+00 1.1 8E+00 8.54E-02 No Data 3.64E-01 1.89E-01 6.03E-05 Am-241 1.68E+O0 1.1 3E+00 6.71 E-02 No Data 5.04E-01 6.06E-02 4.60E-05 Am-242m 1.70E+00 1.06E+00 6.73E-02 No Data 5.01 E-01 2.44E-02 5.79E-05 Am-243 1.68E+00 1.10E+00 6.57E-02 No Data 4.95E-01 5.75E-02 5.40E-05 Cm-242 2.22E-02 1.77E-02 9.84E-04 No Data 4.48E-03 3.92E-02 4.91 E-05 Cm-243 1.1 OE+00 7.61 E-01 4.61 E-02 No Data 2.15E-01 6.31 E-02 4.84E-05 Cm-244 8.37E-01 5.88E-01 3.51 E-02 No Data 1 .64E-01 6.06E-02 4.68E-05 Cm-245 1.74E+00 1.14E+00 7.14E-02 No Data 3.33E-01 5.85E-02 4.36E-05 Cm-246 1.73E+00 1.14E+00 7.13E-02 No Data 3.33E-01 5.96E-02 4.29E-05 Cm-247 1.68E+00 1.12E+00 7.03E-02 No Data 3.28E-01 5.85E-02 5.63E-05 Cm-248 1.40E+01 9.26E+00 I 5.79E-01 No Data 1 2.70E+00 4.82E-01 9.09E-04 Cf-252 5.43E-01_- No Data I 2.33E-02 I No Data I No Data I 1.99E-01 1 1.78E-04 (1)Data presented in this Table are from Reference 9.

A-14

PNPS-ODCM Rev. 9 TABLE A-1 2 INHALATION DOSE FACTORS FOR TEEN(')

mrem/pCi Inhaled I Totaali Nuclide l Bone l Liver Body Thyroid Kidney -Lung_ GI-LLI H-3 No Data 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 j 9.06E-08 Be-10 2.78E-04 4.33E-05 _ 7.09E-06 No Data No Data 3.84E-04 1.77E-05 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 N-13 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 F-18 6.52E-07 No Data 7.1OE-08 No Data I No Data No Data 3.89E-08 Na-22 1.76E-05 1.76E-05 1.76E-05 1.76E-05 _ 1.76E-05 1.76E-05 1.76E-05 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 No Data No Data No Data 1.16E-05 Ca-41 4.05E-05 No Data 4.38E-06 NoaData NData 1.01 E-01 3.03E-07 Sc-46 7.24E-05 1.41 E-04 4.1 BE-05 No Data I 1.35E-04 INo Data 2.98E-05 Cr-51 No Data No Data 1.69E-OB 9.37E-09 ! 3.84E-09 2.62E-06 3.75E-07 Mn-54 No Data 6.39E-06_ 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 Mn-56 No Data 2.12E-10 3.15E-11 No Data 2.24E-10 1.90E-06 7.1 8E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91 E-04 2.23E-05 Co-57 No Data 1.18E-07 1.15E-07 No Data No Data . 7.33E-05 3.93E-06 Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.1 9E-05 Co-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05 Ni-59 5.44E-06 2.02E-06 9.24E-07 No Data No Data 1.41 E-05 6.48E-07 Ni-63 7.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 No Data No Data 1.17E-06 4.59E-06 Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01 E-1O0 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1 .55E-04 5.83E-06 Zn-69m 1.44E-09 3.39E-09 3.11E-10 No Data 2.06E-09 3.92E-06 2.14E-05 Zn-69 6.04E-1 2 1.1 5E-1 1 8.07E-13 No Data 7.53E-1 2 i 1.98E-07 3.56E-08 Se-79 No Data 5.43E-07 1 8.71 E-08 No Data 8.13E-07 17.71 E-05 3.53E-06 Br-82 No Data No Data ; 2.28E-06 No Data No Data No Data No Data Br-83 i No Data No Data i 4.30E-08 No Data No Data j No Data No Data Br-84 i No Data No Data 5.41 E-08 No Data NO Data i No Data No Data Br-85 No Data No Data 2.29E-09 No Data No Data No Data No Data Rb-86 j No Data 2.38E-05 1i.05E-05 No Data No Data No Data 2.21 E-06 Rb-87 No Data 1.40E-05 4.58E-06 No Data No Data l No Data 3.05E-07 Rb-88 l No Data 6.82E-08 3.40E-08 No Data No Data No Data 3.65E-15 Rb-89 j No Data 4.40E-08 2.91 E-08 No Data No Data I No Data 4.22E-17 Sr-89 _ 5.43E-05 No Data 1 .56E-06 No Data No Data 3.02E-04 4.64E-05 Sr-90 i 4.14E-03 No Data 8.33E-05 No Data No Data i2.06E-03 9.56E-05 Sr-91 I 1.1OE-08 No Data 4.39E-10 No Data No Data l 7.59E-06 3.24E-05 Sr-92 l 1.19E-09 No Data l5.08E-11 No Data No Data j 3.43E-06 1.49E-05 Y-90 3.73E-07 No Data 1.OOE-08 No Data No Data 3.66E-05 l6.99E-05 Y-91m 4.63E-11_ No Data 1.77E-12 No Data No Data j 4.OOE-07 . 3.77E-09 Y-91 8.26E-05 No Data 2.21 E-06 No Data NoData 3.67E-04 5.11E-05 Y-92 I1.84E-O9 _No Data 5.36E-11 INo Data INo Data I3.35E-06 12.06E-05 Y-93 1.69E-08 No Data 4.65E-10 No Data No Data 1.04E-05 l7.24E-05 (1)Data presented in this Table are from Reference 9.

A-15

PNPS-ODCM Rev. 9 TABLE A-12 (continued)

INHALATION DOSE FACTORS FOR TEENW) mremlpCi Inhaled Nuclide Bone l

l Liver i T~~otal Body yroid Kidney 1 Lung= l Gl-LLI Zr-93 i 6.83E-05 3.38E-06 I1.84E-06 No Data 1.16E-05 3.67E-05 1.60E-06 Zr-95 I1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 Zr-97 I 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05 Nb-93m : 4.14E-05 1.36E-05 3.41 E-06 No Data 1.59E-05 5.36E-05 2.52E-06 Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05 Nb-97 3.92E-1 1 9.72E-12 3.55E-12 No Data 1.14E-11 4.91 E-07 2.71 E-07 Mo-93 No Data 1.66E-06 4.52E-08 No Data 5.06E-07 8.81 E-05 3.99E-06 Mo-99 No Data 2.11 E-08 4.03E-09 No Data 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-1 3 4.83E-1 3 6.24E-1 2 No Data 7.20E-1 2 1.44E-07 7.66E-07 Tc-99 4.48E-08 6.58E-08 1.79E-08 No Data 8.35E-07 1.74E-04 7.99E-06 Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 No Data 5.42E-11 No Data 1.76E-10 2.27E-06 1.1 3E-05 Ru-106 1.23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01 E-03 1.20E-04 Rh-105 1.32E-09 9.48E-10 6.24E-10 No Data 4.04E-09 4.09E-06 1.23E-05 Pd-107 No Data 1.17E-07 8.39E-09 No Data 9.39E-07 1.63E-05 7.49E-07 Pd-1 09 No Data 6.56E-1 0 1.66E-10 No Data 3.36E-09 3.19E-06 1.96E-05 Aq-1 1Om 1.73E-06 1.64E-06 J 9.99E-07 No Data 3.13E-06 8.44E-04 3.41 E-05 Ag-111 6.07E-08 2.52E-08 1.26E-08 No Data 8.17E-08 4.00E-05 3.00E-05 Cd-113m No Data 2.17E-04 7.1 OE-06 No Data 2.43E-04 3.59E-04 1.68E-05 Cd-115m No Data 3.48E-05 1.14E-06 No Data 2.82E-05 3.03E-04 5.1 OE-05 Sn-1 23 4.31 E-05 9.44E-07 1.40E-06 7.55E-07 No Data 4.96E-04 4.16E-05 Sn-125 I 1.66E-06 4.42E-08 9.99E-08 3.45E-08 No Data 1.26E-04 7.29E-05 Sn-126 2.18E-04 5.39E-06 8.24E-06 1.42E-06 No Data 1.72E-03 1.68E-05 Sb-124 5.38E-06 9.92E-08 2.1 OE-06 1.22E-08 No Data 4.81 E-04 4.98E-05 Sb-1 25 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 No Data 3.42E-04 1.24E-05 Sb-1 26 6.19E-07 1.27E-08 2.23E-07 3.50E-09 No Data 1.55E-04 6.01 E-05 Sb-127 4.64E-08 9.92E-10 1.75E-08 5.21 E-10 No Data 3.31 E-05 3.94E-05 Te-125m I 6.1OE-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06 Te-127rn 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 I 2.51 E-10 1.14E-10 5.52E-11 1.77E-10 9.1 OE-10 1.40E-06 1.01 E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-1 1 14.12E-07 2.02E-07 Te-1 31 m I1.23E-08 7.51 E-09 5.03E-09 19.06E-09 5.49E-08 1 2.97E-05 7.76E-05 Te-1 31 1.97E-12 1.04E-12 6.30E-1 3 1.55E-12 7.72E-1 2 2.92E-07 1.89E-09 Te-1 32 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 1 5.61 E-05 5.79E-05 Te-133m 1.01E-11 7.33E-12 5.71 E-12 l 8.18E-12 5.07E-11 8.71 E-07 1.23E-07 Te-134 5.31E-12 4.35E-12 3.64E-12 14.46E-12 2.91E-11 1 6.75E-07 1.37E-09 1-129 3.53E-06 2.94E-06 4.90E-06 13.66E-03 5.26E-06 i No Data 2.29E-07 1-130 i 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 j No Data 1.14E-06 1-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 j No Data 8.11E-07 1-132 f 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 j No Data 1.59E-07 1-133 11 .52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 I No Data 1.29E-06 1-134 11.11 E-07 2.90E-07 1 .05E-07 4.94E-06 4.58E-07 l NO Data 2.55E-09 1-135 I 4.62E-07 1.18E-06 1 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07 (1)Data presented in this Table are from Reference 9.

A-1 6

PNPS-ODCM Rev. 9 TABLE A-12 (continued)

INHALATION DOSE FACTORS FOR TEEN(')

mrem/pCi Inhaled Nuclide Cs-134m BoeBLieotal Bone 2.20E-08 Liver 4.35E-08

_Total BodyI_

2.35E-08 Thyroid No Data I Kidney

-Th_____

2.54E-08 I _o___d_

Lung 4.56E-09 l GI-LLI 2.02E-08 Cs-1 34 6.28E-05 1.41 E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 Cs-135 2.08E-05 1.82E-05 4.47E-06 No Data 7.30E-06 2.70E-06 2.23E-07 Cs-136 6.44E-06 2.42E-05 1.71 E-05 No Data 1.38E-05 2.22E-06 _1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51 E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-11 Cs-139 3.65E-08 5.12E-08 1.97E-08 No Data 4.34E-08 4.86E-09 1.66E-23 Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.11 E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 No Data 1.23E-14 4.11 E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 La-1 40 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05 La-1 41 7.63E-10 2.35E-1 0 3.87E-11 No Data No Data 2.31 E-06 1.54E-05 La-1 42 1.20E-1 0 5.31 E-11 1.32E-1 1 No Data No Data 1.27E-06 1.50E-06 Ce-1 41 _ 3.55E-06 2.37E-06 2.71 E-07 No Data 1.11 E-06 7.67E-05 1.58E-05 Ce-1 43 3.32E-08 2.42E-08 2.70E-09 No Data 1.08E-08 1.63E-05 3.19E-05 Ce-1 44 6.11 E-04 2.53E-04 3.28E-05 No Data 1.51 E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 No Data 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 No Data 6.28E-07 4.65E-05 2.28E-05 Pm-147 1.1 5E-04 1.1 OE-05 4.50E-06 No Data 2.1 OE-05 1.1 4E-04 5.87E-06 Pm- 148m 1.32E-05 3.35E-06 2.62E-06 No Data 5.07E-06 3.20E-04 4.1OE-05 Pm- 148 5.44E-07 8.88E-08 4.48E-08 No Data 1.60E-07 6.52E-05 6.14E-05 Pm-149 1 4.91 E-08 6.89E-09 2.84E-09 No Data 1.31 E-08 1.24E-05 2.79E-05 Pm-151 1.20E-08 1.99E-09 1.01E-09 No Data 3.57E-09 6.56E-06 2.27E-05 Sm-1 51 j 1.07E-04 2.1OE-05 4.86E-06 No Data 2.27E-05 7.68E-05 3.53E-06 Sm-153 1 2.43E-08 2.01E-08 1.47E-09 No Data 6.56E-09 7.11E-06 1.77E-05 Eu-1 52 I 2.96E-04 7.19E-05 6.30E-05 I No Data 3.34E-04 5.01E-04 1.35E-05 Eu-i 54 9.432-04 1.23E-04 8.60E-05 No Data 5.44E-04 9.12E-04 3.34E-05 Eu-1 55 12.00E-04 1.96E-05 1.21E-05 No Data 7.65E-05 1.51 2-03 5.97E-05 Eu-1 56 12.70E-06 2.03E-06 3.30E-07 No Data 1.36E-06 1.37E-04 4.56E-05 Tb-1 60 3.04E-05 No Data 3.79E-06 No Data 1.20E-05 2.97E-04 2.60E-05 Ho-1 66m 1 4.40E-04 1.36E-04 9.87E-05 No Data 2.00E-04 6.24E-04 1.68E-05 W-181 I 8.90E-09 2.88E-09 3.01 E-10 No Data No Data 2.95E-06 2.69E-07 W-185 i2.78-07 9.172-08 9.73E-09 No Data No Data 9.60E-05 1.14E-05 W-1 87 1.50E-09 1.22E-09 4.29E-10 No Data No Data I 5.92E-06 2.21E-05 Pb-21 0 3.09E-02 8.28E-03 .1.07E-03 No Data 2.95E-02 j 4.52E-02 1.60E-06 Bi-210 3.30E-07 2.26E-06 1.89E-07 No Data 2.74E-05 1.91E-03 3.19E-05 Po-21 0 5.68E-04 1.22E-03 1.37E-04 No Data 4.21E-03 5.41E-02 1 4.45E-05 Ra-223 2.57E-04 3.93E-07 5.14E-05 No Data 1.12E-05 4.39E-02 3.04E-04 Ra-224 2.83E-05 6.77E-08 5.65E-06 No Data 1.93E-06 1.51 E-02 3.29E-04 Ra-225 4.28E-04 5.04E-07 8.56E-05 No Data 1.44E-05 5.04E-02 2.89E-04 Ra-226 1.33E-01 3.38E-06 9.87E-02 No Data 9.67E-05 2.02E-01 3.11E-04 Ra-228 5.34E-02 1.74E-06 I 5.88E-02 No Data I 4.97E-05 2.78E-01 5.30E-05 1)Data presented in this Table are from Reference 9.

A-17

PNPS-ODCM Rev. 9 TABLE A-12 (continued)

INHALATION DOSE FACTORS FOR TEEN(')

mrem/pCi Inhaled ITotal Nuclide Bone Liver l Body Thyroid I Kidney Lung, GI-LLI Ac-225 6.04E-04 8.25E-04 4.06E-05 No Data _ 9.47E-05 l 3.81 E-02 [2.70E-04 Ac-227 2.49E+00 3.69E-01 1.48E-01 No Data 1.07E-01 4.16E-01 5.38E-05 Th-227 3.09E-04 5.56E-06 8.93E-06 No Data 3.18E-05 6.50E-02 3.57E-04 Th-228 2.60E-01 4.37E-03 8.78E-03 No Data 2.45E-02 1.69E+00 3.70E-04 Th-229 1.54E+01 4.44E-01 2.56E-01 No Data 2.18E+00 5.24E+00 5.12E-05 Th-230 I 2.34E+00 1.34E-01 6.49E-02 No Data 6.55E-01 8.98E-01 3.95E-05 Th-232 1 2.61 E+00 1.14E-01 9.21 E-04 No Data 5.60E-01 8.60E-01 3.36E-05 Th-234 2.32E-06 1.35E-07 6.71 E-08 No Data 7.73E-07 3.26E-04 7.49E-05 Pa-231 5.32E+00 2.OOE-01 2.07E-01 No Data 1.12E+00 9.91 E-02 4.71 E-05 Pa-233 1.68E-06 3.24E-07 2.89E-07 No Data 1.22E-06 5.39E-05 1.00E-05 U-232 7.31 E-02 No Data 5.23E-03 No Data 7.94E-03 3.84E-01 4.46E-05 U-233 1.55E-02 No Data 9.42E-04 No Data 3.63E-03 9.18E-02 4.12E-05 U-234 1.48E-02 No Data 9.23E-04 No Data 3.55E-03 8.99E-02 4.04E-05 U-235 1.42E-02 No Data 8.67E-04 No Data 3.34E-03 8.44E-02 5.13E-05 U-236 ! 1.42E-02 No Data 8.86E-04 No Data 3.41 E-03 8.62E-02 3.79E-05 U-237 i 5.25E-08 No Data 1.40E-08 No Data 2.16E-07 1.76E-05 1.29E-05 U-238 11.36E-02 No Data 8.10E-04 No Data 3.1 2E-03 7.89E-02 3.62E-05 Np-237 l.1.64E+00 1.06E+00 7.21 E-02 No Data 5.35E-01 8.99E-02 5.22E-05 Np-238 4.23E-07 1.02E-07 6.59E-09 No Data 3.88E-08 1.75E-05 2.38E-05 Np-239 4.23E-08 3.60E-08 2.21 E-09 No Data 1.25E-08 8.11 E-06 1.65E-05 Pu-238 1.50E+00 1.03E+00 7.22E-02 No Data 3.1 OE-01 3.1 2E-01 4.79E-05 Pu-239 1.73E+00 1.12E+00 8.05E-02 J No Data 3.44E-01 2.93E-01 4.37E-05 Pu-240 1.72E+00 1.1 2E+00 8.04E-02 No Data 3.43E-01 2.93E-01 4.46E-05 Pu-241 3.74E-02 9.56E-03 1.40E-03 No Data l 6.47E-03 2.60E-04 9.17E-07 Pu-242 1.60E+00 1.08E+00 7.75E-02 J No Data 3.31 E-01 2.82E-01 4.29E-05 Pu-244 1.87E+00 1.24E+00 8.88E-02 No Data 3.79E-01 3.23E-01 6.39E-05 Am-241 1.77E+00 1.20E+00 7.1OE-02 No Data 5.32E-01 1.05E-01 4.88E-05 Am-242m 1.79E+00 1.13E+00 7.15E-02 No Data 5.30E-01 4.21 E-02 6.14E-05 Am-243 1.77E+00 1.1 7E+00 6.95E-02 I No Data 5.21 E-01 9.91 E-02 5.72E-05 Cm-242 3.17E-02 2.51 E-02 1.41 E-03 i No Data 6.40E-03 6.76E-02 5.21 E-05 Cm-243 1.19E+00 8.30E-01 5.00E-02 No Data 2.34E-01 1.09E-01 5.13E-05 Cm-244 9.19E-01 6.53E-01 3.88E-02 No Data 1.81 E-01 1.05E-01 4.96E-05 Cm-245 I1.83E+00 1.22E+00 7.53E-02 No Data 3.522-01 1.1.01E-01 4.63E-05 Cm-246 1.1.81E+00 1.22E+00 7.52E-02 No Data 3.51E-01 11.03E-01 4.54E-05 Cm-247 1.77E+00 1.19E+00 7.41E-02 No Data j 3.462-01 1.01E-01 5.97E-05 Cm-248 1.47E+01 9.83E+00 6.11E-01 No Data l 2.85E+00 8.32E-01 9.63E-04 Cf-252 I 7.16E-01 No Data 3.07E-02 - No Data No Data i 3.43E-01 1 1.89E-04 (1)Data presented in this Table are from Reference 9.

