ML20206F680

Rev 0 to 6575-PLN-4542.08, ODCM, for SNEC

ML20206F680
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Site:	Saxton File:GPU Nuclear icon.png
Issue date:	04/22/1998
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ML20206F649	List: ML20206F645 ML20206F669 ML20206F680
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6575-PLN-4542.0, NUDOCS 9905060207
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. ' ..e Number Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 8575-PLN-4542.08 TIio Revmon No.

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SNEC Facility Offsite Dose Calculation Manual 0 aM/Soope Calcusses offets donos due to resoectue emuente for Responeme Omco Effechve Date demonstrenne comptance wth See Tochrhi specmcebons to CFR 20 &

10 CFR 50. Appendk 1 6575 04/23/98 This document is within QA plan scope X Yes No Safety Reviews Required X Yes No Ust of Effective Pages Eagt Revision Eagg Revision Eagg Revision Eagg . Revision 1: 0 17 0 33 0 49 0 l 2 0 18 0 34 0 50 0  ;

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8 4 Number SaMon Nuclear Sperin1 ental Comoration SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tme Revisen No.

SNEC Facility Offsite Dose Calculation Manual 0 List of Effective Pages (Cont'd)

Eggg Revision Eggg Revision Easte Revision Eaag Revision 45 0 66 0 67 0 68 0 69 0 70 0 71 0 72 0 73 0 74 0 75 0 76 0 77 0 78 0 79 0 80 0 81 0 82 0 83 0 84 0 85 0 86 0 87 0 88 0 89 0 90 0 91 0 92 0 93 0 94 0 95 0 GPUN 00CUUCNT CCNTROL 1 CoelTROLLED COPY k 2 39180.00C

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Number SAXTON NUCLEAR SaMon Nuclear Egenmental CopMon Fadlity Policy and Procedure Manual 6575 PLN 4542.08 Tee Romeen No.

SNEC Facility Offsite Dose Calculation Manual 0 l

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Number Saxton Nudear Expenmental Co@ ration SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tae Roweson No.

SNEC Facility Offsite Dose Calculation Manual 0 INTRODUCTION The OFFSITE DOSE CALCUt.ATION MANUAL (ODCM) is a supporting document of the Saxton Nudear Experimental Corporation (SNEC) Facility Technical Specifications and implements SNEC Facility radiological effluent controls. The ODCM contains the controls, bases, and surveillance requirements for liquid and gaseous radiological effluents. In addition, the ODCM desenbes the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents. This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm / trip set points.

Ventilation Exhaust Treatment System configurations are also included.

The ODCM also is used to define the requirements for the SNEC Facility Radiological Environmental Monitoring Program (REMP) and contains a list of the specific sample locations used in the REMP.

The ODCM is maintained at the site for use as a reference guide and training document of accepted methodologies i and calculations. Chtnges in the calculation methods or parameters will be incorporated into the ODCM to ensure '

the ODCM represents the present methodology in all applicable areas. SNEC Facility initiated changes to the

. ODCM will be implemented in accordance with the SNEC Facility Technical Specifications.

The ODCM follows the methodology and models suggested by NUREG-0133, and Regulatory Guide 1.109, Revision i for calculation of off-site doses due to plant effluent releases. Simplifying assumptions have been appiled in this manual where applicable to provide a more workable document for implementation of the Radiological Effluent Controls requirements.

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SAXTON NUCLEAR Facility Policy and Pmcedure Manual 6575-PLN 4542.08 The Reveskm No.

SNEC Facility Offsite Dose Calculation Manual 0 Table of Contents Sechon PART l RADIOLOGICAL EFFLUENT CONTROLS E999 1.0 DEFINITIONS 12 Table 1.1, Frequency Notations 14 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 15 2.1 Radioactive Effluent Instrumentation 15 2.1.1 Radioactive Liquid Effluent instrumentation 15 2.1.2 Radioactive Gaseous Effluent Monitoring Instrumentation 15 Table 2.1-2, Radioactive Gaseous Effluent Monitoring Instrumentation 16 2.2 Radiological Effluent Controls 17 2.2.1 Liquid Effluent Controls 17 2.2.2 Gaseous Effluent Controls ,

19 2.2.3 Total Radioactive Effluent Controls 22 2.3 - SNEC Facility Radiological Environmental Monitoring Program (REMP) 23 2.3.1 Monitoring Program Requirements 23 l

2.3.2 Land Use Census 24 l

2.3.3 Interlaboratory Comparison Program 25

' Table 2.3-1, REMP Sample Analysis, Collection, and Analysis 27  ;

Frequency by Sample Medium Table 2.3-2, REMP Analytical Required Sensitivities (LLD) and Reporting 29 Levels for Radioactivity Concentrations in Environmental Samples 3.0 SURVElLLANCES 3.1 Radioactive Effluent instrumentation 31 l

3.1.1 Radioactive Liquid Effluent instrumsntation 31 3.1.2 Radioactive Gaseous Effluent Monitoring Instrumentation 31 Table 3.1-2, Radioactive Gaseous Effluent Monitoring instrumentation 32 Surveillance Requirements .

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SNEC Facility Offsite Dose Caica6ation Manual 0 Table of Contents (Cont'd)

PART I RADIOLOGICAL EFFLUENT CONTROLS (Cont'd)

Se4ina East 3.2 Radioactive Effluents 33 3.2.1 Liquid Effluents 33 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 34 3.2.2 Gaseous Effluents 35 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 36 3.2.3 Total Radioactive Effluents 38 3.3 GNEC Facility Radiological Environmental Monitoring Program 38 3.3.1 Monitoring Program Surveillance Requirements 38 Table 3.3-1, Saxton Nuclear Experimental Corporation Facility Radiological 39 Environmental Monitoring Program Description S

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Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revenson No.

SNEC Facility Offsite Dose Calculation Manual 0

, Table of Contents (Cont'd)

PART11 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Egin 1.0 LIQUID EFFLUENT MONITORS 43 1.1 Liquid Radiation Monitor Set Points 43 1.2 Liquid Effluent Release Points 43 1.3 Control of Liquid Releases 43 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 44 2.1 Liquid Effluents - 10 CFR 50 Appendix i 44 2.2 Liquid Radwaste System Dose Calcs Once per Month 45 2.3 - Altemative Liquid Dose Calculational Methodology 45 3.0 LIQUID EFFLUENT WASTE TREATMENT SYSTEM 50 3.1 Liquid Effluent Waste Treatment System 50 4.0 GASEOUS EFFLUENT MONITORS 50 4.1 Particulate Monitor Set Points 50 4.2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 51 4.3 Control of Gaseous Effluent Releases 52 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 55 5.1 Gaseous Effluents- Dose Rate Limits 55 I

5.1.1 Tritium and Particulates 55 l l

5.2 Gaseous Effluents - 10 CFR 50 Appendix I 55 l l l

5.2.1 Tritium and Particulates 55 l l 1 5.3 Ventilation Exhaust Treatment System Dose Calculations once per Month 56 j i 5.4 Altemative Dose Calculational Methodologies 56 l 6.0 EFFLUENT TOTAL DOSE ASSESSMENT 78 l

7.0 PART 11 REFERENCES 78 7 3918D. doc

e Number Saxton Nu&ar Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revision No SNEC Facility Offsite Dose Calculation Manual 0 Table of Contents (Cont'd)

PART11 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES si229.g Eagg TABLES Table 2.1 Liquid Dose Conversion Factors (DCF): Dfji 46 Table 2.2 Bioaccumulation Factors, BFi 49 Table 4.1 Atmospheric Dispersion Factors for SNEC Facility 53 i

Table 4.2 Dose Parameters for Radioiodines and Radioactive Particulate, 54 i Gaseous, Effluents Table 5.2.1 Pathway Dose Factors, Ri- Infant, Inhalation 57 Table 5.2.2 Pathway Dose Factors, Ri - Child, inhalation 58 Table 5.2.3 Pathway Dose Factors, R4 ' Teen, inhalation 59 Table 5.2.4 Pathway Dose Factors, Ri- Adult, Inhalation 60 Table 5.3.1 Pathway Dose Factors, Ri- All Age Groups, Ground Plane 61 Table 5.4.1 Pathway Dose Factors, Ri- Infant, Grass-Cow-Milk 62 Table 5.4.2 Pathway Dose Factors, Ri- Child, Grass-Cow-Milk 63 Table 5.4.3 Pathway Dose Factors, R6 - Teen, Grass-Cow-Milk 64 Table 5.4.4 Pathway Dose Factors, R4 - Adult, Grass-Cow-Milk 65 Table 5.5.1 Pathway Dose Factors, Ri- Infant, Grass-Goat-Milk 66 Table 5.5.2 Pathway Dose Factors, Ri- Child, Grass-Goat-Milk 67 Table 5.5.3 Pathway Dose Factors, R4 - Teen, Grass-Goat-Milk 68 Table 5.5.4 Pathway Dose Factors, Ri- Adult, Grass-Goat-Milk 69 Table 5.6.1 Pathway Dose Factors, Ri - Infant, Grass-Cow-Meat 70 Table 5.6.2 Pathway Dose Factors, Ri - Child, Grass-Cow-Meat 71 Table 5.6.3 Pathway Dose Factors, R4 - Teen, Grass-Cow-Meat 72 8 391BD. DOC

Number SAXTON NUCLEAR SaMon Nuclear Expe&nental Corporation Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Reymon No.

SNEC Facility Offsite Dose Calculation Manual 0 Table of Contents (Cont'd) l i

PARTll EFFLUENT DATA AND CALCULAT10NAL METHODOLOGIES (Cont'd)

Section PJi92

' TABLES (Cont'd)

Table 5.6.4 Pathway Dose Factors, Re - Adult, Grass-Cow-Meat 73 Table 5.7.1 Pathway Dose Factors, Re . Infant, Vegetation 74 Table 5.7.2 Pathway Dose Factors, Ri - Child, Vegetation 75 Table 5.7.3 Pathway Dose Factors, Ri- Teen, Vegetation 76

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Table 5.7.4 Pathway Dose Factors, Ri - Adult, Vegetation 77 l

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SNEC Facility Offsite Dose Calculation Manual 0 Table of Contents (Cont'd)

PARTlil REPORTING REQUIREMENTS Section Eagt 1.0 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 81 l 2.0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 81 3.0 PART 111 REFERENCES 82 APPENDICES A. Pathway Dose Rate Parameter (PJ 84 ,

B. Inhalation Pathway Dose Factor (R,) 85 C. Ground Plane Pathway Dose Factor (R,) 86 i D. Grass-Cow-Milk Pathway Dose Factor (R) i 87 E. Cow Meat Pathway Dose Factor (R,) 89 F. Vegetation Pathway Dose Factor (R,) 91 APPENDIX A - F REFERENCES 92 10 39180.00C

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SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN 4542.08 l T1ue Roweson No.

SNEC Facility Offsite Dose Calculation Manual 0 1,0 DEFINITIONS l 1.1 Defined Terms l The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part i of the ODCM. I 1.2 Decommissioning Removing the facility safely from service and reducing residual radioactivity to a level that permits release of the property for unrestricted use and tennination of license.

1.3 Action ACTION shall be those additional requirements specified as corollary statements to each control and shall be part of the controls.

1.4 Operable - Operability A system, subsystem, train, component or device shall be OPERABLE or have OPERABILIT(

when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, electrical power sources, cooling or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function (s), are also capable of performing their related support function (s).

l 1.5 Channel Calibration A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CAllBRATION may be performed by any series of sequential, overiapping or total channel steps such that the entire channel is calibrated.

1.6 Channel Check A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shallinclude, where possible, comparison of the channelindication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

1.7 Source Check A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

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SNEC Facility Offsite Dose Calculation Manual 0 1.8 Channel Functional Test -

A CHANNEL FUNCTIONAL TEST shall be:

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

b. Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.

1.g Composite Sample ,

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A COMPOSITE SAMPLE is a combination of individual samples obtained at regular intervals over a time period. Either the volume of each individual sample is proportional to the low rate discharge at the time of sampling or the number of equal volume samples is proportional to the time period used to produce the composite.

1.10 Grab Sample A GRAB SAMPLE is an individual sample collected in less than fifteen minutes.

1.11' Batch Release

'A BATCH RELEASE is the. discharge of fluid waste of a discrete volume.

1.12 Continuous release A CONTINUOUS RELEASE is the discharge of fluid waste of a non-discrete volume, e.g., from a volume or system that has an input flow during the CONTINUOUS RELEASE.

1.13 SNEC Facility Offsite Dose Calculation Manual (ODCM)

The SNEC Facility OFFSITE DOSE CALCULATION MANUAL (ODCL1) contains the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and ,

in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) j the Radiological Effluent Controls, (2) the Radiological Environmental Monitoring Program and (3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

1.14 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 GPU System, GPU contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

1.15 Site boundary The SITE BOUNDARY is the boundary line forming the basis for the limits on the release of

. gaseous effluents. At the SNEC Facility, the SITE BOUNDARY for gaseous effluents is the line formed by a 200 meter radius from the center of the Containment Vessel (CV).

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SNEC Facility Offsite Dose Calculation Manual 0 1.16 Ventilation Exhaust Treatment System j A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce radioactive material in particulate form in effluent by passing ventilation or vent exhaust gases through HEPA filters for the purpose of removing particulates from the gaseous exhaust system prior to the release to the environment.

1.17 Frequency Notation The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. All Surveillance Requirements shall be performed within the specified time interva! with a maximum allowable extension not to exceed 25% of the surveillance interval.

TABLE 1.1 l

Frequency Notation NOTATION EBEQUENCY S (Shiftly) At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D (Daily) At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W (Weekly) At least once per 7 days.

M (Monthly) At least once per 31 days. j Q (Quarterly) At least once per 92 days.

SA (Semi-Annually) At least once per 184 days. 1

- A (Annually) At least once per 12 months.

E At least once per 18 months.

N. A. Not applicable.

1.18 Measurable Release A Measurable Release is defined as those potential radioactive releases which meet or exceed the Lower Limit of Detection (LLD) for liquid and gaseous radioactive effluents as specified in this procedure.

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p SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tme- Rension No, SNEC Facility Offsite Dose Calculation Manual 0 2.0 CONTROLS AND BASES i

> 1, Controls and ACTION requirements shall be applicable during the conditions specified for each control.

2. Adherefice to the requirements of the Commi mer associated ACTION within the specified time interval shall constitute compliance wi'h the mit A in the event the Control is restored prior to expiration to the specified time interv&.. cornor. ant of the ACTION statement is not required.

3. In the event the Control and associated ACllON requirements cannot be satisfied because of

circumstances in excess of those addressed in the Control, initiate appropriate actions to rectify the

! problem to the extent possible under the circumstances, and submit a special report to the Commission pursuant to Technical Specification (Tech. Spec.) Sechon 3.8.1 within 30 days unless 3 l otherwise specified. 4 2.1 - Radioactive Effluent instrumentation 2.1.1 Radioactive Liquid Effluent instrumentation There is no Radioactive Liquid Effluent Instrumentation in service during the DECOMMISSIONING of the Saxton Nuclear Station. Any liquid effluents will be BATCH RELEASED and sampled and analyzed prior to release. .

1 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL:

The radioactive gasmus process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall N OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 2.2.2.1 am not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 2.12.

ACTION:

a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control,  ;

immediately suspend the release of radioactive effluent monitored by the affected l channel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in ,

Table 2.1-2.

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' BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as j applicable, the releases of radioactive materials in Gaseous effluent during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.

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SNEC Facility Offsite Dose Calculation Manual 0 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration ,

CONTROL:

The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.100120.2401, Appendix B, Table 2, Column 2.

APPLICABILITY: At alltimes

' ACTION:

I With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits.

t BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix 8 Table 2.

These Controls permit flexibility under unusual conditions, which may temporarily result in higher than normal releases, but still within ten times the concentrations, specified in 10 CFR 20, it is expected that by using this flexibility under unusual conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the annual average concentrations specified in 10 CFR 20. As a result, this Control provides reasonable assurance that the resulting annual exposure to an individual in off-site areas will not exceed the design objectives of Section ll.A of Appendix 1 to 10 CFR Part 50.

2.2.1.2 Liquid Effluent Dose ]

CONTROL:

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials i in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:

a. - During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ,

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

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Number SMMN NWNR Saxt n Nuclear Experimental Corporation Facility Policy and Procedure Manual 6575-PLN 4542.08 Title Revieson No.

SNEC Facility Offsite Dose Calculation Manual 0 ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents 1 exceeding any of the above limits, prepare and submit to the NRC Region 1 Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

BASES i This Control requires that the dose to offsite personnel be limited to the design objectives of Appendix i cf 10 CFR Part 50. This will assure the dose received by the public during DECOMMISSIONING is equivalent to or less than that from a normal operating reactor.

The ACTION statements provide the required flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably  ;

achievable". The dose calculations in the ODCM implement the requirements in i Section Ill.A. of Appendix I that conformance with the guides of Appendix I is to be shown I by calculational procedures based on models and data such that the actual exposure of a l MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially s underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1,109, " Calculation of Annual Doses to Man  ;

from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with j 10 r'?R Part 50, Appendix 1," Revision 1, October,1977, and Regulatory Guide 1.113, l

" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases  !

for the Purpose of implementing Appendix 1," April,1977. NUREG-0133 provides methods i for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

2.2.1.3 Liquid Radwaste Treatment System CONTROL: ,

j The appropriate portions of a liquid radwaste treatment system shall be used to reduce the l radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total  :

tmdy or 0.2 mrem to any organ in any calendar month.

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l NmW Saxton Nuclear Experimenta' corporation I SMMN NUaBR Facility Policy and Procedu? Aanual 6575-PLN-4542.08 Title Revissori No SNEC Facility Offsite Dose Calculation Manual 0 ACTION:.

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepere and submit to the NRC Region 1 Administrator within 30 days, a Special Report which includes the following infonhation:

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

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

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

BASES 1

The requirement that the appropriate portions of a treatment 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 l of 10 CFR Part 50.36a, General Desi0n Criterion 60 of Appendix A to 10 CFR Part 50 and j the design objective given in Section 11.D of Appendix l to 10 CFR Part 50. The intent of Section ll.D. is to reduce effluents to as low as is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section ll.A of Appendix 1,10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction.

2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL: l The dose rate due to tritium and all radionuclides in particulate form with half lives greater than 8 days released in gaseous effluent from the site shall be limited to less than or equal to 1500 mrem /yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the release rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limit (s).

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Number Saxton uudear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 l Tae. Revision No.

4 SNEC Facility Offsite Dose Calculation Manua! O BASES.

The control provides reasonable assurance that the annual dose at the SITE BOUNDARY from gaseous effluent from the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. At the same time, these Controls permit flexibility under unusual conditions, which may temporarily result in higher than the design objective levels, but still within the dose limits specified in 10 CFR 20 and within the design objectives of Appendix 1 to 10 CFR 50. It is expected that using this flexibility under unusual conditions, and by exerting every effort to keep levels of radioactive material in gaseous wastes as low as practicable, the annual releases will not exceed a small fraction of the annual dose limits specified in 10 CFR 20 and will not result in doses which exceed the design objectives of Appendix 1 to 10 CFR 50. These gaseous release rates provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in the exposure of a l MEMBER OF THE PUBLIC in an unrestricted area, either within or outside the SITE l BOUNDARY, to annual average concentrations exceeding the values specified in

. Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The absence of noble gases ensures that, at all times, the correspondin0 Damma and beta dose rates above back0round to a MEMBER  ;

OF THE PUBLIC at or beyond the SITE BOUNDARY are less than 500 mrem / year to the  ;

total body or to less than or equal to 3000 mrem / year to the skin. Additionally, the absence of iodine ensures that the corresponding thyroid dose rate above background to an infant via the inhalation pathway is always less than 1500 mrem /yr (NUREG 0133).

