ML20140D261

to SNEC Facility Offsite Dose Calculation Manual

ML20140D261
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	06/03/1997
From:	Kuehn G GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6575-PLN-4542.0, C301-97-2018, NUDOCS 9706100310
Download: ML20140D261 (94)

Text

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l l GPU Nuclear, Inc.

( Route 441. South NUCLEAR Post 0'hcc Bo' 480 Middletown. PA 17057 0480 Tel717 944-7621 C301-97-2018 June 04, 1997 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

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Subject:

Saxton Nuclear Experimental Corporation Facility i Operating License No. DPR-4  !

Docket No. 50-146  :

SNEC Facility Offsite Dose Calculation Manual l

Enclosed is the SNEC Facility Offsite Dose Calculation Manual (ODCM). Submittal of the ODCM satisfies a GPU Nuclear commitment, to provide the document when issued, made in its {

July 18,1996 response to Question 37 of the NRC Request for Additional Information Regarding i the SNEC facility Decommissioning Plan and Environmental Report dated June 6,1996. l Questions regarding this document should be directed to W. Heysek of the Licensing and Regulatory Affairs Depanment at (717) 948-8191.

Sincerely, 9706100310 970603 G. A. Kuehn

{b I PDR P

ADOCK 05000146 pga Vice President SNEC h.I j j

WGH Attachment l

cc: Administrator, NRC Region I- Huben Miller l NRC Project Manager, NRR- Alexander Adams I

[

NRC Project Scientist, Region I- Thomas Dragoun 1

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Number SaMon Nuclear Experimental Corporation i

' SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 TCle Revisen No.

SNEC Facility Offsite Dose Calculation Manual 0 Apphcability/ scope Calculate offsite doses due to radioactwo effluents for Responsible Office Effectue Date demonstrating comphance with Site Technmal Specircations 10 CFR 20 &

10 CFR 50 - Appendir 1 6575 l

This document is within QA plan scope X Yes No Safety Reviews Required X Yes No List of Effective Pages Pace Revision Pace Revision Pace Revision Pace Revision l 1 0 17 0 33 0 49 0 2 0 18 0 34 0 50 0 3 0 19 0 35 0 51 0 4 0 20 0 36 0 52 0 5 0 21 0 37 0 53 0 6 0 22 0 38 0 54 0 7 0 23 0 39 0 55 0 8 0 24 0 40 0 56 0 9 0 25 0 41 0 57 0 10 0 26 0 42 0 58 0 11 0 27 0 43 0 59 0 12 0 28 0 44 0 60 0 13 0 29 0 45 0 61 0 14 0 30 0 46 0 62 0 15 0 31 0 47 0 63 0 16 0 32 0 48 0 64 0

- Signature c Date .:

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1 Number Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual a

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

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69 0 70 0 71 0 72 0 73 0 74 0 75 0 76 0 77 0 l 78 0 79 0 80 0 i

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Number Sad n Nu&ar Ege$nental Corporadon SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN4542.08 Title Rewson No.

SNEC Facility Offsite Dose Calculation Manual 0 l

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SAXTON NUCLEAR EXPERIMENTAL CORPORATION FACILITY OFFSITE DOSE CALCULATION MANUAL 1

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Saxton Nuclear Experimental Corporation l

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6575-PLN-4542.08 Title Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM)is a supporting document of the Saxton Nuclear 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 describes the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents. This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm / trip set points.

Ventilation Exhaust Treatment System configurations are also included.

The ODCM also is used to define the requirements for the SNEC Facility Radiological Environmental Monitoring l 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 and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM to ensure the ODCM represents the present methodology in all applicable areas. 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 1 for calculation of off-site doses due to plant effluent releases. Simplifying assumptions have been applied in this manual where applicable to provide a more workable document for implementation of the Radiological Effluent Controls requirements. l 1

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Humter Saxt n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revision No. j SNEC Facility Offsite Dose Calculation Manual 0 Table of Contents PARTI RADIOLOGICAL EFFLUENT CONTROLS S*ction Pace 1.0 DEFINITIONS 12 l

Table 1.1, Frequency Notations 14 1 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 Monitoririg Instrumentation 15 Table 2.1-2, Radioactive Gaseous Effluent Monitoring Instrumentation 17 2.2 Radiological Effluent Controls 18 2.2.1 Liquid Effluent Cont.ols 18 l 2.2.2 Gaseous Effluent Controls 20 2.2.3 Total Radioactive Effluent Controls 23 2.3 SNEC Facility Radiological Environmental Monitoring Program (REMP) 24 2.3.1 Monitoring Program Requirements 24 2.3.2 Land Use Census 25 2.3.3 Interlaboratory Comparison Program 26 Table 2.31, REMP Sample Analysis, Collection, and Analysis 28 Frequency by Sample Medium Table 2.3-2, REMP Analytical Required Sensitivities (LLD) and Reporting 30 Levels for Radioactivity Concentrations in Environmental Samples 3.0 SURVEILLANCES 3.1 Radioactive Effluent instrumentation 32 3.1.1 Radioactive Liquid Effluent Instrumentation 32 i

3.1.2 Radioactive Gaseous Effluent Monitoring Instrumen'ation 32 l Table 3.12, Radioactive Gaseous Effluent Monitoring instrumentation 33 Surveillance Requirements s 3918D_ DOC

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1 Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual

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l 6575 PLN-4542.08 TO Revision No.

l SNEC Facility Offsite Dose Calculation Manual 0 l

Table of Contents (Cont'd)

PART I RADIOLOGICAL EFFLUENT CONTROLS (Cont'd) l Section E!!ge 3.2 Radioactive Effluents 34 l 3.2.1 Liquid Effluents 34 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 35 3.2.2 Gaseous Effluents 36 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 37 '

3.2.3 Total Radioactive Effluents 39 3.3 SNEC Facility Radiological Environmental Monitoring Program 39 3.3.1 Monitoring Program Surveillance Requirements 39 Table 3.3-1, Saxton Nuclear Experimental Corporation Facility Radiological 40 Environmental Monitoring Program Description l

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Table of Contents (Cont'd)

PARTll EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES l

, Section Eag 1.0 LIQUID EFFLUENT MONITORS 44 i 1.1 Liquid Radiation Monitor Set Points 44 1.2 Liquid Effluent Release Points 44 l 1.3 Control of Liquid Releases 44 l

2.0 LIQUID EFFLUENT DOSE ASSESSMENT 45 1 1

2.1 Liquid Effluents - 10 CFR 50 Appendix I 45 2.2 Liquid Radwaste System Dose Calcs Once per Month 46 2.3 Attemative Liquid Dose Calculational Methodology 46 3.0 LIQUID EFFLUENT WASTE TREATMENT SYSTEM 51 3.1 Liquid Effluent Waste Treatment System 51 4.0 GASEOUS EFFLUENT MONITORS 51 4.1 Particulate Monitor Set Points 51 4.2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 52 4.3 Control of Gaseous Effluent Releases 53 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 56 5.1 Gaseous Effluents - Dose Rate Limits 56 5.1.1 Tritium and Particulates 56 5.2 Gaseous Effluents - 10 CFR 50 Appendix I 56 5.2.1 Tritium and Particulates 56 l I

5.3 Ventilation Exhaust Treatment System Dose Calculations Once per Month 57 5.4 Altemative Dose Calculational Methodologies 57 6.0 EFFLUENT TOTAL DOSE ASSESSMENT 79 7.0 PART il REFERENCES 79 7 3918D. DOC

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

PART11 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Pace TABLES Table 2.1 Liquid Dose Conversion Factors (DCF): Dfij 47 l

Table 2.2 Bioaccumulation Factors, BF; 50 Table 4.1 Atmospheric Dispersion Factors for SNEC Facility 54 )

l Table 4.2 Dose Parameters for Radiciodines and Radioactive Particulate, 55 Gaseous, Effluents Table 5.2.1 Pathway Dose Factors, Ri- Infant, Inhalation 58 Table 5.2.2 Pathway Dose Factors, R,- Child, Inhalation 59 Table 5.2.3 Pathway Dose Factors, Ri- Teen, Inhalation 60 Table 5.2.4 Pathway Dose Factors, Ri- Adult, Inhalation 61 Table 5.3.1 Pathway Dose Factors, Ri- All Age Groups, Ground Plane 62 Table 5.4.1 Pathway Dose Factors, R4 - Infant, Grass-Cow-Milk 63 Table 5.4.2 Pathway Dose Factors, Ri- Child, Grass-Cow-Milk 64 Table 5.4.3 Pathway Dose Factors, Re - Teen, Grass-Cow-Milk 65 Table 5.4.4 Pathway Dose Factors, R,- Adult, Grass-Cow-Milk 66 Table 5.5.1 Pathway Dose Factors, R6 - Infant, Grass-Goat-Milk 67 Table 5.5.2 Pathway Dose Factors, R;- Child, Grass-Goat-Milk 68 Table 5.5.3 Pathway Dose Factors, F - ten, Grass-Goat-Milk 69 Table 5.5.4 Pathway Dose Factors, Ri- Adult, Grass-Goat-Milk 70 Table 5.6.1 Pathway Dose Factors, R,- Infant, Grass-Cow-Meat 71 Table 5.6.2 Pathway Dose Factors, R;- Child, Grass-Cow-Meat 72 Table 5.6.3 Pathway Dose Factors, R4 - Teen, Grass-Cow-Meat 73 8 39180 DOC

l Number S xt n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revision No.

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PART11 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES (Cont'd)

Section Paae i l

TABLES (Cont'd)

Table 5.6.4 Pathway Dose Factors, R,- Adult, Grass-Cow-Meat 74 Table 5.7.1 Pathway Dose Factors, Ri - Infant, Vegetation 75 Table 5.7.2 Pathway Dose Factors, Ri - Child, Vegetation 76 l Table 5.7.3 Pathway Dose Factors, Ri - Teen VeDetation 77 Table 5.7.4 Pathway Dose Factors, Ri- Adult, Vegetation 78 FIGURES None 9 3918D. DOC

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

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

PART ll1 REPORTING REQUIREMENTS Section Pace 1.0 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 82 2.0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 82 3.0 PART 111 REFERENCES 83 APPENDICES A. Pathway Dose Rate Parameter (P)i 85 B. Inhalation Pathway Dose Factor (R)i 86 C. Ground Plane Pathway Dose Factor (Ri) 87  ;

D. Grass-Cow-Milk Pathway Dose Factor (R,) 88 l

I E. Cow-Meat Pathway Dose Factor (R)i 90 F. Vegetation Pathway Dose Factor (R)i 92 ,

1 APPENDIX A - F REFERENCES 93 I

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Number S xt n Nuclear Experimental Corporation SAXTON NUCLEAR Faci!!ty Policy and Procedure Manual 6575-PLN-4542.08 Title Rensson No.

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1.0 DEFINITIONS l

1.1 Defined Terms The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part I of the ODCM.

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 termination 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 OPERABILITY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, 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).

1.5 Channel Calibration ,

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRATION shall encompass the entire channelincluding the sensor and alarm and/or trip functions, and shallinclude the CHANNEL FUNCTIONAL TEST. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps I 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 shall include, where possible, comparison of the channelindication and/or status with other indications and/or status derived from independent instrument channels I measuring the same parameter.