A-18

PNPS-ODCM Rev. 9 TABLE A-13 INHALATION DOSE FACTORS FOR CHILD"'

mrem/pCi Inhaled I lTotal Nuclide Bone Liver Thyo Kidney L G H-3 No Data 1.73E-07 1.73E-07 1.73E-07 l 1.73E-07 1.73E-07 1 1.73E-07 Be-10 8.43E-04 9.83E-05 2.12E-05 No Data j No Data 7.41 E-04 1.72E-05 C-14 9.70E-06 1.82E-06 1.82E-06_ 1.82E-06 1 .82E-06 1.82E-06 1.82E-06 N-13 2.33E-08 l 2.33E-08 2.33E-08 2.33E-08 ; 2.33E-08 2.33E-08 2.33E-08 F-18 1.88E-06 No Data 1.85E-07 No Data i No Data No Data 3.37E-07 Na-22 4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 ]4.41 E-05 4.41 E-05 4.41 E-05 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 j 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 No Data l No Data No Data 1.14E-05 Ca-41 7.06E-05 No Data 7.70E-06 No Data I No Data 7.21 E-02 I 2.94E-07 Sc-46 1.97E-04 2.70E-04 1.04E-04 No Data 2.39E-04 No Data 2.45E-05 Cr-51 No Data No Data 4.17E-08 2.31 E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 No Data 1.1 6E-05 2.57E-06 No Data 2.71 E-06 4.26E-04 6.19E-06 Mn-56 No Data 4.48E-10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51 E-06 No Data No Data 3.43E-04 1.91 E-05 Co-57 No Data 2.44E-07 2.88E-07 No Data No Data 1.37E-04 3.58E-06 Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06 Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91 E-03 2.60E-05 Ni-59 1.66E-05 4.67E-06 2.83E-06 No Data No Data 2.73E-05 6.29E-07 Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 1.71 E-06 Ni-65 8.08E-1 0 7.99E-11 4.44E-1 1 No Data l No Data 2.21 E-06 2.27E-05 Cu-64 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.1 5E-05 3.06E-05 1.90E-05 No Data I 1.93E-05 2.69E-04 4.41 E-06 Zn-69m 4.26E-09 7.28E-09 8.59E-10 No Data T 4.22E-09 7.36E-06 2.71E-05 Zn-69 1.81 E-11 2.61 E-11 2.41 E-12 No Data I 1.58E-11 3.84E-07 2.75E-06 Se-79 No Data 1.23E-06 2.60E-07 No Data 1.71 E-06 1.49E-04 3.43E-06 Br-82 No Data No Data 5.662-06 No Data No Data No Data No Data Br-83 No Data No Data 1.28E-07 No Data No Data No Data j No Data Br-84 No Data No Data 1.48E-07 No Data No Data No Data l No Data Br-85 No Data No Data 6.84E-09 No Data No Data No Data No Data Rb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 Rb-87 No Data 3.16E-05 1.37E-05 No Data No Data No Data 2.96E-07 Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 Rb-89 No Data 9.33E-08 7.83E-08 No Data No Data No Data 5.1 1E-10 Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 1.04E-02 No Data 2.07E-04 No Data No Data 3.99E-03 9.28E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 j 6.55E-05 Y-90 1.11 E-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 Y-91 m i.37E-10 No Data 4.98E-12 No Data No Data 7.60E-07 i 4.64E-07 Y-91 2.47E-04 No Data 6.59E-06 No Data No Data 7.1 OE-04 j 4.97E-05 Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 16.46E-05 Y-93 5.04E-08 j No Data 1.38E-09 No Data No Data 2.01 E-05 1 1.05E-04 (1)Data presented in this Table are from Reference 9.

A-i 9

PNPS-ODCM Rev. 9 TABLE A-13 (continued)

INHALATION DOSE FACTORS FOR CHILD"')

mrem/pCi Inhaled I I Total Nuclide l Bone Liver Body Thyroid Kidne Lung GI-LLI Zr-93 2.07E-04 7.80E-06 5.55E-06 No Data 3.OOE-05 7.10E-05 1.47E-06 Zr-95 5.13E-05 1.13E-05 1.00E-05 No Data 1.61 E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05 Nb-93m 1.27E-04 3.17E-05 1.04E-05 No Data 3.44E-05 1.04E-04 2.45E-06 Nb-95 6.35E-06 2.48E-06 1.77E-06 No Data 2.33E-06 1.66E-04 1.00E-05 Nb-97 1.16E-10 2.08E-11 9.74E-12 No Data 1 2.31 E-11 9.23E-07 7.52E-06 Mo-93 No Data 3.76E-06 1.35E-07 No Data 11.06E-06 1.70E-04 3.78E-06 Mo-99 No Data 4.66E-08 1.15E-08 No Data ! 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81 E-13 9.41E-13 1.56E-11 No Data 1.37E-11 2.57E-07 _ 1.30E-06 Tc-99 1.34E-07 1.49E-07 5.35E-08 No Data I 1.75E-06 3.37E-04 7.75E-06 Tc-101 2.19E-14 2.30E-14 2.91 E-13 No Data 13.92E-13 1.58E-07 4.41 E-09 Ru-103 7.55E-07 No Data 2.90E-07 No Data I 1.90E-06 1.79E-04 1.21 E-05 Ru-105 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04 Rh-105 3.91 E-09 2.1 OE-09 1.79E-09 No Data 8.39E-09 7.82E-06 1.33E-05 Pd-107 No Data 2.65E-07 2.51 E-08 No Data 1.97E-06 3.16E-05 7.26E-07 Pd-109 No Data 1.48E-09 4.95E-10 No Data 7.06E-09 6.16E-06 2.59E-05 A:-11 Om 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71 E-05 A-1 1 1.81 E-07 5.68E-08 3.75E-08 No Data 1.71 E-07 7.73E-05 2.98E-05 Cd-i 13m No Data 4.93E-04 2.12E-05 No Data I 5.13E-04 6.94E-04 1.63E-05 Cd-1 15m No Data 7.88E-05 3.39E-06 No Data I 5.93E-05 5.86E-04 4.97E-05 Sn-123 1.29E-04 2.14E-06 4.19E-06 2.27E-06 1No Data 9.59E-04 4.05E-05 Sn-125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 No Data 2.43E-04 l 7.17E-05 Sn-126 6.23E-04 1.04E-05 2.36E-05 2.84E-06 No Data 3.02E-03 1.63E-05 Sb-1 24 1.55E-05 2.00E-07 5.41 E-06 3.41 E-08 No Data 8.76E-04 _ 4.43E-05 Sb-125 2.66E-05 12.05E-07 5.59E-06 2.46E-08 No Data 6.27E-04 1.09E-05 Sb-126 1.72E-06 12.62E-08 6.16E-07 1.OOE-08 No Data 2.86E-04 5.67E-05 Sb-127 1.36E-07 2.09E-09 4.70E-08 1.51E-09 No Data 6.17E-05 3.82E-05 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06 Te-127m 6.72E-06 J 2.31E-06 8.16E-07 1.64E-06 j1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71 E-06 1.52E-05 Te-1 29m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-1 31 m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 I 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-1l1 5.55E-07 i 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 13.72E-05 Te-133m 2.93E-11 1.51E-11 1.50E-11 j 2.32E-1 1 1.01E-10 1.60E-06 14.77E-06 Te-134 1.53E-11 8.81 E-12 9.40E-12 1.24E-1 1 5.71 E-11 1.23E-06 14.87E-07 1-129 1.05E-05 6.40E-06 5.71E-06 4.28E-03 I 1.08E-05 No Data I 2.15E-07 1-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 l 6.61E-06 No Data 1.38E-06 1-131 1.30E-05 l 1.30E-05 7.37E-06 4.39E-03 12.13E-05 No Data I 7.68E-07 1-132 5.72E-07 1.10E-06 5.07E-07 .5.23E-05 1.69E-06 No Data j 8.65E-07 1-133 4.48E-06 1 5.49E-06 2.08E-06 11.04E-03 9.13E-06 No Data 1.48E-06 1-134 3.17E-07 _ 5.84E-07 2.69E-07 1.37E-05 18.92E-07 No Data I2.58E-07 1-135 1.332-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 No Data j 1.20E-06

' Data presented in this Table are from Reference 9.

A-20

PNPS-ODCM Rev. 9 TABLE A-13 (continued)

INHALATION DOSE FACTORS FOR CHILD(')

mrem/pCi Inhaled I ~~Total I1 Nuclide I Bone Liver Bod Thyroid Kidne Lung GI-LLI Cs-1 34m 6.33E-08 8.92E-08 6.12E-08 No Data 4.94E-08 8.35E-09 1 7.92E-08 Cs-134 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 3.27E-05 j 1.04E-06 Cs-135 6.23E-05 4.13E-05 4.45E-06 No Data 1.53E-05 5.22E-06 2.17E-07 Cs-136 1.76E-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81 E-05 9.78E-07 Cs-1 38 1.71 E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 Cs-1 39 1.09E-07 1.1 5E-07 5.80E-08 No Data 9.08E-08 9.36E-09 7.23E-1 2 Ba-139 4.98E-10 2.66E-13 .45E-11 No Data 2.33E-13 1.56E-06 1.56E-05 Ba-1 40 2.OOE-05 1.75E-08 1.17E-06 No Data 5.71 E-09 4.71 E-04 j 2.75E-05 Ba-1 41 5.29E-11 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-1 5 7.54E-13 No Data 7.87E-15 4.44E-07 7.41 E-10 La-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.1 OE-05 La-1 41 2.28E-09 5.31 E-1 0 1.1 5E-1 0 No Data No Data 4.48E-06 4.37E-05 La-142 3.50E-10 1. 1 E-10 3.49E-11 No Data No Data 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31 E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05 Ce-1 44 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.1 1E-07 1.17E-04 l 2.63E-05 Pr-144 1.61 E-11 4.99E-12 8.1 OE-13 No Data 2.64E-12 4.23E-07 I 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22E-05 Pm-147 3.52E-04 2.52E-05 1.36E-05 No Data 4.45E-05 2.20E-04 5.70E-06 Pm-148m 3.31 E-05 6.55E-06 6.55E-06 No Data 9.74E-06 5.72E-04 3.58E-05 Pm-148 1.61 E-06 1.94E-07 1.25E-07 No Data 3.30E-07 1.24E-04 6.01 E-05 Pm-1 49 1.47E-07 1.56E-08 8.45E-09 No Data 2.75E-08 2.40E-05 2.92E-05 Pm-151 3.57E-08 4.33E-09 2.82E-09 i No Data 7.35E-09 1.24E-05 2.50E-05 Sm-151 3.14E-04 4.75E-05 1.49E-05 I No Data 4.89E-05 1.48E-04 3.43E-06 Sm-1 53 7.24E-08 4.51 E-08 4.35E-09 No Data 1.37E-08 1.37E-05 1.87E-05 Eu-152 7.42E-04 1.37E-04 1.61 E-04 No Data 5.73E-04 9.OOE-04 1.14E-05 Eu-1 54 2.74E-03 2.49E-04 2.27E-04 No Data 1.09E-03 1.66E-03 2.98E-05 Eu-1 55 5.60E-04 4.05E-05 3.18E-05 No Data 1.51 E-04 2.79E-04 5.39E-05 Eu-1 56 7.89E-06 4.23E-06 8.75E-07 No Data 2.72E-06 2.54E-04 4.24E-05 Tb-1 60 7.79E-05 No Data 9.67E-06 No Data j 2.32E-05 5.34E-04 2.28E-05 Ho-1 66m 1.34E-03 I 2.81 E-04 2.37E-04 No Data 4.01 E-04 1.1 3E-03 1.63E-05 W-181 2.66E-08 j 6.52E-09 8.99E-10 No Data No Data 5.71 E-06 2.61 E-07 W-185 8.31 E-07 2.08E-07 2.91 E-08 No Data I No Data 1.86E-04 1.11 E-05 W-187 4.41 E-09 i 2.61 E-09 1.17E-09 No Data I No Data 1.11 E-05 2.46E-05 Pb-21 0 8.03E-02 1.85E-02 3.18E-03 No Data i 6.31 E-02 8.74E-02 1.55E-06 Bi-210 9.85E-07 I 5.11 E-06 5.65E-07 No Data 5.76E-05 3.70E-03 3.21 E-05 Po-210 1.70E-03 2.76E-03 4.09E-04 No Data l 8.85E-03 1.05E-01 i 4.32E-05 Ra-223 7.69E-04 8.89E-07 1.54E-04 No Data 1 2.36E-05 8.48E-02 13.OOE-04 Ra-224 8.44E-05 1.53E-07 1.69E-05 No Dta 4.06E-06 2.92E-02 3.34E-04 Ra-225 1.28E-03 11.1 4E-06 2.56E-04 No Data 1 3.02E-05 9.74E-02 J 2.84E-04 Ra-226 2.34E-01 I 7.66E-06 1.92E-01 No Data j 2.03E-04 3.90E-01 3.02E-04 Ra-228 1.49E-01 3.94E-06 1.68E-01 No Data 11.04E-04 5.37E-01 15.14E-05 (1) Data presented in this Table are from Reference 9.

A-21

PNPS-ODCM Rev. 9 TABLE A-13 (continued)

INHALATION DOSE FACTORS FOR CHILD(')

mrem/pCi Inhaled Nuclide l Bone Uver Bdy TThyroid Kidney l Lung l GI-LLI Ac-225 1.81 E-03 1.87E-03 1.21 E-04 No Data 11.99E-04 7.37E-02 2.67E-04 Ac-227 4.96E+00 8.05E-01 3.07E-01 No Data 1.77E-01 8.04E-01 5.22E-05 Th-227 9.24E-04 1.26E-05 2.67E-05 No Data I 6.67E-05 1.26E-01 3.49E-04 Th-228 8.06E-01 1.04E-02 2.72E-02 No Data 5.41 E-02 3.34E+00 3.59E-04 Th-229 2.18E+01 5.74E-01 3.63E-01 No Data 2.83E+00 1.08E+01 4.99E-05 Th-230 3.30E+00 1.73E-01 9.20E-02 No Data I 8.52E-01 1.85E+00 3.84E-05 Th-232 3.68E+00 1.47E-01 1.28E-03 No Data j 7.28E-01 1.77E+00 3.27E-05 Th-234 6.94E-06 3.07E-07 2.00E-07 No Data 1.62E-06 6.31 E-04 7.32E-05 Pa-231 8.62E+00 - 2.86E-01 3.43E-01 No Data I .56E+00 1.92E-01 4.57E-05 Pa-233 4.14E-06 6.48E-07 7.25E-07 No Data I 2.38E-06 9.77E-05 8.95E-06 U-232 2.19E-01 No Data 1.56E-02 No Data j 1.67E-02 7.42E-01 4.33E-05 U-233 4.64E-02 No Data 2.82E-03 No Data 7.62E-03 1.77E-01 4.OOE-05 U-234 4.46E-02 No Data 2.76E-03 No Data 7.47E-03 1.74E-01 3.92E-05 U-235 4.27E-02 No Data 2.59E-03 No Data 7.01 E-03 1.63E-01 4.98E-05 U-236 4.27E-02 No Data 2.65E-03 No Data 7.16E-03 1.67E-01 3.67E-05 U-237 1.57E-07 No Data' 4.17E-08 No Data 4.53E-07 3.40E-05 1.29E-05 U-238 4.09E-02 No Data 2.42E-03 No Data 6.55E-03 1.53E-01 3.51 E-05 Np-237 2.72E+00 1 .62E+00 1.19E-01 No Data 7.41 E-01 1.74E-01 5.06E-05 Np-238 1.26E-06 I 2.30E-07 1.97E-08 No Data 8.16E-08 3.39E-05 2.50E-05 Np-239 1.26E-07 8.14E-08 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 Pu-238 2.55E+00 1.60E+00 1.21 E-01 No Data 4.47E-01 6.08E-01 4.65E-05 Pu-239 2.79E+00 11.68E+00 1.28E-01 No Data 4.78E-01 5.72E-01 4.24E-05 Pu-240 2.79E+00 1.68E+00 1.27E-01 No Data 4.77E-01 5.71 E-01 4.33E-05 Pu-241 7.94E-02 1.75E-02 2.93E-03 No Data 1.10E-02 5.06E-04 8.90E-07 Pu-242 2.59E+00 1.62E+00 1.23E-01 No Data 4.60E-01 5.50E-01 4.16E-05 Pu-244 3.02E+00 1.85E+00 1.41 E-01 No Data 5.27E-01 6.30E-01 6.20E-05 Am-241 2.97E+00 1.84E+00 1.24E-01 No Data 7.63E-01 2.02E-01 4.73E-05 Am-242m 3.07E+00 1.76E+00 1.27E-01 No Data _ 7.71 E-01 8.14E-02 5.96E-05 Am-243 2.94E+00 1.78E+00 1.20E-01 No Data I 7.42E-01 1.92E-01 5.55E-05 Cm-242 9.48E-02 5.68E-02 4.20E-03 No Data 1 .34E-02 1.31E-01 I 5.06E-05 Cm-243 2.32E+00 1.42E+00 9.95E-02 No Data j 3.74E-01 2.1 0E-01 _ 4.98E-05 Cm-244 1.94E+00 1.18E+00 8.31 E-02 No Data I 3.06E-01 2.02E-01 I 4.82E-05 Cm-245 3.05E+00 1.84E+00 1.28E-01 No Data 1 5.03E-01 1.95E-01 4.49E-05 Cm-246 3.02E+00 I 1.84E+00 1.28E-01 No Data I 5.03E-01 1.99E-01 4.41E-05 Cm-247 2.94E+00 1.82E+00 1.26E-01 No Data T 4.952-01 1.95E-01 5.80E-05 Cm-248 2.45E+01 1.50E+01 1.04E+00 No Data 4.08E+00 1.61 E+00 9.352-04 Cf-252 2.18E+00 No Data 9.33E-02 No Data I No Data 6.62E-01 1.84E-04

(') Data presented in this Table are from Reference 9.

