ML20063L962

Rev 0 to DVP-01.02, Radiological Effluent Controls & Odcm

ML20063L962
Person / Time
Site:	FitzPatrick
Issue date:	12/28/1993
From:	Sipp J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20063L959	List: JAFP-94-0116, Forwards Ja FitzPatrick Nuclear Power Plant Effluent & Waste Disposal Semiannual Rept Jul-Dec 1993 & Rev 0 to DVP-01.02, Radiological Effluent Controls & Odcm ML20063L960 ML20063L962
References
DVP-01.02, DVP-1.02, NUDOCS 9403080151
Download: ML20063L962 (317)

Text

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l NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l

~" DOCUMENTS AND VENDOR PROCEDURES i RADIOLOGICAL EFFLUENT CCNTROL8 AND OFF8ITE DO8E CALCULATION MANUAL

• DVP-01.02 REVISION 0 i

4 REVIEWED BY: PLANT OPERATING REVIEW COMMITTEE MEETING NO.93-170 DATE 12/22/93 APPROVED BY: NO49 J DATE / M .3 RE NSIBLE PROCEDURE OWNER APPROVED BY: /NMs [- DATE / kk)

/ RESIDEN'f MANAGER i,

December 28, 1993 EFFECTIVE DATE:

FIRST ISSUE N FULL REVISION O Jt;ITED REVISION O

• INFORMATIONAL USE *

• TSR *

• TECH

• A

)

PERIODIC REVIEW DUE DATE December 23, 1995 9403080151 940224 PDR ADOCK 05000333 R PbR J

PROCEDURE

SUMMARY

SHEET REV.NO. REASON FOR CHANGE 0 1) New procedure number and title - Per AP-02.01 and procedure upgrade.

2) Procedural requirements of the RETS were added to part one of l the ODCM in response to NRC Generic Letter 89-01.

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3) Incorporate OA Audit 805 recommendations. ACTS #8617 and

1. 8618.

4) Updated meteorological dispersion data to include 1985-1992, and Appendix "C" Tables.

5) Revised effective dose factor in Appendix "E" for 1985-1991 release data.

l l 8) Revised release rate calculation for gaseous effluents based on new meteorological data and revise effective dose factors.

7) Added methodologies for intermittent gaseous releases and non-routine liquid releases.

8) Environmental sample location in Appendix "H" revised to reflect latest land use census.

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l TABLE OF CONTENTS PARTI l

RADIOLOGICAL EFFLUENT CONTROLS (RECS)

SECTION PAGE .

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1.0 INTRODUCTION

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1.1 Purpose 1 l

1.2 Definitions 2 2.0 LlOUID EFFLUENTS 4 2.1 Uquid Effluent Monitors 4 2.2 Concentration of Uquid Effluents 9 2.3 Dose From Uquid Effluents 14 2.4 Uquid Radioactive Waste Treatment System Operations 16 3.0 GASEOUS EFFLUENTS 18 l

3 18 l(d l'

3.1 Gaseous Effluent Monitors l 3.2 Gaseous Dose Rates 23 3.3 Air Dose, Noble Gases 29 3.4 Dose Due to lodine-131, lodine-133, Tritium and Radionuclides in Particulate Form 31 3.5 Offgas Treatment System 33 4.0 TOTAL DOSE 35 4.1 Total Dose From Uranium Fuel Cycle 35 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 39 l

5.1 Monitoring Program 39 5.2 Land Use Census Program 49 5.3 Interlaboratory Comparison Program 51 U

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Ust of Tables l

l l Paae 2.1-1 Radioactive Uquid Effluent Monitoring instrumentation 6 O

2.1-2 Minimum Test and Calibration Frequency for Radiation 7 Monitoring Systems 2.2-1 Radioactive Uquid Waste Sampling and Analysis Program 11 3.1-1 Radiation Monitoring Systems that initiate and/or Isolate Systems 20 3.1-2 Minimum Test and Calibration Frequency for Radiation 21 Monitoring Systems 3.2-1 Radioactive Gaseous Waste Sampling and Analysis Program 2S 5.1-1 Operational Radiological Environmental Monitoring Program 42 5.1-2 Reporting Level for Radioactmty Concentrations in Environemntal 46 l

Samples Reporting Levels 5.1-3 Detection Capabilities for Environmental Sample Analysis - 47 Lower Umit of Detection O

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Ust of Floures Pace 4.1 1 Site Boundary Map O

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TABLE OF CONTENTS PART ll - ODCM SECTION PAGE h l

1.0 INTRODUCTION

1 1.1 Purpose 1 l

1.2 Methodologies and Parameters 1 i

i 2.0 DEFINITIONS 2 3.0 LIQUID EFFLUENT METHODOLOGY 6 3.1 Applicable Site Characteristics 6 l 3.2 10 CFR 20, MPC Umits-Determination of The Fraction (FJ of Release Umits and Minimum Required Dilution 6 l

3.3 Determination of Setpoints for Radioactive Uquid Effluent Monitors 10 3.4 Dose Determination for Radioactive Uquid Effluents 14 3.5 Dose Projections - Determination of Need to Operate Uquid Radwaste Treatment system 26 h

4.0 GASEOUS EFFLUENT METHODOLOGY 32 4.1 Gaseous Waste Streams 32 4.2 Data Requirements for Gaseous Effluent Calculations 32 4.3 Instantaneous Release Rate and Set Point Determination 33 4.4 Dose Determination for Radioactive Gaseous Effluents 48 4.5 Dose Projections - Determination of Need to Operate Offgas Radwaste Treatment System 75 5.0 40 CFR 190 DOSE EVALUATION 77 5.1 Evaluation Bases 77  ;

5.2 Doses From Uquid Releases 78 O

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SECTION PAGE 5.3 Doses From Atmospheric Releases 78 5.4 Doses From Direct Radiation 78

6.0 REFERENCES

79 7.0 ATTACHMENTS 7.1 Appendix A, Uquid Dose Calculation Data A-1 7.2 Appendix B, Gaseous Dose Calculated Data B-1 7.3 Appendix C, Meteorological Data C-1 7.4 Appendix D, Umited Analysis Dose Assessment for Uquid Radioactive Effluents D-1 7.5 Appendix E, Technical Bases for Effective Dose Factors E-1 7.6 Appendix F, Effluent Monitor Sampling Locations and Descriptions F-1 7.7 Appendix G, Unrestricted Area Map G-1  ;

7.8 Appendix H, Environmental Sample Locations H-1 7.9 Appendix 1, Summari Tables 1-1 1

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DVP-01.02 RADIOLOGICAL EFFLUENT CONTROLS AND OFFSITE DOSE CALCULATION MANUAL

• g PARTI RADIOLOGICAL EFFLUENT CONTROLS (REC)

1.0 INTRODUCTION

1.1 Purpose This Radioactive Effluent Controls Program (REC) was added to the Offsite Dose Calculation Manual (ODCM) in response to NRC generic letter 89-01. The program intent is to conform with 10 CFR 50.36a fcr the control of radioactive effluents and for maintaining the doses to members of the public as low as reasonably achievable. Generic letter 89-01 described the NRC's determination that the Radiological Effluent Technical Specification (RETS) should be simplified to improve Technical Specifications (TS) by implementing programmatic controls into the TS and procedural details into the ODCM.

The REC program relocates the procedural details of the RETS into the ODCM. The RETS provide the current requirements for effluent controls. The REC program may provide effluent control after the plant technical specifications are ammended to h

relocate the programmatic and reporting requirements of the RETS into the Administrative Controls section of the Technical Specification.

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Rev. No. O Page 1 of REC I

1.2 Definitions

. A. Dose Eauivalent I-131 l The Dose Equivalent 1-131 is the concentration of l-131 (microcurie / gram)

' which alone would produce the same thyroid dose as the quantity and isotopio

mixture of I-131,1-133,1-134 and 1-135'actually present. The thyroid dose j conversion factors used for this calculation shall be those listed in Table lil of -

. TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites"

or in NRC Regulatory Guide 1.109, Revision 1, October 1977.

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B. Instrument Channel Calibration See Appendix A Technical Specifications.

f- C. Instrument Channel Functional Test i

! See Appendix A Technical Specifications.

j- . D. Instrument Check

See Appendix A Technical Specifications.

i E. Loaic System Function Test -

( See Appendix A Technical Specifications.

F. Member (s) of the Public j Member (s) of the Public includes all persons who are not occupationally

associated with the facilities on the NYPA/(NMPC) Niagara Moha,wk Power Corporation site. This category does not include employees of the utilities, its- l l contractors or vendors. Also excluded from this category are persons who i enter the site to service equipment or to make deliveries. .This category does include persons who use portions of the site for recreational,' occupational, or other purposes not associated with the plants.

G. Offaas Treatment System l

i The Offgas Treatment System is the system designed and installed to: reduce

[ radioactive gaseous effluents by collecting primary coolant system offgases

from the main condenser; and, providing for delay of the offgas for the

purpose of reducing the total radioactivity prior to release to the environment.

H. Offsite Dose Calculation Manual (ODCM)

The ODCM describes the methodology and parameters to be used in the calculation of the offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluents monitoring instrumentation alarm / trip set points and the conduct of the environmental i- monitoring program. . l 1

j l. Ooerable .

See Appendix A Technical Specifications.

Rev. No. O Page _2_ of REC 1

J. Rated Thermal Power See Rated Power, Appendix A Technical Specifications.

g K. Site Boundary The Site Boundary is that line beyond which the land 's not owned, leased, or otherwise controlled by NYPA and NMPC. Refer to Figure 4.1-1 for the map of the site boundary with regard to liquid and gaseous releases.

L Source Check A Source Check is the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

M. Treatment Any process which effectively reduces the concentration of radioactive material per unit measure released to the environment. This includes such processes as filtration, evaporation /cc,ndensation, settling / decanting, and solidification.

I N. Unrestricted Area An unrestricted area shall be any area at or beyond the site boundary access to which is not controlled by NYPA for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

The definition of unrestricted area used in implementing the RadioJogical Effluent Technical Specifications has been expanded over that in 10 CFR 20.3(a)(17). The unrestricted area boundary may coincide with the exclusion l (fenced) area boundary, as defined in 10 CFR 100.3(a), but the unrestricted l area does not include areas over water bodies. The concept of unrestricted  :

areas, established at or beyond the site boundary, is utilized in the Umiting )

Conditions for Operation to keep levels of radioactive materials in liquid and I gaseous effluents as low as is reasonable achievable, pursuant to 10 CFR 50.36a.

O Rev. No. O Page 3 of REC

2.0 LIQUID EFFLUENTS 1

2.1 Liquid Effluent Monitors 2.1.1 Umiting Conditions For Operation

a. Applicability 1

Applies to the instrumentation required for monitoring radioactive liquid effluent discharges to the environment as specified in Table 2.1-1.

Objective b.

To ensure that radioactive liquid effluent discharges are properly monitored i

and recorded during release in accordance with 2.1 of Appendix B to the

Technical Specifications.

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c. Specifications i 1. The controls of the instruments that monitor radioactive liquid effluents

are given in Table 2.1-2. Wrth a radioactive liquid effluent monitoring instrumentation channel alarm / trip set point less conservative than required by the ODCM, without delay suspend the release of p radioactive liquid effluents monitored by the affected channel, or

(/ declare the channel inoperable, or change the set point so it is

! acceptably conservative.

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2. With less than the minimum number of radioactive liquid effluent

monitoring instrumentation channels operable, take the action shown in 4 Table 2.1-1. Take corrective actions to return the instruments to 2 operable status within 30 days and, if unsuccessful, explain in the next

Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

j NOTE: This reporting requirement does not apply to instruments which would not have been required to be operable during the 30 day period.

2.1.2 Surveillance Requirements

a. Applicability l Applies to the instrumentation for monitoring radioactive liquid effluent discharges.

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b. Objective To ensure that instrumentation required for radioactive liquid effluent O discharges are maintained and calibrated,

c. Specifications

1. The alarm / trip set points of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).

2. The surveillance requirements for the radioactive liquid effluent monitoring instrumentation is shown on Table 2.1-2.

2.1.3 Bases The radioactive liquid effluent instrumentation is provided to monitor and control the releases of radioactive materials in liquid effluents during planned or unplanned releases. The alarm / trip set points for these instruments shall be calculated in accordance with methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR 20. The operability and use of this instrumentation is consistent with the requirements of 10 CFR 50, Appendix A, General Design Criteria 60, 63, and 64.

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Table 2.1-1

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RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Operable Action Gross radioactivity monitors providing alarm and automatic termination of release Liquid radwaste effluent line 1 (a)

Gross beta or gamma radioactivity monitors providing alarm but not providing automatic termination of release Service water system effluent line 1 (b)

Flow rate measurement devices Uquid radwaste effluent line 1 (c)

O Q) NOTES FOR TABLE 2.1-1 (a) With the number of operable channels less than the required minimum number, effluent releases may continue provided that prior to initiating a release:

1. Two independent samples are analyzed;

2. Two technically qualified members of the facility staff verify the discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

(b) Wrth the number of operable channels less than the required minimum number, effluent releases in this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for principal gamma emitters at a limit of detection of at least 5x10'7 microcuries/ml. The principal gamma emitters for which the LLD specification applies exclusively are described in Note (c) to Table 2.2-1.

(c) With the number of operable channels less than the required minimum number, effluent releases via this pathway may continue provided the flow rate is estimated at least once per four hours during actual releases. Pump curves or g)

( tank level decreases generated in situ may ba used to estimate flow.

Rev.No. O Page 6 of REC

Table 2.1-2 MINIMUM TEST AND CAUBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS (*)

Instrument i

Channel Instrument logic System l Instrgent Funegional Channel Functjg Instrument channels Check Test Calibration Test Liquid Radwaste Daily When Quarterly Quarterly Semiannually Discharge Discharging Monig g sola-tion l

l Liquid Radwaste Daily Quarterly Once per ---

Discharge Operating Radioactgity Cycle Recorder Liquid Radwaste Daily Quarterly Once per Semiannually l Discharge Flow Rate Operating l Measuring Devices

• Cycle Normal Sgrvice Water Daily Quarterly Quarterly ---

Effluent SBGTS Actuation --- --- ---- Semiannually NOTES FOR TABLE 2.1-2 g'

l l (a) Functional tests, calibrations and instrument checks need not be performed when j these instruments are not required to be operable or are tripped.

(b) Instrument checks shall be performed at least once per day during these periods when the instruments are required to be operable.

l (c) A source check shall be performed prior to each release.

(d) Uquid radwaste effluent line instrumentation surveillance requirements need not be l

performed when the instruinents are not required as the resuit of the discharge path not being utilized.

(e) An instrument channel calibration shall be performed with known radioactive sources standardized on plant equipment which has been calibrated with NBS traceable standards.

(f) Simulated automatic actuation shall be performed once each operating cycle.

Where possible, all logic system functional tests will be performed using the test Jacks.

O Rev. No. O Page 7 of _RE_Q_

(g) The logic system functional tests shall include a calibration of time delay relays and timers necessary for proper functioning of the trip systems.

(h) This instrumentation is excepted from the functional test definition. The functional test will consist of injecting a simulated electrical signal into the measurement channel. These instrument channels will be calibrated using simulated electrical signals once every three months.

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2.2 Concentration of Liquid Effluents 2.2.1 Limiting Conditions For Operation

a. Applicability Applies to the concentration of radioactive materials in liquid effluents,

b. Objective To ensure that the concentrations of radioactive materials in liquid effluents are kept to acceptable levels in accordance with 2.2 of Appendix B to the Technical Specifications.

c. Specifications

1. The concentration of radioactive materials released to the unrestricted areas shall not exceed the values specified in 10 CFR 20, Appendix B, Table 11, Column 2. For dissolved or entrained noble gases the concentration shall be limited to 2x10" Ci/ml.

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2. With the concentration of radioactive material released from the plant to unrestricted areas exceeding the above limits, restore the concentration to within the above limits or terminate the release. g 2.2.2 Surveillance Requirements i  !

a. Applicability Applies to the analysis of radioactive liquid wastes from the plant through a l l liquid pathway to an unrestricted area. l

b. Objective To ensure that analyses are performed and concentration determined for radioactive liquid releases.

c. Specifications

1. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analyses program of Table 2.2-1,

2. The results of the radioactivity analyses shall be used in accordance with the methods in the ODCM to ensure that the concentrations at the point of release are maintained within the limits of Control 2.2.1.

O Rev.No. O Page 9 of _ REC

l 2.2.3 Bases O This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to unrestricted areas will be less than the concentration levels specified in 10 CFR 20, Appendix B, Table 11, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposure above (1) the design objectives of 10 CFR 50, Appendix 1, Section ll.A, to a member of the public and (2) the limits of 10 CFR 20, Appendix B, Table ll, Column 2 to the population. The concentration limit for dissolved or entrained noble gases is based on Xe-135 as the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using '

methods described in ICRP Publication 2.

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-w.r . - - - - e- r- = w, v.w.+..e-.s.v.,--, ,-.,-w .- ---4,,,.-.-+,-,ws,,w ,ce .-- .-ww-, w

TABLE 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Umit  !

Minimum Type of Activity of Detection Uquid Release Sampling Analysis Analysis (LLD)(*)

Type Frequency Frequency (uCl/ml)

Batch Waste Releasg Tanks Prior to each Each batch Principal 5 x 10'7 l l

batch gamma l

emitters (*)

l-131 1 x 104 One batch per Monthly Dissolved and 1 x 104 month entrained gases (gamma  !

emitters)

Prior to each Quarterly H-3 1 x 10 4 batch composite (d) l Gross alpha 1 x 10'7 Prior to each Quarterly Sr-89, Sr-90 5 x 10

batch composite (d)

Fe-55 1 x 104 Continuous ContinuousM Weekly Principle 5 x 10'7 Releases (*) composite M Gamma Emitters (*) l 4

l-131 1 x 10 Monthly grab Monthly dissolved and 1 x 10 4 sample entrained gases (gamma emitters)

Continuous

• Monthly H-3 1 x 104 corrposite Gross alpha 1 x 10'7 Continuous

• Sr-89, Sr-90 4 5 x 10 Fe-55 1 x 104 O

Rev. No. O Page 11 of REC

NOTES FOR TABLE 2.2-1 O

O (a) The LLD (Lower Umit of Detection) is defined, for the purpose of these specifications, 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 and 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):

4.66 s3 LLD =

E + V 2.22 x 108 Y exp (-A A t)

Where:

LLD is the a priori lower limit of detection, as defined above (in microCuries per unit mass or volume);

sois the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (in counts per minute);

O E is the counting efficiency (in counts per disintegration);

V is the sample size (in units of mass or volume);

8 2.22 x 10 is the number of disintegrations per minute per microcurie; Y is the fractional radiochemical yield (when applicable);

A is the radioactive decay constant for the particular radionuclide; and At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting, it should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as an a costeriori (after the fact) limit for a particular measurement.

(b) A batch release is the discharge of liquid waste of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then mixed to ensure representative sampling.

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Rev. No. O Page 12 of REC

(c) The principal gamma emitters for which the LLD specification appiles exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,

, Cs-134, and Cs-137. This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Semiannual Radioactive Effluent Release Report. The LLD for Mo-99, Ce-141, and Ce-144 is 4

5x10 .

(d) A composite sample is one for which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(e) To be representative of the quantitles and concentrations of radioactive materials in liquid effluents, samples shall be coilected continuously in proportion to the rate

< of flow of the effluent stream. Prior to analyses, all samples taken for the composite sample to be representative of the effluent release.

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4 2.3 Dose From Uquid Effluents O 2.3., um, tin, con.itions F , o,e,ation

a. Applicability

, Applies to radiation doses from liquid effluents containing radioactive

. materials.

b. Objective To ensure that the dose limitations of 10 CFR 50, Appendix I for liquids are met in accordance with 2.3 of Appendix B to the Technical Specifcstions.

c. Specifications

1. The dose to a member of the public from radioactive materials released from the plant in liquid efMuents to unrestricted areas shall be limited as follows:

a) During any calendar quarter, limited to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ; and, O e) Derino any ceiendar vear. ii=>ied to iess tnan or equai to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

2. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, the following shall be done:

a) Identify the causes for such release rates; b) Define and initiate a program of corrective action; and c) Prepare and submit a report to the NRC within 30 days.

2.3.2 Surveillance Requirements

. a. Applicability Applies to the calculation of the radiation dose from liquid effluents containing radioactive materials.

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b. Objective To ensure that the radiation dose from radioactive liquid effluents is determined.

c. Specifications

1. Cumulative dose contributions from liquid effluents shall be determined j in accordance with the ODCM at least monthly for the current calendar l quarter and current calendar year.

2.3.3 Bases 1

This specification is provided to ensure that the requirements of 10 CFR 50, Appendix 1, Section ll.A, Ill.A and IV.A are met. The Limiting Conditions for  !

Operation ensures that the guides set forth in 10 CFR 50, Appendix 1, Section ll.A are met. The specdications provide the required operating flexibiftty and, at the same time, implement the guides set forth in 10 CFR 50, Appendix 1, Section IV.A, to ensure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable."

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i 2.4 Uquid Radioactive Waste Treatment System Operations jO j 2.4.1 Umiting Conditions For Operation 1

! a. Applicability i ,

, Applies to the operability of radioactive liquid processing equipment.

b. Objective

To ensure liquid radwaste treatment system (s) are operated to prevent j exceeding the dose limits of Control 2.3 in accordance with 2.4 of Appendix B to the Technical Specifications.

c. Specircations ,

1 j 1. The liquid radioactive waste treatment system shall be used when the

projected dose from untreated liquid releases, over a 31 day period, to i a member of the public would exceed:

a) 0.06 mrem to the whole body; or,

! b) 0.2 mrem to any organ.

i O 2. Wrth radioactive liquid waste being discharged in excess of the above

> limits, prepare and submit to the Commission within 30 days a report i that includes the following information:

a) Explanation if liquid radwaste was being discharged without

treatment; and if so:

i b) Identification of any inoperable equipment or subsystems and the reason for the inoperability; c) Action (s) taken to restore the inoperable equipment to operable j status; and d) Summary description of action (s) taken to prevent a recurrence.

j 2.4.2 Surveillance Requirements

a. Applicability i Dose projections apply to liquid effluents released to unrestricted areas.

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b. Objective To ensure that action levels to require operation 'of waste treatment systems

, are determined.

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l c. Specifications

1. Doses to individuals in unrestricted areas due to liquid releases shall be projected at least monthly in accordance with the ODCM.

2.4.3 Bases The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable". This speerfication ensures that the requirements of 10 CFR 50.26a,10 CFR 50, Appendix A, l General Design Criterion 50, and design objective of 10 CFR 50, Appendix 1,

' Section ll.D are met. The specified limits goveming the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set torth in 10 CFR 50, Appendix 1, Section ll.A, for liquid effluents.

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i 3.0 GASEOUS EFFLUENTS 3.1 Gaseous Effluent Monitors i

j 3.1.1 Limiting Conditions For Operation i a. Applicability i

! Applies to the instrumentation required for monitoring the radioactive gaseous emuent discharges to the environment.

i e b. Objective 1

l To ensure that radioactive gaseous emuent discharges are property 1

monitored and recorded in accordance with 3.1 of Appendix B to the Technical Specifications.

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c. Specifications 4

j 1. Radioactive gaseous wastes released to the environment via the Lh listed pathways shall be monitored and recorded during release from

the respective pathway.

a) Main stack iO i

b) Refuel floor vent l c) Reactor building vent 4

i d) Turbine building vent i

2 e) Radwaste building vent

2. Each pathway listed above shall also be sampled for iodine and j particulate radioactivity on a continuous basis during release from the respecbve pathway.

} 3 If Control 3.1.1.c above, cannot be met, effluent releases may continue via the respective pathway provided gasaous grab samples are

collected in the case of a monitor out of service or auxiliary samplers are used in case a particulate and iodine sampler is out of service and

a) Retum the instrument to operable status within 30 days; or

b) Provide an explanation in the next Semiannual Radioactive Release Report as to why the inoperability was not corrected within 30 l

days.

Rev. No. O Page _1lL. of REC .

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4. Alarm / trip set points shall be determined in accordance with the ODCM and set to ensure that the limits of Control .3.2 are not exceeded. Wrth a radioactive gaseous effluent monitoring instrumentation channel gI I alarm / trip set point less conservative than required by the above control:

a) Without delay, suspend the release of radioactive gaseous effluents monitored by the affected channel; or b) Declare the channel inoperable; or c) Change the set point so it is acceptably conservative.

3.1.2 Surveillance Requirements l l

a. Applicability Applies to instrumentation listed in Control 3.1 and analyses of gaseous effluent releases. j

b. Objective To ensure that instrumentation required for gaseous effluent releases is maintained and calibrated and the radioactivity of gaseous releases is determined.

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c. Specifications

1. Operation of the gaseous effluent monitors shall be verified by i performing instrument surveillance as specified on Table 3.1-2. l

2. The lodine cartridge and the particulate filter for each pathway listed in Control 3.1 shall be changed out at least weekly.

3. Grab samples, when required, shall be collected at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of collection. Auxiliary samplers shall run continuously and be changed out at least weekly.

3.1.3 Bases The radioactive gaseous effluent instrumentation is provided to monitor and control the releases of radioactive materials in gaseous effluents. The alarm / trip set points for these instruments shall be calculated in accordance with methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR 20.

O Rev. No. O Page ._1tL of REC 1

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Table 3.1 1 RADIATION MONITORING SYSTEMS THAT INiflATE AND/OR ISOLATE SYSTEMS Total No. of Minimum No. Instrument of Operable Trip Channels Instrument Trip Level Provided by Channels Function Setting Design Action 1(a) Refuel Area (b) 2 (c) or (d)

Exhaust Monitor 1(a) Reactor (b) 2 (d)

Building Area Exhaust Manitors 1(a) Turbine (b) 2 (f)

Building Exhaust Monitors Radwaste O 1(a)

Building (b) 2 (f)

Exhaust Monitors NOTES FOR TABLE 3.1-1 (a) Whenever the systems are required to be operable, there shall be one operable or tripped instrument channel per system. From and after the time it is found that this cannot be met, the indicated action sh# be taken.

(b) Trip level setting is in accordance with the methods and procedures of the ODCM.

(c) Cease operation of the refueling equipment.

(d) Isolate secondary containment and start the SBGTS.

(f) Refer to Control 3.1.1.c.4.

Rev. No. O PaQe _2Q__ of REC

Table 3.1-2 MINIMUM TEST AND CAllBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS")

I instrument l Channel Instrument Logic System Instrument instrument Functional Channel Function Channels Check"I Test") Calibration Test *M*

Main Stack Daily Quarterly Quarterly -

Exhaust Monitors 1

Refuel Area Daily Quarterly Quarterly -

Exhaust j Monitors Reactor Daily Quarterly Quarterly Semiannually Building N< a Exhaust Monitors / isola-tion Turbine Daily Quarterly Quarterly ,

Building ,

Exhaust l Monitors Radwaste Daily Quarterly Quarterly -

Building Exhaust Monitors NOTES FOR TABLE 3.1-2 I

(a) Functional tests, calibrations and instrument checks need not be performed when these instruments are not required to be operable or are tripped.

(b) Instrument checks shall be performed at least once per day during these periods when the instruments are required to be operable.

O Rev. No. O Page 21 of REC

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(c) Simulated automatic actuation shall be performed once each operating cycle.

Where possible, all logic system functional tests will be performed using the test .

Jacks.

(d) The logic system functional tests shall include a calibration of time delay relays and timers necessary for proper functioning of the trip systems.

(e) This instrumentation is excepted from the functional test definition. The functional test will consist of injecting a simulated electrical signal into the measurement .

channel. These instrument channels will be calibrated using simulated eiedical signals once every three months.

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Rev.No. O Page _22_ of REC

- . , - , , . ~ . . - - - . . . - - . -- ..-..-....--:._._.

3.2 GASEOUS DOSE RATES 3.2.1 Umiting Conditions of Operation

a. Applicability Applies to the radiation dose rate from radioactive material in gaseous effluents from the plant.

b. Objective To ensure that the dose rates at or beyond the site boundary from gaseous effluents do not exceed the annual dose limits of 10 CFR 20 for unrestricted i areas in accordance with 3.2 of Appendix B to the Technical Specrfications.

c. Specifications I i

1. The dose rate at or beyond the site boundary due to radioactive materials released from the plant in gaseous effluents shall be limited as follows:

a) s500 mrem / year to the whole body and s3000 mrem / year to the skin from noble gases; and, b) s1500 mrem / year to any organ from lodine-131, lodine-133, Tritium and for radioactive materials in particulate form with half-lives greater than 8 days (inhalation pathway only).

2. With the dose rates exceeding the above limits, without delay restore the release rate to within the above limits.

3.2.2 Surveillance Requirements

a. Applicability Applies to the calculation of the dose rates from radioactive materials in gaseous effluents from the plant.

b. Objective To ensure that appropriate calculations are performed to determine the dose rate.s from gaseous effluents from the plant.

O Rev. No. O Page 23 of REC

c. Specifications

1. The dose rate due to noble gases in gaseous effluents shall be determined to be continuously within the limits of Control 3.2, in accordance with the irmibocis and procedures of the ODCM.

2. The dose rate due to lodine-131, lodine-133, Tritium and to radionuclides in particulated form with half-lives greater than 8 days in gaseous effluents, shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM. This will be done by obtaining representative samples and performing analyses in accordance with the sampling and analyses program specified in Table 3.2-1.

3.2.3 Bases This specification is provided to ensure that the dose rate at or beyond the site ' '

boundary from gaseous effluents will be within the annual dose limits of 10 CFR

20. The annual dose limits are the doses associated with the concentrations of 10 CFR 20, Appendix B, Table ll, Column 1. These limits provide reasonable assurance that radioactive material discharges in gaseous effluents will not result in the exposure of a member of the public to annual average concentrations

' exceeding the limits specified in 10 CFR 20, Appendix B, Table 11 (10 CFR 2.106[b]). The specified limits restnct, at all times, corresponding gamma and ,

beta dose rates above background to an individual at or beyond the exclusion i

. area boundary to 5500 mrem / year to the total body or to 53000 mrem / year to the skin. These limits also restrict the corresponding thyroid dose rate above background to a child via the inhalation pathway to 51500 mrem / year.

O Rev. No. O Page _24_ of REC

TABLE 3.2-1 RADIOACTIVE GASEOUS WASTE SAMPUNG AND ANALYSIS PROGRAM Lower Umit of Minimum Type of Detection Gaseous Sampling Analysis Actmty (LLD)(*) l Release Type Frequency Frequency Analysis (uCi/ml) 1 d

Main Stack Monthly Grab Principal 1 x 10 Monthg Noble and Refuel Sample (d) Gases ) Gamma Floor Vent Emitters *)

Bu d ng jet Quarterly Grab Quarterly H-3 1 x 10*

Sample j and Turbine 4

Building Vent Continuous (*) Weekly 1-131 1 x 10 and Radwaste Charcoal Building Vent Sample (*)

1-133 None Continuous (*) Weekly Principal 1 x 10'"

Particulate Gamma Sample(*) Emitters *)

(1-131,1-133, None others)

Continuous (*) 1 Wk/Or Gross Alpha 1 x 10'"

Particulate Sample Continuous (*) 4 Wk/Or Sr-89, Sr-90 1 x 10'"

Composite Particulate Sample Continuous (*) Noble Gas Noble Gases 1 x 104 Monitor Gross Beta or Gamma incinerated Prior to Each Each Batch5) Principal 5 x 10

0i10 Batch5) Gamma Emitters *)

1-131 1x10*

O Rev. No. O Page 25 of REC

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unt (above ity of lsely fa#.rGsTdetecteo with 95% probability concluding that a blank observation and with only 5%

represents a "real" signai.

For a particular measurement system (which may incl d u e radiochemical separation):

LLD = - #*

E V 2.22 x 10a Y exp (-lat).-

Where:

mass or volume);LLD is the a oriorilower limit of detection as defined b a ove (in microcuries per unit O 3 of a blank sample, as appropriate r of the counting (in rate counts per minute);s E is the counting efficiency (in counts n; per disintegratio )

V is the sample size (in units of mass or volume);

8 2.22 x 10 is the number of disintegrations per minut e per microcurie; Y is the fractional radiochemical yield e; (when applicabl )

\ A is the radioactive decay constant for the particul

{ ar radionuclide; and j

At for plant effluents is the elapsed time between th and time of counting.

e midpoint of sample collection

(

{ It should be recognized that the LLD is denned as

\

the fact) limit for a particular measurementrepresenting not an _a costeriori (after the capability of a me Rev. No. O Page 20 of REQ

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, l NOTES FOR TABLE 3.2-1 l (a) The LLD is defined, for purpose of these specifications, 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 and with only 5%

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

't For a particular measurement system (which may include radiochemical separation):

4 i 4.68 s,

LLD =

E V 2.22 x 10* Y em (-Ah4 i

Where:

LLD is the a oriori lower limit of detection, as defined above (in microcuries per unit mass or volume);

(]. s, is the standard deviation of the background counting rate or of the counting rate

(> of a blank sample, as appropriate (in counts per minute);

1 E is the counting efficiency (in counts per disintegration);

V is the sample size (in units of mass or volume);

8 2.22 x 10 is the number of disintegrations per minute per microcurie; Y is the fractional radiochemical yield (when applicable);

l A is the radioactive decay constant for the particular radionuclide; and At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not an a costerio_ri (after

, the fact) limit for a particular measurement.

O V

Rev. No. O Page 26 of REC

(b) The principal gamma emitters for which the LLD specification applies exclusM , o the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m, at eJ Xe-138 for gaseous emissions; and, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, and Os-137 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Semiannual Radioactive Effluent Release Report. The LLD for Mo-99, Ce-141, and Ce-144 is 5x10'". For oil samples, Table 2.2-1, Note (c) applies. 1 (c) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications. This determination shall be made using design flow rates if flow meters are not provided or are inoperable.

(d) Main stack gaseous sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 20% of rated thermal power in one hour.

1. This requirement applies only if:

o Ane'ysis shows that the dose equivalent 1-131 concentration in the primary coalant has increased more than a factor of 3; and o Tne noble gas monitor shows that effluent activity has increased by more tnan a factor of 3; and gi l

o Corrections for increases due to changes in thermal power level have been made in both cases.

(e) Main stack iodine and particulate sampling shall also be performed daily following each shutdown, startup or thermal power change exceeding 20% of rated thermal power in one hour.

1. Daily sampling is not required for thermal power changes if the offgas charcoal filters are in service.

2. In addition, this requirement applies only if:

o Analysis shows that the dose equivalent I-131 concentration in the primary coolant has increased more than a factor of 3; and o The noble gas monitor shows that effluent activity has increased by more than a factor of 3; and o Corrections for increases due to changes in thermal power level have been made in both cases.

g Rev. No. O Page 27 of REC

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1 3. Daily sampling shall be performed until two consecutive samples show no increase in concentration but not to exceed 7 consecutive days.

l. 4. LLDs may be increased by a factor of 10 for analysis of daily samples.

1 l 5. Analysis of daily and weekly samples shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of .

! changing.

i j (f) incinerated oil may be discharged via points other than the main stack and building

vents (i.e., auxiliary boiler). Whenever oil samples cannot be filtered such as No. 6 i bunker fuel oil, raw oil samples shall be collected and analyzed.

! (g) Samples of incinerated oil releases shall be collected from and representative of

! filtered oil in liquid form. Whenever oil samples cannot be filtered such as No. 6 j bunker oil, raw oil samples shall be collected and analyzed.

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Rev. No. O Page 28 of REC a

i L__.________________ . , _ . . .. . . _ _ . . , _ _ _ , _ . . _ , . _

3.3 Air Dose, Noble Gases 3.3.1 Limiting Conditions For Operation h

a. Applicability Applies to the air dose due to noble gases released from the plant.

't

b. Objective To ensure that the noble gas dose limitations of 10 CFR 50, Appendix 1, are 4

met in accordance with 3.3 of Appendix B to the Technical Speerfications.

c. Specifications

1. The air dose to areas at or beyond the site boundary from noble gases released from the plant in gaseous effluents shall be limited:

a) During any calendar quarter, to less than or equal to 5 mrad from 1 gamma radiation, and less than or equal to 10 mrad from beta radiation; and, b) During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.

2. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission, within 30 days, a report that:

a) Identifies the cause(s) for exceeding the limit (s); and b) Defines the corrective actions that have been taken to reduce the

. releases; and c) Identifies the proposed corrective actions to be taken to ensure that subsequent releases will be in compliance with the above limits.

3.3.2 Surveillance Requirements

a. Applicability Applies to the calculation of the air dose due to noble gas effluent.

O Rev. No. O Page 29 of REQ

b. Objective O

V To ensure that appropriate calculations are performed to determine the air dose from noble gas effluents.

c. Specifications

1. Cumulative air dose contributions for noble gases shall be calculated at least monthly in accordence with the ODCM for the current calendar quarter and the current calendar year.

3.3.3 Bases This specification is provided to ensure that the requirements of 10 CFR 50, Appendix 1, Section ll.B, Ill.A and IV.A are met. The Umiting Conditions for Operation are the guides set forth in 10 CFR 50,- Appendix 1, Section ll.B. The specification provides the required operating flexibility and, at the same time, implements the guides set forth in 10 CFR 50, Appendix 1, Section IV.A, to ensure that the releases of radioactive material in gaseous effluents will be kept 'as low as is reasonably achievable."

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Rev. No. O Page M of. REC W

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3.4 Dose Due to lodine-131, lodine-133, Tritium and Radlonuclides in Particulate Form g 3.4.1 IJmiting Conditions For Operation

a. Applicability l l

Applies to the cumulative dose from lodine-131, lodine-133, Tritium, and l radionuclides in particulate form in gaseous effluents. l l

b. Objective To ensure that the dose limitations of 10 CFR 50, Appendix 1, are met in accordance with 3.4 of Appendix B to the Technical Specifications,

c. Specifications

1. The dose to a member of the public at or beyond the site boundary from ,

lodine-131, lodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days released from the plant in gaseous effluents shall be limited:

a) During any calendar quarter to less than or equal to 7.5 mrem to i any organ; and, g

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

c) Less than 0.1% of the limits above as a resuit of burning contaminated oil.

2. With the calculated dose from the release of lodine-131, lodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a report that:

a) Identifies the cause(s) for exceeding the limit; and b) Defines the corrective actions that have been taken to reduce the releases; and c) Identifies the proposed corrective actions to be taken to ensure that subsequent releases will be in compliance with the above limits.

O Rev. No. O Page 31 of REC

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3.4.2 Surveillance Requirements O a. Applicability

. Applies to the calculation of the dose due to lodine-131, lodine-133, Tritium, and radionuclides in particulate form in gaseous effluents.

b. Objective d

To ensure that appropriate calculations are performed to determine the dose from lodine-131, lodine-133, Tritium, and radionuclides in particulate form.

1

. c. Specifications I 1. Cumulative dose contributions shall be calculated at least monthly in accordance with the ODCM for the current calendar quarter and the s current calendar year.

3.4.3 Bases This specification is provided to ensure that the requirements of 10 CFR 50, 3 Appendix 1, Section ll.C, ll.A and IV. are met. The Umiting Conditions for Operation are the guides set forth in 10 CFR 50, Appendix 1, Section ll.C. The

~I specifications provide the required operating flexibility and, at the same time, implement the guides set forth in 10 CFR 50, Appendix I, Section IV.A, to ensure

~

that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

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1 Rev.No. O Page _32_ of . REC a

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3.5 Offgas Treatment System 3.5.1 Lirniting Conditions For Operation h

, a. Applicability Applies to the system installed for reduction of radioactive materials in gaseous waste prior to discharge.

b. Objective To minimize concentration of radioactive materials released from the site in accordance with 3.6 of Appendix B to the Technical Specifications.

c. Specifications

1. The offgas treatment system shall be used to reduce the concentration of radioactive materials in gaseous effluents prior to release from the plant within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the start-up of the second turbine driven feedwater pump.

2. The offgas charcoal beds shall be used, when offgas treatment system operation is required and the projected doses over a 31 day period due to gaseous effluent releases to a member of the public would exceed:

a) 0.2 mrad for gamma radiation -

O b) 0.4 mrad for beta radiation; or c) 0.3 mrem to any organ

3. With gaseous effluent from the main condenser being discharged without use of the charcoal beds for greater than seven days when treatment is required, and projected doses are in excess of the above limits, prepare and submit to the Commission, within 30 days, a Special Report that includes the following information:

a) Explanation of why gaseous effluent is being discharged without charcoal bed treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.

b) Action (s) taken to restore the inoperable equipment to operable status; and c) Summary description of action (s) taken to prevent a recurrence. ,

1 0\j Rev. No. O Page 33 of REC L

3.5.2 Surveillance Requirements

a. Applicability Applies to the calculation of the radiation dose from gaseous effluents containing radioactive materials.'

b. Objective To ensure that treatment of gaseous wastes by the offgas system is implemented when required.

c. Specifications

1. If the charcoal beds are not in service when the offgas treatment system is required, doses'due to gaseous releases from the site shall be projected at least monthly in accordance with the ODCM.

3.5.3 Bases This specification is provided to ensure that the system will be available for use when required to reduce projected doses due to gaseous releases. This speedication ensures that the requirements of 10 CFR 50.36a,10 CFR 50,-

A Appendix A, General Design Criterion 60, and design objective in 10 CFR 50,'

V Appendix 1, Section ll.D are met. The specified limits governing the use of appropriate portions of the' systems are specified as a suitable fraction of the guide values set forth in 10 CFR 50, Appendix 1, Sections ll.B and ll.C, for gaseous effluents. -

The requirement for offgas treatment system operability provides assurance that the release of radioactive materials in gaseous waste will be kept "as low as is  ;

reasonably achievable." Operability of the system is based upon start-up of the )

second turbine driven feedwater pump. This is due to the fact that excess air in- {

leakages in the main condenser as a result of operating only one turbine driven feedwater pump will exceed offgas treatment system limitations and consequently render the system inoperable. Start-up of the second turbine driven feedwater pump will decrease air in-leakages and ensure offgas treatment system availability.

O Rev. No. O Page 34 of REC l

4.0 TOTAL DOSE 4.1 Total Dose From Uranium Fuel Cycle h 4.1.1 Limiting Conditions For Operation

a. Applicability Applies to radiation dose from releases of radioactivity and radiation from uranium fuel cycle sources.

b. Objective To ensure that the requirements of 40 CFR 190 are met in accordance with 5.1 of Appendix B to the Technical Specifications.

c. Specificatic,. 3

1. The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited as follows:

a) Less than or equal to 25 mrem / year to the whole body; and, b) Less than or equal to 25 mrem / year to any organ except the thyroid which shall be limited to less than or equal to 75 mrem / year.

g

2. Wrth the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 2.3 or 3.3 or 3.4, calculations shall be made including an estimate of direct radiation contributions to determine whether the limits of Control 4.1 have been exceeded, if this is the case, a report defining corrective actions to be taken to reduce subsequent releases to levels within limits, along with a schedule for achieving conformance, shall be prepared and submitted to the Commission within 30 days. This report, as defined in 10 CFR 20.405c, shall include estimates of the radiation exposure (dose) to a member of the public from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceed (s) the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the report shall include a request for variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a i variance is granted until staff action on the request is complete. l O1 Rev. No. O Page ._35... of REQ l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - -

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Surveillance Requirements 4.1.2

!O l

a. Applicability l Applies to the calculation of total dose due to releases of radioactmty and l radiation from uranium fuel cycle sources.

j b. Objective To ensure that appropriate calculations are performed to determine total dose j to a member of the public.

c. Specificationa

1. Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 2.3, 3.3, and 3.4 and in accordance with the ODCM.

2. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Control 4.1.

4.1.3 Bases This specification is provided to meet the dose limitations of 40 CFR 190. This y specification requires the preparation and submittal of a report whenever the

, calculated dose from plant radioactive effluents exceed twice the design objective doses of 10 CFR 50, Appendix 1. The 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 190 limits. For the purpose of the report, it may be assumed the dose commitment to the member of the public from other uranium fuel cycle sources is negligible. However, 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 190, the report, with a request for variance (provided the release conditions resutting in a violation of 40 CFR 190 have not already been corrected), shall be submitted in accordance with provisions of 40 CFR 190.11 and 10 CFR 20.405c.

This request is considered a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190 and does not apply in any way to the requirements for dose limitation addressed in Controls 2.0 and 3.0. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

O Rev.No. O Page 36 of REC

4 FIGURE 4.1-1

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! O Rev.No. O Page 37 of REC 4

NOTES TO FIGURE 4.1-1 l

pb (a) NMP1 stack (height is 350 feet)

(b) NMP2 stack (height is 430 feet)

(c) JAFNPP stack (height is 385 feet)

(d) Building vents (e) NMP1 radioactive liquid discharge (Lake Ontario, bottom)

(f) NM?2 radioactive liquid discharge (Lake Ontario, bottom)

(g) JAFNPP radioactive liquid discharge (Lake Ontario, bottom)

(h) Site boundary (i) Lako Ontario shoreline

, ) Additional Information:

NMP2 reactor building vent is located 187 feet above ground level JAFNPP reactor and turbine building vents are located 173 feet above ground level JAFNPP radwaste building vent is 112 feet above ground level 1

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Rev.No. O Page 38 of REC f

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Monitoring Program h 5.1.1 Limiting Conditions For Operation

a. Applicability At all times.

b. Objective To evaluate the effects of plant operation on the environs and to verify the effectiveness of the controls on rad.ioactive material in accordance with 6.1 of Appendix B to the Technical Specifications.

c. Specifications I

1. With the radiological environmental monitoring program not being conducted as specrfied in Table 5.1-1, 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.

(Deviations are permitted from the required sampling sche (fule if samples l are unobtainable due to hazardous conditions, seasonal unavailability, theft, uncooperative residents, or to malfunction of automatic sampling equipment. If the latter, efforts shall be made to complete corrective i action prior to the end of the next sampling period.)

2. Wrth the level of radioactivity (as the result of plant effluents) in an environmental sampling medium at a specified location exceeding the reporting levels of Table 5.1-1 when averaged over any calendar quarter, prepare and submit to the Commission a report within thirty (30) days from the end of the affected calendar quarter or within thirty (30) days from the time it is determined that a reporting level has been exceeded.

This report shall identify the cause(s) for exceeding the limits (s) and define the corrective action (s) to be taken to reduco radioactive effluents so that the calculated annual dose to a member of the public is less than the calendar year limits of Controls 2.3,3.3, and 3.4. When more than one of the radionuclides in Table 5.1-2 are detected in the sampling medium, this report shall be submitted if:

O Rev.No. O Page.39 of REC

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concentation (1) concentanon (2) "'

MirWt level (1) limit level (2) l When radionuclides other than'those in Table 5.1-2 are detected and are j

the result of plant effluents, this report shall be submitted if the calculated annual dose to an individual is equal to or greater than the calendar year

limits of Controls 2.3,3.3, and 3.4.

This report is not required if the measured level of radioactivity was not l 1 the result of plant effluents; however, in such an event, the condition shall .

l be reported and described in the Annual Radiological Environmental l l Operating Report.

l l

3. With milk or fresh leafy vegetable samples unavailable from one or more j of the sample locations required by Table 5.1-1, locations for obtaining  ;

, replacement samples shall be identified and added to the radiological l environmental monitoring program within 30 days. The specific locations j

from which samples were unavailable may then be deleted from the i monitoring program. The cause of the unavailability of samples and the )

new location (s) for obtaining replacement samples shall be identified in j j the next Semiannual Radioactive Effluent Release Report. Also included j

]' in the report shall be a revised figure (s) and table for the ODCM i

reflecting the new location (s). l j 5.1.2 Surveillance Requirements

! The radiological environmental monitoring samples shall be collected, pursuant to i Table 5.1-1, from the locations given in the table and figure (s) in the ODCM and i j shall be analyzed pursuant to the requirements of Table 5.1-1, and the detection -

l capabilities required by Table 5.1-3.

4 5.1.3 Bases l The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those j exposure pathways and for those radionuclides that lead to the highest potential

radiation exposures to members of the' public resulting from station operation.

j This monitoring program ensures that 10 CFR 50, Appendix 1, Section IV.B.2 is met. It 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, based on the effluent measurements and i the modeling of the environmental exposure pathways.

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l Rev.No. O Page 40 of REC 9

- r -- . - , . -- < r- .- .~

The required detection capabilities for environmental sample analyses are tabulated in terms of the Lower Umit of Detection (LLDs). The LLDs required by Table 5.1-3 are considered optimum for routine envircnmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an _a h

oriori (before the fact) limit representing the capability of a measurement system.

The LLD is not an a costeriori (after the fact) limit for a particular measurement.

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O Rev. No. O Page 41 of REQ

J Table 5.1-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and and/or Collection Frequency of Sample Number of Samples (*) and Locations Frequency (*) Analysis AIRBORNE Radiciodine Samples from 5 locations: Continuous Radiciodine and sample Canisters:

Particulates a. 3 samples from offsite locations in operation with Analyze weekly different sectors of the highest sample for 1-131.

calculated site average D/O collection (based on all licensed site weekly or as Particulate reactors). required by Samoles:

dust loading, Gross beta b.1 sample from the vicinity of a whichever is radioactivrty community having the highest more frequent. following) filter calculated site average D/O change ,

(based on alllicensed site composite (by reactors). location) for gamma b] c.1 sample from a control location 9 isotopic (*)

quarterly (as a to 20 miles distant and in a least ,

prevalent wind direction (d) . minimum).  !

Direct 32 stations with two or more Quarterly Gamma dose Radiation (*) dosimeters placed as follows: monthly or quarterly.

a. An inner ring of stations in the general area of the site boundary.

b. An outer ring in the 4 to 5 mile range from the site with a station in each of the land based sectors.

There are 16 land based sectors in the inner ring and 8 land based sectors in the outer ring.

c. The balance of the stations (8) are placed in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

O Rev. No. O Page 42 of REC

Table 5.1-1 (continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Number of Samples (*) and Sampling and Type and Pathway Locations Collection Frequency of and/or Sample Frequency (*) Analysis WATERBORNE SurfaceM a.1 sample upstream. Composite Gamma sample over isotopic b.1 sample from the site's most one month analysis downstream cooling water period# . monthly.

intake". Composite for Tritium analysis  !

quarteriyM. l Sediment from 1 sample from a downstream Twice per Gamma Shoreline area with existing or potential year. isotopic recreational value. analysis serr.;-

annuallyM. ,

i INGESTION Milk a. Samples from milch animals in Twice per Gamma  !

3 locations within 3.5 miles month, April isotopic and l-distant having the highest through 131 analysis ,

calculated site average D/O. December twice per )

If there are none, then 1 (samples will month when sample from milch animals in be collected in milch animals each of 3 areas 3.5 to 5.0 January are on pasture miles distant having the through (April through highest calculated site average March if I-131 December);

D/O (based on all licensed site is detected in monthly reactors)N. November (January and through b.1 sample from milch animals at December of March), M if a control location (9 to 20 the preceding required .

miles distant and in a less year).

prevalent wind direction)W.

O Rev. No. O Page 43 of REC

i Table 5.1-1 (continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Fish a.1 sample of each of 2 Twice per Gamma commercially or recreationally year. isotopic M important species in the vicinity analysis of of a site discharge point. edible portions.

b.1 sample of each of 2 species (same as in a. above or of a species with similar feeding habits) from an area at least 5 miles distant from the siteW.

Food Products a. In lieu of the garden census as Once during Gamma specified in Control 5.2, harvest isotopic" samples of at least 3 different season, analysis of kinds of broad leaf vegetation edible (such as vegetables / plant portions.

leaves) grown nearest each of (Isotopic to two different offsite locations of include l-highest predicted site average 131.)

rm D/O (Based on all licensed site Reactors).

One (1) sample of each of the similar broad leaf vegetation grown at least 9.3 miles distant in a least prevaient wind direction sectorW.

NOTES FOR TABLE 5.1-1 (a) It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question. Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report. Calculated site averaged D/O values and meteorological parameters are based on historical data (specified in the ODCM) for m! licensed site reactors.

l (b) Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after 1 sampling to allow for radon and thoron daughter decay. If gross beta actrvrty in air is greater than 10 times a historical yearly mean of control samples, gamma isotopic q analysis shall be performed on the individual samples.

LJ Rev.No. O Page 44 of REC l

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

g (d) The purpose of these samples is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.

(e) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, l integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a pocket may be considered as two or more dosimeters. Film badges shall not be used for measuring direct radiation.

(f) The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The " downstream sample" shall be taken in an area beyond, but near, the mixing zone, if practical.

(g) Composite samples should be collected with equipment (or equivalent) which is  !

l capable of collecting an aliquoit at time intervals which are very short (e.g., hourty) relative to the compositing period (e.g., monthly) in order to ensure that a representative sample is obtained.

(h) A milk sampling location, as required in Table 5.1-1 is defined as a location having at g least 10 milking cows present at a designated milk sample location. It,has been W found from past experience, and as a result of conferring with local farmers, that a minimum of 10 milking cows is necessary to guarantee an adequate supply of milk twice per month for analytical purposes. Locations with less than 10 milking cows are usually utilized for breeding purposes which eliminates a stable supply of milk for samples as a result of suckling calves and periods when the adult animals are dry.

In the event that 3 milk sample locations cannot meet the requirement for 10 milking cows, then a sample location having less than 10 milking cows can be used if an adequate supply of milk can reasonably and reliably be obtained based on communications with the farmer, l

i l

O Rev. No. O Page 45 of REC

l Table 5.1-2 REPORTING LEVEL FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS 1

Airbome Food i Particulate Fish Products Water or Gases (pCl/kg. Milk (pCi/kg.

Analysis (pCi/l) (pCi/m ) wet) (pCi/l) wet)

H3 30,000 Mn-54 1,000 30,000

Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn45 300 20,000 Zr/Nb-95 400 1-131 20 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba/La-140 200 300 Rev. No. O Page 46 of REC

Table 5.1-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (*)

LOWER LIMIT OF DETECTION (LLD)*)

1 Airborne Particulate Fish Water or Gases (pCi/kg. Milk Food Analysis (pCl/l) (pCl/m ) wet) (pCl/l) Products Sediment gross 4 0.01 beta

. H-3 3,000  ;

1 Mn-54 15 130 I

Fe-59 30 260 l Co-58,60 15 130 Zn-65 30 260 I

Zr/Nb-95 15 l-131 15(*) 0.07 1 60 '

Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 )

Ba/La- 15 15 140 NOTES FOR TABLE 5.1-3 I

' (a) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability and with 5% probability of falsely concluding that a blank observation represents a "real' signal.

For a part%lar measurement system (which may include radiochemical separation),

4.66 s, g , E V 2.22 Y exp (-AAf)

O Rev. No. O Page 47 of REC

Where:

LLD is the a oriori lower limit of detection, as defined above (in picocurie per unit mass or volume);

s, is the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (in counts per minute);

E is the counting efficiency (in counts per transformation);

V is the sample size (in units of mass or volume);

2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);

1 is the radioac0ve decay constant for the particular radionuclide; At is the elapsed time be.. een sample collection (or end of the sample collection period) and time of counting.

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

(c) No drinking water pathway exists at the Nine Mile Point Site under normal operating conditions due to the direction and distance of the nearest drinking water intake.

Therefore, an LLD value of 15 pCi/ liter is used.

O Rev. No. O Page 48 of REC

5.2 Land Use Census Program 5.2.1 Limiting Conditions For Operation

a. Applicability At all times. ,

b. Objective To identify locations of milch animals and gardens of greater than 50 square meters within 3 miles of the site in accordance with 6.2 of Appendix B to the Technical Specifications.

c. Specifications

1. A land use census shall be conducted and shall identify'the locations of all milch animals, the nearest residence, and all gardens of greater than 50 square meters producing fresh leafy vegetables, in each of the 18 meteorological sectors within a dis ^2nce of 5 miles from the site.

2. With a land use census identifying a milch animal in a location (s) which represents a calculated D/O value greater than the values currently being used in calculating Surveillance Raquirement 3.4, identify the new g' location (s) in the next Semiannual Radioactive Effluent Release Report. W

3. Wrth the land use census identifying a milch animal location (s) that represents a calculated D/O (via the sarr.c exposure pathway) 50%

greater than at a location from which samples are currentiy being obtained in accordance with Table 5.1-1, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated D/O (via the same exposure pathway) may be deleted 4

from this monitoring program after October 31 of the year in which this ,

land use census is conducted. Identify the new location (s) in the next '

Semiannual Radioactive Effluent Release Report and include the additions in the ODCM.

5.2.2 Surveillance Requirements  !

The land use census shall be conducted during the growing season at least once per 12 months using the information that will provide the best resuits, such as by I a door-to-door survey, serial survey, or by consuiting local agriculture authorities, l etc. The resuits of the land use census shall be included in the Annual 1 Radiological Environmental Operating Report. l O 1 Rev.No. O Page 49 of REC

- - )

5.2.3 Bases This specification is provided to ensure that ' changes in the use of areas at and beyond the site boundary are identified and tnat modifications to the monitoring program are made if required by the results of this census. The best survey information, such as that from door-to-door surveys, serial surveys, consultations with local agricultural autnorities, etc., shall be used. This census satisfies the requirements of 10 CFR 50, ppendix 1, Section IV.B.3. Restricting the census to l gardens of greater than 50m provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimurn required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109, Revision 1, October 1977, for  !

consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabhaQA), and, (2) a Vegetable yield of 2 kg/m 2. In lieu of the garden census the significance of the garden exposure pathway can be evaluated by the sampling of green leafy vegetables as specified i in Table 5.1-1.

' Broad leaf vegetation sampling may be performed in lieu of the garden census as O specific in Table 5.1-1. ,

4 1

Rev.No. O Page jgL of -REC j

.- .- , ~ . - - _

__[, , _ ._ __,_ _ _;

5.3 Interlaboratory Comparison Program 5.3.1 Umiting Conditions For Operation

a. Applicability At all times.

b. Objective To provide quality control of environmental sample analyses in accordance with 6.3 of Appendix B to the Technical Speerfications.

c. Specifications

1. Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission. Participation in this program shall include all media for which samples are routinely collected and for which intercomparison samples are available. ,

i

2. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmental Operating Report. ,

5.3.2 Surveillance Requirements i l

A summary of the results obtainad as part of the above required Interlaboratory l Comparison Program shall be included in the Annual Radiological Environmental )

Operating Report.

5.3.3 Bases The requirement for participation in an interiaboratory Comparison Program is provided to ensure that independent checks on the precisio;. and accuracy of the measurements of radioactive material in the environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

O' Rev. No. O Page 51 of REC  ;

DVP-01.02 RADIOLOGICAL EFFLUENT CONTROLS AND O OFFSITE DOSE CALCULATION MANUAL * ~

PART 11 I

l

1.0 INTRODUCTION

l 1.1 Purpose  !

This manual provides the methodology to calculate radiation doses to individuals in the vicinity of the James A. FitzPatrick Nuclear Power Plant. It also provides methodology for calculating emuent monitor set points and allowable release rates to ensure compliance with the Technical Specifications, Appendix B, of the New York Power Authority, James A. FitzPatrick Nuclear Power Plant, Docket Number 50333, and 10 CFR 20 release criteria.

1.2 Methodologies and Parameters The ODCM follows the moticAciogy and models suggested by the " Guidance Manual For Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG-0133 October 1978) and " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of O Evaluating Compliance with 10 CFR 50, Appendix l' (Regulatory Guide 1.109, '

Revision 1 dated October 1977). Simplifying assumptions have been made and justified where applicable to provide a more workable document for implementing the Technical Specifications, Appendix B, requirements. Alternate calculating methods to those presented here may be used provided the general methodology is similar, well documented and the results are more precise.

Additionally, as available, the most up-to-date revision of the Regulatory Guide 1.109 dose conversion factors and site specific environmental transfer factors may be substituted for those currently included and used in this document. <

O Rev. No. _Q_. Page 1 of ODCM

2.0 DEFINITIONS Age Groups h Infants, children, teens and aduits are age groups evaluated by this ODCM.

Bem A beta particle (electron)

Beta Dose The dose component to skin dose due to beta emitting radionuclides in air, cc Cubic Centimeter Cl Curie. A unit of radioactivity equal to 3.7E+10 disintegrations per second. See also microcurie (pCi).

C, Concentration of a nuclide in the release source. Units of pCi/cc or pCi/ml.

CFR Code of Federal Regulations Dose A measure of the radiation energy deposited per unit mass (in mrem or mrad), that the organ or the individual receives from h

exposure to radioactive effluents dispersed in the environment.

Dose Commitment The total dose delivered to the organ or total body over a 50 year period resulting from uptake of radioactive material.

Dose Factor Normally, a factor that converts the effect of ingesting or inhaling radioactive material into the body, to dose to a specific organ.

Body elimination, radioactive decay, and organ uptake are some of the factors that determine a dose factor for a given nuclide.

Dose Pathway A specific path that rat wetive material physically travels through in the environment prior to exposing an individual to its emitted radiation. The grass / cow / milk food chain is a dose pathway.

O Rev. No. O Page _.2_ of ODCM i r

i l I Dose Rate  ;

The dose received per unit time. ,,

! (d/q) The short-term atmospheric deposition factor (m 2) for ground-level releases and a specified release duration.

(D/0) A long term relative deposition coefficient. A factor with units of 1/m2 which describes the deposition of particulate matter from a plume at a point downrange from the source, it can be thought of as the part of the cloud that will fall out and deposit over one -

square meter of ground. 4 Gamma A gamma photon Gamma Dose The dose component to skin or total body dose due to gamma-emitting radionuclides in air.

Ground Plane Radioactive material deposited uniformly over the ground emits  ;

radiation that produces an exposure pathway when an individual is present in the area. It is assumed that an adult receives the same exposure as an infant, regardless of the physical height-O differences. Only the total body and skin is considered for the purpose of the ODCM.

H-3 Hydrogen-3, or tritium. An isotope of hydrogen that is a low-energy beta emitter. j l&8DP Radiolodines and particulates with half-lives greater than eight days (includes H-3 where applicable).

LLD Lower Limit of Detection. The smallest concentration of '

radioactive material in a sample that will yield a net count, above system background that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

LCO Limiting Conditions for Operation in Technical Specifications, Appendix B.

T m8 Cubic meters m2 Square meters O

Rev.No. O Page _1. of ODCM I f

1 MPC Maximum Permissible Concentration Nuclide For the purpose of the ODCM, a radioactive isotope. Nuclide (i) l signifies a specific nuclide under consideration (e.g.,1st, 2nd,3rd, etc.), if nuclide (i) is 1-131, then the Mi (dose factor) under consideration should be Mg33, for example.

Organ For the purpose of the ODCM, either the bone, liver, thyroid, kidney, lung, GI-LIJ, skin or the T Body (Total Body). T. Body is considered an organ for consistency with the ODCM nomenclature.

Oi O, (dotted) denotes a release rate in Cl/sec or Ci/sec for nuclide I

(i).

O, Denotes Cl of nuclide (i) released over a specified time interval.

Receptor The individual receiving radiation exposure from effluent releases at JAFNPP at a given location, or who ingests food products contained with trace amounts of radioactive materials. A receptor can receive dose from one or more dose pathways.

Release Source A subsystem, tank, vent or stack where radioactive material can be released independently of other radioactive release points.

Restricted Area An area within the site boundary to which access is controlled by NYPA for purposes of protection of individuals from exposure to radiation and radioactive materials.

Technical Specifications, Appendix B The JAFNPP Radiological Effluent Technical Specifications (RETS).

pCi MicroCuries.1 Ci = 1E+6 pCuries. The pCiis the standard unit of radioactivity for all doce calculations in the JAFNPP ODCM.

(x/q) The short-term atmospheric deposition factor (sec/m ) for ground-level releases and a specified release duration.

(X/O) A long term relative atmospheric dispersion coefficient. It describes the physical dispersion characteristics of a seml-infinite cloud of noble gases as the cloud travels downwind from the release point.

g Rev.No. O Page 4 of ODCM

0 (X/0), Long term finite cloud atmospheric dispersion parameter for computation of external gamma radiation exposures (sec/m') -

(By definition, the gamma (X/0) is the equivalent relative concentration of radioactivity in a semi-infinite cloud that would yield the same radiation exposure as a finite cloud aloft; it ..

accounts for the actual plume dimensions and elevation above the receptor, and gamma radiation spectra.)

A Unrestricted Area An unrestricted area shall be any area at or beyond the site

. boundary where access is not controlled by NYPA for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or for industrial, commercial, institutio 1al, and/or recreational purposes. (Refer to Technical Specifications, Appendix B, Section 1.0 for an expanded definition).

Vent Building ventilation air exhausts via roof top ducts.

'(W/O) The annual average relative concentration (sec/m') for a given liquid pathway (potable water or fish ingestion) for a specified release duration.

i O

Rev.No. O Page 5 of ODCM

3.0 LIQUID EFFLUENT METHODOLOGY 3.1 Applicable Site Characteristics The JAFNPP Final Safety Analysis Report (FSAR) contains the official description of the site characteristics. The description that follows is a brief summary for dose calculation purposes.

The James A. FitzPatrick Nuclear Power Plant is located on the eastem portion of the Nine Mile Point promontory on Lake Ontario in Oswego County, NY. The site is approximately seven miles northeast of the City of Oswego. Radioactive liquid releases normally enter Lake Ontario where the Circulating Water Discharge Tunnel terminates on the lake bottom approximately 1,400 feet from the shoreline.

3.2 10 CFR 20, MPC Limits-Determination of the Fraction (F) of Release Limits and Minimum Required Dilution J

3.2.1 Requirements In accordance with Technical Specifications, Appendix B, Section 2.2, the concentration of liquid radioactive material released to unrestricted areas (Appendix G) shall not exceed the concentrations specified in 10 CFR 20, i

Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases. Concentration of radionuclides in liquid waste is g

determined by sampling and analyses in accordance with Technical Specifications, Appendix B, Section 2.2 and Radiological Effluent Controls, Section 2.2.

In accordance with Technical Specifications, Appendix B, Section 2.2 and Radiological Effluent Controls, Section 2.2. for dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml.

3.2.2 Methodology This section presents the calculating method to be used for determining F t, the fraction of 10 CFR 20 limits, of release concentrations of liquid radioactive effluents.

a. General Approach This method addresses the calculation for a specific release source.