2.2.2.2 Gaseous Effluent Dose CONTROL:

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

a. During any calendar quarter less than or equal to 7.5 mrem to any organ, and

b. During any calendar year: less than or equal to 15 mrem to any organ.

APPLICABILITY: At alltimes.

ACTION:

With the calculated dose from the release of Tritium, and radionuclidas in particulate form with half lives greater than 8 days,'in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region l Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

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Number Saxton Nuclear Experimental CorporaHon SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08  !

Title Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 BASES This control and associated action is provided to implement the requirements of Section ll.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Controls are the guides set forth in Section ll.C of Appendix 1. The ACTION statement provides flexibility during unusual conditions and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1 October,1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine )

Releases from Light-Water-Cooled Reactors," Revision 1, July,1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for tritium and radion'iclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) Individual inhalation of airbome radionuclides,2) deposition of radionuclides onto green leafy  !

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

2.2.2.3 Ventilation Exhaust Treatment System CONTROL:

The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE during activities within the Containment Vessel / Decommissioning Support Building that have the potential to cause a MEASURABLE RELEASE to the environment of airbome radioactivity.

The VENTILATION EXHAUST TREATMENT SYSTEM is OPERABLE when its surveillance requirements are met and:

a. The pressure drop across the HEPA filters is between 0.5 and 3 inches of water.

b. The results of required in-place filter tests at flows 2 6500 cfm show < 0.05%

penetration with profilters installed.

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m Number Saxt n Nudear Experimental Cwpwation SAXTON NUCLEAR _ Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revoort No.

SNEC Facility Offsite Dose Calculation Manual 0 APPLICABILITY: At all times.

ACTION:

a. With the VENTILATION fiXHAUST TREATMENT SYSTEM inoperable, suspend all activities within the Containment Vessel / Decommissioning Support Building that have the potential to cause a MEASURABLE RELEASE to the envimnment of airbome radioactivity.

BASES The use of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section ll.D of Appendix i to 10 CFR Part 50.

2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL:

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem.

APPLICABILITY: At alltimes.

ACTION:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a,2.2.1.2.b,2.2.2.2.a or,2.2.2.2.b, calculations should be made including direct radiation contributions from the unit and from outside storege tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region i Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLic from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

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' Saxton Nudear Experimental Corporation SAXTON NUCLEAR. Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Reveon No SNEC Facility ONsite Dose Calculation Manual 0 I

BASES This control is provided to meet the dose limitations of 40 CFR Part 190 that have been j referenced in 10 CFR Part 20. .301(d). This control requires the preparation and submittal i of a Special Report whenever the calculated doses from plant generated radioactive I effluents and direct radiation exceed 25 mrem to the total body or any organ, except the l thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 !

reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain withb twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other I uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190,' and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individualis not considered a MEMEER OF THE PUBLIC during any period in which he/she is engaged in carryin2 out any operation that is part of the nuclear fuel cycle.

2.3 SNEC FACILITY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 2.3.1 Monitoring Program Requirements CONTROL:

in accordance with the SNEC Facility Tech Specs, the radiological environmental monitoring program shall be conducted as specified in Table 2.3-1.

]

APPLICABILITY: At alltimes.

ACTION:

a. With the radiological environmental monitoring program not being conducted as

. specified in Table 2.3-1, prepare and submit to the Commission in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

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l SNEC Facility Offsite Dose Calculation Manual 0 I

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 2.3-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a special report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

• to a member of the )

public is less than the calendar year limits of ODCM Part i Controls 2.2.1.2, and 2.2.2.2. When more than one of the radionuclides in Table 2.3-2 are detected as the result of plant effluents in the samplir.g medium, this report shall be submitted if:

concentration fil + concentration (2) + ... h tf reporting level (1) reporting level (2)

When radionuclides other than those in Table 2.3-2 are detected and are the result I of plant effluents, this report shall be submitted if the potential annual dose

• to a l member of the public is equal to or greater than the calendar year limits of ODCM Part i Controls 2.2.1.2 or 2.2.2.2. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

BASES .

The radiological monitoring program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of members of the general public resulting from the station operation. This monitoring program implementsSection IV B.2 of Appendix i to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

Guidance for this monitoring is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1. November 1979). Program changes may be initiated based on operational experience.

2.3.2 Land Use Census CONTROL:

As part of the SNEC Facility radiological environmental monitoring program (REMP), broad leafy vegetation will be collected and analyzed for gamma-emitting radionuclides. Other analyses will be performed, as necessary. The samples will be collected annually during j the growing season at the site boundary in the two highest D/Q sectors. This sampling of l

broad leafy vegetation will be performed in lieu of performing a land use census.

APPLICABILITY: At all times.

The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.

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Number Saxt n Nudear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Reweion No.

SNEC Facility Offsite Dose Calculation Manual 0 ACTION:

a. If sampling of broad leafy vegetation is not performed as described above, a land use census will be conducted. The census willidentify within a distance of 5 miles (of the SNEC Facility) the closest milk animal and garden (equal to or > 500 sq. ft.

and producing broad leafy vegetation) in each meteorological sector. The results of this census will be included in the Annual Radiological Environmental Operating Report. One milk and one broadleaf vegetation sample will be collected at the highest D/Q locations identified in the land use census.

BASES i During SNEC Facility decommissioning operations, very small amounts of radioactivity are expected to be released to the atmosphere. The predominent radionuclide in airbome effluents is expected to be Cs-137 and there will be no radiciodine, Using this fact and the Ri values listed in the SNEC Facility ODCM, the critical exposure pathway for airbome effluents will be ingestion of milk. Comparable doses can also be calculated from another important human exposure pathway - ingestion of leafy vegetation. As part of the SNEC ,

Facility radiological environmental monitoring program (REMP), broad leafy vegetation will ]

be collected and analyzed for gamma-emitting radionuclides. Other analyses will be performed, as necessary. The samples will be collected annually during the growing season a

]

at the site boundary in the two highest D/Q sectors. Since the data from monitoring broad leafy vegetation (and other environmental media such as air particulates) will be just as representative to validate the doses calculated from effluent data, samples of milk will not be collected and analyzed on a routine basis. Additionally, collecting vegetation samples on a routine basis at the highest D/Q locations and not sampling milk, eliminates the need to perform a land use census to locate gardens and milk animals in the area. Another reason for not needing a land use census is that doses including those from ingesting milk and leafy vegetation will be conservatively calculated at the site boundary where doses are expected to be a small fraction of ODCM limits.

2.3.3 Interiaboratory Comparison Program

. CONTROL:

In accordance with the SNEC Facility Tech. Specs, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program. Samples and analyses which are selected for inclusion in the program shall be representative of those required by Table 2.3-1.

APPLICABILITY At alltimes.

ACTION:

With analysis not being performed as required above, report the corrective action taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

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SNEC Facility Offsite Dose Calculation Manual o BASES j l

The requirement for participation in an Interlaboratory Comparison Program is provided to j ensure that independent checks on precision and accuracy of the measurements of j radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV. B.2 of Appendix i to 10 CFR 50.

I I

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SNEC Facility Offsite Dose Calculation Manual 0  ;

l

. TABLE 2.3-1 Page 1 of 2 Saxton Nuclear Experimental Corporation Facility REMP Sample Analysis, Collection and Analysis Frequency by Sample Medium SAMPLE COLLECTION ANALYSIS ANALYSIS MEDIUM FREQUENCY TYPE (a) FREQUENCY (b)

Air Particulate ' Biweekly (c) Gr-A - On each sample (d)

(AP) Gr-B On each sample (d)

Gamma (e) Quarterly Composite (f)

Aquatic Sediment (g) Quarterly Gamma On each sample

]

4 (SD)

Dosimeters (h) Quarterly Gamma Quarterly (lD) Immersion Dose Potable Water (i) Quarterly Gr-B On each sample j (GW) Gamma On each sample H-3 On each sample Ground Water Quarterly Gamma On each sample (GW) H-3 On each sample Soil As needed Gamma On each sample (S)

Surface Water Quarterly (j) Gamma On each sample (SW) H-3 On each sample j 1

Vegetation Annually (k) Gamma On each sample (BR)

Milk As needed Gamma On each sample (M)

Table Notations

a. Additional analyses, i.e., Strontium-90, Transuranics, etc., may be performed if requested by the Program Director, SNEC Facility.

b. The listed frequencies for collection and analysis of REMP required media are recommended as good practice. A maximum allowable extension of these frequencies should not exceed 25% of the interval as listed here. Deviations are permitted from the required sampling schedule if samples are unobtainable due to seasonal unavailability, hazardous conditions, malfunction of automatic sampling equipment or other l legitimate reasons.  !

c. Samples are normally collected biweekly from 4 locations (3 indicators and 1 control). Frequency may be chan0ed at the discretion of the Program Director, SNEC Facility.

d. Airbome particulate samples should bo analyzed for Gross beta and alpha radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after collection to allow for radon and thoron daughter decay. If gross beta activity on an indicator sample is greater than 10 times the mean of the control, analyze the filter for gamma emitters and Sr-90.

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r l Number l Sax n Nuclear Expwimental Corporation

! SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN 4542.08 i Tme Revisson No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 2.3-1 Page 2 of 2 ,

Saxton Nuclear Experimental Corporation Facility l REMP Sample Analysis, Collection and Analysis Frequency by Sample Medium I

{

G. Gamma (isotopic saalysis) means the identification and quantification of gamma-emitting radionuclides. l

f. If any positive gamma emitting radionuclides are present as a result of SNEC Facility activities recount

{

each filter separately. l

g. As a minimum, sediment samples shall be taken from indicator station A1-4 and one control station. The indicator station A1-4 sample shall be taken as close to the storm drain outfall as possible. If unable to collect a sediment sample due to rocks move downstream but stay as close as possible to the outfall line.

A control sediment shall be taken upstream of the outfall or from an area not influenced by SNEC Facility activities. Document any comments on the collection / receipt sheet.

{

h. As a minimum, TLDs shall be sampled from at least 17 locations, including at least 16 indicators and one l control station, from the locations listed in Table 3.3-1. l l

l

1. The potable water stations are E1-1 and G1-1. Groundwater samples not used for drinking are collected at Stations GEO-1 through GEO-8 and MW-1 and MW-2. Surface water samples are typically collected from Stations A1-4 and Q1-2. .

J. Additional surface water collections will be performed during any liquid effluent releases to the river. As a minimum, a grab sample downstream of the release will be taken at the start, midpoint, and end of each release.

k. Broad leaf vegetation collection will occur during the growing season in the two highest D/Q sectors, typically Sectors A and B.

l i

I i

l l

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Number Saxton Nuclear Experimental Corpoistion SMTON NUaMR Facility Policy and Procedure Manual 6575-PLN-4542.08 l

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SNEC Facility Offsite Dose Calculation Manual 0 l TABLE 2.3-2 Page 1 of 2 REMP Analytical Required Sensitivities (LLD)"

and Reporting Levels EXPOSURE / PATHWAYS 8

l AND/OR SAMPLE UNITS ANALYSIS REQUIRED LLD

• REPORTING LEVEL 3 j

' Air Particulate pCi/m Gr-Alpha 1.5E-3 1.0E-1 (AP) Gr-Beta 1.0E-2 1.0E0 J Cs-134 5.0E-2 1.0E1 l Cs-137 6.0E-2 2.0E1 l Sr-90 1.0E-2 1.0E-1 i 1

Sediment / Soil pCl/g (dry) Cs-134 1.5E-1 1.0E0 j (SD/SO) Cs-137 1.8E-1 5.0E0 Sr-90 5.0E-2 5.0E-1 Water pCi/L Gr Alpha 5.0E0 1.0E2 j (SW/GW) Gr Beta 4.0E0 5.0E1  !

Tritium 2.0E3 2.0E4 .

Co-60 1.5E1 3.0E2 Cs-134 1.5E1 3.0E1 Cs-137 1.8E1 5.0E1 Sr-90 2.0E0 8.0E0 Vegetation pCl/g (wet) Cs-134 6.0E-2 1.0E0 (BR) Cs-137 8.0E-2 2.0E0 Sr90 1.0E-2 1.0E 1 Milk pCl/L pCl/L Cs-134 1.5E1 6.0E1 (MI) Cs-137 1.8E1 7.0E1 Sr-90 2.0E0 8.0E0 l

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' SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 l Title Revision No. l l

SNEC Facility Offsite Dose Calculation Manual 0 i

TABLE 2.3-2 Page 2 of 2 Detection Capabilities for Environmental Sample Analysis Table Notation j i

a. This list does n'ot mean that only these nuclides are to be considered. Other peaks that are identifiable, I which may be related to plant operations, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

b. Required detection capabilities for thermoluminescent dosimetets used for environmental measurements I are given in Regulatory Guide 4.13 (Rev.1). j i

c. The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a l sample that will yield a net count, above system background, that will be detected with 95% probability with {

only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation): J 4.66Sb LLD =

E V 2.22 Y f exp(-AAt}

Where:

LLD is the "a priori" lower limit of detection as defined above, as picocuires per unit mass or volume, Se is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable),

A,is the radioactive decay constant for the particular radionuclide and af for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting.

' Typical values of E, V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori"(after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small samples sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable, in such cases, the contributing factor shall be identified and described in the Annual Radiological Environmental Operating Report.

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SNEC Facility Offsite Dose Calculation Manual 0  ;

1 3.0 SURVEILLANCES

1. Surveillance Requirements shall be applicable dudng the conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement. The Surveillance J Requirements shall be performed to demonstrate compliance with the OPERABILITY requirements of the Control. q i

2. Each Surveillance Requirement shall be performed within the specified time interval wMh a {

maximum allowable extension not to exceed 25% of the surveillance interval. ]

3. Failure to perform a Surveillance Requirement within the time interval specified in Section 3.0.2 shall constitute non compliance with OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requ!rement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit  ;

completion of the surveillance when the allowable outage time limits of the ACTION requirements )

are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on inoperable equipment. ,

)

3.1 Radioactive Effluent instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation There is no Radioactive Liquid Effluent instrumentation in service during the DECOMMISSIONING of the Saxton Nuclear Experimental Corporation Facility.

3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation SURVEILLANCE REQUIREMENTS l

3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel l shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.

31 3918D.00C

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m Nurnber Sadon Nu&ar Eprimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN 4542.08 Trio Revisen No.

SNEC Facility Offsite Dose Calculation Manual 0 3.2 Radioactive Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 3.2-1.

The results of analyses shall be used with the calculational rrethods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

1 3.2.1.1.2 Analysis of samples composited from batch releases shall be performed I in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1.

3.2.1.2 Dose Calculations 3.2.1.2.1 dumulative dose contributions from liquid effluents shall be determined in )

accordance with the ODCM at least once a month when liquid releases .

are in progress.

)

3.2.1.3 Dose Projections 3.2.1.3.1 Doses due to liquid releases shall be projected at least once per month when liquid releases are anticipated.

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Number Saxt n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN 4542.08 Trio - Revason No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 3.2-1 Page 1 of 1 Radioactive Liquid Waste Sampling and Analysis (4,5)

A. Llauid Releases Sampling Frequency Type of Activity Analysis - Detectable Concentration (3) l Each Batch Individual Gamma SE 7 pCl/ml(2) l H-3 1E-5 nCl/ml Quarterly Composite (1) Gross Alpha 1E-7 Cl/mi Sr 90 SE-8 nCl/mi l l

l NOTES:

~

(1) A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.

,(2)- For certain mixtures cf gamma emitters, it may not be possible to rneasure radionuclides in concentrations near this sensitivity limit when other nuclides are present in the sample in much greater concentrations. l Urwr these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides i usity :teasured ratios with those radionuclides which are routinely identified and measured.

(3) The detectability limits for radioactivity analysis are based on the technical feasibility and on the potentici significance in the environment of the quantPies released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.

(4) The results of these analyses should t:e used as the basis for recording and reporting the quantities of radicactive material released in liquid effluents during the sampling period. In estimating releases for a period when analyses were not performed, the average of the two adjacent data points spanning this period should be used. Such estimates should be included in the effluent records and reports; however, they should tK clearly identified as estimates, end the method used to obtain these data should be described.

J (5) Deviations from the sampling / analysis regime will be noted in the report specified in ODCM Part lli.

3 j

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. SNEC Facility Offsite Dose Calculation blanual 0 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates 3.2.2.1.1 The dose rate of radioactive materials in gaseous effluents shalf be determined to be within the limits of Control 2.2.2.1. in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.2-2.

3.2.2.2 Dose 3.2.2.2.1 Cumulative dose contributions from Tritium, and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM monthly.

3.2.2.3 Ventilation Exhaust Treatment 3.2.2.3.1 Doses due to gaseous releases from the unit shall be projected monthly 1,n accordance with the ODCM.

3.2.2.3.2 The pressure drop across the combined prefilter/HEPA filter banks shall be demonstrated to be less than 3 inches of water at a flow rate 2 6500 cfm annually.

3.2.2.3.3 in-place filter testing specified in ODCM Control 2.2.2.3 shall be performed after each complete or partial replacement of a HEPA filter bank or after any structural maintenance on the system housing that could affect the HEPA filter bank bypass leakage. As a minimum, this testing shall be performed annually.

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Number Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tme Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 3.2-2 Page 1 of 2 Radioactive Gaseous Waste Sampling and Analysis Program (3)

SAMPLE SAMPLING TYPE OF DETECTABLE SAMPLE POINT TYPE FREQUENCY ACTIVITY ANALYSIS CONCENTRATION (1)(a)

Unit Exhaust Vent Release Points Gas Monthly H-3 1E-6 pCvec.

Particulates Weekly Individual (b) Gamma 1E-10 pCUcc (2)

Emitters Monthly Sr-90 1E-11 pCvec Composite Monthly Gross Alpha Emitters 1E-11 pCuce Composite (1) The above detectability limits are based on technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.

(2) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios for those radionuclides whicti are measurable.

(3) Deviations from the sampling and analysis regime will be noted in the report specified in ODCM Part 111.

i 36 3918D DOC

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Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575 PLN-4542.08 Trio Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 3.2 2 Page 2 of 2 Radioactive Gaseous Waste Sampling and Analysis Program (3)

Table Notation

a. The LLD .is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 S.

LLD =

E x V x 2.22 x 10 6 xY x exp(-ut I Where:

LLD is the "a priori" lower limit of detection as defined above, as micocuire per unit mass or volume, So is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 10' is the number of disintegrations per minute per micoeurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive deccy constant for the particular radionuclide and At is the elapsed time between midpoint of sample collection and time of counting.

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement,

b. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported.

l Other peaks which are measurable and identifiable, together with the above nuclides, shall also be l identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.

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SNEC Facility Offsite Dose Calculation Manual 0 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1 and 3.2.2.2.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.