A-22

PNPS-ODCM Rev. 9 TABLE A-14 INHALATION DOSE FACTORS FOR INFANT(')

mrem/pCi Inhaled Nuclide l Bone I Liver JBod Thyroid I Kidney Lung GI-LLI H-3 No Data 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 Be-1 0 9.49E-04 1.25E-04 2.65E-05 No Data No Data 1.49E-03 1.73E-05 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 N-13 4.39E-08 14.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 F-18 3.92E-06 I No Data 3.33E-07 No Data No Data No Data l 6.1 OE-07 Na-22 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 Na-24 7.54E-06 _ 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 _ 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 No Data No Data No Data 1.1 5E-05 Ca-41 7.i8E-05 No Data 8.16E-06 No Data No Data 6.94E-02 2.96E-07 Sc-46 3.75E-04 5.41 E-04 1.69E-04 No Data 3.56E-04 No Data I 2.19E-05 Cr-51 No Data J No Data 6.39E-08 4.11 E-08 9.45E-09 9.17E-06 i 2.55E-07 Mn-54 No Data !1.81 E-05 3.56E-06 No Data 3.56E-06 7.14E-04 5.04E-06 Mn-56 No Data 1 1.1OE-09 1.58E-10 No Data 7.86E-10 8.95E-06 i 5.12E-05 Fe-55 1.41 E-05 8.39E-06 2.38E-06 No Data No Data 6.21 E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 Co-57 No Data 4.65E-07 4.58E-07 No Data j No Data 2.71 E-04 3.47E-06 Co-58 No Data 8.71 E-07 1.30E-06 No Data I No Data 5.55E-04 7.95E-06 Co-60 No Data I 5.73E-06 8.41 E-06 No Data I No Data 3.22E-03 2.28E-05 Ni-59 1.81 E-05 5.44E-06 3.10E-06 No Data I No Data 5.48E-05 6.34E-07 Ni-63 2.42E-04 1.46E-05 8.29E-06 No Data i No Data 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 No Data i No Data 5.80E-06 3.58E-05 Cu-64 No Data 1.34E-09 5.53E-10 No Data I 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 No Data F2.32E-05 4.62E-04 3.67E-05 Zn-69m 8.98E-09 1.84E-08 1.67E-09 No Data I 7.45E-09 1.91 E-05 2.92E-05 Zn-69 3.85E-11 6.91 E-11 5.13E-12 No Data 2.87E-11 1.05E-06 I 9.44E-06 Se-79 No Data 2.25E-06 4.20E-07 No Data 2.47E-06 2.99E-04 j 3.46E-06 Br-82 No Data No Data 9.49E-06 No Data No Data No Data I No Data Br-83 No Data No Data 2.72E-07 No Data No Data No Data No Data Br-84 No Data No Data 2.86E-07 No Data No Data No Data I No Data Br-85 No Data No Data 1.46E-08 No Data No Data No Data _ Data

_No Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 Rb-87 No Data 7.11 E-05 2.64E-05 No Data No Data No Data I 2.99E-07 Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data i2.42E-07 Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08 Sr-89 2.84E-04 No Data 8.15E-06 No Data I No Data 1.45E-03 _ _4.57E-05 Sr-90 1.11E-02 No Data 2.23E-04 No Data j No Data 8.03E-03 9.36E-05 Sr-91 6.83E-08 ! No Data 2.47E-09 No Data j No Data 3.76E-05 5.24E-05 Sr-92 7.50E-09 I No Data 2.79E-10 No Data I No Data 1.70E-05 1.OOE-04 Y-90 2.35E-06 I No Data 6.30E-08 No Data I No Data 1.92E-04 7.43E-05 Y-91m 2.91E-10 l No Data 9.90E-12 No Data l No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data I No Data 1.75E-03 5.02E-05 Y-92 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 Y-93 1.07E-07 j No Data 2.91 E-09 No Data [No Data 5.46E-05 1.1 9E-04 (1)Data presented in this Table are from Reference 9.

A-23

PNPS-ODCM Rev. 9 TABLE A-14 (continued)

INHALATION DOSE FACTORS FOR INFANT(')

mrem/pCi Inhaled I IITotalt Nuclide J Bone Liver Bodv Thyroid Kidnev Lunq Gl-LLI Zr-93 2.24E-04 9.51 E-06 6.18E-06 No Data l 3.19E-05 1.37E-04 1.48E-06 Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.OOE-04 Nb-93m 1.38E-04 3.59E-05 1.15E-05 No Data 3.68E-05 2.09E-04 2.47E-06 Nb-95 1.1 2E-05 4.59E-06 2.70E-06 JNo Data 3.37E-06 3.42E-04 9.05E-06 Nb-97 2.44E-10 5.21 E-11 1.88E-1i No Data i4.07E-11 2.37E-06 1.92E-05 Mo-93 No Data 6.46E-06 2.22E-07 No Data 1.54E-06 3.40E-04 3.76E-06 Mo-99 No Data 1.18E-07 2.31 E-08 No Data I 1.89E-07 9.63E-05 3.48E-05 Tc-99mr 9.98E-13 2.06E-12 2.66E-1i No Data 2.22E-11 5.79E-07 1.45E-06 Tc-99 2.09E-07 2.68E-07 8.85E-08 No Data 2.49E-06 6.77E-04 7.82E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 No Data 4.85E-07 No Data I 3.03E-06 3.94E-04 1.15E-05 Ru-105 J8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-1 06 6.20E-05 I No Data 7.77E-06 No Data 7.61 E-05 8.26E-03 1.17E-04 Rh-1 05 8.26E-09 5.41 E-09 3.63E-09 No Data [1.50E-08 2.08E-05 1.37E-05 Pd-1 07 No Data 4.92E-07 4.11 E-08 No Data 2.75E-06 6.34E-05 7.33E-07 Pd-1 09 No Data 3.92E-09 1.05E-09 No Data 1.28E-08 1.68E-05 2.85E-05 Ag-1 1Om 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 Ag-1 11 3.75E-07 1.45E-07 7.75E-08 No Data 3.05E-07 2.06E-04 3.02E-05 Cd-i 13m No Data 6.67E-04 2.64E-05 No Data 5.80E-04 1.40E-03 1.65E-05 Cd-i1 Sm No Data 1.73E-04 6.19E-06 j No Data l 9.41 E-05 1.47E-03 l 5.02E-05 Sn-1 23 2.09E-04 4.21 E-06 7.28E-06 I 4.27E-06 I No Data 2.22E-03 I 4.08E-05 Sn-1 25 1.01E-05 [2.51E-07 6.OOE-07 1 2.47E-07 . I,I NoData No D.at..

6.43E-04 7.26E-05 Sn-1 26 8.30E-04 1.44E-05 3.52E-05 3.84E-06 I No Data 4.93E-03 11.65E-05 Sb-1 24 2.71 E-05 1 3.97E-07 _ 8.56E-06 7.18E-08 I No Data 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 i No Data 1.17E-03 1.05E-05 Sb-1 26 3.08E-06 I 6.01 E-08 1.1 1E-06 2.35E-08 No Data 6.88E-04 i 5.33E-05 Sb-1 27 2.82E-07 T5.04E-09 8.76E-08 3.60E-09 l No Data 1.54E-04 l 3.78E-05 Te-1 25m 3.40E-06 i 1.42E-06 4.70E-07 1.16E-06 I No Data 3.19E-04 I 9.22E-06 Te-127m 1.1 9E-05 4.93E-06 1.48E-06 3.48E-06 j 2.68E-05 9.37E-04 J 1.95E-05 Te-1 27 1.59E-09 6.81 E-1 0 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-1 29m 1.01E-05 4.35E-06 1.59E-06 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-1 1 2.48E-1I 1.34E-1 1 4.82E-1 1 1.25E-10 2.14E-06 j 1.88E-05 Te-1 31 m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 18.51E-05 Te-131 1.24E-11j 5.87E-12 3.57E-12 1.1 3E-11 l2.85E-11 1.47E-06 5.87E-06 Te-1 32 2.66E-07 1.69E-07 1.26E-07 1 .99E-07 7.39E-07 2.43E-04 3.15E-05 Te-133m 6.13E-1 1 3.59E-1I 2.74E-11 1 5.52E-1 1 1.72E-10 3.92E-06 1.59E-05 Te-134 3.18E-1 i 2.04E-i 1 1.68E-li_ 2.91 E-i 1 9.59E-11 2.93E-06 1 2.53E-06 1-129 2.16E-05 1.69E-06 1.16E-05 1.04E-02 i 1.88E-05 No Data i 2.12E-07 1-130 4.54E-06 9.91 E-06 3.98E-06 t1.142-03 1.09E-05 No Data i 1.42E-06 1-131 2.71 E-05 3.17E-05 1.40E-05 1.06E-02 j 3.70E-05 No Data 7.56E-07 1-132 1.21 E-06 2.53E-06 8.99E-07 1.21 E-04 12.82E-06 No Data 1 .36E-06 1-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 .1.60E-05 No Data 1.54E-06 1-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data 9.21E-07 1-135 2.76E-06 1 5.43E-06 1.98E-06 , 4.97E-04 1 6.05E-06 No Data 11.31E-06 Data presented in this Table are from Reference 9.

A-24

PNPS-ODCM Rev. 9 TABLE A-14 (continued)

INHALATION DOSE FACTORS FOR INFANT(')

mremlpCi Inhaled r I Total i oi K y Nuclide Bone Liv~ Bod Thydner GI-LLI Cs-1 34m 1.32E-07 1 2.10E-07 1.11 E-07 No Data 8.50E-08 2.00E-08 1.1 6E-07 Cs-1 34 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07 Cs-1 35 1.OOE-04 8.66E-05 4.73E-06 No Data 2.58E-05 1.01 E-05 2.18E-07 Cs-136 3.45E-05 9.61 E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61 E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 l16.26E-07 Cs-139 2.32E-07 3.03E-07 1.22E-07 No Data 1.65E-07 2.53E-08 1 .33E-08 Ba-139 1.06E-09 7.03E-13 3.07E-11 No Data 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-1I 2.36E-14 1.40E-12 No Data 1.36E-14 1.11 E-06 4.95E-07 La-1 40 3.61 E-07 1.43E-07 3.68E-08 No Data INo Data 1.20E-04 6.06E-05 La-141 4.85E-09 1.40E-09 2.45E-10 No Data No Data 1.22E-05 5.96E-05 La-1 42 7.36E-1 0 2.69E-1 0 6.46E-1 1 No Data No Data 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 No Data 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 No Data i 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.OOE-05 3.74E-06 4.99E-07 No Data 1 1.41 E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 No Data 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 No Data 2.25E-06 2.30E-04 2.23E-05 Pm-147 3.91E-04 3.07E-05 1.56E-05 No Data 4.93E-05 4.55E-04 5.75E-06 Pm-148m 5.00E-05 1.24E-05 9.94E-06 No Data j 1.45E-05 1.22E-03 3.37E-05 Pm-1 48 3.34E-06 4.82E-07 2.44E-07 No Data 5.76E-07 3.20E-04 6.04E-05 Pm-i 49 3.1 OE-07 4.08E-08 1.78E-08 No Data 4.96E-08 6.50E-05 3.01 E-05 Pm-151 7.52E-08 1.10E-08 5.55E-09 No Data 1.30E-08 3.25E-05 2.58E-05 Sm-1 51 3.38E-04 6.45E-05 1.632-05 No Data 5.24E-05 2.98E-04 3.46E-06 Sm-1 53 1.53E-07 1.18E-07 9.06E-09 No Data 2.47E-08 3.70E-05 1.93E-05 Eu-152 7.83E-04 1.77E-04 1.72E-04 No Data 5.94E-04 1.48E-03 9.88E-06 Eu-154 2.96E-03 3.46E-04 2.45E-04 No Data 1.14E-03 3.05E-03 2.84E-05 Eu-155 5.97E-04 5.72E-05 3.46E-05 No Data 1.58E-04 5.20E-04 ! 5.19E-05 Eu-1 56 1.56E-05 9.59E-06 1.54E-06 No Data 4.48E-06 .6.12E-04 4.14E-05 Tb-160 1.12E-04 No Data 1.40E-05 No Data 3.20E-05 1.11E-03 2.14E-05 Ho-166m 1.45E-03 3.07E-04 2.51 E-04 TNo Data i 4.22E-04 2.05E-03 1.65E-05 W-1 81 4.86E-08 1.46E-08 1.67E-09 i No Data l No Data 1.33E-05 2.63E-07 W-1 85 1.57E-06 J 4.83E-07 5.58E-08 1No Data l No Data 4.48E-04 1.12E-05 W-187 9.26E-09 i 6.44-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 Pb-210 8.62E-02 1 2.02E-02 3.43E-03 JNo Data 6.85E-02 1.76E-01 1.57E-06 Bi-210 2.06E-06 11.33E-05 1.18E-06 No Data 1.03E-04 9.96E-03 [3.27E-05 Po-210 2.98E-03 5.63E-03 7.12E-04 No Data ; 1.30E-02 2.40E-01 14.36E-05 Ra-223 1.56E-03 2.26E-06 3.12E-04 No Data j 4.16E-05 2.25E-01 [3.04E-04 Ra-224 .77E-04 4.00E-07 3.54E-05 No Data 7.30E-06 7.91E-02 [3.42E-04 Ra-225 2.57E-03 2.88E-06 5.13E-04 No Data 5.31E-05 2.57E-01 j 2.87E-04 Ra-226 2.48E-01 1.46E-05 2.05E-01 No Data 2.94E-04 7.83E-01 3.05E-04 Ra-228 1.60E-01 7.61E-06 1.80E-01 I No Data . 1.53E-04 1.09E+00 I 5.19E-05 Data presented in this Table are from Reference 9.

A-25

PNPS-ODCM Rev. 9 TABLE A-14 (continued)

INHALATION DOSE FACTORS FOR INFANT(')

mrem/pCi Inhaled I I Total I Nuclide I Bone I Liver Body _Throid Kidney I Lung !GI-LLI Ac-225 3.69E-03 4.72E-03 2.48E-04 No Data 3.49E-04 1.96E-01 12.71 E-04 Ac-227 5.29E+00 8.76E-01 3.28E-01 No Data 1.86E-01 1.62+00 j 5.27E-05 Th-227 1.82E-03 3.03E-05 5.24E-05 No Data 1.1 3E-04 3.27E-01 I3.53E-04 Th-228 8.46E-01 1.10E-02 2.86E-02 No Data 5.61E-02 j 4.65E+00 3.62E-04 Th-229 2.28E+01 5.94E-01 3.81 E-01 No Data 9.32E-01 1.27E+01 5.02E-05 Th-230 _3.46E+00 1.79E-01 9.65E-02 No Data 8.82E-01 J 2.18E+00 3.87E-05 Th-232 3.86E+00 1.53E-01 2.29E-03 No Data 7.54E-01 I 2.09E+00 3.29E-05 Th-234 1.33E-05 7.17E-07 3.84E-07 No Data 2.70E-06 1.62_-03 7.40E-05 Pa-231 9.10OE+00 _.OE-01 3.62E-01 No Data 1.62E+00 3.85E-01 4.61 E-05 Pa-233 6.84E-06 1.32E-06 1.19E-06 No Data 3.68E-06 2.19E-04 9.04E-06 U-232 2.57E-01 No Data 2.13E-02 No Data 2.40E-02 1.49E+00 4.36E-05 U-233 5.44E-02 No Data 3.83E-03 No Data 1.09E-02 3.56E-01 4.03E-05 U-234 5.22E-02 No Data 3.75E-03 No Data 1.07E-02 3.49E-01 3.95E-05 U-235 5.01 E-02 No Data 3.52E-03 No Data 1.01E-02 3.28E-01 5.02E-05 U-236 5.01E-02 No Data 3.60E-03 No Data 1.03E-02 3.35E-01 3.71E-05 U-237 3.25E-07 No Data 8.65E-08 No Data 8.08E-07 9.13E-05 1.31E-05 U-238 4.79E-02 No Data 3.29E-03 No Data 9.40E-03 3.06E-01 3.54E-05 Np-237 2.88E+00 1.71 E+00 1.26E-01 No Data 7.69E-01 3.49E-01 5.1 0E-05 Np-238 2.67E-06 6.05E-07 4.16E-08 No Data 1.47E-07 9.19E-05 2.58E-05 Np-239 2.65E-07 2.13E-07 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E-05 Pu-238 I 2.69E+00 1.68E+00 1.27E-01 No Data 4.64E-01 9.03E-01 4.69E-05 Pu-239 i 2.93E+00 1.76E+00 1.34E-01 No Data 4.95E-01 8.47E-01 i 4.28E-05 Pu-240 T2.93E+00 1.75E+00 1.34E-01 No Data J 4.94E-01 8.47E-01 I 4.36E-05 Pu-241 I 8.43E-02 1.85E-02 3.11 E-03 No Data 1.15E-02 7.62E-04 I 8.97E-07 Pu-242 2.72E+00 1.69E+00 1.29E-01 No Data 4.77E-01 8.1 5E-01 I 4.20E-05 Pu-244 3.17E+00 1.94E+00 1.48E-01 No Data 5.46E-01 19.33E-01 16.26E-05 Am-241 3.15E+00 1.95E+00 1.31 E-01 No Data 7.94E-01 4.06E-01 I 4.78E-05 Am-242m 3.25E+00 1.86E+00 1.35E-01 No Data 8.03E-01 1.64E-01 6.01E-05 Am-243 3.10E+00 1.88E+00 1.27E-01 No Data 7.72E-01 3.85E-01 T 5.60E-05 Cm-242 1.28E-01 8.65E-02 5.70E-03 No Data 1.692-02 2.972-01 15.10E-05 Cm-243 2.47E+00 1.52E+00 1.06E-01 No Data 3.91E-01 4.24E-01 l 5.02E-05 Cm-244 2.07E+00 I1.27E+00 8.89E-02 No Data 3.21 E-01 4.08E-01 j 4.86E-05 Cm-245 ; 3.22E+00 i1.96E+00 1.36E-01 l No Data 5.23E-01 3.92E-01 j 4.53E-05 Cm-246 1 3.20E+00 1.962+00 11.36E-01 I No Data 5.23E-01 3.99E-01 1 4.45E-05 Cm-247 13.11E+00 1.93E+00 1 1.33E-01 No Data 5.15E-01 3.92E-01 I 5.85E-05 Cm-248 I 2.58E+01 1.59E+01 11.10E+00 I No Data 4.24E+00 3.23E+00 i 9.43E-04 Cf-252 12.37E+00 No Data 1.01E-01 7 No Data No Data I 1.37E+00 ! 1.85E-04

') Data presented in this Table are from Reference 9.