Administrative controls are applied to assure that the summation of Ft values for each release source does not exceed the 10 CFR 20 limit.

O Rev. No. O Page 6 of ODCM

l i

. Normally, all potentially radioactive liquid effluents are released to the

{ unrestricted area through a single monitored release path as indicated in Appendix F. However, the service water system presents.a potential

release point for radioactive liquid effluents. To assure the combined releases do not exceed 10 CFR 20 limits, the alarm set point, as j determined in section 3.3 includes a conservatism factor of 0.5.

a j The basic equation which determines the fraction (Ft) of the 10 CFR 20 ,

j MPC limits is:

l Eq. 3-1 L

+ '

F' = f x -

\

_ 2_ i=1 (MPC) got, (MPC) zygoz,_

F Where:

Ft = The fraction of 10 CFR 20 MPC limits resulting from the release source being discharged (dimensionless).

f, = The undiluted release rate of the release source as P\ measured at the liquid effluent monitor location, in ,

gpm.

f2 = The discharge structure exit flow in gpm.

(Summation of circulating water pump and service water pump discharge flow; minus the flow .

redirected for tempering.)

C RURAE i = The undiluted concentration of nuclide (i) in pCl/ml from filtrate sample assay.

(MPC) = Soluble Maximum Permissible Concentration of nuclide (i) from Appendix A, in pCl/ml.

Cnuq = The undiksted concentration of nuclide (i) in pCl/mi from filter sample assay.

O Rev.No. O Page 7 of ODCM

I l

(MPC),O = Insoluble Maximum Permissible Concentration of nuclide (i) from Appendix A, in pCl/ml. g Using the general approach, the fraction of the 10 CFR 20 MPC limit may be determined using a nuclide-by-nuclide evaluation.

b. Simplified Approach For purposes of simplifying the calculation, the value of 3E-8 pCi/ml (unidentified 10 CFR 20 MPC value) should be substituted for (MPC), in the equation 3-1 and the cumulative concentration (Cw = sum of all identified radionuclide concentrations) or the gross beta-gamma concentration should be substituted for C.i

c. Approach Selection Criteria As long as the diluted concentration (C, x f i/f 2) is less than or equal to 3E-8 Ci/ml, the nuclide-by-nuclide calculation is not required to demonstrate compliance with the 10 CFR 20, MPC limit.

3.2.3 Calculating Process for Determining fgf, lhe following section provides a procedure for determining the minimum l required dilution factor (f2 /f,) to ensure that Ft = 1 during the actual release.

With Ft = 1, the minimum required dilution factor can be expressed as:

g)

Eq. 3-2 ff>g n C,

_ = E t

/

1% /=1 WPC), j i

a. Obtain (C),i the undiluted assay value of nuclide (i), in Cl/ml. If a gross activity determination (simplified approach) is used, the cumulative concentration (Cw) is used.

b. From Appendix A, Table A-1, obtain the corresponding (MPC) for nuclide (i) in pCi/ml. The value of 3E-8 Cl/ml should be used for the gross activrty method.

c. Divide Ci by (MPC)i.

d. If determining the MPC fraction using the nuclide-by-nuclide evaluation, repeat steps b and c above for each nuclide and sum the totals.

O Rev. No. O Page _a_ of ODCM

e, if the gross activity method is used, then O ,,,

A fI s mif) is given by Crw /3E-8

f. Enter the total activity (C) and the minimum required dilution factor (f2 /f,),in on the liquid release permit.

O E

l O

Rev. No. _Q_ Page _Q_ of ODCM

3.3 Determination of Setpoints for Radioactive Liquid Effluent Monitors 3.3.1 Requirements O Technical Specifications, Appendix B, Section 2.1.a requires that the radioactive liquid effluent monitor be operable and set to initiate an alarm and/or trip in the event that the limits of Technical Specifications, Appendix B, Section 2.2 are approached. The alarm and/or trip set points shall be determined and adjusted by the methodology which follows. The set point values should be applied above normal background levels.

The alarm set point for the liquid effluent radiation monitor is derived from the concentration limit provided in 10 CFR 20, Appendix B, Table ll, Column 2 applied at the unrestricted area boundary where the discharge tunnel flows -

into Lake Ontario.

3.3.2 Methodology The alarm set points do not consider dilution, dispersion, or decay of radioactive material beyond the unrestricted area boundary (i.e., the alarm setpoints are based on a concentration limit at the end of the discharge tunnel).

3.3.3 Radwaste Liquid Effluent Monitor g

a. A sample of each batch of liquid radwaste is analyzed for 1-131 and other principal gamma emitters prior to release. The fraction Ft of 10 CFR 20, MPC limits and the minimum required dilution factor to achieve Ft = 1 is determined in accordance with the preceding section for the activity to be released. For cases other than minimum dilution calculation, F t <0.5.

b. A conservative alarm and/or trip setpoint ( Ci/ml) is determined in accordance with the following equation.

Eq. 3-3 S = 0.5 x E Ft Where:

S =

The alarm and/or trip set point above background corresponding to the limiting concentration of undiluted liquid effluent ( Cl/ml).

O Rev. No. O Page 10_ of ODCM

i

- .i l 0.5 = Conservatism factor to account for releases from multiple points, I and to allow for nuclides not detected by the monitor.  ;

C = Total gamma isotopic or gross activity concentration'( Ci/mi) of I j sample as determined in the laboratory.  ;

i

! Ft = The fraction of 10 CFR 20, MPC limits for unrestricted areas resulting from the release source being discharged, F t _<0.5.

i 1 3.3.3.1 Calculating Proceae J

The following section provides a procedure for determining the j radwaste liquid effluent monitor set point. Typical parameter values are used for illustration.

a. Determine C from laboratory analysis of the liquid effluent sample.

For the purpose of this example, assume a value of 3E-5 pCi/mi in a gross beta gamma activity analysis.

)

b. Determine f, from pump curves and current plant operating configuration. A typical value is 3.78E+5 gpm.

! c. Determine the minimum required dilution factor in accordance with equation 3-2.  ;

i  :

I ' f,- n C ,

- = E i i /

1 4 /=1 (MNi i

4

For a gross activity determination, the unidentified MPC of 3E-8 j pCi/miis used. Therefore i f, '

i

= 3E-5/3E-8 = 1,000 i f

1. min

d. Determine or calculate the required 1f at the liquid effluent monitor i location. A typical value is 100 gpm.

e. A typical value of the dilution factor from current plant operating 4 conditions is:

lo Page 11 Rev. No. O of ODCM ,

1 J

_.__-__________.__.,.--,,_..m.,e. -

- , ,-,,-3-.--r.,-.%.- , . , , . . . . , . . , . . . , . , , , ,.,,,,,,,..,...,..-,.vv..,,.gp g g .e...,. - _ _ _ , , .

(3.78E+5 gpm)/100 gpm = 3,780, which is >1,000. Therefore the release can be made at the current release rates and concentrations maintained within the 10 CFR 20 limits, g

f. Determine Ft , the fraction of 10 CFR 20 MPC limits resulting from the release source being discharged at a dilution factor of 3,780, in accordance with equation 3-1.

I f- n l xE C' F=

t

f2 /=1 (M N )/

= (100/3.78E+5) x (3E-5/3E-8)

= (2.65E-4) x 1,000

= 0.265

g. Ele liquid effluent monitor set point, S in pCi/mi, from equation 3-3 is:

Eq. 3-3a S = 0.5 x C

= 0.5 x [(3E-5)/(0.265)]

= 5.66E-5 pCl/mi

h. Appropriate calibration factors are applied to this limiting concentration determined in step 3.3.3.g to determine an effluent monitor alarm potentiometer set point.

3.3.4 Service Water Uquid Effluent Monitor

a. A conservative alarm setpoint (cps) for the service water liquid effluent monitor is determined in accordance with the following methodology:

Eq. 3-3b DF =

Rev. No. O Page 12 of ODCM

J 1

Where:

!p k DF = the dilution factor which results from the flow rate in the a

discharge structure divided by the undiluted release rate of the effluent re!caso scuroa.

i 1 f, = the undiluted release rate of the effluent source measured at the service water liquid effluent monitor (gpm).

f2 = the discharge structure flow rate in gpm (summation of circulating water pumps and service water pumps discharge flows; minus the flow redirected for tempering).

4 Eq. 3-3c i

SP = O.5 x MPC, x DF + Bkg y

Where:

SP = set point of liquid effluent monitor in cps.

'C 0.5 = conservatism factor to account for releases from multiple

\

points or a reduction in the DF value due to changes in discharge canal flow, and to allow for nuclides not detected by the monitor.

1

MPC,= maximum permissible concentration for isotopic mixture being

released in service water per 10 CFR 20, Appendix B, Table 2,

Column 2 (Section b below).

l Eff = efficiency of the liquid effluent monitor in pCl/ml/ cps.

l Bkg = normal monitor background (cps).

b. Those nuclides present in previous batch releases from the liquid radwaste effluent system, nuclides present in historical semi-annual Radioactive Effluent Release Reports or those nuclides present in the service water system may be used to calculate the MPC, value. Other values for MPC, may be used based on plant conditions (i.e. In the event of known leakage into the RBCLC system).

,/]

o Rev. No. O Page 13 of ODCM

4 3.4 Dose Determination for Radioactive Uquid Effluents 4

3.4.1 Annual Dose Assessment-Radioactive Effluent Release Report Submittal

a. Requ!riments

'l Technical Specifications, Appendix B, Section 7.3 requires a semi-annual Radioactive Effluent Release Report to be submitted that includes an assessment of the radiation doses to the public due to the J radioactive liquid and gaseous effluents released from the unit during the previous calendar year. The dose assessment required by this report is due annually 90 days after January first of each year.

b. Methodology This section provides the methodology to calculate the doses to all age 1 groups and organs from all radionuclides identified in the liquid i effluents. The method is based on the methodology suggested by NUREG-0133, October 1978, Sections 4.3 and 4.3.1 and Regulatory Guide 1.109. The determination of viable liquid dose pathways ic described in Appendix A, Table A 4.3. The site-related dose factom for all viable pathways are listed in Appendix A, Tables A-2 and A-3. Table A-3 dose factors are compiled by age groups, for all organs and radionuclides common to a Boiling Water Reactor (BWR).

l The following equation provides for a dose calculation to the total body or any organ for a given age group based on actual release conditions during a calendar year for radioactive liquid releases. The equation for D,, is to be summed over all i nuclides:

Eq. 3-4a Ai , h t, On p*,

(DF),

Eq. 3-4b n

D, = E D,,

1-1 Where:

D, = Total dose commitment for organ r of an age group.

g Rev. No. O Page 14 of ODCM

i i Da

= Dose commitment in mrom received by organ r of age A group (to be specified) resulting from releases during jV time interval At, for nuclide (i).

Ay = 1he site-related dose commitment factor to the total body or any organ , for each identified radionuclide (i). The A gvalues listed in Appendix A, Tables A-2 and i A-3 are site specific, in mrom/hr per pCl/ml. Dose commitment factors are compiled by age groups, for i

organs and radionuclides common to a BWR

environment. The derivation of Ag values is described In Appendix A, Table A4.1.

l I

At, = The number of hours in the calendar year.

O,i = The total quantity of nuclide (i) released during the time period Ati , in pCl l (DF), = The total volume d dilution released during At, (i.e.,

summation of eteulating water pump and service water l

pump dischart,e flow; minus the flow redirected for tempering).

a I By entering the appropriate annual parameter values onto a form similar j to that shown in Table 3.4.2, total body or organ doses may be

. calculated as outlined in step 3.4.2.c.

4 in addition, more realistic assumptions may be made concerning the dilution and ingestion of fish and potable water by individuals who live

and fish in the area.

I 3.4.2 Monthly Dose Assessment - Verification of Compliance with 10 CFR 50, j Appendix 1 Umits 1 l l a. Requirements i Technical Specification, Appendix B, Section 2.3 requires an i assessment to be performed at least once every month in any quarter l' in which radioactive effluent is discharged, to verify that radioactive liquid effluents from the plant do not result in a cumulative dose in

excess of 1.5 mrem to the total body and 5 mrem to any organ in a calendar quarter, and to verify that radioactive liquid effluents from the plant do not result in a cumulative dose in excess of 3.0 mrem to the

whole body and 10 mrem to any organ during a calendar year.

i iO

.V Rev. No. _Q_ Page _15_.'of ODCM i

b. Methodology This section presents the calculating method to be used for the 10 CFR 50 Appendix I compliance verification. The method is based on the models suggested by NUREG4133 October 1978 Sections 4.3 and

. 4.3.1 and Regulatory Guide 1.109.

1. General Approach l The general approach used is similar to that described for use in i calculations for the Annual Dose Assessment Report. The liquid ,

effluent dose pathways considered are fresh water fish, potable l water and lake shoreline deposits (Appendix D). These pathways l need to be considered for verifying compliance with the l requirements specified above.

Site-specific dose factors for the fresh water fish, potable water and shoreline pathways are provided in Appendix A, Tables A-2 and A-3. l l

For JAFNPP, both the adult and teenager are normally the most limiting age groups (Appendix D), but the dose for child and infant I may also be calculated by this method using the appropriate dose l factors from Appendix A, Table A-3. )

The following equation is used to determine a dose to the total body or any organ for a given age group based on actual release conditions during a specified time interval for radioactive liquid releases. The equation for Da is to be summed over alli nuclides: l s

Eq. 3-Sa Di ' = Ai , h t, On (DF),

Eq. 3-5b n

D, = E D,i

/-1 O

Rev. No. O Page 16 of ODCM

i Where:

o D, = Dose commitment for organ r of an age group.

e D, 3

= Dose commitment in mrem received by organ r

of age group (to be specified) from release time j- interval At, for nuclide (1).

l A, = The dose factor for the fresh water fish, potable

~

water lake shoreline deposits pathways for

nuclide (i) for organ r of age group (to be j specified). (Appendix A, Tables A-2 and A-3 for i

Aa,, A% and A%).

l At, = The number of hours in the reporting period.

l 3

- O,, = The total quantity of nuclide (i) released during j the time period Ati in pCl.

l (DF), = The total volume of dilution released during At, J (i.e., the summation of circulating water pumps i and service water pumps discharge volumes; l minus the volume redirected for tempering).

lO

2. Umited Analysis Approach' .

{ Based on the radionuclide distribution typical in radioactive j - effluents at JAFNPP, the calculated dose to individuals are j dominated by the radionuclides, Cs-134, Cs-137,2n-65, Mn-54

and Co-60. From 1980 through 1987, these nuclides, in the fresh water fish and potable water pathways, contributed at least 92 percent of the adult's total body dose and at least 81 percent of the teenager's liver dose, which is the critical organ. Therefore,

the dose commitment due to radioactivity in liquid effluents may be l reasonably evaluated by limiting the dose calculating process to 1 these radionuclides for the adult's total body and the teenager's j liver dose.

To allow for any unexpected variability in the radionuclide distribution, a conservatism factor of 0.8 is introduced into the l'

equation. After calculating the dose based on these five nuclides, the cumulative dose should therefore be divided by 0.8. (Refer to

. Appendix D for a detailed evaluation and explanation of this limited  ;

j analysis approach). j O

Rev. No. O Page 17 of ODCM i l

- - - - . . - - - - , - - - , - . . - ---,-% y .--- ,--n , -

. , . , ,, ,3.e--e- -, ,w w, , -,e--

if the limited analysis approach is used, the calculation should be limited to the adult's total body dose and teenager's liver dose from the fish and potable water pathways. Only the five previously specified nuclides need be evaluated.

3. Approach Selection Criteria The limited analysis approach fully satisfies the requirements and can thus be used for routine releases. The more general approach may be used for more refined calculations for routine releases.

l For non-routine releases, i.e., other than through the discharge canal, Section 3.4.3 is to be used.

c. Calculating Method l The methodology that follows is a step-by-step breakdown to calculate i doses based on equation 3-5. If the limited analysis approach is used, the calculation should be limited to the adult total body dose and teenager's liver dose from the fish and potable water pathways. Only the five previously specified radionuclides need to be evaluated for the limited approach.

NOTE: Table 3.4.2 provides a convenient form for compiling the dose accounting information.

h

1. Determine (At,) the number of hours of the reporting period.

2. Obtain (DF), for the time period At, for the release source (s) of interest. DF, is the total volume of dilution, (i.e. the circulating water flow multiplied by the time) in milliliters.

3. Obtain 0,, ( Cl) for nuclide (i) for the time period At,.

l 4. Obtain Agfrom the appropriate Liquid Dose Factor Table:

Appendix A, Table A-2 for the fish and potable water pathways; Appendix A, Table A-3 for all other pathways.

5. Solve for Dose (i)

Eq. 3-6a g' , A ,x ht, x Qn i

(DF),

h Rev. No. O Page 18 of ODCM

i 1

6. Repeat steps 3 through 5 above for each nuclide reported and sach organ required. If the limited analysis method is used, limit O- the radionuclides to Co40, Mn-54,2n-65, Cs-134 and Cs-137 and determine the adult's total body dose and the teenager's. liver dose.

7. Sum the Dyvalues to obtain the total dose. If the limited analysis

, method is being used, divide the cumulative dose by a conservatism factor of 0.8 to account for any unexpected variability in radionuclide distribution and any contribution from the lake shoreline deposits pathway.

Eq. 3-6b n

Dg, D, . I"1 (0.8.)

When limited approach is used O

O Rev.No. O Page 19 of ODCM

,y 4 w.- . . - . , _ -

g. ,.y . . y. ,y.p,p,-..- . . . , , ... ., .-,.,,=r,m,*

-m,- , ..uu_m-,____

TABLE 3.4.2 FISH PATHWAY Time /Date Start: Time /Date Stop: At, hours Total Dilution Volume (DF)3: mis Age Group: Organ: Dose Factor Table No.

Nuclide (i) O,, A,, Dose (i) mrem Mn-54 Co-60 Zn-65 Cs-134 Cs-137 Others:

Total Dose r = mrem Eq. 3-6a if based on limited analysis + 0.8 mrem O

Rev. No. O Page 20 of ODCM

l l

3.4.3 Dose Assessment - Methodology For Uquid Releases Through the

(],, Storm Drain This section provides the methodology to calculate the doses to all age groups and organs from liquid releases other than routine releases through  :

the discharge canal, such as releases via the storm drain.

a. Requirements Non-routine liquid releases, when they occur, are to be added into the Radioactive Effluent Release Report (s) and the annual dose assessment report (Section 3.4.1) and the verification of compliance with 10 CFR 50 Appendix l regulatory guidelines (Section 3.4.2). The following are the Technical Specifications requirements for non-routine liquid releases, other than through the discharge canal.

Technical Specifications, Appendix B, Section 7.3 requires a semi-annual Radioactive Effluent Release Report to be submitted that includes an assessment of the radiation doses to the public due to the radioactive liquid and gaseous effluents released from the unit during the previous calendar year. The dose assessment required by this report is due annually 90 days after January first of each year.

Technical Specifications, Appendix B, Section 2.3 requires an p)

( assessment to be performed at least once every month in any quarter in which radioactive effluent is discharged, to verify that radioactive liquid effluents from the plant do not result in a cumulative dose in excess of 1.5 mrem to the total body and 5 mrem to any organ in a calendar quarter, and to verify that radioactive liquid effluents from the plant do not result in a cumulative dose in excess of 3.0 mrem to the whole body and 10 mrem to any organ during a calendar year,

b. Methodology Exposure pathways of interest are the ingestion of contaminated fish and drinking of contaminated water. Exposure from shoreline deposits following non-routine releases was determined to be insignificant and has been excluded from this section.

The model used accommodates (in a single unified approach) releases ranging from instantaneous (slug) to continuous (steady-state).

The method of analysis selected for dilution of tne released radioactivity in the lake makes use of the continuous-release model in Regulatory Guide 1.113, adapted to provide annual average concentrations for releases of shorter duration (including instantaneous). The model q assumes an exposure interval of one year, regardless of the duration of V the release.

Rev.No. O Page 21 of ODCM

I i

l For the fish-ingestion pathway, the fish is assumed to be adjacent to the release point for the duration of the release, and then to follow the radioactive plume for an overall exposure interval of one year. For the g'

l potable water pathway, the water supply is at 8.5 miles west of the plant l

(Oswego water intake), and is assumed to be continuously contaminated as a resuit of frequent current reversals.

The following equations present the annual dose due to the potable water and freshwater fish pathways for any given release, regardless of the release duration. These doses are to be assigned to an appropriate reporting interval (e.g., quarter) during which the release occurred.

Potable Water Pathway Eq. 3 7a Di , = K, x U, x DF, x C x 4 x (XI W) x A t i i ,

, Eq. 3-7b l

n D, = E D , i l /-1 Where:

D, = Dose commitment for organ r of an age group (mrem).

g l

D,, = Dose commitment received by organ r of an age group (to be specified) for nuclide i (mrem).

K, = ls the unit conversion factor,1.0E+09 (ml-pCi per liter-pCi).

U, = ls the water consumption rate for the age group of interest.

Adult: 730 liters /yr Teen: 510 liters /yr Child: 510 liters /yr Infant: 330 liters /yr l DF,i = Dose conversion factor (mrem per pCi ingested) for radionuclide i, for organ r and age group of interest, from Tables E-11 through E-14 of Regulatory Guide 1.109.

Ci = The average activity concentration of nuclide i in the effluent at the release point into the lake ( Ci/ml).

g Rev.No. O Page 22 of ODCM

1 1

3 q = The volumetric discharge rate of the effluent (m /sec).

O q is equal to the total volume of contaminated liquid release (m8 ) dMded by the duration of the release.

(X/W) = The annual average relative concentration (sec/m') for the potable water pathway, as shown in Table 3.4.3 for a list of release durations. Release durations were selected to accommodate a change of no more than 20% between consecutive X/Ws.

At .= The exposure period which is one year (yr).

Freshweter Fish Pathway Eq. 3-8a l D;, = K, x U, x BF, x DF, i x C, x 4 x (XJ W) x At Eq. 3-8b l

n n D, = E D;,

t U /=1 Where:

D, = Dose commitment of organ r of an age group (mrem),

D,, = Dose commitment received by organ r of an age group (to be specified) for nuclide I (mrom).

K, = ls the unit conversion factor,1.0E+09 (ml-pCi per liter-pCl).

U, = ls the freshwater fish consumption rate for the age group of interest, as follows:

Adult: 21 (kg/yr)

Teen: 16 (kg/yr)

Child: 6.9 (kg/yr)

BF, = The bioaccumulation factor for radionuclide i, in freshwater fish (pCl/kg per pCl/ liter), from Table A 1 of Regulatory Guide 1.109.

Rev.No. O Page _ZL of ODCM

_ __- _ - _ . . . _ _ _ _ _ , _ _ _ - _ _ _ . . _ ._ _ . _ ~ _ - . _ . . _ _ 1J_ _ _ . . .

DF,, = Dose conversion factor (mrem per pCI ingested) for radionuclide i, for organ and age group of interest, from Tables E-11 through E-14 of Regulatory Guide 1.109.

h C, = The average activity concentration of nuclide I in the effluent ( Cl/ml) at the release point into the lake.

q = The volumetric discharge rate of the effluent (m3 /sec).

q is equal to the total volume of contaminated liquid released (m8 ) divided by the duration of the release.

(X/W) = The annual average relative concentration (sec/m') for the fish ingestion pathway, as shown in Table 3.4.3 for a list of release durations. Release durations were selected to accommodate a change of no more than 20% between consecutive X/Ws.

At = The exposure period which is one year (yr).

O O

Rev.No. O Page 24 of ODCM e P

TABLE 3.4.3 RELEASE INTERVAL VERSUS ANNUAL AVERAGE CONCENTRATION (X/W)

Release (X / * ) (* * * / * *)  :

Duration (days) Fish ingestion Potable Water  !

0.0 3.49E44* 1.84E-04*  !

> 0.0 - 0.5 3.89E 04 1.88E-04  !

> 0.5 - 1.0 4.28E 04 1.92E-04 l

> 1.0 - 1.5 4.68E-04 1.96E-04

> 1.5 - 2.5 5.47E-04 2.04E-04 i > 2.5 - 3.5 6.26E-04 2.12E-04 4 > 3.5 - 5.0 7.44E-04 2.25E-04

> 5.0 - 6.5 8.62E-04 2.37E-04

> 6.5 - 8.5 1.02E-03 2.54E-04

> 8.5 - 11.0 1.22E-03 2.75E-04

> 11.0 - 13.5 1.41E-03 2.95E-04

. > 13.5 - 17.0 1.69E-03 3.24E-04

> 17.0 - 21.0 2.01 E-03 3.57E-04

> 21.0 - 25.5 2.36E-03 3.95E-04

> 25.5 - 31.0 2.80E-03 4.40E-04

> 31.0 - 38.0 3.35E-03 4.98E-04

> 38.0 - 46.0 3.98E-03 5.64E-04

> 46.0 - 56.0 4.77E-03 6.47E 04

> 56.0 - 68.0 5.71E-03 7.46E-04

> 68.0 - 82.0 6.82E-03 8.61 E-04

> 82.0 - 99.0 8.16E-03 1.00E-03

> 99.0 - 119.5 9.77E-03 1.17E-03

> 119.5 - 144.0 1.17E-02 1.37E-03

> 144.0 - 173.5 1.40E-02 1.62E-03

> 173.5 - 209.0 1.68E-02 1.91 E-03

> 209.0 - 251.5 2.02E-02 2.25E-03

> 251.5 - 302.5 2.42E-02 2.67E-03

> 302.5 - 365.0 2.90E-02*

• 3.13E-03**

Instantaneous release (for reference)

• • Continous release O

Rev. No. O Page 25 of ODCM

---y y ..v, e- w-

3.5 Dose Projections - Determination of Need to Operate Liquid Radwaste Treatment System gJ W I 3.5.1 Requirements Technical Specifications, Appendix B, Section 2.4 requires that appropriate subsystems of the liquid radwaste treatment system be used to reduce radioactive material in untreated liquid effluents when the projected monthly dose due to liquid releases to unrestricted areas, averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ. Doses are to be projected at least once per month.

3.5.2 Calculating Methodology The method is based on total body dose and limiting organ dose (liver) as calculated for the Monthly Dose Assessment. The adult is normally the i limiting age group to be used for the dose projection to the total body. The teen is normally the limiting age group to be used for the dose projection to the liver. Other age groups and/or limiting organs may be used if previous i dose calculations indicate that the adult and teen are not the limiting age groups and the liver is not the limiting organ.

The following calculating methodology is provided for performing this dose projection. l

a. Monthly Dose Projection Each month the expected dose to man shall be projected. Projections shall be based on historical or prior month dose / Curie and historical or prior month concentration conversion factors. The historical factors are ,

calculated from historical release data for both a refuel outage year and l a nonrefuel outage year. The current historical factors are on file within the RES Department.

1. Each month make an estimate of the volume of liquid radwaste to be discharged during that month. The following variables should l be considered in estimating radwaste volumes to be released:

(a) Projected plant operational status (run, shutdown, refuel, etc.).

(b) Status of radwaste treatment equipment. Equipment which ,

is inoperable, such as the waste concentrator, should be '

factored into the source term or volume of liquid waste to be discharged from the plant.

O Rev.No. O Page 26 of ODCM j

i-i

(c) ' Additional factors indicating that actual liquid releases could differ significantly in the next month.

(d) Historical liquid waste discharge volumes.

l-i 2. Determine which dose /Cl and Ci/ gal conversion factors should be used. Historical corr /ersion factors can be used. Prior month -

conversion factors may be used if they are more representatue of current release conditions. In the event that there was no release 4

of # quid radwaste during the prior month, then the historical conversion factors em be used if liquid releases are expected during the projection month.

(a) The prior month dose /Ci conversion factors are calculated l by obtaining the results of the prior month adult total body i and teen liver dose MbJatinn.

1

! (b) Divide the doses by the total number of Curies released i from the plant during this same time period. This calculation yields a dose per Curie conversion factor for the adult total body and teen liver for the most recent pnor calendar

month.

i

! (c) The prior month Ci/ gal concentration factor is calculated by -

obtaining the total number of Curies released from the plant i during the prior month. Dwide the Curie total by the total j number of gallons of waste discharged during this same i time period. This calculation yields the Ci/ gal concentration

. conversion factor for the most recent month.

i l 3. Multiply the estimated volume of liquid radwaste to be discharged, by the historical or prior month dose /Ci and Ci/ gal conversion i factors. This calculation yields a dose estimate to the adult total

body and teen liver for the projected month.

! (a) Adult Total Body Dose Dw " T yx C, x Dcw 3

(b) Teen Uver Dose

• TD, = T, x C, x Dc1 iO!

i Rev. No. O Page _2Z_ of ODCM 1

i .

Where: I T, = Total volume of radwaste to be discharged during the O!

month in gallons (estimated)

C, = Curies per gallon conversion factor (historical or prior month)

D. = Dose per Curies adult total body (historica! or prior month) in mrem TD. = Total dose for adult total body in mrem Da = Dose per Curies teen liver (historical or prior month) in  !

mrem TD, = Total dose for teen liver in mrem If the calculated doses are greater than 0.06 mrem to the total ,

body or 0.2 mrem to the liver, the appropriate subsystems of the  !

liquid radwaste system shall be used to reduce the radioactmty levels prior to release.

4 4

b. Batch Dose Projections g The projected dose due to releast of each batch can be made prior to the release of the batch. The projection of the dose related to each batch allows for an accurate method of estimating the dose from each batch prior to release and confirms the need to operate the subsystems of the radwaste system. The projection of dose based on each batch release helps to eliminate any inaccuracies as a result of using historical or estimated values in the monthly projection. The use of this dose projection on a batch release basis is not required by the technical specification and is used at the discretion of the Radiological and Environmental Services Management.

The method is based on total body dose and limiting organ dose (liver) as calculated in step 3.4.2. The adult is the limiting age group for projecting dose to the total body and the teen is the limiting age group for projecting dose to the liver.

The following calculating methodology is provided for performing this dose projection:

1. Obtain the latest result of the monthly calculation of the adult total body and teen liver dose (step 3.4.2).

Rev. No. O Page 28 of ODCM

4 i

2. Dmde the doses by the total number of Curies released from the l

i plant during the month. This yields a dose per Curie conversion 2- factor for the adult total body and teen liver for the most recent

. calendar month, i

! 3. Maintain a running total of the Curies released during the past 30

( days. Add to this the Curie content of the current batch to be l released (31 day total).

1 .

i 4. Multiply the 31 day total from step (3), above by the dose per -

! Curie conversion factors calculated in step (2), above. This yields i the 31 day, total body and liver doses projected for the release of j the current batch.

i

! 5. ' If the calculated doses are greater than 0.06 mrom to the total

! body or 0.2 mrom to the liver, the appropriate subsystems of the 4 i liquid radwaste system shall be used to reduce the radioactuty l l levels prior to release.  :

i c. Continuous Uquid Release Dose Projections t

i j Each month that a continuous liquid release is in progress, or is i anticipated, the expected dose to man can be projected. The

. projection shall be based on historical, prior month or current -

~

l l dose / Curie and nuclide concentration (Curie / gallon) conversion factors.

The historical conversion factors are calculated from prior releases.

l j The prior month conversion factors are calculated from the prior month j- continuous liquid releases if such releases occurred. - Current i i conversion factors are calculated from samples obtained at or near the l beginning of the dose projection month.

i l 1. Determine which dose /Cl and Ci/ gal conversion factors should be -

used. Historical conversion factors can be used. Prior month or i current conversion factors should be used if they are more representative of current release conditions.

{  !

i (a) The current month Cl/ gal concentration is calculated by i using current sample results for radionuclide concentration

!- and converting the results to Ci/ gal.

(b) The current month estimated Curies released is calculated by j'

multiplying the concentration by the known or expected flow rates for the effluent pathway times the period of release.

L ,

l O l l Rev.No. O Page 29_ of ODCM i

T h r

,c

(c) Using the dose assessment methodology specified in secbon 3.4, calculate the adult total body and teen liver doses using known or estimated flow rates and dilution factors. h (d) Divide the doses calculated in section (c) above by the estimated number of Curies to be released. This calculation j yields a dose per Curie conversion factor for the current l release parameters.

i (e) The prior month dose /Ci conversion factors are calculated l by obtaining the results of the prior month adult total body and teen liver dose calculations.

! (f) Divide the doses by the total number of Curies released from the plant via continuous releases during this same time period. This calculation yields a dose per Curie conversion l factor for the adult total body and teen liver for the most  !

recent prior calendar month.

l (g) The prior month Ci/ gal concentration factor is calculated by obtaining the total number of Curies released from the plant via continuous releases during the prior month. Divide the Curie total by the total number of gallons of waste discharged during this same time period. This calmfatinn h:

yields the Cl/ gal concentration conversion factor for the most recent month.

2. Multiply the estimated volume of continuous liquid effluent to be discharged by the historical, prior month or current dose /Cl and Cl/ gal conversion factors. This calculation yields dose estimates l to the adult total body and teen liver for the projected month.

(a) Adult Total Body Dose Dw " T, x C, x Dcw (b) Teen Liver Dose TD, = T, x C, x Dc1 O

Rev. No. O Page 30 of ODCM t r

Where:

T, = Total volume of radwaste to be discharged during the month in gallons (estimated)

C, = Curies per gallon conversion factor (historical, prior month, or current)

D. = Dose per Curies adult total body (historical, prior month, or current) in mrem TD. = Total dose for aduk total body in mrem Da = Dose per Curie teen liver (historical, prior month, or current) in mrem TD, = Total dose for teen liver in mrem if the calculated doses are greater than 0.06 mrem to the total body or 0.2 mrem to the liver or other critical organ, efforts should be made to reduce the effluent release rate or concentration. The dose contribution from liquid batch releases (projected) should be evaluated in addition to continuous release dose.

l l

i O

Rev. No. O Page 31 of ODCM i

4.0 GASEOUS EFFLUENT METHODOLOGY 4.1 Gaseous Waste Streams James A. FitzPatrick Nuclear Power Plant (JAFNPP) discharges gaseous ef-fluents through a stack, and discharges ventilation air from the reactor building, turbine building, radwaste building, and refuel floor through separately monitored vent release points. There are three vent release locations. The refuel floor and reactor building vent is a combined release point. Normal gaseous effluent streams, and effluent discharge points are tabulated in Appendix F, Table F-1.

For the purpose of estimating offsite radionuclide concentrations and radiation doses, radionuclide concentrations are first measured in gaseous effluents and ventilation air exhausted from the plant. Table 3.2-1 of the Technical Specifications, Appendix B and Radiological Effluent Controls, Table 3.2-1 identifies the specific radionuclides in gaseous discharges for which rampling and analysis is done.

4.2 Data Requirements for Gaseous Effluent Calculations Dose calculations to demonstrate compliance with Technical Specifications, Appendix B, Sections 3.2,3.3 and 3.4 are normally performed using historical meteorological data and receptor location (s). Historical meteorological data for use in performing dose calculations are provided in Appendix C. Dose gi calculations to show conformance with Technical Specifications, Appendix B dose limits may be performed using real meteorological data, real receptor locations, and sector wind frequency distribution if desired.

Historical meteorological data factors are calculated and used in dose calculations for the semi-annual Radioactive Effluent Release Report. The report is submitted 60 days after January 1 of each year. The dose assessment sections of this report are submitted 90 days after January 1 of each year as an addendum to the Semi-annual Radioactive Effluent Release Report. Historicalinformation and conservative receptor assumptions, are also used for ease of Technical Specrfications, Appendix B, Limiting Conditions for Operation (LCO) dose limit calculations. JAFNPP uses an elevated release model for stack discharges and mixed mode model for reactor, turbine, radwaste 'and refuel floor vents. Those radionuclides that appear in the gaseous effluent dose factor tables are representative of BWR isotopes that may be considered in dose calculations.

O Rev. No. __Q_ Page 32 of ODCM

4.3 Instantaneous Release Rate and Set Point Determination 4.3.1 Determining instantaneous Noble Gas Rolesse Rates

a. Requirements Technical Specifications, Appendix B, Sechon 3.2.a and Radiological Effluent Controls, Section 3.2.1.c limit the instantaneous dose rate from l noble gases in airbome releases from the plant to <500 mrem /yr - total body, and <3,000 mrem /yr - skin.

The results of the sampling and analysis program of Technical Specrfications, Appendix B, Table 3.2-1 and Radiological Effluent Controls, Table 3.2-1 are used to demonstrate compliance with these limits.

b. Methodology The instantaneous dose rates to the total body and skin from noble gases are evaluated to determine gaseous effluent release rates and alarm and/or trip set points.

The following calculating method is provided for determining the p instantaneous dose rates to the total body and skin from noble gases in all monitored airbome release paths from JAFNPP. Conservatism factors in the instantans.aus v relerce ra^e equations are adequate to account for simultaneous releases from N NMP stack and vent.

JAFNPP discharges gaseous effluents through a stack, and ventilation air from the reactor building, turbine building, radwaste building, and refuel floor through monitored vent release points.

The calculating methods are in accordance with NUREG-0133, October 1978, Section 5.1 and 5.2.

The equations for computing instantaneous dose rates are:

Total Body Dose Rate Vent Eq. 4-1a 4

4 DRg= ,L K x (XJD) x d i i 2=1 i

O Rev. No. O Page _Q3_ of ODCM

Elevated Stack Eq. 4-1b DR 7 ,= , K x (XfC), x i 3 h

.1 = 1 The equations for DRmare to be summed over all vent and elevated stack release sources.

Skin Dose Rate Vent Eq. 4-2a n

DRm = E [L, + 1.1 M;} (XiQ) x 6; l-1 Elevated Stack Eq. 4-2b n

DRm = E [L,(X/Q) +1.1 M,(X/Q),) x d,

/-1 Where:

DRm = Total body dose rate from noble gases in airborne releases, in mrem /sec.

DRm = Skin dose rate from noble gases in airbome releases in mrem /sec.

Ki = The total body dose factor due to gamma emissions for each noble gas nuclide (i) reported in the release source, in mrem-m8/ Cl-sec.

=

h The skin dose factor due to beta emissions for each noble gas nuclide (i) reported in the assay of the release source in mrem-m8/ Cl-sec.

M, = The air dose factor due to gamma emissions for each noble gas nuclide (i) reported in the assay of the release source. The constant 1.1 converts ' mrad' to

' mrem' since the units of M, are in: (mrad-m8/ Cl-sec)

O Rev. No. O Page 34 of ODCM I

1

) (X/O) = For vent or elevated stack releases, the highest annual j average, concentration X/O,' calculated using long i term historic meteorological data, for any land sector,

at or beyond the site boundary, in sec/m8 (Appendix

! C, Table C-1).

1 (X/O), = For elevated stack releases, the highest annual

average, finite cloud X/O, calculated using long term j histonc meteorological data, for any land sector, at or i beyond the site boundary, in sec/m3 (Appendix C, i Table C-2).

i .

i O, = The release rate of noble gas nuclide (i) from the release souros of interest, in pCi/sec.

l The equations for DR are to be summed over all vent and

{ elevated stack release sources.

I j 1. Umited Analysis Approach -Instantaneous Noble Gas

! Release Rate 1 i

) The above methodology can be simpilflod to provide for a rapid s i determination of cumulative noble gas release limits based on the-requirements specified above. For ease of calculation and without i]

j unduly reducing the conservatism of the calculations, all relamaan i may be treated as if discharged from two release points, an

! elevated stack and the reactor 'vont. The :sactor vent is used to .

j represent the combined discharge of the reector building, turbine

! building, radweste building, and refuel floor vents. Beginning with i equations 4-1a and 4-1b, the simpl% proceeds as follows.

1

! From an evaluation of past releases, an effective total body dow -

i factor (K,) can be derived. This dose factor is, in effect, a .

j weighted average total body dose factor (i.e., weighted by the

! radionuclide distribution typical of past operation). See Appendix i E for a detailed explanation and evaluation of K,. The value of K, has been derived from the radioactive noble gas effluents for

the years 1985 through 1991 for the plant.

i

{ To compensate for any unusual variability in the radionuclide i distribution, 3 sigma was added to the average K, values and are i as follows:

1 j K, = 9.27E-5 + 3a

j. = 9.27E-5 + (3 X 4.78E-5)

! = 2.38E-4 (mrom-m*)/(pCi-sec)

! (Vent Releases) i i Rev.No._Q_ Page _35_ of ODCM l

i

-___._..._.___._._.b__._.~...,_m...- . . . . _ .

K, = 1.51E-4 + 3a

= 1.51E-4 + (3 x 4.51E-5) 8

= 2.86E-4 (mrem-m / Cl-sec) g (Stack Releases)

Either of these values, as appropriate, may be used in conjunction I

with the total noble gas release rate (IO,) to verify that the instantaneous dose rate is within the allowable limits. The simplified dose equations are as follows:

Vent Eq. 4-3a n

DRm= Ka x (XIQ) x E 6,

/=1 Elevated Stack Eq. 4-3b n

DRm=Ka x (XIQ), x E D;

/-1 Where: -

DR 73 = Total body dose rate from noble gases in airborne releases, in mrem /sec.

(X/0) = For vent releases, the highest annual average reactor I vent concentration X/O, calculated using long term I historic meteorological data, for any land sector, at or beyond the site boundary, in sec/m8 (Appendix C, Table C-1)

(X/0), = For elevated stack releases, the highest annual average finite cloud X/O, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/m2 (Appendix C, Table C-2)

Ii .

c O, = The total release rate of all noble gas nuclides i=1 from the release source of interest, in Cl/sec.

O Rev. No. O Page _QQ_ of ODCM l

i I

A single cumulative (or gross) noble g,as release O rate limit for elevated stack releases (O stack) 1 V

and vent releases (O vent) may be derived by combining equations 4-3a and 4-3b.

Eq. 4-4a DRm = [K,(vent) x (X/0) x d(vent)] . +

[K,(stack) x (X/0), x d(stack)]

These limits may be determined by taking the highest calculated annual average (X/O),, for elevated stack releases and the highest calculated annual average reactor vent (X/0) for vent releases, at any of the land based sectors, at or beyond the site' boundary. From Appendix C, Tables C-1 and C-2, these values are:

(X/O)., = 1.16E-7 g (Stack Releases) m (X/O) = 3.58-7 q (Reactor Vent Releases) m

, Also, the technical specification dose limit is ,

Drys = 500 mrem /yr = 1.585E-5 mrem /sec. O (stack) was selected by requiring the stack not to yield a dose in excess of 300 mrem /yr or 9.51E-6 mrem /sec.

Eq. 4-4b g ,

DRm (stack)

[K, (stadr) x (X/Q),]

Substituting the preceding values into equation 4-4b, O(stack) = 2.87E5 pCi/sec which was roundea to 3.0E+5 Cl/sec. O(stack) was then substituted into equation 4-4a and solved for O(vent). Therefore, the following are the cumulative (or gross) noble gas release rate limits:

Elevated Stack Release Rate Limit = 3.00E+5 pCi/sec Vent Release Rate Limit = 6.98E+4 pCi/sec O

Rev. No. O Page 37 of ODCM

J As long as the noble gas release rates do not exceed these values (3.00E+5 Cl/sec for elevated stack releases and 6.98E+4 g pCl/sec for vent releases), no additional dose rate calculations are W needed to verify compliance with the instantaneous release rate lirnits of Technical Specifications, Appendix B, Section 3.2.a.1 and Radiological Effluent Controls, Section 3.2.a.c.

2. General Approach - Total Body and Skin Nuclide Specific Instantaneous Release Rate Calculations

The methods described herein may be used for more refined calculations or used if the actual releases exceed the values of

Elevated Stack Release = 3.00E+5 Ci/sec Vent Release = 6.98E+4 pCi/sec Total Body Dose Rate Eq. 4-Sa

. Vent i

1 n

DRm - E K, x (XIQ) x D, hl \

,t l=1 l n

l The equation for DRTs is to be summed over all vent release l sources. l Eq. 4-Sb Elevated Stack i

n

E K x (XIQ), x D, g

^

DRm = /=1 Where:

l DR7 , = Dose rate to the total body due to gamma emissions from all noble gas nuclides, mrem /sec.

Ki = The total body dose factor due to gamma emissions 8

from noble gas radionuclide (i), in mrem-m / Cl-sec (see Appendix B, Table B-2). g Rev. No. O Page 38 of ODCM e

q (X/O) = For vent releases, the highest annual average C/ concentration X/O, calculated'using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/m3(Appendix C, Table C-1).

(X/O), = For elevated stack releases, the highest annual i average finite cloud X/O, calculated using long term historic meteorological data, for any land sector, at or 4 beyond the site boundary, in sec/m3 (Appendix C, l Table C-2).  !

I Stack (X/O)y =

1.16E-7 sec/m8 Vent (X/O) = 3.58E-7 sec/m8 O, = Release rate of the i* nuclide from the release source l of interest, in pCl/sec.

Skin Dose Rate Vent Eq. 44a n

DRm = EI-1 [L, + 1.1 M,) (X/0) x d, The equation for DR m is to be summed over all vent release sources.

Elevated Stack Eq. 4-6b n

DRm = E 'L; (XIQ) + 1.1 Mg (XIQ),' x 6,

/=1 Where:

DR SKIN = Dose rate to skin due to beta and gamma radiation from all noble gas nuclides (mrem / sec).

1 3

= The skin dose factor due to beta emissions from noble gas nuclide (i), in mrsm-m3/pCi-sec (Appendix B, Table B-2).

Rev. No. O Page 39 of ODCM

, A..-- a -- - -- --- - - - - - , .

W j

a k

4 4

k

(

4 4

e 4

O i

f i

1 4

k d

9 4

4 1

.$l

.r 4

! O e

i l

)

i I

i 1

4 1

4 4

4 k

J r

1 4

2 Iil i

a 4

O J

1 4

r 3

A l

M, = The air dose factor due to gamma emissions from noble gas nuclide (i), in mrad-m8/pCi-sec (Appendix B, O Table B-3).

1.1 = Conversion factor for M, from mrad to mrom.

= For vent or elevated stack releases, the highest annual X/O average conceisoi;cn X/O, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/m3 (Appendix

~ C, Table C-1).

(X/Q)., = For elevated stack releases, the highest annual average finite ekxxi X/O, calculated using long term meteorological data, for any land sector, at or beyond the site boundary, in sec/m8 (Appendix C, Table C-2).

',O = Release rate of the i* nuclide from the release source of interest in pCi/sec.

c. Calculating Process ,

The following outline provides a step-by-step explanation of how the total body and skin dose rates are calculated on a nuclide-by-nuclide O. basis to evaluate compliance with Technical Specificer;Ons, Appendix B, Section 3.2 and Radiological Effluent Controls, Section 3.2. This method is used for more refined calculations or if the actual releases exceed the value specified in the Limited Analysis Approach -

Instantaneous Noble Gas Release Rate.

1. For a vent, the X/O value = sec/m8 and is the most limiting land sector at or beyond the site boundary.

For an elevated stack release, the (X/O) value

= sec/m8 and is the most limiting land sector at or beyond the site boundary and the (X/O), value = sec/m8 and is the most limiting land sector at or beyond the site boundary.

2. Enter the release rate in ft3/ min of the release source and convert it to oc/sec;

=( Ift8 x 2.8317E+4 cc x min min ft' 60 sec cc/ c voi"- < i < t-

'O -

Rev. No. _Q_ Page _4Q_ of ODCM

. _ . - , . , ~ . . , , , ___y_,,,- . ,-...,,,,.+,._,-.,s., ,, _ ,

3. Determine b, for nuclide (i) by obtaining the Ci/cc assay value of 3 the release source and multiplying it by the release rate computed W in the previous steps.

",=(

O luci x ( ice cc sec j

. l Q, = Cl/sec for nuclide (i) l

4. To evaluate the total body dose rate, obtain the Ki value for nuclide (i) from Appendix B, Table B-2.

5. Solve for DRm:

Vent

~E DRai = Ki x (XIQ) x b; = p""C/-sec xm*** s x *sec O

l Elevated Stack l

~I DRai = K i x (XIQ), x b; = **I-sec x ***

pC m3 x sec 40 DRm = Total body dose rate from nuclide (i) for the specified release source in mrem /sec

6. To evaluate the skin dose rate obtain the h and M, values from Appendix B Table B-2 for nuclide (i).

7. Solve for DRai:

Vent  !

1 DRm; = {L + i 1.1 M i} (XIQ) x b; O1 l

Rev. No. O Page 41 of ODCM

Elevated Stack O DRa, = L,(Xfd) + 1.1 M (RTd), , x d, i

DRsmNI = Skin dose rate from nuclide (i) for the specified release source, in mrem /sec 1

-i

8. Repeat steps 1 through 7 above for each noble gas nuclide (i) reported in the assay of the release source.

9. The dose rate to the total body from radioactive noble gas gamma radiation from the specified release source is: ,

n E

DRm = I-1 DRm

10. The dose rate to the skin due to noble gas radiation from the ,

specified release source is:

' n E

DRm /=1 DRm ,

The dose rate contribution of this release source shall be added to all other gaseous release sources that are in progress at the time

. of interest.

Technical Specifications, Appendix B, Section 3.2.a.1 and Radiological Effluent Controls, Section 3.2.1.c requires the  :

following.

DR is $500 mrem /yr (1.585E 5 mrem /sec)

DR SMN s3,000 mrem /yr (9.513E 5 mrem /sec)

Where:

DR7 , = The sum of the total body dose rate contributions (mrem /sec) from all noble gas nuclides from all concurrent releases.

O Rev.No. O Page _2_. of ODCM

DR a = The sum of skin dose rate contnbutions (mrem /sec) from all noble gas nuclides from all g concurrent releases. W 4.3.2 Set Point Determination

a. Requirements To comply with Technical Specifications, Appendix B, Section 4.2.a(1),

the alarm / trip set points are established to ensure that the noble gas releases do not exceed the appropriate cumulative (or gross) noble gas release rate limit specified in Umited Analysis Approach - Instantaneous '

Noble Gas Release Rate.

b. Methodology This section describes the methodology for determining alarm / trip set points for the stack and vent gaseous release pathways. To allow for multiple sources of releases from different or common release points, the allowable operating set points will be administratively controlled to allocate a percentage of the total allowable release to each of the release sources. The cumulative noble gas release rate limit for the stack (elevated) release is 3.0E+5 pCl/sec. The individual release rate limits for the other gaseous release points (assumed to be vent g.

releases), are based upon an allocated percentage of the cumulative W vent release rate limit (6.98E+4 Ci/sec).

The sum of the four vent release points cannot exceed 6.98E+4 Ci/sec. The setpoint release rates for the vents follow.

Setpoint Release K-fac*or Setpoint Release Point Rate (uCi/sec) fuCil/(sec-com) Umit (com)

Turbine 42,000 0.56 75,000 Building Reactor 9,600 0.32 30,000 Building Refuel Floor 11,100 0.37 30,000 Radwaste 5,100 0.17 30,000 Building 9

Rev. No. O Page 43 of ODCM

! i i

i lC

U The K-factors for the vents were calculated by multiplying the manufacturer's efficiency for Kr-85,1.11E 8 pCl/(cc-cpm), by the flow

! rate for the release point.

Flow rate K factor

! Release Point (cfm)~ (uCI)/(sec-com)

Turbine Building 107,000 0.56 L

i Reactor Building 61,000 0.32 i

Refuel Floor 70,000 0.37 l

Radwaste 32,000 0.17 l

{ Building i

Stack monitor K-factors are reviewed on a periodic basis. A conservative factor of 2.5 pCi/(sec-cpm) was selected taking into account potential worst case conditions. 'The setpoint limit for the stack 3

i was calculated by dividing the wWit release rate by the K-factor.

j The setpoint limit for the stack follows.

Setpoint Release K-factor Setpoint

) - .

Umit (cos)

Rate (uCi/sec) (uCl)/(sec-cos) i Stack 300,000 2.5 120,000 l

i The total body dose is more limiting than the calculated skin dose.

I Therefore, the skin dose rate calculations are not required if the i simphfied dose rate calculation is used (i.e., using K, to determine i release rate limits).

) The calculating prdcesses of step 4.3.1.c are to be used if the actual

releases of noble gases exceed the predetermined limits of 3.0E+5

! pCi/sec for elevated stack releases or 6.9BE+4 pCl/sec for vent 4 releases.

\

Under these conditions, a nuclide-by-nuclide evaluation is required to evaluate compliance with the dose rate limits of Technical Specifications, Appendix B, Section 3.2.a.1.

i

!O Rev.No. S_. Page 44 of ODCM 1 .

4

4.3.3 Determining the Radiolodine, Trftfum, and Eight Day Particulate Instantaneous Release Rates

a. Requirements Technical Specifications, Appendix B, Section 3.2 and Radiological Effluent Controls, Section 3.2 limit the instantaneous dose rate from 1 131,1-133, tritium, and particulate with half-lives greater than eight days released from the plant to 1,500 mrem /yr to any organ, from the inhalation pathway only.

b. Methodology The following calculating method is provided for determining the dose rate from radiciodines, tritium, and particulate. It is based on NUREG-0133, October 1978, Sections 5.2.1 and 5.2.1.1.

Actual concentrations of lodine-131, lodine-133, and radionuclides in particulate form with half-life greater than 8 days released from the plant in gaseous effluents shall be determined using gamma isotopic analysis.

Tritium and strontium are determined by offsite analysis. Sampling and analysis shall be performed in accordance with frequency specified in Table 3.2-1 of the Technical Specifications, Appendix B and the Radiological Effluents Controls.

The limiting age group is the child, and the limiting organ is the thyroid, per Table B-7.5, Appendix B. Based on an analysis of doses to various organs and age groups for the inhalation pathway, the child was verified as being the controlling age group and the thyroid as being the limiting organ. This pathway is the only one that need be considered for  ;

instantaneous releases. The long term sector average concentration 1 (X/0) values are based on historical meteorological data. Dose factors for nuclides listed in Appendix B, Table B-4 will be used.

Inhalation Pathway The equation for DRi&BDP is to be summed over all release sources (s). r Eq. 4-9 m n DR mp, = E ,E P3 , x (X/ Q) , x D3 ,

S=1 2=1 O

Rev. No. O Page 45 of ODCM s

L

.i

[

Where:

I r = The organ of interest for the age group of interest ,

l (thyroid, child).

l 'O , = Total release rate of 'nuclide (i), (pCi/ sec) for each f

~ release source (s).

DR = Total dose rate to the child thyroid from iodines,  ;

m' tritium, and eight day particulate via the inhalation i pathway (mrem /yr) for all release points p.  !

(X/O), = The long term sector average concentration X/O value based on historical meteorological data in (sec/m8) for l

release source s (Appendix C). l Pg = The dose factor for the inhalation pathway in (mrem /yr -

per pCl/m8) for nuclide (i) (Appendix B, Table B-4).

The derivation of Pi values is given in Appendix B, Table B-7.1.

i m = The number of release sources of interest.

l The maximum allowable release rate of all radiciodines, tritium, and particulate, summed together, is determined by the following relationship: ,

Eq. 4-10

• (FRAC), DR 7ny,oig Oz , f x 0.8 s=1 (X/0), P3 z 7ny,oig; _

l l Where:

DR , = Dose rate to the child's thyroid from the inhalation pathway set equal to the Technical Specifications, Appendix B, Section 3.2.a.2 and Radiological Effluent Controls, Section 3.2.1.c limit of 1,500 mrem / year.

P = The dose factor of I-131 for the inhalation pathway, m) 1.62E+7 mrem /yr per pCl/m3 (Appendix B, Table B-4).

(X/O), = The long term sector average concentration X/Q value for any land sector value based on historical-meteorological data in (sec/m8) for release source s O (Appendix C).

Rev. No. _Q_ Page 46 of ODCM

i

= Maximum allowable release rate of ell radioiodines, W

O, tritium, and particulate summed together in pCi/sec.

(FRAC), = Fraction of 1500 mrem /yr limit allocated to release source s, such that I(Frac), = 1.0.

0.8 = A conservatism factor.

O O

Rev.No. O Page 47 of ODCM

/S 4.4 Dose Determination for Radioactive Gaseous Effluents O

This section addresses the methodologies for calculating the offsite radiation exposures (to all age groups and organs) from radionuclides in the gaseous effluents for the following:

(a) Long-term (routine) releases - Annual dose assessment for inclusion in the semi-annual Radioactive Effluent Release Report (Sec. 4.4.1),

(b) Long-term (routine) releases - Verification of compliance with 10 CFR 50 Appendix 1 (Sec. 4.4.2), and (c) Short term releases (Sec. 4.4.3).

As described in NUREG-0133 (Ref. 6.2, Sec. 3.3), gaseous releases are characterized as "long" or "short" term depending on the frequency and duration of the releases. This characterization forms the basis for more accurate offsite dose assessments by matching the releases with more appropriate atmospheric dispersion and decay conditions.

Long-term gaseous releases refer to releases that are generally continuous and stable, with small fractional variations. Short-term releases, on the other hand, are intermittent or infrequent, with a defined total cumulative duration of 500 b'N hours or less during a calendar year, and no more than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> per quarter; they also include anticipated non-routine operational occurrences.

Offsite radiation doses from short-term releases [ item (c) above), when they occur, are to be incorporated into both the annual dose assessment [ item (a))

and the verification of compliance with regulatory guidelines [ item (b)).

However, routine releases from JAF are essentially all long term and are continuously monitored by stack and vent effluent radiation monitors.

iherefore, short-term releases at JAF are considered to be only unmonitored non-routine releases and are not applicable for definition of the alarm / trip setpoints for the stack and vent efMuent monitors. In addition, in line with NUREG-0133, short-term releases are not used in assessing compliance with the 10 CFR 20 release limits (namely, Sec. 4.3 of the ODCM).

O V

Rev. No. O Page 48 of ODCM

9 4.4.1 Annual Dose Assessment - Radioactive Effluent Release Report Submittal h

a. Requirements Technical Specifications, Appendix B, Section 7.3 requires a semi-annual Radioactive Effluent Release Report be submitted 60 days after January 1 of each year. Technical Specifications also requires that this report includes an assessment of the radiation doses to the public due

! to the radioactive liquid and gaseous effluents released from the unit during the previous calendar year. The dose assessment sections of this report are submitted 90 days after January 1 of each year as an addendum to the Semi-annual Radioactive Effluent Release Report.

b. Methodology l This section provides the methodology to calculate the doses to all age groups and organs from radionuclides identified in the gaseous i effluents.

i The method is based on the methodology suggested by NUREG-0133, l October 1978, Sections 5.3 and 5.3.1. The determination of viable l gaseous dose pathways is described in Appendix B, Table B-7.4. The l site related dose factors for viable pathways are listed in Appendix B. I Dose factors are compiled by age groups, for organs and radionuclides l common to a BWR environment. Normally calculated annual long term historical atmospheric dispersion factors are used to perform the annual dose assessment. Actual meteorological data and sector wind frequency distributions for the year of interest may be used in lieu of the annual long term historical factors.

The following equations provide for a dose calculation to the total body or any organ for a given age group based on actual releases during a specific time interval for radioactive gaseous release sources:

1. Annual Air Dose Due to Noble Gases Vent Eq. 4-11a n

Dm.g, = ,E M3 x (X/Q) x Q3 l=1 I O

Rev. No. O Page 49 of ODCM

l I

Elevated Stack Eq. 4-11b Dm.u, = ,L1 M3 x (X[C), x Q 3 l=1 Where:

Dw = The gamma air dose from radioactive noble gases, in mrad.

M, = The gamma air dose factor for radioactive noble gas nuclide 'i', in mrad-ms/pCl-sec (Appendix B, Table B-3).

(X/0) = The long term historical atmospheric dispersion factors for vent releases (annual average) for the location of interest. Actual meteorological data and sector wind frequency distributions may be

- used to determine annual X/O for the year of interest in sec/m8 (X/Q)., = The long term historical atmospheric dispersion factor for elevated stack releases (annual average) for the location of interest based on the finite cloud methodology. _ Actual meteorological data and sector wind frequency distributions may be used to determine annual X/O for the year of interest in sec/m3 O, = The number of pCi of nuclide 'i' released during the year of interest from the release source of interest.

'Ihe equations for DGamma Air are to be summed over all vent and elevated stack release sources.

Eq.4-12 Daeta-Mr * .

N3 x (~X{Q) x 03 2=1 O

Rev. No. __Q_. Page _.ji(L. of ODCM 9

- , - - - ..-, _.n..,.-,- -_w._, -----.m, . rn,, -y . , - , ,, .c

Where:

Dw,= Beta air dose from radioactive noble gases in mrad.

N, = The beta air dose factor for radioactive noble gas nuclide (i) in mrad-m8/ Cl-sec (see Appendix B, Table B-3). l (X/0) = The long term historical atmospheric dispersion factors for vent or elevated stack releases (annual I average) for the location of interest. Actual l

meteorological data and sector wind frequency I distributions may be used to determine annual X/O for the year of interest in sec/m8 O, = The number of pCl of nuclide 'i' released during the year of interest from the release source of interest.

The equations for DBeta-Air are to be summed over all vent and elevated stack release sources, j

2. Annual Total Body Dose Due to Noble Gases Vent Eq. 4-12a l

n Du= ,E K3 x (X/ Q) x 03 l=1 Elevated Stack Eq. 4-12b i

n D.m = ,E K3 x (X/ 0) , x 03 2=1 Where:

D rs = Total body dose from noble gases in airbome .

releases, in mrem.

K, = The total body dose factor due to gamma emissions for each noble gas nuclide (i) reported in the release source, in mrem-m8/pCi-sec (Appendix B, Table B-2).

Rev. No. O Page 51 of ODCM I

l l

I (X/O) = The long term historical atmospheric dispersion factors for vent or elevated stack releases (annual average) for the location of interest. Actual meteorological data and sector wind frequency distributions may be used to determine annual X/O for 8

the year of interest in sec/m .

(X/O), = The long term historical abucspheric dispersion factor '

for elevated stack releases (annual average) for the location of interest based on the finite cloud methodology. Actual meteorological data and sector wind frequency distributions may be used to determine annual X/O for the year of interest in sec/ma, Qi = The number of microCuries for each noble gas nuclide (i) released during the year of interest from the release ,

source of interest.

The equations for DTB are to be summed over all vent and elevated ,

stack release sources.  ;

3. Annual Total Skin Dose Due to Noble Gases  ;

Vent Eq. 4-12c n .

Dsm " 1=1 .E [Lj + 1.1 Mj] (X/0) x O f Elevated Stack Eq. 4-12d n

Dsm

• 2=1 .E Lj (X/0) + 1.1 Mj (X/0) y- x Oj i

Where: l l

Da = Skin dose from noble gases in airbome releases in mrem.

O Rev. No. _Q_. Page _52_. of.ODCM

1, = The skin dose factor due to beta emissions for each noble gas nuclide (i) reported in the assay of the release source in mrem-m3/pCl-sec (Appendix B, Table B-2).

M, = The air dose factor due to gamma emissions for each noble gas nuclide (i) reported in the assay of the releasa murce. The constant 1.1 converts ' mrad' to

'mrt - 's the units of M, are in mrad-m3/ Cl-sec (Appe .. .3, Table B-2).

(X/0) = The long term historical atmospheric dispersion factors for vent or elevated stack releases (annual average) for the loc $on of interest. Actual meteorological dat ,

sector wind frequency distributions may L ,d to determine annual X/O for the year of interest in sec/m'.

(X/O), = The long term historical atmospheric dispersion factor for elevated stack releases (annual average) for the location of interest based on the finite cloud methodology. Actual meteorological data and sector wind frequency i butions may be used to determine annuan J for the year of interest in sec/m .

O, = The number of microCuries for each noble gas nuclide (i) released during the year of interest from the release source of interest.

The equations for DSKIN are to be summed over all vent and elevated stack release sources.

4. Annual Dose Due to Radiolodines, Tritium, and Eight Day Particulate Inhalation Pathways Eq. 4-13 n

(Dyggop), = ( 3 .17 E-8 ) ,E Rj, x (X/0) x Oj 2=1 Rev.No. O Page 53 of ODCM

4 I

Ground Plane Deposition Pathway Eq. 4-14 n

l (Dyssop), = ( 3 .17 E-8 ) ,E R3 ,x (D/0) x Og 2=1 l

4 Cow's Milk Pathway Eq. 4-15 n

Rj,x (D/0) x 0

! (DJ&BDP), = ( 3 .17 E-8 ) ,E 3

f 1=1 i

Goat's Milk Pathway Eq. 4-16 b n

, (Drasor), = ( 3 .17 E-8 ) ,E Rj,x (D/O) x 0 3 2=1 i

1 Meats Eq. 4-17 iO i n

~

(Dr&8or), = ( 3 .17 E-8 ) ,E Rj,x (D/0) x 0 3 2=1 i

Vegetation Eq. 4-18

e. n I

(Dr&8vr), = ( 3 .17 E-8 ) ,E Rj,x (D/Q) x Oj i l=1 4

For tritium, the dose is calculated by substituting X/O for (D/0) and R for R in equations 4-15 to 4-18.

l 9 i

l O

Rev.No. O Page 54 of ODCM 1

, - - - ~ - - - - - , -,.

---n , , , - , , - - -

.a,-

l 2

l Total Annual Dose From Release Source of interest g

Eq. 4-19a P

D,, = E ig ,op),,

z=1 (D J

Total Annual Dose Eq. 4-196 i

m

, D, = s=1 E. (D,,)

l I

Where: ,

i r = The organ of interest for the age group of interest.

l s = The release source of interest.

z = Pathway of interest.

p = The number of pathways of interest.

O m = Number of release sources of interest.

(Dm), = Annual dose to the organ r for the age group of interest from iodines, tritium, and eight day particulate via the pathway of interest in (mrem).

3.17E-8 = The inverse of the number of seconds per year in (years /sec).

Do = Total annual dose to organ r from all applicable pathways for the age group of interest and for the release source of interest in (mrem).

D, = Total annual dose to organ r from all applicable pathways for the age group of interest and for all release sources of interest in (mrem).

O, =

The number of pCl of nuclide T released during the year of interest from the release source of interest.