3.3 SNEC FACILITY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.3.1 Monitoring Program Surveillance Requirements

a. The radiological environmental monitoring samples shall be collected pursuant to Table 2.31, from the specific locations given in Table 3.3-1 and shall be analyzed pursuant to the requirements of Table 2.3-1 and the detection capabilities required by Table 2.3-2.

b. Broad leafy vegetation will be collected and analyzed for gamma-emitting radionuclides. Other analyses will be performed, as necessary. The samples will be collected annually during the growing season at the site boundary in the two highest D/Q sectors. This sampling of broad leafy vegetation will be performed in lieu of performing a land use census. If sampling of broad leafy vegetation is not performed as described above, a land use census will be conducted. The census willidentify within a distance of 5 miles (of the SNEC Facility) the closest milk animal and garden (equal to or > 500 sq. ft. and producing broad leafy vegetation) in each meteorological sector. The results of this census will be included in the Annual Radiological Environmental Operating Report One milk and one broadleaf vegetation sample will be collected annually at the highest D/Q locations identified in the land use census.

c. A summary of the Inte1aboratory Comparison Program results shall be included in ,

- the Annual Radiological Environmental Operating Report. l 1

38 3918D. doc

o Number Saxt n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Trio Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 3.3-1 Page 1 of 3 Saxton Nuclear Experimental Corporation Facdity l Radiological Environmental Monitoring Program Description i Station Media Local Description Note A1 1 Sediment Drain outfall outside perimeter fence Water rarely present A1-2 Air Particulate Westinghouse Yard Area A1-4 Surface Water Sediment Juniata River at the Westinghouse Weir bulkhead A1-5 TLD N Sector, perimeter fence A1-6 Broadleaf Vegetation N Sector, site boundary B1-4 Surface Water Sediment Drop weir in the Westinghouse Yard Area.

B16 TLD NNE Sector, perimeter fence B1-7 Broadleaf Vegetation N NE Sector, site boundary C1-6 Sediment Drain outfall, NE comer of perimeter Water rarely present l fence C1-9 TLD NE Sector, perimeter fence C21 TLD Weaver Ridge,0.8 miles from CV D1 1 Air Particulate Open Field ENE Sector j D1-4 TLD ENE Sector, perimeter fence l D2-1 TLD Weaver Bridge,1.3 miles from CV e E1-1 Potable Water Penelec Line Shack E1-7 TLD E Sector, perimeter fence E1-17 TLD Penelec Line Shack E21 TLD E Sector,0.25 miles from CV E3-1 TLD 3 miles East of CV in State Gameland

1. 67 F1-2 TLD ESE Sector, perimeter fence 39 3918D. doc

I Number Saxton Nuclear Experimental Corporation j SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 l l

TABLE 3.3-1 Page 2 of 3 Saxton Nuclear Experimental Corporation Facility Radiological Environmental Monitoring Program Description l

Station Media Local Description NA SE Sector, private residence in Saxton I G11 TLD Potable Water G12 TLD ' SE Sector, perimeter fence  ;

1 G2-1 TLD SE Sector, closest private residence G10-1 Air Particulate Reichley Microwave Tower Offsite Control Station l G10-2 TLD New Granada Offsite Control Station ,

H15 TLD SSE Sector, perimeter fence H21 TLD Tussey Mt. High School j 1

H10-1 TLD Wells Tannery Offsite Control Station J1-1 TLD S Sector, perimeter fence J1-3 Air Particulate Penelec Area S Sector K15 TLD Saxton Borough Hall Offsite Control Station K1-8 TLD SSW Sector, perimeter fence L1-1 TLD SW Sector, perimeter fence L2-1 TLD SW Sector, Stonerstown,1 mile from CV M1-6 TLD WSW Sector, perimeter fence i

N1-4 TLD W Sector, perimeter fence P1-1 TLD WNW Sector, perimeter fence Q12 Surface Water Sediment Old Station Discharge Upstream, control Q1-3 TLD NW Sector, perimeter fence R1-1 TLD NNW Sector, perimeter fence 40 39180.00C

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Nurnber Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Revisen No.

Title SNEC Facility Offsite Dose Calculation Manual 0 TABLE 3.3-1 Page 3 of 3 Saxton Nuclear Experimental Corporation Facility Radiological Environmental Monitoring Program Description Local Description Note Station Mgslig Geo 1 Groundwater Monitoring well South of CV fenr.ed area Geo 2 Groundwater Monitoring well West of CV fenced area Geo 3 Groundwater Monitoring well West of CV fenced area Geo 4 Groundwater Monitoring well East of CV fenced area Geo 5 Groundwater Monitoring well East of CV fenced area Geo 6 Groundwater Monitoring well North of CV fenced area Geo 7 Groundwater Monitoring well East of CV fenced area Geo 8 Groundwater Monitoring well North of CV fenced area Geo 9 Groundwater Piezometer inside of CV Fenced area MW1 Groundwater Northeast to Northwest diagona! well MW2 Groundwater Northwest to Southwest diagonal well 41 3918D. Doc l

Number SaMon Nuclear Egenntental Corporadon SAXTON NUCLEAR Facility Policy and Procedure Manual ' 6575-PLN-4542.08 Revision No.

Title 0

SNEC Facility Offsite Dose Calculation Manual I

PART11 l l

1 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES i

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Trio SNEC Facility Offsite Dose Calculation Manual 0 i l

1.0 LIQUID EFFLUENT MONITORS 1.1 Liould Radiation Monitor Set Points There is no Radioactive Liquid Effluent Instrumentation in service during the decommissioning of the Saxton Nuclear Station.

1.2 Liquid Effluent Release Points The outfall for liquid effluents to the Juniata River will be through a temporary hose to the riverbank on Penelec property when release of such effluents is required.

1.3 Control of Liquid Releases Liquid effluent releases are controlled to less than ten times the 10CFR20 concentrations by ensuring that the parameters for the release meet the following equation:

c*f $C (eq j,1)

F+f where: ,

C= ten times the effluent concentration of 10 CFR 20 for the site, in pCi/ml.

c= the radioactivity concentration in the effluent line prior to dilution and release.

f= the flow in the effluent line prior to dilution and release. In volume per unit time, but in the same units as F below.

F= flow rate of any dilution water measured prior to the release point, in volume per unit time.

- The radioactivity content of each batch of radioactive liquid waste is determined prior to release by sampling and analysis in accordance with ODCM Part i Table 3.2-1. The results of pre-release analyses are used with the calculational method described above to assure that the concentration at the point of release is maintained within the ODCM Part i Control 2.2.1.1.

Post-release analysis of samples composited from batch releases are performed in accordance with ODCM Part i Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the ODCM Part I Control 2.2.1.1.

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Trio -

0 SNEC Facility Offsite Dose Calculation Manual 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liould Effluents - 10 CFR 50 Apoendix I The dose from liquid effluents results from the consumption of fish and drinking water. Other pathways contribute negligibly at SNEC Facility. The use of the flow of the Juniata River as the dilution flow for both fish and drinking water consumption is justified based on low liquid effluent flow rates, the lack of normal dilution flow normally associated with a power plant and the small size of the Junista River. This is further described in Reference 3.10. The dose contribu all radionuclides in liquid effluents released to the unrestricted area is calculated using the following expression:

m*

Dose j = E E (At) X (C 3) X e

q>+r g (eq 2.1)

AWij X FR s ( AFij X FR s ,

iJ _s where:

Dose j = the cumulative dose commitment to the total body or any organ, J, from the liquid effluents for the total time period, in mrem.

At = the length of the time period of actual releases, over which Ciand f are averaged for allliquid releases,in hours.

C; = the average concentration of radionuclide,i,in undiluted liquid effluent dur period At from any liquid release,in Cl/ml.

f = undiluted liquid waste flow, in gpm.

FR = actual river flowrate during the period of release or average river flowrate for the month the release is occurring, in gpm.

AWij and gAF = the site-related ingestion dose commitment factor to the total bo for each identified principle gamma and beta emitter, in mrem /hr per Cl/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway.

Values for AW are determined by the following equation:

g (eq 2.2)

AWy= (1.14E5) x (U.) x (DFU) where:

1.45E5 = (1.0E6 pCi/ Cl) x (1.0E3 ml/kg) x (8760 hrlyr)

U, = Water consumption rate for adult is 730 kglyr (Reg. Guide 1.109, Rev.1).

DF = ingestion dose conversion factor for radionuclide, I, for adults total body and for g

" worst case" organ, j, in mrem /pCl, from Table 2.1 (Reg. Guide 1.109) 3918D. doc 44

i Number Saxion mei.ar experimentai Corporauon I SAXTON NUCLEAR Facility Policy and Procedure Manual 6575 PLN 4542.08 Revision No.

0 SNEC Facility Offsite Dose Calculation Manual f

Values for AF are determined by the following equation:

9 (eq2.2.2)

AF,= (1.14E5) x (Ug) x (DFu) x (BF,)

where: I

! 1.45ES = defined above l

_ U, = adult fish consumption, assumed to be 21 kglyr (Reg. Guide 1.109, Rev.1).

DF = ingestion dose conversion factor for radionuclide, I, for adult total body and for g

" worst case" organ, j, in mrem /pCl, from Table 2.1 (Reg. Guide 1.109 Rev.1).

BF = Bioaccumulation factor for radionuclide, i, in fish, in pCl/kg per pCl/L from Table 2.2 i

(Reg. Guide 1.109, Rev.1).

l 2.2 Liquid Radwaste System Dose Calcs Once/ Month ODCM Part I Control 2.2.1.3 requires that appropriate portions of a liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent releases from each unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month.

The following calculational method is provided for performing this dose projection.

At least once per month, when liquid releases are in progress or expected, the total dose from all liquid releases anticipated during the next 31 days shall be calculated. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, appropriate portions of a Liquid Radwaste Treatment System, as defined in Section 3.1, shall be used to reduce radioactivity levels prior to release.

- 2.3 Attemative Liquid Dose Calculational Methodology As an attemative, models in, or based upon, those presented in Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. Default parameter values from Reg.

Guide 1.109 (Rev.1) and/or actual site specific data are used where applicable.

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Number SaMon Nuclear Evelinwntal Corporation

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SNEC Facility Offsite Dose Calculation Manual 0 i

TABLE 2.1 Page 1 of 3 i l

I Liquid Dose Conversion Factors (DCF): DFji l Ingestion Dose Factors for Adults *

(MREM Per pCiIngested) j LIVER T. BODY THYROID KIDNEY LUNG GI-LLI NUCLIDE BONE 1.05E-07 1.05E-07 1.05E 07 1.05E-07 1.05E-07 H '3 NO DATA 1.05E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 I C 14 2.84E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 NA 24 1.70E-06 NO DATA 2.66E-09 1.59E-09 5.86E 10 3.53E-09 6.69E-07 CR 51 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 54 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E 06 MN 56 NO DATA 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 55 2.75E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 FE' 59 4.34E-06 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO- 58 NO DATA 7.45E-07 2.14E 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 CO 60 NO DATA 9 41E 06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 64 1.30E-04 6.86E-08 3,13E 08 NO DATA NO DATA NO DATA 1.74E 06  !

NI 65 5.28E-07 8.33E-08 3.91E 08 NO DATA 2.10E-07 NO DATA 7.10E 06 CU 64 NO DATA 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E 06 ZN 65 4.84E-06 1.97E-08 1.37E 09 NO DATA 1.28E-08 NO DATA 2.96E-09 ZN 69 1.03E-08 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR. 83 NO DATA NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 84 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E 24 BR 85 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 86 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E 19 RB 88 NO DATA

- 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E 21 RB ~89 NO DATA NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 89 3.08E-04 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 90 ' 7.58E 03 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 91 5.67E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 SR 92 2.15E-06 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04

'Y 90 9.62E-09 l

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Tme SNEC Facility Offsite Dose Calculation Manual 0 TABLE 2.1 Page 2 of 3

- Liquid Dose Conversion Factors (DCF):'DFj i ingestion Dose Factors for Adults *

(MREM Per pCI In9ested)

BONE LIVER LBODY THYROtD KIDNEY LUNG 91-LLI NUCLIDE NO DATA 3 % 7-12 NO DATA NO DATA NO D/TA 2.67E-10 Y 91M . 9.09E 11

' . E 09 NO DATA NO DATA NO DATA 7.76E-05 Y 91 1.41E 07 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y '92 8.45E-10 - NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05

=Y 93 2.68E-09 NO DATA 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 95 3.04E-08 9.75E-09

' 1.55E 10 NO DATA 5.12E-10 NO DATA 1.05E-04 ZR 97 1.68E-09 S.39E-10 3.46E-09 1.86E 09 NO DATA 3.42E-09 NO DATA 2.10E-05 NB 95 6.22E-09 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 MO 99 NO DATA 4.31E 06 6.98E 10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC 99M 2.47E-10 ~

3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 TC 101 2.54E-10 3.66E-10 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E 05 RU 103 1.85E-07 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 RU 105 1.54E-08 NO DATA 3.48E 07 NO DATA 5.31E 06 NO DATA 1.78E-04 RU 106 2.75E-06 NO DATA 8.79E-08 NO DATA 2.91E 07 NO DATA 6.04E 05 AG 110M 1.60E-07 1.48E-07 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E 05 SB. 125 1.79E-06 2.00E-08 3.59E 07 8.06E-07 1.09E-05 NO DATA 1.07E 05

~TE .125M 2.68E-06 9.71E-07 8.25E 07 1.73E-06 2.75E 05 NO DATA 2.27E 05 TE 127M 6.77E-06 2.42E-06 3.95E-08 2.38E-08 8.15E-08 4.48E 07 - NO DATA 8.68E 06 TE 127 1.10E-07

.1.82E-06 3.95E 06 4.80E 05 NO DATA 5.79E 05 TE 129M .1.15E-05 4.29E-06 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E 08 TE 129 3.14E-08 1.18E-08 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE' 131M 1.73E-06 8.46E 07 6.22E 09 1.62E 08 8.63E-08 NO DATA 2.79E-09

. TE - 131 1.97E-08 8.23E-09 1.53E 06 1.80E-06 1.57E-05 NO DATA 7.71E-05 TE 132 2.52E 1.63E 06 8.80E-07 1.89E-04 3.48E 06 NO DATA 1.92E-06 i 130 7.56E-07 2.23E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 1 131 4.16E-06 5.95E 06 1.90E-07 1.90E 05 8.65E-07 NO DATA 1.02E-07 l 132 2.03E-07 5.43E 07 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 l '133 1.42E-06 2.47E-06 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 1 134 1.06E-07 2.88E 07 1

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SNEC Facility Offsite Dose Calculation Manual TABLE 2.1 Page 3 of 3 Liquid Dose Conversion Factors (DCF): DF ij j ingestion Dose Factors for Adults

• i (MREM Per pCiIngested)

LIVER Tl BODY THYROID KIDNEY (Qfiq GI-LLI NUCLlDE BONE 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 i 135 4.43E-07 1.18E-06 1.21E-04 NO DATA 4.79E-05 1.59E 05 2.59E 06 j CS 134 6.22E 05 1.48E-04 1.85E-05 NO DATA - 1.43E-05 1.96E 06 2.92E-06 CS 136 6.51E-06 2.57E-05 NO DATA 3.70E 05 1.23E-05 2.11E-06 CS 137 7.97E 05 1.09E-04 7.14E-05 5.40E-08 NO DATA 8.01E-08 7.91E 09 4.65E-13 l CS 138 5.52E-08 1.09E-07 NO DATA 6.46E-11 3.92E-11 1.72E-07 f BA 139 9.70E-08 6.91E-11 2.84E-09 1.33E-06 NO DATA 8.67E 09 1.46E-08 4.18E-05 BA 140 2.03E-05 2.55E 08 1.59E-09 NO DATA 3.31E 11 2.02E-11 2.22E-17 {

BA 141 4.71E 08 3.56E-11 1.34E 09 NO DATA 1.85E 11 1.24E-11 3.00E-26 f BA 142 2.13E 08 2.19E 11 I

3.33E 10 NO DATA NO DATA NO DATA 9.25E-05 LA 140 2.50E-09 1.26E-09 NO DATA NO DATA NO DATA 4.2SE-07 LA - 142- 1.28E 10 5.82E-11 1.45E 11 7.18E 10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE 141 9.36E-09 6.33E-09 1.35E 10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 143 1.65E-09 1.22E-06 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 CE 144 4.88E-07 2.04E-07 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 143 9.20E-09 3.69E-09 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 PR 144-

• 3.01E 11 1.25E 11 4.35E 10 No DATA 4.25E-09 NO DATA 3.49E-05 ND 147 6.29E 09 ' 7.27E-09 3.01E-08 NO DATA NO DATA NO DATA . 2.82E-05 W 187 1.03E 07 8.61E 08 2.40E-05  !

1.17E 10 - 6.45E 11 NO DATA '3.65E 10 NO DATA NP 239 1.19E-09

• ' Dose factors of intemal exposure are for continuous intake over a one-year period and include the dose commitment over a 50-year period; from Reg. Guide 1.109 (Rev.1). Additional dose factors for nuclides not included in this table may be obtained from NUREG-0172.

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 2.2 Page 1 of 1 Bioaccumulation Factors, BFg Bioaccumulation Factors to be Used in the Absence of Site-Specific Data *

(pCl/kg per pCl/ liter)

ELEMENT FRESHWATER FISH INVERTEBRATE H 9.0E-01 9.0E-01 ,

C 4.6E+03 9.1 E+03 NA 1.0E+02 2.0E+02 CR 2.0E+02 2.0E+03 MN 4.0E+02 9.0E+04 '

FE 1.0E+02 3.2E+03 CO 5.0E+01 2.0E+02 NI 1.0E+02 1.0E+02 CU 5.0E+01 4.0E+02 ZN 2.0E+03 1.0E+04 BR . 4.2E+02 3.3E+02 RB 2.0E+03 1.0E+03 SR 3.0E+01 1.0E+02 Y 2.5E+01 1.0E+03 l ZR 3.3E+00 6.7E+00 NB 3.0E+04 1.0E+02 MO 1.0E+01 1.0E+01 TC 1,5E+01 5.0E+00 RU 1.0E+01 3.0E+02 I RH 1.0E+01 3.0E+02

• SB 1.0E+00 1.0E+00 TE 4.0E+02 6.1 E+03 1 1.5E+01 5.0E+00 CS 2.0E+03 1.0E+03 BA 4.0E+00 2.0E+02 LA 2.5E+01 1.0E+03 CE 1.0E+00 1.0E+03 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 W 1.2E+03 1.0E+01 NP 1.0E+01 l 4.0E+02

• ED Bioaccumulation factor values are taken from Reg. Guide 1.109 (Rev.1), Table A-1J.

Sb bioaccumulation factor value is taken from EPRI NP 3840.

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~ SNEC Facility Offsite Dose Calculation Manual 0 3.0 LIQUID EFFLUENT WASTE TREATMENT SYSTEMS 3.1 ' . Liquid Effluent Waste Treatment System 3.1.1 There will be no permanently installed liquid radwaste treatment system at SNEC Facility during decommissioning. Liquid radioactive wastes generated during decommissioning will be processed as necessary using temporary systems supplied by GPU Nuclear or by experienced vendors and contractor where appropriate. Temporary waste treatment systems will be connected to tanks for storage of processed water prior to discharge. They will be batch released after they have been verified to meet the limits of Part I Controls 2.2.1.1 and 2.2.1.2.

4.0- GASEOUS EFFLUENT MONITORS .

4.1 Particulate Monitor Set Points Set points for monitors which detect radionuclides other than noble gases are also established to assure that concentrations of these radionuclides in gaseous effluents do not exceed the limits of ODCM Part i Control 2.2.2.1.

Set points are established so as to satisfy the following equations:

1500 >(C;)(F)(q)(Dy ) (eq 4.1) where:

C; = set point concen' ration based on Sr-90, in pCl/cc F = gaseous effluent flow rate at the monitor, in cc/sec 3

P; = pathway dose parameter, in mrem /yr per Cl/m for the inhalation pathway from Table 4.2. The dose factors are based on the actual Individual organ and most restrictive age group (child) (NUREG-0133).

NOTE Appendix A contains Pi calculational methodology.

1500 = annual dose rate limit to any organ from particulates with half lives greater than 8 days in mrem /yr.

Dy = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary from Table 4.1 for all releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 3.41E-3 sec/m3 at Sector N.