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

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i SNEC Facility Offsite Dose Calculation Manual 0 3 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. 1 i b. Bistable channels - the injection of a simulated signal into the channel sensor to verify I OPERABILITY including alarm and/orinp functions.

1.9 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 1

at the time of sampling or the number of equal volume samples is proportional to the time period I 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 i

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 f!ow during the CONTINUOUS RELEASE.

i 1.13 SNEC Facility Offsite Dose Calculation Manual (ODCM)

The SNEC Facility OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodology )

and parameters used in the calculation of offsite doses resulting from radioactive gaseous and  ;

liquid effluent, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) j the Radiological Effluent Controls, (2) the Radiological Environrr. ental Monitoring Program and (3) descaptions of the information that should be included in the Annual Radiological Environmental

Operating and Annual Radioactive Effluent Release Reports.

j 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 building.

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l SNEC Facility Offsite Dose Calculation Manual 0 l 1.16 Ventilation Exhaust Treatment System 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 pnor 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 interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

TABLE 1.1 Frequency Notation NOTATION FREQUENCY S (Shiftly) At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

W (Weekly) At least once per 7 days.

M (Monthly) At least once per 31 days.

Q (Quarterly) At least once per 92 days. I l

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

A (Annually) At least once per 12 months.

E At least once per 18 months.

N. A. Not applicable.

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2.0 CONTROLS AND BASES l

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

2. Adherence to the requirements of the Control and/or associated ACTION within the specified time interval shall constitute compliance with the control. In the event the Control is restored prior to expiration to the specified time interval, completion of the ACTION statement is not required.

3. In the r /ent the Control and associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the Control, initiate appropriate actions to rectify the problem to the extent possible under the circumstances, and submit a special report to the Commission pursuant to Technical Specification (Tech. Spec.) Section 3.8.1 within 30 days unless otherwise specified.

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 an&lyzed prior to release.

2.1.2 Radioactive Gaseous Process an 1 Effluent Monitoring Instrumentation CONTROL:

The radioactive gaseous process and effluent monitonng instrumentation channels shown in Table 2.12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alaim/ trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 2.1-2.

ACTION:

a. With a radioactive gaseous process or effluent monitoring instrumentation < hannel alarm / trip setpoint less conservative than required by the aboi control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable,

b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to retum the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

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BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive matenals 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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Table 2.1-2 6575-PLN-4542.08  !

Revision 0 i Page 1 of 1 l Radioactive Gaseous Process and Effluent Monitoring instrumentation i

MINIMUM L CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Station Ventilation System 1 NOTE 1 NOTE 2  ;

a. Particulate Monitor (RMA 1) ,

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i NOTES:

1. Dt. ring operation of the monitored system. l

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2. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within four hours after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment.

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

l l SNEC Facility Offsite Dose Calculation Manual 0 2.2 Radioactive Effluent Controls l 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 20.1001-20.2401, Appendix B. Table 2, Column 2.

APPLICABILITY: At all times ACTION:

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

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

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

l APPLICABILITY: At all times l

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Mumber S xt n Nuclear ExperimentalCorporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tiit] Revision No.

l SNEC Facility Offsite Dose Calculation Manual 0 ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region 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 This Control requires that the dose to offsite personnel be limited to the design objectives of Appendix I of 10 CFR Part 50. This will assure the dose received by the public dunng 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 I

same time implement the guides set forth in Section IV.A of Appendix i to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably )

achievable". The dose calculations in the ODCM implement the requirements in Section Ill.A. of Appendix I that conformance with the guides of Appendix ! is to be shown 1 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  !

underestimated. The equations specified in the ODCM for calculating the doses due to the l actual release rates of radioactive materials in liquid effluents are consistent with the i methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man l from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with l 10 CFR Part 50, Appendix 1," Revision 1, October,1977, and Regulatory Guide 1.113,

" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April,1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

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2.2.1.3 Liquid Radwaste Treatment System CONTROL:

The 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 projected doses due I to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month.

APPLICABILITY: At alltimes l

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S xt n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 TRie Revision No.

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ACTION:

I a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region i Administratorwithin 30 days, a Special Report which includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for 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 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 of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix I 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 li.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 l 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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S xt n Nuclear Egenmental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575 PLN-4542.08 Title Revisson No.

SNEC Facility Offsite Dose Calculation Manual 0 BASES i

l 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 l 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 resdt in doses which exceed the design objectives of 4

Appendix 1 to 10 CFR 50. These gaseous release rates provide reasonable assurance that 4 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 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 atmosphenc diffusion factor above that for the exclusion area boundary. The absence of noble gases ensures that, at all times, the corresponding gamma and beta dose rates above background 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 all times.

ACTION:

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

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l l SNEC Facility Offsite Dose Calculation Manual 0 )

I BASES '

l This control and associated action is provided to implement the requirements of Section ll.C, Ill.A and IV.A of Appendix l.10 CFR Part 50. The Controls are the guides set I 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 l ,

that conformance with the guides of Appendix I be shown by calculational procedures  !

based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 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 radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man,3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. The absence of noble gases and lodines at the site eliminates the need to specify dose limits for these  ;

nuclides. l 2.2.2.3 Ventilation Exhaust Treatment System 1

CONTROL 1

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%

l penetration with prefilters installed.

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

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

l ACTION:

a. With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable, suspend all activities within the Containment Vessel / Decommissioning Support Building that have the potential to cause a MEASURABLE RELEASE to the environment 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: l 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 squal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or eq ial to 75 mrem.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a. 2.2.1.2.b, 2.2.2.2.a. or,2.2.2.2.b, calculations should be made including direct radiation contribut'ons from the unit and from outside sto M tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. ch is the case, prepare and submit to the NRC Region i Administrator within 30 dap ) 3pecial Report which defines the corrective action to be taken to reduce subsequent n  : s to prevent recurrence of exceeding the above limits and includes the schedule for a . ring conformance with the above limits. This Special Report, as defined in 10 CFR Part s2203(b), shall include an analysis which estimates the radiation exposure (dose) to a ME', ~ R OF THE PUBLIC from uranium fuel cycle sources, including all

effluent pathways and direct radiation, for the calendar year that includes the release (s) i covered by this report. It shall also describe levels of radiation and concentrations of I

radioactive materialinvolved, and the cause of the exposure levels or concentrations. If I 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 shallinclude a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the 7 report is considered a timely request, and a variance is granted until staff action on the

request is complete.

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! Nmber S xtan Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 TRie Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 BASES This control is provided to meet the dose Smitations of 40 CFR Part 190 that have been incorporated into 10 CFR Pert 20.1301(d). This control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 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 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 l 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 requ:.ements 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 MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuct 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 cor. ducted as specified in Table 2.3-1.

APPLICABILITY: At all times.

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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b. With the level of radioactivity as the result of plant effluents in an environmental l 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 l 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 sampling medium, this report shall be submitted if:

concentration fil + concentration fd + ... iL1A reporting level (1) reporting level ('2) 1 1

When radionuclides other than those ir Table 2.3-2 are detected and are the result  ;

of plant effluents, this report shall be submitted if the potential annual dose

• to a i member of the public is equal to or gre ater 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 1 condition shall be reported and described in the Annual Radiological Environmental Operating Report.

BASES The radiological monitoring program required by ti,is control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for i those radionuclides which lead to the highest potential radiation exposures of members of l the general public resulting from the station operation. This monitoring program 1 implementsSection IV B.2 of Appendix ! 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 I the effluent measurements and modeling of the environmental exposure pathways.

Guidance for this monitonng is provided by'.e 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 j 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.

APPLICABILITY: At all times.

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

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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/O locations identified in the land use census.

BASES i I

During SNEC Facility decommissioning operations, very small amounts of radioactivity are 1 expected to be released to the atmosphere. The predominant radionuclide in airbome effluents is expected to be Cs-137 and there will be no radioiodine. Using this fact and the Ri values listed in the SNEC Facility ODCM, the entical 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 I be collected and analyzed for gamma-emitting radionuclides. Other analyses will be l performed, as necessary. The samples will be collected annually during the growing season 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 I be collected and analyzed on a routine basis. Additionally, collecting vegetation samples on a routine basis at the highest D/O 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 Interlaboratory 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 l and analyses which are selected for inclusion in the program shall be representative of those required by Table 2.3-1.

APPLICABILITY At all times.

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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S xt n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 TKlJ Reviskm No.

SNEC Facility Offsite Dose Calculation Manual 0 BASES The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on precision and accuracy of the measurements of

)

radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV, B.2 of Appendix I to 10 CFR 50.

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l l

SNEC Facility Offsite Dose Calculation Manual 0 i TABLE 2.31 Page 1 of 2 l

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

~

SAMPLE COLLECTION ANALYSIS ANALYSIS MEDIUM FREQUENCY TYPE (a) FREQUENCY (b)

Air Particulate Biweekly (c) Gr-A On each sample (d) i (AP) Gr-B On each sample (d)

Gamma (e) Quarterly Composite (f)

Aquatic Sediment (g) Quarterly Gamma On each sample (SD)

Dosimeters (h) Quarterly Gamma Quarteriy (lD) Immersion Dose Potable Water (i) Quarterly Gr-B On each sample (GW) Gamma On each sample H-3 On each sample l

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 i

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, hazr.rdous conditions, malfunction of automatic sampling equipment or other j legitimate reasons.

1

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

d. Airbome particulate samples should be 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 rnean of the control, analyze the filter for gamrna emitters and Sr-90.

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Numtw S xt n 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 2.3-1 Page 2 of 2 Saxton Nuclear Experimental Corporation Facility REMP Sample Analysis, Collection and Analysis Frequency by Sample Medium

e. Gamma (isotopic analysis) means the identification and quantification of gamma-emitting radionuclides.

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

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 control station, from the locations listed in Table 3.3-1. I

i. 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 A14 and Q12.

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.

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

l.

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

REMP Analytical Required Sensitivities (LLD)" l and Reporting Levels EXPOSURE / PATHWAYS b

AND/OR SAMPLE UNITS ANALYSIS REQUIRED LLD

• REPORTING LEVEL Air Particulate pCi/m Gr-Alpha 1.5E-3 1.0E-1 l (AP) Gr-Beta 1.0E-2 1.0E0 Cs-134 5.0E-2 1.0E1 Cs-137 6.0E-2 2.0E1 Sr-90 1.0E-2 1.0E-1 Sediment / Soil pCi/g (dry) Cs-134 1.5E-1 1.0E0 (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 (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 pCi/g (wet) Cs-134 6.0E-2 1.0E0 (BR) Cs-137 8.0E-2 2.0E0 Sr-90 1.0E-2 1.0E 1 Milk pCi/L pCl/L Cs-134 1.5E1 6.0E1 l (MI) Cs-137 1.8E1 7.0E1 l Sr-90 2.0E0 8.0E0 i

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l TABLE 2.3 2 Page 2 of 2 Detection Capabilities for Environmental Sample Analysis Table Notation

a. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, which may be related to plant operations, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

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

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

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

LLD =

E V 2.22 Y exp(-Mt)

Where:

LLD is the "a priori" lower limit of detection as defined abovo, 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 picocurie, Y is the fractional radiochemical yield (when applicable),

). is the radioactive decay constant for the particular radionuclide and at 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 l be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally l

background fluctuations, unavoidab;e 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 Operatmg Report.