O Rev. No. O Page 55_ of ODCM

b 1

1 iO j

a- - '" do ' c*or 'or ""cd- (') 'or ora a < 'or 'a-pathway specified, units vary with pathway. The 4 derivation of R, values is given in Appendix B, Table B-7.2.

i l (D/Q) = The long term historical annual average relative

deposition values for elevated stack or vent releases j for the ground plane deposition pathway. For the i meat, cow, goat, and vegetable pathways, the long term historical grazing average riapamWinn values for j elevated stack and vent releases are used (Appendix l C). A factor with units of m.

which desenbes the deposition of particulate matter from a plume at a i

. point downrange from the source. Actual meteorological data and sector wind frequency j

distribution may be used to determine annual average l

D/O for the year of interest. D/O is not used to j calculate doses associated with H-3 releases.

3 j (X/Q) = The long term historical annual average atmospheric dispersion factors for vent or elevated stack releases for the location of interest (Appendix C). Actual meteorological data and sector wind frequency .

lQ distributions may be used to determine annual X/O for j the year of interest in sec/m3 The X/O is used to determine doses for H-3 releases.

t i

l 4.4.2 Monthly Dose Assessment - Verification of Compilance with 10 CFR 50, j Appendix I i

a. Determining the Gamma Air Dose for Radioactive Noble Gas l

Release Source (s) l 1. Requirement

Technical Specifications, Appendix B, Section 3.3 and Radiological i Effluent Controls, Section 3.3 limit the air dose from gamma j radiation due to noble gases released from the plant in the gaseous j effluent s10 mrad during any calendar year, and s5 mrad in any

calendar quarter.

Technical Specifications, Appendix B, Surveillance Requirement, j- Section 3.3, requires that cumulative air dose contributions from noble gases be calculated at least monthly for the current calendar

] quarter and current calendar year.

i Rev.No._Q_ Page 2L of ODCM i

i*

l 1

2. Methodology g The following calculational method is provided for determining the

, noble gas gamma air dose and is based on NUREG-0133 October 1978 Section 5.3.1. The dose calculation is independent of age group. The equation may be used for Technical Speerfications, ,

Appendix B dose calculations, the dose calculation for the annual 4 report, or for projecting dose, provided that the appropriate value of (X/O) is used. The equation for gamma air dose is:

Vent Eq. 4-20a n

. Dm -Mr

• 2=1 .b M X (X/0) X 01 i

Elevated Stack Eq. 4-20b 1 n Dm.u, = ,E M3 x (X/ Q), x 03 2=1 Where:

4 D %m, = The gamma air dose from radioactive noble gases in mrad.

M, = The gamma air dose factor for radioactive noble

, gas nuclide 'l', in mrad-m3/ Cl-sec (Appendix B, Table B-3).

(X/O' = The highest long term annual average atmospheric dispersion factors for vent releases for any land sector, in sec/m3 (Appendix C, Table C-1).

(X/Q), = The highest long term annual average -

atmospheric dispersion factor for elevated stack releases for any land sector based on the finite cloud methodology, in sec/m3 (Appendix C, Table C-2).

O Rev. No. O Page 57 of ODCM

i The number of pCi of nuclide 'i' released (or n

V O, =

projected to be released) during the dose calculation exposure period (e.g., month, quarter, or year) from the release source of interest.

l The equations for DGamma-Air are to be summed over all vent and i elevated stack release sources.

(a) .Umited Analysis Approach The following limited analysis approach may be used to establish monthly release objectives ( Cl/ month) that will ensure compliance with 10 CFR 50, Appendix ! gamma dose limits.

From an evaluation of past releases, a single effective gamma air dose factor (M,) has been derived, which is representative of the radionuclide abundances and corresponding dose contributions typical of past operation.

(Appendix E has a detailed explanation and evaluation of -

M,). The value of M, has been derived from the radioactive noble gas effluents for the years 1985 through 1991.

To compensate for any unusual variability in the-radionuclide distribution,3 sigma was added to the average M, value, and are as follows.

M, = 9.75E-5 + 3a

= 9.75E-5 + (3 X 4.95E-5)

=

2.46E-4 (mrad-m )/( Ci-sec)

(vent release)

M, = 1.57E-4 + 3a

=

1.57E-4 + (3 X 4.70E-5) 8

=

2.98E-4 (mrad-m )/( Cl-sec)

(stack release)

The effective gamma air dose factor may be used in conjunction with the total noble gas release to simplify the dose evaluation and to verify that the cumulative gamma air dose is within the equivalence of the limits of Technical Specification 3.3 and Radiological Effluent Controls, Section i 3.3.

O ,

Rev. No. _Q_ Page _2L of ODCM i

e

l i

Equations 4-20s and 4-20b can be used to establish monthly release objectives. Combining equations 4-20a a

T

and 4-20b yields the following

Eq. 4-21

Do .,2, = [#,u (vent) x (Y/D) x p(vent)) +

[N.n(scack) x (Y7D), x o(stack))

Technical Speerfications, Appendix B, Section 3.3.a and 1

Radiological Effluent Controls, Section 3.3 state that the doses must be evaluated once per month. The yearly dose limit is 10 mrads, which corresponds to a monthly allotment of 0.83 mrads. 0.83 mrads can be substituted into equation 4-21 for Dw,. The highest calculated annual average 8

(X/0) ,1.16E-7 sec/m , for elevated stack releases and the highes,t calculated annual average reactor vent (X/0),

3.58E-7 sec/m , for vent releases, can be substituted into 4 equation 4-21. O(stack) and O(vent) were selected so that the technical specifications limit of 10 mrad /yr or 0.83 mrad / month would not be exceeded. In addition, O(stack) was selected by requiring the stack not to exceed 80% of 0.83 mrad / month.

"""""~*l' '

O(stack) =

[M,ff (s tack) x (X/ 0) y]

Substituting the preceding values into equation 4-22, yields O(stack) = 1.44E10 Cl/ month. O(stack) was then substituted into equation 4-21 and solved for O(vent).

, Therefore, the following are the cumulative noble gas monthly release objectives.

O(vent release) = 3.77E+9 pCi/ month 4

O(elevated stack release) = 1.44E+10 pCl/ month As long as these values are not exceeded during any month, compliance with the quarterly and annual noble gas release limits of Technical Specifications, Appendix B,

- Section 3.3.a and Radiological Effluent Controls, Section 3.3 is demonstrated. When the limited approach method is used, the calculations of 4.4.2.a(2) must be performed monthly at a minimum.

Rev. No. O Page 59 of ODCM f

i i

The gamma air dose limit does not cause the beta air dose j' limit to be exceeded when the limited analysis approach of this section is used.

/

j b. Determining the Beta Air Dose for Radioactive Noble Gas Release ,

,i Sources i

! The beta air dose calculations of this step are required to be performed r j when the radionuclide specdic dose analysis of Gamma Air Dose is '

1 performed. The radionuclide specific dose analysis is performed at j

least monthly in accordance with Appendix B of the Technical i Specifications.

t

] 1. - Requirement j Technical Specifications, Appendix B, Section 3.3 and Radiological Effluent Controls, Section 3.3 limits the air dose from beta radiation, due to noble gases released from the plant in the gaseous j

effluents, to less than or equal to 20 mrad during any calendar year '

and less than or equal to 10 mrad in any calendar quarter.

i l Technical Specifications, Appendix B, Surveillance Requirement,

• Section 3.3, requires that cumulative air dose contributions from jO i

mobi o rei a'romta gimta ciceito tie tmootair for the current calendar quarter and current calendar year.  :

j When the nuclide specific dose calculation is used to evaluate i j compliance with the gamma air dose limits, the beta air dose shall 3

be evaluated on a nuclide specific basis using the methodology  :

i presented below.

i 2. Methodology i' The.following calculating midicd is provided for determining the i beta air dose and is based on NUREG 0133, October 1978, Section - i 1 5.3.1. The dose calculation is independent of any. age group. The  !

l equation may be used for dose calculations for Appendix B of the

Technical Specifications, semi-annual Radiological Effluent Release Reports, or for projecting dose, provided that the appropriate value  ;

i s

of (X/O) is used.

i l O

~

i Rev. No. _Q_ Page _jQ_ of ODCM b'

_ _ . - _ _ - . . _ , .m. .. - . . _ m . .-. - _ - - , . . . _ _ __ .

l l

? l l The equation for beta air dose is: g Eq. 4-23 t n Du e,.g, = ,E N 3x (~X/0) x Qi 2=1 Where:  !

D u, = Beta air dose from radioactive noble gases in (mrad).

N, = The beta air dose factor for radioactive noble gas nuclide 'i' in mrad m3/ Cl-sec (Appendix B, Table i I

B-3).

(X/O) = For vent or elevated stack releases, the highest annual average, X/O, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/m3 (Appendix C).

O, = The number of Cl of nuclide 'i' released (or projected to be released) during the dose calculation exposure g period from the release source of interest. W The equation for Du, is to be summed over all release sources.

c. Determining the Radiolodine, Tritium, and Eight Day Particulate Dose to any Organ from Cumulative Releases

1. Requirement Technical Specrfications, Appendix B,3.4 and Radiological Effluent l Controls, Section 3.4 limit the dose to the total body or any organ resulting from the release of radioiodines, tritium, and particulate with half-lives greater than eight days released from the plant to less than 7.5 mrem / quarter and less than 15 mrem /yr to any organ.

Technical Specrfications, Appendix B, Surveillance Requirement, Section 3.4, requires that cumulative dose contributions be calculated at least monthly for the current calendar quarter and current calendar year.

O Rev. No. O Page 61 of ODCM i

l I

b-

}

i 4

2. Methodology The following calculating method is provided for determining the j organ dose due to releases of radioiodines (1-131,1-133), tritium, j and particulate with half-lives greater than 8 days it is based on i

NUREG-0133, October 1978, Section 5.3.1. The equations can be 4

used for any age group provided that the appropriate dose factors are used and the total dose reflects only those pathways that are applicable to the age group and the receptor location. The deposition factor, (D/Q), represents the rate of fallout from the

' cloud that affects a square meter of ground at various distances from the site. The total dose to an organ can then be determined i by summing the pathways that apply to the . receptor in the sector, j The equations are:

inhalation Pathway Eq. 4-24 l

i

, n (Drssor), = ( 3 .17 E-8 ) ,E Rj, x (X/0) x Og 2=1 i

Ground Plane Pathway Eq. 4-25 1 n

} (Dr&8vP), = ( 3 .17 E-8 ) ,E Rj,x (D/0) x Og

2=1 l

i Cow's Milk Pathway Eq. 4-26a l

! n 5 (DIsapp), = ( 3 .17 E-8 ) ,E Rj,x (D/0) x Oj 2=1 lj Goat's Milk Pathway Eq. 4-26b D

(D2& sop), = ( 3 .17 E-8 ) ,E Rj, x (ZI/Q) x Oj 2=1 i

i O

! Rev.No. O Page _62 of ODCM

Meats Eq. 4-26c n

(Drusop), = ( 3 .17 E-8 ) ,E Rj, x (370) x 03 2=1 Vegetation Eq. 4-26d n

(Drasor), = ( 3 .17 E-8 ) ,E Rj,x (D/0) x Og 2=1 For tritium, the dose is calculated by substituting X/Q for (D/Q) and R in R equations 4-26a to 4-26d.

8 r

Total Dose From a Release Source for Applicable Pathways Eq.4-27a P

D,, = E ya ,3p),, &

z=1 (D ,

W Total Annual Dose From All Release Sources of Interest Eq.4-27b m

D, = s=1E (D,,)

Where:

r = The organ of interest in a specified age group, s = The release source of interest.

z = The pathway of interest.

p = The number of pathways of interest.

O Rev. No. O Page __Qsl of ODCM

m = The number of release sources of interest.

= Dose in mrom to the organ r of a specified age group (Dw )f from radioiodines, tritium, and 8 day particulate due to a particular pathway. .

D,, = Total dose to organ r from all applicable pathways for a specified age group for the release source of interest in (mrem).

D, = Total dose to organ r from all applicable pathways for a specified age group and for all release sources of interest in (mrem).

3.17E-8 = ..The inverse of the number of seconds per year in (years /sec).

Rg = The dose factor for nuclide (i) organ r of the specified age group. The units are either mrom-m8/yr- Ci for pathways using (X/O), or mrom- ma .sec/yr-pCi for pathways using (D/0) (Appendix B, Tables B 5 and B-6).

(X/0) = The concentration (X/O) value for a specific location where the receptor is located. The units are (sec/m8)

(Appendix C). The X/O is used to determine doses for H-3 releases.

(D/0) = The deposition value for a specific location where the receptor is located. The units are (m 2) (Appendix C).

D/O is not used to calculate doses associated with H-3 releases.

O, = The number of pCl of nuclide (i) released (or projected t6 be released) during the dose calculation exposure period from the release source of interest.

l 1

I l

O Rev. No. Q Page 6L.of ODCM 4

. i

.- .- -- -- .-. - .-_ -- - . . _ , a

4 (a) Umited Analysis Approach Based on an analysis of doses to all organs from all monitored atmospheric release pathways and age groups, the milk pathway has been idontified as the most limiting pathway. The infant's thyroid has been identified as being the most limiting organ and age group. This pathway contributes, on average, over 91 per cent of the total dose received by infant's thyroid and the radiolodines contribute essentially all of this dose. Therefore, it is possible to demonstrate compliance with the dose limit of Techn* cal Specifications, Appendix B, Section 3.4 and Radiological -

Effluent Controls, Section 3.4 for radiolodines, tritium, and particulate with half-lives greater than 8 days by only evaluating the infant's thyroid dose due to radiolodines in the milk pathway.

The calculating method to be used includes a conservatism factor of 0.7 which assures that the calculated dose is always greater than or equal to the actual dose despite possible atypical distributions of radionuclides in the gaseous effluent. The simplified dose equation reduces to:

Eq.4-28a h D,, =

3.17E-8 (1T[Q), 3o'g ngg R,x0, 3 3

/ 0.7 Eq.4-28b m

D, = E D,,

s=1 Where:

D, = Dose in mrem to the infant's thyroid due to radiolodines in the milk pathway for the release source of interest.

D, = Total dose in mrem to the infant's thyroid due to radioiodines in the milk pathway for all release sources of interest.

O Rev. No. ,,_Q Page _fgi_. of ODCM

1 i

a s = The release source of interest.

lk j m = The number of release sources of interest.

1

= For elevated stack releases, O is the total O.

number of microCuries of nuclides released from I the stack during the dose calculation exposure period. For vent releases, O, is the total number l

of microCuries of nuclide i released from the four

! vents during the dose calculation period.

D/O, = The deposition value for a specific location where l the receptor is located in (mi. For elevated i

j stack releases the D/O for the stack will be

! used. For vent releases, the D/O for the reactor l vent will be used.

i i (b) Approach Selection Criteria .

The limited analysis approach may be used for long-term '

(routine) releases to demonstrate compliance with the dose limit of Technical Speerfications, Appendix B, Section 3.4

)p and Radiological Effluent Controls, Section 3.4 (7.5 mrem /qtr and 15 mrem /yr) for radioiodines, tritium, and 1

j particulate.

1 i However, for the dose assessment included in the semi-

! annual Radioactive Effluent Release Report, doses will be -

l evaluated for designated age groups and organs via designated pathways from radioiodines, tritium, and particulates measured in the gaseous effluents according to sampling and analyses required by Technical Specificetion.

4

}

1 i

i O

Rev. No. _Q_ Page _06_ of ODCM i

i i . .

4.4.3 Short Term Releases , ,,

As described in the introductory part to Sec. 4.4 (and in NUREG-0133),

short-term releases are intermittent or infrequent, with a defined total cumulative duration of 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> or less during a calendar year, and no more that 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> per quarter. Radiological impact assessment models for i short-term releases may make use of the long-term atmospheric dispersion factors (as described in Sections 4.4.1 and 4.4.2) if it can be demonstrated that past short-term releases were sufficiently random in both time of day and duration to be represented by the annual average dispersion conditions.

Otherwise, use should be made of the short-term dose equations, as i described below. l

a. Requirements Short-term releases, when they occur, are to be incorporated into the Radioactive Effluent Release Report (s) and the annual dose assessment report (Section 4.4.1) and the verification of compliance with 10 CFR 50 Appendix 1, regulatory guidelines (Section 4.4.2). The following are the Technical Specifications requirements for short-term releases.

1 Technical Specifications, Appendix B, Section 7.3.c requires a semi-annual Radioactive Effluent Release Report be submitted 60 days after 3 January 1 of each year. Technical Specifications also require that this W 4

report includes an assessment of the radiation doses to the public due J

to the radioactive liquid and gaseous effluents released from the unit-during the previous calendar year. The dose assessment sections of 1

this report are submitted 90 days after January 1 of each year as an addendum to the semi-annual Radioactive Effluent Release Report.

Technical Specifications, Appendix B, Section 3.3.a limits the air dose from gamma radiation due to noble gases released from the plant in the gaseous effluent to $10 mrad during any calendar year, and s5 mrad in any calendar quarter.

Technical Specifications, Appendix B, Surveillance Requirement, Section 3.3.a, requires that cumulative air dose contributions from noble gases be calculated at least monthly for the current calendar quarter and current calendar year.

b. Methodology Routine releases via the main stack and vents are continuous. The methodology described below for short-term releases is thus for non-routine unmonitored ground-level releases.

g Rev. No. O Page 67 of ODCM

'N The equations for offsite radiation exposures resulting from short-term releases are similar to those provided for vent releases in Sections 4.4.1 and 4.4.2 above. They are as follows:

1. Air Dose Due to Noble Gases Eq. 4-29 n

D gs,,e m _,1, = ,E M 3 x (x/q) x qi 2=1 Eq. 4-30 i

l D

I Dshorc seca-Air = .E N 3 x (x/q) x qi 2=1 Where:

l l q, = The overall total activity ( Cl) of radionuclide "i" l released (or projected to be released) during the dose l calculation exposure period (month, quarter, or year, l

x as applicable) from a selected vent or unmonitored path, as a result of short-term releases.

1 (x/q) = The short term atmospheric dispersion factor (sec/mi for ground-level releases and the receptor of interest, defined as (from NUREG-0324):

(x/q) = (x/q)meec (t 5 2 hr)

(x/q) = (x/q)%w ec x t* (2 < t1500 hr)

(x/q) = (X/0)w a (t > 500 hr)

Where:

, , los [(X/0)%m/ (x/q)wywl log (8760) t = release duration (hrs) (or the total sum of frequent short-term release durations) during the dose calculation exposure period O

Rev. No. ._Q_ Page __60__ of ODCM

(Note: The limits 2 < t $500 are for annual analysis; for 3 quarterly analysis, they are 2 < t $150) W (X/O)ma = long-term sector average (SA) atmospheric dispersion factor (sec/m ) for ground level releases and the selected receptor, for distances out to 45 miles (from Table C-15 for the site boundary, Table C-18 for annual (all-season) meteorology, and Table C-22 for grazing-season meteorology)

(x/q)% pc = shori-term 85th percentile hourty plume centerline (PC) atmospheric dispersion factor (sec/m*) for ground-level releases and the selected receptor (from Table C-15 for the site boundary, Table C-17 for annual meteorology, and Table C-21 for grazing-season meteorology]

All other parameters have been defined in Section 4.4.1.b.(1).

Short-term gamma air doses are to be added to the long term gamma air doses. Combining equations 4-11a,4-11b, (or g 4-20a, 4-20b for quarterly) and 4-29 results in the following: W Eq. 4-31 l

Duu; m.u, = Do,,,,.u, (STACK) +Dm .u,(Vents) l

+Dssage o,,,,.u, ( Unmoni tored Non-routine Releases)

Short-term beta air doses are to be added to the long term beta air doses. Combining equations 4-12 (or 4-23 for quarterly) and 4-30 results in the following:

Eq. 4-32 Du al u u-us = Duu.u,

+Dano,, uu.u,(Unmonitored Non-routine Releases)

2. Annual Total Body Dose and Skin Dose Due to Noble Gases Die equations for total body dose and skin dose which follow are for use in the preparation of the semi-annual Radioactive Effluent Release Report (described above in Section 4.4.1). They are not applicable for the verification of compliance with 10 CFR 50, Appendix l (Section 4.4.2).

g Rev. No. O Page 69 of ODCM

Eq. 4-32a 2nhose rs

• Kg x (X/q) X qi Eq. 4-32b p,3,,, ,un " IL 4 + 1 1 MJ I X (X/0) X Gl All parameters in Equations 4-32a and 4-32b are as previously defined in Sections 4.1.4.b(2) and 4.4.3.b(1).

Short-term total body and skin doses are to be added to the corresponding doses from long-term releases. Combining Equations 4-12a,4-12b and 4-32a yields the following equation for the total TB dose:

Eq. 4-32c Ducal n " Dn (STACK) +Dn ( VODCB)

+ Dmte n (Unmonitored Non-routine Releases)

Similarly, combining Equations 4-12c,412d and 4-32b for the skin, O vieide:

. Eq. 4-32d Ducal sua

• Dsun (STACA1 + Dsu,(Vents)

+ Dm,e su,(Unmonitored Non-routine Releases)

3. Dose Due to Radiolodines, Tritium, and Eight Day Particulates

! i l Inhalation Pathway Eq. 4-33

! l i I (Ds nore morr), = (3.17 E-8) b Rj,x (x/q) x gj

.f = 1 All parameters have been defined previously. Short-term doses from the inhalation pathway are to be added to the corresponding l long term doses from the same pathway. Combining equations 4-13 (or 4-24 for quarterty) and 4-33 results in the following:

O Rev. No. O Page 70 of ODCM

Eq. 4-34 g

(Ducal usorr), = (D umort is

+ (Dme unorri s (Unmonitored Non-routine Releases) l Ground Plane Deposition Pathway Eq. 4-35

. 1 2

(Dsnan mm), = ( 3 .17 E-8 ) Rj,x (d/q) x gj Where:

(d/q) = The short term deposition factor (1/m*) for ground-level releases and the receptor of interest, defined as:

(d/q) = (d/q)%wpc (t12 hr)

(d/q) = (d/q)%wec x t'" (2 < t 5 500 hr)

(d/q) = (D/Q)ung a (t > 500 hr)

Where:

los [(D/0)m2u/ (d/q),,,,yw]

log (8760) '

{ l t =

release duration (hrs) (or the total sum of frequent short term release durations) during the l dose calculation exposure period (Note: the i limits 2 < t s 500 are for annual analysis; for l l

quarterly analysis, they are 2 < t s 150)

(D/O)ung a = long term sector average (SA) deposition (1/m2 ) l for ground level releases and the selected l' receptor, for distances out to 45 miles (from Table C 16 for the site boundary, Table C-20 for annual (all-season) meteorology, and Table C-24 for grazing-season meteorology) 4 O

Rev,No. O Page 71 of ODCM

(d/q)%pc = short term 85th percentile hourly plume O centerline (PC) deposition factor (1/m*) for ground-level releases and the selected receptor

[from Table C-16 for the site boundary,. _ Table C-19 for annual meteorology, and Table C-23 for grazing-season meteorology)

All other parameters have been defined in Section 4.4.1.b.(4).

Short-term doses from the ground plane pathway are to be added to the corresponding long term doses from the same pathway.

Combining equations 4-14 (or 4-25 for quarterly) with 4-35 results in the following:

Eq. 4-36 (Dnus 1seon}, - (D xseon],

+ (Dmze 1 senn], (Unmonitored Non-routine Releases)

Cow's Milk Pathway Eq. 4-37

!O (Dshore ssoon), = (3.17E-8).1,=1 R3 , x (d/q) x qi All parameters have been defined previously. Short-term doses from the cow's milk pathway are to be added to the corresponding  ;~

long term doses from the same pathway. Combining equations 4-15 (or 4-26a for quarterly) with 4-37 results in the following: ,

Eq. 4-38 1

l

[Dau2 isson}, " (Disson],

+ (Dmre 1seon}, (Unmonitored Non-routine Releases)

D)

L Rev. No. _.Q_ Page Z2_ of ODCM I

l

. _-.---.--.L-----..

Goat's Milk Pathway Eq. 4-39 g W l j

{Dsbozczsever), " (3 D M ) .

Rj,x (W q) x gj 2=1 All parameters have been defined previously. Short-term doses from the goat's milk pathway are to be added to the corresponding long term doses from the same pathway. Combining equations 4-16 (or 4-26b for quarterly) with 4-39 results in the following:

Eq. 4-40

[Due 2 rsever), " (Drseorr),

+ [D,so,e ,sen,7}, (Unmoni tored Non-routine Releases)

Meats Eq. 4-41 )

n (Dshore 1 sever), = ( 3 .17 5-8 ) ,E Rj, x (d/q) x gj 2=1 All parameters have been defined previously. Short-term doses from the meat pathway are to be added to the corresponding long term doses from the same pathway. Combining equations 4-17 (or 4-26c for quarterly) with 4-41 results in the following:

Eq. 4-42

[Ducas rsearr}, * (D,senyy},

+

[Dsso,e 1sso,7}, (Unmanitored Non-routine Re1 eases)

Vegetation Eq. 4-43 (Dg so,essepp7), = (3.17 E-8) , R3 , x (d/q) x gj 2=1 All parameters have been defined previously. Short-term doses from the vegetation pathway are to be added to the corresponding long term doses from the same pathway. Combining equations 4-18 (or 4-26d for quarterty) with 4-43 results in the following:

O Rev. No. O Page 73 of ODCM

Eq. 4-44 (Dwe,2morf,=[Dworf,

+ [Dgso,e ,ssopf, (Unmonitored Non-routine Releases)

For tritium, the dose is calculated by substrtuting x/q for d/q, and R, for R iny Equations 4-37, 4-39, 4-41, and 4-43.

Total Annual Dose From Release Point of Interest Eq. 4 i I

= E D gso ,e, z=1 (D gna,e 3 sepp),,

Short-term doses from unmonitored non-routine releases are to be added to the corresponding long term doses from the stack and  ;

vents. Combining Equations 4-19b (or 4-27b for quarterly) and 4-45, results in the following:

l Total Annual Dose l

Eq. 4-46 02btal,

• OT +O Short, i

l l

l l

'O Rev.No. O Page 74 of ODCM 4

l

, , ..-2. - y...-.c...,

4.5 Dose Projections - Determination of Need to Operate Offgas Radwsste l Treatment System 4.5.1 Requirement Technical Specifications, Appendix B, Section 3.6 as well as Surveillance l

l. Requirements 3.5 of Radiological Effluent Controls requires that doses to gaseous releases from the site be projected at least monthly if the charcoal I beds are not in service when offgas treatment system operation is required. l 4.5.2 Methodology De following calculational method is provided for determining the projected doses. i Eq. 4-47

! =

31 xD x 1. 2 PD, y 1 Eq. 4-48 ,

31 PD, =

x D, x 1. 2 l Eq. 4-49 bA PD,g, = xD zsr X 12 4

Where: I l

PD, = Projected air dose due to noble gas gamma radiation during the current month (mrad) from all routine effluent pathways j PD, = Projected air dose due to noble gas beta radiation during the current month (mrad) from all routine effluent pathways PD, = Projected dose to any organ due to Tritium, lodine-131, lodine-133 and particulates with half-lives greater than 8 days (mrem)

-l 31 = Time period for projection (days)  !

X = Number of days to date during sample period used to project the doses O

Rev.No. O Page 75 of ODCM

~ . - - - - - .. .. .. - - - - - - - .

l l

~

D, = Air dose due to noble gas gamma radiation corresponding to the time period X (mrad)

D, = Air dose due to noble gas beta radiation corresponding to the ~

time period X (mrad) i D, = Organ dose due to lodines, Tritium and Particulates corresponding to the time period X (mrom) 1.2 = Consewatism factor to provide a margin for changes in mixture and operational line up, etc.

A formal dose projection would be based on the most appropriate results of the monthly calculations of the gamma air dose, the beta air dose, and the organ dose due to Tritium, lodines and particulates with half-lives greater than 8 days. The doses calculated will be divided by the number.of days in --

the sample period determined to be most appropriate for projecting doses.

An appropriate period to base projection on should renect similar radioactive release rates effective at the time of the prajar* inn. The per-day doses will be multiplied by 31 days, i.e., the time period for projection. The product is the projeded dose for the coming 31 day period, its value may be adjusted to account for any changes in operating conditions that could significantly

. alter the actual releases, such as failed fuel.

The calculated projected doses, PD,, PD,, and PD, will be compared to the following Technical Specifications, Appendix B, Section 3.6.b and Radiological Effluent Controls, Section 3.5 limits:

0.2 mrad for gamma radiation, 0.4 mrad for beta radiation, or 0.3 mrem to any organ, if any doses exceed the above limits, the offgas charcoal beds will be used whenever the operation bf the offgas treatment system is required during the projected time period.

a. Limited Analysia Approach and Selection Criteria A simpler approach, a linear extrapolation of the most recent three-month dose for the coming month, could be used as long as the limits of Technical Sperficetions, Appendix B, Section 3.6.b and Radiological Effluent Controls, Section 3.5 are not reached, and that releases of .

radioactive material have not changed significantly during the time l period used for projection.

Rev. No. _D._ Page _Z6_ of ODCM I

I 5.0 40 CFR 190 DOSE EVALUATION g

Technical Specifications, Appendix B, Sections 5.1 and 7.3 and Radiological Effluent Controls, Section 4.1 requires that the annual (calendar year) dose or dose commitment to any member of the public from uranium fuel cycle sources be limited to 525 mrem to the total body or any organ (except the thyroid which is limited to s75 mrem). The following approach should be used to  !

demonstrate compliance with these dose limits.

5.1 Evaluation Bases Dose evaluation to demonstrate compliance with the 40 CFR 190 dose limits need only be performed if the quarterly or annual doses calculated in steps 3.4.1,3.4.2,4.4.1,4.4.2, and 4.4.3 exceed twice the dose limits of Technical Specification, Appendix B and Radiological Effluent Controls, Sections 2.3,3.3 or 3.4 respectively. Quarterly doses exceeding 3 mrem to the total body (liquid releases),10 mrem to any organ (liquid releases),10 mrads equivalent gamma i air dose, 20 mrads equivalent beta air dose, or 15 mrem to the thyroid or any l organ from radiciodines and particulates (atmospheric releases) and annual doses exceeding 6 mrem to the total body (liquid releases), 20 mrem to any l organ (liquid releases),20 mrads equivalent gamma air dose,40 mrads equivalent beta air dose, or 30 mrem to the thyroid or.any organ from radio-iodines and particulate (atmospheric releases) would require 40 CFR 190 - g' evaluation. The dose evaluation includes dose contributions to a maximally W exposed real individual from the calendar quarter in which the quarterly or annual limits were exceeded in addition to plant offsite dose contributions q

during the balance of the current calendar year. l 40 CFR 190 dose assessments, when required, will be made using actual meteorological data and frequency distribution data for the year covered by the  !

evaluation.

For purposes of the evaluation, if required, it may be assumed that the dose commitment to the maximally exposed real individual from other uranium fuel cycle sources is negligible. However, doses from JAFNPP will be added to the j doses to the maximum exposed individual at Nine Mile Point Unit 1 and Unit 2, or to the nuclear fuel cycle facilities within a radius 8 km of the site.

O Rev. No. O Page 77 of ODCM

5.2 Doses From Uquid Releases For the evaluation of doses to real indMduals from liquid releases, the same calculating method as employed for Liquid Effluents Annual Dose Assessment will be used. However, more realistic assumptions and any current field data or updated estimates may be used, if available, concoming the dilution and ingestion of fish and potable water by indMduals who live and fish in the area.

Also, the resuits of the Radiological Environmental Monitoring Program will be i included in determining more refined estimates of doses to real indMduals by providing data on actual measured levels of plant-related radionuclides in the l environment.

5.3 Doses From Atmospheric Releases For the evaluation of doses to real indMduals from the atmospheric releases,-

the same calculating methods as employed for Gaseous Effluent Annual Dose Assessment will be used except that the gamma and beta air doses are not calculated. Otherwise the same calculating sequence applies. However, any l current field data or updated estimates may be used, if avaliable, concoming the achial location of real individuals, the meteorological conditions, and the consumption of food (e.g., milk, meat and vegetation). Data obtained from the latest land use census Technical Specrfications, Appendix B, Section 6.2 should be used to determine locations for evaluating doses. Also, the results of the O Radiological Environmental Monitoring Program will be included in determining more refined dose estimates to real individuals by providing data on' actual J

measured levels of radioactMty and radiation at locations of interest.

5.4 Doses From Direct Radiation Because 40 CFR 190 requirements include consideration of the offsite dose contribution from direct radiation, an estimate must be provided in the evaluation. Direct radiation dose contribution from turbine shine and from outdoor facilities containing radioactive material, if applicable, may be estimated by shielding calculations or from the resuits of the environmental monitoring program for direct radiation.

4 O Page ._Z8_. of ODCM Rev. No. _Q_.

l 6.0

6.1 REFERENCES

Regulatory Guide 1.109, Rev.1, October 1977.

g 6.2 NUREG-0133, October 1978.

6.3 Deleted 6.4 Technical Specifications, Appendix B.

6.5 James A. FitzPatrick Nuclear Power Plant, Docket 50-333, Compliance with 10 CFR 50, Appendix l.

6.6 Final Environmental Impact Statement Related to Operation of James A.

FitzPatrick Nuclear Power Plant, New York Power Authority, Docket No. 50-333, March 1973.

6.7 Environmental Report, Operating Ucense Stage, James A. FitzPatrick Plant, New York Power Authority, May 1971.

6.7.1 Supplement Environmental Report, Operating Ucense Stage, November 1971.

6.7.2 Supplement #2 Environmental Report, Benefit / Cost Analysis, May 1972.

g 6.7.3 Supplement #3 Environmental Report, Answers to Atomic Energy Commission Questions, August 1982.

6.8 Final Safety Analysis Report, James A. FitzPatrick Plant, New York Power Authority, Docket No. 50-333, Operating Ucense No. DPR 59.

6.9 New York Power Authority, Intemal Memorandum from D. Dunning to G. Re, September 20,1988.

6.10 New York Power Authority, Corporate Radiological Engineering Calculation No.

JAF-CALC-RAD-00025, Revision 1, Atmospheric Dispersion and Deposition Parameters for Routine Releases (1993).

O Rev.No. O Page ._Z9_ of ODCM

i l

O E

APPENDIX A LIQUID DOSE CALCULATION DATA 1

!O F

0 Rev. No. O Page A-1 -of ODCM

,i,w ,,ve-,, --,-+.. wee,v-r , , - . - - - , - , - , wc.,,-,,,me--, - - - - - .,ww. <w- ---...-.-,.m... . ..-- -,---..<-.,+.--.e,-..,,----.- -..4.=~<- - - .-

i l

APPENDIX A LIQUID DOSE CALCULATION DATA TABLE TITLE PAGE A-1 Unrestricted Area MPC's A-3 A-2 Dose Factors, Umited Analysis Approach A-4 A-3 Dose Factors, All Remaining Pathways A-9 l A-4 Dose Factor Derivation A-18 1

l O\

1 l

l O

Rev. No. O Page A-2 of ODCM l

t . - -

TABLE A-1 MAXIMUM PERMISSIBLE CONCENTRATIONS IN WATER IN UNRESTRICTED AREAS NPC ( Ci/ml) NPC ( Ci/ml) h NUCLIDE' H-3 (Insol.)

3 E-3 (Sol.)

3 E-3 NUCLIDE Ru-103 (Insol.)

8 E-5 (Sol.)

8 E-5 Na-24 3 E-5 2 E-4 Ru-105 1 E-4 1 E-4 P-32 2 E-5 2 E-5 Ru-106 1 E-5 1 E-5 Cr-51 2 E-3 2 E-3 Ag-110m 3 E-5 3 E-5 Mn-54 1 E-4 1 E-4 Sn-113 8 E-5 9 E-5 Mn-56 1 E-4 1 E-4 in-113m 1 E-3 1 E-3 Fe-55 2 E-3 8 E-4 Sb-122 3 E-5 3 E-5 Fe-59 5 E-5 6 E-5 Sb-124 2 E-5 2 E-5 Co-57 4 E-4 5 E-4 St> 125 1 E-4 1 E-4 Co-58 9 E-5 1 E-4 Te-125m 1 E-4 2 E-4 Co-60 3 E-5 5 E-5 Te-127m 5 E-5 6 E-5 Ni-65 1 E-4 1 E-4 Te-127 2 E-4 3 E-4 Cu-64 2 E-4 3 E-4 Te-129m 2 E-5 3 E-5 Zn-65 2 E-4 1 E-4 Te-129 8 E-4 8 E-4 Zn-69 2 E-3 2 E-3 Te-131m 4 E-5 6 E-5 Br-82 4 E-5 3 E-4 Te-131 None None Br-83 3 E-6 3 E-6 Te-132 2 E-5 3 E-5  ;

2 Br-84 None None I130 3 E-6 3 E-6 Br-85 None None I-131 6 E-5 3 E-7 l Rb-86 2 E-5 7 E-5 l-132 2 E-4 8 E-6 l Rb-88 None None I-133 4 E-5 1 E-6 l( Rb-89 None None I-134 6 E-4 2 E-5 Sr-89 3 E-5 3 E-6 l-135 7 E-5 4 E-6 Sr-90 4 E-5 3 E-7 Cs-134 4 E-5 9 E-6 Sr-91 5 E-5 7 E-5 Cs-136 6 E-5 9 E-5 Sr-92 6 E-5 7 E-5 Cs-137 4 E-5 2 E-5 Y-90 2 E-5 2 E-5 Cs-138 None None Y-91m 3 E-3 3 E-3 Ba-139 None None l Y-91 3 E-5 3 E-5 Ba-140 2 E-5 3 E-5 Y-92 6 E-5 6 E-5 Ba-141 None None Y-93 3 E-5 3 E-5 Ba-142 None None i Zr-95 6 E-5 6 E-5 La-140 2 E-5 2 E-5 l Zr-97 2 E-5 2 E-5 La-142 None None  !

Nb-95 1 E-4 1 E-4 Ce-141 9 E-5 9 E-5 Nb-97 9 E-4 9 E.4 Ce-143 4 E-5 4 E-5 Mo-99 4 E-5 2 E-4 Ce-144 1 E-5 1 E-5 Tc-99m 3 E-3 6 E-3 Pr-144 None None l Tc-101 None None W-187 6 E-5 7 E-5 l Np-239 1 E-4 1 E-4 l

l (1) If a nuclide is not listed, refer to 10 CFR 20, Appendk B, and use the most conservative insoluble / soluble MPC where they are given in Table 11, Column 2. All MPC values are taken from

10CFR20, Revised as of January 1,1984.

l (2) None - (As per 10 CFR 20, Appendk B) No MPC limit for any single radionuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half-life of less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Rev. No. O Page _A-1. of ODCM

1 TABLE A-2 DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES Limited Analysis Approach PAGE Freshwater Fish (A m ) - Adult A-5

Potable Water (A,) - Adult A-6 Freshwater Fish (A m ) - Teenager A-7 Potable Water (A,) - Teenager A-8 l

f O

O; Rev. No. O Page A-4 of ODCM  !

l

.- - _ . ~ . . _ . . - . . . . - . . - . . . . - . - - . _ - . . - _ - ...- --. .- .- .

O O O TABLE A-2

.g A,,, VALUES - FRESHWATER FISH - ADULT

% (ares /hr per uCi/ml) l NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY (3 H-3 0 1.89E-02 1.89E-02 1.89E-02 1.89E-02 1.89E-02 0 1.89E-02 Na-24 3.39E 01 3.39E 01 3.39E 01 3.39E 01 3.39E 01 3.39E 01 0 3.39E 01 Cr-51 0 0 6.34E-02 2.34E-02 1.41E-01 2.67E 01 0 1.06E-01 Mn-54 0 3.65E 02 0 1.09E 02 0 1.12E 03 0 6.96E 01 Fe-55 5.49E 01 3.79E 01 0 0 2.11E 01 2.17E 01 0 8.84E 00 Fe-59 8.66E 01 2.03E 02 0 0 5.69E 01 6.78E 02 0 7.80E 01 ,

C0-57 0 1.74E 00 0 0 0 4.43E 01 0 2.90E 00

~

Co-58 0 7.43E 00 0 0 0. 1.51E 02 0 1.67E 01 Co-60 0 2.13E 01 0 0 0 4.01E 02 0 4.71E 01 Cu-64 0 8.31E-01 0 2.09E 00 0 7.08E 01 0 3.90E-01 Zn-65 1.93E 03 6.14E 03 0 4.llE 03 0 3.87E 03 0 2.78E 03 Sr-89 1.84E 03 0 0 0 0 2.96E 02 0 5.29E 01 Sr-90 4.54E 04 0 0 0 0 1.31E 03 0 1.llE 04 Nb-95 3.72E 01 2.07E 01 0 2.05E 01 0 1.26E 05 0 1.llE 01 Zr-95 2.00E-02 6.42E-03 0 1.01E-02 0 2.03E 01 0 4.35E-03 As-76 0 9.46E-01 0 1.78E 00 0 2.29E 03 0 9.04E-01 Nb-95m 3.27E 01 2.07E 01 0 2.05E 01 0 1.26E 05 0 1.11E 01 Zr-97 1.llE-03 2.23E-04 0 3.37E-04 0 6.91E 01 0 1.02E-04 Mo-99 0 8.60E 00 0 1.95E 01 0 1.99E 01 0 1.64E 00

, Tc-99m 7.39E-04 2.09E-03 0 3.17E-02 1.02E-03 1.24E 00 0 2.66E-02 Ag-110m 7.34E-02 6.79E-02 0 1.34E-01 0 2.77E 01 0 4.03E-02 Sb-124 5.59E-01 1.05E-02 1.35E-03 0 4.35E-01 1.59E 01 0 2.21E-01 I-131 1.24E 01 1.78E 01 5.84E 03 3.05E+01 0 4.70E 00 0 1.02E 01 1-133 4.25E 00 7.39E 00 1.09E 03 1.29E 01 0 6.64E 00 0 2.25E 00 n I-135 1.33E 00 3.47E 00 2.29E 02 5.57E 00 0 3.92E 00 0 1.28E 00 cp Cs-13A 2.48E 04 5.91E 04 0 1.91E 04 6.34E 03 1.03E 03 0 4.83E 04 in Cs-137 3.18E 04 4.35E 04 0 1.48E 04 4.91E 03 8.42E 02 0 2.85E 04 y Ba-140 1.62E 01 2.03E-02 0 6.92E-03 1.17E-02 3.34E 01 0 1.06E 00 n La-140 1.25E-02 6.28E-03 0 -

0 0 4.61E 02 0 1.66E-03 Ce-141 1.87E-03 1.26E-03 0 5.87E-04 0 4.83E 00 0 1.43E-04 E Ce-144 9.74E-02 4.07E-02 0 2.41E-02 0 3.29E 01 0 5.23E-03 1 O W-187 2.47E 01 2.06E 01 0 0 0 6.75E 03 0 7.21E 00 8 Np-239 2.37E-03 2.33E-04 0 7.28E-04 0 4.79E 01 0 1.29E-04 e

i

TABLE A-2 A,,, VALUES - POTABLE WATER - ADULT o

y (ares /hr per uC1/al) z NUCLIDE B0NE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY c3 H-3 0 5.29E-02 5.29E-02 5.29E-02 5.29E-02 5.29E-02 0 5.29E-02 Cr-51 0 0 8.02E-04 2.96E-04 1.78E-03 3.37E-01 0 1.34E-03 Mn-54 0 2.30E 00 0 6.86E-01 0 7.06E 00 0 4.39E-01 Fe-55 1.39E 00 9.58E-01 0 0 5.35E-01 5.50E-01 0 2.23E-01 Fe-59 2.19E 00 5.14E 00 0 0 1.44E 00 1.71E+01 0 1.97E 00 Co-57 0 8.83E-02 0 0 0 2.24E 00 0 1.47E-01 Co-58 3.76E-01 0 0 0 7.62E 00 0 8.42E-01 Co-60 0 1.08E 00 0 0 0 2.03E 01 0 2.38E 00 Zn-65 2.44E 00 7.77E 00 0 5.19E 00 0 4.89E 00 0 3.51E 00 Sr-89 1.55E 02 0 0 0 0 2.49E 01 0 4.45E 00 Sr-90 3.82E 03 0 0 0 0 1.10E 02 0 9.38E 02 Zr-95 1.53E-02 4.92E-03 0 7.72E-03 0 1.56E 01 0 3.33E-03 Zr-97 8.47E-04 1.71E-04 0 2.58E-04 0 5.29E 01 0 7.82E-05 Nb-95 3.14E-03 1.75E-03 0 1.72E-03 0 1.06E 01 0 9.38E-04 Mo-99 0 2.17E 00 0 4.92E 00 0 5.04E 00 0 4.13E-01 Ag-110m 8.07E-02 7.46E-02 0 1.47E-01 0 3.05E 01 0 4.43E-02 Sb-124 1.41E 00 2.67E-02 3.42E-03 0 1.10E 00 4.01E 01 0 5.59E-01 I-131 2.10E 00 3.00E 00 9.83E 02 5.14E 00 0 7.92E-01 0 1.72E 00 1-133 7.16E-01 1.25E 00 1.83E 02 2.17E 00 0 1.12E 00 0 3.79E-01 I-135 2.23E-01 5.85E-01 3.86E 01 9.38E-01 0 6.61E-01 0 2.16E-01 Cs-134 3.14E 01 7.46E 01 0 2.42E 01 8.02E 00 1.31E 00 0 6.10E 01 Cs-137 4.02E 01 5.49E 01 0 1.87E 01 6.20E 00 1.06E 00 0 3.61E 01 Ba-140 1.02E 01 1.29E-02 0 4.37E-03 7.36E-03 2.11E 01 0 6.71E-01 La-140 1.26E-03 6.35E-04 0 0 0 4.66E 01 0 1.68E-04 Ce-141 4.72E-03 3.19E-03 0 1.48E-03 0 1.22E 01 0 3.62E-04 5? Ce-144 2.46E-01 1.03E-01 0 6.10E-02 0 8.32E 01 0 1.32E-02 i$ Na-24 8.57E-01 8.57E-01 8.57E-01 8.57E-01 8.57E-01 8.57E-01 0 8.57E-01 3,

Cu-64 0 4.20E-02 0 1.06E-01 0 3.58E 00 0 1.97E-02 33 W-187 5.19E-02 4.34E-02 0 0 0 1.42E 01 0 1.51E-02 Np-239 6.00E-04 5.90E-05 0 1.84E-04 0 1.21E 01 0 3.25E-05 El Tc-99m 1.25E-04 3.52E-04 0 5.35E-03 1.72E-04 2.08E-01 0 4.48E-03 C) As-76 0 2.39E-02 0 4.50E-02 0 5.80E 01 0 2.28E-02 Nb-95m 3.14E-03 1.75E-03 0 1.72E-03 0 1.06E 01 0 9.38E-04

[]

s:

1 O O O

. _ _ _ _ - _ . _ _.m _._.-_-.. __ _ . . _ _ .- ___. ._. . . _ . _ _ _ . _ ._

O O O TABLE A-2 A,,, VALUES - FRESHWATER FISH - TEENAGER

$ (ares /hr per uCi/ml)

Z P NUCLIDE B0NE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY o H-3 0 1.45E-02 1.45E-02 1.45E-02 1.45E-02 1.45E-02 0 1.45E-02 Na-24 3.50E 01 3.50E 01 3.50E 01 3.50E 01 3.50E 01 3.50E 01 0 3.50E 01 Cr-51 0 0 6.08E-02 2.40E-02 1.56E-01 1.84E 01 0 1.09E-01 Mn-54 0 3.59E 02 0 1.07E 02 0 7.35E 02 0 7.llE 01 Fe-55 5.75E 01 4.07E 01 0 0 2.58E 01 1.76E 01 0 9.50E 00 Fe-59 8.92E 01 2.08E 02 0 0 6.57E 01 4.92E 02 0 8.04E 01 Co-57 0 1.81E 00 0 0 0 3.37E 01 0 3.03E 00 Co-58 0 7.39E 00 0 0 0 1.02E 02 0 1.70E 01 Co-60 0 2.14E 01 0 0 0 2.78E 02 0 4.81E 01 Cu-64 0 .8.74E-01 0 2.21E 00 0 6.78E 01 0 4.11E-01 Zn-65 1.75E 03 6.08E 03 0 3.89E 03 0 2.57E 03 0 2.84E 03 Sr-89 2.01E 03 0 0 0 0 2.39E 02 0 5.75E 01 Sr-90 3.78E 04 0 0 0 0 1.06E 03 0 9.35E 03 Nb-95 3.75E 01 2.08E 01 0 2.02E 01 0 8.89E 04 0 1.14E 01 Zr-95 2.07E-02 6.52E-03 0 9.58E-03 0 1.50E 01 0 4.48E-03 As-76 0 1.02E 00 0 1.93E 00 0 1.96E 03 0 9.83E-01 Nb-95m 3.75E 01 2.08E 01 0 2.02E 01 0 8.89E 04 0 1.14E 01 Zr-97 1.19E-03 2.35E-04 0 3.57E-04 0 6.37E 01 0 1.08E-04 Mo-99 0 9.17E 00 0 2.10E 01 0 1.64E 01 0 1.75E 00 Tc-99m 7.57E-04 2.llE-03 0 3.15E-02 1.17E-03 1.39E 00 0 2.74E-02 Ag-110m 7.17E-02 6.78E-02 0 1.29E-01 0 1.91E 01 0 4.13E-02 Sb-124 5.88E-01 1.08E-02 1.33E-03 0 5.14E-01 1.19E 01 0 2.29E-01 I-131 1.33E 01 1.87E 01 5.45E 03 3.21E 01 0 3.69E 00 0 1.00E 01 1-133 4.58E 00 7.77E 00 1.09E 03 1.36E 01 0 5.88E 00 0 2.37E 00 I-135 1.39E 00 3.58E 00 2.30E 02 5.56E 00 0 3.97E 00 0 1.33E 00 Cs-134 2.54E 04 5.99E 04 0 1.90E 04 7.27E 03 7.45E 02 0 2.78E 04

[e Cs-137 3.40E 04 4.53E 04 0 1.54E 04 5.99E 03 6.44E 02 0 1.58E 04 8a-140 1.73E 01 2.12E-02 0 7.17E-03 1.42E-02 2.66E 01 0 1.llE 00

( La-140 Ce-141 1.32E-02 2.02E-03 6.50E-03 1.35E-03 0

0 0

6.35E-04 0

0 3.73E 02 3.86E 00 0

0 1.73E-03 1.55E-04

9. Ce-144 1.06E-01 4.38E-02 0 2.61E-02 0 2.66E 01 0 5.68E-03 O W-187 2.66E 01 2.17E 01 0 0 0 5.87E 03 0 7.61E 00 8 Np-239 2.68E-03 2.52E-04 0 7.92E-04 0 4.06E 01 0 1.40E-04 m

TABLE A-2 33 A., VALUES - POTABLE WATER - TEENAGER y! (arem/hr per uci/ml)

Z 9 NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY c3 H-3 0 3.73E-02 3.73E-02 3.73E-02 3.73E-02 3.73E-02 0 3.73E-02 Cr-51 0 0 7.05E-04 2.78E-04 1.81E-03 2.13E-01 0 1.27E-03 Mn-54 0 2.08E 00 0 6.20E-01 0 4.26E 00 0 4.12E-01 Fe-55 1.33E 00 9.44E-01 0 0 5.99E-01 4.09E-01 0 2.20E-01 Fe-59 2.07E 00 4.83E 00 0 0 1.52E 00 1.14E 01 0 1.86E 00 Ca-57 0 8.39E-02 0 0 0 1.56E 00 0 1.41E-01 Co-F3 0 3.42E-01 0 0 0 4.72E 00 0 7.89E-01 Ce 60 0 9.90E-01 0 0 0 1.29E 01 0 2.23E 00 Zn-65 2.03E 00 7.05E 00 0 4.51E 00 0 2.98E 00 0 3.29E 00 Sr-89 1.55E 02 0 0 0 0 1.85E 01 0 4.44E 00 Sr-90 2.92E 03 0 0 0 0 8.21E 01 0 7.22E 02 Zr-95 1.45E-02 4.58E-03 0 6.73E-03 0 1.06E 01 0 3.15E-03 Zr-97 8.35E-04 1.65E-04 0 2.51E-04 0 4.47E 01 0 7.61E-05 Nb-95 2.30E-03 1.61E-03 0 1.56E-03 0 6.87E 00 0 8.84E-04 Mo-99 0 2.12E 00 0 4.86E 00 0 3.81E 00 0 4.05E-01 Ag-110m 7.22E-02 6.84E-02 0 1.30E-01 0 1.92E 01 0 4.16E-02 Sb-124 1.36E 00 2.51E-02 3.09E-03 0 1.19E 00 2.75E 01 0 5.32E-01 I-131 2.06E 00 2.89E 00 8.42E 02 4.97E 00 0 5.71E-01 0 1.55E 00 1-133 7.08E-01 1.20E 00 1.67E 02 2.llE 00 0 9.09E-01 0 3.66E-01 I-135 2.15E-01 5.53E-01 3.56E 01 8.74E-01 0 6.13E-01 0 2.05E-01 Cs-134 2.95E 01 6.94E 01 0 2.21E 01 8.42E 00 8.63E-01 0 3.22E 01 Cs-137 3.95E 01 5.25E 01 0 1.79E 01 6.94E 00 7.47E-01 0 1.83E 01 Ba-140 1.00E 01 1.23E-02 0 4.16E-03 8.25E-03 1.54E 01 0 6.54E-01 La-140 1.23E-03 6.03E-04 0 0 0 3.46E 01 0 1.60E-04

,3 Ce-141 4.69E-03 3.13E-03 0 1.47E-03 0 8.95E 00 0 3.59E-04 o> Ce-144 2.45E-01 1.01E-01 0 6.06E-02 0 6.17E 01 0 1.31E-02 I! Ha-24 8.60E-01 8.60E-01 8.60E-01 8.60E-01 8.60E-01 8.60E-01 0 8.60E-01 3, Cu-64 0 4.05E-02 0 1.03E-01 0 3.14E 00 0 1.91E-02 da W-187 5.14E-02 4.19E-02 0 0 0 1.13E 01 0 1.47E-02 o Np-239 6.20E-04 5.85E-05 0 1.84E-04 0 9.41E 00 0 3.25E-05

-~

Tc-99m 1.17E-04 3.26E-04 0 4.86E-03 1.81E-04 2.14E-01 0 4.23E-03 C) As-76 0 2.36E-02 0 4.48E-02 0 4.55E 01 0 2.28E-02 h3 Nb-95m 2.90E-03 1.61E-03 0 1.56E-03 0 6.87E 00 0 8.84E-04 s:

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TABLE A-3 DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES All Remaining Pathways Page Lake Shoreline Deposits (Am) - Adult A-10 Lake Shoreline Deposits (Am) - Teenager' A-11 Potable Water (A,) - Child A-12 Freshwater Fish (Am) - Child A-13 Lake Shoreline Deposits (Am) - Child A-14 Potable Water (A,) - Infant A-15 l

Freshwater Fish (Am) '- Infant A-16 Lake Shoreline Deposits (A,) - Infant A-17 O

l i

1 l

4 O

Rev. No. O Page A-9 of ODCM

TABLE A-3 3 A_ VALUES - LAKE SHORELINE DEPOSITS - ADULT E (mres/hr per uC1/ml) z 9 NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY a H-3 0 0 0 0 0 0 0 0 Na-24 3.56E-02 3.56E-02 3.56E-02 3.56E-02 3.56E-02 3.56E-02 4.13E-02 3.56E-02 Cr-51 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.64E-02 1.38E-02 Mn-54 4.13E 00 4.13E 00 4.13E 00 4.13E 00 4.13E 00 4.13E 00 4.85E 00 4.13E 00 Fe-55 0 0 0 0 0 0 0 0 Fe-59 8.13E-01 8.13E-01 8.13E-01 8.13E-01 8.13E-01 8.13E-01 9.55E-01 8.13E-01 Co-57 5.62E-02 5.62E-02 5.62E-02 5.62E-02 5.62E-02 5.62E-02 6.18E-01 5.62E-02 Co-58 1.13E 00 1.13E 00 1.13E 00 1.13E 00 1.13E 00 1.13E 00 1.32E 00 1.13E 00 Co-60 6.42E 01 6.42E 01 6.42E 01 6.42E 01 6.42E 01 6.42E 01 7.55E 01 6.42E 01 Cu-64 1.81E-03 1.81E-03 1.81E-03 1.81E-03 1.81E-03 1.81E-03 2.05E-03 , 1.81E-03 Zn-65 2.23E 00 2.23E 00 2.23E 00 2.23E 00 2.23E 00 2.23E 00 2.56E 00 2.23E 00 Sr-89 6.46E-05 6.46E-05 6.46E-05 6.46E-05 6.46E-05 6.46E-05 7.5 E-05 6.46E-05 Sr-90 0 0 0 0 0 0 0 0 Nb-95 4.08E-01 4.08E-01 4.08E-01 4.08E-01 4.08E-01 4.08E-01 4.80E-01 4.08E-01 Zr-95 7.30E-01 7.30E-01 7.30E-01 7.30E-01 7.30E 01 7.30E-01 8.46E-01 7.30E-01 As-76 1.14E-02 1.14E-02 1.14E-02 1.14E-02 1.14E-02 1.14E-02 3.96E-01 1.14E-02 Nb-95m 5.85E-03 5.85E-03 5.85E-03 5.85E-03 5.85E-03 5.85E-03 3.67E-02 5.85E-03 Zr-97 8.78E-03 8.78E-03 8.78E-03 8.78E-03 8.78E-03 8.78E-03 1.02E-02 8.78E-03 Mo-99 1.19E-02 1.19E-02 1.19E-02 1.19E-02 1.19E-02 1.19E-02 1.38E-02 1.19E-02 Tc-99m 5.47E-04 5.47E-04 5.47E-04 5.47E-04 5.47E-04 5.47E-04 6.27E-04 5.47E-04 Ag-110m 1.03E 01 1.03E 01 1.03E 01 1.03E 01 1.03E 01 1.03E 01 1.20E 01 1.03E 01 Sb-124 1.78E 00 1.78E 00 1.78E 00 1.78E 00 1.78E 00 1.78E 00 2.06E 00 1.78E 00 I-131 5.13E-02 5.13E-02 5.13E-02 5.13E-02 5.13E-02 5.13E-02 6.23E-02 5.13E-02 I-133 7.34E-03 7.34E-03 7.34E-03 7.34E-03 7.34E-03 7.34E-03 8.93E-03 7.34E-03 a I-135 7.66E-03 7.66E-03 7.66E-03 7.66E-03 7.66E 03 7.66E-03 8.94E-03 7.66E-03 N Cs-134 2.05E 01 2.05E 01 2.05E 01 2.05E 01 2.05E 01 2.05E 01 2.39E 01 2.05E 01 3 Cs-137 3.07E 01 3.07E 01 3.07E 01 3.07E 01 3.07E 01 3.07E 01 3.58E 01 3.07E 01

> Ba-140 6.13E-02 6.13E-02 6.13E-02 6.13E-02 6.13E-02 6.13E-02 7.00E-02 6.13E-02 a La-140 5.81E-02 5.81E-02 5.81E-02 5.81E-02 5.81E-02 5.81E-02 6.58E-02 5.81E-02 O Ce-141 4.08E-02 4.08E-02 4.08E-02 4.08E-02 4.08E-02 4.08E-02 4.59E-02 4.08E-02

o. Ce-144 2.07E-01 2.07E-01 2.07E-01 2.07E-01 2.07E-01 2.07E-01 2.39E-01 2.07E-01 O W-187 7.07E-03 7.07E-03 7.07E-03 7.07E-03 7.07E-03 7.07E-03 8.21E-03 7.07E-03 g Np-239 5.20E-03 5.20E-03 5.20E-03 5.20E 03 5.20E-03 5.20E-03 6.02E-03 5.20E-03 s:

O O O

O O O TABLE A-3 (Continued) m A VALUES - LAKE SHORELINE DEPOSITS - TEENAGER l E (ares /hr per uC1/ml) z 9 NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY O H-3 0 0 0 0 0 0 0 0 Na-24 1.98E-01 1.98E-01 1.98E-01 1.98E-01 1.98E-01 1.98E-01 2.31E-01 1.98E-01 Cr-51 7.76E-02 7.76E-02 7.76E-02 7.76E-02 7.76E-02 7.76E-02 9.17E-02 7.76E-02 Mn-54 2.31E 01 2.31E 01 2.31E 01 2.31E 01 2.31E 01 2.31E 01 2.71E 01 2.31E 01 Fe-55 0 0 0 0 0 0 0 0 Fe-59 4.54E 00 4.54E 00 4.54E 00 4.54E 00 4.54E 00 4.54E 00 5.34E 00 4.54E 00 Co-57 3.14E 00 3.14E 00 3.14E 00 3.14E 00 3.14E 00 3.14E 00 3.45E 00 3.14E 00 Co-58 6.31E 00 6.31E 00 6.31E 00 6.31E 00 6.31E 00 6.31E 00 7.39E 00 6.31E 00 Co-60 3.58E 02 3.58E 02 3.58E 02 3.58E 02 3.58E 02 3.58E 02 4.21E 02 3.58E 02 Cu-64 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.14E-02 1.01E-02 Zn-65 1.24E 01 1.24E 01 1.24E 01 1.24E 01 1.24E 01 1.24E 01 1.43E 01 1.24E 01 Sr-89 3.61E-04 3.61E-04 3.61E-04 3.61E-04 3.61E-04 3.61E-04 4.18E-04 3.61E-04 Sr-90 0 0 0 0 0 0 0 0 Nb-95 2.28E 00 2.28E 00 2.28E 00 2.28E 00 2.28E 00 2.28E 00 2.68E 00 2.28E 00 Zr-95 4.07E 00 4.07E 00 4.07E 00 4.07E 00 4.07E 00 4.07E 00 4.72E 00 4.07E 00 As-76 6.38E-02 6.38E-02 6.38E-02 6.38E-02 6.38E-02 6.38E-02 2.21E 00 6.38E-02 Nb-95m 3.27E-02 3.27E-02 3.27E-02 3.27E-02 3.27E-02 3.27E-02 2.05E 01 3.27E-02 Zr-97 4.90E-u2 4.90E-02 4.90E-02 4.90E-02 4.90E-02 4.90E-02 5.70E-02 4.90E-02 No-99 6.65E-02 6.65E-02 6.65E-02 6.65E-02 6.65E-02 6.65E-02 7.70E-02 6.65E-02 Tc-99m 3.05E-03 3.05E-03 3.05E-03 3.05E-03 3.05E-03 3.05E-03 3.50E-03 3.05E-03 Ag-110m 5.73E 01 5.73E 01 5.73E 01 5.73E 01 5.73E 01 5.73E 01 6.68E 01 5.73E 01 Sb-124 9.96E 00 9.96E 00 9.96E 00 9.96E 00 9.96E 00 9.96E 00 1.15E 01 9.96E 00 1-131 2.87E-01 2.87E-01 2.87E-01 2.87E-01 2.87E-01 2.87E-01 3.48E-01 2.87E-01 I-133 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.98E-02 4.09E-02 g I-135 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.99E-02 4.28E-02 o Cs-134 1.14E 02 1.14E 02 1.14E 02 1.14E 02 1.14E 02 1.14E 02 1.33E 02 1.14E 02 Cs-137 1.71E 02 1.71E 02 1.71E 02 1.71E 02 1.71E 02 1.71E 02 2.00E 02 1.71E 02

? Ba-140 3.42E-01 3.42E-01 3.42E-01 S.42E-01 3.42E 01 3.42E-01 3.91E-01 3.42E-01 d La-140 3.24E-01 3.24E-01 3.24E-01 3.24E-01 3.24E-01 3.24E-01 3.67E-01 3.24E-01 Ce-141 2.28E-01 2.28E-01 2.28E-01 2.28E-01 2.28E-01 2.28E-01 2.56E-01 2.28E-01 E Ce-144 1.16E 00 1.16E 00 1.16E 00 1.16E 00 1.16E 00 1.16E 00 1.34E 00 1.16E 00 0 W-187 3.95E-02 3.95E-02 3.95E-02 3.95E-02 3.95E-02 3.95E-02 4.58E-02 3.95E-02 8 Np-239 2.90E-02 2.90E-02 2.90E-02 2.90E-02 2.90E-02 2.90E-02 3.36E-02 2.90E-02 m

TABLE A-3 (Continued) 3 A , VALUES - POTABLE WATER - CHILD y (ares /hr per uC1/ml)

Z 9 NUCLIDE B0NE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY c) H-3 0 7.15E-02 7.15E-02 7.15E-02 7.15E-02 7.15E-02 0 7.15E-02 Cr-51 0 0 1.74E-03 4.76E-04 3.18E-03 1.66E-01 0 3.14E-03 Mn-54 0 3.77E 00 0 1.06E 00 0 3.16E 00 0 1.00E 00 Fe-55 4.05E 00 2.15E 00 0 0 1.22E 00 3.98E-01 0 6.66E-01 Fe-59 5.81E 00 9.41E 00 0 0 2.73E 00 9.79E 00 0 4.69E 00 Co-57 0 1.74E-01 0 0 0 1.42E 00 0 3.52E-01 Co-58 0 6.34E-01 0 0 0 3.70E 00 0 1.94E 00 Co-60 0 1.86E 00 0 0 0 1.03E 01 0 5.49E 00 Zn-65 4.83E 00 1.29E 01 0 8.10E 00 0 2.26E 00 0 7.99E 00 Sr-89 4.65E 02 0 0 0 0 1.80E 01 0 1.33E 01 Sr-90 5.99E 03 0 0 0 0 8.07E 01 0 1.52E 03 Zr-95 4.09E-02 8.99E-03 0 1.29E-02 0 9.37E 00 0 7.99E-03 Zr-97 2.46E-03 3.56E-04 0 5.11E-04 0 5.39E 01 0 2.10E-04 7.93E-03 3.09E-03 2.90E-03 5.71E 00 Nb-95 0 0 0 2.21E-03 Mo-99 0 4.69E 00 0 1.00E 01 0 3.88E 00 0 1.16E 00 Ag-110m 1.90E-01 1.28E-01 0 2.39E-01 0 1.52E 01 0 1.02E-01 Sb-124 3.91E 00 5.07E-02 8.63E-03 0 2.17E 00 2.45E 01 0 1.37E 00 I-131 6.06E 00 6.10E 00 2.01E 03 1.00E 01 0 5.43E-01 0 3.46E 00 I-133 2.09E 00 2.58E 00 4.79E 02 4.30E 00 0 1.04E 00 0 9.76E-01 I-135 6.17E-01 1.llE 00 9.83E 01 1.70E 00 0 8.46E-01 0 5.25E-01 Cs-134 8.25E 01 1.35E 02 0 4.19E 01 1.50E 01 7.29E-01 0 2.85E 01 Cs-137 1.15E 02 1.10E 02 0 3.59E 01 1.29E 01 6.91E-01 0 1.63E 01 Ba-140 2.93E 01 2.57E-02 0 8.35E-03 1.53E-02 1.48E 01 0 1.71E 00 La-140 3.56E-03 1.24E-03 0 0 0 3.47E 01 0 4.19E-04 13 Ce-141 1.40E-02 6.98E-03 0 3.06E-03 0 8.70E 00 0 1.03E-03