The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors.

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SNEC Facility Offsite Dose Calculation Manual 0 4.2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data SNEC Facility has one required effluent gaseous radiation monitor. This is RMA-1. Surveillance frequencies for this monitor are specified in Part I of the ODCM.

4.2.1 RMA-1 RMA-1 is an Eberline AMS-3 particulate radiation monitor for the Saxton Containment Vessel Ventilation System Exhaust. The monitor is located in the Rad Monitor enclosure just south of the containment ventilation system filters. Sampling for particulate activity is performed off of the monitor. This radiation monitor is interlocked to the containment ventilation system and will automatically stop the ventilation exhaust fan upon a high radiation alarm, monitor failure, or loss of power to the monitor.

4.2.2 RMA-1 Alarm Setpoint Sensitivity; (2.22E6 dpm/ Cl)(0.3 ct/ dis)(SE4 cc/ min) = 3.33E10 com/ min Ci/cc Alarm Setpoint: 4000 cpm above background Alarm Setpoint Basis:

c = jlQ 0mrem /vr (F)(P)(X/Q)

F= Effluent flow rate (cc/sec) 3 P, = Pathway Dose Parameter for Sr 90 (Inhalation pathway: mrem /yr/uCi/m )

X/Q = Dispersion Parameter (sec/ m3 )

1500 = Annual Dose Rate limit for unrestricted areas (mremlyr)

F = 7500 cfm = 3.54E6 cc/sec Pi = 1.01E8 l l

X/Q = 3.41E-3 l c = Inhalation Pathway Limiting Concentration l c = 1.23E-9 Ci/cc l t

Setpoint Calculation Alarm will activate after 180 minutes with above conditions (1.23E-9 Cl/cc)(3.33E10 cpm / Ci/cc)(180 min) = 7380 cpm The alarm setpoint will be set at 4000 cpm. approximately 50% of the calculated setpoint.

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SNEC Facility Offsite Dose Calculation Manual 0 4.3 Control of Gaseous Effluent Releases SNEC Facility gaseous effluent combined releases are controlled (per ODCM Part !) by effluent sampling and radiation monitor set points. These measures assure that releases do not combine to produce dose rates at the site boundary exceeding 1500 mrem per year to an organ. The absence of noble gases at the site precludes producing dose rates at the site boundary exceeding 500 mrem per year total body or 3000 mrem per year to the skin. The vent radiation monitor set point is based on a fraction of the above limits so they do not exceed the above limits. This effluent radiation monitor set point is calculated using the methodology described in equation 4.1.

Post-release analyses of samples composited from continuous releases are performed in accordance with ODCM Part 1. The results of the analyses are used to assure that the dose rctes at the site boundary are maintained within the limits of ODCM Part 1. l 1

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 4.1 Page 1 of 1 Results Summary ATMOSPHERIC Dl8PER810N FACTORS FOR SNEC FACILITY 4 GROUND RELEASE DISTANCE -

SECTOR AVERAGE X/Q IN SEC/CU.M. (IN METERS)

TO SECTOR 200 1000 3200 4800 8000 11000 ~16000 24000 '40000 56000 80000 N 3.41E43 1.10E 04 3.61E 05 1.95E-05 1.15E-05 7.70E-08 5 26E-06 2.98E 06 1.71 E-06 1.12E-06 7 48E-07 NNE 116E43 3.70E-05 1.21 E-05 6 61E-06 3.83E 06 2.58E-06 1.74E-06 9 83E-07 S eDE 07 3.74E-07 2 48E-07 NE 3 75E 04 1.19E 05 3 88E-06 2.13E-08 1.23E-06 8.24E 07 5 56E 07 3.13E 07 1.81E 07 1.19E 07 7.90E-06 ENE- 268E 04 8.38E 06 2.72E 06 1.40E 08 8 40E-07 5.71E 07 3.83E-07 2.14E 07 1.25E-07 8.21E 08 5 44E-06 E 3 64E-04 1.15E-05 3.76E 06 2.04E 06 1.18E-06 7.91 E-07 5.38E 07 3.03E 07 1.74E-07 1.15E 07 7.62E-08 ESE 8 24E-05 2.56E-06 8.25E 07 4.61 E-07 2.57E-07 1.74E-07 1.14E-07 6.38E 06 3 75E 06 2.48E 06 1.64E-06 SE 5 27E-05 185E 06 5 38E-07 2.90E 07 1.68E-07 1.14E-07 7 53E 08 4.22E-08 2.48E-08 1.63E 08 1.08E-06 SSE 9 50E-05 2.97E-06 985E 07 5.26E-07 3.00E-07 2.01E 07 136E-07 7.61E 08 4.40E 06 2.90E 08 193E-08 S 2 27E-04 7.12E-06 2.31E-06 1.27E 08 7.24E-07 4 88E-07 3.26E47 1.83E-07 1.08E-07 7.01E 08 4 64E-08 SSW 2 50E 04 8 01E 00 2 58E-06 1.46E 06 8 00E 07 5 48E47 3 55E-07 1.98E-07 1.18E-07 7.77E-08 512E-06 SW 2 81E-04 8 75E 06 2.83E-06 1.50E 08 8.46E-07 6.00E 07 3 94E 07 2.20E 07 1.30E-07 8 56E 08 585E-08

, , ,. WSW 419E-04 1.33E 05 4 33E-06 2.41 E-06 1.37E-06 9.30E-07 6.18E 07 3.48E 07 2.04E 07 1.34E-07 8 85E 08 4-83 W 130E-03 4 44E 06 1.46E 05 7.97E 08 4.63E-06 3.12E 06 2.11E 06 1.19E-06 6.90E 07 4 54E 07 3 00E-07 4 34 WNW 1.47E43 4 71E 05 1.55E 05 8 43E-08 4 92E 08 3 31E-06 2.25E-06 1.27E 06 7.34E 07 4 82E-07 3.20E-07

• - NW 9 91E-04 3.18E-05 1.04E 05 5.71E 06 3.32E-06 2.24E 06 152E-06 8 56E 07 4 95E47 3.25E 07 2.15E-07 NNW 162E43 5 21E 05 1.71 E-05 9.32E-06 5 46E-06 3.66E-06 l 2.40E-06 1.41 E-06 8.13E-07 5.34E 07 3 54E 07 GROUND RELEASE DISTANCE SECTOR AVERAGE D/Q IN 1/SQ.M. (IN METERS)

TO SECTOR 700 1800 3200 4000 8000 11000 16000 24000 40000 56000 80000 N 2 56E 07 9.88E 00 2.98E 00 1.40E-00 5 42E-10 3 23E-10 1.72E 10 9.20E 11 3.55E 11 1.83E-11 9 86E-12 NNE 207E 07 7.98E 00 2.3BE 00 1.13E 00 4 30E-10 2 61E 10 140E-10 7.45E 11 2.67E 11 1.48E 11 7.96E 12 NE 1 14E-07 4.40E-00 1.32E 00 6.24E-10 2.42E-10 1.44E-10 7 70E 11 411E 11 1.58E-11 818E-12 4 40E 12

- ENE 155E 07 5 96E 00 1.79E-09 8 44E 10 3.26E-10 195E 10 104E 10 5.56E-11 2.15E 11 1.11 E-11 5 98E 12 E 1.24E-07 4.75E 00 1.43E-00 6.73E 10 2.61E 10 1.55E-10 8 31E 11 4 43E-11 1.71E-11 8.82E 12 4 75E 12 ESE 3.31E-08 1.27E 00 3.82E-10 1.80E-10 7.00E-11 4.17E 11 223E 11 1.19E-11 4.58E 12 2.36E-12 1.27E 12 SE 2.15E-08 8.28E-10 2.48E-10 1.17E-10 4.55E 11 2.71E 11 145E 11 7.72E 12 2.98E 12 1.54E-12 8.28E 13 SSE 4 27E-06 164E-00 4 93E 10 2.33E-10 9.03E 11 5.36E 11 2.87E 11 153E-11 5 91E 12 3.05E-12 164E-12 S 8 77E 08 3.37E 00 1.01E 00 4.78E-10 1.85E-10 1.10E 10 5.90E 11 3.15E 11 1.21E 11 6.28E-12 3.37E 12 SSW 924E 08 3.55C-00 1.07E 00 5.03E-10 1.95E-10 1.16E-10 6 22E-11 3.32E-11 128E-11 6 60E 12 3 55E 12 SW 7.20 ! 08 2.80E-00 8 40E 10 3.97E-10 1.54E 10 917E-11 4 90E 11 2.61 E-11 1.01 E-11 5.20E-12 2 80E 12 WSW 5.05 ! 08 1.94E 00 5.83E-10 2.75E-10 1.07E-10 6 35E-11 3 40E-11 1.81E-11 6 90E 12 3 61E-12 1.94E 12 W 9 98E 08 3 84E-00 1.15E 00 5.44E 10 2.11 E-10 1.26E 10 6.72E-11 3.58E 11 1.30E-11 7.13E 12 3 84E-12 WNW 1.08E 07 414E 00 124E 00 5.86E-10 2.28E-10 1.35E 10 7.24E.11 3 86E 11 1.40E 11 7.68E-12 414E-12 NW 8.23E 06 3.16E-00 9 40E-10 4 48E-10 1.74E 10 1.04E 10 5 54E-11 2.95E 11 1.14E-11 5 88E 12 316E-12 NNW 1.08E-07 4.16E-00 1.25E-00 5.90E 10 2.29E-10 1.36E 10 7.29E-11 3.80E 11 1.50E-11 7.73E 12 416E 12 I

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5.1 Gaseous Effluents - Instantaneous Release Limits ,

5.1.1 ' Tritium and Radionuclides in Particulate Form. with Half-Lives Greaterthan 8 Days For Tritium and Radionuclides in Particulate Form, with half-lives Greater than 8 days, the following equation applies:

DOSE RATE,p = E (Pg )(Dy)(Qg) (eq5.1) where:

Dose Ratep = mrem / year organ dose rate.

Pi = dose parameter for Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, for the inhalation pathway, in mrem /yr per Ci/m', from Table 4.2. The dose factors are based on the critical individual organ and most restrictive age group (child).

Dy = hi hest 0 sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m', from Table 4.1 for all releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 3.41E-3 se'c/m'. at Sector N.

Qi = release rate of each radionuclide,I,in C1/sec Calculated using the concentration of each radionuclide, i, in Ci/cc, times the release pathway flow rate, in cc/second.

5.2 Gaseous Effluents - 10 CFR 50 Anoendix I 5.2.1 Tritium and Radionuclides in Particulate Form. with Half-Lives Greater than 8 Days The dose to an individual from Tritium and Radionuclides in Particulate Form with half-lives greater than 8 days in gaseous effluents released from the site to an unrestricted area is determined by solving the following expression:

DOSE , = I (R g)(D y)(Qg)(3.17E - 8) (eq 5.2) where:

Doseo= dose to all real pathways, p, to organ, o, of an individual in age Group, a, i

from Tritium and Radionuclides in Particulate Form, with half-lives greater

{ than 8 days, in mrem, during any desired time period.

j Ri = the dose factor for each identified radionuclide, I, pathway, p, age group, a, 3

and organ, o, in mrem /yr per Cl/m for the inhalation pathway and I

m*- rem /yr per Ci/sec for other pathways, from Tables 5.2 to 5.7.

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-NOTE 3

Tritium. H 3, dose factor is mrom/ year per Cl/m for all pathways.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m', for the inhalation  ;

pathway, and D/Q, in m'*, for other pathways. Table 4.1 is used for all )

releases. Maximum value of X/Q presently uAed is 3.41E-3 sec/m' at Sector N. Maximum value of D/Q in m is 2.56E-7 m at Sector N.

Dv(H-3)= In the case of H-3 only the X/Q's are used for all pathways from Table 4.1 for all releases.

Qi = release of Tritium and Radionuclides, i, in Particulate Form with half lives greater than 8 days, in Cl, cumulative over the specified time period (pCi/second

• seconds).

3.17E-8= inverse of the number of seconds in a year, t 5.3 Ventilation Exhaust Treatment System Dose Calculations Once oer Month

. ODCM Part i Surveillance 2.2.2.3 requires that doses due to gaseous releases from the unit be projected monthly. The following calculational method is provided for performing this dose projection.

At least once per month the maximum organ dose for the quarter to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual release during the period for which the projection is made, if these projected doses exceed the value listed above, appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactivity levels prior to release.

At the discretion of Radiological Engineering, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter to-date is not believed to be representative of the dose per day projected for the next month.

5.4 Altemative Dose Calculational Methodolooies for Gaseous Effluents As an altemative to the methods described above, the models in/or based upon, those presented in Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. {

Default parameter values from Regulatory Guide 1.109 (Rev.1) and/or actual sue specific data can be used where applicable.

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l SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.2.1 Page 1 of 1 Pathway Dose Factor 4, Ri ,

. AGE GROUP: INFANT PATHWAY: INHALATION E .

3 ORGAN DOSE FACTORS; mrem / year per C1/m NUCLIDE . BONE LIVER T. BODY THYROID KIDNEY LUNG ' GI-LLI H-3. 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 C-14 2.65E+04 5.31 E+03 5.31E+03 5.31 E+03 5.31E+03 5.31E+03 5.31E+03 CR-51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN-54 ' O.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+03 FE-55 1.97E+04 1.17E+04- 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 FE 59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 CO-58 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 CO-60 0.00E+00 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06 3.19E+04 NI-83 3.39E+05 2.04E+04 1.16E+04 0.00E+00 0.00E+00 2.09E+05 2.42E+03 ZN-65 1.93E+04 6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47E+05 5.14E+04 RB-86 0.00E+00 1.90E+05 8.82E+04 0.00E+00 0.00E+00 0.00E+00 3.04E+03 SR-89 3.98E+05 0.00E+00 1.14E+04 0.00E+00 - 0.00E+00 2.03E+06 6.40E+04 i SR 90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 Y-91 5.88E+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.03E+04 ZR 1.15E+05 2.79E+04 -

2.03E+04 0.00E+00 3.11 E+04 1.75E+06 2.17E+04 NB-95 1.57E+04 6.43E+03 3.78E+03 0.00E+00 4.72E+03 4.79E+05 1.27E+04 RU-103 2.02E+03 0.00E+00 6.79E+02 0.00E+00 4.24E+03 5.52E+05 1.61E+04 RU-106 8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.07E+05 1.16E+07 1.64E+05 -

AG-110M 9.98E+03 7.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 TE-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.00E+00 4.47E+05 1.29E+04 1 TE-127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31 E+06 2.73E+04 TE-129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 l-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 1133 1.32E+04 1.92E+04 5.60E+03. 3.56E+06 2.24E+04 0.00E+00 2.16E+03 CS-134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 i CS-136 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 BA-140 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 CE 141 2.77E+04 1.67E+04 = 1.99E+03 0.00E+00 5.25E+03 5.17E+05 2.16E+04

. CE 144 - 3.19E+06 1.21 E+06 1.76E+05 0.00E+00 5.38E+05 9.84E+06 1.48E+05 PR-143 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 ND-147 . 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3.22E+05 3.12E+04 57 3018D. DOC

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.2.2 Page 1 of 1 Pathway Dose Factors, Ri l AGE GROUP: CHILD ' PATHWAY: INHALATION I ORGAN DOSE FACTORS; mrem / year per pCl/m*

NUCLIDE . BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 . 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 . 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 CR-51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN-54 0.00E+00 ' 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 FE 55 4.74E+04 ~ 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 FE-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 CO-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 CO 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 NI-63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 ZN-65 4.26E+04 1.13E+05 7.03+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 RB-86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03

- SR-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 ,

I SR-90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y-91 9.14E+05 0.00E+00 2.44E+04 0.00E+00, 0.00E+00 2.63E+06 1.84E+05  ;

ZR 95 1.90E+05 4.18E+04 - 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 1 NS-95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 I RU-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 RU-106 ' 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 AG-110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 TE 125M 6.73E+03 2.33E+03 9.14E+02 - 1.92E+03 0.00E+00 4.77E+05 3.38E+04 TE 127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE 129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 1131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 ,

1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 CS-134 . 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 -

. CS-136 - 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 CS-137 ' 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 BA-140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11 E+01 1.74E+06 1.02E+05 CE-141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61 E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 PR-143 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 ND-147 1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 8.21 E+04 58 301so. Doc

Number Saen Nuciear Experimentai Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6576-PLN-4542.08 Tme Revision No.

SNEC Facility ONsite Dose Calculation Manual 0 TABLE 5.2.3 Page 1 of 1 Pathway Dose Factors, Ri l

AGE GROUP: TEEN PATHWAY: INHALATION l

ORGAN DOSE FACTORS; mrem / year per Ci/m' NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 l CR-51 0.00E+00 0.00E+00 ,1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 MN-54 0.00E+00 5.11 E+04 8.40E+03 ' 0.00E+00 1.27E+04 1.98E+06 6.68E+04 FE 55 3.34E+04 2.38E+04 5.54E+03 0.00E+00 0.00E+00 1.24E+05 6.39E+03 FE 59 .1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05

- CO-58 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+0S 9.52E+04 l

' CO-60 0.00E+00 1.51 E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 NI-63 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 i RB-86 0.00E+00 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 1.77E*04 SR-89 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 SR-90 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 Y-91 6.61E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06 4.09E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 NS-95 . 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 RU-103 - 2.10E+03 0.00E+00 8.96E+02 0.00E+00 7.43E+03 7.83E+05 1.09E+05 RU-106 9.84E+04 0.00E+00 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05  ;

AG 110M 1.38E+04 1.31 E+04 7.99E+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 i 6.67E+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 i TE 125M 4.88E+03 2.24E+03 TE 127M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 TE-129M '1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 l-131 3.54E+04 4.91 E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 t 1-133 - - 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 CS 134 - 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 CS-136 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04

' CS 137 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 BA-140 5.47E+04 6.70E+01 3.52E+03 0.00E+00 2.28E+01 2.03E+06 2.29E+05 CE 141 -- 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 CE 144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+06 - 1.34E+07 8.64E+05 PR 143 1.34E+04 5.31 E+03 - 6.62E+02 0.00E+00 3.09E+03 4.83E+05 2.14E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 0.00E+00 5.02E+03 3.72E+05 1.82E+05 59 391BD. DOC

I Number SaMon Nelear Egenmental Cgoradon

~SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tme Revision No.