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

l SNEC Facility Offsite Dose Calculation Manual 0 3.0 SURVEILLANCES ]

I

1. Surveillance Requirements shall be applicable dunng the conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement. The Surveillance l Requirements shall be performed to demonstrate compliance wrth the OPERABILITY requirements of the Control.

]

2. Each Surveillance Requirement shall be performed within the specified time interval with a I 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 tit. a limits of the ACTION requirements are applicable at the time it is identified that a Surveillance R quirement 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 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.

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Tcble 3.1-2 6575-PLN-4542.08 Revision 0 Page 1 of 1 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements INSTRUMENT CHANNEL SOURCE CHANNEL CHANNEL CHECK CHECK CAllBRATION TEST APPLICABILITY

1. Station Ventilation System

a. Particulate Monitor (RMA-1) O(D W SA W #

O During operation of the monitored system (1) Daily channel check only required when decommissioning activities are occurring in the Containment Vessel / Decommissioning Support Building.

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Mumber i Sad n Nu&ar Sperimental Corporation l SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 TRie Revtsen No. l 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 methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

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

3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once a rr Enth when liquid releases are in progress.

3.2.1.3 Dose Projections i 3.2.1.3.1 Doses due to liquid releases shall be projected at least once per month ,

when liquid releases are anticipated. I

(

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TABLE 3.2-1 Page 1 of 1 1

Radioactive Liquid Waste Sampling and Analysis (4,5)

A. Liauid Releases Sampling Frequency Type of Activity Analysis Detectable Concentration (3)

Each Batch Individual Gamma SE-7 Ci/mi(2)

H-3 1E-5 pCl/mi Quarterly Composite (1) Gross Alpha 1E-7 Ci/ml Sr90 SE-8 C1/mi NOTES:

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

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

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

reported. )

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

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

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l 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS j

3.2.2.1 Dose Rates ,

I 3.2.2.1.1 The dose ra'e of radioactive materials in gaseous efiluents shall be j determined to be within the limits of Control 2.2.2.1. In accordance with  !

methods e.1d procedures of the ODCM by obtaining representative  ;

sample = and performing analyses in accordance with the sampling and I analyus program, specified in Table 3.2-2.

3.2.2.2 Dose i

3.2.2.2.1 Cumulative dose contributions from Tritium, and radionuclides in '

pnticulate form with half lives greater than 8 days for the current l calendar quarter and current calendar year shall be determined in accordanca 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 in accordance with the ODCM.

J 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 j 2 6500 cfm annually. I 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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I Number Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 l Tele Revisen No 1

SNEC Facility Offsite Dose Calculation Manual 0 l l TABLE 3.2-2 Page 1 of 2 l

l Radioactive Gaseous Waste Sampling and Analysis Program (3) I l

l 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 uCl/cc Particulates Weekly Individual (b) Gamma 1E-10 pCi/cc (2)

Emitters Monthly Sr-90 1E-11 pCi/cc Composite Monthly Gross Alpha Ermtters 1E-11 pCi/cc  !

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 l their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these I circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed I ratios for those radionuclides which are measurable. )

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

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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):

4.66S 3 LLD =

E x V x 2.22 x 10 8 x Y x exp(-ut)

Where:

LLD is the "a priori" lower limit of detection as defined above, as micocuire 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 x 10'is the number of disintegrations per minute per micocurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay 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.

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

b. The principal pcmma emitters for which the LLD specification applies exclusively are tb3 following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be I

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 j 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 Monrtoring Program Surveillance Requirements

a. The radiological environmental monitoring samples shall be collected pursuant to Table 2.3-1. 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. I 1

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/O 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 will identify 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/O locations identified in the land use census,

c. A summary of the Interlaboratory Comparison Program results shall be included in the Annual Radiological Environmental Operating Report.

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 3.3-1 Page 1 of 3 Saxton Nuclear Experimental Corporation Facility i Radiological Environmental Monitoring Program Description ,

l Station Media Local Description Note '

A1-1 Sediment Drain outfall outside perimeter fence Water rarely present A12 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 l

B14 Surface Water Sediment Drop weir in the Westinghouse Yard i Area.

81-6 TLD NNE Sector, perimeter fence B1-7 Broadleaf Vegetation N NE Sector, site boundary C16 Sediment Drain outfall, NE comer of perimeter Water rarely present fence C19 TLD NE Sector, perimeter fence C2-1 TLD Weaver Ridge,0.8 miles from CV D1-1 Air Particulate Open Field ENE Sector D1-4 TLD ENE Sector, perimeter fence D2-1 TLD Weaver Bridge,1.3 miles from CV E1-1 Potable Water Penelec Line Shack E1-7 TLD E Sector, perimeter fence E1-17 TLD Penelec Line Shack E2-1 TLD E Sector. 0.25 miles from CV

! E3-1 TLD 3 miles East of CV in State Gameland

#67 F1-2 TLD ESE Sector, perimeter fence 40 39180. DOC

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 3.3-1 Page 2 of 3 Saxton Nuclear Experimental Corporation Facility Radiological Environmental Monitonng Program Description Station Media Local Description Note G1-1 TLD Potable Water SE Sector, private residence in Saxton G1-2 TLD SE Sector, perimeter fence G21 TLD SE Sector, closest private residence 1

G10-1 Air Particulate Reichley Microwave Tower Offsite Control Station G10-2 TLD New Granada Offsite Control Stcison H15 TLD SSE Sector, perimeter fence H2-1 TLD Tussey Mt. High School H10-1 TLD Wells Tannery Offsite Control Station Ji-1 TLD S Sector, perimeter fence J1-3 Air Particulate Penelec Area S Sector K1-5 TLD Saxton Borough Hall Offsite Control Station l

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 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 j i

R1-1 TLD NNW Sector, perimeter fence 41 3018D DOC

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t SNEC Facility Offsite Dose Calculation Manual 0 l TABLE 3.3-1 Page 3 of 3 Saxton Nuclear Experimental Corporation Facility Radiological Environmental Monitoring Program Description Station Media Local Description Note Geo 1 Groundwater Monitoring well South of CV fenced 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 Geo5 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 diagonal well MW2 Groundwater Northwest to Southwest diagonal well l

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i PART11 I

EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES l

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6575-PLN-4542.08 TO Revtsson No. l SNEC Facility Offsite Dose Calculation Manual 0 1.0 LIQUID EFFLUENT MONITORS 1.1 Llauid Radiation Monitor Set Points 1

There is no Radioactive Liquid Effluent instrumentation in service during the decommissioning of j the Saxton Nuclear Station.

1.2 Liquid Effluent Release Points )

l The outfall for liquid effluents to the Juniata River will be through a temporary hose to the riverbank l on Penelec property when release of such effluents is required. 1 l

1.3 Control of Liquid Releases j i

Liquid effluent releases are controlled to less than ten times the 10CFR20 concentrations by i ensunng that the parameters for the release meet the following equation:

1 l

c*f SC (eq1,3)

F+f l l

where:

C= ten times the effluent concentration of 10 CFR 20 for the site, in Cl/ml. I 4

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 3.21. 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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SNEC Facility Offsite Dose Calculation Manual 0 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liauld Effluents - 10 CFR 50 Accendix 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 Juniata River. This is further described in Reference 3.10. The dose contribution from all radionuclides in liquid effluents released to the unrestricted area is calculated using the following expression:

~r g8 r g 8 '

Dose j = % E (At) X (C;) X AWij X + AFij X (eq 2.1) i j _

t FR s s FR s _

4 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.

I At = the length of the time period of actual releases, over which C iand f are averaged

for all liquid releases, in hours.

C = the average concentration of radionuclide, I, in undiluted liquid effluent during time period at from any liquid release, in Ci/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 AF;)= the site-related ingestion dose commitment factor to the total body or any organ, J, for each identified principle gamma and beta emitter, in mrem /hr per Cl/ml. AW l is the factor for the water pathway and AF is the factor for the fish pathway.

Values for AWgare determined by the following equation:

AWy= (1.14E5) x (U.) x (DFy) (eq 2.2) s where:

1.4SES = (1.0E6 pCil Ci) x (1.0E3 ml/kg) x (8760 hrlyr)

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

DFq= ingestion dose conversion factor for radionuclide, i, for adults total body and for

" worst case" organ, j, in mrem /pCl, from Table 2.1 (Reg. Guide 1.109) 4s 3918D doc

Number Saxt n Nuclear Experimental Corporabon SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 Values for AF,) are determined by the following equation:

AF y= (1.14E5) x (Ug) x (DFy) x (BF,) (eq 2.2.2) where:

1.45E5 = defined above 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 q

" 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 pCi/kg per pCi/L from Table 2.2 (Reg. Guide 1.109 Rev.1).

2.2 Liquid Radwaste System Dose Calcs Once/ Month l 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 antici 'ed during the next 31 days shall be calculated. If this projected dose exceeds 0.06 mrem ' ul body or 0.2 mrem any organ, appropriate portions of a Liquid Radwaste Treatment System, c. ,1 fined in Section 3.1, shall be used to reduce radioactivity levels prior to ,

release. j 2.3 Altemative Liquid Dok Jalculational Methodology I

As an altemative, 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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! SNEC Facility Offsite Dose Calculation Manual 0 TABLE 2.1 Page 1 of 3 l Liquid Dose Conversion Factors (DCF): DFj i ingestion Dose Factors for Adults" (MREM Per pCi Ingested)

NUCLIDE BONE LIVER T. BODY THYROID K.IDNEY LUNG GI-LLI l

H 3 NO DATA 1.0SE-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 1 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.705-06 1.70E-06 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91 E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51 E-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01 E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91 E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21 E-08 NO DAT NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11 E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RS 88 NO DATA 6.05E-08 3.21 E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01 E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.625-09 NO DATA 2.58E 10 NO DATA NO DATA NO DATA 1.02E-04 47 3918D. DOC

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 2.1 Page 2 of 3 Liquid Dose Conversion Factors (DCF): DFji ingestion Dose Factors for Adults *

(MREM Per pCi Ingested)

NUCLIDE BONE UVER T. BODY THYROID KIDNEY LUNG GI-LLI Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41 E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E 10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.665-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31 E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07

~

, TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10EI21 RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 i RU 105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 i RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31 E-06 NO DATA 1.78E-04 AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91 E-07 NO DATA 6.04E-05 SB 125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E-05 TE 125M 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E-05 4.29E-06 1.82E 06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71 E-05 l 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 l 131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E 05 NO DATA 1.57E-06 1 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 1 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 NO DATA 2.22E-06 i 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51 E-10 i

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 2.1 Page 3 of 3 Liquid Dose Conversion Factors (DCF): DFj i ingestion Dose Factors for Adults *

(MREM Per pCi Ingested)

NUCLIDE BONE 1,lVER T. BODY THYROID KIDNEY LUNG GI-LLI I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31 E-06 CS 134 6.22E-05 1.48E-04 1.21 E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS 136 6.51 E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS 137 7.97E 05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11 E-06 CS 138 5.52E 08 1.09E 07 5.40E-08 NO DATA 8.01 E-08 7.91 E-09 4.65E-13 )

BA 139 9.70E-08 6.91 E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 l BA 140 2.03E-05 2.55E-08 1.33E 06 NO DATA 8.67E-09 1.46E ]8 4.18E-05 BA 141 4.71 E-08 3.56E 11 1.59E-09 NO DATA 3.31 E-11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E 11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E 26 I

LA 140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE 143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21 E-07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 144 3.01 E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E 18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61 E-08 3.01 E-08 NO DATA NO DATA NO DATA 2.82E-05 NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 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 l 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, BFi Bloaccumulation Factors to be Used in the Absence of Site-Specific Data' (pCl/kg per pCi/ 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 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 RH 1.0E+01 3.0E+02

• SB 1.0E+00 1.0E+00 TE 4.0E+02 6.1 E+03 i 1.5E+01 5.0E+00 i

CS 2.0E+03 1.0E+03

! BA 4.0E+00 2.0E+02 LA 2.5E+01 1.0E+03 l CE 1.0E+00 1.0E+03 PR 2.5 E+01 1.0E+03 ND 2.5E+01 1.0E+03 W 1.2E+03 1.0E+01 NP 1.0E+01 4.0E+02 i

• 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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l SNEC Facility Offsite Dose Calculation Manual 0 j 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 l 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 liraits of ,

ODCM Part i Control 2.2.2.1.