$* Ce-144 7.33E-01 2.30E-01 0 1.27E-01 0 5.99E 01 0 3.91E-02 Na-24 2.04E 00 2.04E 00 2.04E 00 2.04E 00 2.04E 00 2.04E 00 0 2.04E 00

}* Cu-64 0 8.63E-02 0 2.09E-01 0 4.05E 00 0 5.21E-02 g W-187 1.51E-01 8.95E-02 0 0 0 1.26E 01 0 4.02E-02 Np-239 1.85E-03 1.33E-04 0 3.84E-04 0 9.83E 00 0 9.34E-05 9- Tc-99m 3.25E-04 6.38E-04 0 9.27E-03 3.24E-04 3.63E-01 0 1.06E-02 O As-76 0 5.36E-02 0 9.44E-02 0 5.43E 01 0 6.80E-02 8 Nb-95m 7.93E-03 3.09E-03 0 2.90E-03 0 5.71E 00 0 2.21E-03 I

O -- - - - -

O O

p (

O U J TABLE A-3 (Continued)

A. VALUES - FRESHWATER FISH - CHILD g (ares /hr per uC1/ml) z 9 NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY c3 H-3 0 1.19E-02 1.19E-02 1.19E-02 1.19E-02 1.19E-02 0 1.19E-02 Na-24 3.80E 01 3.80E 01 3.80E 01 3.80E 01 3.80E 01 3.80E 01 0 3.80E 01 Cr-51 0 0 6.48E-02 1.77E-02 1.18E-01 6.19E 00 0 1.17E-01 Mn-54 0 2.81E 02 0 7.87E 01 0 2.35E 02 0 7.47E 01 Fe-55 7.54E 01 4.00E 01 0 0 2.26E 01 7.41E 00 0 1.24E 01 Fe-59 1.08E 02 1.75E 02 0 0 5.07E 01 1.82E 02 0 8.72E 01 Co-57 0 1.62E 00 0 0 0 1.32E 01 0 3.27E 00 C0-58 0 5.90E 00 0 0 0 3.44E 01 0 1.81E 01 Co-60 0 1.73E 01 0 0 0 9.60E 01 0 5.llE 01 Cu-64 0 8.03E-01 0 1.94E 00 0 3.77E 01 0 4.85E-01 Zn-65 1.80E 03 4.79E 03 0 3.02E 03 0 8.40E 02 0 2.98E 03 Sr-89 2.60E 03 0 0 0 0 1.00E 02 0 7.41E 01 Sr-90 3.34E 04 0 0 0 0 4.50E 02 0 8.48E 03 Nb-95 4.42E 01 1.72E 01 0 1.62E 01 0 3.19E 04 0 1.23E 01 Zr-95 2.51E-02 5.52E-03 0 7.90E-03 0 5.75E 00 0 4.91E-03 As-76 0 9.96E-01 0 1.76E 00 0 1.01E 03 0 1.27E 00 Nb-95m 4.42E 01 1.72E 01 0 1.62E 01 0 3.19E 04 0 1.23E 01 Zr-97 1.51E-03 2.18E-04 0 3.14E-04 0 3.31E 01 0 1.29E-04 Mo-99 0 8.72E 00 0 1.86E 01 0 1.86E 01 0 2.16E 00 Tc-99m 9.08E-04 1.78E-03 0 2.59E-02 9.07E-04 1.01E 00 0 2.95E-02 Ag-110m 8.13E-02 5.49E-02 0 1.02E-01 0 6.53E 00 0 4.39E-02 Sb-124 7.28E-01 9.44E-03 1.61E-04 0 4.04E-01 4.55E 00 0 2.55E-01 1-131 1.69E 01 1.70E 01 5.62E 03 2.79E 01 0 1.51E 00 0 9.67E 00 I-133 5.82E 00 7.20E 00 1.34E 03 1.20E 01 0 2.90E 00 0 2.72E 00 o I-135 1.72E 00 3.10E 00 2.74E 02 4.75E 00 0 2.63E 00 0 1.47E 00 Cs-134 3.07E 04 5.03E 04 0 1.56E 04 5.60E 03 2.71E 02 0 1.06E 04 l"E' Cs-137 4.29E 04 4.10E 04 0 1.34E 04 4.81E 03 2.57E 02 0 6.06E 03

>- Ba-140 2.18E 01 1.19E-02 0 6.21E-03 1.14E-02 1.10E 01 0 1.27E 00 l l' La-140 1.66E-02 5.78E-03 0 0 0 1.61L 02 0 1.95E-03 Ce-141 2.60E-03 1.30E-03 0 5.69E-04 0 1.62E 00 0 1.93E-04 GL Ce-144 1.36E-01 4.27E-02 0 2.37E-02 0 1.llE 01 0 7.28E-03 C) W-187 3.37E 01 2.00E 01 0 0 0 2.81E 03 0 8.97E 00

[?, Np-239 3.44E-03 2.47E-04 0 7.14E-04 0 1.83E 01 0 1.74E-04 s

j

TABLE A-3 (Continued) g A,,,, VALUES - LAKE SHORELINE DEPOSITS - CHILD y (aren/hr per uC1/ml) z 9 NUCLIDE B0NE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY l

o H-3 0 0 0 0  ! 0 0 0 0 Na-24 4.15E-02 4.15E-02 4.15E-02 4.15E-02

• 4.15E-02 4.15E-02 4.82E-02 4.15E-02 Cr-51 1.62E-02 1.62E-02 1.62E-02 1.62E-02 1.62E-02 1.62E-02 1.92E-02 1.62E-02 Mn-54 4.82E 00 4.82E 00 4.82E 00 4.82E 00 4.82E 00 4.82E 00 5.66E 00 4.82E 00 Fe-55 0 0 0 0 0 0 0 0 Fe-59 9.49E-01 9.49E-01 9.49E-01 9.49E-01 9.49E-01 9.49E-01 1.11E 00 9.49E-01 Co-57 6.56E-01 6.56E-01 6.56E-01 6.56E-01 6.56E-01 6.56E-01 7.21E-01 6.56E-01 Co-58 1.31E 00 1.31E 00 1.31E 00 1.31E 00 1.31E 00 1.31E 00- 1.54E 00 1.31E 00 Co-60 7.49E 01 7.49E 01 7.49E 01 7.49E 01 7.49E 01 7.49E 01 8.81E 01 7.49E 01 Cu-64 2.11E-03 2.11E-03 2.11E-03 2.llE-03 2.11E-03 2.11E-03 2.40E-03 2.llE-03 Zn-65 2.60E 00 2.60E 00 2.60E 00 2.60E 00 2.60E 00 2.60E 00 2.99E 00 2.60E 00 Sr-89 7.54E-05 7.54E-05 7.54E-05 7.54E-05 7.54E-05 7.54E-05 8.75E-05 7.54E-05 Sr-90 0 0 0 0 0 0 0 0 Nb-95 4.76E-01 4.76E-01 4.76E-01 4.76E-01 4.76E-01 4.76E-01 5.60E-01 4.76E-01 Zr-95 8.51E-01 8.51E-01 8.51E-01 8.51E-01 8.51E-01 8.51E-01 9.87E-01 8.51E-01 As-76 1.33E-02 1.33E-02 1.33E-02 1.33E-02 1.33E-02 1.33E-02 4.62E-01 1.33E-02 Nb-95m 6.83E-03 6.83E-03 6.83E-03 6.83E-03 6.83E-03 6.83E-03 4.28E-02 6.83E-03 Zr-97 1.02E-02 1.02E-02 1.02E-02 1.02E-02 1.02E-02 1.02E-02 1.19E-02 1.02E-02 Mo-99 1.39E-02 1.39E-02 1.39E-02 1.39E-02 1.39E-02 1.39E-02 1.61E-02 1.39E-02 Tc-99m 6.38E-04 6.38E-04 6.38E-04 6.38E-04 6.38E-04 6.38E-04 7.31E-04 6.38E-04 Ag-110m 1.20E 01 1.20E 01 1.20E 01 1.20E 01 1.20E 01 1.20E 01 1.39E 01 1.20E 01 Sb-124 2.08E 00 2.08E 00 2.08E 00 2.08E 00 2.08E 00 2.08E 00 2.40E 00 2.08E 00 I-131 5.98E-02 5.98E-02 5.98E-02 5.98E-02 5.98E-02 5.98E-02 7.27E-02 5.98E-02 i I-133 8.56E-03 8.56E-03 8.56E-03 8.56E-03 8.56E-03 8.56E-03 1.04E-02 8.56E-03 l u I-135 8.94E-03 8.94E-03 8.94E-03 8.94E-03 8.94E-03 8.94E-03 1.04E-02 8.94E-03

$* Cs-134 2.39E 01 2.39E 01 2.39E 01 2.39E 01 2.39E 01 2.39E 01 2.79E 01 2.39E 01 Cs-137 3.58E 01 3.58E 01 3.58E 01 3.58E 01 3.58E 01 3.58E 01 4.18E 01 3.58E 01

? Ba-140 7.15E-02 7.15E-02 7.15E-02 7.15E-02 7.15E-02 7.15E-02 8.17E-02 7.15E-02 y La-140 6.78E-02 6.78E-02 6.78E-02 6.78E-02 6.78E-02 6.78E-02 7.68E-02 6.78E-02 Ce-141 4.75E-02 4.75E-02 4.75E-02 4.75E-02 4.75E-02 4.75E-02 5.36E-02 4.75E-02

9. Ce-144 2.42E-01 2.42E-01 2.42E-01 2.42E-01 2.42E-01 2.42E-01 2.79E-01 2.42E-01 O W-187 S.25E-03 8.25E-03 8.25E-03 8.25E-03 8.25E-03 8.25E-03 9.57E-03 8.25E-03 8 Np-239 6.06E-03 6.06E-03 6.06E-03 ,

6.06E-03 6.06E-03 6.06E-03 7.02E-03 6.06E-03 m:

O O O

O O O TABLE A-3 (Continued)

A , VALUES - POTABLE WATER - INFANT g (ares /hr per uC1/ml) z NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY c) H-3 0 7.02E-02 7.02E-02 7.02E-02 7.02E-02 7.02E-02 0 7.02E-02 Cr-51 0 0 2.10E-03 4.58E-04 4.08E-03 9.37E-02 0 3.21E-03 Mn-54 0 4.54E 00 0 1.01E 00 0 1.67E 00 0 1.03E 00 Fe-55 3.17E 00 2.05E 00 0 0 1.00E 00 2.60E-01 0 5.47E-01 Fe-59 7.02E 00 1.23E 01 0 0 3.63E 00 5.86E 00 0 4.83E 00 Co-57 0 2.62E-01 0 0 0 8.94E-01 0 4.26E-01 C0-58 0 8.21E-01 0 0 0 2.04E 00 0 2.05E 00 Co-60 0 2.46E 00 0 0 0 5.86E 00 0 5.81E 00 Zn-65 4.20E 00 1.43E 01 0 6.98E 00 0 1.22E 01 0 6.63E 00 Sr-89 5.72E 02 0 0 0 0 1.18E 01 0 1.64E 01 Sr-90 4.22E 03 0 0 0 0 5.27E 01 0 1.07E 03 Zr-95 4.70E-02 1.14E-02 0 1.23E-02 0 5.70E 00 0 8.12E-03 Zr-97 3.37E-03 5.79E-04 0 5.84E-04 0 3.69E 01 0 2.64E-04 Nb-95 9.58E-03 3.94E-03 0 2.83E-03 0 3.33E 00 0 2.28E-03 Mo-99 0 7.75E 00 0 1.16E 01 0 2.55E 00 0 1.51E 00 Ag-110m 2.27E-01 1.66E-01 0 2.37E-01 0 8.59E 00 0 1.09E-01 Sb-124 4.88E 00 7.18E-02 1.29E-02 0 3.05E 00 1.50E 01 0 1.51E 00 I-131 8.19E 00 9.64E 00 3.17E 03 1.13E 01 0 3.44E-01 0 4.24E 00 I-12 2.85E 00 4.15E 00 7.54E 02 4.88E 00 0 7.02E-01 0 1.21E 00 1-135 8.30E-01 1.65E 00 1.47E 02 1.84E 00 0 5.97E-01 0 6.02E-01 Cs-134 8.60E 01 1.60E 02 0 4.13E 01 1.69E 01 4.35E-01 0 1.62E 01 Cs-137 1.19E 02 1.39E 02 0 3.74E 01 1.51E 01 4.35E-01 0 9.87E 00 Ba-140 3.89E 01 3.90E-02 0 9.26E-03 2.39E-02 9.58E 00 0 2.01E 00  ;

La-140 4.81E-03 1.90E-03 0 0 0 2.23E 01 0 4.87E-04 7 Ce-141 1.79E-02 1.09E-02 0 3.37E-03 0 5.65E 00 0 1.28E-03 y Ce-144 6.79E-01 2.78E-01 2.30E 00 0

2.30E 00 1.12E-01 2.30E 00 0

2.30E 00 3.89E 01 2.30E 00 0 3.81E-02 2.30E 00 Na-24 2.30E 00 0

? Cu-64 0 1.39E-01 0 2.35E-01 0 2.85E 00 0 6.43E-02

$ W-187 2.0SE-01 1.43E-01 0 0 0 8.41E 00 0 4.95E-02 Np-239 2.53E-03 2.26E-04 0 4.51E-04 0 6.54E 00 0 1.28E-04.

9. Tc-99m 4.38E-04 9.03E-04 0 9.71E-03 4.72E-04 2.62E-01 0 1.16E-02 C) As-76 0 9.14E-02 0 1.llE-01 0 3.65E 01 0 9.33E-02 8 Nb-95m 9.58E-03 3.94E-03 0 2.83E-03 0 3.33E 00 0 2.28E-03 m:

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Rev. No. O Page A-17 of ODCM

4 TABLE A-4 g

DERIVATION OF UQUID DOSE FACTORS 4

Table Page

A-4.1 Dose Factor (A3) Derivation A-19 A-4.2 Parameters for the Uquid Effluent Pathway A-23 5

3 A-4.3 Justification for Uquid Pathways Used to A-25 Assess Dose to Man J

J 1

1 J

O E

1 4

i 4

I

G Rev. No. O Page A-18 of ODCM

l TABLE A-4.1 O LIQUID DOSE FACTOR (Ag) DERIVATION U

For purposes of calculating the dose contribution to organs of various receptor age groups, a composite dose factor, An, may be used for each radionuclide 1. The composite dose factor, An , is the sum of the freshwater fish, An ,, potable water, A,,

and shoreline deposits pathway, nA , dose factors. A nembodies pathway transfer parameters (e.g., bioaccumulation factors), pathway usage factors, organ dose conversion factors, and dilution factors between the release point and assumed point of exposure pathway. The composite dose factor may be expressed as:

(A-4.1)

A,, = (K, (U,lD,) + K, U, BF,jD,) DF, + (K, Z W T, V a lDa ) (1-eN* ) DE, l Where:

An = is the composite dose parameter for the total body or organ of an age group for radionuclide, i, for all appropriate pathways, mrem /hr per pCi/ml.

K, = is a unit conversion factor,1.14E5 yr-pCl-ml per pCl-br-1 (NUREG-0133).

1 U, = water consumption rate for age group of interest (Table A-4.2).

n U, = freshwater fish consumption rate for age group of interest (Table A-4.2).

l U. =

duration of time an individualis located on the beach (Table A-4.2).

D, = dilution factor which reflects the dilution from the point of release to the nearest potable water intake (Table A-4.2).

D, = diMion factor which reflects the dilution from the point of release to the nearest point assumed for the freshwater fish catch Uable A-4.2).

De = dilution factor which reflects the dilution from the point of release to the nearest point assumed for shoreline deposit (Table A-4.2).

BFi = bioaccumulation factor for radionuclide i, in freshwater fish, pCi/kg per pCl/l, from Table A-1 of Regulatory Guide 1.109.

l Ti = is the radiological half-life of radionuclide, i, in days.

1 Ai = is the radiological decay constant for radionuclide, I, in seed .

W- =

is the shoreline width factor (Table A-4.2).

n T3 = the period of time for which sediment or soil is exposed to the contaminated C) water (Table A-4.2).

Rev. No. O Page A-19 of ODCM

l K, = assumed transf r const nt from wat:r to sedim:nt, in lit:rs/kg per hr as defined in Z.

M, = mass of sediment, in kg/m2 of surface as defined in Z. g 2

Z = K, x M, x (24/.693), in i per m -day (Table A-4.2).

l DF, = dose conversion factor for radionuclide, i, for organ and age group of interest. Used to calculate the radiation dose from an intake of a radionuclide, mrem /pCi (Regulatory Guide 1.109, Tables E-11 to E-14).

! DE, = dose conversion factor for radionuclide, i, for organ and age group of interest. Used to calculate the radiation dose from an externai exposure of a radionuclide, mrem /hr per pCl/m (Regulatory Guide 1.109, Table E-6).

Examole Calculation:

1. Potable Water l The potable water pathway dose factor, A%, is calculated from Equation A-4.1 by setting the usage factors for freshwater fish and shoreline deposits equal to zero. Equation A-4.1 reduces to the following:

Au = K, (U,lD,) DF, For Co-60, the total body dose factor for an adult due to the ingestion of potable water is l

DF, = 4.72E-06 mrem /pCl  !

U, = 730 liters /yr D, = 165 K, = 1.14E5 yr-pCl-ml per pCl-hr-l These values yleid an A, factor of 2.38 mrem /hr per Cl/ml as listed in Table A-2 of this appendix.

O Rev. No. O Page A-20 of ODCM

ll. ~ Freshwater Fish -

The freshwater fish pathway dose factor, A , is calculated from Equation A-4.1 O by setting the usage factors for potable water and shoreline deposits equal to -

zero. Equation A-4.1 reduces to the following:

A,,, - K, (U, BF,JD,) DF, For Co40, the total body dose factor for an adult due to the ingestion of freshwater fish is:

DF, = 4.72E-06 mrem /pCl U, = 21 kg/yr D, = 12 BF, = 50 pCl/kg per pCl/l .

K, = 1.14E5 yr-pCl-ml per Cl-br-l These values yield an A g factor of 47.1 mrem /hr per Cl/ml as listed in Table A-2 of this appendix.

O 111. Lake Shoreline Deposits The shoreline deposits pathway dose factor, A , is calculated from Equation A-4.1 by setting the usage factors for potable water and freshwater fish equal to zero. Equation A-4.1 reduces to the following:

I A,,,, = (K, Z W T, ValDa) ( 1-e ** *) DE, For Co-60, the total body dose factor for an adult from shoreline deposits is:

U = 12 hrs /yr D = 18 W = 0.30 l-Ti = 1.92E3 days T3= 15 years or 4.73E8 see t

Rev. No. O Page A-21 'of ODCM

[.

, -. m.,

K, = 1.14E5 yr-pCi-ml per Ci-hr-l Z = 100 I per m*-day O

11 = 4.2E-9 sec" DE, = 1.70E-8 mrem /hr per pCl/m (Regulatory Guide 1.109, Table E-6) l l These values will yield and A,, factor of 64.2 mrem /hr per pCl/ml as listed in Table AG of this appendix.

l l

1 O l

t O

Rev. No. O Page A-22 of ODCM

TABLE A-4.2 q PARAMETER FOR THE LIQUID EFFLUENT PATHWAY j V l PARAMETER VALUE REFERENCE TABLE U, (liters /yr)-Potable Water /

- infant 330 R.G.1.109 E-5

- child 510 R.G.1.109 E-5

- teen 510 R.G.1.109 E-5

- aduit 730 R.G.1.109 E-5 U, (kg/yr)-Freshwater Fish /

- infant 0 R.G.1.109 E-5

- child 6.9 R.G.1.109 - E-5

- teen 16 R.G.1.109 E-5

- adult 21 R.G.1.109 E-5 U (hr/yr)-Lake Shoreline p Deposits /

V ' E-5

- infant 0 R.G.1.109

- child 14 R.G.1.109 E-5

- teen 67 R.G.1.109 E-5 aduit 12 R.G.1.109 E-5 BF, (pCl/kg per pCi/l)- Each R.G.1.109 A-1 Freshwater Fish Radionuclide D (dimensionless)-Potable 165 Site Specific Water (JAF FSAR Fig.16.1-19)

D, (dimensionless)-Freshwater 12 Site Specific Fish (JAF FSAR Fig.16.1-19) ,

l 1

D (dimensionless)-Lake 18 Site Specific Shoreline Deposits (JAF FSAR Fig.16.1-19)

O Rev. No. O Page A-23 of ODCM

TABLE A-4.2 (Continued)

PARAMETER FOR THE LIQUID EFFLUENT PATHWAY PARAMETER VALUE REFERENCE TABLE DF, Potable Water / Freshwater Each R.G.1.109 E-11 to Fish (mrem /pCi) Radionuclide E-14 DE, Lake Shoreline Deposits Each R.G.1.109 E-6 (mrem /hr per pCi/m ) Radionuclide Z (1 per m'-day)-Lake 100 R.G.1.109 pg 1.109-14 Shoreline Deposits W (dimensionless)-Lake 0.3 R.G.1.109 A-2 Shoreline Deposits T3 (sec)-Lake Shoreline 4.73E8 R.G.1.109 E-15 Deposits Transit Time (hours)- 31 Site Specific Potable Water (Based on a current speed of 0.4 ft./sec JAF FSAR Fig.16.1-19) h Transit Time (hours)- 0 Site Specific Freshwater Fish (JAF FSAR Fig.16.1-19)

Consumption Transit Time (hours)- 2.9 Site Specific Lake Shoreline Deposits (JAF FSAR Fig.16.1-19)

Location of maximally exposed individual for potable water is Oswego, 8.5 miles west of JAF discharge. Location of maximally exposed individual for freshwater fish consumption is the JAF discharge vicinity. Location of maximally exposed individual for lake shoreline deposits is Sunset Bay,0.8 miles east of JAF discharge. 1 1

O.I Rev. No. O Page A-24 of ODCM

~

J k

. TABLE A-4.3 JUSTIFICATION FOR UQUID PATHWAYS USED TO ASSESS DOSE TO MAN

, PATHWAY JUSTIFICATION FOR OMISSION OR INCLUSION I

1

1. POTABLE WATER This pathway is considered for all required analysis.

l j 2. FRESHWATER FISH This pathway is considered for all required analysis.

l l 3. FRESHWATER SHELL This pathway was not considered for the a; qual

deze calculations and the 40CFR190 dose analysis.

Reference 6.9 states that direct ingestion of aquatic invertebrates from Lake Ontario is not a common

practice.

4. FRESHWATER PLANTS No known pathway exists for the J.A. FitzPatrick plant and none is included in the dose analysis of References 6.5 through 6.8. Regulatory Guide 1.109, Appendix E, Section 2, page 1.109-36, states

" Ingestion of aquatic plant materialis not normally assumed."

./3 Not applicable to a freshwater site.

lV 5. SALTWATER FISH

6. SALTWATER SHELL Not applicable to a freshwater site.

FISH l

7. SALTWATER PLANTS Not applicable to a freshwater site.

. 8. DISCHARGE CANAL This pathway is not applicable since SHOREUNE the J.A. FitzPatrick Plant discharges through a tunnel to a diffuser offshore.

Not applicable to a Great Lake site.

9. RIVER SHOREUNE DEPOSITS I

10. LAKE SHOREUNE This pathway is not necassary to l DEPOSITS demonstrate compliar'.:e with 10CFR20 and

10CFR50 as specifie0 in Sections 4.2, and 4.3.1 of NUREG4133. This pathway is considered for the

< annual dose calculations, the 40CFR190 dose 1 analysis, and Section 3.4.2.b (1).

4

11. OCEAN SHOREUNE Not applicable to a Great Lake Site.

O DEPOSES Rev. No. O Page A-25 of ODCM l

i

TABLE A-4.3 (Continued)

JUSTIFICATION FOR LIQUID PATHWAYS USED TO ASSESS DOSE TO MAN PATHWAY JUSTIFICATION FOR OMISSION OR INCLUSION O

12. TIDAL BASIN Not applicable to a Great Lake site.

DEPOSITS

13. SWIMMING This pathway is not necessary to demonstrate compliance with 10CFR20 and 10CFR50 as specified in Sections 4.2, and 4.3.1 of NUREG-0133. This pathway is not used in the ODCM since its dose contribution is very small (Appendix D, ,

Table D-8).

14. BOATING This pathway is not necessary to demonstrate l compliance with 10CFR20 and 10CFR50 as l specified in Sections 4.2, and 4.3.1 of NUREG-0133. This pathway is not used in the ODCM since its dose contribution is very small (See Appendix D, Table D-8).

15. STORED FRUITS There are two possible methods of AND VEGETABLES establishing this pathway; by using water from the h, lake for irrigation or using well water for inigation, j which may have become contaminated through I discharges to the lake. References 6.6 and 6.7 I I

document that a limited irrigation pathway exists-however, Reference 6.5 states that recent surveys indicate that the irrigation pathways discussed in the other documents no longer use lake water for irrigation. Since Reference 6.5 is the most recent document it is concluded that the irrigation pathway does not exist and need not be considered in any dose analysis. References 6.5 through 6.8 state that the possibility of groundwater contamination is extremely remote and no impact on groundwater is expected.

16. FRESH FRUITS This pathway need not be considered.

AND VEGETABLES See justification for pathway 15.

17. MEAT (CONTAMI- This pathway need not be considered.

NATED FORAGE) Se justification for pathway 15.

Rev. No. O Page A-26. of ODCM

TABLE A-4.3 (Continued)

JUSTIFICATION FOR LIQUID PATHWAYS USED TO ASSESS DOSE TO MAN PATHWAY JUSTIFICATION FOR OMISSION OR INCLUSION

18. MEAT (CONTAMI- This pathway need not be considered.

NATED FEED) See Justification for pathway 15.

19. MEAT (CONTAMI- This pathway is not necessary to NATED WATER) demonstrate compliance with 10CFR20 and 10CFR50 as specified in Section 4.2 and 4.3.1 of NUREG-0133. The dose calculations shown in References 6.5 through 6.8 do not consider this pathway as a part of the analysis; hence, it is concluded that this pathway is insignificant and E need not be considered for annual and 40CFR190 dose calculations.

20. COWS MILK This pathway need not be considered.

(CONTAMINATED See justification for pathway 15.

FORAGE)

21. COWS MILK This pathway need not be considered.

E O (CONTAMINATED FEED)

See justification for pathway 15.

22. COWS MILK This pathway need not be considered.

(CONTAMINATED See justification for pathway 19.

WATER)

23. GOATS MILK This pathway need not be considered.

(CONTAMINATED See justification for pathway 15.

FORAGE)

24. GOATS MILK This pathway need not be considered.

(CONTAMINATED See justification for pathway 15.

FEED)

25. GOATS MILK This pathway need not be considered.

(CONTAMINATED See justification for pathway 19.

WATER)

O Rev. No. O Page A-27 of ODCM l

O APPENDIX B GASEOUS DOSE CALCULATION DATA O

O Rev.No. O Page B-1 of ODCM

i t

APPENDIX B

O GASEOUS DOSE CALCULATION DATA l

i a

TABLE TITLE PAGE B-1 Unrestricted Area MPC's B-3 B-2 Noble Gas Data Transfer Factors (K, i ()

B-4 B-3 Air Dose Transfer Factors (Mi , N)i B-5 i

B-4 inhalation Environmental Pathway Dose B-6 Conversion Factors (P,) - Instantaneous 5

B-5 Child Umited Analysis Approach - Gaseous B-7 l Discharge Environmental Pathway Dose Conversion Factors (R,)

B-6 Environmental Pathway Dose Conversion B-9 i

Factors (R,) for All Remaining Pathways lO i.

B-7 Derivation of Gaseous Dose Factors . B-31 1

i 4

i l

]

I-l 1

O Rev. No. O Page 3-2_ of ODCM

-o.g., v.-- n

TABLE B-1 MAXIMUM PERMISSIBLE CONCENTRATIONS IN AIR IN UNRESTRICTED AREA g NUCIJDE%Y i MPC6 uCr/cc NUCLIDEI MPC uCI/cc Ar-41 4 E-8 Y-91 1 E-9 Kr-83m 3 E-8 Zr-95 1 E-9 Kr-85m 1 E-7 Nb-95 3 E-9 Kr-85 3 E-7 Ru-103 3 E-9 Kr-87 2'E-8 Ru-106 2 E-10 Kr-88 2 E-8 Ag-110m 3 E-10 Kr-89 3 E-8 Sn-113 2 E-9 Kr-90 3 E-8 In-113m 2 E-7 Xe-131m 4 E-7 Sn-123 1 E-10 Xe-133m 3 E-7 Sn-126 1 E-10 Xe-133 3 E-7 Sb-124 7 E-10 Xe-135m 3 E-8 Sb-125 9 E-10 Xe-135 1 E-7 Te-125m 4 E-9 Xe-137 3 E-8 Te-127m 1 E-9 Xe-138 3 E-8 Te-129m 1 E-9 H-3 2 E-7 I-130 1 E-10 P-32 2 E-9 I-131 1 E-10 Cr-51 8 E-8 I-132 3 E-9 Mn-54 1 E-9 I-133 4 E-10 Fe-59 2 E-9 I-134 6 E-9 Co-57 6 E-9 I-135 1 E-9 Co-58 2 E-9 Cs-134 4 E-10 Co-60 3 E-10 Cs-136 6 E-9 Zn-65 2 E-9 Cs-137 5 E-10 Rb-86 2 E-9 Ba-140 1 E-9 Sr-89 3 E-10 La-140 4 E-9 Sr-90 3 E-11 Ce-141 5 E-9 Rb-88 3 E-8 Ce-144 2 E-10 (1) Appendix If B, a and nuclide is not use the listed, most refer to 10insoluble conservative CFR 20,luble

/so MPC '

where they are given in Table II, Column 1.

Ref.10 CFR Part 20, Appendix B, Table II, Column 1.

O Rev.No. O Page _B.;L ti ODCM

TABLE B-2 TRANSFER FACTORS FOR MAXIMUM DOSE TO A

\ PERSON OFFSITE DUE TO RADIOACTIVE NOBLE GASES Dose Transfer Factors i

5,'~. . ,;.- r y ,,

, {p s GAM 4A "B TA ' GAMMA:+' BETA

?.'

K'i"> .(L + 1.1 M)i-

.t RADIONUCLIDE"*

mremi .nrem mrem uCi?sec/m3 .uCissec/m3- uCi sec/m3 Kr-83m 2.4E-9 --

6.7E-7 '

Kr-85m 3.7E-5 4.6E-5 8.9E-5 Kr-85 5.1E-7 4.2E-5 4.3E-5 Kr-87 1.9E-4 3.1E-4 5.3E-4 Kr-88 4.7E-4 7.5E-5 6.0E-4 Kr-89 5.3E-4 3.2E-4 9.3E-4 O' Kr-90 Xe-131m 4.9E-4' 2.9E-6 2.3E-4 1.5E-5 8.0E 2.0E-5 Xe-133m 8.0E-6 3.1E-5 4.2E Xe-133 9.3E-6 9.7E-6 2.2E-5 Xe-135m 9.9E-5 2.3E-5 1.4E-4 .

Xe-135 5.7E-5 5.9E-5 1.3E-4 Xe-137 4.5E-5 3.9E-4 4.4E-4  !

Xe-138 2.SE-4 1.3E-4 4.5E-4 Ar-41 2.8E-4 8.5E-5 4. 0 E -4 Ref: Regulatory ' Guide 1.109, Revision 1, Table B-1.

1 O

Rev. No. O Page J__ of ODCM

i TABLE B-3 l

! TRANSFER FACTORS FOR MAXIMUM OFFSITE AIR DOSE Air Dose Transfer Factors GAMMA BETA Mj Ni RADIONUCLIDE mrad mrad uCi sec/m3 uCi sec/m3 f

Kr-83m 6.1E-7 9.1E-6 Kr-85m 3.9E-5 6.2E-5 Kr-85 5.4E-7 6.2E-5 Kr-87 2.0E-4 3.3E-4 Kr-88 4.8E-4 9.3E-5 Kr-89 5.5E-4 3.4E-4 Kr-90 5.2E-4 2.5E-4 Xe-131m 4.9E-6 3.5E-5 Xe-133m 1.0E-5 4.7E-5 &

W Xe-133 1.1E-5 3.3E-5 Xe-135m 1.1E-4 2.3E-5 Xe-135 6.1E-5 7.8E-5 Xe-137 4.8E-5 4.0E-4 Xe-138 2.9E-4 1.5E-4 '

Ar-41 2.9E-4 1.0E-4 Ref: Regulatory Guide 1.109, Revision 1, Table B-1.

O Rev. No. O Page B-5 of ODCM

O O O 2

TABLE B-4 Pi VALUES - INHALATION - CHILD z

9 mrem /vr c3 uCi/m3 NUCLIDE B0NE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY H-3 0 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 0 1.12E 03 Cr-51 0 0 8.55E 01 2.43E 01 1.70E 04 1.08E 03 0 1.54E 02 Mn-54 0 4.29E 04 0 1.00E 04 1.58E 06 2.29E 04 0 9.51E 03 Fe-55 4.74E 04 2.52E 04 0 0 1.11E 05 2.87E 03 0 7.77E 03 Fe-59 2.07E 04 3.34E 04 0 0 1.27E 06 7.07E 04 0 1.67E 04 Co-57 0 9.03E 02 0 0 5.07E 05 1.32E 04 0 1.07E 03 Co-58 0 1.77E 03 0 0 1.11E 06 3.44E 04 0 3.16E 03 Co-60 0 1.31E 04 0 0 7.07E 06 9.62E 04 0 2.26E 04 Zn-65 4.26E 04 1.13E 05 0 7.14E 04 9.95E 05 1.63E 04 0 7.03E 04 Sr-89 5.99E 05 0 0 0 2.16E 06 1.67E 05 0 1.72E 04 Sr-90 1.01E 08 0 0 0 1.48E 07 3.43E 05 0 6.44E 06 Zr-95 1.90E 05 4.18E 04 0 5.96E 04 2.23E 06 6.11E 04 0 3.70E 04 Nb-95 2.35E 04 9.18E 03 0 8.62E 03 6.14E 05 3.70E 04 0 6.55E 03 Mo-99 0 1.72E 02 0 3.92E 02 1.35E 05 1.27E 05 0 4.25E 01 Ag-110m 1.69E 04 1.14E 04 0 2.12E 04 5.48E 06 1.00E 05 0 9.14E 03 Sb-124 5.74E 04 7.40E 02 1.26E 02 0 3.24E 06 1.64E 05 0 2.00E 04 I-131 4.81E 04 4.81E 04 1.62E 07 7.88E 04 0 2.84E 03 0 2.73E 04 I-133 1.66E 04 2.03E 04 3.85E 06 3.38E 04 0 5.48E 03 0 7.70E 03 I-135 4.92E 03 8.73E 03 7.92E 05 1.34E 04 0 4.44E 03 0 4.14E 03 Cs-134 6.51E 05 1.01E 06 0 3.30E 05 1.21E 05 3.85E 03 0 2.25E 05 Cs-136 6.51E 04 1.71E 05 0 9.55E 04 1.45E 04 4.18E 03 0 1.16E 05 2 Cs-137 9.07E 05 8.25E 05 0 2.82E 05 1.04E 05 3.62E 03 0 1.28E 05 S Ba-140 7.40E 04 6.48E 01 0 2.11E 01 1.74E 06 1.02E 05 0 4.33E 03 La-140 6.44E 02 2.25E 02 0 0 1.83E 05 2.26E 05 0 7.55E 01 y Ce-141 3.92E 04 1.95E 04 2.12E 06 0 8.55E 03 1.17E 06 5.44E 05 1.20E 07 5.66E 04 3.89E 05 0 2.90E 03 3.61E 05 Ce-144 6.77E 06 0 0 9

o 8

m

TABLE B-5 g

Ri VALUES - COW MILK - INFANT h

9 m2-mrem /vr c) uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIM T. BODY H-3* 0 2.38E 03 2.38E 03 2.38E 03 2.38E 03 2.38E 03 0 2.38E 03 Cr-51 0 0 5.45E 04 1.19E 04 1.06E 05 2.43E 06 0 8.35E 04 Mn-54 0 2.51E 07 0 5.56E 06 0 9.22E 06 0 5.69E 06 Fe-55 8.98E 07 5.80E 07 0 0 2.83E 07 7.36E 06 0 1.55E 07 Fe-59 1.22E 08 2.13E 08 0 0 6.29E 07 1.02E 08 0 8.39E 07 Co-57 0 5.72E 06 0 0 0 1.95E 07 0 9.30E 06 Co-58 0 1.39E 07 0 0 0 3.46E 07 0 3.47E 07 Co-60 0 5.90E 07 0 0 0 1.40E 08 0 1.39E 08 Zn-65 3.53E 09 1.21E 10 0 5.87E 09 0 1.02E 10 0 5.58E 09 Sr-89 6.93E 09 0 0 0 0 1.42E 08 0 1.99E.08 Sr-90 8.19E 10 0 0 0 0 1.02E 09 0 2.09E 10 Zr-95 3.85E 03 9.39E 02 0 1.01E 03 0 4.68E 05 0 6.66E 02 Nb-95 3.14E 05 1.29E 05 0 9.27E 04 0 1.09E 08 0 7.48E 04 Mo-99 0 1.04E 08 0 1.55E 08 0 3.42E 07 0 2.02E 07 Ag-110m 2.46E 08 1.79E 08 0 2.56E 08 0 9.30E 09 0 1.19E 08 Sb-124 1.18E 08 1.73E 06 3.13E 05 0 7.37E 07 3.63E 08 0 3.65E 07 I-131 1.36E 09 1.60E 09 5.27E 11 1.87E 09 0 5.72E 07 0 7.05E 08 I-133 1.84E 07 2.67E 07 4.86E 09 3.14E 07 0 4.52E 06 0 7.83E 06 I-135 5.65E 04 1.12E 05 1.01E 07 1.25E 05 0 4.07E 04 0 4.10E 04 Cs-134 2.41E 10 4.50E 10 0 1.16E 10 4.75E 09 1.22E 08 0 4.54E 09 m) Cs-136 9.91E 08 2.91E 09 0 1.16E 09 2.37E 08 4.42E 07 0 1.09E 09 fj Cs-137 3.47E 10 4.06E 10 0 1.09E 10 4.41E 09 1.27E 08 0 2.88E 09 u Ba-140 1.21E 08 1.21E 05 0 2.87E 04 7.42E 04 2.97E 07 0 6.23E 06 La-140 2.03E 01 8.01E 00 0 0 0 9.41E 04 0 2.06E 00 g3 1.64E 03 Ce-141 2:28E 04 1.39E 04 0 4.29E 03 0 7.18E 06 0 l 4 1.49E 06 6.10E 05 0 2.46E 05 0 8.55E 07 0 8.35E 04 Ce-144 0.,

o g

• mrem /vr E uCi/m3 O O O

O O O TABLE B-5 (CONTINUED) g N Ri VALUES - GOAT MILK - INFANT Z

9 m2-mrem /vr i

uCi/sec o

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI. SKIN T. BODY H-3* O 4.86E 03 4.86E 03 4.86E 03 4.86E 03 4.86E 03 0 4.86E 03 Cr-51 0 0 6.54E 03 1.43E 03 1.27E 04 2.92E 05 0 1.00E 04 Mn-54 0 3.01E 06 0 6.67E 05 0 1.11E 06 0 6.82E 05 .

~

Fe-55 1.17E 06 7.54E 05 0 0 3.69E 05 9.57E 04 0 2.01E 05 Fe-59 1.58E 06 2.77E 06 0 0 8.18E 05 1.32E 06 0 1.09E 06 i Co-57 0 6.86E 05 0 0 0 2.34E 06 0 1.12E 06 Co-58 0 1.67E 06 0 0 0 4.15E 06 0 4.16E 06 !

Co-60 0 7.08E 06 0 0 0 1.69E 07 0 1.67E 07 Zn-65 4.23E 08 1.45E 09 0 7.04E 08 0 1.23E 09 0 6.70E 08 Sr-89 1.46E 10 0 0 0 0 2.99E 08 0 4.17E 08 Sr-90 1.72E 11 0 0 0 0 2.15E 09 0 4.38E 10 Zr-95 4.63E 02 1.13E 02 0 1.21E 02 0 5.61E 04 0 7.99E 01 Nb-95 3.77E 04 1.55E 04 0' 1.11E 04 0 1.31E 07 0 8.97E 03 -

Mo-99 0 1.25E 07 0 1.86E 07 0 4.10E 06 0 2.43E 06 Ag-110m 2.95E 07 2.15E 07 0 3.08E 07 0 1.12E 09 0 1.42E 07 Sb-124 1.41E 07 2.08E 05 3.75E 04 0 8.85E 06 4.36E 07 0 4.38E 06 i

I-131 1.63E 09 1.92E 09 6.32E 11 2.25E 09 0 6.86E 07 0 8.45E 08 I-133 2.20E 07 3.21E 07 5.84E 09 3.77E 07- 0 5.43E 06 0 9.40E 06 I-135 6.78E 04- 1.35E 05 1.21E 07 1.50E 05 0 4.88E 04 0 4.92E 04 i Cs-134 7.24E 10 1.35E 11 0 3.47E 10 1.42E 10 3.67E 08 0 1.36E 10 Cs-136 2.97E 09 8.74E 09 0 3.48E 09 7.12E 08 1.33E 08 0 3.26E 09 Cs-137 1.04E 11 1.22E 11 0 3.27E 10 1.32E 10 3.81E 08 0 8.63E 09 R

o 1.45E 04 0 3.44E 03 8.91E 03 3.56E 06 0 7.47E 05 ;

1.45E 07 Ba-140 2.47E-01 La-140 2.44E 00 9.61E-01 0 0 0 1.13E 04 0

' 03 Ce-141 2.73E 03 1.67E 03 0 5.14E 02 0 8.62E 05 0 1.96E 02 6' Ce-144 1.79E 05 7.32E 04 0 2.96E 04 0 1.03E 07 0 1.00E 04 9.

• mrem /vr g uCi/m3 I

33 TABLE B-6 2

Ri VALUES - GROUND. PLANE - ADULT h

m2-mrem /vr o uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN .T. BODY H-3 0 0 0 0 0 0 0 0 Cr-51 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 5.50E 06 4.65E 06 Mn-54 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.62E 09 1.38E 09 Fe-55 0 0 0 0 0 0 0 0 Fe-59 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 3.20E 08 2.73E 08 Co-57 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 2.07E 08 1.88E 08 Co-58 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 4.45E 08 3.80E 08 Co-60 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.53E 10 2.15E 10 Zn-65 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 8.57E 08 7.46E 08 Sr-89 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.51E 04 2.16E 04 Sr-90 0 0 0 0 0 0 0 0 Zr-95 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.85E 08 2.45E 08 Nb-95 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.61E 08 1.37E 08 Mo-99 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 4.62E 06 3.99E 06 Ag-110m 3.45E 09 3.45E 09 3.45E 08 3.45E 09 3.45E 09 3.45E 09 4.02E 09 3.45E 09 Sb-124 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 6.92E 08 5.99E 08 I-131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 1.72E 07 I-133 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 3.00E 06 2.46E 06 I-135 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 .2.53E 06 2.95E 06 2.53E 06 Cs-134 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 8.05E 09 6.90E 09 i m Cs-136 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.71E 08 1.51E 08 di Cs-137 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 1.03E 10

• Ba-140 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.35E 07 2.05E 07 b3 La-140 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 2.18E 07 1.92E 07 6 Ce-141 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.54E 07 1.37E 07 6.96E 07 6.96E 07 6.96E 07 8.05E 07 6.96E 07 i Ce-144 6.96E 07 6.96E 07 6.96E 07 9

O b

c -

9 O O

O O O 33 TABLE B-6 (CONTINUED)

Ri VALUES - INHALATION - ADULT 5

- mrem /vr c) uCi/m3 NUCLIDE B0NE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY H-3 0 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 0 1.26E 03 0 0 5.95E 01 2.28E 01 1.44E 04 3.32E 03 0 1.00E 02 Cr-51 1.40E 06 7.74E 04 0 6.30E 03 Mn-54 0 3.96E 04 0 9.84E 03 Fe-55 2.46E 04 1.70E 04 0 0 7.21E 04 6.03E 03 0 3.94E 03 1.18E 04 2.78E 04 0 0 1.02E 06 1.88E 05 0 1.06E 04 Fe-59 3.69E 05 3.14E 04 0 6.71E 02 Co-57 0 6.92E 02 0 0 Co-58 0 1.58E 03 0 0 9.28E 05 1.06E 05 0 2.07E 03 Co-60 0 1.15E 04 0 0 5.97E 06 2.85E 05 0 1.48E 04 Zn-65 3.24E 04 1.03E 05 0 6.90E 04 8.64E 05 5.34E 04 0 4.66E 04 Sr-89 3.04E 05 0 0 0 1.40E 06 3.50E 05 0 8.72E 03 Sr-90 9.92E 07 0 0 0 9.60E 06 7.22E 05 0 6.10E 06 Zr-95 1.07E 05 3.44E 04 0 5.42E 04 1.77E 06 1.50E 05 0 2.33E 04 Nb-95 1.41E 04 7.82E 03 0 7.74E 03 5.05E 05 1.04E 05 0 4.21E 03 Mo-99 0 1.21E 02 0 2.91E 02 9.12E 04 2.48E 05 0 2.30E 01 Ag-110m 1.08E 04 1.00E 04 0 1.97E 04 4.63E 06 3.02E 05 0 5.94E 03 Sb-124 3.12E 04 5.89E 02 7.55E 01 0 2.48E 06 4.06E 05 0 1.24E 04 I-131 2.52E 04 3.58E 04 1.19E 07 6.13E 04 0 6.28E 03 0 2.05E 04 I-133 8.64E 03 1.48E 04 2.15E 06 2.58E 04 0 8.88E 03 0 4.52E 03 I-135 2.68E 03 6.98E 03 4.48E 05 1.11E 04 0 5.25E 03 0 2.57E 03 Cs-134 3.73E 05 8.48E 05 0 2.87E 05 9.76E 04 1.04E 04 0 7.28E 05 Cs-136 3.90E 04 1.46E 05 0 8.56E 04 1.20E 04 1.17E 04 0 1.10E 05 W 4.78E 05 6.21E 05 0 2.22E 05 7.52E 04 8.40E 03 0 4.28E 05 o Cs-137

• Ba-140 3.90E 04 4.90E 01 0 1.67E 01 1.27E 06 2.18E 05 0 2.57E 03 03 La-140 3.44E 02 1.74E 02 0 0 1.36E 05 4.58E 05 0 4.58E 01 l' Ce-141 1.99E 04 1.35E 04 0 6.26E 03 3.62E 05 1.20E 05 0 1.53E 03 C'

Ce-144 3.43E 06 1.43E 06 0 8.48E 05 7.78E 06 8.16E 05 0 1.84E 05 9.

o 8

m

TABLE B-6 (CONTINUED) 2

- Ri VALUES - VEGETATION - ADULT z

9 m2-mrem /vr c) uCi/sec NUCLIDE BONE LIVER THYROID K1DNEY LUNG GI-LLI SKIN T. BODY H-3* 0 2.25E 03 2.25E 03 2.25E 03 2.25E 03 2.25E 03 0 2.25E 03 Cr-51 0 0 2.77E 04 1.02E 04 6.15E 04 1.17E 07 0 4.64E 04 Mn-54 0 3.13E 08 0 9.31E 07 0 9.58E 08 0 5.97E 07 Fe-55 2.10E 08 1.45E 08 0 0 8.08E 07 8.31E 07 0 3.38E 07 Fe-59 1.26E 08 2.96E 08 0 0 8.27E 07 9.87E 08 0 1.13E 08 Co-57 0 1.17E 07 0 0 0 2.97E 08 0 1.94E 07 Co-58 0 3.08E 07 0 0 0 6.24E 08 0 6.90E 07 Co-60 0 1.67E 08 0 0 0 3.14E 09 0 3.69E 08 Zn-65 3.17E 08 1.01E 09 0 6.75E 08 0 6.36E 08 0 4.56E 08 Sr-89 9.95E 09 0 0 0 0 1.60E 09 0 2.86E 08 Sr-90 6.05E 11 0 0 0 0 1.75E 10 0 1.48E 11 Zr-95 1.18E 06 3.77E 05 0 5.92E 05 0 1.20E 09 0 2.55E 05 Nb-95 1.42E 05 7.91E 04 0 7.82E 04 0 4.80E 08 0 4.25E 04 Mo-99 0 6.14E 06 0 1.39E 07 0 1.42E 07 0 1.17E 06 Ag-110m 1.05E 07 9.75E 06 0 1.92E 07 0 3.98E 09 0 5.79E 06 Sb-124 1.04E 08 1.96E 06 2.52E 05 0 8.08E 07 2.94E 09 0 4.12E 07 I-131 8.07E 07 1.15E 08 3.78E 10 1.98E 08 0 3.05E 07 0 6.62E 07 I-133 2.10E 06 3.66E 06 5.38E 08 6.39E 06 0 3.29E 06 0 1.12E 06 I-135 3.91E 04 1.02E 05 6.75E 06 1.64E 05 0 1.16E 05 0 3.78E 04 Cs-134 4.67E 09 1.11E 10 0 3.60E 09 1.19E 09 1.94E 08 0 9.08E 09 m Cs-136 4.26E 07 1.68E 08 0 9.37E 07 1.28E 07 1.91E 07 0 1.21E 08

$C Cs-137 6.36E 09 8.70E 09 0 2.95E 09 9.81E 08 1.68E 08 0 5.70E 09 Ba-140 1.29E 08 1.61E 05 0 5.49E 04 9.25E 04 2.65E 08 0 8.42E 06 a3 La-140 1.98E 03 9.99E 02 0 0 0 7.33E 07 0 2.64E 02

' Ce-141 1.97E 05 1.33E 05 0 6.19E 04 0 5.09E 08 0 1.51E 04 Ce-144 3.29E 07 1.38E 07 0 8.16E 06 0 1.11E 10 0 1.77E 06 9.

o g

• mrem /yt E: uCi/m3 O O O

O O O m TABLE B-6 (CONTINUED)

Ri VALUES - C0W MEAT - ADULT l z i 9 m_2-mrem /vr I

o uCi/sec i

NUCLIDE' BONE LIVER THYROID KIDNEY LUNG LGI-LLI- SKIN- T. BODY t

H-3* 0 3.24E 02 3.24E 02 3.24E 02 3.24E 02 3.24E 02 0 '3.24E 02 l

Cr-51 0 0 2.18E 03 8.04E 02 4.84E 03 9.18E 05 0 3.65E 03 Mn-54 0 5.90E 06 0 1.76E 06 0 1.81E 07 0 1.13E 06 1.95E 08 1.35E 08 0 0 7.51E 07 7.72E 07 0 3.14E 07 Fe-55 1.13E 09 1.30E 08 Fe-59 1.44E 08 3.39E 08 0 0 9.46E 07 0 .

Co-57 0 3.60E 06 0 0 0 9.14E 07- 0 5.99E 06 Co-58 0 1.04E 07 0 0- 0 2.12E 08 0 2.34E 07 Co-60 0 5.03E 07 0 0 0- 9.46E 08 0 1.11E 08 Zn-65 2.26E 08 7.19E 08 0 4.81E 08 0 4.53E 08 0 3.25E 08 Sr-89 1.66E 08 0 0 0 0 2.66E 07 0 4.76E 06 Sr-90 8.38E.09 0 0 0 0 2.42E'08 0 2.06E 09

Zr-95 1.06E 06 3.40E 05 0 5.34E 05 0 1.08E 09 0 2.30E 05

Nb-95 1.22E 06 6.76E 05 0 6.68E 05 0 4.10E 09 0 3.64E 05 Mo-99 0 4.96E 04 0 .1.12E 05 0 1.15E 05 0 9.44E 03 Ag-110m. 4.25E 06 3.94E 06 0 7.74E 06 0 .

1.61E-09 0 2.34E 06 '

Sb-124 1.11E 07 2.10E 05 .2.70E 04 0- 8.67E 06 3.16E 08 0 4.41E 06 I-131 5.37E 06 7.68E 06 2.52E 09 -1.32E 07~ 0 2.03E 06 0 4.40E 06 I-133 1.99E-01 3.46E-01 5.09E 01 6.04E-01 0 3.11E 0- 1.05E-01 1-135 2.33E-17 6.10E-17 4.02E-15 -9.77E-17 0 6.88E-17 0 2.25E-17 Cs-134 4.35E 08 1.03E.09 0 3.35E 08 1.11E 08 1.81E 07 0 -8.46E 08 l

r Cs-136 6.04E'06 2.38E 07 0 1.33E 07' 1.82E.06 2.71E 06 0. 1.72E 07 O. Cs-137 5.88E 08. :8.04E 08 0 2.73E 08 9.07E'07 1.56E 07 0 5.27E-08 Ba-140 1.44E 07 1.81E 04 0 6.16E 03 -1.04E 04 2.97E 07' 0 9.44E 05 1.88E 9.48E-03 0 0 0 6.96E 02 'O 2.50E-03 -i

? La-140 7.38E 03 4.99E 03 0 2.32E 03 0 1.91E 07 0 -5.66E 02 G Ce-141 5.01E 04 Ce-144 9.34E 05 3.90E 05 0 2.32E 05' 0 3.16E 08 0 1

SL O

g

• mrem /vr E uCi/m3

TABLE B-6 (CONTINUED) gp Ri VALUES - COW MILK - ADULT 9 m2-mrem /vr c) uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY H-3* 0 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 0 7.63E 02 Cr-51 0 0 8.85E 03 3.26E 03 1.96E 04 3.72E 06 0 1.48E 04 Mn-54 0 5.41E 06 0 1.61E 06 0 1.66E 07 0 1.03E 06 Fe-55 1.67E 07 1.15E 07 0 0 6.43E 06 6.61E 06 0 2.69E 06 Fe-59 1.61E 07 3.79E 07 0 0 1.06E 07 1.26E 08 0 1.45E 07 Co-57 0 '8.18E 05 0 0 0 2.07E 07 0 1.36E 06 Co-58 0 2.70E 06 0 0 0 5.47E 07 0 6.05E 06 Co-60 0 1.10E 07 0 0 0 2.06E 08 0 2.42E 07 Zn-65 8.72E 08 2.77E 09 0 1.86E 09 0 1.75E 09 0 1.25E 09 Sr-89 7.99E 08 0 0 0 0 1.28E 08 0 2.29E 07 Sr-90 3.15E 10 0 0 0 0 9.11E 08 0 7.74E'09 Zr-95 5.34E 02 1.71E 02 0 2.69E 02 0 5.43E 05 0 1.16E 02 Nb-95 4.37E 04 2.43E 04 0 2.40E 04 0 1.48E 08 0 1.31E 04 Mo-99 0 1.24E 07 0 2.80E 07 0 2.87E 07 0 2.35E 06 Ag-110m 3.71E 07 3.43E 07 0 6.74E 07 0 1.40E 10 0 2.04E 07 Sb-124 1.45E 07 2.73E 05 3.51E 04 0 1.13E 07 4.11E 08 0 5.74E 06 I-131 1.48E 08 2.12E 08 6.94E 10 3.63E 08 0 5.59E 07 0 1.21E 08 I-133 1.96E 06 3.41E 06 5.01E 08 5.95E 06 0 3.06E 06 0 1.04E 06 I-135 6.46E 03 1.69E 04 1.12E 06 2.71E 04 0 1.91E 04 0 6.24E 03 Cs-134 3.74E 09 8.89E 09 0 2.88E 09 9.55E 08 1.56E 08 0 7.27E 09 2 Cs-136 1.32E 08 5.21E 08 0 2.90E 08 3.97E 07 5.92E 07 0 3.75E 08 o Cs-137 4.98E 09 6.BuE 09 0 2.31E 09 7.68E 08 1.32E 08 0 4.46E 09

• 1.69E 04 5.76E 03 9.69E 03 2.78E 07 0 8.83E 05 Ba-140 1.35E 07 0 P La-140 2.26E 00 1.14E 00 0 0 0 8.37E 04 0 3.01E-01 g; Ce-141 2.55E 03 1.72E 03 0 8.00E 02 0 6.58E 06 0 1.95E 02 Ce-144 2.29E 05 9.58E 04 0 5.68E 04 0 7.75E 07 0 1.23E 04 R.

o 8

• mrem /vr K uCi/m3 O O O

O a

O O '

t TABLE B-6 (CONTINUED) 7.

- Ri VALUES - GOAT MILK - ADULT ,

z 9 m2 -mrem /vr ,

a uCi/sec ,

i

-NUCLIDE BONE LIVER THYROID KIDNEY LUNG -GI-LLI SKIN T. BODY H-3* 0 1.56E 03 1.56E 03 1.56E 03 1.56E 03 1.56E 03 0 1.56E 03 ,

Cr-51 0 0 1.06E 03 3.91E 02' 2.36E 03 4.47E.05 0 1.78E 03 i Mn-54 0 6.49E 05 0 1.93E 05 0 1.99E 06 0 1.24E-05 i' 0 8.36E 04 8.60E 04 0 3.49E 04 Fe-55 2.17E 05 1.50E 05 0 Fe-59 2.10E 05 4.93E 05 0 0 l'.38E 05 1.64E 06 0 1.89E 05 -

Co-57 0 9.81E 04 0 0 0 2.49E 06 0 1.63E 05 Co-58 0 3.24E 05 0 0 0 6.57E 06 0 7.27E 05 Co-60 0 1.32E 06 0 0 0 2.48E 07 0 2.91E 06 -

Zn-65 1.05E 08 3.33E 08 0 2.23E 08 0 2.10E 08 0 1.50E 08 i Sr-89 1.68E 09 0 0 0 0 2.69E 08 0 4.81E 07  ;

6.62E 10 0 0 :0 0 1.91E 09 0 1.63E 10 .l Sr-90 Zr-95 6.41E 01 2.06E 01 0 3.23E 01 0- 6.52E 04- 0 1.39E 01 Nb-95 5.24E 03 2.92E 03 0 2.88E 03 0 1.77E 07- 0 1.57E 03 i Mo-99 0 1.48E 06 'O 3.36E 06 0 3.44E 06 0 2.82E 05 i Ag-110m 4.45E 06 4.11E 06 0 8.09E 06 0- 1.68E 09 0 2.44E 06 Sb-124 1.74E 06 3.28E 04 4.21E 03 0- 1.35E 06 4.93E 07 0 6.89E 05 I-131 1.78E 08 2.54E 08 8.33E 10 4.36E 08 0 6.70E 07 0 1.46E 08 I-133 2.35E 06 4.09E 06 6.01E 08 7.14E 06 0 3.68E 06 0 1.25E-06  ;

i I-135 7.75E 03 2.03E 04 1.34E 06 3.25E 04 0 2.29E 04 0 7.49E 03 i Cs-134 1.12E 10 2.67E 10 0 8.64E 09 2.87E 09 4.67E 08 0 2.18E 10 g Cs-136 3.96E 08 1.56E 09 0. 8.70E 08 1.19E 08 1.78E 08- 0 1.13E 09 i o Cs-137 1.49E 10 2.04E 10 0 6.93E 09 2.30E 09 3.95E 08- 0 1.34E 10 Ba-140 1.62E 06 2.03E 03 0 6.91E 02 1.16E 03 3.33E 06 0 1.06E 05 .

? La-140 2.71E-01 1.37E-01 0 0 0 1.00E 04 0 3.61E-02 g Ce-141 3.06E 02 2.07E 02 0 9.60E 01 0 7.90E 05 0 2.34E 01 1

!- Ce-144 2.75E 04 1.15E 04 0 6.82E 03 0 9.30E 06 0 1.48E 03

9. ,

l j_

f g

• mrem /vr uCi/m3

TABLE B-6 (CONTINUED) gg Ri VALUES - GROUND PLANE - TEEN d

m2 -mrem /vr a uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY H-3 0 0 0 0 0 0 0 0 Cr-51 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 5.50E 06 4.65E 06 Mn-54 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.62E 09 1.38E 09 Fe-55 0 0 0 0 0 0 0 0 Fe-59 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 3.20E 08 2.73E 08 Co-57 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 2.07E 08 1.88E 08 Co-58 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 4.45E 08 3.80E 08 Co-60 2.15E 10 2.15E 10 2 15E 10 2.15E 10 2.15E 10 2.15E 10 2.53E 10 2.15E 10 Zn-65 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 8.57E 08 7.46E 08 Sr-89 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.51E 04 2.16E 04 Sr-90 0 0 0 0 0 0 0 0 Zr-95 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.85E 08 2.45E 08 Hb-95 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.61E 08 1.37E 08 Mo-99 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 4.62E 06 3.99E 06 Ag-110m 3.45E 09 3.45E 09 3.45E 09 3.45E 09 3.45E 09 3.45E 09 4.02E 09 3.45E 09 Sb-124 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 6.92E 08 5.99E 08 I-131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 1.72E 07 I-133 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 3.00E 06 2.46E 06 I-135 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.95E 06 2.53E 06 Cs-134 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 8.05E 09 6.90E 09

? Cs-136 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.71E 08 1.51E 08 o Cs-137 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 1.03E 10

" 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.35E 07 2.05E 07 Ba-140 a3 La-140 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 2.18E 07 1.92E 07 i Ce-141 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.54E 07 1.37E 07

• 6.96E 07 6.96E 07 6.96E 07 6.96E 07 6.96E 07 6.96E 07 8.05E 07 6.96E 07 Ce-144 9.

o

. b s:

O O O

. O O O TABLE B-6 (CONTINUED) .

m Ri VALUES - INHALATION - TEEN 4

z P mrem /vr uCi/m3 a '

MUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY -

a H-3 0 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 0 1.27E 03 '

Cr-51 .0 0 7.50E 01 3.07E 01 2.10E 04 3.00E 03 0 1.35E 02 Mn-54 0 5.11E 04 0 1.27E 04 1.98E 06 6.68E 04 0 8.40E 03 -

Fe-55 3.34E 04 2.38E 04 0 0 1.24E 05 6.39E 03 0 5.54E 03 Fe-59 1.59E 04 3.70E 04 0 0 1.53E 06 1.78E 05 0 1.43E 04 i Co-57 0 9.44E 02 0 0 5.86E'05 3.14E 04 0 9.20E 02  ;

Co-58 0 2.07E 03 0 0 1.34E 06 9.52E 04 0 2.78E 03 Co-60 0 1.51E 04 0 0 8.72E 06 2.59E 05 0 1.98E 04 Zn-65 3.86E 04 1.34E 05 0 8.64E 04 1.24E 06 4.66E 04 0 6.24E 04 -

Sr-89 4.34E 05 0 0 0 2.42E 06 3.71E 05 0 1.25E 04  !

Sr-90 1.08E 08 0 0 0 1.65E 07 7.65E 05 0 6.68E 06 '

Zr-95 1.46E 05 4.58E 04 0 6.74E 04 2.69E 06 1.49E 05 0 3.15E 04 Nb-95 1.86E 04 1.03E 04 0 1.00E 04 7.51E 05 9.68E 04 0 5.66E 03 Mo-99 0 1.69E 02 0 4.11E 02 1.54E 05 2.69E 05 0 3.22E 01 Ag-110m 1.38E 04 1.31E 04 0 2.50E 04 6.75E 06 2.73E 05 0 7.99E 03 Sb-124 4.30E 04 7.94E 02 9.76E 01 0 3.85E 06 3.98E 05 0 1.58E 04 I-131 3.54E 04 4.91E 04 1.46E 07 8.40E 04 0 6.49E 03 0 2.64E 04 I-133 1.22E 04 2.05E 04 2.92E 06 3.59E 04 0 1.03E 04 0 6.22E 03 I-135 3.70E 03 9.44E 03 6.21E 05 1.49E 04 0 6.95E 03 0 3.49E 03 Cs-134 5.02E 05 1.13E 06 0 3.75E 05 1.46E 05 .9.76E 03 0 5.49E 05- !

Cs-136 5.15E 04 1.94E 05 0 1.10E 05 1.78E 04 1.09E 04- 0 1.37E'05

! W 6.70E 05 8.48E 05 0 3.04E 05 1.21E 05 -8.48E 03 0 3.11E 05

> c Cs-137 i "

Ba-140 5.47E 04 6.70E 01 0 2.28E 01 2.03E 06 2.29E 05 0 3.52E 03 -

a3 La-140 4.79E 02 2.36E 02 0 0 2.14E 05 4.87E 05 0 6.26E 01 a Ce-141 2.84E 04 1.90E 04 0 8.88E 03- 6.14E 05 1.26E 05 0 2.17E 03 i

~

Ce-144 4.89E 06 2.02E 06 0 1.21E 06 1.34E 07 8.64E 05 0 2.62E 05 -

R ,

O

' 8 s .