SNEC Facility ONsite Dose Calculation Manual 0 TABLE 5.2.4 - Page 1 of 1 Pathway Dose Factors, Ri

^ AGE GROUP: ADULT PATHWAY: INHALATION ORGAN DOSE FACTORS; mrem / year per pCi/m' NUCLIDE BONE LIVER T. BODY THYRolD KlDNEY LUNG GI-LLI H-3 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 C 14 - 1.82E+04 ' 3.41E+03 3.41 E+03 3.41 E+03 3.41E+03 3.41E+03 3.41E+03 CR-51 0.00E+00 - 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 .0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 FE-55 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 FE-59 .1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 CO 58 0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 1.06E+05 CO-60 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 NI-63 4.32E+05 3.14E+04 1.45E+04 0.00E+00 0.00E+00 1.78E+05 1.34E+04 ZN-65 3.24E+04 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 RB-86 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 1.66E+04 SR-89 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 1.40E+06 3.50E+05 SR-90 9.92E+07 0.00E+00 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 Y 91 4.62E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.85E+05 ZR 95 1.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 NS-95 1.41E+04 7.82E+03 4.21 E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05 RU-103 - 1.53E+03 0.00E+00 6.58E+02 0.00E+00 5.83E+03 5.05E+05 1.10E+05 RU-106 - 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1.34E+05 9.36E+06 9.12E+05 AG-110M 1.08E+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 TE 125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 TE 127M .1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 TE-129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 l-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03 CS-134 3.73E+05 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 CS 136 3.90E+04 - 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04

' CS-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 BA 140 3.90E+04 4.90E+01 2.57E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.26E+03 3.62E+05 1.20E+05 CE 144 - 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05

' PR 143 9.36E+03 3.75E+03 4.64E+02 0.00E+00 2.16E+03 2.81E+05 2.00E+05 ND-147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 80 39180. DOC

r -- 1 1

Number SaMon Nuclear Expenmental Copration I SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 litie Revison No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.3.1 Page 1 of 1 Pathway Dose Factors, Ri

- AGE GROUP: ALL PATHWAY: GROUND PLANE ORGAN DOSE FACTORS

• NUCLIDE T. BODY SKIN H-3 0.00E+00 0.00E+00 C-14 0.00E+00 0.00E+00 CR-51 4.65E+06 5.50E+06 MN-54 1.39E+09 1.62E+09 FE-55 0.00E+00 0.00E+00 FE 59 2.73E+08 3.21E+08 CO-58 3.79E+08 4.44E+08 CO-60 2.15E+10 2.53E+10 NI-63 0.00E+00 0.00E+00 ZN-65 7.47E+08 8.59E+08 RB 86 8.97E+06 1.03E+07 SR-89 2.16E+04 2.51 E+04 SR-90 0.00E+00 0.00E+00 Y-91 1.07E+06 1.21E+06 ZR 95 2.45E+08 2.84E+08 NS-95 1.37E+08 1.61 E+08 RU-103 1.08E+08 1.26E+08 RU-106 4.22E+08 5.06E+08 AG 110M 3.44E+09 4.01E+09 TE-125M 1.55E+06 2.13E+06 TE-127M 9.17E+04 1.08E+05 TE-129M 1.98E+07 2.31E+07 l-131 1.72E+07 2.09E+07 l-131 2.45E+06 2.98E+06 CS-134 6.86E+09 8.00E+09

. CS 136 1.51 E+08 1.71E+08 C3-137 1.03E+10 1.20E+10 BA 140 2.06E+07 2.36E+07 CE-141 1.37E+07 1.54E+07 CE 144 6.96E+07 8.05E+07 PR 143 0.00E+00 0.00E+00 ND-147 8.39E+06 1.01E+07 2

• m - mrem / year per Cl/sec.

61 3918D DOC l

Number S xton Nucie r Experiment.:Corpor. tion SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Trio Revoon No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.4.1 ' Page 1 of 1 Pathway Dose Factors, Ri ,

AGE GROUP; INFANT PATHWAY: GRASS-COW-MILK ORGAN DOSE FACTORS; m*- mrem / year per Ci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.38E+03 ' 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 l C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+08 5.00E+08 . 5.00E+08 5.00E+08 I CR 51 0.00E+00 0.00E+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN-54 0.00E+00 3.91E+07 8.85E+06 0.00E+00 8.65E+06 0.00E+00 1.43E+07 FE 55 ~ 1.35E+08 8.74E+07 2.34E+07 0.00E+00 0.00E+00 4.27E+07 1.11E+07 FE-59 2.25E+08 3.93E+08 1.55E+08 0.00E+00 0.00E+00 1.16E+08 1.88E+08 CO-58 0.00E+00 2.43E+07 6.06E+07 0.00E+00 0.00E+00 0.00E+00 6.05E+07 CO-60 0.00E+00 8.83E+07 2.08E+08 0.00E+00 0.00E+00 0.00E+00 2.10E+08 NI-63 3.50E+10 - 2.16E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 1.08E+08 ZN 5.56E+09 1.91E+10 8.79E+09 0.00E+00 9.24E+09 0.00E+00 1.61E+10 RB-86 0.00E+00 . 2.23E+10 1.10E+10 0.00E+00 0.00E+00 0.00E+00 5.70E+08 SR-89 1.26E+10 0.00E+00 3.62E+08 0.00E+00 0.00E+00 0.00E+00 2.59E+08 SR-90 1.22E+11 0.00E+00 3.10E+10 0.00E+00 0.00E+00 0.00E+00 1.52E+09 Y-91 7.34E+04 0.00E+00 1.95E+03 0.00E+00 0.00E+00 0.00E+00 5.26E+06 ZR-95 6.81E+03 1.66E+03 1.18E+03 0.00E+00 1.79E+03 0.00E+00 8.27E+05 NS-95 5.94E+05 2.45E+05 - 1.41E+05 0.00E+00 1.75E+05 0.00E+00 2.07E+08 RU-103 8.68E+03 0.00E+00 2.90E+03 0.00E+00 1.81E+04 0.00E+00 1.06E+05 RU-106 1.91E+05 0.00E+00 2.38E+04 0.00E+00 2.25E+05 0.00E+00 1.45E+06 AG-110M ' 3.86E+08 2.82E+08 - 1.87E+08 0.00E+00 4.03E+08 0.00E+00 1.46E+10 TE 125M 1.51E+08 5.05E+07 2.04E+07 5.08E+07 0.00E+00 0.00E+00 7.19E+07 TE-12iM 4.22E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 0.00E+00 1.70E+08 - !

TE-129M 5.58E+08 1.91 E+08 8.59E+07 2.14E+08 1.39E+09 0.00E+00 3.33E+08 l l-131 . 2.72E+09 3.21 E+09 1.41E+09 1.05E+12 3.75E+09 0.00E+00 1.15E+08 l-133 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 0.00E+00 8.96E+06 CS 134 3.65E+10 6.81E+10 6.88E+09 0.00E+00 1.75E+10 7.19E+09 1.85E+08 CS 136 1.98E+09 5.83E+09 2.18E+09 0.00E+00 2.32E+09 4.75E+08 8.85E+07 CS-137 5.15E+10 6.03E+10 4.27E+09 0.00E+00 1.62E+10 6.55E+09 1.89E+08 BA 140 ' 2.42E+08 2.42E+05 1.25E+07 0.00E+00 5.75E+04 1.49E+05 5.94E+07 l CE-141 4.34E+04 2.65E+04 3.12E+03 0.00E+00 8.17E+03 0.00E+00 1.37E+07 CE-144 2.33E+06 9.53E+05 1.30E+05 0.00E+00 3.85E+05 0.00E+00 1.34E+08 PR 143 1.49E+03 5.56E+02 7.37E+01 0.00E+00 2.07E+02 0.00E+00 7.84E+05 ND-147 8.83E+02 9.07E+02 . 5.55E+01 0.00E+00 3.50E+02 0.00E+00 5.75E+05 62 3918D. DOC

Number Samon Nuclear Experirnental Corporadon SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tme Rowsion No.

l SNEC Facility Offsite Dose Calculation Manua: 0 i TABLE 5.4.2 Page1 of1 Pathway Dose Factors, Ri AGE GRC' R CHILD PATHWAY: GRASS-COW-MILK 2

ORGAN DOSE FACTORS; m -mrern/ year per Ci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 1 H3 0.00E+00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 ;

C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 l CR-51 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 i MN-54 0.00E+00 2.10E+07 5.59E+06 0.00E+00 5.89E+06 0.00E+00 1.76E+07 l FE 55 1.12E+08 5.94E+07 1.84E+07 0.00E+00 0.00E+00 3.36E+07 1.10E+07 !

FE-59 1.20E+08 1.95E+08 9.70E+07 0.00E+00 0.00E+00 5.65E+07 2.03E+08  !

CO-58 0.00E+00 1.21E+07 3.72E+07 0.00E+00 0.00E+00 0.00E+00 7.08E+07 CO-60 0.00E+00 4.32E+07 1.27E+08 0.00E+00 0.00E+00 0.00E+00 2.39E+08 NI-63 2.97E+10 1.59E+09 1.01 E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 l ZN-65 4.14E+09 1.10E+10 6.86E+09 0.00E+00 6.95E+09 0.00E+00 1.94E+09 !

RB-86 0.00E+00 8.78E+09 5.40E+09 0.00E+00 0.00E+00 0.00E+00 5.65E+08 )

SP-89 6.63E+09 0.00E+00 1.89E+08 0.00E+00 0.00E+00 0.00E+00 2.57E+08 SR-90 1.12E+11 0.00E+00 2.84E+10 0.00E+00 0.00E+00 0.00E+00 1.51E+09 .

Y-91 3.91 E+04 0.00E+00 1.05E+03 0.00E+00 0.00E+00 0.00E+00 5.21E+06 I ZR 95 3.84E+03 8.43E+02 7.51E+02 0.00E+00 1.21E+03 0.00E+00 8.80E+05 NB-95 3.18E+05 1.24E+05 8.86J+04 0.00E+00 1.16E+05 0.00E+00 2.29E+08 RU-103 4.29E+03 0.00E+00 1.65E+03 0.00E+00 1.08E+04 0.00E+00 1.11E+05 RU-106 9.25E+04 0.00E+00 1.15E+04 0.00E+00 1.25E+05 0.00E+00 1.44E+06 AG-110M 2.09E+08 1.41E+08 1.13E+08 0.00E+00 2.63E+08 0.00E+00 1.68E+10 TE-125M 7.39E+07 2.00E+07 9.85E+06 2.07E+07 0.00E+00 0.00E+00 7.13E+07 TE-127M 2.08E+08 5.61E+07 2.47E+07 4.98E+07 5.94E+08 0.00E+00 1.69E+08 TE-129M 2.72E+08 7.59E+07 4.22E+07 8.76E+07 7.98E+08 0.00E+00 3.31E+08 l-131 1.31E+09 1.31E+09 7.46E+08 4.34E+11 2.16E+09 0.00E+00 1.17E+08 l-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 0.00E+00 8.58E+06 CS-134 2.27E+10 3.72E+10 7.85E+09 0.00E+00 1.15E+10 4.14E+09 2.01E+08 CS-136 1.01E+09 2.79E+09 1.80E+09 0.00E+00 1.49E+09 2.21E+08 9.80E+07 CS-137 3.23E+10 3.09E+10 4.56E+09 0.00E+00 1.01 E+10 3.62E+09 1.93E+08 BA-140 1.18E+08 1.03E+05 6.86E+06 0.00E+00 3.35E+04 6.14E+05 5.96E+07 CE-141 2.19E+04 - 1.09E+04 1.62E+03 0.00E+00 4.79E+03 0.00E+00 1.36E+07 CE-144 1.63E+06 5.09E+05 8.67E+04 0.00E+00 2.82E+05 0.00E+00 1.33E+08 PR-143 7.18E+02 2.16E+02 3.56E+01 0.00E+00 1.17E+02 0.00E+00 7.75E+05 ND-147 4.45E002 3.61E+02 2.79E+01 0.00E+00 1.98E+02 0.00E+00 5.71E+05 63 3916D. DOC

Number Saxton Nuclear Experimental Corporation

~ SAXTON NUCLEAR - Facility Policy and Procedure Manual 6575-PLN-4542.08 Tme Revieson No.

SNEC Facility ONsite Dose Calculation Manual 0 TABLE 5.4.3 Page 1 of 1 Pathway Dose Factors, Rn AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK ORGAN DOSE FACTORS; m' - mrom/ year per Ci/sec NUCLIDE BONE LIVER T. BODY THYRotD KIDNEY LUNG ' GI-LLI H-3 0.00E+00 9.93E+02 9.93E+02 9.93E+02 ' 9.93E+02 9.93E+02 9.93E+02 C-14 4.86E+08 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 CR 51 0.00E+00 0.00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 MN-54 0.00E+00 1.40E+07 2.78E+06 0.00E+00 4.19E+06 0.00E+00 2.88E+07 1 I

FE-55 4.46E+07 3.16E+07- 7.37E+06 0.00E+00 0.00E+00 2.01E+07 1.37E+07 FE-59 5.19E+07 1.21E+08 4.68E+07 0.00E+00 0.00E+00 3.82E+07 2.86E+08 CO 58 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00E+00 1.10E+08 CO-60 0.00E+00 2.78E+07 6.27E+07 0.00E+00 0.00E+00 0.00E+00 3.62E+08 Ni-63 1.18E+10 8.36E+08 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+08 ZN-65 2.11E+09 7.32E+09 3.42E+09 0.00E+00 4.69E+09 0.00E+00 3.10E+09 RB-86 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.00E+00 0.00E+00 7.00E+08 SR-89 2.68E+09 0.00E+00 7.67E+07 0.00E+00 0.00E+00 0.00E+00 3.19E+08 SR-90 6.62E+10 0.00E+00 1.63E+10 0.00E+00 0.00E+00 0.00E+00 1.86E+09 Y-91 1.58E+04 0.00E+00 4.24E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06 ZR 95 1.65E+03 5.21E+02 - 3.58E+02 0.00E+00 7.65E+02 0.00E+00 1.20E+06 NS-95 1.41E+05 7.82E+04 4.30E+04 0.00E+00 7.58E+04 0.00E+00 3.34E+08 RU-103 1.81 E+03 0.00E+00 7.75E+02 0.00E+00 6.39E+03 0.00E+00 1.51E+05 RU-106 3.76E+04 0.00E+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1.80E+06 AG-110M 9.64E+07 9.12E+07 5.55E+07 0.00E+00 1.74E+08 0.00E+00 2.56E+10 TE 125M 3.01 E+07 1.08E+07 4.02E+06 8.40E+06 0.00E+00 0.00E+00 8.87E+07 TE-127M 8.45E+07 3.00E+07 1.00E+07 2.01E+07 3.42E+08 0.00E+00 2.11E+08 TE-129M 1.10E+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 0.00E+00 4.14E+08 l-131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 0.00E+00 1.49E+08 l-133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.11E+07 0.00E+00 9.09E+06 CS-134 9.83E+09 2.31E+10 1.07E+10 0.00E+07 7.35E+09 2.81E+09 2.88E+08 CS-136 4.49E+08 1.77E+09 1.19E+09 0.00E+00 9.63E+08 1.52E+08 1.42E+08 CS-137 1.34E+10 1.78E+10 6.21E+09 0.00E+00 6.06E+09 2.36E+09 2.54E+08 BA-140 4.87E+07 5.97E+04 3.14E+06 0.00E+00 2.02E+04 4.01E+04 7.51E+07 CE-141 8.89E+03 5.94E+03 6.82E+02 0.00E+00 2.80E+03 0.00E+00 1.70E+07 CE 144 6.59E+05 2.73E+05 3.54E+04 0.00E+00 1.63E+05 0.00E+00 1.66E+08 ,

PR 143 2.90E+02 1.16E+02 1.44E+01 0.00E+00 6.73E+ 01 0.00E+00 9.55E+05 i ND-147 1.81 E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7.12E+05 j i

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l 64 3C180. DOC

Number Samon Nuciear Emerimentai Cupwation

'SAXTON NUCLEAR- - Facility Policy and Procedure Manual 6575-PLN-4542.08 Tme Roweson No.

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.4.4 - Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK 2

- ORGAN DOSE FACTORS; m -mrem / year per Ci/sec  !

- NUCLIDE BONE' . LIVER ' T. BODY - THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 7.62E+02 . 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 C-14 = 2.63E+08 ' 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 CR 51 ' O.00E+00 0.00E+00 2.85E+04 1.70E+04 6.28E+03 3.78E+04 7.17E+06 MN 54 0.00E+00 8.40E+06 1.60E+06 0.00E+00 2.50E+06 0.00E+00 2.57E+07 FE 55 2.51E+07 1.73E+07 4.04E+06 0.00E+00 0.00E+00 9.66E+06 9.93E+06 FE-59 2.97E+07 6.97E+07 - 2.67E+07 0.00E+00 0.00E+00 1.95E+07 2.32E+08 CO-58 0.00E+00 4.71E+06 1.05E+07 0.00E+00 0.00E+00 0.00E+00 9.54E+07 CO-60 'O.00E+00 1.64E+07 3.61E+07 0.00E+00 0.00E+00 0.00E+00 3.08E+08 NI-63 6.72E+09 4.65E+08 2.25E+08 0.00E+00 0.00E+00 0.00E+00 9.71E+07 ZN-65 1.37E+09 4.36E+09 1.97E+09 0.00E+00 2.91E+09 0.00E+00 2.74E+09 RB-86 0.00E+00 2.59E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 5.10E+08 SR-89 1.45E+09 - 0.00E+00 - 4.16E+07 0.00E+00 0.00E+00 0.00E+00 2.32E+08

. SR-90 4.67E+10 0.00E+00 1.15E+10 0.00E+00 0.00E+00 0.00E+00 1.35E+09 Y 91~ 8.57E+03 0.00E+00 2.29E+02 0.00E+00 0.00E+00 0.00E+00 4.72E+06 ZR-95 9.41E+02 3.0;iE+02 2.04E+02 0.00E+00 4.74E+02 0.00E+00 9.57E+05 NB-95 8.24E+04 4.58E+04 2.46E+04 0.00E+00 4.53E+04 0.00E+00 2.78E+08 RU-103 1.02E+03 0.00E+00 4.38E+02 0.00E+00 3.88E+03 0.00E+00 1.19E+05 RU-106 2.04E+04 0.00E+00 2.58E+03 0.00E+00 3.93E+04 0.00E+00 1.32E+06 AG-110M 5.81E+07 5.38E+07 3.19E+07 0.00E+00 1.06E+08 0.00E+00 2.19E+10 TE 125M 1.63E+07 5.89E+06 2.18E+06 ~ 4.89E+06 6.61 E+07 0.00E+00 6.49E+07 i

. TE 127M 4.57E+07 1.63E+07 5.57E+06 1.17E+07 f.86E+08 0.00E+00 1.53E+08 TE-129M 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51E+08 0.00E+00 3.02E+08 l-131 - 2.96E+08 4.23E+08 2.42E+08 1.39E+11 7.2SE+08 0.00E+00 1.12E+08 l-133 3.87E+06 6.73E+06 2.05E+06 9.88E+08 1.17E+07 0.00E+00 6.04E+06 1

' CS-134 5.64E+09 1.34E+10 1.10E+10 0.00E+00 4.34E+09 1.44E+09 2.35E+08 CS-136 2.63E+08 1.04E+09 7.48E+08 0.00E+00 ~ 5.78E+08 7.92E+07 1.18E+08 CS-137- 7.37E+09 1.01E+10 ~ 6.60E+09 0.00E+00 3.42E+09 1.14E+09 1.95E+08 BA-140  : 2.69E+07 3.38E+04 1.76E+06 0.00E+00 1.15E+04 1.94E+04 5.54E+07 l CE-141 4.84E+03 3.27E+03 3.71E+02 0.00E+00 1.52E+03 0.00E+00 1.25E+07 l CE-144 3.57E+05 1.49E+05 1.92E+04 0.00E+00 8.85E+04 0.00E+00 1.21E+08 PR-143 1.57E+02 6.32E+01 7.81E+00 0.00E+00 3.65E+01 0.00E+00 6.90E+05 ND-147 - 9.40E+01 1.09E+02 6.50E+00 0.00E+00 6.35E+01 0.00E+00 5.22E+05 SS 30180.D0C

I Number

- SaMon Nuclear Experimental Corpwadon SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 i Tme Pwman t4o.