A-26

PNPS-ODCM Rev. 9 TABLE A-15 INGESTION DOSE FACTORS FOR ADULT(')

mrern/pCi Ingested

§ I I ~Total Nuclide Liver BoBone_ l Thyroid Kidney Lung G-LLI H-3 No Data j 5.99E-08-- 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 Be-10 3.18E-06 1 4.91 E-07 7.94.E-08 J No Data J 3.71E-07 No Data 2.68E-05 C-14 2.84E-06 I 5.68E-07 I 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 N-13 8.36E-09 J 8.36E-09 l 8.36E-09 l 8.36E-09 8.36E-09 8.36E-09 8.36E-09 F-1 8 6.24E-07 I No Data I 6.92E-08 I No Data I No Data I No Data 1.85E-08 Na-22 1.74E-05 1.74E-05 l 1.74E-05 I 1.74E-05 J 1.74E-05 1.74E-05 1.74E-05 Na-24 1.70E-06 1.70E-06 j1.70E-06 j1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 ! No Data l No Data No Data 2.17E-05 Ca-41 1.85E-04 j No Data 1 2.00E-05 I No Data I No Data No Data 1.84E-07 Sc-46 5.51 E-09 j 1.07E-08 _ 3.11 E-09 I No Data j 9.99E-09 No Data 5.21 E-05 Cr-51 No Data 7No Data l 2.66E-09 11.59E-09 j 5.86E-10 . 3.53E-09 6.69E-07 Mn-54 No Data ! 4.57E-06 8.72E-07 ! No Data j 1.36E-06 j No Data 1.40E-05 Mn-56 No Data 11.152-07 2.04E-08 I No Data 1.46E-07 I No Data 3.67E-06 Fe-55 2.75E-06 J 1.90E-06 4.43E-07 J No Data No Data i 1.06E-06 1.09E-06 Fe-59 4.34E-06 11.02E-05 I 3.91 E-06 ! No Data No Data ! 2.85E-06 3.40E-05 Co-57 ] No Data 11.752-07 2.91 E-07 j No Data i No Data I No Data 4.44E-06 Co-58 No Data i 7.45E-07 1.67E-06 I No Data I No Data j No Data 1 1.51 E-05 Co-60 No Data i 2.14E-06 4.72E-06 j No Data r No Data No Data 1 4.02E-05 Ni-59 9.76E-06 j 3.35E-06 1.63E-06 No Data No Data No Data 6.90E-07 Ni-63 1.30E-04 ! 9.01 E-06 4.36E-06 No Data No Data No Data 1.88E-06 Ni-65 1 5.28E-07 1 6.86E-08 3.13E-08 No Data J No Data No Data 1.74E-06 Cu-64 i No Data 8.33E-08 3.91E-08 No Data j 2.1OE-07 No Data 7.10E-06 Zn-65 [4.84E-06 I 1.54E-05 6.96E-06 1 No Data 1.03E-05 No Data 9.70E-06 Zn-69m 1.70E-07 I 4.08E-07 3.73E-08 I No Data 2.47E-07 No Data 2.49E-05 Zn-69 1.03E-08 1.97E-08 1.37E-09 1 No Data I 1.28E-08 No Data 2.96E-09 Se-79 _ No Data j 2.63E-06 J 4.39E-07 I No Data 4.55E-06 No Data 5.38E-07 Br-82 No Data I No Data 2.26E-06 ! No Data i No Data No Data 2.59E-06 Br-83 No Data I No Data 4.02E-08 I No Data l No Data No Data l5.79E-08 Br-84 No Data I No Data 5.21 E-08 No Data I No Data No Data 4.09E-13 Br-85 No Data I No Data 2.14E-09 No DNoD No Data No Data No Data Rb-86 No Data 2.11 E-05 I 9.83E-06 No Data I No Data No Data 4.16E-06 Rb-87 No Data l 1.23E-05 l 4.28E-06 l No Data I No Data No Data 5.762-07 Rb-88 I No Data j 6.05E-08 3.21 E-08 i No Data I No Data No Data 8.36E-19 Rb-89 No Data 4.01 E-08 2.82E-08 i No Data i No Data No Data j 2.33E-21 Sr-89 I 3.08E-04 j No Data 8.84E-06 l No Data I No Data I No Data l 4.94E-05 Sr-90 18.71E-03 No Data 1.75E204 No Data No Data I No Data 12.19E-04 Sr-91 5.67E-06 ! No Data j 2.29E-07 No Data - No Data t No Data J 2.70E-05 Sr-92 I2.15E-06 No Data 9.30E-08i No Data INo Data [NoData 14.26E-05 Y-90 I 9.62E-09 I No Data 2.58E-10 I No Data I No Data No Data I 1.02E-04 Y-91m 9.09E-111 No Data 13.52E-12 No Data jNo Data No Data 2.67E-10 I 7.76E-05 Y-91 Y-92 Y-93 j 1.41 E-07 ; No Data 8.45E-10 l 3.77E-09 i No Data i No Data No Data j 2.47E-11 12.68E-09 1 No Data No Data I 7.40E-11 1 No Data I No Data I No Data No Data NoData 1 .48E-05 I 8.50E-05

< Data presented in this Table are from Reference 9.

A-27

PNPS-ODCM Rev. 9 TABLE A-15 (continued)

INGESTION DOSE FACTORS FOR ADULT(')

mrem/pCi Ingested i i Total I . I I Nuclide Bone Liver Bod Thyroid Kidney lLun GI-LLI Zr-93 4.1 8E-08 1 2.34E-09 1 .09E-09 I No Data 8.87E-09 1 No Data I 2.43E-06 Zr-95 3.04E-08 9.75E-09 6.60E-09 -I No Data 1.53E-08 I No Data 3.09E-05 Zr-97 1.68E-09 3.39E-1 0 1.55E-10 No Data 5.12E-1 0 iNo Data 1.05E-04 Nb-93m 2.55E-08 8.32E-09 2.05E-09 No Data 9.57E-09 l No Data 3.84E-06 Nb-95 6.22E-09 I 3.46E-09 1.86E-09 j No Data 3.42E-09 No Data 2.10E-05 Nb-97 5.22E-1i j1.32E-11 4.82E-12I No Data I 1.54E-1 1 No Data 4.87E-08 Mo-93 No Data 7.51 E-06 2.03E-07 I No Data *[ 2.13E-06 No Data 1.22E-06 Mo-99 I No Data 1 4.31 E-06 8.20E-07 I No Data I 9.76E-06 No Data 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-1 0 4.13E-07 Tc-99 1.25E-07 1.86E-07 5.02E-08 I No Data 2.34E-06 1.58E-08 6.08E-06 Tc-101 2.54E-10 T 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.1 OE-21 Ru-1 03 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 Ru-1 05 1.54E-08 I No Data I 6.08E-09 INo Data i1.99E-07 No Data I 9.42E-06 Ru-1 06 ', 2.75E-06 1 No Data i 3.48E-07 j No Data 5.31 E-06 No Data ; 1.78E-04 Rh-1 05 1.21 E-07 8.85E-08 ! 5.83E-08 ! No Data ! 3.76E-07 No Data 1.41 E-05 Pd-1 07 J No Data 1.47E-07 19.40E-09 I No Data 1.32E-06 No Data 9.11 E-07 Pd-1 09 I No Data 1.77E-07 j 3.99E-08 l No Data 1.01 E-06 No Data 1.96E-05 Ag-1 1Om 1 .60E-07 1 .48E-07 8.79E-08 No Data 2.91 E-07 No Data 6.04E-05 Ag-11l i 5.81 E-08 2.43E-08 11.21 E-08 I No Data 7.84E-08 No Data 4.46E-05 Cd-1i13m i No Data 3.18E-06 l 1.02E-07 I No Data 3.50E-06 No Data 2.56E-05 Cd-1 15m No Data 1.84E-06 ' 5.87E-08 i No Data 1.46E-06 No Data 7.74E-05 Sn-123 ! 3.11E-05 5.15E-07 ! 7.59E-07 4.38E-07 No Data No Data 6.33E-05 Sn-125 1 8.33E-06 1.68E-07 13.78E-07 1.39E-07 [ No Data oData f 1.04E-04 Sn- 26 8.45E-05 1.67E-06 2.40-06 4.92-07 No Data No Data 2.43E-05 Sb-1 24 J 2.80E-06 5.29E-08 I 1.11E-06 I 6.79E-09 1 No Data 2.182-06 1 7.95E-05 Sb-125 1 1.79E-06 2.00E-08 4.26E-07 I 1.82E-09 i No Data 1.38E-06 1.97E-05 Sb-126 1.15E-06 2.34E-08 I 4.15E-07 I 7.04E-09 l No Data 7.05E-07 9.40E-05 Sb-127 2.58E-07 5.65E-09 l 9.90E-08 3.10E-09 No Data 1.53E-07 5.90E-05 Te-125m 2.68E-06 9.71 E-07 i 3.59E-07 8.06E-07 1.09E-05 No Data I 1.07E-05 Te-127m 6.102-07 2.45E-06 8.25E-07 1.732-06 J2.75-05 -No Data 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 1 4.48E-07 No Data 8.68E-06 Te-129m 1.15E-05 4.29E-06 I 1.82E-06 I 3.95E-06 4.80E-05 No Data 5.79E-05 Te-129 3.14E-08 11.18E-08 j 7.65E-09 12.41E-08 1.32E-07 No Data 2.37E-08 Te-1 31 m 1.73E-06 8.46E-07 I 7.05E-07 I 1.34E-06 8.57E-06 I No Data 8.40E-05 Te-131 J 1.97E-08 8.23E-09 l 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 Te-1 32 2.522-06 f1.63E-06 11.53E-06. 11.802-06 1.572-05 No Data 7.71 2-05 Te-133m 4.62E-08 2.70E-08 12.60E-08 13.91E-08 2.67E-07 No Data 9.26E-09 Te-134 3.24E-08 12.12E-08 11.30E-08 2.83E-08 2.05E-07 No Data 3.59E-1 1 1-129 3.27E-06 2.81E-06 19.21E-06 7.23E-03 6.04E-06 No Data 4.44E-07 1-130 7.56E-07 2.23E-06 1 8.80E-07 1.89E-04 3.48E-06 i No Data 1.92E-06 1-131 4.16E-06 i 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 No Data I 1.57E-06 1-132 2.03E-07 1.902-07 1.902-05E5432-078.65E-07 No Data 1.02E-07 1-133 1 1.42E-06 12.47E-06 7.53E-07 3.63E-04 L4.31E-06 No Data 2.22E-06 1-134 J 1.06E-07 1 2.88E-07 1 1.03E-07 I 4.99E-06 I 4.58E-07 l No Data l 2.51E-10 1-135 1 4.43E-07 1 1.16E-06 14.28E-07 17.65E-05 i 1.86E-06 I No Data 1.31E-06 1)Data presented in this Table are from Reference 9.

A-28

PNPS-ODCM Rev. 9 TABLE A-15 (continued)

INGESTION DOSE FACTORS FOR ADULTf' mrem/pCi Inhaled II Total I i I I Nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI Cs-i34m 2.13E-08 I 4.48E-08 i 2.29E-08 No Data 2.43E-08 3.83E-09 l 1.58E-08 Cs-1 34 6.22E-05 1 .48E-04 11.21 E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-135 1.95E-05 j 1.80E-05 ! 7.99E-06 No Data I 6.81 E-06 2.04E-06 4.21 E-07 Cs-136 6.61E-06 2.57E-05 11.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 j 1.09E-04 I 7.14E-05 No Data I 3.70E-05 1.23E-05 2.11 E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data _8.O1E-08 7.91 E-09 4.65E-13 Cs-1 39 3.41 E-08 5.08E-08 1.85E-08 No Data I 4.07E-08 3.70E-09 1.10e-30 Ba-1 39 9.70E-08 6.91 E-1 1 2.84E-09 No Data 6.46E-1 1 3.92E-1 1 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data j 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 I 3.56E-1 1 1.59E-09 i No Data I 3.31 E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 I No Data I 1.85E-11 1.24E-11 3.00e-26 La-1 40 2.50E-09 1.26E-09 3.33E-10 I No Data ! No Data No Data 9.25E-05 La-1 41 3.1 9E-1 0 9.90E-11 1.62E-11I No Data I No Data No Data f 1.1 8E-05 La-142 i1.28E-10 5.82E-11 1.45E-1I No Data I No Data No Data J 4.25E-07 Ce-1 41 I 9.36E-09 6.33E-09 7.18E-10 No Data l 2.94E-09 No Data 12.42E-05 Ce-1 43 .i165E-09 1 1.22E-06 i 1.35E-10 I No Data 1 5.37E-10 No Data I 4.56E-05 Ce-1 44 4.88E-07 I 2.04E-07 I 2.62E-08 I No Data 1.21 E-07 No Data 11.65E-04 Pr-1 43 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data l 4.03E-05 Pr-1 44 3.01 E-1 1 i 1.25E-1 1 1.53E-12 No Data 7.05E-12 No Data l 4.33E-18 Nd-1 47 6.29E-09 17.27E-09 4.35E-10 I No Data I 4.25E-09 No Data I 3.49E-05 Pm-147 7.54E-08 7.09E-09 2.87E-09 No Data 1.34E-08 No Data 8.93E-06 Pm-148m 3.07E-08 7.95E-09 I 6.08E-09 No Data 11.20E-08 No Data 6.74E-05 Pm-148 7.17E-09 31.79E-09 5.99E-10 No Data J2.25E-09 No Data 9.35E-05 Pm-1 49 i1.52E-09 2.15E-10 8.78E-i1 No Data j 4.06E-10 No Data 4.03E-05 Pm-151i 6.97E-10 117E-10 I 5.91 E-1 INo Data I 2.09E-10 No Data I 3.22E-05 6.90E-08 1.1 9E-08 2.85E Data 33E-08 No Data j 5.25E-06

Sm-153 8.57E-10 l 7.15E-10 l 5.22E-11 I No Data I 2.31E-10 No Data l 2.55E-05 Eu-152 I1.95E-07 l 4.44E-08 3.90E-08 j No Data 2.75E-07 No Data j 2.56E-05 Eu-1 54 i 6.15E-07 J 7.56E-08 5.38E-08 I No Data _ 3.62E-07 No Data i 5.48E-05 Eu-1 55 8.60E-08 1.22E-08 7.87E-09 7 No Data I 5.63E-08 No Data 9.60E-06 Eu-1 56 1.37E-08 1 .06E-08 1.71 E-09 I No Data J 7.08E-09 No Data I 7.26E-05 Tb-1 60 4.70E-08 l No Data 5.86E-09 I No Data I_1.94E-08 No Data 4.33E-05 Ho-166m 2.70E-07 8.43E-08 6.40E-08 No Data 1.26E-07 No Data j 2.56E-05 W-1 81 9.91 E-09 3.23E-09 3.46E-1 0 No Data j No Data No Data I 3.68E-07 W-1 85 4.05E-07 j 1.35E-07 1.42E-08 I No Data l No Data No Data 1.56E-05 W-1 87 1.03E-07 8.61 E-08 3.01 E-08 No Data No Data No Data j 2.82E-05 Pb-210 ,b2 1.53E-02 ,

4.37E-03 j.3E6 5.44E-04 I No Data .2E0 N

NoDt 2.24E-06 Bi-210 4.61 E-07 1 3.18E-06 [2.64E-07 I No Data 3.83E-05 No Data I 4.75E-05 Po-21 0 3.56E-04 l 7.56E-04 l 8.59E-05 i No Data j 2.52E-03 No Data 6.36E-05 Ra-223 4.97E-03 F7.65E-06 9.94E-04 I No Data I 2.17E-04 No Data 1 3.21 E-04 Ra-224 I 1.61E-03 3.90E-06 3.23E-04 j No Data l 1.10E-04 No Data ; 3.40E-04 Ra-225 6.56E-03 i 7.78E-06 1.31 E-03 I No Data i 2.21 E-04 No Data I3.06E-04 Ra-226 I 3.02E-01 1 5.74E-06 2.20E-01 I No Data 1.63E-04 i No Data 3.32E-04 Ra-228 I 1.12E-01 3.12E-06 ri.21E-01 i No Data i 8.83E-05 I No Data I 5.64E-05 Data presented in this Table are from Reference 9.

A-29

PNPS-ODCM Rev. 9 TABLE A-15 (continued)

INGESTION DOSE FACTORS FOR ADULTf 1 mremrpCi Inhaled Total I I Nuclide Bone Liver Body Thvroid Kidney Lung GI-LLI Ac-225 4.40E-06 i 6.06E-06 2.96E-07 I No Data j 6.90E-07 No Data [4.07E-04 Ac-227 1 .87E-03 2.48E-04 1.11 E-04 No Data , 8.OOE-05 No Data 8.19E-05 Th-227 1.37E-05 2.48E-07 3.95E-07 I No Data .11.41 E-06 No Data 5.40E-04 Th-228 4.96E-04 j 8.40E-06 1.68E-05 No Data 14.67E-05 No Data 5.63E-04 Th-229 1.36E-02 3.89E-04 2.25E-04 No Data 1.88E-03 No Data 7.81 E-05 Th-230 2.06E-03 11.17E-04 5.70E-05 -No Data 5.65E-04 No Data 6.02E-05 Th-232 2.30E-03 1.OOE-04 1.50E-06 i No Data - 4.82E-04 No Data j 5.12E-05 Th-234 8.01 E-08 14.71 E-09 2.31E-09 I No Data 2.67E-08 No Data 1.13E-04 Pa-231 4.10E-03 1 1.54E-04 1.59E-04 I No Data 8.64E-04 No Data j 7.17E-05 Pa-233 5.26E-09 1.06E-09 9.12E-10 I No Data I 3.99E-09 No Data ! 1.64E-05 U-232 T 4.13E-03 No Data I 2.95E-04 J No Data 1 4.47E-04 No Data I 6.78E-05 U-233 8.71 E-04 No Data I 5.28E-05 No Data I 2.03E-04 No Data j 6.27E-05 U-234 8.36E-04 No Data I 5.17E-05 INo Data 1.99E-04 No Data ! 6.14E-05 U-235 8.01 E-04 No Data I 4.86E-05 I No Data 1.87E-04 £ No Data 1 7.81 E-05 U-236 1 8.01E-04 No Data I 4.96E-05 No Data 1.91 E-04 No Data 5.76E-05 U-237 5.52E-08 No Data 1.47E-08 No Data 2.27E-07 No Dataa 1.94E-05 U-238 7.67E-04 No Data 4.54E-05 No Data 1.75E-04 No Data ! 5.50E-05 Np-237. 1.26E-03 8.96E-05 1 5.54E-05 I No Data 4.12E-04 No Data i 7.94E-05 Np-238 1.37E-08 3.69E-10 2.13E-1 0 No Data 1.25E-09 No Data 3.43E-05 Np-239 _ 1.19E-09 1.17E-10 16.45E-11 No Data 3.65E-1 0 No Data 2.40E-05 Pu-238 6.30E-04 j 7.98E-05 1i.71E-05 i No Data 7.32E-05 No Data J 7.30E-05 Pu-239 1 7.25E-04 I 8.71 E-05 11.91E-05 I No Data 8.11E-05 No Data j 6.66E-05 Pu-240 7.24E-04 8.70E-05 11.91E-05 No Data 8.1 OE-05 No Data 6.78E-05 Pu-241 1.57E-05 7.45E-07 j 3.32E-07 I No Data 1.53E-06 No Data j 1.40E-06 Pu-242 I 6.72E-04 i 8.39E-05 I 1.84E-05 I No Data 7.81 E-05 No Data j 6.53E-05 Pu-244 j 7.84E-04 i 9.61E-05 1 2.11E-05 j No Data 8.95E-05 No Data 9.73E-05 Am-24m 7.61E-04 7.05E-04 5.41E-05 o Data 4.0_E-04 No Data 7.42E-05 Am-242m 7.61E-04 I 6.63E-04 l 5.43E-05 I No Data 4.05E-04 No Data I 9.34E-05 Am-243 7.54E-04 16.90E-04 1 5.30E-05 l No Data I 3.99E-04 No Data 8.70E-05 Cm-242 2.06E-05 J2.19E-05 l 1.37E-06 I No Data 6.22E-06 No Data l 7.92E-05 Cm-243 5.99E-04 I 5.49E-04 3.75E-05 No Data 1.75E-04 No Data 7.81 E-05 Cm-244 I 4.56E-04 4.27E-04 I 2.87E-05 I No Data I 1.34E-04 No Data 7.55E-05 Cm-245 9.38E-04 18.17E-04 5.76E-05 I No Data I 2.69E-04 No Data 7.04E-05 Cm-246 9.30E-04 18.16E-04 I 5.75E-05 INo Data I 2.68E-04 No Data 6.91 E-05 Cm-247 J9.07E-04 J 8.04E-04 l 5.67E-05 I No Data 2.64E-04 No Data 9.09E-05 Cm-248 I 7.54E-03 16.63E-03 1 4.67E-04 I No Data I 2.18E-03 I No Data 1.47E-03 Cf-252 2.61 E-04 I No Data I 6.29E-06 I No Data I No Data I No Data 2.88E-04

(') Data presented in this Table are from Reference 9.