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

1500 > (Cg )(F)(P;)(Dy ) (eq 4.1) where: I l

C; = set point concentration based on Sr-90, in Ci/cc ]

l F = gaseous effluent flow rate at the monitor, in cc/sec P = pathway dose parameter, in mrem /yr per Ci/m3for the inhalation pathway from Table 4.2. The dose factors are based on the actualindividual organ and most restrictive age group (child) (NUREG-0133). j l

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.

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

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

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S xt n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 l Title Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 4.2 l Gaseous Effluent Release Points and Gaseous Radiation Monitor Data  !

l SNEC Facility has one required effluent gaseous radiation monitor. This is RMA-1 Surveillance 1 l frequencies for this monitor are, specified in Part I of the ODCM.

4.2.1 RMA-1 l RMA-1 is an Eberline AMS-3 particulate radiation monitor for the Saxton Containment l 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. I 4.2.2 RMA-1 Alarm Setpoint l

Sensitivity: (2.22E6 dpm/ Ci)(0.3 ct/ dis)(SE4 cc/ min) = 3.33E10 com/ min l Ci/cc j Alarm Setpoint: 4000 cpm above background l l Alarm Setpoint Basis. ,

l c = 1500 mrem /vr  ;

(F)(P)(X/Q) I j F= Effluent flow rate (cc/sec)

P = Pathway Dose Parameter for Sr-90 (Inhalation pathway: mrem /yr/uCl/m3)

X/O = Dispersion Parameter (sec/ m3) 1 1500 = Annual Dose Rate limit for unrestncted areas (mrem /yr) l l

F = 7500 cfm = 3.54E6 cc/sec I Pi = 1.01E8 X/Q = 3.41E-3 c = Inhalation Pathway Limiting Concentration c = 1.23E-9 Ci/cc l l

Setpoint Calculation Alarm will activate after 180 minutes with above conditions (1.23E-9 Ci/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 l

SNEC Facility gaseous effluent combined releases are controlled (per ODCM Part I) by effluent

! sampling and radiation monitor set points. These measures assure that releases do not combine to l 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 l 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.

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

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 4.1 Page 1 Of 1 Results Summary ATMOSPHERIC DISPERSION FACTORS FOR SNEC FACILITY GROUND RELEASE DISTANCE SECTOR AVERAGE X/O IN SEC/CU.M. (IN METERS)

TO SECTOR 200 1600 3200 4800 8000 11000 16000 24000 40000 56000 80000 N 3 41E-03 1.10E 04 3 61 E-05 195E-05 1 15E-05 7.70E-06 5 26E-06 2 98E-06 171 E-06 1.12E-06 7 46E-07 NNE 1.16E-03 3.70E-05 121 E-05 6 61E 06 3 83E-06 2.58E-06 1.74E-06 9 83E-07 5 69E-07 3 74E-07 2.48E-07 NE 3 75E-04 1.19E-05 3 88E-06 213E-06 123E 06 8 24E-07 5 56E-07 3.13E-07 181 E-07 1.19E-07 7.90E-08 ENE 2 68E-04 8 38E-06 2.72E-06 149E-06 8 49E-07 5 71 E-07 3 83E-07 2.14E-07 125E-07 8 21 E-08 5 44E-08 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 174E-07 1 15E-07 7 62E-08 ESE 8 24E 05 2 55E-06 8 25E-07 4 61 E 07 2.57E 07 174E-07 1.14E-07 6 38E-08 3 75E-08 2 48E 08 164E 08 SE 5 27E 05 165E-06 5 36E-07 2 99E-07 168E-07 1 14E-07 7.53E-08 4 22E-08 2 48E-08 163E-08 108E-08 SSE 9 50E-05 2 97E-06 9 65E 07 5 26E-07 3 00E-07 2 01 E-07 136E-07 7 61E-08 4 40E 08 2.90E 08 1.93E-08 S 2.27E-04 712E 06 2.31E 06 127E-06 7 24E-07 4 88E-07 3 26E-07 183E-07 106E-07 7.01 E-08 4 64E 08 SSW 2 59E 04 8 01 E-06 2 58E-06 146E-06 8 06E-07 5 48E 07 3 55E-07 198E-07 1.18E-07 7.77E-08 512E-08 SW 2 81E-04 8.75E-06 2.83E-06 1.59E-06 8.86E-07 6 00E 07 3 94E-07 2.20E-07 130E-07 8.56E-08 5 65E-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 W 139E-03 4 44E-05 1.46E-05 7 97E-06 4 63E 06 312E-06 2.11 E-06 1 19E-06 6 90E 07 4 54E-07 3.00E-07 WNW 147E-03 4 71E-05 1.55E-05 8 43E 06 4 92E-06 3 31 E-06 2 25E 06 127E-06 7 34E 07 4 82E-07 3.20E-07 NW 9 91 E-04 318E 05 104E-G5 5 71E 06 3 32E-06 2.24E-06 152E-06 8 56E-07 4 95E-07 3 25E-07 2.15E-07 MNW 162E-03 5 21E 05 1.71 E-05 9 32E-06 5 45E-06 3 66E-06 2 49E-06 141 E-06 813E-07 5 34E-07 3 54E-07 GROUND RELEASE DISTANCE SECTOR AVERAGE D/O IN 1/SO.M. (IN METERS)

TO j SECTOR 200 1600 3200 4800 8000 11000 16000 24000 40000 56000 80000  ;

N 2 56E-07 9 86E 09 2 96E-09 140E-09 5 42E-10 3 23E-10 1.72E-10 9 20E-11 3 55E 11 183E-11 9 86E-12 NNE 2 07E-07 7.98E-09 2 39E-09 1 13E-09 4 39E-10 2 61 E-10 1.40E 10 7 45E-11 2 87E-11 148E-11 7 98E-12 RE 1 14E-07 4 40E-09 132E-09 6 24E-10 2 42E-10 144E 10 7.70E-11 411E-11 158E-11 8.18E-12 4 40E-12 ENE 1.55E 07 5 96E-09 179E-09 8 44E-10 3 28E 10 195E 10 104E-10 5 56E 11 215E-11 1 11 E-11 5 96E 12 E 124E-07 4 75E 09 143E-09 6 73E-10 2 61 E-10 155E 10 8 31E.11 4 43E 11 171E 11 8 82E-12 4 75E-12 ESE 3 31E-08 127E-09 3 82E-10 1.80E 10 7 00E 417E 11 2 23E 11 1.19E-11 4 58E-12 2.36E-12 1.27E-12 SE 215E-08 8 28E-10 2.48E-10 1.17E-10 4 55E-11 2.71 E-11 145E 11 7.72E-12 2 98E-12 154E-12 8 28E-13 SSE 4 27E 08 1.64E-09 4 93E-10 2 33E-10 9 03E-11 5.38E 11 2.87E-11 1.53E 11 5 91 E-12 3 05E-12 1.64E-12 S 8.77E 08 3 37E-09 101 E-09 4 78E 10 1.85E 10 1.10E-10 5 90E-11 315E-11 121E 11 6 26E-12 3 37E 12 SSW 9 24E 08 3 55E-09 107E-09 5 03E-10 195E 10 1 16E-10 6 22E-11 3.32E-11 128E-11 6 60E 12 3 55E-12 SW 7.28E 08 2.80E-09 8 40E-10 3 97E-10 154E-10 917E-11 4 90E-11 2.61 E-11 101 E-11 5 20E-12 2.80E-12 WSW 5 05E-08 1.94E-09 5 83E-10 2.75E-10 107E-10 6 35E 11 3 40E-11 181 E-11 6 99E-12 3 61E 12 194E-12 W 9 98E-08 3 84E-09 1 15E-09 5 44E 10 211 E-10 1.26E-10 6 72E-11 3 58E 11 138E-11 7.13E 12 3 84E-12 WNW 108E-07 414E-09 124E-09 5 86E-10 2 28E-10 1.35E-10 7.24E-11 3 86E-11 149E-11 7 68E-12 414E-12 i NW 8 23E-08 3.16E-09 9 49E 10 4 48E-10 1.74E 10 1.04E 10 5 54E-11 225E-11 1.14E 11 5 88E-12 316E-12 I l NNW 108E-07 416E-09 1.25E-09 5 90E-10 2 29E 10 1.36E-10 7 29E-11 3 89E-11 150E 11 7.73E-12 416E-12 l

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Number S 4 n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tr3 Revisson No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 4.2 Page 1 of 1 Dose Parameters for Radioiodines and Radioactive Particulate in Gaseous Effluents