SNEC Facility Offsite Dose Calculation Manual - 0 1

' TABLE 5.5.1 Page 1 of 1 Pathway Dose Factors, Ri

- AGE GROUP: INFANT - P%THWAY: GRASS-GOAT-MILK

- ' ORGAN DOSE FACTORS; m* - mrem / year per Ci/sec NUCLlDE ' BONE' LIVER ' T. BODY - -THYRolD KIDNEY LUNG GI-LLI H-3 0.00E+00 4.84E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 C-14 2.34E+09 5.00E+08 - 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 CR 51 0.00E+00 0.00E+00 - 1.94E+04 1.26E+04 2.76E+03 2.46E+04 . 5.64E+05 MN-54 0.00E+00 4.68E+06 1.06E+06 0.00E+00 1.04E+06 0.00E+00 1.72E+06

- FE-55 1.76E+06 1.14E+06 3.03E+05 0.0CE+00 0.00E+00 5.55E+05 1.44E+05 FE-59 2.92E+06 - 5.10E+06 2.01E+06 0.00E+00 0.00E+00 1.51E+06 2.44E+06

- CO 0.00E+00 2.91E+06 7.26E+07 0.00E+00 0.00E+00 0.00E+00 7.25E+06 CO-60 0.00E+00 1.06E+07 - 2.50E+07 0.00E+00 - 0.00E+00 0.00E+00 2.52E+07 NI-63 4.19E+09 2.59E+08 -1.46E+08 0.00E+00 0.00E+00 0.00E+00 1.29E+07 ZN-65 6.67E+08 2.29E+09 1.05E+09 0.00E+00 1.11E+09 0.00E+00 1.93E+09

RB 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 6.83E+07 SR-89 2.65E+10 0.00E+00 7.59E+08 0.00E+00 0.00E+00 0.00E+00 5.44E+08 SR 90 2.55E+11 0.00E+00 6.50E+10 0.00E+00 0.00E+00 0.00E+00 3.19E+09 Y 91 8.80E+03 'O.00E+00 2.34E+02 0.00E+00 0.00E+00 0.00E+00 6.31 E+05

' ZR 8.17E+02 1.99E+02 1.41E+02 0.00E+00 2.15E+02 0.00E+00 9.91E+04 NS-95 7.13E+04 2.93E+04 1.70E+04 0.00E+00 2.10E+04 0.00E+00 2.48E+07 RU-103 1.04E+03 0.00E+00 3.48E+02 0.00E+00 2.17E+03 0.00E+00 1.27E+04 RU-106 2.28E+04 0.00E+00 2.85E+03 0.00E+00 2.70E+04 0.00E+00 1.73E+05 AG-110M 4.63E+07 3.38E+07 2.24E+07 . 0.00E+00 4.84E+07 0.00E+00 1.75E+09 TE-125M 1.81E+07 6.05E+06 2.45E+06 6.09E+06 0.00E+00 0.00E+00 8.62E+06 TE-127M - 5.06E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 0.00E+00 2.04E+07 TE-129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.00E+00 3.99E+07 1-131- 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 0.00E+00 1.37E+08 I-133 4.36E+07 6.35E+07 1.86E+07 1.15E+10 7.46E+07 0.00E+00 1.07E+07 i CS-134 1.09E+11 2.04E+11 2.06E+10 0.00E+00 5.26E+10 2.15E+10 5.55E+08 CS 136 5.94E+09 1.75E+10 6.52E+09 0.00E+00 6.96E+09 1.42E+09 2.65E+08 CS 137 1.54E+11 1.81E+11 - 1.28E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 BA 140 2.90E+07 2.90E+04 1.50E+06 0.00E+00 6.89E+03 1.78E+04 7.13E+06 CE-141. 5.21E+03 3.18E+03 3.74E+02 0.00E+00 9.79E+02 0.00E+00 1.64E+06 CE-144 2.79E+05 1.14E+05 1.56E+04 0.00E+00 4.62E+04 0.00E+00 1.60E+07

. PR 143 1.78E+02 6.66E+01 8.83E+00 0.00E+00 - 2.48E+01 0.00E+00 9.40E+04 ,

ND 147- 1.06E+02 1.09E+02 6.66E+00 0.00E+00 4.19E+01 0.00E+00 6.89E+04 e6 39180.00c

Numtw Samon Nueear Eneiimentai Corporauon SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Rennen No.

I SNEC Facility Offsite Dose Calculation Manual 0 4

TABLE 5.5.2 Page 1 of 1 l

- Pathway Dose Factors, Ri i i

AGE GROUP; CHILD PATHWAY: GRASS-GOAT MILK ORGAN DOSE FACTORS; m'- mrem / year per Ci/sec .

- NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3 0.00E+00 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 ,

C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08  !

CR 51 0.00E+00 0.00E+00 1.22E+04 8.78E+03 1.85E+03 1.24E+04 6.48E+05 i MN-54 0.00E+00 2.52E+06 6.71 E+05 0.00E4 00 7.06E+05 0.00E+00 2.11E+06 FE 55 1.45E+06 7.71E+05 2.39E+05 0.00E+00 0.00E+00 4.36E+05 1.43E+05 ' l FE 59 1.56E+06 2.53E+06 - 1.26E+06 0.00E+00 0.00E+00 7.34E+05 2.64E+06 CO-58 . 0.00E+00 1.46E+06 4.46E+06 0.00E+00 0.00E+00 0.00E+00 8.49E+06 CO-60 0.00E+00 5.18E+06 1.53E+07 0.00E+00 0.00E+00 0.00E+00 2.87E+07 I

NI-83 3.56E+09 1.91E+08 1.21E+08 0.00E+00 0.00E+00 0.00E+00 1.28E+07 ZN-65 4.96E+08 1.32E+09 8.22E+08 0.00E+00 8.33E+09 0.00E+00 2.32E+08 RB-86 0.00E+00 1.05E+09 6.47E+08 0.00E+00 0.00E+00 0.00E+00 6.77E+07 SR-89 1.39E+10 0.00E+00 3.97E+08 0.00E+00 0.00E+00 0.00E+00 5.39E+08 SR 90 2.35E+11 0.00E+00 5.95E+10 0.00E+00 0.00E+00 0.00E+00 3.16E+09 Y-91 4.69E+03 0.00E+00 1.25E+02 0.00E+00 0.00E+00 0.00E+00 6.24E+05 ZR-95 4.60E+02 1.01 E+02 9.00E+01 0.00E+00 1.45E+02 0.00E+00 1.05E+05 NB-95 3.82E+04 1.49E+04 1.06E+04 0.00E+00 1.40E+04 0.00E+00 2.75E+07 RU-103 ' 5.14E+02 0.00E+00 1.98E+02 0.00E+00 1.29E+03 0.00E+00 1.33E+04 RU-106 1.11E+04 0.00E+00 1.38E+03 0.00E+00 1.50E+04 0.00E+00 1.73E+05 AG 110M 2.51E+07 1.69E+07 1.35E+07 0.00E+00 3.15E+07 0.00E+00 2.01E+09 TE 125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 0.00E+00 0.00E+00 8.55E+06 i TE-127M 2.50E+07 6.72E+06 - 2.96E+06 5.97E+06 7.12E+07 0.00E+00 2.02E+07

' TE-129M 3.26E+07 9.10E+06 5.06E+06 1.05E+07 9.56E+07 0.00E+00 3.97E+07 l-131 '1.57E+09 1.57E+09 8.95E+08 5.21E+11 2.58E+09 0.00E+00 1.40E+08 l133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 0.00E+00 1.03E+07

- CS 134 6.80E+10 1.12E+11 2.35E+10 0.00E+00 3.46E+10 1.24E+10 6.01E+08 CS 136 3.04E+09 8.36E+09 5.41E+09 0.00E+00 4.45E+09 6.64E+08 ' 2.94E+08 CS-137 9.68E+10 9.26E+10 1.37E+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 BA-140 ' 1.41E+07 1.24E+04 8.23E+05 0.00E+00 4.02E+03 7.37E+03 - 7.15E+06 j CE-141 2.63E+03 1.31E+03 1.95E+02 0.00E+00 5.74E+02 0.00E+00 1.63E+06 CE-144 1.95E+05 6.11E+04 1.04E+04 0.00E+00 3.38E+04 0.00E+00 1.59E+07 PR-143 8.61E+01 2.59E+01 4.27E+00 0.00E+00 1.40E+01 0.00E+00 9.29E+04

- ND-147 5.34E+01 4.33E+01 3.35E+00 0.00E+00 2.37E+01 0.00E+00 6.85E+04 i

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67 3018D. DOC l

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Number Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revision No.

. SNEC Facility Offsite Dose Calculation Manual 0 TABLE 8.5.3 Page 1 of 1 Pathway Dose Factors, Ri l

g

' AGE GROUP: TEEN ~ PATHWAY: GRASS-GOAT-MILK l

ORGAN DOSE FACTORS; m' - mrem / year per pCi/sec

- NUCLIDE BONE LIVER T. BODY THYROlO KIDNEY LUNG GI-LLI l H3 0.00E+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 '

C 14 ' 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07

- CR 51 0.00E+00 0.00E+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 i MN-54 0.00E+00 1.68E+06 3.34E+05 0.00E+00 5.02E+05 0.00E+00 3.45E+06 I FE-55 5.79E+05 . 4.11 E+05 9.58E+04 0.00E+00 0.00E+00 2.61E+05 1.78E+05 l l FE-59 6.74E+05 1.57E+06 6.08E+05 0.00E+00 0.00E+00 4.96E+05 3.72E+06 CO 0.00E+00 9.53E+05 2.20E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+07 I

CO-60 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0.00E+00 0.00E+00 4.35E+07

' NI-63 1.42E+09 1.00E+08 4.81 E+07. 0.00E+00 0.00E+00 0.00E+00 1.60E+07 ZN-65 2.53E+08 8.78E+08 4,10E+08 0.00E+00 5.62E+06 0.00E+00 3.72E+08 i RB-86 0.00E+00 5.67E+08 2.67E+08 0.00E+00 0.00E+00 0.00E+00 8.40E+07 {

SR-89 5.62E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+08 q SR-90 ~ 1.39E+11 0.00E+00 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+09 >

Y 91 1.90E+03 0.00E+00 5.09E+01 0.00E+00 0.00E+00 0.00E+00 7.78E+05 ZR-95 1.98E+02 6.25E+01 4.30E+01 0.00E+00 9.18E+01 0.00E+00 1.44E+05 NB 1.69E+04 9.38E+03 5.16E+03 0.00E+00 9.09E+03 0.00E+00 4.01E+07 RU-103 : 2.17E+02 0.00E+00 9.29E+01 0.00E+00 7.66E+02 0.00E+00 1.82E+04 RU-106 4.50E+03 0.00E+00 5.68E+02 0.00E+00 8.69E+03 0.00E+00 2.16E+05 AG-110M 1.16E+07 1.09E+07 6.65E+06 0.00E+00 2.09E+07 0.00E+00 3.07E+09 TE-125M 3.61 E+06 1.30E+06 4.82E+05 1.01E+06 0.00E+00 0.00E+00 1.06E+07 TE 127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.11E+07 0.00E+00 2.52E+07 TE 129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.00E+00 4.96E+07 J

l-131 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 0.00E+00 1.79E+08 1133- 8.49E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07 CS-134 2.95E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.41E+09 8.62E+08 CS-136 1.35E+09 5.30E+09 3.56E+09 0.00E+00 2.89E+09 4.55E+08 4.27E+08 CS-137 4.02E+10 5.34E+10 1.86E+10 0.00E+00 1.82E+10 7.07E+09 7.60E+08 ,

BA-140 5.84E+06 7.16E+03 3.76E+05 0.00E+00 2.43E+03 4.81E+03 9.01E+06 CE 141 - 1.07E+03 7.12E+02 8.18E+01 0.00E+00 3.35E+02 0.00E+00 2.04E+06 i CE-144 7.90E+04 3.27E+04 4.25E+03 0.00E+00 1.95E+04 0.00E+00 1.99E+07 i PR-143 3.48E+01 1.39E+01 1.73E+00 0.00E+00 8.08E+00 0.00E+00 1.15E+05 ND-147 2.18E+01 2.37E+01 1.42E+00 0.00E+00 1.39E+01 0.00E+00 8.54E+04 es seiso coe l l

l I

7

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Number Sadon Nuclear Equimental Corporadon SAXTON NUCLEAR Facility Policy and Procedure Manual 65'/5-PLN-4542.08 Tme Revieson No.

SNEd Facility Offsite Dose Calculation Manual 0 TABLE 5.8.4 Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: ADULT - PATHWAY: GRASS-GOAT-MILK ORGAN DOSE FACTORS; m* -mrem / year per Cl/sec NUCLIDE BONE LIVER T. BODY THYRolD KIDNEY LUNG Gl-LLI H-3 0.00E+00 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 C 14 2.64E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 CR-51 0.00E+00 0.00E+00 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 MN-54 0.00E+00 1.012+06 1.93E+05 0.00E+00 3.01E+05 0.00E+00 3.10E+06 FE-55 3.27E+03 21:6E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+05 1.30E+05 FE 59 3.87E+05 9.09E+05 3.48E+05 0.00E+00 0.00E+00 2.54E+05 3.03E+06 CO-58 0.00E+00 5.66E+05 1.27E+06 0.00E+00 0.00E+00 0.00E+00 1.15E+07 CO-60 0.00E+00 1.97E+06 . 4.35E+06 0.00E+00 0.00E+00 0.00E+00 3.70E+07 N143 8.08E+08 5.60E+07 2.71E+07 0.00E+00 0.00E+00 0.00E+00 1.17E+07 ZN-65 .1.65E+08 5.24E+08 2.37E+08 0.00E+00 3.51E+08 0.00E+00 3.30E+08 RB-86 0.00C:+00 3.12E+08 1.45Ef+08 0.00E+00 0.00E+00 0.00E+00 6.14E+07

, SR-89 3.05E+09 0.00E+00 8.76E+07 0.00E+00 0.00E+00 0.00E+00 4.89E+08 SR-90 9.84E+10 0.00E+00 2.41E+10 0.00E+00 0.00E+00 0.00E+00 2.84E+09

-Y-91 1.03E+03 0.00E+00 2.76E+01 0.00E+00 0.00E+00 0.00E+00 5.68E+05 ZR-95 1.13E+02 3.63E+01 - 2.46E+01 0.00E+00 5.70E+01 0.00E+00 1.15E+05 NB-95 9.92E+03 5.52E+03 2.97E+03 0.00E+00 5.45E+03 0.00E+00 3.35E+07 RU-103 1.22E+02 0.00E+00 5.27E+01 0.00E+00 4.67E+02 0.00E+00 1.43E+04 RU-106 2.45E+03 0.00E+00 3.10E+02 0.00E+00 4.73E+03 0.00E+00 1.59E+05 AG 110M 6.99E+06 6.47E+06 3.84E+06 0.00E+00 1.27E+07 0.00E+00 2.64E+09 TE 125M 1.96E+06 7.09E+05 2.62E+05 5.89E+05 7.96E+06 0.00E+00 7.81E+06

- TE 127M 5.50E+06 1.97E+06 6.70E+05 1.41E+06 2.23E+07 0.00E+00 1.84E+07 TE-129M 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 0.00E+00 3.64E+07 l-131 3.56E+08 5.09E+08 2.92E+08 1.67E+11 8.73E+08 0.00E+00 1.34E+08

'l133 4.65E+06 8.10E+06 2.47E+06 1.19E+09 1.41E+07 0.00E+00 7.28E+06 CS-134 1.70E+10 4.04E+10 3.30E+10 0.00E+00 1.31E+10 4.34E+09 7.07E+08 CS-136 7.92E+08 3.13E+09 2.25E+09 0.00E+00 1.74E+09 2.38E+08 3.55E+08

' CS-137 2.22E+10 3.03E+10 1.99E+10 0.00E+00 1.03E+10 3.42E+09 5.87E+08 BA-140 3.24E+06 - 4.07E+03 2.12E+05 0.00E+00 1.38E+03 2.33E+03 6.67E+06 CE-141 5.82E+02 3.94E+02 - 4.47E+01 0.00E+00 1.83E+02 0.00E+00 1.51E+06 CE-144 4.30E+04 1.80E+C.'. 2.31E+03 0.00E+00 1.07E+04 0.00E+00 1.45E+07 PR-143 1.90E+01 7.60E+00 9.40E+01 0.00E+00 4.39E+00 0.00E+00 8.30E+04 ND-147 1.13E+01 1.31 E+01 7.82E-01 0.00E+00 7.65E+00 0.00E+00 6.28E+04 69 3918D. DOC

Number Smen Nuclear Expenmental Cwpwadon c

.SAXTON NUCLEAR-Facility Policy and Procedure Manual 6575-PLN-4542.08 Tee Revieson No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.6.1 Page 1 of 1 Pathway Dose Factors, Ri

' AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT ORGAN DOSE FACTORS; m* -mrem / year per Cl/sec NUCLIDE BONE LIVER T. BODY ~ THYRotD . KIDNEY LUNG GI-LLI H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

- C-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CR-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MN-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

- CO-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

' ZN-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-90 . 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y 91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZR-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

. NS-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU-103 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU-106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 AG-110M 0.00E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '

TE-125M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-127M - 0.00E+00 0.00E+00 0.0CE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-129M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CG-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE 144 - 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PR-143 - 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND-147 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 70 3918D DOC

. .< ~. .. . .-

y Number Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revisaon No.