A-30

PNPS-ODCM Rev. 9 TABLE A-16 INGESTION DOSE FACTORS FOR TEEN' 1 mrem/pCi Inhaled Live Boe Nuid Total GI-L Nuclide Bone Liver Body Thyroid Kidney . Lung l-LLI H-3 No Data I 6.04E-08 l 6.04E-08 I 6.04E-08 6.04E-08 6.04E-08 I 6.04E-08 Be-10 4.48E406 6.94E-07 1.1 3E-07 No Data 5.30E-07 No Data 2.84E-05 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 N-13 l 1.15E-08 g 1.15E-08 1.15E-08 l 1.15E-08 1.15E-08 1.15E-08 1.15E-08 F-1 8 I 8.64E-07 I No Data 9.47E-08 I No Data No Data No Data 7.78E-08 Na-22 J 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 [2.34E-05 Na-24 l 2.30E-06 J2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 230E-06 P-32 I 2.76E-04 1.71 E-05 i 1.07E-05 I No Data i No Data No Data 2.32E-05 Ca-41 1.97E-04 No Data 2.13E-05 I No Data No Data No Data 1.95E-07 Sc-46 7.24E-09 1.41 E-08 4.18E-09 l No Data 1.35E-08 No Data 4.80E-05 Cr-51 No Data o ata l 3.60E-09 l 2.00E-09 [7.89E-10 5.14E-09 6.05E-07 Mn-54 No Data 5.90E-06 1.17E-06 No Data I 1.76E-06 No Data 1.21 E-05 Mn-56 No Data 1.58E-07 2.81 E-08 No Data I 2.OOE-07 No Data 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 j No Data No Data 1.70E-06 1.1 6E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 i No Data i No Data 4.32E-06 3.24E-05 Co-57 No Data 2.38E-07 3.99E-07 No Data j No Data No Data 4.44E-06 Co-58 No Data I 9.72E-07 I 2.24E-06 I No Data I No Data No Data 1.34E-05 Co-60 No Data 1 2.81 E-06 _ 6.33E-06 No Data ! No Data No Data 3.66E-05 Ni-59 1.32E-05 4.66E-06 I 2.24E-06 I No Data i No Data No Data 7.31 E-07 Ni-63 1.77E-04 1.25E-05 !6.OOE-06 No Data ! No Data No Data 1.99E-06 I 5.1 9E-06 Ni-65 I7.49E-07 9.57E-08 I 4.36E-08 I No Data I No Data No Data Cu-64 _ No Data 11.1 5E-07 1 5.41 E-08 No Data I 2.91 E-07 No Data 8.92E-06 Zn-65 _ 5.76E-06 2.OOE-05 j 9.33E-06 No Data J 1.28E-05 No Data i 8.47E-06 Zn-69m 2.40E-07 5.66E-07 j 5.19E-08 No Data l 3.44E-07 No Data I 3.11 E-05 Zn-69 1.47E-08 2.80E-08 1.96E-09 No Data ! 1.83E-08 No Data j 5.16E-08 Se-79 No Data j 3.73E-06 j 6.27E-07 j No Data 6.50E-06 JNo Data J 5.70E-07 Br-82 No Data I No Data 3.04E-06 I No Data No Data No Data I No Data Br-83 NoData No Data N No Data l No N Data No Data Br-84 No Data J No Data I 7.22E-08 J No Data No Data No Data I No Data Br-85 No Data I No Data I 3.05E-09 i No Data No Data INo Data I No Data Rb-86 No Data j'2.98E-05 1.40E-05 No Data No Data No Data j 4.41 E-06 Rb-87 No Data l1.75E-05 6.11E-06 N No Data No Data 6.11E-07 Rb-88 No Data J 8.52E-08 4.54E-08 I No Data No Data No Data 7.30E-15 Rb-89 No Data 5.50E-08 13.89E-08 I No Data No Data No Data 8.43E-17 Sr-89 4.40E-04 No Data _1.26E-05 I No Data No Data No Data 5.24E-05 Sr-90 1.02E-02 I No Data I 2.04E-04 I No Data No Data No Data 2.33E-04 Sr-91 8.07E-06 No Data 3.21 E-07 { No Data No Data No Data i 3.66E-05 Sr-92 3.05E-06 No Data 1.30E-07 No Data No Data No Data ;7.77E-05 Y-90 1.37E-08 I No Data 3.69E-10 I No Data No Data No Data 11.13E-04 Y-91m I 1.29E-10 I No Data [4.93E-12 I No Data [No Data No Data I 6.09E-09 Y-91 _ 2.01 E-07 No Data g 5.39E-09 No Data No Data No Data I 8.24E-05 Y-92 1.21 E-09 j No Data [3.50E-1 1 No Data No Data No Data I3.32E-05 Y-93 3.83E-09 j No Data 1.05E-10 I No Data No Data No Data I 1.17E-04

() Data presented in this Table are from Reference 9.

A-31

PNPS-ODCM Rev. 9 TABLE A-16 (continued)

INGESTION DOSE FACTORS FOR TEEN( 1 )

mrem/pCi Inhaled B L Total Troidj ______ Lung Nuclide Bone Liver T I Kidney L I GI-LLI Zr-93 5.53E-08 2.73E-09 ! 1.49E-09 No Data I 9.65E-09 No Data i 2.58E-06 Zr-95 4.12E-08 1.30E-08 18.94E-09 No Data 1.91E-08 -No Data 3OOE-05 Zr-97 2.37E-09 4.69E-10 1 2.16E-10 No Data I 7.11 E-10 No Data 1.27E-04 Nb-93m 3.44E-08 1.13E-08 1 2.83E-09 j No Data 1.32E-08 No Data 4.07E-06 Nb-95 8.22E-09 4.56E-09 12.51E-09 I No Data 4.42E-09 No Data 1.95E-05 Nb-97 7.37E-1 1 1.83E-11 1 6.68E-12 No Data 2.14E-11 No Data 4.37E-07 Mo-93 No Data 1.06E-05 2.90E-07 No Data 3.04E-06 No Data 1.29E-06 Mo-99 No Data I 6.03E-06 1.15E-06 No Data 1.38E-05 No Data 1.08E-05 Tc-99m 3.32E-10 1 9.26E-10 i 1.20E-08 NoData I.38E-08 5.14E-10 6.08E-07 Tc-99 j 1.79E-07 i 2.63E-07 j 7.17E-08 I No Data i 3.34E-06 2.72E-08 6.44E-06 Tc-101 3.60E-10 l 5.12E-10 I 5.03E-09 No Data 9.26E-09 3.12E-10 l 8.75E-17 Ru-1 03 2.55E-07 INo Data 1.09E-07 No Data I 8.99E-07 No Data 2.13E-05 Ru-1 05 2.18E-08 I No Data 8.46E-09 No Data I 2.75E-07 No Data 1.76E-05 Ru-1 06 3.92E-06 i No Data j 4.94E-07 1 No Data I7.56E-06 No Data 1.88E-04 Rh-1 05 1.73E-07 1 .25E-07 I 8.20E-08 I No Data 15.31 E-07 No Data 1 .59E-05 Pd-1 07 No Data i 2.08E-07 11.34E-08 i No Data i 1.88E-06 No Data l 9.66E-07 Pd-1 09 No Data 2.51 E-07 5.70E-08 I No Data I 1.45E-06 I No Data I 2.53E-05 Aq-11 Om 2.05E-07 1.94E-07 .1.1 8E-07_ INo Data I 3.70E-07 l No Data l 5.45E-05 A-1 11 8.29E-08 3.44E-08 1.73E-08 No Data 1.1 2E-07 No Data I 4.80E-05 Cd-1 13m No Data 14.51 E-06 I1.45E-07 I No Data [4.99E-06 jNo Data 2.71 E-05 Cd-1 15m No Data 2.60E-06 8.39E-08 No Data 2.OBE-06 No Data 8.23E-05 Sn-123 4.44E-05 7.29E-07 1 1.08E-06 l 5.84E-07 No Data No Data 6.71E-05 Sn-125 1.9E-0 i 2.37E-07 1 5.37E-07 11.86E-07 j No Data No Data 1.12E-04 Sn-126 1.1i6E-04 2.16E-06 I 3.30E-06 l 5.69E-07 [No Data No Data 2.58E-05 Sb-1 24 13.87E-06 7.13E-08 11.51 E-06 ! 8.78E-09 No Data 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71 E-08 I 5.80E-07 [2.37E-09 [No Data 2.18E-06 1.93E-05 Sb-1 26 i 1.59E-06 3.25E-08 I 5.71 E-07 l8.99E-09 I No Data 1.14E-06 9.41 E-05 Sb-1 27 3.63E-07 7.76E-09 1.37E-07 l4.08E-09 ; No Data 2.47E-07 6.16E-05 Te-125m 3.83E-06 1.38E-06 j 5.12E-07 1.07E-06 INo Data No Data 1.13E-05 Te-127m 9.67E-06 3.43E-06 1 1.15E-06 I 2.30E-06 [3.92E-05 No Data 2.41 E-05 Te-127 I1.58E-07 5.60E-08 I 3.40E-08 i1.09E-07 1 6.40E-07 No Data 1.22E-05 Te-129m l 1.63E-05 6.05E-06 1 2.58E-06 I 5.26E-06 i 6.82E-05 No Data I 6.12E-05 Te-1 29 4.48E-08 7 1.67E-08 11.09E-08 1 3.20E-08 I 1.88E-07 No Data j 2.45E-07 Te-1 31 m i 2.44E-06 j 1.1i7E-06 9.76E-07 1.76E-06 I1.22E-05 No Data i 9.39E-05 Te-131 I2. 79E-08 1.15E-081 8.72E-09 i 2.15E-08 11.22E-07 No Data i2.29E-09 Te-132 j 3.49E-06 i 2.21 E-06 2.08E-06 i 2.33E-06 j 2.12E-05 No Data [7.OOE-05 Te-1 33m 6.44E-08 3.66E-08 l 3.56E-08 5.11 E-08 l 3.62E-07 No Data i 1.48E-07 Te-134 4.47E-08 2.87E-08 3.OOE-08 3.67E-08 l 2.74E-07 lNoData 1.66E-09 1-129 l 4.66E-06 3.92E-06 6.54E-06 I 4.77E-03 7.01E-06 No Data I 4.57E-07 1-130 1.03E-06 j2.98E-06 1.19E-06 i 2.43E-04 f 4.59E-06 No Data l 2.29E-06 1-131 I 5.85E-06 I 8.19E-06 I 4.40E-06 j 2.39E-03 1.41 E-05 No Data 1.62E-06 1-132 2.79E-07 l 7.30E-07 1 2.62E-07 1 2.46E-05 1 1.15E-06 INoData I 3.18E-07 1-133 J 2.01 E-06 3.41 E-06 11.04E-06 I 4.76E-04 5.98E-06 No Data j 2.58E-06 1-134 1.46E-07 3.87E-07 11.39E-07 I 6.45E-06 I 6.10E-07 No Data i 5.10E-09 1-135 i 6.10E-07 11.57E-06 1 5.82E-07 1 .01E-04 I 2.48E-06 I No Data I 1.74E-06

(') Data presented in this Table are from Reference 9.

A-32

PNPS-ODCM Rev. 9 TABLE A-16 (continued)

INGESTION DOSE FACTORS FOR TEENW')

mremlpCi Inhaled Total__

Nucside Bone 2E Liver Body Thvroid Kidney Lung GI-LLI Cs-134mn I 2.94E-08 6.09E-08 . 3.13E-08 j No Data I 3.39E-08 5.95E-09 _ 4.05E-08 Cs-134 8.37E-05 1.97E-04 9.14E-05 i No Data I 6.26E-05 2.39E-05 2.45E-06 Cs-135 2.78E-05 2.55E-05 5.96E-06 No Data 9.73E-06 3.52E-06 4.46E-07 Cs-136 8.59E-06 3.38E-05 2.27E-05 No Data 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 I 5.19E-05 i No Data 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 J 7.45E-08 No Data 1.10E-07 1.28E-08 6.76E-11 Cs-139 4.87E-08 7.17E-08 2.63E-08 No Data 5.79E-08 6.34E-09 3.33E-23 Ba-1 39 1.39E-07 9.78E-1 I 4.05E-09 No Data 9.22E-1 1 6.74E-1 1 1 .24E-06 Ba-140 2.84E-05 3.48E-08 i 1.83E-06 No Data 11.18E-08 2.34E-08 4.38E-05 Ba-141 - 6.71 E-08 5.01 E-11 I 2.24E-09 No Data I 4.65E-1 1 3.43E-11_ 1.43E-13 Ba-142 2.99E-08 12.99E-11 I 1.84E-09 I No Data I 2.53E-11I 1.99E-11 9.18E-20 La-140 3.48E-09 11.71 E-09 4.55E-10 ; No Data i No Data i No Data 9.82E-05 La-1 41 4.55E-10 ! 1.40E-10 I2.31E-11 l No Data ! No Data No Data 2.48E-05 La-i42 1.792-10 7.95E 1.98E-11 I No Data I No Data No Data 2.42E-06 Ce-1 41 1 1.33E-08 I 8.88E-09 I 1.02E-09 I No Data I 4.18E-09 No Data 2.54E-05 Ce-143 I 2.35E-09 1 1.71E-06 1.91 E-10 [ No Data l 7.67E-10 No Data 1.5.14E-05 Ce-i44 6.96E-07 I 2.88E-07 13.74E-08 I No Data 1.72E-07 No Data. 1.75E-04 Pr-143 1.312-08 5.23E-09 6.522-10 .No Data 3.042-09 No Data 4.31 E-05 Pr-144 4.30E-11i 1.76E-1i 2.1 BE-12 j No Data 11.01E-11 No Data 4.74E-14 Nd-1 47 9.38E-09 !1.02E-08 6.11E-10 J No Data a 5.992-09 No Data 3.68E-05 Pm-147 11.05E-07 I 9.96E-09 I 4.06E-09 No Data 1.90E-08 No Data 9.47E-06 Pm-148m 14.14E-08 1.05E-08 ! 8.21E-09 ! No Data I 1.59E-08 No Data 6.61E-05 Pm-148 1.02E-08 1.66E-09 [8.36E-10 I NoData I 3.002-09 NoData 9.902-05 Pm-149 I 2.17E-09 I 3.05E-10 1 1.25E-10 INo Data 15.81E-10 No Data 4.49E-05 Pm-151 _9.87-10 1.632-10 8.252-i1 No Data 2.932-10 No Data 3.662-05 Sm-151 j 8.73E-08 i 1.68E-08 j 3.94E-09 No Data t 1.84E-08 No Data 5.70E-06 Sm-153 1.22E-09 11.01E-09 t 7.43E-11 I No Data I 3.30E-10 No Data 2.85E-05 Eu-152 2.45E-07 5.90E-08 1 5.20E-08 J No Data 2.74E-07 No Data 2.17E-05 Eu-1 54 7.91E-07 1.1.02E-07 1 7.19E-08 j No Data 4.56E-07 No Data 5.39E-05 Eu-1 55 1.74E-07 1..68E-08 I 1.04E-08 No Data _ 6.57E-08 No Data 9.63E-05 Eu-1 56 1.92E-08 1.1.44E-08 2.35E-09 I No Data 9.69E-09 No Data 7.36E-05 Tb-1 60 6.47E-08 § No Data 8.07E-09 No Data 2.56E-08 No Data 4.19E-05 Ho-i66m I 1.10E-07 I 7.962-08 O3.572-07 j NoData 1.61E-07 No Data 2.71E-05 W-181 1.42E-08 _ 4.58E-09 14.79E-10 No Data No Data No Data 3.90E-07 W-185 * .79E-07 11 1E-07 i2.02E-08 No Data No Data No Data I 1.65E-05 W-187 1.46E-07 11.19E-07 I 4.17E-08 No Data No Data No Data _ 3.22E-05 Pb-21 0 1.812-02 5.44E-03 17.01E-04 No Data 1.72E-02 No Data [2.37E-06 Bi-210 l 6.59E-07 4.51E-06 13.77E-07 No Data 5.48E-05 No Data 5.15E-05 Po-21 0 5.09E-04 1.07E-03 I 1.23E-04 No Data I 3.60E-03 No Data 6.75E-05 Ra-223 0 7.11E-03 1.08E-05 11.42E-03 No Data 3.10E-04 No Data 3.43E-04 Ra-224 12.31 E-03 1 5.52E-06 14.61 E-04 No Data 1.58E-04 No Data 3.71 E-04 Ra-225 j 9.37E-03 11.10E-05 I 1.87E-03 I No Data I 3.15E-04 No Data 3.27E-04 Ra-226 1 3.22E-01 I 8.13E-06 12.39E-01 I No Data 2.32E-04 No Data 3.51 E-04 Ra-228 1.37E-01 14.41E-06 11.51E-01 No Data 11.26E-04 I No Data 5.98E-05 i Data presented in this Table are from Reference 9.