• CRITICAL ORGAN CRITICAL ORGAN NUCLIDE ORGAN FACTOR Pi"* NUCLIDE ORGAN FACTOR Pi**

H-3" TOTAL BODY 3.04E-07 1.12E+03 RU-103 LUNG 1.79E-04 6.62E+05 C-14 BONE 9.70E-06 3 59E+04 RU-105 GI-LLI 2.69E-05 9 95E+04 NA-24 TOTAL BODY 4.35E-06 1.61 E+04 RU-106 LUNG 3.87E-03 1.43E+07 P-32 BONE 7.04E-04 2.60E+06 AG-110M LUNG 1.48E-03 5.48E+06 CR-51 LUNG 4 59E-06 1.70E+04 TE-125M LUNG 1.29E-04 4.77E+05 MN-54 LUNG 4.26E-04 1.58E+06 SB-125 LUNG 6.27E-04 2.32E+06 MN-56 GI-LLI 3.33E-05 1.23E+05 TE-127M LUNG 4.00E-04 1.48E+06 FE-55 LUNG 3.00E-05 1.11 E+05 TE-127 LUNG 1.52E-05 5.62E+04 FE-59 LUNG 3.43E-04 1.27E+06 TE-129M GI-LLI 4.76E-04 1.76E+06 CO-58 LUNG 2.99E-04 1.11 E+06 TE-129 LUNG 6.89E-06 2.55E+04 CO-60 LUNG 1.91 E-03 7.07E+06 TE-131M GI-LLI 8.32E-05 3.08E+05 NI-63 BONE 2.22E-04 8.21 E +05 TE-131 LUNG 5.55E-07 2.05E *03 NI-65 GI-LLI 2.27E-05 8.40E+04 TE-132 LUNG 1.02E-04 3.77E+05 CU-64 GI-LLI 9.92E-06 3.67E+04 l-130 THYROID 4.99E-04 1.85E4 06 ZN-65 LUNG 2.69E-04 9.95E+05 l-131 THYROID 4.39E-03 1.62E+07 ZN-69 GI-LLI 2.75E-06 1.02E+04 l132 THYROID 5.23E-05 1.94E+05 BR-83 TOTAL BODY 1.28E-07 4.74 E+02 1133 THYROID 1.04 E-03 3.85E+06 BR-84 TOTAL BODY 1.48E-07 5.48E+02 1-134 THYROID 1.37E-05 5.07E+04 BR-85 TOTAL BODY 6.84E-09 2.53E+ 01 1-135 THYROID 2.14 E-04 7.92E+05 j RB-86 LIVER 5. 36E-05 1.98E+05 CS-134 LIVER 2.74E-04 1.01 E+06 i RB-88 LIVER 1.52E-07 5.62E+02 CS-136 LIVER 4.62E-05 1.71E+05 RB-89 LIVER 9.33E-08 3.45E+02 CS-137 BONE 2.45E-04 9.07E+05 SR-89 LUNG 5.89E-04 2.16E+06 CS-138 LIVER 2.27E-07 8.40E+02 SR-90 BONE 2.73E-02 1.01 E+08 BA-139 GI-LLI 1.56E-05 5.77E+04 SR-91 GI-LLI 4.70E-05 1.74E+05 BA-140 LUNG 4.71 E-04 1.74E+06 SR-92 GI-LLI 6.55E-05 2.42E+05 BA-141 LUNG 7.89E-07 2.92E+03 l Y-90 GI-LLI 7.24E-05 2.68E+05 BA-142 LUNG 4.44E-07 1.64E+03 Y-91 M LUNG 7.60E-07 2.81 E+ 03 LA-140 GI-LLI 6.10E-05 2.26E+05 Y-91 LUNG 7.10E-04 2.63E+06 LA-142 GI-LLI 2.05E-05 7.59E+04 Y-92 GI-LLI 6.46E-05 2.39E+05 CE-141 LUNG 1.47E-04 5.44E+05 Y-93 GI-LLI 1.05E-04 3.89E+05 CE-143 GI-LLI 3.44E-05 1.27E+05 ZR 95 LUNG 6.03E-04 2.23E+06 CE-144 LUNG 3.23E-03 1.20E+07 ZR-97 GI-LLI 9.49E-05 3.51 E+05 PR-143 LUNG 1.17E-04 4.33E+05 NB-95 LUNG 1.66E-04 6.14 E+05 PR-144 LUNG 4.23E-07 1.57E403 MO-99 LUNG 3.66E-05 1.35E+05 ND-147 LUNG 8 87E-05 3.28E+05 TC-99M GI-LLI 1.30E-06 4.81 E+03 W-187 GI-LLI 2.46E-05 9.10E+04 TC-101 LUNG 1.58E-07 5.85E+02 NP-239 GI-LLI 1.73E-05 6.40E+04 The listed dose parameters are for radionuclides, other than noble gases that may be detected in gaseous effluents. Pi factors include the inhalation pathway and are based on the most restrictive age group (child) entical organ. Additional dose parameters for nuclides not included in this Table may be calculated using the methodology described in NUREG-0133.

Tntium dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin.

• " rem / year per Ci/m l

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SNEC Facility Offsite Dose Calculation Manual 0 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents - Instantaneous Release Limits 5.1.1 Tritium and Radionuclides in Particulate Form. with Half-Lives Greater thari 8 Days For Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation applies:

DOSE RATE ip = E (Pg )(Dy )(Q g) (eq 5.1) where:

Dose Rateip = 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 pCi/m', from Table 4.2. The dose factors are based on the critical I individual organ and most restnctive age group (child).

Dv = highest 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 sec/m'. at Sector N.

Qi = release rate of each radionuclide, i,in Ci/sec. Calculated using the concentration of each radionuclide, i, in pCl/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 o = E (R;)(Dy)(Q g)(3.17E - 8) (eq 5.2) where:

Doseo = dose to all real pathways, p, to organ, o, of an individual in age group, a, from Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, in mrem, during any desired time period.

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

and organ, o, in mrem /yr per Ci/m for the inhalation pathway and 2

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

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

SNEC Facility Offsite Dose Calculation Manual 0 NOTE 3

Tritium, H-3, dose factor is mrem / year per pCi/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-2, for other pathways. Table 4.1 is used for all releases. Maximum value of X/Q presently used is 3.41E-3 sec/m' at

-2 Sector N. Maximum value of D/Q in m'* is 2.56E-7 m at Sector N.

Dy(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.

Og = release of Tritium and Radionuclides, i, in Particulate Form with half-lives greater than 8 days, in Cl, cumulative over the specified time period

( Ci/second

• seconds).

3.17E-8= inverse of the number of seconds in a year.

5.3 Ventilation Exhaust Treatment System Dose Calculations Once per 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 Aiso, this dose projection shallinclude 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 Alternative Dose Calculational Methodoloaies for Gaseous Effluents l

l As an attemative to the methods described above, the models in/or based upon, those presented in l Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. l l Default parameter values from Regulatory Guide 1.109 (Rev.1) and/or actual site specific data can  !

l be used where applicable.

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

AGE GROUP: INFANT PATHWAY: INHALATION ORGAN DOSE FACTORS; mren /yearperyCUm l NUCLIDE BONE LIVER T. BODY THYROlO KIDNEY LUNG GI-LLI l H-3 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 l C-14 2.65E+04 5.31 E+03 5.31 E+03 5.31 E+03 5.31 E+03 5.31E+03 5.31E+03 I 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 0.00E+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 l

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 1.11 E+04 CO-60 0.00E+00 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06 3.19E+04 i NI-63 3.39E+05 2.04E+04 1.16E+04 0.00E+00 0.00E+00 2.09E+05 2.42E+03 l ZN-65 1.93E+04 6.26E+04 3.11 E+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 3.96E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 SR-90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31 E+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-95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11 E+04 1.75E+06 2.17E+04 NS-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 1.61 E+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 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 1.41 E+04 6.09E+03 2.23E+03 5.47E+03 3.1 EE+04 1.68E+06 6.90E+04 1-131 3.79E+04 4.44E+04 1.96E+04 1,48E+07 5.18E+04 0.00E+00 1.06E+03 1-133 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 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 i 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 i

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i SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.2.2 Page 1 of 1

) Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: INHALATION ORGAN DOSE FACTORS; mre_m/yearper uCl/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 +0S ,

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 l

, 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 I i

MN-54 0.00E+00 4.29E+04 9.51 E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 j FE-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11 E+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 1.11 E+06 3.44E+04 I CO-60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04  !

NI-63 8.21 E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 l 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 l 1 SR-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05  !

SR-90 1.01 E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 l Y 91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 l ZR 95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11 E+04  ;

, NB-95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04  !

RU-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 1 j RU 106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 )

i 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 l-131 4.81E+04 4.81 E+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 6.51 E+05 1.01 E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 CS-136 6.51 E+04 1.71 E+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 6.81 E+02 0.00E+00 4.81E+03 3.28E+05 8.21 E+04 1

1 i

l i

h i 59 3918D. DOC

I i am-l l SAXTON NUCLEAR Sa4 n Nudear Emnantal Comoradon Facility Policy and Procedure Manual 6575-PLN-4542.08 TQe Revision No, I SNEC Facility Offsite Dose Calculation Mantal 0 TABLE 5.2.3 Page 1 of 1 l Pathway Dose Factors, Ri i ,

AGE GROUP: TEEN PATHWAY: INHALATION l

___7_______________

~~~

3 ~~~~00 Ol)-~ ~1 2 03-~~~1 27 03-~ 7 ~~~1 03 12 03- ~ ~ ~1 - 3--

C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 CR-51 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

-~ - ~ ~ " " ~~ ~ ~ ~ ~ -~ ~~~ ~ ~~~

Ch-58 ~ 0~~~ 0 3 0- 00 '~ ~ ~4 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 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 3.71 E+05 SR 90 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05

% 91 6.61 E+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 NB-95 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51 E+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

~A-

- - - - ~~- - - - ~~~ ~

Oll-'-- 0~ ~ ' ~ 9 0- ~ ~ ~ 0~

TE 125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 j 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 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

~~~ 9

- ~ ~~ ~ ~

~~A- 40--- 0 - 7 0- ~ ~ ~ 0- ~0 0----

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 1.21 E+ 06 1.34E+07 8.64E+05 PR-143 1.34E+04 5.31E+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 I

l l

l l

60 39180. DOC

Number SAXTON NUCLEAR SaMon Nu&ar Expenmental Corporation Facility Policy and Procedure Manual 6575-PLN-4542.08

, Title Reymon No.

SNEC Facility Offsite Dose Csiculation Manual 0 TABLE 5.2.4 Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: INHALATION ORGAN DOSE FACTORS: mre_m_/ year peryCl/m NUCLIDE BONE LIVER T. BODY THYROID KIDNEY 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 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 3.41E+03 l CR-51 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.2EE+ 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 7.74 E+ 04 FE-55 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21 E+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 7.22EK5 I 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 NB-95 1.41 E+04 7.82E+03 4.21 E+03 0.00E+00 7.74 E+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 6.91 E+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 6.21 E+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 2.81 E+05 2.00E+05 ND-147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21 E+05 1.73E+05 61 3918D. DOC

Number I

S xt n Nuclear Experimental Corporation i

SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 l Tme Reymon No.  !