SNEC Facility Offsite Dose Calculation Manual- 0 TABLE 5.6.2 Page 1 of 1 Pathway Dose Factors, Ri -

AGE GROUP: ~ CHILD PATHWAY: GRASS-COW-MEAT ORGAN DOSE FACTORS; m* -mrem / year per Ci/sec NUCLIDE BONE LIVER T. BODY - THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.34E+02 ' 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 7.67E+07  ;

C-14 3.84E+08 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 '

CR-51 0.00E+00 0.00E+00 8.78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 MN-54 0.00E+00 8.01E+06 2.13E+06 - 0.00E+00 2.25E+06 0.00E+00 6.73E+06 FE-55 4.57E+08 2.43E+08 7.52E+07 0.00E+00 0.00E+00 1.37E+08 4.49E+07 FE 59 3.77E+08 6.10E+08 3.04E+08 0.00E+00 0.00E+00 1.77E+08 6.35E+08 CO-58 0.00E+00 1.64E+07 5.03E+07 0.00E+00 0.00E+00 0.00E+00 9.58E+07 CO-60 0.00E+00 6.93E+07 2.04E+08 0.00E+00 0.00E+00 0.00E+00 3.84E+08 NI-63 2.91 E+10 1.56E+09 9.91 E+08 0.00E+00 0.00E+00 0.00E+00 1.05E+08

' ZN-65 ' 3.76E+08 1.00E+09 6.22E+08 0.00E+00 6.31E+08 0.00E+00 1.76E+08 RB-86 0.00E+00 5.76E+08 3.54E+08 0.00E+00 0.00E+00 0.00E+00 3.71E+07 l SR-89 4.82E+08 - 0.00E+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07 SR 90 1.04E+10 0.00E+00 2.64E+09 0.00E+00 0.00E+00 0.00E+00 1.40E+08 Y 91 1.80E+06 0.00E+00 4.82E+04 0.00E+00 0.00E+00 0.00E+00 2.40E+08 ZR 95 2.66E+06 5.86E+05 5.21E+05 0.00E+00 8.38E+05 0.00E+00 6.11E+08 NB-95 3.10E+06 1.21E+06 8.63E+05 0.00E+00 1.13E+06 0.00E+00 2.23E+09 l

RU 103 1.55E+08 0.00E+00 5.96E+07 0.00E+00 3.90E+08 0.00E+00 4.01E+09 RU-106 4.44E+09 0.00E+00 5.54E+08 0.00E+00 6.00E+09 0.00E+00 6.91 E+10 l AG-110M 8.39E+06 5.67E+06 4.53E+06 - 0.00E+00 1.06E+07 0.00E+00 6.74E+08

! TE 125M 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.00E+00 0.00E+00 5.49E+08 TE-127M 1.78E+09 4.78E+08 2.11 E+08 4.25E+08 5.06E+09 0.00E+00 1.44E+09 TE 129M 1.79E+09 5.00E+08 2.78E+08 5.77E+08 5.26E+09 0.00E+00 2.18E+09 l131' 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 0.00E+00 1.48E+06 l-133 5.72E-01 7.08E-01 2.68E-01 1.31 E+02 1.18E+10 0.00E+00 2.85E-01 CS-134 9.23E+08 1.51E+09 3.19E+08 0.00E+00 4,69E+08 1.68E*08 8.16E+06 L

- CS-136 1.63E+07 4.48E+07 2.90E+07 0.00E+00 2.39E+07 3.56E+06 1.57E+06 CS 137 - 1.33E+09 1.28E+09 1.89E+08 0.00E+00 4.16E+08 1.50E+08 8.00E+06 l BA 140 4.42E+07 3.87E+04 2.58E+06 0.00E+00 1.26E+04 2.31E+04 2.24E+07 l

CE 141 2.22E+04 1.11E+04 1.65E+03 0.00E+00 4.86E+03 0.00E+00 1.38E+07 CE-144 2.32E+06 7.26E+05 1.24E+05 0.00E+00 4.02E+05 0.00E+00 1.89E+08 PR 143 3.33E+04 1.00E+04 1.65E+03 0.00E+00 5.42E+03 0.00E+00 3.60E+07 l

ND-147 1.17E+04 9.48E+03 7.34E+02 0.00E+00 5.20E+03 0.00E+00 1.50E+07 1

71 3918D. DOC l

C

y ,

Number saxion Nuciear Emerimental Corporation L LSAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 l

N; Revieson No.

l I SNEC Facility Offsite Dose Calculation Manual 0 l TABLE 5.6.3 Page 1 of 1

! Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT ORGAN DOSE FACTORS; m'-mrem / year per Ci/sec NUCLIDE BONE . LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3 0.00E+00 1.93E+02 1.93E+02 - 1.93E+02 1.93E+02 1.93E+02 ' - 1.93E+02 C-14 2.04E+08 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 CR 51 0.00E+00 0.00E+00 5.63E+03- 3.13E+03 1.23E+03 8.03E+03 9.46E+05 MN-54 0.00E+00 7.00E+06 1.39E+06 0.00E+00 2.09E+06 0.00E+00 1.44E+07 FE-55 . 2.38E+08 ~ 1.69E+08 - 3.94E+07 0.00E+00 _ 0.00E+00 1.07E+08 7.31 E+07 FE-59 2.12E+08 - 4.95E+08 1.91E+08 0.00E+00 - 0.00E+00 1.56E+08 1.17E+09 CO-58 0.00E+00 1.40E+07 3.24E+07 0.00E+00 0.00E+00 0.00E+00 1.94E+08

' CO-60 0.00E+00 5.83E+07 1.31 E+08 0.00E+00 0.00E+00 0.00E+00 7.60E+08 l NI-63 1.52E+10 1.07E+09 5.15E+08 0.00E+00 - 0.00E+00 0.00E+00 1.71E+08

- ZN-65 2.50E+08 - - 8.68E+08 4.05E+08 0.00E+00 5.56E+08 0.00E+00 3.68E+08 RB 0.00E+00 4.06E+08 1.91E+08 0.00E+00 - 0.00E+00 0.00E+00 6.00E+07 SR-89 2.55E+08 0.00E+00 7.29E+06 0.00E+00 0.00E+00 0.00E+00 3.03E+07 SR-90 8.04E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.00E+00 2.26E+08 Y 91 9.54E+05 0.00E+00 2.56E+04 0.00E+00 0.00E+00 0.00E+00 3.91E+08 ZR-95 - 1.50E+06 4.73E+05 3.25E+05 0.00E+00 6.95E+05 0.00E+00 1.09E+09 l NB-95 1.79E+06 ' 9.95E+05 5.48E+05 0.00E+00 9.64E+05 0.00E+00 4.25E+09 RU-103 8.56E+07 - 0.00E+00 3.66E+07 0.00E+00 3.02E+08 0.00E+00 7.15E+09 RU-106 2.36E+09 0.00E+00 2.97E+08 0.00E+00 4.54E+09 0.00E+00 1.13E+11 AG-110M 5.06E+06 4.78E+06 2.91 E+06 0.00E+00 9.13E+07 0.00E+00 1.34E+09 TE 125M 3.03E+08 1.09E+08 4.05E+07 8.46E+07 0.00E+00 0.00E+00 8.94E+08 TE-127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.81E+09 0.00E+00 2.35E+09 TE-129M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 0.00E+00 3.56E+09 l-131 -' 8.93E+06 1.25E+07 6.72E+06 3.65E+09 2.15E+07 0.00E+00 2.47E+06 l-133- 3.08E-01 5.22E-01 1.59E-01 7.29E+01 9.16E-01 0.00E+00 3.95E-01 CS-134 5.23E+08- 1.23E+09 5.71E+08 0.00E+00 3.91E+08 1.49E+08 1.53E+07 CS-136 9.43E+06 3.71E+07 2.49E+07 0.00E+00 2.02E+07 3.18E+06 2.99E+06

.. CS-137 7.24E+08 9.63E+08 3.35E+08 0.00E+00 3.28E+08 1.27E+08 1.37E+07 l BA-140 . 2.39E+07 2.93E+04 1.54E+06 0.00E+00 9.94E+03 1.97E+04 3.69E+07

' CE-141 1.18E+04 7.87E+03 9.05E+02 0.00E+00 3.71E+03 0.00E+00 2.25E+07 CE-144 - 1.23E+06 5.08E+05 6.60E+04 0.00E+00 3.03E+05 0.00E+00 3.09E+08 !

PR 143 1.76E+04 7.03E+03 8.76E+02 0.00E+00 4.08E+03 0.00E+00 5.79E+07 l ND-147 6.23E+04 6.78E+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 I

72 3918D. Doc j

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Number saxton Nuciear Experimentai Corporation SMMN NUaMR Facility Policy and Procedure Manual 6575-PLN 4542 08 Tme Revesson No.

SNEC Facility Offsite Dose Calculation Manual 0-TABLE 5.6.4 Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT ORGAN DOSE FACTORS; m'-mrem / year per Cl/sec NUCLIDE BONE LIVER T. BODY THYROlO KIDNEY LUNG GI-LLI H-3 0.00E+00 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 C 14 2.42E+08 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 CR-51 0.00E+00 0.00E+00 7.04E+03 ' 4.21 E+03 1.55E+03 9.35E+03 1.77E+06 MN 54 - 0.00E+00 9.18E+06 1.75E+06 - 0.00E+00 2.73E+06 0.00E+00 2.81E+07 FE 2.93E+08 2.03E+08 - 4.73E+07 0.00E+00 0.00E+00 1.13E+08 1.16E+08 FE-59 2.66E+08 6.25E+08 2.39E+08 0.00E+00 0.00E+00 1.75E+08 2.08E+09 CO-58 0.00E+00 1.82E+07 4.09E+07 0.00E+00 0.00E+00 0.00E+00 3.70E+08 CO-60 0.00E+00 7.52E+07 1.66E+08 0.00E+00 0.00E+00 0.00E+00 1.41E+09 Ni63 ' 1.89E+10 1.31E+09 6.33E+08 0.00E+00 0.00E+00 0.00E+00 - 2.73E+08 ZN-65 ~- 3.56E+08 1.13E+09 5.12E+08 0.00E+00 7.57E+08 0.00E+00 7.13E+08

~ RS-86 ' 0.00E+00 4.87E+08 2.27E+08 0.00E+00 0.00E+00 0.00E+00 9.59E+07 SR-89 3.02E+08 0.00E+00 8.66E+06 0.00E+00 0.00E+00 0.00E+00 4.84E+07 SR-90 1.24E+10 0.00E+00 3.05E+09 0.00E+00 0.00E+00 0.00E+00 3.60E+08

.Y-91 1.13E+06 0.00E+00 3.03E+04 0.00E+00 0.00E+00 0.00E+00 6.24E+08 ZR 95 1.87E+06 6.01E+05

• 4.07E+05 0.00E+00 9.43E+05 0.00E+00 1.90E+09 NS-95 2.30E+06 1.28E+06 6.87E+05 0.00E+00 1.26E+06 ~ 0.00E+00 7.76E+09 RU-103 1.05E+08 0.00E+00 4.53E+07 0.00E+00 4.02E+08 0.00E+00 1.23E+10 RU-106 - 2.80E+09 0.00E+00 3.54E+08 - 0.00E+00 5.41E+09 0.00E+00 1.81E+11 AG-110M 6.68E+06 6.18E+06 - 3.67E+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09 TE-125M 3.59E+08 1.30E+08 4.81 E+07 1.08E+08 1.46E+09 0.00E+00 1.43E+09 -

TE 127M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 0.00E+00 3.74E+09 TE-129M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 0.00E+00 5.71E+09 l-131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 0.00E+00 4.06E+06 l133 3.68E-01 S.41E-01 1.95E-01 9.42E+01 1.12E+00 0.00E+00 5.76E-01 CS-134 - 6.58E+08 1.57E+09 1.28E+09 0.00E+00 5.07E+08 1.68E+08 2.74E+07 CS-136 1.21E+07 4.78E+07 3.44E+07 0.00E+00 2.66E+07 3.65E+06 5.43E+06 CS-137 8.72E+08 1.19E+09 7.82E+08 0.00E+00 4.05E+08 1.35E+08 2.31E+07 BA 140 2.90E+07 ' 3.64E+04 1.90E+06 0.00E+00 1.24E+04 2.08E+04 5.96E+07 CE-141 1.41 E+04 9.51E+03 1.08E+03 0.00E+00 4.42E+03 0.00E+00 3.64E+07

' CE-144 1.46E+06 6.10E+05 7.83E+04 0.00E+00 3.62E+05 0.00E+00 4.93E+08 PR 143 - 2.09E+04 8.40E+03 1.04E+03 0.00E+00 4.85E+03 0.00E+00 9.17E+07 ND-147 ~ 7.08E+03 8.18E+03 4.90E+02 0.00E+00 4.78E+03 0.00E+00 3.93E+07 1

73 3918D. Doc l I

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Saxton Nuclear Experimental Corporation l SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 l Title Rowston No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.7.1 Page 1 of 1 Pathway Dose Factors, R1 AGE GROUP: INFANT PATHWAY: VEGETATION ORGAN DOSE FACTORS; m' -mrem / year pt,r Ci/sec NUCLlDE BONE LIVER T. BODY THYRolD KIDNEY LUNG GI-LLI H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CR 51 : 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MN-54 . 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 - 0.00E+00 FE-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE 59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

. CO-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

- ZR-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00 NS-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU 103 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i RU-106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 -

AG 110M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-125M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00  ;

1 TE-127M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-129M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-133. - 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-134 - 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS 137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PR-143 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

' ND-147 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 74 3918D DOC

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l SNEC Facility ONsite Dose Calculation Manual 0 TABLE 5.7.2 Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: VEGETATION l l-ORGAN DOSE FACTORS; m' -mrem / year per Ci/sec NUCLIDE BONE LIVER T. BODY THYRolO KIDNEY LUNG GI-LLI '

H3 0.00E+00 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 C 8.119E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 CR-51 0.00E+00 - 0.00E+00 - 1.17E+05 6.49E+04 ' 1.77E+04 1.18E+05 6.20E+06 MN 54 0.00E+00 6.65E+08 1.77E+08 0.00E+00 1.86E+08 0.00E+00 5.58E+08 FE 55 8.01E+08 4.25E+08 1.32E+08 0.00E+00 0.00E+00 2.40E+08 7.87E+07 FE 59 . 3.98E+08 6.44E+08 3.21E+08 0.00E+00 0.00E+00 1.87E+08 6.71E+08 CO 58 0.00E+00 6.44E+07 1.97E+08 - 0.00E+00 0.00E+00 0.00E+00 3.76E+08 Co-60 0.00E+00 3.78E+08 - 1.12E+09 0.00E+00 0.00E+00 0.00E+00 2.10E+09 NI-63 3.95E+10 2.11E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+08 ZN-65 8.12E+08 2.16E+09 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08

' RB-86 0.00E+00 4.51E+08 - 2.77E+08 0.00E+00 0.00E+00 0.00E+00 2.90E+07 SR-89 3.60E+10 0.00E+00 ' 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1.39E+09 SR-90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 i Y-91 1.87E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.49E+09 ZR-95 3.86E+06 8.48E+05 -

7.55E+05 0.00E+00 1.21E+06 0.00E+00 8.85E+08 NS 4.11E+05 1.60E+05 1.14E+05 ' O.00E+00 1.50E+05 0.00E+00 2.96E+08 RU 103 1.53E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 RU-106 7.45E+08 0.00E+00 9.30E+07 0.00E+00 1.01E+09 - 0.00E+00 1.16E+10 AG-110M

• 3.21 E+07 2.17E+07 1.73E+07 0.00E+00 4.04E+07 0.00E+00 2.58E+09 TE-125M 3.51E+08 9.50E+07 4.67E+07 9 84E+07 0.00E+00 0.00E+00 3.38E+08 TE-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00E+00 1.07E+09 TE 129M 8.40E+08 2.35E+08 1.30E+08 2.71 E+08 2.47E+09 0.00E+00 1.02E+09 l-131- 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2.36E+08 0.00E+00 1.28E+07 l-133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 0.00E+00 1.76E+06 CS-134 1.60E+10 2.63E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 CS-136 ' 8.28E+07 2.28E+08 1.47E+08 0.00E+00 1.21E+08 1.81E+07 8.00E+06 CS-137 2.39E+10 - 2.29E+10 3.38E+09 0.00E+00 7.46E+09 2.68E+09 1.43E+08 BA-140 2.79E+08 2.44E+05 1.63E+07 0.00E+00 7.96E+04 1.46E+05 1.41E+08

' CE-141 6.57E+05 - 3.28E+05 4.86E+04 0.00E+00 1.44E+05 0.00E+00 4.09E+08 CE-144 1.27E+08 3.99E+07 6.79E+06 0.00E+00 2.21E+07 0.00E+00 1.04E+10 PR-143 1.45E+05 4.36E+04 7.21E+03 0.00E+00 2.36E+04 0.00E+00 1.57E+08 ND 147 7.15E+04 5.79E+04 4.49E+03 0.00E+00 3.18E+04 0.00E+00 9.18E+07 L

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TABLE 8.7.3 Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: VEGETATION l-ORGAN DOSE FACTORS; m'- mrem / year per Ci/sec NUCLIDE BONE LIVER T. BODY THYROlD. KIDNEY LUNG GI-LLI H-3 0.00E+00 ' 2.59E+03 . 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 C-14 3.69E+08 7.38E+07 7.38E+07 ' 7.38E+07 7.38E+07 7.38E+07 7.38E+07 CR 51 0.00E+00 0.0CE+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 MN-54 0.00E+00 4.54E+08 9.01 E+07 0.00E+00 - 1.36E+08 0.00E+00 9.32E+08 -

FE-55 3.26E+08 ' 2.31E+08 5.39E+07 0.00E+00 0.00E+00 1.47E+08 1.00E+08 FE-59 ' 1.80E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.91E+08 CO-58 0.00E+00 4.36E+07 1.01E+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08

. CO-60 ' O.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 Ni-63 1.61E+10 - 1.13E+09 5.45E+08 0.00E+00 0.00E+00 0.00E+00 - 1.81 E+08

- ZN-65 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9.42E+08 0.00E+00 6.23E+08 RB-86 0.00E+00 - 2.73E+08 1.28E+08 0.00E+00 0.00E+00 0.00E+00 4.04E+07 i- SR 89 1.52E+10 0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09 SR-90 7.51E+11 - 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 Y 91 - 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.22E+09 ZR-95 ' 1.72E+06. 5.43E+05 3.73E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 NS-95 1.92E+05 1.07E+05 5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 '

RU 103 ' 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 5.70E+08 RU 106 3.09E+08 0.00E+00 3.90E+07 0.00E+00 5.97E+08 0.00E+00 1.48E+10 AG-110M 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 TE-125M 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 4.37E+08 TE-127M 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.00E+00 1.37E+09 TE 129M 3.61 E+08 1.34E+08 5.72E+07 1.17E+08 1.51 E+09 0.00E+00 1.36E+09 2.13E+07 <

l-131 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00E+00 l133 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.77E+06 0.00E+00 2.49E+06 CS-134 7.10E+09 1.67E+10 7.75E+09 0.00E+00 5.31E+09 2.03E+09 2.08E+08 CS-136 4.39E+07 1.73E+08 1.16E+08 0.00E+00 9.41E+07 1.48E+07 1.39E+07

, - CS-137 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 BA-140 1.39E+08 1.71E+05 8.97E+07 0.00E+00 5.78E+04 1.15E+05 2.15E+08 CE-141 2.83E+07 1.89E+05 2.17E+04 0.00E+00 8.90E+04 0.00E+00 5.41 E+08 CE 144 5.28E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.00E+00 1.33E+10 PR 143 ; 6.99E+04 2.79E+04 3.48E+03 0.00E+00 1.62E+04 0.00E+00 2.30E+08 ND-147 ~ 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 1.42E+08 1

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Number SaMon Nuclear Egerimental Corporadon SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Rowsion No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.7.4 Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: VEGETATION ORGAN DOSE FACTORS; m2 -mrem / year per Ci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 C-14 2.28E+08 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 CR-51 0.00E+00 0.00E+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 MN 54 0.00E+00 3.13E+08 5.97E+07 0.00E+00 9.31E+07 0.00E+00 9.58E+08 FE-55 2.10E+08 1.45E+08 - 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 FE 59 1.26E+08 2.97E+08 1.14E+08 0.00E+00 0.00E+00 8.29E+07 9.89E+08 CO-58 0.00E+00 3.07E+07 - 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+08 CO-60 0.00E+00 1.67E+08 3.69E+08 0.00E+00 0.00E+00 0.00E+00 3.14E+09 NI-63 1.04E+10 7.21E+08 3.49E+08 0.00E+00 0.00E+00 0.00E+00 1.50E+08 ZN-65 3.17E+08 1.01E+09 4.56E+08 0.00E+00 6.75E+08 0.00E+00 6.36E+08 RB-86 0.00E+00 2.19E+08 1.02E+08 0.00E+00 0.00E+00 0.00E+00 4.32E+07 SR-89 9.98E+09 0.00E+00 2.86E+08 0.00E+00 0.00E+00 0.00E+00 1.60E+09 SR-90 6.05E+11 0.00E+00 1.48E+11 0.00E+00 0.00E+00 0.00E+00 1.75E+10 Y-91 5.12E+06 0.00E+00 1.37E+05 0.00E+00 0.00E+00 0.00E+00 2.82E+09 ZR 95 1.17E+06 3.77E+05 2.55E+05 0.00E+00 5.91E+05 0.00E+00 1.19E+09 .