A-33

PNPS-ODCM Rev. 9 TABLE A-16 (continued)

INGESTION DOSE FACTORS FOR TEEN )

mrernlpCi Inhaled Nuclide Bone Liver Bod Thyroid l Kidne l Lung GI-LLI Ac-225 I 6.29E-06 8.59E-06 l 4.22E-07 No Data 9.85E-07 No Data l 4.36E-04 Ac-227 J 2.05E-03 3.03E-04 1.22E-04 I No Data 8.81E-05 No Data l-8.68E-05 Th-227 1.96E-05 3.52E-07 5.65E-07 No Data i 2.01E-06 No Data 5.75E-04 Th-228 J 6.80E-04 1.1 4E-05 2.30E-05 No Data J6.41 E-05 i No Data 5.97E-04 Th-229 i 1.43E-02 4.11 E-04 I 2.37E-04 No Data l 1.99E-03 l No Data 8.28E-05 Th-230 i 2.16E-03 1.23E-04 6.OOE-05 No Data I 5.99E-04 I No Data 6.38E-05 Th-232 i 2.42E-03 1.05E-04 j 1.63E-06 I No Data 1 5.11 E-04 i No Data 5.43E-05 Th-234 i 1.14E-07 6.68E-09 3.31 E-09 I No Data I 3.81E-08 j No Data 1.21 E-04 Pa-231 i 4.31 E-03 1.62E-04 1.68E-04 No Data 1 9.1 0E-04 No Data 1 7.60E-05 Pa-233 i 7.33E-09 1.41 E-09 1.26E-09 i No Data I 5.32E-09 No Data I1'1.61 E-05 U-232 i 5.89E-03 No Data 4.21 E-04 l No Data l 6.38E-04 No Data l 7.19E-05 U-233 i 1.24E-03 I No Data 7.54E-05 No Data I 2.90E-04 No Data I 6.65E-05 U-234 T 1.19E-03 l No Data 7.39E-05 No Data 2.85E-04 No Data J 6.51 E-05 U-235 1.14E-03 No Data 6.94E-05 No Data 2.67E-04 I No Data 8.28E-05 U-236 1.14E-03 l No Data 7.09E-05 No Data 2.73E-04 I No Data 6.11E-05 U-237 7.89E-08 i NoData J 2.10E-08 No Data j 3.24E-07 I No Data j 2.09E-05 U-238 1.09E-03 I No Data 6.49E-05 No Data I 2.50E-04 No Data 5.83E-05 Np-237 l 1.33E-03 9.55E-05 5.85E-05 No Data i 4.33E-04 No Data 8.41 E-05 Np-238 1.95E-08 5.22E-1 0 3.04E-10 No Data 1.79E-09 No Data 3.83E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 No Data 5.21E-10 No Data 2.67E-05 Pu-238 6.70E-04 8.58E-05 1.82E-05 No Data 7.80E-05 No Data 7.73E-05 Pu-239 7.65E-04 99.29E-05 l 2.01E-05 No Data 8.57E-05 No Data I 7.06E-05 Pu-240 7.64E-04 r 9.27E-05 2.01E-05 1No Data 1 8.56E-05 No Data 7.1 9E-05 Pu-241 1.75E-05 8.40E-07 3.69E-07 No Data 1.71 E-06 No Data I1.48E-06 Pu-242 l 7.09E-04 8.94E-05 8 1.94E-05 No Data i 8.25E-05 No Data 6.92E-05 Pu-244 l 8.28E-04 1 .02E-04 2.22E-05 No Data i 9.45E-05 No Data 1.03E-04 Am-241 ! 7.98E-04 7.53E-04 5.75E-05 No Data j 4.31E-04 No Data 7.87E-05 Am-242m J8.07E-04 7.11 E-04 5.80E-05 l No Data j 4.30E-04 l No Data 9.90E-05 Am-243 I 7.96E-04 7.35E-04 5.62E-05 No Data I 4.22E-04 j No Data 9.23E-05 Cm-242 T 2.94E-05 3.1 OE-05 I1.95E-06 No Data I8.89E-06 INo Data 8.40E-05 Cm-243 i 6.50E-04 6.03E-04 4.09E-05 ; No Data 311.91E-04 ; No Data 8.28E-05 Cm-244 5.04E-04 1 4.77E-04 3.19E-05 I No Data i .49E-04 No Data I 8.O4E-05 Cm-245 j 9.90E-04 8.71 E-04 ; 6.10E-05 j No Data 32.85E-04 No Data 7.46E-05 Cm-246 9.82E-04 J8.70E-04 I6.09E-05 INo Data 2.84E-04 No Data I7.33E-05 Cm-247 9.57E-04 8.57E-04. i 6.OOE-05 f No Data [2.80E-04 j No Data i 9.63E-05 Cm-248 l 7.95E-03 17.06E-03 4.95E-04 No Data I 2.31 E-03 -No Data j 1.55E-03 Cf-252 I 3.47E-04 I No Data I 8.37E-06 I No Data I No Data i No Data I 3.05E-04 (1)Data presented in this Table are from Reference 9.

A-34

PNPS-ODCM Rev. 9 TABLE A-17 INGESTION DOSE FACTORS FOR CHILD ')

mremlpCi Inhaled II I Total I I iI Nuclide Bone Liver lBody Throid Kidney Lung GI-LLI H-3 No Data I 1.16E-07 1.16E-07 I 1.16E-07 I 1.16E-07 1.16E-07 1.16E-07 Be-10 1.35E-05 1 .57E-06 3.39E-07 I No Data ; 1.11 E-06 No Data 2.75E-05 C-14 1.21 E-05 2.42E-06 2.42E-06 I 2.42E-06 1 2.42E-06 2.42E-06 2.42E-06 N-13 3.1 OE-08 j 3.10E-08 3.10E-08 i 3.10E-08 l 3.10E-08 3.1OE-08 3.1OE-08 F-1 8 2.49E-06 ! No Data 2.47E-07 ! No Data ! No Data No Data 6.74E-07 Na-22 5.88E-05 5.88E-05 5.88E-05 1 5.88E-05 [ 5.88E-05 5.88E-05 5.88E-05 Na-24 j 5.80E-06 5.80E-06 5.80E-06 j 5.80E-06 l 5.80E-06 5.80E-06 5.80E-06 P-32 l 8.25E-04 3.86E-05 3.18E-05 No Data ! No Data No Data 2.28E-05 Ca-41 3.47E-04 No Data 3.79E-05 No Data i No Data j No Data 1.90E-07 Sc-46 1.97E-08 2.70E-08 1.04E-08 No Data 1 2.39E-08 I No Data 3.95E-05 Cr-51 [No Data I No Data 8.90E-09 1 4.94E-09 j 1.35E-09 i 9.02E-09 4.72E-07 Mn-54 I No Data 1.07E-05 2.85E-06 No Data l 3.OOE-06 I No Data 8.98E-06 Mn-56 No Data 3.34E-07 7.54E-08 No Data I 4.04E-07 No Data 4.84E-05 Fe-55 1.15E-05 i 6.1OE-06 1.89E-06 j No Data I No Data 3.45E-06 i 1.13E-06 Fe-59 1 .65E-05 2.67E-05 i 1.33E-05 I No Data I No Data i 7.74E-06 2.78E-05 Co-57 No Data 4.93E-07 i 9.98E-07 l No Data l No Data No Data 4.04E-06 Co-58 I No Data 1 1.80E-06 15.51E-06 I No Data I No Data No Data 1.05E-05 Co-60 1NoDat I.56E-05 JNo Data No Data N 2.93E-05 Ni-59 4.02E-05 1.07E-05 7 6.82E-06 No Data No Data No Data ! 7.10E-07 Ni-63 j 5.38E-04 1 2.88E-05 1 1.83E-05 I No Data I No Data No Data I 1.94E-06 Ni-65 2.22E-06 J2.09E-07 .22E-07 ]No Data No Data No Data 2.56E-05 Cu-64 No Data ! 2.45E-07 T 1.48E.07 i No Data ! 5.92E-07 No Data 1.15E-05 Zn-65 1.37E-05 3.65E-05 12.27E-05 i No Data 2.30E-05 No Data 6.41 E-06 Zn-69m 7.10E-07 11.21 E-06 1.43E-07 ! No Data 7.03E-07 No Data 3.94E-05 Zn-69 I 4.38E-08 16.33E-08 15.85E-09 I NoData f 3.84E-08 No Data 3.99E-06 Se-79 No Data i 8.43E-06 i 1.87E-06 No Data 1.37E-05 No Data 5.53E-07 Br-82 I No Data I No Data 7.55E-06 I No Data I No Data No Data No Data Br-83 No Data JNo Data 1.71E-07 No Data [No Data No Data No Data Br-B4 l No Data I No Data 1.98E-07 No Data I No Data I No Data No Data Br-85 NoData] No Data l9.12E-09 l No Data No Data [NoData No Data Rb-86 I No Data 6.70E-05 14.12E-05 l No Data No Data No Data 4.31 E-06 Rb-87 No Data 1 3.95E-05 11.83E-05 No Data No Data No Data 5.92E-07 Rb-88 j No Data j 1.90E-07 11.32E-07 l No Data No Data No Data 9.32E-09 Rb-89 I No Data 1.17E-07 I 1.04E-07 I No Data I No Data I No Data I 1.02E-09 Sr-89 1.32E-03 No Data If3.77E-05 IfNo Data No Data No Data 5.1 1E-05 Sr-90 I 2.56E-02 , No Data j 5.15E-04 !No Data No Data ! No Data ! 2.29E-04 Sr-91 i 2.40E-05 I No Data I 9.06E-07 No Data No Data I No Data I 5.30E-05 Sr-92 9.03E-06 l No Data I 3.62E-07 j No Data I No Data I No Data 1.71 E-04 Y-90 I 4.11E-08 I No Data 1.1OE-09 ! No Data ! No Data ! No Data 1.17E-04 Y-91 m 3.82E-1 0 No Data 1.39E-1 1 INo Data No Data INo Data 7.48E-07 Y-91 i 6.02E-07 No Data 1.61 E-08 i No Data j No Data j No Data j 8.02E-05 Y-92 i 3.6OE-09 I No Data I1.03E-10 I No Data INo Data I No Data I 1.04E-04 Y-93 1.14E-08 I No Data I 3.13E-10 I No Data I No Data ! No Data 1.70E-04 (1)Data presented in this Table are from Reference 9.

A-35

PNPS-ODCM Rev. 9 TABLE A-17 (continued)

INGESTION DOSE FACTORS FOR CHILD ('

mrem/pCi Inhaled Nuclide Bone Liver o Thyroid l Kidney l Lung Gl-LLI Zr-93 1.67E-07 16.25E-09 4.45E-09 No Data 2.42E-08 No Data _ 2.37E-06 Zr-95 1.1 6E-07 2.55E-08 2.27E-08 No Data 3.65E-08 No Data 2.66E-05 .

Zr-97 6.99E-09 5.96E-1 0 No Data ! 1.45E-09 No Data 1.53E-04 Nb-93m 1.05E.07 j 2.62E-08 8.61 E-09 I No Data !2.83E-08 No Data 3.95E-06 Nb-95 J 2.25E-08 ! 8.76E-09 6.26E-09 No Data ! 8.23E-09 No Data 1.62E-05 Nb-97 2.17E-1 0 ! 3.92E-1 I 1.83E-11 No Data !4.35E-1i1 No Data 1.21 E-05 Mo-93 No Data 2.41 E-05 8.65E-07 No Data 6.35E-06 No Data 1.22E-06 Mo-99 t No Data 1.33E-05 3.29E-06 No Data 2.84E-05 No Data 1.1 OE-05 Tc-99m I 9.23E-1 0 1.81 E-09 3.00E-08 No Data 2.63E-08 9.19E-10 1.03E-06 Tc-99 5.35E-07 5.96E-07 2.14E-07 No Data 7.02E-06 5.27E-08 6.252-06 Tc-101 1.07E-09 11.12E-09 1.42E-08 No Data 1.91 E-08 j 5.92E-10 1_3.56E-09 Ru-103 7.31E-07 No Data 2.81E-07 No Data 1.84E-06 No Data 1.89E-05 Ru-105 6.45E-08 I No Data 2.34E-08 No Data 5.67E-07 No Data 4.21E-05 Ru-106 I1.17E-05 No Data 1.46E-06 No Data 1.58E-05 No Data 1.82E-04 Rh-105 5.14E-07 2.76E-07 2.36E-07 I No Data 1.10E-06 I No Data 1.71E-05 Pd-1 07 No Data I 4.72E-07 l 4.01 E-08 I No Data I 3.95E-06 No Data 9.37E-07 Pd-1 09 I No Data j 5.67E-07 11.70E-07 I No Data 1 3.04E-06 No Data 3.35E-05 Aa-i1 Om 5.39E-07 E07 12.91E-07 j No Data I 6.78E-07 -No Data 4.33E-05 Ag- 1 2.48E-07 r 7.76E-08 5.12E-08 No Data J 2.34E-07 No Data i 4.75E-05 Cd-1i13m No Data 1i.02E-05 4.34E-07 No Data 1.05E-05 No Data 2.63E-05 Cd-1 15m No Data j 5.89E-06 2.51E-07 No Data I 4.38E-06 No Data 8.01E-05 Sn-123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 No Data No Data 6.52E-05 Sn-125 3.55E-05 j 5.35E-07 1.59E-06 5.55E-07 No Data No Data 1.1 0E-04 Sn-126 I 3.33E-04 I 4.15E-06 9.46E-06 1.14E-06 No Data No Data 2.50E-05 Sb-1 24 1i.11E-05 I 1.44E-07 I 3.89E-06 2.45E-08 No Data 6.16E-06 6.94E-05 Sb-1 25 7.16E-06 15.52E-08 j 1.50E-06 6.63E-09 No Data 3.99E-06 1.71 E-05 Sb-126 i 4.40E-06 i 6.73E-08 I 1.58E-06 I 2.58E-08 No Data 2.10E-06 8.87E-05 Sb-127 1 1.06E-06 11.64E-08 1 3.68E-07 1.18E-08 [ No Data 4.60E-07 5.97E-05 Te-125m 1.14E-05 3.09E-06 i 1.52E-06 3.20E-06 No Data No Data 1.1 OE-05 Te-127m J 2.89E-05 J 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 No Data 2.34E-05 Te-127 I 4.71E-07 11.27E-07 11.01E-07 13.26E-07 1.34E-06 No Data 1.84E-05 Te-129m 4.87E-05 i 1.36E-05 7.56E-06 l 1.57E-05 1.43E-04 j No Data 5.94E-05 Te-129 I1.34E-07 13.74E-08 1 3.18E-08 9.56E-08 3.92E-07 ! No Data 8.34E-06 Te-i31m 7.20E-06 2.492-06 2.65E-06 5.122-06 2.41 E-05 No Data 1.01 E-04 Te-1 31 j 8.302-08 J 2.53E-08 _ 2.47E-08 6.35E-08 2.51E-07 No Data 4.36E-07 Te-132 I 1.01E-05 14.47E-06 5.40E-06 6.51E-06 4.15E-05 No Data 4.50E-05 Te-133m I 1.87E-07 1i7.56E-08 9.37E-08 1.45E-07 7.18E-07 No Data I 5.77E-06 Te-134 i 1.29E-07 15.80E-08 7.74E-08 i1.02E-07 j 5.37E-07 No Data 5.89E-07 1-129 1.39E-05 8.53E-06 7.62E-06 5.58E-03 1.44E-05 No Data I 4.29E-07 1-130 j 292E-06 J 5.90E-06 l 3.04E-06 l 6.50E-04 l 8.82E-06 No Data l 2.76E-06 1-131 11.72E-05 I 1.73E-05 9.83E-06 1 5.72E-03 12.84E-05 I No Data 154E-06

.I 1-132 8.00E-07 I 1.47E-06 6.76E-07 6.82E-05 2.25E-06 l No Data 1.73E-06 1-133 15.92E-06 17.32E-06 2.77E-06 1 .36E-03 1.22E-05 i No Data 2.95E-06 1-134 4.19E-07 17.78E-07 3.58E-07 11.79E-05 1.19E-06 No Data i 5.16E-07 1-135 1.75E-06 I 3.15E-06 1 1.49E-06 I 2.79E-04 4.83E-06 No Data 2.40E-06 Data presented in this Table are from Reference 9.