~- - . _ .- _ _ _ _

m TABLE B-6 (CONTINUED) e Ri VALUES - VEGETATION - TEEN 9 m2-mrem /vr o uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY H-3* 0 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03 0 2.59E 03 Cr-51 0 0 3.42E 04 1.35E 04 8.79E 04 1.03E 07 0 6.16E 04 Mn-54 9 4.54E 08 0 1.36E 08 0 9.32E 08 0 9.01E 07 Fe-55 3.2SE 08 2.31E 08 0 0 1.47E 08 1.00E 08 0 5.39E 07 Fe-59 1.79E 08 4.18E 08 0 0 1.32E 08 9.89E 08 0 1.61E 08 Co-57 0 1.79E 07 0 0 0 3.34E 08 0 3.00E 07 Co-58 0 4.37E 07 0 0 0 6.02E 08 0 1.01E 08 Co-60 0 2.49E 08 0 0 0 3.24E 09 0 5.60E 08 Zn-65 4.24E 08 1.47E 09 0 9.41E 08 0 6.23E 08 0 6.86E 08 Sr-89 1.51E 10 0 0 0 0 1.80E 09 0 4.33E 08 Sr-90 7.51E 11 0 0 0 0 2.11E 10 0 1.85E 11 Zr-95 1.72E 06 5.44E 05 0 7.99E 05 0 1.26E 09 0 3.74E 05 Nb-95 1.92E 05 1.07E 05 0 1.03E 05 0 4.56E 08 0 5.86E 04 Mo-99 0 5.64E 06 0 1.29E 07 0 1.01E 07 0 1.08E 06 Ag-110m 1.52E 07 1.44E 07 0 2.74E 07 0 4.03E 09 0 8.73E 06 Sb-124 1.55E 08 2.85E 06 3.51E 05 0 1.35E 08 3.12E 09 0 6.03E 07 I-131 7.68E 07 1.08E 08 3.14E 10 1.85E 08 0 2.13E 07 0 5.78E 07 I-133 1.95E 06 3.32E 06 4.63E 08 5.81E 06 0 2.51E 06 0 1.01E 06 I-135 3.53E 04 9.10E 04 5.85E 06 1.44E 05 0 1.01E 05 0 3.37E 04 Cs-134 7.10E 09 1.67E 10 0 5.31E 09 2.03E 09 2.08E 08 0 7.76E 09 2 Cs-136 4.37E 07 1.72E 08 0 9.36E 07 1.48E 07 1.38E 07 0 1.15E 08 o' Cs-137 1.01E 10 1.35E 10 0 4.59E 09 1.78E 09 1.92E 08 0 4.69E 09 Ba-140 1.38E 08 1.69E 05 0 5.74E 04 1.14E 05 2.13E 08 0 8.91E 06 03 La-140 1.81E 03 8.89E 02 0 0 0 5.11E 07 0 2.37E 02 i Ce-141 2.83E 05 1.89E 05 0 8.89E 04 0 5.40E 08 0 2.17E 04

" 5.27E 07 2.18E 07 0 1.30E 07 0 1.33E 10 0 2.83E 06 Ce-144 9.

f g

• mrem /vr uCi/m3 O O O .

O O O l l

3 TABLE B-6 (CONTINUED)

$ Ri VALUES - COW MEAT - TEEN Z

9 m2-mrem /vr c) uCi/sec NUCLIDE B0NE LIVER THYROID KIDNEY LUNG GI-LLI SKIN- T. BODY H-3* 0 1.93E 02 1.93E 02 1.93E 02 1.93E 02 1.93E 02 0 1.93E 02 Cr-51 0 0 1.62E 03 6.39E 02 4.17E 03 4.90E 05 0 2.92E 03 Mn-54 0 4.50E 06 0 1.34E 06 0 9.24E 06 0 8.93E 05 '

Fe-55 1.58E 08 1.12E 08 0 0 7.12E 07 4.86E 07 0 2.62E 07 Fe-59 1.15E 08 2.69E 08 0 0 8.48E 07 6.36E 08 0 1.04E 08 Co-57 0 2.89E 06 0 0 0 5.40E 07 0 4.85E 06 4 Co-58 0 8.06E 06 0 0 0 1.11E 08 0 1.86E 07 Co-60 0 3.91E 07 0 0 0 5.09E 08 0 8.80E 07 Zn-65 1.59E 08 5.52E 08 0 3.53E 08 0 2.34E 08 0 2.58E 08 Sr-89 1.40E 08 0 0 0 0 1.67E 07 0 4.01E 06 1.52E 08 1.34E 09 Sr-90 5.42E 09 0 0 0 0 0 Zr-95 8.50E 05 2.68E 05 0 3.94E 05 0 6.19E 08 0 1.84E 05 Nb-95 9.49E 05 5.27E 05 0 5.11E 05 0 2.25E 09 0 2.90E 05 Mo-99 0 4.10E 04 0 9.39E 04 0 7.35E 04 0 7.83E 03 Ag-110m 3.22E 06 3.05E 06 0 5.81E 06 0 8.56E 08 0 1.85E 06 Sb-124 9.09E 06 1.68E 05 2.06E 04 0 7.94E 06 1.83E 08 0 3.55E 06 I-131 4.46E 06 6.24E 06 1.82E 09 1.08E 07 0 1.24E 06 0 3.35E 06 I-133 1.66E-01 2.82E-01 3.94E 01 4.95E-01 0 2.14E-01 0 8.61E-02 1-135 1.89E-17 4.88E-17 3.14E-15 7.70E-17 0 5.40E-17 0 1.81E-17 Cs-134 3.46E 08 8.14E 08 0 2.59E 08 9.87E 0/ 1.01E 07 0 3.78E 08 72 Cs-136 4.71E 06 1.85E 07 0 1.01E 07 1.59E 06 1.49E 06 0 1.24E 07

$o Cs-137 4.88E 08 6.49E 08 0 2.21E 08 8.59E 07 9.24E 06 0 2.26E 08 8a-140 1.19E 07 1.46E 04 0 4.95E 03 9.82E 03 1.84E 07 0 7.68E 05 ao La-140 1.55E-02 7.60E-03 0 0 0 4.36E 02 0 2.02E-03 a Ce-141 6.20E 03 4.14E 03 0 1.95E 03 0 1.18E 07 0 4.75E 02 Ce-144 7.87E 05 3.26E 05 0 1.94E 05 0 1.98E 08 0 4.23E 04 9

• mrem /vr 3: uCi/m3

TABLE B-6 (CONTINUED) y Ri VALUES - COW MILK - TEEN z

9 m2 -mrem /vr c) uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY H-3* 0 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 0 9.94E 02 Cr-51 0 0 1.44E 04 5.67E 03 3.69E 04 4.34E 06 0 2.59E 04 Mn-54 0 9.02E 06 0 2.69E 06 0 1.85E 07 0 1.79E 06 Fe-55 2.96E 07 2.10E 07 0 0 1.33E 07 9.08E 06 0 4.89E 06 Fe-59 2.81E 07 6.57E 07 0 0 2.07E 07 1.55E 08 0 2.54E 07 Co-57 0 1.43E 06 0 0 0 2.68E 07 0 2.41E 06 Co-58 0 4.55E 06 0 0 0 6.27E 07 0 1.05E 07 Co-60 0 1.86E 07 0 0 0 2.42E 08 0 4.19E 07 Zn-65 1.34E 09 4.65E 09 0 2.97E 09 0 1.97E 09 0 2.17E 09 Sr-89 1.47E 09 0 0 0 0 1.75E 08 0 4.22E.07 Sr-90 4.46E 10 0 0 0 0 1.25E 09 0 1.10E 10 Zr-95 9.34E 02 2.95E 02 0 4.33E 02 0 6.80E 05 0 2.03E 02 Nb-95 7.45E 04 4.13E 04 0 4.01E 04 0 1.77E 08 0 2.28E 04 Mo-99 0 2.23E 07 0 5.11E 07 0 4.00E 07 0 4.26E 06 Ag-110m 6.13E 07 5.80E 07 0 1.11E 08 0 1.63E 10 0 3.53E 07 Sb-124 2.58E 07 4.76E 05 5.86E 04 0 2.25E 07 5.20E 08 0 1.01E 07 I-131 2.69E 08 3.76E 08 1.10E 11 6.47E 08 0 7.44E 07 0 2.02E 08 I-133 3.58E 06 6.07E 06 8.48E 08 1.06E 07 0 4.59E 06 0 1.85E 06 I-135 1.15E 04 2.95E 04 1.90E 06 4.66E 04 0 3.27E 04 0 1.09E 04 Cs-134 6.49E 09 1.53E 10 0 4.85E 09 1.85E 09 1.90E 08 0 7.09E 09 2 Cs-136 2.25E 08 8.84E 08 0 4.81E 08 7.59E 07 7.12E 07 0 5.94E 08 g Cs-137 9.02E 09 1.20E 10 0 4.08E 09 1.59E 09 2.00E 04 1.71E 08 3.75E 07 0 4.18E 09 Ba-140 2.43E 07 2.98E 04 0 1.01E 04 0 1.57E 06 a3 La-140 4.06E 00 2.00E 00 0 0 0 1.15E 05 0 5.31E-01 g Ce-141 4.67E 03 3.12E 03 0 1.47E 03 0 8.91E 06 0 3.58E 02 Ce-144 4.22E 05 1.74E 05 0 1.04E 05 0 1.06E 08 0 2.27E 04 9.

O g

• mrem /vr E uCi/m3 O O O

V O O O TABLE B-6 (CONTINUED) g he Ri VALUES - GOAT MILK - TEEN o

m2-mrem /vr o uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY H-3* 0 2.03E 03 2.03E 03 2.03E 03 2.03E 03 2.03E 03 0 2.03E 03 Cr-51 0 0 1.72E 03 6.80E 02 4.43E 03 5.21E 05 0 3.10E 03 Mn-54 0 1.08E 06 0 3.23E 05 0 2.22E 06 0 2.15E 05 Fe-55 3.85E 05 2.73E 05 0 0 1.73E 05 1.18E 05 0 6.36E 04 Fe-59 3.66E 05 8.54E 05 0 0 2.69E 05 2.02E 06 0 3.30E 05 Co-57 0 1.72E 05 0 0' 0 3.21E 06 0 2.89E 05 Co-58 0 5.46E 05 0 0 0 7.52E 06 0 1.26E 06 Co-60 0 2.23E 06 0 0 0 2.91E 07 0 5.03E 06 Zn-65 1.61E 08 5.58E 08 0 3.57E 08 0 2.36E 08 0 2.60E 08 Sr-89 3.09E 09 0 0 0 0 3.68E 08 0 8.85E 07 Sr-90 9.36E 10 0 0 0 0 2.63E 09 0 2.31E 10 Zr-95 1.12E 02 3.54E 01 0 5.20E 01 0 8.16E 04 0 2.43E 01 Nb-95 8.94E 03 4.96E 03 0 4.81E 03 0 2.12E 07 0 2.73E 03 Mo-99 0 2.68E 06 0 6.13E 06 0 4.80E 06 0 5.11E 05 Ag-110m 7.35E 06 6.96E 06 0 1.33E 07 0 1.95E 09 0 4.23E 06 Sb-124 3.10E 06 5.71E 04 7.03E 03 0 2.71E 06 6.24E 07 0 1.21E 06 I-131 3.22E 08 4.51E 08 1.32E 11 7.77E 08 0 8.93E 07 0 2.42E 08 I-133 4.30E 06 7.29E 06 1.02E 09 1.28E 07 0 5.51E 06 0 2.22E 06 I-135 1.38E 04 3.54E 04 2.28E 06 5.60E 04 0 3.93E 04 0 1.31E 04 Cs-134 1.95E 10 4.58E 10 0 1.46E 10 5.56E 09 5.70E 08 0 2.13E 10 2 Cs-136 6.74E 08 2.65E 09 0 1.44E 09 2.28E 08 2.13E 08 0 1.78E 09 2.71E 10 3.60E 10 0 1.23E 10 4.76E 09 5.12E'08 0 1.25E 10

$ Cs-137 2.92E 06 3.58E 03 0 1.21E 03 2.41E 03 4.50E 06 0 1.88E 05 Ba-140

? La-140 4.87E-01 2.40E-01 0 0 0 1.38E 04 0 6.37E-02 8 Ce-141 5.60E 02 3.74E 02 0 1.76E 02 0 1.07E 06 0 4.30E 01 Ce-144 5.06E 04 2.09E 04 0 1.25E 04 0 1.27E 07 0 2.72E 03 q

O

• mrem /vr E uCi/m3

_ - _ _ _ _ _ _ _ _ _ _ _ ___.m _. __ _-- __-_____-_m- ._

TABLE B-6 (CONTINUED) g Ri VALUES - GROUND PLANE - CHILD

-E m2-mrem /vr a uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY H-3 0 0 0 0 0 0 0 0 Cr-51 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.56E 06 5.50E 06 4.65E 06 Mn-54 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.62E 09 1.38E 09 Fe-55 0 0 0 0 0 0 0 0 Fe-59 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 3.20E 08 2.73E 08 Co-57 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 2.07E 08 1.88E 08 Co-58 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 4.45E 08 3.80E 08 Co-60 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.53E 10 2.15E 10 Zn-65 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 8.57E 08 7.46E 08 Sr-89 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.51E 04 2.16E 04 Sr-90 0 0 0 0 0 0 0 0 Zr-95 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.85E 08 2.45E 08 Nb-95 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.61E 08 1.37E 08 Mo-99 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 4.62E 06 3.99E 06 Ag-110m 3.45E 09 3.45E 09 3.45E 09 3.45E 09 3.45E 09 3.45E 09 4.02E 09 3.45E 09 Sb-124 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 6.92E 08 5.99E 08 I-131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 1.72E 07 I-133 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 3.00E 06 2.46E 06 I-135 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.95E 06 2.53E 06 Cs-134 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 8.05E 09 6.90E 09 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.71E 08 1.51E 08

$*7 Cs-136 Cs-137 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 1.03E 10 Ba-140 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.35E 07 2.05E 07 9 La-140 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 2.18E 07 1.92E 07 S Ce-141 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.54E 07 1.37E 07 Ce-144 6.96E 07 6.96E 07 6.96E 07 6.96E 07 6.96E 07 6.96E 07 8.05E 07 6.96E 07 9 '

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q w w.J LJ TABLE B-6 (CONTINUED) go Ri VALUES - INHALATION - CHILD

[h P mrem /vr o uCi/m3 NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY 0 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 0 1.12E 03 H-3 1.70E 04 1.08E 03 0 1.54E 02 Cr-51 0 0 8.55E 01 2.43E 01 0 4.29E 04 0 1.00E 04 1.58E 06 2.29E 04 0 9.51E 03 Mn-54 1.11E 05 2.87E 03 0 7.77E 03 Fe-55 4.74E 04 2.52E 04 0 0 2.07E 04 3.34E 04 0 0 1.27E 06 7.07E 04 0 1.67E 04 Fe-59 5.07E 05 1.32E 04 0 1.07E 03 Co-57 0 9.03E 02 0 0 0 1.77E 03 0 0 1.11E 06 3.44E 04 0 3.16E 03 Co-58 9.62E 04 2.26E 04 Co-60 0 1.31E 04 0 0 7.07E 06 0 4.26E 04 1.13E 05 0 7.14E 04 9.95E 05 1.63E 04 0 7.03E 04 Zn-65 2.16E 06 1.67E 05 0 1.72E 04 Sr-89 5.99E 05 0 0 0 Sr-90 1.01E 08 0 0 0 1.48E 07 3.43E 05 0 6.44E 06 Zr-95 1.90E 05 4.18E 04 0 5.96E 04 2.23E 06 6.11E 04 0 3.70E 04 Nb-95 2.35E 04 9.18E 03 0 8.62E 03 6.14E 05 3.70E 04 0 6.55E 03 Mo-99 0 1.72E 02 0 3.92E 02 1.35E 05 1.27E 05 0 4.25E 01 Ag-110m 1.69E 04 1.14E 04 0 2.12E 04 5.48E 06 1.00E 05 0 9.14E 03 Sb-124 5.74E 04 7.40E 02 1.26E 02 0 3.24E 06 1.64E 05 0 2.00E 04 I-131 4.81E 04 4.81E 04 1.62E 07 7.88E 04 0 2.84E 03 0 2.73E 04 I-133 1.66E 04 2.03E 04 3.85E 06 3.38E 04 0 5.48E 03 0 7.70E 03 I-135 4.92E 03 8.73E 03 7.92E 05 1.34E 04 0 4.44E 03 0 4.14E 03 Cs-134 6.51E 05 1.01E 06 0 3.30E 05 1.21E 05 3.85E 03 0 2.25E 05 2? Cs-136 6.51E 04 1.71E 05 0 9.55E 04 1.45E 04 4.18E 03 0 1.16E 05 Cs-137 9.07E 05 8.25E 05 0 2.82E 05 1.04E 05 3.62E 03 0 1.28E 05 S 7.40E 04 6.48E 01 0 2.11E 01 1.74E 06 1.02E 05 0 4.33E 03 Ba-140 7.55E 01 9 La-140 6.44E 02 2.25E 02 0 0 1.83E 05 2.26E 05 0 y Ce-141 3.92E 04 1.95E 04 0 8.55E 03 5.44E 05 5.66E 04 0 2.90E 03 Ce-144 6.77E 06 2.12E 06 0 1.17E 06 1.206 07 3.89E 05 0 3.61E 05 R

l 1 O 8

m

m TABLE B-6 (CONTINUED)

$ Ri VALUES - VEGETATION - CHILD z

9 m2 -mrem /vr c) uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN. T. BODY H-3* 0 4.01E 03 4.01E 03 4.01E 03 4.01E 03 4.01E 03 0 4.01E 03 Cr-51 0 0 6.49E 04 1.77E 04 1.18E 05 6.20E 06 0 1.17E 05 Mn-54 0 6.65E 08 0 1.86E 08 0 5.58E 08 0 1.77E 08 Fe-55 8.01E 08 4.25E 08 0 0 2.40E 08 7.87E 07 0 1.32E 08 Fe-59 3.97E 08 6.42E 08 0 0 1.86E 08 6.69E 08 0 3.20E 08 Co-57 0 2.98E 07 0 0 2.44E 08 0 6.04E 07 Co-58 0 6.45E 07 0 0 0 3.76E 08 0 1.97E 08 Co-60 0 3.78E 08 0 0 0 2.10E 09 0 1.12E 09 Zn-65 8.12E 08 2.16E 09 0 1.36E 09 0 3.80E 08 0 1.35E 09 Sr-89 3.59E 10 0 0 0 0 1.39E 09 0 1.03E 09 Sr-90 1.24E 12 0 0 0 0 1.67E 10 0 3.15E 11 Zr-95 3.86E 06 8.50E 05 0 1.22E 06 0 8.86E 08 0 7.56E 05 Nb-95 4.10E 05 1.60E 05 0 1.50E 05 0 2.95E 08 0 1.14E 05 Mo-99 0 7.70E 06 0 1.64E 07 0 6.37E 06 0 1.91E 06 Ag-110m 3.21E 07 2.17E 07 0 4.04E 07 0 2.E8E 09 0 1.74E 07 Sb-124 3.52E 08 4.57E 06 7.78E 05 0 1.95E 08 2.20E 09 1.23E 08 I-131 1.43E 08 1.44E 08 4.75E 10 2.36E 08 0 1.28E 07 0 8.17E 07 I-133 3.56E 06 4.41E 06 8.19E 08 7.34E 06 0 1.78E 06 0 1.67E 06 I-135 6.28E 04 1.13E 05 1.00E 07 1.73E 05 0 8.61E 04 0 5.34E 04 Cs-134 1.60E-10 2.63E 10 0 8.16E 09 2.93E 09 1.42E 08 0 5.55E 09 m Cs-136 8.23E 07 2.26E 08 0 1.21E 08 1.80E 07 7.95E 06 0 1.46E 08 E Cs-137 2.39E 10 2.29E 10 0 7.46E 09 2.68E 09 1.43E 08 0 3.38E 09

• Ba-140 2.77E 08 2.43E 05 0 7.90E 04 1.45E 05 1.40E 08 0 1.62E 07 gs La-140 3.25E 03 1.14E 03 0 0 0 3.17E 07 0 3.83E 02 g Ce-141 6.56E 05 3.27E 05 0 1.43E 05 0 4.08E 08 0 4.85E 04 Ce-144 1.27E 08 3.98E 07 0 2.21E 07 0 1.04E 10 0 6.78E 06 R

• mrem /vr f uCi/m3 3:

O O O

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( J D TABLE B-6 (CONTINUED) y Ri VALUES - C0W HEAT - CHILD h

m2-mrem /Yr i o uCi/sec NUCLIDE B0NE LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BODY l

2.33E 02 2.33E 02 2.33E 02 2.33E 02 2.33E 02 0 2.33E 02 H-3* 0 4.61E 03 2.41E 05 0 4.55E 03 Cr-51 0 0 2.53E 03 6.90E 02 Mn-54 0 5.15E 06 0 1.44E 06 0 4.32E 06 0 1.37E.06 3.04E 08 1.61E 08 0 0 9.11E 07 2.98E 07 0 4.99E 07 Fe-55 0 9.58E 07 3.44E 08 0 1.65E 08 Fe-59 2.04E 08 3.30E 08 0 Co-57 0 3.78E 06 0 0 0 3.10E 07 0 7.66E 06 Co-58 0 9.41E 06 0 0 0 5.49E 07 0 2.88E 07 Co-60 0 4.64E 07 0 0 0 2.57E 08 0 1.37E 08 Zn-65 2.39E 08 6.35E 08 0 4.00E 08 0 1.12E 08 0 3.95E 08 Sr-89 2.65E 08 0 0 0 0 1.03E 07 0 7.57E 06 Sr-90 7.01E 09 0 0 0 0 9.44E 07 0 1.78E 09 Zr-95 1.51E 06 3.32E 05 0 4.75E 05 0 3.46E 08 0 2.95E 05 Nb-95 1.64E 06 6.38E 05 0 6.00E 05 0 1.18E 09 0 4.56E 05 Mo-99 0 5.71E 04 0 1.22E 05 0 4.72E 04 0 1.41E 04 Ag-110m 5.34E 06 3.61E 06 0 6.72E 06 0 4.29E 08 0 2.88E 06 Sb-124 1.65E 07 2.13E 05 3.63E 04 0 9.13E 06 1.03E 08 0 5.77E 06 I-131 8.27E 06 8.32E 06 2.75E 09 1.37E 07 0 7.41E 05 0 4.73E 06 I-133 3.09E-01 3.82E-01 7.10E 01 6.37E-01 0 1.54E-01 0 1.45E-01 I-135 3.43E-17 6.17E-17 5.46E-15 9.46E-17 0 4.70E-17 0 2.92E-17 Cs-134 6.10E 08 1.00E 09 0 3.10E 08 1. lie 08 5.39E 06 0 2.11E 08 y 1.77E 06 7.85E 05 0 1.45E 07 m Cs-136 8.12E 06 2.23E 07 0 1.19E 07

% Cs-137 8.99E 08 8.60E 08 0 2.80E 08 1.01E 08 5.39E 06 0 1.27E 08 Ba-140 2.20E 07 1.93E 04 0 6.27E 03 1.15E 04 1.11E 07 0 1.28E 06 P La-140 2.83E-02 9.90E-03 0 0 0 2.76E 02 0 3.34E-03

% Ce-141 1.17E 04 5.82E 03 0 2.55E 03 0 7.26E 06 0 8.64E 02 Ce-144 1.48E 06 4.65E 05 0 2.57E 05 0 1.21E 08 0 7.92E 04 q

0 8

• mrem /vr iC uCi/m3

g TABLE B-6 (CONTINUED) h Ri VALUES - C0W HILK - CHILD m2 -mrem /vr o uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG -GI-LLI SKIN -T. BODY H-3* 0 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 0 1.57E 03 Cr-51 0 0 2.93E 04 8.00E 03 5.34E 04 2.80E 06 0 5.27E 04 Mn-54 0 1.35E 07 0 3.78E 06 0 1.13E 07 0 3.59E 06 Fe-55 7.43E 07 3.94E 07 0 0 2.23E 07 7.30E 06 0 1.22E 07 Fe-59 6.53E 07 1.06E 08 0 0 3.06E 07 1.10E 08 0 5.26E 07 Co-57 0 2.45E 06 0 0 0 2.01E 07 0 4.96E 06 Co-58 0 6.95E 06 0 0 0 4.05E 07 0 2.13E 07 Co-60 0 2.89E 07 0 0 0 1.60E 08 0 8.52E 07 Zn-65 2.63E 09 7.00E 09 0 4.41E 09 0 1.23E 09 0 4.35E 09 Sr-89 3.64E 09 0 0 0 0 1.41E 08 0 1.04E.08 Sr-90 7.53E 10 0 0 0 0 1.01E 09 0 1.91E 10 Zr-95 2.17E 03 4.77E 02 0 6.83E 02 0 4.98E 05 0 4.25E 02 Nb-95 1.68E 05 6.55E 04 0 6.15E 04 0 1.21E 08 0 4.68E 04 Mo-99 0 4.06E 07 0 8.67E 07 0 3.36E 07 0 1.00E 07 Ag-110m 1.33E 08 8.98E 07 0 1.67E 08 0 1.07E 10 0 7.18E 07 Sb-124 6.11E 07 7.92E 05 1.35E 05 0 3.39E 07 3.82E 08 0 2.14E 07 I-131 6.52E 08 6.55E 08 2.17E 11 1.08E 09 0 5.83E 07 0 3.72E 08 I-133 8.70E 06 1.08E 07 2.00E 09 1.79E 07 0 4.33E 06 0 4.07E 06 I-135 2.72E 04 4.89E 04 4.33E 06 7.49E 04 0 3.72E 04 0 2.31E 04 Cs-134 1.50E 10 2.46E 10 0 7.61E 09 2.73E 09 1.32E 08 0 5.18E 09 8 Cs-136 5.07E 08 1.39E 09 0 7.42E 08 1.11E 08 4.90E 07 0 9.02E 08 jj Cs-137 2.17E 10 2.08E 10 0 6.78E 09 2.44E 09 1.30E 08 0 3.07E 09 Ba-140 5.87E 07 5.15E 04 0 1.68E 04 3.07E 04 2.98E 07 0 3.43E 06 9' La-140 9.73E 00 3.40E 00 0 0 0 9.48E 04 0 1.15E 00 N Ce-141 1.15E 04 5.73E 03 0 2.51E 03 0 7.15E 06 0 8.51E 02 Ce-144 1.04E 06 3.26E 05 0 1.80E 05 0 8.50E 07 0 5.55E 04 9.

o 8

• mrem /vr E uCi/m3 O O O

p p O U O(m TABLE B-6 (CONTINUED) ga 6 Ri VALUES - GOAT MILK - CilILD z

9 m2 -mrem /vr uCi/sec c) 80NEL LIVER -THYROID KIDNEY LUNG- GI-LLI SKIN T. BODY NUCLIDE 3.20E 03 3.20E 03 3.20E 03 3.20E 03 3.20E 03 0 3.20E 03 H-3* 0 6.41E 03 3.36E 05 0 6.33E 03 Cr-51 0 0 3.51E 03 9.60E 02 0 1.62E 06 0 4.54E 05 0 1.36E 06 0 4.31E 05 Mn-54 2.90E 05 9.49E 04 0 1.59E 05 Fe-55 9.65E 05 5.12E 05 0 0 8.48E 05 1.37E 06 0 0 3.98E 05 1.43E 06 0 6.84E 05 Fe-59 0 0 2.41E 06 0 5.96E 05 Co-57 0 2.94E 05 0 2.55E 06 Co-58 0 8.34E 05 0 0 0 4.86E 06 0 0 3.47E 06 0 0 0 1.92E 07 0 1.02E 07 Co-60 1.47E 08 0 5.22E 08 Zn-65 3.15E 08 8.40E 08 0 5.29E 08 0 7.65E 09 0 0 0 0 2.96E 08 0 2.19E 08 Sr-89 0 0 2.13E 09 0 4.01E 10 Sr-90 1.58E 11 0 0 2.60E 02 5.73E 01 0 8.20E 01 0 5.97E 04 0 5.10E 01 Zr-95 7.39E 03 0 1.45E 07 0 5.62E 03 Nb-95 2.02E 04 7.86E 03 0 0 4.87E 06 0 1.04E 07 0 4.03E 06 0 1.21E 06 Mo-99 1.28E 09 0 8.61E 06 Ag-110m' 1.59E 07 1.08E 07 0 2.01E 07 0 Sb-124 7.33E 06 9.15E 04 1.62E 04 0 4.07E 06 4.58E 07 0 2.57E 06 I-131 7.82E 08 7.86E 08 2.60E 11 1.29E 09 0 7.00E 07 0 4.47E 08 I-133 1.04E 07 1.29E 07 2.40E 09 2.15E 07 0 5.20E 06 0 4.88E 06 I-135 3.26E 04 5.87E 04 5.19E 06 8.99E 04 0 4.47E 04 0 2.77E 04 Cs-134 4.49E 10 7.37E 10 0 2.28E 10 8.19E 09 3.97E 08 0 1.55E 10 1.52E 09 4.18E 09 0 2.23E 09 3.32E 08 1.47E 08 0 2.71E 09

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o Cs-136 6.52E 10 6.24E 10 0 2.03E 10 7.32E 09 3.91E 08 0 9.21E 09 Cs-137 4.11E 05 Ba-140 7.05E 06 6.17E 03 0 2.01E 03 3.68E 03 3.57E 06 0 1.17E 00 4.08E-01 0 0 0 1.14E 04 0 1.38E-01 9 La-140 6.88E 02 0 3.02E 02 0 8.58E 05 0 1.02E 02 M Ce-141 1.38E 03 6.66E 03 Ce-144 1.25E 05 3.91E 04 0 2.17E 04 0 1.02E 07 0 9.

O g

• mrem /vr I uCi/m3

TABLE B-6 (CONTINUED) go Ri VALUES - GROUND PLANE - INFANT i

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9 m2 -mrem /vr c) uCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LLUNG. GI-LLI SKIN T. BODY H-3 0 0 0 0 0 0 0 0 Cr-51 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 5.50E 06 4.65E 06 Mn-54 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.62E 09 1.38E 09 Fe-55 0 0 0 0 0 0 0 0 Fe-59 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E OS 2.73E 08 3.20E 08 2.73E 08 Co-57 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 2.07E 08 1.88E 08 Co-58 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 4.45E 08 3.80E 08 Co-60 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.53E 10 2.15E 10 Zn-65 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 8.57E 08 7.46E 08 Sr-89 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.51E 04 2.16E 04 Sr-90 0 0 0 0 0 0 0 0 Zr-95 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.85E 08 2.45E 08 Nb-95 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.61E 08 1.37E 08 Mo-99 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 4.62E 06 3.99E 06 Ag-110m 3.45E 09 3.45E 09 3.45E 09 3.45E 09 3.45E 09 3.45E 09 4.02E 09 3.45E 09 Sb-124 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 6.92E 08 5.99E 08 I-131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 1.72E 07 I-133 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 3.00E 06 2.46E 06 I-135 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.95E 06 2.53E 06 Cs-134 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 8.05E 09 6.90E 09 2 Cs-136 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.71E 08 1.51E 08 y Cs-137 1.03E 10 1.03E 10 2.05E 07 1.03E 10 2.05E 07 1.03E 10 2.05E 07 1.03E 10 2.05E 07 1.03E 10 2.05E 07 1.20E 10 2.35E 07 1.03E 10 2.05E 07 Ba-140 2.05E 07 93 La-140 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 2.18E 07 1.92E 07 y Ce-141 1.37E 07 1.37E 07 6.96E 07 1.37E 07 6.96E 07 1.37E 07 6.96E 07 1.37E 07 6.96E 07 1.37E 07 6.96E 07 1.54E 07 8.05E 07 1.37E 07 6.96E 07 Ce-144 6.96E 07 9.

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O O O TABLE B-6 (CONTINUED) m Ri VALUES - INHALATION - INFANT z

P mrem /vr uCi/m3 c3 NUCLIDE B0NE- LIVER THYROID KIDNEY LUNG GI-LLI SKIN T. BDDY-H-3 0. 6.47E 02 6.47E 02 6.47E 02 6.47E 02 6.47E 02 0 6.47E 02 Cr-51 0 0 5.75E 01 1.32E 01 1.28E 04 3.57E 02 0 8.95E 01 Mn-54 0 2.53E 04 0 4.98E 03 1.00E 06 7.06E 03 0 4.98E 03 Fe-55 1.97E 04 1.17E 04 0 0 8.69E 04 1.09E 03 0 3.33E 03 Fe-59 1.36E 04 2.35E 04 0 0 1.02E 06 2.48E 04 0 9.48E 03 Co-57 0 6.51E 02 0 0 3.79E 05 4.86E 03 0 6.41E 02 Co-58 0 1.22E 03 0 0 7.77E 05 1.11E 04 0 1.82E 03 Co-60 0 8.02E 03 0 0 4.51E 06 3.19E 04 0 1.18E 04 Zn-65 1.93E 04 6.26E 04 0 3.25E 04 6.47E 05 5.14E 04 0 3.11E 04 Sr-89 3.98E 05 0 0 0 2.03E 06 6.40E 04 0 1.14E 04 Sr-90 4.09E 07 0 0 0 1.12E 07 1.31E 05 0 2.59E 06 Zr-95 1.15E 05 2.79E 04 0 3.11E 04 1.75E 06 2.17E 04 0 2.03E 04 Nb-95 1.57E 04 6.43E 03 0 4.72E 03 4.79E 05 1.27E 04 0 3.78E 03 Mo-99 0 1.65E 02 0 2.65E 02 1.35E 05 4.87E 04 0 3.23E 01 Ag-110m 9.98E 03 7.22E 03 0 1.09E Oi 3.67E 06 3.30E 04 0 5.00E 03 Sb-124 3.79E 04 5.56E 02 1.00E 02 0 2.65E 06 5.91E 04 0 1.20E 04 I-131 3.79E 04 4.44E 04 1.48E 07 5.18E 04 0 1.06E 03 0 1.96E 04 I-133 1.32E 04 1.92E 04 3.56E 06 2.24E 04 0 2.16E 03 0 5.60E 03 1-135 3.86E 03 7.60E 03 6.96E 05 8.47E 03 0 1.83E 03 0 2.77E 03 Cs-134 3.96E 05 7.03E 05 0 1.90E 05 7.97E 04 1.33E 03 0 7.45E 04 Cs-136 4.83E 04 1.35E 05 0 5.64E 04 1.18E 04 1.43E 03 0 5.29E 04

@ 5.49E 05 6.12E 05 0 1.72E 05 7.13E 04 1.33E 03 0 4.55E 04 o Cs-137 Ba-140 5.60E 04 5.60E 01 0 1.34E 01 1.60E 06 3.84E 04 0 2.90E 03 La-140 5.05E 02 2.00E 02 0 0 1.68E 05 8.48E 04 0 5.15E 01 P 5.25E 03 5.17E 05 2.16E 04 0 1.99E 03 g Ce-141 2.77E 04 1.67E 04 0 5.38E 05 9.84E 06 1.48E 05 0 1.76E 05 Ce-144 3.19E 06 1.21E 06 0 9.

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i Rev. No. O Page B-30 of ODCM l l

l

I TABLE B-7  !

DERIVATION OF GASEOUS DOSE FACTORS TABLE PAGE B-7.1 Derivation of (P)i Values B-32 B-7.2 Derivation of Gaseous Dose Factors (R)3 B-33 B-7.3 Parameters for the Gaseous Effluent Pathway B-42 B-7.4 Justification for Gaseous Pathways Used to B-45 Assess Dose B-7.5 Organ Doses for Gaseous Releases - Inhalation B-47 Pathway 9

O Rev. No. O Page B-31 of ODCM J

l l

TABLE B-7.1 DERIVATION OF (P) VALUES Die pathway dose factor, P,, for radioiodines, tritium, and 8-day particulates includes transport parameters of the ith nuclide, the receptor usage rate of the pathway media, and the appropriate dose conversion factor. For the inhalation pathway, the value of Pi is calculated as follows:

P = K' (BR) DFA, (mremlyr per pCifm')

g I

Where-1 8

K' = a constant of unit conversion,10 pCi/ Cl.

(BR) = the breathing rate of the age group, in m8/yr (Table E-5 of Regulatory Guide 1.109).

DFA, = the maximum organ inhalation dose factor for the appropriate age groep for the ith radionuclide, in mrem /pCl (Tables E-7 to E-10 of Regulatory Guide 1.109).

Example Calculation:

For the 1-131 child thyroid dose factor for exposure from inhalation:

DFAi = 4.39E-03 mrem /pCI BR = 3700 m'/yr These values will yield a P, factor of 1.62E7 mrem /yr per Ci/m as listed in Table B-4 of this appendix.

l O

Rev. No. O Page B-32 of ODCM

I TABLE B-7.2 DERIVATION OF GASEOUS DOSE FACTORS (R) h The pathway dose factor R, for radiciodines, tritium, and 8 day particulates include transport parameters of the ith nuclide, the receptor usage rate of the pathway media, and the appropriate dose conversion factor. In developing the Ri values, separate 1 expressions are written for each of the potential pathways.

j l. INHALATION For the inhalation pathway, the value of R, is calculated as follows:

l R, = K' (BR), (DFA ), (mremlyr per pCi/m')

g Where:

K' = a constant of unit conversion,10e pCl/pCl.

(BR), = the breathing rate of the receptor of age group (a) in m8 /yr 1 (Table B-7.3). l (DFA,), = the organ inhalation dose factor for the receptor of age group (a) for the ith radionuclide, in mrem /pCi (Tablos E-7 to E-10 of g

Regulatory Guide 1.109).

1 Exarnole Calculation:

For the Co-60 child total body dose factor from exposure due to inhalation:

(DFA),

i = 6.12E-6 mrem /pCi (BR), =3700m/yr These values yield a R, factor of 2.26E4 mrem /yr per pCi/m as listed in Table B-6 of this appendix.

I

11. GROUND PLANE For the ground plane pathway, the value of R3 is calculated as follows:

R, = K' K" (SF) DFG, ~( 1 -e **)lz (m'-mremlyr per pCifsec)

Rev. No. O Page B-33 of ODCM

TABLE B-7.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS (R)

K' = a constant of unit conversion,10' pCi/ Cl.

K" = a constant of unit conversion,8760 hr/yr.

Al = the decay constant for the ith radionuclide, sec".

i

! t = the exposure time,4.73E8 sec (Table B-7.3).

DFGi = the ground plane dose conversion factor for the ith radionuclide, mrem /hr per pCi/m*. (See Table E-6 cf Regulatory Guide 1.109).

SF = the shielding factor,0.7, dimensionless (Table B-7.3).

Examole Calculation:

l l For the Co40 child total body dose factor from exposure due to the ground

! plane:

11 = 4.20E-9 sec" DFG, = 1.70E-8 mrem /hr per pCi/m" These values yield a R, factor of 2.15E10 m*-mrem /yr per pCl/sec as listed in Table B4 of this appendix.

Ill. VEGETATION A. Radiciodines And Eiaht Day Partim!ataa For the vegetation pathway, Ri , is calculated as follows:

(') **

R, = K' Y, ( A, + A ) (DFL,), U,' fz e + U,' f, e'**'s (m'-mremlyr per pCifsec)

Where:

8 I

K' = a Constant of unit conversion,10 pCi/ Cl.

LI, = the consumption rate of fresh leafy vegetation by the receptor in age group (a), in kg/yr (Table B-7.3).

Rev. No. O Page B-34 of ODCM

._. . _ ___..___.._ _ _ _. _ -_ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ -

I 1

TABLE B-7.2 (Continued) l l

DERIVATION OF GASEOUS DOSE FACTORS (R)

U, = the consumption rate of stored vegetation by the receptor in age group (a), in kg/yr (Table B-7.3),

ft = the fraction of the annual intake of fresh leafy vegetation grown locally (Table B-7.3).

f, = the fraction of the annual intake of stored vegetation grown locally (Table B-7.3).

tt = the average time between harvest of leafy vegetation and its consumption, in seconds (Table B-7.3).

tn = the average time between harvest of stored vegetation and its consumption, in seconds (Table B-7.3).

2 Yy = the vegetation areal density, in kg/m (Table B-7.3).

r = fraction of deposited actnnty retained on vegetation (Table B-7.3).

11 = the decay constant for the ith radionuclide, in sec.

Aw = the decay constant for removal of activity on leaf and plant O

surfaces by weathering, 5.73E-7 sec (corresponding to a 14 day half-life).

(DF(), = the maximum organ ingestion dose factor for the ith radionuclide for the receptor in age group (a), in mrem /pCl (Tables E-11 to E-14 of Regulatory Guide 1.109).

Examole Calculation:

For the Co-60 child total. body dose factor from exposure due to ingestion of vegetation:

L U, = 26 kg/yr S

U, = 520 kg/yr ft =1 f, = 0.76 Rev. No. O Page B-35 of ODCM

TABLE B-7.2 (Continued) t DERNATION OF GASEOUS DOSE FACTORS (R)i to = 8.6E4 see tn = 5.18E6 sec Y, = 2 kg/m2 r = 0.2 11 = 4.2E-9 sec" Aw = 5.73E-7 sec" (DFh), = 1.56E-5 mrem /pCi These values yield an R factor of 1.12E9 m -mrem /yr per Ci/sec as listed in 3

Table B-6 of this appendix.

B. Tritium The concentration of tritium in vegetation is based on the airbome

]G concentration rather than the deposition. R, is calculated as follows:

R, = K' K" (U,' ft + Ul f,) (DFL,), [0.75 (0.5/H)]

] \

3 (mremlyr per pCifm )

Where: i l

8 K' = unit conversion constant,10 pCi/ Cl. ,

1 K'" = unit conversion constant,10 gm/kg.

0.75 = the fraction of vegetation which is water (NUREG-0133).

0.50 = the ratio of the specific actmty of the vegetation that is water to the atmospheric water (NUREG-0133).

H = absolute atmospheric humidity, in gm/m' (Table B-7.3).

All other parameters are as previously defined above.

C'\

V Rev. No. O Page B-36 of ODCM ll

TABLE B-7.2.(Continued)

DERIVATION OF GASEOUS DOSE FACTORS (R)i Examole Calculation For the H-3 child total body dose factor from exposure due to ingestion of vegetation:

L U, = 26 kg/yr U, = 520 kg/yr ft =l f, = 0.76 (DF13 ), = 2.03E-7 mrem /pCi H = 8 gm/m (NUREG-0133)

These values yield a R i factor of 4.01E3 mrem /yr per Cl/m as listed in Table B-6 of this appendix.

IV. MEAT O

A. Radiciodines And Elaht Day Particulates R, = K, Qr (U,p) Ff (r) (DFL,), fpf, + (1-fpf,)c'#' e

-x,,f

( A, + A ) Y, Y, (m2 -mremlyr per pCifsec)

Where:

U, = the receptor's meat consumption rate for age (a), in kg/yr (Table

, B-7.3).

l F, = the stable element transfer coefficients, in days /kg (Table E-1 of Regulatory Guide 1.109).

! t, = the transport time from pasture to receptor, in sec (Table B-7.3).

tn = the transport time from crop field to receptor, in sec (Table B-7.3).

Rev. No. O Page B-37 of ODCM l

TABLE B-7.2 (Continued)

O- a=a'v>Tioa or a^==ou= ao== racroa= (aa Y, = the agricultural productivity by unit area of pasture feed grass, in kg/m (Table B-7.3). j 2 i Y, = the agricultural productivity by unit area of stored feed, in kg/m (Table B-7.3).

f, = fraction of the year that the cow is on pasture (Table B-7.3).

f, = fraction of the cow feed that is pasture grass while the cow is on pasture (Table B-7.3).

' O, = the cow's consumption rate, in kg/ day (wet weight). See Table B-7.3.

Ali other parameters were defined previously.

Examole Calculation:

For the Co-60 child total body dose factor from exposure due to ingestion of meat:

e U,, = 41 kg/yr -

F, = 1.3E-2 days /kg tn = 7.78E6 sec t, = 1.73E6 sec

, f, = 6/12 = 0.5 f, =1 (DF(), = 1.56E-5 mrem /pCi Y, = 0.7 kg/m Y, = 2.0 kg/m'  !

l Og = 50 kg/ day j a

These values yield a Ri factor of 1.37E8 m -mrem /yr per Ci/sec as listed in Table B-6 of this appendix.

Rev. No. O Page B-38 of ODCM l

TABLE B-7.2 (Continued)

DERIVATION OF GASEOUS DOSE FAC(ORS (R) g B. Tritium The concentration of tritium in meat is based on the airbome concentration rather than the deposition. R, is calculated as follows:

R, = K' K'" F, Q, U, (DFL,), [0.75 (0.5lH)]

(mremfyr per pCi/m')

Examole Calculation:

All parameters have been defined in the previous sections for the H-3 child total body dose factor from exposure due to ingestion of meat. Substituting values into the preceding equation, results in a R, factor of 2.33E2 mrem /yr per pCi/m' as listed in Table B-6 of this appendix.

V. COW'S MILK A. Radiciodines and Elaht Day Particulates For the cow's milk pathway, R, is calculated as follows:

R, v K' F, (r) (DFL,), ' *+ '*# e%*

( A, + A,) Y, Y, (m2-mremlyr per pCllsec)

Where:

U, = the receptor's milk consumption rate for age (a), in liters /yr (Table B-7.3).

t, = the transport time from pasture to cow, to milk, to receptor in sec (Table B-7.3).

F, = the stable element transfer coefficients, in days / liter (from Regulatory Guide 1.109, Table E-1).

All other parameters were defined previously.

Rev. No. O Page .B-39 of ODCM

I TABLE B-7.2 (Continued)

[ DERIVATION OF GASEOUS DOSE FACTORS (R,)

Examole Calculation:

For the Co-60 child total body dose factor from exposure due to ingestion of cow's milk:

t, = 1.73E5 sec U, = 3301/yr Fm = 1.0E-3 days /l 2

These values yield a R, factor of 8.52E7 m -mrem /yr per Cl/sec as listed in Table B-6 of this appendix.

B. Tritium The concentration of tritium in cow's milk is based on the airborne concentration rather than the deposition. Ri is calculated.as follows:

R, = K' K'" F, Q7 U,, (DFL,), [0.75(0.5lH)]

(mieml year per pCijm')

Examole Calculation:

All parameters have been defined in the previous sections for the H-3 child ,

total body dose factor from exposure due to ingestion of cow's milk. '

Substituting values into the preceding equation, results in a R, factor of 1.57E3 mrem /yr per Cl/m as listed in Table B4 of this appendix.  ;

i VI. GOATS MILK A. Radioiodines and Eloht Day Particulates For the goat's milk pathway, R, is calculated as follows:

L = K' F" (r) (DFL,)* ' I* + ' *' e '**'t (1, + 1.) Y, Y, (m2-mrem /yr per pCl/sec)

Rev. No. O Page B-40 of ODCM

TABLE B-7.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS (R) g Where:

t, = the transport time from pasture to goat, to milk, to receptor in sec (Table B-7.3).

F, = the stable element transfer coefficients. For the radionuclide in question, use Table E-2 of Regulatory Guide 1.109. If the radionuclide is not listed in Table E-2, use Table E-1 (i.e., the same value used for the cow's milk pathway).

All other parameters were defined previously.

Examole Calculation:

For the Co-60 child total body dose factor from exposure due to ingestion of goat's milk:

Og = 6 kg/ day (wet weight)

F, = 1.0E-3 days /l t, = 1.73E5 sec These values yield a R, factor of 1.02E7 m'-mrem /yr per Ci/sec as listed in Table B-6 of this appendix.

B. Tritium The concentration of tritium in goat's milk is based on the airbome concentration rather than the deposition. Ri is calculated as follows:

R, = K' K"' F, Q, U,, (DFL,), [0.75(0.$1H)}

(miemlyr per pCijm')

Examole Calculation:

All parameters have been defined in the previous sections for the H-3 child total body dose factor from exposure due to ingestion of goat's milk. l Substituting values into the preceding equation, result in a R, factor of 3.20E3 ,

mrern/yr per pCl/m 8as listed in Table B-6 of this appendix. '

O\

Rev.No. O Page B-41 of ODCM

TABLE B-7.3 O

V PARAMETER FOR THE GASEOUS EFFLUENT PATHWAY PARAMETERS VALUE REFERENCE TABLE U, (liters /yr)-cow's milk /

- infant 330 R.G. 1.109 E-5

- child 330 R.G. 1.109 E-5

- teen 400 R.G. 1.109 E-5

- adult 310 R.G. 1.109 E-5 U, (liters /yr)-goat's milk /

- infant 330 R.G. 1.109 E-5

- child 330 R.G. 1.109 E-5

- teen 400 R.G. 1.109 E-5

- adult 310 R.G. 1.109 E-5 U, (kg/yr)-vegetation /

- infant 0 R.G. 1.109 E-5

- child 26 R.G. 1.109 E-5 A - teen 42 R.G. 1.109 E-5

() - adult 64 R.G. 1.109 E-5 U, (kg/yr)-vegetation / .

- infant 0 R.G. 1.109 E-5

- child 520 R.G. 1.109 E-5

- teen 630 R.G. 1.109 E-5

- adult 520 R.G. 1.109 E-5 U, (kg/yr)-meat /

- infant 0 R.G. 1.109 E-5 A child 41 R.G. 1.109 E-5

- teen 65 R.G. 1.109 E-5

- adult 110 R.G. 1.109 E-5 3

(BR), (m /yr)-inhalation /

- infant 1400 R.G. 1.109 E-5

- child 3700 R.G. 1.109 E-5

- teen 8000 R.G. 1.109 E-5

- adult 8000 R.G. 1.109 E-5 0 -

l Rev. No. O Page 3-42 of ODCM i

TABLE B-7.3 (CONTINUED)

PARAMETER FOR THE GASEOUS EFFLUENT PATHWAY h

PARAMETERS VALUE REFERENCE JABLJ r (dimensionless) 1.0 for R.G. 1.109 E-15 Radiciodine 0.2 for R.G. 1.109 E-15 Particulates fg (dimensionless) 1.0 R.G. 1.109 E-15 f, (dimensionless) 0.76 R.G. 1.109 E-15 tg (sec)-vegetation 8.6E4 R.G. 1.109 E-15 i

th (sec)-vegetation 5.18E6 R.G. 1.109 E-15 )

(DFA ), (mrem /pci)-

g Each R.G. 1.109 E-7 to -

inhalation Radionuclide E-10 DFG, (mrem /hr per pCi/m2 )- Each R.G. 1.109 E-6 ground plane Eadionuclide SF (dimensionless) 0.7 R.G. 1.109 E-15 t (sec)-ground plane 4.73E8 R.G. 1.109 E-15 Q7 (kg/ day)-cow milk 50 R.G. 1.109 E-3 Q, (kg/ day)-goat milk 6 R.G. 1.109 E-3 Yp (kg/m 2) 0.7 R.G. 1.109 E-15 Y, (kg/m2) 2.0 R.G. 1.109 E-15 (DFL,), (mrem /pCi)-meat / Each R.G. 1.109 E-11 to milk / vegetation Radionuclide E-14 1, ( sec) 5.73E-7 R.G. 1.109 E-15 t, (sec)-cow milk / 1.73E5 R.G. 1.109 E-15 goat milk t3 (sec)-cow milk / 7.78E6 R.G. 1.109 E-15 goat milk ,

2 Y, (kg/m ) 2.0 R.G. 1.109 E-15 f" (dimensionless) 0.5 site specific f, (dimensionless) 1.0 NUREG-0133 page 33 O Rev. No. O Page B-43 of ODCM

l l

TABLE B-7.3 (CONTINUED)

O PARAMETER FOR THE GASEOUS EFFLUENT PATHWAY PARAMETERS VALUE REFERENCE TABLE F, (days / liter) Each R. G. 1.109 E-1  ;

Radionuclide l Ff (days /kg) Each R.G. 1.109 E-1 l i

Stable Element l

I 1.73E6 R.G. 1.109 E-15 l l t, (sec)-meat '

l 7.78E6 R.G. 1.109 E-15 th (sec)-meat 3 page 34 H (gm/m ) 8.0 NUREG-0133 l

!O .

O Rev. No. O Page B-44 of ODCM

l l

l TABLE B-7.4 JUSTIFICATION FOR GASEOUS PATHWAYS USED TO ASSESS llhi DOSE AT THE J. A. FITZPATRICK NUCLEAR POWER PLANT 4

1 PATHWAY JUSTIFICATION FOR USAGE i

1. NOBLE GAS EXPOSURE l (GAMMA)

a. Total Body This pathway is used in the ODCM to calculate dose rates only. This  !

pathway is required by the Technical Specifications and NUREG-0133.  !

b. Gamma Air This pathway is used in the ODCM. This pathway is required by the Technical Specifications and NUREG-0133.

2. NOBLE GAS EXPOSURE (BETA)

a. Skin This pathway is used in the ODCM to calculate dose rates only. This pathway is required by the Technical Specifications and NUREG-0133.

b. Beta Air This pathway is used in the ODCM. This pathway is required by the Technical Specifications and NUREG-0133.

3. GROUND PLANE This pathway is used in the ODCM to DEPOSITION calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculation by the Technical Specifications. The Technical Specifications do not require l it to be used for dose rate

' calculations.

4. INHALATION This pathway is used in the ODCM to calculate dose and dose rates. This pathway is required for use in dose and dose rate calculations by the Technical Specifications and NUREG-0133. -

5. VEGETATION This pathway is used in the ODCM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-0133. The Technical specifications and NUREG-0133 do not Rev. NO. O Page B-45 Of ODCM

TABLE B-7.4 (CONTINUED)

() JUSTIFICATION FOR GASEOUS PATHWAYS USED TO ASSESS DOSE AT THE J. A. FITZPATRICK NUCLEAR POWER PLANT

(

l i

PATHWAY JUSTIFICATION FOR USAGE l

require it to be used for dose rate calculations. The calculation of dose factors for stored fruit and vegetables  ;

and fresh fruit and vegetables is l combined in one equation in both the ODCM and NUREG-0133.

6. MEAT This pathway is used in the ODCM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-0133. The Technical Specifications do not require it to be used for dose' rate calculations. The calculation of dose factors for Meat Contaminated Feed and Meat Contaminated Forage is combined in one equation in both the ODCM and NUREG-0133.

7. COW'S MILK This pathway is used in the ODCM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-0133. The Technical Specifications do not require it to be used for dose rate calculations.- The calculation of dose factors for Milk Contaminated Feed and Milk Contaminated Forage is combined in one equation in both the ODCM and NUREG-0133.

8. GOAT'S MILK This pathway is used in the ODCM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-0133. The Technical ,

Specifications and NUREG-0133 do not I require it to be used for dose rate calculations. The calculation of dose factors for Milk Contaminated Feed and Milk Contaminated Forage is combined in one equation in both the ODCM and NUREG-0133.

O Rev. No. O Page B-46 of ODCM l

-- - -. _=. .

3 TABLE B-7.5 N ORGAN DOSES FOR GASEOUS RELEASES (INHALATION PATHWAYS)

• ~ . .

A. A. DULTP. <

e -

BONE LIVER THYROID KIDNEY LUNG GI-LLI T. BODY YEAR (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) 1980 5.6E-05 6.0E-05 1.1E-02 8.2E-05 1.6E-03 1.2E-04 3.5E-05 1981 8.6E-05 5.2E-05 1.1E-02 7.6E-05 8.4E-04 1.4E-04 3.3E-05 1982 1.6E-04 9.5E-05 1.7E-02 1.5E-04 7.8E-04 1.8E-04 4.8E-05 I

I

, siTEENs ,

s ,

BONE LIVER THYROID KIDNEY LUNG GI-LLI T. BODY YEAR (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) 1980 7.4E-05 8.0E-05 1.4E-02 1.1E-04 2.2E-03 1.2E-04 7.7E-05 1981 1.2E-04 6.8E-05 1.4E-02 1.0E-04 1.3E-03 1.5E-04 9.3E-05 1982 2.1E-04 1.3E-04 2.2E-02 2.0E-04 1.2E-03 1.9E-04 7.2E-05 I

i

. (OIILDs w;& -

BONE LIVER THYROID KIDNEY LUNG GI-LLI T. BODY YEAR (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) 1980 9.7E-05 7.7E-05 2.1E-02 1.0E-04 1.9E-03 4.8E-05 4.2E-05 1981 1.6E-04 6.6E-05 1.6E-02 9.5E-05 1.1E-03 6.8E-05 4.0E-05 1982 2.9E-04 1.3E-04 2.6E-02 1.9E-04 1.1E-03 8.8E-05 6.1E-05

[

u i f h;$[ - '

'! [ '

s o BONE LIVER THYROID KIDNEY LUNG GI-LLI T. BODY g YEAR (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) 8 1980 6.5E-05 6.6E-05 1.5E-02 1.4E-04 1.1E-03 1.8E-05 2.8E-05 g 1981 1.1E-04 5.8E-05 1.5E-02 7.0E-05 8.2E-04 2.7E-05 2.7E-05 1982 1.9E-04 1.2E-04 2.4E-02 1.3E-04 8.5E-04 3.4E-05 4.2E-05

~

O O O

O 1

APPENDIX C METEOROLOGICAL INDEX lO .

l 1

1 O l Rev.No. O Page C-1 of ODCM

i l

APPENDIX C METEOROLOGICAL INDEX g The atmospheric dispersion and deposition tables presented in this Appendix were prepared using 8 years' worth of hourly meteorological data (at 10 m and 61 m above grade) collected on site by Niagara Mohawk during the period 1985 through 1992.

The tables include the following:

(a) Long term annual average concentration (X/O)s, finite-cloud gamma (X/O)s, and (D/O)s for the main stack, the four building vents, and unmonitored ground-level releases (Site boundary and offsite receptors) [ Tables C-1 through C-8, C-18, and C 20],

(b) Long-term grazing season concentration (X/0), and (D/0)s for the main stack, the four building vents, and unmonitored ground-level releases (offsite receptors excluding the site boundary) [ Tables C-9 through C-13, C-22 and C-24],

1 (c) Short-term 85th percentile hourly plume centerline concentration (X/O)s and )

(D/O)s for unmonitored ground-level releases, based on year-round meteorological data (Site boundary and offsite receptors) [ Tables C-15, C-16, C-17 and C-19),

(d) Short-term 85th percentile hourly plume centerline concentration (X/0)s and (D/0)s for unmonitored ground-level releases, based on meteorological data g

for the grazing season (offsite receptors excluding the site boundary [ Tables C-21 and C-23),

(e) Critical receptor long-term dispersion and deposition parameters for vent and elevated release, year-round and grazing season averages [ Table C-14).

The receptors of interest include the site boundary (SB) and various offsite locations in each sector at distances out to 45 miles. Note the following:

(1) The long-term annual average concentration (X/O)s and finite-cloud gamma (X/O)s which were based on the sector-average model, are for use in assessing the air doses (gamma and beta), total body and skin dose, and doses due to inhalation from the various release points. The long-term annual average (D/0)s are for assessing the radiation exposures due to ground plane deposition of radioactivity.

(2) The long-term grazing season concentration (X/O)s and (D/0)s are for l use in assessing the radiation exposures for the ingestion pathway. l Based on census data, the grazing season was taken to be six months l (May through October).

Rev.No. O Page _Q-jl of ODCM l l

!- i l

l (3) The 85th percentile hourly concentration (X/O)s and (D/O)s were based i on the plume-centerline model and are for use in conjunction with short- I

^

term releases, as described in Section 4.4.3 of the ODCM. The selected l-]'

j-percentile (85%) is applicable for the assessment of intermittent releases; it implies that the probability of exceeding the calculated hourly  ;

) dispersion and deposition values is only 15%. j

> i (4) The dispersion and deposition parameters for the ' stack were based on  !

l the " elevated plume" model (with plume rise effects, and terrain features, but without building wake effects). and the meteorological data collected i i on the 61-m elevation of the meteorological tower. The dispersion and l deposition parameters for the building vents (reactor building, refuel floor, turbine building, and radwaste building) were based.on the ' mixed-mode' release (with plume rise and building wake effects), and the data collected on the 10-m elevation of the tower. Unmonitored ground-level releases made use for the " ground release" model (with building wake effects, but without plume rise) and the meteorological data collected on -

the 10-m elevation of the tower.

(5) For vent releases and unmonitored ground-level releases, the equations for gamma air dose, total body dose, and the gamma portion of skin -

dose make use of the concentration (X/O) (i.e., the semi-infinite cloud model). For stack releases, on the other hand, the equations for the said exposures make use of the finite-cicud ~ gamma (X/O). By definition, the gamma (X/O) is the equivalent relative concentration of radioactivity in a O- semi-infinite cloud that would yield the same radiation exposure as a finite cloud aloft; it accounts for the actual plume dimensions, elevation -

above the receptor, and gamma radiation spectra.

Complete details on the definition of the dispersion and deposition values presented in  !

this appendix may be found in Reference 6.10.

O Rev. No. O Page _Q-3, of ODCM ,

- , _ . _ .- _ , . _ . . -__ _ _ ~ . _ _ . _ . . . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . . _

APPENDIX C METEOROLOGICAL DATA g TABLE TITLE PAGE C-1 Concentration X/O Values for Site Boundary Determined From C-7 Annual Average Meteorological Data C-2 Finite Cloud Gamma X/O Values for Site Boundary Determined C-8 From Annual Average Meteorological Data C-3 Deposition D/O Values for Site Boundary Determined From C-9 4

Annual Average Meteorological Data C-4 Sector Average Dispersion And Deposition Values For Reactor C-10 )

Vent Determined From Annual Average Meteorological Data C-5 Sector Average Dispersion And Depsition Values For Refuel C-12 Floor Vent Determined From Annual Average Meteorological Data C-6 Sector Average Dispersion And Deposition Values For Turbine C-14 ,

Vent Determined From Annual Average Meteorological Data l I

C-7 Sector Average Dispersion And Deposition Values For Radwaste Vent Determined From Annual Average Meteorological Data C-16 gl '

C-8 Sector Average Dispersion And Deposition Values For The Stack C-18 Determined From Annual Average Meteorological Data C-9 Sector Average Dispersion And Deposition Values For Reactor C-19 Vent Determined From Grazing Meteorological Data C-10 Sector Average Dispersion And Deposition Values For Refuel C-20 Floor Vent Determined From Grazing Meteorological Data l

C-11 Sector Average Dispersion And Deposition Values For Turbine C-25 Vent Determined From Grazing. Meteorological Data l C-12 Sector Average Dispersion And Deposition Values For Radwaste C-27 l Vent Determined From Grazing Meteorological Data  ;

1 C-13 Sector Average Dispersion And Deposition Values For The Stack C-29  !

Determined From Grazing Meteorological Data O

Rev. No. O Page C-4 of ODCM

__ _ _ _ -.. ~

1 APPENDIX C j (m

\

METEOROLOGICAL DATA (CONTINUED) l TABLE TITLE PAGE C-14 Critical Receptor Dispersion And Deposition Parameters For Vent C-32 )

And Elevated Releases C-15 85th Percentile Hourly Plume Center;ine Dispersion Values and C-33 Annual Sector Average Dispersion Values For Unmonitored Ground Level Releases Determined From Annual Average Meteorological Data (1985-1992) (For Use With Short Term Releases)

C-16 85th Percentile Hourly Plume Centerline Deposition Values and C-34 Annual Sector Average Deposition Values For Unmonitored Ground Level Releases Determined From Annual Average Meteorological Data (1985-1992) (For Use With Short Term Releases)

C-17 85th Percentile Hourly Plume Centerline Dispersion Values For C-35 Unmonitored Ground Level Releases Determined From Annual (3 Average Meteorological Data (1985-1992) (For Use With Short Term Releases)

C-18 Sectar Average Dispersion Values For Unmonitored Ground Level C-36 Releases Determined From Annual Average Meteorological Data (1985-1992) (For Use With Long Term Releases)

C-19 85th Percentile Hourly Plume Centerline Deposition Values For C-37 Unmonitored Ground Level Releases Determined From Annual Average Meteorological Data (1985-1992) (For Use With Short Term Releases)

C-20 Sector Average Deposition Values For Unmonitored Ground Level C-38 Releases Determined From Annual Average Meteorological Data (1985-1992) (For Use Wrth Long Term Releases)

C-21 85th Percentile Hourly Plume Centerline Dispersion Valucs For C-39 Unmonitored Ground Level Releases Determined From Grazing Meteorological Data (1985-1992) (For Use With Short Term Releases)

D Rev.No. O Page _Q-5_ of ODCM

I APPENDIX C METEOROLOGICAL DATA (CONTINUED) h TABLE TITLE PAGE C-22 Sector Average Dispersion Values For Unmonitored Ground Level C-40 Releases Determined From Grazing Meteorologicai Data (1985-1992) (For Use With Long Term Releases)

C-23 85th Percentile Hourly Plume Centerline Deposition Values For C-41 Unmonitored Ground Level Releases Determined From Grazing Meteorological Data (1985-1992) (For Use With Short Term Releases)

C-24 Sector Average Deposition Values For Unmonitored Ground C-42 Level Releases Determined From Grazing Meteorological Data (1985-1992) (For Use With Long Term Releases) i O

1 I

O Rev. No. O Page QS_ of ODCM

TABLE C-1 CONCENTRATION X/O VALUES FOR SITE BOUNDARY DETERMINED FROM ANNUAL AVERAGE METEROLOGICAL DATA (1985 TO 1992)

Sector Average Concentration X/Q a

(sec/m )

Turbine Refuel Radwaste Reactor Unmonitored Distance Building Floor Building Building Ground Level Direction M Stack Vent Vent Vent Vent Re l e a s e ,__._

N w 225 1.05E-10 3.81E-06 4.65E-06 5.75E-06 4.65E-06 3.50E-05 NNE w 225 3.58E-11 1.68E-06 2.05E-06 2.60E-06 2.05E-06 1.78E-05 NE w 354 7.52E-10 6.53E-07 8.02E-07 1.12E-06 8.02E-07 5.34E-06 ENE w 563 1.51E-08 7.82E-07 9.21E-07 1.35E-06 9.21E-07 3.435-06 E 1 950 1.64E-08 3.19E-07 3.58E-07 5.39E-07 3.58E-07 1.05E-06 ESE 1 1030 1.78E-08 1.78E-07 1.97E-07 3.02E-07 1.97E-07 -5.86E-07 SE 1 1110 1.94E-08 1.22E-07 1.33E-07 2.28E-07 1.33E-07 4.17E-07 SSE 1 1754 1.57E-08 4.74E-08 4.94E-08 9.17E-08 4.94E-08 1.73E-07 S 1 2205 1.79E-08 4.71E-08 4.80E-08 8.30E-08 4.80E-08 1.36E-07 SSW 1 2269 2.19E-08 6.11E-08 6.25E-08 1.14E 07 6.25E-08 2.00E-07 SW 1 2382 1.64E-08 7.97E-08 8.17E-08 1.60E-07 8.17E-08 3.14E-07 WSW w 1867 3.55E-09 4.08E-08 4.52E-08 1.23E-07 4.52E-08 4.14E-07 W w 644 1.33E-09 9.17E-08 1.43E-07 2.48E-07 1.43E-07 2.68E-06 WNW w 370 1.87E-09 6.82E-07 9.99E-07 1.37E-06 9.99E-07 1.39E-05 NW w 306 2.50E-09 1.77E-06 2.37E-06 3.09E-06 2.37E-06 2.60E-05 NNW w 241 3.96E-10 2.98E-06 3.85E-06 4.81E 06 3.85E-06 3.68E-05 1 - land w - water tO V

Rev.No. O Page C-7 of ODCM

TABLE C-2 i l

FINITE CLOUD GAMMA X/Q VALUES FOR SITE BOUNDARY DETERMillED FROM ANNUAL AVERAGE METEROLOGICAL DATA (1985 TO 1992)

Finite Cloud Gamma X/Q (sec/mi  !

l i

Distance Direction (m) Stack N w 225 1.32E-07 l 1.06E-07 NNE w 225 NE w 354 1.12E-07 ENE w 563 1.82E-07 I E 1 950 1.16E-07 l ESE 1 1030 7.71E-08 SE 1 1110 6.23E-08 SSE 1 1754 3.34E-08 S 1 2205 3.02E-08 SSW 1 2269 3.89E-08 SW l 2382 3.45E-08 WSW w 1867 2.20E-08 W w 644 5.43E-08 WIN w 370 8.40E-08 NW w 306 1.38E-07 NNW w 241 1.38E-07 1 - land w - water O

Rev. No. O Page C-8 of ODCM

2 TABLE C-3 t DEPOSITION D/Q VALUES FOR SITE BOUNDARY. DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 TO 1992)

(D/Q) Sector Averago Deposition (1/ma) )

. SEGMENT BOUNDARIES IN MILES Turbine Refuel Radwaste Reactor Unmonitored Distance Building Floor Building Building Ground Level i Direction (m) Stack Vent Vent Vent Vent Release N w 225 2.95E-10 2.27E-08 2.65E-08 3.63E-08 2.65E-06 1.33E-07 NNE w 225 9.26E-11 1.02E-08 1.18E-08 1.65E-08 1.18E-08 7.09E-08 NE w 354 9.30E-11 6.21E-09 7.30E-09 1.05E-08 7.30E-09 3.00E-08

ENE w 563 1.65E-09 1.40E-08 1.55E-08 2.00E-08 1.55E-08 3.23E-08 E 1 950 1.73E-09 9.03E-09 9.49E-09 1.11E-08 9.492-09 1.35E-08 ESE 1 1030 1.70E-09 6.22E-09 6.49E-09 7.43E-09 6.49E-09 8.76E-09 SE 1 1110 1.61E-09 4.37E-09 4.54E-09 5.42E-09 4.54E-09 6.46E-09

\ SSE 1 1754 7.57E-10 1.16E-09 1.19E-09 1.39E-09 1.19E-09 1.85E-09 S 1 2205 5.52E-10 9.15E-10 9.31E-10 1.06E-09 9.31E-10 1.41E-09

, SSW 1 2269 6.50E-10 7.66E-10 7.76E-10 9.33E-10 7.76E-10 1.37E-09 i SW 1 2382 3.23E-10 7.01E-10 7.09E-10 9.00E-10 7.09E-10 1.51E-09 WSW w 1867 9.10E-11 2.97E-10 3.08E-10 4.68E-10 3.08E-10 1.25E-09 W w 644 7.43E-11 7.58E-10 9.15E-10 1.59E 09 9.15E-10 7.79E-09 WNW w 370 1.89E-10 4.56E-09 5.56E-09 8.40E-09 5.56E-09 4.10E-08  !