NS-95 1.42E+05 7.92E+04 4.26E+04 0.00E+00 7.83E+04 0.00E+00 4.81 E+08 RU 103 4.77E+06 0.00E+00 2.06E+06 0.00E+00 1.82E+07 0.00E+00 5.57E+08 RU-106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+08 0.00E+00 1.25E+10 AG 110M 1.05E+07 9.75E+06 5.79E+06 0.00E+00 1.92E+07 0.00E+00 3.98E+09 TE-125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 0.00E+00 3.86E+08 TE 127M 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 0.00E+00 1.17E+09 TE-129M 2.51E+08 9.37E+07 3.97E+0'7 8.63E+07 1.05E+09 0.00E+00 1.26E+09 l-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 0.00E+00 3.05E+07 l133 2.09E+06 3.63E+06 1.11E+06 5.34E+08 6.33E+06 0.00E+00 3.26E+06 CS-134 4.67E+09 1.11E+10 9.08E+09 0.00E+00 3.59E+09 1.19E+09 1.94E+08 CS-136 4.28E+07 1.69E+08 1.22E+08 0.00E+00 9.41 E+07 1.29E+07 1.92E+07 i CS-137 6.36E+09 8.70E+09 5.70E+09 0.00E+00 2.95E+09 9.81E+08 1.68E+08 BA 140 1.29E+08 1.62E+05 8.74E+06 0.00E+00 5.52E+04 9 29E+04 2.66E+08 CE-141 1.97E+05 1.33E+05 1.51E+04 0.00E+00 6.20E+04 0.00E+00 5.10E+08 CE-144 3.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0.00E+00 1.11 E+10 PR-143 6.25E+04 2.51 E+04 3.10E+03 0.00E+00 1.45E+04 0.00E+00 2.74E+08  ;

ND-147 3.'34E+04 3.85E+04 2.51 E+03 - 0.00E+00 2.25E+04 0.00E+00 1.85E+08 l l

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' 6.01 SFFLUENT TOTAL DO8E ASSESSMENT 6.1 Total Dose Calculation -

, The annual (calendar year) dose or dose commitment to any member of the public, due to releases l of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. This control is provided in order to meet the dose limitations of 40 CFR 190.

The total dose from SNEC Facility (uranium fuel cycle facilities within 8 kilometers) is calculated by summing the calculated annual doses to critical organs of a real individual for liquid effluent using Section 2.1 methodology, for gaseous effluent using Section 5.2.1 methodology, and the direct

. radiation from the site from the environmental monitoring program's direct radiation (TLD) monitors.

7.0 : PART 11 REFERENCES

1. EPRI NP-3840, RP 1560-3 Final Report, " Environmental Radiation Doses From Difficult To-j' Measure Nuclides," January 1985

. 2. SNEC Facility Final Safety Analysis Report (FSAR)

.3. NUREG-0017," Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWR," Revision 1,1985

4. NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978 5, NUREG-0172. " Age-Specific Radiation Dose Commitment Factors For A One-Year Chronic Intake,"

November 1977

6. Reg 0latory 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

7. Regulatory Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix 1," Revision 1, October 1977

8. Simplified Environmental Effluent Dosimetry System (SEEDS)

9. Title 10,' Code of Federal Regulations, " Energy" l

10. SNEC Facility Technical Specifications, attached to Facility Operating License No. DPR 4

11. 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

- 12. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 13; Title 40, Code of Federal Regulations, " Protection of Environment" 78 39180. DOC l

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14. Regulatory Guide 4.13, " Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications," Revision 1, July 1977

15. RAF 6612-95-019," Calculation of Maximum Annual Average X/Q's for SNEC Facility" l

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Number j Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575 PLN-4542.08 Tftle Revie4cn No.

1 SNEC Facility Offsite Dose Calculation Manual 0 1 1.0 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted to the Commission prior to May 1 of each year.

1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring activities for the report period, including a comparison with pre-decommisioning studies, with decommissioning controls as appropriate, and with previous environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census if required by the Action statement of Control 2.3.2.

1.3 The Annual Radiological Environmental Operating Reports shall include the summarized tabulated results of analysis of all radiological environmental samples and environmental radiation measurements required by Part I Table 2.31 taken during the period pursuent to the locations specified in the tables and figures in this ODCM, as well as summarized and tabulated results of these analyses and measurements in a format similar to the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report the report shall be submitted explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

1.4 The reports shall also incluile the following: a summary description of the radiological environments monitoring program; a map (s) of all sampling locations keyed to a table giving distances and directions from the SNEC Facility Containment Building; the results of licensee participation in the Interlaboratory Comparison Program, required by Part I, Control 2.3.3; discussion of all deviations from the sampling schedule of Part I, Table 2.3-1; discussion of all the i required analyses in which the LLD required by Part 1. Table 2.3-2 was not achievable.

2.0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2.1 Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous calendar year of operation shall be submitted prior to May 1.

2.2 The following information shall be included in both Radioactive Effluent Release Reports to be submitted each year; The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev.1, with data summarized on a quarterly basis following the format of Appendix B thereof.

2.3 The Radioactive Effluent Release Reports shall include the following information for each type of solid waste shipped offsite during the report period:

a. container volume,

b. total curie quantity (specify whether determined by measurement or estimate),

c. principal radionuclides (specify whether determined by measurement or estimate),

d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

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e. type of shipment (e.g., LSA, Type A, Type B) and  ;

f. solidification agent (e.g., cernent).

2.4 The Radioactive Effluent Release Reports shall include a summary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.

2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of aew locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part I Control 2.3.2.

2.6 The Radioactive Effluent Release Reports shall include the instrumentation not retumed to 1 OPERABLE status within 30 days per ODCM Part I Control 2.1.2.b.

2.7 The Radioactive Effluent Release Report shallinclude an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. All assun;ptions used in making these assessments shall be included in these reports. The assessment of cliation doses shall be performed in accordance with this ODCM. )

2.8 The Radioactive Effluent Release Repcrt shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period to verify compliance with the requirements of 10CFR20.1301 and 10CFR20.1302.

2.9 The Radioactive Effluent Release Report shall also include an assessment of rMiation doses to the likely most exposed real individual from reactor releases and other nearby uranium fuel cycle j sources including doses from primary effluent pathways and direct radiation for the previous 12 consecutive months to show conformance with 40 CFR 190 " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1.

. 3.0 PART 111 REFERENCES 3.1 Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 3.2 Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974 3.3 SNEC Facility Technical Specifications, attached to Facility Operating License No. DPR-4 3.4 Title 40, Code of Federal Regulations, " Protection of Environment" 3.5 Regulatory Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 3.6 Title 10, Code of Federal Rogulations.

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SNEC Facility Offsite Dose Calculation Manual 0 3.7 Regulatory Guide 1.111," Methods of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977 3.8 Regulatory Guide 1.112, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors," Revision 0-R, May 1997 3.9 Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine . '

Reactor Releases for the Purpose of implementing Appendix 1," Revision 1, April 1977 3.10 RAF 6612-96-007, " Maximum Offsite Dose from Release of Saxton Pipe Tunnel Water' l

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SNEC Facility Offsite Dose Calculation Manual 0 APPENDIX A Pi - Pathway Dose Rate Parameter Pi (inhalation) = k'(BR)DFAl (Eq A-1)

Where; Pi = the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation -

3 pathway, in mrem /yr per microcurielm The dose factors are based on the critical individual organ for the child age group.

k' = conversion factor,1E6 pCi/ microcurie BR = 3700 m'/yr, breathing rate for child (Reg. Guide 1.109, Rev.1, Table E-5)

DFAi = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide (mrem /pCl). Values are taken from Table E-10, Reg. Guide 1.109 (Rev.1).

3 Resolution of the units yields: (ODCM Part ll Table 4.3)

Pi (inhalation) = 3.7E9 DFAl (mrem / yr per Ci / m3) (EqA-2)

NOTE

'1 The latest NRC Guidance has deleted the requirement to determine Pi (ground plane) and Pi (food). In addition, the critical age group has been changed from infant to child.

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SNEC Facility Offsite Deze Calculation Manual 0 APPENDIX B

. Ri -Inhalation Pathway Dose Factor 3

Ri = k'(BR)(DFA i,,,o)(mrom/ yr permicrocurie / m ) (Eq B-1)

Where:

k' = conversion factor,1E6 pCl/ microcurie BR = breathing rate, 1400,3700,8000,8000 m*/yr for infant, child, teenager, and adult age groups, respectively. (Reg. Guide 1.109. Rev.1 Table E-5)

DFAi,e,.= the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrem /pci. The total body is considered as an organ in the selection of DFA ,a,o.

i Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Rev.1).  ;

Resolutions of the units yields:

R=

i (1.4E9) (DFAi ,a,o) infant (ODCM Part il Table 5.2.1)

Ri= (3.7E9) (DFAi,a,o) child (ODCM Part ll Table 5.2.2)

Rim (8.0E9) (DFAi ,a,o) teen and adult (ODCM Part il Tables 5.2.3 and 5.2.4) i 85 3918D. DOC

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SNEC Facility Offsite Dose Calculation Manual 0 l

APPENDIX C i

Ri - Ground Plane Pathway Dose Factor (EqC1) l R i = k 'k"(SF)(DFGl)[(1 - e - Ai t) /1l]

Where:

k' = conversion factor,1E6 pCi/ microcurie I k" = conversion factor,8760 hr/yr

' A. = decay constant for the ith radionuclide, sec -1 t = the exposure time (this calculation assumes that decay is the only operating removal mechanism)

- 4.73 x E8 sec. (15 yrs), Reg. Guide 1.109 (Rev.1), Appendix C l DFGi = the ground plane dose conversion factor for the i* radionuclide (mrem /hr per pCi/m*). Values are taken from Table E-6, Reg. Guide 1.109 (Rev.1). These values apply to all age groups.

l I

SF= 0.7, shielding factor, from Table E-15 Reg. Guide 1.109 (Rev.1)

Reference ODCM Part ll Table 5.3.1 l l

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SNEC Facility Offsite Dose Calculation Manual 0 APPENDIX D Page 1 of 2 Ri- Grass Cow-Milk Pathway Dose Factor R i = k '[(Q, x U,) / (1l + A w )] x (F ) x (r) x (DFL ,,, i o) x (Eq D-1)

[((fpx f ) / Y p) + ((1 - fpx f,) e - Yh) / Y.] e - A lty l

Where:

I k' = conversion factor,1E6 pCi/ microcurie j l

Qp= cow consumption rate, 50 kg/ day, (Reg. Guide 1.109, Rev.1) goat consumption rate,6 kg/ day, (Reg. Guide 1.109, Rev.1, Table E-2)

I Uap = Receptor's milk consumption rate; 330, 330,400, 310 liters /yr for infant, child, teenager, and adult I age groups, respectively (Reg. Guide 1.109. Rev.1) 2  !

Yp = agricultural productivity by unit area of pasture feed grass,0.7 kg% (NUREG-0133)

Ys = agricultural productivity by unit area of stored feed,2.0 kg/m'(NUREG-0133)

Fu= stable element transfer coefficient (Table E-1, Reg. Guide 1.109, Rev.1) r = fraction of deposited activity retained in cow's feed grass,0.2 for particulates,1.0 for radioiodine (Table E-15, Reg. Guide 1.109, Rev.1)

DFL,e,. = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1) {

Ai = decay constant for the ith radionuclide, sec^

1. d Aw = decay constant for weathering, 5.73 x 10 sec (NUREG-0133); based on a 14 day half life 5

t t= 1.73 x 10 sec, the transport time from pasture to cow to milk to receptor (Table E-15, Reg. Guide

.1.109, Rev.1), or 2 days in = 7.78 x 10'sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-15, Reg. Guide 1.109, Rev.1), or 90 days fp= '1.0, the fraction of the year that the cow is on pasture

f. = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture 87 3918D. DOC

Number Saxt n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tale Revtson No.

SNEC Facility Offsite Dose Calculation Manual 0 APPENDIX D Page 2 of 2 The concentration of tritium in milk is based on the airbome concentration rather than the deposition. Therefore, Ri is based on (X/Q):

Rct, a, o = k ' k"' Fm QFUAP DFL t, a, o (.75 [.5 / H]) (EqD-2)

Where; k"' = 1E3 grams /kg l

H = 8 grams /m', absolute humidity of the atmosphere

.75 = fraction of the total feed grass mass that is water

.5= ratio of the specific activity of the feed grass water to the atmospheric water (NUREG-0133)

DFla,e,o = the ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-11 to {

E-14, Reg. Guide 1.109, Rev,1) {

All other parameters and values are as given above. l

• 1 NOTE Goat-milk pathway factor, Ri, will be computed using the cow-milk pathway factor equation. Fm factor for goat-milk will be from Table E-2 Reg. Guide 1.109, Rev.1. ,

Reference:

- ODCM Part 11 Tables 5.4.1 to 5.4.4 l

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Number Saxton Nuclear Experimental Corporation SAXTON NUCLEAR' Facility Policy and Procedure Manual 6575 PLN-4542.08 Tme Revioson No.

SNEC Facility Offsite Dose Calculation Manual 0 I i

APPENDIX E Page 1 of 2 Ri -Cow-Meat Pathway Dose Factor R l = k '[(Q, x U,) / (1, + A w)] x (F,) x (r) x (DFL,,,,,) x (Eq E-1)

[((fp x f,) \ Yp) + ((1 - pf f,) e - Ai b) / Y,) ex - l ty i Where:

k'= conversion factor,1E6 picocurie / microcurie (pci/ ci)

Qp= cow consumption rate,50 kg/ day, (Reg. Guide 1.109, Rev.1)

Up = Receptor's meat consumption rate; 0,41,65,110 kg/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109 Rev.1)

{

1 Fr = the stable element transfer coefficients, days /kg (Table E-1, Reg. Guide 1.109, Rev.1) r = fraction of deposited activity retained in cow's feed grass,0.2 for particulates,1.0 for radiciodine 1 (Table E-11, Reg. Guide 1.109, Rev.1)

I DFl.4,,,. = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E 14, Reg. Guide 1.109, Rev.1) 1 Ai = decay constant for the radionuclide i, sec^

Aw= decay constant for weathering,5.73 x 10'# secd(NUREG-0133), based on a 14 day half life tr = 1.73 x 10'sec, the transport time from pasture to receptor (NUREG-0133) 8 tn = 7.78 x 10 sec, the transport time from crop to receptor (NUREG-0133) i Yp= agricultural productivity by unit area of pasture feed grass,0.7 kg/m* (NUREG-0133)

Y = agricultural productivity by unit area of stored feed,2.0 kg/m* (NUREG-0133) f, = 1.0, the fraction of the year that the cow is on pasture

f. = .1.0, the fraction of the cow feed that is pasture grass while t'ne cow is on pasture 89 39180. doc

Number Saxton Nuclear Experimental Corporation e SAXTON ho. v* LEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tme Revisen No.

_SNEC Facility Offsite Dose Calculation Manual 0 APPENDIX E Page 2 of 2 The concentration of tritium in meat is based on the airbome concentration rather than the deposition. Therefore, Ri is based on (X/Q):

R ,,,, = k'k'" F,Q,Un(DFL,,,,,)x0.75 x(0.5 / HJ) (EqE-2)

Where:

All terms are as defined above and in Appendix D.

R;ference: ODCM Part II, Tables 5.6.1 to 5.6.4 90 3918D. DOC i

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SNEC Facility Offsite Dose Calculation Manual 0 l APPENDIX F RJ -Vegetation Pathway Dose Factor I

Ri = k ' x [r / (Yy / Ag +1,))] x (DFLi ,a, o) x [(U ,)t f e - il tt+US AI 9e -ltih) (Eq F-1)

Where:

k'= 1E6 picocurie / microcurie (pCi/ ci)

U'A = the consumption rate of fresh leafy vegetation,0,26,42,64 kglyr for infant, child, teenager, or adult age groups, respectively (Reg. Guide 1.109, Rev.1)

U*A = the consumption rate of stored vegetation,0,520,630,520 kg/yr for infant, child, teenager, or adult

)

age groups respectively (Reg. Guide 1.109, Rev.1) I l

ft= the fraction of the annualintake of fresh leafy vegetation grown locally, = 1.0 (NUREG-0133) fg = the fraction of the stored vegetation grown locally = 0.76 (NUREG-0133) t t= the average time between harvest of leafy vegetation and its consumption,8.6 x 10' seconds

[ Table E-15, Reg. Guide 1.109, Rev.1 (24 hrs)]

in = the average time between harvest of stored leafy vegetation and its consumption,5.18 x 10' ,

seconds, [ Table E-15, Reg. Guide 1.109, Rev.1 (60 days)) l Y, = the vegetation area density,2.0 kg/m'(Table E-15, Reg. Guide 1.109, Rev.1)

' All other parameters are as previously defined.

The concentration of tritium in vegetation is based on the airbome concentration rather than the deposition.

Therefore, R4 is based on (X/Q)

R t, a, o = k ' k" '[U'A Lf + U S A Ig](DFL ,t a, o)(.75 [.5 / H]) (EqF2)

Where:

s All terms are as defined above and in Appendix D.

Refe.rence: ODCM Part II, Tables 5.7.1 to 5.7.4 91 3918D. DOC

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Number Sad n Nudear Egerimental Corporation j L SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revisson No.

SNEC Facility ONsite Dose Calculation Manual 0 APPENDlX A-F REFERENCES Page 1 of 4 Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G.1.109 NUREG-0133 Specific

" For Pi * ,

Each radionuclide E-9 Note 1

)

DFAi BR 3700 m'/yr (child) E-5 l

"For R4 (Vegetation)" '

r Each element type E-1 3

Yv 2.0 kg/m E-15 Aw 5.73E 7 sec" 5.3.1.3 Each age group and radionuclide E-11 thru E-14 Note 1 DFLi U' Each age group E-5

, ft 1.0 5.3.1.5 t.

t 8.6E+4 seconds E 15 U.8 Each age group E5 y, 0.76 5.3.1.5 5.18E+6 seconds E-15 th H- 8.0 grams /kg 5.2.1.3 "For Ri (Inhalation)*

BR Each age group E5 Each age group and nuclide E 7 thru E-10 Note 1 DFAi-l 92 39180. DOC

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SNEC Facliity Offsite Dose Calculation Manual 0 APPENDIX A-F REFERENCES Page 2 of 4 Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G.1.109 NUREG-0133 Specific

• " For R4 (Ground Plane) ***

SF 0.7 E 15 Each radionuclide E-6 DFG6 l t 4.73E+8 sec 5.3.1.2 -

• " For R4 (Grass / Animal / Meat) *"

Op(Cow) 50 kO/ day E-3 Or(Goat) 6 kg/ day E3 Ref. Only Each a0e group E5 Uso Aw S.73E 7 sec' 5.3.1.3 Fe(Both) Each element E1 r Each element type E-15 DFLi Each age group and nuclide E 11 thru E-14 Note 1 g, 1.0 5.3.1.3 Note 2 y, 1.0 5.3.1.3 Note 2 3

y, 0.7 kg/m E-15 th 7.78M m E-n 3

Ys 2.0 kg/m E-15 1.73E+6 see E-15 tt H 8.0 grams /kg 5.2.1.3 I

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SNEC Facility Offsite Dose Calculation Manual 0 APPENDIX A-F REFERENCES Page 3 of 4 Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site- ,

Parameter Value - R.G.1.109 NUREG-0133 Specific  !

"* For R4(Grass / Cow / Milk)"*

og 50 kg/ day E-3 Each age group E-5 j Uno Aw 5.73E-7 sec' 5.3.1.3 Fm Each element E-1 i r Each element type E-15 DFL, Each age group and nuclide E-11 thru E-14 Note 1 Yo 0.7 kg/m' E 15 th 7.78E+6 sec E-15 3

Y, 2.0 kg/m E-15 t, 1.73E+5 sec E-15 )

fp 1.0 5.3.1.3 1.0 5.3.1.3 f.

H 8.0 grams /kg 5.2.1.3 l

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1 SNEC Facility Offsite Dose Calculation Manual 0 l APPENDlX A-F REFERENCES Page 4 of 4 l NOTES l

1. Inhalation and ingestion dose factors were taken from the indicated source. For each age group, for each nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the

referenced table.

I 2. Typically beef cattle are raised all year on pasture REFERENCES

1. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1. October 1977.

2. SNEC Facility Technical Specifications, attached to Facility Operating License No. DPR-4.

3. NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978.

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