SNEC Facility Offsite Dose Calculation Manual 0 l

l TABLE 5.3.1 Page 1 of 1 l Pathway Dose Factors, Ri l l

l AGE GROUP: ALL PATHWAY: GROUND Pl.ANE l 1

_98GM ppSE.MC_T_O_R_S*

~~~

~~-3 0~ ~ ~ ~0 I00 60-~

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

~ ~

~h-58 ~~~~~ EE~ ~ ~ ' - ~

CO-60 2.15E+10 2.53E+10 NI-63 0.00E+00 0.00E+00 ZN-65 7.47E+08 8.59E+08 l RB 86 8.97E+06 1.03E+07 1 SR-89 2.16E+04 2.51 E+04 SR-90 0.00E+00 0.00E+00 l Y-91 1.07E+06 1.21 E+06 ZR-95 2.45E+08 2.84 E+08 NB-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 4.01 E+09 TE-125M 1.55E+06 2.13E+06 TE-127M 9.17E+04 1.08E+05 TE-129M 1.98E+07 2.31 E+07 l-131 1.72E+07 2.09E+07

~

34~~~~~ . 6E+ E~ ~ ~8 0 9-~

CS-136 1.51 E+08 1.71 E+08 CS 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 1.01 E+07 2

• m - mrem / year per Cl/sec.

1 1

62 39180.00C

Number I

S 4 n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revwon No. 1 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

_g _7_

~~ ~~~~

-3 -- 0 0)----2 38E 03 23 03-~~2 ~-~2 03~ ~~ ~2 I3- 63-~~2 3--

C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 1 CR-51 0.00E+00 0.00E+00 1.61 E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 l MN 54 0.00E+00 3.91 E+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 1.11 E+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

~Z 5 ----~ I~ ~ ~---

0

~ ~

00~-- I2

-~

- - 6 RB-86 0.00E+00 2.23E+10 1.10E+10 0.00E+00 0.00E+00 0.00E+00 5.70E+08

- ~ ~~~~ ~~ ---

0-~-

~ ~ - - ~ ~

12 00-~ 0 0- E-Y-91 7.34E+04 0.00E+00 1.95E+03 0.00E+00 0.00E+00 0.00E+00 5.26E+06 s-5

--~~~

I - ~~

0-

-~ ~- ~ - ~ ~

0

- -7 RU-103 8.68E+03 0.00E+00 2.90E+03 0.00E+00 1.81 E+04 0.00E+00 1.06E+05 RU-106 1.91 E+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 1.51 E+08 5.05E+07 2.04E+07 5.08E+07 0.00E+00 0.00E+00 7.19E+07 TE-127M 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 1-131 2.72E+09 3.21 E+09 1.41 E+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 6.81 E+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 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 63 3918D. DOC

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

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.4.2 " age 1 of 1 Pathway Dose Factors, Ri

! AGE GROUP: CHILD PATHWAY: GRASS-COW-MILK NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 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 CR 51 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 MN-54 0.00E+00 2.10E+07 5.59E+06 0.00E+00 5.89E+06 0.00E+00 1.76E+07 FE-55 1.12E+08 5.94E+07 1.84E+07 0.00E+00 0.00E+00 3.36E+07 1.10E+07 i FE-59 1.20E+08 1.95E+08 9.70E+07 0.00E+00 0.00E+00 5.65E+07 2.03E+08 l CO-58 0.00E+00 1.21 E+07 3.72E+07 0.00E+00 0.00E+00 0.00E+00 7.08E407 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 i 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 SR-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 1.51 E+09 Y-91 3.91 E+04 0.00E+00 1.05E+03 0.00E+00 0.00E+00 0.00E+00 5.21 E+06 ZR-95 3.84E+03 8.43E+02 7.51 E+02 0.00E+00 1.21E+03 0.00E+00 8.80E+05 i

NB-95 3.18E+05 1.24E+05 8.86E+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 1.11 E+05 l

RU-106 9.25E+04 0.00E+00 1.15E+04 0.00E+00 1.25E+05 0.00E+00 1.44E+06 E 125 .0 + 06 + 00 E + .

TE-127M 2.08E+08 5.61 E+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 3.31 E+08 l-131 1.31 E+09 1.31 E+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 2.01 E+08 l

i CS-136 1.01 E+09 2.79E+09 1.80E+09 0.00E+00 1.49E+09 2.21 E+08 9.80E+07 i 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 4.45E+02 3.61 E+02 2.79E+01 0.00E+00 1.98E+02 0.00E+00 5.71 E+05 1

64 39180.D0C

Number sam n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Title Revison No.

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.4.3 Page 1 of 1 Pathway Dose Factors, Rn AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK

_____7_

j NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI l H-3 0.00E+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 l 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 FE-55 4.46E+07 3.16E+07 7.37E+06 0.00E+00 0.00E+00 2.01 F ' 07 1.37E+07 FE 59 5.19E+07 1.21 E+08 4.68E+07 0.00E+00 0.00E+00 3.81 eu 2.86E+08 CO-58 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00ii+00 1.10E+08 CO-60 0.00E+00 2.78E+07 6.27E+07 0.00E+00 0.00E+00 0.0ut'mc 3.62E+08 ,

NI-63 1.18E+10 8.36E+08 4.01 E+08 0.00E+00 0.00E+00 0.00E; 133E+08 ZN-65 2.11 E+09 7.32E+09 3.42E+09 0.00E+00 4.69E+00 0.00Etub 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 l l Y-91 1.58E+04 0.00E+00 4.24 E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06 I

~~~ ~ ~~~ ~~~ ~ ~ ~ ~ - ~

~sB-5 0 ~~~ ~0 60~~~ 60~~~ ~4 RU-103 1.81 E+03 0.00E+00 7.75E+02 0.00E+00 6.39E+03 0.00E+00 1.51 E+05 RU-106 3.76E+04 0.00E+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1.80E+06 l AG-110M 9.64E+07 9.12E+07 5.55E+07 0.00E+00 1.74E+08 0.00E+00 2.56E+10 i 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 2.01 E+07 3.42E+08 0.00E+00 2.11 E+08 TE-129M 1.10E+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 0.00E+00 4.14E+08 1-131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 0.00E+00 1.49E+08

~~ ~ ~ ~~-~~ ~ ~ ~ ~ ~~

5-34-~~~ 0~ ~~~~6 0 ~~~ 8 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 6.21 E+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 4.01 E+04 7.51 E+07 CE-141 8.89E+03 5.94E+03 6.82E+02 0.(,0E+00 2.80E+03 0.00E+00 1.70E+07 l CE-144 6.59E+05 2.73E+05 3.54E+04 0.00E+00 1.63E+05 0.00E+00 1.66E+08 l PR-143 2.90E+02 1.16E+02 1.44E+01 0.00E+00 6.73E+01 0.00E+00 9.55E+05 ND-147 1.81 E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7.12E+05 l

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S en Ndar Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 l TIO Recsson No, SNEC Facility Offsite Dose Calculation Manual 0 1 1 1

TABLE 5.4.4 Page 1 of 1 1

Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK j l 1

~-~

3 ~~~0 E 0'0- ~ ~ ~7 6 E 02- - - - ~72 02~ ~ ~ 7~ ~ ~ ~ ~ ~7 02-~76- 62-~7 ~ 2 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 0.00E+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 2.51 E+07 1.73E+07 4.04 E+06 0.00E+00 0.00E+00 9.66E+06 9.93E+06

-~~ ~ ~~~ ~~ ~~

C6-58 -~~~~ 0~~~ 67' ~~ ~ 0 ~ ~ ~ ~ 54 CO-60 0.00E+00 1.64E+07 3.61 E+07 0.00E+00 0.00E+00 0.00E+00 3.08E+08 l N!-63 6.72E+09 4.65E+08 2.25 E+08 0.00E+00 0.00E+00 0.00E+00 9.71 E+07 ZN 65 1.37E+09 4.36E+09 1.97E+09 0.00E+00 2.91 E+09 0.00E+00 2.74E+09 RB 86 0.00E+00 2.59E+09 1.21 E+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 9.41 E+02 3.02E+02 2.04E+02 0.00E+00 4.74E+02 0.00E+00 9.57E+05 l NB-95 8.24E+04 4.58E+04 2.46E+04 0.00E+00 4.53E+04 0.00E+00 2.78E+08 l

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 i AG-110M 5.81E+07 5.38E+07 3.19E+07 0.00E+00 1.06E+08 0.00E+00 2.19E+10 1 l

TE-125M 1.63E+07 5.89E+06 2.18E+06 4.89E+06 6.61E+07 0.00E+00 6.49E+07 l TE-127M 4.57E+07 1.63E+07 5.57E+06 1.17E+07 1.86E+08 0.00E+00 1.53E+08 TE-129M 6.01 E+07 2.24E+07 9.51 E+06 2.06E+07 2.51 E+08 0.00E+00 3.02E+08 l

l-131 2.96E+08 4.23E+08 2.42E+08 1.39E+11 7.25E+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 CS-134 5.64E+09 1.34 E+10 1.10E+10 0.00E400 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 1.01 E+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 CE-141 4.84E+03 3.27E+03 3.71 E+02 0.00E+00 1.52E+03 0.00E+00 1.25E+07 CE-144 3.57E+05 1.49E+05 1.92E+04 0.00E+00 8.85E+04 0.00E+00 1.21 E+08

, PR-143 1.57E+02 6.32E+01 7.81 E+00 0.00E+00 3.65E+01 0.00E+00 6.90E+05 ND-147 9.40E+01 109E+02 6.50E+00 0.00E+00 6.35E+01 0.00E+00 5.22E+05 l

66 39180.00C l

WumDer i 1

Saxt n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual f 6575-PLN-4542.08 .

Title Revision No. )

SNEC Facility Offsite Dose Calculation Manual 0  ;

I TABLE 5.5.1 Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK i

ORGAN DOSE FACTORS: m' - mrem / year _perfi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 CR-51 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 l FE-55 1.76E+06 1.14E+06 3.03E+05 0.00E+00 0.00E+00 5.55E+05 1.44E+05 )

FE 59 2.92E+06 5.10E+06 2.01 E+06 0.00E+00 0.00E+00 1.51 E+06 2.44E+06 1 CO-58 0.00E+00 2.91 E+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 l 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 1.11 E+09 0.00E+00 1.93E+09 l RB-86 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 0.00E+00 2.34E+02 0.00E+00 0.00E+00 0.00E+00 6.31 E+05 ZR-95 8.17E+02 1.99E+02 1.41 E+02 0.00E+00 2.15E+02 0.00E+00 9.91 E+04 NB-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 1.81 E+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 l-131 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 0.00E+00 1.37E+08 ,

l l133 4.36E+07 6.35E+07 1.86E+07 1.15E+10 7.46E+07 0.00E+00 1.07E+07 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 1.81 E+ 1'i 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 i

1 67 3918D. DOC

1 Number Saxton Nu&ar Experimental Co poration SAXTON NUCLEAR Facility Policy and Procedure Manual i

6575-PLN-4542.08 l Titt2 Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 i l TABLE 5.5.2 Page 1 of 1 I l Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-GOAT-MILK l ORGAN DOSE FACTORS: m - mrern/yearper uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI l H-3 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

~~ ~~~ ~

65- ~ ~ 60 - ~~I

~ ~ ~ ~ ~ ~ ~ ~~

5 ~~~~ 0 7 0.