1 NW w 306 4.28E-10 1.22E-08 1.45E-08 2.08E-08 1.45E-08 8.55E-08 NNW w 241 3.63E-10 1.71E-08 2.03E-08 2.80E-08 2.03E-08 1.14E-07 j 1

1 - land w - water c

(o)

Rev.No. O Page C-9 of ODCM

7 TABLE C-4 SECTOR AVERAGE DISPERSION VALUES FOR REACTOR VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992) h Sector Average Concentration X/O (sec/m')

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 5.667E-07 3.319E-07 2.409E-07 1.596E-07 9.380E-08 6.472E-08 NNE 2.600E-07 1.591E-07 1.198E 07 8.235E 08 4.960E-08 3.446E-08 NE 2.296E-07 1.410E-07 1.048E 07 7.034E 08 4.129E 08 2.830E-08 ENE 5.479E-07 3.185E-07 2.260E-07 1.452E 07 7.962E-08 5.287E-08 E 4.528E-07 2.601E-07 1.808E 07 1.132E-07 5.918E-08 3.843E 08 ESE 2.804E-07 1.631E-07 1,142E-07 6.935E-08 3.941E-08 2.559E-08 SE 1.991E-07 1.204E 07 8.715E-08 5.~609E-08 3.276E-08 2.602E-08 SSE 1.071E-07 6.936E-08 5.348E-08 3.911E-08 2.835E-08 2.013E-08 S 1.150E-07 7.388E-08 5.963E-08 4.379E-08 3.218E-08 2.223E-08 SSW 1.388E 07 9.086E 08 7.603E-08 5.888E-08 3.860E-08 2.786E-08 SW 1.688E-07 1.129E-07 1.094E-07 8.073E-08 5.290E-08 3.576E-08 WSW 8.263E-08 5.551E-08 4.795E-08 4.949E-08 3.369E-08 2.430E-08 W 1.040E 07 6.463E 08 5.213E-08 4.115E-08 2.881E-08 2.151E-08 WNW 2.926E-07 1.754E-07 1.326E-07 9.420E-08 5.955E-08 4.260E-08 NW 5.036E-07 3.005E-07 2.226E-07 1.520E-07 9.183E-08 6.416E-08 NNW 5.247E-07 3.041E-07 2.202E-07 1.468E 07 8.737E-08 6.082E-08 4.5 7.5 15.0 25.0 35.0 45.0 )

N 4.865E-08 2.687E-08 1.186E-08 6.640E-09 4.458E-09 3.915E-09 NNE 2.595E 08 1.428E-08 6.212E-09 4.945E-09 3.183E-09 2.299E-09 NE 2.110E-08 1.138E-08 5.166E-09 3.338E-09 2.130E-09 1.530E-09 ENE 3.870E-08 2.034E-08 1.024E-08 5.223E-09 3.362E-09 2.430E-09 i E 2.779E-08 1.440E 08 7.309E-09 3.751E-09 2.434E 09 1.772E 09 ESE 1.849E-08 1.133E 08 4.571E 09 2.357E-09 1.535E-09 1.121E-09 SE 1.833E-08 9.165E 09 3.693E 09 1.922E-09 1.261E-09 9.270E-10 SSE 1.438E-08 7.159E-09 2.869E-09 1.492E 09 9.784E-10 7.185E-10 l S 1.595E 08 7.922E 09 3.182E-09 1.659E-09 1.091E-09 8.025E-10 SSW 2.231E-08 1.089E 08 4.278E-09 2.156E-09 1.385E-09 1.002E-09 SW 2.896E-08 1.667E-08 6.450E-09 3.357E-09 2.135E-09 1.532E-09 WSW 1.856E-08 1.029E-08 4.799E 09 2.500E-09 1.783E-09 1.393E-09 l W 1.690E-08 9.922E-09 4.586E-09 2.552E-09 1.729E-09 1.294E-09 l WNW 3.276E-08 1.885E-08 8.746E-09 4.942E-09 3.391E 09 2.562E-09 NW 4.862E-08 2.733E-08 1.241E 08 6.932E-09 4.729E-09 3.560E-09 NNW 4.607E-08 2.596E-08 1.186E-08 6.657E-09 4.554E-09 3.433E-09 O

Rev. No. O Page C-10 of ODCM

TABLE C-4 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR REACTOR VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

(D/Q) Sector Average Deposition (1/m*)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 4.951E-09 2.856E-09 1.927E-09 1.065E-09 4.777E-10 2.756E-10

! NNE 2.348E-09 1.421E-09 9.951E-10 5.692E-10 2.619E-10 1.528E-10

! NE 2.456E-09 1.458E-09 1.004E-09 5.654E-10 2.556E-10 1.477E-10 ENE 9.540E-09 5.276E-09 3.429E-09 1.835E-09 8.030E-10 4.595E-10 E 1.212E-08 6.587E-09 4.219E-09 2.224E-09 9.594E-10 5.450E-10 ESE 9.330E-09 5.097E-09 3.260E-09 1.707E-09 7.428E-10 4,219E-10 SE 7.165E-09 3.997E-09 2.587E-09 1.378E-09 6.078E-10 3.473E-10 SSE 3.529E-09 2.047E-09 1.348E-09 7.357E-10 3.353E-10 1.926E-10 l S _ 791E-09 2.219E-09 1.477E-09 8.098E-10 3.723E-10 2.142E-10 l SSW 2.906E-09 1.760E-09 1.231E-09 7.082E-10 3.322E-10 1.950E-10 l SW 2.421E-09 1.564E-09 1.185E-09 6.960E-10 3.340E-10 1.972E-10

't USW 6.780E-10 4.656E-10 3.626E-10 2.368E-10 1.188E-10 7.206E-11 W 7.119E 10 4.615E-10 3.455E-10 2.100E-10 1.041E-10 6.282E-11 WNW 2.129E-09 1.329E-09 9.567E-10 5.617E-10 2.648E-10 1.561E-10 l

NW 4.192E-09 2.500E-09 1.735E-09 9.847E-10 4.514E-10 2.629E-10 NNW 4.251E 09 2.462E-09 1.669E-09 9.270E-10 4.186E-10 2.423E-10 4.5 7.5 15.0 25.0 35.0 45.0 N 1.805E-10 7.499E-11 2.350E-11 1.000E-11 5.731E-12 5.309E-11 )

NNE 1.006E-10 4.197E-11 1.303E-11 1.958E-11 9.064E-12 5.188E-12 NE 9.681E-11 4.014E 11 1.237E-11 9.909E-12 5,316E-12 3.291E-12 ENE 2.998E-10 1.245E-10 9.570E-11 2.256E-11 1.210E-11 7.496E-12 l

E 3.539E-10 1.462E-10 6.692E-11 2.192E-11 1.176E-11 7.287E-12 ESE 2.738E-10 1.133E-10 4.636E-11 1.651E-11 8.777E-12 5.439E-12 SE 2.252E-10 9.507E-11 3.796E-11 1.493E-11 7.928E-12 4.765E-12 SSE 1.266E-10 5.635E-11 2.578E-11 1.172E-11 4.605E-12 2.811E-12 S 1.434E-10 6.420E-11 2.776E-11 1.370E-11 5.149E-12 3.137E-12 SSW 1.279E-10 5.527E-11 3.074E-11 1.119E-11 5.882E-12 3.129E-12 SW 1.318E-10 5.575E-11 3.290E-11 1.541E-11 7.800E-12 4.596E-12 USW 4.828E-11 2.055E 11 6.450E-12 2.997E-12 2.323E-11 2.807E-12 W 4.194E-11 1.780E-11 5.615E 12 2.418E-12 1.384E-12 9.038E-13 WNW 1.032E-10 4.323E-11 1.338E-11 5.670E-12 3.207E-12 2.082E-12 NW 1.730E-10 7.212E-11 2.246E-11 9.534E-12 5.405E-12 3.520E-12 i NNW 1.590E-10 6.621E-11 2.081E-11 8.887E-12 5.062E-12 3.309E-12 Rev.No. O Page C-11 of ODCM

TABLE C-5 SECTOR AVERAGE DISPERSION VALUES FOR REFUEL FLOOR VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA h

(1985 To 1992)

Sector Average Concentration X/Q (sec/m )

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 5.667E-07 3.319E-07 2.409E-07 1.596E-07 9.380E-08 6.472E-08 NNE 2.600E-07 1.591E-07 1.198E-07 8.235E-08 4.960E-08 3.446E-08 NE 2.296E-07 1.410E-07 1.048E-07 7.034E-08 4.129E-08 2.830E-08 ENE 5.479E-07 3.185E-07 2.260E-07 1.452E-07 7.962E-08 5.287E-08 E 4.528E-07 2.601E-07 1.808E-07 1.132E-07 5.918E-08 3.843E-08 ESE 2.804E-07 1.631E-07 1.142E-07 6.'935E-08 3.941E-08 2.559E-08 SE 1.991E-07 1.204E-07 8.715E-08 5.609E-08 3.276E-08 2.602E-08 SSE 1.071E-07 6.936E-08 5.348E-08 3.911E-08 2.835E-08 2.013E-08 S 1.150E-07 7.388E-08 5.963E-08 4.379E-08 3.218E-08 2.223E-08 SSW 1.388E-07 9.086E-08 7.603E-08 5.888E-08 3.860E-03 2.786E-08 SW 1.688E-07 1.129E-07 1.094E-07 8.073E-08 5.290E-08 3.576E-08 g WSW 8.263E-08 5.551E-08 4.795E-08 4.949E-08 3.369E-08 2.430E-08 W W 1.040E-07 6.463E-08 5.213E-08 4.115E 08 2.881E-08 2.151E-08 WNW 2.926E-07 1.754E-07 1.326E-07 9.420E 08 5.955E-08 4.260E-08 NW 5.036E-07 3.005E-07 2.226E-07 1.520E-07 9.183E-08 6.416E-08 NNW 5.247E-07 3.041E-07 2.202E-07 1.468E-07 8.737E-08 6.082E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 4.865E-08 2.687E-08 1.186E-08 6.640E-09 4.458E-09 3.915E-09 NNE 2.595E-08 1.428E-08 6.212E-09 4.945E-09 3.183E-09 2.299E-09 NE 2.110E-08 1.138E-08 5.166E-09 3.338E-09 2.130E-09 1.530E-09 ENE 3.870E-08 2.034E-08 1.024E-08 5.223E-09 3.362E-09 2.430E-09 E 2.779E-08 1.440E-08 7.309E-09 3.751E-09 2.434E-09 1.772E-09 ESE 1.849E-08 1.133E-08 4.571E-09 2.357E-09 1.535E-09 1.121E-09 SE 1.833E-08 9.165E-09 3.693E-09 1.922E-09 1.261E-09 9.270E-10 SSE 1.438E-08 7.159E-09 2.869E-09 1.492E-09 9.784E-10 7.185E-10 S 1.595E-08 7.922E-09 3.182E-09 1.659E-09 1.091E-09 8.025E-10 SSW 2.231E-08 1.089E-08 4.278E-09 2.156E-09 1.385E-09 1.002E-09 SW 2.896E-08 1.667E-08 6.450E-09 3.357E-09 2.135E-a9 1.532E-09 WSW 1.856E-08 1.029E-08 4.799E-09 2.500E-09 1.783E-09 1.393E-09 W 1.690E-08 9.922E-09 4.586E-09 2.552E-09 1.729E-09 1.294E-09 WNW 3.276E-08 1.885E-08 8.746E-09 4.942E-09 3.391E-09 2.562E 09 NW 4.862E-08 2.733E-08 1.241E-08 6.932E-09 4.729E-09 3.560E-09 NNW 4.607E-08 2.596E-08 1.186E-08 6.657E-09 4.554E-09 3.433E-09 Rev.No. O Page C-12 of ODCM

TABLE C-5 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR REFUEL FLOOR VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

(D/Q) Sector Average Deposition (1/m*)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 l

N 4.951E 09 2.856E-09 1.927E-09 1.065E-09 4.777E-10 2.756E-10 NNE 2.348E-09 1.421E-09 9.951E-10 5.692E-10 2.619E-10 1.528E-10 .

NE 2.456E-09 1.458E-09 1.004E-09 5.654E-10 2.556E-10 1.477E-10 ENE 9.540E-09 5.276E-09 3.429E-09 1.835E-09 S.030E-10 4.595E-10 l E 1.212E-08 6.587E-09 4.219E-09 2.224E-09 9.594E-10 5.450E-10 ]

ESE 9.330E-09 5.097E-09 3.260E-09 1~707E-09

. 7.428E-10 4.219E-10 )

SE 7.165E-09 3.997E-09 2.587E-09 1.378E-09 6.078E-10 3.473E-10 SSE 3.529E 09 2.047E-09 1.348E-09 7.357E-10 3.353E-10 1.926E-10 S 3.791E-09 2.219E-09 1.477E-09 8.098E-10 3.723E-10 2.142E-10 SSW 2.906E-09 1.760E-09 1.231E-09 7.082E-10 3.322E-10 1.950E-10 SW 2.421E-09 1.564E-09 1.185E-09 6.960E-10 3.340E-10 1.972E 10 O. USW 6.780E-10 4.656E-10 3.626E-10 2.368E-10 1.188E-10, 7.206E-11 6.282E-11 W 7.119E-10 4.615E-10 3.455E-10 2.100E-10 1.041E-10 i WNW 2.129E-09 1.329E-09 9.567E-10 5.617E-10 2.648E-10 1.561E-10  !

NW 4.192E-09 2.500E-09 1.735E-09 9.847E-10 4.514E-10 2.629E-10 NNW 4.251E-09 2.462E-09 1.669E-09 9.270E-10 4.186E-10 2.423E-10 4.5 7.5 15.0 25.0 35.0 45.0 N 1.805E-10 7.499E-11 2.350E-11 1.000E-11 5.731E-12 5.309E-11 NNE 1.006E-10 4.197E-11 1.303E-11 1.958E-11 9.064E-12 5.188E-12 NE 9.681E-11 4.014E-11 1.237E-11 9.909E-12 5.316E-12 3.291E-12 ENE 2.998E-10 1.245E-10 9.570E-11 2.256E-11 1.210E-11 7.496E-12 E 3.539E-10 1.462E-10 6.692E-11 2.192E-11 1.176E-11 7.287E-12 ESE 2.738E-10 1.133E-10 4.636E-11 1.651E-11 8.777E-12 5.439E-12 SE 2.252E-10 9.507E-11 3.796E-11 1.493E-11 7.928E-12 4.765E-12 SSE 1.266E-10 5.635E-11 2.578E-11 1.172E-11 4.605E 2.811E-12 S 1.434E-10 6.420E-11 2.776E-11 1.370E-11 5.149E-12 3.137E-12 SSW 1.279E-10 5.527E-11 3 0742-11 1.119E-11 5.882E-12 3.129E-12 SW 1.318E-10 5.575E-11 3.290E-11 1.541E-11 7.800E-12 4.596E-12 USW 4.828E-11 2.055E-11 6.450F 1 's 2.997E-12 2.323E-11 2.807E-12 W 4.194E-11 1.780E-11 5.615E-12 "I.418E-12 1.384E-12 9.038E-13 WNW 1.032E-10 4.323E-11 1.338E-11 5.670E-12 3.207E-12 2.082E-12 NW 1.730E-10 7.212E-11 2.246E-11 9.534E-12 5.405E-12 3.520E-12 NNW 1.590E-10 6.621E-11 2.081E-11 8.887E-12 5.062E-12 3.309E-12 Rev.No. O Page C-13 of ODCM

TABLE C-6 SECTOR AVERAGE DISPERSION VALUES FOR TURBINE VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992) h Sector Average concentration X/Q (sec/m*)

SEGMENT BGUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 4.745E-07 2.863E-07 2.135E-07 1.455E-07 8.729E-08 6.072E-08 NNE 2.185E-07 1.391E-07 1.080E-07 7.646E-08 4.692E-08 3.283E.08 NE 1.908E-07 1.216E-07 9.320E-08 6.460E-08 3.878E-08 2.680E-08 ENE 4.685E-07 2.784E-07 2.016E-07 1.333E-07 7.437E-08 4.972E-08 E 4.004E-07 2.349E-07 1.660E-07 1.065E-07 5.619E-08 3.664E-08 ESE 2.495E-07 1.493E-07 1.063E-07 6.567E-08 3.806E-08 2.477E-08 SE 1.786E-07 1.116E-07 8.218E-08 5.383E-08 3.190E-08 2.554E-08 SSE 9.585E-08 6.492E-08 5.110E-08 3.820E-08 2.809E-08 1.988E-08 S 1.034E-07 6.930E-08 5.745E-08 4.300E-08 3.197E-08 2.199E-08 SSW 1.215E-07 8.350E-08 7.256E-08 5.767E-08 3.815E-08 2.758E 08 SW 1.416E-07 1.007E-07 1.047E-07 7.883E-08 5.215E-08 3.523E 08 WSW 5.908E-08 4.428E-08 4.183E-08 4.757E-08 3.288E-08 2.378E-08 W 6.826E-08 4.692E-08 4.159E-08 3.599E-03 2.653E-08 2.013E 08 WNW 2.087E-07 1.345E-07 1.079E-07 8.132E-08 5.342E-08 3.877E-08 NW 3.914E-07 2.458E-07 1.897E-07 1.349E-07 8.370E-08 5.909E-08 NNW 4.173E-07 2.514E-07 1.883E-07 1.300E-07 7.933S-08 5.580E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 4.584E-08 2.550E-08 1.134E-08 6.384E-09 4.294E-09 3.815E-09 NNE 2.481E-08 1.372E-08 5.996E-09 4.845E-09 3.117E-09 2.252E 09 NE 2.007E-08 1.089E-08 4.994E-09 3.250E-09 2.074E-09 1.489E-09 ENE 3.653E-08 1.930E-08 9.903E 09 5.042E-09 3.245E-09 2.346E-09 E 2.656E-08 1.381E-08 7.100E-09 3.641E-09 2.362E-09 1.720E-09 ESE 1.792E-08 1.108E-08 4.459E-09 2.297E-09 1.496E-09 1.093E-09 SE 1.797E-08 8.964E-09 3.605E-09 1.875E-09 1.230E-09 9.044E-10 SSE 1.416E-08 7.035E-09 2.816E-09 1.463E-09 9.598E-10 7.048E-10 S 1.571E-08 7.792E.09 3.126E-09 1.629E-09 1.071E-09 7.880E-10 SSW 2.205E-08 1.074E-08 4.204E-09 2.118E-09 1.360E-09 9.842E-10 SW 2.862E-08 1.648E-08 6.362E-09 3.300E-09 2.098E-09 1.506E-09 WSW 1.817E-08 1.008E-08 4.723E-09 2.459E-09 1.757E-09 1.368E-09 W 1.593E-08 9.451E-09 4.406E-09 2.462E-09 1.672E 09 1.253E-09 WNW 3.006E-08 1.752E-08 8.236E-09 4.686E-09 3.228E-09 2.445E-09 NW 4.505E-08 2.558E-08 1.174E-08 6.598E-09 4.516E-09 3.407E-09 NNW 4.254E-08 2.422E-08 1.119E-08 6.323E-09 4.340E-09 3.279E-09 O

i Rev. Nc,. O Page .C-14 of ODCM l

l l

TABLE C 6 (CONTINUED)

O S=CTOa Av=aaa= oneosirion va'ues eOa rua=ine veNr o=TeaMiNeo FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

(D/Q) Sector Average Deposition (1/m*)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 4.471E-09 2.622E-09 1.788E-09 9.981E-10 4.499E-10 2.601E-10 NNE 2.162E-09 1.335E-09 9.453E-10 5.462E-10 2.521E-10 1.472E-10 NE 2.186E-09 1.329E-09 9.286E-10 5.298E-10 2.409E-10 1.395E-10 ENE 8.763E-09 4.896E-09 3.204E-09 1.729E-09 7.605E-10 4.363E-10 E 1.148E 08 6.289E-09 4.047E-09 2.149E-09 9.307E-10 5.299E-10 ESE. 8.909E-09 4.906E-09 3.151E-09 1.660E-09 7.258E-10 4.130E-10 SE 6.876E-09 3.858E 09 2.503E-09 1.341E-09 5.937E-10 3.397E-10  ;

SSE- 3.429E.09 1.995E-09 1.315E-09 7.210E-10 3.289E-10 1.8901-10 j S 3.698E-09 2.171E-09 1.447E-09 7.965E-10 3.662E-10 -2.108E-10 1 SSW 2.822E-09 1.722E-09 1.209E-09 G.197E-10 3.281E-10 1.923E-10 l SW 2.314E-09 1.520E-09 1.164E-09 6.882E-10 3.299E-10 1.945E-10 WSW 6.070E-10 4.358E-10 3.469E-10 2.310E-10 1.159E-10 7.021E-11 g() W 6.082E-10 4.138E-10 3.183E-10 1.977E-10 9.874E-11 5.972E-11 l WNW 1.870E-09 1.209E-09 8.870E-10 5.293E-10 2.511E-10 1.483E-10 )

NW 3.749E-09 2.290E-09 1.611E-09 9.262E-10 4.269E-10 2.492E-10 NNW 3.807E-09 2.246E-09 1.540E 09 8.652E-10 3.928E-10 2.280E-10 4.5 7.5 15.0 25.0 35.0 45.0 i

N 1.706E-10 7.094E-11 2.218E-11 9.588E-12 5.736E-12 8.525E-11 NNE 9.706E-11 4.050E-11 1.253E-11 1.916E-11 8.919E-12 5.122E-12 NE 9.157E-11 3.799E-11 1.175E-11 9.911E-12 5.318E-12 3.292E-12 ENE 2. 851Edo 1.186E-10 9.504E-11 2.256E-11 1.211E-11 7.499E-12 E 3.447E 10 1.427E-10 6.735E-11 2.192E-11 1.177E-11 7.290E-12 ESE 2.684E 10 1.124E-10 4.674E 11 1.645E-11 8.781E-12 5.440E-12 SE 2.212E 10 9.493E-11' 3.784E-11 1.485E 7.867E-12 4.731E-12 SSE 1.257E-10 5.742E-11 2.530E-11 1.104E-11 4.586E-12 2.812E-12 S 1.444E-10 6.569E-11 2.721E-11 1.289E-11 5.120E-12 3.138E-12 SSW 1.262E-10 5.539E-11 2.941E-11 1.103E-11 5.812E-12 3.129E-12 SW 1.299E-10 5.523E-11 3.711E-11 1.548E-11 7.792E-12 4.577E-12 WSW 4.707E-11 2.001E-11 6.249E-12 3.103E-12 3.395E-11 2.790E-12 W 3.996E-11 1.697E-11 5.314E-12 2.295E-12 1.321E-12 8.690E-13 WNW 9.827E-11 4.117E-11 1.267E 11 5.391E-12 3.075E-12 2.019E 12 NW' 1.642E-10 6.851E-11 2.125E-11 9.075E-12 5.220E-12 3.464E-12 NNW 1.498E-10 6.246E-11 1.958E-11 8.426E-12 4.885E-12 3.267E-12 O

Rev.No. O Page C-15 of ODCM

l TABLE C-7 l SECTOR AVERAGE DISPERSION VALUES FOR RADWASTE VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

Sector Average Concentration X/O (sec/m*)

SEGMENT BOUNDARIES IN MILES l

, Direction 0.5 0.75 1.0 1.5 2.5 3.5

N 9.289E-07 6.007E-07 4.440E-07 2.832E-07 1.567E-07 1.052E-07 l NNE 4.668E-07 3.155E-07 2.371E-07 1.529E-07 8.435E-08 5.617E-08

! NE 4.087E-07 2.683E-07 1.978E-07 1.247E-07 6.698E-08 4.381E-08 ENE 8.420E-07 5.096E-07 3.592E-07 2.227E-07 1.142E-07 7.324E-08 E 6.787E-07 3.900E-07 2.660E-07 1.626E-07 8.118E-08 5.158E-08 ESE 4.270E-07 2.525E-07 1.727E-07 1.002E-07 5.512E-08 3.467E-08 SE 3.397E-07 2.050E-07 1.413E-07 8 476E-08

. 4.607E-08 3.077E 08 SSE 1.996E-07 1.413E-07 1.017E-07 6.620E-08 3.908E-08 2.419E-08 l S 2.112E-07 1.498E-07 1.138E-07 7.360E-08 4.310E-08 2.660E-08 l SSW 2.970E-07 2.024E-07 1.587E-07 1.052E-07 5.857E-08 3.831E-08 l SW 3.696E-07 2.716E-07 2.542E-07 1.569E-07 8.631E-08 5.441E-08 USW 1.939E-07 1.634E-07 1.376c-07 1.185E-07 6.500E-08 4.262E-08 W 2.088E-07 1.643E-07 1.369E-07 9.847E-08 5.958E-08 4.143E-08 l

WNW 5.250E-07 3.657E-07 2.245E-07 1.925E-07 1.135E-07 7.900E 08 NW 8.757E-07 5.846E-07 4.402E-07 2.869E-07 1.634E-07 1.120E-07 NNW 8.560E-07 5.557E-07 4.144E-07 2.685E-07 1.531E-07 1.051E-07 4.5 7.5 15.0 25.0 35.0 45.0 l N 7.785E-08 4.199E-08 1.805E-08 9.939E-09 6.584E-09 5.508E-09 NNE 4.127E-08 2.189E-08 9.195E-09 5.947E-09 3.828E-09 2.766E-09 NE 3.177E 08 1.642E-08 7.167E-09 3.976E-09 2.538E-09 1.823E-09 ENE 5.250E-08 2.670E-08 1.191E-08 6.030E-09 3.879E-09 2.803E-09 E 3.681E-08 1.868E-08 8.370E-09 4.283E-09 2.778E-09 2.022E-09 ESE 2.458E-08 1.326E-08 5.225E-09 2.684E-09 1.747E-09 1.276E-09 SE 2.154E-08 1.063E-08 4.246E-09 2.205E-09 1.446E-09 1.062E-09 SSE 1.695E-08 8.373E-09 3.340E 09 1.733E 09 1.136E-09 8.335E-10 S 1.865E-08 9.222E-09 3.690E-09 1.920E-09 1.261E-09 9.272E-10 SSW 2.696E-08 1.300E-08 4.993E-09 2.515E-09 1.615E-09 1.168E-09 SW 4.155E-08 2.103E-08 7.964E-09 3.960E-09 2.520E-09 1.809E-09 WSW 3.087E-08 1.587E-08 6.862E-09 3.473E 09 2.331E-09 1.681E-09 W 3.125E-08 1.729E-08 7.572E-09 4.088E-09 2.722E-09 2.012E-09 WNW 5.992E-08 3.374E-08 1.518E-08 '8.361E-09 5.637E-09 4.201E-09 NW 8.418E-08 4.678E-08 2.083E-08 1.141E-08 7.675E-09 5.711E-09 NNW 7.914E-08 4.414E-08 1.974E-08 1.085E-08 7.307E-09 5.443E-09 Ol Rev. No. O Page C-16 of ODCM  ;

4 TABLE C-7 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR RADWASTE VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

(D/Q) Sector Average Deposition (1/m')

i SEGMENT BOUNDARIES IN MILES i

. Direction 0,5 0.75 1.0 1.5 2.5 3.5 N 7.139E 09 3.957E-09 2.509E-09 1.308E-09 5.489E-10 3.053E-10

NNE 3.697E-09 2.120E 09 1.363E 09 7.217E-10 3.046E-10 1.697E-10 NE 3.738E-09 2.100E-09 1.337E-09 6.993E-10 2.930E-10 1.625E 10 ENE 1.197E-08 6.395E-09 3.998E-09 2.058E-09 8.649E-10 4.834E-10 E 1.429E-08 7.542E-09 4.691E-09 2.400E-09 1.006E-09 5.616E-10 l ESE 1.088E-08 5.771E-09 3.590E-09 1.833E-09 7.733E-10 4.331E-10 SE 8.853E-09 4.728E-09 2.941E-09 1.510E-09 6.410E 10 4.709E-10 SSE 4.668E-09 2.551E-09 1.593E-09 8.277E-10 3.887E-10 3.189E-10 S 5.074E-09 2.781E-09 1.752E-09 9.121E-10 4,447E-10 3.448E-10 SSW 4.395E-09 2.459E-09 1.585E-09 8.439E-10 3.627E-10 2.380E-10 SW 4.104E-09 2.423E-09 1.653E-09 8.807E-10 3.772E-10 2.107E-10 g WSW 1.314E-09 8.355E-10 5.716E-10 3.315E-10 1.429E-10 8.030E-11 1.257E-09 7.732E-10 5.198E-10 2.877E-10 1.248E-10 7.047E-11

} Q) W WNW 3.526E-09 2.077E-09 1.355E-09 7.280E-10 3.094E-10 1.727E-10 NW 6.440E-09 3.665E-09 2.353E-09 1.242E-09 5.239E-10 2.917E-10 NNW 6.161E-09 3.436E-09 2.187E-09 1.144E-09 4.817E-10 2.683E-10 )

4.5 7.5 15.0 25.0 35.0 45.0

$ N 1.960E-10 8.595E-11 1.329E-10 3.272E-10 3.824E-10 2.186E-11

) NNE 1.089E-10 4.740E-11 6.689E-11 1.218E-11 6.526E-12 4.037E-12 l NE 1.040E-10 4.433E-11 5.931E-11 9.899E-12 5.306E-12 3.283E-12 ENE 3.114E-10 1.326E-10 8.260E-11 2.254E-11 1.209E-11 7.484E-12 4 E 3.613E-10 1.508E-10 6.296E-11 2.190E-11 1.175E-11 7.278E-12 ES ? 2.795E 10 1.565E-10 4.490E-11 1.635E-11 8.770E-12 5.432E-12 SE 3.152E-10 1.283E-10 3.658E-11 1.382E-11 7.413E-12 4.590E-12 SSE 2.167E-10 8.427E-11 2.362E-11 8.810E-12 4.534E-12 2.805E-12 S 2.195E-10 8.754E-11 2.582E-11 9.909E-12 5.060E-12 3.130E-12

SSW 2.885E-10 1.221E-10 2.685E-11 9.418E-12 5.047E-12 3.122E-12 SW 1.536E-10 1.603E-10 4.503E-11 1.117E-11 5.944E-12 3.669E-12 WSW 5.191E-11 2.346E-11 3.839E-11 4.126E-11 4.659E-12 1.963E-12 W 4.561E-11 1.917E-11 2.377E-11 8.037E-11 1.204E-10 1.255E-10

, WNW 1.110E-10 4.715E-11 6.492E-11 1.955E-10 2.750E-10 2.777E-10 NW 1.873E-10 8.094E 11 1.173E-10 3.145E-10 4.176E-10 4.099E-10 NNW 1.725E-10 7.523E-11 1.182E-10 3.151E-10 4.133E-10 4.025E-10

. Rev. No. O PaDe C-17 of ODCM

l l

l TABLE C-8 l SECTOR AVERAGE DISPERSION VALUES FOR THE STACK DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992) h ,

Sector Average Concentration X/Q (sec/ma )

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 6.304E-09 7.537E-09 9.600E-09 1.382E-08 1.504E-08 1.366E-08 NNE 2.263E-09 3.378E-09 5.419E-09 9.466E-09 1.092E-08 1.011E-08 NE 1.092E-09 2.089E-09 4.269E-09 8.509E-09 1.005E-08 9.366E-09 l

EdE 1.260E-08 1.222E-08 1.454E-08 2.100E-08 2.117E-08 1.845E-08 E 1.547E-08 1.816E-08 2.136E-08 2.978E-08 2.655E-08 2.150E-08 j ESE 1.888E-08 1.914E-08 2.056E-08 2.174E-08 2.283E-08 1.737E-08 SE 2.187E-08 1.933E-08 1.993E-08 2.243E-08 2.028E-08 2.229E-08 SSE 1.833E-08 1.560E-08 1.566E-08 1.731E-08 2.077E-08 1.817E-08 S 1.747E-08 1.440E-08 1.540E-08 1.730E-08 2.211E-08 1.900E-08 SSW 1.689E-08 1.479E-08 1.724E-08 2.180E-08 2.270E-08 1.996E-08 SW 6.866E-09 6.874E-09 1.247E-08 1.675E-08 1.789E-08 1.442E-08 WSW 1.163E-09 1.723E-09 2.811E-09 6.821E-09 7.244E-09 6.414E-09 W 1.151E-09 1.393E-09 2.274E-09 4.102E-09 4.796E-09 4.483E-09 WNW 2.266E-09 3.077E-09 4.890E-09 8.276E-09 9.171E-09 8.262E-09 NW 5.561E-09 6.833E-09 9.696E-09 1.511E-08 1.648E-08 1.481E-08 NNW 6.602E-09 7.476E-09 9.456E-09 1.365E-08 1.498E-08 1.370E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 1.190E 08 7.990E-09 4.005E-09 2.317E-09 1.572E-09 1.348E-09 NNE 8.882E-09 6.046E-09 3.081E-09 4.716E-09 3.041E-09 2.200E-09 NE 8.270E-09 5.69?E-09 3.376E-09 5.591E-09 3.622E-09 2.629E 09 l ENE 1.569E-08 1.021E-08 8.735E-09 6.410E-09 4.121E-09 2.977E-09 l E 1.748E-08 1.059E-08 7.444E-09 4.667E-09 2.974E-09 2.137E-09 l ESE 1.362E-08 1.066E-08 4.756E-09 3.000E-09 1.017E-09 1.381E-09 SE 1.624E-08 8.678E-09 3.802E-09 2.282E-09 1.464E-09 1.059E-09 SSE 1.421E-08 7.626E-09 3.217E-09 1.770E-09 - 1. 263E-09 9.154E-10 l S 1.632E-08 8.545E-09 3.558E-09 1.953E-09 1.440E-09 1.045E-09 i SSW 1.910E-08 1.011E-08 4.845E-09 2.835E-09 1.813E-09 1.306E-09 SW 1.354E-08 9.554E-09 4.078E-09 2.987E-09 1.946E-09 1.454E-09 USW 5.511E-09 3.659E-09 2.100E-09 1.197E-09 9.790E-10 1.201E-09 W 3.977E-09 2.773E-09 1.472E-09 8.742E-10 6.133E-10 4.7012-10 WNW 7.135E-09 4.716E-09 2.335E-09 1.322E-09 9.004E-10 6.765E-10 NW 1.277E-08 8.409E-09 4.115E-09 2.298E-09 1.5483-09 1.152E-09 NNW 1.198E-08 8.121E-09 4.120E-09 2.355E-09 1.608E-09 1.207E-09 l

Rev.No. O Page C-18 of ODCM i

\

l i

TABLE C-8 (CONTINUED)

O ==croa av=aaa= oisa=asio" v^'u== roa Ta': = Tack o=T=a=ia==

FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

Sector Average Finite Cloud Gamma X/Q (sec/m*)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.6 2.5 3.5 N 1.056E-07 7.326E-08 5.707E-08 4.048E-08 2.615E 08 1.930E-08 NNE 8.423E-08 5.830E-08 4.543E-08 3.233E-08 2.100E-08 1.554E-08 NE 8.669E-08. 5.979E-08 4.651E-08 3.304E-08 2.144E-08 1.588E-08 ENE 1.359E-07 9.388E-08 7.314E-08 5.381E-08 3.443E-08 2.522E-08 E 1.345E-07 9.409E 08 7.352E-08 5.582E-08 3.486E-08 2.500E-08 ESE -9.666E-08 6.962E-08 5.419E-08 3.785E-08 2.627E 08 1.849E-08 SE 8.156E-08 5.786E-08 4.497E-08 3.227E-08 2.186E-08 1.919E-08 SSE 6.370E-08 4.642E-08 3.607E-08 '2.673E-08 2.041E-08 1.573E-08 S 6.367E-08 4.638E-08 3.736E-08 2.774E-08 2.192E-08 1.668E-08 SSW 8.747E-08 6.029E-08 4.886E-08 3.679E-08 2.549E-08 1.9585-08 SW 7.805E-08 5.421E-08 4.798E-08 3.412E-08 2.313E-08 1.662E-08 WSW 4.633E-08 3.206E-08 2.498E-08 2.009E-08 1.289E-08 9.455E-09 Os W 4.390E-08 3.020E-08 2.344E-08 1.660E-08 1.074E-08 7.954E-09 WNW 6.518E-08 4.519E-08 3.531E-08 2.520E-08 1.636E-08 1.207E-08 IN 1.075E-07 7.471E-08 5.846E-08 4.177E-08 2.713E-08 2.002E-08 NNW 1.090E-07 7.544E-08 5.873E-08 4.163E-08 2.689E-08 1.987E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 1.520E-08 9.085E-09 4.282E-09 2.428E-09 1.640E-09 1.343E-09 NNE 1.228E-08 7.377E-09 3.510E-09 3.242E-09 2.140E-09 1.574E-09 NE 1.255E-08 7.577E-09 3.990E-09 3.674E-09 2.441E-09 1.803E-09 ENE 1.975E-08 1.168E-08 7.533E-09 4.588E-09 3.017E-09 2.213E-09 E 1.925E-08 1.103E-08 6.332E-09 3.583E-09 2.329E-09 1.695E-09 ESE 1.405E-08 9.511E-09 4.144E-09 2.339E-09 1.522E-09 1.110E-09 SE 1.411E-08 7.582E-09 3.268E-09 1.809E-09 1.181E 09 8.637E-10 SSE 1.197E-08 6.451E-09 2.751E-09 1.485E-09 1.011E-09 7.413E-10 l S i M7E-08 f 7.027E-09 2.988E-09 1.616E-09 1.116E-09 8.202E-10 l SSW 1.669E-08 8.946E-09 4.025E-09 2.212E-09 1.441E-09 1.051E-09 )

SW 1.405E-08 8.902E 09 3.815E-09 2.323E-09 1.522E-09 1.125E-09 WSW 7.417E-09 4.409E-09 2.259E 09 1.259E-09 9.433E-10 8.792E-10 )

W 6.295E-09 3.815E-09 1.849E-09 1,061E-09 7.318E-10 5.545E-10 WNW 9.503E-09 5.659E-09 2.658E-09 1.485E-09 1.006E-09 7.536E-10 NW 1.574E-08 9.343E-09 4.349E-09 2.405E-09 1.617E-09 1.203E-09 1 NNW 1.567E-08 9.395E-09 4.454E-09 2.499E-09 1.696E-09 1.269E-09 I O I Rev.No. O Page C-19 of ODCM

TABLE C-8 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR THEi STACK DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992) h (D/Q) Sector Average Deposition (1/m')

4 SEGMENT BOUNDARIES IN MILES Direction

, 0.5 0.75 1.0 1.5 2.5 3.5 N 5.867E-10 5.512E-10 5.298E-10 3.807E-10 2.303E-10 1.496E-10 j NNE 2.220E-10 2.564E-10 2.787E-10 2.173E-10 1.374E-10 9.029E-11  ;

NE 1.569E-10 2.254E-10 2.692E-10 2.210E-10 1.434E-10 9.484E-11  !

ENE 1.440E-09 1.219E-09 1.078E-09 7.247E-10 4.209E-10 2.708E-10 E 1.868E-09 1.566E-09 1.378E-09 9.226E-10 5.343E-10 3.433E-10 ESE 1.970E-09 1.546E-09 1.277E-09 8.070E-10 4.493E-10 2.857E-10 SE 2.009E-09 1.513E-09 1.195E-09 7.215E-10 3.920E-10 2.675E-10 SSE 1.472E 09 1.088E-09 8.401E-10 4.952E-10 2.782E-10 1.783E-10 S 1.432E-09 1.062E-09 8. 21'J E- 10 4.064E-10 2.765E-10 1.758E-10 SSW 1.448E-09 1.145E-09 9.499E-10 6.029E-10 3.398E 10 2.227E-10 SW 4.816E-10 4 577E-10 4.424E-10 3.191E-10 1.934E-10 1.258E-10 t

WSW 7.953E-11 9.105E-11 9.852E-11 7.657E-11 4.834E-11 3.175E-11

, W 7.596E-11 8.732E-11 9.453E-11 7.349E-11 4.641E-11 3.049E-11 WNW 2.259E-10 2.548E-10 2.733E-10 2.114E 10 1.331E-10 8.739E 11 NW 5.672E-10 5.729E-10 5.770E-10 4.285E-10 2.640E-10 1.724E-10 NNW 6.313E-10 5.755E 10 5.408E-10 3.820E-10 2.288E-10 1.483E-10 4.5 7.5 15.0 25.0 35,0 45.0 N 1.024E-10 4.512E-11 1.499E-11 6.634E-12 3.864E-12 2.538E-12 NNE 6.187F-11 2.717E-11 8.936E-12 1.079E-11 1.877E-11 2.331E-11 NE 6.504E-11 2.852E-11 9.333E-12 1.922E-11 7.686E-12 4.762E-12 ENE 1.851E-10 8.191E-11 2.723E-11 2.589E-11 1.390E-11 8.613E-12

~

E 2.345E-10 1.038E-10 3.439E-11 2.443E-11 1.312E-1. 8.128E-12 ESE 1.949E-10 9.097E-11 2.905E-11 1.009E-10 9.057F-12 5.613E-12 SE 1.804E-10 7.805E-11 2.518E-11 1.564E-11 3.64cE-11 5.691E-11 SSE 1.212E-10 5.228E-11 1.700E-11 7.764E-12 1.078E-11 3.148E-12 S 1.203E-10 5.162E-11 1.675E-11 7.661E-12 2.380E-11 3.375E-12 SSW 1.581E-10 6.827E-11 2.174E-11 2.120E-11 3.021E-11 5.082E-12 SW 8.713E-11 3.976E-11 1.252E-11 5.266E-12 3.020E-12 2.782E-12 WSW 2.175E-11 9.548E-12 3.137E-12 1.362E-12 7.678E-13 5.268E-13 W 2,089E-11 9.176E-12 3.018E-12 1.312E-12 7.520E-13 4.906E-13 WNW 5.988E-11 2.631E-11 8.665E-12 3.775E-12 2.168E-12 1.417E-12 NW 1.181E-10 5.197E-11 1.720E-11 7.561E-12 4.378E-12 2.873E-12 NNW 1.014E-10 4.475E-11 1.490E-11 6.628E-12 3.876E-12 2.556E-12 O

Rev.No. O Page C-20 of ODCM

.m. _ . . - . . . . . , __. . . . _ _ . . _ . . - m __.-__.m m__ _., m _ - . . . .

l TABLE C-9 l SECTOR AVERAGE DISPERSION VALUES FOR REACTOR VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct.,1985 To 1992)

Sector Average Concentration X/O (sec/m*)

l SEGMENT BOUNDARIES IN MILES '

Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 6.872E 07 3.876E-07 2.760E-07 1.809E-07 1.070E 07 7.473E-08 NNE 2.784E-07 1.618E-07 1.187E-07 8.049E-08 4.922E-08 3.490E-08 NE 2.146E-07 1.293E-07 9.637E-08 6.593E-08 4.010E-08 2.814E-08 ENE 5.379E-07 3.161E 2.287E-07 1.517E-07 8.544E-08 5.754E-08 E 4.349E-07 2.511E-07 1.781E-07 1.161E-07 6.271E-08 4.151E-08 ESE 2.237E-07 1.316E-07 9.517E-08 6.077E-08 3.752E-08 2.507E-08 SE 1.404E-07 8.555E-08 6.434E-08 4.391E-08 2.761E-08 2.379E-08 SSE 8.466E-08 5.343E-08 4.251E 08 3.290E-08 2.625E-08 1,947E-08 S 1.138E 07 7.142E-08 5.844E-08 4.397E-08 3.334E-08 2.340E-08 SSW 1.195E 07 7.622E-08 6.418E-08 5.096E-08 3.474E-08 2.567E-08 SW 1.568E 07 1.021E-07 9.798E-08 7.350E-08 4.952E-08 3.388E-08 WSW 8.303E-08 5.439E-08 4.638E-08 4.813E-08 3.323E-08 2.418E-08 O W WNW 1.023E-07 2.768E-07 6.109E-08 1.563E-07 4.808E-08 1.144E-07 3.752E-08 8.024E-08 2.675E-08 5.180E-08 2.039E-08 3.796E-08 NW 4.819E-07 2.733E-07 1.974E-07 1.336E-07 8.207E-08 5.850E-08 NNW 5.836E-07 3.255E-07 2.311E 07 1.525E-07 9.119E 08 6.415E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 5.682E-08 3.229E-08 1.487E-08 8.630E-09 5.900E-09 5.432E-09 NNE 2.674E-08 1.527E-08 6.981E-09 6.259E-09 4.065E-09 2.955E-09 NE 2.133E-08 1.186E-08 5.653E-09 3.842E-09 2.467E-09 1.778E-09 ENE 4.249E-08 2.266E-08 1.191E-08 6.123E-09 3.960E-09 2.874E-09 E 3.039E-08 1.610E-08 8.670E-09 4.499E-09 2.939E 09 2.151E-09 ESE 1.846E-08 1.219E-08 .5.018E-09 2.620E-09 1.719E 09 1.262E-09 SE 1.691F 0.9 8.600E-09 3.531E-09 1.859E 09 1.229E 09 9.077E-10 SSE 1.406E-08 7.122E-09 2.909E-09 1.533E 09 1.014E-09 7.489E-10 S 1.694E-08 8.538E 09 3.497E-09 1.849E-09 1.227E-09 9.083E-10 SSW 2.096E-08 1.036E-08 4.152E-09 2.119E 09 1.372E-09 9.979E-10' SW 2.774E 08 1.607E-08 6.287E-09 3.285E-09 2.100E-09 1.512E-09 WSW 1.858E-08 1.043E-08 5.006E-09 2.642E-09 1.930E-09 1.538E-09 W 1.628E-08 9.996E-09 4.778E-09 2.735E-09 1.885E-09 1.426E 09 WNW 2.983E-08 1.804E-08 8.977E-09 5,317E-09 3.751E-09 2.887E-09 NW 4.517E 08 2.656E-08 1.290E-08 7.554E-09 5.303E-09 4.069E-09 NNW 4.913E-08 2.849E-08 1.363E-08 7.907E-09 5.519E-09 4.218E-09 O

Rev.No. O Page C-21 of ODCM e

l l

I TABLE C-9 (CONTINUED) l l

SECTOR AVERAGE DEPOSITION VALUES FOR REACTOR VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May Oct.,1985 To 1992) h (D/Q) Sector Average Deposition (1/m')

SEGMENT BOUNDARIES IN MILES i

l Direction 0.5 0.75 1.0 1.5 2.5 3.5 l N 5.293E-09 3.001E-09 1.993E-09 1.084E-09 4.833E-10 2.788E-10 NNE 2.213E-09 1.282E-09 8.672E-10 4.796E-10 2.178E-10 1.268E-10 NE 1.943E-09 1.129E-09 7.661E-10 4.253E-10 1.923E-10 1.114E-10 1 ENE 9.567E-09 5.374E-09 3.526E-09 1.908E-09 8.486E 10 4.910E-10 E 1.195E-08 6.594E-09 4.262E-09 2.273E-09 9.946E-10 5.705E-10 ,

ESE 7.360E-09 4.098E-09 2.647E-09 1.400E-09 6.200E-10 3.559E-10 l SE 4.567E-09 2.616E-09 1.713E-09 9.208E-10 4.141E-10 2.395E-10 l I

SSE 2.349E-09 1.404E-09 9.335E-10 5.095E-10 2.374E-10 1.385E-10 S 3.680E-09 2.178E-09 1.449E-09 7.904E-10 3.660E-10 2.123E-10 SSW 2.552E-09 1.539E-09 1.065E-09 6.032E-10 2.835E-10 1.674E-10 SW 2.250E-09 1.407E-09 1.024E-09 5.859E-10 2.795E-10 1.655E-10 WSW 7.002E-10 4.587E-10 3.426E-10 2.133E-10 1.060E-10 6.420E-11 W 6.960E-10 4.315E-10 3.101E-10 1.811E-10 8.844E-11 5.324E-11 WNW 1.630E-09 9.674E-10 6.706E-10 3.802E-10 1.774E-10 1.045E-10 NW 3.128E-09 1.814E-09 1.232E-09 6.840E-10 3.116E-10 1.814E-10 NNW 4.161E-09 2.381E-09 1.595E-09 8.757E-10 3.947E-10 2.289E-10 1 4.5 7.5 15.0 25.0 35.0 45.0 N 1.827E-10 7.623E-11 2.436E-11 1.057E-11 6.134E-12 5.692E-11 l NNE 8.343E-11 3.499E-11 1.119E-11 2.150E-11 9.789E-12 5.547E-12 1 NE 7.311E-11 3.048E-11 9.592E-12 9.504E 12 5.097E-12 3.154E-12 ENE 3.225E 10 1.353E-10 1.156E-10 2.576E-11 1.382E-11 8.557E-12  !

E 3.727E-10 1.553E-10 7.770E-11 2.423E-11 1.300E-11 8.052E-12 )

ESE 2.326E-10 9.743E-11 4.546E-11 1.508E-11 7.942E-12 4.919E-12 i SE 1.566E-10 6.774E-11 3.081E-11 1.184E-11 6.303E-12 3.709E-12 SSE 9.207E-11 4.261E-11 2.281E-11 1.017E-11 3.707E-12 2.214E-12 S 1.426E-10 6.463E-11 2.960E-11 1.496E-11 5.349E-12 3.211E-12 SSW 1.104E-10 4.819E-11 2.963E-11 1.059E 11 5.586E-12 2.816E-12 l SW 1.109E-10 4.744E-11 3.118E-11 1.551E-11 7.818E-12 4.584E-12 USW 4.303E-11 1.843E-11 5.936E-12 2.825E-12 2.461E-11 2.913E-12 '

W 3.556E-11 1.520E-11 4.937E-12 2.188E-12 1.280E-12 8.473E-13 WNW 6.913E-11 2.912E-11 9.300E-12 4.046E-12 2.335E-12 1.535E-12 i NW 1.193E-10 4.998E-11 1.589E-11 6.865E-12 3.941E-12 2.584E-12  !

NNW 1.504E-10 6.233E-11 2.015E-11 8.774E 12 5.073E-12 3.346E-12 )

O i

Rev. No. O Page C-22 of ODCM l

i

i TABLE C-10 0 ==oToa av=aaa= oisreasion va'ues eoa aeru=' e'ooa veur DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct.,1985 To 1992)

Sector Average Concentration X/Q (sec/m*)

l SEGMENT BOUNDARIES IN MILES I l

l Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 6.872E-07 3.876E-07 2.760E-07 1.809E-07 1.070E-07 7.473E-08 NNE 2.784E-07 1.618E-07 1.187E-07 8.049E 08 4.922E-08 3.490E-08 NE 2.146E-07 1.293E-07 9.637E-08 6.593E-08 4.010E-08 2.814E-08  !

ENE 5.379E 07 3.161E-07 2.287E-07 1.517E-07 8.544E-08 5.754E-08 E 4.349E 07 2.511E-07 1.781E-07 1.161E-07 6.271E-08 4.151E-08 ESE 2.237E-07 1.316E-07 9.517E-08 6.077E-08 3.752E-08 2.507E-08 SE 1.404E-07 8.555E-08 6.434E-08 4.391E-08 2.761E-08 2.379E-08 SSE 8.406E-08 5.343E 08 4.251E-08 3.290E-08 2.625E-08 1.947E-08 S 1.138E-07 7.142E-08 5.844E-08 4.397E-08 3.334E 08 2.340E-08 SSW 1.195E-07 7,622E-08 6.418E-08 5.096E-08 3.474E-08 2.567E 08 =

O SW 1.568E-07 1.021E-07 9.798E-08 7.350E-08 4.952E-08 3.388E-08 V WSW 8.303E-08 5.439E-08 4.638E-08 4.813E-08 3.323E-08 2.418E-08 W 1.023E-07 6.109E-08 4.808E-08 3.752E-08 2.675E-08 2.039E-08 WNW 2.768E-07 1.563E-07 1.144E-07 8.024E-08 5.180E 0? 3.796E 08 NW 4.819E-07 2.733E-07 1.974E-07 1.336E-07 8.207E-08 5.850E-08 NNW 5.836E-07 3.255E-07 2.311E-07 1.525E 07 9.119E-08 6.415E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 5.682E-08 3.229E-08 1.487E-08 8.630E-09 5.900E 09 5.432E-09 NNE 2.674E-08 1.527E-08 6.981E-09 6.259E-09 4.065E-09 2.955E 09 NE 2.133E-08 1.186E-08 5.653E-09 3.842E-09 2.467E-09 1.778E 09 ENE 4.249E-08 2.266E-08 1.191E-08 6.123E-09 3.960E-09 2.874E-09 l E 3.039E-08 1.610E-08 8.670E-09 4.499E-09 2.939E-09 2.151E 09 ESE 1.846E-08 1.219E-08 5.018E-09 2.620E-09 1.719E-09 1.262E-09 SE 1.691E-08 8.600E-09 3.531E-09 1.859E-09 1.229E-09 9.077E-10 ,

SSE 1.408E-08 7.122E-09 2.909E 09 1.533E 09 1.014E-09 7.489E-10 S 1.694E-08 8.538E-09 3.497E-09 1.849E-09 1.227E-09 9.083E-10 SSW 2.096E-08 1.036E-08 4.152E-09 2.119E-09 1.372E-09 9.979E-10 SW 2.774E-08 1.607E-08 6.287E-09 3.285E-09 2.100E-09 1.512E-09 WSW 1.858E-08 1.043E-08 5.006E-09 2.642E-09 1.930E-09 1.538E-09 W 1.628E-08 9.896E-09 4.778E-09 2.735E-09 1.885E-09 1.426E-09 4 WNW 2.983E-08 1.804E-08 8.977E-09 5.317E-09 3.751E-09 2.887E-09 l NW 4.517E-08 2.656E-08 1.290E-08 7.554E-09 5.303E-09 4.069E 09 '

O 4.913E-08 2.849E-08 1.363E-08 7.907E-09 5.519E-09 4.218E-09 (V NNW Rev.No. O Page C-23 of ODCM l

1

TABLE C-10 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR REFUEL FLOOR VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA h

(May-Oct.,1985 To 1992)

(D/Q) Sector Average Deposition (1/m*)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 5.293E-09 3.001E-09 1.993E-09 1.084E-09 4.833E-10 2.788E-10 NNE 2.213E-09 1.282E-09 8.672E-10 4.796E-10 2.178E-10 1.268E-10 NE 1.943E-09 1.129E-09 7.661E-10 4.253E-10 1.923E-10 1.114E-10 ENE 9.567E-09 5.374E-09 3.526E-09 1.908E-09 8.486E-10 4.910E-10 E 1.195E 08 6.594E-09 4.262E-09 2.273E-09 9.946E-10 5.705E-10 ESE 7.360E-09 4.098E-09 2.647E-09 1.400E-09 6.200E-10 3.559E-10 SE 4.567E-09 2.616E-09 1.713E-09 9.208E-10 4.141E-10 2.395E-10 SSE 2.349E-09 1.404E 09 9.335E-10 5.095E-10 2.374E-10 1.385E-10 S 3.680E-09 2.178E-09 1.449E-09 7.904E-10 3.660E-10 2.123E-10 SSW 2.552E-09 1.539E-09 1.065E-09 6.032E-10 2.835E-10 1.674E-10 SW 2.250E-09 1.407E-09 1.024E-09 5.859E 10 2.795E-10 1.655E-10 USW 7.002E-10 4.587E-10 3.426E-10 2.133E-10 1.060E-10 6.420E-11 W 6.960E-10 4.315E-10 3.101E-10 1.811E-10 8.844E-11 5.324E-11 WNW 1.630E-09 9.674E-10 6.706E-10 3.802E-10 1.774E-10 1.045E-10 l NW 3.128E-09 1.814E-09 1.232E-09 6.840E-10 3.116E-10 1.814E-10 l NNW 4.161E 09 2.381E-09 1.595E-09 8.757E-10 3.947E-10 2.289E-10 l 4.5 7.5 15.0 25.0 35.0 45.0 N 1.827E-10 7.623E-11 2.436E 11 1.057E-11 6.134E-12 5.692E-11 NNE 8.343E-11 3.499E-11 1.119E-11 2.150E-11 9.789E-12 5.547E-12 NE 7.311E-11 3.048E-11 9.592E-12 9.504E-12 5.097E-12 3.154E-12 ENE -3.225E-10 1.353E-10 1.156E-10 2.576E-11 1.382E-11 8.557E-12 E 3.727E-10 1.553E-10 7.770E-11 2.423E-11 1.300E-11 8.052E-12 ESE 2.326E-10 9.743E-11 4.546E-11 1.508E-11 7.942E-12 4.919E-12 SE 1.566E-10 6.774E-11 3.081E-11 1.184E-11 6.303E-12 3.709E-12 SSE 9.207E-11 4.261E-11 2.281E-11 1.0173-11 3.707E-12 2.214E-12 l S 1.426E-10 6.463E-11 2.960E-11 1.4963-11 5.349E-12 3.211E-12 1 SSW 1.104E-10 4.819E-11 2.963E 11 1.059E-11 5.586E-12 2.816E-12 SW 1.109E-10 4.744E-11 3.118E-11 1.551E-11 7.818E-12 4.584E-12 WSW 4.303E-11 1.843E-11 5.936E-12 2.825E-12 2.461E-11 2.913E-12 W 3.556E-11 1.520E-11 4.937E-12 2.188E-12 1.280E-12 8.473E-13 WNW 6.913E-11 2.912E-11 9.300E-12 4.046E-12 2.335E-12 1.535E-12 NW 1.193E-10 4.998E-11 1.589E-11 6.865E-12 3.941E 12 2.584E-12 NNW 1.504E-10 6.293E-11 2.015E-11 8.774E-12 5.073E-12 3.346E-12 Rev.No. O Page C-24 of ODCM

TABLE C-11 l q

Q SECTOR AVERAGE DISPERSION VALUES FOR TURDINE VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct.,1965 To 1992)

Sector Average Concentration X/O (sec/m )

SEGMENT BOUNDARIES IN MILES ,

Direction 1 0.5 0.75 1.0 1.5 2.5 3.5 l l

N 5.709E-07 3.305E-07 2.412E-07 1.625E-07 9.818E-08 6.921E-08 l NNE 2.285E-07 1.372E-07 1.037E-07 7.275E-08 4.562E-08 3.268E-08 NE 1.764E 07 1.102E-07 8.477E-08 6.015E-08 3.755E-08 2.661E-08 ENE 4.616E-07 2.776E-07 2.055E-07 1.405E-07 8.050E-08 5.457E-08 l E 3.792E-07 2.246E-07 1.625E-07 1.091E-07 5.960E-08 3.964E-08 l ESE 1.965E-07 1.194E-07 8.826E-08 5.753E-08 3.635E-08 2.434E-08 l SE 1.272E-07 7.992E-08 6.120E-08 4.254E-08 2.712E-08 2.351E-08 l SSE 7.646E-08 5.020E-08 4.085E-08 3.235E-08 2.618E-08 1.933E-08 S 1.036E-07 6.737E-08 5.658E-08 4.335E-08 3.322E-08 2.320E-08 SSW 1.046E-07 6.974E-08 6.111E-08 4.995E-08 3.438E 08 2.545E 08 i SW 1.314E-07 9.022E-08 9.323E-08 7.163E-08 4.882E-08 3.339E-08 !

O WSW 5.958E-08 4.293E-08 4.003E-08 4.609E-08 3.238E-08 2.412E-08 2.363E-08 1.880E-08 I

V W 6.396E-08 4.183E-08 3.639E-08 3.164E-08 WNW 1.777E-07 1.075E-07 8.434E 08 6.407E 08 4.390E-08' 3.301E-08 NW 3.558E-07 2.118E-07 1.598E-07 1.134E-07 7.213E-08 5.224E-08 NNW 4.537E-07 2.623E-07 1.924E-07 1.315E-07 8.085E 08 5.761E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 5.294E-08 3.037E-08 1.413E-08 8.267E-09 5.666E-09 5.296E-09 NNE 2.518E-08 1.451E-08 6.687E-09 6.127E-09 3.978E-09 2.891E-09 l NE 2.028E-08 1.135E-08 5.477E-09 3.750E-09 2.407E-09 1.735E-09 ENE 4.044E-08 2.168E-08 1.158E-08 5.945E-09 3.845E-09 2.790E-09 <

E 2.910E-08 1.547E-08 8.448E-09 4.380E-09 2.862E-09 2.094E-09 ESE 1.794E-08 1.196E-08 4.909E-09 2.560E-09 1.680E-09 1.233E-09 SE 1.669E-08 8.467E 09 3.468E-09 1.826E-09 1.207E 09 8.915E-10 SSE 1.392E-08 7.028E-09 2.868E 09 1.511E-09 9.997E-10 7.383E-10 S 1.673E-08 8.418E-09 3.445E-09 1.821E-09 1.208E-09 8.947E-10 SSW 2.075E-08 1.023E-08 4.085E-09 2.083E-09 1.349E-09 9.812E-10 SW 2.742E-08 1.588E-08 6.199E-09 3.229E-09 2.064E-09 1.486E 09 WSW 1.818E-08 1.022E-08 4.932E-09 2.603E-09 1.905E-09 1.512E-09 W 1.518E-08 9.366E-09 4.578E-09 2.636E-09 1.821E-09 1.381E-09 WNW 2.633E-08 1.632E-08 8.318E-09 4.988E-09 3.541E-09 2.735E 09 NW 4.074E-08 2.438E-08 1.207E-08 7.141E-09 5.039E 09 3.879E-09 NNW 4.450E-08 2.620E-08 1.274E-08 7.463E-09 5.234E 09 4.013E-09 A

V Rev. No. O Page _G-25_ of ODCM

TABLE C-11 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR TURBINE VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct.,1985 To 1992) h (D/Q) Sector Average Deposition (1/m')

SEGMENT BOUNDARIES IN MILES Direction  !