A-36

PNPS-ODCM Rev. 9 TABLE A-17 (continued) iNGESTION DOSE FACTORS FOR CHILD mrem/pCi Inhaled i § Total I I I Nuclide I Bone Liver Bod Thvroid Kidney lLung -LLI Cs-1 34m 8.44E-08 j 1.25E-07 8.16E-08 ! No Data ! 6.59E-08 1.09E-08 11.58E-07 Cs-134 2.34E-04 3.84E-04 8.10E-05 I No Data I 1.1 9E-04 4.27E-05 2.07E-06 Cs-1 35 8.30E-05 5.78E-05 5.93E-06 No Data i 2.04E-05 6.81 E-06 4.33E-07 Cs-136 2.35E-05 6.46E-05 4.1 8E-05 No Data I 3.44E-05 15.13E-06 2.27E-06 Cs-137 3.27E-04 I 3.13E-04 4.62E-05 iNo Data 1.02E-04 l 3.67E-05 1.96E-06 Cs-138 1 2.28E-07 13.17E-07 2.01 E-07 l No Data __ 2.23E-07 I 2.40E-08 11.46E-07 Cs-139 I 1.45E-07 1 1.61 E-07 7.74E-08 No Data 1.21 E-07 1.22E-08 1.45E-11 Ba-1 39 4.14E-07 12.21 E-1 0 1.20E-08 No Data 1.93E-1 0 1.30E-1 0 2.39E-05 Ba-1 40 8.31 E-05 7.28E-08 4.85E-06 No Data I 2.37E-08 4.34E-08 4.21 E-05 Ba-141 2.OOE-07 ! 1.12E-10 6.51E-09 No Data 9.69E-11 6.58E-1Q 1.14E-07 Ba-142 I 8.74E-08 I 6.29E-11 4.88E-09 No Data i 5.09E-1 1 3.70E-1i1 1.14E-09 La-1 40 1.01 E-08 3.53E-09 1.1 9E-09 No Data I No Data No Data 9.84E-05 La-141 1.36E-09 3.17E-10 6.88E-1 1 No Data No Data No Data 7.05E-05 La-i 42 5.24E-1 0 1.67E-10 5.23E-1 1 No Data j No Data No Data 3.31 E-05 Ce-1 41 3.97E-08 1.98E-08 2.94E-09 t No Data I 8.68E-09 No Data 2.47E-05 Ce-1 43 ! 6.99E-09 3.79E-06 5.49E-1 0 I No Data 1.59E-09 No Data If 5.55E-05 Ce-1 44 2.08E-06 6.52E-07 1.11 E-07 I No Data I 3.61 E-07 No Data 1 .70E-04 Pr-1 43 3.93E-08 1.18E-08 1.95E-09 No Data 6.39E-09 No Data I 4.24E-05 Pr-144 1.29E-101 3.99E-11 6.49E-12 No Data I 2.i1 E-1 1 No Data 8.59E-08 Nd-1 47 2.79E-08 2.26E-08 1.75E-09 No Data 1_.24E8 No Data 3.SBE-05 Pm-147 I 3.1 8E-07 2.27E-08 1.22E-08 I No Data 4.01 E-08 INo Data 1 9.19E-06 Pm-148m I 1.03E-07 12.05E-08 j 2.05E-08 I No Data I 3.04E-08 No Data 5.78E-05 Pm-148 3.02E-08 3.63E-09 2.35E-09 I No Data 6.17E-09 No Data [9.70E-05 Pm-1 49 6.49E-09 6.90E-101 3.74E-10 I No Data I1.22E-09 No Data I4.71E-05 Pm-1 51 2.92E-09 3.55E-10 2.31E-10 I No Data 6.02E-10 No Data 4.03E-05 Sm-1 51 2.56E-07 13.81E-08 i 1.20E-08 I No Data 3.94E-08 No Data 5.53E-06 Sm-1 53 3.65E-09 12.27E-09 i 2.19E-10 i No Data j 6.91E-10 No Data 3.02E-05 Eu-1 52 6.15E-07 i1.1i2E-07 i1.33E-07 I No Data 4.73E-07 No Data i184E-05 Eu-1 54 2.30E-06 12.07E-07 1.89E-07 I No Data 9.09E-07 No Data 4.81 E-05 Eu-1 55 4.82E-07 3.47E-08 2.72E-08 I No Data 1.30E-07 No Data 18.69E-05 Eu-1 56 I 5.62E-08 13.01 E-08 6.23E-09 I No Data ! 1.94E-08 I No Data 6.83E-05 Tb-1 60 11.66E-07 No Data 2.06E-08 I No Data I 4.94E-08 I No Data 3.68E-05 Ho-1 66m 1.08E-06 i 2.26E-07 1 1.91 E-07 I No Data 3.22E-07 I No Data j 2.63E-05 W-181 4.23E-08 1.04E-08 1.43E-09 l No Data No Data I No Data I 3.79E-07 W-185 1 .73E-06 4.32E-07 I 6.05E-08 I No Data No Data No Data 1.61 E-05 W-1 87 4.29E-07 2.54E-07 1.14E-07 I No Data No Data -No Data I 3.57E-05 Pb-210 4.75E-02 1.22E-02 I 2.09E-03 No Data 3.67E-02 No Data I 2.30E-06 Bi-210 I1.97E-06 11.02E-05 1 1.13E-06 No Data I1.15E-04 INo Data If5.17E-05 Po-210 I 1.52E-03 I 2.43E-03 3.67E-04 I No Data 7.56E-03 No Data I 6.55E-05 Ra-223 I 2.12E-02 i 2.45E-05 4.24E-03 No Data 6.50E-04 No Data i 3.38E-04 Ra-224 6.89E-03 j 1.25E-05 1.38E-03 j No Data 13.31 E-04 No Data l 3.78E-04 Ra-225 2.80E-02 i 2.50E-05 5.59E-03 I No Data I 6.62E-04 No Data I 3.21 E-04 Ra-226 5.75E-01 1 .84E-05 4.72E-01 No Data I 4.88E-04 No Data I 3.41 E-04 Ra-228 I 3.85E-01 19.99E-06 4.32E-01 I NoData I 2.65E-04 I No Data I 5.81 E-05 (1)Data presented in this Table are from Reference 9.

A-37

PNPS-ODCM Rev. 9 TABLE A-17 (continued)

INGESTION DOSE FACTORS FOR CHILD ()

mrem/pCi Inhaled I Total I I * .I I Nuclide Bone Liver Body Thyroid Kidney

' Lul GI-LLI Ac-225 1.88E-05 J 1.94E-05 1.26E-06 No Data j 2.07E-06 $ No Data 4.31E-04 Ac-227 4.12E-03 6.63E-04 12.55E-04 No Data l 1.46E-04 .j No Data 8.43E-05 Th-227 5.85E-05 7.96E-07 ! 1.69E-06

No Data 4.22E-06 No Data 5.63E-04 Th-228 2.07E-03 12.65E-05 7.00E-05 No Data 1.38E-04 No Data 5.79E-04 Th-229 2.35E-02 I 5.91 E-04 j 3.92E-04 No Data 2.89E-03 No Data . 8.04E-05 Th-230 3.55E-03 1 .78E-04 9.91 E-05 No Data 8.67E-04 No Data 6.19E-05 Th-232 3.96E-03 1.52E-04 3.01 E-06 No Data 7.41 E-04 No Data 5.27E-05 Th-234 ; 3.42E-07 1.51 E-08 9.88E-09 No Data 8.01 E-08 No Data 1.1 8E-04 Pa-231 7.07E-03 I 2.34E-04 2.81 E-04 No Data 1.28E-03 No Data 7.37E-05 Pa-233 1 1.81 E-08 I 2.82E-09 3.16E-09 No Data 1.04E-08 No Data 1.44E-05 U-232 ! 1.76E-02 No Data 1.26E-03 No Data 1.34E-03 No Data 6.98E-05 U-233 3.72E-03 No Data 2.25E-04 4 No Data 6.10E-04 No Data 6.45E-05 U-234 ! 3.57E-03 No Data 2.21E-04 I No Data j 5.98E-04 No Data 6.32E-05 U-235 1 3.42E-03 No Data 2.07E-04 No Data 5.61 E-04 o Data 8.03E-05 U-236 3.42E-03 No Data 2.12E.04 I No Data I 5.73E-04 No Data 5.92E-05 U-237 4 2.36E-07 I No Data f 6.27E-08 J No Data I 6.81 E-07 No Data 2.08E-05 V-238 J 3.27E-03 i No Data 1.94E-04 No Data I 5.24E-04 No Data 5.66E-05 Np-237 I 2.23E-03 I 1.47E-04

9.79E-05 No Data l 6.05E-04 No Data 8.16E-05 Np-238 5.83E-08 11.1 8E-09 . 9.08E-10 No Data 3.76E-09 No Data 4.04E-05

,Np-239 5.25E-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-05 Pu-238 1.1 9E-03 1.38E-04 3.16E-05 No Data 1.1 5E-04 No Data 7.50E-05 Pu-239 I 1.29E-03 1.38E-04 3.31E-05 I No Data 1.22E-04 No Data _6.85E-05 Pu-240 11.28E-03 f 1.43E-04 3.31 E-05 _No Data 1.22E-04 No Data 6.98E-05 Pu-241 I 3.87E-05 11.58E-06 8.04E-07 No Data 2.96E-06 No Data I 1.44E-06 Pu-242 1.19E-03 1.382-04_ 3.19E-05 No Data 1.17E-04 No Data j 6.71E-05 Pu-244 1.39-03_ 1.582-03 3.65E-05 j No Data 1.35E-04 No Data 1.00E-04 Am-241 1.36E-03 l 1.17E-03 1.02E-04 I No Data J 6.23E-04 No Data 7.64E-05 Am-242m 1.1.40E-03 1.12E-03 1 .04E-04 j No Data 6.30E-04 No Data 9.61E-05 Am-243 1.34E-03 1.13E-03 9.83E-05 l No Data 6.06E-04 No Data 8.95E-05 Cm-242 I 8.78E-05 17.01E-05 5.84E-06 I No Data 1.87E-05 No Data 8.1 6E-05 Cm-243 11.28E-03 11.04E-03 j 8.24E-05 ! No Data 3.08E-04 No Data 8.03E-05 Cm-244 I1.08E-03 18.74E-04 6.93E-05 I No Data I 2.54E-04 No Data 7.77E-05 Cm-245 L1.67E-03 11.34E-03 i1.05E-04 l No Data i 4.11 E-04 No Data l7.24E-05 Cm-246 I 1.65E-03 I 1.34E-03 1.1.05E-04 I No Data 1 4.10E-04 No Data 7.11E-05 Cm-247 1.61 E-03 ! 1.32E-03 11.03E-04 l No Data l 4.04E-04 No Data 9.35E-05 Cm-248 I 1.34E-02 1.09E-02 8.52E-04 I No Data 1 3.33E-03 No Data 1.51 E-03 Cf-252 11.05E-03 I No Data 1l2.54E-05 I No Data I No Data No Data 2.96E-04 (1)Data presented in this Table are from Reference 9.

A-38

PNPS-ODCM Rev. 9 TABLEi A-18 INGESTION DOSE FACTORS FOR INFANTM' mremlpCI Inhaled

! Bone Nuclide TotTali I-L

____I___ ier I' GILI H-3 No Data 1.76E-07 1i.76E-07 I1 .76E-07 I1 .76E-07 1.76E-07 11.76E-07 Be-1lO 1.71 E-05 I2.49E-06 j5.1 6E-07 j oDt Data lNo o aa 278E-05 C-14 2.37E-05 I5.06E-06 5.06E-06 I5.06E-06 I 5.06E-06 5.06E-06 I15.06E-06 N-13 5.85E-08 j5.85E-08 5.85E-08 J5.85E-08 If5.85E-08 5.85E-08 5.85E-08 F-l1 8 5.19E-06 INo Data j4.43E-07 .jNo Data No Data No Data 1.22E-06 Na-22 j9.83E-05 :[J 9.83E-~05 j9.83E-05 j9.83E-05 9.83E-05 9.83E-05 9.83E-05 Na-24 1.O1E-05 1.01E-05 j1.O1 E-05 I1.01 E-05 J1.O1 E-05 1.O1 E-05 1.O1 E-05 P-32 11.70E-03 1i.OOE2-04 I6.59E-05 INo Data INo Data jNo Data 2.30E-05 Ca-41 I3.74E-04 No Data 4.08E-05 No Data [No Data No Data 1.91 E-07 Sc-46 3.75E-08 I5.41 E-08 I .69E-08 INo Data I3.56E-08 No Data 3.53E-05 Cr-5i1 No Data JNo Data If1.41 E-08 If9.20E-09 'F2.01 E-09 1.79E-08 4.1 1E-07 Mn-54 jNo Data I1.99E-05 4.51 E-06 INo Data. I4.41 E-06 No Data j 7.31 E-06 Mn-56 INo Data 18.1 8E-07 I1.41 E-07 INo Data If7.03E-07 No Data 7.43E-05 Fe-55 If1.39E-05 If .98E-06 j2.40E-06 jNo Data jNo Data I4.39E-06 J1.14E-06 Fe-59 I3.OSE-05 I5.38E-05 I2.12E-05 INo Data No Data I1.59E-05 I2.57E-05 Co-57 Co-58 Co-60 fNoNo Data Data

-NoData J1.15E-06 ~1 87E-~06 jNo Data JNo Data I3.60E-06 8.98E.06 No Data INo Data 11.08E-05 j2.55E-05 No Data 1No Data

.No Data No Data No Data 3.92E-06 I8.97E-06 I2.57E-05 Ni-59 j4.73E-05 1.45E-05 j8.1 7E-06 No Data JNo Data No Data 7.1 6E-07 Ni-63 6.34E-04 3.92E-05 2.20E-05 jNo Data INo Data No Data 1.95E-06 Ni-6S 4.70E-06 j5.32E-07 2.42E-07 jNo Data 1No Data No Data 4.OSE-05 Cu-64 No Data I6.09E-07 I2.82E-07 No Data I1 .03E-06 No Data 1.25E-05 Zn-65 1.84E-05 6.31 E-05 f2.91 E-05 IfNo Data j3.06E-05 No Data 5.33E-05 Zn-69m 1.50E-06 3.06E-06 j2.79E-07 jNo Data 11.24E-06 No Data 4.24E-05 Zn-69 9.33E-08 1.68E-07 1i.25E-08 I No Data I 6.9BE-08 No Data 1.37E-05 Se-79 No Data 2.10OE-05 43.90E-06 jNo Data 2.43E.05 No Data 5.58E-07 Br-82 No Data No Data 1i.27E-05 INo Data INo Data No Data No Data Br-83 No Data No Data If3.63E-07 IfNo Data No Data No Data No Data Br-84 No Data INo Data J,3.82E-07 No Data -No-Data No Data No Data I I Br-85 Rb-86 Rb-87 f No Data No Data No Data j oData 11.70E-04 I .88E-05 11.94E-08 8.40E-05 3.52E-05 No Data No Data IfNo Data No Data No Data No-Data No Data No Data No Data J 4.35E-06 No Data If5.98E-07 Rb-88 IfNo Data j4.98E-07 2.73E-07 No Data No Data INo Data I4.85E-07 Rb-89 Sr-89 jNo Data 2.51 E-03 I2.86E-07 I1I.97E-07 IfNo Data No~~ Dat 7.20E-05 IfNo Data No Data No Data IfNo Data If9.74E-08 IfNo Data 45.16GE-05 Sr-90 12.83 E-02 IfNo Data 15.74 E-04 No Data No Data INo Data I2.31 E-04 Sr-91 j5.0OE-05 I No Data 11.81 E-06 If NoDa~ta INo Data No Data If5.92E-05 Sr-92 j1.92E-05 IfNo Data 17.1 3E-07 1.No Data jjNo Data No Data If2.07E-04 Y-90 8.69E-08 No Data I2.33E-09 INo Data INo Data No Data 1.20E-04 Y-91 m 8.10QE-lO0I No Data j2.76E-1 1 INo Data IfNo Data No Data j2.70E-06 Y-91 J1.13E-06 IfNo Data J3.01 E-08 No Data INo Data No Data j8.1 OE-05 Y-92 j7.65E-09 IfNo Data J2.15E-1 0 INo Data IfNo Data No Data j1.46E-04 Y-93 I2.43E-08 I No Data 6.62E-1O0 No Data No Data No Data I1.92E-04

()Data presented in this Table are from Reference 9.

A-39

PNPS-ODCM Rev. 9 TABLE A-18 (continued)

INGESTION DOSE FACTORS FOR INFANTO) mrem/pCi Inhaled Nuclide Il

_______ BoneTotal LUver

_Bone l BodThyroid Kidney l Lung G-L G-LLI Zr-93

1.93E-07 9.19E-09 5.54E-09 No Data 2.71E-08 i No Data 2.39E-06 Zr-95 2.06E-07 5.02E-08 3.56E-08 No Data J5.41 E-08 No Data 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 No Data I 2.56E-09 No Data 1.62E-04 Nb-93m 1.23E-07 3.33E-08 1.04E-08 No Data 3.25E-08 No Data 3.98E-06 Nb-95 4.20E-08 1.73E-08 1.OOE-08 l No Data 1.24E-08 No Data 1.46E-05 Nb-97 4.59E-10 9.79E-11 3.53E-11 I No Data 7.65E-1 1 No Data 3.09E-05 Mo-93 No Data 5.65E-05 1.82E-06 No Data 1.13E-05 No Data 1.21 E-06 Mo-99 No Data 3.40E 6.63E-06 No Data 5.0BE-05 No Data 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.1OE-08 No Data T4.26E-08 2.07E-09 1.15E-06 Tc-99 1.08E-06 1.46E-06 I 4.55E-07 No Data 11.23E-05 1.42E-07 631 E-06 Tc-101 2.27E-09 2.86E-09 !2.83E-08 No Data 3.40E-08 1.56E-09 4.86E-07 Ru-1 03 1.48E-06 No Data j 4.95E-07 No Data 3.08E-06 No Data No Data 1.80E-05 5.41 E-05 Ru-1 05 1.36E-07 No Data 4.58E-08 No Data 1 .00E-06 Ru-106 2.41 E-05 No Data 1 3.01E-06 No Data 2.85E-05 No Data 1.83E-04 Rh-105 1.09E-06 7.13E-07 4.79E-07 ! No Data I 1.98E-06 No Data 1.77E-05 Pd-107 No Data l 1.192-06 18.45E-08 j No Data i 6.79E-06 No Data 9.46E-07 Pd-109 No Data 1.50E-06 I 3.62E-07 No Data 5.51E-06 No Data 3.68E-05 Ag-110m 9.96E-07 7.27E-07 4.81 E-07 No Data 1.04E-06 No Data 3.77E-05 Ag-111 5.20E-07 2.02E-07 1.07E-07 No Data 4.22E-07 No Data 4.82E-05 Cd-1i 3m No Data 1.77E-05 6.52E-07 No Data 1.34E-05 No Data 2.66E-05 Cd-1 15m No Data I 1.42E-05 4.93E-07 No Data j 7.41E-06 No Data 8.09E-05 Sn-123 I 2.49E-04 1 3.89E-06 6.50E-06 13.91E-06 I No Data -No Data 6.58E-05 Sn-125 7.41E-05 11.38E-06 3.29E-06 11.36E-06 1 No Data No Data j 1.11E-04 Sn-126 I 5.53E-04 J 7.26E-06 11.80E-05 1.91E-06 I No Data No Data 2.52E-05 Sb-1 24 2.14E-05 i 3.15E-07 16.63E-06 I 5.68E-08 I No Data 1.34E-05 6.60E-05 Sb-1 25 1.23E-05 1.19E-07 12.53E-06 11.54E-08 I No Data 7.12E-06 1.64E-05 Sb-126 8.06E-06 I 1.58E-07 2.91E-06 I 6.19E-08 l No Data 5.07E-06 8.35E-05 Sb-127 J 2.23E-06 13.98E-08 16.90E-07 12.84E-08 [No Data 1.15E-06 5.91 E-05 Te-125m 1 2.33E-05 1 7.79E-06 1 3.15E-06 1 7.84E-06 No Data No Data 11.11E-05 Te-127m 1 5.85E-05 1.94E-05 7.08E-06 [1.69E-05 1.44E-04 No Data 2.36E-05 Te-127 I1.00E-06 i 3.35E-07 2.15E-07 8.14E-07 1 2.44E-06 No Data 2.10E-05 Te-129m [1.00E-04 ! 3.43E-05 1.54E-05 3.84E-05 12.50E-04 No Data 5.97E-05 Te-129 2.842-07 9.792-08 6.63E-08 12.38E-07 17.07E-07 No Data 2.27E-05 Te-131m 1.52E-05 1 6.12E-06 5.05E-06 1.24E-05 14.21E-05 No Data 1.03E-04 Te-131 . 1.76E-07 i 6.50E-08 4.94E-08 1.57E-07 j_4.50E-07 No Data 7.11E-06 Te-132 2.08E-05 11.03E-05 9.61E-06 j 1.52E-05 [6.44E-05 No Data 3.81E-05 Te-133m - 3.91 E-07 I 1.79E-07 1.71E-07 -3.45E-07 11.22E-06 No Data 1.93E-05 Te-134 2.67E-07 11.34E-07 11.38E-07 2.39E-07 9.03E-07 No Data 3.06E-06 1-129 2.86E-05 2.12E-05 11.55E-05 11.36E-02 12.51E-05 No Data 4.24E-07 1-130 - 6.00E-06 11.32E-05 5.302-06 l 1.48E-03 11.45E-05 No Data 2.83E-06 1-131 3.59E-05 14.232-05 1.862-05 1.392-02 4.942-05 No Data 1.51E-06 1-132 1.66E-06 13.37E-06 1.20E-06 1.58E-04 13.76E-06 No Data 2.73E206 1-133 1.25E-05 11.82E-05 5.33E-06 3.31 E-03 i 2.14E-05 No Data 3.08E-06 1-134 8.69E-07 1.78E-06 I 6.33E-07 4.15E-05 11.99E-06 No Data 1.84E206 1-135 3.64E-06 17.24E-06 1 2.64E-06 16.49E-04 1 8.07E-06 No Data 2.622-06

)

Data presented in this Table are from Reference 9.