FE-55 1.45E+06 7.71 E+05 2.39E+05 0.00E+00 0.00E+00 4.36E+05 1.43E+05 1 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

~~~ ~ ~ ~~~ - ~ ~ ~ ~ ~ ~ ~ ~~~

~Z 5 4 9~~~ 0 ~~ ~ -0

~ ~ ~ ~8 8 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 1.11 E+04 0.00E+00 1.38E+03 0.00E+00 1.50E+04 0.00E+00 1.73E+05 AG-110M 2.51 E+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 l 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 l 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 6.01 E+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 1.41 E+07 1.24E+04 8.23E+05 0.00E+00 4.02E+03 7.37E+03 7.15E+06 CE-141 2.63E+03 1.31 E+03 1.95E+02 0.00E+00 5.74E+02 0.00E+00 1.63E+06 l CE-144 1.95E+05 6.11 E+04 1.04E+04 0.00E+00 3.38E+04 0.00E+00 1.59E+07 l PR-143 8.61 E+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 l

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Number 1 SaMon Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 TitD Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 1

TABLE 5.5.3 Page 1 of 1  !

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Pathway Dose Factors, Ri l AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK l

~ ~~ ~~~

l ORGAN DOSE FACTORS; mM7e~m/yha_r p~er ~Cl/sec ________

l

~

53

~~~

~~~0 0 E OT-~2 0 E 03~ ~ ~ ~2 04 03~~~2 ~ ~ ~ ~2 03 20~ 63~~~2 3~~ 1 C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 l CR-51 0.00E+00 0.00E+00 5.99E+03 3.33E+03 1.31 E+03 8.55E+03 1.01 E+06 MN-54 0.00E+00 1.68E+06 3.34E+05 0.00E+00 5.02E+05 0.00E+00 3.45E+06 .

FE-55 5.79E+05 4.11 E+05 9.58E+04 0.00E+00 0.00E+00 2.61 E+05 1.78E+05 I

, FE 59 6.74E+05 1.57E+06 6.08E+05 0.00E+00 0.00E+00 4.96E+05 3.72E+06 l CO-58 0.00E+00 9.53E+05 2.20E+06 0.00E+00 0.00E+00 0.00E+00 1.31 E+07  !

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 l ZN-65 2.53E+08 8.78E+08 4.10E+08 0.00E+00 5.62E+08 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 i

SR-89 5.62E+09 0.00E+00 1.61 E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+08 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 NS-95 1.69E+04 9.38E+03 5.16E+03 0.0C.i+00 9.09E+03 0.00E+00 4.01 E+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 l 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 1.01 E+06 0.00E+00 0.00E+00 1.06E+07 l TE-127M 1.01 E+07 3.59E+06 1.20E+06 2.41 E+06 4.11 E+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 i 6.45E+08 9.03E+08 4.85E+08 1.56E+09 0.00E+00 1-131 2.64E+11 1.79E+08 l133 8.49E+06 1.44E+07 4.40E+06 2.01 E+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 8.41 E+09 8.62E+08 l 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 4.81 E+03 9.01 E+06 CE-141 1.07E+03 7.12E+02 8.18E+01 0.00E+00 3.35E+02 0.00E+00 2.04E+06

)

CE-144 7.90E+04 3.27E+04 4.25E+03 0.00E+00 1.95E+04 0.00E+00 1.99E+07 )

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 I

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69 3918D. DOC

Number I l

S x1 n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 1

6575-PLN-4542.08 l Title Revtsson No.

l SNEC Facility Offsite Dose Calculation Manual 0 1

TABLE 5.5.4 Page 1 of 1 l 1

Pathway Dose Factors, Ri j I i AGE GROUP

ADULT PATHWAY: GRASS-GOAT-MILK l

___7_

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG . GI-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 l MN-54 0.00E+00 1.01 E+06 1.93E+05 0.00E+00 3.01 E+05 0.00E+00 3.10E+06 l FE-55 3.27E+05 2.26E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+05 1.30E+05 l 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 l

NI-63 8.08E+08 5.60E+07 2.71 E+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 3.51 E+08 0.00E +00 3.30E+08 RB-86 0.00E+00 3.12E+08 1.45E+08 0.00E+00 0.00E+00 0.00E+00 6.14E+07 l 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 2.41 E+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 l 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 l 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 1.41 E+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 i l l-133 4.65E+06 8.10E+06 2.47E+06 1.19E+09 1.41 E+07 0.00E+00 7.28E+06 l CS-134 1.70E+10 4.04E+10 3.30E+10 0.00E+00 1.31 E+10 4.34E+09 7.07E+08 l 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 1.51 E+06 CE-144 4.30E+04 1.80E+04 2.31 E+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

}

e 70 3918D. DOC

l l

Number Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Faciiity Poiicy and Procecure Manuai es7s.PLN-4542.08 TRie Revision No SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.6.1 Page 1 of 1 i l

l Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT

____7_

NUCLlDE BONE LIVER T. BODY THYROID 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 j CO-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,

i 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-86 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 NB-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+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 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 l-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 C'E-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 l

l l

71 39180. DOC

Numtw S xt n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575 PLN-4542.08 Tdle Revision No.

SNEC Facility Offsite Dose Calculation Manual 0 l

TABLE 5.6.2 Page 1 of 1 1

Pathway Dose Factors, Ri l AGE GROUP: CHILD PATHWAY: GRASS-COW-MEAT g ____

, 7

! 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 C-14 3.84E+08 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 CR-51 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 8.01 E+06 2.13E+06 0.00E+00 2.25E+06 0.00E+00 6.73E+06 I FE-55 4.57E+08 2.43E+08 7.52E+07 0.00E+00 0.00E+00 1.37E+08 4.49E+07 I

- ~ ~ ~ ~

h-58-~~-~ ~ 0 ~

~~- ~ ~ ~ ~~~~

00 7 03 7~~ 0 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 6.31 E+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 3.71 E+07 SR-89 4.82E+08 0.00E+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07 l

SR-90 1.04E+10 0.00E+00 2.64E+09 0.00E+00 0.00E+00 0.00E+00 1.40E+08 l 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 5.21 E+05 0.00E+00 8.38E+05 0.00E+00 6.11 E+08 NB-95 3.10E+06 1.21 E+06 8.63E+05 0.00E+00 1.13E+06 0.00E+00 2.23E+09 RU-103 1.55E+08 0.00E+00 5.96E+07 0.00E+00 3.90E+08 0.00E+00 4.01 E+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 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 1.31E+02 1.18E+10 0.00E+00 2.85E-01 CS-134 9.23E+08 1.51 E+09 3.19E+08 0.00E+00 4.69E+08 1.68E+08 8.16E+06 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 BA-140 4.42E+07 3.87E+04 2.58E+06 0.00E+00 1.26E+04 2.31E+04 2.24E+07 CE-141 2.22E+04 1.11 E+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 ND-147 1.17E+04 9.48E+03 7.34E+02 0.00E+00 5.20E+03 0.00E+00 1.50E+07 72 39180 DOC l

l

4 Number S 4 n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.03 TED Revisen No.

SNEC Facility Offsite Dose Calculation Manual 0 )

l TABLE 5.6.3 Page 1 of 1 l l

Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT l NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG Gl-LLI I H-3 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 00---

~~ --- - - - ~-~~ ~~~

Ch-58-~~~-0 0 E-CO-60 0.00E+00 5.83E+07 1.31 E+08 0.00E+00 0.00E+00 0.00E+00 7.60E+08 Ni-63 1.52E+10 1.07E+09 5.15E+08 0.00E+00 0.00E+00 0.00E+00 1.71 E+08 ZN-65 2.50E+08 8.68E+08 4.05E+08 0.00E+00 5.56E+08 0.00E+00 3.68E+08 i RB-86 0.00E+00 4.06E+08 1.91 E+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 j 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 3.91 E+08 ZR-95 1.50E+06 4.73E+05 3.25E+05 0.00E+00 6.95E+05 0.00E+00 1.09E+09 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 9.41 E+08 3.34E+08 1.12E+08 2.24E+08 3.81 E+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 S- 34-- -52 08-~~12 09-- 71E 8-~~ 0 ~~~~3 08-~~ ~~~153E 67-~

CS-136 9.43E+06 3.71 E+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 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 3.71 E+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 ND-147 6.23E+04 6.78E+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 i

73 3918D. DOC

Number S 4 n Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 TC Revtsion No.

l SNEC Facility Offsite Dose Calculation Manual 0 l

l TABLE 5.6.4 Page 1 of 1 )

Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT l

l NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI l 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 2.81 E+07 FE-55 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 l 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 1.41 E+09 Ni-63 1.89E+10 1.31 E+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 RB-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 l ZR-95 1.87E+06 6.01 E+05 4.07E+05 0.00E+00 9.43E+05 0.00E+00 1.90E+09 NB-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 5.41 E+09 0.00E+00 1.81 E+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 l-133 3.68E-01 6.41 E-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 1.21 E+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 2.31 E+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 9.51 E+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 i

74 3918D. DOC

Number Sa4 n Nuclear Experimental Corporation l

i SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Tea Revision No, 1

SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.7.1 Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: VEGETATION l l

NUCLIDE BONE LIVER T. BODY THYROID 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 l 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 i RB-86 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 NB-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+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 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 l 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 o

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.7.2 Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: VEGETATION NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG Gl-LLI H-3 0.00E+00 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+ 03 4.02E+03 C-14 8.89E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08

~ ~ ~ - --- ~~~ ~ - ~~

--~

8 0 - ----1 0 00----

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 3.21 E+08 0.00E+00 0.00E+00 1.87E+08 6.71 E+08 1 CO-58 0.00E+00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 I 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 2.11 E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+08 l 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 4.51 E+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 l SR-90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 l 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 1.21 E+06 0.00E+00 8.85E+08 NB-95 4.11 E+05 1.60E+05 1.14E+05 0.00E+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 1.01 E+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 l TE-125M 3.51 E+08 9.50E+07 4.67E+07 9.84E+07 0.00E+00 0.00E'+00 3.38E+08 l TE-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00E+00 1.07E+09 l 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 8.18 E+07 4.76E+10 2.36E+08 0.00E+00 1.28E+07 l133 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 l CS-136 8.28E+07 2.28E+08 1.47E+08 0.00E+00 1.21 E+08 1.81 E+07 8.00E+06 l CS-137 l 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 1.41 E+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 2.21 E+07 0.00E+00 1.04E+10 PR-143 1.45E+05 4.36E+04 7.21 E+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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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.7.3 Page 1 of 1 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: VEGETATION ORGAN DOSE FACTORS; m'- mrem /yearper Cl/sec NUCLIDE BONE LIVER T. BODY THYROID KlDNEY 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

~ ~ ~~

-5 ~~~~

~~~~ ~~~~ ~~~

0 ~~ E 0 8 i ~~ 3 8 FE-55 3.26E+08 2.31 E+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 9.91 E+08 CO-58 0.00E+00 4.36E+07 1.01 E+08 0.00E+00 0.00E+00 0.00E+00 6.01 E+08 CO 60 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 i

NI-63 1.61 E+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 0.00F.+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 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 7.51 E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11 E+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

NB-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 2.41 E+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 1.31 E+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 l-131 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 l-133 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 9.41 E+07 1.48E+07 1.39E+07 CS-137 1.01 E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 BA-140 1.39E+08 1.71 E+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 5.41E+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 2.31 E+04 0.00E+00 1.42E+08 77 3918D DOC

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SNEC Facility Offsite Dose Calculation Manual 0 TABLE 5.7.4 Page 1 of 1 l

Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: VEGETATION l

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 l

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 4.64 E+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 9.31 E+07 0.00E+00 9.58E+08 i FE-55 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31 E+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 ,