0.5 0.75 1.0 1.5 2.5 3.5

, N 4.847E-09 2.779E-09 1.860E-09 1.020E-09 4.566E-10 2.639E-10 NNE 2.032E-09 1.194E-09 8.146E-10 4.548E-10 2.075E-10 1.210E-10 i NE 1.740E-09 1.030E-09 7.073E-10 3.972E-10 1.806E-10 1.049E-10 ENE 8.906E-09 5.042E-09 3.325E-09 1.812E-09 8.095E-10 4.694E-10 E 1.133E-08 6.299E-09 4.090E-09 2.199E-09 9.662E-10 5.554E-10 ESE 7.061E-09 3.955E-09 2.563E-09 1.364E-09 6.063E-10 3.486E-10 SE 4.447E-09 2.551E-09 1.671E-09 9.025E-10 4.067E-10 2.352E-10 i SSE 2.328E-09 1.388E-09 9.215E-10 5.051E-10 2.350E-10 1.369E-10 l S 3.634E-09 2.148E-09 1.428E-09 7.821E-10 3.617E-10 2.097E-10 SSW 2.496E-09 1.510E-09 1.047E-09 5.968E-10 2'.803E-10 1.653E-10 SW 2.157E-09 1.362E-09 1.001E 09 5.766E-10 2.750E-10 1.628E-10 WSW 6.331E-10 4.276E-10 3.252E-10 2.063E-10 1.026E-10 6.218E-11 '

W 5.976E-10 3.834E-10 2.817E-10 1.680E-10 8.284E-11 5.007E-11 I WNW 1.388E-09 8.480E-10 5.993E-10 3.462E-10 1.632E-10 9.657E-11 1 NW 2.777E-09 1.641E-09 1.128E-09 6.346E-10 2.909E-10 1.699E-10 NNW 3.765E-09 2.185E-09 .477E-09 8.192E-10 3.712E-10 2.158E-10 1

4.5 7.5 '5.0 2S.0 35.0 45.0 N 1.732E-10 7.236E 11 2.311E-11 1.013E-11 6.026E-12 8.848E-11 NNE 7.973E-11 3.347E-11 1.068E-11 2.103E-11 9.625E-12 5.470E-12 NE 6.896E-11 2.878E-11 9.085E-12 9.506E-12 5.098E-12 3.156E-12 ENE 3.089E-10 1.298E-10 1.140E-10 2.577E-11 1.382E-11 8.559E-12 E 3.636E-10 1.518E-10 7.743E-11 2.424E-11 1.300E-11 8.054E-12 ESE 2.282E-10 9.672E-11 4.575E-11 1.498E-11 7.946E-12 4.920E-12 SE 1.544E-10 6.793E-11 3.047E-11 1.174E-11 6.217E-12 3.655E-12 SSE 9.165E-11 4.352E-11 2.187E-11 9.446E-12 3.670E-12 2.215E-12 S 1.435E-10 6.606E-11 2.883E-11 1.384E-11 5.297E-12 3.212E-12 SSW 1.090E-10 4.835E-11 2.801E-11 1.041E-11 5.507E-12 2.816E-12 SW 1.090E-10 4.691E-11 3.601E-11 1.557E-11 7.813E-12 4.562E-12 WSV 4.171E-11 1.784E-11 5.729E-12 2.935E-12 3.639E-11 2.915E-12 W 3.353E-11 1.435E-11 4.643E-12 2.068E-12 1.217E-12 8.100E-13 WNW 6.407E-11 2.705E-11 8.612E-12 3.772E-12 2.196E-12 1.457E-12 NW 1.120E-10 4.697E-11 1.490E 11 6.476E-12 3.751E-12 2.485E-12 NNW 1.420E-10 5.952E-11 1.904E-11 8.344E-12 4.874E-12 3.254E-12 O

Rev. No. O Page C-26 of ODCM

TABLE C-12 SECTOR AVERAGE DISPERSION VALUES FOR RADWASTE VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct.,1985 To 1992)

Sector Average Concentration X/Q (sec/m*)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 1.033E-06 6.607E-07 4.934E-07 3.221E-07 1.851E-07 1.275E-07 NNE 4.455E-07 2.987E-07 2.285E-07 1.525E-07 8.827E-08 6.054E-08 NE 3.625E-07 2.468E-07 1.879E-07 1.232E-07 6.884E-08 4.598E-08 ENE 8.475E-07 5.272E-07 3.794E-07 2.416E-07 1.263E-07 8.178E-08 E 6.881E-07 4.030E-07 2.806E-07 1.778E-07 9.089E-08 5.854E-08 ESE 3.637E-07 2.260E-07 1.604E-07 9.717E-08 5.730E 08 3.661E-08 SE 2.507E-07 1.591E-07 1.137E-07 7.166E 08 4.147E 08 2.871E-08 SSE 1.528E-07 1.153E-07 8.631E-08 5.956E-08 3.778E 08 2.365E 08 S 2.033E 07 1.462E-07 1.136E-07 7.515E-08 4.517E-08 2.814E-08 SSW' 2.465E-07 1.710E-07 1.378E-07 9.433E-08 5.423E-08 3.604E-08 SW 3.232E-07 2.419E 07 2.349E-07 1.473E-07 8.225E-08 5.213E-08 WSW 1.847E-07 1.571E-07 1.341E-07 1.183E-07 6.589E-08 4.363E-08 O- W 1.925E-07 1.496E-07 1.266E-07 9.400E-08 5.935E-08 4.234E-08 UNU 4.533E-07 3.100E-07 2.455E-07 1.732E-07 1.090E-07 7.925E 08 NW 7.620E-07 5.042E-07 3.862E-07 2.611E-07 1.583E 07 1.133E-07 NNW 8.836E 07 5.647E-07 4.242E 07 2.807E-07 1.666E-07 1.178E-07 4.5 7.5 15.0 25.0 35.0 45.0 N 9.616E-08 5.366E-08 2.398E-08 1.359E-08 9.122E-09 7.874E-09 NNE 4.539E-08 2 496E-08 1.093E-08 7.546E-09 4.900E-09 3.562E 09 NE 3.379E-08 1.787E-08 8.096E-09 4.598E-09 2.952E-09 2.128E-09 ENE 5.900E-08 3.037E-08 1.395E 08 7.112E-09 4.597E-09 3.334E-09 E 4.216E-08 2.175E-08 1.009E-08 5.213E-09 3.404E-09 2.490E 09 ESE 2.622E 08 1. 462 F.- 08 5.848E 09 3.039E-09 1.992E 09 1.462E 09 SE 2.025E-08 1.013E 08 4.110E-09 2.159E-09 1.426E-09 1.053E-09 SSE 1.670E-08 8.369E-09 3.400E-09 1.788E-09 1.181E-09 8.713E-10 S 1.986E-08 9.951E-09 4.056E-09 2.139E-09 1.417E 09 1.048E 09 )

SSW 2.557E 08 1.246E-08 4.861E-09 2.477E-09 1.603E-09 1.166E-09 l

SW 3.986E-08 2.025E-08 7.746E-09 3.881E-09 2.481E 09 1.786E-09 WSW 3.183E-08 1.658E-08 7.380E-09 3.775E-09 2.571E 09 1.863E-09 W 3.249E-08 1.853E-08 8.383E-09 4.616E 09 3.108E 09 2.313E-09 WNW 6.191E-08 3.671E-08 1.744E-08 9.907E-09 6.795E-09 5.122E-09 NW 8.779E-08 5.149E-08 2.428E-08 1.376E-08 9.425E-09 7.099E-09 NNW 9.054E-08 5.244E-08 2.444E-08 1.376E-08 9.398E-09 7.065E-09 Rev.No. O Page C-27 of ODCM l

l

TABLE C-12 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR RADWASTE VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct.,1985 To 1992) h (D/Q) Sector Average Deposition (1/m')

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 7.161E-09 3.910E-09 2.468E-09 1.281E-09 5.399E-10 3.016E-10 NNE 3.098E-09 1.725E-09 1.100E-09 5.785E-10 2.454E 10 1.375E-10 NE 2.767E-09 1.546E-09 9.859E-10 5.168E-10 2.179E-10 1.215E-10 ENE 1.236E-08 6.620E-09 4.148E-09 2.151E-09 9.130E-10 5.142E 10 E 1.471E-08 7.775E 09 4.841E-09 2.489E-09 1.051E-09 5.901E-10 ESE 8.980E-09 4.777E-09 2.975E-09 1.527E 09 6.496E-10 3.661E-10 SE 5.951E-09 3.176E 09 1.973E-09 1.018E 09 4.362E-10 3.758E-10 SSE 3.184E-09 1.734E-09 1.082E-09 5.670E-10 2.795E-10 2.748E-10 S 4.939E-09 2.682E-09 1.686E-09 8.791E-10 4.358E-10 3.566E-10 SSW 3.731E-09 2.062E-09 1.325E-09 7.054E-10 3.056E-10 2.065E-10 SW 3.491E-09 2.008E-09 1.354E-09 7.203E-10 3.108E-10 1.753E-10 WSW 1.216E-09 7.473E-10 5.065E-10 2.908E-10 1.262E 10 7.139E-11 W 1.108E-09 6.552E-10 4.355E-10 2.391E-10 1.045E-10 5.944E-11 WNW 2.417E 09 1.382E-09 8.957E-10 4.786E 10 2.049E-10 1.152E-10 NW 4.435E-09 2.485E-09 1.590E 09 8.377E-10 3.551E 10 1.988E-10 NNW 5.741E-09 3.164E-09 2.007E-09 1.049E-09 4.437E-10 2.484E-10 4.5 7.5 15.0 25.0 35.0 45.0 N 1.944E-10 8.685E-11 1.650E 10 4.423E-10 5.252E-10 2.758E-11 NNE 8.880E-11 3.942E-11 7.098E-11 1.219E-11 6.530E-12 4.038E-12 NE 7.813E-11 3.424E-11 6.883E-11 9.492E-12 5.086E-12 3.146E 12 ENE 3.330E-10 1.437E 10 9.824E 11 2.573E-11 1.380E-11 8.541E-12 E 3.813E-10 1.608E-10 7.197E-11 2.421E-11 1.298E-11 8.039E-12 ESE 2.378E-10 1.543E-10 4.294E-11 1.480E-11 7.934E-12 4.911E-12 SE 2.575E-10 1.053E 10 2.854E-11 1.033E-11 5.540E-12 3.428E-12 SSE 1.909E-10 7.321E-11 1.969E-11 7.139E-12 3.573E 12 2.208E 12 S 2.295E-10 9.154E-11 2.687E-11 1.032E-11 5.181E-12 3.203E-12 SSW 2.750E-10 1.176E 10 2,497E 11 8.477E-12 4.541E-12 2.807E-12 SW 1.329E 10 1.642E-10 4.605E-11 1.041E-11 5.525E-12 3.393E-12 WSW 4.643E-11 2.156E-11 4.157E-11 4.604E-11 4.839E-12 1.971E-12 W 3.868E-11 1.646E-11 2.393E-11 8.590E-11 1.303E-10 1.365E-10 WNW 7.449E 11 3.222E-11 6.113E-11 2.097E 10 3.048E-10 3.120E 10 NW 1.282E-10 5.677E-11 1.156E-10 3.505E 10 4.802E 10 4.775E-10 NNW 1.602E 10 7.077E-11 1.317E-10 3.775E 10 5.051E-10 4.961E-10 e !

Rev. No. O Page C-28 of ODCM i

l'

l i

TABLE C-13 O seCTOa AveRAG= oiseeasion va'ues roa rse srAcx osteaMineo rROM GRAZING METEOROLOGICAL DATA (May-Oct.,1985 To 1992)

Sector Average Concentration X/O (sec/m*)

SEGMENT BOUNDARlES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 1.027E-08 1.097E-08 1.194E 08 1.411E 08 1.486E-08 1.339E-08 NNE 3.203E-09 4.104E 09 5.361E-09 7.740E-09 9.169E-09 8.589E 09 NE 1.541E-09 2.147E-09 3.601E-09 6.414E-09 8.365E-09 8.095E-09 ENE 2.136E-08 1.920E-08 2.080E-08 2.654E-08 2.643E-08 2.296E-08 E 2.418E-08 2,669E-08 2.929E-08 3.752E-08 3.256E 08 2.619E-08 ESE 2.SoSE-08 2.362E-08 2.317E-08 2.243E-08 2.257E-08 1.729E-08 SE 2.484E-08 1.862E 08 1.761E-08 1.750E 08 1.669E-08 1.992E-08 SSE 2.207E 08 1.569E 08 1.476E 08 1.572E-08 1.921E-08 1.773E-08 S 2.327E-08 1.668E-08 1.630E-08 1.732E-08 2.215E-08 1.961E-08 SSW 1.929E 08 1.592E-08 1.765E-08 2.163E-08 2.276E-08 2.047E-08 SW 7.525E-09 6.805E-09 1.138E-08 1.499E 08 1.706E-08 1.411E-08

/N WSW 1.477E 09 1.939E 09 2.783E 09 6.039E 09 6.782E-09 6.122E-09 (s-) W 1.621E-09 1.537E-09 2.124E-09 3.3448 09 4.143E-09 3.951E-09 WNW 3.121E 09 3.456E-09 4.222E-09 S.656E-09 6.317E-09 5.765E-09 NW 7.262E 09 7.526E 09 8.766E 09 1.127E 08 1.242E-08 1.130E-08 NNW 9.840E 09 1.035E-08 1.126E-08 1.325E-08 1.394E-08 1.259E-08 4.5 7.5 15.0 25.0 35.0 45.0 i

N 1.166E-08 7.912E 09 4.057E-09 2.400E 09 1.651E 09 1.473E-09 NNE 7.654E-09 5.395E-09 2.899E 09 5.959E-09 3.873E-09 2.818E-09 NE 7.362E 09 5.385E-09 3.568E-09 7.949E-09 5.187E-09 3.784E-09 ENE 1.956E-08 1.284E 08 1.211E 08 9.552E 09 6.177E-09 4.480E 09 E 2.126E 08 1.291E-08 9.490E-09 6.183E 09 3.959E 09 2.853E-09 ESE 1.367E-08 1.137E-08 5.359E 09 3.641E-09 2.348E-09 1.702E-09 SE 1.483E 08 8.319E-09 3.902E 09 2.516E 09 1.633E 09 1.189E-09 SSE 1.426E 08 7.927E 09 3.472E 09 1.969E-09 1.445E-09 1.052E-09 S 1.720E 08 9.169E-09 3.894E-09 2.170E-09 1.617E-09 1.178E-09 SSW 2.008E-08 ' 080E-08

. 5.377E 09 3.251E-09 2.089E-09 1.510E-09 SW 1.368E-08

• 015E 08

. 4.452E 09 3.488E-09 2.294E 09 1.730E-09 WSW 5.337E-09 3.643E-09 2.196E-09 1.283E-09 1.101E 09 1.497E-09 W 3.568E-09 2.588E 09 1.451E 09 8.966E 10 6.449E-10 5.031E 10 WNW 5.053E-09 3.461E 09 1.805E-09 1.063E 09 7.440E-10 5.702E-10 NW 9.881E 09 6.705E 09 3.423E 09 1.972E-09 1.356E-09 1.024E-09 NNW 1.100E-08 7.528E-09 3.920E 09 2.292E 09 1.590E 09 1.208E 09 Rev.No. O Page C-29 of ODCM

TABLE C-13 (CONTINUED)

SECTOR AVERAGE DISPERSION VALUES FOR THE STACK DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct.,1985 To 1992) hl Sector Average Finite Cloud Gamma X/O (sec/m')

SEGMENT BOUNDARIES IN MILES 1

l Direction O.5 0.75 1.0 1.5 2.5 3.5 l

l N 1.158E-07 8.009E-08 6.198E-08 4.338E-08 2.763E-08 2.031E-08 NNE 8.837E-08 6.084E-08 4.707E-08 3.305E 08 2.119E-08 1.565E-08 NE 1.004E-07 6.872E-08 5.300E-08 3.714E-08 2.383E-08 1.764E-08 ENE 1,844E-07 1.268E-07 9.832E-08 7.168E 08 4.551E-08 3.328E-08 E 1.719E-07 1.199E-07 9.332E-08 7.016E-08 4.346E-08 3.109E-08 ESE 1.054E-07 7.510E 08 5.799E-08 3.997E-08 2.748E-08 1.939E-08 SE 7.518E-08 5.213E-08 4.029E-08 2'.868E-08 1.954E-08 1.780E-08 SSE 6.310E-08 4.479E-08 3.474E 08 2.569E-08 1.995E-08 1.574E-08 S 6.769E-08 4.821E-08 3.859E-08 2.845E-08 2.262E-08 1.744E-08 SSW 9.202E-08 6.303E-08 5.095E-08 3.824E-08 2.660E-08 2.061E-08 SW 8.132E-08 5.613E-08 4.944E 08 3.503E-08 2.387E-08 1.725E-08 WSW 5.017E-08 3.457E 08 2.681E-08 2.139E-08 1.367E-08 1.004E-08 W 4.869E-08 3.326E-08 2.566E-08 1.797E-08 1.151E-08 8.521E-09 WNW 5.779E-08 3.977E-08 3.077E-08 2.159E 08 1.379E 08 1.015E-08 NW 9.748E 08 6.725E-08 5.218E-08 3.674E-08 2.357E 08 1.737E-08 NNW 1.133E-07 7.823E-08 6.053E 08 4.235E 08 2.696E-08 1.982E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 1.599E 08 9.594E-09 4.587E 09 2.642E-09 1.803E-09 1.510E-09 NNE 1.238E 08 7.517E 09 3.669E 09 3.858E 09 2.576E-09 1.909E-09 NE 1.400E-08 8.577E-09 4.739E-09 4.937E 09 3.317E-09 2.468E-09 ENE 2.608E-08 1.550E 08 1.048E-08 6.589E 09 4.365E-09 3.218E-09 E 2.393E 08 1.373E-08 8.069E 09 4.645E-09 3.035E-09 2.217E-09 ESE 1.480E 08 1.035E-08 4.652E-09 2.723E-09 1.792E-09 1.316E-09 SE 1.326E-08 7.323E-09 3.289E-09 1.896E 09 1.256E 09 9.271E-10 SSE 1.216E-08 6.698E-09 2.936E-09 1.621E-09 1.123E 09 8.295E-10 S 1.392E-08 7.524E-09 3.256E 09 1.785E-09 1.244E 09 9.190E-10 SSW 1.778E-08 9.626E-09 4.425E-09 2.476E-09 1.623E-09 1.189E-09 SW 1.478E 08 9.614E-09 4.201E-09 2.647E-09 1.750E-09 1.302E-09 WSW 7.897E-09 4.740E-09 2.495E-09 1.413E 09 1.085E 09 1.056E-09 W 6.758E-09 4.136E-09 2.051E-09 1.200E-09 8.395E-10 6.423E-10 WNW 8.007E-09 4.832E-09 2.340E-09 1.344E 09 9.281E-10 7.043E-10 NW 1.369E-08 8.224E-09 3.930E-09 2.224E 09 1.520E-09 1.143E 09 NNW 1.561E-08 9.393E-09 4.520E-09 2.573E-09 1.765E-09 1.331E-09 O

Rev.No. O Page C-30 of ODCM

TABLE C-13 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR THE STACK DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct.,1985 To 1992) l l

(D/Q) Sector Average Deposition (1/m*)

l SEGMENT BOUNDARIES IN MILES  :

Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 8.120E-10 6.726E-10 5.859E-10 3.891E-10 2.241E-10 1.437E-10 NNE 2.594E-10 2.425E-10 2.324E-10 1.666E-10 1.006E-10 6.537E-11 NE 1.367E-10 1.617E-10 1.778E-10 1.396E-10 8.856E-11 5.825E-11' ENE 2.061E-09 1.641E-09 1.373E-09 8.782E-10 4.932E-10 3.145E 10 E 2.344E-09 1.893E-09 1.611E-09 1.048E-09 5.954E-10 3.804E-10 ESE 1.916E-09 1.446E-09 1.148E-09 6.978E-10 3.772E-10 2.378E-10 SE 1.509E-09 1.111E 09 8.536E-10 5.001E-10 2.647E-10 1.788E-10 SSE 1.381E-09 9.953E-10 7.444E-10 4.225E-10 2.282E-10 1.451E-10 S 1.637E 09 1.173E-09 8.706E-10 4.899E-10 2.644E-10 1.664E-10 SSW 1.380E 09 1.068E-09 8.670E-10 5.385E-10 2.985E-10 1.946E-10 SW 4.653E-10 4.167E-10 3.854E 10 2.688E-10 1.598E-10 1.034E-10 i USW 8.735E-11 8.698E-11 8.685E-11 6.410E-11 3.936E-11 2.568E-11 W 8.824E-11 8.612E-11 8.467E-11 6.182E 11 3.773E-11 2.459E-11 WNW 2.513E-10 2.214E 10 2.025E-10 1.401E 10 8.281E-li 5.351E-11 NW 5.753E-10 4.944E-10 4.434E-10 3.018E-10 1.766E-10 1.138E 10 NNW 8.411E-10 6.830E-10 5.837E-10 3.811E-10 2.170E-10 1.388E-10 4.5 7.5 15.0 25.0 35.0 45.0 N 9.813E-11 4.342E 11 1.458E 11 6.584E-12 3.899E-12 2.583E-12 NNE 4.471E-11 1.970E-11 6.541E-12 1.089E-11 2.064E-11 2.610E-11 NE 3.992E-11 1.753E-11 5.759E-12 2.237E-11 8.393E-12 5.198E-12 ENE 2.147E-10 9.530E-11 3.198E-11 3.184E-11 1.709E-11 1.059E-11 E 2.596E-10 1.151E-10 3.834E-11 2.707E-11 1.453E-11 9.002E 12 ESE 1.620E-10 7. 545E- 11 2.442E 11 1.053E-10 7.907E-12 4.897E-12 SE 1.206E-10 5.231E-11 1.711E 11 1.248E-11 3.737E 11 6.706E-11 SSE 9.856E-11 4.268E-11 1.416E-11 6.581E-12 1.193E-11 2.789E-12 S 1.136E-10 4.896E-11 1.630E-11 7.617E-12 2.812E-11 3.396E-12 SSW 1.379E-10 5.967E-11 1.916E 11 2.198E-11 3.347E-11 4.991E-12 SW 7.147E-11 3.262E 11 1.036E-11 4.400E-12 2.543E-12 2.759E-12 WSW 1.757E-11 7.730E-12 2.554E 12 1.121E-12 6.388E-13 4.550E-13 W 1.684E 11 7.414E-12 2.457E-12 1.084E-12 6.291E-13 4.130E 13 WNW 3.659E-11 1,616E-11 5.394E-12 '2.412E-12 1.417E-12 9.362E-13 NW 7.779E-11 3.438E-11 1.151E-11 5.170E-12 3.048E-12 2.018E-12 NNW 9.472E-11 4.197E-11 1.413E 11 6.421E 12 3.821E-12 2.541E-12 Rev. No. O Page C-31 of ODCM )

/

TABLE C-14 CRITICAL RECEPTOR DISPERSION AND DEPOSITION PARAMETERS FOR VENT AND ELEVATED RELEASES h

DISPERSION PARAMETER DESCRIPTION RECEPTOR Annual Average X/Q - Total Body; Stack Site Boundary Annual Average X/Q - Skin; Stack Site Boundary

• Annual Average X/Q - Gamma Air; Stack Site Boundary Annual Average X/Q - Beta Air; Stack Site Boundary

• Annual Average X/Q - Dep. Inhal.; Stack Resident Annual Average D/Q - GPD; Stack Resident Grazing D/Q - SFV & FFV; Stack Garden Grazing D/Q - Cow; Stack Milk Animal Grazing D/Q - Goat; Stack Milk Animal Grazing D/Q - Meat; Stack Meat Animal Annual Average X/Q - Total Body; Vent Site Boundary Annual Average X/Q - Skin; Vent Site Boundary Annual Average X/Q - Gamma Air; Vent Site Boundary Annual Average X/Q - Beta Air; Vent Site Boundary Annual Average X/Q - Dep. Inhal.; Vent Resident i Annual Average D/Q - GPD; Vent Resident l Grazing D/Q - SFV & FFV; Vent Garden Grazing D/Q - Cow; Vent Milk Animal Grazing D/Q - Goat; Vent Milk Animal Grazing D/Q - Meat; Vent Meat Animal l

l l

• The highest X/Q is located beyond the site boundary.

O Rev.No. O Page _C-32_ of ODCM s

TABLE C-15 85TH PERCENTILE HOURLY PLUME CENTERLINE DISPERSION VALUES (m

) AND ANNUAL SECTOR AVERAGE DISPERSION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (19851992) 4 (FOR USE WITH SHORT TERM RELEASES) l 3

Concentration X/Q (sec/m )

l Site Hourly Annual Boundary Plume Cent. Sector Ave.

Distance Conc. (X/Q) Conc. (X/Q) Slope m Direction (m) (sec/m3 ) ( sec /m')

N w 225 1.284E-03 3.496E-05 -0.3970 NNE w 225 1.061E-03 1.775E-05 -0.4506 NE w 354 4.704E-04 5.342E-06 -0.4933 ENE w 563 1.650E-04 3.429E-06 -0.4267 E 1 950 4.960E-05 1.054E-06 -0.4243 ESE 1 1030 3.611E-05 5.862E-07 -0.4539 SE 1 1110 3.204E-05 4.168E 07 -0.4783 SSE 1 1754 2.213E-05 1.732E-07 -0.5343 S 1 2205 1.640E-05 1.363E-07 -0.5277 SSW 1 2269 2.610E-05 2.003E-07 -0.5365 SW 1 2382 3.489E-05 3.141C-07 -0.5189 WSW w 1867 7.570E-05 4.141E-07 -0.5737 W w 644 3.338E-04 2.683E-06 -0.5314 WNW w 370 S.355E-04 1.389E-05 -0.4513 NW w 306 9.082E-04 2.596E-05 -0.3916 NNW w 241 1.395E-03 3.684E-05 -0.4003 (Refer to Section 4.4.3) i l

i O

Rev.No. O Page C-33 of ODCM

TABLE C-16 85TH PERCENTILE HOURLY PLUME CENTERLINE DEPOSITION VALUES - g AND ANNUAL SECTOR AVERAGE DEPOSITION VALUES T FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985-1992)

(FOR USE WITH SHORT TERM RELEASES) 2 Deposition (D/Q) (1/m)

Site Hourly Annual Boundary Plume Cent. Sector Ave.

Distance (D/Q) (D/Q) Slope m Direction (m) (1/m*) (1/m*)

N w 225 3.819E-06 1.331E-07 -0.3698 NNE w 225 3.549E-06 7.094E-08 -0.4310 NE w 354 1.840E-06 3.000E-08 -0.4534 ENE w 563 1.166E-06 3.235E-08 -0.3949 E 1 950 4.777E-07 1.352E-08 -0.3927 ESE 1 1030 3.797E-07 8.757E-09 -0.4152 SE 1 1110 3.096E-07 6.456E-09 -0.4263 SSE 1 1754 1.560E-07 1.852E-09 -0.4884 S 1 2205 1.083E-07 1.409E 09 -0.4783 SSW 1 2269 1.300E-07 1.371E-09 -0.5014 SW 1 2382 1.366E-07 1.507E-09 -0.4965 USW w 1867 2.155E-07 1.247E-09 -0.5676 W w 644 1.008E-06 7.794E-09 -0.5356 WNW w 370 2.080E-06 4.097E 08 -0.4326 NW w 306 2.588E-06 8.546E-08 -0.3757 NNW v 241 3.727E-06 1.139E-07 -0.3842 (Refer to Section 4.4.3)

O Rev. No. __ _0 Page C-34 of ODCM

TABLE C-17

'q 85TH PERCENTILE HOURLY PLUME CENTERLINE DISPERSION VALUES y FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985-1992)' i i

(FOR USE WITH SHORT TERM RELEASES) l 3

Plume Centerline Concentration I/Q (sec/m ) i SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 1.699E-04 1.076E-04 7.986E-05 4.929E-05 3.382E-05 2.338E-05 NNE 1.607E-04 1.046E-04 7.674E-05 4.790E 05 2.941E-05 2.237E-05 NE 1.443E-04 8.910E-05 6.364E-05 3.787E-05 2.353E-05 1.628E-05 ENE 9.691E-05 6.042E-05 4.300E-05 2.458E 05 1.431E-05 9.546E-06 E 6.170E-05 3.762E-05 2.673E 05 1.457E-05 8.488E-06 5.543E-06 ESE 4.999E-05 2.937E-05 2.013E-05 1.079E-05 5.958E-06 3.790E-06 SE 4.934E-05 2.856E-05 1.944E-05 1.003E-05 5.698E-06 3.529E-06 SSE 6.206E-05 3.660E-05 2.469E-05 1.349E 05 7.622E-06 4.850E-06 S 6.415E-05 3.732E-05 2.483E-05 1.356E 05 7.681E-06 4.949E-06 ,

SSW 1.018E-04 5.889E-05 4.124E-05 2.228E-05 1.334E 05 9.017E-06 SW 1.254E-04 7.730E-05 5.343E-05 3.173E-05 1.959E-05 1.331E-05 WSW 1.937E-04 1.217E-04 9.179E-05 5.636E-05 3.565E-05 2.610E-05 Q W 2.334E-04 1.519E-04 1.131E-04 7.255E-05 4.837E-05 3.588E-05 V WNW NU 2.266E 04 2.003-04 1.507E-04 1.305E-04 1.154E-04 9.910E-05 7.694E-05 6.428E-05 4.867E-05 4.403E 05 3.613E-05 3.137E-05 NNW 1.950E-04 1.251E-04 9.565E-05 6.064E-05 4.107E-05 3.028E-05 4.5 Miles 7.5 Miles 15.0 Miles 25.0 Miles 35.0 Miles 45.0 Miles N 1.787E-05 1.084E-05 5.123E-06 3.189E-06 2.506E-06 2.232E-06 NNE 1.640E 05 9.724E-06 4.242E-06 2.665E-06 2.197E-06 1.946E-06 NE 1.202E-05 6.775E-06 3.149E-06 2.240E-06 1.763E-06 1.658E-06 ENE 7.055E-06 3.816E-06 1.880E-06 1.244E-06 1.024E-06 9.608E-07 E 3.976E-06 2.256E-06 1.239E-06 8.773E-07 7.968E 07 7.410E-07 ESE 2.708E-06 1.508E-06 8.402E-07 6.951E-07 6.563E-07 6.136E-07 SE 2.529E-06 1.446E-06 9.104E-07 7.173E-07 6.712E-07 6.380E-07 1 SSE 3.487E-06 1.855E-06 1.336E-06 1.005E-06 9.152E-07 8.714E-07 5 3.617E-06 1.977E-06 1.347E-06 9.941E-07 8.840E-07 8.540E-07 SSW 6.567E-06 3.377E-06 1.965E-06 1.491E-06 1.158E-06 1.102E-06 SW 9.555E-06 5.304E-06 2.844E-06 2.096E-06 1.490E-06 1.505E-06 WSW 2.015E-05 1.144E-05 6.078E-06 3.816E-06 2.824E 06 2.563E-06 W 2.801E 05 1.656E-05 8.601E 06 5.208E 06 4.080E-06 3.717E-06 WNW 2.841E-05 1.784E-05 8.792E-06 5.268E-06 4.015E-06 3.663E-06 NW 2.484E-05 1.399E-05 '7.019E-06 4.387E 06 3.446E-06 3.205E-06 NNW 2.416E-05 1.525E 05 7.180E-06 4.311E 06 3.235E-06 3.083E-06 l

O Rev.No. O Page C-35 of ODCM

1 TABLE C-18 SECTOR AVERAGE DISPERSION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985-1992) h (FOR USE WITH LONG TERM RELEASES)

Sector Average Concentration X/O (sec/m*)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 3.948E-06 2.078E-06 1.348E-06 7.608E-07 3.800E-07 2.415E-07 NNE 2.048E-06 1.091E-06 7.116E-07 3.995E-07 1.969E-07 1.241E-07 NE 1.427E-06 7.723E-07 5.060E-07 2.825E-07 1.373E-07 8.575E-08 ENE 1.985E-06 1.070E-06 6.992E-07 3.889E-07 1.884E-07 1.176E-07 E 1.375E-06 7.249E-07 4.692E-07 2.593E-07 1.254E-07 7.838E-08 ESE 8.717E-07 4.596E-07 2.977E-07 1.639E-07 7.877E-08 4.911E-08 SE 6.983E-07 3.671E-07 2.384E-07 1.315E-07 6.333E-08 3.958E-08 SSE 5.697E-07 3.018E-07 1.968E-07 1.089E-07 5.258E-08 3.289E-0B S 6.334E-07 3.339E-07 2.169E-07 1.195E-07 5.752E-08 3.595E-08 SSW 9.625E-07 5.148E-07 3.338E-07 1.828E-07 8.685E-08 5.362E-08 SW 1.601E-06 8.640E-07 5.612E-07 3.081E-07 1.465E-07 9.029E-08 WSW 1.457E-06 7.891E-07 5.157E-07 2.866E-07 1.385E-07 8.613E-08 W 1.881E-06 9.925E-07 6.461E-07 3.645E-07 1.815E-07 1.150E-07 VNW 3.757E-06 1.944E-06 1.254E-06 7.106E-07 3.593E-07 2.300E 07 NW 5.025E-06 2.605E-06 1.678E-06 9.490E-07 4.789E-07 3.063E 07 NNW 4.607E-06 2.382E-06 1.534E-06 8.699E-07 4.408E-07 2.826E-07 4.5 7.5 15.0 25.0 35.0 45.0 N 1.726E-07 8.781E-08 3.565E-08 1.855E-08 1.212E-08 8.843E-09 NNE 8.811E-08 4.427E-08 1.769E-08 9.098E-09 5.901E-09 4.285E-09 NE 6.049E-08 2.998E-08 1.176E-08 5.962E-09 3.832E-09 2.764E-09 ENE 8.299E-08 4.122E-08 1.627E-08 8.305E-09 5.365E-09 3.887E-09 E 5.540E-08 2.769E-08 1.109E-08 5.734E-09 3.740E-09 2.731E-09 1 ESE 3.465E-08 1.728E-08 6.916E-09 3.581E-09 2.339E-09 1.711E-09 SE 2.799E-08 1.402E-08 5.659E-09 2.952E 09 1.939E-09 1.425E-09 SSE 2.326E-08 1.164E-08 4.686E-09 2.438E-09 1.598E-09 1.172E-09 S 2.541E-08 1.272E-08 5.133E-09 2.678E-09 1.759E-09 1.293E-09 SSW 3.755E-08 1.840E-08 7.166E-09 3.633E-09 2.341E-09 1.696E-09 SW 6.312E-08 3.078E-08 1.186E-08 5.954E 09 3.807E-09 2.741E-09 USW 6.060E-08 2.988E-08 1.165E-08 5.884E-09 3.773E-09 2.718E-09 W 8.207E-08 4.159E-08 1.680E-08 8.704E-09 5.673E-09 4.133E-09 WNW 1.653E-07 8.495E-08 3.494E-08 1.834E-08 1.206E-08 8.836E-09 NW 2.199E-07 1.130E-07 4.643E-08 2.436E-08 1.601E 08 1.173E-08 NNW 2.033E-07 1.048E-07 4.324E-08 2.275E-08 1.498E-08 1.099E-08 l l

9 l

Rev.No. O Page __Q96 of ODCM l

l

l TABLE C-19 85TH PERCENTILE HOURLY PLUME CENTERLINE DEPOSITION VALUES

( FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (19851992)

(FOR USE WITH SHORT TERM RELEASES)

(D/Q) Plume Centerline Deposition (1/m#)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 9

N 8.196E 07 4.879E 07 3.235E-07 1.745E-07 7.680E-08 4.389E-08 NNE 7.499E-07 4.421E-07 2.918E-07 1.568E-07 6.889E-08 3.933E 08 j NE 7.015E-07 4.084E-07 2.680E-07 1.434E-07 6.279E-08 3.582E-08 ENE 7.513E-07 4.265E-07 2.758E-07 1.458E-07 6.348E-08 3.618E-08 E 6.000E-07 3.392E-07 2.198E-07 1.164E-07 5.095E-08 2.906E 08 ESE 5.379E-07 2.994E 07 1.925E-07 1.013E-07 4.402E 08 2.510E-08 SE 4.920E-07 2.729E-07 1.756E-07 9.248E 08 4.022E-08 2.294E-08 SSE 4.987E-07 2.787E-07 1.793E-07 9.390E-08 4.076E-08 2.322E-08 S 5.035E-07 2.780E-07 1.784E-07 9.367E-08 4.064E-08 2.315E-08 i SSW 6.150E 07 3.456E-07 2.231E-07 1.178E-07 5.125E-08 2.924E-08 SW' 6.826E-07 3.885E-07 2.522E-07 1.337E-07 5.831E 08 3.312E-08 WSW 7.002E-07 4.101E-07 2.698E-07 1.446E-07 6.339E-08 3.617E-08

/ -

W 7.821E-07 4.647E-07 3.077E-07 1.658E-07 7.294E-08 4.168E-08

' 5 WNW 8.673E-07 5.222E-07 3.480E-07 1.886E-07 8.325E-08, 4.764E-08 NW 8.526E 07 5.116E-07 3.403E-07 1.841E-07 8.119E-08 4.643E-08 j NNW 8.945E-07 5.382E-07 3.586E-07 1.943E-07 8.572E-08 4.903E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 2.868E 08 1.216E-08 4.258E-09 1.853E-09 1.097E-09 8.646E-10 NNE 2.569E-08 1.087E 08 3.874E-09 1.831E-09 1.092E-09 8.632E-10

NE 2.339E-08 9.896E-09 3.653E-09 1.815E-09 1.091E-09 8,661E-10 l

. ENE 2.344E-08 9.104E-09 3.470E-09 1.779E-09 1.102E-09 8.689E-10 l 1.884E-08 8.362E 09 3.407E-09 1.768E-09 1.099E-09 8.723E-10 E

ESE 1.644E-08 7.454E-09 3.210E-09 1.772E-09 1.094E-09 8.726E-10 SE 1.522E-08 7.432E-09 3.238E-09 1.752E 09 1.098E-09 8.714E-10 SSE 1.524E 08 7.294E-09 3.216E-09 1.72SE-09 1.093E-09 8.703E-10 S 1.518E 08 7.268E 09 3.248E-09 1.760E-09 1.092E-09 8.686E-10 SSW 1.909E-08 7.815E-09 3.324E-09 1.801E 09 1.089E-09 8.654E-10 SW 2.164E-08 8.873E-09 3.386E-09 1.767E-09 1.086E-09 8.625E-10 USW 2.362E 08 1.002E-08 3.516E-09 1.747E 09 1.081E-09 8.607E-10 V 2.724E-08 1.156E-08 3.953E-09 1.818E-09 1.082E-09 8.582E-10 WNW 3.117E-08 1.325E 08 4.389E-09 1.856E-09 1.088E-09 8.598E-10 NW 3.035E-08 1.288E-08 4.349E 09 '1.863E-09 1.091E-09 8.632E-10 NNW 3.206E-08 1.348E-08 4.593E-09 1.895E-09 1.094E-09 8.638E-10 0

Rev. No. O Page C-37 of ODCM

TABLE C-20 l SECTOR AVERAGE DEPOSITION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985-1992) h (FOR USE WITH LONG TERM RELEASES)

(D/Q) Sector Average Deposition (1/m*)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 1.937E-08 9.969E-09 6.130E-09 3.059E-09 1.257E-09 6.930E 10 NNE 1.032E-06 5.308E-09 3.264E-09 1.629E-09 6.689E-10 3.688E-10 NE 8.393E-09 4.317E-09 2.654E-09 1.324E 09 5.436E-10 2.996E-10 l ENE 1.845E-08 9.552E-09 5.899E-09 2.962E-09 1.227E-09 6.800E-10 1 E 1.764E-08 9.161E-09 5.670E-09 2.856E 09 1.187E-09 6.598E-10 ESE 1.294E-08 6.744E-09 4.184E-09 2.114E-09 8.826E-10 4.920E-10 SE 1.076E-08 5.627E-09 3.499E-09 1.774E-09 7.439E-10 4.158E-10 SSE 6.557E-09 3.433E-09 2.137E-09 1.085E-09 4.555E-10 2.548E-10 S 7.306E-09 3.827E-09 2.383E-09 1.210E-09 5.084E-10 2.845E-10 SSW 7.625E-09 3.959E-09 2.450E-09 1.234E-09 5.125E-10 2.848E-10 SW 9.231E-09 4.768E 09 2.940E-09 1.473E-09 6.079E-10 3.363E-10 USW 5.073E-09 2.611E 09 1.606E-09 8.018E-10 3.294E-10 1.816E-10 W 5.456E-09 2.807E-09 1.725E-09 8.608E-10 3.534E-10 1.947E-10 WNW 1.224E-08 6.296E-09 3.870E 09 1.930E-09 7.922E-10 4.365E-10 NW 1.930E-08 9.928E-09 6.103E 09 3.044E-09 1.250E-09 6.888E-10 NNU 1.827E-08 9.403E-09 5.782E-09 2.886E-09 1.185E-09 6.535E-10 4.5 7.5 '

0 25.0 35.0 45.0 N 4.420E-10 1.789E 10 5.648E-11 2.279E-11 1.219E-11 7.527E-12 NNE 2.352E-10 9.517E-11 3.004E-11 1.212E-11 6.481E-12 4.001E-12 NE 1.911E-10 7.733E-11 2.442E 11 9.857E-12 5.274E-12 3.258E-12 ENE 4.346E-10 1.760E-10 5.563E-11 2.248E-11 1.204E-11 7.449E 12 E 4.221E-10 1.709E-10 5.406E-11 2.186E-11 1.172E-11 7.255E 12 l ESE 3.150E-10 1.276E-10 4.035E-11 1.632E-11 3.750E-12 5.416E-12 SE 2.665E-10 1.079E-10 3.412E-11 1.379E-11 7.393E-12 4.574E 12 )

SSE 1.634E-10 6.612E-11 2.089E-11 8.433E-12 4.514E-12 2.789E-12 S 1.824E-10 7.383E 11 2.332E-11 9.413E-12 5.038E 12 3.112E-12 SSW 1.821E-10 7.369E-11 2.327E-11 9.385E-12 5.020E-12 3.099E-12 l SW 2.147E-10 8.686E 11 2.740E-11 1.104E-11 5.900E-12 3.639E-12 l WSW 1.158E-10 4.682E 11 1.474E-11 5.924E-12 3.156E-12 1.941E-12 l W 1.241E-10 5.017E-11 1.579E-11 6.346E-12 3.381E-12 2.079E 12 WNW 2.783E-10 1.126E-10 3.548E-11 1.428E-11 7.624E-12 4.697E-12 NW 4.392E-10 1.777E 10 5.606E 11 2.259E-11 1.207E-11 7.446E-12 NNW 4.168E-10 1.686E 10 5.321E-11 2.145E-11 1.147E-11 7.074E-12 O

Rev. No. O Page C-38 of ODCM l \

l l

I TABLE C-21 lO 85TH PERCENTILE HOURLY PLUME CENTERLINE DISPERSION VALUES V FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM GRAZING METEOROLOGICAL DATA (1985-1992)

(FOR USE WITH SHORT TERM RELEASES) 3 Plume Centerline Concentration I/Q (sec/m )

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 l

N 2.035E-04 1.319E-04 9.688E-05 6.511E-05 4.473E-05 3.234E-05 l NNE 1.879E-04 1.270E-04 9.123E-05 5.931E-05 3.831E-05 2.740E-05

! NE 1.632E-04 1.030E-04 7.465E-05 4.782E-05 2.895E-05 1.998E-05 l ENE 1.029E 04 6.414E-05 4.529E " 2.778E-05 1.533E-05 1.037E-05 E 6.347E-05 3.871E-05 2.645E-Da 1.643E-05 8.680E-06 5.704E-06 t

ESE 5.529E-05 3.284E-05 2.249E-05 1.344E-05 7.231E-06 4.554E-06 5.878E-05 3.449E-05 2.322E-05 1.327E-05 7.155E-06 4.530E-06

( SE l'.929E-05 1.017E-05 6.744E-06 l SSE 7.662E-05 4.653E-05 3.199E-05

! S 6.387E-05 3.657E-05 2.530E-05 1.454E-05 7.813E-06 5.065E-06 SSW 1.002E-04 6.046E-05 4.342E-05 2.548E-05 1.416E-05 9.655E-06 SW 1.271E-04 7.949E-05 5.718E-05 3.660E-G5 2.001E-05 1.420E-05 WSW 2.173E-04 1.416E-04 1.017E-04 7.040E-05 4.171E-05 3.095E-05 2.657E-04 1.695E-04 1.282E-04 8.955E-05 5.926E-05 4.564E-05

,Cp/ W WNW 2.947E-04 1.962E-04 1.530E-04 1.115E-04 7.065E-05 5.353E-05 l NW 2.589E-04 1.711E-04 1.294E-04 9.394E-05 5.940E-05 4.747E-05 NNW 2.240E-04 1.457E-04 1.122E-04 7.873E-05 5.217E-05 4.167E-05 l 4.5 7.5 15.0 25.0 35.0 45.0 N 2.466E-05 1.477E-05 7.229E-06 4.548E-06 3.258E-06 2.939E-06 NNE 2.146E-05 1.237E-05 5.954E-06 3.551E-06 2.874E-06 2.555E-06 NE 1.480E-05 8.449E-06 4.107E 06 2.760E-06 2.172E-06 1.943E-06 ENE 7.723E-06 4.094E-06 2.113E-06 1.431E-06 1.194E-06 1.080E-06 E 4.203E-06 2.450E-06 1.520E-06 1.093E-06 9.532E-07 9.103E-07 ESE 3.277E-06 2.083E-06 1.212E-06 8.868E-07 9.226E-07 9.234E-07 SE 3.284E-06 2.108E-06 1.223E-06 9.083E-07 9.658E-07 9.015E-07 SSE 4.949E-06 3.255E-06 1.759E-06 1.451E-06 1.200E-06 1.125E-06 S 3.595E-06 2.290E-06 1.634E-06 1.226E-06 1.051E-06 9.739E-07 SSW 7.015E-06 3.692E-06 2.072E-06 1.640E-06 1.361E-06 1.212E-06 SW 1.059E-05 5.604E-06 2.972E 06 2.285E-06 1.926E-06 1.784E-06 WSW 2.380E-05 1.346E-05 6.594E-06 4.291E-06 3.372E-06 3.081E-06 W 3.488E-05 2.109E-05 1.008E-05 6.435E-06 5.014E-06 4.515E-06 WNW 4.291E-05 2.492E-05 1.284E-05 8.174E-06 5.922E-06 5.432E-06 NW 3.796E-05 2.30)E-05 1.200E-05 7.419E-06 4.994E-06 4.573E-06 NNW 3.380E-05 2.018E-05 9.838E-06 5.947E-06 4.413E-06 4.003E-06 l

Rev. No. O Page _Q-39_ of ODCM

TASLE C-22 SECTOR AVERAGE DISPERSION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM GRAZING METEOROLOGICAL DATA (1985-1992) g (FOR USE WITH LONG TERM RELEASES)

Sector Average Concentration X/Q (sec/m*)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 5.300E-06 2.743E-06 1.774E-06 1.010E-06 5.125E-07 3.291E-07 NNE 2.423E-06 1.273E-06 8.309E-07 4.714E-07 2.365E-07 1.507E-07 NE 1.607E-06 8.669E-07 5.697E-07 3.202E-07 1.572E-07 9.874E-08 ENE 2.342E-06 1.257E-06 8.224E-07 4.586E-07 2.232E-07 1.398E-07 E 1.650E-06 8.651E-07 5.604E-07 3.111E-07 1.517E-07 9.540E-08 ESE 9.686E-07 5.088E-07 3.309E-07 1.837E-07 8.941E-08 5.619E-08 SE 6.517E-07 3.422E-07 2.237E-07 1.250E-07 6.131E-08 3.878E-08 SSE 5.531E-07 2.919E-07 1.915E-07 1.072E-07 5.265E-08 3.332E-08 S 6.636E-07 3.486E 07 2.274E-07 1.262E-07 6.142E-08 3.870E-08 SSW 8.999E-07 4.813E-07 3.136E-07 1.731E-07 8.310E-08 5.169E-08 SW 1.540E-06 8.357E-07  %.447E-07 2.999E-07 1.430E-07 8.841E-08 USW 1.549E-06 8.355E-07 5.452E-07 3.039E-07 1.479E-07 9.243E-08 W 2.100E-06 1.097E-06 7.138E-07 4.055E-07 2.043E-07 1.305E-07 VNW 4.454E-06 2.263E-06 1.452E-06 8.306E-07 4.280E-07 2.7 awe-07 NW 6.109E-06 3.102E-06 1.987E-06 1.135E-06 5.847E-07 3.787E-07 NNW 5.849E-06 2.971E-06 1.903E-06 1.087E-06 5.593E-07 3.621E-07 4.5 7.5 15.0 25.0 35.0 45.0 N 2.369E-07 1.223E-07 5.055E-08 2.663E-08 1.753E-08 1.286E-08 NNE 1.079E-07 5.507E-08 2.245E-08 1.171E-08 7.663E-09 5.598E-09 NE 6.998E-08 3.501E-08 1.389E-08 7.107E-09 4.592E-09 3.324E-09 ENE 9.892E-08 4.941E-08 1.967E-08 1.011E-08 6.559E-09 4.768E-09 E 6.774E-08 3.416E-08 1.385E-08 7.224E-09 4.739E-09 3.475E-09 ESE 3.988E-08 2.010E-08 8.165E-09 4.270E-09 2.807E-09 2.062E-09 SE ." 764E-08 1.405E-08 5.767E-09 3.044E-09 2.013E-09 1.486E-09 SSE 2.376E-08 1.207E-08 4.950E-09 2.609E-09 1.724E-09 1.272E-09 2.753E-08 1.395E-08 5.723E-09 3.022E-09 2.002E-09 1.480E-09 iSW 3.639E-08 1.802E-08 7.121E-09 3.649E-09 2.367E-09 1.723E-09 SJ 6.194E-08 3.035E-08 1.178E-08 5.946E-09 3.814E-09 2.750E-09 WSW 6.527E-08 3.245E-08 1.279E-08 6.514E-09 4.200E-09 3.037E-09 W 9.357E-08 4.793E-08 1.962E-08 1.026E-08 6.727E-09 4.920E-09 VNW 2.008E-07 1.049E-07 4.398E-08 2.339E-08 1.550E-08 1.142E-08  !

NW 2.744E-07 1.433E-07 6.013E-08 3.200E-08 2.120E-08 1.563E-08 NNW 2.622E-07 1.369E-07 5.743E-08 3.056E-08 2.025E-08 1.493E-08 9

Rev.No. O Page C-40 of ODCM

TAILE C-23 85TH PERCENTILE HOURLY PLUME CENTERLINE DEPOSITION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM GRAZING METEOROLOGICAL DATA (1985-1992)

(FOR USE WITH SHORT TERM RELEASES)

(D/Q) Sector Average Deposition (1/m")

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 9.063E-07 5.471E-07 3.636E-07 1.966E-07 8.666E-08 4.952E-08 NNE 8.251E-07 4.868E 07 3.215E-07 1.728E-07 7.592E-08 4.334E-08 NE 7.357E-07 4.285E-07 2.771E-07 1.482E-07 6.503E-08 3.718E-08 ENE 7.139E-07 4.059E-07 2.633E-07 1.390E-07 6.056E-08 3.455E-08 E 5.942E-07 3.352E-07 2.174E-07 1.145E-07 4.986E-08 2.843E-08 ESE 5.161E-07 2.898E-07 1.872E-07 9.833E-08 4.282E-08 2.443E-08 SE 5.089E-07 2.831E-07 1.820E-07 9.577E-08 4.161E-08 2.372E-08 SSE 5.281E-07 2.921E-07 1.855E-07 9.735E-08 4.223E-08 2.406E-08 S 4.971E-07 2.780E-07 1.795E-07 9.481E-08 4.129E-08 2.356E-08 SSW 6.017E-07 3.342E-07 2.150E-07 1.132E-07 4.916E-08 2.802E-08 SW 6.735E-07 3.808E-07 2.459E-07 1.297E-07 5'.629E-08 3.210E-08 WSW 7.454E-07 4.299E-07 2.812E-07 1.501E-07 6.569E-08 3.750E-08 W 8.255E-07 4.942E-07 3.284E-07 1.775E-07 7.813E-08 4.461E-08 O WNW NW 9.768E-07 9.981E-07 5.984E-07 6.144E-07 4.019E-07 4.117E-07 2.191E-07 2.241E-07 9.694E-08 9.911E-08 5.542E-08 5.667E-08 NNW 9.449E-07 5.713E-07 3.826E-07 2.082E-07 9.205E-08 5.265E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 3.236E-08 1.356E-08 4.621E-09 1.897E-09 1.098E-09 8.646E-10 NNE 2.831E-08 1.195E-08 4.113E-09 1.839E-09 1.092E-09 8.622E-10 NE 2.433E-08 1.035E-08 3.679E-09 1.802E-09 1.091E-09 8.636E-10 ENE 2.248E-08 8.997E-09 3.623E-09 1.798E-09 1.100E-09. 8.672E-10 E 1.850E-08 8.152E-09 3.457E-09 1.792E-09 1.096E-09 8.705E-10 ESE 1.618E-08 7.794E-09 3.226E-09 1.746E-09 1.094E-09 8.718E-10 SE 1.571E-08 7.255E-09 3.160E 09 1.748E-09 1.091E-09 8.694E-10 SSE 1.606E-08 7.248E-09 3.154E-09 1.790E-09 1.087E-09 8.633E-10 S 1.556E-08 7.412E-09 3.201E-09 1.765E-09 1.089E-09 8.651E-10 SSW 1.833E-08 7.403E-09 3.328E-09 1.773E-09 1.086E-09 8.637E-10 SW 2.098E-08 8.312E-09 3.361E-09 1.789E-09 1.083E-09 8.606E-10 WSW 2.451E-08 1.061E-08 3.594E-09 1.728E-09 1.078E-09 8.604E-10 l W 2.912E-08 1.229E-08 4.144E-09 1.869E-09 1.081E-09 8.576E-10 WNW 3.619E-08 1.527E-08 5.019E-09 1.940E-09 1.088E-09 8.569E-10 NW 3.702E-08 1.563E-08 4.880E-09 1.914E-09 1.092E-09 8.605E-10 NNW 3.440E-08 1.450E-08 4.799E 09 1.929E-09 1.096E-09 8.631E-10 0

Rev. No. O Page C-41 of ODCM

TAGLE C-24 SECTOR AVERAGE DEPOSITION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DEYERMINED FROM GRAZING METEOROLOGICAL DATA (1985-1992)

(FOR USE WITH LONG TERM RELEASES)

(D/Q) Sector Average Deposition (1/m')

SEGMENT BOUND?. RIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 2.265E-08 1.167E-08 7.177E-09 3.585E-09 1.474E-09 8.132E-10 NNE 1.028E-08 5.295E-09 3.258E-09 1.627E-09 6.691E-10 3.691E-10 NE 8.034E-09 4.134E-09 2.542E-09 1.269E-09 5.213E-10 2.874E-10 ENE 2.078E-08 1.079E-08 6'.675E-09 3.361E-09 1.397E-09 7.762E-10 E 1.924E-08 1.002E-08 6.213E-09 3.138E-09 1.309E-09 7.293E-10 ESE 1.159E-08 6.054E-09 3.762E-09 1.906E-09 7.979E-10 4.456E-10 SE 7.983E-09 4.184E-09 2.605E-09 1.324E-09 5.563E-10 3.114E-10 SSE 5.124E-09 2.690E-09 1.677E-09 8.534E-10 3.593E-10 2.014E-10 S 7.383E-09 3.880E-09 2.421E-09 1.233E-09 5.198E-10 2.916E-10 SSW 6.769E-09 3.525E-09 2.186E-09 1.104E-09 4.602E-10 2.563E-10 SW 8.471E-09 4.384E-09 2.706E-09 1.358E-09 5.619E-10 3.113E-10 USW 5.062E-09 2.608E-09 1.605E-09 8.019E-10 3.298E-10 1.820E-10 W 5.392E-09 2.777E-09 1.708E-09 8.529E-10 3.506E-10 1.933E-10 WNW 1.123E-08 5.780E-09 3.555E-09 1.774E-09 7.289E-10 4.019E-10 NW 1.792E-08 9.223E-09 5.671E-09 2.830E-09 1.162E-09 6.408E-10 NNW 1.976E-08 1.018E-08 6.260E-09 3.126E-09 1.285E-09 7.091E-10 4.5 7.5 15.0 25.0 35.0 45.0 N 5.188E-10 2.099E-10 6.626E-11 2.672E-11 1.429E-11 8.820E-12 NNE 2.355E-10 9.527E-11 3.006E-11 1.212E-11 6.476E-12 3.995E-12 NE 1.833E-10 7.418E-11 2.341E-11 9.442E-12 5.048E-12 3.116E-12 ENE 4.965E-10 2.010E-10 6.352E-11 2.565E-11 1.374E-11 8.493E-12 i E 4.669E-10 1.890E-10 5.976E-11 2.415E-11 1.294E-11 8.006E-12  ;

ESE 2.855E-10 1.156E-10 3.653E-11 1.476E-11 7.905E-12 4.888E-12 SE 1.997E-10 8.083E-11 2.553E-11 1.031E-11 5.516E-12 3.408E-12 SSE 1.292E-10 5.225E-11 1.648E-11 6.643E-12 3.550E-12 2.189E-12 S 1.871E-10 7.570E-11 2.390E-11 9.637E-12 5.153E-12 3.181E-12 SSW 1.641E-10 6.637E-L1 2.094E-11 8.442E-12 4.512E-12 2.783E-12 SW 1.988E-10 8.042E-11 2.536E-11 1.021E-11 5.453E-12 3.361E-12 USW 1.161E-10 4.691E-11 1.476E-11 5.930E-12 3.158E-12 1.942E-12 W 1.233E-10 4.981E-11 1.567E-11 6.292E-12 3.349E-12 2.058E-12 WNW 2.562E-10 1.036E-10 3.262E-11 1.311E-11 6.990E-12 4.301E-12 NW 4.086E-10 1.652E-10 5.209E-11 2.097E-11 1.119E-11 6.894E-12 NNW 4.523E-10 1.830E-10 5.771E-11 2.325E-11 1.242E-11 7.660E-12 O

Rev.No. O Page C-42 of ODCM

1 l

O APPENDIX D l

UMITED ANALYSIS APPROACH DOSE ASSESSMENT FOR UQUID RADIOACTIVE EFFLUENTS O .

O l

Rev. No. O Page Q-1_ of ODCM l

APPENDIX D LIMITED ANALYSIS APPROACH DOSE ASSESSMENT FOR LIQUID RADIOACTIVE EFFLUENTS h

TABLE TITLE PA E D-1 Calculation of Total Ci/yr Releases for Uquids D-5 D-2 Organ Doses For Uquid Releases D-6 D-3 Dose Contribution to the Adult's Total Body From the D-8 Freshwater Fish Pathway D-4 Dose Contribution to the Teenager's Uver from the D-9 Freshwater Fish Pathway D-5 Dose Contribution to the Adult's Total Body from the D-10 Potable Water Pathway D-6 Dose Contribution to the Teenager's Uver from the D-11 Potable Water Pathway D-7 Dose Contribution to the Adutt's Total Body and to the Teenager's Uver from the Lnke Shoreline Deposits D-12 h

Pathway D-8 Dose Contribution to the Adutt's Total Body and to D-13 the Teenager's Uver from the Swimming and Boating Pathways O

Rev. No. O Page D-2 of ODCM

l LIMITED ANALYSIS APPROACH DOSE ASSESSMENT FOR LIQUID RADIOACTNE EFFLUENTS l

The radioactive liquid effluents for the years 1980 through 1987 (from the JAFNPP Semi- l Annual Effluent release reports) were evaluated to determine the critical pathways, organs, age groups, and nuclides which contributed to environmental doses. The liquid release nuclide distribution used in this analysis is shown in Table D-1. This analysis was performed to develop a limited dose analysis for determination of liquid effluent environmental doses. Limiting the dose calculation to a few selected nuclides that contribute the majority of the dose, along with the application of an appropriate conservatism factor to compensate for variations in isotopic mixtures, provides a simplified method of determining compliance with the dose limits of Technical Specification 2.3.

Tables D-2 through D4 show the results of this evaluation. Table D2 presents the dose for 8 organs and 4 age groups from all available pathways. The adult's total body and teenager's age groups (adult, teenager, child, and infant) and all organs (bone, liver, kidney, thyroid, lung, skin, and GI-LLI). The dominant pathway contribution to these doses is freshwater fish ingestion. Table D-3 presents the percent of the adutt's total body dose contribution by the major radionuclides through the dominant pathway, ingestion of freshwater fish. Table D-4 presents the same data for the teenager's liver dose. The data in Tables D-3 and D-4 show that the fish pathway contributes at least O

d 92% to the adutt's total body dose and at least 80.9% to the teenager's liver dose from all pathways considered. The data in the tables also show that during 1980-1987 the radionuclides Cs-134, Cs-137, Zn-65, Co-60, and Mn-54 contributed over 91% of the total dose to the total body and over 80% of the total liver dose via the freshwater fish ingestion pathway.

The data in Tables D-5 and D-6 show that the potable water pathway contributed no more than 1% to the adult's total body dose and no more than 0.5% to the teenager's liver dose. This pathway is necessary to demonstrate compliance with 10CFR50 as specified in Sections 4.2 and 4.3.1 of NUREG-0133. As mentioned in Appendix A, Table A-4.3, this pathway is considered for all required analysis.

Table D-7 shows that 17.9% of the teenager's dose to the liver in 1984 was from the lake shoreline deposits pathway. The lake shoreline pathway contributed 5.7% of the adult's total body dose in 1984. This pathway contributed 9.3% of the teenager's liver dose in 1986 and 2.8% of the adutt's total body dose in 1986. The lake shoreline deposits pathway is second to the freshwater fish pathway when the concentrations of Cs-134, Cs-137, Zn-65, Co-60, and Mn-54 are low as in 1984 and 1986.

O v

1 Rev.No. O Page D-3 of ODCM

UMITED ANALYSIS APPROACH DOSE ASSESSMENT FOR UQUID RADIOACTIVE EFFLUENTS (Continued) g Table D-8 shows that the swimming and boating pathways, combined, contribute no

more than 1.5% to the adutt's total body dose and no more than 0.8% to the teenager's liver dose from 1980 to 1987. The swimming and boating pathways are not used in the ODCM since their dose contributions are very small.

A conservatism factor of 0.8 is introduced into the equation (i.e., calculated doses using 1 this approach should be divided by 0.8) to compensate for any unexpected variability in nuclide and pathway dose contribution. therefore, the dose commitment to the adutt's total body and teenager's liver due to radioactive material in liquid effluents can be -

reasonably estimated by limiting the dose calculation to these 5 nuclides and the fish and potable water pathways, which cumulatively contribute the bulk of the total dose calculated by accounting for all nuclides and all pathways.

O O

Rev.No. O Page _Q-4 of ODCM

O O O TABLE D-1 m

o F CALCULATION OF TOTAL Ci/yr RELEASES FOR LIQUIDS y (Based on semi-annual effluent release reports for the years 1980 through 1987)

AVERAGE-sci /yr' c) IS0 TOPE 1980 1981 1982 1983 1984: :19855 1986 J19871 H-3 2.81E 00 4.11E 00 6.55E-01 2.72E 00 4.77E 00 4.20E 00 5.00E 00 2.48E 00 3.34E 00 Ag-110m 1.12E-04 2.21E-04 1.15E-05 9.49E-05 2.66E-05 5.34E-06 -- --

5.90E-05 l

Cu-64 3.42E-02 -- -- -- -- -- -- --

4.28E-03 Cs-134 7.30E-02 8.00E-02 5.47E-02 5.11E-02 2.19E-04 8.71E-03 6.68E-05 1.47E-03 3.37E-02 Cs-137 1.06E-01 1.26E-01 6.96E-02 7.77E-02 8.80E-04 1.27E-02 1.01E-03 6.65E-03 5.01E-02 I-131 2.77E-02 4.50E-02 9.05E-04 1.95E-03 4.73E-05 2.32E-05 -- --

9.45E-03 4.61E-04 1.12E-03 1.82E-03 4.49E-04 5.86E-04 5.55E-04 2.61E-06 2.58E-05 6.27E-04 Ba/La-140 3.23E-03 6.82E-03 2.90E-03 4.78E-02 Co-58 1.07E-01 2.08E-01 2.94E-02 2.49E-02 --

Co-60 8.03E-01 1.40E 00 3.66E-01 4.86E-01 3.99E-02 9.96E-02 1.56E-02 4.32E-02 4.07E-01 Fe-59 1.31E-02 1.10E-02 3.46E-03 4.40E-03 3.21E-04 2.79E-04 --

3.49E-04 4.11E-03 3.11E-02 4.57E-02 9.81E-03 5.27E-03 1.29E-03 6.14E-03 7.20E-04 4.67E-04 1.26E-02 Zn-65 2.86E-02 7.30E-04 1.60E-02 9.76E-02 Mn-54 2.10E-01 3.44E-01 6.76E-02 1.04E-01 1.02E-02 4.63E-02 4.79E-02 2.77E-03 2.83E-03 8.30E-04 1.51E-04 2.95E-05 --

1.26E-02 Cr-51 1.27E-04 1.27E-03 Sb-124 4.87E-03 3.83E-03 5.37E-04 7.62E-04 1.87E-05 -. --

1.41E-02 6.44E-04 1.22E-04 7.61E-04 --

2.32E-04 2.07E-06 --

1.98E-03 Mo-99 2.85E-04 Tc-99m 1.81E-04 1.67E-03 3.17E-05 2.40E-04 1.38E-04 1.94E-05 3.10E-07 --

1.72E-05 6.99E-05 3.83E-05 1.03E-04 1.23E-04 1.32E-04 1.53E-06 --

6.06E-05 Ce-141 3.55E-04 Zr/Nb-95 2.14E-03 2.54E-04 5.50E-05 1.45E-04 1.74E-04 7.02E-05 1.20E-06* --

Ce-144 6.33E-05 6.58E-04 2.46E-05 5.68E-05 1.88E-05 6.87E-04 1.27E-04 --

2.04E-04 l I-133 1.22E-03 5.35E-03 1.03E-03 2.16E-03 1.08E-04 9.72E-06 1.67E-06 --

1.23E-03 Na-24 1.79E-02 3.77E-02 1.70E-03 2.01E-03 2.02E-04 2.22E-05 --

2.78E-04 7.48E-03 As-76 2.46E-04 2.08E-04 8.67E-05 3.40E-06 2.89E-04 2.24E-05 -- --

1.07E-04 Np-239 2.24E-03 4.29E-02 1.88E-02 3.55E-03 2.02E-03 2.45E-04 -- --

8.72E-03

,? Xe-133 9.65E-03 3.98E-02 1.05E-02 6.81E-04 2.82E-03 5.29E-03 1.82E-04 4.51E-uS 8.62E-03 6 3.28E-03 5.85E-02 1.01E-02 7.03E-04 3.31E-02 9.86E-03 6.67E-04 --

1.45E-02

• Xe-135 5.70E-05 Kr-85m 2.88E-04 7.28E-06 7.14E-05 3.52E-05 5.40E-05 -- -- --

O 4.97E-05 2.47E-03 1.45E-04 6.20E-04 --* -- -- --

4.11E-04 I-135 --

7.20E-05 5.76E-04 o' Sr-89 -- -- -- -- --

o Sr-90 3.47E-05 1.27E-04 1.88E-04 1.38E-04 -- -- -- --

6.10E-05 2.19E-03 --

6.78E-03 1.12E-03 Fe-55 -- --

3 Co-57 -- -- -- -- -- --

1.29E-05 --

1.61E-06 o

o -- -- --

2.26E-04 --

2.83E-05 Zr-97 -- --

K Nb-95m -- -- -- -- -- --

4.32E-06 --

5.40E-07 3.42E-05 4.28E-06 W-187 -- ,

• Nb-95 Only

n TABLE D-2 E

y ORGAN DOSES FOR LIQUID RELEASES (ALL PATHWAYS) 9 a

!?liflL , .' 'm'y'& yy

, gi@D%T['f?\ l&M - , ', ~ n; ' ? '

]'{; q

SKIM BONE LIVER T. BODY THYROID KIDNEY LUNGt. . .GI-LLI' YEAR L(mrem)1~(mrem)

? (mrem) 1(mrem); 1(mrem)t (mrem) -(mrem)? L(mrem).