A-40

PNPS-ODCM Rev. 9 TABLE A-18 (continued)

INGESTION DOSE FACTORS FOR INFANT(')

mremlpCi Inhaled Nuclide Bone Liver Bod Thyroid l Kidney l Lun Gl-LLI Cs-134m 1.76E-07 i 2.93E-07 I 1.48E-07 I No Data I1.13E-07 2.60E-08 1 2.32E-07 Cs-134 ; 3.77E-04 j 7.03E-04 7.10E-05 No Data 1i.81 E-04 7.42E-05 1.91 E-06 Cs-1 35 11.33E-04 11.21 E-04 6.30E-06 No Data 3.44E-05 1.31E-05 1 4.37E-07 Cs-1 36 j 4.59E-05 1.35E-04 [5.04E-05 I No Data 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11 E-04 4.33E-05 ! No Data 1.64E-04 6.64E-05 1.91 E-06 Cs-i38 4.81 E-07 17.82E-07 3.79E-07 I No Data 3.90E-07 6.09E-08 1 .25E-06 Cs-1 39 3.10E-07 4.24E-07 1.62E-07 I No Data 2.19E-07 3.30E-08 2.66E-08 Ba-1 39 8.81 E-07 ! 5.84E-1 0 2.55E-08 0 No Data 3.51 E-1 0 3.54E-10 5.58E-05 Ba-1 40 1.71 E-04 1.71 E-07 8.81 E-06 No Data 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 I 2.91E-10 1.34E-08 i No Data 1.75E-10 1.77E-10 5.19E-06 Ba-1 42 1.84E-07 1.53E-1 0 9.06E-09 l No Data 8.81 E-1 1 9.26E-1 1 7.59E-07 La-1 40 I 2.11E-08 8.32E-09 1 2.14E-09 I No Data I-No Data No Data 9.77E-05 La-141 I 2.89E-09 8.38E-10 i 1.46E-10 I No Data I No Data I NoData 9.61E-05 La-1 42 1.10E-09 4.04E-10 j 9.67E-11 j No Data 2 No Data No Data 6.86E-05 Ce-141 I 7.87E-08 14.80E-08 I 5.65E-09 I No Data I 1.48E-08 No Data 2.48E-05 Ce-143 _ 1.48E-08 9.82E-06 1 1.12E-09 I No Data I 2.86E-09 No Data 5.73E-05 Ce-144 j 2.98E-06 ! 1.22E-06 j 1.67E-07 No Data I 4.93E-07 No Data 1.71 E-04 Pr-1 43 j 8.13E-08 3.04E-08 1 4.03E-09 No Data ! 1.13E-08 No Data j 4.29E-05 Pr-1 44 2.74E-10 11.06E-10 1.38E-11 i No Data I 3.84E-1 1 No Data 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 ! No Data 1 2.19E-08 No Data 3.60E-05 Pm--147 3.88E-07 3.27E-08 1.59E-08 I No Data I 4.88E-08 No Data 9.27E-06 Pm-148m 1.65E-07 I 4.18E-08 I 3.28E-08 No Data I 4.80E-08 No Data 5.44E-05 Pm-1 48 6.32E-08 I 9.13E-09 4.60E-09 No Data 1.09E-08 No Data 9.74E-05 Pm-149 1.38E-08 1 1.81 E-09 7.90E-10 No Data 2.20E-09 No Data 4.86E-05 Pm-151 6.18E-09 1 9.01 E-10 I 4.56E-10 No Data 1.07E-09 No Data _ 4.17E-05 Sm-151 j 2.90E-07 16.67E-08 1.44E-08 No Data 4.53E-08 No Data I 5.58E-06 Sm-153 1 7.72E-09 i 5.97E-09 4.58E-10 No Data 1.25E-09 No Data 3.12E-05 Eu-1 52 i 6.74E-07 1i.79E-07 i1.51E-07 1 No Data 5.02E-07 j No Data i.59E-05 Eu-1 54 2.64E-06 j 3.67E-07 2.20E-07 j No Data ! 9.95E-07 I No Data I 4.58E-05 Eu-155 5.42E-07 1 6.25E-08 3.23E-08 No Data 1.40E-07 No Data 8.37E-05 Eu-1 56 1.14E-07 7.06E-08 1.12E-08 j No Data 3.26E-08 No Data 6.67E-05 Tb-1 60 2.59E-07 1No Data I 3.24E-08 I No Data I 7.37E-08 I No Data 3.45E-05 Ho-1 66m 1.25E-06 2.69E-07 J 2.13E-07 j No Data j 3.57E-07 1 No Data i2.66E-05 W-1 81 8.852-08 2.72E-08 I 3.04E-09 ! No Data I No Data No Data 3.82E-07 W-185 f 3.62E-06 l 1.13E-06 1.29E-07 ! No Data I NoData No Data 1.62E-05 W-187 1 9.03E-07 6.28E-07 2.17E-07 I No Data I No Data No Data 3.69E-05 Pb-210 7 5.282-02 i1.42E-02 2.38E-03 l No Data 1 4.33E-02 No Data 2.32E-06 Bi-21 0 _ 4.16E-06 j 2.68E-05 i 2.39E-06 No Data 2.08E-04 No Data 5.27E-05 Po-210 3.1 OE-03 1 5.93E-03 7.41 E-04 I No Data I 1.26E-02 No Data 6.61E-05 Ra-223 4.41 E-02 6.42E-05 8.82E-03 No Data 1.17E-03 No Data 3.43E-04 Ra-224 I 1.46E-02 1 3.29E-05 2.91E-03 I NoData I 6.OOE-04 I No Data 3.86E-04 Ra-225 5.782-02 J 6.52E-05 1.15E-02 j No Data j 1.192-03 No Data 3.24E-04 Ra-226 6.20E-01 4.76E-05 5.14E-01 No Data ! 8.71 E-04 No Data 3.44E-04 Ra-228 4.32E-01 1 2.58E-05 4.86E-01 i No Data I 4.73E-04 I No Data 5.86E-05 (1) Data presented in this Table are from Reference 9.

A-41

PNPS-ODCM Rev. 9 TABLE A-18 (continued)

INGESTION DOSE FACTORS FOR INFANT(')

mremlpCi Inhaled Nuclide Bone l Liver To Thyroid Kidny Lung G-LLI Ac-225 ! 3.92E-05 5.03E-05 I 2.63E-06 No Data 3.69E-06 No Data 4.36E-04 Ac-227 4.49E-03 I 7.67E-04 2.79E-04 No Data 1.56E-04 No Data 8.SOE-05 Th-227 1.20E-04 12.01 E-06 3.45E-06 No Data 7.41 E-06 No Data 5.70E-04 Th-228 2.47E-03 1 3.38E-05 8.36E-05 No Data 1.58E-04 No Data 5.84E-04 Th-229 2.52E-02 i 6.33E-04 4.20E-04 No Data 3.03E-03 No Data 8.1 OE-05 Th-230 I 3.80E-03 l 1.90E-04 1.06E-04 No Data 9.12E-04 No Data _ 6.24E-05 Th-232 4.24E-03 1.63E-04 1.65E-06 I No Data 7.79E-04 No Data 5.31 E-05 Th-234 _ 6.92E-07 i 3.77E-08 2.OOE-08 i No Data 1.39E-07 No Data -1.19E-04 Pa-231 J7.57E-03 2.50E-04 3.02E-04 J No Data I 1.34E-03 No Data 7.44E-05 Pa-233 I 3.11 E-08 6.09E-09 5.43E-09 I No Data 1.67E-08 No Data 1.46E-05 U-232 I 2.42E-02 No Data 2.16E-03 I No Data 2.37E-03 No Data _ 7.04E-05 U-233 5.08E-03 NoData 3.87E-04 No Data l 1.08E-03 No Data I 6.51 E-05 U-234 4.88E-03 No Data 3.80E-04 I No Data I 1.06E-03 No Data _ 6.37E-05 U-235 4.67E-03 No Data 3.56E-04 I No Data I 9.93E-04 No Data 18.1 OE-05 f No Data i 3.64E-04 I No Data U-236 U-237 U-238 4.67E-03 4.95E-07 4.47E-03 l No Data I No Data i 1.32E-07 3.33E-04 J No Data No Data 1.01 E-03 11.23E-06 i 9.28E-04

[

No Data No Data I No Data 5.98E-05 2.11E-05 5.71 E-05 Np-237 2.40E-03 ! 1.59E-04 1.05E-04 No Data !6.34E-04 l No Data 8.23E-05 Np-238 1.24E-07 3.12E-09 1.92E-09 No Data I6.81E-09 No Data 4.17E-05 Np-239 1.11 E-08 9.93E-10 1 5.61 E-1 0 I No Data 1.98E-09 No Data 2.87E-05 Pu-238 1 .28E-03 1i.50E-04 3.40E-05 I No Data 1.1.21 E-04 No Data 7.57E-05 Pu-239 j 1.38E-03 j 1.55E-04 3.54E-05 j No Data 1i.28E-04 No Data 6.91E-05 Pu-240 I 1.38E-03 1 1.55E-04 13.54E-05 I No Data 1.28E-04 No Data 7.04E-05 Pu-241 _ 4.25E-05 11.76E-06 8.82E-07 I No Data 3.17E-06 No Data 1 .45E-06 Pu-242 _1 1.28E-03 Pu-244 Am-2412 1.49E-03 1.46E-03 I 1.49E-04 13.41 E-05 I No Data 1 1.71E-04 1.27E-03 3.91E-05 i No Data 1.09E-04 I No Data 1.23E-04 1.41E-04 6.55E-04 1 No Data No Data No Data 6.77E-05 1.01E-04 7.70E-05 Am-242m 1.51 E-03 1 .2 E-03 I 1.13E-04 I No Data 6.64E-04 No Data 9.69E-05 Am-243 1.44E-03 .1.23E-03 1 .06E-04 ! No Data 6.36E-04 No Data ! 9.03E-05 Cm-242 1.37E-04 I1.27E-04_1 9.10E-06 I No Data 2.62E-05 No Data 8.23E-05 Cm-243 1.40E-03 I 1.15E-03 1 8.98E-05 No Data 3.27E-04 No Data 8.1 OE-05 Cm-244 I 1.18E-03 I9.70E-04 I 7.59E-05 I No Data 2.71 E-04 No Data 7.84E-05 Cm-245 1.79E-03 1.45E-03 i1.13E-04 I No Data 4.32E-04 No Data 7.30E-05 Cm-246 1.77E-03 I I 1.45E-03 1 1.13E-04 No Data 44.31 E-04 No Data 7.17E-05 Cm-247 I 1.73E-03 j .43E-03 1.1 IE-04 j No Data 4.24E-04 No Data 9.43E-05 Cm-248 1.43E-02 ! 1.18E-02 I 9.16E-04 L No Data 1 3.50E-03 No Data 1.52E-03 Cf-252 1.22E-03 I No Data I 2.95E-05 INo Data I No Data No Data 2.99E-04 1)Data presented in this Table are from Reference 9.

A-42

PNPS-ODCM Rev. 9 TABLE A-1 9 RECOMMENDED VALUES FOR GASEOUS EFFLUENTS (1)

Parameter Symbol Parameter Description Values S Attenuation factor that accounts for 0.7 (maximum individual) the shielding provided by residential 0.5 (average individual.)

structures 1.0 (noble gas-gamma instantaneous dose) (2) te Time period that crops are exposed to contamination during growing season i) for forage ingested by animals 720 hrs (30 days, for pasture grass) 1440 hr (60 days for stored feed) I,"

ii) for crops ingested by man 1440 hrs (60 days) tf Average transport time of activity 48 hr (2 days, maximum individual) from the feed into the milk and to the 96 hr ( 4 days, average individual) receptor th Time delay between harvest of vegetation or crops and ingestion i) for forage ingested by animals Zero (for pasture grass) 2160 hr (90 days for stored feed) ii) for crops ingested by man 24 hr (1 day, for leafy vegetables & max.

individual) 1440 hr (60 days, for produce & max.

individual) 336 hr (14 days, for average individual)

Yv Agricultural productivity by unit area (measured in wet weight) i) for forage ingested by animals 0.42 kg/M2 (for pasture grass) (3) 2.5 kg/M 2 (for stored feed) (3) ii) for crops ingested by man 2.0 kg/M 2 (1)All data presented in this table are from Reference 8, unless otherwise indicated.

(2) From Reference 12.

(3) From Reference 4.

A-43

PNPS-ODCM Rev. 9 APPENDIX B DEFINITION OF THE LOWER LIMIT OF DETECTION For purposes of analyzing effluents and environmental samples for radioactivity, the lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability, with only 5%probability of falsely concluding that a blank observation represents a "real" signal.

It should be recognized that the listed LLD is defined as an a Priori (before the fact) limit representing the capability of the measurement system or analytical process, and not as an a posteriori (after the fact) limit for a particular measurement. Analyses should be performed in such a manner that the stated LLDs will be achieved under routine conditions. Usually, samples are counted for a period of time sufficient to ensure that the listed LLDs, based on normal analytical and counting parameters, are achieved.

Printouts of analytical results typically list the a posterion minimum detectable concentration (MDC) which was actually achieved on a particular measurement. In those cases where a given sample MDC is less than or equal to the listed a priori LLD, the required LLD has been achieved.

Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering radionuclides, or other uncontrollable circumstances may result in the MDC for a particular measurement not meeting the listed LLD. In such cases, the contributing factors shall be identified and described in the Semiannual Radioactive Effluent and Waste Disposal Report (for effluents) or the Annual Radiological Environmental Monitoring Report (for environmental samples).

The value of the counting standard deviation (sb) used in the calculation of the LLD for a particular measurement system should be based on the actual observed standard deviation of the background counting rate or of the counting rate of an appropriate blank sample, rather than on an unverified, theoretically-predicted variance. One acceptable method for deriving sb is as follows:

Sb = F//

where:

Sb = standard deviation of the background counting rate or of the counting rate of an appropriate blank sample (counts/minute);

B = background counting rate or counting rate of an appropriate blank sample (counts/minute);

T = counting time interval for sample analysis (minutes).

B-1

PNPS-ODCM Rev. 9 Lower Limit of Detection For Effluent Samples For a particular measurement system or analytical process which may include radiochemical separation used to analyze effluent samples, the lower limit of detection is calculated as follows:

LLD = 4.66 Sb E V 222E6 Y e-At where:

LLD1 = a Priori lower limit of detection for radionuclide i, (giCVmL or gC/g);

4.66 = combined numerical constant corresponding to 95% probability of detection, with 5% probability of falsely identifying background as a "real" signal; Sb = standard deviation of the background counting rate or of the counting rate of an appropriate blank sample, (counts/minute);

E = counting efficiency, (counts/disintegration);

V = sample size, (milliliters or grams);

2.22E6 = conversion factor for disintegrations/minute per 0Ci; Y = fractional radiochemical yield, when applicable; Ax = radioactive decay constant for radionuclide i, (hr 1 );

t = elapsed time between the midpoint of sample collection and time of counting, (hr).

Typical values of E, V, Y, and t used for normal effluent sample analyses should be used in this calculation.

B-2

PNPS-ODCM Rev. 9 Lower Limit of Detection For Environmental Samples For a particular measurement system or analytical process which may include radiochemical separation used to analyze effluent samples, the lower limit of detection is calculated as follows:

LLD. - 4.66 Sb EV222 YeX"t where:

LLDI = a Drior lower limit of detection for radionuclide i, (pCiliter, pCi/m3, or pCVkg);

4.66 = combined numerical constant corresponding to 95% probability of detection, with 5% probability of falsely identifying background as a 'real" signal; Sb = standard deviation of the background counting rate or of the counting rate of an appropriate blank sample, (counts/minute);

E = counting efficiency, (counts/disintegration);

V = sample size, (liters, cubic meters, or kilograms);

2.22 = conversion factor for disintegrations/minute per pCi; Y = fractional radiochemical yield, when applicable; Ale = radioactive decay constant for radionuclide i, (hr- 1 );

t = elapsed time between environmental sample collection or end of the sample collection period, and time of counting, (hr).

Typical values of E, V, Y, and t used for normal effluent sample analyses should be used in this calculation.

B-3

PNPS-ODCM Rev. 9 APPENDIX C NRC SAFETY EVALUATION FOR ONSITE DISPOSAL OF SLIGHTLY CONTAMINATED CONSTRUCTION SOIL In May 1993, the NRC approved a permit under 10CFR20.302 to allow Boston Edison Company to dispose of construction soil containing small amounts of cobalt-60 and cesium-1 37. This soil was disposed of via onsite burial at a location on company property adjacent to the Pilgrim Station meteorological tpwer. Dose calculations performed as part of the permit application and within the NRC Safety Evaluation concluded that the maximum dose from the disposal area would be less than 0.1 mrem/year during the year of disposal. Doses during subsequent years through the time of site decommissioning would be less than 0.01 mrem/year. Such exposure levels are considered insignificant relative to radiation dose arising from naturally-occurring sources of radiation and radioactivity, and other exposure pathways arising from operation of Pilgrim Nuclear Power Station.

Complete details regarding the NRC permit for disposal, and the accompanying NRC Safety Evaluation, can be found in NRC Docket No. 50-293, "APPROVAL UNDER 10CFR20.302(a)

RELOCATION AND PLACEMENT OF CONSTRUCTION SOIL WITH TRACES OF RESIDUAL RADIOACTIVITY ON SITE AT PILGRIM NUCLEAR POWER STATION (TAC NO. M85501)",

dated May 4, 1993.

C-1

ML041400430

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