~Z 5 ~~~~

~ ~ ~ ~

~~~ 5 ~~~~0 8 ~0 0~ I ~~

0 0~ ~~~6

- ~

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 2.51 E+08 9.37E+07 3.97E+07 8.63E+07 1.05E+09 0.00E+00 1.26E+09 l131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 0.00E+00 3.05E+07 l-133 2.09E+06 3.63E+06 1.11 E+06 5.34E+08 6.33E+06 0.00E+00 3.26E+06 1 CS-134 4.67E+09 1.11 E+10 9.08E+09 0.00E+00 3.59E+09 1.19E+09 1.94E+08 i 1.92E+07 CS-136 4.28E+07 1.69E+08 1.22E+08 0.00E+00 9.41E+07 1.29E+07 CS-137 6.36E+09 8.70E+09 5.70E+09 0.00E+00 2.95E+09 9.81 E+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 1.51 E+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 2.51E+04 3.10E+03 0.00E+00 1.45E+ 04 ~ 0.00E+00 2.74E+08 ND-147 3.34E+04 3.85E+04 2.31 E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 l

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SNEC Facility Offsite Dose Calculation Manual 0 6.0 EFFLUENT TOTAL DOSE ASSESSMENT i

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 shoi! De 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 realindividual 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) monitoa.

7.0 PART ll REFERENCES

1. EPRI NP-3840, RP 1560-3 Final Report,

• Environmental Radiation Doses From Difficult-To-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. 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 5

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 cf Federal Regulations. " Energy'

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, l November 1979 l

13. Title 40, Code of Federal Regulations," Protection of Environment" 79 39180 DOC

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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" I

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SNEC Facility Offsite Dose Calculation Manual 0 l

l PART lil REPORTING REQUIREMENTS i

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SNEC Facility Offsite Dose Calculation Manual l 0  !

l l 1.0 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT i 1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the ,

i previous calendar year shall be submitted to the Commission prior to May 1 of each year. '

l 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, ana with previous environmental monitoring reports, and l

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. I 1.3 The Annual Radiological Environmental Operating Reports shallinclude the summanzed tabulated results of analysis of all radiological environmental samples and environmental radiation measurements required by Part I Table 2.3-1 taken during the period pursuant to the locations

! specified in the tables and figures in this ODCM, as well as summarized and tabulated results of ,

I these analyses and measurements in a format similar to the table in the Radiological Assessment  !

l Branch Technical Position, Revision 1, November 1979. In the event that some individual results i

! are not available for inclusion with the report, the report shall be subrritted explaining the reasons l

! for the missing results. The missing data shall be submitted as soon as possible in a l su;plementary report.

1.4 The repc s shall also include the following: a summary description of the radiological environments monitoring program; a map (s) of all sampling locations keyed to a table giving distances and directions from 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 !, Table 2.3-1; discussion of all the l required analyses in which the LLD required by Part I, 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 l previous 12 months of operation shall be su'omitted prior to May 1.

2.2 The following information shall be includea in both Radioactive Effluent Release Reports to be submitted each year:

The Radioactive Effluent Release Reports shallinclude 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),

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

l SNEC Facility Offsite Dose Calculation Manual 0

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

l

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

l f. solidification agent (e.g., cement).

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.

1 2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or i 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 OPERABLE status within 30 days per ODCM Part I Control 2.1.2.b.

i l 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 assumptions used in making these assessments shall be included in these reports. The assessment of radiation doses shall be performed in accordance with this ODCM.

2.8 The Radioactive Effluent Release Report shallinclude 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 l 10CFR20.1301.

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

3.0 PART lli REFERENCES 3.1 Radiological Assessment Branch Technical Position on Environmental Monitonng, Revision 1, November 1979 l 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-Cooied Nuclear Power Plants," Revision 1, June 1974 SNEC Facility Technical Specifications, attached to Facility Operating License No. DPR-4 3.3 i 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 j October 1977 83 3918D. DOC I

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SNEC Facility Offsite Dose Calculation Manual 0 3.6 Title 10, Code of Federal Regulations, " Energy" 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 i

! 3.8 Regulatory Guide 1.112. " Calculation of Releases of Radioactive Materials in Gaseous and Liquid l Effluents from Light-Water-Cooled Power Reactors," Revision O-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 l 3.10 RAF 6612-96-007, " Maximum Offsite Dose from Release of Saxton Pipe Tunnel Water" f

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1 S 4 n Nuclear Spenmental Corporadon SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 Trde Revision No, i SNEC Facility Offsite Dose Calculation Manual 0 l

APPENDIX A l l

l Pi- Pathway Dose Rate Parameter Pi (inhalation) = k'(BR)DFAl (Eq A-1)

Where:

P i = the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation 3

pathway, in mrem /yr per microcune/m 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 /pCi). Values are taken from Table E-10, Reg. Guide 1.109 (Rev.1).

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

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

NOTE l 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 Dose Calculation Manual 0 i

APPENDIX B Ri -Inhalation Pathway Dose Factor Ri = k'(BR)(DFA ,a,o)(mremi / yr permicrocurie / m3) (Eq B-1)

I 1 l Where:

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

DFA4...o= the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrem /pCl. 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:

1 l

R=

i (1.4E9) (DFAi ,a,c) infant (ODCM Part ll Table 5.2.1)

R=

i (3.7E9) (DFA i.a.o) child (ODCM Part 11 Table 5.2.2)

R=

i (8.0E9) (DFA i.a.c) teen and adult (ODCM Part 11 Tables 5.2.3 and 5.2.4)

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SNEC Facility Offsite Dose Calculation Manual 0 APPENDIX C Ri- Ground Plane Pathway Dose Factor R i = k 'k"(SF)(DFG l)[(1 - e - ht) / A i ] (Eq C-1)

Where:

k' = conversion factor,1E6 pCl/ microcurie k" = conversion factor,8760 hr/yr A.i= 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 2

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

Reference ODCM Part ll Table 5.3.1 l 1

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l SNEC Facility Offsite Dose Calculation Manual 0 l

APPENDIX D Page 1 of 2 .

1 l

Ri- Grass Cow-Milk Pathway Dose Factor R i = k '[(Q, x U,p) / ( A] + %)] x (F m) x (r) x (DFL ,i s, o) x

1. M

[((fpx f )s / Y )p + ((1 - f xp f ) se - A 'h) l / Ys) e - A ity 1

Where: l k' = conversion factor,1E6 pCl/ microcurie Qu = cow consumption rate,50 kg/ day, (Reg. Guide 1.109, Rev.1) goat consumption rate. 6 kg/ day, (Reg. Guide 1.109, Rev.1, Table E-2)

Uap = Receptor's milk consumption rate; 330, 330,400,310 liters /yr for infant, child teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev.1) 2 Yp= agricultural productivity by unit area of pasture feed grass,0.7 kg/m (NUREG-0133) 2 Ys= agricultural productivity by unit area of stored feed 2.0 kg/m (NUREG-0133) l 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 radiciodine (Table E-15, Reg. Guide 1.109 Rev.1) l DFLi,..o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1)

Ai = decay constant for the ith radionuclide, sec^

^7 d L = decay constant for weathering,5.73 x 10 sec (NUREG-0133); based on a 14 day half life l

5 l tr = 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 8

I tri = 7.78 x 10 sec, the transport time from pasture to harvest to cow to milk to receptor (Table E 15, Reg. Guida 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 4

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SNEC Facility Offsite Dose Calculation Manual 0 APPENDIX D Page 2 of 2 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore.

Riis based on (X/Q):

R C t, a, o = k ' k" ' Fm Qp. UAP DFL t ,a, o(.75 [.5 / H]) (Eq D-2)

Where:-

k"' = 1E3 grams /kg 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)

DFLt ,... = 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.

~

NOTE Goat-milk pathway factor, R,, will be computed usir.; 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 ll Tables 5.4.1 to 5.4.4 l

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SNEC Facility Offsite Dose Calculation Manual 0 APPENDIX E Page 1 of 2 Ri - Cow-Meat Pathway Dose Factor R i = k '[(Q, x U,) / (1, + %)] x (Fj ) x (r) x (DFL,,,, o) x (Eq E-1)

[((fp x f,) \ Yp) + ((1 - fp f,) e - th) / Y,] x e - A ity Where:

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

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

Uxp = Receptor's meat consumption rate: 0,41,65,110 kglyr for infant child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev.1)

Fr = the stable elernent transfer coefficients, days /kg (Table E-1, Reg. Guide 1.109, Rev.1) r = fraction of deoosited activity retained in cow's feed grass,0.2 f 3r particulates,1.0 for radioiodine (Table E-11, Reg. Guide 1.109, Rev.1)

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

Ai = decay constant for the radionuclide i, sec^

Aw= decay constant for weathenng,5.73 x 10'7 sec^ (NUREG-0133), based on a 14 day half life e

tr = 1.73 x 10 sec. the transport time from pasture to receptor (NUREG-0133) th= 7.78 x 10'sec. the transport time from crop to receptor (NUREG-0133) 2 Yp= agricultural productivity by unit area of pasture feed grass,0.7 kg/m (NUREG-0133) 2 Y, = agricultural productivity by unit area of stored feed,2.0 kg/m (NUREG-0133) fp= 1.0, the fraction of the year that the cow is on pasture

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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, Riis based on (X/Q):

R,,,,, = k 'k'" F,Q,Uap(DFL,,,,o)x 0.75 x(0.5 / H]) (Eq E-2)

Where:

All terms are as defined above and in Appendix D.

Reference:

ODCM Part II, Tables 5.6.1 to 5.6.4 0

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SNEC Facility Offsite Dose Calculation Manual 0 l APPENDIX F Ri -Vegetation Pathway Dose Factor l R i = k ' x [r / (Yy / A i + Aw))] x (DFLi ,a,o) x [(U',)t f e - li tt+US AI 9e- Atih) (Eq F-1) 1 Where:

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

U'a = the consumption rate of fresh leafy vegetation. O,26,42,64 kg/yr for infant, child, teenager, or l adult age groups, respectively (Reg. Guide 1.109, Rev.1) l s

l UA= 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) ft = the fraction of the annualintake of fresh leafy vegetation grown locally, = 1.0 (NUREG-0133) i fg= the fraction of the stored vegetation grown locally = 0.76 (NUREG-0133) i t L= 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)] '

l l tn = 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)]

i 2

l Yv = 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, Riis based on (X/Q)

R t, a, o = k ' k" ' [U'A Lf + U S A Ig](DFL ,t a, o)(.75 [.5 / H]) (Eq F-2)

Where:

All terms are as defined above and in Appenda D.

Reference:

ODCM Part 11, Tables 5.7.1 to 5.7.4 i

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SaMon Nuclear Expenmental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual 6575-PLN-4542.08 '

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l SNEC Facility Offsite Dose Calculation Manual 0 APPENDIX A-F REFERENCES Page 1 of 4 Parameters Used in Dose Factor Calculations )

i Origin of Value I Table in l Section of Site- I Parameter Value R.G.1.109  ! NUREG-0133 Specific l

"* For Pi "" l DFAi Each radionuclide E-9 Note 1 l

3 BR 3700 m /yr(child) E-5 l l t

• "For Ri(Vegetation)"* l r Each element type E-1 I 2

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

U' Each age group E5 l ft 1.0 5.3.1.5 tt 8.6E+4 seconds E-15 U.6 Each age group E-5 yq 0.76 5.3.1.5 th 5.18E+6 seconds E-15 l H 8.0 grams /kg i 5.2.1.3 _

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• "For Ri (Inhalation)"* I i BR Each age group E-5  !

l DFAi Each age group and nuclide E-7 thru E-10 i Note 1 l

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