1980 8.85E-04 7.11E-02 1.24E-01 9.04E-02 3.25E-03 4.26E-02 1.41E-02 1.63E-03 1981 1.44E-03 7.99E-02 1.38E-01 1.00E-01 5.18E-03 4.81E-02 1.61E-02 1.98E-03 1982 4.09E-04 4.76E-02 8.37E-02 6.17E-02 5.12E-04 2.82E-02 9.46E-03 5.66E-03 1983 5.22E-04 4.91E-02 8.42E-02 6.16E-02 7.22E-04 2.84E-02 9.67E-03 6.82E-03 1984 3.60E-05 4.63E-04 7.97E-04 5.38E-04 4.63E-05 3.21E-04 1.10E-04 7.12E-04 1985 1.16E-04 9.05E-03 1.59E-02 1.15E-02 1.29E-04 5.53E-03 1.79E-03 1.93E-03 1986 1.47E-05 4.47E-04 6.69E-04 4.47E-04 1.97E-05 2.56E-04 8.58E-05 1.58E-04 1987 1.32E-04 9.38E-03 1.44E-02 9.98E-03 1.46E-04 4.97E-03 1.71E-03 1.85E-03 i

': t Q h@iM N $ie G $ m %i M ,/ '@ N glIEESGE % n f$$sd$4gs %' W ! ,' g y g gtpg gf$g7 -

iSKIN . 80NEL LIVER T. BODY" ' THYROID! . KIDNEY LUNG YEAR '(mrem)6 mrem) (mrem) (mrem)'  ?(mrem)L "(mrem) . (mrem)-. I-LLhi mrem 1980 4.94E-03 7.82E-02 1.31E-01 5.58E-02 6.52E-03 4.67E-02 2.00E-02 1.50E-02 1981 8.05E-03 8.97E-02 1.48E-01 6.43E-02 1.05E-02 5.45E-02 2.44E-02 1.97E-02 1982 2.28E-03 5.17E-02 8.75E-02 3.71E-02 2.10E-03 3.03E-02 1.27E-02 5.67E-03 1983 2.92E-03 5.37E-02 8.86E-02 3.74E-02 2.74E-03 3.10E-02 1.34E-02 6.94E-03 1984 2.01E-04 6.08E-04 9.56E-04 4.94E-04 1.86E-04 4.64E-04 2.63E-04 6.44E-04 2

1985 6.46E-04 9.98E-03 1.68E-02 7.18E-03 5.79E-04 6.07E-03 2.55E-03 1.82E-03 1986 8.21E-05 5.31E-04 7.48E-04 3.29E-04 7.58E-05 3.17E-04 1.56E-04 1.71E-04 1987 7.35E-04 1.05E-02 1.54E-02 6.24E-03 6.57E-04 5.62E-03 2.54E-03 1.83E-03 S

a o

8 m

l O O O

O O O TABLE D-2 (CONTINUED) o

$ ORGAN DOSES FOR LIQUID RELEASES (ALL PATHWAYS)

? $$lDj@d$)','Q$i!}; g$$ f MWp3fThitsgs9lill$$$h@jjIf 3

'" ;y':d "'

t'*'  : g g r ;?; p M r'f' ^;" tf"

1 GI-LLI LIVER T."B0DY THYROID' -KIDNEY LUNGS m SKIN . BONE (mrem)' '(mrem)!'1 A(miem)-

YEAR (mrem)~ '(mrem)-' (mrem) '(mrem) - (mrem) .~

9.27E-02 1.12E-01 2.22E-02 3.64E-03 3.68E-02 1.34E-02 4.86E-03 1980 1.03E-03 4.16E-02 1.53E-02 5.95E-03 1981 1.68E-03 1.04E-01 1.25E-01 2.56E-02 4.79E-03 6.18E-02 7.48E-02 1.43E-02 5.58E-04 2.43E-02 8.87E-03 1.74E-03 1982 4.77E-04 7.70E-04 f.46E-02 9.13E-03 2.12E-03 1983 6.09E-04 6.39E-02 7.57E-02 1.43E-02 4.20E-05 5.96E-04 7.16E-04 2.13E-04 4.76E-05 2.78E-04 1.09E-04 2.01E-04 1984 1.41E-04 4.75E-03 1.69E-03 5.58E-04 1985 1.35E-04 1.17E-02 1.42E-02 2.89E-03 5.89E-04 6.16E-04 1.38E-04 1.81E-05 2.24E-04 8.23E-05 4.99E-05 1986 1.72E-05 1.60E-04 4.40E-03 1.66E-03 5.55E-04 1987 1.53E-04 1.24E-02 1.33E-02 2.42E-03 1

% :!$i#2'ij@$N!@ ?@!$ 1$ ' ig i~' *? MIN @j'r :iSW $P@ 9$ 7 !$PhEl@$$$$

SKIN BONE- LIVER T. 80DY_ THYROID. ~ KIDNEY LUNG 1:GI-LLI:

YEAR (mrem) ' (mrem) ' (mrem) . (mrem)' f(mrem). .(mrem) -(mrem).? -(mrem)c 0 4.12E-04 5.60E-04 2.58E-04 1.16E-03 2.58E-04 1.93E-04 2.34E-04 1980 3.69E-04 2.95E-04 3.83E-04 1981 0 5.45E-04 7.24E-04 4.08E-04 1.84E-03 1982 0 2.52E-04 3.26E-04 1.20E-04 1.01E-04 1.32E-04 9.22E-05 1.01E-04 1983 0 2.67E-04 3.54E-04 1.47E-04 1.59E-04 1.52E-04 1.12E-04 1.27E-04 0 7.73E-06 1.38E-05 1.31E-05 1.16E-05 1.06E-05 1.01E-05 1.34E-05 1984 2.78E-05 3.38E-05 1985 0 5.14E-05 7.43E-05 3.61E-05 2.38E-05 3.57E-05 u 7.81E-06 6.50E-06 7.07E-06 6.70E-06 7.83E-06 m 1986 0 3.78E-06 8.99E-06 E 1987 0 5.64E-05 7.85E-05 4.16E-05 2.78E-05 4.00E-05 3.28E-05 3.90E-05 9

y k

O -

8 r

4

TABLE D4 DOSE CONTRIBUTION TO THE ADULT'S TOTAL BODY FROM THE g FRESHWATER FISH PATHWAY (PERCENT)

ISOTOPE 1980 1981 1982 1983 1984 1985 1986 1987 Cs-134 52.7 50.3 56.5 52.2 25.2 52.1 9.2 26.8 Cs-137 45.2 46.8 42.4 46.8 59.7 44.9 82.5 71.5 Zn-65 1.3 1.7 0.6 0.3 8.5 2.1 5.7 0.5 Co-60 0.6 0.9 0.4 0.5 4.5 0.6 2.1 0.8 Mn-54 0.2 0.3 0.1 0.2 1.7 0.2 0.1 0.4 The percentage (%) 100 100 100 100 99.6 99.9 99.6 100 of the total body dose from five nuclides in the fish pathway The percentage (%)

of the total dose 98.8 98.3 99.2 98.9 92.0 98.8 95.8 98.4 &

W to the adult's total body from the fish pathway The percentage (%) 98.8 98.3 99.2 98.9 91.6 98.7 95.2 98.4 of the total dose to the adult's total body from the five nuclides in the fish pathway O\

Rev.No. O Page Q-fL of ODCM

i TABLE D 4 DOSE CONTRIBUTION TO THE TEENAGER'S LNER FROM THE FRESHWATER FISH PATHWAY (PERCENT)

ISOTOPE 1980 1981 1982 1983 1984 1985 1986 1987 Cs-134 46.2 43.8 50.2 45.9 20.0 45.5 7.3 22.0 Cs-137 50.8 52.2 48.4 52.9 60.9 50.2 83.5 75.5 Zn-65 2.0 2.5 0.9 0.5 11.9 3.3 8.0 0.7 Co-60 0.2 0.3 0.1 0.2 1.3 0.2 0.6 0.2 ;

Mn-54 0.8 1.1 0.4 0.6 5.6 0.9 0.5 1.4 l l

1 The percentage (%) 100 99.9 100 100 99.7 100 99.9 99.8 of the liver dose from five nuclides in the fish path-way The percentage (%) 96.5 95.0 97.6 97.0 80.9 96.4 89.9 95.6 ;

(]' ' of the total dose to the teen's liver from the i fish pathway The percentage (%) 96.5 94.9 97.6 97.0 80.7 96.4 89.8 95.4 of the total dose to the teen's liver from the five nuclides in the fish pathway .

O Rev. No. O Page _Q-9_ of ODCM

TABLE D-6 DOSE CONTRIBUTION TO THE ADULTS TOTAL BODY FROhii THE g POTABLE WATER PATHWAY (PERCENT)

ISOTOPE 1980 1981 1982 1983 1964* 1985 1986 1987 Cs-134 41.5 35.7 47.5 41.9 3.29 35.7 1.18 15.5 Cs-137 35.6 33.2 35.7 37.6 7.82 30.7 10.5 41.5 Zn-65 1.01 1.2 0.5 0.25 1.11 1.44 0.73 0.28 Co-60 17.8 24.4 12.4 15.5 23.4 15.9 10.8 17.8 Mn-54 0.86 1.1 0.4 0.61 1.10 0.84 0.09 1.22 The percentage (%) 96.8 95.6 96.5 95.9 36.7 84.6 23.3 76.3 of the total body dose from the nuclides from the potable' water pathway The percentage (%) 0.16 0.18 0.15 '

0.15 0.89 0.18 0.94 0.21 the total dose to the adult's total body from the potable water pathway The percentage (%) 0.15 0.17 0.14 0.14 0.33 0.15 0.22 0.16 of the total dose of the adult's total body from the five nuclides in the potable water pathway

• Tritium was the major contributor to the potable water pathway for 1984.

O Rev.No. O Page ..D-10 of ODCM

! TABLE D4 DOSE CONTRIBUTION TO THE TEENAGER'S LNER FROM THE POTABLE WATER PATHWAY i

(PERCENT)

ISOTOPE 1980 1981 1982 1983 1984* 1985 1986 1987 Cs-134 40.9 37.0 47.0 41.7 4.87 36.9 1.74 16.1 Cs-137 45.0 44.2 45.3 48.0 14.8 40.8 19.9 55.3 2

Zn45 1.8 2.14 0.85 0.44 2.90 2.63 1.90 0.52 Co-60 6.43 9.25 4.49 5.66 12.7 6.03 5.8 6.77 Mn-54 3.5 4.76 1.73 2.54 6.77 3.62 0.57 5.24 The percentage (%) 97.6 97.4 99.4 98.3 42.0 90.0 29.9 83.9 of the liver dose from the nuclides from the potable water pathway O

'd The percentage (%)

of the total dose 0.12 0.13 0.12 0.12 0.38 0.14 0.44 0.15 to the teen's liver from the ,

potable water l pathway .

l The percentage (%) 0.11 0.12 0.11 0.11 0.16 0.13 0.13 0.12 '

of the total dose to the teen's liver from the five nuclides in the potable water pathway

• Tritium was the major contributor to the potable waer pathway for 1984 Rev.No. O Page D-11 of ODCM

4

! TABLE D-7 DOSE CONTRIBUTION TO THE ADULT'S TOTAL BODY AND TEENAGER'S g l LNER FROM THE LAKE SHOREUNE DEPOSITS PATHWAY l 1980 1981 1982 1983 1984 1985 1988 1987 i The percentage (%) 0.83 1.22 0.56 0.72 5.68 0.85 2.79 1.12 of the total dose to the adult's total body from the lake shoreline

deposits pathway Maximum percentage from 1980 to 1987 - 5.68%

Average percentage from 1980 to 1987 - 1.72%

The percentage (%)

of the total dose 3.22 4.62 2.22 2.80 17.91 3.27 9.33 4.04 g to the teenager's liver from the lake shoreline deposits pathway Maximum percentage from 1980 to 1987 - 17.9 %

Average percentage from 1980 to 1987 - 5.93 %

O Rev. No. O Page D-12 of ODCM 4

TABLE D-8 DOSE CONTRIBUTION TO THE ADULT'S TOTAL BODY AND TEENAGER'S LNER FROM THE SWIMMING AND BOATING PATHWAYS 1980 1981 1982 1983 1984 1985 1988 1987 Percentage (%) of 0.21 0.31 0.13 0.17 1.39 0.20 0.82 0.27 the total dose to the Adult's total body from the swimming and boating pathways Maximum percentage from 1980 to 1987 - 1.39 %

Average percentage

• from 1980 to 1987 - 0.41 %

0.14 0.37 0.18 O Percentage (%) of the total dose to 0.14 0.21 0.09 0.12 0.78 the teenager's liver from the swimming and boating pathways Maximum percentage from 1980 to 1987 - 0.78 %

Average percentage from 1980 to 1987 - 0.25 %

23 O

Rev.No. O Pa0s R of ODCM

O APPENDIX E TECHNICAL BASES FOR EFFECTNE DOSE FACTORS O

O Rev.No. O Page J-1 of ODCM

APPENDIX E TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS TABLE TITLE PAGE E-1 Effective Dose Factors for Noble Gases - Total Body Effective E-6 Dose (K,)

E-2 Effective Dose Factors for Noble Gases - Air Doses (M,) and (N,) E-7 E-3 Effective Dose Factors for Noble Gases - Skin Effective Dose E-8 (L + 1.1 M,) and (L,)

E-4 Tables of Source Terms Used for Development of Effective Dose E9 Transfer. Factors (Elevated Release)

E-5 Tables of Source Terms Used for Development of Effective Dose E-10 Transfer Factors (Vent Release)

E-6 Radionuclide Distribution of Vent and Elevated Releases E-11 O

O Rev.No. O Page JdL of ODCM

l TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS I The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific. These effective factors, which are based on the typical radionuclide distribution in the releases, can be applied to the total radioactivity released to approximate the dose in the environment, i.e., instead of having to sum the isotopic distribution multiplied by the isotope specific dose factor, only a single multiplication (K,,, L,y, M,, or N,n) times the total quantity of radioactive material released, would be needed. This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculating technique.

Determination of Effective Dose Factors The effective dose transfer factors are based on past operating data. The radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations.

E-1 n

K, = E K i . f i

i=1 Where:

g K,n = the effective total body dose factor due to gamma emissions from all noble gases released.

K, = the total body dose factor due to gamma emissions from each noble gas radionuclide 'i' released.

f, = the fractional abundance of noble gas radionuclide 'i' is of the total noble gas radionuclides.

A K,n is calculated for elevated releases and also for vent releases.

n L, = E L i . f i

i=1 Where: l L,3 =

the effective skin dose factor due to beta emissions from all noble gases released.  !

Ol Rev. No. O Page E-3 of ODCM l

1 l

t l

TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (Continued)

( = the skin dose factor due to the beta emissions from each noble gas radionuclide 'i' released.

For ease of calculation, L ,is calculated for elevated releases and (L + 1.1M),,is calculated for vent releases.

E-2 n

(L + 1.1 M), = E (L, + 1.1 M,) . f, i=1 Where:

(L + 1.1 M),n = the effective skin dose factor due to beta and gamma emissions from all noble gases released from the vents.

(( + 1.1 M,) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide 'i' released from the vents.

E-3 n

M, = E M, . fi i=1 Where:

M,n = the effective air dose factor due to gamma emissions from all noble gases released.

M, = the air dose factor due to gamma emissions from each noble gas radionuclide 'i' released.

A M,n is calculated for elevated releases and also for vent releases.

O O

Rev. No. O Page E-4 of ODCM l

I TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (Continued)

E-4 4

n N, = E N, . fi i=1 Where:

N,n = the effective air dose factor due to beta emissions from all noble gases released.

1 N, = the air dose factor due to beta emissions from each noble gas radionuclide l

'i' released.  ;

A N,3 is calculated for elevated releases and also for vent releases.

l To determine the appropriate effective factors to be used and to evaluate the degree i of variability, the atmospheric radioactive effluents for the years 1985 through 1991 l have been evaluated. Tables E-1, E-2, and E-3 present the resuits of this evaluation.  !

To compensate for any unusual variability in the radionuclide distribution,3 sigma was added to the average K,3, M,n, N,3, L,n, and (L + 1.1 M),3 values. This added conservatism provides additional assurance that the evolution of doses by the use of a single effective factor will normally overestimate actual doses in the environment, and any underestimation will be of insignificant magnitude.

O Rev.No. O Page E-5 of ODCM

TABLE E-1 EFFECTIVE DOSE FACTORS FOR NOBLE GASES -

TOTAL BODY EFFECTIVE DOSE

[K ,]

YEAR VENT RELEASE ELEVATED RELEASE

[ mrem /sec per Ci/m ) [ mrem /sec per Cl/m8]

Total Body Effective Total Body Effective Dose Factor K, Dose Factor K, 1985 4.32E-05 1.97E-04 1986 1.42E-04 2.19E-04 1987 4.34E 05 1.08E-04 1988 1.08E-04 1.12E ) 1989 1.64E-04 1.73E-04 1990 8.80E-05 1.20E-04 1991 6.03E-05 1.252-04 mean a 9.27E-05 1.51 E-04 4.78E-05 4.51 E-05 mean + 3a 2.36E 04 2.86E 04 l

l I

O Rev.No. O Page _E-9 of ODCM i

I TABLE E-2 EFFECTIVE DOSE FACTORS FOR NOBLE GASES -

AIR DOSE g

[M, & N,]

YEAR VENT RELEASE ELEVATED RELEASE

[ mrad /see per Ci/m ] [ mrad /sec per Cl/m*]

Gamma-Air Beta-Air Gamma-Air Beta-Air Effective Effective Effective Effective Dose Factor Dose Factor Dose Factor Dose Factor M en N on M en N,n 1985 4.57E-05 6.78E-05 2.06E-04 1.26E-04 1986 1.49E-04 1.14E-04 2.28E-04 1.30E-04 1987 4.66E-05 5.21 E-05 1.13E-04 6.58E-05 1988 1.13E-04 7.25E-05 1.17E-04 7.49E-05 1989 1.71 E-04 7.30E-05 1.81 E-04 1.52E-04 1990 9.29E-05 8.87E-05 1.25E-04 1.39E-04 1991 6.41 E-05 6.30E-05 1.31 E-04 9.02E-05 mean a 9.75E-05 7.59E-05 1.57E-04 1.11 E-04 4.95E-05 2.01 E-05 4.70E-05 3.37E-05 l mean + 3a 2.46E-04 1.36E-04 2.98E-04 2.12E-04 l

l Rev.No. O Page E-7 of ODCM

l TABLE E-3 1

! EFFECTIVE DOSE FACTORS FOR NOBLE GASES -

SKIN EFFECTIVE DOSE l

t YEAR VENT RELEASE ELEVATED RELEASE  !

8  !

[ mrem /sec per yCi/m ] [ mrem /sec per pCi/m']

Total Skin Effective Skin Effective

Dose Factor Dose Factor j (L + 1.1M),, L, j l

l

' 1985 9.87E-05 1.09E-04 1986 2.37E-04 1.13E-04 1987 8.44E-05 4.57E-05 1988 1.77E-04 5.51 E-05

' 2.43E-04 1.34E-04 1989 1990 1.58E-04 1.20E-04  ;

i i 1991 1.04E-04 7.08E-05 i

i mean a 1.57E-04 9.25E-05 i 6.54E-05 3.47E-05 1

l mean +3a 3.54E-04 1.97E-04

+

l.

e Rev.No. O Page .fd. of ODCM

TABLE E-4 TABLES OF SOURCE TERMS USED FOR DEVELOPMENT OF EFFECTIVE DOSE TRANSFER FAC10RS g

(Based on Semi-Annual Effluent Data Reports

. for the years 1985 through 1991)

ELEVATED RELEASE (Curles) 1 RADIONUCLIDE 1985 1986 1987 1988 Ar-41 4.34E + 01 3.65E+ 01 6.90E + 01 1.34E+ 01 Kr-83m -- -- - -

Kr-85m 3.47E + 02 7.48E + 01 6.66E + 02 3.85E+ 02 Kr-85 - -- - -

, Kr-87 1.57E + 03 2.15E + 02 8.39E + 01 1.59E+ 02 2

Kr-88 1.13E + 03 3.32E + 02 4.60E + 02 5.18E+ 02 Kr-89 -- -- -- -

Kr-90 -- - - --

Xe-131m 8.51 E + 02 7.79E + 00 2.30E+ 00 -

Xe-133m -

9.92E+ 00 2.73E-01 5.88E+ 00 Xe-133 2.77E + 02 1.01 E + 02 1.63E+ 03 1.13E+ 03 Xe-135m 1.76E + 03 2.03E + 02 9.13E + 01 3.69E + 01 Xe-135 2.22E+ 03 3.34E + 02 2.35E+ 02 1.00E+ 03 Xe-137 --

3.86E + 01 - --

Xe-138 TOTAL 5.59E+ 03 1.38E + 04 7.45E + 02 2.10E + 03 2.26E + 02 3.47E +03 1.53E+ 01 3.27E+ 03 h

RADIONUCLIDE 1989 1990 1991 Ar-41 1.73E + 01 3.68E + 01 1.57E + 01 Kr-83m -- -- --

Kr-85m 1.28E + 02 7.78E + 01 1.94E + 02 l Kr-85 -- -

l Kr-87 9.26E + 00 3.85E + 01 7.30E + 01 Kr-88 2.20E + 01 1.17E + 02 2.99E + 02 Kr-89 - - --

Kr-90 - -- --

Xe-131m 7.41 E + 00 1.88E + 01 1.16E + 02 )

Xe-133m -

3.38E+ 00 5.23E + 00 Xe-133 7.17E + 00 2.97E + 02 4.74E + 02 Xe-135m 6.09E + 00 2.99E + 01 2.38E + 01 Xe-135 2.49E + 01 1.40E+ 02 4.00E + 02 Xe-137 2.40E + 01 1.87E+ 02 7.22E+ 01 Xe-138 2.04E + 01 1.01 E+ 02 7.55E+ 01  !

TOTAL 1.51 E + 02 1.05E + 03 1.75E + 03 g Rev. No. O Page E-9 of ODCM l

- j l

~

TABLE E-5 TABLES OF SOURCE TERMS USED FOR DEVELOPMENT OF EFFECTIVE

DOSE TRANSFER FACTORS  ;

(Based on Semi-Annual Effluent Data Reports l j for the years 1985 through 1991) l

! l

VENT RELEASE (Curles)

RADIONUCLIDE 1985 1986 1987 1988 ]

! Ar-41 -- -- - - )

i Kr-83m -- -- - -

Kr-85m -

3.35E+ 01 6.42E + 01 3.14E + 01

l Kr-85 4.36E+ 02 - - --

! Kr-87 8.95E + 00 4.61 E + 01 1.38E + 01 7.78E + 00

Kr-88 1.45E + 01 7.25E + 01 4.81 E + 01 4.13E + 01 Kr-89 -- -- -- -

Kr-90 -- -- -- -

I Xe-131m 1.44E+ 02 1.24E + 02 1.19E + 01 1.26E + 01 l Xe-133m 2.81 E+ 01 4.65E + 01 4.37E+ 02 5.33E+ 01

Xe-133 6.29E + 01 4.91 E + 01 5.06E + 02 2.75E+ 02 Xe-135m 9.66E+ 00 1.33E + 01 3.39E+ 01 1.48E+ 01

. Xe-135 1.68E + 02 3.54E + 01 1.31 E+ 02 5.14E+ 01

! m Xe-137 -

3.10E + 01 - --

j Xe-138 7.27E + 01 1.06E + 02 3.18E + 01 1.35E + 02 TOTAL 9.44E + 02 5.57E + 02 1.28E + 03 6.23E + 02 RADIONUCLIDE 1889 1990 1991 Ar-41 3.35E-01 9.02E + 01 4.70E-01

) r- m 7.08E + 01 1.[7E+01 1.[4E+01 i Kr-85 -

Kr-87 3.68E + 00 1.13E + 01 3.72E + 00 Kr-88 1.01 E + 02 1.36E + 01 1.63E + 01

{

Kr-89 -- -- -

Kr-90 -- -- -

! Xe-131m 5.57E + 01 1.67E + 01 1.11 E + 02 3 Xe-133m 5.05E+ 01 8.95E + 01 1.70E + 01 Xe-133 4.03E + 01 5.54E + 01 7.19E + 01 Xe-135m 1.53E+ 01 8.81 E + 00 1.35E + 01

) Xe-135 2.62E + 01 3.27E+ 01 2.39E + 01 Xe-137 -

1.11 E + 01 7.85E+ 00

Xe-138 4.42E+ 01 4.57E+ 01 1.74E + 01 TOTAL 4.08E+02 3.04E+02 3.01 E + 02 l

Rev.No. O Page E-10 of ODCM 4

TABLE E-6 RADIONUCLIDE DISTRIBUTION OF VENT AND ELEVATED RELEASES g (Based on Semi-Annual Effluent Data Reports for the years 1985 through 1991)

Fraction of Total Vent Release l RADIONUCUDE l 1985 1986 *987 1988 1989 1990 1991 l

Ar-41 - - - - 8.21E44 2.97E-03 1.57E43 Kr-83m - - - - - - -

Kr-85m -

8.01 E-02 5.03E-02 5.04E-02 1.73E-01 5.83E42 5.80E-02 Kr 85 4.62E41 - - - - - -

I Kr-87 9.48E-03 8.27E42 1.08E-02 1.25E-02 9.02E-03 3.73E-02 1.24E-02 Kr-88 1.53E-02 1.30E41 3.76E-02 6.63E 02 2.48E 01 4.48E-02 5.43E-02 Kr-89 -- -- - -- -- -- --

l Kr-90 -- -- -- -- - -- --

l Xe-131m 1.52E-01 2.23E-01 9.32E 03 2.02E 02 1.36E-01 5.51 E-02 3.70E-01 Xo-133m 2.97E-02 8.34E-02 3.42E 01 8.56E-02 1.24E-01 2.95E-01 5.67E 02 Xe-133 6.66E-02 8.80E42 3.96E-01 4.42E 01 9.87E42 1.82E 01 2.39E 01 Xe-135m 1.02E-02 2.39E-02 2.65E42 2.37E-02 3.74E-02 2.90E 02 4.49E42 Xe-135 1.78E-01 6.35E-02 1.02E-01 8.26E-02 6.42E-02 1.08E-01 7.97E-02 l Xe-137 -

5.56E-02 - - -

3.65E-02 2.61E 02 Xe-138 7.70E-02 1.89E41 2.49E-02 2.17E 01 1.08E-01 1.51 E-01 5.66E 02 FRACTION OF TOTAL ELEVATED RELEASE RADIONUCUDE 1985 1986 1987 1988 1989 1990 1991 Ar-41 3.15E-03 1.74E-02 1.99E 02 4.09E-03 1.14E 01 3.52E-02 8.97E43 Kr-83m - - - - - - -

Kr-85m 2.52E-02 3.56E-02 1.92E-01 1.18E 01 8.45E42 7.44E-02 1.11 E-01 Kr-85 -- - -- -- -- -- --

Kr-87 1.14E 01 1.03E-01 2.42E-02 4.85E-02 6.12E 02 3.68E-02 4.17E-02 Kr-88 8.17E42 1.58E-01 1.33E41 1.58E-01 1.45E.01 1.12E 01 1.71 E-01 Kr-09 -- - - - -- -- --

Kr-90 - - - - - - -

l Xe 131m 6.18E-02 3.71E43 6.64E44 -

4.90E42 1.79E-02 6.62E42 l Xe-133m -

4.73E-03 7.88E-05 1.80E-03 -

3.23E-03 2.99E 03 l Xe-133 2.01E-02 4.83E42 4.71E41 3.47E-01 4.74E-02 2.84E-01 2.71 E-01 Xe-135m 1.27E-01 9.68E-02 2.63E 02 1.13E-02 4.03E-02 2.86E 02 1.36E42 Xe-135 1.61 E-01 1.59E-01 6.78E-02 3.06E 01 1.65E-01 1.33E-01 2.28E 01 Xe-137 -

1.84E 02 - -

1.59E-01 1.79E-01 4.13E-02 Xe-138 4.06E-01 3.55E 01 6.51 E-02 4.67E-03 1.35E-01 9.62E-02 4.32E-02 O

Rev No. O Page E-11 of ODCM 1

O APPENDIX F EFFLUENT MONITOR SAMPLING LOCATIONS AND DESCRIPTIONS O

• l 1

1 1

O Rev. No. O Page F-1 of ODCM )

1

I APPENDIX F EFFLUENT MONITOR SAMPLING LOCATIONS AND DESCRIPTIONS TABLE TITLE PAGE l

F-1 Atmospheric Gaseous Release Point Data F-3 F2 Effluent Monitoring System Data F-4 l

FIGURE F-1 Gaseous Release Points Building Elevations F-6 F-2 Gaseous Release Points Plant Yard Layout F-7 F-3 Liquid Release Point F-8 F-4 Gaseous Effluent Release Paths F-9 F-5 Liquid Effluent Release Paths F-10 F-6 Solid Radwaste Treatment System F-11 F-7 Standby Gas Treatment System F-12 .

1 I

O Rev. No. O Page F-2 of ODCM

O O O TABLE F-1

.I JAMES A. FITZPATRICK NUCLEAR POWER PLANT k 0FFSITE DOSE CALCULATION MANUAL (ODCM) o ATMOSPHERIC GASE0US RELEASE POINT DATA RELEASE REACTOR

• TURBINE RADWASTE REFUEL

• POINT STACK BUILDING BUILDING BUILDING FLOOR Height Above 385 172 172 111 172 Grade (feet)

Release Mode Elevated Roof Top Vent Roof Top Vent Roof Top Vent Roof Top Vent Ef fluent Turbine Gland Secondary Turbine Waste Disposal Refuel Floor Source Seal Condenser and Auxiliary Building Building Exhaust Gases Mechan- Building Exhaust Ventilation Ventilation ical Vacuum Exhaust Ventilation Pump Building Exhaust. Steam Jet Air Ejector Exhaust I

S m

6 R

o

• The Refuel Floor and Reactor Building vent is a combined release point.

8 E

TABLE F-2 22 y JAMES A. FITZPATRICK NUCLEAR POWER PLANT z

P 0FFSITE DOSE CALCULATION MANUAL (ODCM)

O EFFLUENT MONITORING SYSTEM DATA SAMPLING DETECTON RANGE CONTROL Al. ARM REFERENCE HONITOR DESCRIPTION LOCATION TYPE FUNCTIONS SETPOINT CAllBRATION USED SOURCE Hain steam Located near 4-gamma 0-10 mR/hr Direct scram. Yes Victoreen Cs' the main steam sensitive contamination, gamma dose rate line monitor

. lines dounstream ion chambers isolation source of the outboard (closure of HSIV's, HSIV's in the recirc isolation steam tunnel valves, vacuum pump line valve) 6 Off-gas Turbine 252' 2-gamma 0-10 mR/hr Initiate closure Yes Cas sample radiation west sensitive of off-gas system counted on monitoring lon chambers isolation valves Ce(L1) system 0

Off-gas pipe Stack Scintillation 0-10 CP3 indicate and record Yes Gas vent 0 (Stack) detectors rate of release of marinelli

$o monitor radioactive material to the environment counted on Ce(L1) r1 1 6 Process 11guld Rad Waste - Scintillation 10 -10 Honitor for leaks Yes HepresentatIve O

~*

radiation RW 272' detectors CPS of closed systems. 11guld sample O monitors Service n 0 2

Honitor normal re- counted on leane of radio- ce ( 3,g )

h g Heater llay 252' active materiaal to the environment O O O

F-2 _

y (Continued)  !

3 EFFIAJENT MONITORING SYSTEM DATA Z

.O O HOWITOR SAMPLING DETECTOR RANCE CONTROL ALARM 3EFERENCE DESCRIPTION LOCATION TYPE FUNCTIONS SETPOINT CALIRRATION USED -SOURCE Plant stack & Turbine - CM Detectors 0-10 CPM Provide isolation Yes Cas vent noble HC Set 300' '

of potentially marinelli  !

gas monitors Reactor - contaminated counted on RX 344' systema Ce(L1)

Refuel -

RX 369 6 Radweste - Scintillation 0-10 CPS R8 272' Detector Stack 6

Dryve11 Reactor 300' Scintillation 0-10 ' CPM Honitor airborne Yes Cas continuous south side detectors radioactivity in marinelli mir monitor . Dryvell during counted on normal operation Ce(L1)

Containment Drywell 2-ton chamber 0-10 R/hr Accident enntrol Yes Victoreen i high range penetrations detectors and initiates Cs-137 gamma monitors Xil0C and isolation dose rate D X100D source  ;

on o

e y High range Stack, 2-ton chamber 0-10 R/hr Accident control Yes Victoreen

& affluent Turbine, detectors und initiates Cs-137 gamma monitors Radwasta lentation dune rate k source o __

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                                                                               "^

STACK @ A-A EASY ELEVATIOg PART NORTH ELEVATION OFF-SITE DOSE CALCULATION MANUAL FIGURE F-1 GASEOUS RELEASE POINTS BUILDING ELEVATIONS JAMES A. FITZPATRICK NUCLEAR POWER PLANT Rev.No. O NEW YORK POWER AUTHORITY Page f_&_ of ODCM

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AUX SLR HEATER SAY noou RADWASTE E 64e too . N,.6 T E 6 ..maa y j , c ) OFF-SITE DOSE CALCULATION MANUAL i I -T FIGURE F-2 GASEOUS RELEASE POWTS . i d E e4e.soo PLANT YARD LAYOUT JAMES A. FITZPAT7HCK NUCLEMI POWER PLANT , NEW YORK POWER AUTHORITY h Na o Page f_-Z,.of ODCM

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oiscwaRe . TuMNEL PROFILE ALohG DR ANCH TUNNE,L OFF-S!TE DOSE CALCULATION MANUAL ELEVATION LOO 'NG SOUTH FIGURE F-3 woTE GASEOUS RELEASE POfNTS OlrS'tE'//tNs Elu'= xa eur" DISCHARGE TUNNEL PLAPs & PROFILE JAMES A. FITZPATRICK NUCLEAR POWER PLANT l NEW YORK POWER AunOUTY Rev. No. O Page _EfL of ODCM _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ - . _ _ . _ _ _ _ _ . - - r - _ _ _ _ _ _ . - _ _ _ - _ _ -______m

F12URE F-4 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM) GASEOUS EFFLUENT RELEASE PATHS T Y' O

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t -_ . . , . _ . . . _ .

O O O I T

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                            ~                                                    Pref 11ter                                               _

HEPA _ Charcoal _ HEPA - Fan - Filter Deceu Beds Filter Reactor Bustdiro 3 CS 4 m M - _ Prineru j C k C Contairnent Q { m i Profilter _ HEPA _ Charcoal ~ HEPA - an O O 7 Filter Decau Beds Filter td mI a5-M Z T c 0 M>( r m 3 m Eo' O a

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O APPENDIX G  ; UNRESTHICTED AREA MAP , 1 O O Rev.No. O Page fa-1 of ODCM y .- .,,-e - .- -

APPENDIX G UNRESTRICTED AREA MAP FIGURE g PAGE G-1 JAFNPP Site Boundary Map G-3 l l i I i I l l O O Rev. No. O Page fa-2. of ODCM

FIGURE G-1 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSTTE DOSE CALCULATION MANUAL (ODCIWI) JAFNPP SITE BOUNDARY MAP h l 0 N fA N ' LAX[ - m

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1 1 1 i i i i d i i i t t 4 1 i i APPENDlX H i r ! ENVIRONMENTAL SAMPLE LOCATIONS i 1 l 3 i' t i l i l t t I i

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lk,

!                         Rev. No.       O                                                                                                                   Page H-1 of ODCM 4!,
                                           , , . - . . ,             , - , . ,   , . - -     - - . . . . ,    .         , _ . -          ..,       ,._,..,,...._m>,,,,m....-,.   ,.y.,,...,   ,

1 APPENDIX H ENVIRONMENTAL SAMPLE LOCATIONS TABLE TITLE P_ AGE H-1 Radiation Environmental Monitoring Sampling H-5 Locations H-2 Uquid Effluent Pathway - Water intake Points H-13 Description and Pumpage l l FIGURE H1 Environmental Sampling Location Map H 10 H-2 Environmental Sampling Location Map H-11 H-3 Uquid Effluent Pathway - Water Intake Points H-12 l l l O l I t Rev.No, O Page Li2_ of ODCM

    . -     . - .                 .   -=

ENVIRONMENTAL SAMPLING LOCATIONS 1.0 ENVIRONMENTAL MONITORING PROGRAM I 1.1 Sampling Stations The current sampling locations are specified in Table H-1 and Figures H 1, H-2. The Radiological Environmental Monitoring Program is a joint effort between the Niagara Mohawk Power Corporation and the New York Po.ver Authority, the owners and operators of the Nine Mile Point Unit 1 and the James A. FitzPatrick Nuclear Power Plant, respectively. Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from both units. The average dispersion and deposition parameters for the two units have been l calculated for a five (5) year period,1978 through 1982. The calculated dispersion or deposition parameters will be compared to the results of the annual land use census. If it is determined that a milk sampling location exists at a location that yields a significantly higher (e.g. 50%) calculated D/O rate, the new milk sampling location will be added to the monitoring program within 30 days. If a new location is added, the old location that yields the lowest calculated D/O may be dropped from the program after October 31 of tha: year. 1.2 Interlaboratory Comparison Program Analyses shall be performed on samples containing known quantities of radioactive material that are supplied as part of a Commission approved or sponsored Interlaboratory Comparison Program, such as the EPA Cross-check Program. Participation shall be only for those media, (e.g. air, milk, water, etc.), that are included in the Nine Mile Point Environmental ' Monitoring Program and for which cross check samples are available. De actual Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Report so that the Commission staff may evaluate the results. Specific sample media for which EPA Cross Check Program samples are available include the following: o gross beta in air particulate filters o gamma emitters in air particulate filters o 1131 in milk l o gamma emitters in milk l O I' Rev. No. O Page .11.3 of ODCM

l l , o gamma emitters in water l o tritium in water I o I 131 in water 1.3 Thermoluminescent Dosimeters Used for Environmental Measurements l Thermoluminscent Dosimeters (TLDs) are placed in an inner ring of stations in the general area of the site boundary (TLDs 7,18,23,75-87), and in an outer ring in the 4 to 5 mile range from the site (TLDs 88-95). There are 16 land based sectors in the inner ring and 8 land based sectors in the outer ring. TLDs are also placed in special interest areas such as population centers, nearby residences, schools, and control locations (TLDs 14, 15, 18, 49, 56, 96). l l l l O i ! Rev.No. O Page H-4 of ODCM

i 1 j TASLE H-1 i RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS j - TYPE OF MAP

• j SAMPLE LOCATION COLLECTION SITE LOCATION +

l _ i Radiciodine and 1 Nine Mile Point Road 1.8 mi @ 88' E Particulates (air) North (R-1)

 !               Radioiodine and                                                           2                            Co. Rt. 29 & Lake Road (R 2)                                          1.1 mi @ 104' ESE
 ,               Particulates (air) i j                 Radiciodine and                                                           3                            Co. Rt. 29(R-3)                                                       1.5 ml @ 132' SE j                 Particulates (air) j                                                                                                                                                                                                                                            '

j Radiciodine and 4 Village of Lycoming, NY(R-4) 1.8 ml @ 143' SE i Particulates (air) l Radiolodine and 5 Montario Point Road (R-5) 16.4 ml @ 42' NE l Particulates (air) j Direct Radiation (TLD) 6 North Shoreline Area (75) 0.1 ml @ 5' N 1 ircct Radiation (TLD) 7 North Shoreline Area (76) 0.1 ml @ 25' NNE l Direct Radiation (TLD) 8 North Shoreline Area (77) 0.2 mi @ 45' NE ~ l Direct Radiation (TLD) 9 North Shoreline Area (23) 0.8 ml @ 70' ENE i Direct Radiation (TLD) 10 JAF East Boundary (78) 1.0 mi @ 90' E i Direct Radiation (TLD) 11 l, Rt. 29(79) 1.1 ml @ 115' ES f Direct Radiation (TLD) 12 Rt. 29(80) 1.4 ml @ 133' SE i 4 Direct Radiation (TLD) 13 Miner Road (81) 1.6 ml @ 159' SSE l Direct Radiation (TLD) 14 Miner Road (82) 1.6 ml @ 181' S j 4 Direct Radiation (TLD) 15 Lakeview Road (83) 1.2 ml @ 200' SS . Direct Radiation (TLD) 16 Lakeview Road (84) 1.1 ml @ 225' SW l j

• Ste Figures H 1 and H-2 for map locations (T-) Based on 9 Mile Point Unit 2 Reactor Centerline v  :

l Rev.No. . O Page ti-5 of ODCM 3

   .           ,         - . , . . . . - _ _ . , , . . . .                   , , , , ,          ,.,.._,m.,   .,_ . , . . ..            ,,.~.....,._.~._..,..,_......_........,.....,..,.m., -

TABLE H-1 (C:ntinued) RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS l TYPE OF MAP

• SAMPLE LOCATION COLLECTION SITE LOCATION +

l Dircet Radiation (TLD) 17 Site Meteorological Tower (7) 0.7 ml @ 250' WSW Dircct Radiation (TLD) 18 Energy information Center (18) 0.4 mi @ 265' W Direct Radiation (TLD) 19 North Shoreline Area (85) 0.2 mi @ 294' WNW Direct Radiation (TLD) 20 North Shoreline Area (86) 0.1 ml @ 315' NW Direct Radiation (TLD) 21 North Shoreline Area (87) 0.1 ml @ 341' NNW Direct Radiation (TLD) 22 Hickory Grove (88) 4.5 mi @ 97' E Direct Radiation (TLD) 23 Leavitt Road (89) 4.1 mi @ 111' ESE Direct Radiation (TLD) 24 Rt.104(90) 4.2 ml @ 135' SE Direct Radiation (TLD) 25 Rt. 51 A(91) 4.8 ml @ 156' SSE 1 Direct Radiation (TLD) 26 Maiden Lane Road (92) 4.4 ml @ 183' S h Direct Radiation (TLD) 27 Rt. 53(93) 4.4 mi @ 205' SSW Dircct Radiation (TLD) 28 Co. Rt.1(94) 4.7 ml @ 223' SW Direct Radiation (TLD) 29 Lake Shoreline (95) 4.1 mi @ 237' WSW Direct Radiation (TLD) 30 Phoenix, NY Control (49) 19.8 ml @ 170' S-SSE Direct Radiation (TLD) 31 SW Oswego Control (14) 12.6 mi @ 226' SW Direct Radiation (TLD) 32 Scriba, NY(96) 3.6 ml @ 199' SSW Direct Radiation (TLD) 33 Alcan Aluminum, Rt.1A(58) 3.1 ml @ 220' SW Direct Radiation (TLD) 34 Lycoming, NY(97) 1.8 ml @ 143' SE Direct Radiation (TLD) 35 New Haven, NY(56) 5.3 ml @ 123' ESE

• See Figures H-1 and H-2 for map locations

 + Based on 9 Mile Point Unit 2 Reactor Centerline h

Rev. No. O Page H-6 of ODCM

! TABLE H-1 (C:ntinued) i RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS i_ TYPE OF MAP

• SAMPLE LOCATION COLLECTION SITE LOCATION +

l Dircct Radiation (TLD) 36 W. Boundary, Bible Camp (15) 0.9 ml @ 237' S j Direct Radiation (TLD) 37 Lake Road (98) 1.2 ml @ 101* E-ESE Surface Water 38 OSS Inlet Canal (NA) 7.6 ml @ 235* SW-WS

Surface Water 39 JAFNPP Inlet Canal (NA) 0.5 ml @ 70* ENE -

j Shorcline Sediment 40 Sunset Bay Shoreline (NA) 1.5 mi @ 80* E Fish 41 NMP Site Discharge Area (NA) 0.3 ml @ 315' NW

and/or Fish 42 NMP Site Discharge Area (NA) 0.6 ml @ 55* NE Fish 43 Oswego Harbor Area (NA) 6.2 mi @ 235' WSW Milk 44 Milk Location #50 (NA) 9.3 mi @ 93* SE ilk 45 Milk Location #7 (NA) 5.5 mi @ 107 ESE l NA 46 Intentionally Left Blank NA l NA 47 Intentionally Left Blank NA  !

Milk 63 Milk Location #73 (NA) 13.9 ml @ 234* SW i I l Food Products ** 48 Garden #1 (78) Cary 1.5 mi @ 83 E ! (Broad Leaf Vegetation) i j NA 49 Intentionally Left Blank NA e l Food Products ** 50 Garden #2 (79) Nerewski 1.6 mi @ 84* E j (Broad Leaf Vegetation) i

• See Figures H-1 and H-2 for map locations

          **        Food product samples need not be samples from each locations listed. Two onsite samples will be collected from the location with the highest calculated average D/O value from which broad leaf vegetation is available. One control sample will be collected at a location listed from which j                    broad leaf vegetation is available.

4 Based on 9 Mile Point Unit 2 Reactor Centerline } Rev.No. -0 Page H-7 of ODCM i

TACLE H-1 (Continued) RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS TYPE OF MAP * ' SAMPLE LOCATION COLLECTION SITE LOCATION + Food Products ** 51 Garden #3 (134) Kronenbitter 1.7 ml @ 84* E (Broad Leaf Vegetation) Food Products ** 52 Garden #4 (133) Culeton 1.7 mi @ 84* E (Broad Leaf Vegetation) Food Product ** 53 Garden #5 Dickenson 1.7 ml @ 82 E (Broad Leaf Vegetation) Food Products ** 54 Garden #6 Vitullo 1.9 ml @ 101" E (Broad Leaf Vegetation) Food Products ** 62 Garden #7 (165) Koeneke 1.9 mi @ 96 E (Broad Leaf Vegetation) Food Product ** 55 Garden #8 (76) Johnson 1.7 mi @ 82 E (Broad Leaf Vegetation) Food Product ** (Broad Leaf Vegetation) 63 Garden #9 (175) Murray 1.2 mi @ 215* SSW h Food Product ** 56 Garden #10 (59) 1.5 ml @ 115 ES (Broad Leaf Vegetation) C.S. Parkhurst Food Product ** 64 Garden #11 (132) 1.9 mi @ 112 ESE (Broad Leaf Vegetation) Barton Food Product ** 58 Garden #12 (143) 1.7 mi @ 137 SE (Broad Leaf Vegetation) NM #541/2, Whaley Food Product ** 57 Garden #13 (142) 1.7 mi @ 142 SE (Broad Leaf Vegetation) NM #49, Hall See Figures H 1 and H-2 for map locations Food product samples need not be samples from each locations listed. Two onsite samples will be collected from the location with the highest calculated average D/O value from which broad leaf vegetation is available. One control sample will be collected at a location listed from which , bread leaf vegetation is available. l I

 +     Based on 9 Mile Point Unit 2 Reactor Centerline Rev. No. O                                                        Page H-8 of ODCM

l ! l 1  ! l TABLE H-1 (Continued) l RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS l TYPE OF MAP

• SAMPLE LOCATION COLLECTION SITE LOCATION +

l i Food Products ** 62 Garden #4 (190) Fox 1.8 ml @ 101* SW (Broad Leaf Vegetation) Food Products ** 59 Control #1 (NA) McMillen 15.0 ml @ 223* SW j (Broad Leaf Vegetation) l Food Products ** 60 Control #2 (NA) Denman 12.6 ml @ 225* SW l (Broad Leaf Vegetation) i Food Product ** 61 Control #3 (NA) Flack 15.6 ml @ 220* SW j (Broad Leaf Vegetation) 4

• See Figures H-1 and H-2 for map locations

] ! Food product samples need not be samples from each locations listed. Two onsite samples will

O** ee coiiected from 18e iocetion wita the rioheet ceiceietee evereoe D/O vaiue from whicn broed leaf vegetation is available. One control sample will be collected at a location listed from which broad leaf vegetation is available.

J

              +    Based on 9 Mile Point Unit 2 Reactor Centerline i

i i i i l 1 l 1 ]

  !O 1                     Rev. No.             O                                                          Page HS.of ODCM i

I

     + -- --       -e-             -                         - ' -mw--     e w,                , ,              ---=m---- < -- - - - -

• FIGURE H-1 JAMES A. FITZPATRICK NUCLEAR POWER PLANT g OFFSITE DOSE CALCULATION MANUAL (ODCM)

ENVIRONMENTAL SAMPLING LOCATION MAP FIGURE H-1 IS OVERSIZED AND IS LOCATED IN A FOLDER AT THE BACK OF THIS DOCUMENT. O O Rev. No. O Page H-10 of ODCM

u A-a s- --uJ- _ m - A J-+ n L-- - -.a- x -- FIGURE H-2 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM) 1 ENVIRONMENTAL SAMPLING LOCATION MAP 1 FIGURE H-2 IS OVERSIZED AND IS LOCATED IN A FOLDER AT THE BACK OF THIS DOCUMENT. O l O Rev.No. O Page H 11 of ODCM

FIGURE H-3  : JAMES A. FITZPATRICK NUCLEAR POWER PLANT gi OFFSITE DOSE CALCULATION MANUAL (ODCM) LIQUID EFFLUENT PATHWAY - WATER INTAKE POINTS Kingston 10 p#/  ; 4+ 15 11 -~~~ 16 12 J'f  !

                                            -                                                     s p
                                       /                                 9              8                  'N               '
                                /                                                                             %

N 17 U \ 7 watertown s l JEFFERSON f LAKE ONTARIO I I _ ( -- FITZPATRICK NUCLEAR POWER PL AN 50 MILE S

            }

t o ,,, oswego

                \                                      5 N
                   \
                       \                                                         L_
                          \     WAYNE                    CAYUGA n oasse.,                  N Syfacuse o

Rev. No. O Page ,1h12., of ODCM

i I TAILE H-2 i LIQUID EFFLUENT PATHWAY - WATER INTAKE POINTS O V DESCRIPTION AND PUMPAGE ' Location of Water k; tag Averaae Water Pumoaae Millions of Gallons Per Day

1. At a point between Dennison Creek and Bear 0.80 Creak at a site north of the intersection of lake and Knickerbocker Roads

2. At Puttneyville 1.0

3. At a point north of the village of Sodus 1.0 near the intersection of Shore Road i and an extension of Maple Avenue

4. In Sodus PoiM Village on Lake Road 0.133

5. At east of Port Bay 0.095 1'

6. In the wes.orn part of the City of Oswego 20.0 between Gixth and Sheldon Avenues and 4 S of West Schuyler Street O 7. At east of the Vitage of Sackets Harbor 0.30 O. In Sawmill Bay at a location on indepdendence 0.04 Point approximately 0.5 miles south of Chaumont Village's southerly limit

9. Cape Vincent 0.246.

10. Township of Pittsburg (Mil ton) 0.015 l

11. Township of Pittsburg (Glen Lawrence) 0.015

12. City of Kingston (2 intakes) 9.72

13. Township of Kingston (Pt. Pleasant) 0.705

14. Township of Kingston (Queen's Acres) 0.037

15. Township of Ernestown (Amherst'Aew) -

0.270

16. Village of Bath 0.150

17. Town of Picton 0.679 Rev. No. O Page H-13 of ODCM 1

 ,   .       . . . , -             .   -          - . . _ .     -     -.   . . - . - - . . . . . . . .              .----_.._A

i 9 e i + i APPENDIX 1 ODCM

SUMMARY

TABLES O 1 O Rev.No. O Page I-1 of ODCM

t APPENDIX l ODCM

SUMMARY

TABLES i l l' TABLE TITLE PAE! l-1 Radioactive Effluent Release Umits Summary l-3 Table i l l2 ODCM Summary 1-4 l l l l 1 l l .O O Rev. No. O Page J-2_ of ODCM

TABLE I-l

  .n
  .%                               RADI0 ACTIVE EFFLUENT RELEASE LIMITS - 

SUMMARY

TABLE o SDOSE/ DOSER LPATH/ SOURCE MONTHLYlPERIOD (1)- .' CALENDAR QUARTERI- :CALENDARlYEAR. COMMITMENT

                  ~

WHOLE ANY WHOLE ANY WHOLE ANY BODY SKIN ORGAN BODY SKIN ORGAN BODY SKIN ORGAN (MREM) (MRAD) (MREM) (MREM) (MRAD) (MREM) (MREM) (MRAD) (MREM) Plant Member of Liquid (2) the Public Effluents 0.06 None 0.2 1.5 None 5 3 None 10 Plant Member of Gaseous (2) the Public Effluents None None None 5* 10* 7.5 10* 20* 15 Plant At or Beyond Gaseous (3) Site Boundary Effluents None None None None None None 500 3000 1500 Uranium (4) Member of Fuel Cycle the Public (Site) None None None None None None 25 None 25(5) y (1) Equipment operability re for projected exposures. Refer to Specifications 2.4 g (Liquid) and 3.6 (Gaseous)quirements e __ (2) Plant Liquid and Gaseous release limitations in accordance with Appendix I to 10 CFR 50. 6 Refer to Specifications 2.3 (Liquids), 3.3 (Noble Gases) and 3.4 (Iodines and Particulates). E (3) Plant Gaseous release limitations in accordance with 10 CFR 20. Refer to Specification 3.2. O , 8 (4) Site Gaseous release limitations in accordance with 40 CFR 190. Refer to Specification 5.0.

 !E:

(5) Limits to any organ except the thyroid which shall be limited to 75 mrem. mrad, air dose.

, ~ . __ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ __ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ _ _ ! O . C' O t 33 TABLE l-2 d> N ODCM

SUMMARY

Z o

• FREeUENCY TECN. SPEC. CORRESPouDING 00CM IMPUT DATA REPotTING REGULAfoty APPENDIX 5 LINITING ODCM EeUATION EFFLUENT PURPOSE OF OF REQUIRENENTS REQUIRENENTS MISCELLANEOUS VALUES SECTIOE NUMBER C3 PATWWAY CALCULATION CALCULATION REGUIRENENT RESUIRENENT Section 3-1 . Discharge Re n eese May use a Fraction of Each batch 10CFR20.10 Section 2.2 10 CFR 20 LIQUID MPC(e) or, 3.2.2 structure permit simplified MPC, F L reteese (c) exit flow approach of 10 CFR 20 for nobte

                                                                                                                                                           . Weste tank                00CM Section Appendia 3,               gases 4                               reteese                   3.2.2 Table 2,                  2 x to rete                              x Column 2                  uCl/mt
                                                                                                                                                           . Sample                      C**)*l2 I*

f concentre- tesg tnen 3 x tions 10' uCl/st Section 2.2 to CFR 20 Section 3-2 . $seple Release LIQUID Minimum Each batch 10CFR20.10 concentre- permit reteese (e) MPC(s) or, 3.2.3 required tions dilution 10 CFR 20, for dissolved factor Appendix 3, noble ggses, Tebte 2 2a 10 f 2/It min. Column 2 uCi/ml Secticn Ft less then Section 3-3 . Ft input to LIQUID Determine- Each batch 10CFR20.10 or equel to 1 3.3.2 Sample operations tion of reteese (e) 2.1.s . concentre-10 CFR 20 when calcule-effluent ting minimum tions monitor Appendix B, set-points Tabte 2, dilution flou Column 2 USNRC Reg- Section 7.3 N/A Section 3-42 . Site Annual LIQUID Annual Dese Calender 3.4.1 3-4t specific Radioactive Assessment year totory Guide 1.21 dose Effluent commit- Report taent factors

                                                                                                                                                             . Previous year's reteese volumes 90                                                                                                                                       and curies Di
                                                                                                                                                             . Site spec-
                     %l                                                                                                                                         ific ditu-tion &

ingestion l$w l Monthly Calender 10 CFR 50, Section 2.3 Whole tody section 3-Se . Composite N/A May use b( LIQUl0 Appendix I dose - 1.5 3.4.2 3 5b dose- timited Dose month () Assessment arem/qtr. . Duration of enetysis approach 3 mrem /yr orgen dose - retesse of 00CM 5 mrem /qtr, . Curies Section 3E 10 mrea/yr reteesed 3.4.2

                                                                                                                                                             . Volume of dilution
        --.___---______.______________-.___-_a              -
                                                                                 . _ _ _ _ _ _                        ~7                                                   _   a

TABLE l-2 (continued) C ODCM

SUMMARY

z FREQUENCY TECN. SPEC. CORRESPONDING ODCN INPUT C) 00CM EQUATION DATA REPORTING OF RESULATORT APPEuDIK B LIMITING EFFLUERT PURPOSE OF VALUES SECTION NUMSER REQUIREnENTS REQUIREMEETS MISCELLANEOUS PATEUAY CALCULATION CALCULATICE REQUIREREET REQUIREMENT O Whole body Section N/A . Number of If non-Dose pro- Prior to N/A Section 2.4 LIOUID dose - 0.06 3.5 batch compliance, jection - release of releases, 30-day MRC determina- untreated eres/ month Organ dose - previous report tion of liquid month need to effluents .2 ares / month

                                                                                                                        . Projected operate                                                                                number of liquid                                                                                 releases reduaste                                                                               current systems                                                                                month Whole Body      Section    4-1 to . Highest       N/A         May use a Gaseous                        Determining Calender     10CFR20.105 Section                                 4-6       annuet                   timited 3.2.a.1     dose - 500      4.3.1 instantan-   week                                                                      average                  ansty.is pres /yr eous noble                                                                             a/0 for                  apprcach of gas release                                       Skin dose -

3000 mrem /yr vent and of OL CM rates elevated Sect'on 4.3.1 releases to de' ermine

                                                                                                                        . Tota'                     noble gas body,                    release rate skin, and                limits air dose factors
                                                                                                                        . Noble gas release rate (ucl/sec)
                                                                                                                         . Effective dose transfer factor for went releases, 90                                                                                                                         fraction of 03                                                                                                                         release rate limit h

rJ1 R o 8 m O O O

O 1, O x TABLE t-2 (Continued) 00CM

SUMMARY

Z o

• FREGUENCY TECW. SPEC. CORRESPOuttuG OOCW INPUT DATA REPORTING RECULATOtt APPENDIX 3 LIMIT 35G 00CN EeUATION EFFLUENT PURPOSE OF OF uuMEER REQUIRENENTS REeulRENENTS NISCELLANEOUS VALUES SECTION C) PATNUAT CALCULATION CALCULATIOR REGUIRENENT REGUIREMEET 10CFR20.105 Section Elevated Section 4-7 . Maxleum Input to GASEOUS Determina- Celendar 4-8 volume operations 3.1 4.3.2 tion of month or Release 6.29 x 10-5 release effluent upon major source monitor operational uti/sec vent . Calibre-set-points transients tion curve (i.e., Reteese 3.42 m 10-4 tuct/cc vs power level CPM) for changes and uC1/sec specified failed fuet) effluent monitor

                                                                                                          . For ground levet releases, fraction of release rete timit ellocated to specified reteese point 10CFR20.105 section        1500 mrem /yr. section     4-9    . Long-term          N/A GASEOUS   Determining Calender                                                              4-10      sector radiolodine, week                      3.2.e.2       any organ        4.3.3 average Tritium                                                                                    concentra-and 8 day                                                                                   tion particulate                                                                                 X/0 instanten-                                                                                 (Appendia C) eous                                                                                     . Long-term release                                                                                     relative rates                                                                                      deposition value "Il                                                                                                       Appendix C)
                                                                                                           . Dose factors for applicable enviroc-d5                                                                                                        mental pathways C(                                                                                                        (Tables S-4 through
  . ()                                                                                                        B-6) t od i ne ,.

a i Tritium and 8-e.y 3: particulate release rate (uct/ sec) s

                                                                                                  -     =             .            . . . .

y M TABLE t-2 tContinued) CD

  $                                                                        00Cm 

SUMMARY

Z

  -O                                                        TECN. SPEC. CORRESPONDING                OOCN         INPUT FREQUENCY                                                                         DATA         REPORTING OF           REGULATORY APPENDIX e       LIMITING     ODCN      EQUATION EFFLUENT PURPOSE OF                                                      VALUES     SECTIou     suMBEE   REQUIREMEETS REQUIREREETS MISCELLANEOUS PATRWAY       CALCULATION CALCULAftou REQUIREMEET REQUIREMENT c)

Section 7.3 N/A section 4-11 to . Previous Annuat GASEQUS Annual Dose Calendar USNRC 4.4.1 4-19 year's Radioactive Assessment Year Regulatory Guide 1.21 annual Effluent average Report D/G and X/o

                                                                                                              . Activity released (utt/yr.)

for the previous year from vent and elevated releases Monthly Calender 10 CFR 50, Section Gamma air Section 4-20 . Gamma Air CASE 0US 4-23 Dose Month Appendix 1 3.3.a Dose - 4.4.2 Dose factors, M Assessment 5 mrad /qtr. 10 mrad /yr. . Beta Air

                   - Gamma air                                                                                   Dose factor, Dose                                               Beta air Dose -                                   N
                   - Beta air                                                                                    Highest Dose                                               10 mrad /qtr.                         .

20 mrad /yr. annual average X/o for vent and elevated releases

                                                                                                              . Noble Gas curies released during the month "U                                                                     Any organ -      Section 4-24 to                      N/A          May use 03  GA$EOUS       Monthly     Calender          10 CFR 50, Section 4-27                                   timited
  !                Dose
                   - radio.

sonth Appendia 1 3.4.a.1 7.5 mres/qtr. 15 mres/yr. 4.4.2 analysis fodine, approach of 1- CDCM Sec-

 '4                  tritium and 8-day                                                                                                             tion 4.4.2.c bk                  particu-O 8

m: O ---- - - - - O - - O ---- -

                                                                                                                                 ,a  -~.~-r                                 ~ , . - . . -,. . ~

f

-.A -

                                                                           )

l . x cp TABLE I-2 (Continued) 00CM $UMMARY

     $0 Z

o

• FREeUENCY TECN. SPEC. CORRESPONOING 00CR IMPUT REPORTING REGUL AT ORY APPE50lX 5 LIMITING 00CN EeUATION DATA EFFLUEui PUPPOSE OF OF VALUES SECTIOR EUNSER REQUIREMENTS REGUIREMENTS MISCELLANEOUS PATEUAY CALCULATION CALCULATIDE REeUIREMENT REeUIREMENT C3 0.2 mrad section 4-20 . Gamma and if non- May use a GASEOUS Dose Prior to N/A Section gamma 4.5 4-31 sets air compilance, timited anal-Projection release of 3.6 0.4 arad done and 30 day NRC ysis approach Determina- unprocessed beta particu- report of ODCM Sec-tion of gaseous late, to- tion 4.5.2 need to effluents 0.3 arem organ dine, and operate tritium off gas organ dose treatment during the system quarter to date

                                                                                                              . Number of days the plant is projected to be i

operational during the coming ' month 40 CFR 190 section whole Rody or Section 3-4 . Actual LIQUID Demonstrate Calendar any organ 5.2 dilution compliance year if 5.1.a (except ingestion with annual liquid thyroid) - factors fuel / cycle releases 25 mres/yr (fish and ! dose commit- exceed 3 thyroid - potable ment limits aren, total 4 body, or 10 75 mres/yr water) aren, any Radio-organ Logical Environ-mental monitoring Pf*8f*"

• 9D results a

i EL

C) i h3 4

i: 4 _ _ _ _ . _ _ - . _ . _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ _ _._._m_v

                                                                                                                                                    \

i i i i " l 33 TABLE I-2 (Continued) i CD 00CM

SUMMARY

lC Z 00CM IzPUT FREQUENCY TECN. SPEC. CORRESPou0fMG b DATA REPORTtWG OF REGULATORT APPEuptX B LIMITIEC 00CM EQUATION EFFLUENT PURPOSE OF VALUES SECTION NUNGER REQUIREMENTS REQUIREMENTS MISCELLANEDUS PATWWAT CALCULATION CALCULAfl0E REQUIREMENT REQUIREMENT

       )

Whole body or Section Equation Current 30 day MRC Substitute GASEOUS Demonstrate Calendar 40 CFR 190 Section data, Report the total 5.1.s any organ 5.3 Section compliance year, if including: body dose with annual gaseous (except 4.4 thyrold) - actual factor (EI) fuel cycle releases Location of for the samma 25 mrem /yr. donc commit- exceed 10 thyroid - rest air dose fac-ment limits mrads gaema Individuals, tor (MI) air dose, 75 mrem /yr. meteoro-15 mrem Logical thyroid conditions, or any and consump-organ of food (e.g., milk, meat, and vegetation) 40 CFR 190 Section Whole Body - Section N/A . Shielding Direct 3emonstrate Calender 25 mrem /yr. 5.4 calculations Radia+ compilance year, if 5.1.a with annual liquids or . TLD resulta tion from environ-fuel cycle gases exceed mentet dose comit- dose timits program teent limits indicated above T D D e R o pg E d Z- bw V6.

         ^

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